ML16327A032

Final Operating Test (Sections a, B, and C) (Folder 3)

ML16327A032
Person / Time
Site:	Millstone
Issue date:	08/25/2016
From:	Brian Fuller Operations Branch I
To:	Dominion Nuclear Connecticut
Shared Package
ML15308A610	List: ML16078A002 ML16243A013 ML16327A032 ML16327A034 ML16327A035
References
U01927
Download: ML16327A032 (345)

Text

SIMULATOR SCENARIO #1 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 1 Op-Test No.: ES16LI1 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% Power IC-139, No Equipment OOS, Ch-Y PZR Level in service.

Turnover: 100% Power, steady state, no equipment OOS. 24E is aligned to 24C.

Critical Tasks:

1. SPTA-5; Manually shutdown the reactor

2. Fully implement Once Thru Cooling prior to either SG reaching 32 Event No. Malf. No. Event Event Description Type*

1 N N/A Start "B" TBCCW Pump, Secure "A" TBCCW Pmp.

(BOP/S) 2 03A1A5S2 C C04L-B11B (ATC/S) Trip "A" CEDM Cool Fan.

3 I RP10A Ch. A PZR Pressure fails low (TS)

(ATC/S) 4 I RX04A Ch-X PZR Level (LT110X) (non-selected) fails to 0% level. (TS)

(ATC/S) 5 C FW01 Main Condenser Vacuum leak.

(BOP/S) 6 R N/A Downpower due to vacuum leak.

(All)

RC11A, 7 M A RCP seizes and trips, TCBs fail to open (ATWS), manual Rx trip RP04A-D, RP27B (All) pushbuttons fail, manually trip by opening MG set breakers.

FW33, 8 C ES01A, Rapid loss of condenser vacuum and failure of AFAS to trigger.

ES01B (BOP/S) 9 FW36A, C (BOP/S)

FW36B AFW pipe rupture at FW-44, inops both headers, results in LOAF.

TS (S)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 39

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 NRC 2016, Scenario 1 Summary:

The crew will take the shift with the unit at 100% power, steady state, with no equipment out of service (IC-30).

TBCCW Pumps: A and C running, B in standby and ready to be started. The crew has been instructed to start the B TBCCW pump (Standby Equipment) and secure the A TBCCW pump.

Event 1: Upon taking the shift, the crew has been instructed to swap a running TBCCW with the Standby pump. The BOP will be directed to start the B TBCCW pump (Standby Equipment) and secure the A TBCCW pump, verifying no change in TBCCW flow. Once this is accomplished, Event 2 will be triggered.

Event 2: The A CEDM Cooling Fan will trip, triggering the CEDM Cooling Fan Trip annunciator. The crew will respond per ARP 2590C-082 and the ATC will be directed to start the standby (B) CEDM cooling fan.

Once this is accomplished, Event 3 will be triggered.

Event 3: The A Safety Channel of Pressurizer Pressure will fail low as a Tech. Spec. only event. The US should address the applicable Tech. Specs. and ARP, which directs all systems affected by the transmitter failure be bypassed. Once the crew has bypassed Ch. A on RPS, ESAS and AFAS, Event 4 is triggered.

Event 4: The Non-Selected (Ch. X) pressurizer level detector (LT-110X) will fail to 0%, causing all pressurizer heaters to trip. The crew will respond per ARP 2590B-215, de-select the failed channel and reset all pressurizer heaters. Once the crew has restored normal RCS pressure control, Event 5 will be triggered.

Event 5: Main Condenser Vacuum will begin to degrade. The crew should enter AOP 2574 for Loss Of Condenser Vacuum, and take the applicable actions to increase condenser air removal capacity. Once this proves ineffective, the US will enter AOP 2575, Rapid Downpower, and commence a plant shutdown.

Event 6: The crew will commence a plant shutdown using AOP 2575, Rapid Downpower, in an attempt to stabilize condenser vacuum by lower the energy load on the main condenser. The crew will insert CEAs to start the power reduction and then continue the downpower by boric acid injection into the RCS. This will be accomplished by aligning charging pump suction directly to the RWST (instead of the VCT).

When the power change evaluation is completed, Event 7 will be triggered.

2 of 39

Appendix D Scenario Outline Form ES-D-1 Event 7: A RCP will seize and trip, but the TCBs will fail to open (ATWS). The crew should recognize the ATWS and immediately trip the reactor manually by pressing the four TCB manual trip buttons. These will also fail to open the TCBs, requiring the opening of the MG Set supply breakers. The crew should then verify all CEAs are inserting (reactor trip successful), the main turbine has tripped and commence Standard Post Trip Actions per EOP 2525.

Event 8: During the performance of SPTA, Main Condenser vacuum will degrade rapidly, causing the loss of Main Feedwater Pumps and Condenser Steam Dumps. This will require the use of the Auxiliary Feedwater System to feed the S/Gs. The AFAS will fail to automatically start AFW flow to the S/Gs, requiring manual actuation of AFW flow. Once Aux. Feedwater is manually aligned to feed both S/Gs, Event 9 is triggered.

Event 9: Shortly after the feed flow has been established to the S/Gs using Auxiliary Feedwater, a rupture will occur on both sides of 2-FW-44 (normally open x-tie between AFW headers), resulting in the loss of both Auxiliary Feedwater headers. Once STPA are completed, and the LOAF is diagnosed, the crew will transition to EOP 2537, Loss Of All Feed, and discus using a Condensate Pump to feed the S/Gs. This will require a plant cooldown using the available SG inventory, to lower SG pressure below the shutoff head of the condensate pumps.

The scenario will ended when the crew has recovered SG feed flow using a Condensate Pump, or at the Examiners discretion.

INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

Delay Ramp Event Sev or Final Rel ID Num Description Time Time Time Value Value Order MALFUNCTIONS RP04A-Failure of all four Manual Trip Buttons N/A 0 RP04D RP27B Failure of ALL RPS trip functions N/A 0

ES01A, AFAS Failure, both Facilities N/A 0 ES01B C04L-F-13A Trip Alarm E-2 ON 2 B11B RP10A Ch. A PZR Pressure fails low E-3 100% 3 RX04A Ch. X PZR Level Cont. fails low E-4 0% 4 FW01 Main Condenser Vacuum Loss E-5 0.5 5 FW01 Main Condenser Vacuum Loss E-6 0.3 6 RC11A A RCP Seizes and tirps E-7 7 FW33 Rapid loss of Condenser Vacuum E-30 100% 8 FW36A Rupture Aux Feedwater, both headers E-9 100% 9 FW36B REMOTE FUNCTIONS TPR02 A TBCCW Pump discharge valve E-10 CLOSED 1 TPR02 A TBCCW Pump discharge valve E-11 OPEN 1 3 of 39

Appendix D Scenario Outline Form ES-D-1 OVERRIDES 03A1A5 Trip the A CEDM Cooling Fan, 2

S2 F-13A 4 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _1__

Event

Description:

Start the B TBCCW Pump, Secure the A TBCCW Pump Time Position Applicants Actions or Behavior Examiner Note: The crew has been instructed to brief the starting of the Standby (B) TBCCW Pump and secure the A TBCCW pump prior to taking the watch.

The following steps are from OP 2330B. OP procedure is marked up with N/A and Unit Supervisor signatures for applicable steps.

4.1.1 ESTABLISH communications between Operators at TBCCW pumps and BOP/PEO Control Room.

Simulator Operator: Establish communications with the control room as the PEO on station at the TBCCW pumps. If asked, local conditions appear ready for starting the B TBCCW pump.

4.1.2 To start standby TBCCW Pump, PERFORM the following:

a. PLACE selected TBCCW PUMP switch to START (C-06).

b. CHECK the following for running pump:

BOP/PEO

• No abnormal noise or vibration (local)

• Normal motor amperage (C-06)

• Maintains normal system pressure (C-06)

• Normal system flow as indicated on FI-6272 (TBCCW HX area)

Simulator Operator: Report as the PEO on station, B TBCCW pump is running no abnormal noise.

4.1.3 IF desired to stop A TBCCW Pump, PERFORM the following:

a. CLOSE 2-TB-3A, TBCCW PUMP A DISCHARGE STOP (TBCCW HX area).

BOP b. PLACE P-7A, A TBCCW PUMP switch to STOP OR PULL-TO-LOCK(C-06).

c. OPEN 2-TB-3A, TBCCW PUMP A DISCHARGE STOP (TBCCW HX area).

Simulator Operator: As the PEO on station, operate TB-3A as directed.

Event-10 [TPR02 CLOSED], Event-11 [TPR02 OPEN]

4.1.4 IF desired to stop B TBCCW Pump, PERFORM the following:

a. CLOSE 2-TB-3B, TBCCW PUMP B DISCHARGE STOP (TBCCW HX area).

b. PLACE P-7B, B TBCCW PUMP switch to STOP OR PULL-TO-BOP LOCK(C-06).

c. OPEN 2-TB-3B, TBCCW PUMP B DISCHARGE STOP (TBCCW HX area).

Examiner Note: This step is N/A 4.1.5 IF desired to stop C TBCCW Pump, PERFORM the following:

a. CLOSE 2-TB-3C, TBCCW PUMP C DISCHARGE STOP (TBCCW HX area).

b. PLACE P-7C, C TBCCW PUMP switch to STOP OR PULL-TO-BOP LOCK(C-06).

c. OPEN 2-TB-3C, TBCCW PUMP C DISCHARGE STOP (TBCCW HX area).

Examiner Note: This step is N/A Examiner Note: When B TBCCW Pump has been started and the A TBCCW Pump has been secured, or at the lead examiners direction, proceed to Event #2, Trip of A CEDM Cooling Fan.

5 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _2__

Event

Description:

A CEDM Cooler Fan Trip Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event #2, A CEDM Cooling Fan trip.

Indications Available:

• CEDM COOLER FAN TRIP (C-04, BB-11).

Examiner Note: The following steps are from ARP 2590C-082.

1. Start idle CEDM cooling fan (C-04).

2. MONITOR the following:

• A CEDM fan air discharge temperature on computer point, T8102

• B CEDM fan air discharge temperature on computer point, T8106

• C CEDM fan air discharge temperature on computer point, T8101 ATC

• If all three CEDM cooling units fail, Go To OP 2204, Load Changes, and PERFORM applicable actions to initiate a plant and reactor shutdown.

3. SUBMIT CR to Electrical Maintenance Department to investigate cause of fan trip.

CUE: If asked to investigate and determine the status of A CEDM Fan breaker, report back that breaker has tripped on over current.

Examiner Note: When the CEDM fan trip has been mitigated or at lead examiners direction, go to Event 3 Ch. A RCS Pressure failure.

6 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _3__

Event

Description:

Failure of Safety Ch. A PZR Pressure (low)

Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 3, Failure of Ch. A RCS Pressure (PT-102A).

Indications Available:

• PPC alarm Ch. A RCS Pressure.

• PZR PRES LO BLOCK A (C01, A-18)

• TM-LP TRIP CH A (C-04, CA-3)

• RPS PRE TRIP (C-04, AA-7)

• PZR PRESS LO LO A (C-01, A-20)

• ESAS COMPONENT UNDER TEST FAILURE (C0-1, B-41) [When ESAS channel is bypassed]

Examiner Note: The following steps are from ARP 2590C-021, TM-LP TRIP CH A.

AUTOMATIC FUNCTIONS

1. If 2 RPS channels actuate, reactor trips.

NOTE ATC

1. TMLP Trip may be manually bypassed when power is less than 1 x 10-4%. However, if power increases above 1 x 10-4%, bypass is automatically removed.

2. Pressurizer pressure is an input to ATWS logic circuitry.

CORRECTIVE ACTIONS

1. IF reactor trips, Go To EOP 2525, Standard Post Trip Actions" and PERFORM necessary corrective actions.

2. OBSERVE channel A" pressurizer pressure indication and TMLP setpoint and COMPARE to other safety channel indications (C-03, PPC, ESAS).

3. OBSERVE channel A" TH and TC instruments indicating properly for present ATC conditions (C-03, PPC, RPS).

4. IF pressurizer pressure or RCS temperature is abnormal AND no automatic reactor trip has occurred, manually TRIP reactor and Go To EOP 2525, Standard Post Trip Actions."

Examiner Note: Applicant observes that Ch. A PZR Pressure failed low by comparing the four Pressure Safety Channels on C-02/3 PZR mimic.

Simulator Operator: If dispatched as a PEO to check indication on C-21, report PI-102A is failed low.

7 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _3__

Event

Description:

Failure of Safety Ch. A PZR Pressure (low)

Time Position Applicants Actions or Behavior

5. IF alarm is due to any instrument malfunction, PERFORM the following:

5.1. IF pressure instrument malfunctioned, OBTAIN necessary keys and PERFORM applicable actions to bypass the following channel A" pressurizer pressure outputs:

• TMLP Trip (RPS)

ATC/BOP

• High Pressurizer Pressure Trip (RPS)

• ESAS pressurizer pressure bistable

• ATWS (C-100)

Examiner Note: The US may chose to have either the ATC or the BOP carry out the above step to bypass the affected safety channels.

5.2. IF temperature instrument malfunctioned, OBTAIN necessary keys and PERFORM applicable actions to bypass the following channel A" temperature outputs:

• TMLP Trip (RPS)

• High Power Trip (RPS)

• Local Power Density Trip (RPS) 5.3. Refer To the following Technical Specifications LCOs and DETERMINE ATC/SRO applicability:

• 3.3.1.1, Table 3.3-1

• 3.3.2.1, Table 3.3-3

• 3.3.3.5, Table 3.3-9 (PI-102A only)

• 3.3.3.8, Table 3.3-11 (PI-102B only) 5.4. Refer To the following TRM LCOs and DETERMINE applicability:

• 3.3.1.1.1 5.5. SUBMIT Trouble Report to I&C Department.

At ESAS Sensor cabinet A, PRESS SIAS/CIAS keyswitch is turned from OPER RO or to INHIBIT BOP 8 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _3__

Event

Description:

Failure of Safety Ch. A PZR Pressure (low)

Time Position Applicants Actions or Behavior Review Tech. Specs. and TRM:

LCO 3.3.1.1 (RPS): As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

Per TS Table 3.3-1: FUNCTIONAL UNIT #4 Pressurizer Pressure - High; Total Number of Channels = 4, Minimum Channels Operable = 3, App. Modes = 1&2, Action = 2 Action 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

SRO c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided one of the inoperable channels is placed in the tripped condition.

Examiner Note: SRO should note TSAS 3.3.1, Action 2 applies and is presently being met by the actions taken per the ARP to bypass the affected channels.

LCO 3.3.2.1 (ESAS): The engineered safety feature actuation system instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an engineered safety feature actuation system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, either adjust the trip setpoint to be consistent with the value specified in the Trip Setpoint column of Table 3.3-4 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or declare the channel inoperable and take the ACTION shown in Table 3.3-3.

b. With an engineered safety feature actuation system instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

Per TS Table 3.3-3: FUNCTIONAL UNIT #1c, Pressurizer Pressure - Low; Total Number of Channels = 4, Minimum Channels Operable = 3, App. Modes = 1,2,3a, Action = 2 9 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _3__

Event

Description:

Failure of Safety Ch. A PZR Pressure (low)

Time Position Applicants Actions or Behavior Action 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided one of the inoperable channels is placed in the tripped condition.

Examiner Note: SRO should note TSAS 3.3.2.1b, Action 2 applies and is presently being met by the actions taken to bypass the affected channels.

TS 3.3.3.5 (PI-102A - High Range): The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2 and 3.

SRO ACTION:

With the number of OPERABLE remote shutdown monitoring instrumentation channels less than required by Table 3.3-9, either:

a. Restore the inoperable channel to OPERABLE status within 7 days, or

b. Be in HOT SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Examiner Note: SRO should note that one of the two channels of PZR Pressure on C-21 is not OPERABLE. However, Table 3.3-9 only requires one channel be OPERABLE, which there still is (PI-102B). Therefore, the TS is still met TS 3.3.3.8 (Acc. Monitoring): SRO should note that this TS is Not Applicable.

TRM 3.3.1.1.1: All pressurizer high pressure reactor protection channels shall be FUNCTIONAL.

APPLICABILITY:

In accordance with Technical Specification LCO 3.3.1.1 Applicability.

ACTION:

Restore any nonfunctional pressurizer high pressure reactor protection channel to FUNCTIONAL status within 30 days of placing the channel in the tripped condition, or be in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with the failed channel in the bypassed condition.

Examiner Note: SRO should note that the Action Requirements of this TRM applies while the instrument channel is not OPERABLE per TS 3.3.1.1.

Examiner Note: When the instrument failure has been evaluated and mitigated, or at the lead examiners direction, proceed to Event 4, Ch. X PZR Level failure.

10 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _4__

Event

Description:

Failure of Control Ch. X PZR Level (low)

Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 4, Failure of the Non-Selected Channel (X) of PZR Level to 0%.

Indications:

• PRESSURIZER CH X LEVEL LO LO (C-02/3, C-38)

• PRESSURIZER CH X LEVEL HI/LO (C-02/3, A-38)

Examiner Note: The following steps are from ARP 2590B-215, PRESSURIZER CH X LEVEL LO LO.

If the steps from PRESSURIZER CH X LEVEL HI/LO (ARP 2590B-213) are used, skip to the next page.

AUTOMATIC FUNCTIONS ATC

1. IF SEL SW is in X+Y position, all heaters de-energize.

CORRECTIVE ACTIONS

1. OBSERVE actual level on pressurizer level recorder, LR---110, pressurizer level controllers (C---03) and PPC.

2. IF annunciator is not valid, SHIFT pressurizer level control to channel Y.

2.1. SHIFT pressurizer heater control SEL SW to channel Y.

2.2. As necessary, RESET the following Pressurizer heater breakers:

• PROP HTR GROUP 1

• PROP HTR GROUP 2

• BACKUP HTRS GROUP 1

• BACKUP HTRS GROUP 2 ATC

• BACKUP HTRS GROUP 3

• BACKUP HTRS GROUP 4 Examiner Note: Because this is an instrument failure of the Non-Controlling channel, and does not reflect an actual change in PZR level, the only Effect is the PZR Heater Breakers tripping open. Therefore, steps 3 - 8 of this ARP are not applicable.

9. IF alarm was caused by channel X malfunctioning, SUBMIT Trouble Report to I&C Department.

10. Refer To Technical Specifications LCOs 3.3.3.5 and 3.3.3.8 to determine ACTION Statement requirements.

11 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _4__

Event

Description:

Failure of Control Ch. X PZR Level (low)

Time Position Applicants Actions or Behavior Examiner Note: The following steps are from ARP 2590B-213, PRESSURIZER CH X LEVEL HI/LO.

AUTOMATIC FUNCTIONS

1. IF level is high:

• All backup heater energize ATC

• All proportional heaters go to maximum output.

• Backup charging pumps stop.

• If level is low, backup signal is generated to start both backup charging pumps.

CORRECTIVE ACTIONS CAUTION While restoring Pressurizer level, Pressurizer pressure must be closely monitored to prevent exceeding DNB limits, or effects on reactivity due to pressure changes.

NOTE ATC Actual Pressurizer level response should track with pressure response.

1. OBSERVE Pressurizer levels on all channels (C-03).

2. OBSERVE Pressurizer pressure on all channels (C-03).

NOTE Failure of the non-controlling Channel X low, will de-energize pressure heaters if heater SEL SW is in X+Y position.

12 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _4__

Event

Description:

Failure of Control Ch. X PZR Level (low)

Time Position Applicants Actions or Behavior

3. IF L110X is the non---controlling channel, and a controller or transmitter failure is indicated in the low direction, PERFORM the following:

3.1. SHIFT pressurizer heater control SEL SW to Y 3.2. As necessary, RESET the following Pressurizer heater breakers:

• PROP HTR GROUP 1

• PROP HTR GROUP 2 ATC

• BACKUP HTRS GROUP 1

• BACKUP HTRS GROUP 2

• BACKUP HTRS GROUP 3

• BACKUP HTRS GROUP 4 3.3. IF desired, COMMENCE forcing Pressurizer sprays.

3.4. Go To Step [13] {Note: a typographical error exists in the procedure at this step, in that the words NO TAG appear in place of 13.}

13. IF alarm was caused by a controller or transmitter malfunction, DETERMINE appropriate channel, and SUBMIT Trouble Report to Instrumentation &

Control Department.

14. To determine ACTION Statement requirements, Refer To the following LCOs:

ATC

• TS 3.2.6 (for DNB)

• TS 3.3.3.5 (for HSD or C-21)

• TS 3.3.3.8 (for Acc Monitoring)

• TS 3.4.4 (LT110X Only)

• TRM 7.1.4 (LT110X Only) 13 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _4__

Event

Description:

Failure of Control Ch. X PZR Level (low)

Time Position Applicants Actions or Behavior Review Technical Specifications:

LCO 3.2.6 (DNB): The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the limits specified in the CORE OPERATING LIMITS REPORT.

ACTION:

With any of the above parameters exceeding its specified limits, restore the parameter to within its above specified limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Examiner Note: Impacted only if RCS pressure dropped below 2225 psia.

TS 3.3.3.5 (HSD): The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With the number of OPERABLE remote shutdown monitoring instrumentation channels less than required by Table 3.3-9, either:

c. Restore the inoperable channel to OPERABLE status within 7 days, or

d. Be in HOT SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SRO Examiner Note: The SRO should note that one of the two channels of PZR Level on C-21 is not OPERABLE. However, Table 3.3-9 only requires one channel be OPERABLE, which there still is (L110Y). Therefore, the TS is still met.

TS 3.3.3.8 (Acc. Monitoring): SRO should note that this TS is Not Applicable.

TS 3.4.4 (PZR): The pressurizer shall be OPERABLE with:

a. Pressurizer water level 70%, and

b. At least two groups of pressurizer heaters each having a capacity of at least 130 kW.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With only one group of pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Examiner Note: The SRO should note the need to log into TSAS a at the approximate time the Proportional Heater breakers tripped, and log out at the approximate time they were reclosed.

14 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _4__

Event

Description:

Failure of Control Ch. X PZR Level (low)

Time Position Applicants Actions or Behavior TRM 7.1.4 (App R Safe Shutdown): The Appendix R Safe Shutdown Related (ARSR) equipment listed in the TRM Table 7.1.4-1 shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, 3, and 4.

Examiner Note: SRO should note the need to reference the TRM when time allows, as the requirements for these actions are not applicable unless the component is not functional for 14 days.

ACTION:

With an ARSR component listed in the above referenced component table nonfunctional (unable to meet its intended Appendix R shutdown function), take the ACTION as specified in the above table under Compensatory Measures.

SRO Examiner Note: Only applicable part of the Table 7.1.4-1 is included.

TR FUNCTIONALITY Compensatory Measures if Comp ID Item Description Component Not Restored in 14 days E LT-110X Loop LT-110X must With loop LT-110X nonfunctional be FUNCTIONAL from Control Room, perform from Control Room. ACTIONS b.1, b.2 for fire area R-2, R-10, and R-15.

Examiner Note: The above Compensatory Measures, contained on TRM page 7.1-1, can be discussed at the Examiners discretion, or following the completion of the scenario.

Examiner Note: When all Pressurizer heater breakers have been reclosed and the SRO has finished evaluating Technical Specifications and the TRM, or at lead examiners direction, proceed to Event 5, Main Condenser Vacuum Leak.

15 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 5, Main Condenser Vacuum Leak.

Indications:

• COND VACUUM LO {PPC, C-06/7, A-37}

• Condensate pressure indicator and recorder show an unexplained rise in condenser pressure.

{PPC, C-05}

• Unexplained drop in electric megawatts.

Examiner Note: The following steps are from ARP 2590E-185, COND VACUUM LO, C-06/7, A-37 annunciator.

AUTOMATIC FUNTIONS

1. None CORRECTIVE ACTIONS

1. IF condenser pressure rise is due to slow fouling of the condenser due to seasonal changes, Refer To OP 2204, Load Changes, and REDUCE Reactor power and turbine load to clear COND VACUUM LO annunciator.

2. IF degraded condenser vacuum is being directed during performance of a SRO/BOP power ramp, PERFORM the following:

2.1. NOTIFY personnel controlling condenser pressure of the alarm, the value, and trend of condenser pressure.

2.2. DIRECT personnel controlling condenser pressure to recover vacuum to the applicable control band.

3. IF steps 1. or 2. recover condenser vacuum, EXIT this ARP.

4. Go To AOP 2574, Loss of Condenser Vacuum.

Examiner Note: Operators should enter AOP 2574, Loss of Condenser Vacuum, prior to beginning a plant downpower, as there was no reason given to suspect condenser fouling.

Examiner Note: The following steps are from AOP 2574, Loss of Condenser Vacuum.

16 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior 3.1 IF ANY of the following conditions exist:

• Reactor power and turbine load is lowered to 30% power AND condenser pressure is still greater than 5 inches of mercury absolute

• Condenser pressure is approaching trip setpoint (7.5 inches of mercury absolute) AND reactor power is greater than or equal to 15%

SRO PERFORM the following:

a. Manually TRIP the reactor and turbine.

b. Go To EOP 2525, Standard Post Trip Actions.

NOTE When power is less than 15% AND level 1 bistable light clears (not lit), on at least 3 RPS channels, the turbine trip is inhibited and turbine trip will not result in an automatic reactor trip.

3.2 IF condenser pressure is approaching trip setpoint (7.5 inches of mercury absolute) AND reactor power is less than 15%, with turbine trip bypassed, manually TRIP the turbine.

3.3 IF condenser pressure is rising to 10 inches of mercury absolute, PERFORM the following:

a. ENSURE reactor power less than 3%.

b. Refer To OP 2322, Auxiliary Feedwater System, and INITIATE AFW flow to SGs.

c. TRIP running SGFPs.

3.4 IF, at any time, efforts to restore vacuum are not successful, Refer To AOP 2575, Rapid Downpower, and LOWER reactor power and turbine load at the maximum attainable rate until pressure stabilizes.

3.5 NOTIFY ISO New England of the loss or imminent loss of unit.

4.1 VERIFY performance of condenser air removal as follows:

a. VERIFY F55A or F55B operating

b. VERIFY condenser air removal fan discharge path is aligned per ONE of the following:

BOP

• EB-55 AND EB-56, condenser air removal to Millstone stack, are open

• EB-57, condenser air removal to Unit #2 stack, is open

c. VERIFY the operating SJAE steam supply pressure is 200- 220 psig.

d. Refer To OP 2329, Condenser Air Removal, and VERIFY both sets of SJAEs in service.

17 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior NOTE Use of the mechanical vacuum pumps may cause a rise in backpressure and mask the original leak and may cause the East condenser pit sump to overflow.

4.2 IF condenser backpressure is greater than 4 inches Hg absolute, PERFORM the following:

a. START mechanical vacuum pumps A and B.

b. VERIFY local vacuum gage is 27 inches Hg or greater.

c. OPEN 2- AR- 11, MECHANICAL VACUUM PUMP COMBINED SUCTION.

d. OPEN 2- AR- 12A, PUMP A SUCTION STOP.

e. OPEN 2- AR- 12B, PUMP B SUCTION STOP.

f. IF condenser air removal fan, F55A, is available, THEN PERFORM the following:

1) START condenser air removal fan, F55A.

2) STOP condenser air removal fan, F55B.

3) ENSURE EB- 171, MAKE- UP DMPR, is closed.

Simulator operator: When asked, SJAE supply pressure is ~210 psig and both sets of SJAEs are in service (do NOT put the second set in service).

If BOP directs a PEO to align the mechanical vacuum pumps, wait a couple minutes and then say the pumps have been aligned per Step 4.2 (do NOT actually perform the alignment).

• • • Activate Event-6 to lower FW01 to 0.3 ***

Examiner Note: At some point the Unit Supervisor should determine that efforts to restore vacuum are not being successful, enter AOP 2575, Rapid Downpower, and direct a reactor and turbine shutdown in an attempt to lower the main condenser heat loading.

Examiner Note: The following steps are from AOP 2575, Rapid Downpower, Section 3.0 Rapid Downpower.

SRO Enters AOP 2575, Rapid Downpower 18 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior 3.1 PERFORM focus brief on the following:

REACTOR TRIP CRITERIA

• Parameters associated with automatic reactor or turbine trips are challenged

• RCS T cold not within 10°F of temperature program and efforts to regain control are unsuccessful SRO RCS TEMPERATURE CONTROL

• RCS T cold to be maintained within 10°F of Attachment 5, Temperature vs. Power program using Attachment 10, Main Turbine Load Set Control.

• To avoid uncontrolled cooldowns or power transients, sudden changes in RCS temperature or boron concentration should be avoided.

3.2 REQUEST SM/STA to Refer To Attachment 8, Required Notifications, and PERFORM notifications.

ATC 3.3 INITIATE forcing pressurizer sprays.

CAUTION In the case of a dropped CEA, rod motion is not used to initiate downpower.

3.4 IF not downpowering due to a dropped rod, INSERT Group 7 CEAs 10 + 2 ATC steps to initiate downpower.

3.5 Using the Load Speed Control switch, REDUCE turbine load to maintain Tc BOP on program (+/-2 deg).

SRO 3.6 Refer To PPC or Reactor Engineering Curve and Data Book and OBTAIN reactivity plan for the initial reactor power condition and desired load reduction.

Examiner Note: The crew should refer to Reactivity Plan for downpower parameters.

19 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior NOTE Attachment 10 Approximate Load Demand vs. Reactor Power, can be used to correlate the desired power level to a turbine load demand setpoint.

3.7 Refer To Attachment 9, Main Turbine Load Set Control, REDUCE turbine BOP load and MAINTAIN Tc on program (+/-2 deg).

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Attachment 9 Main Turbine Load Set Control:

CAUTION Operation of the Load/Speed CONTROL switch will change turbine BOP NOTE Steps provided in this attachment are dependent on plant conditions

1. IF desired to commence or modify a turbine load ramp, PERFORM the following (HMI Load screen):

a. IF previous ramp has stopped, SELECT Load Hold.

BOP b. SELECT Load Setpt and ENTER desired value.

c. SELECT Rate setpt and ENTER desired value.

d. WHEN ready to commence load reduction, SELECT Load Resume.

20 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior BOP 2. IF desired to adjust the Load Ramp Rate, PERFORM any of the following:

• SELECT Rate setpt and ENTER new value.

• SELECT 5% / hour, OR 10% / hour, OR 20% / hour.

• SELECT Raise or Lower (0.25% / hour change).

a. IF Tavg and Tc are high off program, PERFORM the following:

a. SELECT Load Hold to stop ramp.

b. WHEN Tavg and Tc are trending back to program, SELECT Load Resume.

b. IF Tavg and Tc are low off program, PERFORM the following:

a. JOG the Load/Speed CONTROL switch to Lower.

b. WHEN Tavg and Tc are back on program, SELECT Load Setpt and ENTER desired value.

c. IF desired, Go To Step 1 and RESUME turbine load ramp.

c. IF desired load has been reached SELECT Load Hold.

Examiner Note: operator should select x load setpoint, x load rate. Program band for Tavg and Tc is x (+/- 2 deg for Tc).

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Section 3.0 Rapid Downpower.

3.8 Based on required rate of downpower, START additional charging pumps as ATC necessary and balance charging and letdown.

21 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior ATC 3.9 IF desired to borate from the RWST (preferred method)

PERFORM the following:

a. ENSURE at least one charging pump operating.

b. ENSURE CH-196, VCT makeup bypass, closed.

c. ENSURE CH-504, RWST to charging suction, open.

d. OPEN CH-192, RWST isolation.

e. CLOSE CH-501, VCT outlet isolation.

f. CHECK charging flow at desired rate.

g. Go To step 3.11 Examiner Note: Crew should borate from the RWST.

SRO/ATC/ 3.11 During the downpower, Refer To Attachment 1,Rapid Downpower BOP Parameters, and MAINTAIN parameters as specified throughout downpower:

Examiner note: Attachment 1 Rapid Downpower Parameters:

• Condensate and heater drain flows and pressures: sufficient to maintain adequate SGFP suction pressure

• FRV D/P: greater than 40 psid

• Turbine load: responding to changes in load demand, with control valves operating together

• Steam generator levels 55 to 70%.

• MSR parameters tracking together

• Turbine Generator MVARs: as specified by CONVEX

• Reactor power: being monitored using delta T power indication

• ASI: In accordance with reactivity plan or within 0.01 of ESI or per COLR.

• CEA position: greater than PDIL

• Tc: less than or equal to 549 deg

• Pressurizer level: between 35 and 70%

Pressurizer pressure: between 2,225 and 2,300 psia (DNB margin) 22 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _5, 6__

Event

Description:

Main Condenser Vacuum Leak Time Position Applicants Actions or Behavior SRO/ATC NOTE

1. Xenon rate of change should be considered when terminating boration.

2. During rapid downpower, the PPC calorimetric may be inaccurate due to SG level transients. The most accurate available indication of reactor power is RPS delta T power.

Examiner Note: Once power has dropped at least 5%, or at the lead examiners direction, proceed to Event 7, RCP trip and ATWS 23 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7, 8__

Event

Description:

RCP trip, ATWS and total loss of condenser vacuum.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 7 & 8, A RCP seize and trip, ATWS, Loss of MFW.

Indications:

• RCP A MOTOR TRIP {C-02/3, AA-17}

• RCP LO SPEED TRIP CH A {C-04, AA-4}

• RC LO FLOW TRIP CH * {* = All four Channels, A - D; C-04: CA-2, CB-2, DA-2, DB-2}

Examiner Note: An operator should attempt to trip the reactor using the manual pushbuttons. The reactor will not trip because the pushbuttons fail. An operator will open the CEDMS output breakers to trip the reactor manually.

CRITICAL TASK: Manually Shutdown the reactor. The reactor must be manually tripped using the CEDM output breakers immediately (within approximately 1 minute) when an automatic reactor trip fails and/or the manual push buttons do NOT work. (CT-1/SPTA-5)

Time that manual pushbuttons attempted: ___________

Time of MG Set Breakers opened (reactor trip):___________

• Reports alarms on A RCP, RCP tripped

• Reactor failure to auto trip, tripping the reactor manually by push buttons ATC

• Failure of TCBs to manually open, opening MG Set supply breakers (CT)

• Reactor trip successful, CEAs inserting.

SRO Acknowledge need to trip, directs (or acknowledges) reactor trip Examiner Note: The following steps are from EOP 2525, Standard Post Trip Actions, modified slightly to improve clarity.

Determine Status of Reactivity Control - Reactor Trip

1. DETERMINE that Reactivity Control acceptance criteria are met for the ATC reactor by performing ALL of the following steps:

• CHECK that all CEAs are fully inserted.

• CHECK that reactor power is dropping.

• CHECK that SUR is negative.

24 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7, 8__

Event

Description:

RCP trip, ATWS and total loss of condenser vacuum.

Time Position Applicants Actions or Behavior Determine Status of Reactivity Control - Turbine Trip

2. DETERMINE that Reactivity Control acceptance criteria are met for the turbine by performing ALL of the following steps :

a. CHECK that the main turbine is tripped by BOTH of the following:

BOP

• ALL main stop valves are closed.

• Generator megawatts indicate zero.

• Turbine speed is lowering.

b. IF 15G-2XI-4, motor operated disconnect, is closed, CHECK that the main Generator output breakers 8T and 9T are open.

Determine Status of Maintenance of Vital Auxiliaries

3. DETERMINE that Maintenance of Vital Auxiliaries acceptance criteria are met by performing ALL of the following steps:

a. CHECK that ALL Facility 1 and 2 electrical buses are energized:

• 6.9kV Electrical Buses 25A, 25B

• 4.16kV Non-Vital Electrical Buses 24A, 24B BOP

• 4.16vV Vital Electrical Buses 24C, 24D

• Vital DC Buses 201A, 201B, DV-10, DV-20

• Vital AC Instrument Buses VA-10, VA-20

b. CHECK that BOTH facilities of service water are operating.

c. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

25 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7, 8__

Event

Description:

RCP trip, ATWS and total loss of condenser vacuum.

Time Position Applicants Actions or Behavior Determine Status of RCS Inventory Control ATC

4. DETERMINE that RCS Inventory Control acceptance criteria are met by performing ALL of the following:

a. CHECK that BOTH of the following conditions exist:

• Pressurizer level is 20 to 80%

• Pressurizer level is trending to 35 to 70%

a.1 IF the Pressurizer Level Control System is not operating properly in automatic, RESTORE and MAINTAIN pressurizer level 35 to 70% by performing ANY of the following:

1) OPERATE the Pressurizer Level Control System.

2) Manually OPERATE charging and letdown.

b. CHECK that RCS subcooling is greater than or equal to 30°F Determine Status of RCS Pressure Control

5. DETERMINE RCS Pressure Control acceptance criteria are met by BOTH of ATC the following:

• CHECK that pressurizer pressure is 1900 to 2350 psia.

• CHECK that pressurizer pressure is trending to 2225 to 2300 psia.

Determine Status of Core Heat Removal

6. DETERMINE that Core Heat Removal acceptance criteria are met by performing ALL of the following:

a. CHECK that at least one RCP is operating and that loop delta T is less ATC than 10°F

b. CHECK that Th subcooling is greater than or equal to 30°F.

26 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7, 8__

Event

Description:

RCP trip, ATWS and total loss of condenser vacuum.

Time Position Applicants Actions or Behavior Determine Status of RCS Heat Removal

7. DETERMINE that RCS Heat Removal acceptance criteria are met by ALL of the following conditions:

a. CHECK that at least one steam generator has BOTH of the following BOP conditions met:

• Level is 10 to 80%.

• Main feedwater or TWO auxiliary feedwater pumps are operating to restore level 40 to 70%.

b. CHECK that RCS Tc is being maintained between 530°F to 535"F.

c. CHECK that BOTH steam generators pressure are 880 to 920 psia.

Examiner Note: Once the BOP has established AFW flow to each SG, or at the lead examiners direction, proceed to Event 9, Loss Of All Feedwater 27 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 9, Rupture of both AFW Headers, LOAF.

Indications:

• Aux Feed flow indication to both SGs will be < 300 gpm (minimum required).

• EAST COND PIT SUMP LVL HI {C-06/7, CA-22)

7. a. RNO a.1 RESTORE level to 40 to 70% in at least one steam generator using ANY of the following:

BOP

• Motor- driven auxiliary feedwater pump.

• TDAFW Pump. Refer To Appendix 6, TDAFW Pump Normal Startup.

Examiner Note: The BOP should report the loss of all feed to the SGs, due to loss of Aux. Feedwater flow, prior to the transition to an event specific EOP.

Examiner Note: The AFW rupture is simulated as a severe break in the body of FW-44, the cross-connect valve for the two AFW headers and closing the valve will have no effect on the loss of the two headers. The Simulator Operator will report this as a PEO sent to investigate the problem.

Simulator Operator: When a PEO is sent to investigate the problem, inform the crew that the body of FW-44 has a large crack and is leaking badly. Also, due to the nature of the break, you doubt that closing FW-44 will have any effect on the leak.

After Aux. Feed flow is established, if the rupture is not recognized by the crew and an operator is not dispatched, report as the Turbine Building Watch the above conditions.

28 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior Determine Status of Containment Isolation ATC

8. DETERMINE that Containment Isolation acceptance criteria are met by ALL of the following:

a. CHECK that containment pressure is less than 1.0 psig.

b. CHECK that NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Radiation Monitors Inside Containment RM-7890, Personnel Access Area RM-7891, Ctmt Refuel Floor Area RM-8240, High Range RM-8241, High Range RM-8123 A and B, Ctmt Atmosphere RM-8262 A and B, Ctmt Atmosphere

c. CHECK that NONE of the following steam plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Steam Plant Radiation Monitors RM-5099, Steam Jet Air Ejector RM-4262, SG Blowdown RM-4299A and B, Main Steam Line 1 RM-4299C, Main Steam Line 2 Determine Status of Containment Temperature and Pressure Control

9. DETERMINE that Containment Temperature and Pressure Control acceptance criteria are met by BOTH of the following steps:

ATC

a. CHECK that containment temperature is less than 120°F. (PPC or avg. of Points 5 and 6)

b. CHECK that containment pressure is less than 1.0psig.

10. PERFORM the following:

a. DIAGNOSE the event. Refer To Appendix 1, "Diagnostic Flowchart."

SRO b. INITIATE Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions."

c. Go To the appropriate EOP 29 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior

{Step 10.b above}

Perform Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions".

ATC/BOP Examiner Note: EOP Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions." are attached to guide.

Examiner Note: The Unit Supervisor refers to EOP 2541 Appendix 1, Diagnostic Flowchart to diagnose the event.

Enters EOP 2537, Loss Of All Feed.

SRO Examiner Note: The following steps are from EOP 2537 Loss Of All Feedwater. Asterisked steps, within the ORP or selected FRPs being implemented, may be brought forward to restore or preserve a Safety Function. Asterisked steps are Continuously Applicable, and may be performed out of order after they have been accomplished once.

• 1. CONFIRM diagnosis of a Loss of All Feedwater by performing the following.

SRO Examiner Note: SRO checks EOP 2537-001 LOAF Safety Function Status Checks and confirms that all Safety Criteria are satisfied.

• 2. CLASSIFY the event. Refer To MP-26-EPI-FAP06, Classification and PARs SRO IF classification requires RCS sampling, Refer To Appendix 46, Sampling for EAL Determination and DIRECT Chemistry as required.

• 3. PERFORM ALL of the following:

SRO

• OPEN the placekeeper and ENTER the EOP entry time.

• ENSURE the master alarm silence switch is in NORMAL.

• 4. PERFORM the following:

a. STOP ALL RCPs.

b. PLACE HIC- 4165, steam dump TAVG controller, in manual AND closed.

ATC c. PLACE the following pressurizer spray valve controllers in manual and CLOSE the valves:

• HIC- 100E

• HIC- 100F 30 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior

• 5. PERFORM ALL of the following to conserve steam generator inventory:

a. ENSURE MS- 220A, blowdown isolation valve is closed.

BOP b. ENSURE MS- 2206, blowdown isolation valve is closed.

c. CLOSE BOTH steam generator sample isolation valves:

• MS- 191A

• MS- 1918 NOTE OTC should be initiated prior to ONE steam generator wide range level reaching 70 inches, AND ONE steam generator wide range level reaching 165 inches if ANY of the following exist:

1. Main or auxiliary feedwater is not expected to be restored.

2. Less than TWO trains of HPSI, PORVs and ADVs are available.

3. Less than THREE charging pumps are available.

• 6. CHECK for adequate RCS heat removal via the steam generators by BOTH of the following:

• BOTH steam generator wide range levels are greater than 70 inches

• RCS Tc stable or controlled within 5°F or less 6.1 Contingency Actions:

IF steam generator level is not restoring AND ANY of the following BOP conditions exists:

• ONE steam generator wide range level less than or equal to 70 inches AND the REMAINING steam generator wide range level is less than or equal to 165 inches

• RCS TC rises uncontrollably by 5°F or more ESTABLISH heat removal via once- through- cooling by performing ALL of the following:

1. ENSURE ALL proportional heaters are tripped

2. ENSURE ALL backup heaters in PULL- TO- LOCK.

3. IF main condenser is available,THEN OPEN ALL steam dump valves.

4. OPEN BOTH ADVs.

5. ENSURE SIAS actuated.

6. ENSURE BOTH HPSI pumps have started.

7. ENSURE that ALL HPSI loop injection valves are open.

8. ENSURE that ALL available charging pumps are running.

9. ENSURE that BOTH PORV block valves are open.

10. WHEN at least ONE HPSI pump has started, THEN OPEN BOTH PORVs. (Key # 187)

11. Go To EOP 2540, Functional Recovery.

31 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior CRITICAL TASK: Once-Through-Cooling (OTC) shall be fully implemented (both ADVs open, both PORVs open, and two trains of HPSI in operation) prior to either SG level lowering to less than 32 inches wide range level. (CT-2/ OP 2260, EOP Users Guide, Attachment 7, Operator Actions #2]

Steam Generator Level when feed flow was restored or OTC was fully implemented:

Steam Generator 1 Level: ___________

Steam Generator 2 Level: ___________

Examiner Note: The US may decide to use the Once-Through-Cooling success path if all three condensate pumps were secured in error or he feels conditions warrant. In that instance, RNO 6.1 is used for that path. Once complete, the crew will transition to EOP 2540 and the scenario is complete.

RNO (CONTINGENCY ACTIONS) 6.1 IF steam generator level is not restoring AND ANY of the following conditions exists:

• ONE steam generator wide range level less than or equal to 70 inches AND the REMAINING steam generator wide range level is less than or equal to 165 inches ATC

• RCS TC rises uncontrollably by 5°F or more ESTABLISH heat removal via once- through- cooling by performing ALL of the following:

6.1 ENSURE ALL proportional heaters are tripped.

a. ENSURE ALL backup heaters in PULL- TO- LOCK.

b. IF main condenser is available, THEN OPEN ALL steam dump valves.

c. OPEN BOTH ADVs.

d. ENSURE SIAS actuated.

e. ENSURE BOTH HPSI pumps have started.

RNO (CONTINGENCY ACTIONS) 6.1 (continued)

f. ENSURE that ALL HPSI loop injection valves are open.

g. ENSURE that ALL available charging pumps are running.

ATC h. ENSURE that BOTH PORV block valves are open.

i. WHEN at least ONE HPSI pump has started, THEN OPEN BOTH PORVs.

(Key # 187)

j. Go To EOP 2540, Functional Recovery.

Examiner Note: If the crew uses the Once-Through-Cooling success path, once it is implemented and the US transitions to EOP 2540, the remainder of EOP 2537 is N/A. Go to Page 36 for EOP 2540 steps.

32 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior

• 7. WHEN feedwater source becomes available, THEN RESTORE feedwater to the affected steam generators as follows:

a. CHECK steam generator level is less than 33%.

a.1 FEED affected steam generators at any desired flow rate to restore and maintain level within 40% to 70%.

b. FEED each affected steam generator by raising feedwater flow rate in increments of 50 gpm within BOTH of the following limits:

BOP

• Flow limited to wi thin the capacity of the available feedwater source

• Maximum flow rate of less than, or equal to 650 gpm, (325 klbm/hr).

c. WHEN ANY of the following conditions are met:

• Steam generator shows a rising trend

• Feedwater flow rate has been established within the capacity of the available feedwater source, with a maximum flow rate of less than, or equal to 650 gpm, (325 klbm/hr).

• Steam generator level is greater than 33%

THEN FEED affected steam generators at any desired flow rate, within the capacity of the available feedwater source, to restore and maintain level within 40% to 70%.

• 8. IF a main feedwater line break is indicated, ISOLATE the affected portion of the main feedwater system by performing the following:

a. PLACE applicable main feed isolation air assisted check valve, to "CLOSE":

• FW- 5A

• FW- 5B

b. ENSURE applicable main feedwater block valve, is closed:

BOP

• FW- 42A

• FW- 42B

c. CLOSE applicable main feedwater regulating bypass valve:

• LlC- 5215

• LlC- 5216

d. IF leak is in common section of feedwater piping, SECURE BOTH main feedwater pumps.

e. ESTABLISH feedwater to the unaffected header.

f. SECURE steaming the steam generator with feedwater isolated.

• 9. IF a auxiliary feedwater line break is indicated, ISOLATE the affected portion of the auxiliary feedwater system by performing the following:

a. CLOSE FW - 44, auxiliary feedwater cross- connect valve.

BOP b. STOP ANY auxiliary feedwater pumps on the side with the affected header.

c. ESTABLISH feedwater to the unaffected header.

d. SECURE steaming the steam generator with feedwater isolated.

33 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior Examiner Note: The simulated AFW rupture cannot be isolated; therefore, all AFW pumps must be secured.

• 10. IF offsite power has been lost, OR the condenser is not available, PERFORM the following:

a. CLOSE BOTH MSIVs:

• MS - 64A SRO

• MS- 648

b. ENSURE BOTH MSIV bypass valves are closed:

• MS - 65A

• MS - 658

c. OPEN AR- 17, condenser vacuum breaker.

• 11. RESTORE feedwater flow to at least ONE steam generator using the motor-SRO driven AFW pumps as follows:

Examiner Note: Step 11 is N/A due to the actions taken in Step 9 to isolate the AFW rupture.

• 12. IF auxiliary feedwater flow is restored, Go To step 23.

SRO Examiner Note: Step 12 is N/A

• 13. RESTORE feedwater flow to at least one steam generator using the TDAFW SRO pump as follows Examiner Note: Step 13 is N/A

• 14. IF auxiliary feedwater flow is restored, Go To step 23.

SRO Examiner Note: Step 14 is N/A

• 15. START ONE SG feedwater pump by performing the following for the pump SRO to be started:

Examiner Note: Step 15 is N/A due to the loss of condenser vacuum.

• 16. IF SG feedwater flow is restored, Go To step 23.

SRO Examiner Note: Step 16 is N/A Examiner Note: The SRO may quickly proceed to Step 17 once the nature of the feedwater loss is understood.

• 17. ENSURE at least ONE condensate pump is running.

BOP 34 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior

• 18. ESTABLISH a flowpath from the hotwell to at least ONE steam generator as follows:

a. ENSURE BOTH SGFP discharge valves are open:

• FW- 38A

• FW- 38B

b. CLOSE BOTH SGFP "MIN FLOW RECIRC":

• FIC- 5237 BOP

• FIC- 5240

c. OPEN CNM-2, CPF bypass valve.

d. OPEN BOTH main feed reg bypass valves:

• LIC-5215

• LIC-5216

e. ENSURE BOTH main feed isolation air assisted check valves are open:

• FW-5A

• FW-5B

• 19. IF SIAS is not present AND SIAS Block is permitted, THEN BLOCK the BOP automatic initiation as the cooldown and depressurization proceeds.

Examiner Note: The crew should block SIAS as the event does not warrant its actuation.

• 20. IF MSI is not present AND MSI Block is permitted, THEN BLOCK the BOP automatic initiation as the cool down and depressurization proceeds.

Examiner Note: The crew should block MSI as its actuation will delay feed flow restoration.

• 21. IF a flowpath from the hotwell to a steam generator is established, THEN BOP DEPRESSURIZE at least ONE steam generator at the maximum controllable rate, until adequate feed flow is obtained from the condensate pump to restore steam generator level.

• 22. COMMENCE emergency boration.

ATC Refer To Appendix 3, "Emergency Boration."

• 23. IF feed flow is restored, RESTORE and MAINTAIN 40 to 70% level in at BOP least one steam generator.

Scenario Termination: When crew has restored feedwater flow to one SG, or at the lead examiners direction, the scenario is complete.

35 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior Examiner Note: If OTC is initiated in EOP 2537, Loss Of All Feedwater, once initiated, the US will transition to EOP 2540, Functional Recovery.

The following steps are from EOP 2540, Functional Recovery.

Indications:

• #2 S/G Pressure

• RCS Cold Leg Temperature

• Sub Cool Margin

1. CLASSIFY the event. Refer To MP-26-EPI-FAP06, Classification and PARs SRO

• IF classification requires RCS sampling, Refer To Appendix 46, Sampling for EAL Determination and DIRECT Chemistry as required.

Examiner Note: Classified as an Alert/C-1; Equipment Failure, EA1, ATWS w/ Successful Manual Trip.

Also, Alert/C-1; RCS Barrier, RCB2 Loss (RCS Subcooling < 30°F)

2. PERFORM ALL of the following:

SRO

• OPEN the Safety Function Tracking Page and ENTER the EOP entry time.

• ENSURE the master alarm silence switch is in NORMAL.

3. IF pressurizer pressure is less than 1714 psia AND SIAS has initiated, PERFORM the following:

a. ENSURE ONE RCP in each loop is stopped.

b. PLACE associated pressurizer spray valve controller RC-100E or RC-100F in manual and CLOSE the valve.

ATC c. IF pressurizer pressure lowers to less than the minimum RCP NPSH limit, PERFORM the following:

1) STOP ALL RCPs.

2) PLACE TIC-4165, steam dump TAVG controller, in manual and closed.

3) PLACE pressurizer spray valve controllers RC-100E and RC-100F in manual and CLOSE the valves.

36 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior

4. SAMPLE steam generators that are available for RCS heat removal as follows:

a. CHECK B train RBCCW in service.

b. ENSURE 2-RB-210 Degasifier Effluent Cooler Return Outlet is open.

c. OPEN appropriate steam generator sample valves:

• MS-191A

• MS-191B

d. DIRECT Chemistry to perform ALL of the following:

BOP

• Sample ANY steam generator that is available for RCS Heat Removal

• Frisk the samples

• Report frisk results

• Analyze samples for boron and activity

e. WHEN Chemistry reports that samples have been taken, PERFORM the following:

• CLOSE the steam generator sample valves

• IF SIAS has actuated, AND no other sampling is in progress, CLOSE 2-RB-210, Degasifier Effluent Cooler Return Outlet CUE: When directed to sample Steam Generators, respond 20 minutes later that samples have been taken. Report that frisk results show all background levels.

5. PLACE the hydrogen analyzers in service. Refer To Appendix 19, Hydrogen BOP Analyzer Operation.

NOTE If the Safety Function Status Checklist is not satisfied for the selected success path, the US may commence the operator actions for safety functions which are not met based on Safety Function hierarchy. The remaining Safety Functions SRO should be prioritized as time permits.

6. IDENTIFY success paths to be used to satisfy each safety function using BOTH SRO of the following:

• Resource Assessment Trees

• Safety Function Tracking Page 37 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior

7. PRIORITIZE safety functions to be addressed first based on ALL of the following:

a. Safety functions which do not meet the Safety Function Status Checklist for the selected success path.

b. Safety functions for which the equipment to support the success path is SRO not operating.

c. Safety functions for which success path three has been selected.

d. Safety functions for which success path two has been selected.

e. Safety functions for which success path one has been selected.

NOTE: SRO will direct the Board Operators through the Resource Assessment Trees and query plant status to determine the correct Functional Procedure to use.

4.0 SAFETY FUNCTION STATUS CHECKLIST SAFETY FUNCTION TRACKING PAGE EOP ENTRY TIME __________

SRO Safety Function Success Path Procedure SFSC Priority Met RC-1 CEA Insertion Y Reactivity RC-2 Boration CVCS EOP 2540A 4 Control RC-3 Boration SI Maintenance of Battery Chargers/ Y MVA-DC-1 EOP 2540B 5 Vital DC Power Station Batteries MVA-AC-1 RSST Y Maintenance of MVA-AC-2 EDG 6 EOP 2540B Vital AC Power MVA-AC-3 BUS 34A/34B RCS Inventory IC-1 CVCS EOP 2

Control IC-2 Safety Injection 2540C1 Y PC-1 Subcooled RCS Pressure PC-2 Saturated EOP Y 3 Control 2540C2 PC-3 PORVs HR-1 SI no operating RCS Core Heat SRO HR-2 SI operating 1 Removal EOP 2540D HR-3 O-T-C Y Containment Automatic /

CI-1 Manual EOP 2540E Y 7 Isolation 38 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _9__

Event

Description:

Rupture of Auxiliary Feedwater Headers resulting in Loss Of All Feedwater flow Time Position Applicants Actions or Behavior Containment CTPC-1 CARs (Normal) Y 8 May be #4 if SRO Temperature and EOP 2540F May be Y CTMT Pressure Control CTPC-2 CARs (Emerg) >4.42psi if >4.42psi SRO 8. DIRECT the STA to check that Safety Function Status Checklist Criteria are satisfied for chosen success paths.

9. PERFORM operator actions for chosen success paths based on priority assigned.

Examiner Note: The US should transition to EOP 2540D, Functional Recovery of Heat Removal, Success Path HR-3 at which time the scenario is complete.

39 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7__

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior Examiner Note: The following steps are from EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions.

1. IF charging pumps suction is aligned to the VCT, THEN CHECK VCT level is between 72% to 86%:

a. IF VCT level is less than 72%, THEN ALIGN charging pump suction to RWST as follows:

ATC 1) OPEN CH- 192, RWST isolation.

2) ENSURE CH- 504, RWST to charging suction is open.

3) CLOSE CH- 501, VCT outlet isolation.

4) ENSURE CH- 196, VCT makeup bypass is closed.

b. IF VCT level is greater than 88%, THEN PLACE CH- 500, letdown divert handswitch, to the RWS position, and divert as required to maintain VCT level 72% to 86%.

2. TCOA: IF SIAS actuated, THEN ENSURE ONE complete facility of CRAC operating, in RECIRC mode, as follows: (C25A/B)

Facility 1

• HV- 203A, Fan F- 21A exhaust damper open

• Fan F- 21A, supply fan running

• HV- 206A, Fan F- 31A exhaust damper open

• Fan F- 31A, exhaust fan running

• HV- 212A, Fan F- 32A exhaust damper, open

• Fan F- 32A, filter fan, running

• HV- 202, minimum fresh air damper, closed ATC

• HV- 207, cable vault exhaust damper, closed

• HV- 208, exhaust air damper, closed Facility 2

• HV- 203B, Fan F- 21B exhaust damper open

• Fan F- 21B, supply fan running

• HV- 206B, Fan F- 31B exhaust damper open

• Fan F- 31B, exhaust fan running

• HV- 212B, Fan F- 32B exhaust damper, open

• Fan F- 32B, filter fan, running

• HV- 495, fresh air damper, closed

• HV- 496, exhaust air damper, closed

• HV- 497, cable vault exhaust damper, closed 40 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7__

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior

3. TCOA: IF SIAS not actuated, THEN CHECK ONE facility of CRAC operating, in NORMAL mode, as follows: (C25A/B)

Facility 1

• HV- 203A, Fan F- 21A exhaust damper is open

• Fan F- 21A, supply fan running ATC

• HV- 206A, Fan F- 31A exhaust damper open

• Fan F- 31A, exhaust fan running Facility 2

• HV- 203B, Fan F- 21B exhaust damper open

• Fan F- 21B, supply fan running

• HV- 206B, Fan F- 31B exhaust damper open

• Fan F- 31B, exhaust fan running

4. IF charging pumps suction aligned to the RWST AND boration not required, THEN RESTORE charging pump suction to VCT as follows:

a. CHECK BOTH of the following:

ATC 1) VCT level between 72% and 86%

2) VCT pressure greater than 15 psig

b. CHECK letdown is in service.

c. OPEN CH- 501, VCT outlet isolation.

d. CLOSE CH- 192, RWST isolation.

BOP 5. CHECK instrument air pressure greater than 90 psig and stable.

6. IF AFAS has actuated, WHEN BOTH steam generators are restored to greater than 33%, THEN PERFORM the following:

a. PLACE the following switches in M (Manual) and ADJUST to obtain desired flow (C- 05):

1) FW- 43A, AFW- FCV, HIC- 5276A

2) FW- 43B, AFW- FCV, HIC- 5279A

b. PLACE BOTH of the following switches to RESET and ALLOW to spring return to neutral (C- 05):

BOP

1) OVERRIDE/MAN/START RESET (Facility 1)

2) OVERRIDE/MAN/START RESET (Facility 2)

c. ADJUST the following switches to obtain desired flow (C- 05):

1) FW- 43A, AFW- FCV, HIC- 5276A

2) FW- 43B, AFW- FCV, HIC- 5279A

d. IF main feedwater pump is supplying steam generators, THEN STOP BOTH auxiliary feedwater pumps.

Examiner Note: BOP may place both facilities in override (Pull-To-Lock) once the AFW rupture is discovered and the SRO directs AFW be secured.

41 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7__

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior

7. CHECK Main Condenser is available, as indicated by ALL of the following:

• At least ONE MSIV open

• Condenser vacuum better than 15 inches HG - ABS (0 to 15 inches)

• At least ONE condensate pump operating

• At least ONE Circ Water pump operating BOP RNO 7.1 IF Main Condenser is not available, PERFORM the following:

• CLOSE BOTH MSIVs.

• ENSURE BOTH MSIV bypass valves are closed.

• OPEN AR-17, condenser vacuum breaker.

Examiner Note: Not available due to the loss of condenser vacuum.

BOP 8. OPEN HD-106, subcooling valve.

BOP 9. ENSURE BOTH heater drain pumps stopped.

10. IF MFW is supplying feed to the steam generators, THEN PERFORM the following:

a. ENSURE that only ONE main feedwater pump is operating.

b. ENSURE that BOTH main feed block valves are closed:

1) FW- 42A

2) FW- 42B

c. ADJUST the operating main feedwater pump pressure to 50 to 150 psi greater than SG pressure.

d. ENSURE BOTH main feed reg bypass valves are throttled to control SG BOP level:

1) LIC- 5215

2) LIC- 5216

e. IF Main Feedwater Pump A is secured, THEN CLOSE the following:

1) FW- 38A, main feedwater pump discharge valve

2) FIC- 5237, main feedwater pump mini flow recirc valve

f. IF Main Feedwater Pump B is secured, THEN CLOSE the following:

1) FW- 38B, main feedwater pump discharge valve

2) FIC- 5240, main feedwater pump mini flow recirc valve Examiner Note: Loss of condenser vacuum secures both MFW pumps.

11. IF BOTH MFW pumps are secured, THEN PERFORM the following:

BOP a. CLOSE BOTH main feedwater pump mini flow recirc valves.

• FIC- 5237

• FIC- 5240 42 of 39

Op-Test No.: __ ES16LI1___ Scenario No.: __1__ Event No.: _7__

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior

12. IF 25A OR 25B is energized, THEN ALIGN condensate pumps as follows:

BOP a. ENSURE ONE pump is running.

b. ENSURE ONE pump is in PULL TO LOCK.

c. ENSURE ONE pump is in AUTO.

Examiner Note: it is important that at least one condensate pump remain running. If all three are mistakenly secured, the only success path available will be Once-Through-Cooling.

Examiner Note: End of Attachment 4- A 43 of 39

SIMULATOR SCENARIO #2 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 2 Op-Test No.: ES16LI2 Examiners: Operators: SRO ATC BOP Initial Conditions: 90% Power IC-140, No Equipment OOS, Ch-Y PZR Level in service, Fac. 2 CRAC in service.

Turnover: 90% Power, Xenon building in, no equipment OOS. 24E is aligned to 24C. Raise Power IAW OP2204 to 100%.

Critical Tasks:

1. SGTR-6; Manually establish the minimum design Safety Injection System flow.

2. SGTR-5: Isolate the affected SG.

Event No. Malf. No. Event Event Description Type*

R, N 1

N/A (ATC/S) Raise Reactor Power to 100%.

(BOP/S) 2 I, TS RP19C C RPS Lower NI Fails low.

(ATC/S) 3 C CW02D D Traveling Screen D/P high, requires securing "D" Circ. Pump.

(BOP/S) 4 RM01P I, TS CRAC Radiation Monitor, RM-9799B, fails high and B CRAC Filter CH08D (ATC/S) Fan, F-32B, Trips (TS).

5 C, TS SG01A SGTL in #1 SG (TS).

(BOP/S) 6 R N/A Down power due to SGTL.

(All) 7 M SG02B SG Tube Rupture. Manual plant trip.

(All) 8 ES03J / C C HPSI pump fails to start on SIAS. A HPSI pump is degraded SI05A (ATC/S) (100%)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 34

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 NRC 2016, Scenario 2 Summary:

The crew will take the shift with the unit at 90% Xenon slowly building in, with no equipment out of service (IC-30). The crew will begin the shift by raising power to 100%.

Event 1: The crew takes the shift and begins the power ascension to 100% power. Xenon concentration will be slowly rising requiring the Crew to initiate a dilution or reduce Turbine load to maintain RCS temperature. The Crew will be referring to OP 2204, OP 2302A, OP 2304C and OP 2208 to dilute, with draw CEAs and raise Turbine load.

Event 2: After the dilutions to raise power and at the discretion of the Examiners C RPS Nuclear Instrument fails requiring ARP actions to bypass the affected Reactor Trip Modules on Channel C and the U.S. will enter the applicable Tech. Spec.

Event 3: At the discretion of the Examiners the malfunction for the D Traveling Screen DP will be initiated causing the Traveling Screen for D Water box to ramp in above high setpoint requiring the securing of "D" Circ. Pump. The Crew will enter AOP 2517 for Circulating Water Malfunction and take actions to cross-tie C and D Water boxes by closing the D Water box inlet valve and place the tripped Circ Pump handswitch in PTL and lastly the Crew will verify Condenser vacuum <4.5 Hg.

Event 4: At the discretion of the Examiners, the Control Room Air Conditioning (CRAC) Radiation Monitor will fail high, causing the ventilation system to shift into recirculation mode. Five seconds after starting, the B Filter Fan, F32B, will trip due to a broken belt. Per ARP 2590A-159, the crew should verify proper operation of the CRAC system and note the loss of the filter fan. This will require the crew to secure Facility 2 CRAC and ensure Facility 1 CRAC is operating as required per ARP 2590A-159. The US will enter TSAS 3.7.6.1a for an inoperable train of CRAC, TSAS 3.3.3.1 for the failed rad monitor, and call Maintenance/Work Planning for the needed equipment repairs.

Event 5: At the discretion of the Examiners the malfunction for a S/G tube leak is inserted. The Crew will be alerted to a SGTL by C06/07 Alarm for N-16 HIGH and carry out the actions for the ARP and will enter AOP 2569 SGTL. The Crew will verify Reactor Trip Criteria is not exceeded but the Tech. Spec. of 75 gpd will be exceeded requiring a Reactor down power. The Crew will transition to AOP 2575 Rapid Downpower.

2 of 34

Appendix D Scenario Outline Form ES-D-1 Event 6: The crew will enter AOP 2575 Rapid Downpower. The first action for the rapid down power will require the Crew to force PZR sprays then insert Group 7 Rods 10 steps while reducing Turbine load to maintain RCS TCOLD. The Crew will then align for boration from the RWST requiring the ATC operator to start an additional Charging pump if not already started and the BOP to setup the Turbine HMI to lower load to maintain RCS TCOLD.

Event 7: During the Rapid Downpower at the discretion of the Examiner an S/G tube rupture will be inserted requiring the Crew to verify actual rupture using plant parameters and the Main Steam Line Hi alarm and direct a manually trip the Reactor.

Event 8: After the completion of EOP 2525 SPTA the crew will enter EOP 2534 SGTR and upon SIAS the C HPSI pump will fail to start and the A HPSI will be fully degraded requiring the ATC to manually start the C HPSI pump and or start the B HPSI pump to meet SI flow criteria.

INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

ID Num Description Delay Ramp Event Sev or Final Rel Time Time Time Value Value Order MALFUNCTIONS RP19C C Channel Power Range RPS fail E-2 0% 0% 2 CW02D D Traveling Screen D/P 180 sec E-3 65% 65% 3 RM01P RM-9799A CNTRL RM Radmon E-4 100% 100% 4 CH08D B CRAC Filter Fan, F32B, trip 5 sec E-4 N/A N/A 4 SG01A #1 S/G tube leak 120 sec E-5 50% 50% 5 SG02B #1 S/G tube rupture 60 sec E-7 15% 15% 7 ES03J C HPSI start fail on SIAS E-30 N/A N/A 8 SI05A A HPSI pump degradation 60 sec E-30 100% 100% 8 REMOTE FUNCTIONS CWR06B B Screen Wash Pump Start E-10 START 3 CWR07A A Screens to Fast E-10 FAST 3 CWR07B B Screens to Fast E-10 FAST 3 CWR07C C Screens to Fast E-10 FAST 3 CWR07D D Screens to Fast E-10 FAST 3 CWR07D D Screens to Stop E-11 STOP 3 OVERRIDES 3 of 34

Op-Test No.: __ES16LI2___ Scenario No.: __2__ Event No.: _1__

Event

Description:

Raise Power to 100%

Time Position Applicants Actions or Behavior Examiner Note: The crew has been instructed to brief the up power prior to taking the watch. The The following steps are from OP 2204 Load Changes. OP 2204 Load Changes procedure is marked up with N/A and Unit Supervisor signatures for applicable steps.

Up power in accordance with OP 2204 and Reactivity Plan.

Method: dilution and CEAs Rate: 15%/hour

• Crew will dilute to the charging pump suction and raise power to ~100%.

• Turbine load will be increased to maintain RCS Tavg on program.

Examiner Note: When reactor power is 5% higher than initial power or at the lead examiners direction, proceed to Event #2, Trip of C Channel of NI power instrument.

4 of 37

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _2__

Event

Description:

C RPS Lower NI Failure (low)

Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event #2, C RPS Lower NI Fails Low.

Indications Available:

• NIS CHANNEL DEVIATION HI (C-04, BA-12).

• RX POWER T CH DEVIATION (C-04, AA-8).

• TM-LP TRIP CH C (C-04, DA-3)

• LCL PWR DENSE TRIP CH C (C-04, DA-5)

• CEA DROPPED NIS (C-04, CA-18)

Examiner Note: The following steps are from ARP 2590C-089.

Examiner Note: Crew may or may not secure dilution in progress from Event #1.

AUTOMATIC FUNCTIONS

1. None CORRECTIVE ACTIONS

1. To determine the cause of alarm, OBSERVE the following:

• ASI (C-04, PPC, RPS)

• Linear power channel indications (C-04, PPC, RPS)

NOTE This alarm may be indicative of one or more of the following:

• One RPS linear power channel (4 total), deviating from the grand average signal generated by comparator average hi or hi-hi deviation setpoint ATC

• Axial offset condition

• Failure of one power range monitor channel

2. IF power range monitor has failed, PERFORM the following:

2.1 OBTAIN necessary keys and PERFORM applicable actions to bypass the following power outputs for applicable RPS channel causing alarm:

• TM/LP Trip

• High Power Trip

• Local Power Density Trip

• Turbine Trip (RPS) 2.2 LOG entry into applicable ACTION Statement(s) of T/S, 3.3.1.1.

2.3 As necessary, Refer To OP 2380, RPS and NI Safety Channel Operation, and PERFORM applicable actions to remove affected channels input to comparator averager.

5 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _2__

Event

Description:

C RPS Lower NI Failure (low)

Time Position Applicants Actions or Behavior CORRECTIVE ACTIONS (cont.)

3. IF power range control channel has failed, PLACE applicable power ration calculator input switch to OUT (rc-05e):

• IF channel X, CH 9

• IF channel Y, CH 10

4. IF any axial offset condition exists for an unknown reason, NOTIFY Reactor ATC Engineering.

5. Refer To T/S LCO 3.2.4 and DETERMINE applicable and additional actions.

6. WHEN alarm conditions clears, to reset HI DEV and HI-HI DEV alarms, Power range monitor, TOGGLE LED RESET momentarily

7. IF ALL of the following alarms are coincident with this annunciator, REQUEST I&C Department to refer to 25203-39069 sh. 23C and check ruses for interposing relay circuit in RC22:

Examiner Note: The following steps are from OP 2380, RPS and NI Safety Channel Operation.

4.3.2 IF, at any time, it is necessary to remove any power range safety channel input to comparator averager (used in computing average flux power level),

PLACE applicable switch to OFF (rear of channel A RPS):

• IF desired to remove channel A, CHANNEL 5 switch

• IF desired to remove channel B, CHANNEL 6 switch

• IF desired to remove C, CHANNEL 7 switch

• IF desired to remove D, CHANNEL 8 switch Examiner Note: Crew should place the CHANNEL 7 switch in OFF.

Examiner Note: Step 3 - 7 are N/A. SRO Should Review T/S for applicability and required action.

Refer to Tech. Spec. 3.3.1.1:

LCO 3.3.1.1 (RPS): As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

SRO APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

6 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _2__

Event

Description:

C RPS Lower NI Failure (low)

Time Position Applicants Actions or Behavior Per TS Table 3.3-1: FUNCTIONAL UNIT #2 Power Level - High; Total Number of Channels = 4, Minimum Channels Operable = 3, App. Modes = 1, 2, 3(d)

Action = 2 Action 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The SRO inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided one of the inoperable channels is placed in the tripped condition.

Examiner Note: SRO should note TSAS 3.3.1, Action 2 applies and is presently being met by the actions taken per the ARP to bypass the affected channels.

Review LCO 3.2.4 for applicability:

LCO 3.2.4 (TQ): The AZIMUTHAL POWER TILT (Tq) shall be 0.02.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% of RATED THERMAL SRO POWER(1)*.

ACTION:

a. With the indicated Tq > 0.02 but 0.10, either restore Tq to 0.02 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or verify the TOTAL UNRODDED INTRGRATED RADIAL PEAKING FACTOR (FTr) is within the limit of Specification 3.2.3 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; and .

Examiner Note: SRO should note TSAS 3.2.4 does not apply because power tilt indication is due to an instrument faiilure and not an actual uneven power distribution.

Examiner Note: When the actions of ARP 2590C-089 have been addressed and the applicable Technical Specifications have been evaluated, or at lead examiners direction, proceed to Event 3 Failure of the D Traveling Screen P High.

7 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _3__

Event

Description:

D Traveling Screen P Fails High Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 3, Failure of the D Traveling Screen P High.

Indications Available:

• TRAVELING SCREEN P HI (C-06/7, D-10)

• D Screen Differential Pressure indication on C-06/7 rising Examiner Note: The following steps are from ARP 2590E-056, TRAVELING SCREEN P HI (C-06/7, D-10).

AUTOMATIC FUNCTIONS BOP 1. None CORRECTIVE ACTIONS

1. Go To AOP 2517, Circulating Water Malfunctions.

SRO Enter AOP 2517, Circulating Water Malfunctions.

Examiner Note: The following steps are from AOP 2517, Circulating Water Malfunctions.

NOTE When power is less than 15% AND linear power bistable light clears (not lit), on at least 3 RPS channels, the turbine trip is inhibited and turbine BOP trip will not result in an automatic reactor trip.

3.1 IF ANY of the following conditions exist:

• A AND B circulating water pumps not operating

• C AND D circulating water pumps not operating CHECK status of turbine trip bypass and PERFORM the following:

Examiner Note: Step 3.1 is N/A 3.2 IF ONE circulating water pump has tripped, PERFORM the following:

a. ENSURE BOTH of the following exist:

BOP

• A OR B circulating water pump operating

• C OR D circulating water pump operating

b. Go To Section 5.0, Trip of One Circulating Water Pump.

8 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _3__

Event

Description:

D Traveling Screen P Fails High Time Position Applicants Actions or Behavior 3.3 IF CIRC WATER PP LUBE WATER PRES LO (C-06/7, A-10) annunciator in alarm, Go TO Section 6.0, Circulating Water Pump Lube Water Pressure Low.

3.4 IF HI COND D/T (C-06/7, DA-37) annunciator in alarm, Go TO Section 7.0, High Condenser Differential Temperature.

3.5 IF HI COND DIS TEMP (C-06/7, DB-37) annunciator in alarm, Go TO Section 8.0, High Condenser Discharge Temperature.

3.6 IF TRAVELING SCREEN P HI (C-06/7, D-10) annunciator in alarm, Go TO Section 9.0, Traveling Screen Differential Pressure High.

Examiner Note: SRO should transition to Section 9.0 of AOP 2517 and the following is from Sec. 9.0.

9.1 IF TRAVELING SCREEN P HI (C-06/7, D-10) annunciator in alarm, PERFORM the following:

a. PLACE BOTH screen wash pump switches START:

BOP

• A SCREENWASH PP, P8A, HS 6493

• B SCREENWASH PP, P8B, HS 6498

b. PLACE ALL available traveling screens in RUN FAST.

Simulator Operator: When directed, trigger Event-10 to START the B Screen Wash Pump and place all screens in FAST. [E-10; CWR06B (START), CWR07A, B, C & D (FAST)]

When directed to secure the D Traveling Screen, trigger Event-11 [E-11; CWR07D (STOP)]

CAUTION Circulating water pumps may be unstable when operating near 50%

speed; therefore circulating water pump operation below 60% speed is limited to pump starting and stopping only.

c. LOWER circulating water pump speed while monitoring condenser backpressure to lower traveling screen differential pressure.

BOP d. CHECK ALL screens rotating.

d.1 IF ANY traveling screen motor is operating AND associated traveling screen is not rotating, PERFORM the following:

1) PLACE affected traveling screen control switch in STOP (C-47).

2) STOP Circulating Water Pump for the affected traveling screen.

3) Refer To Section 5.0 and PERFORM applicabel steps to cross-tie water boxes.

4) Submit TR to Maintenance Department to replace shear pin on affected traveling screen.

9 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _3__

Event

Description:

D Traveling Screen P Fails High Time Position Applicants Actions or Behavior Examiner Note: Crew may secure D Circ. Pump at any time, based on rising screen dP. When pump is secured, AOP 2517, Section 5.0 should be referenced (Section 5.0 follows).

5.1 IF any Circulating Water Pumps are in the VFD MODE, PERFORM the following:

a. RAISE speed of all VFD mode operating circulating water pumps to 100%.

b. IF TRAVELING SCREEN HI, (C06/7, D10) annunciator in alarm, Refer To section 9.0 of this procedure.

5.2 STOP any in progress liquid waste discharges.

5.3 ENSURE sodium hypochlorite shocking of bays not in progress.

NOTE A 15 to 20 second pause is required after receiving the full closed position indication to allow for full closure prior to opening the crosstie valve.

5.4 CLOSE applicable water box inlet valve for tripped pump:

• CW-11H, A water box inlet BOP

• CW-11G, B water box inlet

• CW-11F, C water box inlet

• CW-11E, D water box inlet CAUTION Supplying two condenser waterboxes from one circulating water pump increases traveling screen differential pressure. During periods of actual or predicted severe weather, where fouling is a concern, waterboxes should not be cross- connected. Water boxes may be cross- connected with SM permission.

Steps 5.5 - 5.10 apply to CW pumps A, B & C and are N/A.

1. IF D circulating water pump tripped, AND cross tying water boxes is required to maintain turbine load, PERFORM the following:

a. PLACE P- 6D Breaker in Pull-To-Lock.

b. ENSURE CW-11D, D water box outlet, is open.

c. OPEN CW-12C, condenser 1B inlet cross-tie

2. IF D circulating water pump tripped, AND isolation of water box is required THEN PERFORM the following:

{The remaining steps involve isolating the vacuum priming system and venting of BOP/PEO the water box, closing CW-11D (water box outlet), notifing Security and monitoring condenser vacuum. None of these actions have any bearing on the scenario.}

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Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _3__

Event

Description:

D Traveling Screen P Fails High Time Position Applicants Actions or Behavior Examiner Note: When the actions of ARP 2590C-089 have been addressed and the applicable Technical Specifications have been evaluated, or at lead examiners direction, proceed to Event 4, CRAC Rad Monitor Failure high.

11 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _4__

Event

Description:

CRAC Rad Monitor and Filter Fan Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 4, CRAC Rad Monitor, and Filter Fan Failure.

Indications:

• C.R.A.C.S. IN AUTO RECIRC MODE (C-01, C-40)

• Fac. 2 CRAC has shifted to recirc. mode.

Examiner Note: The following steps are form ARP 2590A-159 C.R.A.C.S. IN AUTO RECIRC MODE.

AUTOMATIC FUNCTOINS

1. CRACS transfers to recircualtion mode.

CAUTION To ensure proper cleanup of Control Room atmosphere, one complete facility related train of Control Room ventilation (i.e. supply, ATC exhaust, and filter fans), must be in operation.

CORRECTIVE ACTIONS

a. PLACE NORM/RECIRC MODE, HS-8346" AND NORM/RECIRC MODE, HS-8359" switches in RECIR" (C-25A and C-25B).

b. Check damper positions.

c. VERIFY CRACS FLTR FAN, F32A, HS-8006 OR CRACS FLTR FAN, F32B, HS-8007, or both, operating (C-25A and C-25B).

9. MONITOR system operation and VERIFY one complete CRACS train remains in operation.

9.1. IF sudden change in Control Room pressure occurs, VERIFY proper ATC supply and exhaust fan operation (local).

9.2. IF fan belt failure occurs, STOP affected train AND START other train.

Crew may elect to use OP 2315A for specific guidance in starting Fac. 1 CRAC or ATC use step 9.2 above to start it.

Examiner Note: The following are the key steps from OP 2315A for starting of A CRACS.

12 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _4__

Event

Description:

CRAC Rad Monitor and Filter Fan Failure Time Position Applicants Actions or Behavior 4.1.3 ENSURE the following:

a. EMERG FRESH AIR INTAKE RECIRC OVERRIDE, HS-8004C in NORM.

b. EMERG FRESH AIR INTAKE RECIRC OVERRIDE, HS-8004D in NORM.

c. FRESH AIR MU DMPR, HV-211, green CLOSE position indication light, lit.

4.1.4 ENSURE the following:

a. NORM/RECIRC MODE, HS-8346 in O.A.

b. MIN FRESH AIR DMPR, HV-202, red OPEN position indication light lit.

c. CABLE VAULT EXH DMPR, HV-207, red OPEN position indication light lit.

4.1.5 ENSURE the following:

a. NORM/RECIRC MODE, HS-8359 in O.A.

b. FRESH AIR DMPR, HV-495, red OPEN position indication light lit.

c. CABLE VAULT EXH DMPR, HV-497, red OPEN position indication light lit.

4.1.8 PERFORM the following simultaneously (C-25A):

• START CRACS EXH FAN, F-31A, HS-8001

• START CRACS SPLY FAN, F-21A, HS-8009 4.1.9 ENSURE the following:

• CRACS EXH FAN, F-31A, HS-8001 red run light lit

• F-31A, EXH DMPR, HV-206A, red OPEN light lit

• CRACS SPLY FAN, F-21A, HS-8009 red run light lit

• F-21A, EXH DMPR, HV-203A, red OPEN light lit

12. IF radiation monitor alarm is a result of a failure (Green OPERATE light is SRO out), SUBMIT a CR to I&C Dept. and Refer To Tech Spec LCO 3.3.3.1.

Examiner Note: The following is from TS 3.3.3.1 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or declare the channel inoperable.

SRO

b. With the number of OPERABLE channels less than the number of MINIMUM CHANNELS OPERABLE in Table 3.3-6, take the ACTION shown in Table 3.3-6.

The provisions of Specification 3.0.3 are not applicable.

TABLE 3.3-6, #1.b. Control Room Isolation: Minimum Channels Operable = 2, Action 16 Action 16-1: with the number of OPERABLE channels one less than required, restore within 7 days Examiner Note: SRO logs into TSAS 3.3.3.1b, Action 16-1 13 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _4__

Event

Description:

CRAC Rad Monitor and Filter Fan Failure Time Position Applicants Actions or Behavior Refers to TS 3.7.6.1a for CRACS fan inoperable.

SRO Examiner Note: The following is from TS 3.7.6.1 Review Technical Specifications:

LCO 3.7.6.1: Two independent Control Room Emergency Ventilation Trains shall be OPERABLE.*

APPLICABILITY: MODES 1, 2, 3, 4, 5 and 6.

SRO ACTION:

MODES 1, 2, 3, and 4:

a. One Control Room Emergency Ventilation Train Required ACTION: Restore the inoperable ventillation train to OPERABLE status within 7 days or shutdown.

Examiner Note: SRO enters TSAS 3.7.6.1a.

Examiner Note: When the CRACS malfunction has been mitigated and the SRO has finished evaluating Technical Specifications, or at lead examiners direction, proceed to Event 5, SGTL #1 SG.

14 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _5__

Event

Description:

Steam Generator Tube Leak #1 SG Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 5, Steam Generator Tube Leak #1 SG.

Indications:

• S/G N16 monitor on PPC rising leakage for No. 1 Steam Generator

• N16 Alert Alarm (C-06/7 CB-19)

• N16 High Alarm (C-06/7 CA-19)

• SJAE Discharge RIT-5099 level rising Examiner Note: The following steps are from ARP 2590E-094, CB-19 N16 Alert.

AUTOMATIC FUNTIONS

1. None CORRECTIVE ACTIONS

1. OBSERVE radiation monitor indication (RC-14A, PPC N16 screen).

2. COMPARE with trends from RIT-4262, S/G blowdown gross activity and RI-5099, steam jet air ejector.

3. REQUEST Chemistry to perform SP 2833, *Secondary Coolant Analysis for SRO/BOP Primary to Secondary Leak Rate and Dose Equivalent Iodine Concentration" to aid in accomplishing the following:

3.1. DETERMINE the presence of primary to secondary leakage.

3.2. DETERMINE primary to secondary leak rate.

3.3. IDENTIFY the leaking Steam Generator.

4. IF primary to secondary leak is confirmed by chemistry analysis or independent radiation monitor indications, Refer To AOP 2569 Steam Generator Tube Leak and perform applicable actions.

CUE: Chemistry acknowledges request to perform secondary samples for a primary to secondary leak. Wait appropriate time and report back that frisk results indicate activity in No. 1 Steam Generator.

SRO/BOP Enters AOP 2569, Steam Generator Leak.

Examiner Note: The following steps are from AOP 2569 Steam Generator Tube Leak. Steps marked with an

• are performed continuously or once specified conditions are met.

15 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _5__

Event

Description:

Steam Generator Tube Leak #1 SG Time Position Applicants Actions or Behavior 3.1 IF leakage exceeds capability of available charging pumps to maintain pressurizer level, PERFORM the following:

a. IF in MODE 1 or 2, PERFORM the following:

• TRIP the reactor.

• Go To EOP 2525, Standard Post Trip Actions.

b. IF in MODE 3 or lower, PERFORM the following:

SRO/BOP

• ENSURE SIAS is actuated.

• Go To EOP 2541, Appendix 1, Diagnostic Flowchart 3.2 IF MAIN STEAM LINE HI RAD / INST. FAIL (C-01 A-30) is received AND is verified to be valid based on other changing RCS indications, PERFORM the following:

a. TRIP the reactor.

b. Go To EOP 2525, Standard Post Trip Actions.

Examiner Note: Due to the initial size of the SGTL, steps 3.1 and 3.2 are not applicable at this time.

3.3 IF a SJAE OR SGBD Radiation Monitor alarm is received, ENSURE ALL of the following automatic actions occur:

• MS-220A and MS-220B, blowdown isolation, close.

• MS-15, blowdown tank discharge isolation, closes.

SRO/BOP

• MS-135, blowdown quench tank discharge isolation, closes.

• HV-4287 and HV-4288, SG blowdown sample discharge to secondary sample sink, close (secondary sample panel).

• Blowdown values in PPC reset to 0.

3.4 IF N-16 HIGH (C-06/7 CA---19) is received AND is verified to be valid based on other indications, Refer To PPC N16 screen to determine primary to secondary leak rate and PERFORM the following:

a. IF primary to secondary leak rate is greater than or equal to 75 gpd AND is increasing by greater than or equal to 15 gpd / 30 minutes, Refer To AOP 2575, Rapid Downpower, LOWER reactor power to less than 50%

SRO/BOP within one hour, and be in Hot Standby within the following two hours.

b. Refer To MP-26-EPI-FAP06, Classification and PARs, and DETERMINE reportability requirements.

c. Refer To Technical Specification 3.4.6.2, Reactor Coolant System Operational Leakage and PERFORM applicable actions.

Examiner Note: A rapid power reduction is required by this step if primary to secondary leak rate is

>75 gpd AND increasing by > 15 gpd/30minutes.

The US should enter AOP 2575, Rapid Downpower at this time.

16 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _6__

Event

Description:

Rapid Downpower due to Excessive Steam Generator Tube Leak Time Position Applicants Actions or Behavior SRO Enter AOP 2575, Rapid Downpower.

Examiner Note: The following steps are from AOP 2575, Rapid Downpower, Section 3.0 Rapid Downpower.

3.1 PERFORM focus brief on the following:

REACTOR TRIP CRITERIA

• Parameters associated with automatic reactor or turbine trips are challenged

• RCS T cold not within 10°F of temperature program and efforts to regain control are unsuccessful SRO RCS TEMPERATURE CONTROL

• RCS T cold to be maintained within 10°F of Attachment 5, Temperature vs. Power program using Attachment 10, Main Turbine Load Set Control.

• To avoid uncontrolled cooldowns or power transients, sudden changes in RCS temperature or boron concentration should be avoided.

3.2 REQUEST SM/STA to Refer To Attachment 8, Required Notifications, and PERFORM notifications.

ATC 3.3 INITIATE forcing pressurizer sprays.

CAUTION: In the case of a dropped CEA, rod motion is not used to initiate SRO downpower.

Examiner Note: Caution is N/A ATC 3.4 IF not downpowering due to a dropped rod, AND Reactor power is greater than 99% (2673 MWTh) INSERT Group 7 CEAs 10 + 2 steps to initiate downpower.

3.5 Using the Load Speed Control switch, REDUCE turbine load to maintain Tc BOP on program (+/-2 deg).

SRO 3.6 Refer To PPC or Reactor Engineering Curve and Data Book and OBTAIN reactivity plan for the initial reactor power condition and desired load reduction.

17 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _6__

Event

Description:

Rapid Downpower due to Excessive Steam Generator Tube Leak Time Position Applicants Actions or Behavior Examiner Note: The crew should refer to Reactivity Plan RE-G-14.

NOTE BOP Attachment 10 Approximate Load Demand vs. Reactor Power, can be used to correlate the desired power level to a turbine load demand setpoint.

3.7 Refer To Attachment 9, Main Turbine Load Set Control, REDUCE turbine BOP load and MAINTAIN Tc on program (+/-2 deg).

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Attachment 9 Main Turbine Load Set Control:

CAUTION Operation of the Load/Speed CONTROL switch will change turbine BOP load at 600%/hour, and cancel any previous load setpoint.

NOTE Steps provided in this attachment are dependent on plant conditions and may be performed in any sequence, and repeated as necessary.

1. IF desired to commence or modify a turbine load ramp, PERFORM the following (HMI Load screen):

a. IF previous ramp has stopped, SELECT Load Hold.

BOP

b. SELECT Load Setpt and ENTER desired value.

c. SELECT Rate setpt and ENTER desired value.

d. WHEN ready to commence load reduction, SELECT Load Resume.

18 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _6__

Event

Description:

Rapid Downpower due to Excessive Steam Generator Tube Leak Time Position Applicants Actions or Behavior

2. IF desired to adjust the Load Ramp Rate, PERFORM any of the following:

• SELECT Rate setpt and ENTER new value.

• SELECT 5% / hour, OR 10% / hour, OR 20% / hour.

BOP

• SELECT Raise or Lower (0.25% / hour change).

3. IF Tavg and Tc are high off program, PERFORM the following:

a. SELECT Load Hold to stop ramp.

b. WHEN Tavg and Tc are trending back to program, SELECT Load Resume.

BOP 4. IF Tavg and Tc are low off program, PERFORM the following:

a. JOG the Load/Speed CONTROL switch to Lower.

b. WHEN Tavg and Tc are back on program, SELECT Load Setpt and ENTER desired value.

c. IF desired, Go To Step 1 and RESUME turbine load ramp.

5. IF desired load has been reached SELECT Load Hold.

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Section 3.0 Rapid Downpower.

3.8 Based on required rate of downpower, START additional charging pumps as ATC necessary and balance charging and letdown.

19 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _6__

Event

Description:

Rapid Downpower due to Excessive Steam Generator Tube Leak Time Position Applicants Actions or Behavior ATC 3.9 IF desired to borate from the RWST (preferred method)

PERFORM the following:

a. ENSURE at least one charging pump operating.

b. ENSURE CH-196, VCT makeup bypass, closed.

c. ENSURE CH-504, RWST to charging suction, open.

d. OPEN CH-192, RWST isolation.

e. CLOSE CH-501, VCT outlet isolation.

f. CHECK charging flow at desired rate.

g. Go To step 3.11 Examiner Note: Crew should borate from the RWST.

SRO/ATC/ 3.11 During the downpower, Refer To Attachment 1,Rapid Downpower BOP Parameters, and MAINTAIN parameters as specified throughout downpower:

Examiner note: Attachment 1 Rapid Downpower Parameters:

• Condensate and heater drain flows and pressures: sufficient to maintain adequate SGFP suction pressure

• FRV D/P: greater than 40 psid

• Turbine load: responding to changes in load demand, with control valves operating together

• Steam generator levels 55 to 70%.

• MSR parameters tracking together

• Turbine Generator MVARs: as specified by CONVEX

• Reactor power: being monitored using delta T power indication

• ASI: In accordance with reactivity plan or within 0.01 of ESI or per COLR.

• CEA position: greater than PDIL

• Tc: less than or equal to 549 deg

• Pressurizer level: between 35 and 70%

Pressurizer pressure: between 2,225 and 2,300 psia (DNB margin) 20 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _6__

Event

Description:

Rapid Downpower due to Excessive Steam Generator Tube Leak Time Position Applicants Actions or Behavior SRO/ATC NOTE

1. Xenon rate of change should be considered when terminating boration.

2. During rapid downpower, the PPC calorimetric may be inaccurate due to SG level transients. The most accurate available indication of reactor power is RPS delta T power.

Examiner Note: Once power has dropped at least 5%, or at the lead examiners direction, proceed to Event 7, Steam Generator Tube Rupture, Manual Plant Trip.

21 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 7, Steam Generator Tube Rupture in #1 SG.

Examiner Note: A reactor trip will be required by CAS of AOP 2569.

Indications:

• Steam Line Radiation Monitor Alarm (C-01, A30)

• PROCESS RAD MON HI/HI FAIL (C-06, DA-24)

• Letdown lowers

• Pressurizer Level Lowering Examiner Note: The following steps are from EOP 2525, Standard Post Trip Actions.

Determine Status of Reactivity Control - Reactor Trip

1. DETERMINE that Reactivity Control acceptance criteria are met for the ATC reactor by performing ALL of the following steps:

• CHECK that all CEAs are fully inserted.

• CHECK that reactor power is dropping.

• CHECK that SUR is negative.

Determine Status of Reactivity Control - Turbine Trip

2. DETERMINE that Reactivity Control acceptance criteria are met for the turbine by performing ALL of the following steps :

a. CHECK that the main turbine is tripped by BOTH of the following:

BOP

• ALL main stop valves are closed.

• Generator megawatts indicate zero.

• Turbine speed is lowering.

b. IF 15G-2XI-4, motor operated disconnect, is closed, CHECK that the main Generator output breakers 8T and 9T are open.

Determine Status of Maintenance of Vital Auxiliaries

3. DETERMINE that Maintenance of Vital Auxiliaries acceptance criteria are met by performing ALL of the following steps:

3.1. CHECK that ALL Facility 1 and 2 electrical buses are energized:

• 6.9kV Electrical Buses 25A, 25B

• 4.16kV Non-Vital Electrical Buses 24A, 24B BOP

• 4.16vV Vital Electrical Buses 24C, 24D

• Vital DC Buses 201A, 201B, DV-10, DV-20

• Vital AC Instrument Buses VA-10, VA-20 3.2. CHECK that BOTH facilities of service water are operating.

3.3. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

22 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior Determine Status of RCS Inventory Control ATC

4. DETERMINE that RCS Inventory Control acceptance criteria are met by performing ALL of the following:

4.1. CHECK that BOTH of the following conditions exist:

• Pressurizer level is 20 to 80%

• Pressurizer level is trending to 35 to 70%

a.1 IF the Pressurizer Level Control System is not operating properly in automatic, RESTORE and MAINTAIN pressurizer level 35 to 70% by performing ANY of the following:

1) OPERATE the Pressurizer Level Control System.

2) Manually OPERATE charging and letdown.

4.2. CHECK that RCS subcooling is greater than or equal to 30°F 23 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior Determine Status of RCS Pressure Control

5. DETERMINE RCS Pressure Control acceptance criteria are met by BOTH of the following:

• CHECK that pressurizer pressure is 1900 to 2350 psia.

• CHECK that pressurizer pressure is trending to 2225 to 2300 psia.

5.1. IF the Pressurizer Pressure Control System is not operating properly in automatic, THEN RESTORE and MAINTAIN pressurizer pressure between 2225 to 2300 psia by performing ANY of the following:

• OPERATE the Pressurizer Pressure Control System.

• Manually OPERATE pressurizer heaters and spray valves.

ATC 5.2. IF ANY pressurizer spray valve will not close, THEN STOP RCPs as necessary.

5.3. IF any PORV is open AND pressurizer pressure is less than 2250 psia, THEN CLOSE the associated PORV block valve.

5.4. IF pressurizer pressure is less than 1714 psia, THEN ENSURE ALL of the following:

• SIAS actuated. (C01)

• CIAS actuated. (C01)

• EBFAS actuated. (C01) 5.5. IF pressurizer pressure is less than 1714 psia AND SIAS actuated, THEN ENSURE ONE RCP in each loop is stopped.

5.6. TCOA: IF Pressurizer pressure lowers to less than the minimum of Fig. 2 RCP NPSH Curve THEN STOP ALL RCPs Determine Status of Core Heat Removal

6. DETERMINE that Core Heat Removal acceptance criteria are met by performing ALL of the following:

a. CHECK that at least one RCP is operating and that loop delta T is less than 10°F a.1 IF RCPs are not operating, OR loop _T is greater than 10° F, ATC THEN PERFORM the following:

1) PLACE TIC- 4165, steam dump TAVG controller, in manual and closed.

2) PLACE BOTH pressurizer spray valve controllers in manual and CLOSE the valves.

• HIC- 100E

• HIC- 100F

b. CHECK that Th subcooling is greater than or equal to 30°F.

24 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior Determine Status of RCS Heat Removal

7. DETERMINE that RCS Heat Removal acceptance criteria are met by ALL of the following conditions:

a. CHECK that at least one steam generator has BOTH of the following BOP conditions met:

a. Level is 10 to 80%.

b. Main feedwater or TWO auxiliary feedwater pumps are operating to restore level 40 to 70%.

b. CHECK that RCS Tc is being maintained between 530°F to 535°F.

c. CHECK that BOTH steam generators pressure are 880 to 920 psia.

Determine Status of Containment Isolation ATC

8. DETERMINE that Containment Isolation acceptance criteria are met by ALL of the following:

a. CHECK that containment pressure is less than 1.0 psig.

b. CHECK that NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Radiation Monitors Inside Containment

• RM-7890, Personnel Access Area

• RM-7891, Ctmt Refuel Floor Area

• RM-8240, High Range

• RM-8241, High Range

• RM-8123 A and B, Ctmt Atmosphere

• RM-8262 A and B, Ctmt Atmosphere

c. CHECK that NONE of the following steam plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Steam Plant Radiation Monitors

• RM-5099, Steam Jet Air Ejector

• RM-4262, SG Blowdown

• RM-4299A and B, Main Steam Line 1

• RM-4299C, Main Steam Line 2 c.1 IF feed is available to BOTH steam generators, THEN THROTTLE feed to the steam generator with the highest radiation readings to maintain level 40 to 45%.

25 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior Determine Status of Containment Temperature and Pressure Control

9. DETERMINE that Containment Temperature and Pressure Control acceptance criteria are met by BOTH of the following steps:

ATC

a. CHECK that containment temperature is less than 120°F. (PPC or avg. of Points 5 and 6)

b. CHECK that containment pressure is less than 1.0psig.

10. PERFORM the following:

a. DIAGNOSE the event. Refer To Appendix 1, "Diagnostic Flowchart."

SRO b. INITIATE Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions."

c. Go To the appropriate EOP

{Step 10.b above}

Perform Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions".

ATC/BOP Examiner Note: EOP Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions." are attached to guide.

Examiner Note: The Unit Supervisor refers to EOP 2541 Appendix 1, Diagnostic Flowchart to diagnose the event.

SRO Enters EOP 2534, Steam Generator Tube Rupture.

Examiner Note: The following steps are from EOP 2534 Steam Generator Tube Rupture. Asterisked steps, within the ORP or selected FRPs being implemented, may be brought forward to restore or preserve a Safety Function. Asterisked steps are Continuously Applicable, and may be performed out of order after they have been accomplished once.

• 1. CONFIRM diagnosis of Steam Generator Tube Rupture by performing the following:

a. CHECK Safety Function Status Check Acceptance Criteria are satisfied.

SRO Examiner Note: SRO checks EOP 2534-001 SGTR Safety Function Status Checks and confirms that all Safety Criteria are satisfied.

26 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior

b. CHECK for steam generator tube rupture by performing the following:

1) CHECK B train RBCCW in service.

2) ENSURE 2-RB-210 Degasifier Effluent Cooler Return Outlet is open.

3) OPEN the steam generator sample valves:

• MS-191A

• MS-191B

4) DIRECT Chemistry to perform the following:

BOP

• Sample both steam generators

• Frisk the samples

• Report frisk results

• Analyze samples for boron and activity

5) WHEN Chemistry reports that samples have been taken, PERFORM the following:

• CLOSE the steam generator sample valves

• IF SIAS has actuated, AND no other sampling is in progress, CLOSE 2-RB-210, Degasifier Effluent Cooler Return Outlet CUE: When directed to sample Steam Generators, respond 20 minutes later that samples have been taken. Report that frisk results show indication of activity in No. 1 Steam Generator.

• 2. CLASSIFY the event. Refer To MP-26-EPI-FAP06, Classification and PARs SRO

• IF classification requires RCS sampling, Refer To Appendix 46, Sampling for EAL Determination and DIRECT Chemistry as required.

• 3. PERFORM ALL of the following:

SRO

• OPEN the placekeeper and ENTER the EOP entry time.

• ENSURE the master alarm silence switch is in NORMAL.

• 4. IF pressurizer pressure is less than 1714 psia, PERFORM ALL of the following:

a. ENSURE SIAS, CIAS and EBFAS have actuated. (C01)

b. ENSURE ONE complete facility of CRACS is operating in the recirc mode: (C25)

Facility 1 ATC

• HV-203A, Fan F-21A exhaust damper is open.

• Fan F-21A, supply fan is running.

• HV-206A, Fan F-31A exhaust damper is open.

• Fan F-31A, exhaust fan is running.

• HV-212A, Fan F-32A exhaust damper is open.

• Fan F-32A, filter fan is running.

• HV-202, minimum fresh air damper is closed.

• HV-207, cable vault exhaust damper is closed.

• HV-208, exhaust air damper is closed 27 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior Facility 2

• HV-203B, Fan F-21B exhaust damper is open.

• Fan F-21B, supply fan is running.

• HV-206B, Fan F-31B exhaust damper is open.

ATC

• Fan F-31B, exhaust fan is running.

• HV-212B, Fan F-32B exhaust damper is open.

• Fan F-32B, filter fan is running.

• HV-495, fresh air damper is closed.

• HV-496, exhaust air damper is closed.

• HV-497, cable vault exhaust damper is closed.

• 5. IF SIAS has initiated, PERFORM the following:

a. CHECK at least one train of SIAS, CIAS and EBFAS has properly actuated. (C01X) a.1 IF ANY component is not in its required position, manually ALIGN the applicable component.

b. CHECK that safety injection flow is adequate. Refer To Appendix 2, Figures.

b.1 PERFORM ANY of the following to restore safety injection flow within the SI Flow Curve:

1) ENSURE electrical power to safety injection pumps and ATC valves.

2) ENSURE correct safety injection valve lineup.

3) ENSURE operation of necessary auxiliary systems:

1) RBCCW

2) ESF Room Coolers

4) START additional safety injection pumps as needed until safety injection flow is within the SI Flow Curve.

Examiners Note: The C HPSI pump must be manually started using the control switch on C-01.

c. ENSURE ALL available charging pumps are operating.

28 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior CRITICAL TASK: Manually establish the minimum design Safety Injection System flow within 30 minutes of entering the ORP (CT-1/SGTR-6).

The amount of time required to identify and report a failed safety function is subjective. A criteria may be agreed upon as follows: Usually one Safety Function Status Check is to be completed over a predefined time. Failure to report a failed Safety Function with twice the defined time frame may be reason to fail this critical task (SGTR-6). Safety Function assessments are performed upon entering the ORP/FRP and is required every 15 minutes. (OP 2260).

Time that C HPSI pump was started: ___________

Time SIAS of actuation (manual or auto):___________

d. ENSURE vital switchgear cooling is operating for each operating ECCS train as follows:

Facility 1

• Fan F-51 is running.

• Fan F-134 is running.

ATC

• SW-178A, service water supply is open.

• SW-178B, service water supply is open.

Facility 2

• Fan F-52 is running.

• Fan F-142 is running.

• Fan F-133 is running.

• SW-178C, service water supply is open.

• 6. IF pressurizer pressure is less than 1714 psia AND SIAS has initiated, PERFORM the following:

a. ENSURE ONE RCP in each loop is stopped.

b. PLACE associated pressurizer spray valve controller RC-100E or RC-100F in manual and CLOSE the valve.

ATC c. IF pressurizer pressure lowers to less than the minimum RCP NPSH limit, PERFORM the following:

1) STOP ALL RCPs.

2) PLACE TIC-4165, steam dump TAVG controller, in manual and closed.

3) PLACE pressurizer spray valve controllers RC-100E and RC-100F in manual and CLOSE the valves.

29 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior

• 7. IF EBFAS has initiated AND the condenser is available, ALIGN the condenser air removal system to Unit 2 stack:

a. ENSURE condenser air removal fan, MF---55A or MF-55B, is running.

b. IF condenser air removal fan MF-55A is operating, ENSURE makeup damper, EB-171, is open.

c. OPEN EB-57, condenser air removal to Unit 2 stack.

ATC/BOP d. ENSURE AC-11, Purge exhaust filter outlet damper is closed.

e. OPEN AC-59, Outside air makeup damper.

f. START ONE main exhaust fan.

g. ENSURE HV-118, Radwaste exhaust damper is closed.

h. START F-20, Fuel handling area supply fan.

i. ENSURE HV-173, Exhaust mod discharge damper is in MOD position.

j. PLACE AC-59, Outside air makeup damper to MID position.

• 8. COMMENCE an RCS cooldown at the maximum controllable rate to a TH of SRO/BOP less than 515 °F in both loops using the steam dumps.

• 9. DEPRESSURIZE the RCS by performing the following:

a. MAINTAIN pressurizer pressure within ALL of the following criteria:

• IF RCPs are operating, MAINTAIN RCS pressure above the NPSH ATC curve. Refer to Appendix 2, Figures.

• Less than 920 psia

• Within 50 psi of the most affected steam generator pressure

• Within the RCS P/T curve limits. Refer to Appendix 2, Figures.

b. OPERATE main or auxiliary spray.

c. IF HPSI throttle/stop criteria are met, PERFORM ANY of the following to ATC lower RCS pressure:

• CONTROL charging and letdown.

• THROTTLE or STOP HPSI flow.

30 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior

• 10. IF the main condenser is available, MAINTAIN steaming to the condenser by performing the following:

a. IF MSI is not present AND MSI Block is permitted, BLOCK the automatic initiation as the cooldown and depressurization proceeds.

b. IF MSI has actuated AND the following conditions exists:

1) Steam dumps are available

2) Steaming to the condenser is desired PERFORM the following to open the MSIV for the unisolated steam generator:

BOP/ATC 1) UNLOCK and CLOSE the disconnect as applicable for MSIV bypass valves:

1) MS---65A (B5207)

2) MS---65B (B6208)

2) CLOSE the steam dump valves.

3) OPEN the MSIV bypass valves.

4) THROTTLE the ADV as necessary to achieve less than 100 psid.

5) WHEN differential pressure across the MSIVs is less than 100 psid, OPEN the MSIVs.

6) CLOSE the MSIV bypass valves.

31 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior

c. IF MSI will actuate following the isolation of the most affected steam generator AND the following conditions exists:

• Steam dumps are available

• Steaming to the condenser is desired PERFORM the following to ensure steaming to the main condenser is maintained:

1) CLOSE the steam dump valves.

2) Manually initiate MSI.

3) IF differential pressure across the MSIV for the least affected steam generator is less than 100 psid, OPEN the MSIV.

c.1 IF differential pressure across the MSIV for the least affected SRO/ATC/ steam generator is greater than 100 psid, BOP PERFORM the following:

1) UNLOCK and CLOSE the disconnect, as applicable, for least affected steam generator MSIV bypass valve:

• MS-65A (B5207)

• MS-65B (B6208)

2) ENSURE the steam dump valves are closed.

3) OPEN the MSIV bypass valve for the least affected steam generator.

4) THROTTLE the ADV as necessary to achieve less than 100 psid.

5) WHEN differential pressure across the MSIV for the least affected steam generator is less than 100 psid, OPEN the MSIV.

6) CLOSE the MSIV bypass valve.

• 11. IF SIAS is not present AND SIAS Block is permitted, BLOCK the automatic SRO/ATC initiation as the cooldown and depressurization proceeds.

• 12. IF offsite power has been lost OR the condenser is not available, PERFORM the following:

BOP a. CLOSE BOTH MSIVs.

b. ENSURE BOTH MSIV bypass valves are closed.

c. OPEN AR-17, condenser vacuum breaker.

32 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7, 8__

Event

Description:

Steam Generator Tube Rupture, Manual Plant Trip, Loss of Safety Injection Flow Time Position Applicants Actions or Behavior

• 13. DETERMINE the most affected steam generator by considering ALL of the following:

• Steam generator activities

• Main steam piping radiation levels

• Steam generator level change when not feeding

• Steam generator blowdown activities

• Steam generator mismatch in level with essentially the same feed and steaming rate for both steam generators

• Feed flow mismatch between steam generators

• Steam flow versus feed flow mismatch in a steam generator prior to the trip

• 14. WHEN BOTH RCS hot leg temperatures are less than 515° F, ISOLATE the most affected steam generator by performing the following:

Number 1 Steam Generator

a. RECORD in the placekeeper, time and TC of the operating loop.

b. ENSURE ALL of the following for the associated ADV:

• ADV is in AUTO, PIC-4223

• ADV setpoint at 920 psia

• ADV is closed SRO/BOP c. ENSURE the MSIV, MS-64A, is closed.

d. ENSURE the MSIV bypass valve, MS-65A, is closed.

e. CLOSE the main feedwater regulating bypass valve,FW-41A.

f. ENSURE the main feedwater block valve, FW-42A is closed.

g. PLACE main feed isolation air assisted check valve, FW-5A to CLOSE.

h. ENSURE the steam generator blowdown isolation valve, MS-220A is closed.

i. PLACE BOTH auxiliary feed OVERRIDE/MAN/START/RESET handswitches in PULL TO LOCK.

j. CLOSE the aux feedwater regulating valve, FW-43A.

CRITICAL TASK: Isolate the affected SG (CT-2/SGTR-5)

[Within 60 minutes of the tube rupturing, per OP 2260]

Time SG Tube Rupture occurred (time of manual trip): ___________

Time Affected SG Isolated (Step #14 complete):___________

Once the affected SG is isolated, or at the lead examiners direction, the scenario is completed.

33 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7_

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior Examiner Note: The following steps are from EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions.

1. IF charging pumps suction is aligned to the VCT, THEN CHECK VCT level is between 72% to 86%:

a. IF VCT level is less than 72%, THEN ALIGN charging pump suction to RWST as follows:

ATC 1) OPEN CH- 192, RWST isolation.

2) ENSURE CH- 504, RWST to charging suction is open.

3) CLOSE CH- 501, VCT outlet isolation.

4) ENSURE CH- 196, VCT makeup bypass is closed.

b. IF VCT level is greater than 88%, THEN PLACE CH- 500, letdown divert handswitch, to the RWS position, and divert as required to maintain VCT level 72% to 86%.

2. TCOA: IF SIAS actuated, THEN ENSURE ONE complete facility of CRAC operating, in RECIRC mode, as follows: (C25A/B)

Facility 1

• HV- 203A, Fan F- 21A exhaust damper open

• Fan F- 21A, supply fan running

• HV- 206A, Fan F- 31A exhaust damper open

• Fan F- 31A, exhaust fan running

• HV- 212A, Fan F- 32A exhaust damper, open

• Fan F- 32A, filter fan, running

• HV- 202, minimum fresh air damper, closed ATC

• HV- 207, cable vault exhaust damper, closed

• HV- 208, exhaust air damper, closed Facility 2

• HV- 203B, Fan F- 21B exhaust damper open

• Fan F- 21B, supply fan running

• HV- 206B, Fan F- 31B exhaust damper open

• Fan F- 31B, exhaust fan running

• HV- 212B, Fan F- 32B exhaust damper, open

• Fan F- 32B, filter fan, running

• HV- 495, fresh air damper, closed

• HV- 496, exhaust air damper, closed

• HV- 497, cable vault exhaust damper, closed 34 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7_

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior

3. TCOA: IF SIAS not actuated, THEN CHECK ONE facility of CRAC operating, in NORMAL mode, as follows: (C25A/B)

Facility 1

• HV- 203A, Fan F- 21A exhaust damper is open

• Fan F- 21A, supply fan running ATC

• HV- 206A, Fan F- 31A exhaust damper open

• Fan F- 31A, exhaust fan running Facility 2

• HV- 203B, Fan F- 21B exhaust damper open

• Fan F- 21B, supply fan running

• HV- 206B, Fan F- 31B exhaust damper open

• Fan F- 31B, exhaust fan running

4. IF charging pumps suction aligned to the RWST AND boration not required, THEN RESTORE charging pump suction to VCT as follows:

a. CHECK BOTH of the following:

ATC 1) VCT level between 72% and 86%

2) VCT pressure greater than 15 psig

b. CHECK letdown is in service.

c. OPEN CH- 501, VCT outlet isolation.

d. CLOSE CH- 192, RWST isolation.

BOP 5. CHECK instrument air pressure greater than 90 psig and stable.

6. IF AFAS has actuated, WHEN BOTH steam generators are restored to greater than 33%, THEN PERFORM the following:

a. PLACE the following switches in M (Manual) and ADJUST to obtain desired flow (C- 05):

1) FW- 43A, AFW- FCV, HIC- 5276A

2) FW- 43B, AFW- FCV, HIC- 5279A

b. PLACE BOTH of the following switches to RESET and ALLOW to spring return to neutral (C- 05):

BOP

1) OVERRIDE/MAN/START RESET (Facility 1)

2) OVERRIDE/MAN/START RESET (Facility 2)

c. ADJUST the following switches to obtain desired flow (C- 05):

1) FW- 43A, AFW- FCV, HIC- 5276A

2) FW- 43B, AFW- FCV, HIC- 5279A

d. IF main feedwater pump is supplying steam generators, THEN STOP BOTH auxiliary feedwater pumps.

Examiner Note: BOP may place both facilities in override (Pull-To-Lock) once the SG Tube Rupture is identified and AFW flow is under control.

35 of 34

Op-Test No.: __ ES16LI2___ Scenario No.: __2__ Event No.: _7_

Event

Description:

EOP 2541, Followup Actions, Appendix 4A, Reactor Trip Subsequent Actions Time Position Applicants Actions or Behavior

7. CHECK Main Condenser is available, as indicated by ALL of the following:

• At least ONE MSIV open BOP

• Condenser vacuum better than 15 inches HG - ABS (0 to 15 inches)

• At least ONE condensate pump operating

• At least ONE Circ Water pump operating BOP 8. OPEN HD- 106, subcooling valve.

BOP 9. ENSURE BOTH heater drain pumps stopped.

10. IF MFW is supplying feed to the steam generators, THEN PERFORM the following:

a. ENSURE that only ONE main feedwater pump is operating.

b. ENSURE that BOTH main feed block valves are closed:

1) FW- 42A

2) FW- 42B

c. ADJUST the operating main feedwater pump pressure to 50 to 150 psi greater than SG pressure.

BOP d. ENSURE BOTH main feed reg bypass valves are throttled to control SG level:

1) LIC- 5215

2) LIC- 5216

e. IF Main Feedwater Pump A is secured, THEN CLOSE the following:

1) FW- 38A, main feedwater pump discharge valve

2) FIC- 5237, main feedwater pump mini flow recirc valve

f. IF Main Feedwater Pump B is secured, THEN CLOSE the following:

1) FW- 38B, main feedwater pump discharge valve

2) FIC- 5240, main feedwater pump mini flow recirc valve

11. IF BOTH MFW pumps are secured, THEN PERFORM the following:

BOP a. CLOSE BOTH main feedwater pump mini flow recirc valves.

• FIC- 5237

• FIC- 5240

12. IF 25A OR 25B is energized, THEN ALIGN condensate pumps as follows:

BOP a. ENSURE ONE pump is running.

b. ENSURE ONE pump is in PULL TO LOCK.

c. ENSURE ONE pump is in AUTO.

Examiner Note: End of Attachment 4- A 36 of 34

SIMULATOR SCENARIO #3 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 3 Op-Test No.: ES16LI3 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% Power IC-141 Turnover: 100% Power, steady state, Nothing out of service. 24E is aligned to 24C.

Critical Tasks:

1. LOCA-13 Trip two RCPs with SIAS actuation and a LOCA in progress.

2. LOCA-12 (TCOA) Trip ALL RCPs within 5 minutes of NPSH limits not being met.

3. 2260 2536 TCOA (ESDE-6); Isolate Aux Feed Water to the affected SG within 30 minutes following an MSI actuation.

4. LOCA-2; Start the TDAFP.

Event No. Malf. No. Event Event Description Type*

Not Run 1 RP13D TS "D" Ch. SG #1 Level (LI113D) fails to 0%

Deleted (S) 2 C03-A18B C "A" RCP Anti Rev Rot Flow Low (ATC/S) 3 C,TS "A" RCP Seal Cooler Leak of 5-8 gpm RC20A (ATC/S) 4 R N/A Plant shutdown due to RCS leak (ALL) 5 RC20A M "A" RCP Seal Cooler Rupture resulting in an Inter-System SB-LOCA (1005) (ALL) of 550 gpm 6 C ESD outside CTMT (4.75E06 lbm/hr), upstream of #2 MSIV on the MS02B (ALL) trip. 30 second time delay following the Reactor Trip FW30A C A AFW Pump degraded performance and "B" AFW pump trips.

7 FW20B (BOP/S) Start the TDAFW pump.

1 of 29

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual

1. Total malfunctions (5-8) 5

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3 NRC 2016, Scenario 3 Summary:

The crew will take the shift with the unit at 100% power, steady state, nothing out of service.

Event 1: The crew takes the shift, then at the discretion of the Examiner malfunction for Ch. "D" SG #1 Level (LI-113D) failure to 0% is triggered. Crew will refer to applicable ARP(s), bypass the affected inputs on Channel D of RPS and log into the applicable instrumentation T.S.A.S.

Event 2: At the discretion of the Examiner a malfunction for A RCP Anti Reverse Rotation flow alarm will annunciate providing the prelude to the A RCP Seal Cooler leak. The Crew will refer to ARP 2590B-074 and start the A RCP Lift pump, evaluate the need for a Reactor Trip and then submit a CR.

Event 3: At the discretion of the Examiner a malfunction for RCP A seal cooler leak into RBCCW of 5-8 gpm.

The Crew will enter AOP 2568 Reactor Coolant System Leak and validate by stabilizing PZR level, may start an additional Charging Pump and manually adjusting the bias on letdown. The U.S. will enter a Shutdown T.S.A.S and monitor for EAL Classification threshold. U.S. will direct a shutdown and transition to AOP 2575.

Event 4: The crew will enter AOP 2575 Rapid Downpower per the RCS Leak T.S.A.S. and commence a downpower. ATC will insert Group 7 Rods 10 steps while BOP reduces Turbine load to maintain RCS TCOLD.

The Crew will then align for boration from the RWST requiring the ATC operator to start an additional Charging pump if not already started and the BOP to setup the Turbine HMI to lower load to maintain RCS TCOLD.

Event 5: At the discretion of the Examiner the malfunction for A RCP Seal Cooler rupture will causing a small break LOCA of approximately 550 gpm requiring the crew will validate using RCS parameter imitate and initiate a Reactor Trip and transition to perform EOP 2525 SPTA.

Event 6: On the Reactor trip during the performance of EOP 2525 an Excess Steam Demand Event will be initiated outside of CTMT, upstream of #2 S/G MSIV (Non-Isolable) requiring the BOP stop steaming to the condenser by closing both MSIVs and to secure feed the #2 S/G. When the S/G blows dry the BOP will stabilize RCS temperature using the unaffected S/G ADV. The U.S. will diagnose 2 events and enter EOP 2540 and implement the Resource Assessment Trees.

Event 7: Five minutes after the plant trip, the A Motor driven Aux Feedwater Pump performance will degrade and the B Motor driven Aux Feedwater pump will trip, requiring the BOP to start the Turbine driven Aux Feedwater Pump, if not previously already started.

The US should transition to the Functional Recovery Procedure, EOP 2540, and the Crew will begin addressing the CTMT Isolation Safety Function.

The crew is required to isolate the RCS leak into RBCCW and Isolate the #2 S/G while stabilizing RCS temperature after the #2 S/G blowdown.

2 of 29

Appendix D Scenario Outline Form ES-D-1 INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

ID Num Description Delay Ramp Event Sev or Final Rel Time Time Time Value Value Order MALFUNCTIONS RP13D SG #1 Ch. D Level failure E-1 0% 0% 1 C03-A18B "A" RCP Anti Rev Rot Flow Low E-2 ON ON 2 RC20A "A" RCP Seal Cooler Leak of 8 gpm 2 min E-3 8 gpm 8 gpm 3 RC20A "A" RCP Seal Cooler Rupture of 550 gpm E-5 550 gpm 550 gpm 5 (1005)

MS02B ESD outside CTMT, upstream of #2 MSIV 30 Sec. E-30 4.75E06 4.75E06 6 FW30A "A" AFW pump degraded performance. 5 min. E-30 100% 100% 7 FW20B "B" AFW pump trip. 5 min. E-30 N/A N/A 7 FW20A "A" AFW pump trip. E-8 N/A N/A 8 C03-A18B "A" RCP Anti Rev Rot Flow Low E-9 NORMAL NORMAL 2 REMOTE FUNCTIONS CCR35 RBCCW pump A Rad Mon isolation E-10 CLOSE CLOSE 10 CCR35 RBCCW pump A Rad Mon isolation E-11 OPEN OPEN 11 CCR36 RBCCW pump B Rad Mon isolation E-12 CLOSE CLOSE 12 CCR36 RBCCW pump B Rad Mon isolation E-13 OPEN OPEN 13 CCR37 RBCCW pump C Rad Mon isolation E-14 CLOSE CLOSE 14 CCR37 RBCCW pump C Rad Mon isolation E-15 OPEN OPEN 15 OVERRIDES 3 of 29

Op-Test No.: __ES16LI3___ Scenario No.: __3__ Event No.: _1__

Event

Description:

A Ch. RWST Level Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event #1, SG #1 Ch. "D" Level (LI-113D) fails to 0%

Indications Available:

• SG LO LEVEL TRIP CH D C04, DB-1

• RPS PRE TRIP C04, AA-7 Examiner Note:

The following steps are from ARP 2590C-008 (C04, DB-1)

AUTOMATIC FUNCTIONS

1. If 2 RPS channels actuate, reactor trips.

CORRECTIVE ACTIONS

1. IF reactor trips, Go To EOP 2525,
Standard Post Trip Actions" and PERFORM necessary corrective actions.

2. OBSERVE channel
D" SG level indication and COMPARE to other safety channel indications (C-05, PPC).

3. IF SG level is less than 49.5% AND no automatic reactor trip has occurred, manually ATC TRIP reactor and Go To EOP 2525,
Standard Post Trip Actions."

4. IF SG level is greater than 49.5% AND alarm is due to instrument malfunction, PERFORM the following:

4.1 OBTAIN necessary keys and PERFORM applicable actions to bypass channel D SG level bistables on RPS, C-517, and C-518.

4.2 Refer To the following Technical Specifications LCOs and DETERMINE applicability:

• 3.3.1.1, Table 3.3-1

• 3.3.2.1, Table 3.3-3 4.3 SUBMIT Trouble Report to I&C Department.

3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

TOTAL TRIP MIN MODE ACTION

7. Steam Generator Water level - Low 4 2 3 1, 2 2 4b) 1850 psia, operation may continue with the inoperable channel in the SRO bypassed condition, provided the following condition is satisfied:

Action 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

4 of 34

Appendix D Scenario Outline Form ES-D-1 3.3.2.1 The engineered safety feature actuation system instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

TOTAL TRIP MIN MODE ACTION

9. Auxiliary Feed Water SG Level - Low 4 2 3 1, 2, 3 2 SRO Action 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. .

Examiner Note: SRO should note that performing the actions of the ARP and bypassing channel D on RPS, C517 and C-518 meets the action for the LCO 3.3.1.1 and 3.3.2.1.

Examiner Note: Once the actions of TS 3.3.1.1 and 3.3.2.1 have been completed, or at lead examiners direction, proceed to Event 2, A RCP Anti Rev Rot Flow Low.

5 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _2__

Event

Description:

A RCP Anti Rev Rot Flow Low Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event #2, A RCP Anti Rev Rot Flow Low.

Indications Available:

• RCP A ANTIREV ROT FLOW LO C02/3 AB-18 Examiner Note: The following steps are from ARP 2590B-074 (C02/3 AB-18).

AUTOMATIC FUNCTIONS

1. None CORRECTIVE ACTIONS ATC NOTE:

Oil lift pump may be operated indefinitely.

1. START RCP-A LIFT PPS, P-51A/53A" (C-03).

Simulator Operator: ~1 minute after the lift pump is started, trigger Event 9 to clear alarm AB-18.

SRO 2. NOTIFY OMOC (Duty Officer).

Cue: OMOC is notified.

3. MONITOR all A" RCP bearing temperatures (C-04R or PPC).

4. CHECK the following alarm windows not lit (C-02/3):

• RCP A ANTIREV BRG TEMP HI" (AA-19)

• RCP A UPPER GUIDE TEMP HI" (BB-20)

• RCP A UPPER THRUS TEMP HI" (CB-20)

5. IF alarm does not clear AND any alarm listed in step 4. is valid, PERFORM the ATC following:

5.1 TRIP reactor and turbine.

5.2 STOP A" RCP.

5.3 Refer To EOP 2525, Standard Post Trip Actions" and PERFORM required actions.

SUBMIT Trouble Report Examiner Note: Because none of the annunciators listed in Step 4 are in alarm, Step 5 is N/A.

Examiner Note: Once the actions of ARP 2590B-074 have been completed, or at lead examiners direction, proceed to Event 3, A RCP Seal Cooler Leak.

6 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 3, A RCP Seal Cooler Leak of 5-8 gpm Indications Available:

• PPC Alarm for RCS Leakage

• LI-6001 RB Surge TK level rise C06

• RCP A CLG WTR TEMP HI C-02/3 DB-17 (no alarm, but may be referenced for trip criteria)

• PROCESS MON RAD HI HI/FAIL C-06/7 DA-24 Examiner Note: The following steps are from ARP 2590B-072 (C-02/3 DB-17).

AUTOMATIC FUNCTIONS

1. None CORRECTIVE ACTIONS ATC 1. IF A RCP RBCCW outlet temperature is above 125°F, PERFORM the following:

1.1. TRIP Reactor.

1.2. TRIP Turbine.

1.3. STOP A RCP.

1.4. Go To EOP 2525, Standard Post Trip Actions.

Examiner Note: ARP 2590B-072 (C-02/3 DB-17) may be referenced for trip criteria. However, the actual temperature should stabilize far enough below 125°F to not require a plant trip/RCP shutdown.

Examiner Note: The following steps are from ARP 2590E-135 (C-06/7 DA-24).

AUTOMATIC FUNCTIONS

1. None CORRECTIVE ACTIONS NOTE:

SRO 1. When the PROCESS MON RAD HI/HI FAIL alarm is received, all TS and REMODCM radiation monitors associated with this alarm are considered to be INOPERABLE until the alarm is cleared.

2. If the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> maintenance window is applied and the PROCESS MON RAD HI/HI FAIL alarm will remain longer than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then log into appropriate action statements. Track 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> maintenance window using LCO Module.

7 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior

1. Refer To the following LCOs and DETERMINE applicability:

• TS 3.4.6.1 (RM-8123A, RM-8262A - applies only if alarm windows C-01, A-28, CH A CTMT AIR PARTICULATE RADIATION HI and B-28, CH B CTMT AIR PARTICULATE RADIATION HI are not OPERABLE).

• TS 3.3.3.1 (RM-8123A, RM-8262A - applies only if alarm windows C-01, SRO A-28, CH A CTMT AIR PARTICULATE RADIATION HI and B-28, CH B CTMT AIR PARTICULATE RADIATION HI are not OPERABLE).

• REMODCM IV.C.1 TABLE IV.C-1 (RM-6038, RM-4262- REMODCM allows use of 12 hr Maintenance Window)

• REMODCM IV.C.2 TABLE IV.C-3 (RM-8132A/B- REMODCM allows use of 12 hr Maintenance Window), (RM-9095 applies only if performing a Waste Gas discharge)

BOP 2. OBSERVE which process radiation monitor is alarming (RC-14).

Examiner Note: RBCCW rad monitor RM-6038 is in alarm, therefore the SRO should note that REMODCM IV.C.1 TABLE IV.C-1 applies in Step #1 above.

3. IF no ALARM OR INSTRUMENT FAIL lights lit, PERFORM the following BOP (RC-14):

Examiner Note: Step #3 is N/A due to RBCCW rad monitor RM-6038 being in alarm.

4. Refer To ARP 2590H, Alarm Response for Control Room Radiation Monitor SRO/BOP Panels, and PERFORM applicable corrective actions for alarming radiation monitor.

Examiner Note: The SRO should refer to ARP 2590H for additional guidance and direct the BOP to either continue with the guidance of ARP 2590-135 C-06/7 DA-24, or shift to performing ARP 2590H.

Upon referring to ARP 2590H, the SRO should select RBCCW GROSS ACTIVITY RIC-2300B, RC-14D, ARP 2590H-041A. The following are the applicable steps from ARP 2590H-041A.

AUTOMATIC FUNCTIONS

1. None SRO/BOP CORRECTIVE ACTIONS

1. OBSERVE radiation monitor indication (RC-14D, PPC).

2. COMPARE indication to setpoint indicated on SETPOINT" sticker on module.

3. CHECK PROCESS RADIATION, RJR-9373" (Channel 5) for trend data RC-14D).

8 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior

4. IF alarm is high, PERFORM the following:

4.1. One at a time, UNLOCK and CLOSE the following valves and MONITOR instrument response for determination of which header has in-leakage:

SRO/BOP

• A" RBCCW pump radiation element flow stop, 2-RB-43

• B" RBCCW pump radiation element flow stop, 2-RB-41

• C" RBCCW pump radiation element flow stop, 2-RB-39 Simulator Operator: When directed, trigger the applicable Event to close the requested RBCCW valve:

• A RBCCW pump, 2-RB Event #10 to CLOSE, Event #11 to RE-OPEN.

• B RBCCW pump, 2-RB Event #12 to CLOSE, Event #13 to RE-OPEN.

• A RBCCW pump, 2-RB Event #14 to CLOSE, Event #15 to RE-OPEN.

4.2. REQUEST Chemistry Department sample the following for gamma activity:

• Both RBCCW headers

• Service water effluent per SP 2854,
  Reactor Building Closed SRO/BOP Cooling Water (RBCCW) Radiation Monitor RM 6038 Inoperative" 4.3. Refer To OP 2383C,
  Radiation Monitor Alarm Setpoint Control" and EVALUATE need to adjust alarm setpoint.

4.4. IF Chemistry results indicate short-lived activity, Go To AOP 2568, RCS Leak."

Cue: Ten minutes after sample request, report short-lived activity detected in A RBCCW header.

Examiner Note: The remaining steps of ARP 2590H-041A are not applicable and the SRO should enter AOP 2568, RCS Leak at this time.

The applicable steps from AOP 2568 follow the remaining applicable steps of ARP 2590E-135.

The following steps continue from ARP 2590E-135 (C-06/7 DA-24), if they are addressed, but have no bearing on the scenario or crew actions.

5. IF RM-8123A/B or RM-8262A/B, alarms, Refer To the following for additional guidance (C-01):

SRO/BOP

6. CHECK DIGITAL COMPARATOR STACK PARTICULATE, RI---8132A (RC--

-14C), ALARM relay light lit.

Examiner Note: Step #5 and #6 are N/A due to RBCCW rad monitor RM-6038 being in alarm.

9 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior

7. DETERMINE cause of alarm and TRY to reset.

NOTE:

The Latch/Reset pushbutton on RIC-2300A, RIC-2300B, RIC-8123, and RIC-8262 is used to reset a latched, or locked-in alarm.

SRO/BOP

8. ATTEMPT to reset module by pushing RESET button.

9. IF alarm does not reset, to allow other alarms to annunciate, PERFORM applicable action:

9.1. IF RM-6038 alarms, OBTAIN key and place NORMAL BYPASS CH.1 BYPASS, HS-6038B, switch to BYPASS (RC-14D).

Examiner Note: The remaining steps from ARP 2590E-135 (C-06/7 DA-24) are not key to the scenario.

Examiner Note: The following steps are from AOP-2568.

1. Check Pressurizer Level - DECREASING ATC

a. ADJUST the bias on HIC-110, LTDN FLOW CNTL

b. CHECK Pressurizer Level - DECREASING

2. Increase Charging Flow

a. START second Charging Pump

b. STABILIZE Pressurizer Level by performing the following:

ATC

1. On HIC-110, LTDN FLOW CNTL, ADJUST the bias to obtain Pressurizer level to Program level

a. CHECK Pressurizer Level - STABLE or INCREASING ATC 3. INITIATE Forcing Pressurizer Sprays

4. Check Reactor Power and RCS Temperature

a. CHECK Reactor Power - STABLE ATC b. CHECK RCS temperature - STABLE or INCREASING NOTE:

Pumping the Containment Sump with an RCS leak should be avoided.

10 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior

5. Determine RCS Leak Rate By Any Of The Following:

a. ACCOUNT for RCP Bleedoff flow AND CALCULATE the difference in SRO/ATC/

Charging and Letdown flow BOP

b. REFER to ATTACHMENT B, Thumbrules, AND PERFORM a mass balance

c. OBTAIN SPDS Sump leak rate

6. CHECK RCS Leakage Within Limits Of T/S LCO 3.4.6.2, Reactor Coolant System Operational Leakage:

• NO Pressure Boundary Leakage SRO

• 1 gpm Unidentified Leakage

• 10 gpm Identified Leakage

• 75 gpd Primary to Secondary Leakage through any one steam generator ATC 7. CHECK VCT Level - STABLE

8. CHECK For Activities That Could Affect Primary Plant Leakage -

NONE IN PROGRESS SRO/ATC/

BOP

• Valve alignment

• Periodic Testing

• Maintenance

9. Check for Potential Leakage Paths SRO/ATC/ a. Using ATTACHMENT D, Potential Leakage Paths, LOCATE BOP AND ISOLATE leaks while continuing with this procedure NOTE:

SRO Steps 11 through 20 may be performed in any order.

11 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior Examiner Note: SRO should note TSAS 3.4.6.2 a.No PRESSURE BOUNDARY LEAKAGE ACTION:With ACTION and associated completion time of ACTION a. not met, or PRESSURE BOUNDARY LEAKAGE exists, or primary to secondary LEAKAGE not within limits, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

EAL Classification:

BARRIER FAILURE BU2 RCS LEAKAGE (Barrier Unusual Event)

1. Pressure Boundary Leakage > 10 GPM

2. Unidentified Leakage > 10 GPM

10. USE Table 1 to determine the order for dealing with leak identification and isolation.

Table 1 Event Step Completed Steam Generator Tubes Intact 11 SRO RCS Leakage In Auxiliary 12 Building Actions to Locate Leak-13 Containment RBCCW System 14 NOTE:

Any of the following are possible RCS leakage paths to RBCCW System:

SRO

• RCP Thermal Barrier

• Letdown HX

• Primary Sample Sink Coolers 12 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior

14. Check NO RCS Leakage Into RBCCW System

a. CHECK the following parameters:

BOP

• RBCCW Surge Tank level - NORMAL

• RM-6038, RBCCW System Radiation Monitor - NORMAL

b. RETURN TO step 10 RNO Step 14

a. PERFORM the following:

1. REQUEST Chemistry Department to sample the RBCCW System using CP SRO 2802G, Sampling Closed Cooling Water Systems.

2. ATTEMPT to isolate the leak using ATTACHMENT D, Potential Leakage Paths, while continuing with this procedure starting with step 15

3. PROCEED TO step 21.

Attachment D Table 10 RCS to RBCCW Leakage Paths Item Description Equipment Numbers Isolated Initials A and C RCP Seal Coolers RB-30.1A RBCCW CTMT ISOL HDR A SUPPLY _________

RB-37.2A RBCCW CTMT ISOL HDR A RTN _________

Examiner Note: Current plant conditions does not allow isolation, requires plant trip and Securing A and B RCP prior to isolation following actions should be carried out in EOP 2540 Cue: Chemistry acknowledges request to sample the RBCCW for a primary leak. Wait appropriate time and report back RBCCW Sample results.

SRO *21 Check RCS Leakage Has Been Reduced To Within Tech Spec 3.4.6.2 Limits RNO Step 21 PERFORM ONE of the following to place the plant in MODE 5:

SRO

• GO TO AOP 2575, Rapid Downpower OR

• GO TO OP 2207, Plant Cooldown 13 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _3__

Event

Description:

A RCP Seal Cooler Leak Time Position Applicants Actions or Behavior Examiner Note: SRO should note TSAS 3.4.6.2 a.No PRESSURE BOUNDARY LEAKAGE ACTION:

With ACTION and associated completion time of ACTION a. not met, or PRESSURE BOUNDARY LEAKAGE exists, or primary to secondary LEAKAGE not within limits, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Examiner Note: Based on the RCS Leak administrative guidance, the SRO should proceed to Event 4, Plant Shutdown.

14 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _4__

Event

Description:

Plant Shutdown Due to RCS Leak Time Position Applicants Actions or Behavior Examiner Note: The SRO should initiate Event 4, Plant Shutdown Due to RCS Leak.

Indications:

• RBCCW Surge Tank level - Rising

• RM-6038, RBCCW System Radiation Monitor - Rising

• Letdown Flow - Several gpm Less than Charging Flow Examiner Note: The following steps are from AOP-2575, Rapid Downpower, Section 3.0 Rapid Downpower.

SRO Enters AOP 2575, Rapid Downpower.

3.1 PERFORM focus brief on the following:

REACTOR TRIP CRITERIA

• Parameters associated with automatic reactor or turbine trips are challenged

• RCS T cold not within 10°F of temperature program and efforts to regain control are unsuccessful SRO RCS TEMPERATURE CONTROL

• RCS T cold to be maintained within +/- 5°F of Attachment 5, Temperature vs. Power program using Attachment 10, Main Turbine Load Set Control.

• To avoid uncontrolled cooldowns or power transients, sudden changes in RCS temperature or boron concentration should be avoided.

3.2 REQUEST SM/STA to Refer To Attachment 8, Required Notifications, and PERFORM notifications.

ATC 3.3 INITIATE forcing pressurizer sprays.

15 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _4__

Event

Description:

Plant Shutdown Due to RCS Leak Time Position Applicants Actions or Behavior CAUTION SRO In the case of a dropped CEA, rod motion is not used to initiate downpower.

3.4 IF not down powering due to a dropped rod, INSERT Group 7 CEAs 10 + 2 ATC steps to initiate downpower.

3.5 Using the Load Speed Control switch, REDUCE turbine load to maintain Tc BOP on program (+/-2 deg).

3.6 Refer To PPC or Reactor Engineering Curve and Data Book and OBTAIN SRO reactivity plan for the initial reactor power condition and desired load reduction.

Examiner Note: The crew should refer to Reactivity Plan for downpower parameters.

NOTE Attachment 10 Approximate Load Demand vs. Reactor Power, can be SRO used to correlate the desired power level to a turbine load demand setpoint.

3.7 Refer To Attachment 9, Main Turbine Load Set Control, REDUCE turbine BOP load and MAINTAIN Tc on program (+/-2 deg).

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Attachment 9 Main Turbine Load Set Control:

16 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _4__

Event

Description:

Plant Shutdown Due to RCS Leak Time Position Applicants Actions or Behavior CAUTION Operation of the Load/Speed CONTROL switch will change turbine load at 600%/hour, and cancel any previous load setpoint.

BOP NOTE Steps provided in this attachment are dependent on plant conditions and may be performed in any sequence, and repeated as necessary.

1. IF desired to commence or modify a turbine load ramp, PERFORM the following (HMI Load screen):

a. IF previous ramp has stopped, SELECT Load Hold.

BOP b. SELECT Load Setpt and ENTER desired value.

c. SELECT Rate setpt and ENTER desired value.

d. WHEN ready to commence load reduction, SELECT Load Resume.

2. IF desired to adjust the Load Ramp Rate, PERFORM any of the following:

• SELECT Rate setpt and ENTER new value.

• SELECT 5% / hour, OR 10% / hour, OR 20% / hour.

• SELECT Raise or Lower (0.25% / hour change).

a. IF Tavg and Tc are high off program, PERFORM the following:

a. SELECT Load Hold to stop ramp.

b. WHEN Tavg and Tc are trending back to program, SELECT Load BOP Resume.

b. IF Tavg and Tc are low off program, PERFORM the following:

a. JOG the Load/Speed CONTROL switch to Lower.

b. WHEN Tavg and Tc are back on program, SELECT Load Setpt and ENTER desired value.

c. IF desired, Go To Step 1 and RESUME turbine load ramp.

c. IF desired load has been reached SELECT Load Hold.

Examiner Note: operator should select x load setpoint, x load rate. Program band for Tavg and Tc is x (+/- 2 deg for Tc).

17 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _4__

Event

Description:

Plant Shutdown Due to RCS Leak Time Position Applicants Actions or Behavior Examiner Note: The following steps are from AOP 2575 Rapid Downpower Section 3.0 Rapid Downpower.

3.8 Based on required rate of downpower, START additional charging pumps as ATC necessary and balance charging and letdown.

3.9 IF desired to borate from the RWST (preferred method)

PERFORM the following:

a. ENSURE at least one charging pump operating.

b. ENSURE CH-196, VCT makeup bypass, closed.

c. ENSURE CH-504, RWST to charging suction, open.

ATC

d. OPEN CH-192, RWST isolation.

e. CLOSE CH-501, VCT outlet isolation.

f. CHECK charging flow at desired rate.

g. Go To step 3.11 Examiner Note: Crew should borate from the RWST.

18 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _4__

Event

Description:

Plant Shutdown Due to RCS Leak Time Position Applicants Actions or Behavior 3.11 During the downpower, Refer To Attachment 1,Rapid Downpower Parameters, and MAINTAIN parameters as specified throughout downpower:

Examiner note: Attachment 1 Rapid Downpower Parameters:

• Condensate and heater drain flows and pressures: sufficient to maintain adequate SGFP suction pressure

• FRV D/P: greater than 40 psid

• Turbine load: responding to changes in load demand, with control valves operating together SRO/ATC/

• Steam generator levels 55 to 70%.

BOP

• MSR parameters tracking together

• Turbine Generator MVARs: as specified by CONVEX

• Reactor power: being monitored using delta T power indication

• ASI: In accordance with reactivity plan or within 0.01 of ESI or per COLR.

• CEA position: greater than PDIL

• Tc: less than or equal to 549 deg

• Pressurizer level: between 35 and 70%

Pressurizer pressure: between 2,225 and 2,300 psia (DNB margin)

NOTE

1. Xenon rate of change should be considered when terminating boration.

SRO/ATC 2. During rapid downpower, the PPC calorimetric may be inaccurate due to SG level transients. The most accurate available indication of reactor power is RPS delta T power.

Examiner Note: Once power has dropped at least 5%, or at the lead examiners direction, proceed to Event 5, A RCP Seal Cooler Rupture, Manual Plant Trip.

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Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _5__

Event

Description:

A RCP Seal Cooler Rupture of 550 gpm (Inter-System SB-LOCA)

Time Position Applicants Actions or Behavior Simulator Operator: When directed, initiate Event 5, A RCP Seal Cooler Rupture (550 gpm)

Resulting in an Inter-System SB-LOCA of 550 gpm by modifying RC20A to 550 gpm (or trigger E-5).

Verify Event 6 triggers 30 seconds post-trip, ESD Outside CTMT, Upstream of #2 MSIV Verify Event 7 triggers five minutes post-trip; A AFW pump degraded performance and B Motor Driven AFW pump trip. Standby to trigger Event 8 if necessary.

Indications:

• RCS Pressure - Dropping

• Pressurizer Level - Dropping Examiner Note: The following steps are from EOP 2525, Standard Post Trip Actions, modified slightly to improve clarity.

Determine Status of Reactivity Control - Reactor Trip

1. DETERMINE that Reactivity Control acceptance criteria are met for the reactor by performing ALL of the following steps:

ATC

• CHECK that all CEAs are fully inserted.

• CHECK that reactor power is dropping.

• CHECK that SUR is negative.

Determine Status of Reactivity Control - Turbine Trip

2. DETERMINE that Reactivity Control acceptance criteria are met for the turbine by performing ALL of the following steps:

a. CHECK that the main turbine is tripped by BOTH of the following:

BOP

• ALL main stop valves are closed.

• Generator megawatts indicate zero.

• Turbine speed is lowering.

b. IF 15G-2XI-4, motor operated disconnect, is closed, CHECK that the main Generator output breakers 8T and 9T are open.

20 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _5__

Event

Description:

A RCP Seal Cooler Rupture of 550 gpm (Inter-System SB-LOCA)

Time Position Applicants Actions or Behavior Determine Status of Maintenance of Vital Auxiliaries

3. DETERMINE that Maintenance of Vital Auxiliaries acceptance criteria are met by performing ALL of the following steps:

a. CHECK that ALL Facility 1 and 2 electrical buses are energized:

• 6.9kV Electrical Buses 25A, 25B BOP

• 4.16kV Non-Vital Electrical Buses 24A, 24B

• 4.16vV Vital Electrical Buses 24C, 24D

• Vital DC Buses 201A, 201B, DV-10, DV-20

• Vital AC Instrument Buses VA-10, VA-20

b. CHECK that BOTH facilities of service water are operating.

c. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

Determine Status of RCS Inventory Control

4. DETERMINE that RCS Inventory Control acceptance criteria are met by performing ALL of the following:

ATC

a. CHECK that BOTH of the following conditions exist:

• Pressurizer level is 20 to 80%

• Pressurizer level is trending to 35 to 70%

b. CHECK that RCS subcooling is greater than or equal to 30°F RNO a.1 IF the Pressurizer Level Control System is not operating properly in automatic, RESTORE and MAINTAIN pressurizer level 35 to 70% by performing ANY of the following:

ATC

1) OPERATE the Pressurizer Level Control System.

2) Manually OPERATE charging and letdown.

(Starts all avialable Charging pumps and isolates letdown when PZR level

<20% ref:OP2260)

Determine Status of RCS Pressure Control

5. DETERMINE RCS Pressure Control acceptance criteria are met by BOTH of ATC the following:

• CHECK that pressurizer pressure is 1900 to 2350 psia.

• CHECK that pressurizer pressure is trending to 2225 to 2300 psia.

21 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _5__

Event

Description:

A RCP Seal Cooler Rupture of 550 gpm (Inter-System SB-LOCA)

Time Position Applicants Actions or Behavior RNO 5.1 IF the Pressurizer Pressure Control System is not operating properly in automatic, THEN RESTORE and MAINTAIN between 2225 to 2300 psia by performing ANY of the following:

a. OPERATE the Pressurizer Pressure Control System.

b. Manually OPERATE pressurizer heaters and spray valves.

(NOTE PZR Heaters will trip PZR level <20%)

ATC 5.2 PZR Spray valves (Verifies Closed) 5.3 PORVs (Verifies Closed) 5.4 RCS Pressure <1750 psia SIAS CIAS EBFAS on C01 annuciators.

5.5 <1714 psia w/SIAS Secure ONE RCP in each loop (at 1800 psia manually initiates SIAS trips 2 RCP preferably A and C due to A RCP seal Leak) 5.6 TCOA: RCS pressure < NPSH SECURE ALL RCPs CRITICAL TASK: LOCA-13 Trip two RCPs with SIAS actuation and a LOCA in progress.

RCS Pressure when RCPs were tripped _________

CRITICAL TASK: LOCA-12/TCOA: RCP < NPSH Curve - 5 minutes to STOP ALL RCPs (NOTE: RCS conditions may not go below RCP NPSH due to the Crews actions)

Time RCS pressure dropped below NPSH required pressure _________

Time RCPs were tripped due to loss of NPSH pressure _________

Determine Status of Core Heat Removal

6. DETERMINE that Core Heat Removal acceptance criteria are met by ATC performing ALL of the following:

a. CHECK that at least one RCP is operating and that loop delta T is less than 10°F

b. CHECK that Th subcooling is greater than or equal to 30°F.

RNO a.1 IF RCPs are not operating, OR loop T is greater than 10° F, THEN PERFORM the following:

1) PLACE TIC- 4165, steam dump TAVG controller, in manual and ATC closed.

2) PLACE BOTH pressurizer spray valve controllers in manual and CLOSE the valves.

• HIC- 100E

• HIC- 100F 22 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior Simulator Operator:

Verify Event 6 triggers 30 seconds post-trip, ESD Outside CTMT, Upstream of #2 MSIV Verify Event 7 triggers five minutes post-trip; A AFW pump degraded performance and B Motor Driven AFW pump trip. Standby to trigger Event 8 if necessary.

Examiner Note: Once Event 6 ESDE is initiated the BOP will re-perform Step 7 of EOP 2525 if the OPERATOR has already completed the Step.

Determine Status of RCS Heat Removal

7. DETERMINE that RCS Heat Removal acceptance criteria are met by ALL of the following conditions:

BOP a. CHECK that at least one steam generator has BOTH of the following conditions met:

• Level is 10 to 80%.

• Main feedwater or TWO auxiliary feedwater pumps are operating to restore level 40 to 70%.

RNO a.1 RESTORE level to between 40% to 70% in at least ONE steam generator using ANY of the following:

• Main feedwater BOP

• Motor- driven auxiliary feedwater pump

• TDAFW Pump. Refer To Appendix 6, TDAFW Pump Normal Startup.

• TDAFW Pump. Refer To Appendix 7, TDAFW Pump Abnormal Startup.

(EVENT 7 Operator notes that A AFW Pump has degraded performance and the B AFW Pump has tripped, refers to Appendix 7 to start the TDAFW pump)

Simulator Operator: If A AFW pump malfunction is not enough to cause unacceptable loss of feed flow such that the TDAFW pump is not needed, trigger Event 8, A AFW Pump trip.

CRITICAL TASK: LOCA-2; Start the TDAFP (Ensure RCS Heat Sink is maintained).

OP 2260 (TCOA); SG level lowering and no feedwater flow from MDAFW pumps, start TDAFW pump within 10 minutes of loss of feedwater flow.

Time AFW Flow is lost _________

Time TDAFW pump started _________

23 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior BOP b. CHECK that RCS Tc is being maintained between 530°F to 535"F.

RNO BOP b.2 IF RCS TC is less than 530°F, THEN CONFIRM steam generator steam and feed rates are NOT excessive:

BOP c. CHECK that BOTH steam generators pressure are 880 to 920 psia.

CRITICAL TASK: Main Steam Line Break (SFRM 2.8.2.8.2) INITIATING EVENT:

Excess steam demand event resulting in a Main Steam Isolation Signal (MSIS)

OP 2260 (TCOA); Isolate AFW flow to the affected S/G from control room or local Within 30 minutes of a Main Steam Isolation Signal TIME Main Steam Isolation Signal (MSIS):_______________

TIME AFW Isolated EOP 2525 RNO Step 7c2:____________

RNO (CRITICAL TASK START TIME)

BOP c.1 IF ANY SG pressure is less than 572 psia, THEN ENSURE MSI actuated.

(C01)

RNO c.2 TCOA: IF ANY SG pressure is less than 572 psia AND an ESDE is in progress, THEN PERFORM the following to isolate AFW to the most affected SG

1) PLACE BOTH auxiliary feed OVERRIDE/ MAN/START/ RESET handswitches in PULL TO LOCK.

2) CLOSE applicable Aux Feed Reg valve:

• 2- FW- 43A

• 2- FW- 43B

3) IF necessary, CONSIDER use of 2- FW- 44:

BOP

• IF #1 SG faulted, THEN CLOSE 2- FW- 44 and STOP the motor driven AFW pumps

• IF #2 SG faulted, THEN CLOSE 2- FW- 44 and STOP the TDAFW pump

4) IF necessary, DISPATCH operator to to close applicable AFRV manual isolation valve:

• 2- FW- 11A

• 2- FW- 11B (CRITICAL TASK STOP TIME) 24 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior RNO c.3 IF ANY steam generator pressure is less than 572 psia AND an excess steam demand event is in progress, THEN PERFORM the following:

BOP 1) CLOSE the ADV for the most affected steam generator.

2) IF the most affected steam generator has boiled dry, as indicated by CET temperature rising, THEN OPERATE the ADV for the least affected steam generator to stabilize CET temperature.

3) Proceed To Step 8 c.4 IF ANY steam generator pressure is less than 800 psia AND lowering, THEN PERFORM the following:

BOP 1) CLOSE BOTH MSIVs.

2) ENSURE BOTH MSIV bypass valves are closed.

3) NOT APPLICABLE FOR THIS SCENARIO c.5 IF ANY steam generator pressure is less than 880 psia, THEN PERFORM the following:

1) NOT APPLICABLE FOR THIS SCENARIO BOP

2) NOT APPLICABLE FOR THIS SCENARIO

3) CHECK main steam safety valves are closed.

c.6 NOT APPLICABLE FOR THIS SCENARIO 25 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior Containment Isolation

8. ENSURE Containment Isolation met by ALL of the following:

a. CHECK Containment pressure is less than 1.0 psig.

b. CHECK NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Radiation Monitors Inside Containment

• RM- 7890, Personnel Access Area

• RM- 7891, Ctmt Refuel Floor Area ATC

• RM- 8240, High Range

• RM- 8241, High Range

• RM- 8123 A and B, Ctmt Atmosphere

• RM- 8262 A and B, Ctmt Atmosphere

c. CHECK NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Steam Plant Radiation Monitors

• RM- 5099, Steam Jet Air Ejector

• RM- 4262, SG Blowdown

• RM- 4299A and B, Main Steam Line 1

• RM- 4299C, Main Steam Line 2 Containment Temperature and Pressure Control

9. ENSURE Containment Temperature and Pressure Control met by BOTH of the ATC following conditions:

a. CHECK Containment temperature is less than 120°F. (PPC or avg of Points 5 and 6)

b. CHECK Containment pressure is less than 1.0 psig Event Diagnosis

10. PERFORM the following:

SRO a. DIAGNOSE the event. Refer To Appendix 1, Diagnostic Flowchart.

b. INITIATE Appendix 4, Attachment 4A Reactor Trip Subsequent Actions.

c. Go To the appropriate EOP.

Examiner Note: The Unit Supervisor refers to EOP 2541 Appendix 1, Diagnostic Flowchart to diagnose the event.

26 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior

{Step 10.b above}

Perform Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions".

ATC/BOP Examiner Note: EOP Appendix 4, Attachment 4A "Reactor Trip Subsequent Actions." are attached to guide.

Examiner Note: The following steps are from EOP 2540, Functional Recovery.

Indications:

• #2 S/G Pressure

• RCS Cold Leg Temperature

• Sub Cool Margin

1. CLASSIFY the event. Refer To MP-26-EPI-FAP06, Classification and PARs SRO

• IF classification requires RCS sampling, Refer To Appendix 46, Sampling for EAL Determination and DIRECT Chemistry as required.

Examiner Note:

RCS BARRIER CTMT BARRIER .

2. PERFORM ALL of the following:

SRO

• OPEN the Safety Function Tracking Page and ENTER the EOP entry time.

• ENSURE the master alarm silence switch is in NORMAL.

3. IF pressurizer pressure is less than 1714 psia AND SIAS has initiated, PERFORM the following:

a. ENSURE ONE RCP in each loop is stopped.

b. PLACE associated pressurizer spray valve controller RC-100E or RC-100F in manual and CLOSE the valve.

ATC c. IF pressurizer pressure lowers to less than the minimum RCP NPSH limit, PERFORM the following:

1) STOP ALL RCPs.

2) PLACE TIC-4165, steam dump TAVG controller, in manual and closed.

3) PLACE pressurizer spray valve controllers RC-100E and RC-100F in manual and CLOSE the valves.

27 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior

4. SAMPLE steam generators that are available for RCS heat removal as follows:

a. CHECK B train RBCCW in service.

b. ENSURE 2-RB-210 Degasifier Effluent Cooler Return Outlet is open.

c. OPEN appropriate steam generator sample valves:

• MS-191A

• MS-191B

d. DIRECT Chemistry to perform ALL of the following:

• Sample ANY steam generator that is available for RCS Heat BOP Removal

• Frisk the samples

• Report frisk results

• Analyze samples for boron and activity

e. WHEN Chemistry reports that samples have been taken, PERFORM the following:

• CLOSE the steam generator sample valves

• IF SIAS has actuated, AND no other sampling is in progress, CLOSE 2-RB-210, Degasifier Effluent Cooler Return Outlet CUE: When directed to sample Steam Generators, respond 20 minutes later that samples have been taken. Report that frisk results show all background levels.

BOP 5. PLACE the hydrogen analyzers in service. Refer To Appendix 19, Hydrogen Analyzer Operation.

NOTE If the Safety Function Status Checklist is not satisfied for the selected success path, the US may commence the operator actions for safety functions which are SRO not met based on Safety Function hierarchy. The remaining Safety Functions should be prioritized as time permits.

6. IDENTIFY success paths to be used to satisfy each safety function using BOTH SRO of the following:

• Resource Assessment Trees

• Safety Function Tracking Page 28 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior

7. PRIORITIZE safety functions to be addressed first based on ALL of the following:

a. Safety functions which do not meet the Safety Function Status Checklist for the selected success path.

b. Safety functions for which the equipment to support the success path is SRO not operating.

c. Safety functions for which success path three has been selected.

d. Safety functions for which success path two has been selected.

e. Safety functions for which success path one has been selected.

NOTE: SRO will direct the Board Operators through the Resource Assessment Trees and query plant status to determine the correct Functional Procedure to use.

4.0 SAFETY FUNCTION STATUS CHECKLIST SAFETY FUNCTION TRACKING PAGE EOP ENTRY TIME __________

Safety Function Success Path Procedure SFSC Priority Met RC-1 CEA Insertion Y Reactivity RC-2 Boration CVCS EOP 2540A 5 Control RC-3 Boration SI Maintenance of Battery Chargers/ EOP 2540B Y 6 SRO Vital DC Power MVA-DC-1 Station Batteries MVA-AC-1 RSST Y Maintenance of MVA-AC-2 EDG EOP 2540B 7 Vital AC Power MVA-AC-3 BUS 34A/34B RCS Inventory IC-1 CVCS EOP 2 Control IC-2 Safety Injection 2540C1 Y

PC-1 Subcooled NOTE MAYBE Y Sub or Sat RCS Pressure PC-2 Saturated EOP depending on Y crew actions Control 2540C2 7,3 PC-3 PORVs RCS Core Heat HR-1 SI no operating Removal EOP 2540D 3,4 HR-2 SI operating Y SRO HR-3 O-T-C Containment CI-1 Automatic/Manual EOP 2540E N 1 Isolation Containment CTPC-1 CARs (Normal) Y Temperature and EOP 2540F 8 CTPC-1 CARs (Emerg)

Pressure Control CTPC-1 CTMT Spray 29 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior SRO 8. DIRECT the STA to check that Safety Function Status Checklist Criteria are satisfied for chosen success paths.

9. PERFORM operator actions for chosen success paths based on priority assigned.

TRANSITION to EOP 2540E Functional Recovery Containment Isolation Examiner Note: The following steps are from EOP 2540E, Functional Recovery Containment Isolation.

Check SIAS/CIAS Actuation

• 1. IF ANY of the following conditions exist:

• Containment pressure is greater than or equal to 4.42 psig

• Radiation monitors inside containment are greater than their alarm setpoint

• An unexplained rise in containment radiation level or activity NOT APPLICABLE FOR THIS SCENARIO previously checked Identify and Isolate SGTR

• 2. IF a SGTR is indicated by ANY of the following:

NOT APPLICABLE FOR THIS SCENARIO no SGTR Isolate RCS to RBCCW Leakage

• 3. CHECK no leakage in the RBCCW system by BOTH of the following:

• CHECK RM-6038, RBCCW Radiation Monitor, is not alarming or trending to alarm.

• CHECK that the RBCCW surge tank level is not rising.

RNO 3.1 IF ANY RCPs are operating, PERFORM the following:

a. STOP the operating RCPs.

b. PLACE the associated pressurizer spray valve controller, RC-100E or RC-100F, in manual and CLOSE the valve.

c. IF ALL RCPs are stopped, PLACE TIC-4165, steam dump TAVG controller, in manual and closed.

Examiner Note: Completed in previously step for SIAS actuation 30 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior RNO 3.2 CLOSE ALL of the following RBCCW CTMT header isolation valves:

Facility 1

• RB-30.1A

• RB-37.2A Facility 2

• RB-30.1B

• RB-37.2B Examiner Note: Closing Facility 1 isolation satisfies Safety Function for CTMT Isolation

4. CHECK that CI-1 (Automatic/Manual Isolation) is satisfied by ALL of Condition 1 or ALL of Condition 2 is met:

Condition 2

• Each containment penetration required to be closed for current plant conditions has an isolation valve closed

• ONE of the following:

o No steam plant radiation monitors have an unexplained alarm or unexplained rises in activity o ALL release paths from the most affected SG to the environment isolated unless a planned release is in progress

• IF SGTR is present, steam generator pressure is less than 920 psia Examiner Note: Condition 2 is Satisfied SRO should transition to the next priority Safety Function for Inventory EOP 2540C1(IC-2Safety Injection).

Examiner Note: The following steps are from EOP 2540C1 IC-2, Functional Recovery Safety Injection 2.0 SUCCESS PATH: IC-2: SAFETY INJECTION Ensure SIAS Initiated ATC

• 1. PERFORM ALL of the following:

Completed in EOP 2525 or 2540 31 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior Optimize Safety Injection

• 2. PERFORM the following to optimize safety injection flow:

a. CHECK at least one train of SIAS, CIAS and EBFAS has properly actuated. (C01X)

ATC

b. CHECK that safety injection flow is adequate. Refer To Appendix 2, Figures.

c. ENSURE ALL available charging pumps are operating.

d. ENSURE vital switchgear cooling is operating for each operating ECCS train as follows:

(Completed previously)

Examiner Note: Once the SRO meets the SI Injection flow curve the SRO should handoff the rest of the procedure to the ATC and Transition to RCS Core Heat Removal to isolate the #2 S/G EOP 2540D Examiner Note: The following steps are from EOP 2540D HR-2, Functional Recovery Heat Removal 2.0 SUCCESS PATH: HR- 2: SG HEAT SINK WITH SI OPERATING SRO Pulls Forward Step 14 Determine Presence of ESDE

• 14. DETERMINE if an ESDE is in progress by considering ALL of the following:

SRO

• Steam generator pressures

• Steam generator levels

• RCS cold leg temperatures (Determined #2 S/G)

NOTE If there is a conflict between isolating a SG and maintaining adequate heat removal, at least one SG should be maintained for heat removal whenever possible.

Perform ESDE Response SRO

• 15. IF indications of an ESDE exist, PERFORM ESDE actions.

Refer To Appendix 11, ESDE Response.

(SRO Directs the BOP to perform Appendix 11 isolate the #2 S/G)

EOP 2541, Appendix 11 ESDE Response

1. PERFORM the following to isolate the leak:

a. ENSURE MSI has actuated. (C01)

b. CHECK at least one train of MSI has properly actuated. (C01X)

c. OPEN AR-17, condenser vacuum breaker.

32 of 29

Op-Test No.: __ ES16LI3___ Scenario No.: __3__ Event No.: _6&7_

Event

Description:

ESD Outside CTMT, Upstream of #2 MSIV and Loss of AFW Flow Time Position Applicants Actions or Behavior

2. DETERMINE the most affected steam generator by considering ALL of the following:

• High steam flow from steam generator

• Lowering steam generator pressures

• Lowering steam generator levels

• Lowering RCS cold leg temperatures

• 3. IF the leak has not been isolated, ISOLATE the most affected steam generator by performing the following:

Number 2 Steam Generator

a. ENSURE MS-64B, MSIV, is closed.

b. ENSURE MS-65B, MSIV bypass valve, is closed.

c. ENSURE ALL of the following for the associated ADV:

• PIC-4224, ADV controller, is in manual.

• ADV is closed.

d. PLACE ADV Quick Open Permissive switch to OFF.

e. CLOSE LIC-5216, main feedwater regulating bypass valve.

f. ENSURE FW-42B, main feedwater block valve, is closed.

g. PLACE FW-5B, main feed isolation air assisted check valve, to CLOSE.

h. UNLOCK and CLOSE DISC FOR 2-MS-202 (NS6202).

i. CLOSE MS-202, steam to turbine driven aux feed pump supply valve.

j. ENSURE MS-220B, steam generator blowdown isolation valve, is closed. k.PLACE BOTH auxiliary feed OVERRIDE/MAN/START/ RESET handswitches in PULL-TO-LOCK.

l. CLOSE FW-43B, aux feedwater regulating valve.

m. PLACE FW-12B, aux feed isolation air assisted check valve, to CLOSE.

n. CLOSE MS-266B, main steam low point drain.

o. CHECK main steam safety valves are closed.

Examiner discretion the objectives for the scenario are complete and can terminate the session 33 of 29

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Shutdown Safety Assessment Decay Heat Removal JPM Number: JPM-292-R-RO Revision: 0/1 Initiated:

David J. Jacobs 05/18/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 05/18/2016 New JPM for I LT 0/0 08/18/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: MP-2 Examinee:

JPM Number: JPM-292-R-RO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Decay Heat Removal System: Conduct of Operations Time Critical Task: YES NO Validated Time (minutes): 60 Task Number(s): 119-01-044 Applicable To: SRO X STA RO X PEO K/A Number: 2.1.18 K/A Rating: 3.6/3.8 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM the examinee has determined the appropriate color code for the predicted Decay Heat Removal Key Safety Function when in Reduced Inventory.

Required Materials: MP-PROC-000-OU-M2-201[r018.00] Shutdown Safety Assessment Checklist (procedures, equipment, etc.)

General

References:

MP-PROC-000-OU-M2-201[r018.00] Shutdown Safety Assessment Checklist

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-292-R-RO Revision : 0/1 Initial Conditions: The plant is in MODE 5 day 2 of a scheduled 28 day refueling outage.

Reactor disassembly is in progress and the Reactor Head is expected to be removed within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The following additional conditions presently exist:

• A Train is protected.

• B EDG tagged for Maintenance

• Back Feeding from the NSST

• No Off-Site GRID Risk Penalty Factors

• RCS Boron concentration is 2200 ppm.

• RCS temperature is 105°F.

• PZR level is 20%

• PZR Vent Port Removed Initiating Cues: The US has given you the current Shutdown Safety Assessment and directed you perform a predicted SSA for the RCS in Reduce Inventory for the following Sections only:

• Section 3 Decay Heat Removal (DHR)

• Section 7 Power Availability Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-292-R-RO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Decay Heat Removal START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Refers to MP-PROC-000-OU-M2-201 Shutdown Examinee reviews Current Condition SSA Y N S U Safety Assessment Checklist And Current Condition SSA Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 3.1 Key Safety Functions Examinee Assess the following Key Safety Y N S U 3.1.1 ASSESS and MANAGE the following Functions:

KSFs for risk during shutdown conditions:

• Decay Heat Removal

• Decay Heat Removal (DHR)

• Power Availability

• Power Availability Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-292-R-RO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Decay Heat Removal STEP Performance: Standard: Critical: Grade

1. 3 3.3 Shutdown Safety Assessment (SSA) Examinee refers to the following: Y N S U Checklist Preparation

• ATTACHMENT 4 Decay Heat Removal 3.3.1 Using the following detailed information Requirements and performs for each KSF, COMPLETE Attachment 1: Attachment 1Section 3 Decay Heat

f. Section 3 - Decay Heat Removal (DHR) Removal

1. RCS Decay Heat Removal (DHR)

• Subtracts 1 point for Reduced Inventory Operations

• REFER to Attachment 4 for background

• Change Total Condition to 1 points information of each element associated with

• Circles ORANGE the Decay Heat Removal KSF.

• CHECK appropriate boxes for conditions supporting Key Safety Function of RCS decay heat removal.

• TOTAL score and ENTER value in RCS DHR Total box.

• CIRCLE Condition color corresponding to point total.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-292-R-RO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Decay Heat Removal STEP Performance: Standard: Critical: Grade

1. 4 3.3 Shutdown Safety Assessment (SSA) Examinee refers to the following: Y N S U Checklist Preparation 1. ATTACHMENT 8 background information 3.3.1 Using the following detailed information Power Availability Requirements and performs for each KSF, COMPLETE Attachment 1: 2. Attachment 1Section 7 Power Availability

j. Section 7 - Power Availability

• Reviews Required Equipment and does

1. REFER to Attachment 8 for background not meet 2 EDG available = RED information for each element associated with 3. No GRID Penalty Power Availability KSF. 4. Total Score remains 4

2. CHECK appropriate boxes for conditions 5. Circle Condition RED for not meeting supporting Key Safety Function of Power Minimum Equipment Availability.

3. IF required, THEN RECORD applicable Off-Site GRID Risk Penalty Factor and SUBTRACT from Power Availability subtotal to determine Power Availability Total.

4. TOTAL score and ENTER the value in Power Availability Total box.

5. CIRCLE Condition color corresponding to point total.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: JPM-292-R-RO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Decay Heat Removal STEP Performance: Standard: Critical: Grade

1. 5 3.4.6 DOCUMENT notification to OMOC and Examinee Reports going to Reduce Inventory will Y N S U Maintenance Rule Coordinator for any cause a RED Condition for Power Availability unplanned RED or ORANGE conditions.

a. IF OCC is staffed, THEN NOTIFY the SOM and OOM to ensure OMOC notifications are made.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM-292-R-RO Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 30 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 9

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM-292-R-RO Revision: 0/1 Initial Conditions: The plant is in MODE 5 day 2 of a scheduled 28 day refueling outage.

Reactor disassembly is in progress and the Reactor Head is expected to be removed within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The following additional conditions presently exist:

• A Train is protected.

• B EDG tagged for Maintenance

• Back Feeding from the NSST

• No Off-Site GRID Risk Penalty Factors

• RCS Boron concentration is 2200 ppm.

• RCS temperature is 105°F.

• PZR level is 20%

• PZR Vent Port Removed Initiating Cues: The US has given you the current Shutdown Safety Assessment and directed you perform a predicted SSA for the RCS in Reduce Inventory for the following Sections only:

• Section 3 Decay Heat Removal (DHR)

• Section 7 Power Availability Total Score and Condition Color Section 3 Decay Heat Removal (DHR)

Section 7 Power Availability Required Report (If Any) 11

12 13 14 15 16 17 18 19 20 21 22 JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

OP 2304C Batch Makeup to VCT calculation JPM Number: JPM-291-R-RO Revision: 0/1 Initiated:

David Jacobs 05/20/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/12/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 05/20/2016 Modified for ILT NRC Exam 0/0 08/18/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: Examinee:

JPM Number: JPM-291-R-RO Revision: 0/1 Task

Title:

OP 2304C Batch Makeup to VCT Calculation System: CVCS 004 Time Critical Task: YES NO Validated Time (minutes): 30 Task Number(s): 004-01-191 Applicable To: SRO STA RO X PEO K/A Number: A4.12 K/A Rating: 3.8 / 3.3 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM the Examinee will perform a calculation for a Batch Make Up to the Volume Control Tank Required Materials: MP-PROC-OPS-OP 2208[r015] Reactivity Calculations (procedures, equipment, etc.) MP-PROC-OPS-OP 2304C[r026.00] Make UP Portion of CVCS General

References:

MP-PROC-OPS-OP 2208[r015] Reactivity Calculations MP-PROC-OPS-OP 2304C[r026.00] Make UP Portion of CVCS

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-291-R-RO Revision : 0/1 Initial Conditions: The plant is currently at 100% reactor power with the following conditions:

• RCS boron concentration is 605 ppm boron

• C Charging pump in service

• A BAST is in service with a boron concentration of 5445 ppm

• Makeup Reactivity Correction Factor = 1

• The PPC is currently unavailable Initiating Cues: The Unit Supervisor has directed you to perform the following:

• Calculate a Neutral blend to raise VCT level from 75% to 85%

• Disregard volume of the blending tee to the charging pump suction

• Determine Total Gallons

• Determine Gallons of PMW

• Determine Gallons of A BAST Boric Acid Using OP 2304C Makeup (Boration & Dilution) Portion of CVCS section 4.6 Batch Make Up to VCT.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-291-R-RO Revision: 0/1 Task

Title:

OP 2304C Batch Makeup to VCT Calculation START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Using OP 2304C Makeup (Boration & Dilution) Examinee refers to the Initial Conditions and Y N S U Portion of CVCS determines 10%

Section 4.6 Batch Make Up to VCT.

4.6.3 Determine desired VCT level change in %

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 4.6.4 DETERMINE total gallons required to Examinee calculates: Y N S U make desired level change as follows:

Desired level change in 10% x 34 gallons = 340 gallons total desired level change = 1% level

% x 34 gallons = Total gallons for make up 1% level Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-291-R-RO Revision: 0/1 Task

Title:

OP 2304C Batch Makeup to VCT Calculation STEP Performance: Standard: Critical: Grade

1. 3 4.6.5 Refer To OP 2208, Reactivity Examinee refers to OP 2208 Reactivity Y N S U Calculations, or PPC and DETERMINE Calculations required ratio of boric acid flow to PMW flow, corrected for Boron-10 depletion.

Attachment 4 Blended Makeup Flowrate Determination Formula:

flowrate = [K x (boric acid flowrate)] ÷ CF PMW flowrate = [8 x (1)] ÷ 1 = 8 Where, K= (ppm boron in BAST) - (ppm boron in makeup) Where, 8= (5445) - (605) ppm boron in makeup 605 CF= Makeup Reactivity Correction Factor (From Att 5. Reactivity Thumb Rules, sheet OR Reactor CF = 1 from initial conditions Engineer)

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 4.6.6 DETERMINE total gallons of boric acid Examinee determines: Y N S U required to make desired level change as follows:

(BA = boric acid) 340 gallons total x __1___

Total gallons x BA flowrate = Total boric acid volume (1 + 8) for makeup BA + PMW flow rate

= 37.7777777 (38 gallons)

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-291-R-RO Revision: 0/1 Task

Title:

OP 2304C Batch Makeup to VCT Calculation STEP Performance: Standard: Critical: Grade

1. 5 4.6.7 DETERMINE total gallons of PMW Examinee determines: Y N S U required to make desired level change as follows:

(BA = boric acid):

340 gallons total x 8_______

Total gallons x PMW flowrate = Total PMW (8+1) for makeup BA+ PMW flow rate volume

= 302.22222222 (302 gallons)

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

Total Gallons 340 gallons PMW Gallons 302 gallons A BAST Gallons 38 gallons 7

VERIFICATION OF JPM COMPLETION JPM Number: JPM-291-R-RO Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 30 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 8

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: JPM-291-R-RO Revision: 0/1 Initial Conditions: The plant is currently at 100% reactor power with the following conditions:

• RCS boron concentration is 605 ppm boron

• C Charging pump in service

• A BAST is in service with a boron concentration of 5445 ppm

• Makeup Reactivity Correction Factor = 1

• The PPC is currently unavailable Initiating Cues: The Unit Supervisor has directed you to perform the following:

• Calculate a Neutral blend to raise VCT level from 75% to 85%

• Disregard volume of the blending tee to the charging pump suction

• Determine Total Gallons

• Determine Gallons of PMW

• Determine Gallons of A BAST Boric Acid Using OP 2304C Makeup (Boration & Dilution) Portion of CVCS section 4.6 Batch Make Up to VCT.

ANSWER:

Total Gallons PMW Gallons A BAST Gallons 10

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

SP 2602B Transient Temperature, Pressure Verification JPM Number: JPM-290-R-4B Revision: 0/1 Initiated:

David J. Jacobs 05/24/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/13/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 05/24/2016 New JPM for NRC ILT Exam 2016 0 08/18/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: MP-2 Examinee:

JPM Number: JPM-290-R-4B Revision: 0/1 Task

Title:

SP 2602B Transient Temperature, Pressure Verification System: 005 RHR Time Critical Task: YES NO Validated Time (minutes): 30 Task Number(s): 121-01-167 Applicable To: SRO X STA RO X PEO K/A Number: 005 A1.01 / 2.2.42 K/A Rating: 3.5 / 3.6 3.9 /4.6 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of the JPM the Examinee has reviewed the Computer Printout and referred to SP 2602B to determined cooldown rates are NOT within the Tech.

Spec Limits Required Materials: SP 2602B Transient Temperature, Pressure Verification (procedures, equipment, etc.) SP 2602B-001 Transient Temperature, Pressure Verification Data Sheet PPC SP 2602B Printout General

References:

SP 2602B Transient Temperature, Pressure Verification

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-290-R-4B Revision : 0/1 Initial Conditions: The Plant has completed a cooldown to 125°F in accordance with OP 2207 Cooldown using A and B RCPs concurrently with SDC.

• SDC was placed in service at 0105

• RCPs secured at 0300.

Initiating Cues:

The Unit Supervisor has directed you to use the computer data from the cooldown and perform SP 2602B Transient Temperature, Pressure Verification.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-290-R-4B Revision: 0/1 Task

Title:

SP 2602B Transient Temperature, Pressure Verification START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Refers to SP 2602B Transient Temperature, Examinee refers to OP 2602B, the Computer Print Y N S U Pressure Verification outs performs the following:

4.1 Heatup and Cooldown Initial and Conditional

• Records the Cooldown starting at 0000 Actions

• Uses T115 (refer to Stem A&B RCPs Loop #1)

• Uses T351Y at 0330 when RCPs are secured 4.1.2 IF available, DESIGNATE a person not involved in controlling the Heatup or cooldown to perform the following:

• DETERMINE and RECORD required data on SP 2602B-001.

• MONITOR parameters, limits, and Heatup or cooldown rates between entries.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 4.1.3 IF PPC data points are available, Examinee records and determines Hourly Y N S U PERFORM the following: Cooldown Rates recording parameters every half hour

• ESTABLISH trend(s) of selected parameters for trending and data gathering during Heatup or cooldown.

• OBTAIN required 30 minute data sheets from PPC printer, and Go To step 4.1.10.

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-290-R-4B Revision: 0/1 Task

Title:

SP 2602B Transient Temperature, Pressure Verification STEP Performance: Standard: Critical: Grade

1. 3 4.1.10 IF at any time, any administrative limit Examine determines during the transition from Y N S U (except pressurizer spray line differential RCPs to SDC when securing the RCPs the temperature between 200°F and 350°F) or any Technical Specification was exceeded at 51°F per TS/TRM acceptance criteria is not met, hour below 220°F at time 0230 to 0330 and PERFORM the following: informs the Unit Supervisor

• Immediately NOTIFY Shift Manager.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

6

VERIFICATION OF JPM COMPLETION JPM Number: JPM-290-R-4B Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 30 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 7

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: JPM-290-R-4B Revision: 0/1 Initial Conditions:

The Plant has completed a cooldown to 125°F in accordance with OP 2207 Cooldown using A and B RCPs concurrently with SDC.

• SDC was placed in service at 0105

• RCPs secured at 0300.

Initiating Cues:

The Unit Supervisor has directed you to use the computer data from the cooldown and perform SP 2602B Transient Temperature, Pressure Verification.

Circle Technical Specification Limits Exceeded: YES NO If YES TIME(S): _________________________

9

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Review RWP and Survey Map JPM Number: JPM-293-R-RO Revision: 2/3 Initiated:

David Jacobs/Robert L. Cimmino 09/28/2016 Developer Date Reviewed:

Paul Prichard 09/28/2016 Technical Reviewer Date Approved:

John W. Riley 09/29/16 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 10/23/08 Revised JPM for LOIT 2008 NRC Exam 1/0 12/29/08 Incorporated NRC Post-Validation comments 1/0 06/02/2016 Up dated for ILT NRC Exam 2016 2/0 08/18/2016 Incorporated NRC comments 2/1 09/15/2016 Incorporated changes due to abbreviated survey map 2/2 Incorporated changes due to change in interpretation of 09/28/2016 Initiating Cue Item #7 2/3 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-293-R-RO Revision: 2/3 Task

Title:

Review RWP and Survey Map System: Radiation Control Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): 404-01-004 Applicable To: SRO X STA RO X PEO K/A Number: 2.3.7 K/A Rating: 3.5 / 3.6 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM the examinee has reviewed the applicable RWP and survey map to determine the radiological requirements to perform the assigned task.

Required Materials: Operations blanket RWP No. 5.

(procedures, equipment, etc.) Survey map for -5 6 West Piping Penetration Room General

References:

MP-PROC-HP-RPM 5.2.2[r016] Basic Radiation Worker Responsibilities

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-293-R-RO Revision : 2/3 Initial Conditions: The crew is performing a plant heat up in accordance with OP 2201, Plant Heatup The plant is in MODE 3 with pressurizer pressure at 1400 psia.

Two Charging Pumps are in operation.

The gate in the -5 penetration room is currently unlocked Initiating Cues: You have been directed to isolate Letdown Flow Control Valve, 2-CH-110Q.

Based on previous experience, you estimate that this task will take 20 minutes.

Your available dose is 1,000 mR.

State the radiological requirements for entering this area. Include in your answer:

1. Which RWP task (job step) is appropriate for this assignment

2. Highest radiation level in the work area (including units of measure)

3. Highest contamination level in the immediate work area (including units of measure)

4. Protective clothing required in the immediate work area (including transition to and from the area)

5. Expected dose for this assignment area (including units of measure)

6. Dose rate alarm for this area (including units of measure)

7. Assuming significant difficulties are encountered, the longest possible stay time for this area per the RWP requirements The examiner will act as Health Physics (HP) for any related questions.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-293-R-RO Revision: 2/3 Task

Title:

Review RWP and Survey Map START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Review Operations Blanket RWP No. 5 and Examinee reviews Operations Blanket RWP No. 5 Y N S U Radiation Survey Figure 21A and Radiation Survey Figure 21A and answers the following questions:

Cue:

Provide examinee with Operations Blanket RWP No. 205 and Radiation Survey map.

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 1. Determine which RWP task (job step) is Examinee states that task (job step) No. 1 (No. 2, if Y N S U appropriate for this assignment. HRA is noted on map) is appropriate for this task.

Cue:

Comments:

2-CH-110Q is located in an area that has been designated as a High Radiation Area in the past due to changing radiation levels, therefore Task No. 2 may be selected instead of Task No. 1. Critical aspect of JPM is that subsequent data pertains to the chosen task.

STEP Performance: Standard: Critical: Grade

1. 3 2. Determine the highest radiation level in Examinee states that the highest radiation level in Y N S U the immediate work area. immediate work area is 45 mr/hr (may note 400mr/hr hot spot, but not a Critical Step)

Cue:

Comments:

The examinee may point out the 400 mr/hr hot spot near 2-SI-709, but that the assigned task does NOT require him/her to approach that area. Hence the possibility of using Task No. 1.

STEP Performance: Standard: Critical: Grade

1. 4 3. Determine the highest contamination Examinee states that the highest contamination Y N S U level in the work area. level in this area is 2,000 DPM/100cm2.

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-293-R-RO Revision: 2/3 Task

Title:

Review RWP and Survey Map STEP Performance: Standard: Critical: Grade

1. 5 4. Determine what protective clothing is Examinee states that contamination levels require Y N S U required in the area. full PCs (with modesty garments underneath).

Cue:

Comments:

Examinee may state the individual items that make up full PCs (Cotton liners, Booties, Coveralls, Shoe covers, Rubber gloves, Modesty garments)

STEP Performance: Standard: Critical: Grade

1. 6 5. Determine the expected dose for this Examinee states that the expected dose is Y N S U assignment. approximately 15mrem (14-16 mrem ).

Cue:

Comments:

45 mrem/hr Dose Rate X 1/3 hrs. (i.e.; 20 min.) 15 mr STEP Performance: Standard: Critical: Grade

1. 7 6. Determine the expected dose rate alarm Examinee states the following: Y N S U for this assignment. If using Task #1:

50 mr/hr dose rate alarm If using Task #2:

300 mr/hr dose rate alarm Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-293-R-RO Revision: 2/3 Task

Title:

Review RWP and Survey Map STEP Performance: Standard: Critical: Grade

1. 8 7. Determine the longest possible stay time Examinee states the maximum stay time: Y N S U for this assignment. If using Task #1: 26 minutes If using Task #2: 53 minutes Cue:

Comments:

25 mrem Dose Limit Alarm / 45 mrem/hr Dose Rate X 80% RWP Exit Requirement = 26.6 minutes (25 minutes to 28 minutes) 50 mrem Dose Limit Alarm / 45 mrem/hr Dose Rate X 80% RWP Exit Requirement = 53.3 minutes (52 minutes to 55 minutes)

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

7

VERIFICATION OF JPM COMPLETION JPM Number: JPM-293-R-RO Revision: 2/3 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 8

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: JPM-293-R-RO Revision: 2/3 Initial Conditions: The crew is performing a plant heat up in accordance with OP 2201, Plant Heatup The plant is in MODE 3 with pressurizer pressure at 1400 psia.

Two Charging Pumps are in operation.

The gate in the -5 penetration room is currently unlocked Initiating Cues: You have been directed to isolate Letdown Flow Control Valve, 2-CH-110Q.

Based on previous experience, you estimate that this task will take 20 minutes.

Your available dose is 1,000 mR.

State the radiological requirements for entering this area. Include in your answer:

1. Which RWP task (job step) is appropriate for this assignment

2. Highest radiation level in the work area (including units of measure)

3. Highest contamination level in the immediate work area (including units of measure)

4. Protective clothing required in the immediate work area (including transition to and from the area)

5. Expected dose for this assignment area (including units of measure)

6. Dose rate alarm for this area (including units of measure)

7. Assuming significant difficulties are encountered, the longest possible stay time for this area per the RWP requirements The examiner will act as Health Physics (HP) for any related questions.

10

1. RWP Task

2. Highest Rad. Lvl.

3. Highest contamination Lvl.

4. Required PCs

5. Expected Dose

6. Dose Rate Alarm

7. Max Stay Time 11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Shutdown Safety Assessment Review for RIO conditions JPM Number: JPM-295-R-SRO Revision: 0/1 Initiated:

David Jacobs 06/14/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 06/14/2016 Newly Created for NRC ILT Exam 2016 0 08/19/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-295-R-SRO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Review for RIO conditions System: Conduct of Operations Time Critical Task: YES NO Validated Time (minutes): 40 Task Number(s): 119-01-044 Applicable To: SRO X STA RO PEO K/A Number: 2.1.23 K/A Rating: 4.3 / 4.4 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM the examinee has reviewed the SSA for the predicted condition of the Key Safety Functions when in Reduced Inventory.

Required Materials: MP-PROC-000-OU-M2-201[r018.00] Shutdown Safety Assessment Checklist (procedures, equipment, etc.) Handout SSA Predicted Conditions pdf format Handout CTMT pen closure plan pdf format General

References:

MP-PROC-000-OU-M2-201[r018.00] Shutdown Safety Assessment Checklist

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-295-R-SRO Revision : 0/1 Initial Conditions: The plant is in MODE 5 day 1 of a scheduled 28 day refueling outage.

Reactor disassembly is in progress and the RCS is expected to be in Reduced Inventory within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The following additional conditions presently exist:

• PZR level is 20%

• PZR Vent Port Removed

• No Equipment out of service required for Mode 5

• Containment Closure is set with 1 exception Penetration #48 with a closure time of 30 minutes. (See attached Closure Plan)

• Time to Core Boil for Reduced Inventory was verified by the STA Assume no change in Equipment Status from the current condition to when the plant is in Reduced Inventory.

Initiating Cues:

Review the Predicted changes to the Shutdown Safety Assessment for the RCS in Reduce Inventory that was completed by the RO with the exception of Time To Core Boil calculation.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-295-R-SRO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Review for RIO conditions START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Reviews Section 2 Heatup Data: Examinee should note the following: Y N S U

• Time to Core Boil

• Shutdown risk Color should be ORANGE

• Shutdown Risk Color Cue:

Comments:

Section 3 Decay heat removal and Section 6 Containment were incorrectly calculated and should be ORANGE STEP Performance: Standard: Critical: Grade

1. 2 Reviews Section 3 Decay Heat Removal Data: Examinee should note the following: Y N S U

• Reduced Inventory Operation (RIO)

• The RIO Penalty was not subtracted Penalty

• RCS Decay Heat Removal Total was not

• RCS Decay Heat Removal Total calculated correctly and should be 1

• DHR Color Condition

• SF Color ORANGE should be circled Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 3 Reviews Section 4 Inventory Control Data: Examinee should note No Discrepancies Y N S U

• No Discrepancies Cue:

Comments:

For Inventory control refer to Control Room daily Surveillance SP 2619A-003 page 20 for the availability of all 3 HPSI pumps 5

PERFORMANCE INFORMATION JPM Number: JPM-295-R-SRO Revision: 0/1 Task

Title:

Shutdown Safety Assessment Review for RIO conditions STEP Performance: Standard: Critical: Grade

1. 4 Reviews Section 5 Reactivity Control Data: Examinee should note No Discrepancies Y N S U

• No Discrepancies Cue:

Comments:

For Reactivity the difference in the number of HPSI pumps available as compared to Inventory Control is described in a NOTE in OU-M2-201 Attachment 6 page 48 of 57.

STEP Performance: Standard: Critical: Grade

1. 5 Reviews Section 6 Containment Data: Examinee should note the following: Y N S U

• Containment Closure Capability

• Containment Closure Capability o Containment Closure Set with o Set with Exception Tracked, no exceptions tracked and capable longer Qualifies due to the change of being closed prior to the lesser in Time to Core Boil is less than of: the closure time for the penetration

Time to Core Boil

• Decay Heat, Inventory Control, Power

• Decay Heat, Inventory Control, Power Availability Functions NOT Availability Functions NOT Orange/Red(6) should not be checked due (6)

Orange/Red to the discrepancy in the DHR SF changing

• Containment Total Score to ORANGE (Error carried forward)

• CTMT Color Condition

• Containment Total Score should be 1

• CTMT Color ORANGE should be circled Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 6 Reviews Section 7 Power Availability Data: Examinee should note No Discrepancies Y N S U Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

6

VERIFICATION OF JPM COMPLETION JPM Number: JPM-295-R-SRO Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 40 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 7

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: JPM-295-R-SRO Revision: 0/1 Initial Conditions: The plant is in MODE 5 day 1 of a scheduled 28 day refueling outage.

Reactor disassembly is in progress and the RCS is expected to be in Reduced Inventory within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The following additional conditions presently exist:

• PZR level is 20%

• PZR Vent Port Removed

• No Equipment out of service required for Mode 5

• Containment Closure is set with 1 exception Penetration #48 with a closure time of 30 minutes. (See attached Closure Plan)

• Time to Core Boil for Reduced Inventory was verified by the STA Assume no change in Equipment Status from the current condition to when the plant is in Reduced Inventory.

Initiating Cues:

Review the Predicted changes to the Shutdown Safety Assessment for the RCS in Reduce Inventory that was completed by the RO with the exception of Time To Core Boil calculation.

9

10 11 12 13 14 15 16 17 18 19 20 JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

AEAS Broken Boundary Door JPM Number: JPM-297-R-SRO Revision: 0 Initiated:

David Jacobs 06/01/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/12/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 06/01/2016 Modified from JPM-218 for 2016 ILT NRC Exam 0 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-297-R-SRO Revision: 0 Task

Title:

AEAS Broken Boundary Door System: Conduct of Operations / Fuel Handling Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): 119-01-086 Applicable To: SRO X STA RO PEO K/A Number: 2.1.42 K/A Rating: 2.5 / 3.4 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM, examinee will have determined the type of door affected and state the required actions for suspending fuel movement.

Required Materials: MP-PROC-OPS-OP 2356[r004.00] Doors (procedures, equipment, etc.) MP-PROC-OPS-OPS-FH 216[r006.00] Spent Fuel Handling Operations General

References:

MP-PROC-OPS-OP 2356[r004.00] Doors MP-PROC-OPS-OPS-FH 216[r006.00] Spent Fuel Handling Operations

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-297-R-SRO Revision : 0 Initial Conditions: You are currently on watch as the Control Room Unit Supervisor during a refueling outage thats in its 10th day with a Core Offload in progress.

Initiating Cues: The Aux Building Watch reports that Door 205-14-007 Double Door Access From Aux. bldg. to Railway Access has been knocked off its hinges and will not close.

Record any procedural actions required to respond to the Aux Building Watchs report.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-297-R-SRO Revision: 0 Task

Title:

AEAS Broken Boundary Door START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Examinee refers to OP 2356 Doors: Examinee determines the following: Y N S U Section 4.1 Door Class Determination: ID Door 205-14-007 AB 14 6 RR Access 4.1.1 WHEN any Unit 2 Door is, or will be, not Not Operable does not Latch OPERABLE, or not FUNCTIONAL, PERFORM the following: Submits a CR

a. OBTAIN the following information for each affected door:

• Door ID number and location

• Nature of inoperability (blocked open, does not latch, etc.)

• If door is being blocked open, AWO/clearance number/activity

• If known, expected duration of inoperability

b. SUBMIT a CR.

Cue:

Comments:

STEP 4.1.2 Refer To Attachment 1, Unit 2 Door Standard: Critical: Grade

1. 2 Attributes, and DETERMINE whether affected Examinee refers OP 2356 Doors Attachment 1 Y N S U door is classified as any of the following: page 7 of 15 and notes the following Attributes:

• Spent Fuel Pool Ventilation Boundary

• Non TRM Fire Door

• SFP Ventilation Boundary (AEAS)

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-297-R-SRO Revision: 0 Task

Title:

AEAS Broken Boundary Door STEP Performance: Standard: Critical: Grade

1. 3 Examinee refers to OP 2356 Doors: Examinee determines the following for the Door: Y N S U Section 4.7 Spent Fuel Pool Ventilation Boundary (AEAS) (A):

• Will not latch 4.7.1 IF a SFP boundary door cannot be closed

• CR is submitted and latched, PERFORM the following:

• Refers to OPS-FH 216 section 4.10

a. SUBMIT a CR. Maintaining SFP Boundary Integrity

b. DEVELOP a closure plan and TRACK as specified in OPS-FH 216 section Maintaining SFP Boundary Integrity, until door is repaired.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 Examinee refers to OPS-FH 216 Examinee directs the Stopping of Fuel Movement Y N S U Section 4.10 Maintaining SFP Boundary in the Spent Fuel Pool Ventilation Boundary Area Integrity 4.10.2 IF an unplanned breach in the SFP area boundary is identified, PERFORM the following:

a. STOP any movement of irradiated fuel or Cask operation in the SFP.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

6

VERIFICATION OF JPM COMPLETION JPM Number: JPM-297-R-SRO Revision: 2 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 7

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: JPM-297-R-SRO Revision: 2 Initial Conditions: You are currently on watch as the Control Room Unit Supervisor during a refueling outage thats in its 10th day with a Core Offload in progress.

Initiating Cues:

The Aux Building Watch reports that Door 205-14-007 Double Door Access From Aux. bldg. to Railway Access has been knocked off its hinges and will not close.

Record any procedural actions required to respond to the Aux Building Watchs report.

Procedure # Requirement 9

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

TECH SPEC Evaluation LTOP JPM Number: JPM-294-R-SRO Revision: 0/1 Initiated:

David Jacobs 07/12/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/13/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 06/01/2016 New JPM developed for NRC exam 2016 0 08/18/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-294-R-SRO Revision: 0/1 Task

Title:

TECH SPEC Evaluation LTOP System: Generic Equipment Control Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): *MP2* 119-029-01-02 Applicable To: SRO X STA RO PEO K/A Number: 2.2.40 K/A Rating: 3.4 / 4.7 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: Examinee has determined that both PORVs are NOT OPERABLE for MODE 4 requiring entering Tech. Spec. Action Statement and suspending the cooldown.

Required Materials: MP-PROC-OPS-U2-14-OPS-BAP05 Tech. Specs.

(procedures, equipment, etc.) MP-PROC-OPS-OP 2207[r039] Plant Cooldown General

References:

MP-PROC-OPS-U2-14-OPS-BAP05 Tech. Specs.

MP-PROC-OPS-OP 2207[r039] Plant Cooldown MP-PROC-OPS-ARP 2590B-209 Alarm Response C02/03 A-37 LT/OP T115

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-294-R-SRO Revision : 0/1 Initial Conditions: OP 2207 cooldown is in progress with the following conditions:

• RCS temperature at 275°F

• Pressure at 375# P-103-1 and P-103

• 2 PORVs with LT/OP SETPOINT SELECTOR in HIGH

• 2 Charging pump available to inject

• 1 HPSI pump available to inject Initiating Cues: Determine any required actions for the current condition Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-293-R-SRO Revision: 0/1 Task

Title:

TECH SPEC Evaluation LTOP START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 After reviewing the Initial Conditions the SRO SRO determines the need to SUSPEND the Y N S U determines the applicable action required by OP COOLDOWN OP 2207 2207 Cooldown. Section 4.14 Establishing LTOP Protection Step 4.18.8 Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 After reviewing the Initial Conditions the SRO Technical Specification Actions of 3.4.9.3a action Y N S U determines applicable Tech. Spec. Action c Declare BOTH Channels of LTOP not required for the conditions. OPERABLE Perform either of the following:

• Depressurize and vent the RCS through a >

2.2 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

OR

• Raise TCOLD >275°F (MODE above where PORVs are not required)

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

5

VERIFICATION OF JPM COMPLETION JPM Number: JPM-294-R-SRO Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 6

Question #1: What action in the Plant Cooldown cannot be accomplished if P103, PZR PRES LO RGE and P103-1, PZR PRES LO RGE are not within 30 psi of each other?

Answer #1: Concurrent RCP and SDC operations Examinee

Response

Grade: SAT UNSAT Question #2: In MODE 6 when is Low Temperature Over Pressure protection no longer required?

Answer #2: Reactor vessel head has been removed or a vent of sufficient size has been established such that RCS pressurization is not possible. (T.S. Basis)

Examinee

Response

Grade: SAT UNSAT 7

STUDENT HANDOUT JPM Number: JPM-294-R-SRO Revision: 0/1 Initial Conditions: OP 2207 cooldown is in progress with the following conditions:

• RCS temperature at 275°F

• Pressure at 375# P-103-1 and P-103

• 2 PORVs with LT/OP SETPOINT SELECTOR in HIGH

• 2 Charging pump available to inject

• 1 HPSI pump available to inject Initiating Cues:

Determine any required actions for the current conditions.

Examinee

Response

8

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Radiological Assessment and Task Supervision JPM Number: JPM-296-R-SRO Revision: 1 Initiated:

David Jacobs 06/02/2016 Developer Date Reviewed:

Robert L. Cimmino, Jr. 07/06/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 12/07/10 Created JPM for LOIT 2011 NRC Exam 0/0 06/02/2016 Revised and modified for ILT 2016 NRC Exam 1/0 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-296-R-SRO Revision: 1 Task

Title:

Radiological Assessment and Task Supervision System: Radiation Control 2.3 Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s):

Applicable To: SRO X STA RO PEO K/A Number: 2.3.4 K/A Rating: 3.3 / 3.7 Method of Testing: Simulated Performance: Actual Performance:

Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM, the SRO should analyze the given conditions and designate which PEO should perform each of the two specified tasks, based on the radiological concerns of each.

Required Materials:

• RPM 5.2.2 Basic Radiation Worker Responsibilities (procedures, equipment, etc.)

General

References:

• RPM 5.2.2 Basic Radiation Worker Responsibilities

• MP-PROC-EP-MP-26-EPI-FAP09[r004] Radiation Exposure Controls

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-296-R-SRO Revision : 1 Initial Conditions: You are the Unit Supervisor currently mitigating a medium size LOCA and directing steps in EOP 2532 with the following conditions:

• Shift Manager has declared an SITE AREA CHARLIE 2

• 2-RB-30.1A has failed to Close remotely

• RBCCW Surge Tank is slowly Rising

• PEO #1 current year to date exposure is 875 millirem

• PEO #2 current year to date exposure is 203 millirem

• PEO #1 can restore the charging pump in 44 minutes

• PEO #2 can restore the charging pump in 50 minutes

• PEO #1 can manually close RB MOV in 18 minutes

• PEO #2 can manually close RB MOV in 20 minutes Task #1 restore the B charging pump with general area dose rate of 5 rem/hr.

Task #2 manually close MOV 2-RB-30.1A RBCCW CTMT ISOL HDR A SPLY with general area dose rate of 12 rem/hr.

Initiating Cues: Determine the allowable Exposure for PEO #1 and PEO #2 for the given event.

Determine the dose each PEO will receive for each task.

Determine which PEO will perform the individual tasks based on the Radiological requirements for the PEOs.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-296-R-SRO Revision: 1 Task

Title:

Radiological Assessment and Task Supervision START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Review the Initial Conditions and Initiating Cue. Using Emergency Exposure Control Guidance at Y N S U Using Emergency Exposure Control Guidance an ALERT level and higher classification dose limits and the expected exposure rate in the area, limits are automatically extended to 4.5 Rem minus calculate the maximum dose available for each their current dose.

PEO.

• PEO #1 = 4.5R - 0.875R = 3.625R

• PEO #2 = 4.5R - 0.203R = 4.297R Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 Determine the expected Dose each PEO will

• PEO #1 task #1 = 3.667R + 0.001R Y N S U receive for the stated task, the dose rates and

• PEO #1 task #2 = 3.600R + 0.001R times required to accomplish the tasks.

• PEO #2 task #1 = 4.167R + 0.001R

• PEO #2 task #2 = 4.000R + 0.001R Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 3 Based on available Dose, decide which PEO

• PEO #1 task #2 = 3.600R + 0.001R Y N S U must perform each task.

• PEO #2 task #1 = 4.167R + 0.001R Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

5

VERIFICATION OF JPM COMPLETION JPM Number: JPM-296-R-SRO Revision: 1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 6

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 7

STUDENT HANDOUT JPM Number: JPM-296-R-SRO Revision: 1 Initial Conditions: You are the Unit Supervisor currently mitigating a medium size LOCA and directing steps in EOP 2532 with the following conditions:

• Shift Manager has declared an SITE AREA CHARLIE 2

• 2-RB-30.1A has failed to Close remotely

• RBCCW Surge Tank is slowly Rising

• PEO #1 current year to date exposure is 875 millirem

• PEO #2 current year to date exposure is 203 millirem

• PEO #1 can restore the charging pump in 44 minutes

• PEO #2 can restore the charging pump in 50 minutes

• PEO #1 can manually close RB MOV in 18 minutes

• PEO #2 can manually close RB MOV in 20 minutes Task #1 restore the B charging pump with general area dose rate of 5 rem/hr.

Task #2 manually close MOV 2-RB-30.1A RBCCW CTMT ISOL HDR A SPLY with general area dose rate of 12 rem/hr.

Initiating Cues:

Determine the allowable Exposure for PEO #1 and PEO #2 for the given event.

Determine the dose each PEO will receive for each task.

Determine which PEO will perform the individual tasks based on the Radiological requirements for the PEOs.

Exposure Limit Task #1 Dose Task #2 Dose Task to perform PEO #1 PEO #2 8

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Emergency Classification JPM Number: JPM-298-R-SRO Revision: 0 Initiated:

Robert Royce 6 /14/2016 Developer Date Reviewed:

David Jacobs 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2

JPM WORKSHEET Facility: Millstone 2 Examinee:

JPM Number: JPM-298-R-SRO Revision: 0 Task

Title:

Emergency Classification System:

Time Critical Task: X YES NO Validated Time (minutes): 10 Task Number(s):

Applicable To: SRO X RO K/A Number: GEN.2.4.41 K/A Rating: 2.9 / 4.6 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM, the examinee has correctly classified the proposed event and provided the appropriate Protective Action Recommendation.

Required Materials:

• MP-26-EPI-FAP06-002, Millstone Unit 2 Emergency Action Levels (procedures, equipment, etc.)

• MP-26-EPI-FAP06-005, Control Room Protective Action Recommendations.

• MP-26-EPI-FAP06, Classification and PARs General

References:

• MP-26-EPI-FAP06-002, Millstone Unit 2 Emergency Action Levels

• MP-26-EPI-FAP06-005, Control Room Protective Action Recommendations.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-298-R-SRO Revision : 0 Initial Conditions:

• The plant is operating at 100% power.

• Bus 24E is aligned to Bus 24C.

• The "B" LPSI Pump is OOS.

• Wind at the site is from 15 degrees at 3 mph.

Time = 0 Minutes: The following sequence of events occurs:

• The Reactor trips,

• The Turbine trips,

• The crew enters EOP 2525, Standard Post Trip Actions.

Time + 17 Minutes:

• EOP 2525 is complete

• The BOP reports secondary conditions as follows:

• Buses 25A/B, 24A/B, and 24C de-energized

• Bus 24D energized by the 'B' D/G

• S/G press: #1 is 745 psia, #2 is 740 psia, both slowly lowering

• Thot is 289°F, Tcold is 262°F, both slowly lowering

• S/G levels: #1 is 18%, #2 is 16%, both rising slowly

• "B" AFP supplying both S/Gs Time + 19 Minutes:

• RO reports primary conditions as follows:

• Pressurizer level is 0%

• Reactor vessel level (RVLMS) is 0%. (Both #8 string HJTCs are inoperable)

• Pressurizer pressure is 53 psia and slowly lowering

• CETS are 847°F and slowly rising

• Subcooling (CET) indicates -478°F and becoming more negative

• Facility 2 SIAS, CIAS, EBFS have actuated; however, Letdown Isolation Valves, CH-515, 516, and 089, indicate open and will NOT close from C-02

• CTMT pressure is 42 psig, rising slowly

• CTMT temperature is not available 4

Time + 22 Minutes:

• STA reports the following:

• Main Steam Line RM-4299A and B indicate 1.6 R/hr, RM-4299C indicates 1.8 R/hr, all rising

• CTMT Hi Range, RM-8240 / 8241 is 20,000R/hr / 21,000 R/hr, both rising

• CTMT Personnel Access Area, RM-7890, off scale high

• Facility 2 CTMT atmosphere, RM-8262A/B show pre CIAS spikes and alarm

• The Kaman Rad Monitor, RM-8168 is reading 5E+02µCi/cc, rising, and in ALARM.

• All other RMs outside CTMT are elevated, but NOT in alarm

• Main Steam Line RM-4299A/B were reading 0.7 R/hr, RM-4299C was reading 0.9 R/hr, 15 minutes ago

• CTMT Hi Range, RM-8240 / 8241 were reading 350R/hr / 370 R/hr, 15 minutes ago

• The Kaman Rad Monitor, RM-8168 was reading 1.2E+01µCi/cc 15 minutes ago

• All other Rad Monitors outside of CTMT started rising about 15 minutes ago.

Time + 25 Minutes: Crew transitions to EOP 2532, Loss of Coolant Accident Initiating Cues: You are the on-duty SM.

Your task is to determine the NRC and state posture code classification for this event, and as required, provide any additional recommendations.

• • • TIME CRITICAL JPM***

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: JPM-298-R-SRO Revision: 0 Task

Title:

Emergency Classification START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Obtain Millstone 2 Emergency Action Levels, The examinee reads the student Handout and Y[ ] N[X] S[ ] U[ ]

MP EPI-FAP06-002. obtains Millstone 2 Emergency Action Levels, MP EPI-FAP06-002.

Cue: When requested, provide Millstone 2 Emergency Action Levels, MP-26-EPI-FAP06-002 and MP-26-EPI-FAP06, Classification and PARs, to the examinee. The CRDSEO book with EALs may be provided at the start of the JPM.

Comments: The 15 minute clock starts when the examinee obtains Millstone 2 Emergency Action Levels, MP EPI-FAP06-002, and ends when the classification is made.

STEP Performance: Standard: Critical: Grade

1. 2 Classify the event as a GENERAL Using the barrier reference table, examinee Y[X] N[ ] S[ ] U[ ]

EMERGENCY, State Posture Code, ALPHA, determines the event as a GENERAL within 15 minutes, based on Barrier Failure, EMERGENCY, State Posture Code, ALPHA, BG1, any three barriers failed. based on;

• Fuel Clad Barrier failed FCB3 (L)

• RCS Barrier failed RCB2 (L),

• CTMT Barrier, CNB3(P) or CNB4 (P)

Could also arrive at the same classification from Off Site Releases OG1 or In-Plant Radiation RG1.

• OG1 MP2 Kaman Vent Monitor (RM-8168) reading > 2µci/cc for > 15 minutes. Current reading 5E +02 µci/cc (500 µci/cc) and was 1.2 E+01 µci/cc (12 µci/cc) 15 minutes ago.

• RG1 RM-8240/8241 reading > 1,200 R/hr.

Currently reading 20,000 R/hr and 21,000 R/hr.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-298-R-SRO Revision: 0 Task

Title:

Emergency Classification STEP Performance: Standard: Critical: Grade

1. 3 For Control Room PARs, Refer to EPI-FAP06- Using the Control Room PAR Process Flowchart, Y[X] N[ ] S[ ] U[ ]

005, Control Room Protective Action determine that the present wind direction (between recommendations and determines the PAR 340° - 029°) requires the examinee to recommend recommendation as; an evacuation of Zones A, B, and Plum Island, and

• Evacuate Zones A and B and Plum Island. to shelter all other zones.

• Shelter all other zones.

• General Emergency - Yes

• General Emergency - Alpha - Yes

• Rapidly Progressing Event - No (Clad <1200°F)

• Does CTMT Radiation Exceed Table 1 Values

- Yes (20,000 and 21,000 R/hr are >19,000R)

• GE-ALPHA PAR

• Evacuate 5 mile radius

• Evacuate 10 miles downwind: Sector 340-029: Zones to evacuate to 10 miles; A and B and Plum Island.

• Shelter all other zones.

Cue: When requested, provide MP-26-EPI-FAP06-05, Control Room Protective Action Recommendations.

Comments: Thyroid CDE is NOT known; therefore, issuance of KI tablets should not be recommended.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

7

VERIFICATION OF JPM COMPLETION JPM Number: JPM-298-R-SRO Revision: 0 Date Performed:

Candidate:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time 15 minutes for EAL Actual Time to Complete (minutes):

(minutes): PAR within 15 minutes after Classification Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

8

JPM HANDOUT JPM Number: JPM-298-R-SRO Revision: 0 Initial Conditions:

• The plant is operating at 100% power.

• Bus 24E is aligned to Bus 24C.

• The "B" LPSI Pump is OOS.

• Wind at the site is from 15 degrees at 3 mph.

Time = 0 Minutes: The following sequence of events occurs:

• The Reactor trips,

• The Turbine trips,

• The crew enters EOP 2525, Standard Post Trip Actions.

Time + 17 Minutes:

• EOP 2525 is complete

• The BOP reports secondary conditions as follows:

• Buses 25A/B, 24A/B, and 24C de-energized

• Bus 24D energized by the 'B' D/G

• S/G press: #1 is 745 psia, #2 is 740 psia, both slowly lowering

• Thot is 289°F, Tcold is 262°F, both slowly lowering

• S/G levels: #1 is 18%, #2 is 16%, both rising slowly

• "B" AFP supplying both S/Gs Time + 19 Minutes:

• RO reports primary conditions as follows:

• Pressurizer level is 0%

• Reactor vessel level (RVLMS) is 0%. (Both #8 string HJTCs are inoperable)

• Pressurizer pressure is 53 psia and slowly lowering

• CETS are 847°F and slowly rising

• Subcooling (CET) indicates -478°F and becoming more negative

• Facility 2 SIAS, CIAS, EBFS have actuated; however, Letdown Isolation Valves, CH-515, 516, and 089, indicate open and will NOT close from C-02

• CTMT pressure is 42 psig, rising slowly

• CTMT temperature is not available 9

Time + 22 Minutes:

• STA reports the following:

• Main Steam Line RM-4299A and B indicate 1.6 R/hr, RM-4299C indicates 1.8 R/hr, all rising

• CTMT Hi Range, RM-8240 / 8241 is 20,000R/hr / 21,000 R/hr, both rising

• CTMT Personnel Access Area, RM-7890, off scale high

• Facility 2 CTMT atmosphere, RM-8262A/B show pre CIAS spikes and alarm

• The Kaman Rad Monitor, RM-8168 is reading 5E+02µCi/cc, rising, and in ALARM.

• All other RMs outside CTMT are elevated, but NOT in alarm

• Main Steam Line RM-4299A/B were reading 0.7 R/hr, RM-4299C was reading 0.9 R/hr, 15 minutes ago

• CTMT Hi Range, RM-8240 / 8241 were reading 350R/hr / 370 R/hr, 15 minutes ago

• The Kaman Rad Monitor, RM-8168 was reading 1.2E+01µCi/cc 15 minutes ago

• All other Rad Monitors outside of CTMT started rising about 15 minutes ago.

Time + 25 Minutes: Crew transitions to EOP 2532, Loss of Coolant Accident Initiating Cues: You are the on-duty SM.

Your task is to determine the NRC and state posture code classification for this event, and as required, provide any additional recommendations.

• • • TIME CRITICAL JPM***

10

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

LOCA Cooldown A Steam Dump lose Vacuum go to ADVs (ALT PATH)

JPM Number: JPM-270 Revision: 0/1 Initiated:

David J. Jacobs 07/15/2014 Developer Date Reviewed:

Lenny E. Mausteller 07/15/2014 Technical Reviewer Date Approved:

Mike J. Cote 07/17/2014 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 07/15/2014 New JPM for 2013-2014 ILT Audit Exam 0 08/16/2016 Incorporate NRC comments 0/1 2

JPM WORKSHEET Facility: Millstone Unit 2 Examinee:

JPM Number: JPM-270 Revision: 0/1 Task

Title:

LOCA Cooldown A Steam Dump lose Vacuum go to ADVs System: 039 Main and Reheat Steam System Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 30 Task Number(s): 599-05-011 Applicable To: SRO X STA RO X PEO K/A Number: A2.01 K/A Rating: 3.1 / 3.2 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of the JPM the Examinee will have recognized a loss of Condenser Vacuum and transferred Cooling down for the A Steam Dump to both ADVs while maintaining > 40 degree per hour Required Materials: MP-PROC-OPS-EOP 2532 (procedures, equipment, etc.)

General

References:

Ensure S/G levels > 50%

3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: JPM-270 Revision : 0/1 Initial Conditions: The Plant was manually tripped due to a Loss of Primary Coolant Accident.

All actions from EOP 2525 SPTA have been completed and EOP 2532 Loss of Coolant Accident up to Step #17 Initiating Cues: You are directed to commence controlled cool down In Accordance with Step 17 of EOP 2532 LOCA Simulator Requirements: Reset to IC 290 password 2013>loit Insert Malfunction RC04 at 500 gpm Trigger #1 Malfunction FW33 at 7.5 BP@ 10 mins

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-270 Revision: 0/1 Task

Title:

LOCA Cooldown A Steam Dump lose Vacuum go to ADVs START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 NOTE Y [ ] N [X] S[ ] U[ ]

Examinee reads NOTE and understands the

1. RCS cooldown should be initiated within requirements for RCS Cooldown one hour after the event to conserve condensate inventory and comply with the Long Term Cooling Analysis.

2. RCS cooldown rate greater than 40_F/hr should be maintained until the steam dump/bypass valves or atmospheric dump valves are full open.

3. The starting point for the RCS cooldown should be the TC or CET temperatures where RCS has stabilized.

4. TC should be used for monitoring RCS cooldown if in forced or natural circulation. CETs should be used for all other cases.

Cue:

Comments:

5

STEP Performance: Standard: Critical: Grade

1. 2 NOTE Y [ ] N [X] S[ ] U[ ]

Examinee reads and complies with Tech. Spec.

Technical Specification cooldown rates Limits should be observed during the cooldown.

The cooldown rates are as follows:

1. RCS TC greater than 2200F the cooldown rate is 1000F/hr.

2. RCS TC less than or equal to 2200F the cooldown rate is 500F/hr.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 3 Perform Controlled Cooldown Examinee Locates and Places A Steam Dump to Y [X] N [ ] S[ ] U[ ]

Manual, increases the Output approximately by

• 17.INITIATE a controlled cooldown using 10% then monitors Cooldown Rate.

the steam dumps to establish shutdown cooling entry conditions.

Cue:

After the Examinee establishes a control Cooldown rate > 400F per hour and less then TS limit INSERT Malfunction FW33 at 7.5 BP@

10 minutes Comments:

STEP Performance: Standard: Critical: Grade

1. 4 C06/07 A-37 COND VACUUM LO alarms, Examinee uses diverse indications to confirm a loss Y [ ] N [X] S[ ] U[ ]

the Examinee refers to the Alarm Response of the Main Condenser. Examinee understands that 2590E-185 Confirms loss of the Main the A Steam Dump Valve will close when Condenser. Condenser Vacuum rises to 10 Cue:

Comments:

6

STEP Performance: Standard: Critical: Grade

1. 5 Perform Controlled Cooldown Examinee refers back to EOP 2532 Loss of Y [X] N [ ] S[ ] U[ ]

Coolant Accident Step 17.1 Contingency Actions

• 17.1 INITIATE a controlled cooldown and transfers Cooldown to the ADVs using the ADVs to establish shutdown cooling entry conditions.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

7

VERIFICATION OF JPM COMPLETION JPM Number: JPM-270 Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

As necessary, refer to TIG-04 for additional Pass/Fail criteria.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 30 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

8

JPM QUESTIONS Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: JPM-270 Revision: 0/1 Initial Conditions: The Plant was manually tripped due to a Loss of Primary Coolant Accident.

All actions from EOP 2525 SPTA have been completed and EOP 2532 Loss of Coolant Accident up to Step #17 Initiating Cues: You are directed to commence controlled cool down In Accordance with Step 17 of EOP 2532 LOCA 10

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Respond to a 10 Step CEA Misalignment JPM Number: JPM-284-S-1 Revision: 0/1 Initiated:

Robert L. Cimmino, Jr. 03/15/2016 Developer Date Reviewed:

David J. Jacobs 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 03/15/2016 New JPM for 2015-16 NRC License Exam 0 08/15/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: Millstone Unit 2 Examinee:

JPM Number: JPM-284-S-1 Revision: 0/0 Task

Title:

Respond to a 10 Step CEA Misalignment System: CEDS Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): 000-04-097 Applicable To: SRO STA RO X PEO K/A Number: 001/A2.03 K/A Rating: 3.5/4.2 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: The Examinee will attempt to insert Group 7 CEAs to start the downpower, recognize CEA #1 in Group 7 has slipped 10 steps to 170 steps withdrawn, and then perform the required actions to realign CEA #1 with the group.

Required Materials: MP-PROC-OPS-AOP 2575, Rapid Downpower (procedures, equipment, etc.) MP-PROC-OPS-ARP 2590C-111, ACTM TROUBLE MP-PROC-OPS-ARP 2590C-140, CEA GP DEV BK/UP MP-PROC-OPS-OP 2302A, Control Element Drive System General

References:

MP-PROC-OPS-OP 2302A, Control Element Drive System Reactivity Plan for ~ 30%/hr power reduction

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-284-S-1 Revision : 0/1 Initial Conditions: The plant is stable at 100 % power, about to commence a down power to 55%.

The crew has entered AOP 2575, Rapid Downpower, and has completed steps to 3.3, Forcing Pressurizer Sprays.

The BOP is standing by to reduce turbine load.

Initiating Cues: You are the RO.

Insert Group 7 rods 10 steps in accordance with step 3.4 of AOP 2575.

Simulator Requirements: 100% power, steady state, ARO, forcing PZR sprays.

Insert Malfunction RD0301 (10) to slip CEA #1 10 steps when Group 7 is given an insert command.

{Consider creating a Boolean trigger based on CEA #1 being < 180 steps.

[RDCEAPOS(01) < 180]}

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 AOP 2575 Examinee obtains a copy of AOP 2575. Y N S U CAUTION

• Examinee turns to the Caution statement In the case of a dropped CEA, rod motion is not proceeding step 3.4 on page 8.

used to initiate downpower.

• Examinee reads and acknowledges the Caution.

Cue:

Provide the Examinee with a marked up copy of AOP 2575 RAPID DOWNPOWER Comments:

STEP Performance: Standard: Critical: Grade

1. 2 3.4. IF not downpowering due to a dropped rod,

• CEA are inserted Y N S U AND Reactor power is greater than 99%

(2673 MWTh) INSERT Group 7 CEAs 10

+/- 2 steps to initiate downpower.

Cue: Ensure malfunction RD0301 triggers (causing CEA #1 to slip to 170 steps) when Group 7 CEAs begin to insert.

Comments: Ensure the Rod slip does not EXCEED 10 steps which would require entering AOP 2556 CEA MALFUNCTION. The specific steps required for CEA insertion as directed by an AOP are considered Skill Of The Craft and, as such, do not need to be performed using OP 2302A at this time.

STEP Performance: Standard: Critical: Grade

1. 3 CEA #1 slips to 170 steps withdrawn. Examinee performs the following: Y N S U C-04 Annunciators in alarm:

• CEA control switch released.

• C-04/DA-18, CEA GP DEV BK/UP

• C-04 alarms acknowledged.

• C-04/BA-18, CEA MOTION INHIBIT

• US notified of CEA misalignment.

Cue:

Comments: Examinee may refer to AOP 2556 but does not meet entry conditions.

5

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 4 ARP 2590C-136 CEA Motion Inhibit (BA-18) Examinee references ARP 2590C-136 and notes Y N S U

1. VERIFY CEA motion has stopped (C-04, the need to reference additional ARPs pertaining to PPC). the actual cause of the alarm.

2. To determine cause of alarm, OBSERVE any associated CEDS annunciators lit (C-04).

3. IF other associated CEDS annunciators are lit, Refer To applicable alarm response section and PERFORM necessary corrective actions.

4. IF necessary, SUBMIT Trouble Report to I&C Department.

Cue: If Examinee expresses the need to have I&C and/or a PEO investigate CEA #1, state that you have already made the calls and both are enroute to the East DC switchgear room.

Acknowledge any suggestion to submit a Trouble Report and state another operator will submit one.

Comments: Examinee may not reference this ARP as the cause is known based on C-04 annunciator DA-18 and the actions are to simply verify CEA motion has stopped and then reference the applicable ARP that caused the CMI.

6

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 5 ARP 2590C-111 ACTM Trouble (AB-15) Examinee references ARP 2590C-136 and notes Y N S U

1. STOP all CEA motion. the need to reference additional ARPs pertaining to

2. REQUEST I&C Department investigate the actual cause of the alarm.

ACTM trouble condition.

3. IF alarm is momentary, PERFORM the following:

3.1. MONITOR all ACTMs and REPORT all abnormal red lights (East DC switchgear room).

3.2. OPEN the ACTM TROUBLE ALARMS display on CEAPDS.

3.3. RESET ACTMs.

3.4. IF ACTM alarm on CEAPDS display clears (is not flashing or steady red),

CEA motion may be resumed.

3.5. IF ACTM alarm on CEAPDS display does not clear, NOTIFY SM.

Cue: If Examinee expresses the need to have I&C and/or a PEO investigate CEA #1, state that you have already made the calls and both are enroute to the East DC switchgear room.

Comments: Examinee may not reference this ARP as the cause is known based on the other C-04 annunciators, the alarm is momentary and the actions are not critical at this time.

7

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 6 ARP 2590C-140 (DA-18) Y N S U

1. Identifies CEA #1 as being misaligned with

1. IDENTIFY misaligned CEA and Group 7 by (less than or equal to) 10 steps.

DETERMINE actual steps misaligned.

2. IF deviation is greater than 10 steps, Go To 2. Informs US of the need to realign CEA #1 AOP 2556, CEA Malfunctions." with Group 7 using OP 2302A (based on

3. IF deviation is less than or equal to 10 steps, magnitude of CEA misalignment).

Refer To OP 2302A, Control Element Drive System" and PERFORM applicable actions to align all CEAs in affected group to within one step of each other, using manual individual mode in conjunction with bypassing CMI.

4. IF necessary, RESET affected group CEA positions on PPC as follows:

4.1. SELECT CEA POSITION" on PPC.

4.2. SELECT CEA POSITION EDITOR."

4.3. PERFORM directions as indicated on PPC.

5. IF an instrument malfunction is indicated, SUBMIT Trouble Report to I&C Department.

Cue: If Examinee expresses the need to have I&C and/or a PEO investigate CEA #1, state that you have already made the calls and both are enroute to the East DC switchgear room. When later questioned by the Examinee about the status of CEA #1, state that I&C is on station and that they believe they have addressed the cause of the slipped CEA. I&C and a PEO will remain on station in the East DC switchgear room to ensure proper operation of the CEDS during subsequent CEA motion.

The Examinee has permission to proceed with the actions to correct the CEA misalignment.

Comments:

8

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 7 OP 2302A Examinee obtains a copy of OP 2302A, turns to Y N S U Section 4.2 CEA Operation in Manual Section 4.2, reads and acknowledges the Note.

Individual Mode NOTE:

When operating in this mode, any individual CEA in any group can be moved using CEA control switch and is primarily used for trimming CEAs and testing.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 8 4.2.1 IF at any time it is necessary to bypass Examinee reads and acknowledges the need to use Y N S U CMI during CEA movement, using Section 4.5 of OP 2032A to realign CEA #1.

Section 4.5 PERFORM applicable actions in conjunction with this section.

Cue:

Comments:

9

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 9 Section 4.5 Bypass CMI Interlocks Examinee refers to Section 4.5, reads and Y N S U acknowledges the Note.

NOTE

1. This Section may be used to move CEAs in order to clear alarms or continue operations when malfunctions in the alarm or control circuitry exists.

2. When CMI relay actuates, CEDM raise, lower, and lift signals to CPPs are overridden. If this happens during CEA movement, the CEA could slip and result in misalignment.

3. When CMI is bypassed, PDIL alarm circuit and CEA Deviation circuit are both inoperable.

4. Prior to bypassing any interlock, permission must be obtained from SM/US.

Cue: When asked, state that Examinee has permission to bypass the CMI for the purpose of realigning CEA #1 with Group 7 and that all applicable Tech Spec have been entered.

Comments: Examinee may review Section 4.5 up to step 4.5.7, or in its entirety to be prepared to utilize it in concert with Section 4.2 when withdrawing CEA #1. Either way is acceptable as long as the applicable actions of section 4.5 required to bypass the CMI are executed.

10

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 10 4.5.1 REQUEST SM/US authorization to 1. Inhibit Bypass pushbutton for Group 7 is Y N S U bypass CMI. pressed and verified lit, and annunciator 4.5.2 CHECK annunciator C-04, window C-04/BA-19 alarm is acknowledged.

BA-18, CEA MOTION INHIBIT, lit. 2. CEA Motion Inhibit Bypass button is 4.5.3 Refer To the following and LOG entry in pressed and held, button verified lit.

Shift Turnover Log (CMI bypassed):

• TSAS 3.1.3.1, ACTION b

• TSAS 3.1.3.1, ACTION c

• TSAS 3.1.3.6, ACTION d 4.5.4 PRESS appropriate group INHIBIT BYPASS pushbutton and CHECK the following: Note: When the CMI for Group 7 is bypassed, the

• Appropriate group red INHIBIT CEA MOTION INHIBIT annunciator will reset.

BYPASS pushbutton, lit This is a quirk in the system design and totally

• Annunciator C-04, window BA-19, expected. The Examinee may or may not explain.

CEA MOTION INHIBIT BYP, lit 4.5.5 PRESS and HOLD system CEA MOTION INHIBIT BYPASS pushbutton.

4.5.6 CHECK system red CEA MOTION INHIBIT BYPASS, lit.

Cue: If not already done, state that Examinee has permission to bypass the CMI for the purpose of realigning CEA #1 with Group 7 and that all applicable Tech Spec have been entered.

Comments: It is not necessary for the RO to personally address the applicable TSAS that are affected when bypassing the CMI. If the Examinee attempts to do so, state that the US will address them and the RO is to focus on correcting the CEA misalignment.

11

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 11 4.5.7 Using applicable Section and PERFORM Based on the guidance of step 4.5.7, Examinee Y N S U necessary actions to operate CEA(s): returns to Section 4.2 of OP 2302A, if not being

• IF operating in Manual Individual used in concert with Section 4.5.

mode, Section 4.2 Examinee may review the Note proceeding step

• IF operating in Manual Group mode, 4.5.8 at this time, or wait until returning to this Section 4.3 section of the procedure after the CEA is realigned.

• IF operating in Manual Sequential mode, Section 4.4 NOTE CMI should remain bypassed for at least three seconds after CEA motion is stopped to allow CPP operations to be completed.

4.5.8 WHEN CEA motion has been stopped for at least three seconds, RELEASE system CEA MOTION INHIBIT BYPASS pushbutton.

Cue:

Comments:

12

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 12 Section 4.2 CEA Operation in Manual Individual 1. MI button pressed and light verified lit. Y N S U Mode 2. Group 7 Group Select button pressed and verified lit.

4.2.2 PRESS MANUAL INDIVIDUAL, MI

3. CEA #1 button pressed and verified lit.

pushbutton and CHECK light, lit.

4.2.3 SELECT applicable group for CEA to be moved on one of the following scales (CEAPDS MONITOR):

• FULL RANGE

• +/- 15 4.2.4 PRESS applicable GROUP SELECTION pushbutton for CEA to be moved and CHECK light, lit.

4.2.5 PRESS INDIVIDUAL CEA SELECTION pushbutton for CEA to be moved and CHECK light, lit.

4.2.6 MONITOR CEA movement on the following:

• CEAPDS MONITOR

• PPC (desired display)

• Core mimic Cue:

Comments: It is not critical to monitor the Core Mimic for CEA motion until the CEA reaches the fully withdrawn position.

13

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 13 4.2.7 WHEN desired to initiate CEA 1. Examinee moves the CEA control switch to the Y N S U movement, PERFORM applicable withdraw position and monitors CEA action: movement.

• IF desired to insert CEA, PLACE 2. CEA motion is stopped when CEA #1 is and HOLD CEAcontrol switch to aligned with the rest of Group 7 CEAs.

INSERT.

• IF desired to withdraw CEA, PLACE and HOLD CEA control switch to WITHDRAW.

4.2.8 WHEN movement of selected CEA is no longer desired, slowly RELEASE CEA control switch and CHECK CEA movement has stopped.

Cue: If stated, US acknowledges the restoration of CEA alignment.

Comments:

STEP Performance: Standard: Critical: Grade

1. 14 Section 4.5 Bypass CMI Interlocks Examinee may have already reviewed this Note Y N S U and step 4.5.8, performing it immediately after NOTE releasing the CEA control switch.

CMI should remain bypassed for at least three seconds after CEA motion Examinee may verify the CEA Motion Inhibit is stopped to allow CPP operations to be Bypass button light goes out at this time.

completed.

4.5.8 WHEN CEA motion has been stopped for at least three seconds, RELEASE system CEA MOTION INHIBIT BYPASS pushbutton.

Cue:

Comments:

14

PERFORMANCE INFORMATION JPM Number: JPM-284-S-1 Revision: 0/1 Task

Title:

Respond to a 10 Step CEA Misalignment STEP Performance: Standard: Critical: Grade

1. 15 4.5.9 CHECK system red CEA MOTION Examinee performs the following: Y N S U INHIBIT BYPASS, light not lit. 1. Verifies CEA Motion Inhibit Bypass button not 4.5.10 PRESS appropriate group INHIBIT lit when released.

BYPASS pushbutton and CHECK the 2. Inhibit Bypass button is pressed, button is following: verified not lit and annunciator C-04/BA-19 is

• Appropriate group red INHIBIT verified cleared.

BYPASS button, not lit 3. US is informed of ability to log out of TSAS:

• Annunciator C---04, window BA---

• 3.1.3.1, ACTION b 19, CEA MOTION INHIBIT

• 3.1.3.1, ACTION c BYP, not lit

• 3.1.3.6, ACTION d 4.5.11 IF CMI is no longer required to be bypassed, LOG exit of the following in Shift Turnover Log (CMI not bypassed):

• TSAS 3.1.3.1, ACTION b

• TSAS 3.1.3.1, ACTION c

• TSAS 3.1.3.6, ACTION d Cue:

Comments: The JPM is complete once CEA #1 has been realigned with the rest of Group 7 and the CMI circuit is no longer bypassed.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

15

VERIFICATION OF JPM COMPLETION JPM Number: JPM-284-S-1 Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

16

JPM QUESTIONS Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 17

STUDENT HANDOUT JPM Number: JPM-284-S-1 Revision: 0/1 Initial Conditions: The plant is stable at 100 % power, about to commence a down power to 55%.

The crew has entered AOP 2575, Rapid Downpower, and has completed steps to 3.3, Forcing Pressurizer Sprays.

The BOP is standing by to reduce turbine load.

Initiating Cues: You are the RO.

Insert Group 7 rods 10 steps in accordance with step 3.4 of AOP 2575.

18

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Actuation Tests of Various ESF Components JPM Number: JPM 243 Revision: 0 Initiated:

David J. Jacobs 07/14/2014 Developer Date Reviewed:

Doug M. Funk 07/14/2014 Technical Reviewer Date Approved:

Mike J. Cote 07/17/2014 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 07/14/2014 New JPM for Audit Exam ILT 2013-2014 0 08/15/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: Millstone Unit 2 Examinee:

JPM Number: JPM 243 Revision: 0/1 Task

Title:

Actuation Test ESF Components System: Engineered Safety Features Actuation System Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 30 Task Number(s): NUTIMS 013-01-002 Applicable To: SRO X STA RO X PEO K/A Number: 013 A4.03 K/A Rating: 4.5 / 4.7 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of the JPM the Examinee will have Tested an Engineered Safety Features Actuation System Actuation Module AM518 per SP 2604T Actuation Tests of Various ESF Components Required Materials: SP 2604T Actuation Tests of Various ESF Components Section 4.2 AM518 (procedures, equipment, etc.) MP-PROC-OPS-SP 2604T-001 General

References:

SP 2604T Actuation Tests of Various ESF Components Technical Specifications 3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: JPM 243 Revision : 0/1 Initial Conditions: The Plant is operating at 100% power with the following conditions:

• Chilled Water System is in service and aligned per OP 2330C

• Chiller X-169A and X-169B aligned for Standby Operations Initiating Cues: You are directed to perform a test of Actuation Module AM518.

Perform SP 2604T Section 4.2 for Actuation Module AM518 Record data on SP 2604T-001 All Alarms for this activity will be addressed by the Reactor Operator Simulator Requirements: 100% IC Following Overrides for F-54A DC Switchgear Room Fan to OFF:

• CHHS8871_1 --- INSERT NR ( Not Red Light)

• CHHS8871_2 --- INSERT G (Green Light Lit)

• 11A1S5 DC SWGR Fan-54A STOP

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM 243 Revision: 0/1 Task

Title:

Actuation Tests of Various ESF Components START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 1. Refer To OP 2330C, Chilled Water Examinee reads the NOTE and refers to the initial Y [ ] N [X] S[ ] U[ ]

System, and ENSURE vital chiller, X-169A conditions for the Chilled Water System status.

is aligned for standby operation AND X-169B is not in operation.

Cue:

ALL Alarms will addressed by the Reactor Operator Comments:

Normal alignment Chiller X169A and X169B is not normally running No Red Light , but in Standby STEP Performance: Standard: Critical: Grade

1. 2 2. STOP F-54A, A DC SWGR RM A/C Examinee locates panel C-80 and the Handswitch Y [X] N [ ] S[ ] U[ ]

FAN, (C-80). for F-54A and places it to OFF and allows it to spring return to AUTO Cue:

Insert following Override Digital Outputs for F54A fail to Start after the Handswitch for F-54A is placed in STOP

• CHHS8871_1 --- INSERT NR ( Not Red Light)

• CHHS8871_2 --- INSERT G (Green Light Lit)

• 11A1S5 DC SWGR Fan-54A STOP Comments:

PPC Alarm will come in when the Handswitch for F-54A is place in OFF and PPC Alarm may clear when the Actuation Module is triggered.

5

STEP Performance: Standard: Critical: Grade

1. 3 3. Depending on current condition, PERFORM Examinee checks RCS pressure > 1800 psi and Y [ ] N [X] S[ ] U[ ]

applicable action: SIAS is not Blocked on C01 or ESF Cabinets.

• IF SIAS is not Blocked (*PZR pressure Verifies no 1/5 lights lit on ESF actuation modules.

greater than or equal to 1,850 psia), CHECK all 1/5 lights or bistable TRIP lights not lit for SIAS, CIAS, EBFAS, CSAS, or SG on Facility 1 and Facility 2 ESAS actuation and sensor cabinets.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 4. PLACE S-501, TEST PERMISSIVE Examinee locates S-501 and places in test SIAS Y [X] N [ ] S[ ] U[ ]

SWITCH in TEST SIAS. (ESAS actuation cabinet 5)

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 5 5. PLACE S-502, TEST GROUP SWITCH Examinee locates S-502 and places in test Group 5 Y [X] N [ ] S[ ] U[ ]

in GROUP 5. (ESAS actuation cabinet 5)

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 6 6. PLACE S-102, TRIP TEST switch, in Examinee locates S-102 and places in Containment Y [X] N [ ] S[ ] U[ ]

CONT PRESS SIAS/CIAS/EBFAS/MSI. Pressure SIAS/CIAS/EBFAS/MSI (ESAS Sensor Cabinet A)

Cue:

Comments:

6

STEP Performance: Standard: Critical: Grade

1. 7 NOTE Examinee locates and Presses and Holds the trip Y [X] N [ ] S[ ] U[ ]

When the next step is performed, many 1/5 test button on the correct Bistable BA101.

lights illuminate on the actuation modules.

7. PRESS and HOLD TRIP TEST button on bistable, BA101. (ESAS Sensor Cabinet A)

Cue:

Comments:

Most Operators will find and place flag on the correct Actuation Module prior to this step so you are not searching for the AM while holding the trip test button.

STEP Performance: Standard: Critical: Grade

1. 8 8. CHECK lower 1/5 light lit on actuation Y [ ] N [X] S[ ] U[ ]

module, AM518. (ESAS actuation cabinet 5)

Cue:

Comments:

There is a difference in 1/5 lights and Trip Test Buttons between the Simulator and the Plant. In the plant the 1/5 lights and Trip Test Buttons are next to each other. The Simulator has the both 1/5 lights above the two Trip Test Buttons. The procedure Steps as written work for both the Simulator and the Plant.

STEP Performance: Standard: Critical: Grade

1. 9 9. To initiate start signal, PRESS lower 1/5 Examinee presses the Test #2 Button to initiate Y [X] N [ ] S[ ] U[ ]

TEST button on actuation module, equipment on AM518 AM518. (ESAS actuation cabinet 5)

Cue:

Comments:

There is a difference in 1/5 lights and Trip Test Buttons between the Simulator and the Plant. In the plant the 1/5 lights and Trip Test Buttons are next to each other. The Simulator has the both 1/5 lights above the two Trip Test Buttons. The procedure Steps as written work for both the Simulator and the Plant.

STEP Performance: Standard: Critical: Grade

1. 10 10. RELEASE TRIP TEST button on bistable Y [ ] N [X] S[ ] U[ ]

BA101. (ESAS Sensor Cabinet A)

Cue:

Comments:

7

STEP Performance: Standard: Critical: Grade

1. 11 11. OBSERVE the following and INITIAL for Examinee should locate and observe all the listed Y [X] N [ ] S[ ] U[ ]

the Results on SP 2604T-001: equipment running with the exception of

• Actuation module, AM518, red TRIP light F-54A A DC SWGR RM A/C FAN is lit (ESAS actuation cabinet 5)

Examinee should make a report to the Unit

• F-54A, A DC SWGR RM A/C FAN, Supervisor of the discrepancy.

started (C-80)

• P-122A, VITAL CHILL WTR PP, started Critical action of this step is that the Examinee (C-80) recognizes F-54A A DC SWGR RM A/C FAN

• X-169A, VITAL CHILLER, red indicating fails to Start.

light is lit (C-80)

• CHW-3, CHIL WTR SPLY TO DC SWGR Examinee should also identify the LCO for DC A/C X-84A, is open (C-80) Switchgear Operability.

• CHW-11, CHIL WTR PPS P-122A/123 SPLY HDRS X-TIE, is closed (C-80)

• CHW-13, CHILL WATER PUMPS (P122A/P123) RETURN HEADER CROSSTIE, is closed (C-80)

Cue:

As the Unit Supervisor acknowledge the Report from the Examinee.

Comments:

Ask the Examinee for any recommendations regarding the Fan and if any LCO should be entered and any T.S.A.S. required.

Examinee should recommend continuing with the procedure to restore cooling to the DC Switch gear Room by Starting the Fan and that the DC Switch gear maybe considered in-operable.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM 243 Revision: 0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

As necessary, refer to TIG-04 for additional Pass/Fail criteria.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 30 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

9

JPM QUESTIONS Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM 243 Revision: 0/1 Initial Conditions: The Plant is operating at 100% power with the following conditions:

• Chilled Water System is in service and aligned per OP 2330C

• Chiller X-169A and X-169B aligned for Standby Operations Initiating Cues: You are directed to perform a test of Actuation Module AM518.

Perform SP 2604T Section 4.2 for Actuation Module AM518 Record data on SP 2604T-001 All Alarms for this activity will be addressed by the Reactor Operator 11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Pumping the Containment Sump - Faulted JPM Number: JPM-211 Revision: 1/1 Initiated:

Robert L. Cimmino, Jr. 03/22/2016 Developer Date Reviewed:

David J. Jacobs 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 03/22/2016 Updated to the latest format 1/0 08/15/2016 Incorporated NRC comments 1/1 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-211 Revision: 1/1 Task

Title:

Pumping the Containment Sump - Faulted System: Station Sumps and Drains Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): NUTIMS # 092-01-021 Applicable To: SRO STA RO X PEO K/A Number: 103-K1.02 K/A Rating: 3.9/4.1 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of this JPM, the examinee has pumped the containment sump until receipt of the CTMT NORM SUMP DIS PRESS HI annunciator and then stop the pump(s) and report the outboard isolation valve failed to close.

Required Materials: OP 2336, Station Sumps and Drains (procedures, equipment, etc.) ARP 2590E-108, (BB-21) CTMT NORM SUMP DIS PRESS HI General

References:

OP 2336, Section 4.2, Operation of the Containment Sump

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-211 Revision : 1/1 Initial Conditions: The PPC is not available.

Chemistry requires a CTMT sump sample.

Initiating Cues: You are directed to pump the Containment sump for chemistry sampling.

I will notify you when Chemistry has obtained the required sample and the sump pumps should then be secured.

Simulator Requirements: Initialize to any IC with:

Containment sump at > 30%

Malfunction WD02B to fail SSP-16.2 open.

Malfunction WD04 (100%, 20 sec.) to clog the CTMT Sump Strainer.

No SIAS or CIAS in progress Ensure PPC monitors turned OFF When directed after JPM step 2 Actions, trigger the malfunction WD04 (100%, 30 sec. ramp).

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-211 Revision: 1/1 Task

Title:

Pumping the Containment Sump - Faulted START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 OP 2336, Station Sumps and Drains Examinee obtains a copy of OP 2336, Station Y N S U Section 4.2 Sumps and Drains, proceeds to Section 4.2 and CAUTION. reads the Caution.

1. CTMT sump should be treated as contaminated liquid.

2. Note the frequency of pumping.

Cue: As necessary, acknowledge the Chemist has been briefed on the need to treat that sampled liquid as contaminated and you (US) are tracking the frequency of pumping the CTMT sump.

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 NOTE Examinee reads and acknowledges the Note. Y N S U

1. Sump pumps must be manually stopped.

2. Pumping time > 3 minutes could indicate a clogged strainer basket.

3. Normal full range of pumping CTMT sump raises AWDT 6 - 7%.

Cue: If questioned, Rad. Waste PEO has stated the in-service AWDT has sufficient room to receive the entire contents of the CTMT sump.

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-211 Revision: 1/1 Task

Title:

Pumping the Containment Sump - Faulted STEP Performance: Standard: Critical: Grade

1. 3 4.2.1 IF desired, START containment sump Examinee starts one of the CTMT sump pumps. Y N S U pump A or B as follows (C-06):

a. PLACE CTMT SUMP PP A OR CTMT SUMP PP B, control switch(es) to START.

Cue: Wait until both CTMT isolation valves are full open and sump level begins to decrease, then trigger malfunctions WD02B to fail SSP-16.2 open and WD04 (100%, 20 sec. ramp), CTMT Sump Filter Clogged.

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 4.2.1 [START containment sump pump]: Examinee verifies SSP-16.1 and SSP-16.2 open. Y N S U

b. ENSURE the following open:

• CTMT SUMP ISOL INBOARD, SSP-16.1

• CTMT SUMP ISOL OUTBOARD, SSP-16.2 ENSURE associated sump pump starts.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 5 4.2.1 [START containment sump pump]: Examinee verifies applicable sump pump starts. Y N S U

c. ENSURE associated sump pump starts.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-211 Revision: 1/1 Task

Title:

Pumping the Containment Sump - Faulted STEP Performance: Standard: Critical: Grade

1. 6 Annunciator alarm C06/7 BB-21, CTMT Examinee observes annunciator C06/7 BB-21 and Y N S U NORM SUMP DIS PRESS HI takes action to stop the containment sump pump(s).

ARP 2590E-108: The examinee may take immediate action to stop Corrective Actions: the pump [when level stops going down] and then

1. IF alarm is in for greater than one minute OR refer to the ARP or may refer to the ARP and then sump level is not lowering as expected stop the pump.

PERFORM the following:

1.1. PLACE P33A, CTMT SUMP PP A, and P33B, CTMT SUMP PP B" switches to STOP (C_06).

Cue:

Comments: The critical part of this step is to secure the CTMT sump pumps. It is not important that the subsequent steps in the ARP be performed as they do not involve the board operators. However, after taking the action to stop the running sump pump, the examinee should return to OP2336A and complete the step for ensuring the sump isolation valves close. If examinee does not state this, question as to what they are monitoring when the pumps are secured.

STEP Performance: Standard: Critical: Grade

1. 7 4.2.2 IF desired, STOP containment sump Examinee performs the following: Y N S U pump A or B as follows(C---06): 1. Any running sump pump has been stopped.

a. WHEN CTMT sump level has lowered 2. SSP-16.1 is verified closed by its green light to 10 percent, PLACE CTMT SUMP only lit.

PP A OR CTMT SUMP PP B, control switch(es) to STOP. CRITICAL STEP

b. ENSURE the following closed: 3. SSP-16.2 is verified to NOT have closed by its

• CTMT SUMP ISOL INBOARD, red light only lit and the Examinee attempts to SSP-16.1 manually closed valve.

• CTMT SUMP ISOL OUTBOARD, SSP-16.2 Cue:

Booth Operator insert trigger to Allow the Closure of 2-SSP-16.2 Comments:

7

PERFORMANCE INFORMATION JPM Number: JPM-211 Revision: 1/1 Task

Title:

Pumping the Containment Sump - Faulted STEP Performance: Standard: Critical: Grade

1. 8 Examinee reports the status of SSP-16.2 to the The failure of SSP-16.2 to close is reported to the Y N S U US. US.

Cue: As the US, acknowledge the report and state that the applicable Tech. Spec. required actions will be taken.

Comments: After this step is completed, the JPM is considered complete.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM-211 Revision: 1/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 9

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM-211 Revision: 1/1 Initial Conditions: The PPC is not available.

Chemistry requires a CTMT sump sample.

Initiating Cues: You are directed to pump the Containment sump for chemistry sampling.

I will notify you when Chemistry has obtained the required sample and the sump pumps should then be secured.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

EOP 2541 Appendix 23-N Energizing Bus 24E from Unit 3 JPM Number: JPM-285-S-6 Revision: 0/1 Initiated:

Robert L. Cimmino, Jr. 07/12/2016 Developer Date Reviewed:

Dave Jacobs 07/12/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 03/17/2016 Created from JPM-158 for the 2016 NRC License Exam 0 08/15/2016 Incorporated NRC comments 0/1 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-285-S-6 Revision: 0/1 Task

Title:

EOP 2541 Appendix 23-N Energizing Bus 24E from Unit 3 System: 4,160 Volt AC Time Critical Task: YES NO Validated Time (minutes): 30 Task Number(s): 062-01-356 Applicable To: SRO STA RO X PEO K/A Number: 062-A2.12 K/A Rating: 3.2/3.6 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: Upon energizing bus 24E from Unit 3, the examinee has recognized a fault exists on bus 24E and then de-energizes the bus.

Required Materials: EOP 2541 Appendix 23, (procedures, equipment, etc.)

• Attachment 23-N Energizing 4.16 kV Bus 24E From Unit 3

• Attachment 23-U 3 MVA Electrical Limit on Bus 34A/34B" General

References:

EOP 2541 Appendix 23

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-285-S-6 Revision : 0 Initial Conditions: The Unit is currently in EOP 2526 Reactor Trip Recovery and the RSST is degrading.

Unit 3 has given permission to power Bus 24E Initiating Cues: You are directed to energize Bus 24E from Unit 3 per EOP 2541 Appendix 23 Restoring Electrical Power.

Simulator Requirements:

• IC-144 or equivalent NOP/NOT

• EDA-2/2153-24E-2 1106 amps

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-285-S-6 Revision: 0/1 Task

Title:

EOP 2541 Appendix 23-N Energizing Bus 24E from Unit 3 START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 EOP 2541, Attachment 23-N Y N S U Energizing 4.16 kV Bus 24E From Unit 3 NOTE: The following may indicate a fault on Examinee reads and acknowledges the Note.

4.16 kV Bus 24E: Checks that no fault indications are present for

• Annunciator 4KV BUS 24E/34B TIE BKR 4.16 kV bus 24E by verifying associated A505 TRIP" lit (A-9, C08) annunciators are not lit.

• Annunciator 4KV BUS 24C/E TIE BKR A305 TRIP" lit (B-10, C08)

• Annunciator 4KV BUS 24D/E TIE BKR A408 TRIP" lit (D-10, C08)

1. CHECK that no fault indications are present for 4.16 kV Bus 24E.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 2. ENSURE 4.16 kV Bus 24E SPLY VOLTS" Checks bus 24E voltage indicated. (C-08) Y N S U voltage is indicated.

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-285-S-6 Revision: 0/1 Task

Title:

EOP 2541 Appendix 23-N Energizing Bus 24E from Unit 3 STEP Performance: Standard: Critical: Grade

1. 3 3. ENSURE ALL of the following load breakers Ensures all of the following load breakers on 4.16 Y N S U on 4.16 kV Bus 24E are open: kV Bus 24E are open:

• A502, Service Water Pump B

• A502, Service Water Pump B

• A503, HPSI Pump B

• A503, RBCCW Pump B

• A504, RBCCW Pump B

• A504, HPSI Pump B Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 4. ENSURE ALL of the following breakers are

• Opens breaker A305, 24C/24E TIE BKR, Y N S U open: 24C-2T-2" by placing switch to trip, green light on, red light off.

• A305, 24C/24E TIE BKR, 24C-2T-2" Not Critical Step

• A408, 24D/24E TIE BKR, 24D-2T-2"

• Verifies breaker A408, 24D/24E TIE BKR, 24D-2T-2" racked down (open), green light off, red light off.

Cue:

Booth Operator INSERT Malfunction EDA-2/2153-24E-2 1106 amps Comments:

STEP Performance: Standard: Critical: Grade

1. 5 5. REQUEST permission from Unit 3 Shift Verifies initial Conditions Y N S U Manager or Unit Supervisor to energize Unit 2 4.16 kV Bus 24E from Unit 3 4.16 kV Bus 34A/34B.

Cue: as necessary respond as Unit 3 SM/US; You have permission to energize Bus 24E from Unit 3, Bus 34B.

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-285-S-6 Revision: 0/1 Task

Title:

EOP 2541 Appendix 23-N Energizing Bus 24E from Unit 3 STEP Performance: Standard: Critical: Grade

1. 6 NOTE: Due to the Dead Bus" state of 4.16 kV Examinee reads and acknowledges the Note. Y N S U Bus 24E, the synchroscope will not move. Places SYN SEL SW, 34B-24E-2 (A505)" to

6. PLACE SYN SEL SW, 34B-24E-2 (A505)" ON" and checks INCOMING" voltage indicated.

to ON" and CHECK INCOMING" voltage (C-08).

indicated.

Cue:

Comments: If timed out, acknowledges alarm for Sync Selector Switch On.

STEP Performance: Standard: Critical: Grade

1. 7 7. CLOSE A505, 24E/34B TIE BKR, 34B- Closes A505, 24E/34B TIE BKR,34B-24E-2" by Y N S U 24E-2". placing to close and releasing after red light on, green light off.

Cue:

When A505 is closed, trigger the I/O that raises 24E bus amp indication if not already done.

Comments: The Examinee may or may not OPEN the BREAKER and may not get to JPM steps #8 it is irrelevant if this step is skipped to address the malfunction.

STEP Performance: Standard: Critical: Grade

1. 8 8. CHECK voltage indicated on RUNNING" Checks voltage indicated on RUNNING" Y N S U voltmeter. voltmeter (C-08).

9. PLACE SYN SEL SW, 34B-24E-2 (A505)" Places SYN SEL SW, 34B-24E-2 (A505)" to to OFF". OFF".

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: JPM-285-S-6 Revision: 0/1 Task

Title:

EOP 2541 Appendix 23-N Energizing Bus 24E from Unit 3 STEP Performance: Standard: Critical: Grade

1. 9 10. Refer To Attachment 23-U, 3 MVA Examinee notes 24E/34B bus amps (C-08) are Y N S U Electrical Limit on Bus 34A/34B," and ENSURE above the 3MVA limit and recommends that 3 MVA is not exceeded as loads are restored OPENING supply breaker 34B-24E-2 (A505).

to service.

Cue:

If at any time Examinee suggests tripping A505, concur and/or direct.

Comments: Step #10 is listed only because the Examinee may use it when addressing the indications of a problem with 24E.

However, its use is not relevant.

The JPM is completed when breaker A505 is manually tripped from C-08.

STEP Performance: Standard: Critical: Grade

1. 10 11. At the direction of the US, REALIGN as Places B SW pump in service removes A SW Y N S U necessary for the applicable facility and PLACE pump.

the following pumps in service: Examinee notes 24E/34B bus amps (C-08) are

• Service Water Pump B above the 3MVA limit and recommends

• HPSI Pump B OPENING supply breaker 34B-24E-2 (A505).

• RBCCW Pump B Cue:

If the Examinee did not trip the 24E supply breaker DIRECT placing B Service water pump in service Secure ASW pump If at any time Examinee suggests tripping A505, concur and/or direct.

Comments: The only critical part of this step is opening breaker A505.

The JPM is completed when breaker A505 is manually tripped from C-08.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM-285-S-6 Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 30 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 9

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM-285-S-6 Revision: 0/1 Initial Conditions: The Unit is currently in EOP 2526 Reactor Trip Recovery and the RSST is degrading.

Unit 3 has given permission to power Bus 24E Initiating Cues: You are directed to energize Bus 24E from Unit 3 per EOP 2541 Appendix 23 Restoring Electrical Power.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

AOP 2551 SD from Outside the Control Room C21 PZR LVL JPM Number: JPM-288-S-2 Revision: 0 Initiated:

David J. Jacobs 04/13/2016 Developer Date Reviewed:

Robert L. Cimmino 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 04-13-2016 New JPM ILT Exam 2016 0 2

JPM WORKSHEET Facility: MP Unit 2 Examinee:

JPM Number: JPM-288-S-2 Revision: 0 Task

Title:

AOP 2551 SD from Outside the Control Room C21 PZR LVL System: 011 Pressurizer Level Control System Time Critical Task: YES NO Validated Time (minutes): 10 Task Number(s): 000-04-155 Applicable To: SRO X STA RO X PEO K/A Number: 011 A1.01 K/A Rating: 3.2/3.1 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: Operator restores and maintains PZR Pressure 2225-2300 psia and Level 35% to 70% from C-21 Remote Shutdown Panel with a fault on the Controlling Channel of Pressurizer Level.

Required Materials: MP-PROC-OPS-AOP 2551[r009.03] Shutdown from Outside the Control Room (procedures, equipment, etc.)

General

References:

MP-PROC-OPS-AOP 2551[r009.03] Shutdown from Outside the Control Room

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-288-S-2 Revision : 0 Initial Conditions: The Unit was tripped from 100% and the Crew has evacuated the Control Room.

The Unit Supervisor has entered AOP 2551 Shutdown from Outside the Control Room The Shift Manager has Classified the Event.

All steps up to and including 3.10 have been completed.

Initiating Cues: The Unit Supervisor has directed you to perform Steps 3.11 and 3.12

• Maintain Pressurizer Level 35% to 70%

• Maintain Pressurizer Pressure 2225 psia to 2300 psia Simulator Requirements: RCS at NOP/NOT All Charging Pump H/S in NORM after START Malfunction for PZR Level RX04A (X Ch.) or RX04B (Y Ch.) to 100% with a 60 second Ramp

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-288-S-2 Revision: 0 Task

Title:

AOP 2551 SD from Outside the Control Room C21 PZR LVL START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Examinee refers to AOP 2551 Shutdown from Examinee should review the controllers that are Y N S U outside the Control Room Step available at C-21 to control PZR level.

3.11 DETERMINE that RCS Inventory Control

• Letdown flow controller HIC-110 manual acceptance criteria are met by performing ALL

• Charging Pumps in and out of PTL of the following:

a. CHECK that BOTH of the following conditions exist:

• Pressurizer level is 20 to 80%.

• Pressurizer level is trending to 35 to 70%.

Cue:

Provide a copy of AOP 2551 to the Examinee to review.

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 3.12 DETERMINE RCS Pressure Control Examinee should review the controllers that are Y N S U acceptance criteria are met by BOTH of the available at C-21 to control PZR pressure.

following:

• PZR backup Heaters in or out of PTL

• CHECK that PZR pressure is 1900 to

• Spray Valves in manual 2350 psia.

• CHECK that PZR pressure is trending to 2225 to2300 psia.

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-288-S-2 Revision: 0 Task

Title:

AOP 2551 SD from Outside the Control Room C21 PZR LVL STEP Performance: Standard: Critical: Grade

1. 3 Examinee monitors Pressurizer Level and RCS Locates and Monitors PZR level and RCS Pressure Y N S U pressure using the indicators on C-21 on C-21 Cue:

Direct the Examinee to maintain PZR level between 35 and 70% And PZR pressure 2225 to 2300 psia When the Examinee is ready inform Booth Operator to insert RX04A or RX04B for the controlling channel of PZR level on a 60 second ramp to 100% level Comments:

STEP Performance: Standard: Critical: Grade

1. 4 Examinee observes the following: Examinee States the following: Y N S U

• PZR Level Slowly rising on the

• PZR level and Trend Controlling CH.

• RCS pressure and Trend

• PZR Level slowly lowering on the NON Examinee performs the following:

Controlling CH.

• Takes manual control of HIC-110 and

• RCS Pressure slowly rising. (BU HTRS matches Charging and Letdown Flow.

ON)

• Takes manual control of Spray valves and

• @4% PZR level above program level all Initiates Spray to maintain RCS pressure.

Backup Heaters energizing OR

• IF 2 charging pumps were operating 1

• Places PZR BU Heaters in PTL to maintain shuts off (BU SIG OFF) RCS pressure.

• Letdown Flow rising HIC-110 Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-288-S-2 Revision: 0 Task

Title:

AOP 2551 SD from Outside the Control Room C21 PZR LVL STEP Performance: Standard: Critical: Grade

1. 5 Examinee Reports RCS Pressure and PZR level Examinee manually controls Pressure and Level Y N S U in manual control maintaining the following: with in the procedural guidance.

• PZR level 35 to 70%

• RCS pressure 2225 to 2300 psia Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

7

VERIFICATION OF JPM COMPLETION JPM Number: JPM-288-S-2 Revision: 0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 10 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

8

JPM QUESTIONS Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: JPM-288-S-2 Revision: 0 Initial Conditions: The Unit was tripped from 100% and the Crew has evacuated the Control Room.

The Unit Supervisor has entered AOP 2551 Shutdown from Outside the Control Room The Shift Manager has Classified the Event.

All steps up to and including 3.10 have been completed.

Initiating Cues: The Unit Supervisor has directed you to perform Steps 3.11 and 3.12

• Maintain Pressurizer Level 35% to 70%

• Maintain Pressurizer Pressure 2225 psia to 2300 psia 10

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Evaluate RCP Problem JPM Number: JPM-011 Revision: 10 Initiated:

Robert L. Cimmino, Jr. 05/03/2016 Developer Date Reviewed:

David J. Jacobs 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE Updated to reflect changes to OP 2301C and new 1500 psid 06/27/2003 8 criteria.

05/03/2016 Updated to reflect new format and procedure changes. 9 08/12/2016 Revised to NRC comments change to Upper Oil Reservoir 10 LO LVL 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-011 Revision: 10 Task

Title:

Evaluate RCP Problem System: RCP Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): NUTIMS #003-01-033 Applicable To: SRO STA RO X PEO K/A Number: 003/A2.01 K/A Rating: 3.5/3.9 K/A Number: 003/A4.04 K/A Rating: 3.1/3.0 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of this JPM, examinee has evaluated A RCP indications and reported that the upper lube oil level is lowering with conditions meeting trip criteria for the A RCP and the examinee will secure the A RCP.

Required Materials: AOP 2586 RCP Malfunctions (procedures, equipment, etc.) ARP 2590B-083 (BA-19)

General

References:

ARP 2590B-083 (BA-19)

AOP 2586 RCP Malfunctions OP 2272C Plant Operation in MODE 3 prior to Reactor Startup

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-011 Revision : 10 Initial Conditions:

• IF required allow pre-brief of OP 2272C Plant Operation in MODE 3 prior to Reactor Startup

• Plant is in MODE 3

• OP 2272C Plant Operation in MODE 3 prior to Reactor Startup Initiating Cues:

• You are the PPO Simulator Requirements:

• Normal Operating temperature and pressure MODE 3 (IC-144) or equivalent

• Malfunction RC12A 2 minute ramp 75% severity.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-011 Revision: 10 Task

Title:

Evaluate RCP Problem START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 ARP 2590B-083 Examinee refers to ARP 2590B, BA-19 and reads Y N S U Respond to RCP A UPR OIL RSVR LEVEL NO AUTOMATIC FUNCTIONS LO annunciator (BB-19 on C-02/3). SETPOINT 60%

Automatic Functions

1. None Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 Corrective Actions Examinee uses the PPC or the Indications behind Y N S U CHECK A RCP upper reservoir oil level C04R switches to determined A RCP Upper Oil indication and DETERMINE rate of level Reservoir level and notes lowering level.

decrease (C-04R or PPC)

(Normal range, 75 to 85%).

Cue:

Comments: It is not necessary for the Examinee to address all alarming annunciators. It is only Critical that the Examinee refer to AOP 2586 and may get there through any one of the alarming annunciators.

STEP Performance: Standard: Critical: Grade

1. 3 3 IF A RCP upper reservoir oil level is Examinee obtain a copy of and refers to AOP 2586 Y N S U lowering, Go To AOP 2586, RCP RCP Malfunctions.

Malfunctions.

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-011 Revision: 10 Task

Title:

Evaluate RCP Problem STEP Performance: Standard: Critical: Grade

1. 4 AOP 2586, RCP Malfunctions Examinee transitions to AOP 2586 and performs Y N S U Action/Expected Response the following:

NOTE: Foldout page shall be monitored Examinee opens foldout page for monitoring.

throughout this procedure.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 5 1. Check RCP Trip Criteria Met. Examinee reviews PPC data for Upper Oil Level Y N S U and acknowledges RCP trip criteria is met or is rapidly approaching the criteria.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 6 Examinee notes Trip Criteria for A RCP Upper Y N S U THEN PERFORM the following: Oil Reservoir Low Level on the PPC then performs

a. TRIP Reactor the following:

b. TRIP affected RCP a. Notes the Reactor is already Tripped

c. GO TO EOP 2525, Standard Post Trip b. Trips the A RCP Actions. c. Notes EOP 2525 not required Cue:

Comments: Examinee may finish ANO actions by proceeding to Step 2.c. prior to stating any issues noted with the recorded RCP data.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

6

VERIFICATION OF JPM COMPLETION JPM Number: JPM-011 Revision: 10 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 7

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: JPM-011 Revision: 10 Initial Conditions:

• Plant is in MODE 3

• OP 2272C Plant Operation in MODE 3 prior to Reactor Startup Initiating Cues:

• You are the PPO 9

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Respond to LPSI Pump failure to trip on SRAS Actuation JPM Number: JPM-230 Revision: 2/1 Initiated:

John W. Riley 08/21/12 Developer Date Reviewed:

Ken Truesdale 08/22/12 Technical Reviewer Date Approved:

James V. Grogan 08/23/2012 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE N/A, 08/04/2008 New JPM with new malfunction for LPSI Pump breaker failed 0 closed alternate path. New malfunction validated on 08/11/2008 with IC-98. PSS.

N/A Revised for new Trex system and selection of new IC #289 for set 1 up.

JWR 08/21/2012 Revised JPM to new format. Modified JPM in response to NRC 2/0 feedback for alternate path JPMs. Added steps in the beginning of JPM to take action to align charging pump suction to the RWST prior to checking SRAS. Per NRC feedback during the 2010 71111.11 inspection a good alternate path JPM has the operator perform actions prior to taking contingency action.

08/18/2016 Incorporate NRC comments 2/1 2

JPM WORKSHEET Facility: MP 2 Examinee:

JPM Number: JPM-230 Revision: 2/1 Task

Title:

Respond to LPSI Pump failure to trip on SRAS Actuation System: ECCS/ESAS Time Critical Task: ( ) YES ( X ) NO Validated Time (minutes): 15 Task Number(s): NUTIMS #000-05-222 Applicable To: SRO X RO X PEO K/A Number: 013-A4.01 K/A Rating: 4.5/4.8 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of this JPM, the examinee has recognized the failure of the LPSI Pump to trip on SRAS and implemented the appropriate contingency measures from EOP-2532, LOCA.

Required Materials: EOP 2532, Loss of Coolant Accident, steps 46 through 48 (Revision 29 change 01)

(procedures, equipment, etc.)

General

References:

EOP 2532; Loss of Coolant Accident.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-230 Revision : 2/1 Initiating Cues: You are the RO perform Steps 46, 47, and 48 Align Charging pump suction to RWST Ensure Adequate Suction for SI Pumps and SRAS Initiation Criteria Initial Conditions:

• The plant experienced a large-break LOCA.

• EOP 2525 was completed and the crew transitioned to EOP 2532.

• BAST levels are lowering and are at approximately 9%.

• SRAS initiation is expected to occur shortly (RWST level at ~ 14% and lowering with full ECCS flow).

• All RCPs are off.

Simulator Requirements: Initialize simulator with the following conditions:

• Reset to IC-289: post-large break LOCA conditions; RWST at ~14% with RWST lowering due to SI flow and BASTs at ~9% and lowering.

• IC-289 inserts malfunction RH14A for the A LPSI Pump breaker failure to trip

• Steps of EOP 2532 are complete up to step 46, aligning charging pump suction to the RWST (BAST levels at ~ 9%) with SRAS initiation imminent

• RCPs off

• 2-SI-659/660 are in OPER

• CETs are < 345 degrees F

• Rx vessel level < 43%

• Pressurizer level < 20%

• RWST at ~14% (RWST Mass RHMRWST)

• BAST levels at ~ 9% (CVLBAT8A, CVLBAT8B)

• SRAS Annunciators C01 C-35 and D-35 not lit.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-230 Revision: 2/1 Task

Title:

Respond to LPSI Pump Failure to Trip on SRAS Actuation START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 Y[X] N[ ] S[ ] U[ ]

46. IF BAST levels are less than 10% OR BAST levels are < 10% and the following actions boration from the BASTs is not required, must be taken to shift the charging pump suction PERFORM the following: from the BASTs to the RWST.

a. OPEN CH-192, RWST isolation. a. Examinee opens CH-192, RWST isolation.

Verifies red light lit and green light not lit.

b. ENSURE CH-504, RWST to charging suction is open. b. Examinee ensures CH-504, RWST to charging suction is open. Verifies red light lit and green

c. STOP BOTH boric acid pumps. light not lit

c. Examinee stops both boric acid pumps by taking hand switches to start and then to stop.

Verifies green light lit, red light not lit.

Discharge pressure may also be checked to verify pumps are off.

Cue:

Comments: Pages 38 and 39 of EOP 2532 should be provided to the examinee. Allow the examinee to walk down the boards prior to taking the simulator to run.

5

PERFORMANCE INFORMATION JPM Number: JPM-230 Revision: 2/1 Task

Title:

Respond to LPSI Pump Failure to Trip on SRAS Actuation STEP Performance: Standard: Critical: Grade

1. 2 Y[X] N[ ] S[ ] U[ ]

46. IF BAST levels are less than 10% OR d. Examinee closes or verifies closed the following boration from the BASTs is not required, valves and verifies their green lights are lit and PERFORM the following (Cont): red lights are not lit:

d. ENSURE ALL of the following valves are

• CH-514, boric acid isolation.

closed:

• CH-509, gravity feed isolation from BAST A.

• CH-514, boric acid isolation.

• CH-508, gravity feed isolation from BAST

• CH-509, gravity feed isolation from B.

BAST A.

• CH-501, VCT outlet isolation.

• CH-508, gravity feed isolation from

• CH-196, VCT makeup bypass.

BAST B.

• CH-501, VCT outlet isolation.

• CH-196, VCT makeup bypass.

Cue: The Charging pump suction has been transferred from the BASTs to the RWST.

Comments: The examinee should be monitoring the RWST level to be ready to ensure SRAS initiation.

STEP Performance: Standard: Critical: Grade

1. 3 Y[ ] N[X] S[ ] U[ ]

47. Check containment sump wide range level Examinee checks containment sump wide range rising. level rising. Uses level indicator on C101 (L8242)

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-230 Revision: 2/1 Task

Title:

Respond to LPSI Pump Failure to Trip on SRAS Actuation STEP Performance: Standard: Critical: Grade

1. 4

48. IF break is inside containment AND RWST Examinee identifies SRAS has actuated by SRAS Y[X] N[ ] S[ ] U[ ]

level is less than or equal to 9%, ENSURE the annunciators on C01 (C-35 and D-35).

following:

Examinee checks that both LPSI pumps have

a. SRAS has actuated. (C01) stopped. Examinee should use pump amp meters Y[X] N[ ] S[ ] U[ ]

and red and green hand switch lights to determine

b. BOTH LPSI pumps are stopped. status. Examinee identifies that the B LPSI pump has stopped and the A LPSI pump is still running.

Examinee takes action to stop the A LPSI pump Y[ ] N[X] S[ ] U[ ]

by taking its hand switch to start and then to stop.

This will not stop the A LPSI pump but should be attempted. If stopping the A LPSI pump is not attempted it does not constitute a failure of the JPM but should be identified as a weakness.

Cue: At this point, the examinee may dispatch a PEO to open the A LPSI Pump breaker locally. Wait 2-3 minutes and report the breaker did not open when attempted locally Comments:

7

PERFORMANCE INFORMATION JPM Number: JPM-230 Revision: 2/1 Task

Title:

Respond to LPSI Pump Failure to Trip on SRAS Actuation STEP Performance: Standard: Critical: Grade

1. 5 48.b.1 IF LPSI pumps cannot be stopped, Examinee determines that BOTH LPSI pumps are Y[ ] N[X] S[ ] U[ ]

PERFORM the following: not stopped and goes to contingency action 48.b.1.

1. CLOSE SI-635, LPSI injection valve. Examinee closes SI-635, LPSI injection valve.

Verifies valve closed by green light lit and red light Y[X] N[ ] S[ ] U[ ]

2. ENSURE TWO of the following valves are not lit. Should also verify flow at zero gpm on fully closed and only ONE of the valves is fully associated flow meter.

open:

Examinee closes TWO of the other three LPSI

• SI-615, LPSI injection valve injection valves. Closes two of the following:

• SI-625, LPSI injection valve SI-615, SI-625, and/or SI-645. Verifies valves Y[X] N[ ] S[ ] U[ ]

• SI-645, LPSI injection valve closed by green light lit and red light not lit.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM-230 Revision: 2/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

As necessary, refer to TIG-04 for additional Pass/Fail criteria.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

9

JPM QUESTIONS Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM-230 Revision: 2/1 Initiating Cues: You are the RO perform Steps 46, 47, and 48 Align Charging pump suction to RWST Ensure Adequate Suction for SI Pumps and SRAS Initiation Criteria Initial Conditions:

• The plant experienced a large-break LOCA.

• EOP 2525 was completed and the crew transitioned to EOP 2532.

• BAST levels are lowering and are at approximately 9%.

• SRAS initiation is expected to occur shortly (RWST level at ~ 14% and lowering with full ECCS flow).

• All RCPs are off.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

EOP 2541 App. 26 EDG Operations Low Oil pressure JPM Number: JPM-287-C-6 Revision: 0/1 Initiated:

David J. Jacobs 04/29/2016 Developer Date Reviewed:

Robert L. Cimmino 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 04/29/2016 New JPM for 2016 NRC ILT Exam 0 08/12/2016 Incorporate NRC comments 0/1 2

JPM WORKSHEET Facility: MP Unit 2 Examinee:

JPM Number: JPM-287-C-6 Revision: 0/1 Task

Title:

EOP 2541 App. 26 EDG Operations Low Oil pressure System: 064 Emergency Diesel Generators Time Critical Task: YES NO Validated Time (minutes): 25 Task Number(s): 064-010-075 Applicable To: SRO X STA RO X PEO X K/A Number: A 1.01 K/A Rating: 3.0 / 3.1 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: Simulator: In-Plant: X Task Standards: Monitor EDG during operations during Emergency Conditions, Examinee notes the low lube oil pressures and either recommends or trips the EDG Simulator None Requirements:

General

References:

MP-PROC-OPS-EOP 2541-APP26[r001.00] EDG Operations MP-PROC-OPS-ARP 2591A-002[r001.00] C-38 Alarm Response MP-PROC-OPS-ARP 2591B-002[r006.00] C-39 Alarm Response

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-287-C-6 Revision : 0/1 Initial Conditions:

The Reactor Tripped from 100% power due to a loss of the Grid.

Both Emergency Diesels are running aligned to their respective Buses.

The Crew is performing EOP 2528 Loss of Offsite Power.

Initiating Cues:

You have been directed to perform EOP 2541 Standard Appendix 26 Emergency Diesel Operation and locally check diesel operation.

Required Materials:

(procedures, equipment, etc.)

MP-PROC-OPS-EOP 2541-APP26[r001.00] EDG Operations MP-PROC-OPS-ARP 2591A-033[r001.04] C-38 Alarm Response MP-PROC-OPS-ARP 2591B-002[r006.00] C-39 Alarm Response

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-287-C-6 Revision: 0/1 Task

Title:

EOP 2541 App. 26 EDG Operations Low Oil pressure START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 EOP 2541-APP26 Step #1 Examinee Reviews the Appendix Y N S U OBSERVE EDG alarms. (C-38, C-39)

Cue:

Provide Examinee with a copy of EOP 2541-APP26 Comments:

STEP Performance: Standard: Critical: Grade

1. 2 EOP 2541-APP26 Step #2 The Examinee presses the Reset then Acknowledge Y N S U RESET and ACKNOWLEDGE the alarms. button on C-38 or C-39 NOTEs that the C-38 / C-39 B-1 LUBE OIL PRESSURE LOW Alarm remains lit Cue:

After the Examinee states that they press the Acknowledge and the Reset Button, Provide feedback that LUBE OIL PRESSURE LOW B-1 Alarm remains lit.

Comments:

STEP Performance: Standard: Critical: Grade

1. 3 EOP 2541-APP26 Step #3 The Examinee calls the Control Room and reports Y N S U NOTIFY the Control Room of alarm panel C-38 or C-39 B-1 LUBE OIL PRESSURE LOW status. Alarm remains lit Cue:

Acknowledges as Control room Understand Low Lube Oil Pressure Alarm is in, Perform local Alarm Response Panel Procedure.

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 Reviews the Alarm Response for B-1 ARP Examinee removes and obtains the ARP for the Y N S U 2591A/B-002 Low Lube Oil Pressure Alarm Cue:

Hand the Examinee a copy of ARP 2591A or B -002 for the corresponding EDG Comments:

5

PERFORMANCE INFORMATION JPM Number: JPM-287-C-6 Revision: 0/1 Task

Title:

EOP 2541 App. 26 EDG Operations Low Oil pressure STEP Performance: Standard: Critical: Grade

1. 5 Reviews the ARP for Set Points, Automatic Examinee notes the Lube Oil Pressure Setpoints Y N S U Functions and Corrective Actions and the Automatic Functions Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 6 CHECK oil sump level meets one of the Examinee goes to the north side of the EDG and Y N S U locates the Dipstick and states they would unscrew following:

counter clockwise and remove the dipstick IF DG is operating, between ADD OIL checking oil level and FULL mark on dipstick Cue:

Inform the Examinee oil level is half way between the ADD and FULL mark on the dipstick Comments:

6

PERFORMANCE INFORMATION JPM Number: JPM-287-C-6 Revision: 0/1 Task

Title:

EOP 2541 App. 26 EDG Operations Low Oil pressure STEP Performance: Standard: Critical: Grade

1. 7 IF DG is operating, OBSERVE the Examinee goes to the EDG Gage Board northeast Y N S U side of the EDG and observes PI-8755 / 8757 reads following:

10 psig.

• Pressure indicated on PI-8755/8757 (engine skid) (normally 30 to 40 psig). Examinee goes to the front of the EDG skid and

• Upstream and downstream lube oil filter turns selector handle for PI-8759 / 8760 to pressure indicated on PI-8759/8760 upstream and reads 10 psig and turns selector (normally 62 to 72 psig) handle to downstream reads 8 psig

• Upstream and downstream lube oil Examinee goes to the Southside of the EDG skid strainer pressure indicated on and turns selector handle for PI-8765 / 8766 to PI-8765/8766 (normally 45 to 60 psig) upstream and reads 10 psig and turns selector handle to downstream reads 8 psig Cue:

When the Examinee examines the lube oil gages provide the following:

• PI-8755 reads 10 psig

• PI-8759 reads upstream 10 psig and downstream 8 psig

• PI-8765 reads upstream 10 psig and downstream 8 psig Comments:

STEP Performance: Standard: Critical: Grade

1. 8 The Examinee NOTEs that pressure indications Examinee recommends to the Control Room the Y N S U read less than 10 psig and are less than require need to trip the EDG or Manually Trips the EDG for operations. by Depressing the Fuel Rack Trip or Tripping or isolating the Fuel Supply.

Cue:

Acknowledge Report as Control room and then inform examinee that the EDG Trip and the RPMS are reducing.

Comments:

IF the Examinee attempts to trip the EDG using the Trip Button on C-38 / 39 the EDG does not TRIP, must Trip the EDG from the fuel Rack or isolation of Fuel.

If the Examinee Trips the EDG this concludes the JPM or JPM continues step #11 if the Examinee fails to locally trip the EDG.

7

PERFORMANCE INFORMATION JPM Number: JPM-287-C-6 Revision: 0/1 Task

Title:

EOP 2541 App. 26 EDG Operations Low Oil pressure STEP Performance: Standard: Critical: Grade

1. 9 Visually INSPECT system for oil leakage or Examinee walks around the EDG looking for oil Y N S U broken oil lines. leaks.

Cue:

No Oil Leaking Comments:

Reason for the Low Lube Oil pressure is the Engine Driven Oil Pump shaft sheared.

STEP Performance: Standard: Critical: Grade WHEN alarming condition is clear, PRESS

1. 10 ALARM RESET button (engine skid). Examinee attempts to reset alarms on C-38 / C-39 Y N S U Cue: Alarms do not reset Comments:

STEP Performance: Standard: Critical: Grade

1. 11 SUBMIT CR. Examinee state they would submit a CR Y N S U Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 12 Refer To Technical Specification LCOs, States that the EDG is NOT OPERABLE Y N S U 3.8.1.1 and 3.8.1.2, and DETERMINE applicability.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM-287-C-6 Revision: 0/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 25 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 9

Question #1: If the Emergency Diesel was started due to a loss of normal power signal, how many lube oil low pressure switches must actuate to trip the diesel?

Answer #1: If an emergency start signal is present, two of three pressure switches must actuate to trip diesel. ARP 2591A-002 / ARP 2591B-002 Automatic Functions Examinee

Response

Grade: SAT UNSAT Question #2: When the diesel engine is running what supplies lube oil pressure?

Answer #2: Engine driven lube oil pump Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM-287-C-6 Revision: 0/1 Initial Conditions:

The Reactor Tripped from 100% power due to a loss of the Grid.

Both Emergency Diesels are running aligned to their respective Buses.

The Crew is performing EOP 2528 Loss of Offsite Power.

Initiating Cues:

You have been directed to perform EOP 2541 Standard Appendix 26 Emergency Diesel Operation and locally check diesel operation.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Placing CAR RBCCW Valve In Manual Local Operation JPM Number: JPM-245 Revision: 1/1 Initiated:

Robert L. Cimmino, Jr. 05/04/2016 Developer Date Reviewed:

David J. Jacobs 07/05/2016 Technical Reviewer Date Approved:

Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 05/04/2016 Updated to latest template and procedure revision 1/0 08/11/2016 Incorporate NRC changes 1/1 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: JPM-245 Revision: 1/1 Task

Title:

Placing CAR RBCCW Valve In Manual Local Operation.

System: RBCCW Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): NUTIMS # 000-04-104 Applicable To: SRO X STA RO X PEO X K/A Number: 022/A4.04 K/A Rating: 3.1/3.2 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: Simulator: In-Plant: X Task Standards: At the completion of this JPM, the examinee will have simulated placing an RBCCW valve in manual local operation, and open.

Required Materials: OP 2330A, RBCCW System (procedures, equipment, etc.)

General

References:

OP 2330A, Section 4.9

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: JPM-245 Revision : 1/1 Initial Conditions:

• The plant is in MODE 5.

• C CAR Cooler has developed a leak inside Containment.

• The Control Room has attempted to isolate the C CAR cooler by closing the inlet and outlet RB valves.

• 2-RB-28.1C C CAR COOLER INLET ISOLATION remains OPEN Initiating Cues:

• The US has directed you to place 2-RB-28.1C in manual local control and close 2-RB-28.1C C CAR COOLER INLET ISOLATION IAW OP 2330A Section 4.9 Manual Operation of RBCCW CAR Cooler Valves.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-245 Revision: 1/1 Task

Title:

Placing CAR RBCCW Valve In Manual Local Ops.

START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 4.9.1 PERFORM the following to place any Examinee obtains procedure OP 2330A Y N S U Attachment 3 valve in MANUAL:

a. Using Attachment 3, PERFORM applicable actions for the valve to be placed in manual.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 2 Attachment 3 1. Records valve number and function on Y N S U 3.1 DOCUMENT valve number and function on Attachment 3.

top of Attachment. 2. Examinee determines that repositioning the 3.2 IF CAR cooler valve is to be repositioned, valve will not have an effect on RBCCW flow with the outlet valves closed. (initial ENSURE adequate RBCCW header margin conditions) available. 3. Examinee either uses Initial Conditions or 3.3 ENSURE CAR cooler valve, open. locates the valve to determine position.

Cue:

Comments:

2-RB-28.1C located Aux Building -5 FT East Penetration Room, to locally determine position requires checking the handwheel position in relation to the valve lever arm grove. For example if the handwheel position indicates OPEN and the valve lever arm grooves are aligned then the handwheel position indications are the same as the current valve position.

5

PERFORMANCE INFORMATION JPM Number: JPM-245 Revision: 1/1 Task

Title:

Placing CAR RBCCW Valve In Manual Local Ops.

STEP Performance: Standard: Critical: Grade

1. 3 3.4 IF in MODE 1, 2, 3, or 4 LOG entry into the Examinee determines TS and TRM not applicable. Y N S U following: Initial Conditions plant is in MODE 5 3.4.1 TSAS 3.6.3.1 3.4.2 TRM 3.6.3.1 3.5 IF in MODE 1, 2, or 3 (greater than or equal to 1,750 psia), AND valve to be positioned is a CAR cooler inlet valve or a CAR cooler emergency outlet valve, LOG ENTRY in TSAS 3.6.2.1.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade

1. 4 3.6 CLOSE instrument air isolation to air Examinee locates instrument air isolation near Y N S U operator. south wall and rotates handwheel in the clockwise direction.

Cue:

Valve is at a hard stop Comments:

STEP Performance: Standard: Critical: Grade

1. 5 3.7 Refer to Table 5 and determine applicable Examinee refers to Table 5 and identifies that fuse Y N S U fuseblock. CFN on C-01R .

Cue:

Examiner states that the fuse has been removed by Control Room personnel, and that the sound of air release is heard, and the valve is moving to the open position.

Comments:

The fuse block is located inside the main control boards, which have very limited access while at power.

6

PERFORMANCE INFORMATION JPM Number: JPM-245 Revision: 1/1 Task

Title:

Placing CAR RBCCW Valve In Manual Local Ops.

STEP Performance: Standard: Critical: Grade

1. 6 3.8 Loosen Allen head screw on lever arm of air Examinee indicates that he would use the attached Y N S U cylinder operating shaft. Allen wrench to loosen the screw.

Cue:

Examiner states that the Allen screw is loose.

Comments:

STEP Performance: Standard: Critical: Grade

1. 7 3.9 REMOVE fuseblock for valve being placed Examinees states they would call the Control Y N S U in MANUAL (C-01R). Room to remove Fuse Block CFN Cue:

Respond as the Control Room Fuse Block CFN is removed from C01R Comments:

STEP Performance: Standard: Critical: Grade

1. 8 3.10 Operate the manual handwheel to align the Examinee states that he would move the manual Y N S U manual operator shaft to valve stem for the lever handwheel to align the shaft.

arm insertion.

Cue:

Examiner states that the shafts are now aligned.

Comments:

STEP Performance: Standard: Critical: Grade

1. 9 3.11 Loosen Allen screw on lever arm of Examinee states that he must access the area under Y N S U Manual operating shaft and Engage arm. the valve and loosen the allen screw. He then would engage the lever arm for the manual operator.

Cue:

Examiner states that the lever arm is engaged.

Comments:

7

PERFORMANCE INFORMATION JPM Number: JPM-245 Revision: 1/1 Task

Title:

Placing CAR RBCCW Valve In Manual Local Ops.

STEP Performance: Standard: Critical: Grade

1. 10 3.12 Tighten the Allen screw for the manual Examinee states that he would turn Allen screw to Y N S U lever arm. tighten the lever arm for the manual handwheel.

Cue:

Examiner states that the Allen screw is tight.

Comments:

STEP Performance: Standard: Critical: Grade

1. 11 3.13 To prevent inadvertent engagement of lever Examinee states that he would move the lever arm Y N S U arm and air operating shaft, out of the way and that he may need to move the manual handwheel to relieve the tension on the arm PERFORM the following: to allow this. Also states that he would then tighten 3.13.1 DISENGAGE lever arm from air cylinder the Allen screw (clockwise) to prevent the shaft and HOLD in DISENGAGED position. movement of the lever arm.

3.13.2 ROTATE Allen head screw clockwise until it maintains lever arm in DISENGAGED OPERATES VALVE in the REVERSE direction position. to close valve (COUNTER CLOCKWISE) 3.13.3 RELEASE lever arm.

3.13.4 OPERATE handwheel to position valve as directed by SM or US.

Cue:

Examiner states that the lever arm is disengaged and Allen screw is tight.

Comments:

After this step is completed, the JPM is considered complete TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: JPM-245 Revision: 1/1 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

JPM QUESTIONS 9

Question #1:

Answer #1:

Examinee

Response

Grade: SAT UNSAT Question #2:

Answer #2:

Examinee

Response

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: JPM-245 Revision: 1/1 Initial Conditions:

• The plant is in MODE 5.

• C CAR Cooler has developed a leak inside Containment.

• The Control Room has attempted to isolate the C CAR cooler by closing the inlet and outlet RB valves.

• 2-RB-28.1C C CAR COOLER INLET ISOLATION remains OPEN Initiating Cues:

• The US has directed you to place 2-RB-28.1C in manual local control and close 2-RB-28.1C C CAR COOLER INLET ISOLATION IAW OP 2330A Section 4.9 Manual Operation of RBCCW CAR Cooler Valves.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

EOP 2541 Appendix 34 Turbine Building Sump Alignment JPM Number: JPM-265 Revision: 0/2 Initiated:

David J. Jacobs 02/14/2012 Developer Date Reviewed:

Joseph M. Amarello 02/14/2012 Technical Reviewer Date Approved:

Mike J. Cote 02/24/2012 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 06/26/2014 djj Updated to new format 0/1 06/26/2016 djj Incorporated NRC comments 0/2 2

JPM WORKSHEET Facility: Millstone Unit 2 Examinee:

JPM Number: JPM-265 Revision: 0/2 Task

Title:

EOP 2541 Appendix 34 Turbine Building Sump Alignment System: 2336 Station Sumps and Drains Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 15 Task Number(s): NUTIMS 092-01-006 Applicable To: SRO X STA RO X PEO K/A Number: 2.3.11 K/A Rating: 3.8 / 4.3 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: Simulator: In-Plant: X Task Standards: At the completion of this JPM, the examinee has simulated realigning Turbine Building Sumps to CPF.

Required Materials:

• MP-PROC-OPS-EOP 2541-APP34 Turbine Building Sump Alignment (procedures, equipment, etc.)

General

References:

• MP-PROC-OPS-EOP 2541-APP34 REV. 000 3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: JPM-265 Revision : 0/2 Initial Conditions:

• The Unit has been Manually Tripped due to a Steam Generator Tube Rupture approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.

• All Turbine building sumps were placed in off per AOP 2569 Steam Generator Tube Leak.

Initiating Cues:

• The Balance of Plant Operator has directed you to perform EOP 2541 Appendix 34 and pump the Turbine Building East Condenser pit sump to the on service CPF TK-10 or 11.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: JPM-265 Revision: 0/2 Task

Title:

EOP 2541 Appendix 34 Turbine Building Sump Alignment START TIME: __________

STEP Performance: Standard: Critical: Grade

1. 1 1. ENSURE BOTH of the following for the The examinee Verifies the following: Y [ ] N [X] S[ ] U[ ]

in-service CPF tank: (TK-10 or TK-11)

• TK-10 or TK-11 levels on panel

• Adequate tank volume exists to receive 2CND-PNLCDX.

influent.

• Verifies no Discharge Placard for the

• The tank is not being discharged TK in service to receive TB Sump effluent.

Cue:

IF REQUIRED inform examinee ON SERVICE TANK HAS ADEQUATE VOLUME Comments:

Indication for TK-10 and TK-11 on CPF Condensate Demineralizer Waste Treating Panel, 2CND-PNLCDX and the on service TK is denoted by the switch positions of the INLET VALVES to the TK STEP Performance: Standard: Critical: Grade

1. 2 2. UNLOCK and OPEN ONE of the Examinee states they would UNLOCK and Y [X] N [ ] S [ ] U[ ]

following valves to the in-service CPF OPEN either tank:

• AR-81A, CONDENSER PIT SUMP

• AR-81A, CONDENSER PIT SUMP TO TK 10(CPF)

TO TK 10(CPF)

• AR-81B, CONDENSER PIT SUMP

• AR-81B, CONDENSER PIT SUMP TO TK 11 (CPF)

TO TK 11 (CPF) by unlocking and rotating the handwheel in the counter clockwise direction for the on service TK.

Cue:

Valve Stem rising the Valve is at a hard stop Comments:

Located by Acid and Caustic Tanks lower level CPF entry into the area is allowed when no chemical handling is in progress 5

STEP Performance: Standard: Critical: Grade

1. 3 3. PLACE ALL of the following Turbine Examinee refers to the initial conditions and Y [ ] N [X] S[ ] U[ ]

Building Sump Pump handswitches in states that Handswitches are OFF.

STOP:

• Condenser Pit A, P73A (West)

• Condenser Pit A, P73B (West)

• Condenser Pit B, P39A (East)

• Condenser Pit B, P39B (East)

• Motor Driven Auxiliary SGFP Room, P125

• Turbine Driven Auxiliary SGFP Room, P72A

• Turbine Driven Auxiliary SGFP Room, P72B Cue:

Switch is in OFF and Green Light lit for applicable pumps Comments:

STEP Performance: Standard: Critical: Grade

1. 4 4. CLOSE SS-25, CONDENSER PIT AND Examinee locates SS-25, and closes by Y [X] N [ ] S[ ] U[ ]

AFW SUMPS TO OIL SEPARATOR #2". rotating handwheel in clockwise direction (Northeast corner of condenser) using the chain operator.

Cue:

Valve is at a hard stop.

Comments:

Located Northeast corner of condenser in the Turbine Building overhead STEP Performance: Standard: Critical: Grade

1. 5 5. OPEN AR-80, TURBINE BUILDING Examinee locates AR-80, and opens by Y [X] N [ ] S[ ] U[ ]

SUMPS TO CPF TK 10/11. rotating handwheel in counter clockwise (Northeast corner of condenser) direction using the chain operator.

Cue:

Valve is at a hard stop.

Comments:

Located Northeast corner of condenser in the Turbine Building overhead 6

STEP Performance: Standard: Critical: Grade

1. 6 6. PERFORM the following to align Turbine Examinee refers to the initial conditions and Y [X] N [ ] S[ ] U[ ]

states that they turn the switch for the East Building Sumps for automatic operation:

Condenser pit sump pumps (P39A/B) to Start

a. OBTAIN approval to operate the or Automatic.

Turbine Building Sump Pumps in automatic.

Cue:

Select pump Light turns RED, discharge pressure indicated and sump level is lowering Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

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VERIFICATION OF JPM COMPLETION JPM Number: JPM-265 Revision: 0/2 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

As necessary, refer to TIG-04 for additional Pass/Fail criteria.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Work Practice Performance: SAT UNSAT Operator Fundamentals: SAT UNSAT JPM Question Portion Overall [NLO only]: SAT UNSAT N/A Attached Question #1 SAT UNSAT Attached Question #2 SAT UNSAT Overall Result of JPM: SAT UNSAT Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

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JPM QUESTIONS Question #1: What would be the Major consequence if the Turbine Building Sumps were to over flow and fill the Condenser Pit? Ref. CWS-00-C.R9Chg1 Answer #1: Circulating Water pumps would trip causing a Reactor Trip if water level exceeded 10 inches above the Floor of the Condenser Pit Examinee

Response

Grade: SAT UNSAT Question #2: What guidelines are used to minimize water inputs to the Condenser pit sumps during a Steam Generator Tube Leak event in progress?

Ref. AOP 2569 Steam Generator Tube Leak Step 4.4 Answer #2: a. ENSURE the SJAE after cooler drains are aligned to the condenser.

b. AVOID the use of mechanical vacuum pumps.

c. AVOID draining any tanks or lines to the condenser pit sumps.

Examinee

Response

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: JPM-265 Revision: 0/2 Initiating Cues:

• The Balance of Plant Operator has directed you to perform EOP 2541 Appendix 34 and pump the Turbine Building East Condenser pit sump to the on service CPF TK-10 or 11.

Initial Conditions:

• The Unit has been Manually Tripped due to a Steam Generator Tube Rupture approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.

• All Turbine building sumps were placed in off per AOP 2569 Steam Generator Tube Leak.

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