ML15163A232

Draft Operating Exam (Sections a, B, and C) (Folder 2)

ML15163A232
Person / Time
Site:	Indian Point
Issue date:	06/04/2015
From:	D'Antonio J Operations Branch I
To:	Entergy Nuclear Indian Point 3
Shared Package
ML14352A136	List: IR 05000286/2015301 ML14363A296 ML15160A409 ML15160A456 ML15160A464 ML15160A470 ML15163A229 ML15163A230 ML15163A231 ML15163A232
References
TAC U01908
Download: ML15163A232 (271)

Text

Appendix D Scenario Outline Form ES-0-1 Facility: Indian Point 3 Scenario No.: 1 Op-Test No.:

Examiners: Operators:

Initial Conditions: AQQrox. 75% Power, 1;2ower ascension in grogress to 100% Qower IAW 3-POP-2.1, Attachment 2. 2 Condensate PumQs are in service. Fuel is Conditioned.

Turnover: Continue 12ower ascension to 100% IAW 3-POP-2.1, Attachment 2 Returning from maintenance on 32 MBFP (oil leak). 32 Charging Pum12 is out of service, tagged due to a Qacking leak (maintenance has Qum12 disassembled).

Event Malf. No. Event Event No. Type* Description 1 R (ATC) Raise load IAW 3-POP-2.1 N (BOP)

N (CRS) 2 I (BOP) 31 Steam Generator Loop 18 (4198) Steam Flow Channel fails high.

I (ATC)

TS (CRS) 3 TS (CRS) 33 Accumulator Low Pressure Alarm actuates.

4 C (ALL) 32 MBFP trips.

5 C(ALL)* IF crew does not trip reactor due to 32 MBFP trip, insert MTG Voltage Regulator Failure and within 3 minutes a direct MTG Trip from Buchannan.*

6 M(ALL) Automatic Turbine I Reactor Trip I Safety Injection. Coincident with the Reactor Trip, #31 SG Safety Valve will fail open.

7 C (CRS) 31 Safety Injection Pump fails to auto start.

C(BOP) 8 M(ALL) 31 SG Tube Rupture (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)aior

Simulator Exam Scenario # 1 Summary The evaluation begins with the plant at 75% power and power ascension in progress to 100%

power IAW 3-POP-2.1, Attachment 2. 2 Condensate Pumps are in service. Fuel is conditioned.

The plant is returning from maintenance on 32 MBFP (oil leak). 32 Charging Pump is out of service, tagged due to a packing leak (maintenance has pump disassembled).

After starting the 3rd Condensate Pump and raising power approximately 3-5%, 31 Steam Generator Loop 1B (419B) Steam Flow Channel fails high. The team will take actions in accordance with AOP-INST-1, "Instrument I Controller Failures".

After selecting the NON-affected channel for both SG Transfer Switches and tripping the appropriate bistables, an "ACUMULATOR #33 PRESS" on Panel SBF-1 will annunciate. The crew will respond IAW 3-ARP-004 and restore 33 accumulator pressure to within technical specification limits.

Once the CRS has identified the appropriate technical specification and action requirements, the scenario will continue with a trip of the 32 MBFP. Crew responds IAW 3-AOP-FW-1, reduces power if necessary to stabilize and match steam flow I feed flow. The crew may trip the reactor depending on current power level (i.e. > 80% per AOP).

If the crew doesn't trip the reactor, an MTG Voltage Regulator failure will occur following plant stabilization. The team will take actions to stabilize the plant per ARP-8 or may manually trip the unit and enter E-0. They may place the voltage regulator in manual (test). If the team does not trip the unit, 3 minutes after regulator failure, a direct MTG trip from Buchanan will occur.

The team will implement E-0, "Reactor Trip or Safety Injection".

Coincident with the reactor trip, #31 SG Safety valve will fail open. The team will respond per E-2, "Faulted Steam Generator Isolation". While in E-0, the BOP should recognize that 31 Safety Injection Pump failed to start. The BOP operator manually starts 31 SI Pump IAW 3-R0-1.

After the team identifies and attempts to isolate the faulted SG in E-2, they should transition to E-3, "SGTR" due to a faulted /ruptured SG. The team will then transition to and take actions per ECA-3.1, "SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired" at either Step 5 (SG pressure < 400#) or at Step 16. The event will be terminated once a cooldown to cold shutdown conditions at the highest achievable rate but < 100°F/hr is initiated.

Procedure flow path: POP-2.1, AOP-INST-1, ARP-4, AOP-FW-1, ARP-8, E-0, E-2, E-3, ECA-3.1

Scenario# 1 On At Time Action Description Event STEAM GENERATOR

. Insert malfunction MAL-SGN002B to 00:00:00 None PRESSURE TRANSMITTER 1400.00000 in 5 on event 2 FAILURE (PT-419B)

Insert malfunction MAL-ATS004B on

• MAIN FEEDWATER PUMP 00:00:00 None event 4 32 TRIP MAIN GENERATOR Insert malfunction MAL-GENOOl to 00:00:00 None VOLTAGE REGULATOR 30.00000 in 5 on event 5 FAILURE Insert malfunction MAL-GEN002 after 00:00:00 None MAIN GENERATOR TRIP 180 on event 5 STEAM GENERATOR Insert malfunction MAL-SGN004A after 00:00:00 None SAFETY VAL VE FAIL URE 20 to 0 on event 30 (MS-45A)

STEAM GENERATOR Insert malfunction MAL-SGN004B to 0 00:00:00 None SAFETY VAL VE FAILURE on event 9 (MS-46A)

Insert malfunction MAL-SIS003C to ACCUMULATOR 33 None None 20.00000 on event 3 NITROGEN LEAKAGE Insert malfunction MAL-SIS004A to SAFETY INJECTION PUMP 00:00:00 None FAILURE TO AUTOSTART 31 FAILURES Create Event 30 JPPLP4(1)==1 -desc Set 00:00:00 None Trigger 30 to actuate after Reactor Trip Insert malfunction MAL-SGN005A after STEAM GENERATOR 31 00:00:00 None 10 to 30.00000 on event 8 TUBE LEAK

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - Event No.: - Page _1_ of _1_1_

Event

Description:

Raise load to 100% Power IAW 3-POP-2.1, Attachment 2 Time Position Applicant's Actions or Behavior ATC/ Raise Load IAW 3-POP-2.1, Attachments 1 and 2.

BOP

• ADJUST governor control and/or load limits to desired load

• ADJUST Tavg using Control Rods AND Boron concentration changes as required. (Follow Reactivity Plan with Rods in Auto) o MAINTAIN Tavg AND Tret within+/- 0.5°F o Tavg AND Tret NOT to exceed+/- 4.0°F

• MAINTAIN PRZR Pressure

• MAINTAIN PRZR Level

• MAINTAIN SG narrow range levels ATC/ WHEN Turbine power is approximately 800 Mwe, THEN PERFORM the BOP following:

• NOTIFY Watch Chemist to verify secondary chemistry is satisfactory, PRIOR to starting third condensate pump per 3-SOP-C-002, Condensate System Operation.

• NOTE: Normal MBFP Suction Pressure for starting the third condensate pump is approximately 400 psig.

Booth Instructor When contacted, inform the crew that Secondary Chemistry conditions are satisfactory.

ATC/ WHEN secondary chemistry conditions are satisfactory, THEN START BOP third condensate pump per 3-SOP-C-002. Condensate Pump Operation.

• NOTE: Seal injection booster pumps may restart if Seal Water Drain temperature is 180°F or greater.

WHEN THIRD CONDENSATE PUMP IS RUNNING AND Seal Water Drain temperature is less than 180°F, THEN PERFORM the following:

• SHUTDOWN MBFP seal injection booster pumps (one at a time) AND PLACE control switches in AUTO.

NOTE: Evaluator may move on to the next event once the 3rd Condensate Pump is started and/or power has been raised approximately 3-5%.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 1 Event No.: 2 Page __l_ of __1.1_

Event

Description:

31 Steam Generator Loop 18 (4198) Steam Flow Channel fails high.

Booth Instructor When directed by the lead evaluator, activate 31 Steam Generator Loop 1B (419B) Steam Flow Channel fails hiqh malfunction.

Time Position Applicant's Actions or Behavior ATC 1. Are both SG Transfer Switches selected to the NON affected channel?

a. Select both SG Transfer Switches to the NON affected channel.

2. Restore affected SG level to program as necessary.

CRS 3. Refer to the following TS tables for required actions:

a. 3.3.1-1

b. 3.3.2-1 BOP 4. Are fill redundant bistable status lights for failed instrument listed in Attachment 4 (Steam Flow Tables) Table 1 (Page 117) extinguished?

a. H-13: SG 31 LO LEVEL LC417G

b. 1-8: HI STM FLOW LP32 FC429A

c. J-8: HI STM FLOW LP32 FC429B

d. 1-9: HI STM FLOW LP33 FC439A

e. J-9: HI STM FLOW LP33 FC439B

f. 1-10: HI STM FLOW LP34 FC449A

g. J-10: HI STM FLOW LP34 FC449B

5. Trip bistables for failed instrument listed in Attachment 4 (Steam Flow Tables) Table 2 (Page 121) Protection Rack White A-9

a. Loop 1B, SF > FWF

b. Loop 1B, High SF SI

6. Are all bistable lights for failed instrument listed in Attachment 4 (Steam Flow Tables) Table 3 (Page 123) illuminated?

a. J-7: HI STM FLOW LP31 FC419B

b. F-12: STM-FW FL DEV LP31 FC418F ATC 7. Return controls for unaffected equipment used to stabilize plant conditions to auto as desired.

Booth Instructor When directed by the lead evaluator, continue to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 1

~'----

Event No.: 3 -~~

Page _]__ of _1_1_

Event

Description:

33 Accumulator Low Pressure Alarm actuates.

Time Position Applicant's Actions or Behavior Booth Operator When directed by lead evaluator, insert the 33 Accumulator Low Pressure Alarm ma/function. (leak - lowers to less than 600#)

ATC/ Operator responds to the annunciator alarm or "ACCUMULATOR #33 BOP PRESS" on Panel SBF-1 IAW 3-ARP-004.

• VERIFY alarm by observing both pressure channels.

• IF channel failure has occurred, THEN NOTIFY l&C of failure.

• CHECK Accumulator #33 level to see if pressure change was caused by a level change.

CRS

• IF pressure is above the high OR low Technical Specification limit, THEN REFER TO Technical Specifications LCO 3.5.1, Action B.

ATC/

• RETURN accumulator pressure to within operating band using BOP 3-SOP-Sl-001, Safety Injection System Operation.

o VERIFY Sl-HCV-943 is closed.

o OPEN NNE-AOV-863, PORV's & Accumulators N2 Supply Containment Isolation.

o OPEN applicable supply isolation:

• Sl-AOV-891 C, 33 Accumulator N2 Supply Isolation o ADJUST NNE-PCV-942, PORV's and Accumulators N2 Supply Pressure Control Valve, as necessary, to VERIFY outlet pressure is between 660 and 700 psig AND NOTE the number of turns.

• WHEN SI accumulator reaches desired pressure, THEN:

o IF no additional accumulators are to be pressurized, THEN ADJUST NNE-PCV-942, PORVs & Accumulators N2 Supply Pressure Control Valve, as necessary, to the number of turns noted above.

o CLOSE applicable supply isolation: Sl-AOV-891 C, 33 Accumulator N2 Supply Isolation o CLOSE NNE-AOV-863, PORVs & Accumulator N2 Containment Isolation.

Booth Instructor Lead Evaluator may move on to the next event when the CRS identifies the required Technical Specification Action.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 1 Event No.: 4 Page__.+/-__ of _1_1_

Event

Description:

32 MBFP tri12s. Crew res12onds IAW 3-AOP-FW-1. Reduces 12ower if necessary to stabilize & match steam flow/feed flow. (May tri12 reactor de12ending on 12ower level, i.e.>80%)

Booth Instructor When directed by lead evaluator, insert 32 MBFP trip malfunction.

Time Position Applicant's Actions or Behavior ALL 1. Are both MBFPs operating? No

a. If reactor power is >80%, then trip the reactor and go to E-0.

2. Is a MBFP running? Yes

3. Are steam flow and feed flow matched? No

a. Initiate load reduction as necessary per Attachment 1 (Approximate Unit Load With Various Pump Configurations)

Main Boiler Feed Condensate Heater Drain Approximate Pumps( 1l Pumps Pumps Allowable MWE 2 3 2 Full Load 2 2 2 900 MWE( 2l 2 3 1 700 MWE( 2J 1 3 2 650 MWE( 2l 1 2 2 600MWE( 2l 2 2 1 550 MWE(2 l 1 2 1 50Q MWE( 2l 2 2 0 400 MWE( 2l

b. Adjust running MBFP speed as necessary to accomplish the following:

i. Match steam flow and feed flow ii. Maintain MBFP suction pressure > 350 psig iii. Maintain MBFP discharge pressure < 1390 psig iv. Refer to Attachment 5 (Main Feedwater Regulating Valves Program LiP) (Page 55)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 1 Event No.: 4 cont. Page __§___ of _1_1_

Event

Description:

32 MBFP trips. Crew responds IAW 3-AOP-FW-1. Reduces power if necessary to stabilize & match steam flow/feed flow. (May trip reactor depending on power level. i.e.>80%)

Time Position Applicant's Actions or Behavior

4. Are all available condensate pumps running?

ALL

a. Start fill available condensate pumps as necessary to maintain MBFP suction > 350 psig.

5. Are 31 and 33 ABFP running?

6. Start 31 and 33 ABFPs Are §!LSGBD isolation valves closed?

a. Close all SGBD isolation valves

7. Is recirculation valve for tripped MBFP closed?

a. Close recirculation valve for the tripped MBFP.

8. Maintain SG levels on program by performing the following as necessary:

a. Adjusting turbine load or steam dumps (as applicable)

b. Placing MBFP control in manual and adjusting speed

c. Placing MFRVs in manual and adjusting flow

d. Refer to Attachment 5 (Main Feedwater Regulating Valves Program L'1P) (Page 55)

Booth Instructor IF crew does not trip reactor due to 32 MBFP trip, insert MTG Voltage Regulator Failure and within 3 minutes a direct MTG Trip from Buchannan.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - Event No.: - Page __§_ of _1_1_

Event

Description:

As necessary: MTG Voltage Regulator Failure and within 3 minutes a direct MTG trip from Buchannan.

Time Position Applicant's Actions or Behavior IF crew does not trip reactor due to 32 MBFP trip, insert MTG (All)

Voltage Regulator Failure and within 3 minutes a direct MTG Trip from Buchannan.

1. Crew responds to the alarm response procedure

2. Possibly places voltage regulator in manual

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 1

~'---

Event No.: 6

-"---~

Page__]__ of _1_1_

Event

Description:

Automatic Turbine Trip I Reactor Trip I Safety Injection. Coincident with the Reactor Trip #31 SG Safety Valve will fail open.

Booth Instructor Coincident with the Reactor Trip, 151 #31 SG Safety failure is inserted.

Use 2 SG Safeties, 2nd one to differentiate SG pressure. One (1) safety for SI, after SI put second safety in.

Time Position Applicant's Actions or Behavior

1. Crew enters E-0, Reactor Trip or Safety Injection and performs All immediate actions

2. Crew determines that Safety Injection is required if not automatically initiated.

3. Crew progresses through E-0 to step 15:

a. Determine if SGs are Faulted

i. Any SG Pressures decreasing in an uncontrolled manner? Yes ii. Any completely depressurized?

4. Go to 3-E-2, Faulted Steam Generator Isolation While in E-0, the BOP should recognize that 31 Safety Injection Pump BOP fails to auto start. The operator manually starts 31 SI Pump IAW 3-R0-

1. (Step 2)

Critical E - A; Isolate the faulted SG before transition out of E-2.

Task (CT}

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: _1__ Event No.: _7_ _ Page _JL_ of _..11 Event

Description:

31 Safety Injection Pump fails to auto start 11111e Position Applicant's Actions or Behavior (CRS)

While in E-0, the BOP should recognize that 31 Safety Injection Pump (BOP) fails to auto start.

The operator manually starts 31 SI Pump IAW 3-R0-1.

Step 2 - Verify SI pumps - Running

• Three HHSI pumps (only 2)

• Two RHR pumps RNO- Manually START pumps

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 1

~----

Event No.: -~~

8 Page _JL of _1_1_

Event

Description:

Rupture on #31 SG Booth Instructor At E-2 transition, insert SGTR malfunction on #31 SG. NOTE: Crew should see Rad Monitor R62A rising. Subcooling should drop significantly as well (109°F to 58°F). If crew doesn't recognize the rising trend on R-62A and they have contacted HP to perform contact radiation readinqs, then inform them that 31 SG is ruptured.

Time Position Applicant's Actions or Behavior

1. Crew transitions to E-2; Faulted Steam Generator Isolation (ALL)

2. Main Steam Line Isolation Check

a. MSIVs and Bypasses closed

3. Identify faulted SG - #31 (Stuck Open Safety or Safeties - 2)

4. Isolate Faulted SG - #31 (Stuck Open Safety)

5. Check Secondary Radiation?

a. R-15

b. R-19

c. R-62A-D

i. GO To 3-E-3, Steam Generator Tube Rupture

d. Check SG levels -STABLE

i. If level in any SG is increasing in an uncontrolled manner, then GO To 3-E-3, Steam Generator Tube Rupture

6. GO To 3-E-3, Steam Generator Tube Rupture Critical E - A; Isolate the faulted SG before transition out of E-2.

Task (CT)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: _1_____ Event No.: 8 cont Page _jQ_ of _1_1_

Event

Description:

Rupture on #31 SG Time Position Applicant's Actions or Behavior

1. Determine if RCPs should be stopped.

(ALL) 2. Identify Ruptured SG

3. Isolate Flow from Ruptured SG

4. Check Ruptured SG Level

a. Caution - If any Ruptured SG is Faulted, Feed Flow to the SG should remain isolated during subsequent recovery actions unless needed for RCS cooldowm.

5. Check Ruptured SG Pressure - Greater than 400 psig

a. If pressure less than 400#, Go to 3-ECA-3.1, SGTR with Loss of Reactor Coolant- Subcooled Recovery Desired.

6. Go to 3-ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired.

7. OR

8. Step 16 - Check Ruptured SG Pressure - Stable or Increasing?

a. If ruptured SG pressure can NOT be maintained at least 250 psi above the pressure of the intact SG used for cooldown, Then GO to 3-ECA-3.1, SGTR with Loss of Reactor Coolant

- Subcooled Recovery Desired.

9. Transition to ECA-3.1 at Step 5 OR Step 16 depending on plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: _1__ Event No.: 8 cont Page _1_1_ of_11 _

Event

Description:

Rupture on #31 SG I Time Position Applicant's Actions or Behavior CRS 1. Direct actions of ECA-3.1, SGTR w I Loss of Reactor Coolant -

Subcooled Recovery Desired:

a. Initiate Attachment 1, Plant Equipment Status Evaluation

b. Commence CID to CSD ATC 1. Place Pressurizer Modulating Heaters to TPO

2. Place Pressurizer backup Heaters to OFF

3. Start all Charging pumps and establish maximum charging flow

4. Establish plant C/D to CSD at less than 100°F I hr using Atmospherics

1. Stop RHR pumps and place in Auto BOP

2. Perform Attachment 1, Plant Equipment Status Evaluation Critical ECA-3.1 - - B; Cool down the RCS to cold shutdown conditions at Task the highest achievable rate but less than 100°F per hour in all RCS (CT) cold legs.

Terminate scenario when RCS CID established

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: 2 Op-Test No.:

Examiners: Operators:

Initial Conditions: 100% Reactor Power. Fuel is Conditioned.

Turnover: Unit in a 7 day Technical S12ecification due to RWST Level Instrumentation. Tech S12ec LCO 3.5.4.B in effect (7-day). LIC-921 and LC-923 are ino12erable, maintenance is waiting for 12arts to re12air. Parts delivery ex12ected tomorrow. #32 Charging Pum12 is out of service, tagged due to a gacking leak (maintenance has 12um12 disassembled).

Event Malt. No. Event Event No. Type* Description 1 C (ATC) The in service #31 Charging Pump trips.

TRM/TS TRM 3.1.C.1 action A and TRM 3.7.B.3 (CRS) 2 C (ALL) Loss of RWST Level. Fork lift truck crashes into RWST resulting in level lowering to about 11 feet TS over 40 minutes.

(CRS) 3 R (ATC) Tech Spec Required Shutdown due to inoperable RWST (volume). Team commences shutdown.

R (CRS) (Call as Operations Manager if necessary to start N (BOP) shutdown) 4 C (ALL) # 32 RCP Seal Malfunction, high vibrations and #1 Seal deqradation.

5 C (ALL) #32 RCP Seal leak rises to > 6 aom.

6 C (ATC) Automatic & Manual Turbine Trip fails.

7 M (ALL) Hot Leq SBLOCA approx. 800 qpm develops.

8 C (BOP) 31 RHR Pump fails to start.

9 Team transitions to E-1, then ES-1.3, then ECA-1.1 due to loss of Emerqencv Coolant Recirculation.

• (N)ormal, (R)eactivitv, ( l)nstrument, (C)omponent, (M)ajor

Simulator Exam Scenario # 2 Summary The evaluation begins with the plant at 100% power. Fuel is conditioned. 32 Charging Pump is out of service, tagged due to a packing leak (maintenance has pump disassembled). The Unit is in a 7 day Technical Specification action statement due to RWST Level Instrumentation.

Tech Spec LCO 3.5.4.B is in effect (7-day), LIC-921 and LC-923 are inoperable, maintenance is waiting for parts to repair. Parts delivery is expected tomorrow.

After taking the watch, #31 Charging Pump will trip. The crew will take actions in accordance with AOP-AOP-CVCS-1. The ATC operator will start # 33 Charging Pump.

A fork lift truck crashes into the RWST resulting in level lowering to about 11 feet over 40 minutes. RWST Low Level Alarm annunciates at 36"2", Operators respond to the alarm response procedure ARP-012 and dispatch an operator. Field observation is a large hole (split open weld) in the RWST at approximately 12 feet from the bottom of the tank (1/3 of the way up). Water is gushing from the tank. The crew will perform actions of the ARP for RWST Lo Level and determine that a TS required shutdown must commence.

Once the appropriate technical specification has been identified by the CRS and a load reduction has commenced (3-5% power reduction), a 32 RCP Number 1 Seal malfunction will occur. The operators will observe 32 RCP #1 Seal Return flow> 5 gpm but < 6 gpm. The crew will also observe slowly rising 32 RCP vibration as well. Operators will respond in accordance with ARP-009, ARP-013, and AOP-RCP-1.

Following the crew's initial implementation of AOP-RCP-1, the seal degradation will continue, causing leakage > 6 gpm and shaft vibrations rising as well > 15 mils at > 1mil/hr (both IAAT conditions for a reactor trip). The operator will trip the reactor, stop 32 RCP and initiate E-0.

Concurrently, the operator will perform immediate actions of E-0 and also manually close the affected RCP Seal Return Valve (261 B). While performing the immediate actions of E-0, the operator will recognize the failure of the turbine to trip automatically or manually. The operator will initiate MSIV closure.

The failure of the turbine to trip and the resultant cooldown will cause an AUTO SI. #31 RHR Pump will fail to auto start, the BOP operator will start 31 RHR Pump per R0-1. During the immediate actions, a Hot Leg SBLOCA will occur (approx. 800 gpm).

The RWST level will continue to lower. The crew will determine that the RCS is not intact and transition to E-1, Loss of Reactor or Secondary Coolant. When RWST level lowers to 11.5 feet a transition to ES-1.3, Transfer to Cold Leg Recirculation will occur. The containment sump level will be inadequate for recirculation requiring a transition to ECA-1.1, Loss of Emergency Coolant Recirculation.

The crew will make up to the RWST and minimize outflow before the end of the scenario.

Procedure flow path: AOP-CVCS-1,ARP-012, POP-2.1,AOP-RCP-1, E-0, E-1, ES-1.3, ECA-1.1.

Scenario# 2 On At Time Action Description Event Insert malfunction MAL-RHROOIA to 00:00:00 None RHR PUMP 31 FAILURES FAILURE TO AUTOSTART Insert malfunction MAL-CVC005A on 00:00:00 None CHARGING PUMP 31 TRIP event 1 Insert malfunction MAL-RCS007B to 00:00:00 None RCP 32 VIBRATION 9.00000 in 600 on event 4 Insert malfunction MAL-RCSOI2B to RCP 32 NUMBER I SEAL 00:00:00 None 1.30000 in 30 on event 4 FAILURE Insert malfunction MAL-RCS007B to 00:00:00 None RCP 32 VIBRATION 20.10000 on event 5 Insert malfunction MAL-RCS012B to RCP 32 NUMBER I SEAL 00:00:00 None 100.00000 on event 5 FAILURE Insert malfunction MAL-SIS009 to RWST WATER LEAK 00:00:00 None I 0000.00000 on event 1 (HOLE IN TANK)

TURBINE PROTECTION 00:00:00 None Insert malfunction MAL-TUR002A TRIP FAILURE (ELECTRICAL)

TURBINE PROTECTION 00:00:00 None Insert malfunction MAL-TUR002B TRIP FAILURE (MECHANICAL)

Insert malfunction MAL-RCS005F to RCS LEAK (LOOP 2 HOT 00:00:00 None 50.00000 on event 29 LEG)

Create Event 29 jpplp4(1 )==I -desc Set 00:00:00 None Event 29 to actuate after Reactor Trip 297 BLENDER TO None 3 Insert remote LOA-CVC023 to 0 CHARGING PUMP HEADER ISO 350 BLENDER TO RWST None 3 Insert remote LOA-CVCOI6 to 1.00000 ISO Insert remote LOA-RHR005 to NONE LOA TO None 4 ENERGIZE DEENERGIZE V882 None 5 set rrhh8 82=0 Locally Close 882 in manual

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 1 Page _1_ of _1_1_

---

-~~

Event

Description:

1. 31 Charging Pumps Trips. Crew responds IAW 3-AOP-CVCS-1 Time Position Applicant's Actions or Behavior Booth Instructor Start RWST Leak Malfunction, 10,000 gpm leak, 1'/min.

When directed, initiate 31 Charging Pump trip malfunction.

ATC RO recognizes the trip of #31 Charging Pump. Recommends to CRS to enter 3-AOP-CVCS-1. RO performs step 4.2, using RNO starts another (32 or 33) Charging Pump OR RO performs steps 4.2 through 4.20, starts another (32 or 33) Charging Pump and restores letdown to service IAW (step 4.14) Attachment 1, Charging and Letdown Restoration (Page 45).

CRS identifies and enters Technical Requirements Manual (TRM):

TRM 3.1.C.1 action A and TRM 3.7.B.3 CRS Implement 3-AOP-CVCS-1 CRS CRS identifies and enters Technical Requirements Manual (TRM):

TRM 3.1.C.1 action A and TRM 3.7.B.3 Booth Instructor NOTE: Evaluator may more on to the next event once the CRS identifies and enters the TRM actions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: ~~-

2 Event No.: -~~

2 Page _L of _1_1_

Event

Description:

Loss of RWST Level. Fork lift truck crashes into RWST Time Position Applicant's Actions or Behavior Booth Instructor When operators respond to the RWST Low Level Alarm at 36.2" and dispatch an NPO, then after 3 minutes respond from the field:

Field observation is a large hole (split open weld) in the RWST at approximately 12 feet from bottom of tank. (113 of the way up). Water is gushing from the tank. Appears that a fork lift truck has crashed into the RWST.

ALL Diagnose Lowering RWST Level RWST Low Level Alarm annunciates at 36'2", Operators respond to the alarm response procedure 3-ARP-012 (Panel SJF - page 12 of 62).

• Perform ARP for alarm panel SJF REFUELING WATER BOP STORAGE TANK LO LEVEL

• Direct watch personnel to check the following:

o Check piping for breaks Booth Instructor Call as Operations Manager if necessary to start shutdown.

CRS Tech Spec Required Shutdown due to inoperable RWST (volume).

Team commences shutdown.

Evaluate TS 3.5.4 o Determine RWST is not operable o Determine Condition C applies and unlikely to restore operability within one hour o Determine Condition D applies and plant shutdown to mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> required.

Booth Instructor Scenario may continue after CRS completes Technical Specification determination.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 3 Page_]__ of _1_1_

Event

Description:

Tech SQec Reguired Shutown due to inoQerable RWST (volume}.

Time Position Applicant's Actions or Behavior CRS Implement POP-2.1 Attachment 3, Reactor Power Reduction Checklist

• Develop reactivity plan to place unit in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• Direct shutdown activities during TS required shutdown

• Initiate notifications

• Perform pre-job brief ATC Borate the RCS at rate determined by reactivity plan

• Energize all pressurizer heaters

• Monitor TAVE and TREF

• Monitor Delta-Flux and ensure control rods insert when required to maintain TAVE on program and Delta-flux within target band BOP Initiate generator load reduction at rate directed by CRS.

Booth Instructor NOTE: Scenario may move to the next event after an approximate 3-5% power reduction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 4 Page__.!._ of _ll_

Event

Description:

1. 32 RCP Seal Malfunction, high vibrations and #1 Seal degradation within 3-AOP-RCP-1 monitoring actions. Crew res12onds IAW 3-AOP-RCP-1 Time Position Applicant's Actions or Behavior Booth Instructor Instructor:

RCP32 Insert malfunction MAL-RCS012B to 0.90000 in 30 NUMBER 1 on event 3 SEAL FAILURE RCP No. 1 Seal Return High Flow (Common) alarm Show rising shaft vibration as well - slow ramp to 14 mils (SKF alarm at 14.8 mils shaft, 3.3 mils frame)

ATC Diagnose increased seal return flow 32 RCP 0 Observe 32 RCP #1 Seal Return flow> 5 gpm but< 6 gpm.

0 Observe rising shaft vibration as well?

BOP Perform ARPs for associated Alarms:

• ARP-013, REACTOR COOLANT PUMP HIGH VIBRATIONS?

• ARP-009, RCP No, 1 SEAL RETURN HIGH LOW FLOW 0 Observe 32 RCP is affected.

CRS Supervise activities of the crew during response to high seal return flow 0 Enter AOP-RCP-1 0 Determine immediate reactor trip is not required 0 Perform seal section of AOP 0 Review I perform shaft vibration section as well?

0 Ensure notifications are made 0 Steps 4.17, 4.18, 4.19, 4.39-4.43 (Seal Leak) 0 Steps 4.17, 4.113-?

Booth Instructor NOTE: Once AOP is entered and progress through seal section is made, evaluator may move to the next event.

We want the leak to then be on a timer to progress to /AA T numbers for both shaft vibration & seal leakage.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 5 Page_§_ of 11 Event

Description:

1. 32 RCP Seal leak rises to above the AOP IAAT condition, reguiring manual triQ of the RCP IAW 3-AOP-RCP-1 and initiation of E-0; Reactor TriQ or Safety lniection.

Time Position Applicant's Actions or Behavior Booth Instructor Timer for Seal degradation continues to rise, causing leakage > 6 gpm and sha'ft vibration rising as well> 15 mils at >1 mil/hr. (IAAT conditions)

ATC 1. Re-enter AOP-RCP for increased seal leakage & shaft vibration

2. Trip the Reactor CRS 3. Stop 32 RCP

4. INITIATE E-0

5. Steps 4.6 & 4.7- no action required (seal inlet temperature<

225°F

6. GO TO Step 4.12

7. IAAT affected RCP has stopped rotating, then manually close affected RCP Seal Return Valve (261 B)

Booth Instructor NOTE: Scenario moves to next event triggered by the previously inserted auto turbine trip malfunction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 6 Page_§___ of 11 Event

Description:

Automatic & Manual Turbine TriQ fails, reguiring MSIV Closure.

Time Position Applicant's Actions or Behavior CRS Supervise the actions of the crew during E-0, Reactor Trip or Safety Injection 0 Direct the BOP to perform R0-1 0 Concurrently supervise completion of required actions in AOP-RCP-1 0 Close seal return valve 261 B when pump stops rotating

• Loop flow for affected RCP stabilized at approximately 20-30%

ATC Verify reactor is tripped Verify turbine is tripped - NO 0 Manually TRIP turbine - NO 0 Close MSIVs Verify 480V bus status Check SI status 0 Concurrently complete required actions in AOP-RCP-1 0 Close seal return valve 261 B when pump stops rotating

• Loop flow for affected RCP stabilized at approximately 20-30%

Booth Instructor NOTE: Scenario will continue as a Hot Leg SBLOCA (approx. 800 gpm) is inserted. Evaluator may want to ensure seal return valve is also closed per the AOP first.

Insert Hot Leg SBLOCA (approx. 800 gpm) as directed by lead evaluator or coincident with reactor trip.

NOTE: If turbine doesn't trip, they will coo/down enough to cause AUTO SI. They will need to initiate MSIV closure. SI causes loss of stop valve indications to verify turbine trip, they will have to use 1st stage pressure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 7 Page _L_ of 11 Event

Description:

After manual turbine triQ is initiated, a 800 gQm Hot Leg SBLOCA is initiated, resulting in eventual low Qressure SI actuation. {AUTO or Manual}

Time Position Applicant's Actions or Behavior Booth Instructor Depending on the ramped in SBLOCA, they may transition to 3-ES-0.1, Reactor Trip Response.

Would prefer to have RCS pressure dropping rapidly enough that they initiate 51 manually during read through of immediate actions?

CRS Supervise the actions of the crew during E-0, Reactor Trip or Safety Injection 0 Direct the BOP to perform R0-1 ATC Verify reactor is tripped BOP Verify turbine is tripped Verify 480V bus status Check 51 status?

BOP Perform R0-1, BOP Actions During Use of EOPs CRS Verify FW isolation - manually closes all SGBD isolation valves ATC Verify SI flow Verify CS Check RCP seal cooling Check Tavg stable Check if RCPs should be stopped 0 Check subcooling and SI pumps 0 Stop all RCPs WOG CT: E C Critical Task Trip all RCPs before completion of E-1, step 1?

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 7 cont Page _§__ of ...1L Event

Description:

After manual turbine triQ is initiated, a 800 gQm Hot Leg SBLOCA is initiated, resulting in eventual low Qressure SI actuation. {AUTO or Manual}

Time Position Applicant's Actions or Behavior CRS Check PORVs, safeties and spray valves closed ATC Check if SGs are faulted Check if SG tubes are intact Check if RCS is intact Go to E-1 Booth Instructor NOTE: Event 8 is a failure of 31 RHR Pump to auto start, BOP operator starts 31 RHR pump per 3-R0-1. Scenario continues as transition to E-1 occurs and RWST level continues to lower to 11.5'.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 8 Page _JL_ of 11 Event

Description:

31 RHR Pump fails to start, BOP operator starts 31 RHR pump per 3-RO-1.

Time Position Applicant's Actions or Behavior (BOP) 31 RHR Pump fails to start, BOP operator starts 31 RHR pump per 3-R0-1 Booth Instructor NOTE: Event 8 is a failure of 31 RHR Pump to auto start, BOP operator starts 31 RHR pump per 3-R0-1. Scenario continues as transition to E-1 occurs and RWST level continues to lower to 11.5'.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 9 Page _1.Q__ of _1_1_

Event

Description:

Team transitions to E-1 1 then ES-1.3, then ECA-1.1 due to loss of Emergenc~ Coolant Recirculation.

Time Position Applicant's Actions or Behavior CRS Supervise actions of the crew during execution of E-1 When RWST level is 11.5 feet a transition to ES-1.3 is reauired.

ATC Perform E-1 Actions CRS 0 Check RCPs BOP 0 Check for faulted SG 0 Check intact SG levels 0 Check SI reset 0 Reset Phase A 0 Check for ruptured SG 0 Check PORVs and block valves ALL Transition to ES-1.3 0 Determine if transfer to cold leg recirc is required 0 Evaluate if recirculation flow from containment can be established (per the ES-1 .3 foldout page) 0 Judge VC level is inadequate to support recirculation flow and go to ECA-1.1, Loss of Emergency Coolant Recirculation CRS Supervise the activities of the crew during ECA-1.1 CRS Verify recirc trains not affected by sump blockage ATC Check emergency coolant recirculation equipment available Verify FCUs Status Check RWST level greater than 1.5 feet Determine CS requirements Makeup to RWST Critical Task WOG CT: ECA-1.1 -- B Make up to the RWST and minimize outflow before the end of the scenario.

Booth Instructor (Instructor - potential for scenario to end here (two critical tasks completed).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 2 Event No.: 9 cont Page _1_1_ of -11 Event

Description:

Team transitions to E-1, then ES-1.3, then ECA-1.1 due to loss of Emergency Coolant Recirculation.

Time Position Applicant's Actions or Behavior WOG CT: ECA-1.1--C Establish makeup flow from charging pumps at a rate equal to Critical Task VCT makeup capability when required per ECA-1.1 before Core Cooling orange path develops.

ATC Depressurize intact SGs WOG CT: ECA-1.1--D Depressurize intact SGs at a maximum rate to inject the contents of the accumulators before a core cooling orange path develops.

Critical Task CRS, When RWST level reaches 1.5 feet, stop pumps taking suction from ATC RWST and place in pullout:

BOP 0 RHR pumps, HHSI pumps, Charging pumps, Containment Spray pumps WOG CT: ECA-1.1 -- A Stop ECCS pumps with suction aligned to the RWST before RWST decreases to < 1.5 ft.

Critical Task Booth Instructor NOTE: Terminate scenario at the discretion of the lead evaluator.

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: 3 Op-Test No.:

Examiners: Operators:

Initial Conditions: 100% Power,# 31 Com12onent Cooling Water Pum12 is out of service for Maintenance (Motor re12lacement)

Turnover: 100% Power,# 31 Com12onent Cooling Water Pum12 is out of service for Maintenance (Motor re12lacement) . Maintain 100%

Event Malf. No. Event Event No. Type* Description 1 c #33 Condensate Pump Trips, crew responds IAW BOP/CRS 3-AOP-FW-1.

R (ATC) Technical Specification for delta I (discuss at minimum after scenario)

TS (CRS) 2 I (ATC or 32 SG Controlling level channel fails low (LT427B).

BOP)

TS (CRS) 3 M(ALL) Steam Leak in Turbine Buildinq.

4 C/M (ALL) The reactor will not trip from the control room and the crew responds per FR-S-1, ATWS 5 C (BOP) Following SI actuation, #32 RHR Pump and #33 SI did not start. BOP starts pumps per 3-R0-1 RNO.

6 M (ALL) Failure of MSIVs to close from Control Room. (2 will be closed locally after AFW is throttled to 100 qpm per ECA-2.1 ).

• (N)ormal, (R)eactivitv, (l)nstrument, (C)omponent, (M)aior

Simulator Exam Scenario # 3 Summary The evaluation begins with the plant at 100% power. Fuel is conditioned. 32 Component Cooling Water Pump is out of service for Maintenance (Motor replacement).

After taking the watch, #33 Condensate Pump will trip. The crew will take actions in accordance with AOP-AOP-FW-1. Operators will initiate a load reduction as necessary to maintain FW Flow

> STM Flow and SGFP Suction pressure> 265#.

Once the plant is stable, 32 Steam Generator controlling level channel fails low (L T-427B). The crew responds IAW AOP-INST-1 to again stabilize the plant and trip bistables.

Following the tripping of bistables for the SG level channel failure, a steam break will occur in the Turbine Building. The crew will attempt to manually trip the plant, close MSIVs, and perform actions of E-0, Reactor Trip or Safety Injection.

The reactor will not trip from the Control Room and the team will respond per FR-S.1, Response to Nuclear Power Generation I ATWS and will S/D the reactor by manually inserting control rods and initiating Emergency Boration. The reactor trip breakers will be locally opened and the team will transition to E-0, Reactor Trip or Safety Injection. Following SI actuation, 32 RHR Pump and 33 SI pump do not auto start. BOP starts pumps per R0-1 RNO.

The MSIVs will fail to auto close and cannot be closed from the control room. The team will take actions per ECA-2.1, Uncontrolled Depressurization of All Steam Generators. When at least one MSIV is closed locally, the team will transition to E-2, Faulted Steam Generator Isolation. The team will complete E-2 and transition to E-1, Loss of Reactor or Secondary Coolant.

Procedure flow path: AOP-FW-1, AOP-INST-1, AOP-UC-1, E-0, FR-S.1, E-0, E-2, ECA-2.1, E-2, E-1.

Scenario# 3 On At Time Action Description Event CONDENSATE PUMP 33 Insert malfunction MAL-CFW005C to 0 00:00:00 None TRIP DUE TO BRG on event 1 FAILURE STEAM GENERA TOR Insert malfunction MAL-SGNOOlF to 0 00:00:00 None LEVEL TRANSMITTER on event 2 FAILURE (LT-427B)

Insert malfunction MAL-RHROOlB to 00:00:00 None RHR PUMP 32 FAILURES FAILURE TO AUTOSTART Insert malfunction MAL-SIS004C to SAFETY INJECTION PUMP 00:00:00 None FAILURE TO AUTOSTART 33 FAILURES REACTOR TRIP BREAKERS Insert malfunction MAL-RPS002A to 00:00:00 None FAIL TO OPEN (AUTO ALL FAIL FAILURE)

REACTOR TRIP BREAKERS 00:00:00 None Insert malfunction MAL-RPS002B FAIL TO OPEN (AUTO &

MANUAL)

Insert malfunction MAL-MSS009A to MAIN STEAM HEADER 00:00:00 None 1000000.43750 in 300 on event 3 BREAK (EAST HEADER)

Insert malfunction MAL-MSS013A to MAIN STEAM ISOLATION 00:00:00 None FAIL OPEN on event 3 VAL VE FAILURES LOOP 1 Insert malfunction MAL-MSS013B to MAIN STEAM ISOLATION 00:00:00 None

. FAIL OPEN on event 3 VAL VE FAILURES LOOP 2 Insert malfunction MAL-MSS013C to MAIN STEAM ISOLATION 00:00:00 None FAIL OPEN on event 3 VALVE FAILURES LOOP 3 Insert malfunction MAL-MSS013D to MAIN STEAM ISOLATION 00:00:00 None FAIL OPEN on event 3 VALVE FAILURES LOOP 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - Event No.: - - 1 - Page _1_ of _...1Q_

Event

Description:

1. 33 Condensate Pump trips, crew responds IAW 3-AOP-FW-1.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL-CFW005C to 0 on event 1; 33 Condensate Pump Trip due to bearing failure.

ATC RO responds IAW 3-AOP-FW-1, step 4.39.

1. INITIATE load reduction as necessary to maintain the following:

a. Feed flow~ steam flow

b. MBFP suction pressure > 265 psig.

2. IAAT MBFP suction pressure cutback actuates, THEN perform steps 4.42-4.43 if directed by CRS

a. Take manual control of MBFP speed to maintain suction pressure> 265 psig.

3. IAAT Loss of Load Interlock is NOT reset, THEN reset Loss of Load Interlock for Condenser Steam Dumps.

NOTE: Per Attachment 1 of procedure, load reduction to approximately 900 MW(e) should be necessary. Load will be limited by MBFP suction pressure. Per 3-SOP-FW-001, the suction pressure lower limit is 350 psig during normal operation. At 310 psig, the Standby Condensate Booster Pumps will automatically start (if in AUTO) and CD-AOV-521 (POLISHER VESSELS AND POST FILTERS BYPASS) automatically opens. An automatic low suction pressure cutback actuates at 265 psig to lower MBFP speed.

4. IAAT level in any SG is> 60%, THEN perform one of the following:

a. Place MFRV for affected SGs in manual and reduce feed flow below steam flow.

b. Place MBFP speed control in manual and reduce feed flow below steam flow.

5. Adjust Tave within 1.5°F of program using boration and /or rod insertion.

6. Is ~ Flux in target band?

a. Borate RCS as necessary to restore~ Flux to target band.

CRS Refer to TS 3.2.3, Axial Flux Difference -AFD)

This discussion can occur after the scenario, especially if AFD stays in band durinq load reduction.

Booth Instructor NOTE: Evaluator may more on to the next event once the CRS identifies the Technical Specification for AFD or evaluator discretion.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - Event No.: - 2 -- Page _2_ of _1Q_

Event

Description:

32 SG Controlling level channel fails low. Team responds per AOP-INST-1 to stabilize the plant and trip bistables.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL- STEAM GENERA TOR LEVEL SGN001F to 0 on event 2 TRANSMITTER FAILURE (LT-4278)

• SG Low Level Alarms

• Channel 427 indicates downscale

• 32 SG Feedwater flow increase

• Actual level increases ATC 1. Diagnose SG level instrument failure

2. Take manual actions as necessary to control parameters and stabilize the plant.

a. Place 32 SG FRV in Manual and match 32 SG feed and steam flows.

b. Control 32 SG FRV position to maintain 32 SG level on program.

CRS Direct the team during performance of AOP-INST-1

• Directs RO to perform immediate actions and verifies completion of the immediate actions using the procedure

• Supervise actions of the team during subsequent actions.

• Reviews Technical Specifications:

o TS Table 3.3.1-1 Function 13 o TS Table 3.3.2-1 Function 5.b o TS Table 3.3.2-1 Function 6.b o TRM Table 3.3D-1 Function TRO 3.3.D.8 o Determines bistables require tripping within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• Directs BOP to trip bistables.

BOP 1. Are ill! redundant bistable status lights for failed instrument listed in Attachment 1 (Steam Generator Level Tables) Table 1 (Page 79) extinguished?

a. E-8; SG 32 LO-LO LVL LC427D

b. H-8; SG 32 LO-LO LVL LC427B

c. 1-4; SG 32 HI LEVEL LC427C

d. L-4; SG 32 HI LEVEL LC427 A

2. Trip bistables for failed instrument listed in Attachment 1 (Staeam Generator Level Tables) Table 2 (Page 83). Protection Rack Blue B-2)

a. Loop 2B, High Level

b. Loop 2B, Low Level

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: _3__ Event No.: 2 cont Page i _ of _..1Q__

Event

Description:

32 SG Controlling level channel fails low. Team responds per AOP-INST-1 to stabilize the plant and trip bistables.

Time Position Applicant's Actions or Behavior BOP 3. Are all bistable status lights for failed instrument listed in Attachment 1 (Steam Generator Level tables) Table 3 (Page 87) illuminated?

a. G-8; SG 32 LO-LO LVL LC427F

b. K-4; SG 32 HI LEVEL LC427E Booth Instructor Scenario may continue after CRS completes Technical Specification determination.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 3 Event No.: 3 Page __.+/-_ of _.1Q_

Event

Description:

Steam Header Leak in Turbine Building. Team diagnoses steam leak and initiates reactor tri[2 Qer AOP-UC-1, Uncontrolled Cooldown.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL-MSS009A to MAIN STEAM HEADER 1000000.43750 in 300 on event 2 BREAK (EAST HEADER)

Crew should see rising reactor power, loss of 10-30 MWe load, small Tave reduction. Fire alarms will sound indicating issue in Turbine Building.

If necessary call as NPO and state a large steam leak exists in the turbine building.

ALL Diagnose steam leak.

CRS 1. Implement AOP-UC-1; Uncontrolled Cooldown.

• Determine continued operation is unsafe

• Perform a crew update

2. Direct RO/BOP to trip reactor and close MSIVs ATC 1. Manually actuate reactor trip

• Diagnose reactor did not trip

• Attempt to trip reactor from supervisory panel CRS Direct team to perform immediate actions of E-0, Reactor Trip or Safety Injection.

ATC Attempt to initiate reactor trip

• Diagnose reactor is not tripped

• Manually trip the reactor

• Observe both reactor trip breakers are closed

• Dispatch NPO to trip reactor using posted operator aid

• Observe reactor power greater than 5%

Inform crew that entry into FR-S.1 is required.

CRS Direct team to perform 3-FR-S.1; Response to Nuclear Power Generation I A TWS.

Booth Instructor Scenario continues based on A TWS. Do not locally trip the reactor until A TC inserts control rods manually and the crew is implementing 3-FR-S. 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 3 Event No.: 4 Page__§_ of 10 Event

Description:

The reactor will not tri12 from the control room and the crew res12onds 12er FR-S-1, ATWS.

Time Position Applicant's Actions or Behavior Booth Instructor Entered in setup:

Insert malfunction MAL- REACTOR TRIP BREAKERS FAIL RPS002A to ALL FAIL TO OPEN (AUTO FAILURE)

Insert malfunction MAL- REACTOR TRIP BREAKERS FAIL RPS002B TO OPEN (AUTO & MANUAL)

CRS Direct actions of the crew IAW 3-FR-S.1.

ATC Manually insert control rods.

Booth Instructor Trip the reactor trip breakers locally once the A TC has established manual control rod insertion /AW 3-FR-S.1 and NPO has been disoatched.

BOP 1. Dispatch NPO to locally trip the reactor.

2. Manually TRIP Turbine.

3. Establish greater than 686 gpm total AFW flow.

4. Initiate Emergency Boration of RCS

a. Check a charging pump running

b. Open MOV-333, Emergency Boration valve

c. Close BAST recirc control valves

i. HCV-104 ii. HCV-105 ATC/ 5. Start both boric acid pumps in high speed:

a. PLACE switches in FAST BOP

b. RESTART pumps

6. Transfer operating Charging pump to manual control and increase speed to maximum.

7. Check Pressurizer Pressure < 2235 psig.

Critical FR.S-1-C; Insert negative reactivity into the core by inserting Task rods and I or emergency boration.

(CT)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: ---'3;;....__ Event No.: 4 cont Page__§__ of 1O Event

Description:

The reactor will not trip from the control room and the crew responds per FR-S-1 ATWS.

I Time Position Applicant's Actions or Behavior CRS Continue with FR-S.1 actions:

o Verify Containment ventilation isolation ATC o Check SI status BOP o Check is reactor is subcritical

• Power Range < 5%

• Intermediate Range - zero or negative SUR

• All control rods < 20 steps o Secure Emergency Boration

• Close CH-MOV-333

• Place both BATPs in Slow

• Open HCV-104 and 105 to 25% open o Verify RCP seal cooling established o Control Charging pump speed to maintain seal injection o Verify adequate SID margin

• All control rods < 20 steps

• Direct watch chemist to sample RCS

• Adjust RCS M/U to establish > CSD boron per graph RCS-4 Transition to E-0 Booth Instructor Event continues based on earlier failures included in simulator scenario setup (following SI actuation, #32 RHR Pump and #33 SI Pump did not start.) (MS/Vs failed to close as well).

BOP may start the 32 RHR and 33 SI Pumps during the implementation of FR-S.1, step 6; CHECK SI-ACTUATED by performing step 35 of 3-E-O.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - - 3 - Event No.: - 5 -- Page _J_ of 10 Event

Description:

Following SI actuation, #32 RHR Pump and #33 SI did not start. BOP starts pumps per 3-R0-1 RNO.

Time Position Applicant's Actions or Behavior Booth Instructor Inserted during initial simulator setup:

MAL-RHR001B to FAILURE TO AUTOSTART MAL-S!S004C to FAILURE_ TO_AUTOSTART BOP may start the 32 RHR and 33 SI Pumps during the implementation of FR-S.1, step 6; CHECK SI - ACTUATED by performing step 35 of 3-E-O.

OR BOP may start the pumps during the implementation of 3-R0-1 RNO.

CRS BOP will recognize that 32 RHR Pump and 33 SI Pumps have not BOP started in Auto following the SI actuation.

VERIFY SI Pumps - RUNNING

• Three HHSI pumps

• Two RHR pumps RNO

• Manually START pump(s).

Booth Instructor Event continues based on earlier failures included in simulator scenario setup (MS/Vs fail to close).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 3 Event No.: 6 Page~of JQ_

Event

Description:

Failure of MSIVs to close from Control Room. (2 will be closed locally after AFW is throttled to 100 g12m 12er ECA-2.1}

Time Position Applicant's Actions or Behavior Booth Instructor Entered when Event 3 was actuated or during initial simulator setup:

MAL-MSS013A to FAIL OPEN on event 3 MAL-MSS013B to FAIL_ OPEN on event 3 MAL-MSS013C to FAIL OPEN on event 3 MAL-MSS013D to FAIL OPEN on event 3 CRS Supervise the actions of the crew during E-0 CRS Perform E-0 subsequent actions ATC

• Try to stop the RCS Cooldown

• Attempt to close MSIVs

• Dispatch NPOs to locally close MSIVs and bypass valves

• Diagnose all SGs are faulted .

• Go to 3-E-2, Faulted Steam Generator Isolation Booth Instructor Event continues based on transition to 3-E-2, Faulted Steam Generator Isolation. (Step 15 of 3-E-O, Reactor Trip or Safety Injection)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 3 Event No.: 6 cont Pagel of _jQ Event

Description:

Failure of MSIVs to close from Control Room. (2 will be closed locally:

after AFW is throttled to 100 g12m 12er ECA-2.1)

Time Position Applicant's Actions or Behavior CRS Supervise the actions of the crew during E-2 ATC Diagnose all SGs are faulted

• Checks MSIVs cannot be closed from the CCR

• Diagnose none of the SGs are intact CRS Transition to ECA-2.1 ALL Check secondary pressure boundary:

• MS IVs

• MSIV bypass valves

• Main Feed Reg valves

• Bypass FRVs

• MS-41 and 42

• SG atmospheric steam dumps

• SG blowdown isolation valves

• SG sample valves

• Steam traps ALL Control AFW Flow to minimize RCS cooldown

• Verify control rods inserted

• Check cooldown rate < 100°F I hr

• Decrease AFW flow to 100 gpm per SG Critical ECA-2.1 - A, Control AFW flow to not less than 100 gpm per SG to Task minimize RCS cooldown rate before a severe (orange path)

(CT) challenge develops to the integrity CSF.

Booth Instructor After AFW flow has been reduced, close 31 and 32 MS/Vs locally.

ALL Observe MSIVs closed

• Observe rising pressure in 31 and 32 SGs

• Transition to E-2, Faulted SG Isolation

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 3 Event No.: 6 cont Page _.1Q_ of 1.Q_

Event

Description:

Failure of MSIVs to close from Control Room. (2 will be closed locall~

after AFW is throttled to 100 g[2m [2er ECA-2.1}

Time Position Applicant's Actions or Behavior CRS Supervise the actions of the crew during E-2 CRS Check MSIVs for 31 and 32 SGs closed ATC Determine 31 and 32 SGs are intact Identify 33 and 34 SGs are faulted BOP Isolate Faulted SGs

• Dispatch NPO to close MS-42

• Isolate MFW FRVs or MOVs

• Isolate Bypass FRVs or MOVs

• Isolate AFW flow

• Verify SG Atmospherics closed

• Verify SG Slowdown valves closed

• Close SG sample valves

• Isolate upstream traps on faulted SGs

• Reestablish SG sampling:

0 Reset Phase A 0 Depress pushbuttons 17 thru 24 Critical E A, Isolate the faulted SG before transition out of E-2 Task (CT)

CRS Determine E-3 is not required CRS Go to E-1, Loss of Reactor or Secondary Coolant Booth Instructor Terminate scenario at this point or at Lead Evaluator's discretion.

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: 4 Op-Test No.:

Examiners: Operators:

Initial Conditions: 100% Power with 31 EOG out of service due to malfunctioning governor.:.

Turnover: 100% Power with 31 EOG out of service due to malfunctioning governor. Maintain 100% 12ower. 31 Charging Pum12 l/S.

Event Malf. No. Event Event No. Type* Description 1 MAL- C (BOP) 33 SWP trips SWS001C 2 MAL- C (ALL) 480V Bus 5A Fault EPS005C 3 NIA R (ATC) Tech Spec required shutdown TS (CRS) 4 MAL- C (ATS) Power Range Channel 41 Upper Detector Fails High NIS006A C (CRS)

TS (CRS) 5 MAL- M(ALL) Station Blackout EPS001 6 MAL- C (BOP) 32 EOG fail to start DSG001A 7 MAL- C (ATC) PZR PORV Fails Open (455C fails open after loss of all PRS003D AC, we need to isolate block valve later) 8 MAL- C (BOP) SW pump does not auto start after bus energized SWS001E 32 EOG comes back, 6A bus back. Failure of 36 SW pump to auto start.

• (N)ormal, (R)eactivitv, ( l)nstrument, (C)omponent, (M)ajor

Simulator Exam Scenario# 4 Summary The scenario begins with the plant at 100% power. Fuel is conditioned. 32 EOG is out of service due to a malfunctioning governor. 31 Charging Pump is in service.

After taking the watch, #33 Service Water Pump will trip. The crew will take actions in accordance with ARP-012 and start another Service Water Pump. 480V Bus 5A then faults.

Crew enters AOP-480V-1 to stabilize the plant. The CRS evaluates technical specifications following feedback from the field that there is significant damage to the 5A Bus. CRS determines that a shutdown must commence.

Once the plant shutdown is commenced, a failure of Power Range channel N41 upper detector occurs. Control rods auto insert until the ATC places rods in manual. The CRS implements AOP-Nl-1, Nuclear Instrument Failure to stabilize the plant and perform required actions.

During performance of the subsequent actions of the nuclear instrument failure procedure, a loss of grid and loss of offsite power occur. The unit trips and the cew responds per E-0. 33 EOG is the only diesel running, but the 5A bus is faulted and cannot be energized. 31 EOG is tagged and 32 EOG fails to start or tripped. Crew diagnoses that no 480V bus is energized and transitions to ECA-0.0, Loss of All AC.

PRZR PORV 455C fails open and cannot be isolated due to the loss of all AC. PORV block valve will need to be isolated when power is restored to the 6A bus with 32 EOG. Operators will be dispatched to attempt to emergency stat the 32 EOG IAW SOP-EL-1.

BOP operator manually aligns 32 ABFP to supply AFW to the SGs.

Operators implement ECA-0.0 and depressurize intact SGs to 275 psig at maximum rate. Once the SGs are depressurized at a maximum rate to less than 275 psig, then the field NPO will be able to emergency start 32 EOG and supply power to the 6A 480V Bus. However, 36 Service Water Pump will not automatically start to provide cooling for the 32 EOG. Crew manually starts the 36 SWP and manually closes the PORV block valve.

Procedure flow path: ARP-012, AOP-480V-1, POP-2.1, AOP-Nl-1, E-0, ECA-0.0,.

Scenario# 4 On At Time Action Description Event Insert malfunction MAL-SWSOOlC to SERVICE WATER PUMP 33 00:00:00 1 TRIP on event 1 FAILURES Insert malfunction MAL-EPS005C on 00:00:00 2 LOSS OF 480 V BUS 5A event2 DIG #31 MAN/OFF/AUTO 00:00:00 None Insert remote LOA-DSG03 l to OFF MODE SWITCH Insert malfunction MAL-EPSOOl on 00:00:00 5 STATION BLACKOUT event 5 Insert malfunction MAL-DSGOOlB on DIESEL 32 GENERATOR 00:00:00 5 event5 FAILURE PRESSURIZER RELIEF Insert malfunction MAL-PRS003C to 00:00:00 5 VALVE 455C VALVE 100.00000 on event 5 POSITION FAILURE Insert malfunction MAL-SWSOOIF to SERVICE WATER PUMP 36 00:00:00 None FAILURE TO AUTOSTART FAILURES Insert malfunction MAL-NIS006A to POWER RANGE CHANNEL 00:00:00 4 5.00000 on event 4 41 DETECTOR A FAILURE DIESEL 32 GENERATOR None 9 Delete malfunction MAL-DSGOOIB FAILURE None 9 Insert remote LOA-DSG029 to RESET DIG #32 TRIP RESET Insert remote LOA-DSG032 after 15 to DIG #32 MAN/OFF/AUTO None 9 MAN MODE SWITCH Insert remote LOA-DSG045 after 20 to DIG #32 MANUAL START None 9 ACTIVE LOA PUSHBUTTON

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: 1 Page _1_ of _JL_

Event

Description:

33 Service Water Pum12 TriQs. Team res12onds 12er ARP and starts a SWP.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL-SWS001C to TRIP on event 1, 33 SWP Failure BOP Diagnose trip of 33 Service Water Pump

• Perform ARP-012 for alarm "Service Water Header (31,32,33)

High Low Pressure"

• Refers to SOP-RW-5 and starts 31 Service Water Pump

• Dispatch NPO to investigate 33 SWP .

• Operator may take 33 SWP Switch to "pull to lock" to clear "480V SWGR Motor Trip" Alarm.

CRS Direct BOP operator response to service water transient.

The CRS may evaluate TS 3.7.9 Service Water System:

• The LCO is satisfied with 2 pumps and required flow path or the nonessential SWS header operable.

Booth Instructor Continue to the next event at the discretion of the Lead Evaluator.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: 2 Page_L of .JL Event

Description:

480V Bus 5A Fault.

Time Position Applicant's Actions or Behavior Booth Instructor Insert ma/function MAL-EPS005C on event 2, LOSS OF 480 V BUS 5A.

ATC Diagnose bus 5A de-energized

• Start Charging Pump due to the loss of 31 Charging Pump on the 5A bus fault.

BOP Diagnose bus 5A de-energized

• Perform ARPs

• Dispatch NPO to investigate CRS Implement 3-AOP-480V-1, Loss of 480V Bus

• Direct crew actions of AOP-480V-1 .

ATC/ Verify Charging pump running BOP Verify CCW pumps running Check SW essential and non-essential headers > 60 psig Perform ARPs Verify IRPls energized Verify condenser vacuum stable Dispatch an NPO to monitor the EDGs Booth Operator NPO reports back significant damage to the 5A bus.

CRS Evaluate Technical Specification 3.8.9 (Distribution Systems -

Operating)

• OAP-34 to determine if loss of safety function exists

• CRS determines that with a fault on 5A 480V Bus and 31 EOG tagged a shutdown must commence.

• Need to determine if TS 3.0.3 is applicable

• If not cue as operations manager to initiate a shutdown based on reports of significant damage to bus 5A and no chance of 31 EOG being returned in the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Booth Operator Proceed to next event once the CRS has determined Tech Spec applicability and initiated a shutdown. Shutdown requirement may be called in by Operation Manager if necessary.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: _3_ Page -2_ of _JL_

Event

Description:

Technical Sgecification reguired shutdown.

Time Position Applicant's Actions or Behavior CRS Refers to POP-2.1, Operation at Greater than 45% Power

• Implements Attachment 3, Reactor Power Reduction Checklist

• Perform a brief with the crew

• Directs reactivity changes

• Directs load changes ATC

• Energize all pressurizer backup heaters

• Dispatch NPO to swap boric acid transfer pumps 0 31 BA transfer pump is de-energized due to loss of bus 5A 0 Ensures 32 BA Transfer Pump aligned to blender

• Commence Boration per 3-SOP-CVCS-003, Reactor Coolant System Boron Concentration Control

• Monitor Tavg, rod position, delta flux, and RCP seal injection 0 Maintain Tavg on Program 0 Maintain ~I within target band BOP Initiate generator load reduction at rate directed by CRS Maintain SG Level on Program Coordinate load reductions with the ATC Booth Instructor Proceed to the next event when sufficient load reduction has been observed per the lead evaluator.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: 4 Page __+/-._ of l Event

Description:

Power Range Channel 41 U1212er Detector Fails High.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL-NIS006A to 5.00000 on event 4, POWER RANGE CHANNEL 41 DETECTOR A FAILURE.

ATC Diagnose failed nuclear instrument.

Place Control Rods in manual to stop auto rod insertion.

CRS Direct actions of the team during AOP-Nl-1, Nuclear Instrument Failure.

BOP Perform ARPs for alarms associated with the failed instrument.

CRS/ Adjust control rods, boron concentration, or turbine load as necessary ATC to Maintain Tavg at programmed Tref.

CRS Evaluate Technical Specifications

• TS 3.3.1 Function 2a

• TS 3.3.1 Function 2b

• TS 3.3.1 Function 5

• TS 3.3. 1 Function 17.b

• TS 3.3.1 Function 17.c

• TS 3.3.1 Function 17.d Booth Instructor Scenario continues to next event once CRS determines the applicable Technical Specifications.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - Event No.: - Page __§._of _9_

Event

Description:

Station Blackout.

Time I Position Applicant's Actions or Behavior Booth Instructor Ensure simulator initial setup included the following ma/functions:

Remote LOA-DSG031 to OFF, DIG #31 MAN/OFF/AUTO MODE SWITCH MAL-SWS001F to FAILURE_ TO_AUTOSTART, SERVICE WATER PUMP 36 FAILURES Insert the following malfunctions for event 5:

MAL-EPS001 on event 5, STATION BLACKOUT MAL-DSG001B on event 5, DIESEL 32 GENERATOR FAILURE MAL-PRS003C to 100.00000 on event 5, PRESSURIZER RELIEF VALVE 455C VALVE POSITION FAILURE CRS Direct crew to perform immediate actions of E-0, Reactor Trip or Safety Injection.

ATC Verifies reactor is tripped Verifies turbine is tripped BOP Diagnose none of the 480V buses are energized.

• Observe that the only EOG running is 33 EOG and bus 5A cannot be energized due to the fault. 31 and 32 EDGs are not running. 31 EOG is tagged. 32 EOG tripped.

• Informs CRS that transition to ECA-0.0, Loss of All AC Power is required.

CRS Transitions to ECA-0.0, Loss of All AC Power and directs crew actions during implementation of ECA-0.0.

NOTE: Crew may have directly entered ECA-0.0.

Booth Instructor Event continues based on earlier failures included in simulator scenario setup (32 EOG fails to start/trips, PORV 455C fails open)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: _6_ Page __§___ of _9_

Event

Description:

32 EOG fails to start I trips.

Time Position Applicant's Actions or Behavior ALL Crew recognizes that the only EOG running is 33 EOG and bus 5A cannot be energized due to the fault. 31 and 32 EDGs are not running.

31 EOG is tagged. 32 EOG tripped.

• Crew shuts down 33 EOG because it has no Service Water Cooling,

• Crew dispatches an NPO to investigate the loss of 32 EOG and attempt to emergency start it per SOP-EL-1.

Booth Instructor Event continues based on earlier failures included in simulator scenario setup (PORV 455C fails open).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: 7 Page __J_ of _9_

Event

Description:

PZR PORV Fails 0Qen (455C fails OQen after loss of all AC, we need to isolate block valve later when Qower is restored}.

Time Position Applicant's Actions or Behavior ATC/ Operator recognizes that the PORV (455C) is failed open BOP

• Recognizes also that the block valve has no power.

• Operator may place the block valve (535) in the "pull to lock close" position.

0 This will ensure it goes closed when power is restored to the block valve.

0 If not the crew needs to remember to close the block valve once power is restored.

0 Power to the block valve can be restored via the restoration of 32 EOG.

Critical ECA-0.0 - - B; manually close the open PORV or associated block Task valve upon restoration of power to block valve.

(CT)

Booth Instructor Event continues based on earlier failures included in simulator scenario setup (Station Blackout) and continued implementation of ECA-0.0.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: _4__ Event No.: __.;8;;...__ _ Page _§_of JL Event

Description:

Depressurization of intact SGs at maximum rate. 32 EOG comes back energizing 6A bus, but 36 SW Pump fails to auto start.

Time Position Applicant's Actions or Behavior CRS Crews implements ECA-0.0, Loss of All AC Power ATC

• Verify Reactor Trip BOP

• Close all MSIVs

• Close Letdown Isolation Valves

• Maintain SG levels using Turbine-Driven AFW Pump (32) o Adjust 32 ABFP FCV-405A, B, C, and D as necessary to maintain total feed flow> 365 gpm.

o Preferentially feed 32 or 33 SG (selects one and feeds at a higher rate).

o Maintain feed flow in all other SGs at~ 100 gpm.

• Try to restore power to any 480V AC Safeguards Bus o Dispatch NPO to investigate and attempt to emergency start 32 EOG per SOP-EL-1.

Critical ECA-0.0 - - B; establish at least 365 gpm AFW flow to SGs before Task SG WR level decreases to below 16%.

(CT)

Booth Instructor Do not allow 32 EDG to start until the crew has initiated SG depressurization.

CRS Crews continues to implement ECA-0.0, Loss of All AC Power ATC

• Place Control Switches on De-enegized buses in TRIP I BOP PULLOUT I OFF, o PRZR Heaters o Containment Spray Pumps o FCUs o SI Pumps o Motor-driven AFW Pumps o RHR Pumps o CCW Pumps

• Isolate RCP Seals (NPO dispatched)

• Check DC Bus Loads

• Depressurize Intact SGs to 275 psig Critical ECA-0.0 - - G; depressurize intact SGs at maximum rate Task (CT)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 4 Event No.: 8 cont Pagel of ~

Event

Description:

De12ressurization of intact SGs at maximum rate. 32 EOG comes back energizing 6A bus, but 36 SW Pum12 fails to auto start.

Time Position Applicant's Actions or Behavior Booth Operator Once the SGs are depressurized at a maximum rate to less than 275 psig, then allow the NPO to emergency start 32 EDG.

Insert remote LOA-DSG029 to RESET, DIG #32 TRIP RESET Insert remote LOA-DSG032 after 15 to MAN, DIG #32 MAN/OFF/AUTO MODE SWITCH Insert remote LOA-DSG045 after 20 to ACTIVE_LOA, DIG #32 MANUAL START PUSHBUTTON ALL Crew recognizes that the 32 EOG has been restarted and aligned to the 6A 480V bus.

They also recognize that 36 Service Water Pump has not started to provide cooling.

Crew manually starts 36 SWP and also potentially starts 39 Backup SW Pump as well.

Critical ECA-0.0; Start 36 Service Water Pump to provide cooling for 32 Tasks EOG.

(CT)

ECA-0.0 - - B; manually close the open PORV or associated block valve upon restoration of power to block valve.

Booth Instructor Terminate scenario at this point or at Lead Evaluator's discretion.

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: 5 -low power Op-Test No.:

Examiners: Operators:

Initial Conditions: 4% Reactor Power, Plant startup following a forced outage, power ascension IAW 3-POP-1.3. #32 Component Cooling Water Pump is out of service for Maintenance (Motor replacement). Raise power to 10%, the warm up the MTG and Qlace in service.

Turnover: 4% Reactor Power, Plant startuQ following a forced outage, 12ower ascension IAW 3-POP-1.3. #32 Component Cooling Water Pump is out of service for Maintenance (Motor reQlacement). Raise 12ower to 10%, the warm up the MTG and Qlace in service. Fuel is conditioned.

Event Malf. No. Event Type* Event No. Description 1 RATC Perform power ascension to 10% IAW 3-POP-1.3; Plant Startup from Zero to 45% Power.

N CRS I BOP 2 XMT- CATC/BOP Thot fails high. Crew responds per 3-AOP-INST-1 and RCS052 Technical Specifications TSCRS 3 MAL- MALL I TS Initiate RCS Leakage, starting at 23 gpm. Crew to RCS005 CRS respond IAW 3-AOP-Leak-1.

A 4 MAL- MALL Raise RCS leakrate to approximately 223 gpm. Crew RCS005 will trip RX and initiate manual SI.

B 5 CALL AUTO SI Fails, manual initiation required. If manually initiated, then no failure.

6 MAL- MALL LBLOCA RCS001 A

7 CBOP #31 RHR and #32 SI Pump did not start and #34 Fan Cooler Unit dampers did not reposition.

8 MALL Once SI has been verified by the BOP and reset, a loss of Off-Site Power occurs.

9 CALL Crew establishes required SI loads on Diesels.

• (N)ormal, (R)eactivity, {I )nstrument, {C)omponent, (M)ajor

Simulator Exam Scenario # 5 Summary The scenario begins with the plant at 4% power. Plant startup is in progress following a forced outage IAW POP-1.3. 32 Component Cooling Water Pump is out of service for Maintenance (Motor replacement).

Crew will initiate a reactor power increase to between 6% and 12% to establish MODE 1 conditions IAW POP-1.3. During the power ascension, Loop 4 Thot fails high. Crew responds in accordance with AOP-INST-1 and trips bistables.

Once the plant is stable and actions per AOP-INST-1 have been completed, an RCS leak of approximately 23 gpm is initiated. Crew responds per AOP-LEAK-1, reduces letdown to 45 gpm and starts a second charging pump. Once the crew estimates the RCS leak rate and the CRS determines technical specification applicability, then the leak rate increases to 223 gpm.

The crew responds to the increased RCS leakage and IAW AOP-LEAK-1 IAAT statements trips the reactor, initiates SI, and enters E-0. The auto SI actuation does not occur, manual SI is required by the operators if not initiated IAW the AOP. Once SI is initiated the RCS leak will then degrade into a LBLOCA. The crew implements E-0 and transitions to E-1. The operators will recognize that 31 RHR Pump and 32 SI Pumps did not start and will manually start then per R0-1.

Following the verification of Safety Injection and the subsequent resetting of the SI signal, then a loss of offsite power will occur. Following a loss of offsite power after SI has been reset, the operators will suspend performance of the procedure in effect and will refer to LOOP-1 to restore equipment to the conditions in effect prior to the loss of offsite power. Once LOOP-1 is complete, the operator returns to the procedure and step in effect.

Procedure flow path: POP-1.3, AOP-INST-1, AOP-LEAK-1, E-0, E-1, LOOP-1, E-1.

Scenario# 5 On At Time Action Description Event SAFETY INJECTION 00:00:00 None Insert malfunction MAL-SISOO I A FAILURE TRAIN A SAFETY INJECTION 00:00:00 None Insert malfunction MAL-SISOOIB FAILURE TRAIN B Insert malfunction XMT-RCS052 to HOT LEG NR MICROPROC 00:00:00 None 640.00000 on event 2 LOOP4TEMPERATURE

• Insert malfunction MAL-RCS005A to RCSLEAK(LOOPICOLD 00:00:00 None I .00000 on event 3 LEG)

Insert malfunction MAL-RCS005B to RCSLEAK(LOOP2COLD 00:00:00 None 10.00000 on event 4 LEG)

Insert malfunction MAL-RHROOIA to 00:00:00 None RHR PUMP 31 FAILURES FAILURE TO AUTOSTART Insert malfunction MAL-SIS004B to SAFETY INJECTION PUMP 00:00:00 None FAILURE TO AUTOSTART 32 FAILURES Insert malfunction MAL-EPSOOI on event 00:00:00 None STA TION BLACKOUT 8

Insert malfunction MAL-RCSOOIA to RCS RUPTURE (LOOP I 00:00:00 None I 00.00000 on event 6 COLD LEG)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 5 Event No.: 1 Page_1_ of _1Q_

Event

Description:

Perform gower ascension to 10% IAW 3-POP-1.3; Plant Startug from Zero to 45% Power.

Time Position Applicant's Actions or Behavior Booth Instructor Simulator setup is 4% Reactor Power, all steps of 3-POP-1.3; Plant Startup from Zero to 45% Power are signed off up to step 4.30. Cue that all Mode 1 prerequisites and MODE change signoffs are completed.

ATC INllTATE a Reactor power increase to between 6% and 12% to establish Mode 1 conditions.

• Steam Dumps are in pressure mode of control set at 1005#

• Operator will withdraw control rods and I or dilute to raise power.

NOTE: The T-AVG/T-REF DEVIATION ALARM (Panel SCF) may annunciate while performing the power increase. Entry into the ARP is NOT required until after the Turbine is synchronized.

Booth Instructor NOTE: Evaluator may more on to the next event once power has been raised to 7-8% reactor power.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.:

5 Event No.: 2

---

'--~

Page -1.._ of _1Q_

Event

Description:

HOT LEG NR MICROPROC LOOP 4 TEMPERATURE Transmitter fails high. Team responds per AOP-INST-1.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction XMT-RCS052 to 640.00000 on event 2, HOT LEG NR MICROPROC LOOP 4 TEMPERATURE. Loop 4 That fails high.

ATC 1. Diagnose Loop 4 Thot channel instrument failure, Loop 3 Thot fails high.

2. Place charging pumps in manual control

3. Maintain PRZR level in normal band per Graph RCS-2 (Pressurizer Level vs Tavg)

CRS Direct the team during performance of AOP-INST-1

• Directs RO to perform immediate actions and verifies completion of the immediate actions using the procedure

• Supervise actions of the team during subsequent actions .

• Reviews Technical Specifications:

o TS Table 3.3.1-1 Function 5 o TS Table 3.3.1-1 Function 6 o TS Table 3.3.2-1 Function 4.d o Determines bistables require tripping within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• Directs BOP to trip bistables .

BOP 1. PERFORM the following or affected channel using Attachment 8 (Defeating Failed RCS Temperature Channels/Circuits):

a. Place~ T DEFEAT (Rack b-8) in position specified in Table 1 (page 137) (Black Key).

i. 3T/411 B in OFT CH IV

b. Place TAVG DEFEAT (Rack 0-8) in position specified in Table 2 (Page 139) (Black Key).

i. T/412B in LOOP B UNIT-2

2. Are all redundant bistable status lights for failed instrument listed in Attachment 9 (RCS Temperature Tables) Table 1(Page141) extinguished?

a. 1-11; LOTAVG LOOP31 TC412D

b. J-11; LO TAVG LOOP 32 TC422D

c. K-11; LO TAVG LOOP 33 TC4320

d. A-11; OT ~T LOOP 1 TC411A

e. B-11; OT~ T LOOP 2 TC421A

f. C-11; OT~ T LOOP 3 TC431A

g. A-12; OP ~T LOOP 1 TC411C

h. B-12; OP ~T LOOP 2 TC421C

i. C-12; OP ~T LOOP 3 TC431C

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: _5__ Event No.: 2 cont Page _l_ of _1Q__

Event

Description:

HOT LEG NR MICROPROC LOOP 4 TEMPERATURE Transmitter fails high. Team responds per AOP-INST-1.

Time Position Applicant's Actions or Behavior BOP 3. Trip bistables for failed instrument listed in Attachment 9 (RCS Temperature Tables) Table 2 (Page 145). Protection rack Yellow B-10

a. Loop 4, Over Power Trip

b. Loop 4, Over Temp Trip

c. Loop 4, Low Tavg BOP 4. Are all bistable status lights for failed instrument listed in Attachment 9 (RCS Temperature Tables) Table 3 (Page 147) illuminated?

a. L-11; LO TAVG LOOP 34 TC442D

b. D-11; OT Ll T LOOP 4 TC441A

c. D-12; OP LlT LOOP 4 TC441C Booth Instructor Scenario may continue after CRS completes Technical Specification determination. Lead evaluator may determine that the bistab/es are not going to be tripped.

NOTE: Crew may Place Steam Dump Control switch to RESET and return to TEMP CONT. /AW step 4.147 of 3-AOP-INST-1. They should recognize the need to leave steam dump control in Pressure Mode of control per 3-POP-1.3, but if they do we can still more on to the next event. Will only cause the atmospheric dump valves to open.

Crew may also leave charging pump control in manual, also will not affect moving on to the next event.

Follow-up questions can be asked by the evaluators after the scenario is complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 5 Event No.: 3 Page__+/-_ of __1Q_

Event

Description:

RCS Leakage starting at ai;;mroximately 23 g[2m, crew res[2onds IAW 3-AOP-LEAK-1 and Technical S[2ecifications.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL-RCSOOSA to 1.00000 on event 3, RCS LEAK (LOOP 1 COLD LEG). Approximately 23 gpm RCS leak in containment.

ALL Crew responds to indications of an RCS leak. Containment environment parameters rising (dew point, radiation, VC Sump).

ATC Approximates RCS Leak rate using CVCS parameters (Charging, Letdown, Seal Injection, Seal Return, VCT Level, PZR Level).

CRS Enters 3-AOP-LEAK-1; Sudden Increase in Reactor Coolant System Leakage.

• Directs actions IAW Procedure

• Reviews RCS Leakage Technical Specifications 0 TS 3.4.13 0 Recognizes that they have exceeded both identified and unidentified leakage limits. Need to reduce Leakage within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• Possible brief with review of procedure IAAT statements regarding PRZR level and pressure operating limitations ATC/ Perform the following as necessary to maintain PRZR level:

BOP

• Increase charging pump speed .

• Start second charging pump .

• Reduce letdown to 45 gpm ALL Are there indications of leakage inside containment?

• R-2 (80' VC Area Monitor

• R-7 (lncore Inst Room Area)

• R-11 (VC Particulate)

• R-12 (VC Radiogas)

• Sump level

• Humidity

• FCU weir leak rate Initiate preparations for VC entry per OAP-007.

Booth Instructor Scenario continues to next event once crew estimates the RCS leak rate and the CRS determines Technical Specification applicability.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.:

5 Event No.: 4

---

'-~

Page _§___ of 10 Event

Description:

e Position Applicant's Actions or Behavior Booth Instructor Insert ma/function MAL-RCS005B to 10.00000 on event 4 to raise RCS Leakage to approximately 223 gpm.

Also ensure the simulator setup has the failure of AUTO Safety Injection inserted:

MAL-SIS001A, SAFETY INJECTION FAILURE TRAIN A MAL-SIS001B, SAFETY INJECTION FAILURE TRAIN B And MAL-RHR001A to FAILURE_ TO_AUTOSTART, 31 RHR Pump fails to auto start MAL-SIS004B to FAILURE_TO_AUTOSTART, 32 SI Pump fails to auto start ALL Crew responds to increased RCS Leakage and recognizes that one of the following IAAT statements from 3-AOP-LEAK-1 applies:

1. IAAT PRZR pressure decreases to::; 1930 psig, THEN ...

2. IAAT PRZR level can NOT be maintained with two charging pumps in service AND letdown flow ::; 45 gpm OR PRZR level decreases to < 14, THEN perform the following:

a. Trip the reactor

b. Initiate SI.

c. GO TO E-0 Critical E - D, Manually actuate at least one train of SIS actuated Task safeguards before transition to any E-1 series.

(CT)

Booth Instructor NOTE: Crew may not initiate manual SI and wait for AUTO actuation. If AUTO actuation signal is received, crew will need to initiate Safety Injection manually (event 5 only if necessary).

Otherwise scenario continues to event 6 (LBLOCA).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 5 - Event No.: 5 Page _Q__ of 1O Event

Description:

AUTO SI Fails. manual initiation required. If manually initiated, then no failure.

Time Position Applicant's Actions or Behavior ALL 1. Crew recognizes that Safety Injection did not automatically initiate based on reaching actuation setpoint.

2. Crew manually initiates Safety Injection.

NOTE: Crew could manually ACUATE SI per step 5.b of E-0 also.

Critical E - D, Manually actuate at least one train of SIS actuated Task safeguards before transition to any E-1 series.

(CT)

Booth Instructor NOTE: Crew may not initiate manual SI and wait for AUTO actuation. If AUTO actuation signal is received, crew will need to initiate Safety Injection manually (event 5 only if necessary).

Otherwise scenario continues to event 6 (LBLOCA).

Event continues based on earlier failures included in simulator scenario setup (#31 RHR Pump and #32 SJ Pump did not start and #34 Fan Cooler Unit dampers did not reposition.)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: - -

5 - Event No.: - 6 -- Page _L_ of 10 Event

Description:

Following Reactor Trip and manual SI actuation. a Large Break LOCA occurs.

Time Position Applicant's Actions or Behavior Booth Instructor Insert malfunction MAL-RCS001A to 100.00000 on event 6, RCS RUPTURE (LOOP 1 COLD LEG) as soon as Safety Injection has been manually initiated.

ALL Crew implements 3-E-O; Reactor Trip or Safety Injection

• Completes immediate actions

• AFW Status

• Direct BOP Operator to Perform 3-R0-1; BOP Operator Actions During Use of EOPs.

• Verify Feedwater Isolation

• Verify SI Flow

• Containment Spray?

• RCP Seal Cooling

• Establish Charging Flow

• Check RCS Average Temperature

• Check If RCPs Should Be Stopped

• PRZR PORVs, Safety Valves, Spray Valves

• Faulted SG

• Ruptured SG

• RCS Intact o GO TO 3-E-1, Loss of Reactor or Secondary Coolant Critical E - C, Trip all RCPs so that CET temperatures do not become Task superheated when forced circulation in the RCS stops.

(CT)

Booth Instructor Event continues based on earlier failures included in simulator scenario setup (#31 RHR Pump and #32 SI Pump did not start and #34 Fan Cooler Unit dampers did not reposition).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 5 Event No.: 7 Page __§__ of J.Q_

Event

Description:

1. 31 RHR Pum12 and #32 SI Pum12 did not auto start on the SI actuation and #34 Fan Cooler Unit Dam12ers did not re12osition.

Time Position Applicant's Actions or Behavior Booth Instructor Event continues based on earlier failures included in simulator scenario setup (#31 RHR Pump and #32 SI Pump did not start and #34 Fan Cooler Unit dampers did not reposition).

CRS BOP will recognize that 31 RHR Pump and 32 SI Pumps have not BOP started in Auto following the SI actuation.

VERIFY SI Pumps - RUNNING

• Three HHSI pumps

• Two RHR pumps RNO

• Manually START pump(s) .

CRS Place FCU damper control switches in - INCIENT MODE position BOP Check FCU dampers for all FCUs - IN INCIDENT MODE POSITION

• Dampers A/B - CLOSED (inlet dampers)

• Damper C - CLOSED (bypass damper)

• Damper D - OPEN (filter outlet damper)

Booth Instructor BOP operator should start the pumps and reposition the dampers IA W steps 2 and 3 of 3-R0-1; BOP Operator Actions During Use of EOPs.

Event continues based on transition to 3-E-1; Loss of Reactor or Secondary Coolant.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 5 Event No.: 8 Page _J!_ of _1Q Event

Description:

Once SI has been verified by the BOP and reset, a loss of Off-Site Power occurs.

Time Position Applicant's Actions or Behavior Booth Operator Monitor operator actions and once the BOP has verified SI and reset SI per step 14 of 3-R0-1; BOP Operator Actions During Use of EOPs, then insert ma/function for loss of offsite power.

MAL-EPS001 on event 8, Station Blackout CRS Supervise the actions of the crew during E-1 NOTE: Crew could trip the RCPs and Reset SI in 3-E-1, steps 1 and 4 depending on the BOP Operator's progression through 3-R0-1.

BOP Continue performance of 3-R0-1

1. RESET SI as Follows:

a. PRESS both SI reset buttons on panel SBF-2:

• Train 1 SI Reset

• Train 2 SI Reset

b. CHECK SI- RESET

• SI ACTUATED light EXTINGUISHED Booth Instructor Scenario continues with the loss of offsite power.

MAL-EPS001 on event 8, Station Blackout

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 5/11/15 Scenario No.: 5 Event No.: 9 Page _1.Q_ of _1.Q_

Event

Description:

Crew establishes reguired SI loads on Diesels following the loss of offsite Qower.

Time Position Applicant's Actions or Behavior Booth Operator Following a loss of offsite power after SI has been reset, the operator will suspend performance of the procedure in effect and will refer to LOOP-1 to restore equipment to the conditions in effect prior to the loss of offsite power. Once LOOP-1 is complete, the operator returns to the procedure and step in effect.

CRS Directs the performance of LOOP-1; Loss of Offsite Power After SI.

Supervise the actions of the crew during implementation of LOOP-1.

ATC/ 1. VERIFY Power to 480V AC Buses BOP 2. ALIGN Essential SW And CCW Pumps And Letdown

• Start Essential SW pumps as required .

• PLACE CCW pumps in TRIP PULLOUT.

• Ensure letdown is ISOLATED .

3. RESTART SI Or Recirculation Equipment:

• HHSI pumps

• RHR pumps

• Fan Cooler Units

• Containment Spray pumps

• AFW pumps

• Recirculation pumps RNO: START or STOP equipment to re-establish equipment line-up prior to Loss of Offsite Power.

Critical Ensure Service Water Pumps are started to cool the Diesel Task Generators IAW step 2 of 3-LOOP-1.

(CT)

Booth Instructor Terminate scenario at this point or at Lead Evaluator's discretion.

Ensure adequate (reasonable) time to meet critical task.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Respond to Turbine First Stage Pressure Transmitter Failure KIA

Reference:

001 OOOA2.11 Job Performance Measure R0-4.4 SR0-4.7 No: Simulator 1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Reactor at 41 % Power.

• Startup in progress IAW 3-POP-1.3; Plant Startup from Zero to 45% Power.

• Control Rods are in AUTO.

Required Materials: None General

References:

3-AOP-INST-1; Instrument I Controller Failures 3-AOP-ROD-1; Rod Control and Indication System Malfunction Initiating Cue: You are the ATC.

Time Critical Task:

Validation Time: No Task Standard:

1 of 8

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J1. Performance Step: Take manual actions as necessary to control parameters and stabilize the plant.

Standard: Place Rod Control in Manual.

Comment: Procedure Step 3.1

2. Performance Step: Has an instrument failure occurred?

Standard: Determine an instrument failure has occurred; PT-412A has failed low.

Comment: Procedure Step 4.1 {Includes identification of 3-AOP-INST-1 as the appropriate mitigating procedure.)

3. Performance Step: GO TO applicable step for the indicated failure.

Standard: Identify Turbine 1st Stage Pressure, step 4.17 4 as the affected step.

Comment: Procedure Step 4.2

4. Performance Step: Has Channel A failed?

Standard: Determine PT-412A has failed low.

Comment: Procedure Step 4.17 4.

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,/)

5. Performance Step: Are control rods in manual control?

Standard: Rod control should be in manual at this time.

Comment: Procedure Step 4.175.

6. Performance Step: Determine Tret based on PT-4128 using Graph RPC-9 (Tret vs 1st Stage Pressure).

Standard: Using Graph determine Tret.

Comment: Procedure Step 4.176. (Student may note previous Tave value and wish to return to previous temperature)

...J 7. Performance Step: Is Tave within 1.5°F of Tret? Control any of the following as necessary to maintain Tave and Tret on program for current reactor power:

• Rod control

• Boron concentration

• Turbine load CUE: The CRS directs restoring Tave using Control Rods. (Restore to previous rod height is acceptable)

Standard: Withdraw Control Rods to restore Tave. (Restore to previous rod height is acceptable)

Comment: Procedure Step 4.177 & RNO.

NOTE: Malfunction of rods to occur while withdrawing. Continuous outward rod motion.

3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

8. Performance Step: Observe Rods continuing to withdraw in Manual after In-Hold-Out switch released.

Standard: Observe step counters and IRPI continuing outward motion.

Comment: The following steps are from procedure 3- AOP-ROD-1.

The candidate may just trip the reactor and GO TO 3-E-O.

9. Performance Step: Was this procedure entered due to continuous Unwarranted rod motion?

Standard: Determines Yes.

Comment: Procedure Step 4.1.

10. Performance Step: Is rod control in manual?

Standard: Determines rod control is in manual.

Comment: Procedure Step 4.2.

11. Performance Step: Does continuous unwarranted rod motion exist?

Standard: Determines Yes.

Comment: Procedure Step 4.3.

4 of 8

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark .Y)

..../ 12. Performance Step: Trip the Reactor and GO TO E-0.

Standard: Trips the Reactor. (Manual Action)

Comment: Procedure Step 4.4 Terminating Cue: JPM Complete 5 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Approximately 41 % Power IC PT-412A, First Stage Turbine Pressure fails low.

Continuous Outward Unwarranted Rod Motion in Manual (Malfunction will be inserted when rod motion is initiated) 7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Reactor at 41 % Power.

• Startup in progress IAW 3-POP-1.3; Plant Startup from Zero to 45% Power.

• Control Rods are in AUTO.

Initiating Cue:

You are the ATC.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Place Excess Letdown In Service KIA

Reference:

004000A406 Job Performance Measure RO - 3.6 SRO - 3.1 No: Simulator 2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Reactor at 100% Power.

• A packing leak exists on CH-AOV-202; Letdown Isolation Valve in the PAB.

• Maintenance has requested that normal letdown be isolated to allow them to adjust the packing gland.

• 33 Charging Pump is in service.

Required Materials: None.

General

References:

3-SOP-CVCS-002; Charging, Seal water, and Letdown Control Initiating Cue: The CRS has directed that you transfer normal letdown to excess letdown IAW 3-SOP-CVCS-002, section 4.2.3. All Precautions and Limitations have been reviewed as well as Initial Conditions verified.

Time Critical Task: No Validation Time:

Task Standard: Establish Excess Letdown flow to the VCT within operating limits.

1of8

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V) 1 . Performance Step: PLACE Charging Pumps in Manual to minimize PZR level fluctuations.

Standard: Places 33 Charging Pump in Manual.

Comment: Procedure Step 4.2.3.1. Note that 33 Charging Pump is already l/S. Also if necessary, cue that the CRS has determined that this is not being considered an Infrequently Performed Task and Evolution.

2. Performance Step: CONTROL running charging pump speed to maintain Seal Injection between 6 and 12 gpm, and PZR level stable.

Standard: Maintains Seal Injection between 6 and 12 gpm.

Comment: Procedure Step 4.2.3.3.

Instructor Note: Ensure CCW Header Pressure is sufficient to avoid Auto Start of CCWPump .

...J 3. Performance Step: OPEN the following valves to establish CCW flow to Excess Letdown HX:

a) AC-AOV-793, HX CCW Outlet Isolation b) AC-AOV-796, HX CCW Outlet Isolation c) AC-AOP-791, HX CCW Inlet Isolation d) AC-AOV-798, HX CCW Inlet lsoaltion Standard: Opens the CCW Isolation Valves IAW step 4.2.3.6.

Comment: Procedure Step 4.2.3.6.

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

4. Performance Step: VERIFY CH-HCV-123, Excess Letdown Flow Control Valve, is Closed.

Standard: Verify valve is closed.

Comment: Procedure Step 4.2.3.9.

5. Performance Step: VERIFY CH-AOV-215, Excess Letdown Diversion Valve, is in DIVERT to align Letdown flow to RCDT.

Standard: Verify valve is selected to DIVERT.

Comment: Procedure Step 4.2.3.10

6. Performance Step: CRACK OPEN CH-HCV-123, Excess Letdown Flow Control Valve (about 10% open) to preclude pressure surge on eves side of heat exchanger.

Standard: Opens valve approximately 10%.

Comment: Procedure Step 4.2.3.11.

"'7. Performance Step: OPEN the following top valves:

• CH-AOV-213A, Excess Letdown Stop Valve

• CH-AOV-2138, Excess Letdown Stop Valve Standard: Opens both valves.

Comment: Procedure Step 4.2.3.12.

3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

'Ja. Performance Step: Slowly OPEN CH-HCV-123 to allow HX warm-up.

Standard: Slowly opens CH-HCV-123 and ensues that Excess Letdown HX outlet temperature is less than 160°F as indicated on Tl-122.

Comment: Procedure Step 4.2.3.13. Note Caution before step, "When using RCDT pump(s), then Excess Letdown HX outlet temp SHALL be maintained less than 160°F as indicated on Tl-122."

-../ 9. Performance Step: WHEN VCT Level changes (2% - 4% ), THEN Slowly CLOSE CH-HCV-123 to minimize RCP seal perturbation.

• PLACE CH-AOV-215 in NORMAL to align Letdown flow to VCT.

• THROTTLE CH-HCV-123 to achieve desired flow.

Standard: Directs Excess Letdown Flow to the VCT and adjusts CH-HCV-123 to achieve design excess letdown flow (approx.

20 gpm) without exceeding temperature restrictions in caution.

Comment: Procedure Step 4.2.3.14. Note Caution before step, "Excess Letdown HX outlet temp SHALL NOT be allowed to exceed 200°F as indicated on Tl-122."

10. Performance Step: NOTIFY HP, Excess Letdown has been placed in service AND surveys should be conducted due to changes in radiation fields.

Standard: Notifies HP via instructor.

Instructor Cue: HP has been notified.

Comment: Procedure Step 4.2.3.15.

4 of 8

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

....J 11. Performance Step: !E Normal Letdown is in service, THEN CLOSE the following valves:

• CH-AOV-200a, Letdown Valve

• CH-AOV-2008, Letdown Valve

• CH-AOV-200C, Letdown Valve

• CH-LCV-459, Loop 31 INT

• CH-LCV-460, Loop 31 INT Standard: Closes or verifies closed the above valves.

Comment: Procedure Step 4.2.3.17.

Terminating Cue: JPM Complete 5 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Any 100% IC Ensure 33 Charging Pump is in Service Ensure CCW Header Pressure is sufficient to avoid Auto CCW Pump starts.

7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Reactor at 100% Power.

• A packing leak exists on CH-AOV-202; Letdown Isolation Valve in the PAB.

• Maintenance has requested that normal letdown be isolated to allow them to adjust the packing gland.

• 33 Charging Pump is in service.

Initiating Cue:

The CRS has directed that you transfer normal letdown to excess letdown IAW 3-SOP-CVCS-002, section 4.2.3. All Precautions and Limitations have been reviewed as well as Initial Conditions verified.

8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Adjust Accumulator Level and/or Pressure as Required KIA

Reference:

Job Performance Measure Simulator 3 006000A 1. 13 No: (RO Only)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom Simulator X Plant - - - - - -

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

Initial Conditions:

• The plant is at 100% power

• 31 SI Accumulator has a low level

• The Refueling Water Purification pump is NOT in service

• System Engineering has been informed that the accumulator is to be filled

• 32 SI Pump motor starting requirements are satisfied Required Materials: 3-SOP-Sl-001; Safety Injection System Operation General

References:

3-SOP-Sl-001; Safety Injection System Operation Initiating Cue: The CRS has directed you to fill 31 SI accumulator to 24% using 32 SI Pump in accordance with SOP-Sl-001, step 4.3.2.

Time Critical Task: No Validation Time:

Task Standard: 31 SI Accumulator filled to 24% with 32 SI Pump secured.

1of7

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

1. Performance Step: ENTER LCO 3.5.2 Action Statement.

Standard: Recognizes applicability of Technical Specification LCO 3.5.2.

Comment: Procedure Steps 4.3.2.3 through 4.3.2.5.

When Sl-859A, Band C valves are open, then a dedicated operator SHALL be stationed at Sl-859C in continuous communication with the CCR to close Sl-859C and Sl-859A should SI actuation occur. (TS 3.6.3 Basis)

2. Performance Step: UNLOCK and OPEN the following valves:

• Sl-859A, Accumulator Drain/Safety Injection Test Line Isolation

• Sl-859C, Accumulator Drain/Safety Injection Test Line Isolation OPEN Sl-8598, Accumulator Drain/Safety Injection Test Line Isolation.

Standard: Contacts NPO to open valves.

Comment: Procedure Steps 4.3.2.4 and 4.3.2.5 CUE: State that Sl-859A, B, and C valves have been opened by the NPO in field.

The NPO is also stationed at Sl-859C in continuous communication with the CCR to close Sl-859C and Sl-859A should SI actuation occur.

3. Performance Step: PERFORM Step 1.0 of Attachment 2, Data Sheet for Monitoring PRT Level.

Standard: Records initial PRT level, date, and time on Attachment 2.

Comment: Procedure Step 4.3.2. 7 and NOTE on Attachment 2; "Initial and final PRT levels are recorded to determine whether Sl-855, Test Line Relief, leaks by while Safety Injection Pumps are in service."

2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

.Y4. Performance Step: START 32 SI Pump AND VERIFY adequate discharge pressure.

Standard: 32 HHSIP running with adequate discharge pressure Comment: Procedure Step 4.3.2.8

5. Performance Step: VERIFY SI pump recirc flow is 25 gpm or greater on Fl-950, SI Pump Recirculation Flow Indicator. IF less than 25 gpm, THEN immediately STOP pump.

Standard: Request Recirculation Flow from NPO.

CUE: State that the NPO reports Recirculation Flow is 50 gpm.

Comment: Procedure Step 4.3.2.9.

6. Performance Step: VERIFY the following valves are closed:

• Sl-HCV-943, Accumulator Vent Control

• NNE-AOV-863, PORVs And Accumulators N2 Supply Containment Isolation Standard: Verify valves closed.

Comment: Procedure Step 4.3.2.10.

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

.../ 7. Performance Step: IF desired to fill 31 accumulator, THEN:

• OPEN Sl-AOV-891A, 31 Accumulator N2 Supply Isolation.

• OPEN Sl-AOV-890A, 31 Accumulator Fill Isolation.

• MAINTAIN desired pressure by throttling Sl-HCV-943.

• WHEN Desired level is reached, THEN CLOSE the following:

o Sl-HCV-943, Accumulator Vent Control o Sl-AOV-890A, 31 Accumulator Fill Isolation o Sl-AOV-891A, 31 Accumulator N2 Supply Isolation Standard: Recognizes the possible need to vent the accumulator while filling to 24%. Restores 31 Accumulator to required Tech Spec Level & Pressure.

Comment: Procedure Step 4.3.2.11.

'Ja. Performance Step: WHEN accumulator filling is complete, THEN STOP SI pump and PLACE control switch in AUTO.

Standard: Secures 32 HHSIP. Returns control switch to AUTO.

Comment: Procedure Step 4.3.2.16.

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Any 100% IC 31 Accumulator Level is low, out of spec.

6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is at 100% power

• 31 SI Accumulator has a low level

• The Refueling Water Purification pump is NOT in service

• System Engineering has been informed that the accumulator is to be filled

• 32 SI Pump motor starting requirements are satisfied Initiating Cue:

The CRS has directed you to fill 31 SI accumulator to 24% using 32 SI Pump in accordance with SOP-Sl-001, step 4.3.2.

7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Depressurize the RCS following a SGTR (using PORVs) IAW 3-E-3.

KIA

Reference:

Job Performance Measure 01 OOOOA4.03 No: Simulator 4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -

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

Initial Conditions:

• A Steam Generator Tube Rupture has occurred in 32 SG.

• Procedure 3-E-3; Steam Generator Tube Rupture is completed up to and including step 15.

• Steam Generator 32 is isolated and RCS cooldown is complete.

Required Materials: 3-E-3; Steam Generator Tube Rupture General

References:

3-E-3; Steam Generator Tube Rupture Initiating Cue: You are directed to depressurize the RCS to minimize break flow and refill Pressurizer in accordance with 3-E-3. Steps 1 through 15 of 3-E-3 are completed.

Time Critical Task: No Validation Time:

Task Standard: RCS depressurized in accordance with 3-E-3.

1 of 7

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -../)

1. Performance Step: Check Ruptured SG(s) Pressure - Stable or Increasing.

Standard: Observes ruptured SG pressure stable.

Comment: Procedure Step 16.

2. Performance Step: Observes NOTE prior to step 17.

Standard: Reviews NOTE prior to step 17, uses peacekeeping.

Comment: Subcooling is increasing.

3. Performance Step: Check RCS Subcooling Based On Qualified Core Exit TCs

- Greater than 60°F.

Standard: Checks QSPDS for subcooling > 60 degrees.

Comment: Procedure Step 17.

4. Performance Step: Observes NOTE prior to step 18.

Standard: Reviews NOTE prior to step 17, uses peacekeeping.

Comment: Understands NOTE.

2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

,/ 5. Performance Step: DEPRESSURIZE RCS Using PRZR Spray to Minimize Break Flow and Refill PRZR:

a. CHECK normal PRZR spray AVAILABLE

b. INITIATE maximum PRZR spray

c. CHECK RCS pressure DECREASING Standard: Verifies normal spray available (RCPs running). Attempts to open both spray valves using Master Controller and/or Individual Controllers. Both spray valves fail to open. Uses RNO and goes to step 20.

Comment: Procedure Step 18.

6. Performance Step: Observes CAUTION and NOTE prior to step 20.

Standard: Reviews NOTE prior to step 20, uses peacekeeping.

Comment: Understands CAUTION and NOTE.

../ 7. Performance Step: DEPRESSURIZE RCS Using PRZR PORV to Minimize Break Flow and Refill PRZR:

a. CHECK PRZR PORVs -ANY AVAILABLE

b. OPEN one PRZR PORV

c. CHECK RCS pressure DECREASING Standard: Determines both block valves are open and both PORVs have power. Opens one PORV, verifies RCS pressure is decreasing.

Comment: Procedure Step 20. Should review termination criteria prior to initiating the depressurization with the open PORV. Pressure will drop rapidly; PZR Level will rise rapidly as well.

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -.../)

-.../a. Performance Step: DETERMINE If RCS Depressurization Using PRZR PORV Should Be Terminated:

a. CHECK ANY of the following conditions satisfied:

• BOTH of the following:

1. RCS pressure - LESS THAN RUPTURED SG(s) PRESSURE

2. PRZR level-GREATER THAN 14%

(32%)

OR

• PRZR level -GREATER THAN 73% (58%)

OR

• RCS subcooling based on qualified core exit TCs - LESS THAN 40°F

b. CLOSE PRZR PORV Standard: Verifies one of the three criteria is met and depressurization should be stopped. Closes open PORV.

Comment: Procedure Step 21. Should review termination criteria prior to initiating the depressurization with the open PORV.

Pressure will drop rapidly; PZR Level will rise rapidly as well.

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Reset Simulator to any 100% Power IC Insert the following malfunctions:

SWl-AIR002A OFF (turns 1228 green lamp off)

SWl-AIR002B ON (turns 1228 red lamp on)

SWl-AIR002C OFF (keeps valve 1228 closed)

MAL-SGN005B 15 (initiates a tube rupture on 32 SG at - 325 gpm)

Perform the following to setup the JPM:

• Insert a SGTR in 32 SG MAL-SGN005B (- 325 gpm)

• Initiate a Rx Trip and Safety Injection

• Perform the actions in E-0 and R0-1 and transition to E-3

• Perform steps 1-15 in E-3 and freeze the simulator 6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• A Steam Generator Tube Rupture has occurred in 32 SG.

• Procedure 3-E-3; Steam Generator Tube Rupture is completed up to and including step 15.

• Steam Generator 32 is isolated and RCS cooldown is complete.

Initiating Cue:

You are directed to depressurize the RCS to minimize break flow and refill Pressurizer in accordance with 3-E-3. Steps 1 through 15 of 3-E-3 are completed.

7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

RHR Pump Trip while on shutdown cooling IAW 3-AOP-RHR-1 KIA

Reference:

005000A2.03 Job Performance Measure R0-2.9 SR0-3.1 No: Simulator 5 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -

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

Initial Conditions:

• MODE 5

• RCS Temperature is 180°F

• PRZR Level is 22% (Bubble still exits, RCS still pressurized)

• 31 RHR Pump in service for shutdown cooling Required Materials: 3-POP-4.1; Operation at Cold Shutdown 3-AOP-RHR-1; Loss of RHR General

References:

3-POP-4.1; Operation at Cold Shutdown 3-AOP-RHR-1; Loss of RHR Initiating Cue: Maintain Stable MODE 5 conditions with 31 RHR Pump in service for shutdown cooling.

Time Critical Task: No.

Validation Time:

Task Standard: Restore shutdown cooling by starting 32 RHR Pump IAW 3-AOP-RHR-1.

1 of 8

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

1. Performance Step: Operator recognizes the loss of 31 RHR Pump.

Acknowledges Panel SHF - Electrical Annunciator Alarm; "480 V SWGR MOTOR TRIP (COMMON)".

Standard: Acknowledges Annunciator Alarm, recognizes that 31 RHR Pump has tripped.

Comment: Operator is monitoring MODE 5 shutdown cooling, should recognize the loss of 31 RHR Pump and enter 3-AOP-RHR-1. The operator may refer to the Annunciator Response Procedure (ARP) first. If a field operator is dispatched to the breaker, cue that the pump motor has tripped on overcurrent.

CUE: 31 RHR Pump Motor breaker has tripped on motor overcurrent.

(Local breaker flags if NPO dispatched)

2. Performance Step: Operator recommends entry or enters 3-AOP-RHR-1 to respond to the loss of shutdown cooling.

Standard: Operator enters 3-AOP-RHR-1; Loss of RHR.

Comment: Cue student to enter procedure, if they recommend the SRO enter the procedure.

CUE: Cue student to enter 3-AOP-RHR-1 if recommended .

..../ 3. Performance Step: Is RCS temperature< 200°F?

Standard: Operator answers yes and continues to step 4.2 of procedure. Operator recognizes that RHR is out of service, utilizes core exit thermocouples to verify temperature < 200 degrees or RCS Wide Range Temperature< 200 degrees.

Comment: Procedure Step 4.1. RCS Wide Range Temperature indication may be utilized as well.

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

4. Performance Step: Is vacuum fill in progress?

Standard: Operator answers no and proceeds to step 4.4.

Comment: Procedure Step 4.2. RCS is still pressurized.

5. Performance Step: Is the RCS solid?

Standard: Operator answers no and proceeds to step 4.6.

Comment: Procedure Step 4.4.

6. Performance Step: Sound containment evacuation alarm.

Standard: Operator sounds the containment evacuation alarm.

Comment: Procedure Step 4.6.

7. Performance Step: Is RCS at reduced inventory(< 67"-6")?

Standard: Operator answers no and proceeds to step 4.15.

Comment: Procedure Step 4.7.

8. Performance Step: Has containment closure been established?

Standard: Operator answers no and ensures that the RNO task is initiated. "INITIATE containment closure to be achieved within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> OR time to boil, whichever is shorter.

Comment: Procedure Step 4.15. Cue the operator that the Field Supervisor has initiated containment closure. Time to boil determination is not being tested.

CUE: Field Supervisor has initiated containment closure.

3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark..../)

9. Performance Step: Have either of the following valves inadvertently closed?

• AC-MOV-730

• AC-MOV-731 Standard: Operator answers no and proceeds to step 4.19.

Comment: Procedure Step 4.16.

\110. Performance Step: Is an RHR pump running?

Standard: Operator answers no and performs steps in the RNO.

Operator closes RHR heat exchanger flow control valve (Sl-HCV-638/640). Operator determines that the pump was not stopped due to cavitation, but recognizes that 32 RHR Pump is available and proceeds to step 4.25.

Comment: Procedure Step 4.19 and associated RNO. Step 2 of the RNO is a two part; "IF RHR pump was stopped due to cavitation OR any RHR pump is available, THEN GO TO Step 4.25." Operator does not want to go to step 4.37 if a RHR pump is available (32).

11. Performance Step: Is RCS level> 62'-6"?

Standard: Operator answers yes and continues to step 4.26.

Comment: Procedure Step 4.25.

12. Performance Step: Dispatch an operator to monitor RHR pump restart for abnormal indications.

Standard: Operator dispatches an operator to 32 RHR Pump.

Comment: Procedure Step 4.26. Cue that operator is standing by for pump start.

CUE: Operator is standin'g by for pump start.

13. Performance Step: GO TO Step 4.31 Standard: Operator proceeds to step 4.31.

Comment: Procedure Step 4.27.

4 of 8

Appendix C Page 5 Form ES-C-1 v'14. Performance Step: Start an available RHR pump.

Standard: Operator starts 32 RHR while monitoring indications such as pump amps, recirc flow, etc.

Comment: Procedure Step 4.31.

CUE: Local operator reports no abnormal indications, pump running satisfactorily.

v' 15. Performance Step: Slowly open any of the following to establish flow at ~ 1170 gpm:

• Sl-HCV-638

• Sl-HCV-640 Standard: Operator establishes ~ 1170 gpm flow for shutdown cooling.

Comment: Procedure Step 4.32.

Terminating Cue: JPM Complete 5 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup

• MODE 5

• RCS Temperature is 180°F

• PRZR Level is 22% (Bubble still exits, RCS still pressurized)

• 31 RHR Pump in service for shutdown cooling

• 31 RHR Pump trips on motor overcurrent.

7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• MODE 5

• RCS Temperature is 180°F

• PRZR Level is 22% (Bubble still exits, RCS still pressurized)

• 31 RHR Pump in service for shutdown cooling Initiating Cue:

Maintain Stable MODE 5 conditions with 31 RHR Pump in service for shutdown cooling.

8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Swap Essential Service Water Pumps (Check Valve on O/S pump not seated)

KIA

Reference:

076000A2.02 Job Performance Measure R0-2.7 SR0-3.1 No: Simulator 6 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• MODE 1, 100% Power

• Service Water Pump Mode Selector Switch selected to 1-2-3.

Required Materials: 3-SOP-RW-005; Service Water System Operation 3-ARP-012; Panel SJF - Cooling Water and Air 3-AOP-SW-1; Service Water Malfunction General

References:

3-SOP-RW-005; Service Water System Operation 3-ARP-012; Panel SJF - Cooling Water and Air 3-AOP-SW-1; Service Water Malfunction Initiating Cue: You have been directed to swap essential service water pumps IAW 3-SOP-RW-005; Service Water System Operation. System Engineering requests that 33 Service Water Pump be removed from service.

Time Critical Task: No Validation Time:

Task Standard: Swap essential service water pumps IAW 3-SOP-AOP-SW-1, step 4.1.8.

1 of 8

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark..../)

1. Performance Step: REVIEW Unit Log to ensure motor starting requirements of 3-SOP-EL-004a; Electric Motor Operation, will be met.

Standard: Operator requests to review Unit Log.

Cue: Motor starting requirements of 3-SOP-EL-004A have been met.

Comment: Procedure Step 4.1.8.1. Cue operator that motor starting requirements have been met. Cold start criteria. Cue operator if needed that NPO in field has verified pump ready to start.

CUE: NPO in field has verified pump is ready to start.

'J2. Performance Step: START desired SWP.

Standard: Operator starts desired SWP, observing and monitoring pump, motor, and system parameters.

Comment: Procedure Step 4.1.8.2. Operator should observe normal pump parameters including observing an increase in associated SW header pressure. Cue operator if needed that NPO in field has verified pump ready to start and has verified proper operation following start.

CUE: NPO in field has verified pump is operating properly.

3. Performance Step: WHEN pressure increase is noted on affected header, THEN SECURE desired SWP. (33 SWP per system engineering)

Standard: Operator secures 33 SWP monitoring service water header pressure.

Comment: Procedure Step 4.1.8.3.

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -I)

-14. Performance Step: VERIFY affected header pressure stabilizes between 60 and 97.5 psig. Acknowledge Panel SJF Annunciator Alarm for low service water header pressure; "SERVICE WTR.

HOR. (31,32,33) HIGH LOW PRESS", review and take appropriate actions IAW the Alarm Response Procedure (ARP).

IF low pressure condition exists, THEN:

• START 1 additional pump, as necessary.

• INVESTIGATE cause of alarm.

!E necessary, THEN GO TO 3-AOP-SW-1; Service Water Malfunction.

Standard: Operator acknowledges low header pressure condition, recognizes that it is not a normal response and refers to the ARP. Operator may go directly to the AOP. Operator also recognizes entry condition for AOP-SW-1. They may request NPO in field to investigate. If they have an NPO investigate in field, then cue that it appears that 33 SWP shaft is rotating backwards.

Operator should start 1 additional pump, as necessary.

Comment: Procedure Step 4.1.8.4 and ARP step 3.2. (Pressure should stabilize below 60 psig, but above 50 psig)

CUE: (If NPO asked to investigate) It appears that 33 SWP shaft is rotating backwards.

5. Performance Step: Is essential header affected?

Standard: Operator enters 3-AOP-SW-1; Service Water Malfunction. Operator answers yes and proceeds to next step.

Comment: Procedure Step 4.1 of 3-AOP-SW-1.

6. Performance Step: Are Backup SW Pumps available?

Standard: Operator answers yes and proceeds to next step.

Comment: Procedure Step 4.2.

3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

7. Performance Step: Start Backup SW Pumps as necessary to maintain 75 to 11 O psig.

Standard: Operator starts Backup SW Pump if necessary.

Comment: Procedure Step 4.3. Operator should not need to start a backup pump, but may start one. They will start one if they failed to start a normal essential pump per the ARP.

8. Performance Step: IAAT SW Header pressure can NOT be maintained > 50 PSIG, THEN PERFORM one of the following based on system's ability to provide cooling:

• Trip the reactor and INITIATE E-0.

• INITIATE plant shutdown to MODE 3 ...

Standard: Operator recognizes that IAAT statement does not apply as header pressure is greater than 50 psig. Operator proceeds to next step.

Comment: Procedure Step 4.4.

9. Performance Step: IAAT a loss of all normal SW Pumps has occurred, THEN GO TO Step 4.50.

Standard: Operator recognizes that IAAT statement does not apply.

Operator proceeds to next step.

Comment: Procedure Step 4.5.

10. Performance Step: INITIATE determination of affected header from pressure Indications and individual component temperatures.

Standard: Operator determines that the essential service water header is the only header affected.

Comment: Procedure Step 4.6.

4 of 8

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark --./)

11. Performance Step: Dispatch operators as necessary to perform the following:

• Determine cause of low pressure:

o System leakage o SW pump discharge check NOT seated o SW TCV failed open o Strainer '1P CUE: {If NPO asked to investigate} It appears that 33 SWP shaft is rotating backwards.

Standard: Operator requests NPO in field to investigate. From field report, operator recognizes that the SW pump discharge check is NOT seated.

Comment: Procedure Step 4.7. Cue as necessary to describe discharge check valve not seated.

"12. Performance Step: IAAT A SW Pump discharge check valve is determined to be leaking back, THEN notify operator to close Associated SW pump outlet stop.

Standard: Operator recognizes that the SW pump discharge check is NOT seated. Operator notifies field NPO to close associated SW pump outlet stop.

Comment: Procedure Step 4.8. Have the simulator booth operator close the associated SW pump outlet stop.

Terminating Cue: JPM Complete 5 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Any 100% IC Service Water Pump Mode Selector Switch selected to 1-2-3.

33 Service Water Pump l/S.

Discharge check valve failed such that pressure drops to less than 60 psig, but greater than 50 psig. (Ensure pressure does not drop below trip setpoint.)

7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• MODE 1, 100% Power

• Service Water Pump Mode Selector Switch selected to 1-2-3.

Initiating Cue:

You have been directed to swap essential service water pumps IAW 3-SOP-RW-005; Service Water System Operation. System Engineering requests that 33 Service Water Pump be removed from service.

8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Verify Containment Spray Operation IAW E-0, step 9.

KIA

Reference:

026000A2.03 Job Performance Measure RO - 4.1 SRO - 4.4 No: Simulator 7 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -

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

Initial Conditions:

• LOCA or Large Steam Break in Containment

• 3-E-O; Reactor Trip or Safety Injection completed through step 8.

Required Materials: 3-E-O; Reactor Trip or Safety Injection General

References:

3-E-O; Reactor Trip or Safety Injection Initiating Cue: A LOCA or Large Steam Break in Containment is in progress, 3-E-O; Reactor Trip or Safety Injection has been completed through step 8. You have been directed to continue implementation of 3-E-O.

Time Critical Task: No Validation Time:

Task Standard: Manually initiate Containment Spray and Phase B Isolation.

1 of 6

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: CHECK containment pressure - HAS REMAINED LESS THAN 22 PSIG Standard: Operator observes than containment pressure is greater than 22 psig and proceeds to the RNO.

Comment: Procedure Step 9.a. NOTE: Containment Spray and Phase B Isolation has not initiated and will not manually initiate via the red pushbuttons on CR panel SBF-1.

2. Performance Step: ENSURE containment spray has initiated.

Standard: Operator recognizes that containment spray has not initiated although required.

Comment: Procedure Step 9, RNO step a.1 ).

...J 3. Performance Step: IF containment spray has NOT initiated, THEN manually INITIATE.

Standard: Operator recognizes that spray has not initiated and attempts to manually initiate containment spray by simultaneously depressing both red pushbuttons on CR panel SBF-1.

Comment: Procedure Step 9, RNO step a.2).

'14. Performance Step: IF containment spray cannot be initiated manually, THEN manually START pumps and ALIGN valves.

Standard: Operator recognizes that simultaneously depressing both red pushbuttons on CR panel SBF-1 did not work. Operator then manually starts containment spray pumps and aligns appropriate valves to initiate spray flow.

Comment: Procedure Step 9, RNO step a.3).

2 of 6

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

5. Performance Step: Verify containment isolation phase B valves are closed.

Standard: Operator recognizes that containment phase B valves are not closed.

Comment: Procedure Step 9, RNO step a.4).

-V 6. Performance Step: IF containment isolation phase B valves are NOT closed, THEN manually CLOSE valves.

Standard: Operator recognizes that all containment phase B valves are not closed and manually initiates closure from the control room. Operator verifies all containment phase B valves are closed.

Comment: Procedure Step 9, RNO step a.5). All valves will close from the control room.

-V 7. Performance Step: STOP all RCPs.

Standard: Operator stops all RCPs.

Comment: Procedure Step 9, RNO step a.6).

Terminating Cue: JPM Complete 3 of 6

Appendix C Page 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

4 of 6

Appendix C Simulator Setup Form ES-C-1 Simulator Setup LOCA or Large Steam Break in containment.

Containment Pressure> 22 psig.

Containment Spray and Phase B does not actuate automatically.

Containment Spray and Phase B red pushbuttons do not work.

5 of 6

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• LOCA or Large Steam Break in Containment

• 3-E-O; Reactor Trip or Safety Injection completed through step 8.

Initiating Cue:

A LOCA or Large Steam Break in Containment is in progress, 3-E-O; Reactor Trip or Safety Injection has been completed through step 8. You have been directed to continue implementation of 3-E-O.

6 of 6

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Task No:

Task

Title:

Pressurizer Pressure Channel fails low, trip bistables.

KIA

Reference:

012000A4.04 Job Performance Measure RO - 3.3 SRO - 3.3 No: Simulator 8 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• 100% Power.

• PZRZ Pressure Channel Defeat Switch is in the "Defeat Ill and IV" switch position.

Required Materials: 3-ARP-003; Panel SAF Annunciator Alarm Response 3-AOP-INST-1; Instrument/Controller Failures General

References:

3-ARP-003; Panel SAF Annunciator Alarm Response 3-AOP-INST-1; Instrument/Controller Failures Initiating Cue: You are the ATC. Respond to changing plant conditions or events.

Time Critical Task: No Validation Time:

Task Standard: Respond to Alarm Channel PT-456 failing low. Respond to alarms and remove the channel from service IAW 3-INST-1; Instrument/Controller Failures. Trip appropriate bistables.

1of8

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

1. Performance Step: Respond to the following two Panel SAF - Reactor Coolant System alarms using the appropriate alarm response procedure(s):

• "PRESSURIZER LOW PRESS"

• "PRESSURIZER LOW PRESS (SI) CHANNEL TRIP" Standard: Operator acknowledges the annunciators on Panel SAF and enters either or both ARP( s ).

Comment: Annunciator Alarm Response expectations. Student may recognize the failed alarm channel, recognize plant is stable, and then enter 3-AOP-INST-1; Instrument/Controller Failures directly.

2. Performance Step: VERIFY alarm by observing PRZR pressure to determine if a channel or controller has failed.

Standard: Operator observes that Pressurizer Pressure Channel II (PT-456) has failed low. Operator recognizes that this was the alarm channel and observes that pressurizer pressure is stable and remains on program.

Comment: Procedure Step 3.1 (ARP).

3. Performance Step: IF channel or controller failure has occurred, THEN GO TO 3-AOP-INST-1, Instrument/Controller Failures.

Standard: Operator recognizes that a channel failure low has occurred on Pressurizer Pressure Channel II (PT-456).

Operator enters 3-AOP-INST-1, Instrument/Controller Failures.

Comment: Procedure Step 3.2 (ARP).

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark .../)

4. Performance Step: Take manual actions as necessary to control parameters and stabilize the plant.

Standard: Operator recognizes that this was the alarm channel and observes that pressurizer pressure is stable and remains on program. No manual control actions required.

Comment: Procedure Step 3.1 (AOP).

5. Performance Step: Has an instrument failure occurred?

Standard: Operator answers yes and proceeds to the next step. Operator recognizes that a channel failure low has occurred on Pressurizer Pressure Channel II (PT-456).

Comment: Procedure Step 4.1 (AOP).

6. Performance Step: GO TO the applicable step for the indicated failure.

Standard: Operator recognizes a PRZR Pressure channel failure and proceeds to step 4.83.

Comment: Procedure Step 4.2 (AOP).

7. Performance Step: Is PRZR pressure being controlled in auto?

Standard: Operator answers yes and proceeds to the next step.

Comment: Procedure Step 4.83 (AOP).

8. Performance Step: Has Pl-457 failed high?

Standard: Operator answers no and proceeds to step 4.87.

Comment: Procedure Step 4.84 (AOP).

9. Performance Step: Has Pl-474 failed high?

Standard: Operator answers no and proceeds to step 4.89.

Comment: Procedure Step 4.87 (AOP).

3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

-Y10. Performance Step: PERFORM the following for affected instrument using Attachment 5 (Defeating Failed PRZR Pressure Channels)

• Place P/455A PRESS DEFEAT (Rack B-6) in position specified in Table 1 (Black Key).

• Place ~T DEFEAT (Rack B-8) in position specified in Table 2 (Black Key).

Standard: Operator places P/455A PRESS DEFEAT (Rack B-6) in the "OFT CH II Ill" position.

Operator places 3T/411A ~ T Defeat Switch (Rack B-8) in the "OFT CH II" position.

Comment: Procedure Step 4.89 (AOP).

11. Performance Step: Is PRZR pressure recorder transfer switch selected to non-affected channel?

Standard: Operator answers yes and proceeds to next step.

Comment: Procedure Step 4.90 (AOP).

12. Performance Step: Return PRZR heater and spray controls to auto as desired.

Standard: Operator maintains controls in Auto.

Comment: Procedure Step 4.91 (AOP).

13. Performance Step: Refer to Technical Specifications.

Standard: Operator starts to review Technical Specifications per step 4.92.

CUE: STA and the CRS have completed reviewing the Technical Specification actions, step 4.92 may be signed off.

Comment: Procedure Step 4.92 (AOP). Cue operator that step 4.92 is complete.

4 of 8

Appendix C Page 5 Form ES-C-1 v'14. Performance Step: Are ill! redundant bistable status lights for failed instrument listed in Attachment 6 (PRZR Pressure Tables) Table 1 (Page 127) extinguished?

Standard: Operator verifies all redundant bistable status lights are extinguished.

Comment: Procedure Step 4.93 (AOP). Operator overtly points to the extinguished lights. If they don't overtly point, ask them to.

v' 15. Performance Step: Trip bistables for failed instrument listed in Attachment 6 (PRZR Pressure Tables) Table 2 (Page 131).

Standard: Operator trips all required bistables per Attachment 6, Table 2 for Pl-456.

Comment: Procedure Step 4.94 (AOP).

v' 16. Performance Step: Are ill! bistable status lights for failed instrument listed in Attachment 6 (PRZR Pressure Tables) Table 3 (Page 133) illuminated?

Standard: Operator verifies all bistable status lights are illuminated per Attachment 6, Table 3 for Pl-456.

Comment: Procedure Step 4.95 (AOP). Operator overtly points to the illuminated lights. If they don't overtly point, ask them to.

Terminating Cue: JPM Complete 5 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: ~~~~~~~~~~~-

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Any 100% IC PZRZ Pressure Channel Defeat Switch is in the "Defeat Ill and IV" switch position.

Fail Pressurizer Pressure Channel II (selected for alarm)- PT-456 low.

7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• 100% Power.

• PZRZ Pressure Channel Defeat Switch is in the "Defeat Ill and IV" switch position.

Initiating Cue:

You are the ATC. Respond to changing plant conditions or events.

8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Locally Start and Synchronize for Parallel Operation #31 EOG KIA

Reference:

064000A2.03 Job Performance Measure RO - 3.1 SRO - 3.1 No: In-Plant 1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance x Actual Performance Classroom Simulator Plant x READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Unit is at 100% Power

• No equipment is out of service Required Materials: 3-SOP-EL-001; Diesel Generator Operation General

References:

3-SOP-EL-001; Diesel Generator Operation Initiating Cues:

1. The Shift Manager has directed you to manually start 31 EOG, synchronize for parallel operations to 2A Bus, and raise load to 500KW IAW 3-SOP-EL-001; Diesel Generator Operation.

2. All applicable precautions and limitations of 3-SOP-EL-001; Diesel Generator Operation have been reviewed, signed off and met.

3. The pre-start checklist has been completed for 31 EOG.

4. The procedure has been satisfactorily completed and signed off through step 4.1.9.

Time Critical Task: No Validation Time:

Task Standard: 31 EOG started, paralleled with bus 2A and loaded to 500KW.

1 of 12

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: PLACE Lamp Test switch in ON and VERIFY alarm lights operational.

Standard: Place Lamp Test switch to ON and verify alarm lamps illuminated.

Comment: Procedure Step 4.1.10.

CUE: Test switch on, all lamps illuminated.

2. Performance Step: RETURN Lamp Test switch to OFF.

Standard: Place Lamp Test switch to OFF and verify alarm lamps extinguished.

Comment: Procedure Step 4.1.11.

CUE: Test switch OFF, all lamps extinguished .

..,/ 3. Performance Step: VERIFY Lockout Relay switch is RESET.

Standard: The EOG 86 Lockout Relay turned to RESET.

Comment: Procedure Step 4.1.12.

CUE: 86 Relay RESET

4. Performance Step: VERIFY Voltage Regulator Unit-Parallel Switch is in UNIT.

Standard: Verify switch in UNIT Comment: Procedure Step 4.1.13.

5. Performance Step: VERIFY Voltage Regulator Transfer Control switch is in AUTO.

Standard: Verify switch in AUTO Comment: Procedure Step 4.1.14.

2of12

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark "1)

6. Performance Step: VERIFY Local Remote Switch is in LOCAL.

Standard: Verify switch in LOCAL Comment: Procedure Step 4. 1.15.

7. Performance Step: VERIFY the following relay flags on EOG cabinet are reset:

• Reverse Power Relay

• Overcurrent Phase 1, 2 & 3

• Under Over Voltage Relay Standard: Verify all relay flags reset.

Comment: Procedure Step 4.1.16.

8. Performance Step: NOTIFY CCR that EOG will be started in manual.

Standard: Contact CR the EOG will be started.

Comment: Procedure Step 4.1.17.

CUE: Acknowledge as the CCR.

9. Performance Step: IF essential SW pressure is less than 75 psig, THEN START additional pumps, to return SW pressure to 75 psig or greater.

Standard: Verify SW Pressure > 75 psig.

Comment: Procedure Step 4.1.18.

CUE: Service Water Pressure is 80 psig.

3of12

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J10. Performance Step: PLACE Engine Control switch in MAN.

Standard: Engine Control switch in MAN Comment: Procedure Step 4.1.19.

CUE: Engine Control switch in MAN .

...J 11. Performance Step: DEPRESS engine START pushbutton.

Standard: DEPRESS Engine Start pushbutton.

Comment: Procedure Step 4.1.20.

CUE: EOG started .

...J12. Performance Step: WHEN engine speed stabilizes, THEN TEST the Generator frequency response using the Governor Raise Lower Switch as follows:

• RAISE frequency to 61 Hz.

• LOWER frequency to 59 Hz.

• ADJUST frequency to 60 Hz.

Standard: RAISE and LOWER frequency 1.0 Hz using Governor Switch. Return to 60 Hz.

Comment: Procedure Step 4.1.21.

CUE: Frequency increases and decreases 1.0 Hz. Frequency returns to 60 HZ.

4of12

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

-../ 13. Performance Step: TEST Generator Voltage response using the Automatic Voltage Control Rheostat as follows:

• RAISE voltage to 510 volts.

• LOWER voltage to 450 volts.

• RETURN voltage to 480 VAC.

Standard: RAISE and LOWER voltage using Auto Volt Control rheostat. Returns voltage to 480 volts using rheostat.

Comment: Procedure Step 4.2.22.

CUE: Voltage increases and decreases 30 volts. Voltage returns to 480 volts.

14. Performance Step: VERIFY the following Diesel Engine Gage Panel indications:

• Crankcase Exhauster ON light ILLUMINATED.

• Lube Oil Pressure is between 68 and 85 psig

• Fuel Oil Pressure is between 30 and 45 psig (may be as high as 50 psig with EOG unloaded)

• Jacket Water Pressure is between 30 and 35 psig

• Air Manifold Pressure is between 0 and 2 psig (no load)

Standard: Observe the above conditions.

Comment: Procedure Step 4.1.23.

CUE:

• Crankcase exhauster ON

• Lube oil pressure is 73 psig

• Fuel oil pressure is 37 psig

• Jacket water pressure is 32 psig

• Air manifold pressure is 0 psig 5of12

Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

15. Performance Step: VERIFY Diesel Gen. Vent Hood Blower starter indicating light is ON.

Standard: Verifies Hood Blower starter indicating light is energized.

Comment: Procedure Step 4.1.24.

CUE: Light is illuminated.

16. Performance Step: VERIFY SERV WTR COOLING LOW FLOW alarm is clear.

Standard: Verifies alarm not illuminated.

Comment: Procedure Step 4.1.25.

CUE: Alarm not illuminated.

17. Performance Step: RECORD at least one set of running EOG Readings on applicable EOG Data Table.

Standard: Student starts to take readings using Attachment 1, 31 EOG DATA TABLE.

Comment: Procedure Step 4.1.26. Cue operator that readings are complete.

CUE: Attachment 1, 31 EOG DATA TABLE is complete. All readings are SAT.

18. Performance Step: !Ethe Diesel is being run for maintenance AND a shutdown is desired, THEN GO TO Step Error! Reference source not found ..

Standard: Operator recognizes that the step is N/A based on initiating cue and proceeds to section 4.2 of the procedure.

Comment: Procedure Step 4.1.27.

6of12

Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark '\/)

19. Performance Step: NOTIFY CCR that EOG is ready to be synchronized to 480V bus.

Standard: Operator informs CCR that 31 EDG is to be synchronized to 2A bus.

Comment: Procedure Step 4.2.1.

CUE: CCR acknowledges that EOG is ready to be synchronized to 2A bus and directs you to continue synchronization and loading of 31 EOG.

'\/ 20. Performance Step: PLACE Voltage Regulator Unit-Parallel switch in PARALLEL.

Standard: Operator simulates placing Unit-Parallel switch in the parallel position.

Comment: Procedure Step 4.2.2.

CUE: Unit-Parallel switch indicates parallel.

'\/ 21. Performance Step: PLACE applicable Synchroscope switch in ON.

Standard: Operator locates the synchronscope key and simulates turning the correct synchronoscope switch to the on position.

Comment: Procedure Step 4.2.3.

CUE: Synchroscope switch indicates on.

'\/ 22. Performance Step: ADJUST EOG Voltage to match Incoming (EOG) and Running (Bus) AC Volts using the Automatic Voltage Control Rheostat.

Standard: Operator simulates adjusting automatic voltage control rheostat to match EOG voltage to bus voltage.

Comment: Procedure Step 4.2.4.

CUE: EOG and Bus voltage both read 490V.

7of12

Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

-../ 23. Performance Step: ADJUST EOG speed, using the Governor RAISE LOWER switch, to rotate Synchroscope slowly in fast direction.

Standard: Operator simulates adjusting governor so synchroscope rotates slowly in the fast direction.

Comment: Procedure Step 4.2.5.

CUE: Synchroscope is rotating slowly in the fast direction.

-../ 24. Performance Step: WHEN Synchroscope is rotating slowly in fast direction AND indicates approximately 2 minutes before 12 o'clock, THEN CLOSE running EOG output breaker:

Standard: Operator simulates closing the EOG output BKR when the synchroscope indicates two minutes before the 12 o'clock position.

Comment: Procedure Step 4.2.6.

CUE: EOG output BKR indicates closed; Red BKR position light illuminates, green light extinguishes; synchroscope is stationary in the 12 o'clock position.

-../ 25. Performance Step: RAISE load to 50 to 100 KW using Governor Switch.

Standard: Operator simulates increasing load to 50 to 100 KW using the governor switch.

Comment: Procedure Step 4.2.7.

CUE: Load indicates 90 KW.

26. Performance Step: PLACE Synchroscope switch in OFF.

Standard: Operator simulates turning synchroscope switch off.

Comment: Procedure Step 4.2.8.

CUE: Synchroscope control switch indicates off.

8of12

Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J 27. Performance Step: Concurrently PERFORM the following:

• RAISE load using Governor Switch until required load is obtained.

• ADJUST Automatic Voltage Control rheostat to achieve and maintain 350 - 400 lagging KVARS.

Standard: Operator simulates adjusting load with the governor switch and VARS using the voltage control rheostat.

Comment: Procedure Step 4.2.9.

CUE: EOG load indicates 500 KW and VAR meter indicates 400 lagging KVARS.

Terminating Cue: JPM Complete 9of12

Appendix C Page 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

10 of 12

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A, In-Plant JPM 11 of 12

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Unit is at 100% Power

• No equipment is out of service Initiating Cue:

1. The Shift Manager has directed you to manually start 31 EOG, synchronize for parallel operations to 2A Bus, and raise load to 500KW IAW 3-SOP-EL-001; Diesel Generator Operation.

2. All applicable precautions and limitations of 3-SOP-EL-001; Diesel Generator Operation have been reviewed, signed off and met.

3. The pre-start checklist has been completed for 31 EDG.

4. The procedure has been satisfactorily completed and signed off through step 4.1.9.

12 of 12

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Perform a Radioactive Liquid Release IAW 3-SOP-WDS-014 KIA

Reference:

2.3.11 Job Performance Measure RO - 3.8 SRO - 4.3 No: In-Plant 2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance x Actual Performance Classroom Simulator - - - - - - x Plant - - - - -

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

Initial Conditions:

• 31 Monitor Tank has been on recirculation IAW 3-SOP-WDS-006; Monitor Tank Operations and has been appropriately sampled by Chemistry.

• The Most Restrictive Discharge Rate has been determined to be 1980 gpm.

• R-18 is operable and has been source checked satisfactorily.

• The CRS has reviewed the release alignment and release calculations for completeness and signed the release permit authorizing release.

• The Liquid Waste Releases procedure; 3-SOP-WDS-014, has been completed and signed off through step 4.1.14.

Required Materials: 3-SOP-WDS-014; Liquid Waste Releases General

References:

3-SOP-WDS-014; Liquid Waste Releases Initiating Cue: Perform a release of the 31 Waste Monitor Tank IAW 3-SOP-WDS-014, Section 4.1.

Time Critical Task: No.

Validation Time:

Task Standard: Perform a release of the 31 Waste Monitor Tank IAW 3-SOP-WDS-014 and respond to all indications.

1 of 7

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: PLACE RCV-018 permissive to UNBLOCK.

Standard: Operator requests CCR to place RCV-018 permissive in UNBLOCK position.

Comment: Procedure Step 4.1.15.

CUE: RCV-018 permissive in UNBLOCK.

2. Performance Step: OPEN WD-RCV-018, Waste Condensate Discharge to River and PLACE in AUTO.

Standard: Operator requests CCR to OPEN WD-RCV-018 and place in AUTO.

Comment: Procedure Step 4.1.16.

Cue: WD-RCV-018 is OPEN.

3. Performance Step: Operator reviews NOTE and CAUTION prior to step 4.1.17.

Standard: Operator reviews and uses placekeeping.

Comment: NOTE and CAUTION prior to step 4.1.17.

'14. Performance Step: UNLOCK and THROTTLE OPEN WD-1785, Liquid Waste Discharge To River Isolation as necessary to maintain discharge flow rate to less than or equal to the Most Restrictive Discharge Rate from permit (D) as indicated on FT-1064, Release Line Flow Transmitter.

Standard: Operator locates the valve and throttles open. Operator recognizes that per the NOTE and CAUTION, the valve could be completely opened and still not exceed the 120 gpm maximum flow rate.

Comment: Procedure Step 4.1.17. Cue operator flow rate on FT-1064.

CUE: After operator simulates opening WD-1785 and after they view and overtly point to FT-1064, then tell them they read approximately 60 gpm.

(60 x 1.5 = 90 < 120 gpm) 2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

5. Performance Step: THROTTLE as necessary the applicable monitor tank pump discharge to obtain flow on Fl-1064 less than or equal to Most Restrictive Discharge Rate from permit (D).

• CH-1242A; 31 Monitor Tank Pump Discharge Isolation

• CH-12428; 32 Monitor Tank Pump Discharge Isolation Standard: Operator recognizes that an appropriate flow rate has been achieved and that throttling the applicable monitor tank pump discharge valve (CH-1242A) is not necessary.

Comment: Procedure Step 4.1.18. If necessary cue operator that CH-1242A is appropriately throttled, FT-1064 still reads 60 gpm.

CUE: CH-1242A is appropriately throttled, FT-1064 still reads 60 gpm.

6. Performance Step: DETERMINE time required to release previously determined volume.

Standard: Operator calculates an approximate time required to release. Determines based on approximately 85% of tank volume at a release rate of 90 gpm.

Comment: Procedure Step 4.1.19.

7. Performance Step: VERIFY FT-1064 is operable by ensuring a non-zero value is displayed on digital waste release flow meter (55' PAB).

• CIRCLE Yes or No for "Discharge flow meter operable" on permit.

CUE: Report that FT-1064 is now reading zero (0). Appears failed.

Standard: Operator recognizes that the FT-1064 is not reading properly, could be inoperable or could be a lineup issue.

The operator circles No for "Discharge flow meter operable" on permit.

Comment: Procedure Step 4.1.20. Ensure operator acknowledges (3-way communication) that the FT-1064 now reads zero (0).

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

8. Performance Step: IF FT-1064 is inoperable or indicates 0 AND tank level is decreasing, THEN ESTIMATE discharge flow rate at about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> into release by tank level change or pump performance curves and RECORD on permit.

CUE: FT-1064 is reading zero (0) and the 31 Monitor Tank Level is NOT decreasing. Level is staying the same.

Standard: Operator acknowledges that FT-1064 is reading zero (0) and that 31 Monitor Tank Level is NOT decreasing.

Comment: Procedure Step 4.1.20.1. Again ensure 3-way communication is completed regarding the cue.

-'I/ 9. Performance Step: IF FT-1064 is inoperable or indicates 0 AND tank level is NOT decreasing, THEN TERMINATE release and investigate.

Standard: Operator recognizes that the release needs to be terminated and terminates the release. He may call the control room (CCR) directly to close the WD-RCV-018. He may implement Attachment 1O; Monitor Tank Release Termination Alignment.

Comment: Procedure Step 4.1.20.2. Terminate this JPM when he has terminated the release per above standard. He may also locally terminate the release by closing the WD-1785.

CUE: WD-RCV-018 is closed. Release is terminated, this JPM is now complete.

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A In-Plant JPM NOTE: Check on normal values on release permit. Used numbers from ; "Example of Monitor Tank Release Permit." Also assumed that NOTE prior to step 4.1.17 meant that FT-1064 read 60 gpm which is actually 60 x

1.5 90 gpm, not 40 x 1.5 60 gpm?

6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• 31 Monitor Tank has been on recirculation IAW 3-SOP-WDS-006; Monitor Tank Operations and has been appropriately sampled by Chemistry.

• The Most Restrictive Discharge Rate has been determined to be 1980 gpm.

• R-18 is operable and has been source checked satisfactorily.

• The CRS has reviewed the release alignment and release calculations for completeness and signed the release permit authorizing release.

• The Liquid Waste Releases procedure; 3-SOP-WDS-014, has been completed and signed off through step 4.1.14.

Initiating Cue:

Perform a release of the 31 Waste Monitor Tank IAW 3-SOP-WDS-014, Section 4.1.

7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Local Charging Pump Operation from RWST with CCW not available KIA

Reference:

008000A2.01 Job Performance Measure RO - 3.3 SRO - 3.6 No: In-Plant 3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance x Actual Performance Classroom Simulator x Plant - - - - -

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

Initial Conditions:

Following an earthquake:

• The Reactor is Tripped and is being cooled by natural circulation.

• A number of CCR control functions have been lost including the ability to control charging from the control room.

• A loss of all Component Cooling Water has occurred.

Required Materials: 3-SOP-ESP-001; Local Equipment Operation and Contingency Actions General

References:

3-SOP-ESP-001; Local Equipment Operation and Contingency Actions Initiating Cue: The CRS has directed you to start and establish local control of 31 Charging Pump with suction from the RWST and normal B/U City Water aligned for cooling to the charging pump IAW 3-SOP-ESP-001, Sections 4.10 and 4.11.

Time Critical Task: No Validation Time:

Task Standard: Establish local control of 31 Charging Pump with City Water aligned for cooling.

1of7

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

-Y1. Performance Step: VERIFY suction supply is available from VCT or RWST

• VCT (LCV-112C OPEN)

• RWST (LCV-1128 OR 288 OPEN)

Standard: Operator recognizes from initial cue that the CRS directed suction from the RWST. Operator verifies open or simulates opening LCV-1128 or 288.

Comment: Procedure Step 4.10.1 CUE: Neither LCV-1128 or 288 is open. (Note: Once student describes how to open one of these valves, cue them it is now open.)

2. Performance Step: VERIFY CCW is in service to support charging pump operation.

• !E CCW is NOT available, THEN ALIGN city water cooling per Section 4.11, Charging Pump Cooling Using City Water.

Standard: Operator recognizes from initial cue that CCW is not available and proceeds to Section 4.11.

Comment: Procedure Step 4.10.2. Remind operator about initial cue if necessary.

2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

"I/ 3. Performance Step: IF CCW can NOT be established, THEN PROVIDE Normal Backup City Water as follows:

• CLOSE AC-756A, CC Supply Header to Charging Pumps Inlet Isolation.

• CLOSE AC-7568, CC Return Header from Charging Pumps Outlet Isolation.

• OPEN MW-26, City Water Emergency Cooling Supply to Charging Pumps Isolation.

• OPEN AC-701A, Emergency City Water Cooling Supply to Charging Pump Inlet Isolation.

• Verify flange next to AC-7018, Emergency City Water Cooling Return from Charging Pumps Outlet Drain, is REMOVED.

• OPEN AC-7018, Emergency City Water Cooling Return from Charging Pumps Outlet Drain.

Standard: Operator locates and overtly describes (simulates) the positioning of the above valves. The operator then transitions back to step 4.10.2 to complete start and local control of 31 Charging Pump.

Comment: Procedure Step 4.11.1.

CUE: Following the student's overt valve operating description, tell them each valve is in the required I described position. Best to cue following each simulated manipulation.

'14. Performance Step: PLACE speed control of pump(s) to be run to MAN (Charging Pump Speed Control Station PL-6).

Standard: Operator locates and simulates places speed control station to MAN.

Comment: Procedure Step 4.10.3.

CUE: In Manual.

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

-Y 5. Performance Step: ADJUST speed controller to approximately 20% (Charging Pump Speed Control Station PL-6).

Standard: Operator locates and simulates adjusting speed controller to 20%.

Comment: Procedure Step 4.10.4.

CUE: Speed control knob set to 20%.

-Y 6. Performance Step: PLACE charging pump(s) emergency control switch to LOCAL (Charging, Letdown and 31 Pressurizer Heaters Local Control Panel on PL-2).

Standard: Operator locates and simulates placing control switch in LOCAL.

Comment: Procedure Step 4.10.5.

CUE: Control switch is in LOCAL

...J 7. Performance Step: START directed pump(s) via local START pushbutton

{Charging, Letdown and 31 Pressurizer Heaters Local Control Panel on PL-2).

Standard: Operator locates and simulates starting 31 Charging Pump via local pushbutton.

Comment: Procedure Step 4.10.6.

CUE: 31 Charging Pump RUNNING.

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A In-Plant JPM 6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Following an earthquake:

• The Reactor is Tripped and is being cooled by natural circulation.

• A number of CCR control functions have been lost including the ability to control charging from the control room.

• A loss of all Component Cooling Water has occurred.

Initiating Cue:

The CRS has directed you to start and establish local control of 31 Charging Pump with suction from the RWST and normal B/U City Water aligned for cooling to the charging pump IAW 3-SOP-ESP-001, Sections 4.10 and 4.11.

7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Electrical Verification - Offsite Power Sources Surveillance 1940002 .1 .18 Job Performance Measure KIA

Reference:

RO - 3.6

-~~~~~~~-

No: RO Admin 1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - - -

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

Initial Conditions:

• Unit is in MODE 1, 100% Power.

• 6.9 KV Gas Turbine Substation Bus is tagged for an emergent maintenance issue.

• 31 EOG is scheduled to be removed from service or scheduled preventative maintenance activities within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Required Materials: 3-PT-W019; Electrical Verification - Offsite Power Sources and DC Distribution General

References:

3-PT-W019; Electrical Verification - Offsite Power Sources and DC Distribution Initiating Cue: The CRS has requested that you complete surveillance 3-PT-W019; Electrical Verification - Offsite Power Sources and AC Distribution. All procedure precautions, limitations, and prerequisites have been reviewed and signed off. Procedure sections 4.1 and 4.2 have also been completed, including verification that all offsite power feeders are available from the Consolidated Edison District Operator.

Time Critical Task: No Validation Time:

1 of 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Using indications in the simulator and scripted evaluator cues complete procedure sections 4.3 through section 7.0, step 7.1.1.

2of10

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J1. Performance Step: VERIFY 138 K.V. MO. DISC. SW BKR. 5 is Closed (Panel SHF)

Standard: Student locates and verifies breaker is closed and initials step 4.3.1 Comment: Procedure step 4.3.1 .

...J2. Performance Step: VERIFY Station Auxiliary Transformer output voltage as indicated on 6900V Bus Voltmeter (Panel SHF) is between 7.0 and 7.25 kV.

Standard: Student locates and verifies voltage is between 7.0 and 7.25kV. Student initials step 4.3.2.

Comment: Procedure step 4.3.2 .

..,/ 3. Performance Step: VERIFY incoming voltage is indicated on Station Aux High Side Voltage (Panel SHF).

Standard: Student locates and verifies voltage. Student initials step

4.3.3. Comment

Procedure step 4.3.3.

3of10

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark'\/)

4. Performance Step: VERIFY the following with Unit 2 CCR:

• Breaker GT1 at 13.8 kV Gas Turbine Bus is closed.

• Breakers GT2 at 13.8 kV Gas Turbine Bus is closed.

• Unit 2 Appendix R Diesel Generator is NOT only source of power to 13.8KV Gas Turbine Bus Standard: Student makes contact with Unit 2 CCR (simulates), records check marks and initials step 4.4.1.

CUE: Cue student that both breakers (GT1 and GT2) are closed and that Unit 2 Appendix R Diesel is NOT only source of power to 13.8KV Gas Turbine Bus.

Comment: Procedure step 4.4.1.

-V 5. Performance Step: VERIFY either GT-2F or GT-BT is Closed at Panel SHF and supplying Unit 3:

Standard: Student recognizes that both breakers are tagged and open. Student records the position of both as open.

Comment: Procedure step 4.4.2.

6. Performance Step: VERIFY APP R DG is NOT only source of power to 6.9 kV Gas Turbine Substation Bus.

Standard: Student verifies that the APP R DG is NOT only source of power based on cue if necessary. Student initials step 4.4.3.

CUE: Cue student that the APP R DG is NOT only source of power to 6.9 kV Gas Turbine Substation Bus. (Could be confusing because of the bus being tagged out.)

Comment: Procedure step 4.4.3.

4of10

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)

7. Performance Step: VERIFY 6.9kV Gas Turbine Substation Bus Voltage, as indicated at voltmeter on compartment labeled "Incoming Line from 3NBY02" at HSB 53', or at voltmeter labeled "AC Voltmeter Bus" on "Generator Bkr Compt at Appendix R DG is between 6.8 and 7.2 kV.

Standard: Student dispatches an NPO to read voltage locally.

Student acknowledges "O" volts from the field.

CUE: Cue student that local voltage reading is zero (0) volts.

Comment: Procedure step 4.4.4.

~8. Performance Step: VERIFY 6.9 kV buses are aligned and energized as follows:

Standard: Student observes the control console indications an places a check mark next to the normal feeds for each of the 6.9kV buses. Student initials each for each bus.

Comment: Procedure step 4.5.1.

~ 9. Performance Step: !E in Modes 1, 2, 3, or 4, THEN VERIFY Essential Buses are aligned and energized as follows:

Standard: Student observes the control console indications and recognizes that each of the 480V Buses are energized

{STA SERV. TRANS, Supply and Normal Feed Breakers closed) and each 480V bus has acceptable bus voltage.

Student also recognizes that the cross-tie breakers are open in the test position.

Comment: Procedure step 4.6.1. Cue if necessary that the cross-tie breakers are in the test position.

5of10

Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark --./)

10. Performance Step: !E in Mode 5 or 6, THEN VERIFY the necessary Safeguards Buses (2A, 3A, 5A or 6A) required to support LCO 3.8.10 are OPERABLE, by recording energized bus voltages and breaker positions:

Standard: Student N/As the step.

Comment: Procedure step 4.6.2. Unit is in MODE 1.

--./ 11. Performance Step: VERIFY the following MCCs are energized (breakers closed):

Standard: Student observes the control console and determines that MCC 36A through 36E are energized. Student may require a cue for indication of MCC 311. Student should recognize that the MFW Isolation and Bypass valves are powered from MCC 311.

Comment: Procedure step 4.7.1. Cue if necessary that MCC 311 is energized.

12. Performance Step: RECORD date/time test is completed:

Standard: Student records current date/time and initials step 4.8.1.

Comment: Procedure step 4.8.1.

13. Performance Step: Performer Prints name, initials, signs, and dates in Section 5.0.

Standard: Performer Prints name, initials, signs, and dates in Section 5.0.

Comment: Procedure step 5.0.

6of10

Appendix C Page 7 Form ES-C-1 v'14. Performance Step: Offsite AC electrical power sources SHALL be considered OPERABLE in Modes 1 through 4, when the following is satisfied (!E in Modes 5 or 6, THEN "N/A" this table):

Standard: Student circles acceptable YES for all sections (procedure steps) except steps 4.4.1 thru 4.4.4; 6.9kV Gas Turbine Substation Bus energized with voltage between 6.8 and 7.2 kV. Voltage was zero due to the bus being tagged.

Student circles NO for steps 4.4. 1 thru 4.4.4.

Comment: Procedure step 6.1.1.

15. Performance Step: Offsite AC electrical power sources SHALL be considered OPERABLE in Modes 5 and 6, when the following is satisfied (IF in Modes 1 through 4, THEN "N/A" this table):

Standard: Student N/As step.

Comment: Procedure step 6.1.2. Unit is in MODE 1.

v'16. Performance Step: Based on the recorded data, are all Acceptance Criteria of Section 6.1 satisfied for the current plant operating Mode?

Standard: Student circles NO.

Comment: Procedure step 7.1.1. Student may complete the remainder of section 7.0 but it is not necessary.

Terminating Cue: JPM Complete 7of10

Appendix C Page 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

8of10

Appendix C Simulator Setup Form ES-C-1 Simulator Setup Any 100% IC 6.9 KV Gas Turbine Substation Bus is tagged for an emergent maintenance issue.

9of10

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Unit is in MODE 1, 100% Power.

• 6.9 KV Gas Turbine Substation Bus is tagged for an emergent maintenance issue.

• 31 EOG is scheduled to be removed from service or scheduled preventative maintenance activities within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Initiating Cue:

The CRS has requested that you complete surveillance 3-PT-W019; Electrical Verification - Offsite Power Sources and AC Distribution. All procedure precautions, limitations, and prerequisites have been reviewed and signed off. Procedure sections 4.1 and 4.2 have also been completed, including verification that all offsite power feeders are available from the Consolidated Edison District Operator.

10 of 1O

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Hydrogen Recombiner Operation - Determine Required Heater Power KIA

Reference:

1940002.1.25 Job Performance Measure R0-3.9 No: RO Admin 2 Examines: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - - -

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

Initial Conditions:

• Operators are implementing 3-ES-1.2; Post LOCA Cooldown and Depressurization step 27 and are preparing to place 31 Hydrogen Recombiner in service IAW 3-SOP-CB-007; H2 Recombiner Operation.

• 3-SOP-CB-007; H2 Recombiner Operation procedure is completed through step 4.1.4.

• Hydrogen Concentration is 2.2% by volume.

• 4 Containment FCUs are operating and have been operating throughout the accident.

• Current VC Pressure is 3.5 psig.

• Pre-LOCA VC Pressure was 0 psig.

• Pre-LOCA VC Temperature was 90°F Required Materials: 3-SOP-CB-007; H2 Recombiner Operation.

General

References:

3-SOP-CB-007; H2 Recombiner Operation.

Initiating Cue: Determine the Required Heater Power for 31 Hydrogen Recombiner IAW 3-SOP-CB-007. Calculate the value and record on Attachment 4.

Time Critical Task: No 1 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time:

Task Standard: Calculate the Required Heater Power for 31 Hydrogen Recombiner IAW 3-SOP-CB-007, Attachment 4.

2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark .,,/)

1. Performance Step: NOTE the following parameters:

• Current VC Pressure

• Pre-LOCA VC Pressure

• Pre-LOCA VC Temperature Standard: Operator records the above parameter values given as initial conditions.

Comment: Procedure Step 4.1.5 .

.,,/2. Performance Step: DETERMINE Pressure Correction Factor (Cp) using Attachments 1, 2, or 3 as follows:

1. USE applicable attachment that is closest to the Pre-LOCA VC Temperature noted in Step 4.1.5:

• Attachment 1 (60°F)

• Attachment 2 (90°F)

• Attachment 3 ( 120°F)

2. DETERMINE Pressure Correction factor (Cp) for Current VC Pressure noted in Step 4.1.5:

• USE interpolation between Pre-LOCA VC Pressure curves as necessary.

Standard: Operator determines that Attachment 2 (90°F) is applicable. Using 3.5 psig for current VC pressure finds the correction factor to be 1.2 (+/-.005).

Comment: Procedure Steps 4.1.6, 4.1.6.1, and 4.1.6.2. Note that the number should be recorded in the next step .

.../ 3. Performance Step: RECORD Pressure Correction Factor (Cp) determined in Step 4.1.6.2 on Attachment 4.

Standard: Operator records the Pressure Correction Factor (Cp) as 1.2 (+/-.005) on Attachment 4.

Comment: Procedure Step 4.1. 7.

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark "1)

"14. Performance Step: DETERMINE Required Heater Power using Attachment 4 as follows:

1. MULTIPLY Pressure Correction Factor (Cp) (from Step 4.1.7) by Reference Power (Pref) for Recombiner to be placed in service.

2. RECORD calculation on Attachment 4.

Standard: Operator multiplies 1.2 (+/-.005) X 42.3 KW resulting in 50.76 KW(+/-

.2115). Operator records Required Heater Power as 50.76 KW (+/-.2115) on Attachment 4.

Comment: Procedure Step 4.1.8, 4.1.8.1 and 4.1.8.2.

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and d a t e : - - - - - - - - - - - -

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A Classroom Admin JPM 6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Operators are implementing 3-ES-1.2; Post LOCA Cooldown and Depressurization step 27 and are preparing to place 31 Hydrogen Recombiner in service IAW 3-SOP-CB-007; H2 Recombiner Operation.

• 3-SOP-CB-007; H2 Recombiner Operation procedure is completed through step 4.1.4.

• Hydrogen Concentration is 2.2% by volume.

• 4 Containment FCUs are operating and have been operating throughout the accident.

• Current VC Pressure is 3.5 psig.

• Pre-LOCA VC Pressure was 0 psig.

• Pre-LOCA VC Temperature was 90°F Initiating Cue:

Determine the Required Heater Power for 31 Hydrogen Recombiner IAW 3-SOP-CB-007. Calculate the value and record on Attachment 4.

7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Determine Radiological Conditions, RWP Requirements, and Potential Dose KIA

Reference:

1940002.3.7 Job Performance Measure RO Admin 3 R0-3.5 No:

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit is in MODE 1, 100% Power

2. You have been assigned to perform he 31 RHR Pump Functional Test IAW procedure 3-PT-Q134A.

3. You have been provided with a copy of the most recently completed survey of the radiological conditions in 31 RHR Cell when the pump was running for testing.

4. You have been provided with a copy of Radiological Work Permit (RWP) No:

20153002.

Required Materials: Radiological Work Permit (RWP) No; 20153002 31 RHR Cell Radiological Survey Data 3-PT-0134A; 31 RHR Pump Functional Test General

References:

Radiological Work Permit (RWP) No; 20153002 31 RHR Cell Radiological Survey Data 3-PT-Q134A; 31 RHR Pump Functional Test 1of7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: In preparation for a pre-job briefing determine the following from the provided materials:

1. RWP Task Number

2. Dosimetry required

3. Dose Alarm setpoint

4. Dose Rate Alarm setpoint

5. Protective Clothing Requirements

6. Determine Lose Dose Waiting Area in 31 RHR Cell

7. Determine highest contamination reading and location from survey

8. Determine your maximum possible dose using the highest general area dose rate and a stay time of 90 minutes.

9. At what accumulated dose must you leave the RCA in accordance with RWP 20153002?

Time Critical Task: NO Validation Time:

Task Standard: Student uses the RWP and Radiological Survey to properly answer the above questions in preparation for a pre-job briefing.

2 of 7

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark "./)

'\/1. Performance Step: RWP Task Number Standard: Student determines that Task 4 is the proper task for performing tests.

Comment:

-12. Performance Step: Dosimetry required Standard: Student determines that a Whole Body DLR I Electronic Dosimeter is required.

Comment:

"./ 3. Performance Step: Dose Alarm setpoint Dose Rate Alarm setpoint Standard: Student determines that the dose alarm is set at 10.00 mrem and the dose rate alarm is set at 100.00 mrem.

Comment:

'\/4. Performance Step: Protective Clothing Requirements Standard: Student determines that a contaminated entry requires Protective Coveralls, High and Low Shoe covers, Hood, Hard Hat Cover, Cotton Liners and Gloves.

Comment: If asked, cue that HP approval has not been granted for reduced protective clothing requirements.

v5. Performance Step: Determine Lose Dose Waiting Area in 31 RHR Cell Standard: Student determines from survey that the Step off pad (SOP) areas with 0.5 mrem/hr general area dose rates are the low dose waiting areas.

Comment:

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark>/)

...J 6. Performance Step: Determine highest contamination reading and location from survey Standard: Student determines that the pump pedestal area, smear location 13 with a contamination level of 10,000 DPM/cm 2 is the highest level in cell.

Comment:

--./ 7. Performance Step: Determine your maximum possible dose using the highest general area dose rate and a stay time of 90 minutes.

Standard: Student determines that the highest general area radiation level is 2.5 mrem/hr and 90 minutes in that field would result in an accumulated dose of 3.75 mrem.

Comment:

~8. Performance Step: At what accumulated dose must you leave the RCA in accordance with RWP 20153002?

Standard: Student determines that he must leave the RCA at 80% of the accumulated dose alarm setpoint. 80% of 10.0 mrem is 8.0 mrem.

Comment:

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: ~~~~~~~~~~~-

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A RO Admin JPM in classroom 6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. Unit is in MODE 1, 100% Power

2. You have been assigned to perform he 31 RHR Pump Functional Test IAW procedure 3-PT-Q134A.

3. You have been provided with a copy of the most recently completed survey of the radiological conditions in 31 RHR Cell when the pump was running for testing.

4. You have been provided with a copy of Radiological Work Permit (RWP) No:

20153002.

Initiating Cue:

In preparation for a pre-job briefing determine the following from the provided materials:

1. RWP Task Number

2. Dosimetry required

3. Dose Alarm setpoint

4. Dose Rate Alarm setpoint

5. Protective Clothing Requirements

6. Determine Lose Dose Waiting Area in 31 RHR Cell

7. Determine highest contamination reading and location from survey

8. Determine your maximum possible dose using the highest general area dose rate and a stay time of 90 minutes.

9. At what accumulated dose must you leave the RCA in accordance with RWP 20153002?

7 of 7

Indian Point Enerav Center Indian Point Enerav Center

• (tEntetgY.

T~

"Jff.E POWER OF PEOPLE RADIOLOGICAL WORK PERMIT RWP

Title:

Unit 3/NON VC-Operations tours and inspection, watch RWPNo.:

rounds, tests, surveilances, PTO's, peerchecking, training and other 20153002 activities to support unit operations. Rev.00 Comments: Contact HP prior to start of work

• 20153002*

RWP Type: SPECIFIC RWPStatus: Begin Date: Close On Date:

ACTIVE 111/2015 12/31/2015 Prepared By: WILSON, ROBERT Job Supervisor:

All RCA Areas Non VC All Watch NPO rounds and log readings Active 2 COL's, PTO's, walkdowns and peerchecking Active 3 Training & tours Active 4 Functional tests Active Requirement Descriptions Instruction 1: STOP WORK/ ABORT I .Stop work for any unbriefed ED alarms

2. Exit the RCA at 80% of the accumulated dose alarm set point.

3. >30% DAC ifnot posted airborne.

4. If any changes outside of the RWP requirements of job briefing occur.

Instruction 2: Job Coverage:

Intermittent RP coverage- Radiation oversight provided periodically as determined by RP or RWP requirements.

Continuous RP Coverage - Direct radiological surveillance by RP with the sole responsibility for providing constant monitoring during the entire period personnel are in the work area. Continuous surveillance may be provided as follows:

" Locally by maintaining visual or audible contact; OR

" Remotely by maintaining audible and telemetry, with visual contact, if available; OR

" Remotely by using stay times, time keeping, and audible contact.

IF Continuous Job Coverage by RMT is lost THEN re-establish continuous job coverage per EN-RP-141, OR, Suspend work activities and clear personnel from the work area.

~

TAMBURI, ROBIN 12/22/2014 TECHNICIAN BORKOWSKI, MICHAEL NIA

~Entergx TKE POWER OF PEOPLE

'M Indian Point EnerQV Center Indian Point EnerQV Center RADIOLOGICAL WORK PERMIT RWPNo.:

Task Number: 1 20153002 Rev.: 00 Task

Description:

Watch NPO rounds and log readings Task Status: Active Estimate Dose: Estimate Hours:

Hot Particle:

Yes Requirement Groups Requirement Descriptions Contamination Control Additional Requirement:

1. Notify the RP prior to contaminated system opening.

2. Removal of tools from a contaminated area requires RP permission.

3. Notify RP prior to any work in the overhead.

4. Upon exiting Contaminated Areas, worker must perform a hand and foot frisk at the nearest frisker station.

Dosimetry Additional Requirement:

I.Whole Body DLR/ Electronic Dosimeter Exposure Control Additional Requirement:

1. Monitor dosimetry frequently.

2. Utilize Low Dose Waiting Areas.

3. Workers are to be aware for the radiological conditions in their work area.

4. The use of the RP Camera system can be utilized for workers to view work to minimize dose and time in area.

5. DO NOT adjust or move shielding. RP approval required.

Job Coverage Additional Requirement:

Intermittent Precautions & Limitations Additional Requirement:

1) Verbal Radiological brief required for entry into HRA's

2) If dose accrued is expected to exceed 500 mRem, a Stay Time is required.

Protective Clothing Additional Requirement:

1) Contaminated Area Entry: Protective Coveralls, High and Low Shoe Covers, Hood, Hard Hat Cover, Cotton Liners and Gloves.

2) With HP approval, workers may wear partial protective clothing consisting of: High and Low Shoe Covers, Cotton Liners and Gloves while performing work oflow radiological impact. General area contamination levels must be less than 10,000 dpm/100cm2; no climbing or ladder use.

3) High Contaminated Area Entry: Double set of PC's required.

4.)IF working on contaminated components or items that require hand entry only, THEN the RPT may allow the work to ~completed with gloves and other appropriate controls. \

5) If PCs become damaged exit the contari\inated area and contact HP.

RP Personnel Additional Requirement:

1) Particulate and Iodine Air Sampling is required when breaching radioactive systems when contamination is expected to be >50,000 dpm/100cm2.

2) RP escort required for RAM >lOOmr/hr @30cm2.

Rad Worker Training (RWTGEN - RWTSS - PRACFAC)

Instruction 1:

Indian Point EnerQV Center

• EntetgY. ~M Indian Point EnerQV Center TH.E POWE.R OF PEOPLE RADIOLOGICAL WORK PERMIT RWPNo.:

Task Number: 2 20153002 Rev.: 00 Task

Description:

COL's, PTO's, walkdowns and peerchecking Task Status: Active Estimate Dose: Estimate Hours:

Hot Particle: Hi-Contamination:

Hi-Rad: Yes Yes Locked Hi-Rad: No Yes Requirement Groups Requirement Descriptions Contamination Control Additional Requirement:

1. Notify HP prior to contaminated system opening.

2. Removal of tools from a contaminated area requires RP permission.

3. Notify RP prior to any work in the overhead.

4. Upon exiting Contaminated Areas, worker must perform a hand and foot frisk at the nearest frisker station.

Dosimetry Additional Requirement:

1. Whole Body DLR/ Electronic Dosimeter Exposure Control Additional Requirement:

1. Monitor dosimetry frequently.

2. Utilize Low Dose Waiting Areas.

3. Workers are to be aware for the radiological conditions in their work.

4. The use of the RP Camera system can be utilized for workers to view work to minimize dose and time in area.

5. DO NOT adjust or move shielding. RP approval required.

Job Coverage Additional Requirement:

Intermittent Precautions & Limitations Additional Requirement:

1) Verbal Radiological briefrequired for entry into HRA's

2) If dose accrued is expected to exceed 500 mRem, a Stay Time is required Protective Clothing Additional Requirement:

1) Contaminated Area Entry: Protective Coveralls, High and Low Shoe Covers, Hood, Hard Hat Cover, Cotton Liners and Gloves.

2) With HP approval, workers may wear partial protective clothing consisting of: High and Low Shoe Covers, Cotton Liners and Gloves while performing work oflow radiological impact. General area contamination levels must be less than 10,000 dpm/100cm2; no climbing or ladder use.

3) High Contaminated Area Entry: Double set of PC's required.

4.)IF working on contaminated components or items that require hand entry only, THEN the RPT may allow the work to be completed with gloves and other appropriate controls.

5) If PCs become damaged exit the contaminated area and contact HP.

RP Personnel Additional Requirement:

1) Particulate and Iodine Air Sampling is required when breaching radioactive systems when contamination is expected to be >50,000 dpm/100cm2.

2) RP escort for RAM <100rnr/hr@30cm.

TRAINING REQUIREMENT Rad Worker Training (RWTGEN - RWTSS - PRACFAC)

Instruction 1:

~Entergy.

THE POWE.R OF PEOPLE TM Indian Point EnerQV Center Indian Point EnerQV Center RADIOLOGICAL WORK PERMIT RWPNo.:

Task Number: 3 20153002 Rev.: 00 Task

Description:

Training & tours Task Status: Active Estimate Dose: Estimate Hours:

Hot Particle:

Hi-Rad: Yes Yes Locked Hi-Rad:

Requirement Groups Requirement Descriptions Contamination Control Additional Requirement:

1. Notify the RP prior to contaminated system opening.

2. Removal of tools from a contaminated area requires RP permission.

3. Notify RP prior to any work in the overhead.

4. Upon exiting Contaminated Areas, worker must perform a hand and foot frisk as soon as practicable.

Dosimetry Additional Requirement:

1. Whole Body DLR/ Electronic Dosimeter Exposure Control Additional Requirement:

1. Monitor dosimetry frequently.

2. Utilize Low Dose Waiting Areas.

3. Workers are to be aware for the radiological conditions in their work area.

4. The use of the RP Camera system can be utilized for workers to view work to minimize dose and time in area.

5. DO NOT adjust or move shielding. RP approval required.

Precautions & Limitations Additional Requirement:

1) Verbal Radiological brief required for entry into HRA's

2) If dose accrued is expected to exceed 500 mRern, a Stay Time is required Protective Clothing Additional Requirement:

1) Contaminated Area Entry: Protective Coveralls, High and Low Shoe Covers, Hood, Hard Hat Cover, Cotton Liners and Gloves.

2) With HP approval, workers may wear partial protective clothing consisting of: High and Low Shoe Covers, Cotton Liners and Gloves while performing work oflow radiological impact. General area contamination levels must be less than 10,000 dpm/100cm2; no climbing or ladder use.

3) High Contaminated Area Entry: Double set of PC's required.

4.)IF working on contaminated components or items that require hand entry only, THEN the RPT may allow the work to be completed with gloves and other appropriate controls.

5) If PCs become damaged exit the contaminated area and contact HP.

TRAINING REQUIREMENT Instruction 1:

Instruction 2:

Instruction 4:

Instruction 5:

Indian Point Enerav Center

• Entergx 'M Indian Point Enerav Center TKE POWE.R OF PEOPLE RADIOLOGICAL WORK PERMIT RWPNo.:

Task Number: 4 20153002 Rev.: 00 Task

Description:

Functional tests Task Status: Active Estimate Dose: Estimate Hours:

Hi-Contamination:

Yes Contamination Control Additional Requirement:

1. Notify the RP prior to contaminated system opening.

2. Removal of tools from a contaminated area requires RP permission.

3. Notify RP prior to any work in the overhead.

4. Upon exiting Contaminated Areas, worker must perform a hand and foot frisk as soon as practicable.

Dosimetry Additional Requirement:

I.Whole Body DLR/ Electronic Dosimeter Exposure Control Additional Requirement:

1. Monitor dosimetry frequently.

2. Utilize Low Dose Waiting Areas.

3. Workers are to be aware for the radiological conditions in their work area.

4. The use of the RP Camera system can be utilized for workers to view work to minimize dose and time in area.

5. DO NOT adjust or move shielding. RP approval required.

Precautions & Limitations Additional Requirement:

1) Verbal Radiological brief required for entry into HRA's

2) If dose accrued is expected to exceed 500 mRem, a Stay Time is required Protective Clothing Additional Requirement: 1) Contaminated Area Entry: Protective Coveralls, High and Low Shoe Covers, Hood, Hard Hat Cover, Cotton Liners and Gloves. *

2) With HP approval, workers may wear partial protective clothing consisting of: High and Low Shoe Covers, Cotton Liners and Gloves while performing work of low adiological impact. General area contamination levels must be less than 10,000 dpm/100cm2; no climbing or ladder use.

3) High Contaminated Area Entry: Double set of PC's required.

4.)IF working on contaminated components or items that require hand entry only, THEN the RPT may allow the work to be completed with gloves and other appropriate controls.

5) If PCs become damaged exit the contaminated area and contact HP.

RP Personnel Additional Requirement:

1) Particulate and Iodine Air Sampling is required when breaching radioactive systems when contamination is expected to be >50,000 dpm/100cm2.

2) RP escort for RAM <100rnr/hr@30cm.

TRAINING REQUIREMENT Rad Worker Training (RWTGEN - RWTSS - PRACFAC)

Instruction 1:

Instruction 2:

Survey: IPEC-1503-0004 Printed: 03-26-2015 09: 13:22 Indian Point Template: U3 PAB 15FT 31 RHR Cell Page 1 Smear Data (DPM/100cm2) Survey Data 1 <MDA Unit: 3 2 <MDA Building: U3 PAB 3 <MDA Elevation: 15FT SOP 4 Room: 31 RHR Cell 318.06 5 <1000 RxPwr: 96 6 1000 Template: U3 PAB 15FT 31 RHR C 7 <1000 Frequency: Other 8 2000 Survey Date: 03-01-2015 9 2000 Survey Time: 15:04 10 3000 11 1000 Status: Archived SEAL RWP: 20153001 12 3000 Surveyed By: Delamater, Jesse Pedestal Badge: 1234 13 10000 Reviewed By: Phelps, Tom Leaking valve Notes:

14 3000 Survey of 31 RHR following a 15 <1000 pump run. Cell posted RA 16 <1000 17 <1000 Instruments Used 18 <1000 19 <1000 Instrument: R0 01617 20 <MDA SOP Cal Due: 04-30-2015 I I SrcCk Date: 03-01-2015 LAS Data (ccpm/LAS) DIC & Bkg: na na 1 ND MDA: NA B/G to Alpha Ratio Instrument: BC 932 12 NA 14 NA Cal Due: 01-31-2016 SrcCk Date: 03-01-2015 Alpha Data (DPM/100cm2)

DIC & Bkg: 5.89 26 U3PAB15FT 31 RHR 12 ND MDA: 116 14 ND Instrument: RM 5213 Cal Due: 10-31-2015 SrcCk Date: 03-01-2015 DIC & Bkg: 10 100 MDA: NA Instrument: SAC-4 -1376 All Radiation values are in mrem'hr unless otherwise noted 12.5 denotes gamma general area, T denotes RADS telemetry Smear contamination values in DPM'100cm2 unless otherwise noted *75 B denotes beta contact doserate Cal Due: 08-31-2015

[J Smear< 1000 DPM HS. - denotes Hot Spot *12 denotes gamma contact doserate SrcCk Date: 03-01-2015

• 12113 denotes gamma contact I 30cm {11> denotes smear locations DIC & Bkg: 3.99 .28

• 12113 B denotes beta contact I 30 cm [i] denotes large area wipe locations. MDA: 18

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Perform Initial Unusual Event Notification KIA

Reference:

1940002.4.39 Job Performance Measure R0-3.9 No: RO Admin 4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - - -

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

Initial Conditions:

• A 15 GPM UNIDENTIFIED RCS Leak exists.

• Unit Shutdown IAW Technical Specifications has been initiated.

• The Shift Manager Declared an UNUSUAL EVENT based on EAL-SU6.1 five (5) minutes ago.

Required Materials: Simulator RECS phone Completed NYS Radiological Data Form Part 1 Form EP-3N; NOTICE OF UNUSUAL EVENT Notification checklist General

References:

IP-EP-115 Form EP-3, NUE Notification Checklist Initiating Cue: You are the Spare RO, and the Shift Manager has directed you to perform the duties of the Control Room Offsite Communicator.

Time Critical Task: YES Validation Time:

Task Standard: Notification of event complete to State and Counties within 15 minutes of event declaration by Shift Manager.

1 of 9

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -/)

1. Performance Step: Obtain the Control Room Communicator Binder Standard: Obtains Binder from Shift Manager Office Comment: Provide student copy of Form EP-3N; NOTICE OF UNUSUAL EVENT Notification checklist CUE: Provide student copy of Form EP-3N; NOTICE OF UNUSUAL EVENT Notification checklist if necessary. Includes Page 1 completed by Shift Manager. (After he finds the Binder)

2. Performance Step: Inform the Shift Manager that you have assumed the duties of the Control Room Communicator.

Standard: Student informs the Shift Manager they have assumed the duties of the Control Room Communicator.

Comment: CUE: Acknowledge communication .

...J 3. Performance Step: Obtain the completed and signed NTS Radiological Emergency Data Form Part 1 (IP-EP-115 Form EP-1)

Standard: Student requests Form from the Shift manager.

Comment: Provide competed and signed form EP-1.

CUE: Provide Candidate the completed EP-1 Form. Mark the Emergency Declaration time on the form as present date and present time minus 5 minutes. Record Time minus 5 here:

4. Performance Step: Review the form to ensure all required information is entered including the Shift Manager (Emergency Director)

Signature.

Standard: Student determines all necessary data is correctly entered.

Comment:

2 of 9

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

5. Performance Step: Verify Shift Manager has sent electronic Fax and e-mail of the NYS Radiological Emergency Data Form Part 1 to the State/Counties.

Standard: Student either contacts Shift Manager or reviews page 1 of the NOTICE OF UNUSUAL EVENT Notification Checklist and observes that the Shift Manager has initialed the appropriate steps of the bottom of page 1 (Form EP-3N) indicating completion of Fax & e-mail of EP-1.

Comment: Student initials the top line of page 2 of Form EP-3N. If necessary provide cue.

CUE: Fax and e-mail have been sent.

-../ 6. Performance Step: Pick up RECS Handset.

Standard: Student picks up the RECS Handset.

Comment: Note that this is step 1 on page 2 of the NUE Notification Checklist.

...J 7. Performance Step: When you hear the message "Welcome to Wave. Please enter session ID", Depress the "7" button.

Standard: Student depresses the "&" button on the phone.

Comment: Step 2 on page 2 of the NUE Notification Checklist.

8. Performance Step: IF RECS is unavailable, proceed to Alternate State and County Notification on Page 4 of 6.

Standard: Step is N/A, RECS is available and functioning.

Comment: Step 3 on page 2 of the NUE Notification Checklist. Cue that the RECS is available and functional if necessary.

3 of 9

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

,/ 9. Performance Step: You will hear multiple rising tones, indicating facilities joining the call. Wait 15 seconds and State: "This is to report an event at Indian Point Energy Center.

Standby for roll call." Twice.

Standard:

• After 15 seconds, student states: 'This is to report an event at Indian Point Energy Center. Standby for roll call." Twice.

Comment: Step 4 on page 2 of the NUE Notification Checklist.

'110. Performance Step: Initiate roll call by asking "(location title) are you on the line?" for each of the following stations, stopping after each name is read to allow station to identify itself. Check off each location as they answer the roll call:

1. New York State

2. Westchester County

3. Putnam County

4. Rockland County

5. Orange County

6. Peekskill City

7. West Point Standard: Reads each station name, when station acknowledges, checks it on the NUE Notification Checklist.

Comment: Steps 5 and 6 on page 2 of the NUE Notification Checklist.

CUE: If using the booth operator to acknowledge message, no CUE is needed (provided by booth operator). If acknowledging yourself then CUE candidate by acknowledging as each station above.

'1 11. Performance Step: Enter time you receive the first response on the initial roll call: - - - - -

Standard: Student enters time on step 6 of the NUE Notification Checklist. (first response)

Comment: Step 6 on page 2 of the NUE Notification Checklist.

4 of 9

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

...J 12. Performance Step: State, "This is the Indian Point Energy Center. An Unusual Event has been declared. A Part 1 Notification# 1 has been sent to you via FAX And/or Email."

Standard: Student reads statement.

Comment: Step 7 on page 2 of the NUE Notification Checklist.

...J 13. Performance Step: Confirm the receipt of FAX or Email by asking:

"(location Title), do you acknowledge receipt of a FAX OR Email from IPEC?"

1. New York State

2. Westchester County

3. Putnam County

4. Rockland County

5. Orange County

6. Peekskill City

7. West Point Standard: Reads roll call list and asks for acknowledgement. Checks off each station when acknowledgement is received.

Comment: Step 8 on page 2 of the NUE Notification Checklist.

CUE: If using the booth operator to acknowledge message, no CUE is needed (provided by booth operator). If acknowledging yourself then CUE candidate by acknowledging as each station above.

14. Performance Step: IF any of above did not receive either a FAX OR Email, THEN verbally read the entire Part 1 form. IF all locations received (or you completed reading) proceed.

Standard: Student proceeds to next step, all locations received FAX and/or Email.

Comment: Step 9 on page 2 of the NUE Notification Checklist.

5 of 9

Appendix C Page 6 Form ES-C-1

....J 15. Performance Step: End notification by saying "Indian Point out at "

Enter time. Press "End Call" button on RECS phone and hang up the handset, ensuring it is secured in the cradle.

Standard: Student makes above statement and enters current time on line 10. The time entered at checklist step 10 must be within 15 minutes of the time of declaration used for the Part 1 form (EP-1 ).

Comment: Step 1O on page 2 of the NUE Notification Checklist.

Terminating Cue: JPM Complete 6 of 9

Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

7 of 9

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A RO Admin JPM 8 of 9

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• A 15 GPM UNIDENTIFIED RCS Leak exists.

• Unit Shutdown IAW Technical Specifications has been initiated.

• The Shift Manager Declared an UNUSUAL EVENT based on EAL-SU6.1 five (5) minutes ago.

Initiating Cue:

You are the Spare RO, and the Shift Manager has directed you to perform the duties of the Control Room Offsite Communicator.

THIS IS A TIME CRITICAL JPM.

9 of 9

New York State Indian Point Energy Center

---

* -* ------- *- -- ----*--------~~ ._ ..,_ --~-----~-- --*-----~---------------

-RADIOtOGICP\t £MERGE:NCYDATAf'ORM =-PART1-~*- ~-- -- --Notification*#--+/----*+*

( 1. This is an: EXERCISE ACTUAL EMERGENCY at the Indian Point Energy Center The Emergenc~ CA Unusu~IE~ B. Alert c. Site Area Emergency Classification is:

D. General Emergency E. Emergency Terminated 2.

This Emergency Classification declared on: f1.{4~ at -r24""'hr'"clock)

-r(Time iv/.e ,,c (D e)

Release of Radioactive Materials due to the Classified Event To Atmos12here: To Water:

i.---:-**

c~NO Release> ( A NO Release 3.

B. Release BELOW Federal Limits B. Release BELOW Federal Limits C. Release ABOVE Federal Limits C. Release ABOVE Federal Limits D. Unmonitored Release Requiring Evaluation D. Unmonitored Release Requiring Evaluation The following Protective Actions are recommended to be implemented as soon as practicable:

CA. NO NEED for PROTECTIVE ACTIONS outsiae f~ boundary:)

B. EVACUATE and IMPLEMENT the Kl PLAN for the following Sectors C. SHELTER-IN-PLACE and IMPLEMENT the Kl PLAN for the following Sectors

4. 2 miles around 5-miles downwind:

In the following Sectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 2 miles around 10-miles downwind:

In the following Sectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM NOTE: OFFSITE AUTHORITIES SHOULD CONSIDER SHELTER-IN-PLACE+ TAKE Kl IF EVACUATION IS NOT FEASIBLE EAL#: S{A 6, I _ .. IJ. II! 1J-c;/rrf *1:-'J .1.1\, flt1J;i'J*1(1£' 13ovir.IP.'Af'"'J L111111.t,J-f > 10 6P."1

< Affected Location:

A Ir t,,p.--......, i,,ftJ /{);,J71ftf-O e...u L-C1tit... &1.S.-<f'J 1rl c'() rJrt. r.Jf>\i ~ \ A UNIT 2'

~

5.

(oJtr J J.> 'ITT/) 0 ;I J 5""{J."' -rr:tAi t-11tr,. \... c.

.ff i.t:- 1.fi Jt-f'vwUf NA! i3 r: t..J r hr/rt"lfl>.

C. IPEC SITE Reactor Status:

6. Unit 2~tionor Shutdown at (Date) fHWJ (Time) +-j ~k?f ... (24 hr clock)

Unit 3:~~tio~ or Shutdown at (Date) Ntj (Time) -t- J ~PJ-.... (24 hr clock)

7. Wind SQeed: e.~ Meters/Sec at elevation 10 meters

8. Wind Direction: (From} ~X'r Degrees at elevation 10 meters

9. Stabilitv Class: A B @ D E F G

10. Reported by - Communicator: Telephone#

(Communicator's Name)

11. Emergency Director Approval: ('G/t1P Date/Time: _f~;,;~ -+-s~~~

(Directofs Name)

Page 1 of 1 Form EP-1, Rev 5

Control Room Shift Mai. 4 er/Emergency Director NOTICE of UNUSUAL EVENT Notification Checklist NUE DECLARED?

If the Shift Manager does not feel it is safe to relocate personnel at this time, DO NOT sound the Site Assemblv Alarm or call for Time of Declaration: ...rA-.~*'- t'i~o Time: _ _ _ _ _ _ _ __

ONSITE NOTIFICATION

~Designate OR Page an Offsite Communicator to the Control Room. UPDATE: (30 minutes)

.&l_Contact opposite unit's Control Room AND: __EOF is NOT operational; go to

1. Inform them of NUE, time, EAL#, and brief description. "OFFSITE NOTIFICATION" step.

2. Activate OR Request opposite unit to activate Emergency Response OR Organization (ERO) Event Notification Only OR ERO mobilization by __ EOF is operational, STOP. (EOF will obtaining ERO Notification envelope AND completing steps in envelope. continue with Notifications; ensure

3. (Both units) Direct announcement of the following message over both Unit's proper turnover completed)

P.A. systems, three (3) times: (IF determined SAFE to do so)

~ "Attention all personnel. An NUE has been declared. Staffing of facilities (is/GJiOt} required."

~f ,,,o If staffing of facilities (EOF/OSC/TSC/JIC/AEOF) is required, state the following:

"The following facilities are required to be staffed: k iJ ll!1 (fill in with appropriate f a c i l i t i e s . ) /

lf~ Go to "OFFSITE NOTIFICATION" step OFFSITE NOTIFICATION VERIFY the following:

11Ji* NYS Part I Form is completed AND printed.

f( NYS Part I Form is independently verified.

~NYS Part I Form is signed for approval.

jt_NYS Part I Form is electronically sent via FAX, then Email

_Offsite Agencies are being notified by the Offsite Communicator or designee using page 2- 6 within 15 minutes of an initial OR new declaration OR aooroximatelv 30 minutes for an uodate. (see Time above NUE Checklist Page 1 of 6 Form EP-3N Rev 4

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Update Electrical Power Availability for Shutdown Safety Assessment KIA

Reference:

1940002.1.18 Job Performance Measure SROAdmin SR0-3.8 No: 1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - - -

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

Initial Conditions:

• Unit Shutdown in progress due to 32 EDG inoperable and extensive maintenance and repair required to restore operability.

• The Unit has just entered MODE 4.

• The shift has just completed tagging out the 6.9 KV Gas Turbine Substation Bus due to an emergent issue.

• No Substation Work is in progress.

Required Materials: 6.9 KV Gas Turbine Substation Bus Tagout Marked up drawing 9321-F-33853 IP-SMM-OU-104, Shutdown Risk Assessment Procedure Completed IP-SMM-OU-104, Attachment 9.1 Blank IP-SMM-OU-104, Attachment 9.1 General

References:

Drawing 9321-F-33853, Electrical Distribution & Transmission System IP-SMM-OU-104, Shutdown Risk Assessment Procedure Initiating Cue: Given the above initial conditions, the Shift Manager has requested that you update the Electrical Power Availability section of the previously completed Shiftly Shutdown Safety Assessment in accordance with IP-SMM-OU-104.

You have been provided a copy of the recently completed tagout.

1 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time:

Task Standard: Update IP-SMM-OU-104, Attachment 9.1 to show that Electrical Power Availability is now YELLOW from a Shutdown Risk perspective. The Score should be a 5 which would constitute a YELLOW condition.

1. Number of Emergency Diesel Generators Available - (Two) - 2 pts

2. Offsite Power Sources Available - (One)- 1pt

3. Switchyard work in progress - (No) - 1pt

4. Outage Unit's Appendix R Diesel Available - (No) - Opts

5. Severe weather OAP-008 in Effect with the potential for Loss of Offsite Power - (No)

- 1 pt.

Total Points =5 or YELLOW Condition NOTE: The tagout for the 6.9KV Gas Turbine Substation Bus causes a loss of all available 13.8KV (credited offsite source) and the Unit 3 Appendix R Diesel.

2 of 8

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: Student reviews previously completed IP-SMM-OU-104, Attachment 9.1.

Standard: Student recognizes that per the initiating cue, that only the electrical section requires updating.

CUE: All other aspects of the Shutdown Safety Function Assessment remain unchanged, only the electrical portion requires updating. Complete just the Electrical Power Availability section on a blank Attachment 9.1.

Comment: Provide cue and blank form. Cue may be provided as a group in a classroom setting.

'12. Performance Step: Student completes the Number of Emergency Diesel Generators Available line and assigns points per the procedure.

Standard: Student recognizes that only 32 EDG is unavailable and assigns 2 points.

Comment: >=Two Diesels Available is 2 points .

..,/ 3. Performance Step: Student completes the Offsite Power Sources Available line and assigns points per the procedure.

Standard: Student recognizes that no 13.8KV Offsite sources are available and assigns 1 point.

Comment: One (1) is 1 point. Attachment 9.2 guidance states only 1 source of 138KV is credited regardless of the number of live feeders.

3 of 8

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

'14. Performance Step: Student completes the Switchyard work in progress line and assigns points per the procedure Standard: Student recognizes that No Switchyard work is in progress. The tagout is complete and No Substation work is in progress per the initial conditions.

He assigns 1 point.

Comment: No switchyard work in progress results in 1 point. Attachment 9.2 guidance states: NOTE: If mitigating actions have been taken such that the work being performed can no longer be viewed as potential for inducing a LOOP event, then Attachment 1 "Switchyard Work In Progress" Power Availability Safety Function question should be recorded as a NO.

-,/ 5. Performance Step: Student completes the Outage Unit's Appendix R Diesel Generator Available line and assigns points per the procedure.

Standard: Student recognizes that the Appendix R Diesel is unavailable and assigns zero (0) points.

Comment: Student recognizes that the tagout precludes the use of the Appendix R

=

Diesel. No Appendix R Diesel O points.

-,/ 6. Performance Step: Student completes the Severe weather OAP-008 in Effect with the potential for Loss of Offsite Power line and assigns points per the procedure.

Standard: Student recognizes that Severe weather OAP-008 is not in effect and assigns 1 point.

Comment: Severe weather OAP-008 Not in effect =1 point.

4 of 8

Appendix C Page 5 Form ES-C-1

...J 7. Performance Step: Student completes the Electrical Power Availability Score by adding the respective points and determines the shutdown color for Electrical Power.

Standard: Student adds the numbers and determines a Total of 5 points and a YELLOW Condition.

Comment: Total should add to 5 points and a YELLOW Condition.

Terminating Cue: JPM Complete 5 of 8

Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

6 of 8

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A, SRO Admin JPM 7 of 8

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Unit Shutdown in progress due to 32 EOG inoperable and extensive maintenance and repair required to restore operability.

• The Unit has just entered MODE 4.

• The shift has just completed tagging out the 6.9 KV Gas Turbine Substation Bus due to an emergent issue.

• No Substation Work is in progress.

Initiating Cue:

Given the above initial conditions, the Shift Manager has requested that you update the Electrical Power Availability section of the previously completed Shiftly Shutdown Safety Assessment in accordance with IP-SMM-OU-104. You have been provided a copy of the recently completed tagout.

8 of 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Determine Isolation Boundaries for CCW Leak Using Plant Prints KIA

Reference:

1940002.2.41 Job Performance Measure SRO Admin SR0-3.9 No: 2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -

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

Initial Conditions:

• The plant is in COLD SHUTDOWN on RHR.

• CCW Surge Tank level is lowering at approximately 0.5% per minute.

• The NPO in Containment reports a significant leak downstream of Check Valve 770; CCW Supply to RCPs.

Required Materials: NEED DRAWING NUMBERS General

References:

NEED DRAWING NUMBERS Initiating Cue: You are the FSS and the CRS has directed you to identify all valves that must be shut to isolate the leak just on Check Valve 770; CCW Supply to RCPs. Identify valves needed for isolation and list below.

Time Critical Task: No.

Validation Time:

Task Standard: Using appropriate plant drawings, identify and list the valves required to isolate a leak on Check Valve 770; CCW Supply to the RCPs.

1 of 5

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark .../)

1. Performance Step: Obtain Prints Standard: Operator requests desired prints.

Comment: Plant drawings to be provided in classroom or operator may select appropriate drawings from a controlled file in simulator.

.../2. Performance Step: Determine MOV-769 and/or MOV-797 must be shut.

Standard: Identifies that MOV-769 and/or MOV-797, RCP CCW Supply Isolation must be shut.

Comment: Operator lists these valves on the cue sheet as requiring isolation .

.Y 3. Performance Step: Determine 734C must be shut.

Standard: Identifies 734C, Rx Vessel Support Blocks supply must be shut.

Comment: Operator lists this valve on the cue sheet as requiring isolation .

.../4. Performance Step: Determine 771A-D must be shut.

Standard: Identifies 771A-D, CC Supply (individual RCP) Inlet Isolations must be shut.

Comment: Operator lists these valves on the cue sheet as requiring isolation.

5. Performance Step: Determine Isolation Valve Seal Water System Valve????,

RCPs Cooling Water Inlet Stop must be closed.

Standard: Identifies Isolation Valve Seal Water System Valve ????, RCPs Cooling Water Inlet Stop must be closed.

Comment: Student may or may not identify this valve for isolation. This step is NOT critical. Operator lists this valve on the cue sheet as requiring isolation.

Terminating Cue: JPM Complete

. 2 of 5

Appendix C Page 3 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

3 of 5

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A Classroom Admin JPM 4 of 5

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is in COLD SHUTDOWN on RHR.

• CCW Surge Tank level is lowering at approximately 0.5% per minute.

• The NPO in Containment reports a significant leak downstream of Check Valve 770; CCW Supply to RCPs.

Initiating Cue:

You are the FSS and the CRS has directed you to identify all valves that must be shut to isolate the leak just on Check Valve 770; CCW Supply to RCPs. Identify valves needed for isolation and list below.

5 of 5

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Review Completed 33 Service Water Pump Surveillance KIA

Reference:

1940002.2.12 Job Performance Measure SRO Admin SR0-4.1 No: 3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -

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

Initial Conditions:

• An NPO has just completed performing the 33 Service Water Pump Surveillance in accordance with 3-PT-Q092C.

• The completed surveillance has not been peer reviewed.

Required Materials: Completed 3-PT-Q092C; 33 Service Water Pump In-service Test.

General

References:

Completed 3-PT-Q092C; 33 Service Water Pump In-service Test.

Initiating Cue: Review the completed 33 Service Water Pump Surveillance for accuracy and then complete section 7.0, Test Acceptance. Document any discrepancies found if any.

Time Critical Task: NO Validation Time:

Task Standard: Student reviews the completed surveillance, notes any errors, and determines operability status.

1of6

Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

1. Performance Step: Calibration due dates recorded and instruments within calibration?

Standard: Student recognizes that all required calibration due dates are recorded and the instruments used are within calibration.

Comment: Calibration data recorded in step 3.1. All dates are SAT.

2. Performance Step: All required procedure steps completed?

Standard: Student recognizes that all steps have been completed or properly designated N/A per procedure use guidelines.

Comment: All procedure steps completed or properly designated N/A per procedure use guidelines .

...J 3. Performance Step: All calculations correct?

Standard: Student recognizes that the 33 SWP ~p in psid has been improperly calculated in step 4.2.17. Student recognizes that the NPO subtracted the Suction Pressure Head value recorded in step 4.2.16 instead of adding that value to the recorded pump discharge pressure recorded in step 4.2.13. NPO came up with a value of 80.56 psid instead of the correct value of 87.44 psid.

Comment: Student may realize here that this means the pump is not in alert. Student may also determine that the pump surveillance needs to be run again with supervisory oversight to ensure operability.

4. Performance Step: All data properly transcribed?

Standard: Student recognizes that all data has been properly transcribed, but also recognizes that the real pump ~p value should have been 87.44 psid.

Comment: All other data has been properly transcribed.

2 of 6

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

..,/ 5. Performance Step: Operability conclusions correct?

Standard: Student recognizes that the 33 SWP ~ P in psid has been improperly calculated in step 4.2.17. Student may realize here that this means the pump is not in alert. Student may also determine that the pump surveillance needs to be run again with supervisory oversight to ensure operability.

Comment: Key is that the student recognizes that the ~p has been incorrectly calculated and that action is required to correct the error. Student may just make pen & ink corrections to step 4.2.17 and the recorded values I conclusions in Section 6.0 .

.../ 6. Performance Step: Complete Section 7.0; Test Acceptance Standard: Student completes Section 7.0; Test Acceptance using the corrected ~p value of 87.44. Student determines pump is in the acceptable range for all parameters including ~P. (80.1 :::; psid:::; 87.6)

Comment: Student recognizes that the pump meets the IST required values for vibration and ~P. If student wants to re-run surveillance, cue the student to use the corrected ~ P value and complete Section 7 .0 of the Surveillance.

Terminating Cue: JPM Complete 3 of 6

Appendix C Page 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

4 of 6

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A SRO Admin JPM in classroom 5 of 6

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• An NPO has just completed performing the 33 Service Water Pump Surveillance in accordance with 3-PT-Q092C.

• The completed surveillance has not been peer reviewed.

Initiating Cue:

Review the completed 33 Service Water Pump Surveillance for accuracy and then complete section 7.0, Test Acceptance. Document any discrepancies found if any.

6 of 6

Procedure Use Is: Contro ICopy: .'

!(.,,~

-1 *1 *"

r\lCV l;.,, ~

t, li'.'.f Continuous D Reference Effective Date: {1 :J0* *'/fr.,'* ~.tfi*

D Information Page 1 of 43 3-PT-Q092C, Revision 15 33 SERVICE WATER PUMP Approved By:

h,.IJ\'":7,/ It')  :]pre, (4>p*W'~ Q.9~

RPO or Des~l Print Name I Sign I Date Team 30 Procedure Owner EDITORIAL REVISION

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 2 of 43 REVISION

SUMMARY

(Page 1 of 1)

~ REASON FOR REVISION

@ Incorporated changes due to CR-IP3-2013-0417 4 [IP3-11715].

SUMMARY

OF CHANGES Made some wording and punctuation corrections, no rev bars [Editorial change per IP-SMM-AD-102, step 4.6.1].

Revised Acceptance Criteria values in steps 6.1.1 and 6.1.3 (from 79. 1 s; psid s; 87.6 to 80.1 s; psid s; 87.6); due to IST Engineer feedback (IP3-11715) [Editorial change per step 4.6.13].

Added "Calculation No. IP-CALC-13-00063" to Development Docs step 9.2.15 [Editorial change per IP-SMM-AD-102, step 4.6.11].

Deleted 'old' step 10.2 (Documentation) since this test does not produce any documents required for the IPEC Records Retention Schedule

[Editorial change per step 4.6.12].

Per EN-Ll-100, Rev. 10, Section 5.2 [4], changes to those portions of the lnservice Inspection and lnservice Testing Programs that are controlled in accordance with 10 CFR 50.55a do not require PAD review.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP I Page 3 of 43 TABLE OF CONTENTS Section Title Page PURPOSE ....................................................................................................... 4 PRECAUTIONS AND LIMITATIONS ................................................................ 5 PREREQUISITES ............................................................................................. 8 PROCEDURE ................................................................................................... 9

~ Initial Conditions ...................................................................................... 9

~ Test Of 33 Service Water Pump .............................................................. 9

~Test Of Zurn Strainer and SWN-PCV-1207, 33 SWP Zurn Strainer Slowdown Valve .................................................................................... 21

~- Restoration ............................................................................................ 23

~ COMMENTS: .................................................................................................. 24

~ ACCEPTANCE CRITERIA. ............................................................................. 25 7.0 TEST ACCEPTANCE ..................................................................................... 26 8.0 EVALUATION ................................................................................................. 29

9.0 REFERENCES

............................................................................................... 29 10.0 RECORDS AND DOCUMENTATION ............................................................. 30 Attachments:

ATTACHMENT 1 Placing SW Flow Indicator Fl-1142 In-Service for 33 SWP .......... 31 A TIACHMENT 2 Placing an Alternate SW Flow Indicator In-Service for 33 SWP ... 33 ATTACHMENT 3 Placing SW Flow Indicator Fl-1144 In-Service for 31 SWP .......... 35 ATTACHMENT 4 Placing an Alternate SW Flow Indicator In-Service For 31 SWP. 36 ATTACHMENT 5 Placing SW Flow Indicator Fl-1143 In-Service for 32 SWP .......... 38 ATIACHMENT 6 Placing an Alternate SW Flow Indicator In-Service for 32 SWP ... 39 ATTACHMENT 7 LIST OF VARIOUS SERVICE WATER LOADS I Valves ............. 41 ATIACHMENT 8 AS-FOUND AND AS-LEFT TABLE .............................................. 42 ATTACHMENT 9 ASME OM Code Stroke Evaluation Sheet.. .................................. 43

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 4 of 43

~PURPOSE

{,,:;--x.

V This procedure establishes the requirements for the following:

Obtaining and analyzing data for assessment of the operational readiness of 33 Service Water Pump (33 SWP) as required by the lnservice Test (IST) Program (Group A Test).

Obtaining and analyzing data for assessment of the operational readiness of the following valves as required by the IST Program:

t) SWN-1-3, 33 SWP Discharge Check Valve it SWN-9-3, 33 Service Water Pump Vacuum Breaker

~* SWN-PCV-1207, SWP-33 Zurn Strainer Backwash Pressure Control Valve fi:J Verifying the backwash capability of 33 Zurn Strainer.

Si). Inspecting the material condition of SWN-PCV-1207.

{:295. This procedure applies to the following components:

COMPONENT TESTING REQUIREMENTS <1l I I I 33SWP OM ISTB SWN-1-3 EC SWN-9-3 EO EC SWN-PCV-1207 EO EC FST-C 33 Zurn Strainer FUNCTIONAL (1)

OM ISTB: IST Pump Test EO: IST Exercise Open EC: IST Exercise Close FST-C: IST Fail Safe Test Closed

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP I Page 5 of 43

~ PRECAUTIONS AND LIMITATIONS

~-- Precautions And Limitations This test may be performed in any plant mode.

!E. vibration near the top of the motor parallel and perpendicular to the discharge nozzle exceeds 0. 7 in/sec, THEN 33 SWP SHALL be secured.

/157~ Technical Specification LCO 3.7.9 applies during performance of this

~

procedure.

IF Service Water is supplied to the Component Cooling Water Heat Exchanger, THEN Service Water should be regulated to maintain component cooling water temperature above 70°F.

Pump start frequency should be in accordance with applicable limitations.

IF the actual value of 33 SWP ~P or an IST required vibration point falls within the alert range, THEN the test frequency SHALL be doubled until the cause of the deviation is determined and the condition is corrected

(

Reference:

9.2.14).

<Jij General Information

@ Personnel directing this test SHALL read it in its entirety prior to performance. Personnel otherwise involved SHALL read applicable sections.

Test personnel SHALL complete Sections 3.0, 4.0, 5.0, 6.0, and 7.0, as applicable.

@ Any discrepancies found SHALL be identified in Section 5.0, Comments.

> Recorded data may be transposed at any time during testing.

~ System pressure should be maintained between 60 and 97.5 psig to minimize stress on system components.

Fail Safe Testing of SWN-PCV-1207 is verified when the valve goes fully closed during the stroke time test.

An upper case "V" used as a column header in lineup tables or beneath an initial line for a step denotes the requirement for verification by a second individual. This verification may be performed concurrently or independently at the discretion of the SM/Designee.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 6 of 43 This procedure has been upgraded to the requirements of ASME OM 2001 with Addenda through 2003. If a valve fails stroke time criteria, the following corrective action guidance SHALL be used.

!E a valve fails to exhibit required change of valve position or exceeds stroke time acceptance criteria, THEN the valve SHALL be immediately declared inoperable.

WHEN a valve exceeds its stroke time criteria, THEN it can be immediately stroke timed again (3 times) in accordance with Attachment 9. During this second test the valve should be observed locally if possible.

!E the 3 additional stroke times meet stroke time acceptance criteria, THEN the cause of initial deviation SHALL be analyzed, results documented, and valve returned to service.

IF any of the 3 additional stroke times do NOT meet stroke time acceptance criteria, THEN valve SHALL remain inoperable and the following options SHALL be pursued.

)if Valve may be repaired or replaced.

OR Second set of data may be analyzed, in accordance with Attachment 9, to verify new stroke time represents acceptable valve operation. New reference value and acceptance criteria shall be established and incorporated in the IST trending program and implementing procedure.

33 SWP flowrate will be adjusted to approximately 5400 gpm by a combination of valving in and throttling various service water loads.

The Required Ranges in Section 6.0, Acceptance Criteria, were established from the following Reference Values:

VIBRATION (IPS)

FLOW HEAD (gpm)

DATE Motor Top Motor Top (psid) Motor Horizontal Horizontal Axial North-South East-West 10/10/09 85 5400 0.08 0.11 0.13

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP I Page 7 of 43 Performing this test while 31 SWP is on the Essential Header during the colder months of the year is desirable due to the ease of throttling open SWN-TCV-1103, Containment Temperature Control Valve for more flow.

Pressure test gauges SHALL be calibrated to less than or equal to 1/4% accuracy. Gauge ranges may vary from those specified in Step 3.1 provided the range on the gauge does NOT exceed 3 times the expected value.

~

~

A discharge pressure Test Gauge SHALL be installed at the 2nd quarter of every odd year (2011, 2013, etc.) for the IST 2-Year Comprehensive Test. Test Gauge to be installed at the first fitting downstream of valve SWN-58-3, Pl-1191 Isolation.

No: 3-PT-0092C Rev: 15 33 SERVICE WATER PUMP Page 8 of 43 Initials

<gs PREREQUISITES

'@'. Equipment required for test:

EQUIPMENT M&TE No. CAL DUE DATE 33 SWP Discharge Pressure Indicator Pl-1191 (4 ) v~ - \i - it, 0 - 200 PSIG Test Gauge ( 5) \Pi ~-rt-033~1 (5) Ii- 1~~ t~

Vibrometer YY\+\.f\ -o 1,~, - I tJ ]. - J..'-\-- \h Flow Indicator for 33 SWP (1) -t1- w-ia... (4) /0-01-iS Q)

Flow Indicator for 31 SWP (2 ) f .1- tl'i't (4) i IJ-ei \ - IS- (i)

Flow Indicator for 32 SWP (3 ) fl - i I~ 3 (4) to- 0\-\S° CD Stopwatch t'11J- Cl()~ - Io ii-~ -15" Means of measuring from top of lower N/A N/A grating to river water level in inches

[&.

(1) Fl-1142 is the normal flow indicator, for 33 SWP, but an alternate flow indicator may be used. RECORD number of flow indicator actually used.

(2) Fl-1144 is the normal flow indicator FOR 31 SWP, but an alternate flow indicator may be used. RECORD number of flow indicator actually used.

(3) Fl-1143 is the normal flow indicator for 32 SWP, but an alternate flow indicator may be used. RECORD number of flow indicator actually used.

This item may be marked N/A if flow indicator is NOT required.

(4) For installed instrumentation, this may be performed by verifying NO overdue calibration PMs or surveillances exist and documenting this in Section 5.0, Comments.

(5) Needed only for IST 2-Year Comprehensive Test (2nd Quarter of every odd year) OR directed by Test Supervisor.

@ Reason for Test- CHECK applicable listing:

H Normal Surveillance WO# jd s~* t' 0 J? - ()I D Post Maintenance Test WO#_ _ _ _ _ _ _ _ __

WO#_ _ _ _ _ _ _ _ __

WO#_ _ _ _ _ _ __

D Increased Test Frequency WO#_ _ _ _ _ _ _ _ __

D Other

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

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP I Page 9 of 43 Initials

~/ PROCEDURE

~ Initial Conditions OBTAIN permission from SM or Designated Alternate to perform this test.

SM or Des. Alt. Signature I Date

~* Test Of 33 Service Water Pump

!E performing the IST 2-Year Comprehensive Test for 33 SWP OR as directed by Test Supervisor, THEN INSTALL discharge pressure test gauge as follows:

CLOSE SWN-58-3, Pl-1191 Isolation AND DISCONNECT first fitting downstream of valve.

INSTALL test gauge at test connection.

OPEN SWN-58-3.

!E 33 SWP is running, THEN RECORD present time as start time:

Start time:

rJ l'\

!E 33 SWP is NOT in running, THEN COORDINATE with Control Room to ensure another ru.

SWP on 31, 32, 33 SW header is in operation.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 10 of 43 Initials NO counter rotation demonstrates EC for SWN-1-3, 33 SWP Discharge Check Valve.

OBSERVE 33 SWP AND VERIFY EC of SWN-1-3, 33 SWP Discharge Check Valve:

Counter Rotation: (Circle one) Yes@

SWN-1-3 EC: (Circle one) @J No n I. \.tY:

VERIFY proper oil level in sight glass on upper portion of motor.

The following alarms may be received during performance of the following step:

c:)j' SERVICE WTR HOR (31, 32, 33) HIGH/LOW PRESS (Panel SJF)

~ SERVICE WATER TO LUBE OIL COOLERS HIGH/LOW PRESSURE (Panel SJF)

~ SERVICE WATER TO H2 COOLERS HIGH/LOW PRESSURE (Panel SJF)

@ START 33 SWP and RECORD start time:

I .

Start Time{-  :?i'.,,i\.1:::){-.**-.,,.., l{,,.,_v,,~ {.,0

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 11 of 43 Initials Exercise Open (EO) of SWN-9-3, 33 Service Water Pump Vacuum Breaker, is verified by 33 SWP running acceptably.

VERIFY water issued from SWN-9-3, 33 Service Water Pump Vacuum Breaker, when 33 SWP was started.

ISWN-9-3 EO: (Circle one) <!iii>1 No

!E Fl-1142 (33 SWP Flow Indicator) is to be used, THEN PLACE in service per Attachment 1, Instructions for Placing Service Water Flow Indicator in Service.

!E Fl-1142 (33 SWP Flow Indicator) is suspected to be inaccurate or out of calibration, THEN PLACE an alternate flow indicator in service per Attachment 2, Procedure for Using an Alternate Flow Indicator NOTE the use of alternate flow indicator in Section 5.0, Comments.

NOTE rough 4.2.9 are provided to allow placing the associated or alternate flo indicators in service for 31 and 33 SWPs when it is anticipated that the disc arge valve of 1 or both of these pumps may need to be throttled to obtain re uired test flow on 32 SWP.

~

IF Fl-1144 is to be used for 31 SWP, THEN PLACE in service per Attachment 3, Placing SW Flow I Indicator Fl-1144 in Service for 31 SWP.

I v

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 12 of 43 Initials

!E Fl-1144 (31 SWP Flow Indicator) is suspected of being inaccurate or is out of calibration, THEN:

~ PLACE an alternate flow indicator in service per d Attachment 4, Placing an Alternate SW Flow Indicator in Service for 31 SWP. ,.1 Li

~

NOTE use of alternate flow indicator in Section 5.0, Comments.

!E Fl-1143 is to be used for 32 SWP, THEN PLACE in service per Attachment 5, Placing SW Flow Indicator Fl-1143 in Service for 32 SWP.

!E Fl-1143 (32 SWP Flow Indicator) is suspected of being inaccurate or is out of calibration, THEN:

PLACE an alternate flow indicator in service per Attachment 6, Placing an Alternate SW Flow Indicator in Service for 32 SWP.

NOTE use of alternate flow indicator in Section 5.0, Comments.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 13 of 43 Initials

- ~t!jffe

~X Avoid running SWP for a prolonged period of time at flow rates less than 7-"' 2500 gpm and NOT longer than 30 minutes at a flowrate of 2000 gpm.

~Avoid running any SWP at a flowrate greater than 7500 gpm.

(!f Throttling any SWP discharge valve will render the associated SWP inoperable.

C-:.X Attachment 7, List of Various Service Water Loads I Valves, shows SW loads

'T and recommended valves, which may be positioned as required to obtain desired flow rate. Attachment 7 is a guide and NOT necessarily all inclusive.

(if Attachment 8, As-Found and As-Left Table, is used to track valve manipulations required to obtain desired flow rate.

@'Throttling SWN-2-3, 33 SWP Discharge Isolation, may require entry into an AOT per LCO 3.7.9.

~ADJUST 33 SWP flow to 5292 - 5508 gpm on Fl-1142 or alternate flow instrument and RECORD flow {Ref: 9.1.1}:

33 SWP Flow: l

. .,. !~d

(""I gpm

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 14 of 43 Initials I~

~ WHEN 33 SWP has run at least 2 minutes, THEN OBTAIN vibration readings using hand-held vibrometer:

Ji! PLACE probe on locations indicated on motor sketch.

~ RECORD data in the velocity mode (in/sec) for all points.

I I MOTOR 1 ~

2

~

B A

s 5 E

p I~

L A

4

~

T 3 E

I 1 +- I 6

ACTUAL Acceptance Criteria 33 SW PUMP LOCATION (IN I SEC) OPERABILITY ALERT

1. Motor Top North-Soutit) (~), 04-  ::;;0.48  ::;; 0.2

2. Motor Top East-Wes8 (j "01  ::;;0.66  ::::; 0.27

3. Motor Bottom North-South . c' NA NA J. -*

4. Motor Bottom East-West ('). J tf NA NA

5. Motor Axiaf0 (}, (lj  :::::0.7  ::::; 0.32

6. Base Axial () \I IJ,..) NA NA

• Denotes IST data.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1 Page 15 of 43 Initials Alert values are NOT used to determine operability.

~ EVALUATE vibration readings recorded in Step 4.2.11:

ACCEPTANCE CRITERIA ACTUAL ACCEPTABLE INITIALS All Surveillance Operability Criteria satisfied NO I NIA NO I NIA All Surveillance Alert Criteria satisfied NIA NIA

~ RECORD 33 SWP discharge pressure on Pl-1191 OR installed discharge pressure gauge (step 4.2.1.2):

Pl-1191: _rJ_)p_,.__ psig OR o -

)

200 psig Test Gauge X:i_ psig e_~_

Zero or negligible leakage demonstrates EC for SWN-9-3, 33 Service Water Pump Vacuum Breaker.

~~ OBSERVE SWN-9-3 for leakage.

SWN-9-3 EC: (Circle one)@i No

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 16 of 43 Initials MEASURE AND RECORD the distance from river water to top of lower grating in inches:

- - - - - inches BASEPLATE (15' elev.)

p u DISCHARGE LINE M

p t----+---+----\. GRATING WATER LEVEL CALCULATE 32 SWP Suction Pressure Head (pump lift) in psig using distance from top of lower grating to river water level recorded in Step 4.2.15 (Distance Below Grating) and distance from top of lower grating to center line of 32 SWP discharge line (Distance Above Grating):

SPHpsig = (DBGin + DAGin)(0.083 ft/in)(0.432 psi/ft)

SPHpsig = Suction Pressure Head (pump lift) in psig DBGin = Distance Below Grating in inches (Step 4.2.15) (This is a variable value.)

DAGin =Distance Above Grating= 30 inches (This is a fixed value.)

SPHpsig = ( b,.

(Step 4.2.15) in + 30 in)(0.083 ft/in)(0.432 psi/ft) = 3 * '-1 j psig

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 17 of 43 Initials

~

~ CALCULATE 33 SWP L\P in psid using 33 SWP discharge pressure recorded in Step 4.2.13, Suction Pressure Head value recorded in Step 4.2.16:

L\Ppsid = DPpsig + SPHpsig L\Ppsid = Differential Pressure in psid DPpsig = Discharge Pressure in psig (Step 4.2.13)

SPHpsig = Suction Pressure Head in psig (Step 4.2.16)

L\P psid = ~ i.f psig + .l. # psig =__8_o_*._S_/,.,_,_ _ _ psid (Step 4.2.13) (Step 4.2.16)

RETURN valves identified on Attachment 8 to position required by CRS or SM.

IF Fl-1142 (33 SWP Flow Indicator) was used, THEN REMOVE Alternate Flow Indicator from service per Attachment 1 .

!E Alternate Flow Indicator was used for 33 SWP THEN REMOVE Alternate Flow Indicator from service per Attachment 2, Placing an Alternate SW Flow Indicator In-Service for 33 SWP.

4. .21 IF Fl-1144 was placed in service for 31 SWP in Step 4.2.6, THEN REMOVE from service per Attachment 3.

4 .. 22 IF an Alternate Flow Indicator was placed in service for 31 SWP in Step 4.2.7.1, THEN REMOVE Alternate Flow Indicator from service per Attachment 4.

4 .. 23 IF Fl-1142 was placed in service for 32 SWP in Step 4.2.8, THEN REMOVE from service per Attachment 5.

4.. 24 IF an Alternate Flow Indicator was placed in service for 32 SWP in Step 4.2.9.1, THEN REMOVE Alternate Flow Indicator from service per Attachment 6. \kl

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 18 of 43 Initials

~ !E Step 4.2.3 was NOT performed, THEN:

,\ lL:,

J I . NOTE /

The followinJ alarms may be received during performance of the follo)Nihg step:

I /

• SERVIC~ WTR HOR (31, 32, 33) HIGH/LOW PRESS (Pan;}SJF)

• SERVICd WATER TO LUBE OIL COOLERS HIGH/LO PRESSURE (Panel S1F)

• SERVICE! WATER TO H2 COOLERS HIGH/LOW RESSURE (Panel SJF) i I'

4.2.25.1 COORDINA~ ~itf) Control Room to ensure another SWP on 31, F\j ~i SW header is in operation.

4.2.25.2 STOP33SW . A f:

I I ~ NOTE Exercise Opefi (EO) of SWN , 33 Service Water Pump Vacuum Breaker, is verified b an in rush of air into the vacuu , breaker discharge pipe when 33 SWP is stopped .

.1 I I II

/

4.2.25./ VERIFY SWN-9-3, 33 Service Water Pump Vacuum Breaker, opened by feeling an in rush air into the vacuum breaker discharge pipe.

/ . I SWN-9-3 EO: (Circle one) Yes I No I VI ,µ

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 19 of 43 Initials

~

To verify EC for SWN-1-3, 33 SWP must stop and exhibit NO counter rotation.

Some counter rotation may be experienced as water drains from piping between pump and check valve.

~ OBSERVE 33 SWP for counter rotation.

7/-\ Counter Rotation: (Circle one) Yes I No

\ I SWN-1-3 EC: (Circle one) Yes I No tJJis 4.2.2 .5 !EEO of SWN-9-3, 33 Service Water Pump Vacu Breaker, was NOT verified in Step 4.2.25.3, _T_...,.H~

a) VERIFY proper oil level in sight glas on upper portion of motor.

NOTE /

The following alarms m y be received during pe,frnance of the following step:

• SERVICE WTR HD (31, 32, 33) HIGH~efw PRESS (Panel SJF)

• SERVICE WATER 0 LUBE OIL ~~LERS HIGH/LOW PRESSURE (Panel SJF) //

• SERVICE WATER 0 H2 G00LERS HIGH/LOW PRESSURE (Panel SJF)

/

Allow sufficient time pri r to1estarting 33 SWP for SWN-9-3, 33 Service Water Pump Vacuum Breake , Jd open. This will ensure water issues in Step c).

/

b) START 33 SWP.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 20 of 43 Initials Exercise Open (EO) of SWN-9-3, 33 Service Water Pump Vacuum Breaker, is verified by water issuing from the valve when 33 SWP is started.

(()) VERIFY water issued from SWN-9-3, 33

• Service Water Pump Vacuum Breaker, when i/t, 33 SWP was started.

SWN-9-3 EO: (Circle one) Yes I No

('-;~NOTIFY CRS

33 SWP may be operated as required for plant

~ operation.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 21 of 43 Initials

~* Test Of Zurn Strainer and SWN-PCV-1207, 33 SWP Zurn Strainer

/ Slowdown Valve

~ RECORD As-Found position of control switch:

Control Switch As-Found Position Initials 133 Zurn Strainer I .Wtt/\)J) I p.Q I

~~ IF 33 Zurn Strainer control switch is in HAND, Z/ THEN NOTIFY CRS: 33 Zurn Strainer control switch will be placed in AUTO or OFF while testing.

PLACE 33 Zurn Strainer control switch in AUTO OR OFF.

~ VERIFY following conditions:

9J 33 Zurn Strainer is NOT backwashing. Gl_11i_ _

(;J' SWN-PCV-1207, SWP-33 Zurn Strainer Backwash Pressure

/ Control Valve, is closed. _r.~__

'i:J SWN-2-3, 33 SWP Discharge Isolation, is open. ~,fN

~ At least 1 SWP is operating on the 31, 32, 33 SW Header. ris.,

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 22 of 43 Initials Strainer backwash mechanisms are water lubricated. DO NOT operate strainer backwash motors/valves unless pressurized water is available to strainer.

A7f' SWN-PCV-1207 operation SHALL be observed locally in order to record P timing.

I

@Opening and closing valve stroke times for SWN-PCV-1207 are taken from control switch actuation to cessation of valve stem movement.

¢} Zurn Strainer backwash valve position is verified by observing flat areas on valve shaft. Flats in line with piping indicate valve is open. Flats at 90 degrees to piping indicate valve is closed.

@ PLACE 33 Zurn Strainer Control Switch in HAND AND RECORD opening stroke time for SWN-PCV-1207.

VALVE STROKE TIME ACCEPTABLE TIME LIMIT SWN-PCV-1207 opens i 4-~ sec ~2 sec

@ VERIFY 33 Zurn Strainer motor rotates.

33 Zurn Strainer rotates: (Circle one) No PLACE 33 Zurn Strainer Control Switch in OFF and RECORD closing stroke time for SWN-PCV-1207.

VALVE STROKE TIME ACCEPTABLE TIME LIMIT SWN-PCV-1207 closes i,~fq sec  :::; 2 sec VERIFY 33 Zurn Strainer motor stops.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 23 of 43 Initials Visually INSPECT SWN-PCV-1207 and associated SOV and air lines for the following:

Loose bolts Corrosion Leaks Damaged or kinked hoses J£ 33 Zurn Strainer can NOT be backwashed in AUTO or HAND via SWN-PCV-1207 or manually per 3-SOP-RW-005, Service Water System Operation, THEN 33 Zurn Strainer SHALL be declared inoperable.

J£ SWN-PCV-1207 fails to open, THEN PERFORM a manual backwash of 33 Zurn Strainer per 3-SOP-RW-005, Service Water System Operation.

~ Restoration t4rl RESTORE 33 Zurn Strainer Control Switch to AUTO p OR as required by SM/CRS:

CONTROL CONTROL SWITCH SWITCH NORMAL POSITION AS-LEFT INITIALS v 33 Zurn Strainer AUTO ..P1'ATt. f.(l,, 7Jc~~*

IF discharge pressure Test Gauge was installed (in step 4.2.1.2),

THEN CLOSE SWN-58-3, Pl-1191 Isolation. Pi8.

REMOVE test gauge. f ,p, RECONNECT tubing at fitting used for test gauge. (;,,L OPEN SWN-58-3. f',P.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1 Page 24 of 43

~ COMMENTS:

Test Performers:

Print Name: Initials: Sianature/Date:

Rt.'\ fe,~ .~fl'., d -v\ fHtc a

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 25 of 43 o/ ACCEPTANCE CRITERIA

~ IST Requirements 33 SWP Operability Requirements Surveillance Acceptance Parameter Step Actual Acceptable Initials Requirement Criteria 33 SWP Flow 4.2.10 5292 ::::: gpm ::::: 5508 S-'f0G gpm ~/NO/NA e~.

Motor Top Horizontal N-S  ::::: 0.48 in/sec l).0~ in/sec @tNO/NA f,Q, Vibration Motor Top Horizontal E-W 4.2.11

0.66 in/sec v.D'7 in/sec (~)NO/NA Kt

['.._/"

Vibration IST Program Motor Axial

0.7 in/sec 6c.U in/sec @NO/NA C1.~

Vibration 33 SWP iiP 4.2.17 80.1 ::::: psid::::: 87.6

• IST Surveillance r?a.s-l psid §>/NO/NA e8.

• Acceptance Criteria is based on IST 2-Year Comprehensive testing requirements, which are more restrictive than quarterly testing requirements .

...@". 33 SWP Valves Operability Requirements Surveillance Acceptance Actual Component Step Acceptable Initials Requirement Criteria Value 4.2.3.1 SWN-1-3 OR EC @tNO @tNO P.~

4.2.25.4 4.2.3.4 @tNO @tNO fR OR 4.2.25.3 EO

~/ Go

~

SWN-9-3 OR IST Program NO ~/NO 4.2.25.5c}

4.2.14 EC @tNO @tNO ~&

4.3.4 EO ::::: 2 seconds I.off sec @tNO (!

f{ LI)..

SWN-PCV-1207 4.3.6 EC ::::: 2 seconds . 'f' I. Lf*t sec ~/NO P*;\

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 26 of 43

~ 33 SWP Alert Status Determination Actual Value Alert Range Is actual value within Initials Parameter Step the Alert Range?

Motor Top Horizontal N-S O.Dl\f in/sec 0.2 < in/sec:::; 0.48 YES @ NA r.~

Motor Top 4.2.11 in/sec NA

J ,)'} 0.27 < in/sec:::; 0.66 YES(§) (t~

Horizontal E-W Motor Axial o ,of in/sec 0.32 < in/sec::; 0.7 YES@ NA

!?&<

33 SWP ~p 4.2.17 fo;re:,, psid 80.1 :::; psid ~ 80.8

!ST Surveillance 6;> NO NA p,ci P' Other Reguirements Zurn Strainer Surveillance Component Step Acceptance Criteria Acceptable Initials Requirement Necessary 33 Zurn Strainer 4.3.5 Support Equipment Rotates @No R\1 7.0 TEST ACCEPTANCE 7 .1 IST Acceptance Criteria 7.1.1 Based on the recorded data, are all IST Operability Acceptance Criteria of Section 6.1.1 and 6.1.2 satisfied?

YES NO N/A 7.1.2 Actions for SWN-PCV-1207:

7.1.2.1 IF the valve(s) failed to exhibit the required change of position, THEN:

• NOTIFY CRS/SM to declare the valve(s) inoperable.

• INITIATE a WR and CR.

• TAKE applicable action in accordance with LCO 3.7.9.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 27 of 43 7.1.2.2 IF the valve(s) stroke time is outside the IST Acceptance Criteria Limits, THEN:

• NOTIFY CRS/SM to declare the valve(s) inoperable.

• INITIATE a CR.

• PERFORM additional stoke tests in accordance with Attachment 9, ASME OM Code Stroke Evaluation Sheet.

7.1.2.3 Based on stroke test data on Attachment 9, are stroke times within Acceptance Criteria of Section 6.1?

YES NO N/A a) !Ethe stoke test IST Acceptance Criteria are NOT satisfied, THEN INITIATE a WR.

b) !Ethe stoke test IST Acceptance Criteria are satisfied, THEN NOTIFY CRS/SM to declare the valve(s) operable.

7 .1.3 Actions for SWN-1-3 and SWN-9-3:

7.1.3.1 !Ethe valve failed to exhibit the required change of position, THEN:

• NOTIFY CRS/SM to declare the valve inoperable.

• INITIATE a WR and a CR.

• TAKE applicable action in accordance with LCO 3.7.9.

7.1.4 Actions for 33 SWP:

7.1.4.1 IF the pump test results are outside the IST Acceptance Criteria Limits, THEN:

• NOTIFY CRS/SM to declare the pump inoperable.

• INITIATE a WR and a CR.

• TAKE applicable action in accordance with LCO 3.7.9.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 28 of 43 7 .2 33 SWP Alert Status Determination 7.2.1 lE any parameter is within the Alert Range in Section 6.1.3, THEN:

• NOTIFY CRS/SM

• INITIATE a CR 7 .3 Other Requirements Acceptance Criteria 7.3.1 Based on the recorded data, are all Support Acceptance Criteria of Section 0 satisfied?

YES NO N/A 7.3.2 lE the 33 Zurn Strainer test results are outside the Support Acceptance Criteria of Section 0, THEN:

• NOTIFY CRS/SM to declare the 33 Zurn Strainer inoperable.

• INITIATE a WR and a CR.

• TAKE applicable action in accordance with LCO 3.7.9.

7.4 IF NO is circled in Step 7.1.1, 7.1.2.3, OR 7.3.1, THEN LIST corrective action(s) taken and comments:

Comments:

Reviewed By:

SM or Des. Alt: Print Name I Sign I Date

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 29 of 43 8.0 EVALUATION 8.1 IST EVALUATION Comments:

Reviewed By:

IST Engineer: Print Name I Sign I Date 8.2 SURVEILLANCE COORDINATOR REVIEW Comments:

Reviewed By:

Surveillance Coordinator: Print Name I Sign I Date

9.0 REFERENCES

9.1 Commitment Documents 9.1.1 Design Basis Licensing Database COM-83-02582 (Old No. 83-003-C),

IER 82-23, dated 01/14/83 9.2 Development Documents 9.2.1 9321-F-20333, Sheets 1 and 2, Flow Diagram Service Water System 9.2.2 9321-F-27223, Flow Diagram Service Water System Nuclear Steam Supply Plant 9.2.3 Modification Drawings: 9321-F-10063 and 871150-FS-201, Intake Structure Platform Framing Plan and Details 9.2.4 SEP-IST-IP3-001, lnservice Testing Program Plan (IP-RPT-09-00070)

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 30 of 43 9.2.5 3-PT-V059C, 33 SWP Reference Test 9.2.6 Memo to 3PT-M35 file, dated January 8, 1993 (Location of Pump Suction for Determining Suction Pressure for 31-36 SW Pumps) 9.2.7 Memo NOS-93-140 (April 9, 1993) 9.2.8 Memo IP-PRF-93-257 (Timing Requirements for SWN-PCV-1205 thru 1210) 9.2.9 MMP 96-3-507 SWS, Main SW Pump Zurn Strainer Piping Replacement 9.2.10 3PT-Q82, Zurn Strainer Backwash Valve Test PCV-1205 Through PCV-1210.

9.2.11 Technical Manual IP3V-209-100000314 (Service Water Pumps) 9.2.12 Technical Manual IP3V-1158-100000844 (Service Water Strainers) 9.2.13 Technical Manual IP3V-1301-100001015 (Service Water Annubars) 9.2.14 ASME OM 2001through2003 Addenda 9.2.15 Calculation No. IP-CALC-13-00063 9.3 Interface Documents 9.3.1 Technical Specification LCO 3.7.9 9.3.2 3-SOP-RW-005, Service Water System Operation 10.0 RECORDS AND DOCUMENTATION 10.1 Records The following required records are generated by this procedure and SHALL be maintained in accordance with IPEC Records Retention Schedule:

10.1.1 This Surveillance Test becomes a Quality Record when completed.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 31 of 43 Initials ATTACHMENT 1 Placing SW Flow Indicator Fl-1142 In-Service for 33 SWP (Page 1 of 2)

An annubar assembly drawing is provided on Page 2 of 2.

@ PLACE the Normal Flow Indicator in service as follows:

,M~ VERIFY Fl-1142 Hi and Lo side isolation valves are Closed. p,J.,

j;;-;4 ~

~* OPEN SWN-143, Fl-1142 Hi Side Root Isolation.

~AAJ. OPEN SWN-133, Fl-1142 Lo Side Root Isolation. CQ e§I VERIFY Fl-1142 Hi Side Vent valve is OPEN. (~

~ VERIFY Fl-1142 Lo Side Vent valve is OPEN.

~* Simultaneously OPEN Hi Side and Lo Side isolation valves for Fl-1142.

f.,,..,

9{D CLOSE Fl-1142 Hi Side Vent valve.

,@ CLOSE Fl-1142 Lo Side Vent valve.

li"J:l WHEN use of Normal Flow Indicator is complete, x:J THEN REMOVE from service as follows:

_' OPEN Fl-1142 Hi Side Vent.

<ff!} OPEN Fl-1142 Lo Side Vent.

@ Simultaneously CLOSE both Hi side and Lo side isolation valves for Fl-1142.

r:;)'_,

~ CLOSE SWN-143, Fl-1142 Hi Side Root Isolation.

~* CLOSE SWN-133, Fl-1142 Lo Side Root Isolation.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 32 of 43 ATTACHMENT 1 Instructions for Placing Service Water Flow Indicator In-Service (Page 2 of 2)

Annubar Assembly (Typical)

HI SIDES ROOTtSOL.

Fl OW ......

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 33 of 43 Initials ATTACHMENT 2 Placing an Alternate SW Flow Indicator In-Service for 33 SWP (Page 1 of 2) 3.0 CONNECT the Alternate Flow Indicator as follows:

3.1 RECORD Alternate Flow Indicator to be used: -------

3.2 VERIFY Fl-1142 Hi Side and Lo Side Isolations are Closed.

3.3 VERIFY Alternate Flow Indicator Hi side and Lo side isolations are Closed.

3.4 DISCONNECT the Hi and Lo side fittings of Fl-1142 AND the Alternate Flow Indicator.

3.5 INSTALL tubing between the Hi side of Fl-1142 AND the Alternate Flow Indicator.

3.6 INSTALL tubing between the Lo side of Fl-1142 AND the Alternate Flow Indicator.

4.0 PLACE the Alternate Flow Indicator in service as follows:

4.1 VERIFY both Hi and Lo side Flow Indicator isolation valves are closed.

4.2 VERIFY SWN-143 and SWN-133, Fl-1142 Hi and Lo Side Root Isolation Valves, are OPEN.

4.3 VERIFY Alternate Flow Indicator Hi side vent valve is OPEN.

4.4 VERIFY Alternate Flow Indicator Lo side vent valve is OPEN.

4.5 Simultaneously OPEN Hi side and Lo side isolation valves for Fl-1142.

4.6 CLOSE Alternate Flow Indicator Lo side vent.

4. 7 CLOSE Alternate Flow Indicator Hi side vent.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1 Page 34 of 43 Initials ATTACHMENT 2 Procedure for Using an Alternate Flow Indicator (Page 2 of 2) 5.0 WHEN use of Alternate Flow Indicator is complete, THEN REMOVE from service as follows:

5.1 OPEN Alternate Flow Indicator Hi side vent.

5.2 OPEN Alternate Flow Indicator Lo side vent.

5.3 Simultaneously CLOSE Hi side and Lo side isolation valves for Fl-1142.

5.4 CLOSE SWN-143, Fl-1142 Hi Side Root Isolation Valve.

5.5 CLOSE SWN-133, Fl-1142 Lo Side Root Isolation Valve.

5.6 DISCONNECT and REMOVE the tubing from the Hi and Lo side of Fl-1142 and the Alternate Flow Indicator.

5. 7 CONNECT the HI and Lo side fittings of Fl-1142 AND the Alternate Flow Indicator as required.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 35 of 43 Initials ATTACHMENT 3 Placing SW Flow Indicator Fl-1144 In-Service for 31 SWP (Page 1 of 1)

NOTE An annubar assembly drawing is provided on Attachment 1, page 2 of 2.

1.0 PLACE the Normal Flow Indicator in service as follows:

1.1 VERIFY Fl-1144 Hi and Lo side isolation valves are Closed.

1.2 OPEN SWN-141, Fl-1144 Hi Side Root Isolation.

1.3 OPEN SWN-131, Fl-1144 Lo Side Root Isolation.

1.4 VERIFY Fl-1144 Hi Side Vent valve is OPEN.

1.5 VERIFY Fl-1144 Lo Side Vent valve is OPEN.

1.6 Simultaneously OPEN Hi Side and Lo Side isolation valves for Fl-1144.

1. 7 CLOSE Fl-1144 Lo Side Vent valve.

1.8 CLOSE Fl-1144 Hi Side Vent valve.

2.0 WHEN use of Normal Flow Indicator is complete, THEN REMOVE from service as follows:

2.1 OPEN Fl-1144 Hi Side Vent.

2.2 OPEN Fl-1144 Lo Side Vent.

2.3 Simultaneously CLOSE both Hi side and Lo side isolation valves for Fl-1144.

2.4 CLOSE SWN-141, Fl-1144 Hi Side Root Isolation.

2.5 CLOSE SWN-131, Fl-1144 Lo Side Root Isolation.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1 Page 36 of 43 Initials ATTACHMENT 4 Placing an Alternate SW Flow Indicator In-Service For 31 SWP (Page 1 of 2) 1.0 CONNECT the Alternate Flow Indicator as follows:

1.1 RECORD Alternate Flow Indicator to be used:

1.2 VERFIY Fl-1144 Hi Side and Lo Side Isolations are Closed.

1.3 VERIFY Alternate Flow Indicator Hi side and Lo side isolations are closed. _ __

1.4 DISCONNECT the Hi and Lo side fittings of Fl-1144 AND the Alternate Flow Indicator.

1.5 INSTALL tubing between the Hi side of Fl-1144 AND the Alternate Flow Indicator.

1.6 INSTALL tubing between the Lo side of Fl-1144 AND the Alternate Flow Indicator.

2.0 PLACE the Alternate Flow Indicator in service as follows:

2.1 VERIFY both Hi and Lo side Flow Indicator isolation valves are Closed.

2.2 VERIFY SWN-141 and SWN-131, Fl-1144 Hi and Lo Side Root Isolation Valves, are OPEN.

2.3 VERIFY Alternate Flow Indicator Hi side vent valve is OPEN.

2.4 VERIFY Alternate Flow Indicator Lo side vent valve is OPEN.

2.5 Simultaneously OPEN Hi side and Lo side isolation valves for Fl-1144.

2.6 CLOSE Alternate Flow Indicator Lo side vent.

2. 7 CLOSE Alternate Flow Indicator Hi side vent.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 37 of 43 Initials ATTACHMENT 4 Placing an Alternate SW Flow Indicator In-Service For 31 SWP (Page 2 of 2) 3.0 WHEN use of Alternate Flow Indicator is complete, THEN REMOVE from service as follows:

3.1 OPEN Alternate Flow Indicator Hi side vent.

3.2 OPEN Alternate Flow Indicator Lo side vent.

3.3 Simultaneously CLOSE Hi side and Lo side isolation valves for Fl-1144.

3.4 CLOSE SWN-141, Fl-1144 Hi Side Root Isolation Valve.

3.5 CLOSE SWN-131, Fl-1144 Lo Side Root Isolation Valve.

3.6 DISCONNECT and REMOVE the tubing from the Hi and Lo side of Fl-1144 and the Alternate Flow Indicator.

3.7 CONNECT the HI and Lo side fittings of Fl-1144 AND the Alternate Flow Indicator as required.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 38 of 43 ATTACHMENT 5 Placing SW Flow Indicator Fl-1143 In-Service for 32 SWP (Page 1of1)

NOTE An annubar assembly drawing is provided on Attachment 7.

1.0 PLACE the Normal Flow Indicator in service as follows:

1.1 VERIFY Fl-1143 Hi and Lo side isolation valves are Closed.

1.2 OPEN SWN-142, Fl-1143 Hi Side Root Isolation.

1.3 OPEN SWN-132, Fl-1143 Lo Side Root Isolation.

1.4 VERIFY Fl-1143 Hi Side Vent valve is OPEN.

1.5 VERIFY Fl-1143 Lo Side Vent valve is OPEN.

1.6 Simultaneously OPEN Hi Side and Lo Side isolation valves for Fl-1143.

1.7 CLOSE Fl-1143 Lo Side Vent valve.

1.8 CLOSE Fl-1143 Hi Side Vent valve.

2.0 WHEN use of Normal Flow Indicator is complete, THEN REMOVE from service as follows:

2.1 OPEN Fl-1143 Hi Side Vent.

2.2 OPEN Fl-1143 Lo Side Vent.

2.3 Simultaneously CLOSE both Hi side and Lo side isolation valves for Fl-1143.

2.4 CLOSE SWN-142, Fl-1143 Hi Side Root Isolation.

2.5 CLOSE SWN-132, Fl-1143 Lo Side Root Isolation.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1 Page 39 of 43 ATTACHMENT 6, Placing an Alternate SW Flow Indicator In-Service for 32 SWP (Page 1 of 2) 1.0 CONNECT the Alternate Flow Indicator as follows:

1.1 RECORD Alternate Flow Indicator to be used: - - - - - - -

1.2 VERIFY Fl-1143 Hi Side and Lo Side Isolations are Closed.

1.3 VERIFY Alternate Flow Indicator Hi side and Lo side isolations are Closed.

1.4 DISCONNECT the Hi and Lo side fittings of Fl-1143 AND the Alternate Flow Indicator.

1.5 INSTALL tubing between the Hi side of Fl-1143 AND the Alternate Flow Indicator.

1.6 INSTALL tubing between the Lo side of Fl-1143 AND the Alternate Flow Indicator.

2.0 PLACE the Alternate Flow Indicator in service as follows:

2.1 VERIFY both Hi and Lo side Flow Indicator isolation valves are Closed.

2.2 VERIFY SWN-142 and SWN-132, Fl-1143 Hi and Lo Side Root Isolation Valves, are OPEN.

2.3 VERIFY Alternate Flow Indicator Hi side vent valve is OPEN.

2.4 VERIFY Alternate Flow Indicator Lo side vent valve is OPEN.

2.5 Simultaneously OPEN Hi side and Lo side isolation valves for Fl-1143.

2.6 CLOSE Alternate Flow Indicator Lo side vent.

2.7 CLOSE Alternate Flow Indicator Hi side vent.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 40 of 43 ATTACHMENT 6, Placing an Alternate SW Flow Indicator In-Service for 32 SWP (Page 2 of 2) 3.0 WHEN use of Alternate Flow Indicator is complete, THEN REMOVE from service as follows:

3.1 OPEN Alternate Flow Indicator Hi side vent.

3.2 OPEN Alternate Flow Indicator Lo side vent.

3.3 Simultaneously CLOSE Hi side and Lo side isolation valves for Fl-1143.

3.4 CLOSE SWN-142, Fl-1143 Hi Side Root Isolation Valve.

3.5 CLOSE SWN-132, Fl-1143 Lo Side Root Isolation Valve.

3.6 DISCONNECT and REMOVE the tubing from the Hi and Lo side of Fl-1143 and the Alternate Flow Indicator.

3.7 CONNECT the HI and Lo side fittings of Fl-1143 AND the Alternate Flow Indicator as required.

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP 1

Page 41of43 ATTACHMENT 7 LIST OF VARIOUS SERVICE WATER LOADS I VALVES (Page 1 of 1)

NOTE Below is a list of Service Water Loads, valves, and approximate flow rates expected, which may be used to throttle service water flow rates. This list is NOT all inclusive.

EXPECTED FLOW RATES SERVICE WATER LOAD VALVE(S)

(gpm)

Containment FCUs TCV-1103, 1104, 1105 570-1400 (ea) 31-33 EOG Coolers FCV-1176, 1176A 357 (ea) 31 & 32 CCWHX 3 SWN-34-1, 34-2 3500 (ea)

SWPs Strainer Back wash PCV-1205 - 1210 300 (ea)

SWP Discharge Valves SWN-2-1 thru SWN-2-6 NIA

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 42 of 43 ATTACHMENT 8 AS-FOUND AND AS-LEFT TABLE (Page 1 of 1) 1.0 IDENTIFY below any valves manipulated during this test.

2.0 RETURN these valves to the position required by the SM/Designee.

VALVE AS FOUND TEST MANIPULATED POSITION POSITION AS LEFT INITIALS v

No: 3-PT-Q092C Rev: 15 33 SERVICE WATER PUMP Page 43 of 43 ATTACHMENT 9 ASME OM Code Stroke Evaluation Sheet (Page 1 of 1)

!Ea stroke time is outside the limits required by section 6.0, THEN the following corrective ac *on guidance may be initiated. Additional copies of this attachment may be made as required.

!E a valve fails to exhibit the required change of valve position or exceeds the stroke tim acceptance criteria, THEN the valve SHALL be declared INOPERABLE.

!E valve stroke time exceeds its criteria, THEN PERFORM stroke time in accordan with the instructions below.

NOTE During this second test the valve should be locally observed, if ossible, in accordance with applicable attachment.

1 .0 RECORD Valve Number: ~~-~~--~--

2.0 STROKE/TIME the valve three times and 1

OPEN Stroke Section

• Acceptable Timing Test Time Criteri Criteria (Yes/No) 2 3

I 3.0 !Ethe above data meets the Section 6.0 Acceptance Criteria, THEN the results SHALL 1

be recorded below and the valve r?iurned to an OPERABLE status.

4.0 !Ethe above data does NOT melt the Section 6.0 Acceptance Criteria, THEN the valve SHALL remairyfNOPERABLE and the following options initiated:

• Valve SHALL be repaired or rE}iiaced.

/

• Forward stroke time data to ,Performance IST Engineer to be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. The data obtained can be analyzed t6 determine if it represents acceptable valve operation. IST Engineer SHALL determine if new r~ference values and acceptance criteria can be established.

I

/

5.0 COMMENTS

I

---

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

/

r

/

/

/

Reviewed b y : - + - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

S.M. or C.R.S. I Date

/

/

/

Reviewed b y : - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

/

IST ENGINEER I Date

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Review I Authorize a Liquid Waste Release KIA

Reference:

1940002.3.6 Job Performance Measure SRO Admin SR0-3.8 No: 4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -

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

Initial Conditions:

• Unit is in MODE 5 for a forced outage.

• Circulating Water Pumps Status:

o 31, 33, and 35 in service at 215 RPM each.

o No other dilution flow sources are available or authorized.

• A Liquid Radioactive Waste Release Permit Form has been completed manually IAW Section 4.1 of 3-SOP-WDS-014; Liquid Waste Releases for the release of 32 Monitor Tank.

• R-18 is operable and has been appropriately source checked.

o R-18 average value on recirculation = 1.2E-5 µCi/ml

• 32 Monitor Tank has been properly recirculated and sampled by Chemistry.

• Chemistry sample results have been obtained as follows:

o Total Gamma Activity= 1.74E-5 µCi/ml o Allowable Diluted Concentration = 1. 74E-7 µCi/ml o Boron Concentration = 1700 ppm o Boron pounds = 145 lbs

• Release valve alignment has been reviewed SAT.

Required Materials: 3-SOP-WDS-014; Liquid Waste Releases Completed Liquid Radioactive Waste Release Permit Form for 32 Monitor Tank 1 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

3-SOP-WDS-014; Liquid Waste Releases Completed Liquid Radioactive Waste Release Permit Form for 32 Monitor Tank Initiating Cue: Review the provided manually calculated Liquid Radioactive Waste Release Permit Form for the release of 32 Monitor Tank and authorize the release as the CRS.

Time Critical Task: NO Validation Time:

Task Standard: Student reviews the manually calculated Liquid radioactive Waste Release Permit Form and determines that the calculations for most restrictive discharge rate are incorrect based on an incorrect available dilution flow used in the calculations.

2 of 9

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)

-V1. Performance Step: DETERMINE Available Dilution Flow {B) per Attachment 7 and RECORD result on permit:

Standard: Student determines that the recorded available dilution flow for release (B) is incorrect. Permit has recorded 399,000 gpm, however with only three circulating water pumps operating at 215 RPM the flow should be only 199,500 gpm +/-500 gpm. This is determined by using Attachment 7.

(66.5 kgpm x 3 = 199.5 kgpm)

Comment: If student reports this discrepancy to you as the evaluator, cue him to continue to review the calculations on the permit and update the results if necessary using the correct dilution flow rate.

2. Performance Step: Determine that Chemistry sample results have been properly transcribed on the permit:

o Total Gamma Activity= 1.74E-5 µCi/ml o Allowable Diluted Concentration = 1. 7 4E-7 µCi/ml o Boron Concentration = 1700 ppm o Boron pounds = 145 lbs Standard: Student recognizes that the Chemistry sample results have been properly transcribed on the permit Comment: All chemistry sample results have been properly recorded on the permit.

3 of 9

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark '1)

..J 3. Performance Step: DETERMINE Most Restrictive Discharge Rate (D) as follows:

1. CALCULATE the permissible Radioactive Discharge Rate (Dr) per Attachment 8.

2. CALCULATE Permissible (Maximum Boron) Chemistry Discharge Rate (De) per Attachment 8.

3. SELECT a Most Restrictive Discharge rate (D) per Attachment 8.

Standard: Student determines that the Most Restrictive Discharge Rate of 150 gpm is too high based on only having 199,500 gpm dilution flow. Correct numbers are as follows:

1. Permissible Radioactive Discharge Rate (Dr) =

1950+/-50 gpm instead of previous calculated value of 3990 gpm.

2. Permissible Chemistry Discharge Rate (De) 117 =

+/- 2 gpm instead of the previously calculated 235 gpm.

=

3. Most Restrictive Discharge Rate (D) 117 +/- 2 gpm instead of the previously selected value of 150 gpm.

Comment: Attachment 8 calculations and directions.

4. Performance Step: IF R-18 is in service, THEN CALCULATE Alert setpoint for R-18 Channel 1 using Attachment 9 AND RECORD result on permit.

Standard: Student calculates new alarm and alert setpoints for R-18 IAW Attachment

9. New calculated alarm setpoint is higher, so previous incorrect alarm setpoint is conservative and may be left at the previously calculated setpoint. Previous setpoint should have been 4.5E-4 µCi/ml instead of 4.5E-5 µCi/ml as recorded. New Alarm setpoint is 2.9E-4 µCi/ml. Alert value is based on recirculation value of 1.2E-5 µCi/ml from the initial conditions and remains the same.

Comment: Attachment 9 calculations and directions.

Terminating Cue: JPM Complete 4 of 9

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

5 of 9

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A SRO Admin JPM in classroom 6 of 9

Appendix C Attachments Form ES-C-1 Initial Conditions:

• Unit is in MODE 5 for a forced outage.

• Circulating Water Pumps Status:

o 31, 33, and 35 in service at 215 RPM each.

o No other dilution flow sources are available or authorized.

• A Liquid Radioactive Waste Release Permit Form has been completed manually IAW Section 4.1 of 3-SOP-WDS-014; Liquid Waste Releases for the release of 32 Monitor Tank.

• R-18 is operable and has been appropriately source checked.

o R-18 average value on recirculation = 1.2E-5 µCi/ml

• 32 Monitor Tank has been properly recirculated and sampled by Chemistry.

• Chemistry sample results have been obtained as follows:

o Total Gamma Activity= 1.74E-5 µCi/ml o Allowable Diluted Concentration = 1. 74E-7 µCi/ml o Boron Concentration = 1700 ppm o Boron pounds = 145 lbs

• Release valve alignment has been reviewed SAT.

Initiating Cue:

Review the provided manually calculated Liquid Radioactive Waste Release Permit Form for the release of 32 Monitor Tank and authorize the release as the CRS.

7 of 9

Appendix C Attachments Form ES-C-1 LIQUID RADIOACTIVE WASTE RELEASE PERMIT FORM Perm it #: Next Release ID: 32 Mon Tank Volume: 10228 gal. Or Flow rate Number Min. Recirc. Earliest Sample:

Recirc.

Started - Date: Today Time: 0200 Time (T): 4 hr. Date: Today Time:

0600 Rad Monitor Source Check: Available dilution flow for Radiation In Service SAT release (B)

Monitor#: R-18 YES 399.000 gpm Chemistry analysis Sample#: Date: Today Time: 0615 Total Gamma Boron ppm: 1700 Boron pounds: 145 Activity (C): 174 E-5 µCilml Allowable Diluted Concentration Permissible Chemistry (ADC) in discharge canal: 174 E-7 µCilml Discharge Rate (De): 235 gpm Most Restrictive From:

• Waste Chemistty Permissible Radioactive Discharge Rate (D): 150 gpm (Check one) D Discharge Rate (Dr): 3990 gpm Radioactivity Radiation Alert Calculated Alarm Actual Alarm Monitor: Setpoint: 1.5 E-5 µCilml Setpoint (R): 4.63 E-5 µCilml Setpoint: 4.63 E-5 IF Rad Monitor is Monitor taken out of service on: 2nd sample obtained and analyzed by:

Out Of Service (Max. 30 days) Date: Time:

Release calculations performed by: Release calculations verified by:

(I) Release valve alignment reviewed (if applicable) SAT today checked by another operator (2) Release calculations reviewed Release (3) Release authorized by:

Authorization Release Rad Monitor reading initiated: Date: Time: during release:

Discharge flow meter operable: *IE flow meter is OOS, THEN RECORD estimate approx !hr into release and then every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (required by (Circle one)

IP-SMM-CY-001, Radioactive Effluents Control Program):

YES NO* 1 hr 4 hr 8 hr Post-Release Release Actual volume Section terminated: Date: Time: released:

Performed By: Another operator Alert and Alarm setpoints reset per 3-SOP-RM-O I 0: YES COMMENTS:

8 of 9

Appendix C Attachments Form ES-C-1 Key LIQUID RADIOACTIVE WASTE RELEASE PERMIT FORM Release ID: 32 Mon Tank Volume: 10228 gal. Or Flow rate Permit#: Next Number Recirc. Min. Recirc. Earliest Sample:

Started - Date: Today Time: 0200 Time (T): 4 hr. Date: Today Time: 0600 Rad Monitor Source Check: Available dilution flow for release Radiation In Service SAT (B)

Monitor#: R-18 YES l 'J'l)1JO gpm Chemistry analysis Sample#: Date: Today Time: 0615 Total Gamma Boron ppm: 1100 Boron pounds: 145 Activity (C): 1.74 E-5 µC Allowable Diluted Concentration Permissible Chemistry (ADC) in discharge canal: 1.74 E-7 µCi/ml Discharge Rate (De): m gpm Most Restrictive From: *Waste Permissible Radioactive Discharge Rate (D): l l7 gpm Chemistty Discharge Rate (Dr): I 950 gpm (Check one) D Radioactivity Radiation Alert Calculated Alarm Actual Alarm Monitor: Setpoint: 1.5 E-5 µCiiml Setpoint (R): 2.97 E-4 µCi/ml Setpoint:

Can be kit or 2 97 E-4 µCi/ml IF Rad Monitor is Monitor taken out of service on: 2nd sample obtained and analyzed by:

Out Of Service (Max. 30 days) Date: Time:

Release calculations performed by: Release calculations verified by:

(1) Release valve alignment reviewed (if applicable) SAT today checked by another operator (2) Release calculations reviewed (3) Release authorized by: (SM/

Release Authorization Release Rad Monitor reading initiated: Date: Time: during release:

Discharge flow meter operable:

• lE flow meter is OOS, THEN RECORD estimate approx 1hr into release and then every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (required by IP-(Circle one)

SMM-CY-001, Radioactive Effluents Control Program):

YES NO* 1 hr 4 hr 8 hr Post-Release Section Release Actual volume terminated: Date: Time: released:

Performed By: Another operator Alert and Alarm setpoints reset per 3-SOP-RM-O 10: YES COMMENTS:

9 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No:

Task

Title:

Classify Event and Complete Form EP-1, Part 1 KIA

Reference:

1940002.4.40 Job Performance Measure SROAdmin SR0-4.5 No: 5 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

This is a TIME CRITICAL Job Performance Measure from the time you are told to begin until the time you classify the event. Also, from the time you classify the event until you complete the Radiological Emergency Data Form (EP-1, Part 1).

You will be allowed sufficient time to read the initial conditions and cue. You will then be allowed to ask questions about the conditions. However, once you review the E-Plan EALs, your clock starts.

Required Materials: IP-EP-120, Emergency Classification IPEC Emergency Action Level Charts I EAL Book Appropriate E-Plan Forms (EP-1, Part 1)

General

References:

IP-EP-120, Emergency Classification IPEC Emergency Action Level Charts I EAL Book Appropriate E-Plan Forms (EP-1, Part 1) 1 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions:

A Reactor Trip occurred approximately 15 minutes ago after 135 days @ 100% reactor power due to a major steam break on 31 SG in the Turbine Building. The MSIVs had to be closed manually from the Control Room, however, 31 MSIV did not close and cannot be closed remotely. 32 AFW Pump is tagged out.

The CRS has just informed you that he is transitioning from E-0 to FR-H.1 due to a RED condition on Heat Sink. The following conditions also exist:

• 31 SG is approaching dryout

• 31 RCP has been tripped due to high vibrations

• 33 ABFP is operating but has no flow indicated

• RCS pressure is 1550 psig and increasing

• RCS cold legs are 450°F and stable

• High Head Safety Injection Pumps are operating

• 32 RHR pump is operating

• All EDGs are operating

• 480V Bus 3A normal feeder has tripped and the 2AT3A bus-tie breaker will not close.

• All Containment conditions are normal.

• The Turbine Building north end is not accessible but conditions are improving according to the Conventional NPO

• l&C is investigating the cause of the 3A Bus problem and lack of 33 ABFP flow. A cutback controller problem is not suspected for the lack of 33 ABFP flow.

• All SG WR levels are decreasing and below 20%.

• There is no radiological release in progress.

Unit 2 remains stable at 100% power.

METEOROLOGICAL CONDITIONS:

Wind Speed: 0.9 meters/second Wind Direction: 285 degrees @ 10 meters Stability Class: c Initiating Cue:

The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement Shift Manager can arrive on site. You must Classify the event and Complete the NYS Radiological Emergency Data Form, Part 1.

• This is a TIME CRITICAL JPM

• Inform the examiner when you have classified the event.

• Inform the examiner when you have completed the EP-1, Part 1 Form.

Time Critical Task: YES 2 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time:

Task Standard: Event properly classified and EP-1, Part 1 Form completed within the required times.

3 of 7

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

1. Performance Step: Candidates review initial conditions and the initiating cue.

They ask questions if necessary and then obtain the correct procedures.

Standard: Obtains IP-EP-120, Emergency Classification Comment: Allow up to 15 minutes for students to fully understand the initial conditions and requested time critical task. Allow questions as a group and/or individual. Once the student understands the task and has been given the appropriate procedures, the JPM is started. Provide the student with the JPM start time.

Record JPM Start Time here: - - -

CUE: Provide the student with the JPM start time .

..../2. Performance Step: Evaluate Plant Status to determine if GE, SAE, Alert, or NUE applies. Determines the highest classification and makes declaration.

Standard: Determines Event is a SAE per EAL FS-1.1, Loss or potential loss of any two barriers (Table F-1 ). Fuel Clad -

Heat Sink - RED entry conditions met and heat sink is required and RCS - RED entry conditions met and heat sink is required. Must be determined within 15 minutes.

TIME CRITICAL - Must complete this step within 15 minutes of start of JPM.

Comment: Record the Time Declaration Made: -------

'1 3. Performance Step: Completes and approves "New York State Radiological Emergency Data Form, Part 1" (I P-EP-115-EP-1 ).

Standard: Completes all necessary information on the form and signs the form.

TIME CRITICAL - Must complete this step within 15 minutes of Time of Declaration (JPM Step 2)

Comment: Record the Time Form is completed: _ _ _ _ __

Terminating Cue: JPM Complete 4 of 7

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

5 of 7

Appendix C Simulator Setup Form ES-C-1 Simulator Setup N/A SRO Admin JPM in classroom 6 of 7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

A Reactor Trip occurred approximately 15 minutes ago after 135 days @ 100% reactor power due to a major steam break on 31 SG in the Turbine Building. The MSIVs had to be closed manually from the Control Room, however, 31 MSIV did not close and cannot be closed remotely. 32 AFW Pump is tagged out.

The CRS has just informed you that he is transitioning from E-0 to FR-H.1 due to a RED condition on Heat Sink. The following conditions also exist:

• 31 SG is approaching dryout

• 31 RCP has been tripped due to high vibrations

• 33 ABFP is operating but has no flow indicated

• RCS pressure is 1550 psig and increasing

• RCS cold legs are 450°F and stable

• High Head Safety Injection Pumps are operating

• 32 RHR pump is operating

• All EDGs are operating

• 480V Bus 3A normal feeder has tripped and the 2AT3A bus-tie breaker will not close.

• All Containment conditions are normal.

• The Turbine Building north end is not accessible but conditions are improving according to the Conventional NPO

• l&C is investigating the cause of the 3A Bus problem and lack of 33 ABFP flow. A cutback controller problem is not suspected for the lack of 33 ABFP flow.

• All SG WR levels are decreasing and below 20%.

• There is no radiological release in progress.

Unit 2 remains stable at 100% power.

METEOROLOGICAL CONDITIONS:

Wind Speed: 0.9 meters/second Wind Direction: 285 degrees @ 10 meters Stability Class: c Initiating Cue:

The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement Shift Manager can arrive on site. You must Classify the event and Complete the NYS Radiological Emergency Data Form, Part 1.

• This is a TIME CRITICAL JPM

• Inform the examiner when you have classified the event.

• Inform the examiner when you have completed the EP-1, Part 1 Form.

You will be allowed sufficient time to read the initial conditions and cue. You will then be allowed to ask questions about the conditions. However, once you review the E-Plan EALs, your clock starts.

7 of 7