ML092940714

Initial Exam 2008-301 Draft Simulator Scenarios

ML092940714
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/08-301, 50-414/08-301
Download: ML092940714 (97)

Text

Appendix 0, Rl3v. 9 Scenario Outline Form ES-D-1 2008 NRC EXAMINATION Catawba Nuclear Station Facility: Scenario No.: Op-Test No.:

Examiners: Operators:

Initial Conditions:

Stable at 10-8 amps

(

Turnover:

Incease power to 1%.

Event Malf. No. Event Event No. Type* Description 1 RO R Increase power from 10-8 amps and stabilize at 1%.

2 BOP I Total Sealwater Flow meter fails high 3 BOP I IIR channel N35 loss of high voltage (fails low)

SRO TS 4 RO C 1C S/G feedwater bypass valve fails open 5 BOP C Loss of KC train, must swap to alternate train SRO TS 6 RO C 10 S/G PORV fails open 7 ALL M Main Steam Line Break Outside Containment on 1A S/G Additional Failures Failure of automatic feedwater (CF) isolation Failure of automatic S/I both trains 1A MSIV failed open/ 1C MSIV fails to close in auto 1ND-59B failed closed

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

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 1 1 Page Event

Description:

Increase power from 10-8 amps and stabilize at 1%.

Time Position Applicant's Actions or Behavior AQplicant's EXAMINER NOTE: This is a REACTIVITY event using OP/1/A/61 00/001 (Controlling Procedure For Unit Startupl (ControllinR Startup).

ALL NOTE:

1. Control rod withdrawal shall NOT exceed the temporary rod withdrawal limits specified in Unit One RO.D. Section 2.3.

2. Refer to Unit One RO.D. Section 2.4 for the rate at which reactor power can be changed.

3. The throttling of a S/G bypass reg valve affects the other S/G bypass reg valves. Therefore, SM/CF ilP needs to be monitored as the unit approaches POAH.

4. If NC boron concentration is greater than 1000 ppmB, T-AVG control may be very sensitive above the POAH due to a positive MTC. Refer to Unit One RO.D. Section 5.10 for the MTC at the current conditions.

5. When approaching the POAH, a startup rate of < 0.2 dpm is recommended; this rate should NOT be exceeded until the turbine is placed on line. (SOMP 01-02).

RO 2.159 Increase reactor power 1%. (RM.)

to 1%.iRMJ J)owerto END EVENT Page 1 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 2 1 Page Event

Description:

Total Sealwater Flow meter fails high Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using OPf1fBf61 OOf01 OH (Annunciator Response for PaneI1AD-07), Cf4 - NCP SEAL WATER LO FLOW EXAMINER NOTE: SRO may refer to APf1fAf5500f008 (Malfunction of Reactor Coolant Pump), however, this is not required. re~uired.

Immediate Actions BOP 1. Dispatch an operator to 1RFM-14 on 1RFMP1 (AB-574, BB-55, Rm 491) to identify the affected pump(s) and acknowledge the alarm.

BOP 2. Position 1NV-309 (Seal Water Inj Flow) to increase seal water flow.

SRO 3. Refer to AP/1/A/5500108 (Malfunction of Reactor Coolant Pump).

Supplemental Sup(!lemental Actions SRO 1. IF any NC pump is tripped, refer to AP/1/A/5500104 (Loss of Reactor Coolant Pump).

BOP 2. Ensure KC flow to NC PumpPum~ thermal barrier is normal.

BOP 3. Monitor #1 seal leak-off flow and #1 seal outlet temperature.

BOP 4. IF filling the seal water injection filter housing after filter replacement, perform the following:

4.1 Verify flow to the NCPs is maintained.

complete, verify 4.2 WHEN filling is com2lete, verify flow returns to normal.

END EVENT Page 2 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 3 1 Page(s)

Event

Description:

Descri]:>tion: IIR channel N35 blown fuse - fails low Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/016 (Malfunction of Nuclear Instrumentation System).

RO 1. Verify reactor power - GREATER THAN 10%.

RO 1RNO

1. Stop any power increase.

RO 2. Verify 1AD-2, C/3 "I/R HI FLUX LEVEL ROD STOP" - DARK RO 3. Identify affected IIR channel:

• N-35 OR

• N-36.

BOP NOTE 1AD-2, C/4 "Nil SYS SIR & I/R TRIP BYPASS" will actuate in the following step.

4. At the affected I/R drawer, perform the following:

a. Place the "LEVEL TRIP" switch for affected channel in "BYPASS".

Verif~ the "LEVEL TRIP BYPASS" light on the affected I/R drawer - LIT.

b. Verify RO triQt~ypass

5. Verify the affected IIR channel trip bypass status light (1 SI-19) - LIT.

RO 6. Verify 1AD-2, C/4 "Nil SYS SIR & IIR TRIP BYPASS" - LIT.

RO 7. Ensure the "NIS RECORDER" - ALIGNED TO THE OPERABLE I/R CHANNEL.

RO 8. WHEN the operable I/R channel is less than 10-10 Amps, THEN ensure SIR channels are reset.

ALL 9. Determine and correct cause of IIR malfunction.

EXAMINER NOTE: Tech Spec 3.3.1 #4 Condition F applies.

SRO 10. Ensure compliance with Tech Spec 3.3.1 (Reactor Trip System (RTS)

Instrumentation) .

EXAMINER NOTE: No notifications at this time.

SRO 11. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 iNRC (NRC Notification Requirementsl Requirements).

BOP 12. Notify Reactor Group Engineer of occurrence.

SRO CAUTION Installing I/R fuses with any P/R channel inoperable or in a tripped condition, may result in a reactor trip on P/R rate trip due to voltage spikes.

13. WHEN the affected I/R channel is repaired, THEN ensure IAE returns the channel to service.

SRO 14. Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 3 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 4 1 Page Event

Description:

1C S/G feedwater bypass valve fails open Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using OP/1/B/61 00/01 OE (Annunciator Response for PaneI1AD-04).

Al3 - S/G C FLOW MISMATCH CF > STM B/3 - FCV OR BFCV DEVIATION EXAMINER NOTE: SRO may refer to AP/1/A/5500/006 (Loss of S/G Feedwater); however, this is not required.

RO Using responses N3 and/or B/5, candidate will take manual control of 1CF-48 and throttle to stabilize C S/G level.

Al3 actions NOTE: SM flow channel 2 shares a reference tap with channel 1 of S/G narrow range level indication. SM flow channel 1 shares a reference tap with S/G wide range level indication. A failure on one of these level taps will affect the SM flow channel. Other indication of SM flow should be used to determine if it is an instrument failure.

Immediate Actions RO 1. Compare steam and feed flow indications on S/G 1C with other S/Gs to verify condition.

RO 2. IF automatic controls are NOT correcting, take manual control.

RO 3. Check feed and steam pressures of affected S/G to determine if a feedwater line has ruptured.

SRO 4. IF determined to be feedwater line break, refer to AP/1/N5500106 (Loss of S/G Feedwater).

Supplemental Actions RO 1. WHEN malfunction is corrected OR bypassed, restore control to automatic.

EXAMINER NOTE: No Tech Spec Conditions apply.

SRO 2. Refer to Tech Specs for operable channel requirements (TS 3.3.1, 3.3.2, 3.3.3 and 3.3.4).

END EVENT Page 4 of 17

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 1 Event No. 5 3 Pages Event

Description:

Loss of KC train, must swap to alternate train Time Position AQ2Iicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/021 (Loss of Component Cooling).

ALL CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss.

Monitor Enclosure 1 (Foldout Paae).

BOP 2 Verify at least one KC pump - ON.

EXAMINER NOTE: 181 KC pump can not be started manually, however it will start automatically later.

BOP 2 RNO Perform the following:

a. Start at least one KC pump.

b. IF no KC pump can be started, THEN ...

BOP NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4 Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK.

AND

• At least one KC pump - ON .

BOP 5 IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO.

BOP 6 Verify both KC surge tank levels - 50% - 90% AND STABLE.

BOP 7 Start additional KC pump(s) as necessary to supply any KC loads notify presently in service.

BOP 8 CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure.

Verify KC flow to NC pumps as follows:

• 1AD-20, N1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK

• 1AD-21, N1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK .

BOP 9a. Verify the following Train A KC non-essential header isolation valves - OPEN:

• 1KC-230A (Rx Bldg Non-Ess Hdr 1501)

• 1KC-3A (Rx Bldg Non-Ess Ret Hdr 1501)

• 1KC-50A (Aux Bldg Non-Ess Hdr 1501)

• 1KC-1A (Aux Bldg Non-Ess Ret Hdr 1501).

BOP 9b. Verify the following Train B KC non-essential header isolation valves - OPEN:

• 1KC-228B (Rx Bldg Non-Ess Hdr 1501)

• 1KC-18B (Rx Bldg Non-Ess Ret Hdr 1501)

• 1KC-53B (Aux Bldg Non-Ess Hdr 1501)

• 1KC-2B (Aux Bldg Non-Ess Ret Hdr 1501).

Page 5 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. S 3 Pages Event

Description:

Loss of KC train, must swap to alternate train Time Position Applicant's Actions or Behavior BOP 9c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP 10. Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - SO% - 90% AND STABLE.

SRO Ste~ 14.

b. GO TO Step BOP exchan~_er outlet mode switches - PROPERLY ALIGNED.

14 Ensure KC heat exchanger BOP 1S Determine and correct cause of loss of KC.

EXAMINER NOTE: Tech Spec 3.7.7, Condition A applies. a~plies.

SRO 16 Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.9-7 (Boration Systems Flow Path - Shutdown)

• SLC 16.9-8 (Boration Systems Flow Path - Operating)

• SLC 16.9-9 (Boration Systems Pumps - Shutdown)

• SLC 16.9-10 (Boration Systems Charging Pumps - Operating)

• 3.S.2 (ECCS - Operating)

• 3.S.3 (ECCS - Shutdown)

• 3.6.6 (Containment Spray System)

• 3.7.S (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System).

EXAMINER NOTE: No notifications required.

SRO 17 Determine required notifications:

• REFER TO RP/O/A/SOOOI001 (Classification Of Emergency)

• REFER TO RP/O/B/SOOOI013 JNRC (NRC Notification Requirements).

BOP 18 IF KC Hx leak to RN is suspected, THEN ...

BOP 19 Verify KC surge tanks level as follows:

• Greater than SO%

• Stable or increasing.

BOP 20 WHEN plant conditions permit, THEN:

• Return KC pumps to normal operation. REFER TO OP/1/A/6400100S (Component Cooling Water System).

• Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 4 _(Alternate (Alternate Cooling To NV Pump 1A).

BOP 21 Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK

• 1AD-7, H/3 "VCT HI TEMP" - DARK

• Normal letdown - IN SERVICE.

Page 6 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. S 3 Pages Event Descr~tion: Loss of KC train, must swap to alternate train Time Position Applicant's Actions or Behavior BOP 22 Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) Open the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

2) Close the following valves:

• 1NV-2S2A (NV Pumps Suct From FWST)

• 1NV-2S3B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to the "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through the NV demineralizers, THEN' momentarily place 1NV-1S3A (Letdn Hx Otlt 3-Way VI v) to the "DEMIN" position and return to "AUTO".

SRO 23 Determine lon~ term plant status. RETURN TO procedure in affect.

END EVENT Page 7 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 6 2 Page Event

Description:

1 D S/G PORV fails open Time Position AQ2licant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/028 (Secondary Steam Leak) however; they may use OMP 1-7 guidance to isolate a known steam leak. AP/lIAl5500/028 entlY is not "required".

ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Verify turbine - ONLINE.

RO 3. Verify the following:

• Reactor power - LESS THAN OR EQUAL TO 100% POWER

• T-Avg - WITHIN 1.5°F OF T-Ref.

RO 4. Verify proper reactor response as follows:

• Control rods - IN "AUTO" AND STEPPING IN

• P/R neutron flux - DECREASING.

RO 5. IF AT ANY TIME reactor power is greater than 100%, THEN perform Step 3 RNO.

BOP 6. Verify Pzr level- STABLE OR INCREASING.

BOP 7. IF AT ANY TIME while in this procedure Pzr level is decreasing in an uncontrolled manner, THEN RETURN TO Step 6.

BOP 8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows:

a. Open the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. Close the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

BOP 9. Attempt to identify and isolate leak as follows:

a. Verify the following conditions - NORMAL:

• Containment temperature

• Containment pressure

• Containment humidity

• Containment floor & equipment sump level.

b. Dispatch operators to locate and identify source of steam leak.

c. Verify S/G PORVs - CLOSED.

RO 9cRNO.

c. IF S/G pressure is less than 1090 PSIG, THEN perform the following:

1) Close affected S/G PORV.

2) IF S/G PORV is still open, THEN:

a) Close affected S/G PORV isolation valve.

b) IF S/G PORV isolation valve still open, THEN ...

RO 9d. Verify condenser dump valves - CLOSED.

e. Verify atmospheric dump valves - CLOSED.

f. Verify CA PMP #1 - OFF.

g. IF leak is suspected to be in a doghouse, THEN ...

EXAMINER NOTE: No required notifications at this time.

Page 8 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 6 2 Page Event

Description:

10 S/G PORV fails open Time Position Applicant's Actions or Behavior SRO 10. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements) .

BOP 11. Notify RP of leak.

RO 12. Verifi - LEAK ISOLATED.

SRO 13. Determine long term plant status. RETURN TO procedure and step in effect.

END EVENT Page 9 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A S/G Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event entering EP/1/A/5000/E-O.

ALL 1. Monitor Enclosure 1_{Foldout Page).

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers -

• IIR amps - DECREASING.

RO 3 Verify Turbine Trip:

All turbine stop valves - CLOSED BOP 4 Verif:i 1 ETA and 1ETB - ENERGIZED.

BOP 5 Verify SII is actuated:

a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

5aRNO a.Perform the following:

1) Verify conditions requiring SII:

• Pzr pressure - LESS THAN 1845 PSIG OR

• Containment pressure -GREATER THAN 1.2 PSIG .

2) IF SII is required, THEN manually initiate S/I.

3) IF SII is not required, THEN ...

BOP b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

RO 6 Announce "Unit 1 Safety Injection".

EXAMINER NOTE: Classification is 4.S.A.1 (Alert )

SRO 7 Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 {NRC Notification Re~uirements).

RO 8 Verify all Feedwater Isolation status lights (1 SI-5) - LIT.

EXAMINER NOTE: Automatic feedwater isolation is blocked and will require manual initiation.

RO 8RNO Perform the following:

a. Manually initiate Feedwater Isolation.

b. IF proper status light indication is not obtained, THEN manually close valves.

BOP 9 Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

b. Monitor Light Panel Group 5 St lights - LIT.

BOP 10a Verify proper Phase B actuation as follows:

a. Containment pressure - HAS REMAINED LESS THAN 3 PSIG.

ALL b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this

~rocedure, THEN ~erform Step 10.a.

BOP 11 a Verify proper CA pump status as follows:

Motor driven CA pumps - ON.

Page 10 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A SIG Time Position Applicant's Actions or Behavior BOP 11 b 3 SIG NIR levels - GREATER THAN 11 %.

BOP 11 b RNO Ensure CA Pump #1 - RUNNING.

BOP 12 Verify all of the following SII pumps - ON:

• NV pumps

• NO pumps

• NI pumps.

BOP 13 Verify all KC pumps - ON.

BOP 13RNO Perform the following for affected train(s):

a. Reset ECCS.

b. Reset DIG load sequencer.

c. Manually start affected pump.

d. IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

BOP 14 Verify all Unit 1 and Unit 2 RN pumps - ON.

EXAMINER NOTE: Enclosure 2 actions are listed after step 24 BOP 15 Verify proper ventilation systems operation as follows:

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification).

RO 16 Verify all SIG pressures - GREATER THAN 775 PSIG.

EXAMINER NOTE: 1A S/G MSIV is failed open. 1C S/G MSIV fails to close in automatic but can be closed manually.

RO 16RNO Perform the following:

a. Verify the following valves - CLOSED:

• All MSIVs

• All MSIV bypass valves

• All SIG PORVs.

b. IF any valve is open, THEN:

1) Manually initiate Main Steam Isolation.

2) IF any valve is still open, THEN manually close valve.

BOP 17a Verify proper SII flow as follows:

• "NV S/I FLOW' -INDICATING FLOW.

BOP 17b NC pressure - LESS THAN 1620 PSIG.

BOP 17c NIQumps -INDICATING FLOW.

BOP 17d NC pressure - LESS THAN 285 PSIG.

EXAMINER NOTE: 1 NO-5gB is failed closed and the 1B NO pump will be secured per the RNO.

Page 11 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A S/G Time Position Applicant's Actions or Behavior BOP 17d RNO Perform the following:

1) Ensure NO pump miniflow valve on operating NO pump(s) - OPEN.

2) IF the NO pump miniflow valve(s) cannot be opened, THEN perform

3) the following for affected train(s):

a) Reset ECCS.

b) Reset DIG load sequencer.

c) Stop NO pump.

d) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previouslyon.

e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart the NO pump.

4) GO TO Step 18.

BOP 18aControi S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

BOP 18b WHEN at least one S/G NIR level is greater than 11 % (29% ACC), THEN throttle feed flow to maintain all S/G NIR levels between 11 % (29% ACC) and 50%.

BOP 19 Verify all CA isolation valves - OPEN.

BOP 20 Verify SII equipment status based on monitor light panel - IN PROPER ALIGNMENT.

EXAMINER NOTE: Enclosure 4 actions are listed after Enclosure 2 actions.

RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance.

21 Control NC tem~erature. REFER TO Enclosure 4 (NC Temperature Control).

BOP 22 Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

BOP b. Normal Pzr spray valves - CLOSED.

BOP c. At least one Pzr PORV isolation valve - OPEN.

RO 23 Verify NC subcooling based on core exit TICs - GREATER THAN OaF.

RO 24 Verify main steam lines are intact as follows:

• All S/G pressures - STABLE OR INCREASING

• ALL S/Gs - PRESSURIZED .

Page 12 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A S/G Time Position Applicant's Actions or Behavior ALL 24RNO IF pressure in any S/G is decreasing in an uncontrolled manner OR any S/G is depressurized, THEN perform the following:

a. IF both the following conditions exist,

• Containment pressure - GREATER THAN 1 PSIG

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG THEN manually start one VX fan. REFER TO Enclosure S (VX Fan Manual Start)

b. Concurrently:

• Implement EP/1/NSOOO/F-O (Critical Safety Function Status Trees).

• GO TO EP/1/NSOOO/E-2 (Faulted Steam Generator Isolation).

Enclosure 2 actions BOP 1. Verify proper VCNC operation as follows:

a. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRAAHU-1

• CRA PFT-1.

b. Verify the following alarms - DARK:

• 1AD-18, N8 "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-18, B/8 "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-18, 0/8 "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-18, E/8 "UNIT 2 INTAKE HI CHLORINE 2B".

c. Ensure the following VC dampers - OPEN:

• 1VC-SB (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-SB (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

d. Repeat Step 1 of this enclosure until notified by station management as follows:

• At least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR

• Any time VCNC related annunciators on 1AD-18 actuate.

BOP 2. Ensure proper VA System operation as follows:

• Ensure the following fans - OFF:

o ABUXF 1A o ABUXF 1B.

• Ensure VA System filter is in service as follows:

o 1ABF-D-12 (VA Filt A Bypass Damper) - CLOSED o 1ABF-D-S (VA Filt B Bypass Damper) - CLOSED.

• Ensure the following fans - ON:

o ABFXF-1A o ABFXF 1B.

Page 13 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A S/G Time Position Applicant's Actions or Behavior ARPlicant's BOP 3. Verify proper VE System operation as follows:

a. VE fans - ON.

b. Annulus pressure - BETWEEN -1.4 IN. WC AND -1.8 IN. WC.

c. Repeat Step 3.b every 30 minutes until notified by station management.

BOP 4. Record time ventilation systems are verified on following table:

Enclosure 4 actions RO 1. Verify at least one NC pump - ON.

RO 2. Use NC T-Avg to determine NC temperature as required in subseiluent subsequent steps.

RO 3. IF AT ANY TIME NC pumps are tripped, THEN use NC T-Colds to determine stel~s.

NC temperature as required in subsequent steps.

RO 4. Verify one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

RO 4RNO GO TO Step 7.

RO 7. Verify NC temperature - LESS THAN 557°F AND DECREASING.

RO 8. Attempt to stop the NC cooldown as follows:

a. Ensure all steam dumps - CLOSED.

b. Ensure all S/G PORVs - CLOSED.

c. Ensure S/G blowdown is isolated.

d. Close the following valves:

• 1SM-77A (S/G 1A Otlt Hdr Bldwn CN)

• 1SM-76B (S/G 1B Otlt Hdr Bldwn CN)

• 1SM-75A (S/G 1C Otlt Hdr Bldwn CN)

• 1SM-74B (S/G 10 Otlt Hdr Bldwn CN).

e. Depress and hold "SN BEFORE SEAT DRN" "CLOSE" pushbutton (1MC-3) to close the following valves:

• 1SM-41 (Stop Vlv #1 Before Seat Drn)

• 1SM-44 (Stop Vlv #2 Before Seat Drn)

• 1SM-43 (Stop Vlv #3 Before Seat Drn)

• 1SM-42 (Stop Vlv #4 Before Seat Drn).

f. Verify NC cooldown - STOPPED.

Page 14 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A S/G Time Position Applicant's Actions or Behavior RO 8fRNO.

f. IF cooldown continues, THEN throttle 'feed flow as follows:

1) IF S/G N/R level is less than 11 % (29% ACC) in all S/G's, THEN throttle feed flow to achieve the following:

• Minimize cooldown

• Maintain total feed flow greater than 450 GPM.

2) WHEN N/R level is greater than 11 % (29% ACC) in at least one S/G, THEN throttle feed flow further to achieve the following:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11% (29% ACC).

3) IF cooldown continues, THEN close the following valves:

• All MSIVs

• A" MSIV bypass valves.

RO 9. Continue to perform the actions of this enclosure as required to ensure one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 557°F.

SRO Transition to EP/11A15000/E-2 ALL 1 Monitor Enclosure 1 (Foldout Page).

ALL 2 Maintain any faulted S/G or secondary break isolated during subsequent recovery actions unless needed for NC System cooldown.

recove[y RO 3 Verify the following valves - CLOSED:

• A" MSIVs

• A" MSIV bypass valves.

RO valve(s).

3RNO Manua"y close valve(sj.

RO 4 Verify at least one S/G 2!"essure pressure - STABLE OR INCREASING.

RO Identify faulted S/G(s) as follow~:

• Verify any S/G pressure - DECREASING IN AN UNCONTROLLED MANNER OR

• Verify any S/G - DEPRESSURIZED.

RO Verify at least one intact S/G - AVAILABLE FOR NC SYSTEM COOLDOWN.

Page 15 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A S/G I Time Position Applicant's Actions or Behavior RO 7 Isolate all faulted S/G(s) as follows:

• S/G 1A:

a. Verify S/G 1A Feedwater Isolation status light (1 SI-5) - LIT.

b. Verify S/G 1A PORV - CLOSED.

c. Close the following valves:

1) 1SM-77A (S/G 1A Otlt Hdr Bldwn CV).

2) 1CA-62A (CA Pmp A Disch To S/G 1A Iso/).

3) 1CA-66B (CA Pmp 1 Disch To S/G 1A Isol).

d. Verify the following blowdown isolation valves - CLOSED:

1) 1BB-56A (S/G 1A Bldwn Cont Isollnsd).

2) 1BB-148B (S/G 1A Bldwn Cant Isol Byp).

3) 1BB-57B (S/G 1A Bldwn Cont Isol Otsd).

RO 8 WHEN NC T-Hots start to increase, THEN dump steam from intact S/G PORVs to stabilize NC T-Hots.

BOP 9 Verify the following annunciators - DARK

• 1AD-5, H/4 "CACST LO LEVEL"

• 1AD-8, B/1 "UST LO LEVEL".

BOP 10. Verify secondary radiation is normal as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all S/Gs for chemistry sampling.

c. Perform at least one of the following:

• Notify Chemistry to periodically sample all S/Gs for activity.

OR

• Notify RP to periodically frisk all cation columns for activity.

d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steam line 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steamline 1D).

S/Gl~ fault - INSIDE CONTAINMENT.

e. Verify the S/G(s)

BOP e.RNO Request RP to perform the following:

1) Monitor the area of the steam fault for radiation.

2) Notify the control room of any abnormal radiation conditions.

BOP f. WHEN activity results reported, THEN verify all S/Gs indicate no activity.

EXAMINER NOTE: Crew should be able to terminate safety injection at this point.

Page 16 of 17

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 1 Event No. 7 8 Pages Event

Description:

Main Steam Line Break Outside Containment on 1A SIG Time Position Applicant's Actions or Behavior All 11 Verify SII termination criteria as follows:

a. NC subcooling based on core exit TICs - GREATER THAN OaF.

b. Verify secondary heat sink as follows:

• NIR level in at least one intact SIG - GREATER THAN 11 % (29% ACC)

OR

• Total feed flow to all intact SIGs - GREATER THAN 450 GPM.

c. NC pressure - STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11 % (20% ACC).

e. GO TO EP/1/A/5000/ES-1.1 (Safety Injection Terminationl Termination).

SRO Transition to EP/1/A/5000/ES-1.1 All 1 Monitor Enclosure 1 (Foldout Page).

BOP 2 Ensure SII - RESET:

a. ECCS.

b. DIG load sequencers.

c. IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.

BOP 3 Ensure the following containment isolation signals - RESET:

• Phase A

• Phase B.

BOP 4 Establish VI to containment as follows:

• Ensure 1VI-77B (VI Cont Isol) - OPEN.

• Verify VI pressure - GREATER THAN 85 PSIG.

BOP 5 Verify proper NS pump operation as follows:

a. Containment pressure - HAS EXCEEDED 3 PSIG.

BOP 5RNO a. GO TO Step 6.

BOP 6 Ensure only one NV pump - ON.

RO 7 Verify NC pressure - STABLE OR INCREASING.

BOP 8 Verify VI pressure - GREATER THAN 50 PSIG.

BOP 9 Isolate NV SII flowpath as follows:

a. Verify the following valves - OPEN:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

BOP b. Verify the following valves - OPEN

• 1NV-203A (NV Pumps A&B Recirc Isol)

• 1NV-202B (NV Pmps A&B Recirc Isol).

BOP c. Close the following valves:

• 1NI-9A (NV Pmp C/l Inj Isol)

• 1NI-1 OB (NV Pmp C/l Inj Isol).

END EVENT Page 17 of 17

DRAFT Appendix D, Rev. 9 Scenario Outline Form ES-D-1 2008 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.:

2 Op-Test No.:

Examiners: Operators:

Initial Conditions:

• 100% power

• DFCS channel 3 out of service to repair a tubing leak (loop 5142 - CF Header Pressure) -

functional in progress

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Maintain 100%

Event Malf. No. Event Event No. Type* Description 1 RO I NC Loop A Cold Leg Temperature fails high - auto rod motion 2 BOP I PZR level Ch2 fails low - loss of letdown SRO TS 3 BOP C B Train KC mini-flow valve fails open 4 RO R Vacuum leak - manual turbine load decrease 5 RO C Rod H-8 drops partially into the core SRO TS 6 BOP C Loss of running RN pump 7 ALL M Rod M-12 drops, ATWS, loss of heat sink Additional failures Complete loss of vacuum Auto and manual Rx trip fail CAPT O/S, B CA fails to start NV aux spray valve fails closed

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

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 1 2 Page(s)

Event

Description:

NC Loop A Cold Leg Temperature fails high - auto rod motion Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/015 (Rod Control Malfunctions),

MalfunctionsJ. Case 2 Continuous Rod Motion.

RO 1. Ensure "CRD BANK SELECT" switch -IN MANUAL.

RO 2. Verify all rod motion - STOPS.

RO NOTE For T-Ref failures, T-Ref will need to be determined for current power level.

3. Manually adjust control rods as necessary to maintain T-Avg within 1°F of T-Ref.

RO 4. Verify the following parameters - NORMAL FOR EXISTING PLANT CONDITIONS:

• Channel 1 Turbine Impulse Pressure

• T-Ref.

BOP 5. Verify the following channels - NORMAL FOR EXISTING PLANT CONDITIONS:

• NC Loop A T-Avg

• NC Loop B T-Avg

• NC Loop C T-Avg

• NC LoopD Loop 0 T-Avlt-T-Avg.

BOP 5RNO IF channel inoperable, THEN perform the FOR EXISTING PLANT CONDITIONS: following:

a. Place "DJTEMP DEFEAT" switch to failed loop.

b. Place "T-AVG DEFEAT" switch to failed loop.

c. WHEN T-Avg is within +/-1°F ofT-Ref AND auto rod control is desired, THEN return rod control to "AUTO".

d. Ensure P-12 interlock in required state for existing plant conditions. REFER TO Tech Spec 3.3.2.

e. Have IAE trip bistables associated with the failed loop within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. REFER TO Model W/O #91002943:

• OPDT (Tech Spec 3.3.1)

• OTDT (Tech Spec 3.3.1)

• Low T-Avg (Tech Spec 3.3.2).

ALL 6. Determine and correct cause of continuous rod movement.

EXAMINER NOTE: Tech Specs 3.3.1-1 #6 Condition E and 3.3.2 #8.c Condition 0 apply.

SRO 7. Ensure compliance with appropriate Tech Specs:

• 3.1.1 (Shutdown Margin (SDM))

• 3.1.4 (Rod Group Alignment Limits)

• 3.1.5 (Shutdown Bank Insertion Limits)

• 3.1.6 (Control Bank Insertion Limits)

• 3.3.1 (Reactor Trip Instrumentation)

• 3.3.2 (ESFAS Instrumentation)

• 3.4.2 iRCS Tem~erature for Criticality).

(RCS Minimum Temperature EXAMINER NOTE: No notifications at this time.

Page 1 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 1 2 Page(s)

Event

Description:

NC Loop A Cold Leg Temperature fails high - auto rod motion Time Position AppJicant's Appjicant's Actions or Behavior SRO 9. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements) .

RO 9. WHEN rod control problem is repaired, THEN perform the following:

a. Ensure T-Avg - WITHIN 1°F OF T-REF.

b. WHEN desired, THEN place control rods in "AUTO".

c. Ensure steam dumps - IN DESIRED MODE FOR EXISTING PLANT CONDITIONS.

SRO 10 Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 2 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/012 (Loss of Charging or Letdown), Case 2 {Loss of Letdown).

BOP 1 Verify all Pzr level channels - INDICATING THE SAME.

BOP 1RNO IF a controlling channel is failed low, THEN place "PZR LEVEL CTRL SELECT" switch in any alternate operable channel position.

RO 2 Stop any power changes.

BOP 3 Ensure the following letdown isolation valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11 A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 4 Veri~ Pzr level - GREATER THAN 17%.

BOP 5 Control charging to stabilize Pzr level at program level while maintaining seal injection flow.

BOP 6 Ensure "PZR HTR GROUP 1COl - ON.

BOP 7 Control VCT level as follows:

a. Verify NC system makeup - SET FOR DESIRED BORON CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" -IN AUTOMATIC.

BOP 8 Determine and correct cause of loss of letdown.

BOP 9 IF AT ANY TIME excess letdown is required, THEN establish excess letdown.

REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

EXAMINER NOTE: Enclosure 5 actions are listed after step 22.

BOP 10 Verify proper VCIYC system operation. REFER TO Enclosure 5 (Control RoomVentilation System Verification).

BOP 11 Ensure "PZR LEVEL TO REC SEL" is selected to an operable channel.

EXAMINER NOTE: Tech Spec 3.3.1 #9 Condition L applies.

SRO 12 Ensure compliance with appropriate Tech Specs:

• 3.3.1 (Reactor Trip System (RTS) Instrumentation)

• 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

• 3.3.4 (Remote Shutdown System)

• 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits)

• 3.4.12 (Low Temperature Overpressure Protection (LTOP) System)

• 3.6.3 (Containment Isolation Valves).

BOP 13 Verify at least one of the following valves - CLOSED:

• 1NV-1A (NC Letdn To Regen Hx Isol)

OR

• 1NV-2A (NC Letdn To Regen Hx Isol).

Page 3 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown Time Position Applicant's Actions or Behavior BOP 14. Verify the following Letdn Orif Otlt Cont 1501 valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont 1501)

• 1NV-11 A (Letdn Orif 1C Otlt Cont 1501)

• 1NV-13A (Letdn Orif 1A Otlt Cont 1501). 1501}.

BOP NOTE

• If either NC loop letdown valve (1 NV-1A or 1NV-2A) closed before all orifice isolation valves (1 NV-1 OA, 1NV-11A and 1NV-13A), the letdown line will require local repressurization.

• all valves closed from automatic signal(s), it can be assumed the orifice If valves reached the closed position first.

15. Verify all the following valves - CLOSED BY AUTOMATIC SIGNAL(s).

• 1NV-1A (NC Letdn To Regen Hx 1501)

• 1NV-2A (NC Letdn To Regen Hx 1501)

• 1NV-1 OA (Letdn Orif 1B Otlt Cont 1501)

• 1NV-11A (Letdn Orif 1C Otlt Cont 1501)

• 1NV-13A (Letdn Orif 1A Otlt Cont 1501).

RO 15RNO Perform the following:

a. IF all orifice isolation valves are known to have been closed prior to either NC loop letdown valve closing, THEN GO TO Step 18.

BOP 18 Establish letdown as follows:

a. Verify ability to establish normal letdown - RESTORED.

BOP b. Ensure 1NV-849 (Letdn Flow Var OrifCtrl) valve demand position - 0%.

BOP c. Verify the following valves - OPEN:

• 1NV-1A (NC Letdn To Regen Hx 1501)

• 1NV-2A (NC Letdn To Regen Hx 1501).

BOP 18cRNO

c. Perform the following:

1) Manually open the affected valve(s).

2) IF the affected valve(s) 2llF valveJs) will not open, THEN ...

BOP NOTE If LTOP is in service, then 1NC-34A will be made inoperable when 1NV-10A is opened and returned operable when 1NV-11 A or 1NV-13A is opened. (PI P

1. 01-545)

d. Open the following valves:

• 1NV-15B (Letdn Cont 1501)

• 1NV-10AiLetdn 1501) .

NV-10A (Letdn Orif 1B Otlt Cont Isol}.

BOP e. Adjust 1NV-294 (NV Pmps A&B Disch Flow Ctrl) as necessary to maintain letdown subcooled in following steps.

BOP f. Throttle 1NV-148 (Letdn Press Control)

Control} to 45% demand.

Page 4 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown Time Position Applicant's Actions or Behavior BOP g. Throttle open 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5% increments until one of the following conditions is met:

• Letdown flow and letdown pressure increases OR

• Valve demand ~osition position is 60% open .

BOP h. Do not continue until one of the above conditions is met.

BOP i. Verify letdown flow and letdown pressure - HAS INCREASED.

BOP j. Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure between 150 - 200 PSIG.

BOP k. WHEN 5 minutes have elapsed, THEN perform the following:

1) IF AT ANY TIME letdown flow is increased to greater than 80 GPM, THEN ...

2) Adjust 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% increments to desired letdown flow.

3) WHEN letdown at desired flow, THEN perform the following:

a) Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG.

b) Ensure 1NV-148 (Letdn Press Control) - IN "AUTO".

4) IF AT ANY TIME additional letdown flow desired, THEN establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/A162001001 (Chemical and Volume Control System).

BOP I. WHEN Pzr level is restored to programmed level, THEN ensure 1NV-294 (NV Pmps A&B Disch Flow Ctrll Ctrl) is in "AUTO".

EXAMINER NOTE: No notifications required.

SRO 19 Determine required notifications:

• REFER TO RP/OIAl50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

BOP 20 Verify excess letdown - ISOLATED.

SRO 21 Determine long term plant status. RETURN TO procedure in effect.

Enclosure 5 actions BOP 1. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRAAHU-1

• CRA PFT-1.

BOP 2. Verify the following annunciators - DARK:

• 1AD-18, Al8 "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-18, B/8 "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-18, D/8 "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-18, E/8 "UNIT 2 INTAKE HI CHLORINE 2B".

Page 5 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown Time Position Applicant's Actions or Behavior BOP 3. Ensure the following VC dampers - OPEN:

• 1VC-SB (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-SB (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

BOP 4. Repeat this enclosure until notified by Station Management as follows:

• At least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR

• Any time VC/yC related annunciators on 1AD-18 actuate.

END EVENT Page 6 of 21

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 2 Event No. 3 3 Page(s)

Event

Description:

B Train KC mini-flow valve fails open Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an COMPONENT event using AP/1/A15500/021 (Loss of Component Cooling).

ALL CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss.

1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify at least one KC pump - ON.

ALL 3. IF AT ANY TIME all KCpumps KC pumps are lost, THEN RETURN TO STEP 2.

BOP NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4. Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK .

AND At least one KC pump - ON.

BOP 5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO.

BOP 6. Verify both KC surge tank levels - 50% - 90% AND STABLE.

BOP 7. Start additional KC pump(s) as necessary to supply any KC loads notify 2'"esentl~

presently in service.

BOP CAUTION A 105s of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure.

8. Verify KC flow to NC pumps as follows:

• 1AD-20, A11 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK

• 1AD-21, A11 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK .

BOP 9. Verify KC available as follows:

a. Verify the following Train A KC non-essential header isolation valves - OPEN:

• 1KC-230A (Rx Bldg Non-Ess Hdr Isol)

• 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-50A (Aux Bldg Non-Ess Hdr Isol)

• 1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol).

b. Verify the following Train B KC non-essential header isolation valves - OPEN:

• 1KC-228B (Rx Bldg Non-Ess Hdr Isol)

• 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-53B (Aux Bldg Non-Ess Hdr Isol)

• 1KC-2B (Aux Bldg Non-Ess Ret Hdr Isol).

c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP 10. Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - 50% - 90% AND STABLE.

b. GO TO Step 14.

Page 7 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 3 3 Page(s)

Event

Description:

B Train KC mini-flow valve fails open Time Position Applicant's Actions or Behavior BOP 14 Ensure KC heat exchanger outlet mode switches - PROPERLY ALIGNED.

ALL 15 Determine and correct cause of loss of KC.

EXAMINER NOTE: Tech Spec 3.7.7. Condition A applies.

SRO 16 Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.9-7 (Boration Systems Flow Path - Shutdown)

• SLC 16.9-8 (Boration Systems Flow Path - Operating)

• SLC 16.9-9 (Boration Systems Pumps - Shutdown)

• SLC 16.9-10 (Boration Systems Charging Pumps - Operating)

• 3.5.2 (ECCS - Operating)

• 3.5.3 (ECCS - Shutdown)

• 3.6.6 (Containment Spray System)

• 3.7.5 (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component (Component Cooling Water (CCW) System).

System}.

EXAMINER NOTE: No notifications at this time.

SRO 17 Determine required notifications:

• REFER TO RP/0IAl50001001 (Classification Of Emergency)

• REFER TO RP/0/B/50001013 (NRC Notification Requirements).

BOP 18 IF KC Hx leak to RN is suspected, THEN perform the following:

• Notify Radiation Protection that a potential unmonitored release may have occurred.

• Notify Station Management to evaluate a KC Hx to RN leak.

BOP 19 Verify KC surge tanks level as follows:

• Greater than 50%

• Stable or increasing.

BOP 20 WHEN plant conditions permit, THEN:

• Return KC pumps to normal operation. REFER TO OP/11A164001005 (Component Cooling Water System).

• Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 4 (Alternate Cooling To NV Pump 1A).

BOP 21 Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK

• 1AD-7, H/3 "VCT HI TEMP" - DARK

• Normal letdown - IN SERVICE.

Page 8 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 3 3 Page(s)

Event

Description:

B Train KC mini-flow valve fails open Time Position Applicant's Actions or Behavior BOP 22 Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) Open the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

2) Close the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to the "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through the NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) to the "DEMIN" position and return to "AUTO".

SRO plant status. RETURN TO ~rocedure 23 Determine long term Qlant procedure in affect.

END EVENT Page 9 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 4 2 Page(s)

Event

Description:

Vacuum leak - manual turbine load decrease Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an REACTIVITY event using AP/1/A15500/023 (Loss of Condenser Vacuum).

EXAMINER NOTE: When Megawatts have been reduced to approximately 1160 MW, the vacuum leak will be reduced so that vacuum begins to increase.

ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Decrease turbine load as required to stabilize vacuum as follows:

a. IF rapid power reduction required, THEN perform the following:

NOTE In "MANUAL" mode, the control valves are capable of full travel within 3 minutes.

1) Select "MANUAL" and "CONTROL VALVE LOWER" to reduce turbine load as required.

2) REFER TO AP/1/A/55001009 (Rapid Downpower).

3) GO TO Step 3.

BOP 3. Verify proper RC System operation as follows:

a. Verify average condenser inlet temperature OAC point C1 P1493 (Unit 1 C1 &

C2 Average RC Inlet Temp) - LESS THAN 90°F.

b. Verify 1AD-8, B/4 "COOLING TOWER BASIN HIILO LEVEL" - DARK.

BOP 4. Verify "STM PRESS TO CSAE" - GREATER THAN 110 PSIG.

RO 5. Verify steam seal header conditions as follows:

a. Ensure at least one of the following valves - OPEN:

• 1TL-2 (Main Stm To Stm Seal Reg)

• 1TL-8 (Aux Stm To Stm Seal Reg).

b. Adjust 1TL-4 (Stm Seal Reg Byp) as required to obtain steam seal header pressure between 4 psig and 6 psig.

c. Verify Verify OAC - AVAILABLE.

BOP NOTE Most TL valve positions can be displayed by OAC turn on code "TL-TF".

6. Verify supplemental steam flow into the Ensure 1TL-9 (Steam Seal Packing steam seal header by at least one of the Unloader Reg Valve) is partially open by at least one of the following:

• Verify 1TL-3 (Steam Seal Reg Valve) - NOT CLOSED OR

• Verify both the following:

0 Unit 1 - ON LINE.

0 1TL-10 (E Bleed Steam Seal Reg R~g Valve) - NOT CLOSED.

Page 10 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 4 2 Page(s)

Event

Description:

Vacuum leak - manual turbine load decrease Time Position Applicant's Actions or Behavior BOP NOTE Starting additional air ejectors or vacuum pump will not restore vacuum when high RC temperature is the reason for loss of vacuum.

7. Verify condenser vacuum status as follows:

a. Condenser vacuum - STABLE OR INCREASING.

b. IF AT ANY TIME condenser vacuum decreases, THEN observe Note prior to Ste~ 6.

Step 6 and perform Step BOP 8. Ensure proper operation of ZP System. REFER TO OP/O/B/62S01011 (Vacuum Priming System).

BOP 9. Dispatch operator(s) to verify proper seal trough flows. REFER TO Enclosure 2 (Verification Of Seal Flows).

BOP 10. Dispatch operator to ensure CFPT seal system and waterboxes operating properly. REFER TO Enclosure 3 (CFPT Stm Seal And Waterbox Vent Verification).

ALL 11. Determine and correct cause of loss of vacuum.

EXAMINER NOTE: No notifications at this time.

SRO 12. Determine required notifications:

• REFER TO RP/O/A/SOOOI001 (Classification Of Emergency)

• REFER TO RP/O/B/SOOOI013 (NRC Notification Requirements) .

BOP 13. Verify Steam Seal System - IN NORMAL ALIGNMENT.

SRO term plant status. RETURN TO procedure in affect.

14. Determine long term_plant END EVENT Page 11 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. S 1 Page(s)

Event

Description:

Rod H-8 drops partially into the core Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/014 (Control Rod Misalignment), Case 1 Control Rod Misalignment.

RO Verify only one rod - MISALIGNED

1. Verifl RO 2. Ensure "CRD BANK SELECT" switch - IN MANUAL RO 3. Verify affected rod bottom light(sl-light(s) - DARK.

RO 4. Stop any turbine load changes in progress RO S. Adjust turbine load to maintain T-Avg within 1°F of T-Ref.

RO NOTE If either "Data A Failure" or "Data B Failure" is indicated, and the "No Urgent Alarm" block is green, then the affected individual rod position indications will be in the "Half Accuracy" mode providing 12 step increment position indication instead of 6. Individual rod position indication may differ by as much as 10 steps from group step counter indication.

6. Verify any of the following DRPI indications - IN ALARM:

• Data A Failure OR

• Data B Failure SRO 6RNO GO TO Step 11.

EXAMINER NOTE: Tech Spec 3.1.4 Condition B applies.

SRO 11. Ensure compliance with appropriate Tech Specs:

• 3.1.1 (Shutdown Margin (SDM)

• 3.1.4 (Rod Group Alignment Limits)

• 3.1.S (Shutdown Bank Insertion Limit)

• 3.1.6 (Control Bank Insertion Limits)

• 3.1.7 (Rod Position Indication)

• 3.2.3 (Axial Flux Difference (AFD))

• 3.2.4 (Quadrant Power Tilt Ratio (QPTR))

• SLC 16.7-11 (Position Indication System - Shutdownl Shutdown)

BOP 12. Notify:

Notify Reactor Group Engineer of occurrence.

RO 13. Determine and correct cause of rod misalignment RO 14. Verify the affected rod(s) are operable as follows:

a. Verify 1AD-2, Al10 "ROD CONTROL URGENT FAILURE" - DARK.

Reallgn affected rod. REFER TO OP/11A161S01008 (Rod Control)

b. Realign EXAMINER NOTE: No notifications are required.

SRO 1S. Determine required notifications:

• REFER TO RP/OIAlSOOOI001 (Classification Of Emergency)

• REFER TO RP/O/B/SOOOI013 (NRC Notification Requirementst Requirements)

SRO 16. Determine long term plant status. RETURN TO procedure Ql"ocedure in effect END EVENT Page 12 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 6 2 Page(s)

Event

Description:

Loss of running RN pump Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an COMPONENT event using AP/OIAl5500/020 (Loss of Nuclear Service Water), Case 1 Loss of RN Train.

JLoss BOP 1. Start idle RN pump(s) as required.

RO 2. Ensure Unit 1 and Unit 2 OATC monitors Enclosure 1 (Foldout Page).

BOP 3. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM.

BOP Verif~ each operating RN pump discharge flow - LESS THAN 23,000 GPM.

4. Verify BOP 4RNO Perform the following:

CAUTION Closing of the RN supply x-over isolation valves may result in the momentary isolation of an essential header.

NOTE Isolating the Unit 1 or 2 non-essential header will result in loss of cooling supply to the following unit related equipment:

• VA Supply Vent Units

• VF Supply Vent Unit.

a. Ensure the following RN supply X-Over isolation valves - CLOSED:

• 1RN-4 7A (RN Supply X-Over Isol)

• 1RN-48B (RN Supply X-Over Iso I)

• 2RN-47A (RN Supply X-Over Isol)

• 2RN-48B (RN Supply X-Over /sol).

returni~g to normal, THEN GO TO Step

b. IF flow is returning Step_ 5.

EXAMINER NOTE: 2A RN pump will need to be started to supply cooling to A train equipment on both units since the crossovers are closed.

BOP 5. Ensure RN pumps -IN OPERATION AS NEEDED.

BOP 6. Ensure proper alignment of RN to KC Hxs as follows:

a. Verify RN - ALIGNED TO IN SERVICE KC HX(S).

b. Ensure KC Hx Otlt Mode switches - PROPERLY ALIGNED.

BOP 7. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM.

BOP 8. Verify RN - AVAILABLE TO ALL UNIT 1 AND UNIT 2 D/G(Sl D/G(S).

BOP 9, Determine VCIYC status as follows:

• Verify VCIYC - ALIGNED TO OPERATING RN TRAIN.

• Verify Verify_ YC Chiller - RUNNING.

ALL 10. Determine and correct cause of loss of RN train.

EXAMINER NOTE: Tech Spec 3.7.8 Condition A.1 applies.

Page 13 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 6 2 Page(s)

Event

Description:

runni~g RNpump Loss of running RN pump Time Position Applicant's Actions or Behavior SRO 11. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.7-6 (RN Discharge Instrumentation)

• 3.6.S (Containment Air Temperature)

• 3.6.6 (Containment Spray System)

• 3.6.17 (Containment Valve Injection Water System (CVIWS))

• 3.7.S (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System)

• 3.7.8 (Nuclear Service Water System (NSWS))

• 3.7.10 (Control Room Area Ventilation System (CRAVS))

• 3.7.11 (Control Room Area Chilled Water System (CRACWS))

• 3.8.1 (AC. Sources - Operating) 3.8.2 lAC.

(AC. Sources - Shutdown).

EXAMINER NOTE: No notifications at this time.

SRO 12. Determine required notifications:

• REFER TO RP/O/A/SOOOI001 (Classification Of Emergency)

• REFER TO RP/O/B/SOOOI013 (NRC Notification Requirements1-Requirements).

BOP 13. Notify Environmental Chemistry Chemistry_ of an;[

any RN pump shifts that have occurred.

SRO 14. Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 14 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event starting in AP/1/A15500/14 (Control Rod Misalignment), Case 2 Dropped Control Rod.

EXAMINER NOTE: A second rod will drop fully into the core and result in a need to trip the reactor manually.

manually-,

1. Verify only one rod - DROPPED OR MISALIGNED.

1 RNO IF two or more rods are dropped OR misaligned by greater than 24 steps, THEN:

a. Manually trip Reactor.

b. GO TO EP/1/A/SOOO/E-O iReactor (Reactor Trij:)Or TripOr Safety Injectionl Injection)

SRO Transition to EP/1/A/SOOO/E-O (Reactor Trip or Safety Injection).

ALL 1. Monitor Enclosure 1_{Foldout 1 (Foldout Pagel-Page).

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers -

• IIR amps - DECREASING.

RO 3. Perform the following:

a. Manually trip reactor.

b. IF reactor will not trip, THEN

c. OPEN concurrently:

• Implement EP/1/A/SOOO/F-O (Critical Safety Function Status Trees) .

• GO TO EP/1/A/SOOO/FR-S.1 (Response To Nuclear Power Generation/A TWS).

SRO Transition to EP/1/A/SOOO/FR-S.1 (Response To Nuclear Power Generation/ATWS).

RO CAUTION NC pumps should NOT be tripped with reactor power greater than S%

to prevent fuel damage.

1. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• IIR amps - DECREASING.

RO 1RNO Perform the following:

a. Manually trip the reactor.

b. IF reactor will not trip, THEN manually insert rods.

RO 2. Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 3. Verify CA pumps are running as follows:

a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels - GREATER THAN 11 %.

BOP 3a RNO a. Manually Manually start motor driven CA pump(s).

BOP 3b. 3 S/G N/R levels - GREATER THAN 11 %.

Page 15 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior BOP 4. Initiate emergency boration of NC System as follows:

a. Ensure at least one NV pump - ON.

b. Open 1NV-236B (Boric Acid To NV Pumps Suct).

c. Ensure both boric acid transfer pump switches - IN THE "ON" POSITION.

d. Verify emergency boration flow - GREATER THAN OR EQUAL TO 30 GPM.

e. Verify the following charging line isolation valves - OPEN:

• 1NV-312A (Chrg Line Cont Isol)

• 1NV-314B (Chrg Line Cont Isol).

f. Verify Pzr pressure - LESS THAN 2335 PSIG.

BOP 5. Verify the following Monitor Light Panel Group 5 St lights - LIT:

• 112

• 113

• 1/10

• H/11.

BOP 6. Verify SII status as follows:

a. "SAFETY INJECTION ACTUATED" status Ilghtj1SI-132 light (1SI-13) - LIT.

BOP 6a RNO Perform the following:

1) IF AT ANY TIME an SII signal exists OR occurs while in this procedure, THEN perform Step 6.b.

2) GO TO Step 7.

ALL 7. Verify the following trips have occurred:

a. Reactor Trip.

BOP a. Dispatch operator to open the following:

• Reactor trip breakers

• Reactor trip bypass breakers

• The following breakers for CRD MIG sets:

0 "MOTOR" Breaker 0 "GENERATOR" Breaker.

RO 7b. Turbine Trip.

RO 8. Verify the reactor is subcritical as follows:

a. All of the following conditions exist:

• PIR channels - LESS THAN 5%

• WIR NEUTRON POWER channels - LESS THAN 5%

• IIR SUR - NEGATIVE.

b. GO TO Step 17.

BOP 17. Ensure all malfunctioning p_um~s - STOPPED.

malfunctionin_g NC pumps Page 16 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position AppJicant's Actions or Behavior Applicant's BOP 18. Ensure adequate shutdown margin as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) KC NC NI NM St signals.

b. Obtain current NC boron concentration from Primary Chemistry.

c. WHEN current NC boron concentration is obtained, THEN perform shutdown margin calculation. REFER TO OP/O/A/61 001006 (Reactivity Balance Calculation).

d. WHEN following conditions are satisfied, THEN stop NC System boration:

• Adequate shutdown margin is obtained

• Uncontrolled cooldown has been stopp_ed.

stopped.

EXAMINER NOTE: If HEAT SINK CSF is RED, then 4.4.G.1 (General Emergency) is correct, otherwise 4.4.S.1 (Site Area Emergency) is correct.

SRO 19. Determine required notifications:

REFER TO RP/O/A/SOOOI001 (Classification Of Emergency)

REFER TO RP/O/B/SOOOI013 (NRC Notification Requirements).

SRO 20. RETURN TO procedure procedure and step in effect.

SRO Transitions to EP/1/A/SOOO/E-0 and based on RED Path ON Heat Sink, immediately transitions to EP/1/A/SOOO/FR-H.1 (Response to Loss of Secondary Heat Sink)

BOP 1. IF total feed flow is less than 4S0 GPM due to operator action, THEN RETURN TO procedure and step in effect.

BOP CAUTION IF a non-faulted S/G is available, THEN feed flow should only be established to non-faulted S/G(s) in subsequent steps.

2. Verify secondary heat sink is required as follows:

a. NC pressure - GREATER THAN ANY NON-FAULTED S/G PRESSURE.

b. Any NC T-Hot - GREATER THAN 3S0°F.

ALL 3. Monitor Enclosure 1 (Foldout Page).

BOP 4. Verify at least one NV pump - AVAILABLE.

BOP S. Verify bleed and feed is required as follows:

a. W/R level in at least 3 S/Gs - LESS THAN 24% (36% ACC).

ALL SaRNO Perform the following:

1) Monitor bleed and feed initiation criteria. REFER TO Enclosure 1 (Foldout Page).

2) WHEN criteria is satisfied, THEN GO TO Step 18.

3) GO TO Step 6.

RO/BOP 6. Verify S/G inventory loss is minimized as follows:

a. Verify the following blowdown isolation valves on all S/Gs - CLOSED:

• Blowdown Containment Isolation Inside

• Blowdown Containment Isolation Outside

• Blowdown Containment Isolation Bypass.

b. All S/G sample isolation valves - CLOSED.

Page 17 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior BOP 7. Attempt to establish CA flow to at least one S/G as follows:

a. Verify the following annunciators - DARK.

• 1AD-5, H/4 "CACST LO LEVEL"

• 1AD-8, B/1 "UST LO LEVEL".

b. Verify the following CA suction valves - OPEN:

• 1CA-6 (CA Pmps Suct From CA CST)

• 1CA-4 (CA Pmps Suct From UST).

c. Verify proper CA pump status as follows:

• 1) Power to both motor driven CA pumps - AVAILABLE.

EXAMINER NOTE: Crew should acknowledge need to refer to AP/007, but continue in FR-H.1 at this time.

BOP 7c1)RN01) Perform the following:

• IF the essential bus is de-energized, THEN restore power to the affected essential bus. REFER TO AP/1/A/5500/007 (Loss of Normal Power).

• IF the essential bus is energized, THEN dispatch operator to determine cause of breaker failure.

BOP 7c 2) 1AD-5, F/3 "CAPT MECH OS TRIP" - DARK.

BOP 7c2) RNO 2) Perform the following:

a) Dispatch operator to reset the CAPT trip and throttle valve.

b) IF AT ANY TIME the CAPT trip and throttle valve is reset prior to reaching bleed and feed criteria, THEN perform Step 7.

c) c) GO TO Step 7.d.

BOP 7d. Ensure all CA isolation valves - OPEN.

e. Verify all CA flow control valves - OPEN

f. Start all available CA pumps.

g.

Q. Verify total CA flow - GREATER THAN 450 GPM.

BOP 7gRNO Perform the following:

1) IF any CA pump is on, THEN ...

2) IF no CA pumps can be started, THEN perform the following:

a) Dispatch operator and maintenance to CA pumps to attempt to restore one CA pump to service. REFER TO EM/1/A/5200/007 (Troubleshooting Cause For CA Pump(s) Failing to Start).

b) IF AT ANY TIME a CA pump is restored prior to meeting bleed and feed initiation criteria, THEN perform Step 7.

c) GO TO Step 8.

BOP 8. Stop all NC pumps.

BOP 9. Verify CM System is in service as follows:

• Hotwell pump(s) - ON

• Condensate Booster pump(s) ~ump(s) - ON.

Page 18 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior RO 10. Reset Feedwater Isolation as follows:

a. Verify the following annunciators - DARK:

• 1AD-8, 0/7 "INNER DOGHOUSE TRAIN A LEVEL HI"

• 1AD-8, E/7 "INNER DOGHOUSE TRAIN B LEVEL HI"

• 1AD-8, 0/8 "OUTER DOGHOUSE TRAIN A LEVEL HI"

• 1AD-8, E/8 "OUTER DOGHOUSE TRAIN B LEVEL HI".

b. Verify S/I- HAS PREVIOUSLY ACTUATED.

RO 10b RNO b. Perform the following:

1) Reset Feedwater Isolation.

2) IF Feedwater Isolation will not reset, THEN notify IAE to bypass Feedwater Isolation. REFER TO EM/1/A/52001009 (Bypassing Feedwater Isolation).

3) GO TO Step 10.e.

EXAMINER NOTE: Crew may return to this step to reset CF Isolation numerous times while in this _procedure.

procedure.

ALL 10e. IF AT ANY TIME a subsequent Feedwater Isolation occurs, THEN RETURN TO Step 10.

RO 11. Attempt to establish CF flow to at least one SIG as follows:

a. Verify CM System is in service. a. RETURN TO Step 6.

b. Place the following valves in manual and closed:

• All CF control valves

• All CF bypass control valves.

c. Ensure at least one of the following valves - OPEN:

• 1CF-10 (1A CF Pump Disch Isol) (TB-579, 1E-21)

• 1CF-17 (1B CF Pump Disch Isol) (TB-579, 1E-20).

d. Verify at least one CF pump - AVAILABLE TO BE STARTED EXAMINER NOTE: Due to loss of vacuum, they should assume the CF pumps are not capable of starting.

BOP 11 dRNO. IF both CF pumps are known to be incapable of starting, THEN GO TO Step 13.

EXAMINER NOTE: 1 NV-37A will not open and the RNO will be used to depressurize.

Page 19 of 21

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 2 7-Event No. - - 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior AppJicant's BOP 13. Depressurize NC System as follows:

a. Verify letdown - IN SERVICE.

b. Verify power to 1NV-37A (NV Supply To Pzr Aux Spray) - AVAILABLE.

c. Depressurize NC System to less than 1905 PSIG using NV aux spray as follows:

1) Open the following valves:

• 1NV-312A (Chrg Line Cont Isol)

• 1NV-314B (Chrg Line Cont Isol).

2) Ensure the following valves - CLOSED:

• 1NC-27 (pzr Spray Ctrl Frm Loop A)

• 1NC-29 (pzr Spray Ctrl Frm Loop B)

• 1NV-39A (NV Supply To Loop D Isol)

• 1NV-32B (NV Supply To Loop A Isol).

3) Maintain charging flow less than 180 GPM.

4) Throttle 1NV-37A (NV Supply To Pzr Aux Spray) and charging flow as required.

BOP 13cRNO Depressurize NC System to less than 1905 PSIG using one Pzr PORV.

BOP 13d. Maintain NC pressure less than 1905 PSIG.

e. IF AT ANY TIME letdown is lost AND a Pzr PORV is available, THEN:

1) Close 1NV-37A (NV Supply To Pzr Aux Spray).

2) Open one of the following valves:

• 1NV-39A (NV Supply To Loop D Isol)

OR

• 1NV-32B (NV Supply To Loop A Isol).

3) Dej:>ressurize

3) Depressurize NC System to less than 1905 PSIG usi'1g using one Pzr PORV.

EXAMINER NOTE: This permissive will likely not be lit at this time, however, this step will be performed later.

BOP 14. Block SII as follows:

a. Verify "P-11 PZR SII BLOCK PERMISSIVE" status light (1SI-18) - LIT.

b. Depress the "BLOCK" push buttons for the following signals:

• ECCS steam pressure

• ECCS Pzr pressure.

c. Verify the following status lights (1 SI-13) - LIT:

• Main Steam Isol

• Pzr low pressure S/I.

d. IF AT ANY TIME conditions degrade while in this procedure, THEN manual SII actuation will be required.

BOP 14aRNO. Perform the following:

1) WHEN "P-11 PZR SII BLOCK PERMISSIVE" status light (1SI-18) is lit, THEN perform Steps 14 through 16.

2) GO TO Step 17.

BOP 15. Attempt to establish feed flow from CM as follows:

Verify SteQs

a. Verify_ Steps 19 through 32 - HAVE BEEN PREVIOUSLY PERFORMED.

Page 20 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rod M-12 drops, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior RO 15aRNO. Perform the following:

1) Close MSIV on 2 S/Gs not to be depressurized.

2) GO TO Step 15.c.

RO c. Verify the condenser is available as follows:

• "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT

• MSIV on S/G(s) to be depressurized - OPEN RO 15c RNO Perform the following:

1) Dump steam from S/G(s) selected to be depressurized using S/G PORVs at maximum rate.

2) IF no S/G PORV can be operated from the control room, THEN ...

3) IF no S/G PORV can be opened, THEN ...

4) GO TO Step 15.g.

15.£1.

RO 15 g. WHEN S/G pressure is less than 505 PSIG, THEN stabilize S/G pressure less than 505 PSIG.

BOP 15h. Veri& Ste~s 19 throu_9h Verify Steps through 32 - HAVE BEEN PREVIOUSLY PERFORMED.

SRO 15hRNO. GO TO Steg Step 15j.

15.j.

RO 15j. Verify CF Isolation signal - RESET OR BYPASSED.

k. Open the CF to CA valve on the S/G(s) to be fed:

• 1CA-149 (S/G 1A CF Byp To CA Nozzle)

• 1CA-150 (S/G 1B CF Byp To CA Nozzle)

• 1CA-151 (S/G 1C CF Byp To CA Nozzle)

• 1CA-152 (S/G 1D CF Byp To CA Nozzle).

I. Throttle open CF control valve or CF bypass control valve for S/G(s) to be fed.

m. Verify feedwater flow to depressurized S/G(s) -INDICATING FLOW.

RO 15m RNO Perform the following:

1) IF depressurized S/G pressure is less than 505 PSIG, THEN GO TO Step 17.

2) RETURN TO Step Step_ 15.c.

EXAMINER NOTE: This is a procedure loop until pressure is low enough to get flow to the SIGs from the condensate booster pumps. Scenario should be stopped when flow is indicated to the SIGs via the condensate system. s~stem.

END EVENT Page 21 of 21

Appendix D, Rev. 9 scenariolJBAfT scenarioQB fT Form ES-D-1 2008 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.: 3 Op-Test No.:

Examiners: Operators:

Initial Conditions:

• 75% power

• EFPD =450 days

• Boron concentration is 215 ppm

• DFCS channel 3 out of service to repair a tubing leak (loop 5142 - CF Header Pressure) -

functional in progress

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Increase power to 90% at 10%/hr.

Event Malf. No. Event Event No. Type* Description 1 RO R Power increase to 90% at 10%/hr 2 SRO TS FWST level channel 1 fails low 3 RO C Generator breaker opens, auto runback fails BOP N Boration 4 BOP C Respond to EMF33 failed high SRO TS 5 BOP C 1ETA normal feeder opens, restore charging 6 RO I 1B S/G level program fails low 7 ALL M NC PORV fails open - medium break LOCA Additional failures NI pump 1B fails to start in auto VA Fans not aligned as required on S/I

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

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 1 1 Page(s)

Event

Description:

Power increase to 90% at 10%/hr Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a REACTIVITY event using OP/1/B/6300/001 (Turbine Generator).

RO CAUTION:

1. Until it is recognized that the first stage shell metal temperature change rate stays below the allowable limit (1500F/hr), the following loading rate shall NOT be exceeded:

• 1/2%/min - First Stage Inner Shell Temperature (1 MC3 or OAC point C1A1140 (Turbine Lower Inner Shell Temp)) < 3500F

• 1%/min - First Stage Inner Shell Temperature (1 MC3 or OAC point C1A 1140 (Turbine Lower Inner Shell Temp)) > 3500F

2. Normal steady-state load changes shall be made without exceeding the limits shown on Enclosure 4.7 (Generator Operating Limits) and in the Unit One OAC Databook "Recommended Startup and Loading Curves".

3. Unit One Reactor Operating Data, Section 2.4 shall be referred to for allowable ramp rates. A "LOAD RATE" > 6.2 MW/MIN shall NOT be used during normal load changes.

RO 2.1.2 Increase turbine generator load by performing the following:

2.1.2.1 Select "LOAD RATE" and verify it illuminates.

2.1.2.2 Input the desired load rate.

2.1.2.3 Select "ENTER" or "OK" and verify "LOAD RATE" goes dark.

2.1.2.4 Select "TARGET" and verify it illuminates.

2.1.2.5 Input the desired load target.

2.1.2.6 Select "ENTER" and verify" TARGET" goes dark.

2.1.2.7 Verify new load target appears on Target Display.

2.1.2.8 Select "GO" and verify it illuminates to start load increase.

2.1.2.9 S/G blowdown changes shall be coordinated with Secondary Chemistry.

RO CAUTION: The load, hydrogen pressure and power factor limits per the Unit One Revised Data Book Figure 43 shall NOT be exceeded.

END EVENT Page 1 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 2 1 Page(s)

Event

Description:

FWST level channel 1 fails low (3.3.2)

Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a SRO TECH SPEC event only.

OP/1/B/61 00101 OJ (Annunciator Response For Panel 1AD-09)

B/8 - FWST AT MAKEUP LEVEL C/8 - FWST LO LEVEL E/8 - FWST LO-LO LEVEL EXAMINER NOTE: Actions are for C/8.

Immediate Actions BOP Verify low level by checking against the other channels.

Supplemental SU2Qlemental Actions BOP 1. IF low level due to leak OR failure of related piping, isolate if possible.

BOP 2. IF low level due to leak AND level CANNOT be maintained, refer to Catawba Tech 3.5.4, SLC 16.9-11 and SLC 16.9-12 for operability.

BOP 3. Refer to OP/1/A/62001014 _(Refuelin~

(Refueling Water System) for makeup.

EXAMINER NOTE: Tech Spec 3.3.2 (7.b), Condition N applies, SRO 4. IF a channel failure has occurred, perform the following:

4.1 Refer to Tech Spec 3.3.2 for minimum operable channel requirements.

4.2 Issue the appropriate Model W/Os to have IAE provide emergency repairs on the affected channel(s):

• 98615487 - 1FW LT5000: Repair CH 1 FWST Level

• 98615489 - 1FW LT501 0: Repair CH 2 FWST Level

• 98615490 - 1FW LT5120: Repair CH 3 FWST Level

• 98615491 - 1FW LT5130: Repair CH 4 FWST Level re~aired.

4.3 Initiate a work request to have the channel repaired.

END EVENT Page 2 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker opens, auto runback fails, boration Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event for the RO using AP/lIAl5500/003 (Load Rejection) and a REACTIVITY event for the BOP using OP/1/A/6150/009 (Boron Concentration Control).

AP/1/A15000/003 (Load Rejection) Case I (Switchyard Available) steps RO 1. Verify turbine load - DECREASING IN AUTOMATIC.

RO 1RNO Perform the following:

a. Select "MANUAL" on turbine control panel.

b. Depress "CONTROL VALVES LOWER" pushbutton and reduce turbine load as re_quired.

RO 2. Verify proper reactor response:

• Control rods -IN "AUTO" AND STEPPING IN

• P/R neutron flux - DECREASING.

RO 3. Verify proper steam dump operation as follows:

a. Verify T-Ref instrumentation - AVAILABLE.

b. "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT.

c. Verify the following:

• "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI-18) - LIT.

• Steam dump valves - MODULATING.

d. T-Avg - DECREASING TO T-REF.

BOP 4. Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

BOP S. Verify proper CM System operation as follows:

a. WHEN reactor power is less than 7S% THEN ensure both C-htr drain pumps -

OFF.

b. Verify reactor power - GREATER THAN S6% PRIOR TO THE EVENT.

EXAMINER NOTE: They may start hotwell and condensate booster pumps but it should be optional in this case and based on judgment.

BOP Sc. Verify standbl' hotwell p_ump(s) - ON.

BOP ScRNO. Manually start standby hotwell pump(s) as necessary.

BOP Sd. Verify standby condensate booster pump(s) - ON.

BOP SdRNO. Manually start standby condensate booster pump(s) as necessary.

BOP 6. Verify the following generator alarms

• 1AD-11, C/1 "GEN BKR A OVERCURRENT"

• 1AD-11, F/1 "GEN BKR B OVERCURRENT".

RO 7. Verify SIG levels are adequate as follows:

• All SIG low level alert alarms (1AD-4) - DARK

• All SIG low CF flow alarms (1AD-4) - DARK.

Page 3 of27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker opens, auto run back fails, boration Time Position Applicant's Actions or Behavior RO 7RNO Perform the following:

a. Ensure feedwater regulating valves - MODULATING TO CONTROL S/G LEVELS AT PROGRAM SETPOINT.

b. IF any S/G(s) N/R level is decreasing in an uncontrolled manner, THEN:

1) Trip reactor.

EP/11A15000/E-0 (Reactor Trifj

2) GO TO EP/11A15000/E-O(Reactor Trip Or Safety Injection).

Injectiont RO ~ower - GREATER THAN 20%.

8. Verify reactor power RO 9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO.

BOP 10. Verify AS header pressure - GREATER THAN OR EQUAL TO 140 PSIG.

RO 11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG - 6 PSIG.

RO 12. Monitor Enclosure 3 (Rod Insertion Limit Boration).

EXAMINER NOTE: These steps are listed after step ste~ 28 of this AP.

RO 13. Verifyreactorpower Verify reactor power - LESS THAN 30%.

RO 13RNO Perform the following:

a. IF the runback target load is less than 30%, THEN: ...

b. WHEN the appropriate runback target load is reached, THEN:

1) Stabilize unit at current power level.

2) Maintain control rods above insertion limits .

. 3) Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

• Turbine load

• Control rods

• Boron concentration.

c. GO TO Step 15.

BOP 15. Verify the following PCBs - CLOSED:

• Generator breaker 1A

• Generator breaker 1B

• PCB 14

• PCB15

• PCB 17

• PCB 18.

BOP NOTE When separated from the grid the turbine reverts to speed control.

15 RNO Perform the following:

a. IF both generator PCBs are open, THEN ...

b. IF the turbine generator is separated from the grid, THEN ...

c. IF load rejection caused by loss of main busline 1A or 1B, THEN ...

RO 16. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43.

Page 4 of 27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker opens, auto run back fails, boration Time Position Applicant's Actions or Behavior RO 17. WHEN the appropriate runback target load is reached, THEN:

• Stabilize unit at appropriate power level.

• Maintain control rods above insertion limits.

• Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

0 Turbine load 0 Control rods 0 Boron concentration.

RO 18. Notify System Operating Center (SOC) using the red dispatcher telephone of current unit status.

ALL 19. Determine and correct cause of load rejection.

BOP 20. Shut down unnecessary plant equipment as follows:

a. Restore CM and CF as follows:

1) Verify C-htr drain pumps - ON.

BOP 20a1)RNO 1) WHEN time and manpower permit, THEN complete the shutdown of the C-htr drain pumps. REFER TO OP/1/B/62501004 (Feedwater Heater Vents, Drains and Bleed System).

BOP 20a 2) Verify both CF Pumps - IN SERVICE.

3) Shutdown one CF pump as necessary. REFER TO OP/1/A162501001 (Condensate and Feedwater System).

4) Shutdown excess Condensate Booster Pumps. REFER TO OP/1/A162501001 (Condensate and Feedwater System).

5) Shutdown excess Hotwell Pumps. REFER TO OP/1/A162501001 (Condensate and Feedwater System).

b. RC pump(s) and cooling tower fans. REFER TO OP/1/B/64001001A (Condenser Circulating Water System).

RO 21. Reset steam dump valves as follows:

a. Verify reactor power - STABLE.

b. Verify steam dump valves - IN "T-AVG" MODE.

c. Verify steam dump valves - CLOSED.

d. Reset steam dump valves.

e. Verify the following status lights (1 SI-18) - DARK:

• "C-7A LOSS OF LOAD INTLK COND DUMP"

• "C-7B LOSS OF LOAD INTLK ATMOS DUMP".

f. IF "T-AVG" mode of operation is available, THEN ensure steam dump valves in "T-AVG" mode.

g. Verify "STM DUMP CTRL" - IN AUTOMATIC.

RO 22. Verify reactor power - GREATER THAN 15%.

BOP 23. VerifyCA2um~s - OFF.

RO 24. Verify reactor power change - GREATER THAN OR EQUAL TO 15% IN A 1 HOUR PERIOD.

Page 5 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker opens, auto runback fails, boration Time Position Applicant's Actions or Behavior BOP 25. Notify the following sections to take appropriate samples:

• Radiation Protection to sample and analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.11-6.

• Primary Chemistry to sample for isotopic analysis of iodine. REFER TO Tech Specs 3.4.16 (Sample must be taken between 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following last power change greater than or equal to 15% rated thermal power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period).

EXAMINER NOTE: No Technical Specifications apply.

SRO 26. Ensure compliance with appropriate Tech Specs:

• 3.1.1 (Shutdown Margin (SDM))

• 3.1.6 (Control Bank Insertion Limits)

• 3.8.1 CAC Sources - OJ:>erating).

BOP 27. Notify Reactor Group Engineer of occurrence.

SRO 28. Determine long term plant status. RETURN TO OP/1/A/61 001003 (Controlling Procedure For Unit Operation).

AP/1/A15500/003, Enclosure 3 steps BOP 1 IF the control rods cannot be maintained above the rod insertion limits, THEN:

a. Stop any dilutions in progress.

CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

NOTE OAC point C1 L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and RO.D Book (Section 2.2) provide rod insertion limit indication.

b. Borate NC system as required, to restore rods above insertion limits.

c. Ensure compliance with Tech Spec 3.1.6 (Control Bank Insertion Limits).

EXAMINER NOTE: This is the BOP portion of the event.

OP/1/A/61501009 (Boron Concentration Control) Enclosure 4.2 (Boration) steps BOP 1.1 Review the Limits and Precautions.

BOP 1.2 IF in Mode 1 or 2 AND boration is being performed for normal temperature control, ensure R3 reactivity management controls established per SOMP 01-02 (Reactivity Management). (RM1 BOP 1.3 IF in Mode 1 or 2 AND boration is being performed as part of a power change, ensure R2 reactivity management controls established per SOMP 01-02 Reactivity Management). (RM.)

BOP 1.4 Verify the NV System is in operation per OP/1 IA/62001001 (Chemical and Volume Control System).

BOP 1.5 Verify sufficient RHT volume is available to receive the reactor coolant displaced during the planned boration operation.

BOP NOTE: This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of NSD 304 (Reactivity Management). (RM.)

Page 6 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker opens, auto run back fails, boration Time Position Applicant's Actions or Behavior BOP 2.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

BOP 2.2 Ensure the following valve control switches in "AUTO":

1NV-238A (BfA Xfer Pmp To Blender Ctrl) 1NV-186A (BfA Blender Otlt To VCT Otlt)

BOP 2.3 Ensure 1NV-238A (BfA Xfer Pmp To Blender Ctrl) controller in "AUTO".

BOP 2.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON".

BOP 2.5 Adjust the boric acid batch counter to the desired volume of boric acid to be added. (RM.) .

BOP 2.6 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setting of the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl).

BOP 2.7 Place the "NC MAKEUP MODE SELECT" switch in "BORATE".

BOP NOTE: Boric Acid flow rates> 32 gpm (controller pot setting of 8) may result in a boric acid flow deviation annunciator.

BOP 2.8 Adjust the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl) to the desired flow.

BOP NOTE: If necessary, boration can be manually secured at any time by placing the "NC MAKEUP CONTROL" switch to the "STOP" position.

BOP 2.9 Place the "NC MAKEUP CONTROL" switch to the "START" "START"Rosition.

position. (RM.)

BOP 2.10 Verify the following valves open:

1NV-238A (BfA Xfer Pmp To Blender Ctrl) 1NV-186A (BfA Blender Otlt To VCT Otlt)

BOP 2.11 IF in "AUTO", verify the boric acid transfer pump starts.

BOP NOTE: The total makeup flow totalizer is inaccurate at low flow rates.

BOP proper flow by observing the boric acid flow totalizer. {PIP 96-0137}

2.12 Verify PIoper 96-01371 BOP 2.13 WHEN the desired volume of boric acid is reached on the boric acid batch counter, ensure the following valves close: (RM.)

1NV-238A (BfA Xfer Pmp To Blender Ctrl) 1NV-186A (BfA Blender Otlt To VCT Otlt)

BOP NOTE: If additional borations will be performed over the course of the shift, flushing the makeup line is NOT recommended.

2.14 IFIF desired, flush the makeup line as follows: ...

BOP 2.15 IF automatic makeup is desired, perform one of the following:

2.15.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup).

OR 2.15.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

2.15.2.1 Ensure the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 2.6. (RM.)

2.15.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO".

2.15.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (RMl (RM.)

Page 7 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker opens, auto runback fails, boration Time Position Applicant's Actions or Behavior END EVENT Page 8 of27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 4 5 Page(s)

Event

Description:

Respond to EMF33 failed high Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using OP/1/B/61 00/01 OX (Annunciator Response for Radiation Monitoring Panel 1RAD-1 (B/11 and an SRO Tech Spec event.

ARP IMMEDIATE ACTIONS BOP 1. Verify that automatic actions occur by checking computer points C1A0968 through A0971 (S/G 1A through 10 Blowdown Flow)

The following valves close:

• 1NM-267 (S/G Smpl Hdr Rad Monitor Inlet Isol) (SRVOP)

• 1NM-269 (S/G A Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-270 (S/G B Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-271 (S/G C Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-272 (S/G 0 Smpl Hdr To Conv Smpl Sink) (CSP)

• 1BB-27 (BB Tank Vent To Atmos) (1 MC4)

• 1BB-48 (BB Pumps Disch To TB Smp) (1 MC4)

• 1BB-69 (S/G A Blowdown Flow Ctrl) (1 MC4)

• 1BB-73 (S/G B Blowdown Flow Ctrl) (1 MC4)

• 1BB-24 (S/G C Blowdown Flow Ctrl) (1 MC4)

• 1BB-65 (S/G 0 Blowdown Flow Ctrl) (1 MC4 BOP 2. Ensure blowdown flow controllers are set to 0 flow:

"S/G A BLOWN FLOW CTRL" (1MC4)

"S/G B BLOWN FLOW CTRL" (1 MC4)

"S/G C BLOWN FLOW CTRL" (1 MC4)

"S/G 0 BLOWN FLOW CTRL" (1MC4)

EXAMINER NOTE: "S/G C BLOWN FLOW CTRL" must be manually closed.

BOP 3. Contact Primary Chemistry to ensure the following valves are closed:

• 1NM-267 (S/G Smpl Hdr Rad Monitor Inlet Isol) (Sample Room Valve Operating Panel, 1TBOX0132, located outside Unit 1 NM Lab)

• 1NM-269 (S/G A Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-270 (S/G B Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-271 (S/G C Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-272 18/G 0 Sm~1 Hdr To Conv Smpl Sink) (CSP BOP 4. Select "AUTO" on "UNIT 1 CSAE EXH" switch (1MC13)

BOP 5. Verify "VA" indicating light is lit (1 MC13)

BOP 6. IF "VA" indicating light is dark, verify one of the following:

• ABFXF-1A on

• 1ABF-O-11 (AB-594, KK-54) open OR

• ABFXF-1B on

• 1ABF-O-4 (AB-594, KK-54) open ARP SUPPLEMENTAL ACTIONS SRO 1. Refer to AP/11A15500/1 0 (Reactor Coolant Leak).

Page 9 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 4 5 Page(s)

Event Descrigtion:

Description:

Respond to EMF33 failed high Time Position Applicant's Actions or Behavior BOP 2. Notify Secondary Chemistry and Radiation Protection of this alarm.

SRO 3. Refer to Tech Spec 3.4.13 for limitation on S/G tube leakage.

SRO 4. Refer to Tech Spec 3.7.17 for limits on secondary system activity_levels activity levels BOP 5. Refer to OP/1/N62501008 (Steam Generator Blowdown) for continued oRe ration with high activity.

operation BOP NOTE: Operation with ZJ exhausting to the VA system filters should be minimized.

6. Notify RP to sample ZJ exhaust for Iodine.

BOP 7. IF Iodine is NOT detected in the ZJ exhaust, perform the following:

7.1 Return "UNIT 1 CSAE EXH" switch to "UNIT VENT'.

7.2 Verify Verifi "UNIT VENT' indicating light is lit.

SRO SRO REFERS to AP/1/N55001010 (Reactor Coolant Leak), Case 1 (Steam Generator Tube Leak).

Leakl.

EXAMINER NOTE: AP/1/A/5500/010 is entered until it can be determined that EMF33 indications are false.

ALL 1. Monitor Enclosure 1lCase (Case I Steam Generator Tube Leak Foldout Page).

BOP 2. Verify Pzr level- STABLE OR INCREASING.

ALL 3. IF AT ANY TIME Pzr level decreases in an uncontrolled manner or cannot be maintained greater than 4%, THEN perform Step 2.

Page 10 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. - -

4- 5 Page(s)

Event DescrlQtion: Respond to EMF33 failed high Time Position Applicant's Actions or Behavior ALL NOTE In subsequent steps the term "affected S/G" is a S/G with primary to secondary leakage.

4. Identify the affected S/G(s) as follows:

• Notify RP to frisk all cation columns.

OR

• Any S/G NIR level-INCREASING IN AN UNCONTROLLED MANNER.

OR NOTE The S/G Leakage EMFs are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

• Verify any of the following S/G leakage EMF indication(s) - INCREASING OR IN ALARM:

o 1EMF-71 (S/G A Leakage) o 1EMF-72 (8/G B Leakage) o 1EMF-73 (S/G C Leakage) o 1EMF-74 (S/G D Leakage).

OR

• Verify any of the following S/G steamline EMF indication(s) -

INCREASING OR IN ALARM:

o 1EMF-26 (Steam line 1A) o 1EMF-27 (Steamline 1B) o 1EMF-28 (Steamline 1C) o 1EMF-29 (Steam line 1D).

OR

• Verify CF flow - LOWER TO ANY S/G AS COMPARED TO OTHERS.

OR

• Notify Secondary Chemistry to determine affected S/G by sampling.

BOP 5. Verify VCT level able to be maintained by normal makeup as follows:

a. One of the following conditions exists:

• S/G tube leak is less than 90 gpm.

OR

• Automatic makeup stabilizes or increases VCT level.

OR

• Manual makeup stabilizes or increases VCT level.

b. IF AT ANY TIME the following conditions exist:

• 1AD-7, 1/1 "VCT LO LVL" alarm is lit AND

• Reactor trip breakers are closed.

THEN perform Step 5.a RNO.

Page 11 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - - --

3-Event No. -

4-5 Page(s)

Event

Description:

Respond Resj20nd to EMF33 failed high Time Position Ap2!icant's Applicant's Actions or Behavior BOP 6. Minimize Secondary contamination as follows:

a. Remove CM polishing demineralizers from seNice as follows:

1) Ensure "POLSH DEMIN BYP CTRL" - PLACED IN MANUAL.

2) Ensure "POLSH DEMIN BYP CTRL" - OPEN.

3) Notify Secondary Chemistry CM polishing demineralizers have been bypassed.

b. Align auxiliary systems to minimize secondary side contamination as follows:

1) Transfer turbine steam supply to AS as follows:

a) Open 1TL-8 (Aux Stm To Stm Seal Reg).

b) Close 1TL-2 (Main Stm To Stm Seal Reg).

2) Dispatch operator(s) to align auxiliary systems. REFER TO Enclosure 5 (Auxiliary System Alignment).

c. Stop any transfer of water between both Unit's CSTs.

EXAMINER NOTE: At this time RP will call back and report no activity noted on any cation columns.

ALL 7. Determine S/G leak rate by any of the following methods:

• Monitor the following computer points:

o C1P0187 (Estimated Total Pri To Sec Leakrate) o C 1P0189 (Pri To Sec Leakrate 15 Min Running Avg) o EROSLEAK (Primary To Secondary Leakage).

OR NOTE The S/G Leakage EMFs are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

• S/G leakage EMF indication(s):

o 1EMF-71 (S/G A Leakage) o 1EMF-72 (S/G B Leakage) o 1EMF-73 (S/G C Leakage) o 1EMF-74 (S/G D Leakage).

OR

• Compare charging flow and letdown flow OR

• Monitor OAC NV Graphic OR

• Initiate OAC Program "NSNCLEAK" OR

• Monitor OAC point C1 P0976 (Gross NC System Leak Rate, Ten Min Run Avg).

OR

• Secondary Chemistry performance of PT/1/B/4600/028 (Determination of Steam Generator Tube Leak For Unit 1).

Page 12 of 27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 3 Event No. 4 5 Page(s)

Event

Description:

Respond to EMF33 failed high Time Position Applicant's Actions or Behavior SRO 8. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• 3.4.13 (RCS Operational Leakage)

• 3.4.14 (RCS Pressure Isolation Valve (PIV) Leakage)

• 3.5.5 (Seal Injection Flow)

• 3.7.17 (Secondary Specific Activity)

• SLC 16.7-9 (Standby Shutdown System).

SRO Should note that SLC 16.11-7 #2 Condition A 1k applies due to failed EMF33 once confirmation is received.

END EVENT Page 13 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 5 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior Af)plicant's EXAMINER NOTE: This is a COMPONENT event for the BOP using AP/1/A15500/007 (Loss of Normal Power) Case 1, Loss of All Power to an Essential Train.

ALL 1. Monitor Enclosure 1 (Foldout Page).

Paile).

BOP 2. Verify affected bus - ENERGIZED.

EXAMINER NOTE: Bus will only be energized for 1 minute and then the DIG will trip resulting in a loss of all power to ETA.

SRO 2RNO GO TO Case" (Loss of All Power to an Essential Train).

SRO Transition to Case 2.

ALL 1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify the essential loads powered from energized train as follows:

a. RN pump(s) - IN SERVICE AS NEEDED.

b. KC pump(s) - IN SERVICE AS NEEDED.

c. At least one NV pump - ON.

EXAMINER NOTE: SRO will refer to AP/1/A/5500/012 (Loss of Charging or Letdown) to restore charging at some point. The following steps are for AP/07 and the steps for AP/12 follow.

BOP 2 d. CA pump - ON.

BOP 2dRNO IF CA pump is required to maintain SIG levels, THEN manually start pump.

BOP e. VCIYC chiller - ON.

BOP 3. Verify CA Pump #1 - ON.

RO 4. Maintain reactor power f)ower less than or equal to 100%.

BOP 5. Verify DIG on the affected bus - RUNNING.

SRO 5RNO GO TO Step 7.

BOP 7. Dispatch operator with a screwdriver to load shed the affected essential bus as follows:

• REFER TO Enclosure 8 (Manual Load Shed Of 1ETA)

BOP 8. Verify operating RN pump(s) flow - LESS THAN 23,000 GPM.

BOP 9. Stop any dilutions in Qrogress.

progress.

BOP 10. Verify S/I status as follows:

a. S/I- HAS ACTUATED.

b. GO TO Step 12.

BOP 12. Ensure CA System - RESET.

Page 14 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 5 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging chacgin_g Time Position Applicant's Actions or Behavior BOP 13. Control S/G levels as follows:

a. Verify CF flow - MAINTAINING STABLE S/G LEVELS.

b. IF AT ANY TIME CF flow control to S/Gs is lost, THEN perform Step 13.

CAUTION Battery depletion may occur as early as two hours. Battery depletion results in affected CA control valves failing full open. Failure to take local control of S/G level prior to battery depletion may result in S/G overfill.

c. IF AT ANY TIME any vital or auxiliary control channel battery charger has been de-energized for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, THEN dispatch operators to locally control affected CA flow path. REFER TO Enclosure 16 (S/G Level Control).

RO 14. Verify "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT.

BOP 15. Control charging as follows:

a. Maintain charging flow less than 180 GPM.

b. Adjust charging flow as necessary to maintain Pzr level in program band.

BOP 16. Control letdown as follows:

a. Verify Verifynormalletdown normal letdown - IN SERVICE.

BOP 16aRNO. Perform the following:

1) Attempt to restore letdown. REFER TO AP/1/A/5500/012 (Loss of Charging or Letdown).

2) WHEN normal letdown has been established, THEN place additional letdown orifice in service as necessary to control Pzr level.

3) GO TO Step 17.

BOP 17. Determine and correct cause of blackout.

BOP 18. Verify VI pressure - GREATER THAN 85 PSIG AND STABLE.

BOP 19. IF spent fuel pool instrumentation is failed low, THEN dispatch operator to monitor spent fuel pool conditions. REFER TO Enclosure 14 (Spent Fuel Pool Monitoring).

EXAMINER NOTE: Tech Spec 3.8.1 Condition A, Band 0, 3.8.9 Condition A and 3.4.9 Condition B apply.

SRO 20. Ensure compliance with appropriate Tech Specs:

• 3.4.9 (Pressurizer)

• 3.8.1 (AC Sources - Operating)

• 3.8.2 (AC Sources - Shutdown)

• 3.8.4 (DC Sources - Operating)

• 3.8.5 (DC Sources - Shutdown)

• 3.8.7 (Inverters - Operating)

• 3.8.8 (Inverters - Shutdown)

• 3.8.9 (Distribution Systems - Operating)

• 3.8.10 (Distribution Systems - Shutdown).

EXAMINER NOTE: No notifications required at this time.

Page 15 of 27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 3 Event No. 5 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging chargi'lg Time Position Ap~icant's Actions or Behavior Applicant's SRO 21. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

BOP 22. Verify 6.9KV busses - ENERGIZED.

SRO 23. Do not continue in this procedure until the following are satisfied:

• The status of all lockout targets have been determined

• Station management has approved power restoration to the affected bus.

AP/1/Al5500/012 (Loss of Charging or Letdown), Case 1 Loss of Charging actions RO Sto~ any power changes.

1. Stop BOP 2. Ensure the following letdown isolation valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 3. Monitor conditions for continued NC pump operation as follows:

• NC pump #1 seal outlet temperature - LESS THAN 235°F

• NC pump pump lower bearing temperature - LESS THAN 225°F.

BOP NOTE Gas entrainment in the NV pump suction can produce pump failure or degradation. Gas entrainment can result in a complete loss of charging, or in a reduction of charging capacity, without indication of cavitation.

4. Verify NV pump status as follows:

• At least one NV pump - ON.

• Charging flow - ADEQUATE FOR PLANT CONDITIONS.

Page 16 of 27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 5 5 Page(s)

-~- - --'---

Event

Description:

1ETA normal feeder opens, chacgin~

oQens, restore chacging Time Position Applicant's Actions or Behavior BOP 4RNO Perform the following:

a. Ensure malfunctioning NV pump - SECURED.

b. Ensure the following valves - OPEN:

• 1NV-203A (NV Pumps A&B Recirc Isol)

• 1NV-202B (NV Pmps A&B Recirc Isol).

c. Ensure only one suction source as follows:

• VCT o 1 NV-188A (VCT Otlt Isol) - OPEN o 1NV-189B (VCT Otlt Isol) - OPEN o VCT level- GREATER THAN 23%

o 1NV-2S2A (NV Pumps Suct From FWST) - CLOSED o 1NV-2S3B (NV Pumps Suct From FWST) - CLOSED OR

• FWST o Either of the following valves - OPEN:

• 1NV-2S2A (NV Pumps Suct From FWST)

• 1NV-2S3B (NV Pumps Suct From FWST).

o Either of the following valves - CLOSED:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

d. IF operating NV pump tripped due to loss of suction, THEN ...

e. Start the available NV pump as follows:

1) Manually open 1 NV-309 (Seal Water Injection Flow) to full open.

2) Manually close 1NV-294 (NV Pmps A&B Disch Flow Ctrl).

3) Start NV pump aux oil pump.

4) Start available NV pump.

5) Stop NV pump aux oil pump.

6) IF suction is from the FWST, THEN ...

f. IF no NV pump(s) available, THEN ...

BOP 5. Verify charging header is aligned to NC loop as follows:

a. 1NV-312A (Chrg Line Cont Isol) - OPEN.

b. 1 NV-314B (Chrg Line Cont Isol) - OPEN.

c. Verify one of the following valves - OPEN:

o 1NV-32B (NV Supply To Loop A Isol)

OR o 1 NV-39A (NV Supply To Loop D Isol).

d. Verify 1 NV-294 (NV Pmps A&B Disch Flow Ctr!l- Ctrl) - OPEN.

BOP SdRNO d. Perform the following:

1) Manually open 1NV-309 (Seal Water Injection Flow).

2) Throttle 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to establish greater than 32 GPM "N/R CHRG LN FLOW".

BOP 6. Verify the following:

o "TOTAL SEAL WTR FLOW' - GREATER THAN 32 GPM o 1 NV-309 (Seal Water Injection Flow) -IN "AUTO".

Page 17 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 5 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior BOP 6RNO Perform the following:

a. Slowly throttle 1NV-309 (Seal Water Injection Flow) to establish 32 GPM "TOTAL SEAL WTR FLOW".

b. Place 1NV-309 in "AUTO".

BOP Verify Pzr level- GREATER THAN 17%.

7. VerLfyPzr BOP 8. Control charging to stabilize Pzr level greater than 17%.

BOP 9. Ensure "PZR HTR GROUP 1COl - ON.

BOP 10. Control VCT level as follows:

a. Verify NC system makeup - SET DESIRED BORON CONCENTRATION.

b. Verify-"NC Verify "NC MAKEUP MODE SELECT" - IN AUTOMATIC BOP 11. Verify normal letdown - IN SERVICE.

SRO 11 RNO Restore normal letdown. REFER TO Case II (Loss of Letdown).

EXAMINER NOTE: Restoration of letdown is part of another submitted scenario and should not be done per this scenario.

END EVENT Page 18 of27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 6 1 Page(s)

Event

Description:

1B S/G level program fails low Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event for the BOP using OP/1/B/6100/010E (Annunciator Response for PaneI1AD-4)

(C/2 - S/G B FLOW MISMATCH LO CF FLOW)

NOTE: SM flow channel 2 shares a reference tap with channel 2 of S/G narrow range level indication. SM flow channel 1 shares a reference tap with S/G wide range level indication. A failure on one of these level taps will affect the SM flow channel. Other indication of SM flow should be used to determine if it is an instrument failure.

IMMEDIATE ACTIONS RO 1. Compare all flow indication to verify condition.

RO 2. IF automatic controls are NOT correcting, take manual control.

SUPPLEMENTAL ACTIONS RO 1. WHEN malfunction is corrected OR bypassed, restore control to automatic.

EXAMINER NOTE: No technical specification conditions.

SRO 2. Refer to Tech Specs for operable channel requirements (TS 3.3.1, lTS 3.3.2, 3.3.3 and 3.3.4).

3.3.1,3.3.2, END EVENT Page 19 of 27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position AQPlicant's Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event starting with AP/1/A/5500/011 (Pressurizer Pressure Anomalies)

BOP 1. Verify all Pzr pressure channels - INDICATING THE SAME.

BOP 2. Verify all Pzr PORVs - CLOSED.

RO/BOP 2RNO Perform the following:

a. Manually close Pzr PORV(s).

b. IF any Pzr PORV cannot be closed, THEN:

1) Close the affected PORV(s) isolation valve.

2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following:

a) IF in Mode 3 or 4 AND CLAs isolated, THEN GO TO AP/1/A/55001027 (Shutdown LOCA).

b) Trip reactor.

c) Manually initiate S/I.

d) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).

SRO Transition to E-O _{reactor (reactor Trip or Safety Injectionl Injection)

ALL (Foldout Paije).

1. Monitor Enclosure 1 (FOldout Page).

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers -

• I/R amps - DECREASING.

RO 3. Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

BOP 4RNO Perform the following:

a. IF 1ETA AND 1ETB are de-energized,THEN GO TO EP/1/A/5000/ECA-0.0 (Loss Of All AC Power).

b. WHEN time allows, THEN attempt to restore power to de-energized switchgear while continuing with this procedure. REFER TO AP/1/A/55001007 (Loss of Normal Power).

BOP 5. Verify S/I is actuated:

a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

RO 6. Announce "Unit 1 Safety Injection".

4.1.A.1 (Alert)

EXAMINER NOTE: This will be a 4.1.A.11Alert)

SRO 7. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Reguirements).

Requirements).

RO 8. Verify all Feedwater Isolation status lights (1 SI SI-5) - LIT.

BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

b. Monitor Light Panel Group 5 St lights - LIT.

Page 20 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 10 Verify proper Phase B actuation as follows:

a. Containment pressure - HAS REMAINED LESS THAN 3 PSIG.

b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a.

BOP 11 Verify proper CA pump status as follows:

a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels - GREATER THAN 11%.

EXAMINER NOTE: Since crew is aware that there is no power on A train, they should state that when checking A train equipment, but not transition to RNa based on A train equipment alone. However they will transition for B train NI pump_

pump since it has power.

j?ower.

BOP 12 Verify all of the following SII pumps - ON:

• NV pumps

• NO pumps

• NI pumps.

BOP 12RNO Perform the following for affected train(s):

a. Reset ECCS.

b. Reset DIG load sequencer.

c. Manually start affected pump.

~uiQment previously on.

d. IF AT ANY TIME a B/O occurs, THEN restart SII equipment BOP 13 Verify all KC pumps - ON.

BOP 14 Verify all Unit 1 and Unit 2 RN pumps - ON.

EXAMINER NOTE: BOP will find VA not aligned properly per Enclosure 2.

Enclosure 2 steps are after step 22 and before E-1 steps.

BOP 15 Verify proper ventilation systems operation as follows:

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verificationj.

Verification).

BOP 16 Verify all S/G pressures - GREATER THAN 775 PSIG.

S/Gpressures BOP 17 Verify proper SII flow as follows:

a. "NV SII FLOW" - INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps -INDICATING FLOW.

d. NC pressure pressure - LESS THAN 285 PSIG.

BOP 17dRNO

d. Perform the following:

1) Ensure NO pump miniflow valve on operating NO pump(s) - OPEN.

2) IF the NO pump miniflow valve(s) cannot be opened, THEN ...

3) GO TO Step 18.

BOP 18 Control S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

b. WHEN at least one S/G N/R level is greater than 11% (29% ACC), THEN throttle feed flow to maintain all S/G N/R levels between 11 % (29% ACC) and 50%.

Page 21 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 19 Verify all CA isolation valves - OPEN.

EXAMINER NOTE: Some Equipment will not be in proper alignment but no action is available to place it in proper alignment due to loss of A train power.

BOP 20 Verify SII equipment status based on monitor light panel - IN PROPER ALIGNMENT.

EXAMINER NOTE: A Train equipment will not be in proper alignment due to no power.

20RNO Manually align equipment.

EXAMINER NOTE: Enclosure 4 actions are after Enclosure 2 actions.

RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance.

21 Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

BOP 22 Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

BOP 22aRNO

a. IF Pzr pressure is less than 2315 PSIG, THEN:

1) Manually close Pzr PORV(s).

2) IF any Pzr PORV cannot be closed, THEN:

a) Close its isolation valve.

b) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:

(1) IF both the following conditions exist,

• Containment pressure - GREATER THAN 1 PSIG

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG THEN manually start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start).

(2) Concurrently:

• Implement EP/11A15000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/11A15000/E-1 (Loss Of Reactor Or Secondary Coolant).

E-O, Enclosure 2 steps Page 22 of 27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 1. Verify proper VCIYC operation as follows:

a. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRAAHU-1

• CRA PFT-1.

b. Verify the following alarms - DARK:

• 1AD-18, N8 "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-18, B/8 "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-18, D/8 "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-18, E/8 "UNIT 2 INTAKE HI CHLORINE 2B".

c. Ensure the following VC dampers - OPEN:

• 1VC-SB (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-SB (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

d. Repeat Step 1 of this enclosure until notified by station management as follows:

• At least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR

• Any time VCIYC related annunciators on 1AD-18 actuate.

BOP 2. Ensure proper VA System operation as follows:

• Ensure the following fans - OFF:

0 ABUXF1A 0 ABUXF 1B.

• Ensure VA System filter is in service as follows:

0 1ABF-D-12 (VA Filt A Bypass Damper) - CLOSED 0 1ABF-D-S (VA Filt B Bypass Damper) - CLOSED.

• Ensure the following fans - ON:

0 ABFXF-1A 0 ABFXF 1B.

BOP 3. Verify proper VE System operation as follows:

a. VE fans - ON.

b. Annulus pressure - BETWEEN -1.4 IN. WC AND -1.8 IN. WC.

c. Repeat Step 3.b every 30 minutes until notified by station management.

BOP 4. Record time ventilation systems are verified on following table:

Enclosure 4 actions RO 1. Verify at least one NC pump - ON.

RO 2. Use NC T-Avg to determine NC temperature as required in subsequent steps.

RO 3. IF AT ANY TIME NC pumps are tripped, THEN use NC T-Colds to determine NC temperature as required in subsequent ste~s.

Page 23 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior AQ2Iicant's RO 4. Verify one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

RO 5. Continue to monitor NC temperature.

SRO Transition to EP/1/A15000/E-1 (Loss of Reactor or Secondary Coolant)

ALL 1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify main steamlines are intact as follows:

• All S/G pressures - STABLE OR INCREASING

• All S/Gs - PRESSURIZED.

BOP 3. Control intact S/G levels as follows:

a. Verify N/R level in all intact S/Gs - GREATER THAN 11 % (29% ACC).

b. Throttle feed flow to maintain all intact S/G N/R levels between 11 % (29%

ACC) and 50%.

EXAMINER NOTE: Crew should be aware that the EMF33 signal is false and not transition based on this indication with absence of any confirmatory indications.

BOP 4. Verify secondary radiation is normal as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

• Notify Chemistry to sample all S/Gs for activity.

OR

• Notify RP to frisk all cation columns for activity.

d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steam line 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steam line 1D).

e. WHEN activity results are reported, THEN verify all S/Gs indicate no activity.

activity-,

BOP 5. Verify Pzr PORV and isolation valve status as follows:

a. Power to all Pzr PORV isolation valves AVAILABLE.

b. All Pzr PORVs - CLOSED.

BOP 5bRNO

b. IF Pzr pressure is less than 2315 PSIG, THEN:

1) Manually close Pzr PORV(s).

2) IF any Pzr PORV cannot be closed, THEN close its isolation valve.

Page 24 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 5c. At least one Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME a Pzr PORV opens due to high pressure, THEN, after Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated.

RO 6. Verify SII termination criteria as follows:

a. NC subcooling based on core exit TICs - GREATER THAN OaF.

SRO 6aRNO. GO TO Step 6.f.

EXAMINER NOTE: 5/1 termination criteria will not be met for this scenario.

ALL 6f. Monitor SII termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

g. IF AT ANY TIME SII termination criteria is met while in this procedure, THEN RETURN TO Step 6.

BOP 7. Verify proper NS pump operation as follows:

a. At least one NS pump - ON.

BOP 7aRNO

a. Perform the following:

1) IF AT ANY TIME an NS pump(s) starts while in this procedure, THEN perform Step 7.

2) GO TO Step 8.

EXAMINER NOTE: Power will already have been removed from the 1A sequencer per AP/07.

BOP 8. Verify criteria to stop operating NO pumps as follows:

a. NC pressure - GREATER THAN 285 PSIG.

b. NC pressure - STABLE OR INCREASING.

c. At least one NO pump - ON.

d. NO pumps suction - ALIGNED TO FWST.

e. Verify FWST level- GREATER THAN 45%.

f. Ensure SII - RESET:

1) ECCS.

2) DIG load sequencers.

3) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

g. Stop NO pumps.

h. IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart NO pumps.

RO 9. Verify NC and S/G pressures as follows:

a. All SIG pressures - STABLE OR INCREASING.

b. NC pressure - STABLE OR DECREASING.

BOP 10. Verify conditions to stop operating DIGs as follows:

a. At least one DIG - ON.

b. Verify 1ETA is energized by offsite power as follows:

• "DIG 1A BKR TO ETA" - OPEN

• 1ETA - ENERGIZED .

Page 25 of 27

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 10bRNO

b. Perform the following:

1) Attempt to restore offsite power to affected switchgear. REFER TO AP/1/A/55001007 (Loss of Normal Power).

2) GO TO Step 10.d.

BOP d. Verify 1ETB is energized by offsite power as follows:

• "DIG 1B BKR TO ETB" - OPEN

• 1ETB - ENERGIZED .

e. WHEN SII is reset, THEN dispatch operator to stop 1B DIG and place in standby readiness. REFER TO OP/1/A/63501002 (Diesel Generator Operation).

f. Ensure SII - RESET:

1) ECCS.

2) DIG load sequencers.

3) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

BOP 11. Obtain containment H2 concentration as follows:

a. Ensure operator has been dispatched to secure all ice condenser air handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units).

b. Verify containment H2 analyzers - IN SERVICE.

BOP 11bRNO

b. Perform the following:

1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/64501010 (Containment Hydrogen Control System).

2) WHEN H2 analyzers are in service, THEN perform Steps 11.c through 11.e.

31 GO TO Step 12.

3)

EXAMINER NOTE: Crew should determine that one train (8) is available for containment sump swapover and Cold Leg Recirc.

Page 26 of27

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 7- 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 12. Initiate evaluation of plant status as follows:

a. Verify S/I systems - ALIGNED FOR INJECTION MODE.

b. Verify Cold Leg Recirc capability as follows:

1) At least one NO pump - AVAILABLE.

2) Verify power to all of the following valves - AVAILABLE:

• 1FW-27 A (NO Pump 1A Suct From FWST)

• 1NI-185A (NO Pump 1A Cont Sump Suct)

• 1ND-28A (NO Supply To NV & 1A NI Pmps)

• 1FW-SSB (NO Pump 1B Suct From FWST

• 1NI-184B (NO Pump 1B Cont Sump Suct)

• 1NI-332A (NI Pump Suct X-Over From NO)

• 1NI-333B (NI Pump Suct From NO)

• 1NI-334B (NI Pump Suct X-Over From NO)

• 1NI-136B (NO Supply To NI Pump 1B).

3) Verify power to all of the following

• 1NI-11SA (NI Pump 1A Miniflow Isol)

• 1NI-144A (NI Pump 1B Miniflow Isol)

• 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).

4) Verify the "ENABLE" lights for the following switches - LIT:

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"

• "C-LEG RECIR FWST TO CO NT SUMP SWAP TRN B".

c. Verify auxiliary building radiation is normal as follows:

• EMF-41 (Aux Bldg Ventilation) trip 1 light - DARK

• All area monitor EMF trip 1 lights - DARK.

d. WHEN the TSC is activated AND staffed, THEN:

1) Notify the Reactor Engineer to assess core damage. REFER TO RP/O/A/SOOOI01S (Core Damage Assessment).

2) Notify Chemistry to obtain current NC boron concentration.

3) WHEN NO is aligned for Cold Leg Recirc, THEN notify Chemistry to obtain current containment sump boron concentration.

4) Notify Operating Engineer of the following:

a) VA is required to be aligned to normal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the event.

b) Evaluate aligning VA to normal mode. REFER TO OP/O/A/64S01003 (Auxiliary Building Ventilation System).

e. Notify station management to evaluate starting additional plant equipment to recovery.

assist in recoveJY.

SRO 13. Verify NC System cooldown and depressurization is required as follows:

a. NC pressure - GREATER THAN 285 PSIG.

b. GO TO EP/1/A/SOOO/ES-1.2 (Post LOCA Cooldown And Depressurization).

SRO Transition to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization).

END EVENT Page 27 of27

Appendix D, Rev. 9 Form ES-D-1 2008 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.: 4- Op-Test No.:

Examiners: Operators:

Initial Conditions:

• 100% power

• EFPD =450 days

• Boron concentration is 112 ppm

• DFCS channel 3 out of service to repair a tubing leak (loop 5142 - CF Header Pressure) -

functional in progress

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Decrease power to 90% in preparation for performing PT/1/A/4250/002C (Turbine Control Valve Movement Test) on the next shift.

Event Malf. No. Event Event No. Type* Description 1 RO R Power decrease 2 BOP C PZR spray valve fails open, B heaters fail SRO TS 3 RO C Steam Dump valve fails open 4 SRO TS NS pump 1A breaker fails 5 BOP I KC surge tank level fails low 6 BOP C 1NV-148 fails full open in auto/manual control available 7 RO C CFP trip/ T/G runback with rods fail to move 8 ALL M Loss of all AC power/ Large Break LOCA Additional failures 1B CA pump fails to auto start 1NI10B and 1NI185B failed auto actions FWST Puncture

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

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 1 2 Page(s)

Event

Description:

Power decrease Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a REACTIVITY event using OP/1/A/61 00/003 (Controlling Procedure For Unit Operation) and OP/1/B/6300/01 (Turbine Generator).

OP/1/A/61 00/003 actions SRO NOTE:

1. This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of NSD 304 (Reactivity Management) (R.M.)

2. If the desired power reduction rate is ;::15%/hr (3.33 MW/Min), consider using AP/11A155001009 (Rapid Downpower).

2.1 IF shutdown is due to Tech Spec, ensure the NRC has been notified per RP/0/B/50001013 (NRC Notification Requirements).

RO 2.2 IF this is a T-AVG Coastdown, maintain T-AVG > Limiting Curve for Phases 2 and 3 (Enclosure 4.4.1).

RO 2.3 Notify the SOC prior to reducing load per OP/1/B/63001001 (Turbine-Generator).

RO 2.4 Begin load reduction to the desired power level.

OP/1/B/6300/001 actions RO 2.2 IF decreasing turbine generator load, perform the following:

2.2.1 Decrease turbine generator load within the following limitations:

2.2.1.1 Rate of change of First-Stage Bowl Inner Surface Temperature shall NOT exceed 150DF/hr (OAC point C1P1283 (First Stage Metal Temp Rate>>.

2.2.1.2 OAC point C1A1140 (Turbine Lower Inner Shell Temp) vs. Percent Steam Flow (OAC point C1 P1588 (Design Total Main Steam Flow, Measured (%>> shall be maintained above and to the left of curve in the Unit One OAC Databook "Load-Changing Recommendations".

2.2.1.3 Control valve casing difference, OAC point C1A0961 (Turb Valve Chest Inner Surface Metal Temp) minus C1A0967 (Turb Valve Chest Outer Surface Metal Temp), shall NOT exceed curve "Allowable Temp Difference on Control Valve Casing" in the Unit 1 OAC Databook.

2.2.1.4 S/G blowdown flowrates shall be adjusted to obtain maximum blowdown for the appropriate load.

2.2.1.5 IF CV4fuily closes (92% of full load, 1109 MWE), verify 1SM-33 (Ctrl Vlv #4 Stm Lead Drn) opens.

2.2.1.6 IF CV3 fully closes (65% of full load, 783 MWE), verify 1SM-25 (Ctrl Vlv #3 Stm Lead Drn) opens.

Page 1 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 1 2 Page(s)

Event

Description:

Power decrease Time Position Applicant's Actions or Behavior RO CAUTION:

1. Normal steady-state load change shall be made without exceeding limits shown on Enclosure 4.7 (Generator Operating Limits) and in the Unit One OAC Databook "Recommended Starting and Loading Curves".

2. Unit One Reactor Operating Data, Section 2.4 shall be referred to for allowable ramp rates.

2.2.2 Decrease turbine generator load by performing the following:

2.2.2.1 Select "LOAD RATE" and verify it illuminates.

2.2.2.2 Input the desired load rate.

2.2.2.3 Select "ENTER" and verify" LOAD RATE" goes dark 2.2.2.4 Select "TARGET" and verify it illuminates.

2.2.2.5 Input the desired load target.

2.2.2.6 Select "ENTER" and verify" TARGET" goes dark.

2.2.2.7 Verify new load target appears on Target Display.

2.2.2.8 Select "GO" and verify it illuminates to start load decrease.

2.2.2.9 S/G blowdown changes shall be coordinated with Secondary Chemistry.

END EVENT Page 2 of28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 2 2 Page(s)

Event

Description:

PZR spray valve fails open, B heaters fail Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/011 (Pressurizer Pressure Anomalies).

BOP 1. Verify all Pzr pressure channels -INDICATING THE SAME.

BOP 2. Verify all Pzr PORVs - CLOSED BOP NOTE Control rods may withdraw on decreasing NC pressure.

3. Verify Pzr spray valve(s) - CLOSED BOP 3RNO Perform the following:

a. Manually close affected spray valve(s).

b. IF affected spray valve(s) will not close, THEN ...

BOP 4. Verify all Pzr heaters - ENERGIZED BOP 4RNO IF Pzr pressure is less than 2220 PSIG, THEN ensure all Pzr heaters are enecgized.

BOP 5. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED BOP NOTE Positive reactivity is inserted during an increase in NC pressure which may cause auto rod insertion.

6. Verify NC pressure - STABLE OR INCREASING.

RO 7. WHEN NC pressure is stable, THEN:

• Stabilize unit at appropriate power level.

• Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

0 Turbine load 0 Control rods 0 Boron concentration BOP 8. IF a Pzr pressure channel failed high, THEN ...

EXAMINER NOTE: SRO determines that 3.4.9 (Pressurizer), condition B applies.

SRO 9. Ensure compliance with appropriate Tech Specs:

• 3.3.1 (Reactor Trip System (RTS) Instrumentation)

• 3.3.2 (Engineered Safety Features Actuation System (ESFAS)

Instrumentation)

• 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

• 3.3.4 (Remote Shutdown System)

• 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (ON B) Limits)

• 3.4.4 (RCS Loops - MODES 1 and 2)

• 3.4.5 (RCS Loops - MODE 3)

• 3.4.6 (RCS Loops - MODE 4)

• 3.4.9 (Pressurizer)

• 3.4.10 (Pressurizer Safety Valves)

• 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs))

• 3.4.13 (RCS Operational Leakage)

BOP 10. Ensure "PZR PRESS TO REC SELECT" is selected to an operable channel.

SRO 11. Determine long term plant status. RETURN TO procedure in effect.

Page 3 of28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 2 2 Page(s)

Event

Description:

Oescrigtion: PZR spray valve fails open, B heaters fail Time Position Applicant's Actions or Behavior END EVENT Page 4 of28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 3 2 Page(s)

Event

Description:

Steam Dump valve fails open Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/028 (Secondary Steam Leak) however; they may use OMP 1-7 guidance to isolate a known steam leak. AP/1/A15500/028 entry is not "required".

ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Verify turbine - ONLINE.

RO 3. Verify the following:

• Reactor power - LESS THAN OR EQUAL TO 100% POWER

• T-Avg - WITHIN 1.5°F OF T-Ref.

RO 4. Verify proper reactor response as follows:

• Control rods - IN "AUTO" AND STEPPING IN

• P/R neutron flux - DECREASING.

RO 5. IF AT ANY TIME reactor power is greater than 100%, THEN perform Step 3 RNO.

BOP 6. Verify Pzr level- STABLE OR INCREASING.

ALL 7. IF AT ANY TIME while in this procedure Pzr level is decreasing in an uncontrolled manner, THEN RETURN TO Step 6.

BOP 8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows:

a. Open the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. Close the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

ALL 9. Attempt to identify and isolate leak as follows:

a. Verify the following conditions - NORMAL:

• Containment temperature

• Containment pressure

• Containment humidity

• Containment floor & equipment sump level.

b. Dispatch operators to locate and identify source of steam leak.

c. Verify S/G PORVs - CLOSED.

d. Verify condenser dump valves - CLOSED.

RO 9dRNO

d. Perform the following:

1) Select "OFF RESET" on the following switches:

."STEAM DUMP INTLK BYP TRN A"

."STEAM DUMP INTLK BYP TRN B".

2) IF valve will not close, THEN dispatch operator to close affected condenser dump valve isolation valve.

RO 9 e. Verify atmospheric dump valves - CLOSED.

f. Verify CA PMP #1 - OFF.

g. IF leak is suspected to be in a doghouse, THEN ...

EXAMINER NOTE: No required notifications at this time.

Page 5 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 3 2 Page(s)

Event

Description:

DescriQtion: o~en Steam Dump valve fails open Time Position Applicant's Actions or Behavior SRO 10. Determine required notifications:

• REFER TO RP/O/A/SOOOI001 (Classification Of Emergency)

• REFER TO RP/O/B/SOOOI013 (NRC Notification Requirements).

BOP 11. Notify RP of leak.

EXAMINER NOTE: Leak will not yet be isolated at this time so additional steps are provided. The crew will skip to step 14 per the RNO of step 12.

When leak is isolated the event can be ended.

RO 12. Verify - LEAK ISOLATED.

SRO 13. Determine long term plant status. RETURN TO procedure and step in effect.

BOP 14. Verify UST level - STABLE OR INCREASING.

RO 1S. Verify - REACTOR CRITICAL.

RO 16. Determine approximate steam leak size as follows:

a. Verify - TURBINE ONLINE.

b. Ensure stable plant conditions:

• Stable T-Avg

• Condenser dump valves closed.

NOTE Secondary plant configuration can affect Thermal Power Best Estimate.

Diverse reactor power indications should be used to determine reactor power.

c. Determine percent turbine power as follows:

1) Divide turbine impulse pressure by 100% power value for turbine impulse pressure. REFER TO OAC Data Book for 100 % power value for turbine impulse pressure.

2) Multiply result by 100.

d. Verify difference between reactor power and turbine power - LESS THAN S%.

e. Notify RP of leak size.

RO 17. Verify reactor reactorQower power - GREATER THAN 1%.

SRO 18. Evaluate unit shutdown as follows:

a. Verify unit shutdown required based on either of the following:

• Steam leak cannot be isolated or until leak can be isolated or repaired at power OR

• OSM judgement.

b. Initiate unit shutdown. REFER TO one of the following:

• OP/1/A/61 001003 (Controlling Procedure For Unit Operation)

OR

• OP/1/A/61 001002 (Controlling Procedure For Unit Shutdown)

OR

• AP/1/A/SSOOI009 (Rapid Downpower).

c. GO TO Step 20.

END EVENT Page 6 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 4 Event No. 4 1 Page(s)

Event

Description:

NS pump 1A breaker fails Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a SRO Tech Spec event only.

OP/1/B/61 00/01 OL (Annunciator Response For PaneI1AD-11) Al1 - 4KV ESS PWR TRAIN A TROUBLE Immediate actions BOP Dispatch an operator to 1RFM-48 located on 1RFMP3 (AB-560, BB-49) to determine the cause of alarm.

Supplemental Actions BOP 1. IF alarm is due to loss of control power, dispatch an operator t01 EDE-F01 C (SWGR 1ETA Control Power) and 1ETA to determine cause.

BOP 2. Ensure proper operation per OP/1IA163501008 (125 VDC/120VAC Vital Instrument and Control Power System).

BOP 3. Verify proper operation of 125VDC Diesel Auxiliary Power System per OP/11A163501006iJ25 OP/11A163501006 (125 VDC Diesel Auxiliary System).

BOP 4. IF due to a breaker being out of the CONNECT position, ensure this condition is desirable and return to normal as soon as possible.

EXAMINER NOTE: Tech Spec 3.6.6 Condition A applies.

SRO 5. Refer to Tech Specs 3.8.9 and 3.8.10.

END EVENT Page 7 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 5 4 Page(s)

Event

Description:

KC surge tank level fails low Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/021 (Loss of Component lLoss Co",!ponent Cooling).

ALL CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss.

1. Monitor Enclosure 1 (Foldout Pagel Page).

BOP 2. Verify at least one KC pump - ON.

BOP pum~s are lost, THEN RETURN TO STEP 2.

3. IF AT ANY TIME all KC pumps BOP NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK.

AND

• At least one KCQump-KC pump - ON .

BOP 5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO.

BOP Veri~ both KC suCge

6. Verify surge tank levels - 50% - 90% AND STABLE.

EXAMINER NOTE: Level transmitters are working properly, however the relay that controls the valves on low level is actuated. This will separate the KC trains and another pump on the opposite train will need to be started to e~uipment.

support opposite train equipment.

BOP 7. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure.

8. Verify KC flow to NC pumps as follows:

• 1AD-20, N1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK

• 1AD-21, N1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK.

Page 8 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 5 4 Page(s)

Event Descr~tion: KC surge tank level fails low Time Position Applicant's Actions or Behavior BOP 8 RNO Perform the following:

a. Ensure the following valves - OPEN:

• 1KC-425A (NC Pumps Ret Hdr Cont Isol)

• 1KC-338B (NC Pumps Sup Hdr Cont Isol)

• 1KC-424B (NC Pumps Ret Hdr Cont Isol).

b. IF AT ANY TIME any of the following conditions are met:

• Time since loss of KC - GREATER THAN 10 MINUTES OR

• Any NC pump trip criteria from Enclosure 1 (Foldout Page) is met THEN perform the following:

1) IF letdown is isolated, THEN:

a) Ensure NV pump suction aligned to FWST as follows:

(1) 1NV-252A (NV Pumps Suct From FWST) - OPEN (2) 1NV-253B (NV Pumps Suct From FWST) - OPEN (3) 1NV-188A (VCT Otlt Isol) - CLOSED (4) 1 NV-189B (VCT Otlt Isol) - CLOSED.

b) WHEN Reactor is tripped, THEN attempt to establish and maintain a slow cooldown as required to maintain PZR level.

2) Ensure steam dumps -IN PRESSURE MODE.

3) Ensure the Reactor - TRIPPED.

4) WHEN reactor power less than 5%, THEN perform the following:

a) Trip all NC pumps.

b) Ensure the normal spray valve associated with the tripped NC pump(s) -

IN MANUAL AND CLOSED.

5) Secure any dilutions in progress.

6) IF the reactor trip breakers were closed, THEN perform one of the following while continuing with this procedure as time and conditions allow:

• IF above P-11, THEN GO TO EP/11A15000/E-0 (Reactor Trip Or Safety Injection).

OR

• IF below P-11, THEN GO TO AP/11A155001005 (Reactor Trip Or Inadvertent S/I Below P-11).

Page 9 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 4 Event No. 5 4 Page(s)

Event

Description:

KC surge tank level fails low Time Position Applicant's Actions or Behavior BOP 9a. Verify the following Train A KC non-essential header isolation valves - OPEN:

• 1KC-230A (Rx Bldg Non-Ess Hdr Isol)

• 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-50A (Aux Bldg Non-Ess Hdr Isol)

• 1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol).

b. Verify the following Train B KC non-essential header isolation valves - OPEN:

• 1KC-228B (Rx Bldg Non-Ess Hdr Isol)

• 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol)

• 1 KC-53B (Aux Bldg Non-Ess Hdr Isol)

• 1KC-2B (Aux Bldg Non-Ess Ret Hdr Isol).

BOP 9b RNO NOTE The KC non-essential header valves can be reopened when the appropriate train's level switch is reset. This should occur between 40% and 48%

KC surge tank level.

b. WHEN OAC alarm C1D2214 (KC Train B Low-Low Level Surge Tank Isol) is "NOT ACTUATED", THEN ensure the affected valve(s) o~en.

valve(sL are open.

EXAMINER NOTE: The level switch will not reset so an additional KC pump (opposite train) must be started.

BOP 9c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP 10 Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - 50% - 90% AND STABLE.

b. GO TO Step 14.

BOP 14 Ensure KC heat exchanger outlet mode switches - PROPERLY ALIGNED.

BOP 15 Determine and correct cause of loss of KC.

EXAMINER NOTE: SRO determines that no Technical Specifications apply.

The valves are in their safety position and all supported components have coolin~ available.

cooling SRO 16 Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.9-7 (Boration Systems Flow Path - Shutdown)

• SLC 16.9-8 (Boration Systems Flow Path - Operating)

• SLC 16.9-9 (Boration Systems Pumps - Shutdown)

• SLC 16.9-10 (Boration Systems Charging Pumps - Operating)

• 3.5.2 (ECCS - Operating)

• 3.5.3 (ECCS - Shutdown)

• 3.6.6 (Containment Spray System)

• 3.7.5 (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System).

EXAMINER NOTE: No notifications required at this time.

SRO 17 Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 _(NRC (NRC Notification Requirements).

Page 10 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 4 Event No. 5 4 Page(s)

Event

Description:

KC surge tank level fails low Time Position Applicant's Actions or Behavior BOP 18 IF KC Hx leak to RN is suspected, THEN ...

BOP 19 Verify KC surge tanks level as follows:

• Greater than 50%

• Stable or increasitlg_.

increasing.

BOP 20 WHEN plant conditions permit, THEN:

• Return KC pumps to normal operation. REFER TO OP/11A164001005 (Component Cooling Water System).

• Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 4 (Alternate Cooling To NV Pump 1A).

4JAIternate BOP 21 Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK

• 1AD-7, H/3 "VCT HI TEMP" - DARK

• Normal letdown -IN SERVICE.

BOP 22 Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) Open the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

2) Close the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to the "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through the NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) to the "DEMIN" position and return to "AUTO".

SRO 23 Determine long term plant status. RETURN TO procedure in affect.

END EVENT Page 11 of 28

CNS 2008 NRC E>,<am Appendix D, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 4 Event No. 6 1 Page(s)

Descr~tion:

Event

Description:

1NV-148 fails to 20% open in auto/manual control available Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using OP/lIB/6100/010H (Annunciator Response For PaneI1AD-7). (F/1 - LETDN HX OUTLET HI PRESS).

IMMEDIATE ACTIONS BOP 1. Verify alarm using 1NVP5570 (Letdn Press) (1 MC5).

BOP 2. Take manual control of 1NV-148 (Letdn Press Control) and attempt to restore pressure to normal.

BOP 3. Verify proper orifice selection and letdown line valve alignment.

SUPPLEMENTAL ACTIONS BOP 1. IF necessary, place excess letdown in service per OP/1/A/62001001 (Chemical

& Volume Control System).

Systemj.

BOP 2. Determine and correct cause of alarm.

END EVENT Page 12 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 2 Page(s)

Event

Description:

CFP tripl T/G run back with rods fail to move Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/003 (Load Rejection), Case 1- Switchyard Available.

RO 1. Verify turbine load - DECREASING IN AUTOMATIC RO 2. Verify proper reactor response:

• Control rods - IN "AUTO" AND STEPPING

• P/R neutron flux - DECREASING RO 2RNO IF T-Avg is greater than 1.5°F higher than T-Ref, THEN manually insert control rods as required to maintain T-Avg within IN 1°F ofT-Ref.

RO 3. Verify proper steam dump operation as follows:

a. Verify T-Ref instrumentation - AVAILABLE

b. "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT

c. Verify the following:

• "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI-18) - LIT

• Steam dump valves - MODULATING

d. T-Avg - DECREASING TO T-REF.

BOP 4. Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED

b. Normal Pzr spray valves - CLOSED BOP 5. Verify proper CM System operation as follows:

a. WHEN reactor power is less than 75%, THEN ensure both C-htr drain pumps -

OFF.

b. Verify reactor power - GREATER THAN 56% PRIOR TO THE EVENT.

c. Verify standby hotwell pump(s) - ON BOP 5cRNO c. Manually start standbyhotwell pump(s) as necessary BOP 5d. Verify standby condensate booster pump(s) - ON BOP 5dRNO. Manually start standby condensate booster pump(s) as necessary.

BOP 6. Verify the following generator alarms - DARK

• 1AD-11, C/1 "GEN BKR A OVER CURRENT"

• 1AD-11, F/1 "GEN BKR B OVER CURRENT" RO 7. Verify S/G levels are adequate as follows:

• All S/G low level alert alarms (1AD-4) - DARK

• All S/G low CF flow alarms (1AD-4) - DARK RO 8. Verify reactor power - GREATER THAN 20%.

RO 9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO.

BOP 10. Verify AS header pressure - GREATER THAN OR EQUAL TO 140 PSIG BOP 11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG - 6 PSIG.

RO 12. Monitor Enclosure 3 (Rod Insertion Limit Boration)

RO 13. Verify reactor power - LESS THAN 30%

Page 13 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 2 Page(s)

Event

Description:

CFP trip/ T/G runback with rods fail to move Time Position Applicant's Actions or Behavior RO 13RNO Perform the following:

a. IF the runback target load is less than 30%, THEN: ...

b. WHEN the appropriate runback target load is reached, THEN:

1) Stabilize unit at current power level.

2) Maintain control rods above insertion limits.

3) Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

• Turbine load

• Control rods

• Boron concentration.

c. GO TO Step 15.

BOP 15. Verify the following PCBs - CLOSED:

• Generator breaker 1A

• Generator breaker 1B

• PCB 14

• PCB15

• PCB 17

• PCB 18 RO 16. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43 RO 17. WHEN the appropriate runback target load is reached, THEN:

• Stabilize unit at appropriate power level.

• Maintain control rods above insertion limits.

• Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

0 Turbine load 0 Control rods 0 Boron concentration RO 18. Notify System Operating Center (SOC) using the red dispatcher telephone of current unit status ALL 19. Determine and correct cause of load rejection EXAMINER NOTE: This is where the next event is scheduled to begin.

END EVENT Page 14 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. S 14 Page(s)

Event

Description:

Loss of all AC power/ Large Break LOCA Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event and starts in EP/1/A/5000/E-O (reactor Trip or Safety Injection)

ALL 1. Monitor Enclosure 1 (Foldout Page)

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R amps - DECREASING RO Verify Turbine Trip:

• All turbine sto~ valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

BOP 4RNO Perform the following:

a. IF 1ETA AND 1ETB are de-energized, THEN GO TO EP/11A15000/ECA-O.O (Loss Of All AC Power}.

SRO Transition to ECA-O.O (Loss Of All AC Power).

ALL 1. CSF Status trees should be monitored for information only. Do not exit this procedure to implement any of the CSF procedures.

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• Reactor trip and bypass breakers - OPEN

• IIR amps - DECREASING.

RO 3. Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 4. Establish NC pump seal injection from the SSF:

• Notify Security Officer at SSF (Ext. 5251 or 5212) to perform EP/11A15000/ECA-O.O (Loss Of All AC Power), Enclosure 2 (Establishing NC Makeup/Seallnjection From The SSF)

• Dispatch operator to 1ETA switchgear room to align alternate power supply to 1EMXS. REFER TO Enclosure 1 (Align Alternate Power Supply To 1EMXS)

• Dispatch operator to SSF to establish NC pump seal injection. REFER TO Enclosure 2 (Establishin[ NC Makeup/Seal Injection From The SSF).

Page 15 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 5. Verify NC System is isolated as follows:

a. All Pzr PORVs - CLOSED.

b. All the following letdown isolation valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol)

• 1NV-1A (NC Letdn To Regen Hx Isol)

• 1NV-2A (NC Letdn To Regen Hx Isol)

• 1NV-135 (ND Flow To Letdn Hx).

c. All the following excess letdown isolation valves - CLOSED:

• 1NV-122B (Loop C To Exs Letdn Hx Isol)

• 1NV-123B (Loop C To Exs Letdn Hx Isol)

• 1NV-124B (Excess Letdn Press Ctrl1 Ctrl).

BOP 6. Verify total CA flow - GREATER THAN 450 GPM.

BOP 7. Attempt to restore power to 1ETA or 1ETB as follows:

a. Manually start DIGs from control room.

BOP 7a.RNO Perform the following:

1) Manually initiate S/I to emergency start D/G(s).

2) IF no DIG can be started, THEN GO TO Step 8.

BOP 7b. Verify at least one DIG load sequencer - AUTOMATICALL Y LOADING BUS.

c. Verify 1ETA or 1 ETB - ENERGIZED.

d. Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

e. RETURN TO procedure and step in effect.

SRO Transition back to E-O Step 5.

BOP 5a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

BOP 5bRNO b. Manually initiate S/I.

EXAMINER NOTE: By approximately this point a Large Break LOCA will occur.

RO 6. Announce "Unit 1 Safety Injection".

EXAMINER NOTE: Notifications are 4.5.A.2 or 4.1.A.1 JALERTS) (ALERTS)

SRO 7. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/5000/013 (NRC Notification Requirements).

RO 8. Verify all Feedwater Isolation status lights (1 SI-5) - LIT.

BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

b. Monitor Light Panel Group 5 St lights - LIT.

BOP 10. Verify proper Phase B actuation as follows:

a. Containment pressure - HAS REMAINED LESS THAN 3 PSIG.

Page 16 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8- 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 10aRNO

a. Perform the following:

NOTE This time may be used later to determine when to align NO Aux spray.

1) Record approximate time of reactor trip.

2) Verify NS pumps -INDICATINGFLOW.

3) IF flow is not indicated, THEN manually initiate Phase B Isolation for affected train(s).

4) Verify Phase B Isolation hasactuated as follows:

a) Phase B Isolation "RESET" lights - DARK.

b) IF Phase B Isolation "RESET" lights are lit, THEN manually initiate Phase B Isolation.

c) Verify following monitor light panel lights - LIT:

• Group 1 Sp lights

• Group 5 Sp lights

• Group 5 St lights Ll11 and Ll12.

d) IF monitor light panel not in correct alignment, THEN ensure correct alignment.

e) IF NS pump(s) did not start, THEN perform the following for the affected train(s):

(1) Reset ECCS.

(2) Reset DIG load sequencer.

(3) Manually start affected NS pump.

(4) IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.

(5) Stop all NC pumps.

(6) Maintain seal injection flow.

(7) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER TO Enclosure 7 (VX System Operation).

(8) GO TO Step 11.

BOP 11 Verify proper CA pump status as follows:

a. Motor driven CA pumps - ON.

BOP 11aRNO

a. Perform the following for the affected train(s):

1) Reset ECCS.

2) Reset DIG load sequencer.

3) Manually start affected motor driven CA pump.

4) IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.

RO 11 b. 3 SIG NIR levels - GREATER THAN 11 %.

BOP 12 Verify all of the following S/I pumps - ON:

• NV pumps

• NO pumps

• NI pumps.

Page 17 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 13 Veri& all KC pumps - ON.

BOP 14 Verify all Unit 1 and Unit 2 RN pumps - ON.

EXAMINER NOTE: Enclosure 2 actions are after step 26.

BOP 15 Verify proper ventilation systems operation as follows:

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification).

RO 16 Verify all S/G pressures - GREATER THAN 775 PSIG.

BOP 17 Verify proper S/I flow as follows:

a. "NV S/I FLOW' -INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

e. NO I:>ump_s -INDICATING FLOW TO C-LEGS.

BOP 18 Control S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

b. WHEN at least one S/G N/R level is greater than 11 % (29% ACC), THEN throttle feed flow to maintain all S/G N/R levels between 11 % (29% ACC) and 50%.

BOP 19 Verify all CA isolation valves - OPEN.

EXAMINER NOTE: If not already addressed, the BOP should note that 1NI-10B is closed and o~en it manually.

BOP 20 Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT.

BOP 20RNO Manuall~ align equipment.

EXAMINER NOTE: Enclosure 4 actions are listed after Enclosure 2 actions.

RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance.

21 Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

BOP 22 Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

c. At least one Pzr PORV isolation valve - OPEN.

RO 23 Verify NC subcooling based on core exit TICs - GREATER THAN OaF.

BOP 23RNO IF any NV OR NI pump is on, THEN:

a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

RO 24 Verify main steam lines are intact as follows:

• All S/G pressures - STABLE OR INCREASING

• ALL S/Gs - PRESSURIZED.

Page 18 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. --

8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 25 Verify S/G tubes are intact as follows:

• Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steam line 1C)

• 1EMF-29 (Steamline 1D).

• All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.

BOP 26 Verify NC System is intact as follows:

• Containment pressure - LESS THAN 1 PSIG.

• IF normal off-site power is available, THEN verify containment pressure less than 0.3 PSIG.

• Containment high range EMFs - LESS THAN 3 RlHR:

• 1EMF-53A (Containment Trn A)

• 1EMF-53B (Containment Trn B).

• Containment EMF trip 1 lights - DARK:

• 1EMF-38 (Containment Particulate)

• 1EMF-39 (Containment Gas).

• Containment sump level- STABLE.

BOP 26RNO Perform the following:

a. IF both the following conditions exist,

• Containment pressure - GREATER THAN 1 PSIG

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG THEN manually start one VX fan. REFER TO Enclosure 5 (VX Fan Manual start).

b. Concurrently:

• Implement EP/11A15000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/11A15000/E-1 (Loss Of Reactor Or Secondary Coolant).

E-O, Enclosure 2 steps Page 19 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. B 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 1. Verify proper VCIYC operation as follows:

a. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRAAHU-1

• CRA PFT-1.

b. Verify the following alarms - DARK:

• 1AD-1B, AlB "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-1B, BIB "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-1B, DIB "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-1B, E/B "UNIT 2 INTAKE HI CHLORINE 2B".

c. Ensure the following VC dampers - OPEN:

• 1VC-5B (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-5B (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

d. Repeat Step 1 of this enclosure until notified by station management as follows:

• At least once every B hours OR

• Any time VCIYC related annunciators on 1AD-1B actuate.

BOP 2. Ensure proper VA System operation as follows:

• Ensure the following fans - OFF:

o ABUXF 1A o ABUXF 1B.

• Ensure VA System filter is in service as follows:

o 1ABF-D-12 (VA Filt A Bypass Damper) - CLOSED o 1ABF-D-5 (VA Filt B Bypass Damper) - CLOSED.

• Ensure the following fans - ON:

o ABFXF-1A o ABFXF 1B.

BOP 3. Verify proper VE System operation as follows:

a. VE fans - ON.

b. Annulus pressure - BETWEEN -1.4 IN. WC AND -1.B IN. WC.

c. Repeat Step 3.b every 30 minutes until notified by station management.

BOP 4. Record time ventilation systems are verified on following table:

E-O Enclosure 4 actions RO 1. Verify at least one NC pump - ON.

RO 1RNO. Perform the following:

a. Use NC T-Colds to determine NC temperature as required in subsequent steps.

b. GO TO Step 4.

Page 20 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-0-2 Op-Test No. NRC Scenario No. 4 Event No. S 14 Page(s)

Event

Description:

Loss of all AC power/ Large Break LOCA Time Position Applicant's Actions or Behavior RO 4. Verify one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

SRO 4RNO GO TO Step 7.

RO 7. Verify NC teml=>erature temperature - LESS THAN 55rF AND DECREASING.

RO S. Attempt to stop the NC cooldown as follows:

a. Ensure all steam dumps - CLOSED.

b. Ensure all S/G PORVs - CLOSED.

c. Ensure S/G blowdown is isolated.

d. Close the following valves:

• 1SM-77A (S/G 1A Otlt Hdr Bldwn CN)

• 1SM-76B (S/G 1B Otlt Hdr Bldwn CN)

• 1SM-75A (S/G 1C Otlt Hdr Bldwn CN)

• 1SM-74B (S/G 10 Otlt Hdr Bldwn CN).

e. Depress and hold "SN BEFORE SEAT DRN" "CLOSE" pushbutton (1MC-3) to close the following valves:

• 1SM-41 (Stop Vlv #1 Before Seat Drn)

• 1SM-44 (Stop Vlv #2 Before Seat Drn)

• 1SM-43 (Stop Vlv #3 Before Seat Drn)

• 1SM-42 (Stop Vlv #4 Before Seat Drn).

f. Verlfy Verify NC cooldown - STOPPED.

RO SfRNO.

f. IF cooldown continues, THEN throttle feed flow as follows:

1) IF S/G N/R level is less than 11 % (29% ACC) in all S/G's, THEN throttle feed flow to achieve the following:

• Minimize cooldown

• Maintain total feed flow greater than 450 GPM.

2) WHEN N/R level is greater than 11 % (29% ACC) in at least one S/G, THEN throttle feed flow further to achieve the following:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11 % (29% ACC).

3) IF cooldown continues, THEN close the following valves:

• All MSIVs

• All MSIV bypass valves.

RO 9. Continue to perform the actions of this enclosure as required to ensure one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

SRO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

Transition to EP/1/A/5000/E-1_(Loss ALL 1. Monitor Enclosure 1 (Foldout Page).

PC!ge).

Page 21 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior RO 2. Verify main steam lines are intact as follows:

• All S/G pressures - STABLE OR INCREASING OR

• All S/Gs - PRESSURIZED.

BOP 3. Control intact S/G levels as follows:

a. Verify N/R level in all intact S/Gs - GREATER THAN 11 % (29% ACC).

b. Throttle feed flow to maintain all intact S/G N/R levels between 11 % (29%

ACC) and 50%.

BOP 4. Verify secondary radiation is normal as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

• Notify Chemistry to sample all S/Gs for activity.

OR

• Notify RP to frisk all cation columns for activity.

d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steam line 1C)

• • 1EMF-29 (Steamline 1D).

e. WHEN activity results are reported, THEN verify all S/Gs indicate no activity.

BOP 5. Verify Pzr PORV and isolation valve status as follows:

a. Power to all Pzr PORV isolation valves - AVAILABLE.

b. All Pzr PORVs - CLOSED.

c. At least one Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME a Pzr PORV opens due to high pressure, THEN, after Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated.

RO 6. Verify SII termination criteria as follows:

a. NC subcooling based on core exit TICs - GREATER THAN O°F.

SRO 6aRNO GO TO Step 6.f.

ALL 6f. Monitor SII termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

g. IF AT ANY TIME S/I termination criteria is met while in this procedure, THEN RETURN TO Step 6.

Page 22 of28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 7. Verify proper NS pump operation as follows:

a. At least one NS pump - ON.

b. Verify the following valves - OPEN:

• 1FW-27A (NO Pump 1A Suct From FWST).

• 1FW-55B (NO Pump 1B Suct From FWST).

c. Containment IJressure pressure - LESS THAN 2.4 PSIG.

EXAMINER NOTE: Pressure may be less than 2.4 psig and 7cRNO will not be required.

BOP 7cRNO Perform the following:

1) WHEN containment pressure is less than 2.4 PSIG, THEN perform Step 7.

2) GO TO Step 8.

BOP 7d. Verify operating NS pump(s) - HAVE REMAINED RUNNING SINCE INITIAL PHASE B SIGNAL.

e. Ensure S/I - RESET:

1) ECCS.

2) DIG load sequencers.

3) IF AT ANY TIME a B/O occurs,THEN restart SII equipment previously on.

f. Reset NS.

g. Stop NS pumps.

h. Close the following valves:

• 1NS-29A (NS Spray Hdr 1A Cont Isol)

• 1NS-32A (NS Spray Hdr 1A Cont Isol)

• 1NS-15B (NS Spray Hdr 1B Cont Isol)

• 1NS-12B (NS Spray Hdr 1B Cont Isol).

BOP 8. Verify criteria to stop operating NO pumps as follows:

a. NC pressure - GREATER THAN 285 PSIG.

SRO 8a.RNO

a. GO TO Step 10.

BOP 10. Verify conditions to stop operating DIGs as follows:

a. At least one DIG - ON.

b. Verify 1ETA is energized by offsite power as follows:

• "DIG 1A BKR TO ETA" - OPEN

• 1ETA - ENERGIZED.

BOP 10bRNO

b. Perform the following:

1) Attempt to restore offsite power to affected switchgear. REFER TO AP/1/A/55001007 (Loss of Normal Power).

2) GO TO Step 10.d.

BOP 10d. Verify 1ETB is energized by offsite power as follows:

• "DIG 1B BKR TO ETB" - OPEN

• 1ETB - ENERGIZED.

Page 23 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 10dRNO

d. Perform the following:

1) Attempt to restore offsite power to affected switchgear. REFER TO AP/1/A/55001007 (Loss of Normal Power).

2) IF 1ETA is energized from offsite power, THEN GO TO Step 10.f.

3) GO TO Step 11.

BOP 11. Obtain containment H2 concentration as follows:

a. Ensure operator has been dispatched to secure all ice condenser air handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units).

b. Verify containment H2 analyzers - IN SERVICE.

BOP 11bRNO

b. Perform the following:

1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/64501010 (Containment Hydrogen Control System).

2) WHEN H2 analyzers are in service, THEN perform Steps 11.c through 11.e.

3) GO TO Step 12.

BOP 12. Initiate evaluation of plant status as follows:

a. Verify S/I systems - ALIGNED FOR INJECTION MODE.

b. Verify Cold Leg Recirc capability as follows:

1) At least one ND pump -AVAILABLE.

2) Verify power to all of the following valves - AVAILABLE:

• 1FW-27A (ND Pump 1A Suct From FWST)

• 1NI-185A (ND Pump 1A Cont Sump Suct)

• 1ND-28A (ND Supply To NV & NI Pmps)

• 1FW-55B (ND Pump 1B Suct

• 1NI-184B (ND Pump 1B Cont Sump Suct)

• 1NI-332A (NI Pump Suct X-Over From ND)

• 1NI-333B (NI Pump Suct From ND)

• 1NI-334B (NI Pump Suct X-Over From ND)

• 1NI-136B (ND Supply To NI Pump 1B).

BOP 12b2)RNO

2) Perform the following:

IF power cannot be verified to minimum number of valves required to perform the following:

• Transfer one train of ND to the containment sump

• Establish ND flow from containment sump to one train of NV and NI pumps.

THEN GO TO EP/1/A/5000/ECA-1.11Loss Of Emergency Coolant ND)

BOP 12b3) Verify power to all of the following valves - AVAILABLE:

• 1NI-115A (NI Pump 1A Miniflow Isol)

• 1NI-144A (NI Pump 1B Miniflow Isol)

• 1NI-147B (NI PumR Miniflow Hdr To FWST Isol).

Page 24 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 12b3)RNO IF power cannot be verified to valves minimum number of valves required to isolate NI pump miniflow, THEN perform the following:

• Attempt to restore power to miniflow isolation valve(s)

• Have operator standing by to locally close the required valve:

• 1NI-147B (NI Miniflow Hdr To FWST Isol) (AB-548, HH-JJ, 53-54, Rm 234)

• 1NI-115A (NI Pump 1A Miniflow Isol) (AB-549, GG-HH, 53-54, Rm 235)

• 1NI-144A (NI Pump 1B Miniflow Isol) (AB-548, HH-JJ, 53-54, Rm 234).

BOP 12b4) Verify the "ENABLE" lights for the following switches - LIT

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B".

BOP c. Verify auxiliary building radiation is normal as follows:

• EMF-41 (Aux Bldg Ventilation) trip 1 light - DARK

• All area monitor EMF trip 1 lights - DARK.

d. WHEN the TSC is activated AND staffed, THEN:

1) Notify the Reactor Engineer to assess core damage. REFER TO RP/O/A/50001015 (Core Damage Assessment).

2) Notify Chemistry to obtain current NC boron concentration.

3) WHEN NO is aligned for Cold Leg Recirc, THEN notify Chemistry to obtain current containment sump boron concentration.

4) Notify Operating Engineer of the following:

a) VA is required to be aligned to normal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the event.

b) Evaluate aligning VA to normal mode. REFER TO OP/O/A/64501003 (Auxiliary Building Ventilation System).

e. Notify station management to evaluate starting additional plant equipment to assist in recovery.

BOP 13. Verify NC System cooldown and depressurization is required as follows:

a. NC pressure - GREATER THAN 285 PSIG BOP 13a.RNO IF NO flow to C-Legs is greater than 675 GPM, THEN GO TO Step 14.

BOP 14. Verify transfer to Cold Leg Recirc as follows:

a. FWST level- LESS THAN 37% (1AD-9, 0/8 "FWST 2/4 LO LEVEL" - LIT).

EXAMINER NOTE: FWST will likely not be at 37% at this time, but transition will occur at 37% based on Enclosure 1 actions. The procedure loops until that time.

SRO 14a RNO. RETURN TO Ste2 11.

Transition to EP/1/A/5500/ES-1.3 ALL 1. Monitor Enclosure 1 (Foldout Page).

ALL CAUTION S/I recirculation flow to NC System must be maintained at all times.

NOTE

• Steps 2 through 8 should be performed without delay.

• CSF should not be implemented until directed by this procedure.

Page 25 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 2. Verify at least one of the following annunciators - LIT:

• 1AD-20, B/3 "CO NT. SUMP LEVEL >3.3 ft"

• 1AD-21, B/3 "CO NT. SUMP LEVEL >3.3 ft".

BOP 3. Verify KC flow to ND heat exchangers - GREATER THAN 5000 GPM.

BOP 3RNO Establish KC flow to affected ND Hx(s).

BOP 4. Ensure SII - RESET:

a. ECCS.

b. DIG load sequencers.

e_qu~ment previously on.

c. IF AT ANY TIME a BIO occurs, THEN restart SII equipment EXAMINER NOTE: Only B train valves can be aligned due to lack of A train power. The crew will evaluate the RNOs but no actions will be taken based solely on lack of ~ower.

power.

BOP 5. Align SII system for recirc as follows:

a. Verify following valves - OPEN:

• 1NI-185A (ND Pump 1A Cont Sump Suct)

• 1NI-184BiND 1NI-184B (ND Pum21B Pump 1B Cont Sump Suct).

BOP 5aRNOa. Perform the following:

1) Manually open affected valve(s).

2) IF valve(s) will not open, THEN ...

3) IF both containment sump suction valves are closed, THEN:

31lF Page 26 of28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 8 14 Page(s)

--=--

--=---

Event

Description:

Loss of all AC power/ Large Break LOCA Time Position Applicant's Actions or Behavior BOP 5b. Verify following valves - CLOSED:

• 1FW-27 A (NO Pump 1A Suct From FWST)

• 1FW-55B (NO Pump 1B Suct From FWST).

c. Verify NO pumps - ON.

d. Isolate NI pump miniflow as follows:

1) Verify NC pressure - LESS THAN 1620 PSIG.

2) Close the following valves:

• 1NI-115A (NI Pump 1A Miniflow Isol)

• 1NI-144A (NI Pump 1B Miniflow Isol).

3) Place "PWR DISCON FOR 1NI-147B" switch in "ENABLE".

4) Close 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).

e. Close the following valves:

• 1ND-32A (NO Train 1A Hot Leg Inj Isol)

• 1ND-65B (NO Train 1B Hot Leg Inj Isol).

f. Verify at least one of the following NV pumps miniflow valves - CLOSED:

• 1NV-203A (NV Pumps A&B Recirc Isol)

OR

• 1NV-202B (NV Pmps A&B Recirc Isol).

g. Align NO train discharges to NI and NV pump suctions as follows:

1) Open the following valves:

• 1NI-332A (NI Pump Suct X-Over From NO)

• 1NI-333B (NI Pump Suct From NO).

2) Ensure 1NI-334B (NI Pump Suct X-Over From NO) - OPEN.

3) Open the following valves:

• 1ND-28A (NO Supply To NV & 1A NI Pmps)

• 1NI-136B (NO Supply To NI Pump 1B).

h. Isolate FWST from NV and NI pumps as follows:

1) Place "PWR DISCON FOR 1NI-1 OOB" switch in "ENABLE".

2) Close 1NI-100B (NI Pmps Suct From FWST).

3) Close the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

i. Verify proper recirc flow as follows:

• "NV S/I FLOW" - INDICATING FLOW

• NI pumps - INDICATING FLOW

• NO pumps - INDICATING FLOW.

BOP 6. WHEN FWST level decreases to 11 % (1AD-9, E/8 "FWST La-La LEVEL" alarm lit), THEN perform the following:

a. Stop NS Pumps.

b. Align NS for recirc. REFER TO Enclosure 2 (Aligning NS for Recirculation).

Page 27 of28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. B 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Time Position Applicant's Actions or Behavior BOP 7. IF any NS pump in service with suction aligned to FWST, THEN perform the following:

a. Ensure appropriate operator is in possession of Enclosure 2 (Aligning NS for Recirculation).

b. Designate operator to ensure NS pumps immediately secured when FWST level decreases to 11% OR 1AD-9, E/B "FWST La-La LEVEL" alarm lit.

c. IF time and manpower permit, THEN notify designated operator to review Enclosure 2 (Aligning NS for Recirculation) for current plant conditions.

current2lant BOP B. Verify criteria for initiation of NO aux containment spray:

a. Containment pressure - GREATER THAN 3 PSIG.

BOP BARNO

a. Perform the following:

1) IF AT ANY TIME containment pressure exceeds 3 PSIG, THEN perform Step B.

2) Observe Caution priorprior to Step St~ 9.

Ste_p 9 and GO TO Step ALL CAUTION If a BIO occurs, NVINI pump(s) may sequence on or be left in service without adequate suction, It is critical to ensure ECCS pumps are not operated without adequate pump suction.

9. IF AT ANY TIME a BIO occurs, THEN perform the following:

a. Ensure NVINI pumps taking suction from de-energized NO pump(s) - OFF.

b. Restart SII S/I equipment equigment previously on.

ALL 10. EP/1/A/5000/F-O (Critical Safety Function Status Trees) may now be implemented.

BOP Verify proper recirc flow as follows:

• "NV SIIS/I FLOW" - INDICATING FLOW

• NI pumps - INDICATING FLOW

• NO pumps -INDICATING FLOW.

END EVENT Page 28 of28