ML053570240

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Final - Section C Operating Exam (Folder 3)
ML053570240
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 11/28/2005
From: Michael Brown
Operations Branch I
To: Reid J
Public Service Enterprise Group
Conte R
References
50-354/05-301 50-354/05-301
Download: ML053570240 (59)
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Text

HOPE CREEK ELECTRIC GENERATING STATION NRC INITIAL LICENSED EXAMINATION SCENARIO 1 NOVEMBER 28, 2005 SCENARIO TITLE:

Reactor Startup/ Loss of 'B' MB Set/ RCIC Steam Leak SCENARIO NUMBER:

NRC-001 EFFECTIVE DATE:

EXPECTED DURATION:

1.0 Hours REVISION NUMBER:

1 PROGRAM:

L.O. REQUAL X

INITIAL LICENSE OTHER REVISION

SUMMARY

New Scenario.

PREPARED BY:

M. L. Brown 9/29/05 NRC Operations Examiner DATE FACILITY REVIEWER:

Nuclear Operations Training Supervisor -

Hope Creek DATE APPROVED BY:

NRC Chief Examiner DATE

NRC-001 REV-01 NRC-001 Page 2 of 22 Rev.: 01 I.

OBJECTIVE(S):

Enabling Objectives A.

The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an CT-X.)

II.

MAJOR EVENTS:

A.

Withdraw Group 7 Control Rods to position 8 B.

PT-N078B, Steam Dome Pressure Transmitter fails LOW C.

Loss of B MG Set and Control Rod 22-35 inadvertently scrams (TS)

D.

A CRD pump trips E.

Steam Leak from RCIC piping F.

RCIC isolation valves fail to close G.

E SRV fails Open III.

SCENARIO

SUMMARY

The scenario begins with a Reactor Startup in progress with IOP-3 completed up to step 5.3.29.

Reactor power is approximately 4%. 1BP116 EHC pump is tagged out for maintenance and will be out of service until a new pressure compensator arrives tomorrow. After the operators have pulled Group 7 rods to position 8 and placed the Secondary Condensate Pump in service, Pressure Transmitter PT-N078B fails low. After Tech specs are addressed, the B MG Set trips and Control Rod 22-35 inserts, causing a 1/2 scram and RWCU isolation. The operators will have to restore power to the B RPS from the alternate source. The operators will have to declare the rod inop and comply with Tech Specs. After power has been restored and Tech Specs addressed, the A CRD pump trips requiring the operators to start the B CRD pump to avoid a Reactor Scram. Once the B CRD pump has been started, a steam leak develops on RCIC. The RCIC isolation valves fail to close causing RCIC room temperature to increase. The Crew should enter EOP-103 based on high room temperature and may place FRVS in service per HC.OP-AB.CONT-0004, South Plant Vent Activity and attempt to shutdown RCIC. The Crew will discover that the RCIC isolation valves cant be closed. The Crew should scram the reactor based upon RCIC room temperature approaching safe operating limit and enter EOP-101 or AB-0000. When temperature exceeds Max Safe Operation limit in 2 areas, crew should enter EOP-202, Emergency Depressurization. When the crew goes to Emergency Depressurize, E ADS valve will not open, requiring the BOP to open another SRV. Scenario will end after 5 SRVs have been opened.

NRC-001 REV-01 NRC-001 Page 3 of 22 Rev.: 01 IV.

INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to IC-11 (4% power, MOL)

RAISE Pressure to 500#

PREWARM B SJAE RESET HPCI High Level Trip PLACE CP161 Chilled Water Circ Pump in MAN PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description Items required to be set up each time the SG is performed, i.e. tagged equipment, RM11 set points, procedures, etc.

COMPLETE Attachment 2 Simulator Ready-for-Training/Examination Checklist of NC.TQ-DG.ZZ-0002(Z).

EVENT TRIGGER Initial ET # Description 1

EVENT ACTION:

COMMAND:

PURPOSE:

rp:k14a>=1.0 && rp:k14b>=1.0&&lcvposx(106)<=0.0 dmf cd062235 Raises EHC Filter Clogging to 100% severity when B EHC pump is started 2

EVENT ACTION:

COMMAND:

PURPOSE:

rcvv(1) <= 0.98 // RCIC steam isolation Trip breaker when valve closure attempted 3

EVENT ACTION:

COMMAND:

PURPOSE:

rcvv(4) <= 0.98 // RCIC steam isolation Trip breaker when valve closure is attempted 4

EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=130 // RCIC Room Temperature Set hvtr4111 = 120 Raises HPCI Room temp as RCIC temp rises 5

EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=140 // RCIC Room Temperature Set hvtr4111 = 130 Raises HPCI Room temp as RCIC temp rises

NRC-001 REV-01 NRC-001 Page 4 of 22 Rev.: 01 EVENT TRIGGER Initial ET Description 6

EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=150 // RCIC Room Temperature Set hvtr4111 = 140 Raises HPCI Room temp as RCIC temp rises 7

EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=160 // RCIC Room Temperature Set hvtr4111 = 150 Raises HPCI Room temp as RCIC temp rises 8

EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=170 // RCIC Room Temperature Set hvtr4111 = 160 Raises HPCI Room temp as RCIC temp rises 9

EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=180 // RCIC Room Temperature Set hvtr4111 = 170 Raises HPCI Room temp as RCIC temp rises 10 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=190 // RCIC Room Temperature Set hvtr4111 = 180 Raises HPCI Room temp as RCIC temp rises 11 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=200 // RCIC Room Temperature Set hvtr4111 = 190 Raises HPCI Room temp as RCIC temp rises 12 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=210 // RCIC Room Temperature Set hvtr4111 = 200 Raises HPCI Room temp as RCIC temp rises 13 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=220 // RCIC Room Temperature Set hvtr4111 = 210 Raises HPCI Room temp as RCIC temp rises 14 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=230 // RCIC Room Temperature Set hvtr4111 = 220 Raises HPCI Room temp as RCIC temp rises 15 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=240 // RCIC Room Temperature Set hvtr4111 = 230 Raises HPCI Room temp as RCIC temp rises 16 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=250 // RCIC Room Temperature Set hvtr4111 = 240 Raises HPCI Room temp as RCIC temp rises 17 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=255 // RCIC Room Temperature Set hvtr4111 = 245 Raises HPCI Room temp as RCIC temp rises

NRC-001 REV-01 NRC-001 Page 5 of 22 Rev.: 01 EVENT TRIGGER Initial ET Description 18 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=256 // RCIC Room Temperature Set hvtr4111 = 246 Raises HPCI Room temp as RCIC temp rises 19 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=257 // RCIC Room Temperature Set hvtr4111 = 247 Raises HPCI Room temp as RCIC temp rises 20 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=258 // RCIC Room Temperature Set hvtr4111 = 248 Raises HPCI Room temp as RCIC temp rises 21 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>= 259 // RCIC Room Temperature Set hvtr4111 = 249 Raises HPCI Room temp as RCIC temp rises 22 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=260 // RCIC Room Temperature Set hvtr4111 = 250 Raises HPCI Room temp as RCIC temp rises 23 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=261 // RCIC Room Temperature Set hvtr4111 = 251 Raises HPCI Room temp as RCIC temp rises 24 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=262 // RCIC Room Temperature Set hvtr4111 = 252 Raises HPCI Room temp as RCIC temp rises 25 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=265 // RCIC Room Temperature Set hvtr4111 = 255 Raises HPCI Room temp as RCIC temp rises 26 EVENT ACTION:

COMMAND:

PURPOSE hvtr 4110>=270 // RCIC Room Temperature Set hvtr4111 = 260 Raises HPCI Room temp as RCIC temp rises

NRC-001 REV-01 NRC-001 Page 6 of 22 Rev.: 01 MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val RC10 - RCIC steam isolation valves F007 & F008 fail to Auto Close NONE RP17B - RPS PT-N078B failure RT-1 515.205 0

RP02B - RPS MG set B failure RT-2 CD062235 Control Rod 22-35 SCRAM 0:02 RT-2 CD10A - CRD Hydraulic Pump A trip RT-3 RC09 - RCIC Steam Line break inside the RCIC Room 4110 1:00 RT-4 0

100 AN-A2A5 CRYWOLF ANN A2A5 - Fire Prot Panel RT-4 HP09 - HPCI Steam line break inside the HPCI Room 4111 1:00 RT-4 0

1 AD02EC - ADS/Relief valve F013E fails to OPEN NONE REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val PP05 - OD-3 MFLCPR Fraction Limiting NONE

.861

.036 PP06 - OD-3 MFLPD NONE

.723

.028 PP07 - OD-3 MAPRAT NONE

.633

.023 RC03 - GROUP 6A HV-F007 RCIC Steam Supply Valve ET-2 NOR MAL RACK OPEN RC05 - GROUP 6A HV-F008 RCIC Steam Supply Valve ET-3 NOR MAL RACK OPEN I/O OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val NONE

NRC-001 REV-01 NRC-001 Page 7 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Crew assumes the watch at step 5.3.29 of IO.ZZ-0003, and continues plant startup per procedure

  • RO pulls Group 7 rod to position 8 observing the following:
  • Rod only moves 1 notch
  • CRS directs BOP to start the Secondary Condensate Pump IAW SO.AE-0001
  • BOP reviews P&Ls of SO.AE.0001
  • BOP goes to step 5.1.17 of SO.AE-0001 to start the Secondary Cond. Pump (this will refer him/her back to Step 5.1.11)
  • BOP Ensures at least 2 Cond.

Pumps are running

  • BOP dispatches an NEO to start the Lube Oil System After 2 minutes NEO reports back that the Aux Lube Oil Reservoir level for the Secondary Condensate pump to be started is normal
  • BOP observes PI-1669B pressure between 7 to 9 psig.
  • BOP ensures HV-1651B, discharge valve is closed
  • BOP Observes SEC CNDS PUMP B START ENABLE is illuminated.
  • BOP has NEO ensure FIC-1650B is in AUTO with a setpoint of 5500 gpm

NRC-001 REV-01 NRC-001 Page 8 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments The NEO reports FIC-1650B is in AUTO with a setpoint of 5500 gpm

  • BOP Starts Secondary Condensate Pump B and observes:
  • Min flow valve OPEN light is illuminated
  • Motor Amps are < 279 amps
  • BOP stops the B Aux Lube Oil pump and returns it to AUTO
  • BOP presses AD-HV-1710 PRI CNDS FLOW PATH MIN FLOW RECIRC CLOSE PB PT-N078B fails Low Once the crew has started the Secondary Condensate Pump OR At the discretion of the Lead Examiner TRIGGER - RT1
  • RO observes several annunciators illuminate and diagnoses that PT-N078B has failed LOW
  • C3-B4 - RPS TRIP SYS B OUT OF SVCE
  • C8-A5 - NSSSS INBD ISLN SYS OUT OF SVCE
  • CRS determines that PT-N078B is INOP and enters the following LCOs
  • 3.3.1 - Function Unit 3 Action A

- Put in the Trip Condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

  • 3.3.2 Trip Function 7B b.1)b. -

Put in the Trip Condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

  • 3.3.7.5 - Accident Monitoring System Action 80 - Restore to Operable within 30 days or initiate actions of 6.9.2
  • CRS contacts I&C to repair instrument

NRC-001 REV-01 NRC-001 Page 9 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Loss of B MG Set and Rod 22-35 Inadvertently Scrams Once the CRS has addressed Tech Specs and contacted I&C OR At the discretion of the Lead Examiner TRIGGER - RT2

  • Crew recognizes trip of B MG Set
  • RO recognizes that NO actual scram condition exists and DOES NOT scram the reactor
  • CRS enters AB-IC-0003
  • Determines Normal CANNOT be restored
  • Directs RO to Transfer power to Alternate power supply
  • RO verifies Alternate Power is available
  • RO Transfers Power to Alternate Power Supply by Positioning the RPS MG SET TRANSFER SWITCH to the Alternate Position.

Improper operation of this will cause a scram

o Turning the key for the Affected RPS channel to the RESET position o Turning the key back to the NORMAL position o Verify the scram is reset

NRC-001 REV-01 NRC-001 Page 10 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • CRS directs that the tripped NSSS logic be reset
  • RO presses the NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC B RESET Pb.
  • RO Verifies MSIV TRIP LOGIC TRIPPED light goes off
  • CRS directs restoration of isolated Equipment (RWCU isolated and Mechanical Vacuum pumps have tripped)
  • RO Restores isolated equipment IAW applicable SOP
  • Crew observes that Mechanical Vacuum pumps have tripped
  • CRS may elect to restart Mechanical Vacuum pumps here or may wait
  • RO diagnoses that Rod 22-35 has Scrammed This may occur prior to completion of actions for loss of RPS bus
  • RO references ARP for C6-E3, Rod Drift - Digital Point C078
  • Determines only 1 Rod has Scrammed
  • Checks Reactor Thermal Limits
  • Notifies the On-Call Reactor Engineer IAW RE-AP.ZZ-0101

NRC-001 REV-01 NRC-001 Page 11 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • CRS/RO determines that Multiple Rods are NOT drifting or Scrammed
  • CRS determines that Charging water Header pressure is > 940 psig and DOES NOT have the RO scram the Reactor
  • CRS Enters Section C of AB.IC-0001, Malfunction results in Inadvertent Rod Motion
  • Has RO review ARP for Rod Drift
  • Contacts Rx Engineer for guidance
  • Compares present LPRM reading with previously recorded LPRM readings
  • Checks Thermal Limits
  • CRS refers to Tech Specs 3.1.3.1 and determines the Control Rod is INOP and complies with b. 2. and has the Control Rod disarmed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> A CRD Hydraulic Pump Trip Once the Crew has stabilized the plant and addressed Tech Specs OR At the discretion of the Lead Examiner TRIGGER RT-3
  • RO diagnoses A CRD pump has tripped.

NRC-001 REV-01 NRC-001 Page 12 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • RO/CRS dispatches NEOs to:
  • The Aux Building to look at the CRD Breaker
  • The Reactor Building to look at the pump After 2 minutes have the NEO in the Aux. Bldg report that the A pump motor tripped on overcurrent and the NEO in the Rx Bldg report that the motor is hot to the touch.
  • RO places Drive Water Flow controller in Manual and set to 0
  • RO starts B CRD pump and restores system flow to 63 gpm
  • RO Adjusts HV-F003 to restore system pressure to normal
  • RO Returns Drive water flow controller to AUTO RCIC Steam Leak Once the crew has stabilized the plant after the CRD pump trip OR At the discretion of the Lead Examiner TRIGGER - RT4
  • BOP checks Fire Protection CRT and determines Fire alarm is from the RCIC Pump Room
  • Crew dispatches an NEO to the RCIC pump room to investigate After 2 minutes have the NEO report that he sees a lot of steam in the pump room but no fire.
  • BOP attempts to close HV-F007 and HV-F008, RCIC Steam Supply Isolation Valves
  • BOP reports Steam Supply isolation valves wont close

NRC-001 REV-01 NRC-001 Page 13 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • Crew requests assistance from NEO/ WCC to close RCIC isolation valve
  • CRS Enters EO-0103 based on Room Temp in RCIC Room >

Max Normal Op Temp CRS directs RO/BOP to monitor and Control Reactor Building Temps BOP reports RCIC pump room temperature > Column 1 - Max Normal Op Temp

  • CRS determines FRVS is NOT in service
  • CRS directs BOP to verify proper operation of RBVS and Emergency Area Cooling System Note - CRS may elect to put FRVS in service at this time. This action is acceptable
  • BOP determines RBVS and Emergency Area Cooling systems are operating properly
  • BOP reports RCIC pump room temperature > Max Safe Op Temp
  • CRS determines RCS is discharging into the Reactor building CT-1 Crew INITIATES a manual scram BEFORE RCIC Room Temp reaches 250°F
  • CRS directs a Recirc Runback and a Reactor Scram before RCIC room temperature reaches 250°F
  • CRS enters EO-101 concurrently with this procedure
  • RO Performs the Actions of AB.ZZ-0001, Attachment 1, Reactor Scram

NRC-001 REV-01 NRC-001 Page 14 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments RO performs the following:

  • ANNOUNCES Crew - Standby for Scram Report.
  • LOCKS the Mode Switch in Shutdown.
  • ANNOUNCES the following:

Rod Motion status APRM Downscale status Reactor Shutdown status

  • WHEN the above actions are complete, THEN ANNOUNCE Scram Report Complete.
  • INSERTS the SRM/IRMs.
  • SELECTS IRM chart recorders.
  • WHEN Main Generator output reaches zero Mwe THEN TRIPS the Main Turbine.
  • LOCK OUTS the Main Generator.
  • ENSURES the Reactor Scram has been announced (over PA).
  • REPORTS All Scram Actions Complete.
  • BOP verifies H2 Injection System Tripped
  • RO maintains RPV level between

+12.5 and 54 using Condensate/ Feedwater NOTE: If crew attempts to open bypass valves to depressurize the reactor, then fail Bypass valves shut.

NRC-001 REV-01 NRC-001 Page 15 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • CRS determines that all entry conditions have cleared and exits EO-0101 and enters AB.ZZ-0000
  • Crew stabilizes the plant in AB.ZZ-0000
  • BOP reports 2nd area has exceeded its Max Safe Op Limit
  • CRS determines Emergency Depressurization is required and enters EO-0202
  • CRS determines the following:

o Reactor is shutdown from all conditions without boron o DW pressure is < 1.68 psig o Supp Pool level > 0

  • CRS orders 5 ADS valves to be Opened CT-2 Crew Emergency Depressurizes the plant within 5 minutes of when ED conditions are reached.
  • BOP Places all 5 ADS valve hand switches to OPEN Note - Failure of E ADS to open was input as an initial condition
  • BOP recognizes PSV-F013E failed to OPEN
  • CRS directs BOP to open non-ADS SRVs until a total of 5 SRVs are open CT-3 Crew opens at least 5 SRVs to comply with ED criteria
  • BOP opens an additional SRV until a total of 5 SRVs are open Termination Requirement:

When 5 SRV are OPEN OR At Lead Examiner Discretion Put the simulator in Freeze Inform the candidates that the simulator is in freeze and to standby for follow questions

NRC-001 REV-01 NRC-001 Page 16 of 22 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • CRS determines an SAE Classification is required based on 4 points for failure of the RCS barrier (3.2.3 B) and 2 points for the failure of the Containment Barrier (3.3.4)

It is anticipated that the CRS candidate will be asked to classify this event and the results will be counted as one of his JPMs.

NRC-001 REV-01 NRC-001 Page 17 of 22 Rev.: 01 VI.

SCENARIO

REFERENCES:

A.

NC.TQ-DG.ZZ-0002 Conduct of Simulator Training.

B.

NUREG 1021 Examiner Standards C.

JTA Listing D.

Probabilistic Risk Assessment E.

Technical Specifications F.

Emergency Plan (ECG)

G.

Alarm Response Procedures (Various)

H.

SH.OP-AS.ZZ-0001 Operations Standards I.

SH.OP-AP.ZZ-0101 Post Transient Response Requirements J.

SH.OP-AP.ZZ-0108 Operability Assessment and Equipment Control Program K.

HC.OP-IO.ZZ-0003 Startup from Cold Shutdown to Rated Power L.

HC.OP-SO.AE-0001, FEEDWATER SYSTEM OPERATION M.

HC.OP-AB.CONT-0002, PRIMARY CONTAINMENT N.

HC.OP-AB.IC-0001 Control Rod O.

HC.OP-AB.IC-0003, Reactor Protection System P.

HC.OP-AR.ZZ-0002, Overhead Annunciator Window Box A2 Q.

HC.OP-AR.ZZ-0011, Overhead Annunciator Window Box C6 R.

HC.OP-AB.ZZ-000 Reactor Scram S.

HC.OP-AB.ZZ-0001 Transient Plant Conditions T.

HC.OP-EO.ZZ-0101 RPV Control U.

HC.OP-EO.ZZ-0103 Reactor Building Control V.

HC.OP-EO.ZZ-0202 Emergency RPV Depressurization W. HC.RE-IO.ZZ-0001 Core Operations Guidelines

NRC-001 REV-01 NRC-001 Page 18 of 22 Rev.: 01 VII.

NRC CRITICAL TASK RATIONAL NRC-001 / 01

1.

Crew INITIATES a manual scram BEFORE RCIC Room Temp reaches 250°F.

K/A 295032 High Secondary Containment Area Temperature EK3.02 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE : Reactor SCRAM.........................................(CFR: 41.5 / 45.6)

RO 3.6/ SRO 3.8 RCIC Room temperature is approaching the Max Safe Operating Temperature. If the temperature in this room approaches its maximum safe operating value, adequate core cooling, containment integrity, safety of personnel, or continued operability of equipment required to perform EOP actions can no longer be assured. EOP-101 must be entered to make certain the reactor is scrammed. Scramming the reactor reduces to decay heat levels the energy that the RPV may be discharging to the reactor building.

2.

Crew actuates five SRVS within two minutes of RCIC room temperature exceeding 250 degrees by Control Room indication (SPDS/CRIDS).

K/A 295032 High Secondary Containment Area Temperature EK3 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK3.01 Emergency/normal depressurization RO 3.5 SRO 3.8 EA2 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EA2.01 Area temperature RO 3.8 SRO 3.8 The steam leak in the HPCI room is now affecting a second area. The reactor must be depressurized to place it in its lowest energy state due to the potential for multiple inoperable safety systems, to reduce the driving head for the leak, and to reject decay heat to the suppression pool rather than the Reactor Building.

The term Crew actuates five SRVs takes into account the F013D failure, which is already inserted. Two minutes is deemed adequate time to recognize the condition and implement EOP-202 and AB.ZZ-0001 Att.

13.
3.

WHEN the PSV-F013D SRV fails to open, THEN before RPV pressure drops below 50 psig, the Crew ensures a fifth SRV is opened to achieve five open SRVs.

K/A 239002 Relief/Safety Valves A4 Ability to manually operate and/or monitor in the control room:

A4.01 SRVs RO 4.4 SRO 4.4 The Minimum Number of SRVs required for Emergency Depressurization (MNSRED) is five. The MNSRED is utilized to assure the RPV will depressurize and remain depressurized when Emergency Depressurization is required. When the PSV-F013D fails to open, the Crew needs to open an additional SRV to achieve MNSRED. This is directed by both EOP-202 and AB.ZZ-0001. SRVs are designed to open with a minimum differential pressure of 50 psid between the reactor vessel and the suppression chamber. Below this d/p, they may not open. If the Crew does not attempt to open the fifth SRV before this minimum d/p is lost, they cannot validate its operation. This would prevent them from detecting the failure and pursuing the use of the Alternate Depressurization Systems in EOP-202.

NRC-001 REV-01 NRC-001 Page 19 of 22 Rev.: 01 NRC-001 / 00 HOPE CREEK NRC - PRA RELATIONSHIPS EVALUATION FORM EVENTS LEADING TO CORE DAMAGE Y/N EVENT Y/N EVENT TRANSIENTS:

SPECIAL INITIATORS:

Turbine Trip Loss of SSW Loss of Feedwater Loss of SACS MSIV Closure Loss of RACS Loss of Condenser Vacuum Loss of Instrument Air Inadvertent Open SRV Loss Of Offsite Power ATWS Station Black Out LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN HPCI Class 1E 120VAC Bus - A Train Y

RCIC Class 1E 120VAC Bus - D Train Y

One SRV EDG A One SSW Pump / Loop EDG B Circulating Water System - 4 pumps TACS OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Y

Manual RPV Emergency Depressurization when required Manual RPV Depressurization during ATWS Initiation of RHR for Decay Heat Removal Initiation of Containment Venting Restore Offsite power within 45 minutes SACS / SSW restoration after total loss of both systems Avoiding Loss of Feedwater during transient Recovery of the Main Condenser Complete this evaluation form for each Exam.

NRC-001 REV-01 NRC-001 Page 20 of 22 Rev.: 01 VIII.

TURNOVER SHEET:

Rx Power: 4%

Rx Pressure: 480 psig (May vary slightly):

Work Week: Any Risk Color: Green SMD: None River Temp: 65 Activities Completed Last Shift:

Achieved Criticality, raised pressure up to 460 psig.

Major Activities Next 12 Hours:

Continue Reactor Startup currently at step 5.3.29 Pull Group 7 rods to position 8 Place Secondary Condensate Pump in service Protected Equipment:

None Tagged Equipment:

1BP116 EHC pump is tagged out for maintenance and will be out of service until a new pressure compensator arrives tomorrow.

NRC-001 Page 21 of 22 Rev.: 01 IX.

SIMULATOR NRC REVIEW/VALIDATION CHECKLIST NRC EXAMINATION SCENARIO GUIDE REVIEW/VALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF-CHECK NRC-001 REVIEWER:

______ 1. The scenario has clearly stated objectives in the scenario.

______ 2. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events.

______ 3. Each event description consists of:

  • The point in the scenario when it is to be initiated
  • The malfunction(s) that are entered to initiate the event
  • The symptoms/cues that will be visible to the crew
  • The expected operator actions (by shift position)

The event termination point

______ 4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

______ 5. The events are valid with regard to physics and thermodynamics.

______ 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

______ 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

______ 8. If time compression techniques are used, scenario summary clearly so indicates.

______ 9. The simulator modeling is not altered.

______ 10. All crew competencies can be evaluated.

______ 11. Appropriate reference materials are available (SOERs, LERs, etc.)

_____ 12. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

______ 13. Proper critical task methodology used IAW NRC procedures.

NRC-001 Page 22 of 22 Rev.: 01 NRC EXAMINATION SCENARIO GUIDE VALIDATION (cont)

NRC Examination Validation:

Rev.

Date Comments Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios. Therefore, to complete this part of the review, the set of scenarios must be available. The section below should be completed once per scenario set.

NRC:

001 NRC:

SELF-CHECK

1.

Total malfunctions inserted: 4-8/10-14

2.

Malfunctions that occur after EOP entry: 1-4/3-6

3.

Abnormal Events: 1-2/2-3

4.

Major Transients: 1-2/2-3

5.

EOPs used beyond primary scram response EOP: 1-3/3-5

6.

EOP Contingency Procedures used: 0-3/1-3

7.

Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8.

EOP run time: 40-70% of scenario run time

9.

Crew Critical Tasks: 2-5/5-8

10. Technical Specifications are exercised during the test
11. Events used in the two scenarios are not repeated
12. The scenario sets for the exam week do not contain duplicate scenarios Comments:

HOPE CREEK ELECTRIC GENERATING STATION NRC INITIAL LICENSED EXAMINATION SCENARIO 2 NOVEMBER 28, 2005 SCENARIO TITLE:

Loss of 10B130/ Electrical ATWS/ Small Break LOCA SCENARIO NUMBER:

NRC-002 EFFECTIVE DATE:

EXPECTED DURATION:

1.0 Hours REVISION NUMBER:

01 PROGRAM:

L.O. REQUAL X

INITIAL LICENSE OTHER REVISION

SUMMARY

New Scenario.

PREPARED BY:

M. L. Brown 9/29/05 NRC Operations Examiner DATE FACILITY REVIEWER:

Nuclear Operations Training Supervisor -

Hope Creek DATE APPROVED BY:

NRC Chief Examiner DATE

NRC-002 REV-01 NRC-002 Page 2 of 20 Rev.: 01 I.

OBJECTIVE(S):

Enabling Objectives A.

The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an CT-X.)

II.

MAJOR EVENTS:

A.

Power increase using Recirc Flow B.

Place 3 RFP in service C.

Inadvertent HPCI initiation D.

10B130 trips causing a loss of B Recirc pump E.

EHC pump filters clog, Electrical ATWS F.

Small Break LOCA G.

RHR pump being placed in Drywell Spray trips III.

SCENARIO

SUMMARY

The plant is operating at 80% power, Middle Of Cycle with SLC Pump AP-208 tagged out for a motor replacement and is expected back within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The Crew will raise power to ~80%

load by raising Recirc Flow. Once load has been increased to ~80% the Crew will place the 3rd RFP pump in service IAW SO.AE-0001.

When the 3rd RFP has been placed in service, HPCI will inadvertently initiate. The crew will respond per AB.RPV-0001, Reactor Power, and terminate HPCI operation. A scram on high flux may occur if HPCI is not terminated. HPCI will be declared Inoperable and Tech Specs addressed.

Once Tech Specs have been addressed, power will be lost to 480 VAC Unit Substation 10B130.

This results in loss of power to the B Recirc Pump MG Set Lube Oil pump and loss of a Turbine Building Chiller. The Standby Lube Oil pump will fail to start and the B Recirc Pumps MG Set will trip. This places the plant in Region 1 - Immediate Exit region of the power to flow map.

Recirculation flow must be increased or control rods must be inserted to exit Region 1. It is expected that the crew will enter AB.RPV-0003 and take the appropriate actions. In addition, loss of the Turbine Building Chiller will require the crew to either restart the chiller or swap to RACS.

Once the crew has stabilized the plant, the EHC discharge filter will clog. The crew will respond to the annunciator and swap EHC pumps after the 2nd pump is started its filter will also clog requiring a manual scram. Manual scram will not work requiring the crew to initiate RRCS.

Shortly after the Rods are inserted, all the turbine bypass valves fail close. As the crew is stabilizing the plant a LOCA occurs causing Drywell pressure to increase. Suppression pool spray will be placed in service, however, Suppression Pool pressure will continue to rise requiring Drywell spray be placed in service. The first RHR pump that is placed in Drywell Spray will trip requiring the operators to swap loops to initiate Drywell spray. The scenario will terminate once Drywell spray has been initiated.

NRC-002 REV-01 NRC-002 Page 3 of 20 Rev.: 01 IV.

INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to IC-5 (~80% power, MOL)

ESTABLISH conditions with 10A rods at 04, Core Flow at 74 mlbm/hr, Rx Power 83.5%

ENSURE A1P128 Recirc MG Oil pump running PLACE A2P128 Recirc MG Oil pump in MAN PLACE CP161 Chilled Water Circ pump in MAN PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description Items required to be set up each time the SG is performed, i.e. tagged equipment, RM11 set points, procedures, etc.

COMPLETE Attachment 2 Simulator Ready-for-Training/Examination Checklist of NC.TQ-DG.ZZ-0002(Z).

EVENT TRIGGERS:

Initial ET # Description 1

EVENT ACTION:

COMMAND:

PURPOSE:

Tunrhp(2) >= 0.5 // B EHC pump running Imf tc16 100 Raises EHC Filter Clogging to 100% severity when B EHC pump is started 2

EVENT ACTION:

COMMAND:

PURPOSE:

Crqnmi <= 30 // Reactor Power <=30%

Fails turbine bypass valves shut after reactor is scrammed 3

EVENT ACTION:

COMMAND:

PURPOSE:

Rhv021(1) >=1.0 && rh:bkr(2) >=1.0 // A RHR Spray wB RHR running Trips A RHR if placed in Drywell Spray while B RHR is still running 4

EVENT ACTION:

COMMAND:

PURPOSE:

Rhv021(2) >=1.0 && rh:bkr(1) >=1.0 // B RHR Spray wA RHR running Trips B RHR if placed in Drywell Spray while A RHR is still running

NRC-002 REV-01 NRC-002 Page 4 of 20 Rev.: 01 MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val AN-C1B1 CRYWOLF ANN C1B1 SLC Pump/Valve O/PF NONE HP11 Inadvertent HPCI Start RT-1 ED12C Loss of 480 VAC Non-essential bus 10B130 RT-2 TC16 EHC pump discharge filter plugging RT-3 0

15 RP04 Failure of RPS to SCRAM (ATWS)

NONE RZ03A RRCS Channel A - Logic A Failure to Actuate NONE RZ03D RRCS Channel B - Logic B Failure to Actuate NONE TC01-10 All turbine bypass valves fail closes 01:00 ET-2 RR31A2 Recirc loop A Large break [V]

10:00 RT-4 2

5 PC04 Downcomer break RT-4 RH04A RHR pump AP202 trip ET-3 RH04B RHR pump BP202 trip ET-4 REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val ET72 SLC Pump A NONE TAGGED TAGGED PP05 OD-3 MFLCPR Fraction Limiting Critical Power Ratio NONE

.861

.801 I/O OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val 3A24 C OVLO A2P120 MANUAL - LUBE OIL PUMP NONE OFF OFF 3A24 D OVLO A2P120 AUTO-LUBE OIL PUMP - A NONE OFF ON 1A136 C OVLO MANUAL-CH W Circ Pump CP161 NONE OFF OFF 1A136 D OVLO AUTO-CH W CIRC Pump CP161 NONE OFF ON 1A136 D OVDI AUTO-CH W CIRC PUMP CP161 00:15 RT-2 OFF ON

NRC-002 REV-01 NRC-002 Page 5 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Raise Power using Recirc Flow After the crew assumes the watch Have Load Dispatcher contact crew to raise power CRS - directs RO/BOP to raise power to 80% load using IOP-0006.

RO monitors plant for proper operation RO refers to HC.OP-SO.BB-0002 regarding MG set critical vibration and flow instability points

  • RO - raises reactor power by increasing Recirc Flow per IOP-0006 at a rate not to exceed 1%/minute RO slowly turns the Recirc pump Master Speed Control potentiometer in the clockwise direction.

RO monitors the following for proper operation Recirc speed increases Recirc loop flow increases Reactor power increases Place the 3rd RFP in service After the Crew has reached 80% load they perform HC.OP-SO.AE-0001 section 5.6.1 (Note - Feedpump should be on recirc)

  • BOP closes HV-1772C, RFPT C Steam Low Pressure supply stop valve below seat drain

NRC-002 REV-01 NRC-002 Page 6 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • BOP opens HV-1751C, RFPT C Low pressure steam isolation valve
  • BOP depresses the SEL push-button as required to select DEMAND on the in-service RFPT(s) whose demand will be matched BOP Presses SEL push-button for the C RFPT to select SPEED CTRLR DMND BOP Presses Increase or decrease buttons as necessary to equalize demand signals while Monitoring:

RFPT Discharge Pressure RFPT DEMAND

  • BOP matches Flow and speed and transfers RFPT C Speed Control to automatic by depressing the A/M push-button and observing A illuminates BOP reports to CRS that 3rd RFP has been placed in service INADVERTENT HPCI INITIATION Once the 3rd RFP has been placed in service OR At the discretion of the Lead Examiner TRIGGER RT-1
  • RO - diagnoses and reports inadvertent HPCI initiation
  • CRS directs entry into AB.RPV-0001
  • RO verifies Reactor level > -38
  • Drywell pressure < 1.68#

NRC-002 REV-01 NRC-002 Page 7 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments RO presses and holds the HPCI TURB TRIP PB RO observes the following close FD-FV-4880 FD-FV-4879 RO adjusts FIC-R600 HPCI Flow controller to 0 gpm RO place FIC-R600 in MANUAL

  • RO - PRESSES FIC-R600 DECREASE Pb for approximately 7 seconds.
  • RO RELEASES the HPCI TURB TRIP PB.
  • RO VERIFIES the FD-FV-4879 remains shut.
  • BOP reduces reactor power with Reactor recirculation flow as necessary to prevent a reactor scram

Determines Action D applies (Verify RCIC OPERABLE and restore HPCI to Operable within 14 days)

  • CRS refers to ECG and determine reportability requirements (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for loss of single train)

NRC-002 REV-01 NRC-002 Page 8 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments 480V Unit Substation 10B130 trips with failure of standby MG Set lube oil pump to start Once Tech Specs have been addressed OR At the discretion of the Lead Examiner TRIGGER RT-2

  • Crew responds to loss of 10B130
  • Observes the following equipment is lost o B Recirc pump o Turbine Building Chiller
  • RO diagnoses the trip of the B Recirc pump
  • CRS direct entry to AB.RPV-0003 section A - Single Recirc Pump Tripped
  • RO - inserts rods to clear APRM Upscale Alarms
  • RO - ENSURE that the Recirc MG Drive Motor Breaker has TRIPPED for the tripped Pump.
  • RO - CLOSES HV-F031B for approximately 5 minutes, THEN RE-OPENS HV-F031A(B).
  • RO - IMPLEMENT the following:

DL.ZZ-0026 Att. 3n (as required)

DL.ZZ-0026 Att. 3v

  • CRS - DIRECTS the Reactor Engineer to develop a Rod Sequence to achieve an 80%

Rod Line.

  • CRS - IMPLEMENT IO-6 Requirements for Single Loop operations.
  • CRS determines region of operation on power/flow map
  • CRS directs actions to exit Region 1

NRC-002 REV-01 NRC-002 Page 9 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • RO either Raises Recirc flow with Recirc pump A or inserts control rods to exit Region 1
  • CRS refers to Tech Spec 3.4.1 and COLR for SLO, determine APLHGR limit and APRM setpoints must be modified within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per IOP-6)
  • CRS contacts I&C to determine cause of failure and to adjust setpoints as required
  • CRS refers to IOP-6 and determines all appropriate actions have been taken in accordance with Section 5.3
  • BOP diagnoses trip of Turbine Building Chiller
  • CRS directs either the Restart of the Turbine building chiller or swapping Turbine Building cooling to RACS
  • BOP restarts Chiller as directed
  • CRS contacts Electrical to investigate cause of trip of 10B130 EHC Filter Clogging After CRS has stabilized the plant OR At the discretion of the Lead Examiner TRIGGER RT-3
  • Crew responds to Annunciator D3-F5, TURB HYDR PUMP TROUBLE
  • BOP diagnoses problem is high delta P across the EHC pump A filter
  • BOP dispatches an NEO to investigate High delta P on pump

NRC-002 REV-01 NRC-002 Page 10 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments 3 minutes after being dispatched the NEO reports back that he see no problem locally with the filters

  • BOP stops EHC pump AP116 Note - Shortly after starting BP116, this filter will also clog requiring a manual scram
  • BOP observes D3F5 clears and then re-annunciates
  • BOP diagnoses problem is now High Delta P on BP116.
  • CRS determines that the plant can no longer be maintained at power and directs that the reactor be manually scrammed Note - Continue to have the filter clog such that the turbine will automatically trip on low EHC pressure within 5 minutes of receiving the High Delta P alarm on the 2nd EHC pump.
  • CRS - directs RRCS to be initiated if not already completed by RO
  • CRS enters EO.ZZ-0101A if rods are not yet inserted CT-1 RRCS is manually actuated within 2 minutes of reaching an Automatic Scram setpoint.
  • RO reports when all rods are inserted

NRC-002 REV-01 NRC-002 Page 11 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Small Break LOCA Once Rods are inserted OR At Lead Examiner Discretion TRIGGER RT-4

  • RO observes RPV level lowering and Drywell pressure rising.
  • CRS enters EO.ZZ-0102 based on high drywell pressure
  • BOP attempts to control drywell pressure < 1.68 psig using
  • Drywell ventilation
  • Containment Atmosphere control
  • CRS directs the BOP to initiate Suppression Chamber Sprays
  • BOP starts suppression pool cooling IAW AB-0001 Attachment 3

Note: Assume the Operator places B RHR in Supp Pool Cooling

  • BOP performs the following:
  • REDUCE B SACS total loop flow so that the following parameters will NOT be exceeded when the EG-HV-2512B is opened in step (2.0)

(establishing flow through the RHR Hx adds 9000 gpm flow to the SACS loop):

Flow >17,000 with one SACS Pump running.

Flow >30,000 with B SACS supplying TACS.

NRC-002 REV-01 NRC-002 Page 12 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • ENSURE EG-HV-2512B is OPEN.
  • ENSURE BP202 RHR PUMP is RUNNING BOP starts the B RHR pump
  • ENSURE the following valves are CLOSED:

A.

HV-F021B.

B.

HV-F016B.

  • IF required, OVERRIDE THEN CLOSE HV-F017B.
  • IF required, PRESS AUTO CL OVRD PB for HV-F024B.
  • THROTTLE OPEN HV-F024B UNTIL Loop B Flow indicates 10,470 gpm.
  • ENSURE HV-F007B closes when flow is >1400 gpm.
  • CLOSE HV-F048A.

MAINTAIN Loop B Flow 10,470 gpm by THROTTLING OPEN/

CLOSE HV-F024B.

  • IF Suppression Chamber Spray is required, THEN PERFORM the following:

A.

PRESS HV F027B AUTO CL OVRD PB.

B.

OPEN HV F027B.

Note: Suppression Chamber Spray is required.

  • CRS determines that Supp.

Chamber Press CANNOT be maintained < 9.5 psig and orders initiation of Drywell Spray

NRC-002 REV-01 NRC-002 Page 13 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments RO shuts down Recirc pumps BOP shuts down Drywell Cooling Fans BOP initiates 1 Loop of Drywell Spray IAW AB-0001 Att. 2 Note: Assume A Drywell Spray is placed in service

  • BOP performs the following actions in AB.ZZ-0001 Att. 2 ENSURE EG-HV-2512A is OPEN.

ENSURE AP202 RHR PUMP is RUNNING.

BOP starts A RHR pump Note: A RHR pump will trip after being started BOP reports A RHR pump tripped and aligns B RHR pump for Drywell Spray BOP removes B RHR pump from Suppression Pool Spray as follows:

  • INITIATE B RHR Drywell Spray as follows:
  • OVERRIDE THEN ENSURE HV-F017B is CLOSED.
  • ENSURE HV-F024B is CLOSED
  • ENSURE HV F027B is CLOSED.
  • OPEN HV-F016B
  • OPEN HV-F021B
  • VERIFY HV-F007B closes when flow is >1400 gpm.
  • CLOSE HV-F048B
  • THROTTLE HV-F003B to maintain Loop B flow at 10,470 gpm.

NRC-002 REV-01 NRC-002 Page 14 of 20 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments CT-2 Crew places Drywell Spray in service before Emergency Depressurization Criteria is reached.

BOP places Drywell Spray in service before Emergency Depressurization Criteria is reached BOP observes that Drywell and Suppression Chamber pressure is lowering CRS determines that Suppression Chamber Pressure can be maintained below the curve SCP-L Termination Requirement:

When the CRS has determined that ED criteria will NOT be reached OR At Lead Examiner Discretion Put the simulator in Freeze Inform the candidates that the simulator is in freeze and to standby for follow questions

NRC-002 REV-01 NRC-002 Page 15 of 20 Rev.: 01 VI.

SCENARIO

REFERENCES:

A.

NC.TQ-DG.ZZ-0002 Conduct of Simulator Training.

B.

NUREG 1021 Examiner Standards C.

JTA Listing D.

Probabilistic Risk Assessment E.

Technical Specifications F.

Emergency Plan (ECG)

G.

Alarm Response Procedures (Various)

H.

SH.OP-AS.ZZ-0001 Operations Standards I.

SH.OP-AP.ZZ-0101 Post Transient Response Requirements J.

SH.OP-AP.ZZ-0108 Operability Assessment and Equipment Control Program K.

HC.OP-IO.ZZ-0003 Startup from Cold Shutdown to Rated Power L.

HC.OP-AB.IC-0003 REACTOR PROTECTION SYSTEM M.

HC.OP-AB.IC-0001 Control Rod N.

HC.OP-AB.ZZ-000 Reactor Scram O.

HC.OP-AB.RPV-0001 Reactor Power P.

HC.OP-EO.ZZ-0101 RPV Control Q.

HC.OP-EO.ZZ-0101A ATWS-RPV Control R.

HC.OP-EO.ZZ-0102 Primary Containment Control S.

HC.OP-EO.ZZ-0202 Emergency RPV Depressurization T.

HC.RE-IO.ZZ-0001 Core Operations Guidelines U.

HC.OP-IO.ZZ-0006, POWER CHANGES DURING OPERATION V.

NRC-002 REV-01 NRC-002 Page 16 of 20 Rev.: 01 VII.

NRC CRITICAL TASK RATIONAL NRC-002 / 00

1.

RRCS is manually actuated within 2 minutes of reaching an Automatic Scram setpoint..

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

EA1.01 Reactor Protection System RO 4.6 SRO 4.6 EA1.03 ARI/RPT/ATWS RO 4.1 SRO 4.1 RPS has failed to scram the reactor both manually, and automatically. Any Automatic RPS setpoint was chosen to ensure there is adequate protection for the fuel during transient analyses associated with coolant inventory decrease events. With the Turbine Stop valves closed and the reactor at power, reactor pressure will rapidly rise to the point where the SRVs lift and discharge into the Suppression Pool. The Suppression Pool is NOT designed to handle heat loads > Decay heat loads. This could cause Suppression Chamber pressure to rise until the Suppression Chamber ruptures. Additionlly, ARI is failed and will not automatically scram the reactor at any Automatic Setpoint. Operator action is required to shutdown the reactor. The need to manually initiate ARI within 2 minutes of reaching any Automatic Setpoint was chosen because it represents an acceptable level of performance considering the time needed to diagnose the RPS failure and the time required to implement the scram hard card.

2.

Crew places Drywell Spray in service before Emergency Depressurization Criteria is reached.

K/A 295024 High Drywell Pressure EA2 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

EA2.04 Suppression chamber pressure RO 3.9 SRO 3.9 K/A 223001 Primary Containment Systems and Auxiliaries A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions of operations:

A2.02 Steam bypass of the suppressions pool RO 3.9 SRO 4.1 If suppression chamber pressure cannot be maintained below the pressure suppression pressure, EOPs direct actions to emergency depressurize the reactor. Drywell Spray initiation will prevent an unnecessary challenge to the Suppression Chamber and prevent a severe transient to the RPV that emergency depressurization will cause.

NRC-002 REV-01 NRC-002 Page 17 of 20 Rev.: 01 NRC-002 / 00 HOPE CREEK NRC - PRA RELATIONSHIPS EVALUATION FORM EVENTS LEADING TO CORE DAMAGE Y/N EVENT Y/N EVENT TRANSIENTS:

SPECIAL INITIATORS:

Y Turbine Trip Loss of SSW Loss of Feedwater Loss of SACS MSIV Closure Loss of RACS Loss of Condenser Vacuum Loss of Instrument Air Inadvertent Open SRV Loss Of Offsite Power Y

ATWS Station Black Out Y

LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN HPCI Class 1E 120VAC Bus - A Train RCIC Class 1E 120VAC Bus - D Train One SRV EDG A One SSW Pump / Loop EDG B Circulating Water System - 4 pumps TACS OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Y

Manual RPV Emergency Depressurization when required Manual RPV Depressurization during ATWS Y

Initiation of RHR for Decay Heat Removal Initiation of Containment Venting Restore Offsite power within 45 minutes SACS / SSW restoration after total loss of both systems Avoiding Loss of Feedwater during transient Recovery of the Main Condenser Complete this evaluation form for each Examination.

NRC-002 REV-01 NRC-002 Page 18 of 20 Rev.: 01 VIII.

TURNOVER SHEET:

Rx Power: ~83%

MWe: (May vary slightly):

Work Week: Any Risk Color: Green SMD: None River Temp: 65 Activities Completed Last Shift:

Lowered Power to 80% and performed a rod sequence change Removed the C RFP from service for a balance shot, completed balance shot and in process of returning C RFP to service (currently running in Recirc)

Major Activities Next 12 Hours:

Raise load to ~80% and put the 3rd RFP in service.

Raise power to 100%

Protected Equipment:

None Tagged Equipment:

SLC Pump AP-208 is tagged out for pump rebuild and is expected back within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> No other equipment is Out of Service

NRC-002 Page 19 of 20 Rev.: 01 IX.

SIMULATOR NRC REVIEW/VALIDATION CHECKLIST NRC EXAMINATION SCENARIO GUIDE REVIEW/VALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF-CHECK NRC-002 REVIEWER:

______ 1. The scenario has clearly stated objectives in the scenario.

______ 2. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events.

______ 3. Each event description consists of:

The point in the scenario when it is to be initiated The malfunction(s) that are entered to initiate the event The symptoms/cues that will be visible to the crew The expected operator actions (by shift position)

The event termination point

______ 4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

______ 5. The events are valid with regard to physics and thermodynamics.

______ 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

______ 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

______ 8. If time compression techniques are used, scenario summary clearly so indicates.

______ 9. The simulator modeling is not altered.

______ 10. All crew competencies can be evaluated.

______ 11. Appropriate reference materials are available (SOERs, LERs, etc.)

_____ 12. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

______ 13. Proper critical task methodology used IAW NRC procedures.

NRC-002 Page 20 of 20 Rev.: 01 NRC EXAMINATION SCENARIO GUIDE VALIDATION (cont)

NRC Examination Validation:

Rev.

Date Comments Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios. Therefore, to complete this part of the review, the set of scenarios must be available. The section below should be completed once per scenario set.

NRC:

002 NRC:

SELF-CHECK

1.

Total malfunctions inserted: 4-8/10-14

2.

Malfunctions that occur after EOP entry: 1-4/3-6

3.

Abnormal Events: 1-2/2-3

4.

Major Transients: 1-2/2-3

5.

EOPs used beyond primary scram response EOP: 1-3/3-5

6.

EOP Contingency Procedures used: 0-3/1-3

7.

Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8.

EOP run time: 40-70% of scenario run time

9.

Crew Critical Tasks: 2-5/5-8

10. Technical Specifications are exercised during the test
11. Events used in the two scenarios are not repeated
12. The scenario sets for the exam week do not contain duplicate scenarios Comments:

HOPE CREEK ELECTRIC GENERATING STATION NRC INITIAL LICENSED EXAMINATION SCENARIO 3 NOVEMBER 28, 2005 SCENARIO TITLE:

APRM Failure/ Recirc Pump Hi Vibs/ LOP SCENARIO NUMBER:

NRC-003 EFFECTIVE DATE:

EXPECTED DURATION:

1.0 Hours REVISION NUMBER:

1 PROGRAM:

L.O. REQUAL X

INITIAL LICENSE OTHER REVISION

SUMMARY

New Scenario.

PREPARED BY:

M. L. Brown 9/29/05 NRC Operations Examiner DATE FACILITY REVIEWER:

Nuclear Operations Training Supervisor -

Hope Creek DATE APPROVED BY:

NRC Chief Examiner DATE

NRC-003 REV-01 NRC-003 Page 2 of 17 Rev.: 01 I.

OBJECTIVE(S):

Enabling Objectives A.

The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an CT-x.)

II.

MAJOR EVENTS:

A.

Core Spray Pump test B.

Raise Power if desired C.

A APRM Fails D.

Turbine Bldg. Chillers trip E.

B Recirculation Pump High Vibration F.

Loss of Offsite Power G.

A EDG fails to start H.

B RHR pump trips III.

SCENARIO

SUMMARY

The plant is operating at 80% power, Middle Of Cycle returning to power after a mini-outage.

The Operators are at Step 5.4.29 of IOP-3, with the 3rd RFP having just been started on the previous shift. The OPRM System is INOPERABLE due to an existing 10CFR21 issue. The OPRM System is still functional but is considered INOPERABLE per Technical Specifications.

Core Spray Loop A operability PT will be performed. When the test return valve is opened, the pump will trip. Core Spray A should be declared Inoperable.

After declaring the A Core Spray pump inoperable and addressing tech specs, the Load Dispatcher will call and have the crew raise power. While raising power the A APRM fails causing the crew to enter Abnormal Procedure HC.OP-AB.IC-0004,NEUTRON MONITORING and bypass the APRM.

After the APRM is bypassed, the Turbine Building chillers will trip requiring the operators to swap cooling over to RACS, in addition Drywell pressure will rise to > 0.75 psig. The operators will enter AB.CONT-0001, Drywell Pressure to address the high drywell pressure. When pressure rises to > 0.75 psig, Operators will vent drywell. Once preparations are underway to vent the drywell, B Recirc pump vibrations will increase causing the operators to enter AB.RPV-0003, Recirculation system. Operators will reduce recirc pump speed in an attempt to clear the vibration alarm. Vibration will continue to increase and cause the operators to trip the B Recirc pump on high vibration. After tripping the Recirc pump the operators will have to scram the reactor due to being in Region 1 with OPRMs inop. When the operators have stabilized the plant after the scram a loss of offsite power occurs. The A EDG will fail to start and the B RHR pump will trip. With HPCI running the Operators will forced to start the A EDG to place A RHR in suppression pool cooling. The scenario will end once the operators have restarted the A EDG and place A RHR in Suppression Pool cooling.

NRC-003 REV-01 NRC-003 Page 3 of 17 Rev.: 01 IV.

INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to IC-5 (~80% power, MOL)

PLACE the 3rd RFP in service MAKEUP N2 to the drywell until drywell and Suppression Chamber pressure are 0.53-0.57 psig ENSURE BOTH Steam Tunnel unit coolers are in service C/T CP161 TB Chilled water circ pump as follows ENSURE CP161 is not in service PLACE CP161 in MAN C/T DK111 as follows:

ENSURE DK111 is not in service PRESS DK111 STOP pushbutton ENSURE HV-9503D is CLOSED PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description Items required to be set up each time the SG is performed, i.e. tagged equipment, RM11 set points, procedures, etc.

COMPLETE Attachment 2 Simulator Ready-for-Training/Examination Checklist of NC.TQ-DG.ZZ-0002(Z).

PLACE Red bezel cover on DK111 PLACE Red bezel cover on HV-9503D PLACE Red bezel cover on CP161 EVENT TRIGGERS:

Initial ET # Description 1

EVENT ACTION:

COMMAND:

PURPOSE:

Hp:copmp>=1.0 Trip HPCI Aux Oil Pump on start 2

EVENT ACTION:

COMMAND:

PURPOSE:

3 EVENT ACTION:

COMMAND:

PURPOSE:

NRC-003 REV-01 NRC-003 Page 4 of 17 Rev.: 01 MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val AN-E5F1 OHA E5-F1 CHILLED WATER TRBL NONE CS01A Core Spray pump A trip RT-1 NM21A APRM Channel A reads high or low RT-2 0

100 CW18A AP161 Chilled Water Circ pump Trip RT-3 CW18B BP161 Chilled Water Circ pump trip 5 sec RT-3 RR26B2 Recirc Pump BP201 elevated vibration 12:00 RT-4 0

12 EG12 Loss of all off site power RT-5 DG07A Diesel Generator A emergency start NONE RH04B RHR pump BP202 trip NONE REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val HV12 Steam Tunnel unit cooler BVH216 NONE RUN RUN HP08 HPCI Aux Oil Pump ET-1 UNTAGGED TAGGED I/O OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val 1A181 A2 LO DK111 INOP light NONE ON 1A181 D DI DK111 START pb NONE OFF 1A181 E1 DI DK111 SAFETY CKT pb NONE OFF 1A181 F LO DK111 STOP light NONE OFF 1A182 E DI HV-9503D OPEN pb NONE OFF 1A182 F LO HV-9503D CLOSE light NONE OFF 1A136 A2 LO CP161 INOP light NONE ON 1A136 D DI CP161 AUTO pb NONE OFF 1A136 E DI CP161 START pb NONE OFF 1A136 F LO CP161 STOP light NONE OFF

NRC-003 REV-01 NRC-003 Page 5 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Crew assumes the watch and starts performing HC.OP-ST.BE-0002 TRIGGER RT-1

  • BOP Ensures pump suction valve (HV-F001A) is Open
  • BOP Sends an NEO to pump to check pump out prior to start
  • BOP Starts A Core Spray Pump while monitoring pump discharge pressure and confirms discharge pressure rises to > 300 psig in less than or equal to 5.0 seconds
  • BOP ensures the following:
  • BOP - Throttles open Core Spray Full Flow Test Byp Valve, HV-F015A to obtain > 4625 gpm flow.
  • BOP sends an NEO out to determine cause of trip
  • CRS refers to Tech Specs and determines Tech Spec 3.5.1 and determines that Action A (7 day LCO) applies

NRC-003 REV-01 NRC-003 Page 6 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Power Increase Once Core Spray has been returned to a standby alignment and Tech Spec call has been made OR At the discretion of the Lead Examiner (Note: this step may be bypassed if the crew does not need a Normal Reactivity change)

Have Load Dispatcher contact crew to raise power

  • CRS directs RO/BOP to coordinate Power increase to 90% at < 1%/minute using IOP-0003
  • RO/BOP coordinate raising power
  • RO slowly increases Recirc pump speed
  • BOP monitors RFP speed to ensure proper response A APRM Fails After Power has been raised 5%

OR At the discretion of the Lead Examiner TRIGGER RT-2

  • RO diagnoses and reports A APRM has failed UPSCALE Note: Should get a Half scram CRS acknowledges report and enters HC.IO-AB.IC-0004, Neutron Monitoring RO stops all Control Rod Withdrawals Note: Should not be any control rod withdrawals in progress RO bypasses the A APRM RO ensures all RPS trip conditions are clear

NRC-003 REV-01 NRC-003 Page 7 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

  • RO turns the A RPS Trip logic key to reset and returns it to the normal position
  • RO verifies that RPS is reset

only required to have 2 OPERABLE TURBINE BLDG CHILLERS TRIP Once the CRS has addressed Tech Specs OR At the discretion of the Lead Examiner TRIGGER RT-2 BOP diagnoses/ observes that the Turbine Building Chillers have tripped

  • RO/BOP observe Drywell temperature/ pressure rising
  • CRS directs entry into AB.CONT-0001, Drywell Pressure Section C

BOP performs the following:

  • ALIGN RACS to the Chill Water System for Drywell Cooling as follows
  • CLOSE HV-9532-1 AND HV-9532-2.

/RTN OPEN RACS PB.

  • PRESS LOOP B SPLY/RTN OPEN RACS PB.

NRC-003 REV-01 NRC-003 Page 8 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments BOP Observes:

  • HV-9530A1/A3 CLOSED
  • HV-9530B1/B3 CLOSED
  • HV-9530A2/A4 OPEN
  • HV-9530B2/B4 OPEN BOP OPENS HV-9532-1 AND HV-9532-2.
  • IF Drywell Pressure > 0.75 psig, THEN CRS enters Section D -

Drywell Pressure > 0.75psig AND No Evidence of Elevated Coolant System Leakage Note - Crew may enter this section but it is not necessary for them to start the Drywell vent prior to moving on with the scenario B Recirc Pump High Vibration Once Drywell vent actions have been initiated OR At the discretion of the Lead Examiner TRIGGER RT-3 RO diagnoses/ observes rising B Recirc pump vibration CRS directs entry into AB.RPV-0003, Recirculation System Section K

RO PRIOR to reducing Recirc Pump Speed, PERFORM the following:

  • ENSURE the following controllers are in MANUAL o SIC-R621A PUMP A SPD CONT o SIC-R621B PUMP B SPD CONT RO RECORD affected pump speed:

o B Recirc Initial Pump Speed

NRC-003 REV-01 NRC-003 Page 9 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments RO MAINTAIN the affected Pump ALERT limit [REFER to Table 2]

clear as follows:

  • INTERMITTENTLY PRESS SIC-R621A(B) PUMP A(B)

SPD CONT DECREASE push button on the affected Recirculation Pump.

  • INSERT Control Rods as required by Reactor Engineering Instructions.
  • RO IF ALERT limit cannot be maintained clear {REFER to Table 2] AND the affected Recirculation Pump Speed has been lowered by >20%

(below the value logged in Step K.1.B), THEN REMOVE the affected Recirc Pump from service IAW HC.OP-SO.BB-0002, Single Loop Operation.

CT-1 Crew removes Recirc Pump from service within 2 minutes of reaching the Danger Setpoint RO removes pump from service IAW SO.BB-0002 RO performs the following:

If Danger Limit is Reached on Recirc Pump then

  • TRIP the affected Recirc Pump
  • Enter Condition A CRS - IMPLEMENT IO-6 requirements for Single Loop operations.

CRS determines region of operation on power/flow map

NRC-003 REV-01 NRC-003 Page 10 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Crew determines plant is in Region 1 of Power/Flow map and OPRMs are INOP.

CRS directs a Manual Reactor Scram IAW IOP-6 step 3.1.12 CT-2 Crew Manually Scrams the reactor within 3 minutes of entering Region 1 with the OPRMs INOP RO manually scrams reactor RO performs actions of AB.ZZ-0001 Crew stabilizes the plant using AB.ZZ-0000 RO locks Mode Switch in Shutdown RO verifies the Scram RO inserts SRMs and IRMs AND selects IRMs on the Recorders BOP verifies H2 injection system tripped BOP Trips the Main turbine and verifies Generator lockout is 0 Mwe RO maintains level between +12.5 and 54 RO starts RCIC LOSS OF OFFSITE POWER After Crew has stabilized the plant in AB.ZZ-0000 OR At the discretion of the Lead Examiner TRIGGER RT-4

NRC-003 REV-01 NRC-003 Page 11 of 17 Rev.: 01 V.

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments CRS directs that HPCI be placed in service for pressure control.

BOP attempts to place HPCI inservice BOP reports that HPCI has tripped.

CRS directs that RPV pressure be maintained using SRVs and RCIC.

CT-3 Crew places Suppression Pool Cooling in service prior to Suppression Pool temp.

exceeding 95°F RO places RHR Loop A in Suppression Pool cooling Termination Requirement:

When RO has placed RHR train A in Suppression Pool Cooling OR At Lead Examiner Discretion Put the simulator in Freeze Inform the candidates that the simulator is in freeze and to standby for follow questions At Lead Examiner Discretion Have the CRS classify the event

NRC-003 REV-01 NRC-003 Page 12 of 17 Rev.: 01 VI.

SCENARIO

REFERENCES:

A.

NC.TQ-DG.ZZ-0002 Conduct of Simulator Training.

B.

NUREG 1021 Examiner Standards C.

JTA Listing D.

Probabilistic Risk Assessment E.

Technical Specifications F.

Emergency Plan (ECG)

G.

Alarm Response Procedures (Various)

H.

SH.OP-AS.ZZ-0001 Operations Standards I.

SH.OP-AP.ZZ-0101 Post Transient Response Requirements J.

SH.OP-AP.ZZ-0108 Operability Assessment and Equipment Control Program K.

HC.OP-IO.ZZ-0003 Startup from Cold Shutdown to Rated Power L.

HC.OP-AB.IC-0003 REACTOR PROTECTION SYSTEM M.

HC.OP-AB.IC-0001 Control Rod N.

HC.OP-AB.ZZ-000 Reactor Scram O.

HC.OP-AB.RPV-0001 Reactor Power P.

HC.OP-EO.ZZ-0101 RPV Control Q.

HC.OP-EO.ZZ-0101A ATWS-RPV Control R.

HC.OP-EO.ZZ-0102 Primary Containment Control S.

HC.OP-EO.ZZ-0202 Emergency RPV Depressurization T.

HC.RE-IO.ZZ-0001 Core Operations Guidelines U.

HC.OP-IO.ZZ-0006, POWER CHANGES DURING OPERATION V.

NRC-003 REV-01 NRC-003 Page 13 of 17 Rev.: 01 VII.

NRC CRITICAL TASK RATIONAL NRC-003 / 00

1.

CREW secures B Reactor Recirc pump within two minutes of Vibration reaching the DANGER limit IAW guidance in AB.RPV-0003..

K/A 202001 Recirculation System A2 Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.17 Loss of seal cooling water RO 3.1 SRO 3.2 This action is listed as a Retainment Override in the Abnormal Procedure, a time limit of 2 minutes is deemed adequate for the operator to recognize the condition and take the appropriate action.. The basis of this action is to prevent pump damage and potential piping damage due to vibration. Damage to the pump casing is a degradation of a Reactor Coolant System boundary.

2.

Crew Manually Scrams the reactor within 3 minutes of entering Region 1 with the OPRMs INOP K/A 295006 SCRAM AA1 Ability to operate and/or monitor the following as they apply to SCRAM :

AA1.05 Neutron monitoring system.............................

RO 4.2 SRO 4.2 HC.OP-IO.ZZ-0006 precaution 3.1.12 states that IF the OPRMs are INOPERABLE IF Region 1 is entered, THEN MANUALLY SCRAM the reactor Failure to manually scram the reactor when in the Power instability region results in a significant reduction in the safety margin beyond that irreparably introduced by the scenario.

Crew places Suppression Pool Cooling in service prior to Suppression Pool temp.

exceeding 95°F K/A 295013 High Suppression Pool Temperature AA1. Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE AA1.01 Suppression pool cooling..............................RO 3.9 SRO 3.9 AA1.02 Systems that add heat to the suppression pool......... RO 3.9 SRO 3.9 A Loss of Offsite Power has occurred, the only method of pressure control available to the Crew is to dump heat to the Suppression Pool. Failure to maintain Suppression Pool Temperature will result in a significant reduction in the safety margin beyond that irreparably introduced by the scenario.

NRC-003 REV-01 NRC-003 Page 14 of 17 Rev.: 01 NRC-002 / 00 HOPE CREEK NRC - PRA RELATIONSHIPS EVALUATION FORM EVENTS LEADING TO CORE DAMAGE Y/N EVENT Y/N EVENT TRANSIENTS:

SPECIAL INITIATORS:

Turbine Trip Loss of SSW Loss of Feedwater Loss of SACS MSIV Closure Loss of RACS Loss of Condenser Vacuum Loss of Instrument Air Inadvertent Open SRV Y

Loss Of Offsite Power ATWS Station Black Out LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN Y

HPCI Class 1E 120VAC Bus - A Train RCIC Class 1E 120VAC Bus - D Train One SRV Y

EDG A One SSW Pump / Loop EDG B Circulating Water System - 4 pumps TACS OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Manual RPV Emergency Depressurization when required Manual RPV Depressurization during ATWS Y

Initiation of RHR for Decay Heat Removal Initiation of Containment Venting Restore Offsite power within 45 minutes SACS / SSW restoration after total loss of both systems Avoiding Loss of Feedwater during transient Recovery of the Main Condenser Complete this evaluation form for each Examination.

NRC-003 REV-01 NRC-003 Page 15 of 17 Rev.: 01 VIII.

TURNOVER SHEET:

Rx Power: 80%

MWe: (May vary slightly):

Work Week: Any Risk Color: Green SMD: None River Temp: 65 Activities Completed Last Shift:

Power lowered to 80% and Control Rod Sequence Exchange performed Major Activities Next 12 Hours:

Maintain power at 80% until contacted by the Load Dispatcher, then return to 100% power Complete HC.OP-ST.BE-0002, Core Spray Pump Loop A Full Flow Test. Currently in progress and completed up to step 5.23 (pump testing).

Protected Equipment:

None Tagged Equipment:

OPRM System is INOPERABLE due to an existing 10CFR21 issue. The OPRM System is still functional but is considered INOPERABLE per Technical Specifications.

No other equipment is Out of Service

NRC-003 Page 16 of 17 Rev.: 01 IX.

SIMULATOR NRC REVIEW/VALIDATION CHECKLIST NRC EXAMINATION SCENARIO GUIDE REVIEW/VALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF-CHECK NRC-002 REVIEWER:

______ 1. The scenario has clearly stated objectives in the scenario.

______ 2. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events.

______ 3. Each event description consists of:

  • The point in the scenario when it is to be initiated
  • The malfunction(s) that are entered to initiate the event
  • The symptoms/cues that will be visible to the crew
  • The expected operator actions (by shift position)

The event termination point

______ 4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

______ 5. The events are valid with regard to physics and thermodynamics.

______ 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

______ 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

______ 8. If time compression techniques are used, scenario summary clearly so indicates.

______ 9. The simulator modeling is not altered.

______ 10. All crew competencies can be evaluated.

______ 11. Appropriate reference materials are available (SOERs, LERs, etc.)

_____ 12. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

______ 13. Proper critical task methodology used IAW NRC procedures.

NRC-003 Page 17 of 17 Rev.: 01 NRC EXAMINATION SCENARIO GUIDE VALIDATION (cont)

NRC Examination Validation:

Rev.

Date Comments Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios. Therefore, to complete this part of the review, the set of scenarios must be available. The section below should be completed once per scenario set.

NRC:

002 NRC:

SELF-CHECK

1.

Total malfunctions inserted: 4-8/10-14

2.

Malfunctions that occur after EOP entry: 1-4/3-6

3.

Abnormal Events: 1-2/2-3

4.

Major Transients: 1-2/2-3

5.

EOPs used beyond primary scram response EOP: 1-3/3-5

6.

EOP Contingency Procedures used: 0-3/1-3

7.

Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8.

EOP run time: 40-70% of scenario run time

9.

Crew Critical Tasks: 2-5/5-8

10. Technical Specifications are exercised during the test
11. Events used in the two scenarios are not repeated
12. The scenario sets for the exam week do not contain duplicate scenarios Comments:
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