ML090360438

Draft - Operating Exam (Folder 2)

ML090360438
Person / Time
Site:	Hope Creek
Issue date:	01/04/2009
From:	Public Service Enterprise Group
To:	D'Antonio J M Operations Branch I
Hansell S
Shared Package
ML082600269	List: IR 05000354/2009301 ML090270205 ML090360400 ML090360406 ML090360415 ML090360438 ML090680623 ML090720629 ML090720842 ML090720939 ML091140106 ML091310431
References
50-354/09-301, TAC U01693 50-354/09-301
Download: ML090360438 (405)

Text

{{#Wiki_filter:SCENARIO TITLE: NRC SCENARIO 1 SCENARIO NUMBER: ESG-N RC-S 1 EFFECTIVE DATE: Effective when approved. EXPECTED DURATION: 80 minutes REVISION NUMBER: 02 PROGRAM: -1 L.O. REQUAL rl INITIAL LICENSE OTHER REVISION

SUMMARY

1. Added MSL RMS Channel A failure for CRS TS entry.

2. Added MALF AN-D3E3 CRYWOLF ANN D3E3 120VAC UPS TROUBLEfrom validation comments 3. Modified PC06 to ramp leak from 10 to 50% over 8 minutes from validation comments. This is consistent with ESG-005 rates. 4. Validation time 80 minutes. Archie E. Faulkner 12/5/2008 PREPARED BY: DATE Instructor APPROVED BY: DATE APPROVED BY: -Operations Director or Designee SCENARIO TITLE: NRC SCENARIO I SCENARIO NUMBER:

ESG-NRC-SI EFFECTIVE DATE: Effective when approved. EXPECTED DURATION: 80 minutes REVISION NUMBER: 02 PROGRAM: -1 L.O. REQUAL TI INITIAL LICENSE -1 OTHER ~ REVISION

SUMMARY

1. Added MSL RMS Channel A failure for CRS TS entry. 2. Added MALF AN-D3E3 CRYWOLF ANN D3E3 120VAC UPS TROUBLE from validation comments

3. Modified PC06 to ramp leak from 10 to 50% over 8 minutes from validation comments. This is consistent with ESG-005 rates. 4. Validation time 80 minutes. -- PREPARED BY: Archie E. Faulkner 12/5/2008 Instructor DATE APPROVED BY: - .- Operations Training Manager or Designee DATE APPROVED BY: - Operations Director or Designee DATE Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safelb operate the plant during normal, abnormal, and emergency plant conditions. (Critical tasks within this examination scenario guide are identified with an 'I *.") II. MAJOR EVENTS: - A. B. C. D. E. F. G. H. I. Raise Reactor Power with Control Rods lnerting the Containment Stuck Control Rod Main Steam Line RMS failure Loss of 1 AD482 inverter Steam leak in the steam tunnel Small break LOCA/

RHR pump room flooding/ (Failure to isolate) Emergency Depressurization/ SRV Failure to open 111. SCENARIO

SUMMARY

- The scenario starts with the plant at approximately 4% power at rated pressure.

The crew will withdraw Control Rods to 8% power in preparation to place the reactor Mode Switch to Run. The crew will commence inerting the drywell. During the rod withdrawal, a rod will stick. The crew's efforts to unstick the rod will be successful. After the reactivity manipulation and containment inerting are complete, "A" Main Steam Line Rad Monitor will fail upscale resulting in a Tech Spsc entry. The 1A-D-482 inverter will develop a fault resulting in TACS isolation requiring restoration, and loss of various indications. Once TACS has been restored, the plant will develop a steam leak in the steam tunnel requiring the unit to be shutdown and the crew to close the Main Steam Isolation Valves. A LOCA will develop after closing the MSIVs. When RHR Pump D is started, a Suppression Pool leak develops on the suction piping to the pump. Attempts to isolate the leak and to makeup wrll be unsuccessful, requiring an Emergency Depressurization of the RPV (Critical Task). An SRV will fail to open when required and the crew will be required to open an additional SRV (Critical Task). The scenario will be terminated when the reactor is depressurized and level is above - 185 inches. ESG-NRC-S 1 Page 2 of 27 Re:!: 02 I c. - w lnifial Initial INITIALIZE the simulator to IC-94; 4% power, MOC. Pull step 259 INSERT control rods through step 234. Description INITIAL 1O.ZZ-0003 Section 5.3 up to and including step 5.3.39. INITIAL SO.GS-0001 Section 5.1 up to and including step 5.1.8. MARKUP OP-HC-103-105 Forms 1 and 2 to support inerting containment. ENSURE Data Collection is trending the following parameters: 3 DEINERT containment to >4% 02. Secure lineup, but leave H202 analyzers in service. ENSURE lineup to inert containment is up to 5.1.8 of HC.OP-SO.GS-0001. ~~ 0 PREP FOR TRAINING (i.e., RMI I set points, procedures, bezel covers) I I '1 ~~~~ ~ 0 W/R Reactor Pressure 0 Fuel Zone RPV Level ~~~ rr Reactor Dower I WIR Reactor Water Level I ~~ ~~ ~ COMPLETE the Simulator Ready for Training/Examination Checklist. PRE-BRIEF the crew for the power change and Containment lnerting ESG-N RC-S 1 Page 3 of 27 Reti: 02 EVt ET # - 1 5 IT TRIGGERS: -. - Description EVENT ACTION COMMAND PURPOSE EVENT ACTION COMMAND PURPOSE EVENT ACTION COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: LCPNEPOI >= 300 DMF CD033843 Deletes malfunction when drive pressure is 300 psig - ZLMS20A CLOSED light for A MSlV __ ZLRHPMR(4) IMF RH07D Inserts flooding malfunction when RHR D pump is running __ ZDRHFOC(20) HV-F004D Switch to CLOSE - ZDCWZPDM >= 1 .O D SACS Pump MAN PB - ZDCWZPDA >= 1 .O DMF CW15D D SACS Pump AUTO PB - ZDCWZPDS >= 1 .O D SACS Pump START PB - ESG-NRC-SI Page 4 of 27 Re,: 02 1 lnitial Description CD033843 Control Rod 38-43 stuck ADO2EC ADSlRelief valve FOI 3E sticks closed RM9509 Main Steam Line Channel A Radiation Monitor fails upscale ED09A2 Loss of 12OVAC Class 1 E lnstr bus 1 AD482 AN-D3E3 CRYWOLF ANN D3E3 120VAC UPS TROUBLE CWl5D D SACS Pump Process Auto Start Fail MS04A Steam line A leak in tunnel I RR31A2 Recirc Loop A large break I lnitial RR3182 Recirc loop B large break RHO'ID RHR leak via pump D suction Description Delay 5A31 C OVLO DP210 MAN-LOOP B Pumps- Pump --- Pump --- 5A31 D OVLO DP210 AUTO-LOOP B PUMPS- PC06 Suppression Pool Break ri -1 REMOTE/FIELD FUNCTION

SUMMARY

I I I 7 lnitial Description Delay Ramp --- --- ET-7 --- RH21D HV-F004 RHR pump D suction valve 1/0 OVERRIDE

SUMMARY

I Tri er q-f I I I I ESG-NRC-SI Page 5 of 27 REX 02 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - Event I Instructor Activity Expected PlantlStudent Response Comments Raise Reactor Power with Control Rods: NOTE: LPRM downscale 0 alarms can be expected.

As RE, inform crew alarms are expected for this rod pattern. NOTE: Operator may single 0 notch withdraw the rods, as necessary, in which case the CONTINUOUS WITHDRAW PB is NOT used. 0 CRS directs the RO to raise Reactor power with Control Rods in accordance with RE guidance. RO withdraws Control Rods in accordance with HC. OP-S0.S F- 0001 and CRS directions. =, Selected rod PB comes ON (bright white). FOUR ROD DISPLAY indicates the control rod position (1 OC650C). The associated Full Core Display (white) numbered rod identification light comes ON (1 OC650C). At the ROD SELECT MODULE, simultaneously press and hold both the WITHDRAW PB AND the CONTINUOUS WITHDRAW PB and observe the following: The INSERT (white) light comes ON momentarily. The WITHDRAW (white) light comes ON and the CONTINUOUS WITHDRAW (white) light comes ON. FOUR ROD DISPLAY indicates control rod movement. Prior to reaching the desired control rod position, simultaneously release both the WITHDRAW PB and the CONTINUOUS WITHDRAW PB and OBSERVE the following: The WITHDRAW (white) light goes OUT. z CONTROL ROD POSITION z CONTROL ROD POSITION HPI USED: STAR PEER CHECK OP BARRIERS ESG-NRC-SI Page 6 of 27 Rev: 02 I Event I Instructor Activity Expected PlantEtudent Response Cam men ts = The SETTLE (white) light comes ON for =. 6 seconds, then goes out. FOUR ROD DISPLAY indicates the control rod has settled to the desired position. =, At position 48 the applicable Full Core Display FULL OUT (red) light comes on. Perform a control rod coupling integrity check IAW HC.OP- 3 CONTROL ROD POSITION ST.BF-0001. 0 Perform the following while giving HPI USED: the selected Control Rod a continuous wit hd raw signal : Observe the following as indication of the Control Rod being coupled: I. ROD OVERTRAVEL alarm does NOT annunciate.

2. Red Full Out light illuminates on the Full Core Display. 3. RPIS indicates the Control Rod is full out (48). 4. Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. STAR PEER CHECK OP BARRIERS Indicates the completion of the movement on the Pull Listing.

RO determines that Control Rod 38-43 is stuck by observing no change in Rod motion on the 4 Rod Display or the RWM and informs the CRS. CRS directs actions in accordance with H C . OP-AB . IC- 0001 : Condition I. Stuck Control Rod 38-43: Preinserted. ESG-NRC-S I Page 7 of 27 Rev: 02 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - I Event / Instructor Activity Expected PlantlStudent Response Comments NOTE: Crew may request RE guidance. Respond that a withdraw signal then an insert signal may be attempted. ENSURE ET-I triggers when drive water pressure dp >300 psid. This deletes stuck rod malfunction. RO performs actions in accordance with CRS directions: Verifies no Rod Blocks are HPI USED: STAR 0 PEER CHECK CI present. OP BARRIERS Attempts to operate the drive in both directions to determine the exact condition of the Control Rod. Verifies drive water flow fluctuates normally. Verifies proper operation of the SETTL.E, INSERT, AND WITHDRAW lights. Performs the following: Raises the drive water pressure in approximately 50 psid increments, not to exceed 500 psid. a Attempts to notch in notch out the Control Rod at the new pressure increment. RO observes Rod Movement as indicated on the 4 Rod Display or RWM, and notifies the CRS. RO returns the drive water pressure to the normal operating range (260-270 psid on A301 5). CRS directs the PO to inert the containment in accordance with HC.OP-SO.GS-000 1 starting at 5.1.8. ESG-NRC-S1 Page 8 of 27 Re%(: 02 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE .- I Event / Instructor Activity Expected PlantEtudent Response Comments 0 PO commences inerting the containment in accordance with CRS directions by: 0 Opening the following valves: HV-4978 = HV-5035 a P-KH-V9973, Liquid N2 To Vaporizer (local) 3 GU-HD-9372A 3 HV-4958 3 HV-4952 3 HV-4950 Establishes communications between the Main Control Room AND an operator stationed at Tl-3955. a Log start time on Gaseous Effluent Release Permit a Presses the FV-4971 ON push-button. Presses the FIC-4971, N2 FLOW, AUTO push-button. 0 Intermittently presses FIC-4971 attain the desired nitrogen flow rate as indicated on FR-4971-1, N2 RAISE SETPOINT PB to N2 FLOW (UP to 150,000 scfh). Main Steam Line RMS "A" Fails Upscale: TRIGGER ET-2 when Control Rods have been withdrawn, containment inerting is in progress, or at the Lead Zxaminer's discretion. C 0 0 e intermittently OPEN one of the Torus to Drywell Vacuum Breakers, using the TEST OPEN push-button approximately every 15 minutes. Crew recognizes MSL RMS Channel failure by: RADIATION HI" RMll 9RX511 High alarm Other channels reading normally. CRIDS Page 37 MSL Radiation readings. PSV-4946A (B,C,D,E,F,G,H), 3 OHA C6-A3 "MN STM LINE HPI USED: STAR PEER CHECK 0 FLAGGING OP BARRIERS 0 ESG-NRC-SI Page 9 of 27 Red: 02 I I Event I Instructor Activity Expected PlantlStudent Response AND EXPE RE Comments CRS reviews AB.RPV-0008: a Condition A Condition B Condition C and finds them not applicable. CRS rec0gniz.e Tech Specs action 3.3.2 action b.1) c) applies. CRS contacts Maintenance to troubleshoot and repair the MSL RMS channel. NOTE : H C. 0 P-AB . ZZ-000 I e may be referenced also for the transfer of TACS. e WHEN operator starts D SACS Pump, THEN DELETE Overrides 5A31C and 5A31 D. e e Crew identifies and communicates the loss of TACS to the CRS. RO/PO informs CRS that RPV power, level and pressure are stable. CRS orders TACS placed on the B SACS loop IAW HC.OP- AB. COOL-0002: Condition B. PO performs HC.OP-AB-COOL-0002 as directed by the CRS PO ensures the standby SACS pump starts. Ensures BOTH pairs of TACS supply and return valves on the Standby loop open to supply Ensures TACS supply AND return valves on the loop that WAS supplying TACS are TACS. (HV-2522/2496) CLOSED. (HV-2522/2496) HPI USED: STAR 0 OP BARRIERS 0 ESG-NRC-SI Page 10 of 27 Red: 02 Event / Instructor Activity WHEN dispatched to the 1A-D-482 as an operator, THEN REPORT the inverter output breaker CBIO is open, the AC Reg Output breaker CB302 is open and the Static Switch cabinet is de-energized. WHEN dispatched to the IA-D- 482 as maintenance, THEN REPORT there appears to be a fault in the Static Switch cabinet and you will need the inverter tagged. investigate H2 Seal Oil System, respond that alarm was due to low pressure. Using Remote Function acknowledge alarm. lsophase System, alarm was due to high temperature. Using Remote Function acknowledge alarm. NOTE: If dispatched to 0 NOTE: If dispatched to the 0 0 Expected PiantlStudent Response Comments ESG-N RC-S 1 Determines that the HV-2522E re-opens them as follows: HV-2522F are closed THEN Verifies no large break has occurred in TACS by observing SACS expansion tank levels. Determines that no large break in TACS has occurred, then simultaneously presses and holds the HV-2522E and/or HV-2522F OPEN PB's until the valves indicate open. Crew identifies the loss of the 1 AD482 inverter TROUBLE =) OHA D3-E3 120VAC UPS =) CRIDS CRS implements HC.OP-AB.ZZ- 0136, Attachment

5. Crew recognizes loss of RWCU via OHA and trip of both RWCU pumps due to a loss of HV-F001 indication. RO/PO refers CRS to HC.OP-AB.RPV-0007 in accordance with H C . 0 P-AR.ZZ-0008. CRS directs actions to be taken in accordance with HC.OP- AB.RPV-0007, Condition

6. [DIRECT Chemistry to sample and analyze reactor coolant.]

Page 11 of 27 Rev: 02 I XP - 0 CRS may direct Containment lnerting lineup to be secured. WHEN dispatched to SACS or CRS recognize Tech Specs SSW, THEN REPORT the action equipment is ready for starting or post start checks are SAT. a 3.8.3.1 .a.l.e and action A applies. (8 hr Action time) 0 Crew recognizes Steam Tunnel temp rising: = A2541 Stm Tunnel Clr Inlet temp in alarm. CRS directs PO to implement HC.OP-AB.BOP-0005, Condition A: PO implements HC.OP-AB.BOP-0005, Condition A: Isolate the source of the leak if known. determine the source of leak: =, Monitor the following to Main Steam Flow Feedwater Flow RWCU System = Ensures TB Chilled Water Supply Temp is c55F. a HV-9532-1 and HV-9532-2 are open. indication indication ESG-NRC-S 1 Page 12 of 27 Rev: 02 h Event / Instructor Activity Expected PlantlStudent Response = Ensure proper positioning of Steam Tunnel Supply AND Return Backdraft dampers WHEN dispatched to perform BOP-0005 actions, REPORT: Comments Action A.3: Steam Tunnel =1 Ensure both Steam Tunnel supply and return back draft dampers - both sets are open. cooling Fans in-service at Dane1 1 EC281. Ensure GlJ-HD9395A AND GU-HD9395B are closed. Action A.5: Place Both Steam Tunnel cooling fans in service by placing REMOTE FUNCTION HVII and HV12 in RUN. Action A.6: GU-HD9395A and 9395B are closed. WHEN dispatched to perform 0 CRS assigns a crewmember to BOP-0005 actions, REPORT: Action A.3: Steam Tunnel supply and return back draft dampers - both sets are open. monitor Steam Tunnel temperature. 0 CRS implements HC.OP- AB.CONT-0004, Condition A. => Direct Radiation Protection to enter RP-AR.SP-0001 Monitor for indications of fuel damage Monitor activity at the exhaust ducts to localize the source of the activity Determine the Total Release Rates 0 CRS implements HC.OP- AB .CONT-0004, Condition C. Monitor for indications of a steam leak NOTE: 0 Crew responds to RM-11 "High Alarm" for 9RX620 for the Tech Support Center ARM. This alarm may not be .eceived. High alarm is 2.5 mR/hr. ESG-NRC-SI Page 13 of 27 Rev 02 I Event I Instructor Activity Expected PlantlStudent Response The CRS may take 0 conservative action and scram before 145 degrees. Comments VOTE: The MSIVs may automatically close on an isolation signal. ESG-NRC-SI CRS briefs the crew on plant conditions and contingencies for a rising Main Steam Tunnel temperature. Crew monitors HC.OP- AB. BOP-0005 Retainment Override. CRS directs a manual Scram when Steam Tunnel temperature - >I45 degrees IAW the Retainment Override. RO takes actions to manually scram the reactor IAW HC.OP-PO takes action to control, restore and maintain RPV level with Feedwater. AB .ZZ-000 1 . CRS implements HC.OP-EO.ZZ-0101 based on entry condition of - 42.5" RPV Level and directs actions to stabilize the plant. =j RO performs scram actions I A W H C . 0 P-AB . ZZ-000 1 CRS may transfer level and pressure control to RClC and SRVs in anticipation of MSlV clo s u re. RO/PO coordinate transfer of Reactor Pressure and RPV level control . Crew places 'B' RHR in Suppression Pool cooling to support RCIC/SRV operation Attachment 3 CRS directs closing MSlVs and drains to isolate steam leak. IAW HC.OP-AB .ZZ-000 1 Page 14 of 27 HPI USED: STAR 0 HPI USED: STAR 0 HARDCARD 0 HPI USED: STAR 0 HARDCARD 0 HPI USED: STAR 0 HARDCARD 0 Rev 02 ESG-NRC-SI 0 RO closes the MSlVs and drains. The CRS directs the PO to restore and maintain RPV level / pressure with HPCl and/or RClC and SRVs. AB.BOP-0002, Condition A: a Verify the Main Turbine valves are CLOSED => Ensure the Motor Suction Pump and Turning Gear Oil Pump are running When Main Turbine Speed <900 rpm, ensure all Main Turbine Lift Pumps running. CRS implements HC.OP-Crew recognizes LOCA co nd it ion : =) RM-11 DLD monitors. Rising Drywell Pressure. => OHA A4-F5, A7-E4, C6-C2. CRS directs actions for the high Drywell pressure IAW HC.OP- AB.CONT-0001. Maximize Drywell Cooling by ensuring: All Drywell Fan Cooling Coils are Open All Drywell Fans are running in Fast Speed 0 Turbine Bldg. Chill Water system is ope rating properly Perform the following: Check Reactor Recirc. Pump Seals Check SRV Tailpipe Tem pe ra t u res 0 PO maximizes Drywell cooling and checks proper operation of TB Chillers. Page 15 of 27 HPI USED: STAR 0 HPI USED: STAR 0 HPI USED: STAR 0 Rev, 02 r Event I Instructor Activity Expected Plant'Student Response NOTE: At the discretion of the Lead Examiner, raise the severity of PC06. Comments As RBEO, two minutes after being dispatched, REPORT a large leak at D pump suction with approximately two inches of water on floor. You have exited the room and closed the watertight door. e e e WHEN operator places F004D keyswitch in CLOSE, THEN ENSURE ET-7 Triggers. Crew recognizes HI-HI Drywell pressure of 1.68 psig CRS reenters; HC.OP-EO.ZZ-01 01, enters HC.OP-EO.ZZ-0102, and directs actions to mitigate the leak. CRS determines that drywell sprays are required based upon DRWL temperatures / pressure. CREW may recognize Suppression Pool leak via decreasing Suppression Pool level indications on SPDS and annunciator A6-A5 and informs the CRS. CREW determines leak to be in RHR pump D room via SPDS and/or CRlDS alarms D2971 and D2939. RO/PO notifies RBEO to investigate cause of RHR pump room flooded alarm. CRS enters and directs actions Reactor Building and Rad Release to isolate the leak. CRS directs actions to isolate RHR Pump D suction by closing PO attempts to close HV-F004D, observes that the OVLD/PWR FAIL illuminates, and informs the CRS. of HC.OP-EO.ZZ-O103/4, HV-F004D. HPI USED: STAR 0 ESG-NRC-SI Page 16 of 27 Rev 02 I Event / Instructor Activity Expected Plant/Student Response NOTE: 0 Role-play as the building EO to support implementation of EOP 300 level procedures. Comments Do NOT implement EO- 315, use Remote Functions CS02 or CS04. Although, REPORT completion of lineup to the MCR. NOTE: 0 Once Crew determines a major failure of the Torus has occurred and level cannot be maintained, they may stop makeup efforts.

• When Suppression Pool Level drops below 74.5 inches, CRS reenters HC.OP-EO.ZZ-0102, Primary Con1.ainment Control, and directs actions to restore suppression pool level using RCIC, Core Spray, or Service Water. CREW closely monitors Torus level decrease and determines that a major failure of the Torus has occurred. Crew determines that Suppression Pool water level cannot be maintained above 38.5" and opens five SRVs before Suppression Pool level reaches 30". CRS implements HC.OP-EO.ZZ-0202, Emergency RPV Depressurization, when torus level cannot be maintained above 38.5".

PO opens 5 ADS valves IAW CRS direction. PO recognizes failure of SRV F013E to open via closed indication on 1 OC650C and informs CRS. CRS directs PO to open other SRV(s) until 5 SRVs are open. PO opens additional SRV per CRS instructions HPI USED: STAR 0 HARDCARD 0 ESG-N RC-S 1 Page 17 of 27 Re\ : 02 I Event I Instructor Activity Expected PlantlStudent Response NOTE: This task is completed satisfactorily if Emergency Depressurization occurs before 38.5" of SPL is reached.

• Comments 0 a Crew recognizes via acoustic and temperature indications that F013E, ADS SRV, has failed to open and opens an additional SRV PO maintainsh-estores RPV level >-I85 inches in accordance with CRS instructions.

PO initiates Suppression Pool cooling IAW CRS direction. HPI USED: STAR 0 ESG-N RC-S 1 Page 18 of 27 Revr 02 A. B. C. D. E. F. G. H. I. J. K. L. M. N. 0. P. Q. R. S. T. U. v. W. X. Y. Z. AA , BB. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid NUREG 1021 Examiner Standards JTA Listing Probabilistic Risk Assessment Technical Specifications Emergency Plan (ECG) Alarm Response Procedures (Various) HU-AA-101 Performance Tools and Verification Practices HU-AA-104-101 Procedure Use and Adherence OP-AA-1 01 -1 1 1-1 003 Use of Procedures HU-AA-1081 Fundamentals Toolkit HU-AA-1211 Briefing OP-AA-1 01 -1 1 1-1 004 Operations Standards OP-AA-101-111 Roles and Responsibilities of On Shift Personnel OP-AA-106-101-1001 Event Response Guidelines OP-AA-108-114 Post Transient Review OP-HC-108-115-1001 Operability Assessment and Equipment Control Program OP-HC-108-106-1001 Equipment Operational Control OP-AA-101-112-1002 On-Line Risk Assessment HC.OP-AB.BOP-0002 Main Turbine HC.OP-AB.BOP-0005 Main Steam Tunnel Temperature HC.OP-AB.CONT-0001 Drywell Pressure HC.OP-AB.CONT-0004 Radioactive Gaseous Release HC.OP-AB.COOL-0002 Safety Auxiliaries Cooling System HC.OP-AB.IC-0001 Control Rod HC.OP-AB.RPV-0007 Reactor Coolant Conductivity HC.OP-AB.RPV-0008 Reactor Coolant Activity H C . 0 P-AB .ZZ-00 0 1 Trans i en t PI ant Cond it ions CC. HC.OP-AB.ZZ-0136 Loss of 120 VAC Inverter DD. HC.OP-EO.ZZ-0101 RPV Control EE. HC.OP-EO.ZZ-0102 Primary Containment Control FF. HC.OP-EO.ZZ-O103/4 Reactor Building and Rad Release GG. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization HH. HC.OP-IO.ZZ-0003 Startup From Cold Shutdown to Rated Power I I. HC.OP-SO.AE-000 1 Feedwater System Operation JJ. HC.OP-SO.SF-0001 Reactor Manual Control KK. HC.OP-ST.BF-0001 Control Rod Drive Exercise - Weekly ESG-N RC-S 1 Page 19 of 27 Rei: 02 ESG-NRC-S1 I02 1.

• Crew determines that Suppression Pool water level cannot be maintained above 38.5" and opens five SRVs before Suppression Pool level reaches 30". K/A 295030 Low Suppression Pool Water Level EA2 Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL EA2.01 Suppression Pool level RO 4.1 SRO 4.2 KIA 21 8000 Automatic Depressurization System A.4 Ability to manually operate andlor monitor in the control room: A4.01 ADS Valves RO 4.4 SRO 4.4 If Suppression Pool Level drops below 38.5", the downcomer pipes are uncovered and the Pressure Suppression function of the Primary Containment is lost. EOPs direct Emergency Depressurizing if Suppression Pool level cannot be maintained above 38.5". Requiring the Emergency Depressurization to be initiated before Supp Pool Level reaches 30" allows the Crew three minutes to implement this action in this scenario.

2.

• Crew recognizes via acoustic and temperature indications that F013E, ADS SRV, has failed to open and opens an additional SRV. (KIA 239002 RelieflSafety Valves A4 Ability to manually operate and/or monitor in the control room: A4.01 SRV's 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-FO13E fails to open, the Crew needs to open an additional SRV to achieve MNSRED. This is directed by both HC.OP-EO.ZZ-0202 and AB.ZZ-0001. SRV's 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 it's operation. This would prevent them from detecting the failure and pursuing the usca of the Alternate Depressurization Systems in HC.OP-EO.ZZ-0202. ESG-N RC-S 1 Page 20 of 27 Rei 02 ESG-NRC-SI I02 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE Y/N ~~ EVENT YIN EVENT Loss Of Offsite Power/SBO LOCA TRANSIENTS: Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Y Internal Flooding LOSS OF SUPPORT SYSTEMS: Loss of ssw Loss of SACS Loss of Instrument Air Inadvertent MSlV Closure inadvertent SRV Opening Y Manual Scram COMPONENTlTRAlNlSYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Hard Torus Vent HPCl 1E 4.16KV Bus SACS Hx/Pump EDG 120VAC 481 1482 Inverter A/B RHR RClC SSW Pump Y/N KEY EQUIPMENT SLC CRD 1 E 125VDC KEY SYSTEMS 500KV AC Power S RVs Condensate/Feedwater PClG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment Emergency Depressurize RPV W10 High Pressure Injection Initiating LP ECCS with No High Pressure injection Available Restoration of AC Power after a LOP (EDG / Offsite) Monitoring and Control of SACS heat loads Preventing LVL 8 trip of Feedwater during a transient Align Core Spray Suction to CST when at NPSH limits Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus Inhibit ADS during ATWS Complete this evaluation form for each ESG. ESG-NRC-SI Page 21 of 27 Rev 02 0). a-103-105 Revision 0 Page 22 of 27 FORM I CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG Page 1 of 1 PREV. (NOTE 1) HOURS AUTH. THIS PERMIT AUTHORIZING THIS PERMIT 24 NOTE 1: The previous year i s%z? K Tom MacEwan I II TOTAL HOURS PREVIOUS YEAR (NOTE 1) CLOSING THIS PERMIT INITIAL ' :ludes the period from 2400 on today's date back to 0001 on the same date one year earlier OP-HC-I 03- 105 Revisi In 0 Page 23 c f 27 FORM 2 CONTAINMENT PREPURGE CLEANUP, INEFNG OR PRESSURE CONTROL VALVE PERMIT - SECTION A ~____ Date: Todav Gaseous Effluent Permit

1. 2009-01 NOTE: This permit is valid only until 2400 of this date - - _____ SECTION B HOURS VALVESlLlNES OPEN PREVIOUS YEAR (Note 1) Calculate Total Hours Open During Previous Year (NOTE I) DATE NUMBER OF HOURS 06/01 12008 6 (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) I-) 6 Hours available this date (line 1 minus line

2) [=) 446 Hours authorized this date (24 hours or the 24Hrs - hours available this date whichever is less) NCO performing calculation Daterrime

L>aw L'auplfIl4avi Todav/OlOO SM/CRS verification and authorization Da te/Time 6% r.M@Zrn Today/O130 - ___~ SECTION C VALVElLlNE OPEN TIME (Note 2) - START TIME STOP TIME TOTAL HOURS Time at which valvelline was closed or Total number of hours valve/lir-?

Condition 4 or 5 was entered with valve/line opened this cycle opened (NOTE 3) Time at which valvelline was open or Condition 1, 2. or 3 was entered with valve/line open Total number of hours valves/line open this permit: NCO performing calculations Date/Time SM/CRS Closing permit Datemime - NOTE 1: The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier. NOTE 2: Completed Form 2 should be filed in the AP-104 binder in the Control Room. VOTE 3: When computing the total hours (round up to the nearest 0.5 hr or to the nearest 1 .O hr) Rx Power: 4% MWe (May vary slightly): 0 Work Week: B Activities Completed Last Shift: 0 Reactor Startup in progress to step 5.3.40 of 10-3 0 Containment inerting lineup in progress through step 5. .8 of SO-GS-0001. Major Activities Next 12 Hours: 0 Continue with Startup by withdrawing Control Rods @ = 900 I! 'B' CRD pump discharge pressure set Icpaccx(171) 950 Restores HCU accumulator pressure on rod 18-55. lcpdb >= 900 // 'B' CRD pump discharge pressure set Icpaccx(66) = 950 Restores HCU accumulator pressure on rod 42-23. - - __ 13 14 15 16 EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: slnpmpb >= 0.50 // SLC Pump 'B' Start - Triggers Failure of BP208 SLC pump 1c:pbrun I/ 'B' CRD pump in service. dmf cd051855 Deletes accumulator trouble alarm malfunction. 1c:pbrun I/ 'B' CRD pump in service. dmf cd054223 Deletes accumulator trouble alarm malfunction. - ESG-NRC-S2 Page 4 of 28 Rev: 01 Initial Description RP07 Half Core ATWS Right Side SL04A AP208 SLC Pump Failure to Auto Start CDIOA 'A' CRD Pump Trips CD051855 Accumulator Trouble HCU 18-55 CD054223 Accumulator Trouble HCU 42-23 TC07A Trip of API 16 EHC Pump TC16 EHC Discharge Filter Plugging TC07B Trip of BPI 16 EHC pump TCOI-10 Turbine Bypass Valves Fail Shut SLOIB BP208 SLC Pump Failure 00:30 I --- I ET-12 I --- I --- Initial REM OTE/F I EL D FU NCTl 0 N SUM MARY: I Description Delay Ramp Trigger 1 lnit Val Final \ al HV06 CVH300 RBVS Fan --- --- ET-3 --- STO HV05 BVH300 RBVS Fan --- --- ET-3 --- STO ' HV04 AVH300 RBVS Fan --- --- ET-3 --- STO: ' HV03 CV301 RBVE Fan --- --- ET-3 --- STOF' HV02 BV301 RBVE Fan --- --- ET-3 --- STOI' HVOI AV301 RBVE Fan --- --- ET-3 --- STOI' AN24 1 OC382 Acknowledge 00:05 ET-3 --- NORM - ___ REPLASE BY PASS BYPA:;S EMERG REMO /E EP09 EOP 320 ARI Fuses 4:OO --- ET-9 REMO /E EPIO EOP 320 ARI Fuses 4:OO --- ET-9 --- EP11 EOP 320 RPS Div 1 6:OO --- ET-9 --- INSTA .L EP13 EOP 320 RPS Div 3 6:OO --- ET-9 --- INSTA -L INSTA -L EP12 EOP 320 RPS Div 2 8:OO --- ET-9 --- EP14 EOP 320 RPS Div 4 8:OO --- ET-9 --- INSTA -L EP35 EOP-322 HPCl Core Spray Valve 3:OO --- ET-I 0 --- FAIL TC06 'B' EHC Pump Filter Replacement --- --- ET-5 --- EPOI EOP-301 MSlV LVL 1 Isolation 6:OO --- ET-6 --- EP02 EOP-311 Restoring PClG to MSlVs 8:OO --- ET-7 --- EP38 EOP-319 Restoring lnst Air 3:OO --- ET-8 --- ~~ --- ___ ___ __. CLOSE ESG-NRGS2 Page 5 of 28 Rev. 01 __ I/O OVERRIDE

SUMMARY

I I I I I 1A175 E LO HD-9414B OPEN light 1A175 E DI HD-9414B OPEN PB 1A175 F DI HD-9414B CLOSE PB --- ET-2 ESG-NRC-S2 Page 6 of 28 Rev 01 Event I instructor Activity a Crew starts 'D' Circ water Pump and opens all circ water a Expected PlantlStudent Response a a a IF dispatched to respond to a CW Panel 10C502 panel alarm, THEN REPORT the alarm was caused by momentary high discharge pressure on D pump and the alarm has cleared. TOGGLE Remote Function AN06 to NORM. a a a CRS directs 'D' Circ Water Pump to be placed in service. PO starts D Circ Water Pump as follows: OBSERVE CIRCULATING WATER PUMP DP501 STR ENBL is illuminated. PRESS PUMP DP501 START push-button. OBSERVE AI-6325D ClRC WTR PUMP MOT AMP indicates 500 - 61 0 amps (running). 21 52D OPEN/CLOSE MID illuminates. OBSERVE DISCH VALVE HV- OBSERVE CI RCU LATl NG WATER PUMP DP501 START is illuminated.

21 52D OPEN FULL push-button. FULL illuminates. PO opens remaining CW Pump discharge valves OPEN FULL as follows: PRESS DISCH VALVE HV- 21 52A(B,C) OPEN FULL push- PRESS DISCH VALVE HV- OBSERVE HV-2152D OPEN button. HPI USED: STAR 0 PEER CHECK 0 OP BARRIERS 0 ESG-N RC-S2 Page 7 of 28 Rei 01 , Event I Instructor Activity Expected PlantlStudent Response OBSERVE HV/-2152A(B,C) OPEN FULL illuminates. Comments Power Ascension: Crew commences reactor power ascension after assuming the watch As RE PROVIDE the following guidance: 0 SPRI and Enhanced Stability Guidance are valid for the remainder of the maneuver. Power has been steady for the last hour. Raise power to 60% with control rods using 9E rods to position 48. Select a control rod 0 0 0 CRS directs raising power to 80% using RE guidance. 0 RO raises power with control HPI USED: rods using provided Move Sheets STAR 0 as follows: PEERCHECKU OP BARRIERS 17 0 RO selects the desired Control Rod Select PB on the ROD SELECT MODULE. 0 RO observes the following: Selected rod PB comes ON (bright white). FOUR ROD DISPLAY indicates the control rod position (1 OC650C). The associated Full Core Display (white) numbered rod identification light comes ON (1 OC650C). Approximately 6 gpm total flow through both the Insert AND Withdraw Stabilizing valves is indicated on CRlDs point B2117. 3 CONTROL ROD POSITION ESG-NRC-S2 Page 8 of 28 Rev: 01 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - I Event I Instructor Activity Expected PlantlStudent Response Corn men ts Continuous Withdraw 0 Simultaneously PRESS AND HOLD both the WITHDRAW PB AND the CONTINUOUS WITHDRAW PB while observing the following: INSERT (white) light comes ON momentarily. The WITHDRAW (white) light comes ON and the CONTl NUOUS WITHDRAW (white) light comes ON FOUR ROD DISPLAY indicates control rod movement. Full Core Display FULL IN (green) light goes OUT, as applicable. CONTROL ROD POSITION 0 Prior to reaching the desired control rod position, simultaneously RELEASE both the WITHDRAW PB and the CONTINUOUS WITHDRAW PB and OBSERVE the following: The WITHDRAW (white) light goes OUT. =, The SETTLE (white) light comes ON for =: 6 seconds and THEN goes OUT. FOUR ROD DISPLAY indicates the control rod has settled to the desired position. For control rods withdrawn to position 48 (full out), the applicable Full Core Display FULL OUT (red) light comes ON. 0 After the continuous withdrawal s CONTROL ROD POSITION cycle is completed, ENSURE that the rod position indicates that the rod is in the correct, even numbered position. ESG-NRC-S2 Page 9 of 28 Rei': 01 I Coupling check for rods at 48 0 WHEN a control rod is withdrawn to position 48 (full out), THEN PERFORM a control rod coupling integrity check IAW HC.OP-ST.BF-OOOI(Q); Control Rod Drive Exercise as follows: 0 WITHDRAW the control rod to position 48 AND PERFORM the following while giving the selected Control Rod a continuous withdraw signal: 0 OBSERVE the following as indication of the Control Rod being coupled: ROD OVERTRAVEL alarm does NOT annunciate. Red Full Out light illuminates on the Full Core Display. =$ RPlS indicates the Control Rod is full out (48). Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. 0 INDICATE on Pull Sheet the condition of Coupling Check. 0 RO recognizes trip of BP207 CRD pump by: OHA C6-F2 "CRD SYSTEM TROUBLE" CRIDS D2244 CRD WATER PUMP A MOTOR TRBL" IN ALARM" CRIDS D2926 "RECIRC PUMP A SEAL STAGE FLOW HILO" CRI DS D2927 "RECI RC PUMP B SEAL STAGE FLOW HILO" Flashing STOP light for AP207 Flashing OVLD/PWR FAIL for AP207 OHA CI-F5 "COMPUTER PT ENTER time of CRD Pump trip for beginning of 20 minute LCO time: Time: ESG-NRC-S2 Page 10 of 28 Rev: 01 r Event I instructor Activity Expected Piant/Student Response IF dispatched to AP207, e THEN REPORT the pump inboard bearing oil bubbler is broken and the motor is hot to the touch. breaker, THEN REPORT the breaker tripped on overcurrent. E dispatched to AP207 e e Comments WHEN dispatched to e investigate HC U accumulator trouble alarms, THEN REPORT the following: E the alarms are still in, pressures are 920 psig - IF the alarms are clear, pressures are 1040 psig E Crew does NOT recognize second accumulator trouble alarm AND alarm is still in, THEN when dispatched to first alarm, REPORT finding second HCU at 920 psig. CRDM temperatures can be e checked with Monitor Item Ictcrd. ES G-N RC-S2 RO dispatches NE0 to inspect AP207 CRD pump. Crew dispatches NE0 to inspect breaker for AP207 CRD pump. Crew recognizes potentially inoperable accumulators on withdrawn control rods by: 3 OHA C6-D4 "CRD ACCUM TROUBLE" ACCUMULATOR TRBL" Flashing amber ACCUM lights on Full Core Display for 18-55 and 42-23 Crew dispatches NE0 to check HCUs 18-55 and 42-23. 3 CRIDS D5268 "CRD CRS enters AB.IC-0001 CRS directs placing BP207 CRD pump in service IAW either: Condition A 3 AR.ZZ-0011 s SO.BF-0001 Page 11 of 28 Rev; 01 SUPPORT any directed RO place BP207 CRD pump in manipulations of the BP207 discharge valve (v008) using Remote Function CD02. service as directed by CRS. CRS recognize the following Tech Specs apply: = Control Rod Accumulators 3.1.3.5.a.2 1 Loss of RBVS: 1 0 Crew recognizes ~oss of RBVS I After the Crew assumes the watch and at the discretion o the Lead Examiner, by: = RB DIP indication on 1 OC650E D/P indication. IN ALARM" BLDG DlFF PRESS" AREA HVAC PNL 106382" RMT PNL C382 TRBL" SUPPLY RMT PNL C382 TRBL" 3 SPDS RB PARAMETERS 2 OHA EI-F5 "COMPUTER PT = CRIDS B7164 "REACTOR z OHA E6-C5 "RBVS & WING z CRIDS D3960 "RBVS EXH 3 CRIDS D3961 "RBVS 0 CRS implements AB.CONT-003: = Condition A a Condition D IF dispatched to 1 OC382, Crew dispatches RBEO to THEN REPORT Low Flow Trip darms on all Reactor Bldg Supply and exhaust fans. 1 OC382 to investigate. ESG-NRC-S2 Page 12 of 28 HPI USED: STAR 0 PEERCHECKO FLAGGING OP BARRIERS 0 Record Time B 1 CRD Pump started TIME Restore charging wai pressure within 20 minutes or place the mode switch in SHUTDOWN Re\ b Event / Instructor Activity Expected PlantlStudent Response IF directed to secure RBVS, THEN TRIGGER ET-3. Comments - IF dispatched to HD-9414B, THEN REPORT there is no obvious reason for the failure. (GU-HD-9414B is located in Room 4624, on the Rx Bldg roof.) RO/PO recognize HD-9414B failed in mid position by 1 OC651 E indication and inform CRS. RO/PO place FRVS in service IAW SO.GU-0001. Crew dispatches NE0 and Maintenance to investigate closure of HD-9414B. CRS recognize the following Tech Specs apply: Secondary Containment Integrity 3.6.5.1 => Secondary Containment Automatic Isolation Dampers 3.6.5.2 action a or b or c Crew recognizes trip of API 16 EHC pump by: OHA D3-F5 "TURB HYDR PUMP TROUBLE" RESERVOIR TROUBLE" CRIDS D5542 "HYDRAULIC FLUID PUMP A TRBL" CRIDS D5575 "TURBINE HYDRAULIC FLUID PRESS LO" HYDR FLUID PUMP A flashing LOW DISCH PRESS light OHA D3-E5 "TURB HYDR HPI USED: STAR 0 PEER CHECK Cl FLAGGING 0 OP BARRIERS Restore Secondary Containment within 4 hours. 8 Hour LCO Action tirie for damper. If left in AUTO, the BPI 16 EHC pump wii auto-start in about 10 seconds. ESG-NRC-S2 Page 13 of 28 Rev: 0 1 E dispatched to API 16, THEN REPORT the pump outboard motor bearing is hot to the touch. 0 ROlPO ensures start of the BPI 16 EHC pump. ' 'B' EHC Pump Filter CloW: The BPI 16 discharge fi begin clogging one min the pump starts. E dispatched to API 16 breaker, THEN REPORT the breaker tripped on overcurrent. 0 HPI USED: STAR 0 PEERCHECKO Immediate Operator action IAW AB.BOP-0003. Monitor Item: 0 CRS implements AB.BOP-0003. 0 EHC Header Pressure 0 EHC Pump Disch Pressure 0 EHC Pump Filter D/P tupehchd tupehc(2) - 15 tupehcdp(2) There are no subsequent actions in AB.BOP-0003 for a tri of a pump. Crew recognizes BPI 16 discharge filter clogging by: 3 OHA D3-F5 "TURB HYDR PUMP TROUBLE" EHC PUMP B FILTER DP HI" flashing HI FILTER DIP light pressure s CRlDS D3629 "MAIN TURB 3 HYDR FLUID PUMP B =) Lowering EHC header With discharge filter swap, EHC pressure will reach 1100# in about 6 minutes after the pump trip. - IF the discharge filters are swapped, THEN EHC pressure will reach 1100# abou 4 minutes after the swap. 0 CRS implements AB.BOP-0003: a Condition A - IF directed to swap BPI 16 discharge filters, Section 5.20, 0 Crew directs TBEO to swap BPI 16 pump discharge filters. REFER to SO.CH-0001 THEN TRIGGER ET-5. 0 WHEN EHC pressure lowers to 1200 psig, THEN CRS directs locking the Mode Switch in SHUTDOWN. EHC header pressure will recover, then continue to decay. May direct earlier, based on rate of pressure drop and absence of any remaining compensatory act ions ESG-NRC-S2 Page 14 of 28 Rev: 01 ND EXPECT Event / Instructor Activity Expected PlantlStudent Response Comments 0 RO locks the Mode switch in SHUTDOWN. 0 Crew recognizes Scram Condition and Reactor Power Above 4% EOP entry condition: =I APRM indications a Absence af rod FULL IN lights on the right side of Full Core Display =) Rod position indications RO performs scram actions IAW AB.ZZ-0001 Attachment

1. CRS implements EOP-IOIA. PO stabilizes and maintains RPV level as directed by CRS. CRS directs: a Initiating SLC RO initiate SLC and verify RWCU isolates.

Verifying RWCU Isolates

• Crew starts AP208 SLC pump before Suppression Pool temperature reaches 7 70 degrees. Crew recognizes trip of BP208 SLC pump by: 3 OHACI-91 "SLC PUMPNALVE O/PF" I N IT1 AT1 0 N FA1 L U RE" BP208 TROUBLE TRBL" Flashing STOP light for BP208 =) OHA C1-F1 "SLClRRCS 3 CRIDS D3023 "SLC INJ PMP - IF dispatched to investigate trip 0 Crew dispatches NE0 and of BP208, -HEN REPORT the breaker is tripped and will not reset. Maintenance to investigate trip of BP208 SLC pump. (52-2221 01)

HPI USED: HARD CARD 0 HPI USED: STAR 0 ENTER Supp Pool temp when AP208 SL(: pump is started: Temp: ESG-NRC-S2 Page 15 of 28 Rev. 01 0

• REFER to the appropriate EOP and SUPPORT Crew requests for EOPs IAW with the following. Validated execution time delays are built-in:

EOP-301: ET-6 EOP-311: ET-7 EOP-319: ET-8 EOP-320: ET-9 EOP-322: ET-I 0 CRS directs: Verifying Recirc runback to minimum Tripping reactor recirc pumps Verify Recirc runback to minimum Trip reactor recirc pumps RO: CRS directs inhibiting ADS. ROlPO inhibit ADS IAW AB.ZZ-0001 Att.

13. Crew prevents an uncontrolled depressurization during ATWS conditions by preventing ADS ACTUATION.

CRS directs performance of the following EOPs: EO.ZZ-0320 "Defeating ARI and RPS Interlocks" EO.ZZ-0301 "Bypassing MSlV Isolation Interlocks" EO.ZZ-0311 "Bypassing Primary Containment Instrument Gas Isolation Interlocks" EO.ZZ-0319 "Restoring Instrument Air in an Em erg en cy" EO.ZZ-0322 "Core Spray Injection Valve Override" CRS directs terminating and preventing injection to the RPV with the exception of: 3 SLC z CRD z RClC HPI USED: May already be tripped on EOC-RPT. STAR HPI USED: STAR HARD CARD This Critical Task is not applicable if RPV level never reaches -1 29". See justification for failure criteria. The timing, order, and priority of the EOP performance may vat-). ESG-NRGS2 Page 16 of 28 Re\: 01 0 RO/PO terminate and prevent injection IAW AB.ZZ-0001: =) Attachment 16 (1 OC651) = Attachment 17 (1 OC650) 0 CRS directs maintaining RPV water level between -50" and PO control level as directed by CRS with: Feedwater IAW AB.ZZ-0001 Att. 14 -1 85". 0 3 3 HPCl IAW EOP-322 RClC IAW AB.ZZ-0001 Att. 6

• Crew lowers RPV level to -50'; and ensures adequate core cooling by maintaining or restoring RPV level above -185" without Emergency Depressurizing.

0 CRS directs bypassing the RWM and commencing manual rod insertion. 0 RO align CRD for ATWS operation IAW AB.ZZ-0001 Attachment

18. RO bypass RWM and insert control rods IAW RE-AB.ZZ-0001 Attachment.

1. 0 Crew recognizes trip of the

'B' EHC pump by: 3 OHA D3-F5 "TURB HYDR PUMP TROUBLE" HPI USED: STAR 0 HARD CARD Typically, the lower er 3 of the level band is se.* above -1 29". HPI USED: HARD CARD I7 If the turbine trips before the reactor is scrammed, an RRCS feedwater runback may occur. STAR ESG-NRC-S2 Page 17 of 28 Rev: 01 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - Event I Instructor Activity Expected PlantlStudent Response Comments 0 Crew recognizes turbine bypass valves failing shut by: = OHA D3-D5 "EHC UNIT PANEL 106363 = DEHC Bypass Valve Positioning Error alarms Reactor pressure rising above Pressure Setpoint below 1037 psig with: 0 CRS directs stabilizing pressure Main Steam Line Drains 3 SRVS 0 RO/PO control pressure as directed by CRS with: Main Steam Line Drains IAW AB.ZZ-0001 Att. 15 = SRVS IAW AB.ZZ-0001 Att. 13 0 Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by: 3 OHA C8-F1 "SUPPR POOL TEMP HIGH" Flashing 95 degree status light on 1 OC650C a RMI 1 9AX833/834 alarm Various Suppression Pool tem pe ratu re i nd icato rs 0 CRS implements EOP-102. 0 CRS directs placing RHR in Suppression Pool Cooling. RO/PO place RHR in Supp Pool Cooling IAW AB.ZZ-0001 Att. 3. When pressure control swaps to SRVs, maintaining RPV water level between -50" an3 -129" will be very challenging due to shrink and swell and changing reactor pressure with the RFPTs in MAN. HPI USED: STAR HARD CARD R OP BARRIERS R HPI USED: STAR HARD CARD R FLAGGING ESG-N RC-S2 Page 18 of 28 Rev 01 EANDEXPECTE 0 E Suppression Pool temperature is >I 10 degrees, AND Reactor power is >4%, AND SRVs are open or cycling, THEN Crew terminates and prevents injection to the RPV with the exception of SLC, CRD, and RCIC, UNTIL Reactor power is <4%, RPV level reaches -129", SRVs remain closed. - IF RPV level reaches -129", THEN RO/PO terminates and prevents injection from Core Spray IAW AB.ZZ-0001 Attachment

16. WHEN the Crew has reset WHEN EOP-320 Section 5.1 and HPI USED: RPS, 5.2 are complete, STAR 0 THEN DELETE Malfunction RP07 to allow full rod insertion on the next scram.

RPS. At the Lead Examiners WHEN OHA C6-E4 clears, HPI USED: discretion, MODIFY Monitor Item lclsdv to accelerate draining of the SDV. HPI USED: STAR 0 HARD CARD THEN the Crew implements EOP-320 Section 5.3 and resets STAR 0 THEN the Crew initiates a manual scram IAW EOP-320 Section 5.3.

• CREW fully inserts all control rods via RMCS and/or manual scram(s) IA W 0 Crew recognizes the reactor is shutdown by: =. RWM Confirm Shutdown CRIDS Rod positions 0 CRS directs terminating SLC 0 RO/PO terminate SLC injection.

H C. 0 P- EO. ZZ-0320. 5 SPDS ALL. RODS IN injection. HPI USED: STAR 0 ESG-N RC-S2 Page 19 of 28 Rev: 01 Event I Instructor Activity The scenario may be terminated at the discre ained above -1 85 Expected PiantlStudent Response Comments 0 CRS exits EOP-IOIA, enters EOP-101. ESG-NRC-S2 Page 20 of 28 Rev: 01 A. B. C. D. E. F. G. H. I. J. K. L. M. N. 0. P. Q. R. S. T. U. V. W. X. Y. Z. AA. BB. cc. DD. EE. FF. GG. HH. II. JJ. KK. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid NUREG 1021 Examiner Standards JTA Listing Probabilistic Risk Assessment Technical Specifications Emergency Plan (ECG) Alarm Response Procedures (Various) HU-AA-101 Performance Tools and Verification Practices HU-AA-104-101 Procedure Use and Adherence OP-AA-1 01 -1 11 -1 003 Use of Procedures HU-AA-1081 Fundamentals Toolkit HU-AA-1211 Briefing OP-AA-101-111 Roles and Responsibilities of On Shift Personnel OP-AA-106-101-1001 Event Response Guidelines OP-AA-108-114 Post Transient Review OP-HC-108-115-1001 Operability Assessment and Equipment Control Program OP-HC-108-106-1001 Equipment Operational Control OP-AA-101-112-1002 On-Line Risk Assessment HC.OP-IO.ZZ-0006 Power Changes During Operation HC.OP-SO.AE-0001 Feedwater System Operation HC.OP-SODA-0001 Circulating Water System Operation HC.OP-SOSF-0001 Reactor Manual Control HC.OP-SO.SF-0003 Rod Worth Minimizer Operation HC.OP-AB. IC-0001 Control Rod HC.OP-AB.ZZ-0001 Transient Plant Conditions HC.OP-AB.CONT-0004 Reactor Building HC.OP-AB.BOP-0006 Turbine Hydraulic Pressure HC.RE-AB.ZZ-0001 Insertion of Control Rods in Response to an ATWS HC.OP-AB.ZZ-000 Reactor Scram HC.OP-EO.ZZ-0101 RPV Control HC.OP-EO.ZZ-0101 A ATWS-RPV Control HC.OP-EO.ZZ-0102 Primary Containment Control HC.OP-EO.ZZ-0301 Bypassing MSlV Isolation Interlocks HC.OP-EO.ZZ-0311 Bypassing Primary Containment Instrument Gas Isolation Interlocks HC.OP-EO.ZZ-0319 Restoring Instrument Air in an Emergency HC.OP-EO.ZZ-0320 Defeating ARI and RPS Interlocks HC.OP-EO.ZZ-0322 Core Spray Injection Valve Override ESG-NRC-S2 Page21 of28 Re\:: 01 ES ESG-NRC-S2 IO1 1.

• Crew starts AP208 SLC pump before Suppression Pool temperature reaches 1 IO degrees. KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EAI. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor POM Above APRM Downscale or Unknown: EA1.04 SBLC RO 4.5 SRO 4.5 EA2 Ability to determine and/or interpret the following as they apply to SCRAM Cordition Present and Reactor Power Above APRM Downscale or Unknown: EA2.04 Suppression Pool Temperature RO 4.0 SRO 4.1 . The Boron Initiation Injection Temperature above about 9% power is 1 10°F. The post scram power level in this scenario is greater than 9%.

110°F is also one of the conditions that may require intentional lowering of RPV water level to as low as -1 29" to control power. Lowering RPV water level to -1 29" jeopardizes main condenser and RFPT availability, which could significantly complicate mitigation of the ATWS. Initiating SLC before 1 10°F will help reduce power and may prevent the need to lower level to -129". 2.

• Crew prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUATION.

KIA 21 8000 Automatic Depressurization System A4 Ability to manually operate and/or monitor in the control room: A4.04 ADS inhibit RO 4.1 SRO 4.1 K/A 295031 Reactor Low Water Level EAI. Ability to operate andlor monitor the following as they apply to REACTOR LOW WATER LEVEL: EA.06 Automatic depressurization RO 4.4 SRO 4.4 Given the current ATWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor. EOPs direct this action under the current conditions. This critical task is only applicable if RPV water level goes below -129". Failure to satisfactoril) complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure to less than 700 psig. 3.

• K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: EA2.02 Reactor water level RO 4.1 SRO 4.2 Crew lowers RPV level to -50'; and ensures adequate core cooling by maintaining o restoring RPV level above -185" without Emergency Depressurizing. Lowering level RPV level during an ATWS with reactor power >4% is a key strategy for controlling reactc power. Maintaining adequate Core cooling under ATWS conditions is accomplished by maintaining/restoring lev above -1 85". HPCl and RClC are capable of maintaining level under the current conditions.

An Emergency Depressurization is not warranted and would result in a large injection of cold water and the potential displacement of boron from the core. r ESG-NRC-S2 Page 22 of 28 Rev4v: 0 1

4.

• Crew fully inserts all control rods via RMCS and/or manual scram(s) IAW HC. OP-EO.ZZ-0320.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EAI. Ability to operate andlor monitor the following as they apply to SCRAM Condition Present and Reactor Powt-r Above APRM Downscale or Unknown: EA1.01 Reactor Protection System RO 4.6 SRO 4.6 EA1.07 RMCS RO 3.9 SRO 4.0 Manually inserting all control rods, OR, implementing HC.OP-EO.ZZ-0320, provides the only methods for control rod insertion and substantial negative reactivity addition It iscritical for the crew to implement onc of these methods to insert control rods and shut the reactor down. Failure to initiate these actions may result in requiring RPV level to be lowered to or below TAF to reduce power to <4%. This represents a significant challenge to maintaining adequate core cooling. ESG-NRC-S2 Page 23 of 28 Rev: 01 -7x Power: -51 o/o returning from power reduction for condenser water box cleaning. MWe (May vary slightly): 547 Work Week: C Activities Completed Last Shift: Completed all condenser waterbox work and returned to service. Removed 'D' Circ Water Pump from service. Completed OP-1O.ZZ-0006 up to step 5.1 5.6 Major Activities Next 12 Hours: Place 'D' Circ Water Pump back in service. Raise reactor power per RE guidance and 10-0006: - Withdraw 9E Rods to position 48 IAW Move Sheets - Continuous Rod Withdraw is permitted. - Hold at 60% power for Thermal Limit check. Protected Equipment: None fagqed Equipment: None ESG-NRC-S2 Page 25 of 28 Rev: 01 I I 4- I t XAM I NATION S C E N ARI 0 GUIDE (E S G) REV I E W/VA L I DATION Note: This form is used as guidance for an examination team to conduct a review for the propoiied exam scenario(s). Attach a separate copy of this form to each scenario reviewed. ESG- NRC-S2 REVIEWER: The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it do not cue crew into expected events. Each event description consists of: The event termination point 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 use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible precedir: event has occurred. The events are valid with regard to physics and thermodynamics. Sequencingltiming of events is reasonable (e.g. the crew has time to respond to the malfunctions in appropriate time frame and implements procedures and/or corrective actions). Sequencinghiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. If time compression techniques are used, scenario summary clearly so indicates. The simulator modeling is not altered. All crew competencies can be evaluated. Appropriate reference materials are available (SOERs, LERs, etc.) Proper critical task methodology used IAW NRC procedures. ESG-NRC-S2 Page 26 of 28 Re\ - 7 01 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cnn't) Note: The following criteria list scenario traits that are numerical in nature ESG: NRC-S2 SELF-CHECK (ri $7 1. (.; c,J- 2. Total malfunctions inserted: 5-8 Malfunctions that occur after EOP entry: 1-2 0'8 3. Abnormal Events: 2-4 I 4. Major Transients: 1-2 6 q /;- [tL'$f 5. G.52 6. Gi-2 8. Critical Tasks: 2-3 EOPs entered requiring substantive actions: 1-2 EOP Contingency Procedures requiring substantive actions: [I "3- 7. Approximate scenario run time: 60-90 minutes 0-2 + fi k 9. Comments: Technical Specifications are exercised during the test: >2 ESG-NRC-S2 Page 27 of 28 Re\ : 01 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Crew Validation Rev: 00 Date Validated: 11/20/2008 Validation Comments Disposition .................................................................................................................................................................................. Accumulator trouble alarms cleared late. Changed Event Triggers to set accumulator pressures to 950 vs 900 after pump start. Add Yard operator report for CW panel alarm. Simplfy Turnover sheet. Validation time 82 minutes. Add validation time to cover sheet. Added. Minimized wordina on TO sheet. Added. Crew Validation Rev: Date Validated: Crew Validation Rev: Date Validated: Rev.: 01 ESG-NRC-S2 Page 28 of 28 I TRAINING WE ONLY ONLINE RISK: GREEN WORK WEEK CHANNEL: C 1 i Reactor Power: -51 % Returning from power reduction for condenser water box MWe (May vary slightly): 547 cleaning. Activities Completed Last Shift: - 0 Completed all condenser waterbox work and returned to service. 0 Removed 'D' Circ Water Pump from service. 0 Completed OP-I0.ZZ-0006 up to step 5.1.5.B Major Activities Next 12 Hours: - 0 Place 'Dl Circ Water Pump back in service. 0 Raise reactor power per RE guidance and 10-0006 Heightened Aware ness: None Protected Equipment: - None Tagged Equipment: None Reactivity

0 Raise reactor power per RE guidance and 10-0006: Withdraw 9E Rods to position 48 IAW Move Sheets Continuous Rod Withdraw is permitted.

Hold at 60% power for Thermal Limit check. - - - SCENARIO TITLE: RRCS lnst Fails, RWCU Leak, High Rx Pressure, LOCA wlPSP SCENARIO NUMBER: ESG-NRC-S3 EFFECTIVE DATE: Effective when approved EXPECTED DURATION: 63 minutes REVISION NUMBER: 01 PROGRAM: 1-1 L.O. REQUAL 1- INITIAL LICENSE -1 OTHER REVISION

SUMMARY

1. Changed ramp time from 10 minutes to 15 minutes based on validation comments. Overall time to respond is now about 2 minutes from 1 st alarm until scram sctpoint with no action taken.

2. Failed Fool to close manually and automatically based on validation comments.

3. Swapped to 8 TSC Chilled Water System in service for preps for TACS swap.

I PREPARED BY: APPROVED BY: APPROVED BY: Archie E. Faulkner Instructor /? yJd hlw2 0 rations Training Manager or Designee ,- 12/5/08 DATE 7- er tio s 'rector or Designee 4-- Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while I completing a series of CRITICAL TASKS, which measure the crew's ability to safel!' operate the plant during normal, abnormal, and emergency plant conditions. (Critical tasks within this examination scenario guide are identified with an " *.") II. MAJOR EVENTS: A. Power reduction to 84.5% A. Swap TACS to B SACS Loop

9. RRCS Pressure Transmitter Failure C. RWCU Leak w/Failure to Automatically Isolate D. High Reactor Pressure E. LOCA w/Downcomer Failure F. A/C DW Pressure Channel Initiation Failures Ill. SCENARIO

SUMMARY

,-he scenario begins with the plant at 90% power. After turnover, the power reduction from 90 tci 84.5% will be accomplished using control rods per RE instructions.

TACS will be swapped to the '9' SACS Loop for preplanned maintenance on A SACS Pump. The PT-N403A RRCS Pressurrb Transmitter will fail downscale. After Tech Specs for the failure are identified, RWCU will develrjp a leak that will require manual isolation of the system (Critical Task). The automatic isolation i'j failed. After RWCU is isolated, an EHC logic failure will cause reactor pressure to slowly rise. Bypass valves will not respond. Both the RPS and RRCS high pressure scrams will fail and a manual scram will be required to restore reactor pressure to within normal limits (Critical Task: The pressure transient will cause a LOCA and a downcomer will fail. This will require spraying the drywell to avoid exceeding PSP (Critical Task). The Mode switch will fail such that the Lou Main Steam Line Pressure MSlV isolation will NOT be bypassed by taking the Mode Switch oui of RUN. The PT-N094E/G will fail to respond to High Drywell Pressure due to inadvertently being left isolated following maintenance. This will result in the failure of A/C Core Spray and RHR logics to initiate, and the failure of HPCl to initiate. All logics can be manually initiated an( all logics will respond to lowering RPV water level. The scenario ends when RPV level is being maintained and Drywell Sprays are in service. ESG-NRC-S3 Page 2 of 27 Rev : 01 IV. INITIAL CONDITIONS: - I.C. - I INITIALIZE the simulator to 97% power, MOL. REDUCE power to 90% using Reactor Recirc. REMOVE Cross-flow from service and acknowledge annunciator. PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers) I I 1 [ Mia/ I Description _I INITIAL SO.EG-0001 Section 5.7 up to and including stroke timing the valves (Step 5.7.4 of Rev 40). ENSURE TACS is supplied by the 'A' SACS loop ENSURE the 'B' SACS pump is in service and the 'D' SACS pump is in Standby. ENSURE the 'B' TSC Chilled Water System is in sewice and the 'A' TSC Chilled Water Circ pump is in Standby in Auto. ENSURE HC.OP-DL.ZZ-0026 log available. ENSURE Remote Functions PC03ER and PC03GR are changed to RESET. ENSURE Data Collection is trending the following parameters: Suppression Chamber Pressure 0 W/R Reactor Water Level 0 WIR Reactor Pressure 0 TCV 1 Position TCV 2 Position 0 TCV 3 Position 0 TCV 4 Position COMPLETE the Simulator Ready for Training/Examination Checklist. PRE-BRIEF the crew for the power change and TACS swap ESG-NRC-S3 Page 3 of 27 Rev.: 01 I 10 _- EVENT TRIGGERS: I EVENT ACTION: COMMAND: PURPOSE: ET # I Description 11 EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: 12 EVENT ACTION: COMMAND: PURPOSE: 13 EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: cufdelta >= 60 // RWCU Diff Flow in gpm irnf cu03 100 120 Raises severity of RWCU leak after isolation setpoint is exceeded. ~ ~~ ~ crqnrni <= 10 I1 Reactor power < 10% drnf tcOl-IO Deletes stuck closed bypass valves, fails Mode Switch and triggers LOCA. rnspeh <= 900 I/ Main Steam Line Header Pressure < 900 psig irnf TC02-4 0 Closes TCVM to prevent depressurization and MSIV isolation. rnspeh <= 890 /I Main Steam Line Header Pressure < 890 psig irnf TC02-3 0 Closes TCV#3 to prevent depressurization and MSlV isolation. - -_ mspeh <= 880 /I Main Steam Line Header Pressure < 870 psig irnf TC02-2 0 Closes TCV#2 to prevent depressurization and MSlV isolation. rnspeh <= 870 /I Main Steam Line Header Pressure < 860 psig irnf TC02-I 0 Closes TCV#I to prevent depressurization and MSlV isolation. - pcpdw >= 16.4 // Drywell Pressure > 1.7 psig Trips RFPTs to force use of HPCI. ESG-NRC-S3 Page 4 of 27 Rev,: 01 Ramp Trigger lnit Val Final_ AD06 Failure of Lo-Lo Set Valves to Arm --- NONE --- --- ESG-NRC-S3 Page 5 of 27 Rev.': 01 FAIL- 1 --- NONE --- OPEN ET019 GROUP 7A HV-F001 RWCU Supply Is01 Rev.: 01 ESG-NRC-S3 Page 6 of 27 Event I Instructor Activity Power Reduction: CRS directs continuing the power Crew continues reactor pow duction after assuming t reduction to 84.5% using RE guidance . As RE PROVIDE the following guidance : 0 SPRl and Enhanced Sheets. 0 RO reduces power with control rods using provided Move Stability Guidance are valid for the remainder of the maneuver 0 Power has been steady for the last hour 0 Lower power to 84.5% with control rods using 9D and 9E rods. Control rod selection RO selects the desired control rod, PRESS the desired Control Rod Select PB on the ROD SELECT MODULE AND OBSERVE the following: Selected rod PB comes ON (bright white). FOUR ROD DISPLAY indicates the control rod position (1 OC650C). The associated Full Core Display (white) numbered rod identification light comes ON (1 OC650C). Approximately 6 gpm total flow through both the Insert AND Withdraw Stabilizing valves is indicated on CRID's point B2117. 3 CONTROL ROD POSITION Continuous rod insertion 0 At the ROD SELECT MODULE, ( Non-e merge ncy ) PRESS AND HOLD the INSERT PB AND OBSERVE the following: The INSERT (white) light comes ON. Expected PlantlStudent Response Comments ESG-NRC-S3 Page 7 of 27 HPI USED: STAR q PEERCHECKU OP BARRIERS Rev.: 01 Event I instructor Activity Expected PiantlStudent Response PO swaps TACS after e Comments 3 CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod movement. Full Core Display FULL OUT (red) light goes OUT, as applicable . Prior to reaching the desired control rod position, RELEASE the INSERT P 6 AND OBSERVE the following: The INSERT (white) light goes OUT. a The SETTLE (white) light comes ON for = 6 seconds, THEN goes out. FOUR ROD DISPLAY indicates the control rod has settled to the desired position. After the continuous insertion is completed, ENSURE that the rod position indicates that the rod is in the correct position. RO repeats steps as necessary to position rods IAW Move Sheets. CRS direct PO to swap TACS to r;, CONTROL ROD POSITION LOOP B IAW OP-SO.EG-0001. PO performs the following: 3 OBSERVE LOOP B Pump D, REMOTE push-button is OFF. Ij PLACE Loop B Pump D in MAN control. ESG-NRC-S3 Page 8 of 27 Rev.: 01 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - Event I Instructor Activity Expected PiantlStudent Response Comments 3 PRESS the DP210 START pushbutton AND PERFORM the following: OBSERVE the LOOP B PUMP D, LOW DlFF PRESS light extinguishes. THROTTLE OPEN ensure minimum flow requirements of =go00 g Pm. EG-HV-2512B to PO opens either B or D TACS isolation valves in the standby loop which required the most amount of time to stroke fully open. PO opens TACS isolation valves in the standby loop NOT opened in previous step and OBSERVE positive indication that both valves are opening. WHEN positive indication is noted that the remaining TACS Isolation Valves in the standby loop have started to open, THEN: CLOSE the following valves on the SACS Loop being removed from service: . 3 HV-Z522/2496A, TACS INBD SPLY/RTN VLVS ADJUST OPEN HV-2512A, RHR HX OUTLET VALVE, to obtain ~4500 gpm SACS flow through the 'A' RHR HX. ESG-NRC-S3 Page 9 of 27 Re$(.: 01 Event I Instructor Activity Expected PlantlStudent Response PRESS AND HOLD CLOSE PB until EG-HV-25128, RHR HX OUTLET VALVE, indicates closed. CLOSE the following valves on the SACS Loop being removed from service: 3 HV-2522/2496C, TACS OUTBD SPLYlRTN VLVS Comments PERFORM the following to place the SACS Loop A in standby: PRESS the AP210 STOP pushbutton. A in AUTO. ensure minimum flow requirements of ~4500 gpm. 3 PLACE SACS LOOP A Pump 3 THROTTLE EG-HV-2512A to - IF dispatched to RRCS, THEN REPORT there is an "ATM CALI GROSS FAILURE" light lit on 1OC601 and PT-N403A is reading 0 psig. - IF dispatched to RRCS to perform DL-26 Attach 1 b Form 1, THEN PROVIDE DL-26 Attach Ib Form 1, filled out as provided on attached sheet. 'F dispatched to transmitter at instrument rack C004, THEN REPORT no visible problem at instrument rack. 0 Crew recognizes RRCS Failure by: 3 OHA D1-E1 "RRCS TROUBLE" RRCS Channel A Logic A "RRCS LOGIC A TROUBLE" light Crew dispatches ABEO and/or Maintenance to RRCS cabinets 1 OC601/602. PT-N403A output can be seen on the SPDS Reactor Pressure Poird Status display. ESG-NRC-S3 Page 10 of 27 Re\.: 01 Event / Instructor Activity a Expected Plant/Student Response Comments RWCU Leak: a After Tech Spec actions fo PT-N403A have been identified, -1 OR at the discretion of the Lead Examiner, with Auto Isolation failure) AND two minutes after the RWCU leak has been in VERIFY South Plant Vent TRIGGER ET-5 (RWCU CRS recognize the following Tech Spec action applies: a ATWS Recirculation Pump Trip System Instrumentation 3.3.4.1 action b Crew recognizes rising off site release rate by: => SPDS indication RMI 1 SPV Effluent 9RX580 Place the inoperable channel in a tripped condition within one hour. 9RX580 Rate of Rise will alarm 1-2 minute! after the leak starts. This alarm is NOT programmed to be audible in the Control Room THEN CALL as Rad Pro 0 CRS implements AB.CONT-004: Condition C Condition A Monitor Items: 0 RWCU Diff Flow cufdelta ESG-NRC-S3 Crew recognizes leak from RWCU by: 3 Rising differential flows on NUMAC and CRIDS page 61 ISLN TIMER INITIATED" TIMER INITIATED CH D" TIMER INITIATED CH A" 3 OHA D3-*33 "RWCU STM LK CRIDS 05871 "RWCU ISLN 3 CRIDS 05873 "RWCU ISLN Page 11 of 27 Room temperatures v not provide conclusivc. evidence of leak. RWCU differential floi will reach the alarm setpoint about 7.5 minutes after leak starts. If RWCU is isolated before differential flow* setpoint is reached, alarms will not be received. Re\ I1 : 01 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - Event / instructor Activity Expected PlanVStudent Response Comments Monitor Items: 0 0 'A' Channel Isolation 0 'D' Channel Isolation cu: k6a09 cu:k6d7 7 Examiner Note: HV-F001 will not close manually or 3 c automatically. Monitor Items: HV-FOO4 cuvfOO4

• i' 0 IF directed to remove RBVS THEN REFER to SO.GU-0001 AND TRIGGER ET-6. 0 Gm service, Crew recognizes failure of RWCU to isolate by:

=1 OHA CI-A2 "RWCU DlFF FLOW HI" FLOW CH D" FLOW CH A' =. CRIDS D5870 "RWCU DlFF =. CRIDS D5872 "RWCU DlFF RO close RWCU HV-F001 and (May also close HV-F039) HV-FOO4. Crew initiates closure of RWCU HV-F004 within two minutes of receiving OHA (Closing HV-F004 prior to the isolation tim er comple fion satisfies this requirement.) C7-A2 "RWCU DlFF FLOW HI". 3 RO reports the HV-F001 would not close manually or automatically. CRS implements AB.CONT-002: =, Condition B =. Condition A CRS directs placing FRVS in service. PO place FRVS in service IAW SO.GU-0001 Section 5.3. If RWCU is isolated before differential flow setpoint is reached, isolation will not be received. Immediate Operator action IAW AB .CONT-0002. HPI USED: STAR 0 RECORD time betwecm C1-A2 and initiating do su re. TIME: Closing the RWCU HV-F004 prior to receiving OHA C1-A2 satisfies this Critical Task. If crew isolated RWC!J prior to isolation signal, Condition A will not be performed. HPI USED: STAR 0 ESG-NRC-S3 Page 12 of 27 Rev.: 01 I IF contacted as Shift Chem Tech, THEN REPORT RWR is the alternate monitoring point and REQUEST status of the RWR sample line. 0 CRS recognizes the following Tech Spec action applies: Primary Containment Isolation Valves 3.6.3 action a Primary Containment Integrity 3.6.1 .I I MODIFY the initial severity of I Crew recognizes rising reactor pressure by: =) OHA D3-D5 "EHC UNIT PANEL 1 OC363" PRESSURE HI" PRESSURE HI" DEHC Bypass Valve Positioning Error alarms LOAD LIMIT LIMITING Various Reactor Pressure indicators 3 OHA B3-E5 "RPV 3 OHA C5-A5 "RPV =1 CRIDS D3372 MN TURB Need to restore valve: to OPERABLE or deactivate the HV-FOC 1 or HV-F004 in the nexi four hours. May also refer to T/S 3.3.2, although both trip systems would already be tripped, and the valves already shut. Some alarms may no: be received if the pressure excursion is terminated before the r setpoint. 0 RO reduces reactor power to maintain the RPV PRESSURE HI overhead alarm clear. Immediate Operator Action IAW AB. RPV-0005. HPI USED: STAR D ES G- N RC-S 3 Page 13 of 27 Rev.: 01 Event I Instructor Activity Expected PlantlStudent Response NOTE: If the crew is in the process of a manual scram when 1037 psig is reached, failure of RPS may not be -ecognized. However, if it is qecognized that RPS did not automatically scram the reactor at 1037 psig, EOP-IOIA should be entered and exited. Comments 0 0

• e e 0 e 0 CRS implements AB.RPV-0005:

=z Condition A Condition D WHEN reactor pressure cannot be maintained <IO30 psig, THEN Crew locks the Mode Switch in SHUTDOWN. Crew scrams the reactor within one minufe of reactor pressure exceeding 1037 psig. (Scramming prior to reaching 1037 psis safisfies this requirement.) - IF Reactor Pressure was above 1037 psig when the reactor was manually scrammed, THEN Crew recognizes Scram Condition and Reactor Power Above 4% or Undetermined EOP Entry Condition by: PRESSURE HI" Various indications of reactor power 3 OHA C5A5 "RPV - IF Reactor Pressure was above 1037 psig when the reactor was manually scrammed, THEN CRS implements EOP-IOIA until all rods are verified fully inserted, then exits EOP-101A and enters EOP-101. RO performs scram actions IAW A6.ZZ-0001 Att. 1. Crew recognizes RPV Level Below 12.5" EOP entry condition by: => OHA C5-A4 "RPV WATER LEVEL LO" Various water level indicators 3 OHA A7-D5 "RPV LEVEL 3" CRS implements EOP-101. Page 14 of 27 HPI USED: STAR RECORD time when Reactor Pressure goes above 1037 psig. TIME: HPI USED: STAR HARD CARD 0 May also have High Reactor Pressure ent*y condition. ESG-NRC-S3 Re.:.: 01 0 PO maintains reactor water level HPI USED: as directed by CRS IAW AB.ZZ-0001 Att.

14. of Mode Switch functions by STAR HARD CARD STAR 0 Crew may recognize partial loss HPI USED: loss/absence of:

SCRAM" SHUTDOWN SCRAM BYP" CLOSURE TRIP BYP" Absence of SRMllRM status lights and alarms 3 OHA C5A3 "MANUAL 3 OHA C5-GI "MODE SWITCH 3 OHA C5-C3 "MSIV 0 Crew recognizes LOCA condition: 3 OHA C6-61 "DLD SYSTEM 5 RM11 9AX314 DLD FLOOR 3 OHA D3-C3 "DRYWELL 5 OHA A4-F5 "COMPUTER PT 3 OHA A7-E4 "DRYWELL ALA RMITRB L" DRN FLOW alarm SUMP LEVEL HI/LO" IN ALARM" PRESSURE HVLO" Rising Drywell Pressure 0 CRS implements AB.CONT-001: Condition A 0 RO/PO ensures drywell cooling maximized. 0 Crew checks Recirc pump seal parameters SRV temperatures HPI USED: STAR 0 ESG-NRC-S3 Page 15 of 27 Rev.: 01 e AIC Loaic Failures: The failure of Drywell Pressure transmitters N094E/G is already inserted. 0 Crew recognizes Drywell Pressure Above 1.68# EOP entry condition by: q OHA A7-D4 "DRYWELL PRESSURE H I/H I" PRESSURE HI" Various system initiations and isolations. q OHA C5-B5 "DRYWELL CRS enters EOP-102, re-enters RO/PO verify automatic actions. Crew recognizes failure of the AIC Core Spray logics to initiate by: EOP-101. 3 NC INlT AND SEALED IN lights extinguished Pump STOPPED indication NC channel breaker status on 1 OC650E NON CLASS 1 E LOAD ISLN CIRCUIT BREAKER STATUS AND C 0 N TRO I- Various valve failures to isolate s NC EDGs not running RO/PO initiate NC Core Spray logic IAW AB.ZZ-0001 Att 5. Crew recognizes failure of the NC RHR logics to initiate by: 3 NC INlT AND SEALED IN lights extinguished Pump STOPPED indication RO/PO initiate NC RHR logic IAW AB.ZZ-0001 Att 4. Core Spray WILL auto initiate if RPV water level reaches -1 29". PClS isolations will occur due to the availability of NSSSS and the PT-NO94NC. Only the Core Spray logic fanout (EDG, sequencer, etc) will bc affected. Also, no drywell pressure indicators are affected by the failures. HPI USED: STAR 0 HARD CARD 0 RHR WILL auto initia% if RPV water level reaches -1 29". HPI USED: STAR HARD CARD ESG-NRC-S3 Page 16 of 27 ReJ.: 01 Event I Instructor Activity Expected PlanffStudent Response Crew recognizes failure of HPCl HPCI WILL auto initiate to initiate by: if RPV water level reaches -38" and is RPV water level by HPCl INIT AND SEALED IN light extinguished capable of maintaining HV-F001 CLSD indication = FV-4880 CLOSED indication itself. FV-4879 CLOSED indication = SI-4919 Turbine Speed indicates zero rpm FIC-R600 Pump Flow indicates zero gpm I 0 RO/PO manually initiate HPCI HPI USED: IAW AB.ZZ-0001 Att. 6. STAR 0 HARD CARD 0 Comments 0 CRS directs maintaining RPV RFPTs will trip and ' level 12.5" to 54" with any SULCV will fail closed combination of: when drywell pressure, ESG-NRC-S3 3 HPCI a RClC FeedwatedCondensate 0 RO/PO maintain RPV level as directed by CRS with: HPCI JAW AB.ZZ-0001 Att. 6 RCIC IAW AB.ZZ-0001 Att. 6 3 0 CRS implements AB.COOL-003: 0 RO/PO trips recirc pumps. Condition 8 0 WHEN Suppression Chamber pressure exceeds 9.5 psig, reaches I .7 psig and cannot be restored. HPI USED: STAR 0 HARD CARD 0 HPI USED: STAR n RRCS RPT trips are failed. Pumps must t tripped manually. May also be tripped JAW EOP-102 guidar for spraying the dtyw Recirc pumps should be tripped prior to THEN CRS directs initiating drywell spray. initiating drywell spray. 2 :e II. Page 17 of 27 Re&.: 01 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE RO/PO place one loop of RHR in drywell spray IAW AB.ZZ-0001 Att. 2. Crew maintains Suppression Chamber Pressure below the Action Required region of the PSP curve without Emergency Depressurizing. CRS directs placing RHR pump in Suppression Pool Cooling and Suppression Chamber Spray. ROlPO place RHR pump in Suppression Pool Cooling and Suppression Chamber Spray CRS directs restoring PClG to SRVs. RO/PO restore PCIG to SRVs IAW AB.ZZ-0001 Att.

3. IAW AB.=-0001 Att. 9. HPI USED: STAR 0 HARD CARD 0 - IF 'A' RHR logic was NOT manually initiatl THEN 'A' RHR canni spray the drywell.

PSP will by reached approximately elevei minutes after the LO starts with no mitigal action. HPI USED: STAR HARD CARD HPI USED: STAR 0 HARD CARD 0 If necessary, Crew prevents injection from Low Pressure ECCS not required for adequate core cooling. HPI USED: STAR HARD CARD ESG-NRGS3 Page 18 of 27 1 4 3 ' 01 I HC.OP-BL.ZZ-0026{Q] ATTACHMENT Ib Page I of 5 FORM +I ATWS-RPT Channel Check [for Surveillance Log Item 6) T0da.y'~ Date Operational Condition Date RPV LEVEL ilPV PRESSURE )PER 1 ACCEPTABLE LIhllTS : I I COMMENTS: Hope Creek Page 4? of 99 Rev. 222 A. B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Alarm Response Procedures (Various) G. H. I. HU-AA-1081 Fundamentals Toolkit J. HU-AA-1211 Briefing K. OP-AA-101-111-1003 Use of Procedures L. M. OP-AA-101-111-1004 Operations Standards N. OP-AA-101-112-1002 On-Line Risk Assessment

0. OP-AA-106-101-1001 Event Response Guidelines P. OP-HC-108-106-1001 Equipment Operational Control Q. OP-AA-108-114 Post Transient Review R. S. HC.OP-DL.ZZ-0026 Surveillance Log T. HC.OP-SO.BB-0002 Reactor Recirculation System Operation U. HC.OP-SO.BC-0001 Residual Heat Removal System Operation V. HC.OP-SO.BE-0001 Core Spray System Operation W. HCOP-S0,GU-0001 Filtration, Recirculation, and Ventilation System Operation X. HC.OP-SO.%-0001 Reactor Protection System Operation Y. HC.OP-SOSF-0001 Reactor Manual Control System Operation Z. HC.OP-AB.=-0001 Transient Plant Conditions AA. HC.OP-AB.RPV-0005 Reactor Pressure BB. HC.OP-AB.CONT-0001 Drywell Pressure CC. HC.OP-AB.CONT-0002 Primary Containment DD. HC.OP-AB.CONT-0004 Radioactive Gaseous Release EE. HC.OP-AB.ZZ-000 Reactor Scram FF. HC.OP-EO.ZZ-0101 RPV Control GG. HC.OP-EO.ZZ-0102 Primary Containment Control HH. HC.CH-TI.ZZ-0012 Chemistry Sampling Frequencies, Specifications, and Surveillances TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid HU-AA-101 Performance Tools and Verification Practices HU-AA-104-101 Procedure Use and Adherence OP-AA-101-111 Roles and Responsibilities of On Shift Personnel OP-HC-108-115-1001 Operability Assessment and Equipment Control Program Industry Events

11. LER 397-07001 RHR Pressure Switch Found Isolated (3/21/2007)

JJ. LER 354-02001 RHR Min Flow Line Found Isolated (3/20/2002) KK. Event #249-000324-1 RHR Pressure Switch Found Isolated (6/13/2000) ESG-NRC-S3 Page 20 of 27 Re/.: 01 ESG-NRC-S3 IO1 I.

• Crew initiates closure of RWCU HV-FO04 within two minutes of receiving OHA C742 "RWCU DlFF FLOW HI". KIA 223002 Primary Containment Isolation System I Nuclear Steam Supply Shut-Off A4 Ability to operate and/or monitor in the Control Room A4.01 Valve Closures RO 3.6 SRO 3.5 A4.06 Confirm initiation to completion RO 3.6 SRO 3.7 The RWCU System has failed to isolate automatically.

HV-F001 fails to isolate manually. Failurt of the Crew to manually isolate the system will result in a bypass of the Reactor Coolant and Primary Containment boundaries and release of radioactive materials to the Reactor Building. Two minutes is deemed adequate time to affect isolation from the time confirmation of failure of the automatic isolation function is received.

2.

• Crew scrams the reactor within one minute of reactor pressure exceeding 7037 psig. (Scramming prior to reaching 7037 psis satisfies this requirement.)

KIA 241 000 ReactorITurbine Pressure Regulating System A2. Ability to (a) predict the impacts of the following on the REACTORTURBINE PRESSURE REGULATING SYSTEM; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences o* those abnormal conditions or operations: A2.04 Failed open/closed control/governor valves RO 3.7 SRO 3.8 A4 Ability to manually operate and/or monitor in the control room: A4.02 Reactor Pressure RO 4.1 SRO 4.1 The Pressure Regulating System is failed and reactor pressure will continue to rise. Neither RPS nor RRCS will automatically scram the reactor. Lo-Lo set is also failed. Without operator actioa7, reactor pressure will rise until the 1108 psig safety relief valve setpoint is reached. The only w~ty to reduce pressure is to shutdown the reactor to lower steam generation. Manual operator action is required to accomplish this. Based on the worst case rate of pressure rise in this scenario (assuming the Immediate Operator Action to reduce power and maintain the RPV PRESSURE HI overhead alarm clear), it will take reactor pressure over a I .5 minutes to reach the scram setpoint of 1037 psig. An additional minute past this point is adequate time to recognize both the risins reactor pressure and failure to scram and insert a manual scram. ESG-NRC-S3 Page 21 of 27 F:ev.: 01

3.

• Crew maintains Suppression Chamber Pressure below the Action Required region of the PSP curve without Emergency Depressurizing.

K/A 295024 High Drywell Pressure EA1 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: EA1 .I 1 Drywell Spray RO 4.2 SRO 4.2 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 WA 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. A LOCA condition while i I the action required region of the Pressure Suppression Pressure curve, could cause design containment limits to be exceeded. Based upon the rate of pressure increase in this scenario, the Crew has over ten minutes to initiate Drywell Sprays and prevent entry into the Action Required region of the PSP curve. This will prevent an unnecessary Emergency Depressurization, which IS a significant challenge to the Suppression Pool and would cause the Cooldown Limit for the Reactor Coolant system to be unnecessarily exceeded. Reducing reactor pressure within the cooldown limit may also delay/prevent entry into the action required region. ESG-NRC-S3 IO1 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE ylbJ EVENT Loss Of OfFsite PowerISBO Y LOCA yJ EVENT Internal Flooding LOSS OF SUPPORT SYSTEMS: TRANS I ENTS : Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Inadvertent MSIV Closure Loss of ssw Loss of SACS Loss of Instrument Air Inadvertent SRV Opening Y Manual Scram COMPONENTlTRAINlSYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT __ Y/N KEY EQUIPMENT __ Hard Torus Vent HPCI 1 E 4.16KV Bus SLC CRD 1E 125VDC SACS HxlPump EDG KEY SYSTEMS 120VAC 481 /482 Inverter NB RHR SRVs RClC CondensatelFeedwater SSW Pump PClG 500KV AC Power OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE ybJ Y OPERATOR ACTION Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment Emergency Depressurize RPV W/O High Pressure Injection Initiating LP ECCS with No High Pressure Injection Available Restoration of AC Power after a LOP (EDG / Offsite) Monitoring and Control of SACS heat loads Preventing LVL 8 trip of Feedwater during a transient Align Core Spray Suction to CST when at NPSH limits Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus Inhibit ADS during ATWS Complete this evaluation form for each ESG. ESG-NRC-S3 Page 23 of 27 Rev.: 01 Rx Power: 90% MWe (May vary slightly): 11 00 Work Week: A Risk Color: Green Activities Completed Last Shift: 0 0 Power reduction to 90% power. Making preparations to swap TACS to '8' SACS L op IAW HC.OP-SO.EG-0001 for work week planned maintenance on 'A' SACS Pump. The RB EO has been briefed and is standing by at the SACS pumps. SSW C Traveling screen has been run in preparation for the swap. The Yard EO has been briefed and is standing by E i the SSW Intake Structure. Major Activities Next 12 Hours: 0 Continue power reduction to 84.5% for removal of A RFPT for maintenance troubleshooting. o RE Guidance: Insert rods to 84.5% power using 9D and 9E rods. Swap TACS to 'B' SACS Loop IAW HC.OP-SO.EG-0001. The RB EO has been briefed and is standing by at the SACS pumps. Protected Equipment: None Tagged EauiRment: (\lone ESG-NRC-S3 Page 24 of 27 RE:^.: 01 IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST - - - iXAMINATION SCENARIO GUIDE (ESG) REVIEW/VALIDATION Note: This form is used as guidance for an examination team to conduct a review for the propos 3d exam scenario(s). Attach a separate copy of this form to ESG- NRC-S3 REVIEWER. - The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events. Each event description consists of: 0 0 0 0 0 The event termination point 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 use of non-mechanistic failures (e.g pipe break) should be limited to one or a credible preceding event has occurred. The events are valid with regard to physics and thermodynamics. Sequencinghming of events is reasonable (e.g. the crew has time to respond to the malfunctions in i n appropriate time frame and implements procedures and/or corrective actions). Sequencingltiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. If time compression techniques are used, scenario summary clearly so indicates. The simulator modeling is not altered. All crew competencies can be evaluated. Appropriate reference materials are available (SOERs, LERs, etc.) Proper critical task methodology used IAW NRC procedures. ESG-NRC-S3 Page 25 of 27 REV.: 01 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Note: The following criteria list scenario traits that are numerical in nature. for each scenario. ESG: NRC-S3 SELF-CHECK Comments: Total malfunctions inserted: 5-8 Malfunctions that occur after EOP entry: 1-2 Abnormal Events: 2-4 Major Transients: 1-2 EOPs entered requiring substantive actions: 1-2 EOP Contingency Procedures requiring substantive actions: 0-2 Approximate scenario run time: 60-90 minutes Critical Tasks: 2-3 Technical Specifications are exercised during the test 22 The section below should be complc ted , ESG-NRC-S3 Page 26 of 27 Rev'.: 01 A Crew Validation Rev: 00 Date Validated: Validation Comments Disposition ........................................................................... ////////////ri////////////////////////////////////////~/////////////~~//~~////~///~ This will be less time consuming than A. Need to add a failure to either FOOl or F004 because if they close it earlv. then the CRS will not aet TS call. Slow down rate of rise of TCV failure. No real time to do anything about it. Failed Fool to close manually and automatically. Changed ramp time from 10 minutes to 15 minutes. Overall time to respond is now about 2 minutes from 1 st alarm until scram setpoint with no action taken. Crew Validation Rev: Date Validated: ESG-N RC-S3 Page 27 of 27 - Rev.: 01 TRAINING USE ONLY WORK WEEK CHANNEL: A ] 11 E ONLINE RISK: GREEN Reactor Power: 90% MWe (May vary slightly): I100 Activities Completed Last Shift: 0 Power reduction to 90% power. 0 Making preparations to swap TACS to 'B' SACS Loop IAW HC.OP-SO.EG-0001 for work week planned maintenance on 'A' SACS Pump. SSW D Traveling screen has been run in preparation for the swap. Major Activities Next 12 Hours: - Continue power reduction to 84.5% for removal of A RFPT for maintenance troubleshooting . Swap TACS to 'B' SACS Loop IAW HC.OP-SO.EG-0001. The RB EO has been briefed and is standing by at the SACS pumps. The Yard EO has been briefed and is standing by at the SSW Intake Structure. Heightened Awareness: - None Protected Equipment: None Tagged Equipment: None Reactivity: Continue power reduction to 84.5% for removal of A RFPT for maintenance troubleshooting. o RE Guidance: Insert rods to 84.5% power using 9D and 9E rods. SCENARIO TITLE: NRC SCENARIO 4 SCENARIO NUMBER: ESG-NRC-S4 EFFECTIVE DATE: Effective when signed EXPECTED DURATION: 66 minutes REVISION NUMBER: 02 PROGRAM: -1 L.O. REQUAL -1 INITIAL LICENSE I[ OTHER - REVISION

SUMMARY

1. Validated time 66 minutes. 2. Added to TO sheet, "Return

'B' RFPT to service IAW HC.OP-SO-AE-0001 Section 5.7" 3. Added driver guidance for I&C action for Flow Unit 4. Added that the light is extinguished for Seismic panel. - Archie E. Faulkner 12/6/2008 PREPARED BY: Instructor DATE APPROVED BY: fu 2 pJ Cr bper4ions Training A Manag& or Designee DATE APPROVED BY: Operations Director or Designee Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safe1 operate the plant during normal, abnormal, and emergency plant conditions. (Critical tasks within this examination scenario guide are identified with an " *.") II. MAJOR EVENTS: A. B. C. D. E. F. G. H. I. J. Place 'B' RFPT in service Power ascension SRV 'H' Tailpipe temp sensor fails upscale 'C' Recirc Flow Unit Summer fails downscale Seismic Event RClC Steam Leak Trip of Service Air Compressor Air Leak w/Multiple Rod Drift LOP w/ EDG failures LOCA w/Steam Cooling \I. SCENARIO

SUMMARY

The scenario begins with the plant at -84.5% power, 1000 MWe, with

'B' RPFT running at loo( rpm. The PO will place 'B' RFPT in service. Power will be raised to 90% with Reactor Recirc flc SRV 'HI Tailpipe Temperature fails upscale for SRO Tech Spec determination. 'C' Recirc Flow Unit Summer will fail downscale causing a half scram on the AllA2 RPS channels. A seismic event greater than the SSE will occur. Following the seismic event, a steam leak will develop i the RClC room. RClC will fail to automatically isolate, but can be isolated from the Control Rot (Critical Task). After the RClC steam leak is isolated, the 1 OK107 Service Air Compressor wil trip. When the 00K107 is placed in service, the pressure transient will cause an air leak to develop on the scram air header. The air leak will cause multiple control rods to drift in, requiri a manual reactor scram (Critical Task). After the scram, an aftershock will occur. The aftershock will cause a loss of offsite power and LOCA. Only the 'A' EDG will start. The HPCl Fool will fail to open, rendering HPCl inoperable. When the 'A' RHR pump starts, the 'A' EDG will trip. This will result in no available injection sources. When RPV water level reaches -200" the Crew must emergency depressurize (Critical Task). After the Crew opens five SRVs, the ' EDG will be restored to service. The 'C' RHR pump will fail to automatically start and inject, an must be started and aligned for injection by the Crew (Critical Task). After RPV water level is restored to above -185", the 'A' EDG will be restored to service. This will allow containment control to be exercised. The scenario is terminated when the RPV has been depressurized anc RPV water level restored. ESG-NRC-S4 Page 2 of 29 Re Initial INITIALIZE the simulator to full power, MOL. REDUCE power to 84 5% using recirc. ENSURE 10K107 Service Air Compressor is in service. REMOVE B RFPT from service as follows: 1. PRESS RFPT A(B,C) SPEED CONTROLLER "INS" pushbuttonto select "SPD DEMAND." 2. PLACE the Reactor Feed Pump in manual by pressing the M pushbutton on RFPT SPEED CONTROLLER AND OBSERVE "M" (manual) illuminates.

3. PRESS DECREASE J, pushbutton on RFPT A(B,C) SPEED CTRLR to reduce speed/flow of the Reactor Feed Pump to be removed from service AND ALLOW the other Reactor Feed Pumps to assume the flow of the Reactor Feed Pump beinq removed from service.

Initial 4. WHEN the Reactor Feed Pump being removed reaches 0 gpm flow to RPV, PRESS DECREASE J pushbutton on RFPT A(B,C) SPEED CTRLR. UNTIL SPD is < 1000 RPM. Discharge Stop Check Valve Motor Operator. exception of step

5.1.9 Description

PREPARE a Fire Alarm for FA01 6. PREP FOR TRAINING (Le., RMI 1 set points, procedures, bezel covers) I 1 ~ ~~ ~ ~~ i COMPLETE the Simulator Ready for TraininglExammation Checklist. ENSURE Data Collection is trending the following datapool variables: 0 RClC Room Temp hvtr4110 0 0 0 W/R Reactor Water Level: rrlnO9la or equivalent Fuel Zone Reactor Water Level: rrlfzcha or equivalent Instrument Air Header Pressure: iapiarcaliapiarcb or equivalent ESG-NRC-S4 Page 3 of 29 Rt L 7 ET # Description -.'- COMMAND: PURPOSE: imf Initiates PC07B aftershock with LOP/LOCA EVENT ACTION: et-array(6) EVENT ACTION: COMMAND: PURPOSE: ~______ ~ EVENT ACTION: 11 COMMAND: PURPOSE: EVENT ACTION: 12 COMMAND: PURPOSE: EVENT ACTION: 13 COMMAND: PURPOSE: EVENT ACTION: 14 COMMAND: PURPOSE: a ~ iapiarca <= 75 /I Instrument Air header pressure <= 75 psig imf cdOl1827 Inserts drifting rods if pressure drops near 70 psig before delay times out. iapiarca <= 75 // Instrument Air header pressure C= 75 psig imf cd012227 Inserts drifting rods if pressure drops near 70 psig before delay times out. iapiarca C= 75 I/ Instrument Air header pressure c= 75 psig imf cd062627 Inserts drifting rods if pressure drops near 70 psig before delay times out. rh:bkr(l) >= 1.0 // 'A' RHK pump running Trips the 'A' EDG - - __ 9 EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: et-array( 8) dmf dg02a Restores 'A' EDG to service. ia:Oprun >= 1.0 /I OOKl07 running __ Inserts air leak when OOKlO7 is started. 10 EVENT ACTION: COMMAND: PURPOSE: iapiarca C= 75 // Instrument Air header pressure <= 75 psig imf cdO11427 Inserts drifting rods if pressure drops near 70 psig before delay times out. ESG-NRC-S4 Page 4 of 29 Rev: 02 I Init/al Description Delay Ramp Trigger lnit Val Final' 'A RC10 RClC Steam Failure to Autdsolate --- --- --- --- NONE --- --- NONE --- --- HP04 HPCl system fails to start __ __ DGOlC'C' EDG Failure to Start (Auto or Man) --- --- NONE --- --- __ --- 1 --- NONE --- --- DG02B Failure of '6' EDG --- --- NONE --- --- --- --- NONE --- -I- --- --- NONE --- --- --- --- ET-I --- 100' b __ __ __ __ I --- --- ET-2 --- 0% ~~~~ ~ ~~ DG02D Failure of 'D' EDG RH08C 'C' RHR Failure to AuteStarVlnject ADO1 Failure of ADS to Actuate AD04H SRV H Tailpipe Temp fails upscale NM12C Recirc Flow Summer failure RC09 Steam Line Break in the RClC Room AN-A2A5 Cry Wolf Fire Protection Panel Alarm 809,) - 1 :oo 5100 ' ET-3 25% 3:OO --- ET-3 --- --- ~ --- --- ~~ ~ IAOlA Trip of 10K107 Service Air Compressor IA02 Gradual Loss of Instrument Air --- ET-5 --- --- --- ET-9 -- CD011427 Control Rod Drift In 14-27 CD011827 Control Rod Drift In 18-27 CD012227 Control Rod Drift In 22-27 REMOTE/FIELD FUNCTION

SUMMARY

I I 1 --- ET-9 --- -I- 2:oo --- ET-9 --- --- 2:oo 2:oo --- ET-9 --- --- - __ CD062627 Control Rod Scram 26-27 EG12 Loss of Offsite Power

--- ET-9 --- --- --- --- ET-6 --- --- -- 2:oo ~~ ~ ~~ RR31A2 Large Break LOCA 3:OO 500 ET-6 0 Yo 3% DG02A Failure of 'A' EDG 00:03 --- ET-I 4 --- --- _- I HP08 HPCl Aux Oil Pump Breaker Initial 1 --- 1 --- I ET-7 I --- I TAGGZD I Description Delay Ramp Trigger Init Val --- --- ET-4 --- HV06 CVH300 RBVS Fan rDG05 'A' EDG Shutdown Relay ~ HV05 BVH300 RBVS Fan HV04 AVH300 RBVS Fan I 00:05 I --- I ET-8 I --- 1 RESET I STC3 STC3 -4 1 sec E T-4 --- --- ET-4 --- I sec -rDGOl 'A' EDG Lockout Relay HV03 CV301 RBVE Fan HV02 BV301 RBVE Fan HVOI AV301 RBVE Fan I 00:20 I --- I ET-8 I --- I RESt T I 3 sec ET-4 --- ESG-NRC-S4 Page 5 of 29 Rev: 02 Trigger lnit Val Final I i Ramp 2 I I I -1 ESG-NRC-S4 Page 6 of 29 Rev: 02 Event I Instructor Activity Expected PlantlStudent Response Place '6' RFPT in-service: e Crew places IB' RFPT in Comments CRS directs PO to place 'B' RFPT in service IAW OP-SO.AE-0001. PO opens HV-I769B, REACTOR FEED PUMP B DlSCH STOP CHK VLV MOT OPER. PO presses the "INS" pushbutton as required to select "DEMAND" on the in-service RFPT(S), whose demand will be matched PO presses the "INS" pushbutton as necessary, for the RFPT to be placed in-service, to select RFPT B "SPEED CTRLR DEMAND". PO presses the INCREASE t or DECREASE 1 push button on the Pump being placed in-service as necessary, to equalize the " D E MAN D " sign a Is , W H I L E MONITORING the following: a RFPT Discharge Pressure a RFPT "DEMAND" 3 RFPT "FLOW' When flow and speed are approximately equal, PO transfers RFPT B SPEED CTRLR to automatic by pressing the A pushbutton AND observing "A" i I I u m i na t es. CRS directs raising power to 90% using RE guidance. HPI USED: STAR q PEER CHECK OP BARRIERS q HPI USED: STAR PEERCHECKU OP BARRIERS HPI USED: STAR I3 PEER CHECK q OP BARRIERS I7 ESG-NRC-S4 Page 7 of 29 REW: 02 Event I Instructor Activity Expected Plant/Student Response As RE PROVIDE the following guidance: 0 SPRl and Enhanced Stability Guidance are valid for the remainder of the ma neuver 0 Power has been steady for the last hour. 0 Target rod line has been reached. 0 Raise power to 90% with reactor recirculation and hold for thermal limit checks. Comments 0 RO monitors the following when changing Recirc Pump speed: 3 XR-R603A,B,C,D - C51 (NEUTRON MONITORING) APRM A(B) FLOW A(6) JET PUMP FLOW CORE PLATE DlFF PRESS/JET PUMP FLOW 3 B31-FR-RG14 RECIRC LOOP = FR-R61 IA(B) RECIRC LOOP 3 PDR-R613/FR- FR-R613 SRV Tailpipe Temperature After the Crew co 0 0 0 RO raises Reactor Recirc Pump speed by intermittently pressing INCREASE pushbutton on SIC- R621A(B) PUMP A(B) SPD CONT. Crew recognizes SRV FOI 3H high tailpipe temp by: OHA CI-A3 "ADS/SAFETY RELIEF VLV NOT CLOSED" Flashing red alarm light on TRR-6 1 4 Crew validates no SRV open by: Absence of acoustic monitor indication No change in Main Generator MWe No steam flow feed flow mismatch 0 Crew recognizes probable SRV tailpipe temperature failure due to reading unrealistically high. Crew contacts Maintenance. HPI USED: STAR PEERCHECK17 OP BARRIERS ESG-NRC-S4 Page 8 of 29 Red/: 02 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - 7 Event I Instructor Activity Expected PlantlStudent Response Comments RECIRC LOOP FLOW SUMMER 'C' FAILURE: At the discretion o Examiner, LOOP FLOW SUMME FAILURE to 0 percent ~ TRIGGER ET-2 (RECI a CRS recognize the following Tech Spec action applies: a Accident Monitoring IAW TIS 6.9.2 Must restore within 30 days or initiate actions Instrumentation Table 3.3.7.5-1 Action 80a Crew monitors Reactor power, pressure, and level and ensure plant conditions are stable. Ensures no scram setpoints have been exceeded. Crew recognizes RPS 1/2 scram by: 3 OHA C3-A3 "REACTOR SCRAM TRIP LOGIC A2" M 0 N I TOR I N G SYSTEM " RPS Trip Logic A2 NORMALIRESET status lights extinguished Pilot Scram Valve Solenoid LOGIC A NORMAL status lights for all four groups extinguished. MONITORING SYSTEM SCRAM Y TRIP" SCRAM Y TRIP" s OHA C5-A1 "NEUTRON CRIDS D2127 "NEUTRON 3 CRlDS D2132 "REACTOR ESG-NRC-S4 Page 9 of 29 Rev: 02 I Event I Instructor Activity Expected Plant/ Student Response 0 Crew recognizes 'A', 'C', and 'E' APRMs Upscale by: 3 OHA C3-C4 "APRM SYS A UPSCALE TRIP/INOP" APRMs A,C, and E "UPSC TR OR INOP" status lights APRM A,C, and E "UPSC ALARM" status lights CHANNEL C UPSCALE TRIP YES" UPSCALE THERMAL TRIP ALARM" 3 C3-D4 "APRM UPSCALE" =1 CRIDS D2143 "APRM 3 CRIDS D4306 "APRM CH C 0 Crew recognizes 'C' RECIRC LOOP FLOW SUMMER FAILURE Downscale by: FLOW UNIT C and A "COMPAR" status lights APRM A, C, and E "UPSC ALARM" status lights Comments 0 CRS implements AB.IC-0004: 0 RO bypasses 'C' Flow Unit. 0 CRS refers to DD.ZZ-0020 for a failed PPC Sensor. CRS directs Reactor Engineering to Evaluate the flow unit failure on the PPC. RO directs I&C to place the MODE Switch, on the applicable flow unit, to the "UNLABELED" position between STANDBY and 0 RO verifies RPS trip clear. Condition F IF directed to place the Flow Unit C MODE Switch in the unlabeled position, THEN CHANGE Malfunction NM12C Final value to 100%. ZERO. ESG-NRC-S4 Page 10 of 29 RE'K 02 RO resets RPS trip as follows: a TURN the affected RPS Trip Logic key to RESET, AND RETURN to the NORMAL position. VERIFY that RPS is reset. CRS determine no Tech Spec actions required. Enter Tracking Action statement for: Table 3.3.6-1 Function 6 EarthquakeBteam Leak: At the discretion Examiner: PLAYtheEa Sound Effect (if available) a medium volume for about motion then it stops" TRIGGER ET-3 (Seismic Crew recognizes Seismic Event by: 3 OHA C6-C4 "SEISMIC MON PNL C673" TROUBLE ALARM TRBL" Response Spectrum Analyzer indications on 1 OC650C Loud rumbling noise (if available) 3 CRlDS D3977 "SEISMIC - IF Crew calls National Earthquake Center, THEN REPORT a seismic event of 6.0 on Richter scale centered 12 miles east of Wilmington, DE. - IF Crew calls Security, THEN REPORT the Security system is intact. 0 Crew monitors crit ica I parameters to determine if plant is stable. CRS implements AB.MISC-0001: AB.MISC-0001 action: Condition E provided for reference Condition F only. Due to the pace of the scenario, it is unlikely they will be implemented. ESG-NRC-S4 RO/PO implement AR.ZZ-0011 Attachment C4. Page 11 of 29 Rev 02 Event / Instructor Activity Expected PlantlStudent Response dispatched to 106673, 0 THEN REPORT: 0 The Event Indicator is WHITE The tape machines have advanced but are not running The Amber Alarm light on the Seismic Switch Power Supply drawer is lit. Alarm Light is extinguished. 0 The Amber SMA-3 Event Comments IF directed to reset 10C673, THEN DELETE Malfunction PC07B and re-insert Malf PC07B with trigger ET-6. 0 ESG-NRC-S4 Crew dispatches ABEO to 106673. Crew recognizes a seismic event >0.1 g has occurred RO/PO direct ABEO to reset I OC673 IAW SO.SG-0001. RO/PO record Seismic Response Spectrum Analyzer lights on AR.ZZ-001 I Att. C4-I. RO/PO reset Seismic Response Spectrum Analyzer IAW Crew determines a shutdown IAW l0.ZZ-0004 is required. Crew recognizes a steam line break in the RClC room by: SO.SG-0001. z OHA B1-A2 "RCIC STEAM LINE DlFF PRESSURE HI" PANEL 1QC671" Fire Comp Pt FA016 "ROOM 41 10 RClC PUMP AND TURBINE ROOM" RClC room temperature trending up (Rm 41 IO) Lowering Main Gen MWe Offsite release rate trending UP RClC Turbine Inlet Pressure on PI-R602 ISLN INlT status lights 3 OHA A2-A5 "FIRE PROT Page 12 of 29 B1-A2 and ISLN INlT status lights will be received if the leak severity reaches 80% before being isolated. (about 5 minutes) A2-A5 Fire Alarm will be received two minutes after the leak starts. Re\ : 02 i I Event I Instructor Activity Expected Plantistudent Response Comments 0 Crew announces steam leak in RClC room on plant page. Crew recognizes failure of RClC to isolate by: - IF dispatched to RClC Room, THEN REPORT the room is filled with steam. HV-F007 valve position HV-F008 valve position RClC room temperature trending up (Rm 41 IO) HV-F008 using Control Room keylock switches. PO closes HV-F007 AND

• Crew closes the RCIC HV-FO07 OR HV-F008 before RClC Room temperature reaches 250 degE Only applicable if isolation signal received.

HPI USED: STAR I7 PEER CHECK 0 Immediate Operator Action IAW RECORD RClC Room 41 10 temperature whc n HV-F007 F008 arc closed. AB .CONT-0002 Temperature: 0 RClC Room temperature reaches 1 15 degrees, THEN CRS implements 0 Crew recognizes abnormal EOP-I 03. gaseous radioactive release by: 3 OHAC6-C1 RADIATION MON ITORl NG ALARM/TRB L" RMI 1 9RX580 SPV Effluent alarm SPDS indication Condition A Condition C 0 CRS implements AB.CONT-004: ESG-NRC-S4 Page 13 of 29 Reb 02 Event I Instructor Activity Expected PlantlStudent Response - IF dispatched to secure Rx 0 B Id g Ventilation , THEN: REFER to SO.GU-0001 Section 5.3 fans TRIGGER ET-4 to secure Comments 0 PO places FRVS in service IAW SO.GU-0001 Section 5.3. CRS recognize the following Tech Specs actions apply: a Reactor Core isolation Clg

3.7.4 Primary

Containment Isolation Valves 3.6.3 (Only if failure to isolate is observed) Crew recognizes loss of 1 OK1 07 by: OHA A2-B2 "COMPRESSED AIR PANEL OOCI 88" = OHA A2-A1/A2 "INST AIR HEADER NB PRESS LO" = CRIDS D4601 "INSTR AIR SPLY HDR A PRESS LO" SPLY HDR B PRESS" LO OVLD/PWR FAIL light Lowering Service and Instrument Air pressures PO places 00K107 in service IAW AB.ZZ-0001 Attachment

7. = CRIDS D4602 "INSTR AIR 0 CRS implements AB.COMP-001:

Condition A Page 14 of 29 HPI USED: STAR PEERCHECKCI FLAGGING 0 OP BARRIERS 0 With RClC inoperable operation may continue provided HPCl is operable. Must restore RClC in 14 days or be in at least HOT SHUTDOWN within the next 12 hours and reduce reactor pressure to 5 150 psig in the following 24 hours. (Note that a shutdown is already required dut: to the seismic event) The primary purpose crf the air malfunctions is to exercise the immediate operator actions for trip of the inservice service air compressor and multiple rods drifting ir. The pace may not allcw full implementation of the abnormal. Immediate Operator Action IAW AB.COMP-0001. HPI USED: STAR CI HARD CARD CI PEER CHECK 0 ESG-NRC-S4 Re\: 02 - IF dispatched to check status Instrument Air Header of RACS demins, AND the EIAC is running, demins are isolated. =, Condition C Pressure reaches 85 psig, THEN CRS implements THEN REPORT the RACS AB.COMP-0001: dispatched to check status of HV-11416, AND Remote Function IAOI status is ONLINE, THEN REPORT the HV-11416 is open. IF dispatched to investigate the Crew dispatches TBEO and zp of 1OK107, THEN REPORT VIBRATION ALARM and VIBRATION SHUTDOWN alarms were in. Maintenance to investigate trip of 1 OK1 07. The air leak is aut inserted when the started ENSURE ET-9 tri 00K107 is manua I 9ir Leak: I Crew recognizes air leak by: =' 3 = 3 3 - IF dispatched to check status of RACS demins, AND the ElAC is running, THEN REPORT the RACS demins are isolated. - IF dispatched to check status AND Remote Function IAOI itatus is online, THEN REPORT the HV-11416 is open. of HV-11416, OHA AZ-A1/A2 "INST AIR HEADER NB PRESS LO" AIR PANEL OOCI 88" CRlDS D4601 "INSTR AIR SPLY HDR A PRESS LO" CRIDS D4602 "INSTR AIR SPLY HDR B PRESS" LO Lowering Service and Instrument Air pressures OHA A2-B2 "COMPRESSED CRS implements AB.COMP-001: 0 - IF Instrument Air Header Pressure reaches 85 psig, THEN CRS implements = Condition C Condition A AB.COMP-0001: Rev 02 ESG-N RC-S4 Page 15 of 29 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE - Multiple Rod Drifts: 0

• Crew recognizes multiple rods drifting into the core by:

OHA C6-E3 "ROD DRIFT' Multiple "DRIFT', lights on Full Core display RWM drifting rods indication ALARM ALM" = Lowering reactor power and Main Generator output RO locks the Mode Switch in SHUTDOWN. Crew scrams the reactor within two minutes of rod drifts. 3 CRIDS C078 "ROD DRIFT 0 RO performs scram actions IAW AB.ZZ-0001 Att

1. 0 Crew recognizes RPV Level Below 12.5" EOP entry condition by: 3 OHA C5-A4 "RPV WATER LEVEL LO" Various water level indicators 3 OHA A7-D5 "RPV LEVEL 3" 0 CRS implements EOP-101. 0 PO controls RPV water level as directed by CRS IAW AB.ZZ-0001 Att

14. RECORD the time between OHA C6-E3 and reactor scrammec!, TIME: HPI USED: STAR 0 HARD CARD 0 ESG-NRC-S4 Page 16 of 29 Rev 02 I Event I Instructor Activity Expected Plant/

Student Response Comments motion then it stops" TRIGGER ET-6 Afte rs h oc k/LO P/LOC A : 5 minutes after the scram, - 0 R, at the Lead Examiners discretion, PLAY the Earthquake Sound Effect (if available) at (LOP/LOCA) I 0 - IF dispatched to investigate the failure of BID EDGs to start, THEN REPORT both EDGs have Lube Oil Low Pressure Shutdown alarms. There is oil on EDG room floors. Crew recognizes Loss of Offsite Power by: =. OHA "STA SERVICE TRANSFORMER TROUBLE" for all transformers =I TRIP indication for all 500 KV breakers =. Flashing TRIP lights for all previously closed bus infeeds. Numerous OVLDlPWR FAIL lights. Crew recognizes failure of the B/C/D EDGs to start and load by: Engine STOP lights Output breaker TRIP lights OVLD/PWR lights on associated Channel components RO/PO attempt to start the BUD EDGs. CRS implements AB.ZZ-0135. Crew dispatches NE0 and/or Maintenance to investigate failure of B/D EDGs to start. Only 'A' EDG will start. 'A' EDG will trip when the 'A' RHR pump is started. HPI USED: STAR PEERCHECKO Immediate Operator Action IAW AB.ZZ-O1:;5 ESG-NRC-S4 Page 17 of 29 Rei 02 I Event I Instructor Activity Expected Plant/ Student Response - IF dispatched to investigate the failure of the 'C' EDG to start, THEN REPORT there is a blown fuse on DC Circuit 3 on the CC421 panel. - IF directed to start the EDG using either local control switch, THEN REPORT it did not work. - IF dispatched to check 86, SFR, and SDR relays for 'C' EDG, THEN REPORT: 0 86 lockout relays are reset (CC422, elev 137') 0 Blue buttons on SFR and SDR are out (de-energized) (CC421 elev 102') Crew dispatches NE0 and/or Maintenance to investigate failure of 'C' EDG to start. (AR.KJ-0005 Att. 37A) - IF dispatched to determine 0 Crew recognizes HPCI oil status of HPCI, problem by: Comments THEN REPORT =1 0 HPCl Aux oil pump is 3 0 HPCl is idle running . =3 0 HV-F001 is closed IF directed to open the breaker for the HPCl Aux Oil pump, =3 (72-251 042) THEN TRIGGER ET-7. - IF directed to open HV-F001 by hand, REPORT HV-F001 will not move OHA BI-A4 "HPCI TURBINE TRIP" DISCH FLOW LO" HPCl Trip Throttle and Governor valves closed w/Aux Oil pump running and "TURB TRIP SOLENOID ENERGZ" light not lit CRIDS D5435 "HPCI BRG OIL LO PWHVFOOI OPN" OHA BI-E5 "HPCI PUMP 0 CRS directs injecting with 'A' SLC pump. 0 RO/PO start the 'A' SLC pump. Only available injection source. HPI USED: STAR PEER CHECK ESG-NRC-S4 Page 18 of 29 Re! : 02 ND EXPECTED RES - IF called as the ESOC, THEN REPORT both the Hope Creek AND Salem switchyards are de-energized. It will take a minimum of 6-10 hours to restore power once the transient has been investigated. 0 Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by: 3 OHA C8-F1 "SUPPR POOL TEMP HIGH" Flashing 95 degree status light on 1OC65OC RMI 1 9AX8331834 alarm Various Suppression Pool temperature indicators Level Above 78.5 In EOP entry condition by: 0 Crew recognizes Supp Pool 2 OHA B1-C3 "SUPPRESSION POOL LEVEL HIILO'" = Various Suppression Pool level indicators Given the lowering RFV water level, and 'A' RHR being the only available RHR pump, the Crew may not plac,e 'A' RHR in Suppression Pool cooling at this time. Given the LOP and th.3 unavailability of HPCl and RCIC, there is nothing the Crew can do to lower Suppression Pool water level at this time. 0 Crew recognizes trip of the 'A' EDG by: Diesel engine STOP light Flashing generator breaker TRIP light = OVLD/PWR FAIL lights on associated channel loads IF dispatched to investigate the 0 Crew dispatches NE0 and/or trip of the 'A' EDG, THEN REPORT you heard the EDG slow down, then speed up and trip. Alarm on local panel is ENGINE OVERSPEED. Maintenance to investigate trips of the 'A' EDG. 0 CRS recognize no pumps are lined up available for injection and Steam Cooling is required. ESG-NRC-S4 Page 19 of 29 Re\ : 02 0 WHEN RPV water level reaches THEN CRS directs inhibiting ADS. AB.ZZ-0001 Att. 13. STAR D HARD CARD 0 PEER CHECK 0 FLAGGING 0 -1 29", 0 RO/PO inhibit ADS IAW HPI USED: 0 WHEN RPV water level reaches -ZOO", THEN CRS directs opening five ADS SRVs. IAW AB.ZZ-0001 Att. 13. 0 RO/PO open five ADS SRVs HPI USED: STAR 0 HARD CARD PEER CHECK 0 NHEN at least five SRVs are open, THEN DELETE Malfunction DGOIC to restore the 'C' EDG to service AND REPORT the 'C' EDG has been successfully started.

• Crew opens at least five SRWs before reactor water level has been below -200" for two minutes. SUPPORT any requests to place ECCS pumps in PTL using Remote Functions:

Diesel engine START light CSOSC for 'C' Core Spray Generator breaker CLOSE RH23C for 'C' RHR light 0 Crew recognizes start of the 'C' EDG by: OVLD/PWR FAIL lights extinguished on associated channel loads RO/PO starts the 'C' RHR pump, opens the HV-FOI7CI and restores RPV water level to above -1 85" IAW AB.=-0001 Att. 4. The auto-start of the Ti' RHR pump and auto-opening of the FOI 7C are failed. ESG-NRC-S4 Page 20 of 29 Re\. 02 AFTER the Crew restores RPV water level to above -1 85", THEN REPORT you are ready to restore the 'A' EDG to service. The governor oil level was low and has been restored to normal.

• SUPPORT any requests to place ECCS pumps in PTL using Remote Functions:

CS05A for 'A' Core Spray RH23A for 'A' RHR - IF directed to restore the 'A' EDG to service, AND after level has been restored with 'C' EDG, REPORT the 'A' EDG has been successfully restarted. 0 rHEN TRIGGER ET-8 AND 0 The scenario should b terminated at the discretion o the Lead Examiner wh WHEN the 'C' EDG is restored, THEN the Crew injects with the 'C' RHR pump and restores and maintains RPV water level above -185". Crew recognizes start of the 'A' EDG by: Diesel engine START light Generator breaker CLOSE light extinguished on associated channel loads CRS directs restoring PClG to the SRVs. =, OVLDlPWR FAIL lights RO/PO restores PClG to the SRVS IAW AB.ZZ-0001 Att. 9. CRS directs placing the 'A' RHR pump in Drywell Spray. RO/PO places 'A' RHR pump in Drywell Spray IAW AB.ZZ-0001 Att. 2. The restoration of the 'A' EDG makes the 'A' Core Spray Loop available for RPV watc r level control. The AK202 PClG compressor became available when the 'C' EDG was restored. HPI USED: STAR HARD CARD CJ PEER CHECK FLAGGING HPI USED: STAR 0 HARD CARD 17 PEER CHECK FLAGGING ~~ ESG-NRC-S4 Page 21 of 29 Rev 02 A. 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. I. J. K. L. OP-AA-106-101-1001 Event Response Guidelines M. OP-HC-108-106-1001 Equipment Operational Control N. OP-AA-108-114 Post Transient Review

0. P. HC.OP-AB.ZZ-0001 Transient Plant Conditions Q. HC.OP-AB.CONT-0002 Primary Containment R. HC.OP-AB.CONT-0004 Radioactive Gaseous Release S. HC.OP-AB.COMP-0001 Instrument andlor Service Air T. HC.OP-AB.MISC-0001 Acts of Nature U. HC.OP-AB.RPV-0006 Safety/Relief Valve V. W. HC.OP-AB.ZZ-000 Reactor Scram X. HC.OP-EO.ZZ-0101 RPV Control Y. HC.OP-EO.ZZ-0102 Primary Containment Control Z. HC.OP-EO.ZZ-0103 Reactor Building Control AA. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization BB. HC.OP-EO.ZZ-0206 RPV Flooding TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid HU-AA-101 Performance Tools and Verification Practices OP-AA-101-111 Roles and Responsibilities of On Shift Personnel OP-AA-1 01 -1 1 1-1 004 Operations Standards OP-AA-1 01 -1 12-1 002 On-Line Risk Assessment OP-HC-108-115-1001 Operability Assessment and Equipment Control Program HC.OP-AB.ZZ-0135 Station BlackoutlLoss of Offsite Power/Diesel Generator Malfunction CC. HC.OP-SO.AE-0001 FEEDWATER SYSTEM OPERATION DD. HC.OP-SO.BB-0002 Recirculation System operation ESG-NRC-S4 Page 22 of 29 Re\ : 02 ESG-NRC-S4 IO2 1.

• Crew closes the RClC HV-F007 OR HV-F008 before RClC Room temperature reaches 250 degF. KIA 217000 Reactor Core Isolation Cooling System A2 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM; zrd (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnorrr al conditions or operations:

A2.15 Steam Line Break RO 3.8 SRO 3.8 A3 Ability to monitor automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM including A3.01 Valve Operation RO 3.5 SRO 3.5 A4 Ability to manually operate and/or monitor in the control room: A4.03 System valves RO 3.4 SRO 3.3 RCIC has failed to automatically isolate and can only be isolated by the Crew. This represents a bypass of both the RCS and Containment barriers. With indications of high steam flow, high room temperature, rising offsite releases, and an isolation signal to RCIC, the Crew should perform their Immediate Operator Actions IAW AB.CONT-0002 for a failure of a containment isolation valve to close. 250°F is the Max Safe Op temperature for the RClC Room (41 IO). 2.

• Crew scrams the reactor within two minutes of rod drifts. KIA 201003 Control Rod and Drive Mechanism A2 Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 Drifting rod RO: 3.4 SRO 3.7 Having multiple rods inserting into the core out of sequence places the core in an unanalyzed condition. Thermal Limits may be violated resulting in fuel damage and a potential for radiologii al release. The Neutron Monitoring System is not designed to protect the core under these conditions and operator action is required. Two minutes is adequate time to confirm the drifting of multiple rods and take the immediate operator action IAW AB.COMP-0001.

3.

• Crew opens at least five SRVs before reactor water level has been below

-200" for two minutes. KIA 295031 Reactor Low Water Level EA1 . Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA.06 Automatic depressurization RO 4.4 SRO 4.4 When Reactor water level cannot be maintained above -200" without injection to the RPV, adequate core cooling cannot be assured (Minimum Zero Injection Reactor Water Level). EOP 4 direct action to initiate emergency depressurization when RPV water level reaches this value if there are no injection sources available. To restore adequate core cooling, the Crew must Emergency Depressurize and restore level with low pressure ECCS. The two minute time limit provides the Crew adequate time to implement EOP-202 IAW existing standards. ESG-NRC-S4 Page 23 of 29 Rev: 02 4 4: WHEN the 'C' EDG is restored, THEN the Crew injects with the 'C' RHR pump and restores and maintains RPV water level above -785". K/A 295031 Reactor Low Water Level EAI. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA1.01 Low pressure coolant injection (RHR) RO 4.4 SRO 4.4 The automatic start of the 'C' RHR pump and the automatic opening of the HV-FO17C are failed 'C' RHR is the only ECCS pump available for injection (although the 'C' Core Spray pump is running, there is no power to the injection valve due to the loss of the 'A' EDG). Operator actior will be required to initiate injection and restore/maintain adequate core cooling. The absence oi a time limit is due to the potential variance in reactor pressure when the 'C' RHR pump becomes available. The pump may become available before or after the permissible injection pressure fc the RHR pump (IAW AB.ZZ-0001) is reached. This action must therefore be complete before ttbe end of the scenario. Inherent to this critical task is the Crew dispatching personnel to investigatb? the failure of the 'C' EDG to start. If no one is sent to investigate, the EDG will to service. be restorec ESG-NRC-S4 Page 24 of 29 Rei.: 02 ESG-NRC-S4 I 02 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE Y/N ~__ EVENT X Loss Of Offsite Power/SBO X LOCA TRANSIENTS: Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Inadvertent MSlV Closure Y/N EVENT Internal Flooding LOSS OF SUPPORT SYSTEMS: Loss of ssw Loss of SACS Loss of Instrument Air Inadvertent SRV Opening X Manual Scram COMPONENTfrRAINISYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Hard Torus Vent X HPCl X 1E 4.16KV Bus SACS HdPump 120VAC 481 /482 Inverter NB RHR X EDG X RClC SSW Pump YIN X X X X Y/N KEY EQUIPMENT s LC CRD 1 E 125VDC KEYSYSTEMS X 500KV AC Power S RVs CondensatelFeedwater PClG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment Emergency Depressurize RPV W/O High Pressure Injection Initiating LP ECCS with No High Pressure Injection Available Restoration of AC Power after a LOP (EDG / Offsite) Monitoring and Control of SACS heat loads Preventing LVL 8 trip of Feedwater during a transient Align Core Spray Suction to CST when at NPSH limits Cross-Tie De-Energized B/D 125VDC Battery Charger to Energized Bus Inhibit ADS during ATWS Complete this evaluation form for each ESG. ESG-NRC-S4 Page 25 of 29 ReL. 02 ?x Power: -84.5% MWe (May vary slightly): 1000 MWe Activities Completed Last Shift: Completed troubleshooting activities on 'B' RFPT. Major Activities Next 12 Hours: Return 'B' RFPT to service IAW HC.OP-SO-AE-0001 Section

5.7. Raise

power to 90% IAW 10-0006. Protected Equipment: None Tag_qed Equipment: None Reactivity: Raise power to 90% using Reactor Recirc at 51 5%/ hr and hold for RE thermal limit checks. ESG-NRC-S4 Page 26 of 29 Rev IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST - -- iXAMlNATlON SCENARIO GUIDE (ESG) REVIEW/VALIDATION Note: This form is used as guidance for an examination team to conduct a review for the propoibed exam scenario(s). Attach a separate copy of this form to each scenario reviewed. ESG- NRC-S4 REVIEWER: The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it doe: not cue crew into expected events. Each event description consists of: 0 a The event termination point 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 use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred. The events are valid with regard to physics and thermodynamics. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in ari appropriate time frame and implements procedures and/or corrective actions). Sequencingltiming of events is reasonable, and allows for the examination team to obtain complete If time compression techniques are used, scenario summary clearly so indicates. The simulator modeling is not altered. All crew competencies can be evaluated. Appropriate reference materials are available (SOERs, LERs, etc.) Proper critical task methodology used IAW NRC procedures. evaluation results commensurate with the scenario objectives. - -. ESG-NRC-S4 Page 27 of 29 Rev.. 02 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Note: The following criteria list scenario traits that are numerical in nature. ESG: NRC-S4 SELF-CHECK (I *7- 9. Total malfunctions inserted: 5-8 Malfunctions that occur after EOP entry: 1-2 Abnormal Events: 2-4 Major Transients: 1-2 EOPs entered requiring substantive actions: 1-2 EOP Contingency Procedures requiring substantive actions: 0-2 Approximate scenario run time: 60-90 minutes Critical Tasks: 2-3 Technical Specifications are exercised during the test 22 Comments: ESG-NRC-S4 Page 28 of 29 Rev : 02 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Crew Validation Rev: 01 Date Validated: 1 1 /21/2009 Validation Comments Disposition .................................................................................................................................................................................. Need RFPT Startup step on Turnover Sheet. Added to TO sheet. Return 'B' RFPT to service IAW HC.OP-SO-AE-Add guidance for placing Flow unit Mode Switch in unlabeled position. Add status of SMA-3 Event Alarm Light to ABEO report. 0001 Section 5.7. Added driver guidance for I&C action. Added that the light is extinguished. Crew Validation Rev: Date Validated: ESG-N RC-S4 Page 29 of 29 - Rev.: 02 TRAINING 1JSE ONLY - - WORK WEEK CHANNEL: B 11 ONLINE RISK: GREEN Reactor Power: -84.5% MWe (May vary slightly): 1000 Activities Completed Last Shift: - Completed troubleshooting activities on 'B' RFPT. Major Activities Next 12 Hours: 0 Return 'B' RFPT to service IAW HC.OP-SO-AE-0001 Section 5.7. 0 Raise power to 90% IAW 10-0006. Heightened Awareness: None Protected Equipment: None Tagged E qu i pme nt : - None Reactivity: 0 Raise power to 90% using Reactor Recirc at (1 5%/ hr and hold for RE thermal limit checks. SY s YE M : C~rifrd Area Veniifati2i-I System TASK: TASK NUMBER: 48800601 01 Manually Isolate the Control Room Emergency Filter System JPM NUMBER: 305H-JPM.GKOO1 SAP BET: NOH05JPGKOl E ALTERNATE PATH: I] REV#: 05 DEVELOPED BY: Archie E. Faulkner DATE: 8/26/08 Instructor REVIEWED BY: d& DATE: PlA Operations Representative Training depadment TQ-AA-I 06-0303 - STATION: Hope Creek JPM NUMBER: GKOOI SYSTEM: Control Area Ventilation System TASK NUMBER: 4880060101 TASK: Manually Isolate the Control Room Emergency Filter System 290003 A4.01 - ALTERNATE PATH: KIA NUMBER: IMPORTANCE FACTOR: 3.2 3.2 APPLICABILITY: RO SRC? EVALUATION SETTING/METHOD: Simulator/Petform

REFERENCES:

HC.OP-SO.GK-0001 Rev I3 HC.OP-AB.HVAC-0002 Rev 5 rooLs, EQUIPMENT AND PROCEDURES: ESTIMATED COMPLETION TIME: 7 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes _- JPM PERFORMED BY: GRADE: OSAT UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: _- EVALUATOR'S SIGNATURE: DATE: Page 2 of 15 SYSTEW,: Con tro i Are a \/e n r i I a 'ii o il S ys t e rn TASK: fvlanually Isolate the Control roo^ Emergex! Filter Systerr, TASK NUMBER: 4880060101 INITIAL CONDITIONS:

1. A severe Marsh fire had been observed near the site.

Local fire departments responded to the fire.

2. Smoke was observed to be entering the Main Control Room from the Control Room Ventilation System.

3. 'A' CREF was placed in service in accordance with HC.OP-A6.HVAC-0002, Control Room Environment.

4. The fire is out, and the smoke has dissipated.

INITIATING CUE: You are the Plant Operator. Restore the Control Area Ventilation System to normal operation with one Control Area Exhaust Fan in service and one Control Area Exhaust Fan in AUTO. Page 3 of 15 -- .- ~ - w .* GKOOI --- i OPERATOR TRAINING PROGRAM NAME: 1 SYSTEM: TASK: STEP NO. CUE CUE CUE JOB PERFORMANCE MEASURE Control Area Ventilation System Manually Isolate the Control Room Emergency Filter System ELEMENT PROVIQE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INiTIATING CUE: START TIME: Operator obtains the correct procedure. Operator reviews precautions and limitations. if excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. Operator determines beginning step of the procedure. ___._ DATE. Operator repeats back initiating cue. NIA ~ I I I -~ ~ I I 1 Operator obtains procedure I/ ll HC.OP-SO.GK-000j. Operator reviews precautions and limitations. Operator determines correct beginning step to be 5.3.1 then 5.3.5. Examiner Note: The system was placed in Isolate Recirc Mode IAW HC.OP-AB.HVAC-0002. The SOP has not been marked up. Page 4 of 15 .' 1 1 GK001 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Control Area Ventilation System l.l "I. "' , ._ ., TASK: 8.kinUally Isolate the Control Room Emergency Filter System ELEMENT Isolation of Control Area Supply Unit I should be for the running unit. I 5.3.1 ENSURE that all prerequisites have been satisfied IAW Section 2.3. CUE I If excessive time is taken reviewing prerequisites, inform operator that 1 all are satisfied. 5.3.5 E Control Room Emergency Filter Unit operation is no longer required, RE-ESTABLISH normal Control Room Ventilation by performing the following steps: A. DISPATCH an operator to Local Role-play as NE0 sent to lE-C48%. Panel 1 EC485. CUE Operator reviews Prerequisites. I! Examiner Note: Section 5.2.3 may be used in error. The Steps are identical to 5.3.5. Operator dispatches NE0 to local panel 1 EC485. Page 5 of 15

- 1 I GKOOI *, NAME: .. OPERATOR TRAINING PROGRAM

• Operator presses the 'A' CREF Fan STOP pushbutton.

C. STOP A(B) Control Room by pressing the STOP PB. Emergency Filter Unit A(B)V400 I--- ~ -~ ~- DATE. JOB PERFORMANCE MEASURE SYSTEM: Cmtrol Area Ventilation System TASK. Manual!y Isolate the Control Room Emergency Filter System ELEMENT illuminates and the AV400 START light extinguishes.

9. PRESS HD-9598A NORMAL AND SPLYIEXH HD9598A NORMAL pushbutton.

I HD-9598B NORMAL PB. Operator presses CONTROL AREA SPLY/EXH HD9598B NORMAL pushbutton. ___~ I 1 Page 6 of 15 GKOO 1 SYSTEM: TASK: (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines that the system is in RECIRC MODE. Operator depresses the CONTROL ROOM EMER FILTER UNIT A OP MODE switch O.A. MODE push button. i * #

• OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE Control Area Ventilation System Manually Isolate the Control Room Emergency Filter System ELEMENT ! D. E in RECIRC MODE, PLACE CONTROL ROOM EMER FILTER UNIT A AND B OP MODE Switch in OA MODE AND INITIAL Attachment I. CONTROL ROOM EMER FILTER UNIT B OP MODE switch O.A. MODE push button and initials Attachment

1. - Page 7 of 15 GK001 6 ."F._f?'>(]

< 7, EL? _.I JOB PERFORMANCE MEASURE DATE. - __________~ NAME. OPERATOR TRAINING PROGRAM SYSTEM: Control Area Ventilation System TASK: I\nanUaliy isolate the Control Room Emergency Filter System ELEMENT -- OR HS-9599B for A( B)V402 Control Area Exhaust Fan to THEN to the RUN position Operator directs placing one CAE fan in RUN and initials Attachment

1. and support request for CAE fan manipulations using Remote -- the other A(B)V402 Control Area Exhaust Fan HS-9599A Operator directs placing remaining CAE fan in AUTO and initials Attachment

1. HS-9599B to STOP and support request for CAE fan Page 8 of 15 GKOOI OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Control Area Ventilation System iManua0ly isolate the Control Room Emergency Filter System G. Following each run, INSPECT drain openings via port holes in doors. REPORT any water Operator directs inspecting drain openings via port holes in doors for signs of water accumulation or flow. Role-play as NE0 sent to inspect drain openings via port holes in doors, and to report any water WHEN operator informs you the task is complete, other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". the JPM has been terminated for __ ___- - Page 9 of 15 JPM Number: GMOOI TASK: Manually Isoia.2 the Control Room Emergency Filter System TASK NUMBER: 4880060101

__.~ -- QUESTION: -- RESPONSE: RESULT: §AT Ti UNSAT il -- QUESTION: ____ RESPONSE: RESULT: SAT UNSAT - Page IO of 15 "j 4 1 2 1, severe Marsh fire had beer1 mserved near tne siie I-GC~, fire departments respmdec: to the fl re Smoke was observed to be entering the Main Control Roxr from the Control Room Ventilation System. 'A' CREF was placed in service in accordance with H~V.O?-AB.ML/AC-O~O~, Control 2oDm 3. Environment. The fire IS out, and the smoke has dissipated.

4. INITIATING CUE: You are the Plant Operator.

Restore the Control Area Ventilation System to normal operation with one Control Area Exhaust Fan in service and one Control Area Exhaust Fan in AUTO. I. LNITPAL CONDITIONS: -1 INITIALIZE the simulator to 100% power, RlOL ENSURE the A' Control Room Ventilation train IS in service ad the 'B' Train IS in Stby PRESS the HD-959SA ISOLATE pushbutton PRESS the CONTROL RM EMER FILTER UNIT A RECIRC MODE pushbutton ALLOW condltions to stabilize for 3 minutes (CAE fans trip) __- - 1.c. Initial Description - ENSURE simulator IS reset - I lnitiai ET # IT Description - EVENT ACTION: COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: - __- - -. MALFUNCTION

SUMMARY

Delay I 1 __-- initial Description 1 lnitial 1 Descrmtion 1 1 HVD9 CAE Fan AV402 Delay I Ramp Trigger lnit Val Final 'a1 DlREC ED ! HVIO CAE Fan BV402 1/0 OVERRIDE

SUMMARY

I -1 I Delay ~ Ramp I Trigger 1 Init Val I Final Jal 1 Page 13 of I5 _' i $1 Rev # 114 Date 611 5/07 O5 I 8/26/08 Description

___.. _____._~ Sevision 11 of HC.OP-SO.GK-0001 direction to initial Attachment 1 (IV of manipulations) in steps 5.3.5.D/E/F with NO change in action steps. JPt'v'I GKOOI updated to reflect this. No change in actions, validation not required. Converted JPM GK001 to new JPM format. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of i2ction were redundant and dsleted. This change is editorial, validation not required. Removed references to checking offhnitialing steps in procedure. This is a generic, work practice and adds unnecessary clutter to the Standard section. This change is editorial, validation not required. Added Caution text to Element section. This is for examiner reference only and has no associated student actions. This change is editorial, validation not required. Updated Estimated Completion Time based on actual perform a n ce data . Jpdated reference procedurs revisions only. No changes to sperator actions. No ____. validation required. __. Va I idati o 7 Reqlairec __ ? N _- s PATI ON : !-lope Creek SYSTEM: Core Spray TASK: TASK NUMBER: 20900301 01 JPM NUMBER: 305H-JPM.BE005 REV#: 06 SAP BET: NOHOSJPBEO5E ALTERNATE PATH: Manually Start the Core Spray System APPLICABILITY: EO n RO wl STA -1 SRO Fl DATE: 9/4/08 - Archie E. Faulkner Instructor DEVELOPED BY: - REVIEWED BY: DATE: 9- / Z-Og 0 pe rat i ons Re present at ive DATE: CyjJ 1 APPROVED BY: Training Department TQ-AA-106-030 ,I REV: 06 STATION: Hope Creek JPM NUMBER: BE005 SYSTEM: Core Spray TASK NUMBER: 20900301 01 TASK: Manually Start the Core Qpray System ALTERNATE PATH: ml APPLICABILITY: -- K/A NUMBER: 209001 A4.01 IMPORTANCE FACTOR: 3.8 3.7 RO SRO EVA LU AT1 0 N S E TTI N GIM E TH 0 D : S i m u I at o r/P e rfo rm

REFERENCES:

HC.OP-AB.ZZ-0001 Attachment 5 Rev. 16 TOOLS, EQUIPMENT AND PROCEDURES: None EST1 MATED COM P LET10 N TIM E: 13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes JPM PERFORMED BY: GRADE: USAT UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: - DATE: -- EVALUATOR'S SIGNATURE

Page 2 of 12 TASK: Ivlanually StaE the Core Spray System TASK NUMBER: 2090O30101 JNlTlAL CONDITIONS:

1. The plant has experienced a loss of all offsite power coincident with a small break 2. A and C Emergency Diesel Generators have failed to start. 3. HPCl has just tripped 4. Reactor pressure is approximately 500 psig and lowering.

5. Reactor level is approximately

-70 inches and lowering. LOCA. INITIATING CUE: Restore reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop. The simulator is in FREEZE until you are ready to begin. Page 3 of 12 JPM: BE005 Rev: 06 SYSTEM: TASK: STEP NO. CUE CUE k 2.0 3.0 Core Spray Manually Start the Core Spray System ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtainsllocates procedure HC.OP-AB.ZZ-0001, Attachment

5. IF required, ARM THEN PRESS B MAN INlT PBs. ENSURE B Core Spray Pump is RUNNl NG. - IF Required, ARM THEN PRESS D MAN INlT PBs. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TC 106-8383 NAME: ___ DATE: Operator repeats back initiating cue. - Operator obtains the correct procedure.

Operator determines that operation of the MAN lNlT PBs is not necessary based on overhead annunciators B3- AllA21A31A4, CORE SPRAY PUMP AUTO START are in alarm. Operator observes the B Core Spray Pump is not running. __ - ~- - _____ __--~ - /*I I Operator depresses the BP206 START push button. Operator observes that B Core Spray Operator determines that operation of the MAN INlT PBs is not necessary based on overhead annunciators B3- A1/AZ/AYA4, CORE SPRAY PUMP AUTO START are in alarm. Pump is running. - Page 4 of 12 7.0 WHEN flow is > 775 gpm, ENSURE HV-F031 B is CLOSED. Operator observes Core Spray System B flow on FI-RGOIB to be >775 gprn. _____~ Operator observes HV-F031 B is closed. -I_ JPM: BE005 Rev: 06 SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP NO. CUE .. ELEMENT WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE ~- DATE: (*Denotes a Critical Step)

• COMMENTS (#Denotes a Sequential Step)

EVAL (Required for UNSAT STANDARD # SIU evaluation) -_I_ Page 6 of I2 TQ-LA-7 OG-t:. 03 J 0 E ?E r? 0 I? Id k I\J CE bl EA S U F: E 0 P E RAT3 R T Rk 1 N I N G P R 0 GRAM EVkLlJkTOR FOLhO\YUP QUESTION DOCUMENTATION -__ NAME: DATE: -__ JPM Number: BE005 TASK: Manually Start the Core Spray System TASK NUMBER: 2090030101 _____. QUESTION: _____ RESPONSE: RESULT: SAT I/ UNSAT 11 QUESTION: -- RESPONSE: RESULT: SAT UNSAT Page 7 of 12 J 0 E ?E R F 0 R M A I 4 C E MEA S U RE I N I SI AL C 0 N D I TI 0 14 S : 1. 2. 3. 4. 5. The plant has experienced a Ixs of all ofi'site power coincident with ~t small break LOCA. A and C Emergency Diesel Generators have failed to start. HPCl has just tripped. Reactor pressure is approximately 500 psig and lowering. Reactor level is approximately -70 inches and lowering. INITIATING CUE: Restore reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop. The sirnulato. is in FREEZE until you are ready to begin. Page 8 of 12 >Y TQ-Ah-? 06-02 33 hbal JOB PERFOP~I~IAI\JZE iulEASilRE SI lvl U LATOR SETUP I I\JS:'F: J CTI 014 S (OFTIONAL) Description COMPLETE Simulator Ready-for-TrainingiExnmination Checklist. CONDITIONS: Insert below listed malfunctions. Take simulator out of freeze. Let vessel water level drop to approximately -70 inches. Reduce reactor pressure to approximately 500 psig. Freeze the simulator. PREP FOR TRAINING (Le., RM1 I set points, procedures, bezel covers) I -i EVI - Initial ET # If -_--- NT TRIGGERS: _- Description COMMAND: PURPOSE: EVENT ACTION: COMMAND, PURPOSE: -__ Page 9 of 12 - MALFUNCTION

SUMMARY

' Ramp Trigger lnit Val I Final' 1 _-- None --- --- None --_ --- None I _-- None , (i!7rtiai>escrintion EG12 Loss of all Offsite Power DGO2A A Diesel Generator Failure To Start ~ , DG02C C Diesel Generator Failure To Stai Recirc Loop small leak 3 None --_ --- None --_ -3 I:: I --- RR31A2 Recirc Loop large break MSOI Steam line break in the drywell CSD3B Core Spray HV-FOO5B fails to auto open CS04B Core Spray pump fails to auto start CSO4D Core Spray Pump Fails To Auto Start --- None --- lnit Val 1 Fins1 - 4 1 Inibal 1 Description I/O OVERRIDE

SUMMARY

7- - Page 10 of 12 JPIV N3MBER: BE005 Description 06 9/4/2008 Validatio rl Required _- 7 This revision converts to HC LOR format, documents validation, and generates estimated completion time. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted. Revised Initiating Cue. Adds to cue "HPCI has just tripped".

Adds HP03 malf to trip HFCI. Adds Malf RR31A2 Recirc Large break to assist setup. Adds Malf MSOI Steam line break in drywell to assist setup. Y STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: JOB PERFORMANCE MEASURE Hope Creek Main Steam Open The MSlVs With The Reactor Pressurized (>200 23900201 01 305H-JPM .AB006 REV#: 00 NOH05JPABOGE PSQ) - ALTERNATEPATH: I I DEVELOPED BY: Archie E. Faulkner DATE: 12/6/08 Instructor REVIEWED BY: gAvV DATE: !./iiiy perati ns Mresentative APPROVED BY: DATE: A- /L // fi Training Department TQ-AA-I 06-030 STATION: Hope Creek JPM NUMBER: AB006 SYSTEM: Main Steam TASK NUMBER: 2390020101 TASK: Open The MS ALTERNATE PATH: . APPLICABILITY: . REV: 00 Vs With The Reactor Pressurized (>200 psig) -- KIA NUMBER: 239001 A4.01 IMPORTANCE FACTOR: 4.2 4.0 RO SRO Eo u RO[ X I STAm SROF] EVALUATION SETTINGIMETHOD: Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0301, Rev. 6 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 18 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes -- JPM PERFORMED BY: GRADE: OSAT UUNSl ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 2 of 16 TQ-AA-I 06-03C NAME: DATE: SYSTEM: Main Steam TASK: Open The MSlVs With The Reactor Pressurized (>200 psig) TASK NUMBER: 2390020101 INITIAL CONDITIONS: 1. The Reactor is at 5% power following a full core ATWS. 2. The Main Turbine is tripped.

3. The Main Condenser is available.

4. HC.OP-EO.ZZ-OlOlA, ATWS - RPV Control, is being executed.

5. HC.OP-EO.ZZ-0311, Bypassing Primary Containment Instrument Gas Interlocks, ar HC.OP-EO.ZZ-0319, Restoring Instrument Air in an Emergency, have been completed.

6. There is no indication of fuel cladding failure or main steam line break.

7. HC.OP-EO.ZZ-0301 is being implemented.

INITIATING CUE: Re-open the inboard MSlVs IAW HC.OP-EO.ZZ-0301, Bypassing MSlV Interlocks with MSlVs Closed. HC.OP-EO.ZZ-0301 has been completed up to and including step 5.1.9.D. Page 3 of 16 1 4-1 06-0303 NAME: DATE: OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JPM: AB006 Rev: 00 SYSTEM: Main Steam ELEMENT Operator repeats back initiating cue. OPERATOR REPEATS BACK INITIATING CUE: Page 4 of 16 1 \. .+-I 06-0303 * (*Denotes a Critical Step) STANDARD (#Denotes a Sequential Step) EVAL SIU ELEMENT # STEP NO. JPM: AB006 Rev: 00 SYSTEM: Main Steam COMMENTS (Required for UNSAT evaluation) OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE 5.1.10. NAME: DATE: light extinguishes. Operator presses HV-F033 CLOSE PB. HV-F033 DRN HDR OPR DRN VLV

• ll I Operator observes HV-F071 green close light illuminates and red open rves HV-F033 green tes and red open 5.1.11. A SELECT -1, I Pressure Controll Operator uses the DEHC HMI I touchscreen display to select (1, then (Pressure Controll 5.1 .I 1. B SELECT Throttle Pressure Set - (Setpoinij Operator selects Throttle Pressure AND ENTER a pressure setpoint above reactor pressure.

Set - FtJ Operator enters a value higher than current RPV pressure and presses OK. Examiner Note: Any value above the current RPV pressure is acceptable. The upper limit DEHC will accept is ~- Page 5 of 16 JPM: AB006 Rev: 00 (*Denotes a Critical Step)

• ELEMENT (#Denotes a Sequential Step)

STEP NO. STANDARD ## 1 \. e4-106-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: EVAL s/u 5.1 .I 2 OPEN HV-FO19 IICNTMT INBD STM LINE DRAIN HDR ISLN OUTBOARD VALVE//.

• Operator presses HV-FO19 OPEN PB. 5.1 .I 3 Operator observes HV-FO19 red open light illuminates and green close light extinguishes.
• I OPEN HV-F016 //CNTMT INBD STM LINE DRAIN HDR ISLN INBOARD Operator presses HV-FO16 OPEN PB. VALVEII. I Operator observes HV-FO16 red open light illuminates and green close light extinguishes.

I 5.1.14 I THROTTLE OPEN HV-F020 MAIN I Operator presses HV-F020 UP ARROW PB. STM LINE EQUALIZER HEADER DRAIN SHUTOFF to begin pressurizing the main steam piping I downstream of the inboard MSIV's. 1

• Operator observes HV-F020 red open light illuminates and green close remains lit. COMMENTS (Required for UNSAT evaluation) - Page 6 of 16 7 4-1 06-0303 NAME: DATE: JPM: AB006 Rev: 00 SYSTEM: Main Steam OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Open The MSlVs With The Reactor Pressurized

(>20O psig) (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD ELEMENT 5.1.15. WHEN WIDE RANGE PR-1002A (Panel 10C650C) MAIN STEAM PRESSURE, wide range, is within 200 psig of PI-R605 REACTOR PRESSURE, OPEN the following MSIV's by PLACING their respective control switches to OPEN: Operator observes pressure on PR- 1002A is within 200 psig of PLR605. Operator turns handswitch for HV- F022A INBD MSIV A to OPEN position. Operator observes HV-F022A INBD MSlV A red open light illuminates and green closed light extinguishes. 5.1 .I 5. A HV-F022A INBD MSlV A - I 5.lt;15. I HV-F022B INBD MSIV B Operator turns handswitch for HV- F022B INBD MSlV B to OPEN position. 5.1.15. HV-F022C INBD MSlV C i Operator observes HV-F022B INBD MSIV B red open light illuminates and green closed light extinguishes. Operator turns handswitch for HV- F022C INBD MSlV B to OPEN position. 1 Operator observes HV-F022C INBD 1 MSIV C red open light illuminates and I I I green closed light extinguishes.

• (Required for UNSAT evaluation)

Page 7 of 16 1 ~ .4-106-0303 NAME: DATE: * (*Denotes a Critical Step) ELEMENT (#Denotes a Sequential Step) EVAL STANDARD # SIU JPM: AB006 Rev: 00 COMMENTS (Required for UNSAT evaluation) SYSTEM: TASK: STEP NO. 5.1.15. D CUE 5.1.16 5.1.16. A 5.1.16. B OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE HV-F022D INBD MSlV D I*( I Operator turns handswitch for HV- F022D INBD MSlV D to OPEN position. WHEN F022D Handswitch is placed to open, THEN DELETE Overrides: 3838 A 3DS31 B 3DS31 A Operator observes HV-F022D INBD I1IlSIV D red open light illuminates and Operator presses HV-F020 CLOSE PB. Operator observes HV-F020 green close light illuminates and red open DRAIN HDR ISLN OUTBOARD VA LV Ell. Operator presses HV-FO19 CLOSE PB. Page 8 of 16 JPM: AB006 OPERATOR TRAINING PROGRAM

• EVAL ## SIU Rev: 00 SYSTEM: TASK: 7 STEP I NO. ' COMMENTS (Required for UNSAT eva I ua tion) ~ 5.1.16. C ELEMENT 5.1.17 CUE (*Denotes a Critical Step) (#Denotes a Sequential Step)

STANDARD Operator observes HV-FO19 green close light illuminates and red open light extinguishes. HV-F016 //CNTMT INBD STM LINE DRAIN HDR ISLN INBOARD VALVE//. Operator presses HV-F016 CLOSE PB. Operator observes HV-FO16 green close light illuminates and red open light extinguishes. CONTROL reactor pressure IAW WHEN operator informs you the task is complete, other reasons, THEN RECORD the STOP time. HC.OP-EO.ZZ-0101 A(Q). the JPM has been terminated for 4-106-0303 1 ._ NAME: DATE: REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: Page 9 of 16 TQ-AA-106-0203 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: ___ DATE: _- JPM Number: AB006 TASK: Open The MSlVs With The Reactor Pressurized (>200 psig) TASK NUMBER: 2390020101 RESULT: SAT UNSAT TI RESULT: SAT I UNSAT Page 10 of 16 TQ-AA-106-0303 JOBPERFORMANCEMEASURE INITIAL CONDITIONS:

1. The Reactor is at 5% power following a full core ATWS. 2. The Main Turbine is tripped. 3. The Main Condenser is available.

4. HC.OP-EO.ZZ-O1Ol A, ATWS - RPV Control, is being executed.

5. HC.OP-EO.ZZ-0311, Bypassing Primary Containment Instrument Gas Interlocks, an( I HC.OP-EO.ZZ-0319, Restoring Instrument Air in an Emergency, have been completvd.

6. There is no indication of fuel cladding failure or main steam line break.

7. HC.OP-EO.ZZ-0301 is being implemented.

INITIATING CUE: Re-open the inboard MSlVs IAW HCOP-EO.ZZ-0301, Bypassing MSlV Interlocks with MSlVs Closed. HC.OP-EO.ZZ-0301 has been completed up to and including step 5.1.9.D. Page 11 of 16 TQ-AA-106-0?03 Initial JOBPERFORMANCEMEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) i Description COMPLETE "Simulator Ready-for-Training/Examination Checklist".

1. INITIAL CONDITIONS:

-- I.C. -- I INITIALIZE the Simulator to 97 power, MOL MS04 AB HV-F020 change status to UNTAGGED and remove bezel cover. MS05 AB HV-F021 change status to UNTAGGED and remove bezel cover. LOCK the reactor Mode Switch in Shutdown TAKE actions of HC.OP-AB.ZZ-0001 Attachment 1 INITIATE SLC. - TRIP the Main Turbine. CONTROL RPV level with HPCl and RClC above -129 inches. INSERT MALF MS-15 SPURIOUS GROUP I ISOLATION (MSIV CLOSURE) - - - - - -- DELETE MALF MS-15 -- REMOVE bezel covers from AB-HV-F020 and F021. PERFORM HC.OP-EO.ZZ-0301 up to step 5.1.9.D. PLACE the simulator into Freeze. - -- -- PREP FOR TRAINING (Le., RM'I 1 set points, procedures, bezel covers) I ~ ~ - ~ ~ ENSURE copies of HC.OP-EO.ZZ-0301 are available and marked up to and including step 5.1.9.D. for 3re- ENSURE an extra instructor is available to control RPV level using HPCl and acknowlege unrelated a1 drms. briefing JPM. Approx 90 seconds after coming out of freeze, reduce HPCl AUTO flow setpoint to 1200 gpm. -I Page 12 of 15 TQ-AA-106-0: 03 JOBPERFORMANCEMEASURE SIMULATOR SETUF INSTRUCTIONS (OPTIONAL) Initial ET # Description EVENT ACTION: 1 COMMAND: PURPOSE: EVENT ACTION: 2 COMMAND: PURPOSE: Page 23 of 15 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) lnitial TQ-AA-I 06-0 303 Trigger Init Val Fina Val -__. Description Delay Ramp RP06 Half Core ATWS - Left Side I sec. --- None --- __ Mia/ EGI I Main Generator Trip --- --- ET- 1 --- __ TCOI-10 All TBV failed closed. --- --- None --- -. . -__ Ramp Trigger lnit Val Fin2 Val BY F ASS EM; -4 RG - Description Delay EP02 EOP-311 Bypass PClG (-129") isolation I- --- None --- EP05 EOP-319 LOCA Level 2 interlock --- --- None --- SLOIA SBLC Injection pump AP208 failure SLOIB SBLC Injection Pump BP208 failure EP35 EOP-322 HV-FOO6 HPCl to CS EPOI EOP-301 Bypass MSlV (-129") isolation MS04 AB HV-F020 MS05 AB HV-F021 REMOTE/FIELD FU NCTl ON

SUMMARY

I I I I 1 --- --- None --- F-1 IL --- --- None --- --- --- None --- --- --- None --- UNT 4GG UNT 4GG E3 Initial Description Delay Ramp Trigger lnit Val 3838 A HV-F022D CLOSE SWITCH --- --_ None --- 110 OVERRIDE

SUMMARY

I I I I I I 1-1 1 3DS31 A HV-F022D OPEN-INBD MSlV D 1 CZF 1 --- - --- --- None I I3DS31 BHV-F022DCLOSED-INBD MSIVD I --- I --- 1 None 1 --- 1 C N 1 I I I I I Page 14 of 15 I TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AB006 Date 1 1/10/2008 12/5/2008 Description Requirec?

New JPM. Completed validation with C shift crew members. Validation average time 18 minutes. Added SBLC pump trips to stabilize RPV pressure for JPM per validation comments. La1 Q;"% 1 qoN: s Y s T E PA : Hope Creek Residual Heat Removal TASK: Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdovvn Panel (RSP) TASK NUMBER: 50001 10501 JPM NUMBER: 305H-JPM .BC009 REW#: 09 SAP BET: NOH05JPBCOSE Archie E. Faulkner DATE: 8/25/08 DEVELOPED BY: Jnstructor REVIEWED BY: APPROVED BY: DATE: Training Department REV: 09 __ DATE: -___ EVALUATOR'S SIGNATURE: -- ; YS T E M : Residual Heat Removal 'ASK NUMBER: 50001 10501 -ASK: Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) 4LTERNATE PATH: I) WA NUMBER: 295016 AA2.04 __ - IMPORTANCE FACTOR: 3.9 4.1 4P P LI CAB1 LIN: RO SRO f VA LU AT1 0 N S ETTl N GIM E TH 0 D : Si m u I at o r/ P e rfo rm ZEFERE NCES: HC .OP-AB . HVAC-0002 Rev 5 HC.OP-IO.ZZ-0008 Rev 28 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COM P LET10 N TIM E: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes _- JPM PERFORMED BY: GRADE: USAT [7UNSA" Minutes ACTUAL COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF UNSATISFACTORY: Page 2 of 14 s Y STE 1\1! : TASK: Residual Heat Removal Place B RHR Loop In Suppre;sion Pool Cooling From The Remote Shutdown Panel (RSP) TASK NUMBER: 50007 -I0501 INTiAL CONDITIONS: I. The control room has been abandoned due to dense smoke. 2. HC.OP-AB.HVAC-0002, Control Room Environment, has been implemented.

3. The Reactor has been scrammed, all rods are full in. 4. The Turbine is trimed. 5. The MSIVs are cidsed. 6. Control of the plant has been established at the RSP IAW HC.OP-AB.HVAC-0002 AND Section 5.1 of 'HC.OP-IO.ZZ-0008, Shutdown from Outside Control room. RClC has been initiated IAW HC.OP-AB.HVAC-0002 AND Section 5.2 of 7. HC. OP-l0.ZZ-0008.

INITIATING CUE: You are an Extra NCO. Place 'B' RHR in Suppression Pool Cooling from the RSP. You are responsible ONLY for 'B' RHR. Page 3 of 14 ____. JPM: BC009 OPERATOR TRAINING PROGRAM NAME: Rev: 09 SYSTEM: TASK: JOB PERFORMANCE MEASURE DATE. ___ Residual Heat Removal ELEMENT Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) PROVIDE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains the correct procedure. Operator reviews precautions and limitations. If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. Operator determines beginning step of the procedure. I ! Operator repeats back initiating cue. Operator obtains procedure I I - i ~ H C . OP- I 0.ZZ-0008. Operator reviews precautions and limitations. Operator determines correct beginning step to be 5.8.1. Page 4 of 14 TQ, 186-0303 NAME: JPM: BC009 OPERATOR TRAINING PROGRAM Rev: 09 SYSTEM: TASK: 1 NO. ~ STEP 1 NOTE 5.8.1 JOB PERFORMANCE MEASURE DATE: Residual Heat Removai ELEMENT If at any time a situation develops whereby HV-F024A(B) anlor HV-F027A(B) are open and the associated RHR pump is not in operation, a potential system drain down will occur. A subsequent start of the RHR pump will cause water hammer. To preclude this occurrence, ensure both valves are closed and perform a system fill and vent prior to starting the RHR pump. - IF necessary, THEN PLACE the B RHR loop in the Suppression Pool Cooling mode as fo I I OW s A. ENSURE EG-HV-2512B RHR [ C D -9 8 7 X , C D-3 7 0 XI HX SACS RTN ISLN MOV is OPEN. PB must be held depressed to open. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) N/A B. ENSURE HV-F004B RHRPMP B SUPP POOL SUCT MOV is OPEN. C. ENSURE HV-F007B RHRPMP B MIN FLOW MOV is OPEN. Operator presses AND holds the HV2512B INCR OPEN pushbutton until the green CLOSE DECR light extinguishes. Operator observes the red HVF004B OPEN indicator is illuminated and green CLSD indicator is extinguished. Operator observes the red HVFOO7B OPEN indicator is illuminated and green CLSD indicator is extinguished. Page 5 of 14 JPM: BC009 Rev: 09 Operator presses the BP202 START pushbutton. SYSTEM: TASK:

• ____ # ~~ OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE pushbutton whiie observing Fi-4435. When Fl-4435 indicates

= 10,000 gpm, the operator releases the INCR Pb. TQ 106-0303 NAME: DATE: Residual Heat Removal D. START BP202 RHR PUMP. The following two steps should be performed concurrently. E. THROTTLE OPEN HV-F024B RHR LOOP !3 TEST RET MOV EXCHANGER FLOW indicates = 10,000 gpm. UNTIL Fl-4435 RHR HEAT F. WHEN Fl-4435 RHRHEAT EXCHANGER FLOW indicates > 1400 gpm, PMP B MIN FLOW MOV. THEN CLOSE HV-F007B RHR II I Operator observes the red HVF024B OPEN indicator illuminates. When Fl-4435 indicates > 1400 gprn, the Operator presses the HVFOO7B CLOSE pushbutton and observes the green CLSD indicator illuminates and the red OPEN indicator extinguishes. - __ - __ - Page 6 of 14 JPM: BC009 OPERATOR TRAINING PROGRAM NAME: Rev: 09 SYSTEM: TASK: STEP NO. ELEMENT TQ 106-0383 -~ JOBPERFORMANCEMEASURE DATE: -_ Residual Heat Removal Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) ._-_-- G. ENSURE HV-F047B RHRHX INLET VALVE OUTLET MOV are OPEN B SHELL SIDE BYPASS VLV. AND HV-F003B B RHR HX AND CLOSE HV-F048B RHR HX H. THWQTTLE HV-F024B RHR LOOP B TEST RET MOV AS necessary to re-establish loop flow of approx. 10,000 gpm on Fl-4435. I. OBSERVE TR-3647J( M)- SUPPRESSION CHAMBER WATER TEMP. Operator observes the HVF0475 and HVF003B red OPEN indicators are illuminated and green CLSD indicators are extinguished. Operator presses and holds the HVF048B DECR Pb until the green CLSD indicator illuminates AND the red 0 PEN i nd icato r ext i ng u i she s . Operator presses HVF024B INCR andlor DECR pushbuttons as necessary until Fl-4435 flow indicates 9,000 - I 1,000 gpm. Operator observes Suppression Chamber Water Temperature on TR-3647J andlor M. Page 7 of 14 __ - -_ - - - JPM: BC009 OPERATOR TRAINING PROGRAM NAME. Rev: 09 JOB PERFORMANCE MEASURE DATE. __________ __ SYSTEM: Residual Heat Removal TASK: Place 6 RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) ELEMENT OR the JPM has been terminated for THEN RECORD the STOP time. operator on the status of the JPM, and then state "This JPM is complete". ll I REPEAT BACK any message from the 1 I j STOP TIME: Page 8 of 14 33 ___ NAME: DATE: JPM Number: BC009 TASK: Place 8 RHR Loop In Suppression Pool Coolirrg From The Remote Shutdown Panel (RSP) TASK NUMBER: 5000110501 -_ QUESTION: RESPONSE: RESULT: SAT 1 I UNSAT - QUESTION: ___. RESPONSE: RESULT: SAT iI Page 9 of 14 UNSAT

1. 2. 3. 4. 5. 6. 7. The control room has been abandoned due to dense smoke. HC. 9P-AB. HVAC-0002, Control Room Environmeni, has been implemented.

The Reactor has been scrammed, all rods are full In. The Turbine is tripped. The MSlVs are closed. Control of the plant has been established at the RSP IAW HC.OP-AB.HVAC-00Q2 AND Sectiori 5.1 of HC.OP-IO.ZZ-0008, Shutdown from Outside Control room. RClC has been initiated IAW HC.OP-AB.HVAC-0002 AND Section 5.2 of HC.OP-IO.ZZ-0008. INITIATING CUE: You are an Extra NCO. Place 'B' RHR in Suppression Pool Cooling from the RSP. You are responsible ONLY for 'B' RHR. Page 10 of 14

1. INITIAL COIWITI ET # 1 2 - _____ INITIALIZE the simulator to 100% power MOL _________~

Description EVENT ACTION. COMMAND PURPOSE. EVENT ACTION: COMMAND. PURPOSE ENSURE the 'B' SSW pump is in service ENSURE the 'B' SACS pump is in service. EVACUATE the Control Room IAW AB.HVAC-0002. ESTABLISH RPV level at between 0 and -20" inches. IMPLEMENT HC.OP-IO.ZZ-0008 up to the point of placing 'B' RHR in service. INSERT Malfunction HP01 to prevent HPCl from injecting. PREP FOR TRAINING (i.e., RMI 1 set points, procedures, bezel covers) I I 1 I /nitla/ I Description A ANNOTATE a copy of HC.OP-IO.ZZ-0008 up to the point of placing 'B' RHR in service. JOGGLE Control Room Horns to OFF. ENSURE RSP Chart Recorders are ON. ENSURE simulator reset. -- EVENT TRIGGERS: initial Page 11 of 14 D";y 1 Rarmp ~ Trigger 1 lni;-;al I Fin;! \/a1 I HPOI HPCl Auto initiation Failure NONE I I I I I -I _____ REMOTEF I ELD FU NCTl ON S U M MARY: - - Delay Ramp Trigger I/O OVERRIDE

SUMMARY

- _______ - Trigger 1 lnit Val NONE 1 Final Jal -4 Ramp Page 12 af 14 J 3 E P E 2 F 3 R VI AN C E MEA S U F: E a EM s EO N i4 IS TO R Y Rev b: 08 09 JPM NUMBER: EC039 Date Description Val idat ion Required?

-- , 7/23/07 8/25/08 ~ DCP on EG-HV-2512 has valve no longer full open Had 10 add 1 an Operator action to fully open the valve in 5.6.1 .A. I:-- Updated procedure revision numbers. Editorial changes only. i JOB PERFORMANCE MEASURE STAT1 0 N : SYSTEM: Primary Containment TASK: TASK NUMBER: 4000760401 Hope Creek Respond To A Containment Isolation JPM NUMBER: 305H-JPM.SM002 SAP BET: NOH05JPSM02E ALTERNATE PATH: REV#: 00 APPLICABILITY: RO /XI STA (XI SRO (x\ Eo 0 DATE: 12/5/08 DEVELOPED BY: Archie E. Faulkner InstructQlr flNfl- DATE: [I,/ I// - REVIEWED BY: APPROVED BY: DATE: &}I ,/De Operations epresentative Y Training Department - TQ-AA-106-0303 S TAT10 N : Hope Creek JPM NUMBER: S MOO2 REV: 00 SYSTEM: Primary Containment TASK NUMBER: 4000760401 TASK: Respond To A containment Isolation -- ALTERNATE PATH: 1-1 WA NUMBER: 22 3002A3.02 APPLICABILITY: RO SRO __ IMPORTANCE FACTOR: 3.5 3.5 EOI] ROIFl STAL SROR EVALUATION SETTINGIMETHOD: Simulator/Perform

REFERENCES:

HC.OP-AB-CONT-0002 Rev. 7 HC.OP-SO.SM-0001 Rev. 17 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 9 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: Minutes JPM PERFORMED BY: GRADE: USAT UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: Minutes REASON, IF UNSATISFACTORY: -- DATE: -- EVALUATOR'S SIGNATURE: Page 2 of 16 NAME: I TQ-AA-106-0303 DATE: SYSTEM: Primary Containment TASK: Respond To A Containment Isolation TASK NUMBER: 4000760401 INITIAL CONDITIONS:

1. Hope Creek is recovering from a Scram due to loss of all RFP's at 97% power. 2. RPV level dropped to -90" before recovering with HPCI and RCIC. 3. EOP-IO? and EOP-102 are being implemented.

INITIATING CUE: Ensure all required NSSSS and PClS isolations have occurred IAW HCOP-AB.CONT-0002 Attachments 1 and 2. Page 3 of 16 TL .-I 06-0303 NAME: DATE: ~~ JPM: SM002 Rev: 00 SYSTEM: Primary Containment TASK: Respond To A Containment Isolation I 0 PClG MINOR KL-HV-5155, 51 54, 51 56A, 51 568, SE-HV-5161 TIPS SE-SVJ004Al-5 STEP NO. I ELEMENT ~~~~ ~ ~ CUE 1 PROVIDE the operator the initiating cue. CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains procedure HC.OP-AB .CONT-0002 or Attachment 1 and 2 Hardcard. Operator determines beginning step of the procedure. OBSERVE the Valves listed in Attachment 1 have closed under the -38" Automatic Isolation Signal. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD I1 Operator repeats back initiating cue. Operator obtains the correct procedure. Operator determines correct beginning step to be Attachment

1. Operator verifies that ALL of the listed valves/equipment in this group have responded correctly to the initiating event. Operator verifies that ALL of the listed valveslequipment in this group have responded correctly to the initiating event. EVAL SIU COMMENTS (Required for UNSAT evaluation)

Page 4 of 16 JPM: SM002 Rev: 00 SYSTEM: TASK: STEP NO. CUE Primary Containment Respond To A Containment Isolation ELEMENT Twcu EE-HV-4652,4679,4680,4681 0 DWSUMPS HB-HV-FO19, F020, F003, F004 IF the operator requests permission to close the valves, THEN re-read the initiating cue: Ensure all required NSSSS and PClS isolations have occurred IAW HC.OP-AB.CONT-0002 Attachments 1 and2. Immediate Operator Action Primary Containment Isolation Valve FAILS to automatically ISOLATE. PERFORM EITHER of the following: 0 CLOSE a redundant isolation valve 0 CLOSE the valve manually. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator verifies that ALL of the listed valves/equipment in this group have responded correctly to the initiating event. ~ Operator observes the HB-HV-FO19 DRYWELL EQPT DRAIN SUMP AT267 ISLN VLV has failed to isolate and informs the CRS. Operator PRESSES CLOSE PB for HB- SUMP AT267 ISLN VLV. HV-FOl9 DRYWELL EQPT DRAIN TL. .-I 06-0303 NAME: DATE: (Required for UNSAT evaluation) Page 5 of 16 JPM: SM002 Rev: 00 SYSTEM: Primary Containment TASK. Respond To A Containment Isolation EVAL SIU OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE COMMENTS (Required for UNSAT evaluation) STEP NO. ELEMENT Immediate Operator Action Primary Containment Isolation Valve FAILS to automatically ISOLATE. PERFORM EITHER of the following: 0 CLOSE a redundant isolation valve 0 CLOSE the valve manually. ~ HB-HV-F003 DRYWELL FLOOR DRAIN SUMP BT267 ISLN VLV HB-HV-F004 DRYWELL FLOOR DRAIN SUMP BT267 ISLN VLV (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes the HB-HV-FO19 DRYWELL EQPT DRAIN SUMP AT267 ISLN VLV red OPEN light extinguishes and green CLSD light illuminates. Operator observes the HB-HV-F020 DRYWELL EQPT DRAIN SUMP AT267 ISLN VLV has failed to isolate and informs the CRS. Operator PRESSES CLOSE PB for HB- SUMP AT267 ISLN VLV. HV-F020 DRYWELL EQPT DRAIN Operator observes the HB-HV-F020 DRYWELL EQPT DRAIN SUMP AT267 ISLN VLV red OPEN light extinguishes and green CLSD light illuminates. Operator observes the HB-HV-F003 DRYWELL FLOOR DRAIN SUMP BT267 ISLN VLV has closed. Operator observes the HB-HV-F004 DRYWELL FLOOR DRAIN SUMP BT267 ISLN VLV has closed. - * # - -

• TL .-106-0303 NAME: DATE: Page 6 of 16 JPM: SM002 Rev: 00 SYSTEM: Primary Containment TASK: Respond To A Containment Isolation STEP NO. 0 PRIMARY CONTAINMENT MIMIC GS-HV-4950,4952,4951,4963, 4962,4964, KL-HV-5172A. GS-HV-5057AI 5055A, 5052A, 5050A, 5053A, 5054A, 5022A GS-HV-4966A, 4965A, 4959A, 4983A, 4955A, 4984A, 5019A SK-HV-5018,4953,4957,4981, GS-HV-4979,4980, 4956,4958, KL-HV-5172B GS-HV-4978, 5055B, 50578, 5050B, 5052B, 5054B, 5053B GS-HV-5035,4966BI 50226,49596, 4965B, 49558,4983B GS-HV-5019B, 4984B, 4974 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step)

STANDARD Operator verifies that ALL of the listed valveslequipment in this group have responded correctly to the initiating event. TL .-106-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation) Page 7 of 16 JPM: SM002 Rev: 00 SYSTEM: Primary Containment TASK: Respond To A Containment Isolation OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TL .-I 06-0303 NAME: DATE: STEP NO. ELEMENT RBVS SUPPLYlEXH GU-HD-9370A, 93706 GR-HD-9414A, 941 4B 0 DW PURGE SUPlEXH GT-HD-9372A. 9372C RECIRC SAMPLE BB-SV-4310,4311 RWCU BG-HV-F001 , F004 (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator verifies that ALL of the listed valveslequipment in this group have responded correctly to the initiating event. ~~ Operator verifies that ALL of the listed valves/equipment in this group have responded correctly to the initiating event. Operator verifies that ALL of the listed valveslequipment in this group have responded correctly to the initiating event. ~~ Operator verifies that ALL of the listed valves/equipment in this group have responded correctly to the initiating event. EVAL SIU COMMENTS (Required for UNSAT eva I u a t i o n) Page 8 of 16 JPM: SM002 Rev: 00 CUE SYSTEM: Primary Containment TASK: Respond To A Containment Isolation I ~~ ~ WHEN operator informs you the task is complete, the JPM has been terminated for other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: NO. STEP I ELEMENT I OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE T .I 06-0303 NAME: DATE: Page 9 of 16 I TQ-AA-I 06-031 33 EVALUATOR JPM Number: SM002 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM FOLLOWUP QUESTION DOCUMENTATION -- NAME: DATE: TASK: Respond To A Containment Isolation TASK NUMBER: 4000760401 _- QUESTION: - RESPONSE: -- RESULT: SAT 11 UNSAT QUESTION: _- RESPONSE: RESULT: SAT I UNSAT I Page 10 of 16 TQ-AA-106-030 3 306 PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Hope Creek is recovering from a Scram due to loss of all RFP's at 97% power. 2. RPV level dropped to -90" before recovering with HPCl and RCIC. 3. EOP-101 and EOP-102 are being implemented.

INITIATING CUE: Ensure all required NSSSS and PClS isolations have occurred IAW HC.OP-AB.CONT-0002 Attachments 1 and 2. Page 11 of 16 TQ-AA-I 06-0:.03 JOBPERFORMANCEMEASURE SIMULATOR SETUF INSTRUCTIONS (OPTIONAL) I.C. 7 i lnifial INITIALIZE the simulator to 97% power. TRIP all three RFPTs. CONTROL HPCllRClC such that RPV level recovers to the normal band. A IMPLEMENT EOP-101/102 for the transient. PREP FOR TRAINING (ie., RMl1 set points, procedures, bezel covers) I I 1 1 lnifial I Description -.I ~~ ~ ~ ~~ ~ r- 7CHECGiqh;buIbs for -38" RPV level Isolation Valves INCLUDING all TIP drawers. 4 COMPLETE "Simulator Ready-for-Training/Examination Checklist" Page 'l2 of 16 TQ-AA-106-03 13 _- /nit,a/ ET # Description EVENT ACTION: et-array(1) 1 COMMAND: irf et023 normal EVENT ACTION: et-array(2) 2 COMMAND: irf et024 normal PURPOSE: _- PURPOSE: _- EVENT ACTION: JOBPERFORMANCEMEASURE Si MU LATOR SETUP I NSTRUCTI ONS (OPTIONAL) Page I3 of 16 TQ-AA-I 06-0373 lnitial JOBPERFORMANCEMEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) Description Delay Ramp Trigger lnit Val ET023 GROUP 9B HV-FO19 DW Eqp Sump lsol --- --- None --- ET024 GROUP 96 HV-F020 DW Eqp Sump lsol --- --- None --- FAIL 4s IS Ramp Trigger Init Val --- None --- --- lnitial Description FW26A Feedwater Pump Turbine AS105 Trip FW26B Feedwater Pump Turbine BS105 Trip --- None I I FW26C Feedwater Pump Turbine CS105 Trip 1 --- / --- / None 1 --- 1 I REMOTElFlELD FUNCTION

SUMMARY

I I I I I I I -7 I/O OVERRIDE

SUMMARY

- Page 14 of 16 TQ-AA-106-0323 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: SM002 Rev # 00 00 Date Description I Vali:on] 9/6/08 New JPM. 12/5/08 Required?

N I Validated with 2 ROs from C Shift. Avg validation time 9 minutes added to page 2 I- I I I i- -2 JOB PERFORMANCE MEASURE STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: ALTERNATE PATH: APPLlCABl LITY: Eo u Hope Creek Emergency Diesel Generator Perform Non-Emergency Operation of the Diesel Genera tors 2640030101 305H-JPM. KJ008 REV#: 01 NOH05JPKJ08E RO STA Fl SRO Ix/ DEVELOPED BY: Archie E. Faulkner DATE: 12/7/08 REVIEWED BY: &@ DATE: \L\ii[g nstructor pe rat ions Representative APPROVED BY: hl DATE: /<Ah@ L Training Department TQ-AA-I 06-0303 STATION: Hope Creek JPM NUMBER: KJ008 REV: 01 SYSTEM: Emergency Diesel Generator TASK NUMBER: 26400301 01 TASK: Perform Non-Emergency Operation of the Diesel Generators ALTERNATE PATH: 1-1 WA NUMBER: 264000A4.04 IMPORTANCE FACTOR: 3.7 3.7 -- - APPLICABILITY: RO SRQ EOFI ROFi STAI SRO(XI EVALUATION SETTlNGlMETHOD: SimulatorlPerform

REFERENCES:

HC.OP-SO.KJ-0007 Rev 46; HC.OP-SO.PB-0001 Rev 24 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP -SO.PB-0001 Rev 24 ESTIMATED COMPLETION TIME: 14 Minutes N/A Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: JPM PERFORMED BY: GRADE: USAT DUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: _- EVALUATOR'S SIGNATURE: DATE: Page 2 of 16 TQ-AA-I 06-0303 NAME: DATE: SYSTEM: Emergency Diesel Generator TASK: Perform Non-Emergency Operation of the Diesel Generators TASK NUMBER: 2640030101 INITIAL CONDITIONS:

1. 2. 3. 4. 5. 6. 1 OA401 bus had been shifted to the Alternate breaker 401 01 in preparation for work on the NORMAL breaker 401 08. The improper tagout of the 40108 breaker caused the AG400 EDG to start and load onto the 10A401 bus. All components have been restored to their normal condition. Station Service Transformers 1AX501 and 1BX501 are in service to supply power to class I E 4.16Kv Busses. Preparations are in progress to shutdown EDG A in accordance with HC.OP-SO.KJ- 0001, Section 5.7. HC.OP-SO.PB-0001 is complete through step 5.7.4.

INITIATING CUE: Shift the breaker alignment on the 10A401 bus from the Diesel Generator Breaker to the ALTERNATE Supply Breaker (401 01) in accordance with HC.OP-SO.PB-0001, Step 5.7.5. Page 3 of 16 JPM: KJ008 Rev: 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE 1 .-I 06-0303 NAME: DATE: SYSTEM: Emergency Diesel Generator TASK: Perform Non-Emergency Operation of the Diesel Generators (*Denotes a Critical Step)

• COMMENTS STEP ELEMENT

(#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD

1. SIU evaluation)

Operator repeats back initiating cue. 1 CUE I PROVIDE the operator the initiating cue. 1 Operator locates the proper procedure. Operator obtains/locates procedure HC.OP-SO.PB-0001. or reviews Precautions and Precautions and Limitations, inform operator that all are satisfied. Operator determines beginning step of the procedure. ENSURE that the prerequisites of Section 2.7 have been satisfied. Operator reviews Prerequisites and initials each Prerequisite in the space provided in the procedure. Page 4 of 16 JPM: KJ008 Rev: 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator TASK: Perform Non-Emergency Operation of the Diesel Generators ELEMENT .. I STEP NO. STANDARD CUE: If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied. (*Denotes a Critical Step) (#Denotes a Sequential Step) The operator then initials the appropriate procedure step. 5.7.5 SHIFT breaker alignment on the desired Class I E 41 60V Busses (listed in Table PB-002, Section 5.4) from the Diesel Generator Breaker to the Normal (Alternate) FEED BRKR I as follows: 5.7.5. A PRESS DIESEL ENG GOV INCR push-button AND INCREASE Generator frequency to 61 Hz. Operator presses the DIESEL ENG GOV INCR push-button. Operator observes engine frequency rise to 61 Hz on FI-6393A. 5.7.5. B PRESS DIESEL ENG GOV DROOP MODE push-button AND ENSURE that the DROOP MODE light for EDG, is illuminated. Operator depresses the DIESEL ENG GOV DROOP MODE push-button. Operator observes the DROOP MODE light is illuminated. Page 5 of 16 TL. . .~-106-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation) TL i-I 06-0303 ELEMENT JPM: KJ008 OPERATOR TRAINING PROGRAM (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Rev: 01 SYSTEM: TASK: 7 5.7.5. C IF required' ADJUST EDG frequency to 60 Hz by pressing the DIESEL buttons as applicable. ENG GOV INCR DECR push- 5.7.5. D Operator adjusts frequency to 60 Hz by pressing the DIESEL ENG GOV INCR DECR push-buttons 5.7.5. E PLACE the Normal (Alternate) FEED 1 BRKR-SYNC KEYLOCK Switch in the , ON position. Operator observes frequency at approximately 60 Hz on FI-6393A. ENSURE the DROOP MODE light for the Diesel AND the SYNC indicator lights are ON. -~ Operator places the Alternate FEED Switch in the ON position. (401 01) BRKR-SYNC KEYLOCK Operator observes the Alternate FEED Switch in the ON position. (40101) BRKR-SYNC KEYLOCK Operator observes the Sync Scope rotating . Operator observes the DROOP MODE light for the Diesel is ON. ~~ Operator observes the SYNC indicator lights are ON while the sync scope is off 12 O'clock position. - * # - NAME: DATE: COMMENTS (Required for UNSAT evaluation) - Page 6 of 16 1 - A-I 06-0303 NAME: JPM: KJ008 Rev: 01 SYSTEM: Emergency Diesel Generator TASK: STEP NO. 5.7.5. F 5.7.5. G 5.7.5. G.1. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Perform Non-Emergencv Operation of the Diesel Generators ELEMENT ENSURE that the Normal AND Alternate Feeder Breaker AUTO CLOSE BLOCK PB backlights are OFF. PERFORM the following to synchronize across AND CLOSE the Normal (Alternate) FEED BRKR: - IF necessary, ADJUST the Running Voltage using the GEN VR RAISE LOWER PBs, to match Diesel Generator Running Voltage WITH Bus Incoming Voltage. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the Normal (401 08) AUTO CLOSE BLOCK PB, and ensures that the Normal and Alternate Feeder Breaker AUTO CLOSE BLOCK PB backlights are OFF. ~ Operator observes that the Normal and Alternate Feeder Breaker AUTO CLOSE BLOCK PB backlights are OFF. Operator ensures the Diesel Generator Running Voltage and Bus Incoming Voltage are matched on VI-641 1A and VI-641 2A. (Adjustment using the GEN VR RAISE required. Should be within half an increment . ) LOWER PBs may be - * # -

• DATE: COMMENTS SIU evaluation)

EVAL I (Required for UNSAT Page 7 of 16 TL . .A-106-0303 ELEMENT JPM: KJ008 OPERATOR TRAINING PROGRAM (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Rev: 01 SYSTEM: TASK: ADJUST DG Speed UNTIL the SYNCHROSCOPE pointer is moving slowly in the SLOW (counter clockwise) direction by pressing the DIESEL ENG INCR DECR PB. 5.7.5. G.2. Operator presses the DIESEL ENG INCR or DECR PB. 5.7.5. G.3. WHEN synchroscope pointer is at 3 minutes past 12 O'clock (before pointer reaches 12 O'r,!ock in its direction of travel), THEN CLOSE the Normal (Alternate) FEED BRKR. 5.7.5. H When synchroscope pointer is approximately 3 minutes past 12 O'clock, the operator closes the Alternate FEED BRKR (401 0-1 j by pressing the 401 01 CLOSE PB. ~ __~~ ~ PRESS the AUTO CLOSE BLOCK PB for the Normal(A1ternate) Feed Breaker AND VERIFY that the AUTO CLOSE BLOCK PI3 is illuminated. [ C D-0 56 HI Operator presses the AUTO CLOSE BLOCK PB for 40101. Operator observes the synchroscope pointer rotating in the SLOW direction. Operator observes the Alternate FEED BRKR (40101) CLOSE light illuminates and the green TRIP light extinguishes. Operator observes that the AUTO CLOSE BLOCK PB is illuminated. - * # -

• NAME: DATE: 7 COMMENTS (Required for UNSAT Page 8 of 16 JPM: KJ008 Rev: 01 STEP NO. 5.7.5.1 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE

(*Denotes a Critical Step) I

• ELEMENT (#Denotes a Sequential Step) STANDARD # PLACE the Normal (Alternate)

FEED BRKR -SYNC KEYLOCK Switch in the OFF position. OFF position. Operator places the Alternate FEED BRKR-SYNC KEYLOCK Switch in the

• 5.7.5. J ~ ~~ ~ Operator observes that the synchroscope de-energizes. As directed by the CRS, UNLOAD AND STOP the ~i~~~l G~~~~~~~~

IAW Operator informs the CRS of the status of the EDG. HC.OP-SO.KJ-0001 (Q). WHEN operator informs you the task is complete, - OR the JPM has been terminated for other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: TL 4-1 06-0303 NAME: DATE: (Required for UNSAT evaluation) Page 9 of 16 TQ-AA-I 06-02103 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM I EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: KJ008 , TASK: Perform Non-Emergency Operation of the Diesel Generators I I TASK NUMBER: 2640030101 I -- QUESTION: RESPONSE: I -- RESULT: SAT 1 1 UNSAT -1 l- QUESTION: , -__ RESP 0 N S E: RESULT: SAT I] UNSAT Page 10 of 16 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: I TQ-AA-I 06-01 03 1. 2. 3. 4. 5. 6. 10A401 bus had been shifted to the Alternate breaker 40101 in preparation for work on the NORMAL breaker 40108. The improper tagout of the 401 08 breaker caused the AG400 EDG to start and load ontc the 10A401 bus. All components have been restored to their normal condition. Station Service Transformers 1AX501 and 16x501 are in service to supply power to clac s 1E 4.16Kv Busses. Preparations are in progress to shutdown EDG A in accordance with HC.OP-SO.KJ-000' , Section 5.7. HC.OP-SO.PB-0001 is complete through step 5.7.4. INITIATING CUE: Shift the breaker alignment on the 10A401 bus from the Diesel Generator Breaker to the ALTERNATE Supply Breaker (401 01 ) in accordance with HC.OP-SO.PB-0001, Step 5.7.5. Page I1 of 16 TQ-AA-2 06-0: 03 JOBPERFORMANCEMEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) I INITIALIZE the simulator to rated power, MOL. I i TRANSFER 1 OA401 to the ALTERNATE FEED BRKR. START, parallel, and load EDG A. ENSURE Isochronous light is ON. OPEN breaker 401 08. ACKNOWLEDGE overhead and local alarms. ADJUST generator voltage for bus voltage -4300 volts. ADJUST bus frequency to 60 Hertz. SWAP busses 1 OA402, 403, and 404 to Alternate infeeds. PREP FOR TRAINING (i.e., RMI I set points, procedures, bezel covers) I I 1 5.7.4. including Attachment

1. I I I ! ! I Page 12 of 16 TQ-AA-106-0:

io3 initial JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) _- ET # Description EVENT ACTION: 1 COMMAND: EVENT ACTION: 2 COMMAND: PURPOSE: __. EVENT TRIGGERS: - PURPOSE: _- Page 13 of 16 I TQ-AA-106-0: 03 lnitial JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCT I ON S (OPTIONAL) Ramp Trigger lnit Val Final Val - -- -I 1 Description ' Delay --- --- --- --- ~ I --- --- --- --- MALFUNCTION

SUMMARY

I I - lnifial 1 Description I Delay Ramp 1 Trigger I Init Val I Final /a1 1 I i i REMOTElFlELD FUNCTION

SUMMARY

I I I I 110 OVERRIDE

SUMMARY

- Page 14 of 16 TQ-AA-106-0203 Date 11/10/2008 JOB PERFORMANCE MEASURE REVISION HISTORY Description Validaticln Required? - Y This revision converts to HC LOR format, documents validation, and generates estimated completion time. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted. Updated Reference procedure revision numbers. JPM NUMBER: KJ008 1211 1/2008 Rev # 01 Validated with 2 ROs from !3 Shift. Average completion time is N 14 minutes. Incorporated recommendation to swap other bus 01 infeed breaker to alternate to prevent 311 lineup complications.

STATDO !4 : SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: JDE; pEilr:Qg$&&cE pYJig4i,SuxE Hcqe ,Creek Re a '320 I. Auxi I i a ri e s Coo I i n g S y st e rn Respond To A Reactor Auxiliary Cooling Malfunction 4000230401 305H-JPlVI.ED002 NOH05JPED02E REV#: 01 ALTERNATE PATH: APP LICABILIITY: EO n IXI DEVELOPED BY: Archie E. Faulkner DATE: 8/26/08 Instructor Of;erations Representative APPROVED BY: BATE: 9//7,/flt Training Department SYSTEM : Reactoi- Auxiliaries Cooling System TASK NUMBER: 4000230401 TASK: Respond To A Reactor Auxiliary Cooling Malfunction ALTERNATE PATH: Fl K/A NUMBER: 29501 8 AA2.02 __ __ 3.4 IMPORTANCE FACTOR:

3.3 APPLICABILITY

RO SRO EOI ROW1 STAm SROFI EVALUATION SETTlNGlMETHOD: Simulator,'Perform

REFERENCES:

HC.OP-SO.ED-0001 Rev 22 HC.OP-AR.ZZ-0002 Rev 17 HC.OP-AB.COOL-0003 Rev 3 TOOLS, EQUIPMENT AND PROCEDURES: Wone ESTIMATED COMPLETION TIME: 13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: - GRADE: USAT nUNSA7 ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: Page 2 of $6 BATE: S','ST&iM

Reastor Auxiliaries Cooling System TASK: Respnd To A Reactor Auxiliary Cooling Ma1fun::tion TASK NUMBER: 400023040?

INlTlAL CONDITIONS:

1. The RACS System is in service with the AP209 and CP209 RkCS pumps running. 2. AP209 RACS pump is scheduled for an oil change. 3. The Reactor Building EO has been briefed arld is stationed at the BP209 RACS pump. 4. The BP209 has KT been isoiated since the last time it was in service and is ready for a start. INITIATING CUE: You are the Plant Operator.

Place the BP209 RACS pump in service and secure the AP209 RACS pump, Page 3 of 16 T. ___ __ JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 01 SYSTEM: TASK: CUE 5.3.1 JOB PERFORMANCE MEASURE Reactor Auxiliaries Cooling System Respond To A Reactor Auxiliary Cooling Malfunction ELEMENT PROVIDE the operator the initiating cue. Operator repeats back initiating cue. ENTER START TIME AFTER OPERATORREPEATSBACK INITIATING CUE: START TIME: I procedure. I I Operator reviews precautions and limitations. If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. Operator determines beginning step of the procedure. ENSURE all prerequisites have been satisfied IAW Section 2.3. Reactor Auxiliaries Cooling Water System is in service. CUE if excessive time is taken reviewing prerequisites, inform operator that all are satisfied. - - HC.OP-SO.ED-0001. I I limitations. I Operator reviews precautions and Operator determines correct beginning step to be

5.3.1. Operator

ensures that all prerequisites have been satisfied. Operator then initials the appropriate procedure step. .__- -- NIA Page 4 of 16 JPM: EDU02 OPERATOR TRAINING PROGRAM Rev: 01 SYSTEM: TASK: 5.3.4 JOB PERFORMANCE MEASURE Reactor Auxiliaries Cooling System Respond To A Reactor Auxiliary Cooling Malfunction ELEMENT ENSURE that one of the following valves are OPEN (I OC651 A): ED-HV-2537A(B) HX INLET VLVS. ' OBSERVE the following lights are off for the RACS Pumps going in service: e OVLDlPWR FAIL

8) INOP 0 REMOTE For the 1AP209 and/or I BP209, as applicable, ENSURE RACS PMP 1AP209 BKR andlor 1 BP209 BKR 52-4201 1 CLOSED is on. (10C650E) 52-41 01 I, On 10C651A operator observes the HX INLET VALVES: HX AE217 INLET red HV2537A OPEN light is illuminated and green CLOSE light is extinguished HX BE217 INLET red HV2537B OPEN light is illuminated and green CLOSE light is extinguished.

e Operator observes the REACTOR PUMP B amber OVLD/PWR FAIL, INOP, and white REMOTE lights are extinguished. AlJXlLlARlES COOLING PUMPS On 1 OC650E operator observes the red CLOSED light is illuminated and green TRIPPED light is extinguished RACS PMP BP209 BRKR 52-4201 1 Ti. 4-106-0303 NAME: ____I COMMENTS (Required for UNSAT eva I u ati o !I) Page 5 of 16 JPM: EDC02 Rev: 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction STEP N0= 5.3.5 5.3.6 5.3.7 ELEMENT - IF returning a pump to service that has been isolated and drained, PERFORM the following steps as necessary to correctlprevent air binding, otherwise, PROCEED to Step 0 for a normal start of a standby pump: PRESS REACTOR AUXILIARIES COOLING PUMP A(B)(C) START PB (10C651A). START comes on. OBSERVE AI-6460 (Al-6461) REACTOR AUXILIARIES COOLING PUMP A(B)(C) MOT AMPS settles at < 180 amps AND is approximately the same as the other IIS RACS pumps' motor amps. PRESS REACTOR AUXILIARIES COOLING PUMP B(A)(C) STOP PB. STOP comes on. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines to proceed to Step 5.3.6, since the Initiating Cue states that the pump was not isolated. Operator presses the REACTOR AUXILIARIES COOLING PUMPS PUMP B BP209 START pushbutton.

1. - # Operator observes:

0 The red BP209 START light illuminates and the green STOP light extinguishes. e Al-6461 is < 180 amps and settles at approximately the same value as the "A" and 'C' RACS pumps' amps. Operator presses the REACTOR AUXILIARIES COOLING PUMPS PUMP A STOP pushbutton. ~~ Operator observes the green STOP light illuminates and the red AP209 START light extinguishes. 7 EVAL ' si w _ Page 6 of 16 JPM: ED002 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction STEP NO. ELEMENT NIA Operations Fundamental: Control Board Awareness NIA ATT E2 H C . 0 P- AR . ZZ-0 0 0 2 OPERATOR ACTION: 1. REFER to HC. OP-AB . COOL-0003( Q); Reactor Auxiliary Cooling System. 2. ENSURE compliance with Technical Specifications 3.6.3 - Containment Isolation Valves.

3. ENSURE compliance with Technical Specifications 3.6.5 - Secondary Containment Integrity. (*Denotes a Critical Step) (#Denotes a Sequential Step)

STANDARD 5 seconds after the 'A' RACS pump has been secured, the Operator observes the following: e OHA A2-E2, "RACS TROUBLE" CRlDS D5762 RACS PUMP BP209 TRBL 0 Amber OVLDIPWR FAIL is flashing Red BP209 START light is extinguished. Green STOP light is flashing. e o AI-6461 reads 0 amps NIA Operator refers to HC.OP-AB.COOL-0003. T'\ 4-f 06-8303 NAME: EVAL siu Page 7 of 16 JPM: ED002 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction I STEP NO. ELEMENT CUE Direct the Operator to perform Condition 'A' of HCQP-AB.COOL-0003 Reactor Auxiliary Cooling System. N/A I HC.QP-AB.COOL-OQ03 COND A Time A. I CUE ' PRESS the START P.B. for anv available RACS pump in standby Respond to any reports of the 'A' RACS pump failure to start by directing the operator to continue implementing Condition 'A' of H C .O P-AB. COO L-000 3. 6 .-a 06-0393 .___- NAME. DATE. ~ __ 1 T--__I-.---" ("Denotes a Critical Step) + c=OMMJ"sEIJrC I (#Denotes a Sequential Step) EVAL (Required io. !SPiSP,X Operator enters the current Time in the space provided. I I t-------------- - - Operator presses the REACTOR AUXILIARIES COOLING PUMPS PUMP A AP209 START pushbutton. ll r Operator observes: o The red AP209 START light remains extinguished and the green STOP light remains illuminated. o Motor amps continue to indicate 0. I I I JPM: ED002 OPERATOR TRAINING PROGRAM Rev: 01 SYSTEM: TASK: STEP NO. A.2 CUE JOB PERFORMANCE MEASURE Reactor Auxiliaries Cooling System Respond To A Reactor Auxiliarv Coolinq Malfunction ELEMENT I E a second RACS Pump CANNOT be placed in service, THEN ISOLATE RACS to the out of service Off-Gas Train as follows: E the Common Off-Gas Train is in service, e __ IF Unit 1 Off-Gas Train is in service, 0 THEN CLOSE HV-2577. THEN CLOSE HV-7712Al. If the Operator Closes HV2577 the JPM may be terminated. If the operator closes the HV7712A1, allow 1 minute to recognize the mistake and then terminate the JPM. Leaving the HV7712A1 closed andlor causing an isolation of the Common Offgas Train is failure criteria. ("Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes the OFFGAS RECOMB TRAIN SELECT: e COM TRAIN red OPEN light illuminated and green CLOSE light extinguished. TRAIN 1 red OPEN light extinguished and green CLOSE light illuminated. e Operator presses the OFF GAS CLR CNDS COOLli\lG IOE306 Ui\ilT 7 green CLOSE pushbutton 1

• Operator observes the green CLOSE light illuminates and red HV2577 OPEN light extinguishes.

NIA EWAL siu Page 9 of 16 JPM: ED002 OPERATOR TRAINING PROGRAM Rev: 01 SYSTEM: TASK: JOB PERFORMANCE MEASURE Reactor Auxiliaries Cooling System Respond To A Reactor Auxiliary Cooling Malfunction - ELEMENT WHEN operator informs you the task is complete, other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: the JPM has been terminated for NAME: STANDARD eval uatkon) Page 10 of 16 JPM Number: ED002 TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 -_ QUESTION: -_ RESPONSE: RESULT: SAT ,I UNSAT -_ QUESTION: -_ RESPONSE: RESULT: SAT [-I UNSAT I] I N IT I At. c 9 N u i TI Q N s : 1 2 3 4 The RAGS System is in service with the AP209 and CP209 RACS pumps ruiinin~ AP209 RACS pump is schedulec for an oil change The Reactor Building EO has been briefed and IS stationed at the BP209 RACS pump The EP209 has NOT been isolated since the last time it was in service and ts ready for a stai-t fMlTlATlNG CUE: You are the Plant Operator. Place the BP209 RACS pump in service and secure the AQ209 F?ACS pump. Page 1% of 46

1. WITPAL CONDITIONS:

___y INITIALIZE the simulator to any IC with the Main Generator loaded ENSURE the 'A' 8 'C' RACS pumps are in service arid the 'B' RACS pump is in STBY ENSURE the Common OffGas Train IS in service and HV-2577 IS open /n/t/a/ Description ENSURE simulator IS reset 1 COMMAND, - PURPOSE. Trips BP209 RACS pump after the AP209 RACS pump is stopped EVENT ACTION: 2 COMMAND: PURPOSE: - Page 13 sf I6 CW08B Trip of BP209 RACS pump JPM NUMBER: ED002 Required' ______ Rev# 1 Jag [x/ Fk, ;':b$1A%"LSCE FL(&5*s;'LFLE STAT ION : plop6 Creel: SYSTEM: Reactor Rest rculation TASK: TASK NUMBER: 2020080401 Perform Scoop Tube Positioner Lock-Up Operation JPM NUMBER: 305H-JPM.BB002 SAP BET: NOH05JPBB02E ALTERNATE PATH: FI REV#: 16 APPLICABILITY: EO RO PI STA 1-1 SRO Archie E. Faulkner DATE: 9/4/08 DEVELOPED BY: Instructor REVIEWED BY: fl i'r- BATE: fl .IC / Operations Representative Training Department

• ? STATION: !lop3 wreck SPM NIblJIEEht?,:

B3002 5 YS TE I\li : TASK NUMBER: 2020080401 TASK: 2eactor Recirculation Perform Scoop Tube Positioner Lock-Up Operation __ ALTERNATE PATH: FI WA NUMBER: 202002 A2.05 APP LlCAB I LITY: RO SRO __ 3. I 3.1 IMPORTANCE FACTOR: EO[[ RO[XJ STAm SROR EV ALU AT1 0 N S ETTl N GIM ETH OD :

REFERENCES:

HC.OP-SO.BB-0002 Rev 72 S i m u I a to r/Pe rfo rm TOOLS, EQUIPMENT AND PROCEDURES: None Minutes ESTIMATED COMPLETION TIME: TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Vhx~tes 17 _- JPM PERFORMED BY: - GRADE: OSAT UUNSAS. ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF JPM UNSATISFACTORY: __ EVALUATOR'S SIGNATURE: BABE: Page 2 of 23 SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-Up Operation TASK NUMBER: 2020080401 lNfTIAL CONDITIONS:

1. 2. 3. 4. 5. 6. 7. 8. The plant was at 80% Reactor Power with power ascension in progress.

The SPRVESG guidance is valid. Some rods may already be inserted. A control signal failure caused the 'A' Reactor Recirc Pump Motor/Generator Scoop The 'A' Reactor Recirc pump was placed in Scoop Tube Positioner Lockup Operation I&C has repaired the control signal failure. An NCO is stationed at the 'A' Reactor Recirc Pump Motor/Generator Scoop Tube Positioner. Manual adjustment of the 'A' Reactor Recit-c Scoop Tube has been terminated. The 'A' Reactor Recirc Scoop Tube Positioner Power Switch is ON. Tube to lock-up. IAW HC.OP-SO.BB-0002. INITIATING CUE: You are the Reactor Operator Reset the Scoop Tube lockup on the 'A' Reactor Recirc pump. Page 3 of 13 T JPM: BBOu2 OPERATOR TKAlNlNG PROGRAM NAME: Rev: 16 SYSTEM: TASK: I JOB PERFORMANCE MEASURE Reactor Recirculation Perform Scoop Tube Positioner Lock-Up Operation ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: Operator obtains the correct procedure. 0 p e ra to r review s p re ca IJ t i o n s a nd limitations. - IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied. Operator determines beginning step of the procedure. Improper reset of a Scoop Tube Positioner can result in a significant power transient, and possible Scram due to rapid changes in Recirculation Flow. __rr_ - - .-.-. 7 Operator repeats back initiating cue. Operator obtains procedure __ ~. ~~- HC.OP-SO.BB-0002. I/ I I/ I 0 pe ra to r reviews p rem ut io n s a nd limitations. Operator determines correct beginning step to be 5.9.1. Page 4 of 13 JPM: BB002 Rev: 16 SYSTEM: TASK: STEP NO. 5.9.1 CUE 5.9.2 5.9.3 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Reactor Recirculation Perform Scoop Tube Positioner Lock-Up Operation ELEMENT ENSURE all prerequisites have been satisfied IAW Section 2.9. - IF excessive time is taken reviewing prerequisites, THEN INFORM operator that all are satisfied. PRESS SIC-621A MAN AND SIC- 621B MAN push buttons. PRESS SIC-620 OUTPUT A(B) SELECT push button, for the Pump that will be reset. NAME DATE: - (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator ensures that all prerequisites have been satisfied. t NIA Operator observes SIC-R621A/B MAN are illuminated and AUTO is extinguished. Examiner Note: Operator may press buttons even with pumps already in MAN. If buttons are NOT pressed, "CIM" should be entered in place-keeping block. Operator observes OUTPUT A SELECT light is illuminated. Examiner Note: Operator may press button even with OUTPUT A already selected. If button is NOT pressed, TIM" should be entered in place-keeping block. Y N Fiaygiriy Y N Ffagging Page 5 of 13 JPM: BB002 Rev: 16 SYSTEM: TASK: STEP NO. NOTE 5.9.4 Reactor Recirculation Perform SCOOD Tube Pssitioner Lock-Ur, ELEMENT SIC-62lA(B) SPEED DEMAND (demanded scoop tube position) may move while the scoop tube is locked due to a maintained deviation between actual and demanded speeds. Depending on the actual conditions, it may be either above or below the scoop tube position corresponding to the actual speed. This step determines the desired demanded scope tube position for the actual speed. Using Attachment 3, DETERMINE the desired SIC-621A(B) SPEED DEMAND for the actual SPEED indicated on SIC-621A(B). ~- OPERATOR TRAINING PROGRAM NAME. JOBPERFORMANCEMEASURE DATE __ ~- ,era t i on I I NIA I Operator determines the desired 62% IAW Attachment

3. Examiner Note: The target SPEED DEMAND is 60%. Some leeway has been added for meter readability and the potential interpolation of Attachment 3 data. SIC-R621A SPEED DEMAND to be 58- Page 6 of 13 JPM: BBOU2 Rev: 16 SYSTEM: TASK: STEP NO. 5.9.5 NOTE CAUT OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Reactor Rec,, culation Perform Scoop Tube Positioner Lock-Up Operation ELEMENT PRESS SIC-R621A(B)

SPD CONT INCREASE OR DECREASE pushbutton as necessary to obtain the desired SIC-621A(B) SPEED DEMAND from Step 5.9.4. With actual speed (SIC-R621A(B) SPEED) and demanded speed (SIC- 620 AI5 DEMND OUTPT) the same, the controller signal (SIC-R62lA(B) SPEED DEMAND) should not move. Although a constant speed should be maintained when coming out of Lockup, a small speed change may be experienced. When coming out of Scoop Tube Lockup, the potential exists for the Recirc Pump to "Run Away", and the operator should be prepared to take appropriate action. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the SIC-R621 A LOOP A SPD INCR andlor DECR pb until SIC-R621A SPEED DEMND matches the SPEED DEMAND from Step 5.9.4. Examiner Note: SPEED DEMAND is considered to be satisfactorily matched if reactor power does not change by more than 5% when scoop tube is reset. NIA NIA Page 7 of 13 NAME: - EVAL SIU T. -:3%n?Q3 ____________ ~ - JPM. BB002 OPERATOR TRAINING PROGRAM NAME Rev. 16 JOBPERFORMANCEMEASURE DATE. - SYSTEM: Reactor Recirculation TASK Perform Scoop Tube Positioner Lock-Up Operation UP light extinguishes Operator observes that the SCOOP THEN PERFORM the following to manually reduce the speed of the Reactor Recirc Pump A@) from the the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". I i I I - _- Page 8 of 13 c -~ NAME: DATE: -__ JPM Number: BB002 TASK: Periorm Scoop Tube Positioner Lock-Up Operation TASK NUMBER: 2020080401 -_ RESPONSE: RESULT: §AT 1 UNSAT -_ QUESTION: -_ RESPONSE: RESULT: SAT UNSAT Page 9 of 13

1. fp1',B11Al CONDITIONS:

I.C. 7 INITIALIZE the simulator to 80% power, MOL as follows e REDUCE Reactor Recirc pump speeds to 60°h (It IS critical that 'A' Recirc pump speed is 60%). I INSERT IOB rods to 06 PRESS the REACTOR RECIRCULATION PUMP A TRIPS SCOOP TUBE TRIP pushbutton. ENSURE SIC-R621A AND SIC-R621 B are in Manual. ]REDUCE SlC-R621A Demand Output by 4% AND allow SICR621A SPEED DEMAND to saturate low. ENSURE SGR620 MAST CONT OUTPUT A SELECT is selected. Initial Description INITIAL a copy of HC.OP-SO.BB-0002 Section 5.5 f~r the 'A' Reactor Recirc Pump. COMPLETE "Simulator Ready-for-TraininglExamination Checklist". EVENT TRIGGERS: I ~~ Initial ET # Description EVENT ACTION: 1 COMMAND: PURPOSE: EVENT ACTION: COMMAND: PURPOSE: Page 1'1 of 13 r- 800 ZJPI6 -- 91 _- Con'itr-ol Rod Drive Hyci:aulics Conduct Emergency I\/iat;eup To The RPV Using Two CKD Pumps 201 0200'1 04 NQHOSJPBFI 3E REV #: 01 DEVELOPED BY: Archie E. Faulkner - lnstrueQoP REVIEWED BY: APPROVED BY: / DATE: 8/28/2008 Training Department TQ-AA-106-0301 STATION: Hope Creek JPM NUMBER: BFOI 3 REV: 01 SYSTEM: Control Rod Drive Hydraulics TASK NUMBER: 201 02001 04 TASK: Conduct Emergency Makeup To The RPV Using Two CRD Pumps K/A NUMBER: 295031 EA 1.08 IMPORTANCE FACTOR: 3.8 3.9 AP PLlCABl LITY: RO SRO EVALUATION SETTINGIMETHOD: Reactor BuildinglSimulate

REFERENCES:

HC.OP-SO.BF-0001, Rev 28 TOOLS, EQUIPMENT AND PROCEDURES: Drain hose, Pipe wrench ESTIMATED COMPLETION TIME: 26 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes JPM PERFORMED BY: GRADE: USAT DUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF UNSATISFACTORY: DATE: __ EVALUATOR'S SIGNATURE: Page 2 of 12 s Y s T E Fir, : Control Rod Driv6 iiyaraulics TASU: Conduci Emergency Makeup To The EP'v' Using Two CEG Pumps TASK NUMBER: 2010200104 IN ITlAL co ND ITIONS: 1. 2. 3. 4. 5. 6. The plant was scrammed due to a loss of condensate and feedwater. HPCl and RClC are unavailable. EOP-101, ReactorlPressure Vessel (RPV) Control, is being implemented. Emergency Makeup to the RPV with CRD is required. The BP207 CRD pump, BF201 Pump Suction Filter, 5F204 Drive Water Filter, and the 'B' FCV are currently in service. The scram has not been reset. You are the Reactor Building operator. Perform steps 5.4.1 through 5.4.10 of HCOP-S0,BF-0001 to lineup for two CRD pump injection. Another operator will be assigned to perform the remaining steps and control injection. Page 3 of f.2 JPM: BF013 Fie\J: 01 SYSTEM: Control Rod Drive Hydrauiics OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STEP NO. TASK: Conduct Emergency Makeup To The WPV Using TWO CRD Pumps ELEMENT STANDARD CUE CUE CUE 4.0 PROVIDE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: I I Operator obtains procedure HC.OP-SO.BF-0001. Operator reviews precautions and limitations. If excessive the is taken reviewing precautions and limitations, inform operator that all are satisfied. EQUIPMENT REQUIRED QI Wrench to remove cap from Stabilizing valve needle valve. position Stabilizing valve r?eedle valve stern AND locknut Hoses (for filling & venting). e Small adjustable wrench io d Operator determines beginning step nf fhe ~rncedijre~ Operator repeats back initiating cue. Operator obtains the coi-rect procedure. Operator reviews precautions and limitations. Operator obtains hose and pipe wrench. Examiner Note: After operator has demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location. 5ased on initial conditions, Operator may NOT obtain hose to direct venting and may vent to the floor. 0 pera to r determines correct beg inning step to be 5.4.1. Page 4 sb 92 I I -'f OG-0'303 Tk JPM: BF013 OPERATOR TRAINII\!G PROGRAM Rev: 01 SYSTEM: TASK: JOB PERFORMANCE MEASURE Control Rod Drive Hydraulics Conduct Emergency Makeup To The RPV Using Two CRD Pumps ELEMENT (+Denotes 3 Critical Step) (#Qenotes a Sequential Step) STANDARD ENSURE all prerequisites of Section 2.4 are satisfied. Operator ensures that ail prerequisites have been satisfied. If excessive time is taken reviewing prerequisites , i nfo ran opera tor that dl are satisfied. PERFORM the following to place AF201(BF201), A(B) Pump Suction Filter, in-service: A. OPEN l-BF-V078(I-BF-V029), CRD Suct Fltr AF201 (BF201) Inlet Vlv. Operator opens 1 -BF-V078.

• 8 I The valve you indicated is open. I I B. VENT filter using 1-BF-VO81 (I - BF-V036), CRD Suct Fltr AF201 (BF2011 Vent Vlv. Operator uncaps 1

-6F-VQ81 * # Operator connects a hose between valve 2-BF-VQ81 and a drain huh. NAME: .~ ~___--- Operator unlocks I -BF-V081. Ogeraior throttles open I -BF-VQ81.

• - I A steady stream of water flows from the vent line ~ Page 5 of 'i2 JPM: BF013 Rev: 07 OPERATOR TRAINING PROGRAM J05 PERFORMANCE MEASURE SYSTEM. Control Rod Drive Hydraulics TASK. CQnduCt Emergency Makeup TQ The RPV Using Two CRD Pumps ELEMENT __ _______ ~- -~ ~ 1 I Control Rooin based on Initial - Page 6 ~f 12 JPM: BF013 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE Conduct Emergency Makeup Bo The RPV Using Two CRD Prmps SYSTEM: Control Rod Drive Hydraulics TASK: E LE M E Ni CUE You hear flow noise through the walve. The valve you indicated is spen. A. OPEN 1 -BF-VOOS( 1 -BF-VOI 0), I I CRD Drive Wtr Fltr Inlet Vlv. CUE The valve you indicated is open. 1 6. OPEN 1 -BF-VOI 1(1 -BF-V012), CRD Drive Wtr Fltr Outlet Vlv. Operator opens I -BF-VOl I. CUE 5.4.8 The vaive you indicated is open. REQUEST the Main Control Room to open HV-F003, DRIVE WTR PC VLV. r Operator requests the Main Control Room open HV-FGO3. 1 5.4.9 I OPEN 1-5F-VO62, DRIVE WTR PC Operator unlocks and opens the VLV BYPASS. 1 -BF-V062.

Page 7 of 12 JPM: BS-013 Rev: 01 SYSTEM: TASK: 7 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE DAT-E: -~ Csntrcl Rod Drive Hydraulics Conduct Emergency Makeup To The RPV Using Two CRD Pumps The valve you indicated is fully open. WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECQRD the STOP time. REPEAT BACK any messqe frcm the operator on the status of the JPM, and then state "This JPM is complete". STOP TlME: , 3PM iduinbcr: UFO13 TASK: Conduc: Emergency Makeup Yo The EPV Using Two CRD Pui-rlps TASK NUMBER: 201U200104 QUESTION: RESPONSE: RESULT: QUE STI 0 N : RE § PON SE: - - RESULT: UNSAT I, 2. 3. 4. 5. G. 1-hc plant was scrammed due to B 13s of condensm and feedwater. HPZl and RClC are unavailable. EOP-101: ReactorlPressure Vessel (E?V) Control, is Seing implemented. Emergency Makup to the RPV with CRD is required. The BP207 CRB pump, BF2O'i Pump Suction Filter, 6F204 Drive Water Fiker, and the 'E' FCV are currently in service. The scram has not been reset. INiTlAPlNG CUE: You are the Reactor Building operator. Perform steps 5.4.1 through 5.4.10 of IiC.OP-SO.BF-0001 to lineup for two CRD pump injection. Another operator will be assigned to perform the remaining steps and control injection. 7 81282008 Revised to new JPM formal Revalidated JPM time. i 01 I Updated reference procedure revision number. '3perator I I I I -7 Y I I I I -4 i y actions did not change. i 7 -7 ' TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504 JPM NUMBER: 305H-JPM. BE002 REV#: 08 SAP BET: NOH05JPBE02E ALTERNATE PATH: I( APPLICABILITY: EO RO /xJ STA [Ti SRO /XI DEVELOPED BY: Archie E. Faulkner DATE: 9/3/08 Instructor REVIEWED BY: DATE: Operations Representative APPROVED BY: DATE: Training Departtnen t REV: 08 r\ h ii3;je dr~~eI\ c-*-,: ;-l,-JK: &IWr KUM5ER: SEO32 SP'SI'EM: Core Spray TASK NUMBER: 2000530504 TASK: Perform Torus Makeup Via Core Spray System __ ALTERNATEPATH: 1 I KIA NUMBER: 295030 EA1.06 IMPORTANCE FACTOR: 3.4 3.4 APPLICABILITY: RO SRO _- EVALUATION SETTING/METHOD: Reactor Building/Simulate

REFERENCES:

HC.OP-EO.ZZ-0315 (Q) Rev. 4 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 14 Minutes Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A JPM PERFORMED BY: GRADE: 17 SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: __ EVALUATOR'S §le NATU RE: DATE: _- Page 2 of I1 SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504 INITIAL CONDITIONS:

1. A leak on the 'D' RHK Pump suction line has lowered suppression pool level to 73 2. The leak has been isolated and suppression pool level is stable. inches. INITIATING CUE: Make-up to the Suppression Chamber from Core Spray Loop B IAW HC.OP-EO.ZZ-0315 Page 3 of I1 , 4.4 JPM: BE002 OPERATOR TRAINING PROGRAM NAME: Rev: 08 JOB PERFORMANCE MEASURE DATE: SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Sprav Svstem STEP NO. CUE CUE CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

OPERATOR REPEATS BACK INITIATING CUE: Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. Operator determines beginning step of the procedure. Operator determines correct beginning step to be 5.1. Page 4 of 11 JPM: BE002 Rev: 08 SYSTEM: TASK: STEP NO. 4.0 5.7 .I CUE 5.1.2 CUE Core Spray Perform Torus MakeuD Via Core SDrav Svstem OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE ELEMENT EQUIPMENT REQUIRED 4.1 Key #9 for EOP Locker in OSC (obtain from OS office or break red key holder glass in OSC EOP-315 lmplementation Kit (EOP Locker in OSC) Contents: 1 Wire Cutter AND ENSURE that all prerequisites have been satisfied IAW Section 2.1. 14 excessive time is taken reviewing prerequisites, i nform operator that all are satisfied. UNLOCK AND OPEN 1-AP-V068 llCond Stor & Xfr to Core Spray Pump B and D Suction Fill ti Flush lsln Vlvll. (local, Room 4203 reactor building, elevation 77') The valve you indicated is unlocked and open. ("Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator obtains the following required equipment:

1. Key #9 for EOP locker in OSC (obtain from OS office or break red key holder glass in OSC) EOP iocker in OSC 2. EOP-315 implementation kit from Examiner Note:

After operator has demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location. Operator ensures that all prerequisites have been satisfied. Operator UNLOCIS and OPENS 1 -AP- V068, Cond Stor and Xfr to Core Spray Pump B & D Suction Fill & Flush lsln Valve located on the 77 ft. elevation of the reactor building. Page 5 of 11 JPM: BE002 Rev: 08 SYSTEM: Core Spray TASK. Perform Torus Makeup Via Core SDrav Si STEP NO. 5.1.3 CUE 5.1.4 CUE CUE ELEMENT ENSURE the following (PANEL C650) are OPEN: A. HV-F001B CS Pmp B Suct lsln MOV B. HV-FOOID CS Pmp D Suct Ish MQV Respond as the MCR, HV-FOOIB and HV-FO01D are open. UNLOCK AND THRQTTLE OPEN one QR both of the following valves to obtain the desired fill rate while monitoring CST and Torus levels (local, reactor building, elevation 54'): A. BE-VO58 CS Pmps B & D Suct X- Tie Ish Vlv B. BE-V059 CS Pmps B & D Suct X- Tie Ish Vlv (As appropriate) The valve you indicated is throttled open. Flow can be heard past the valve(s). If operator informs Control Room, provide Terminating Cue. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE 'tern ("Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator contacts Control Room and directs Control Room Operator to verify OPEN HV-F001 B and HV-F001 D. Examiner Note: Operator may verify these valves OPEN before leaving the Control Room Area. Operator throttles open BE-V058 and/or BE-V059. __ - Operator informs Control Room that Suppression Chamber makeup is in p rog ress . Page 6 of 11 JPM: BE032 Rev: 08 SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray S STEP NO. ELEMENT THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE

tern (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD NAME - Page 7 of 11 a JPM Number

BE002 TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504

_______ QUESTION: -_ RE§ PONSE: RESULT: SAT UNSAT -_ QUESTION: RESPONSE: RESULT: UNSAT Page 8 of 11 L ,a+ '. . I I-h 1 ,.-$&-::I$-' ,; p f N i-mb. c 0 N DE Ti CSld s : I A leak on the 'D' RHR P~lmp suWi-1 iine has lowered suppressim pool level to 73 inches. 2 The leak has been isolated and suppi-essnn pool level is stable. INITIATING CUE: Make-up to the Suppression Chamber from Core Spray Loop *3 IAW HC.OP-EO.ZZ-0315 Description ~ VaIidatio i , ____ _- format Revalidated JPM time. revision number. Operator actions did not change. for BE-V059. __-__ SYSTEFdI: Re a c t o r P r c) 'is c t I o r I S y 5; t 2 rn TASK: Transfer RPS Bus klE Power FroITi Alternate Source 7-0 RPS IUG Set TASK NgMBER: 21 200501 C1 JPM NUMBER: 305H-JPM.SBOI5 REV#: 02 SAP BET: NOH05JPSB45E ALTERNATE PATH: Archie E. Faulkner DATE: 5128108 DEVELOPED BY: fnseructor APPROVED BY: DATE: Braining Qe part me tit I - TQ-AA-106-0302 STATION: Hope Creek JPM NUMBER: SB015 REV: 02 SYSTEM: Reactor Protection System TASK NUMBER: TASK: 2 120050 I 01 Transfer RPS Bus A/B Power From Alternate Source To RPS MG S 3t ALTERNATEPATH: I X I KIA NUMBER: 21 2000 A2.01 IMPORTANCE FACTOR: 3.7 3.9 APP LlCABl LITY: RO SRO EVALUATION SETTINGIMETHOD: Aux Building/Simulate

REFERENCES:

HC.OP-SOSB-0001 Rev 28 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 12 Minutes I TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes I JPM PERFORMED BY: GRADE: USAT UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY: _- EVALUATOR'S SIGNATURE: DATE: ~~ ~ Page 2 of 14 SYSTE!M: E e 2 c t 0 r Pro t e cii o n S v s t e rr TAS 1;: Transfer RPS Bus hlE POWE; Fr:m Alternate Source To RPS 1dG Set 1. The plant is at 100% power. 2. RPS A is being powered from the ALTERNATE A FEED. 3. Maintenance has been completed on 1A-G-401, RPS MG set. 4. Once the lvlG Set IS running, Maintenance needs to checldadjust NIG Set output voltage in accordance with Step 5.5.2.D. BMlTBAPBMG CUE: Start the 1A-6-4.01, RPS MG SET A, in preparation to transfer RPS Bus A power from RPS Alternate Transformer A to RPS MG SET A in accordance with Section 5.5 of Contact Maintenance when ready for MG set output voltage cheddadji-1st. HC.OP-SO .S B-0001. i JPM: SB015 1 Rev: 02 TL 106-0303 OPERATOR TRAINING PROGRAM NAME: __ JOB PERFORMANCE MEASURE DATE. i SYSTEM: Reactor Protection System TASK: Transfer RPS Bus AIS Power From Alternate Source To RPS MG Set STEP NO. ELEMENT PROVlDE the operator the initiating I CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains procedure HC .OP-SO.SB-0001. I Operator reviews precautions and limitations. CUE If excessive time is taken reviewing operator that all are satisfied. Operator determines beginning step of the procedure. I precautions and limitations, inform ENSURE all prerequisites of Section 2.5 are satisfied. If excessive time is taken reviewing prerequisites, inform operator that all are satisfied. CUE Operator repeats back initiating cue. ____ Operator obtains the correct procedure. li Operator reviews precautions and limitations. II ll Opera tor determines correct beg inning ster, to be 5.5.1 Operator ensures that all prerequisites have been satisfied. Page 4 of 14 JPM: SBulS Rev: 02 SYSTEM: Reactor Protection System Operator observes the Red MOTOR OPERATOR I KAlNlNG PROGRAM JOB PERFORMANCE MEASURE TASK: Transfer RPS Bus AIS Power FKNII Alternate Source To RPS MG Set ELEMENT IF asked about the current statuslindications, state: The Red MOTOR ON lamp is extinguished, and the Green MOTOR OFF lamp is illuminated. The output breaker is I I The operator then initials the appropriate procedure step. Page 5 ~t I4 JPM: Si3015 Rev: 02 b. PRESS AND HBh5 MOTOR OFF push-button. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE __.~ __ The operator then initials the Operator presses and holds the AG401 # MOTOR OFF push-button.

• appropriate procedure

__ step. ___-___ SYSTEM: Reactor Protection System TASK: Transfer RPS Bus AI6 Power From Alternate Source TQ RPS MG Set ELEMENT B. VERIFY A-C VOLTS Generator Operator observes A-C VOLTS Output Voltage AND PERFORM 1. E voltage increases to 11 5 - AND has been stabilized for approximately 5 seconds, THEN RELEASE the MOTOR Generator Output Voltage and expects a voltage increase to 11 5-1 25 volts which stabilizes for approximately 5 The meter identified rises and stabilizes at approximately 100 to 1 15 - 125 volts, THEN PERFORM the following:

a. RELEASE the MOTOR ON Dush-button.

Page 6 of I4 JPM: SBOls Rev: 02 TC ?06-&i393 - - ~ OPERATOR TkAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE. ______~ ~- SYSTEM: Reactor Protection System TASK. Transfer RPS Bus AB Power From Alternate Source To RPS MG Set __c- -- -- ce:B;r'FgF%! lr. (Required fon- IJNFAT S/W e 3 B I i 9 ti 0 f 1) STEP $; NO. 8 ELEMENT I I c. WHEN the MOTOR ON light extinguishes, THEN RELEASE the MOTOR OFF push-button. CUE The Red MOTOR ON lamp is extinguished, and the Green MOTOR OFF lamp is illuminated. I I d. REPEAT Step 5.5.2.A. CUE If asked about restarting the MG Set, inform the operator that one restart attempt is allowed and restart can be attempted while the MG Set is spinning. L I When the AG401 MOTOR ON light extinguishes, the operator releases the AG401 MOTOR OFF push-button. The operator then initials the appropriate procedure step. ~ ~~ Operator returns to Step 5.5.2.A. I The operator then initials the appropriate procedure step. Page I at 44 JPM: 33015 Rev: 02 SYSTEM: Reactor Protection System OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Transfer RPS Bus Ah3 Power From Alternate Source To RPS MG Set STEP NO. 5.5.2 CUE ELEMENT ("Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD - IF start of 1A(B)G401, RPS MG Set, is necessary, THEN PERFORM the following (ACB] MG Set Local Panel): A. PRESS AND HOLD the MOTOR ON push-button (Red MOTOR ON lamp illuminates). Operator presses and holds the AG401 MOTOR ON push-button. Operator observes the Red MOTOR ON lamp illuminates. The Red MOTOR ON lamp is illuminated, and the Green MOTOR OFF lamp is extinguished. The operator then initials the appropriate procedure step. B. VEWlFY A-C VOLTS Generator Output Voltage AND PERFORM the following:

1. voltage increases to 11 5 - 125 volts AND has been stabilized for approximately 5 seconds, THEN RELEASE the MOTOR ON push-button.

Operator observes A-C VOLTS Generator Output Voltage expecting an increase to 'I 15-1 25 volts. Page 8 of 14 JPM: S5015 Rev: 02 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Transfer RPS Bus AIB Power From Alternate Source To RPS MG Set ELEMENT The meter identified has risen from 0 volts, and has stabilized at approximately 120 volts for approximately 5 seconds. Operator releases the AG401 MOTOR ON push-button. The operator then initials the appropriate procedure step.

2. voltage does NOT increase tc! 1 ,I 5 - 125 vo!ts, THEN PERFORM the following: Operator determines this step no longer i I C. ViHEN 1 minute of MG Set operation has elapsed, THEN PLACE RPS MG Set 1 A(B)G401 GENERATOR OUTPUT breaker to ON AND IMlTlAb Attachment I. Operator waits one minute. _- Operator places the RPS M6 Set AG401 GENERATOR OUTPUT breaker to ON CUE The breaker identified is in the stated position. Operator initials Attachment

1. I I I Page 9 of 14 JPM: SBO15 Rev: 02 SYSTEM: Reactor Protection System OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Transfer RPS Bus AI6 Power From Alternate Source To RPS MG Set STEP NO. CUE CUE ELEMENT D. REQUEST Maintenance Department to CHECK AND ADJUST (as necessary), the RPS MG Set(s) output voltage at the input to Electrical Protection Assembly (EPA) Circuit Breaker IAN410 (1 AN41 1 ) (unloaded)

IAW HC. MD-PM .SB-000 I (a), GTHERLYISE, VERIFY A-C VOLTS at local panel meter is 11 5 tc 125 volts. Respond as necessary and provide iie rrn i nati ng Cue. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD The operator then initials the appropriate procedure step. Operator requests maintenance io check and adjust if necessary RPS MG Set A output voltage at the input to Electrical Protection Assembly (EPA) Circuit Breaker 1 AN41 0 (unloaded) otherwise, verify A-C VOLTS at local panel meter is 1 I5 to 'I 25 voIts. IAW HC. MD-PM. S 5-000 1 (Q), WHEN operator informs you the task is complete, OR the JP M has been terminated for other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". SBOP TIME: - TASK: Transfer RPS Eus WE Power From Alternate Source To RPS ME Set TkSK NUMBER: 2t20050101 - QUE STION: -.__I - RESPONSE: RESULT: QUESTION: UNSAT RESPONSE: RES U LT: SAT 1-j LINSA'T i Page 11 of14

7. 2. 3. 4. The plant IS at 100% power. RPS A is being powered from the ALTERNLTE A FEED. Maintenance has been completed on 14-G-401, RPS MG set Once the MG Set IS running, Maintenance needs to checWadjust MG Set output voltage in accordance with Step 5.5.2.D. INITIATING CUE: . Start the I A-G-401, RPS MG SET A, in preparation to transfer RPS Bus A power from RPS Alternate Transformer A to RPS MG SET A in accordance with Section 5.5 of Contact Maintenance when ready for MG set output voltage checkladjust.

HC. OP-SO. SB-0001. b Bate I ______ I I I Descriptio 9: Validation Updated reference procedure revisiori number. Operator I LIT----- i actions did not change. I JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned TASK NUMBER: 2990750302 JPM NUMBER: 305H-JPM.ZZ009 REV#: 01 ***NRC ADMIN JPM SRO AI *** SAP BET: NOH05 J PZZOSE ALTERNATE PATH: FI DEVELOPED BY: J. Berglund DATE: I 1/9/08 Instructor REVIEWED BY: ax@ DATE: / >/ f 0 erations Representative APPROVED BY: /7A Iw' DATE: / yl~/bfi - / I""' Training Department TQ-AA-106-0303 _- STATION: Hope Creek JPM NUMBER: 22009 SYSTEM: TASK NUMBER: 2990750302 TASK: Co nd uct of Ope rat ions Ensure the Operating Shift is Adequately REV: 9annet 01 -- ALTERNATEPATH: I X 1 KIA NUMBER: 2.1.5 APPLICABILITY: RO SRO -- IMPORTANCE FACTOR: 2.9 3.8 EVALUATION SETTINGIMETHOD: Classroom/Perform

REFERENCES:

LS-AA-119 Rev 5 Tech Spec 6.2.2 TOOLS, EQUIPMENT AND PROCEDURES: Blank paper copy of LS-AA-119 Attachment 1 "Overtime Guideline Deviation Authorization." ESTIMATED COMPLETION TIME: 10 Minutes N/A Minutes TIME PERIOD IDENTIFIED FOR TIME CRlTlCAL STEPS: JPM PERFORMED BY: GRADE: USAT UUNSAf ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY: _- DATE: -- EVALUATOR'S SIGNATURE: Page 2 of 16 TQ-AA-106-0303 NAME: - DATE: SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned TASK NUMBER: 2990750302 INITIAL CONDITIONS: The following Hope Creek Generating Station working hour history is given for an Operations crew. The hours worked are in the Main Control Room during Operational Condition

1. Today is 2/5/09. The crew is scheduled to work a 12 hour Dayshift from 0600-1 800 tomorrow, 2/6, on watch in the Main Control Room. INITIATING CUE: EVALUATE the working hour history for the personnel above AND TAKE ANY ACTIONS, if required, to ensure the CRS, RO, and PO watchstations are staffed for the 12 hour 2/6 Dayshift watch tomorrow.

Page 3 of 16 JPM: 22009 Rev: 01 SYSTEM: Conduct of Operations OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Ensure the Operating Shift is Adequately Manned . NO. STEP I ELEMENT PROVIDE the operator the initiating cue AND a paper copy of LS-AA-119. CUE 1 CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: 4.1 .I An individual should not be permitted to work more than 16 hours straight.

1. Activities listed ic Step 1.4.4 may be excluded from time counted toward this time limitation.

An individual should not be permitted to work more than 16 hours in any 24- hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any seven-day (I 68 hr) period. 1. Activities listed in Step 1.4.4 may be excluded from time counted toward these time limitations. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. N/A Operator determines all work hours were applicable and no operator has or will exceed 16 hours straight. Operator determines all work hours were applicable and the RO will exceed 72 hours in a seven-day period if 12 hour 2/6 Dayshift is worked. TQ *I 06-0303 NAME: DATE: f

• COMMENTS (Required for UNSAT evaluation)

Page 4 of 16 JPM: 22009 OPERATOR TRAINING PROGRAM Rev: 01 SYSTEM: TASK: STEP NO. CUE 4.1.3 JOB PERFORMANCE MEASURE Conduct of Operations Ensure the Operating Shift is Adequately Manned ELEMENT I asked whether another RO is available, THEN INFORM the operator that due to a widespread illness, NO other RO's are available. A break of at least eight hours should be allowed between work periods. 1. An eight hour break between work periods only becomes applicable if one of the limitations in Steps 4.1 .I and 4.1.2 has been met or exceeded.

2. Shift turnover time and casual personal time noted in Step 1.4.4 may be included as part of the eight hour break between work periods. ____~ (;Denotes a Critical Step)

(#Denotes a Sequential Step) STANDARD NIA Operator determines CRS will meet the limitations in step 4.1.2 and the RO has met and may exceed the limitations in step 4.1.2, but each operator has had a break of at least eight hours between work periods. Page 5 of 16 1 # *I TQ- .-I 06-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation) TQ. .-I 06-0303 NAME: JPM: 22009 Rev: 01 SYSTEM: Conduct of Operations OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE ELEMENT STEP NO. 4.2 Overtime Guideline Deviation Recognizing that very unusual circumstances may arise (e.g., emergency situations to protect the public safety, critical emergent work requiring specialized skills, actions needed to avoid an unnecessary shutdown, or other urgent activities deemed necessary by station management) requiring deviation from the above guidelines, such deviation shall be considered on an individual basis and authorized by the Plant Manager or designated manager. Authorized deviations to the working hour guidelines shall be documented on Attachment 1 (i.e., each individual's name shall be listed). - IF asked whether another RO is available, THEN INFORM the operator that due to a widespread illness, NO other RO's are available. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines the RO watchstation is required to be staffed in OPCON 1. (Tech Spec 6.2.2) - * # - DATE: (Required for UNSAT evaluation) Page 6 of 16 JPM: 22009 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned STEP NO. 4.2.1 4.2.2 4.2.3 ELEMENT Consistent with GL 82-12, the paramount consideration in such authorization shall be that significant reductions in the effectiveness of personnel would be highly unlikely. Authorized deviations to the working hour guidelines shall be documented on Attachment 1 (Le., each individual's name shall be listed). In an emergency situation, it is acceptable to obtain a verbal overtime guideline deviation authorization prior to an individual exceeding the above guidelines and subsequently complete Attachment 1 when time allows. Overtime hours worked for activities such as vacation coverage, normal shift coverage, do not constitute very unusual circumstances. Overtime worked for these types of activities should not exceed the GL 82-12 limitations. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines Attachment 1 is required to document exceeding work hour guidelines. Operator determines there is sufficient time to complete an Attachment

1. Operator determines lack of operator availability due to widespread illness is unusual circumstance. - * # - TQ. -1 06-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation)

Page 7 of 16 JPM: 22009 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK. Ensure the Operating Shift is Adequately Manned STEP NO. 4.2.4 CUE ELEMENT During activities noted in Step 4.2, overtime guideline deviations shall be considered and approved on an individual basis as noted above. The cognizant supervisor(s) will assess each individual for fatigue and mental alertness prior to an individual exceeding the GL 82-12 overtime guidelines and performing safety-related work. The cognizant supervisor(s) will assess each individual mer the duration an individual is working in excess of the GL 82-12 guidelines. These assessments are not documented.

1. If an individual is observed to be fatigued or exhibits unsatisfactory mental alertness, then the individual will be removed from performing safety-related work. - IF asked about the alertness of the operators, THEN INFORM the operator all three operators appear alert and show no signs of fatigue. (*Denotes a Critical Step) (#Denotes a Sequential Step)

STANDARD Operator assesses workers for alertness and signs of fatigue. NIA - * # - TQ-. .-106-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation) Page 8 of 16 JPM: 22009 Rev: 01 * (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD # Operator determines a single Attachment 1 is required to document exceeding work hour guidelines. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE COMMENTS evaluation) EVAL (Required for UNSAT SIU SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adeauatelv Manned STEP NO. 4.2.5 CUE 4.3 ELEMENT A single Overtime Guideline Deviation Authorization will be completed and remain active for the entire time period an individual exceeds a GL 82- 12 overtime guideline. AFTER the Operator demonstrates the ability to obtain an Attachment 1, THEN PROVIDE a blank copy of Attachment

1. When it has been determined that a deviation from the GL 82-1 2 overtime guidelines is necessary, then prior to an individual exceeding the GL 82-12 overtime guidelines and performing safety-related work, initiate Attachment 1, "Overtime Guideline Deviation Authorization." (cognizant supervisor or designee)

TQ .-I 06-0303 NAME: DATE: NIA Operator obtains blank Attachment 1, "Overtime Guideline Deviation Authorization. Examiner Note: This is included in the provided copy of LS-AA-119. Page 9 of 16 JPM: 22009 Rev: 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned STEP NO. 4.3.1 4.3.2 4.3.3 4.3.4 4.3.5 ELEMENT COMPLETE columns one through four of Attachment

1. 1. If Attachment 1 is being completed for a large number of individuals, multiple forms will be required or a complete list of names may be attached to a single Attachment

1. 2. The "Start Time/Date" in column 4 is the time at which an individual will exceed one of the overtime guidelines, not the start of the shift GT work period.

PROVIDE a description of the work to be performed verifying that the work is safety-related. PROVIDE a justification describing why the safety-related work needs to be performed on overtime. SIGN Attachment 1 as the cognizant supervisor of designee. FORWARD the form to the Plant Manager or designated manager for gpy-nvai (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Examiner Note: Refer to Exhibit I for example of completed form. Operator enters John Jones in Column 1. Operator enters Operations in Column 2. Operator enters D in Column 3. (Long descriptions are also acceptable, such as "72hrs in 7 days") Operator enters 0600 and 2/6/09 in Column 4. Operator enters description of work. Operator enters justification for needing overtime. Description may vary, but should convey "unusual circumstance" and not violate step 4.2. Operator signs and dates the attachment. Operator seeks Plant Manager or designee approval. - - il I-_-- Page 10 of 16 TQ -106-0303 NAME: DATE: EVAL SIU - COMMENTS (Required for UNSAT evaluation) JPM: 22009 Rev: 01 SYSTEM: TASK: STEP NO. CUE CUE OPERATOR TRAINING PROGRAM TQ. 4-1 06-0303 NAME: DATE: JOB PERFORMANCE MEASURE Conduct of Operations Ensure the Operating Shift is Adequately Manned ELEMENT WHEN the operator forwards the Attachment for approval, THEN ROLE PLAY as the Plant Manager and approve the Attachment. WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is c om p I e te " . STOP TIME: COMMENTS (*Denotes a Critical Step) (#Denotes a Sequential Step). I

• I EVAL I (RequiredforUNSAT Page 11 of 16 I TQ-AA-106-03C 3 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION

__ NAME: DATE: __ JPM Number: 22009 TASK: Ensure the Operating Shift is Adequately Manned TASK NUMBER: 2990750302 _- QUESTION: __ __ __ RESPONSE: -- RESULT: SAT UNSAT I __ QUESTION: RESPONSE: RESULT: SAT UNSAT 1 Page 12 of 16 TQ-AA- I 0 6-0 3 13 3 JOB PERFORMANCE MEASURE EXHIBIT 1 overtime guidelines Name DeDartment 1 GL 02-12 1 Time Pe - d ertime Limit is Guideline Exceeded Exceeded Start End (Note 5) TimeIDate TimeIDate (Column 1) (Column 2) (Column 3) (Column 4) (Column 5) - - John Jones Operations D 0600 12-6-09 I I t I I 1 I - I I I I Note 1 : Note 2: The cognizant supervisor will complete the information in columns 1 - 4 above. This form is then forwarded to the Plant Manager (or designated manager) for review. The Plant Manager's (or designated manager's) approval shall be completed prior to an individua exceeding the overtime guidelines and performing safety related work. The Plant Manager's appr wal may be received verbally by telephone. This, form is then forwarded back to the cognizant superv sor. The cognizant supervisor will perform an assessment of each individual's fatigue and mental alertness prior to the start of performing safety-related work; and throughout the duration of the overtime deviation period. If the supervisor observes the individual to be fatigued or not mentally alert, that individual will not be assigned to perform safety-related work. The cognizant supervisor will complete colurnn 5 after the overtime deviation period is complete. GL 82-1 2 Overtime Guideline A - more than 16 consecutive hours to be exceeded: B - more than 16 hours in a 24 hour period C - more than 24 hours in a 48 hour period D - more than 72 hours in a seven day (1 68 hr) period E - less than an 8 hour break between work periods Note 3: Note 4: Note 5: Description of safety-related work to be accomplished: Stand Licensed Operator watch in the Main Contro Room -- Justification for needing overtime: To maintain minimurn staffing IAW T/S 6.2.2. No other operators availab -- r? due to widespread illness. -- -___ -- Submitted by: Opeiratoir NOW / TODAY Cognizant Supervisor (or designee) Time Date Approved by: I Plant Manager (or designated manager) Time Date Page 13 of 16 TQ-AA-106-03 33 Date 1/28/09 1 /29/09 JOB PERFORMANCE MEASURE PO Jim CRS Smith 1 JohEnes BobAdams 12 hours-Days 12 hours-Days 12 hours-Days 12 hours-Davs OFF INITIAL CONDITIONS: 2/3/09 2/4/09 2/5/09 The following Hope Creek Generating Station working hour history is given for an Operation: crew. The hours worked are in the Main Control Room during Operational Condition

1. 12 hours-Days 12 hours-Days 12 hours-Days I2 hours-Days 12 hours-Days 12 hours-Days 12 hours-Days 12 hours-Days 12 hours-Days

/2/2/09120urs-Davs I 12 hours-Daw 1 12 hours-Days 1 Today is 2/5/09. The crew is scheduled to work a 12 hour Dayshift from 0600-1800 tomorrow, 216, on watch i I the Main Control Room. INITIATING CUE: EVALUATE the working hour history for the personnel above AND TAKE ANY ACTIONS, if required, to ensure the CRS, RO, and PO watchstations are staffed for the 12 hour 2/6 Dayshift watch tomorrow. Page 14 of 16 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: TASK NUMBER: Complete The Daily Surveillance Logs 401 001 0201 JPM NUMBER: 305H-JPM.ZZ017 REV#: 01 ***NRC ADMlN JPM SRO A2*** SAP BET: NOH05JPZZ17E J. Berglund DATE: A 1/8/08 lnstryctor DEVELOPED BY: DATE: I /L/P REVIEWED BY: APPROVED BY: TQ-AA-106-0303 - STATION: Hope Creek JPM NUMBER: ZZOl7 REV: 01 SYSTEM: Conduct of Operations TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs _- ALTERNATE PATH: 11 KIA NUMBER: 2.1 .I8 APPLICABILITY: RO SRO _- IMPORTANCE FACTOR: 3.6

3.8 EVALUATION

SETTINGIMETHOD: Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0026 Rev 1 13 TOOLS, EQUIPMENT AND PROCEDURES: Paper copies of HC.OP-DL.ZZ-0026 Attachment 1 Page 1 of I ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: OSAT [7UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY: _- DATE: -- EVALUATOR'S SIGNATURE: Page 2 of 11 TQ-AA- I 06-0 30 : I# NAME: DATE: SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 INITIAL CONDITIONS:

1. The Plant is in OPCON 1 at 35% power 2. A plant startup from a forced outage is in progress IAW HC.OP-I0.Z-0003. 3. The National Weather Service has forecast a Severe Storm Warning for New Castle and Salem Counties for the next 12 hours. 4. River temperature is 83 degF but is NOT expected to exceed 85 degF. 5. All EDGs, SACS, and SSW pumps are operable.

6. The SPV Effluent RMS is inoperable and has been C/T for repairs. INITIATING CUE:

You are the Control Room Supervisor. IMPLEMENT the Daily Surveillance Logs for today IAW HC.OP-DL.ZZ-0026 AND IDENTIFY all required Attachments for current, plant conditions. Page 3 of 11 JPM: 22017 Rev: 01 TQ 4-106-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of Operations ELEMENT Operator repeats back initiating cue. HC.OP-DL.ZZ-0026( Q). Page 4 of 11 JPM: 22017 Rev: 01 SYSTEM: Conduct of Operations TASK: Complete The Dailv Surveillance Logs EVAL SIU STEP NO. COMMENTS (Required for UNSAT evaluation)

2.1 Operator

checks Attachment 3j on Attachment 1 Section A Log Initiation. Operator determines Attachment 3h is required IAW Item 1 and T/S 4.7.1.3.b.l due to current River Water temperature. ELEMENT Shift ManagerlControl Room Supervisor - the SMlCRS is responsible to implement, review, and ensure completion of the log including (CRS has primary responsibility for all log reviews and documentation): 2.1 .I The SM/CRS shall implement the log at the beginning of each day by completing Attachment 1, Section A; Log Initiation, listing those Attachments that require performance due to present conditions. Also, the present Operational Condition shall be listed. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # Examiner Note: Examiner Copy Exhibit 1 is provided for reference. Operator determines Attachment 1 is required due to current Operational Condition. I* Operator checks Attachment 1 on Attachment 1 Section A Log Initiation. Operator determined Attachment 3j is required due to Severe Storm Warning that mav affect Artificial Island.. Operator checks Attachment 3h on Attachment 1 Section A Log Initiation. Operator determines Attachment 3t is required IAW Item 42 due to SPV RMS Inoperable. Operator checks Attachment 3t on Attachment 1 Section A Log Initiation.

• TG t-106-0303 NAME: DATE: Operator places a "I" in the Operational Condition blank.

~- Page 5 of 11 JPM: 22017 Rev: 01 SYSTEM: TASK: CUE Conduct of Operations Complete The Daily Surveillance Logs ELEMENT 2.1 .I The SMlCRS shall implement the log at the beginning of each day by completing Attachment 1, Section A; Log Initiation, listing those Attachments that require performance due to present conditions. Also, the present Operational Condition shall be listed. WHEN operator informs you the task is conplete, the JPM has been terminated for other reasons , THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator checks Attachment 5 on Attachment 1 Section A Log Initiation. Examiner Note: Although not specifically required by the current conditions, Attachment 5 is typically used each day to track surveillance procedures and would be needed the first time a surveillance procedure with an action time is actually logged on. TG &-I 06-0303 NAME: DATE: COMMENTS (Required for UNSAT evaluation) Page 6 of 11 TQ-AA-I 06-01 03 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: 22017 TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 QUESTION: RESULT: SAT UNSAT TI QUESTION: __ RESPONSE: RESULT: UNSAT Page 7 of 11 TQ-AA-106-0303 JOB PERFORMANCE MEASURE ATTACHMENT 1 Surveillance Log A. LOG INITIATION I .Operational Condition 1- 2.Check (J) Attachments to be performed 1 2 B. Pacie 1 of 1 -___ Date 4a 4b 4c - 3w 3s 3t J 3x 3u 3v - - 3m - 3g - 3p - - 31 J 3q - J 3c 3d 3e 3f - - 3h J 3k LOG PERFORMANCE

1. - - - 3y - J - - 3r - - Ensure compliance with T/S by using procedure numbers and additional action.

Attachment la Auxiliary Bldg Attachment IC Attachment 1 Reactor Bldg Attachment Id Turbine Bldg EVE MID DAY 3. Signature below indicates review of all required attachments checked (4) above has bel An completed, and approved for compliance with T/S requirements. Day (Review Before 1300) Eve (Review Before 2100) Mid (Review Before 0500) - SMICRS SMlCRS SMICRS C. LOG COMPLETION 1 .Operational Condition

2. Check (J) Attachments that have been performed

-"- 1 3c 3g 3m 3s 3w 4a 2 3d 3h 3P 3t 3x 4b 3e 3j 3q 3u 3Y 4c 3f 3k 3r 3v 3z 5 -- -- -- Page 8 of 11 JOBPERFORMANCEMEASURE INITIAL CONDITIONS: i TQ-AA-I 06-0: 03 1. 2. 3. 4. 5. 6. The Plant is in OPCON 1 at 35% power A plant startup from a forced outage is in progress IAW HC.OP-IO.ZZ-0003. The National Weather Service has forecast a Severe Storm Warning for New Castle and Salem Counties for the next 12 hours. River temperature is 83 degF but is NOT expected to exceed 85 degF. All EDGs, SACS, and SSW pumps are operable. The SPV Effluent RMS is inoperable and has been C/T for repairs. INITIATING CUE: You are the Control Room Supervisor. IMPLEMENT the Daily Surveillance Logs for today IAW HC.OP-DL.ZZ-0026 AND IDENTIFY all required Attachments for current plant conditions. STATION : SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: JOB PERFORMANCE MEASURE Hope Creek Equipment Control Authorize the Start of a Surveillance Test 2990250302 305H-JPM .ZZ037 REV#: 00 ***NRC ADMIN JPM SRO A3*** NOH05JPZZ37E ALTERNATE PATH: DEVELOPED BY: J. Berglund REV1 E WED APPROVED Instructor BY: Operations Representative BY: I I f Jd (13 I Training Department V DATE: 1 1/7/08 I TQ-AA-I 06-0303 STATION: Hope Creek JPM NUMBER: 22037 REV: 00 - SYSTEM: Equipment Control TASK NUMBER: 2990250302 TASK: Authorize the Start of a Surveillance Test __ ALTERNATE PATH: KIA NUMBER: 2.2.1 2 APPLICABILITY: RO SRO -- IMPORTANCE FACTOR: 3.7 4.1 EO(I Ron STAII SROm EVALUATION SETTING/METHOD: Classroom

REFERENCES:

HC. OP-ST.ZZ-0001 Rev 29 Technical Specification 3.8.1 .I TOOLS, EQUIPMENT AND PROCEDURES: Technical Specification 3.8.1 .I, Blank copy of HC.OP-ST.ZZ-0001. EST1 MATED COMPLETION TIM E: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 50 Minutes JPM PERFORMED BY: GRADE: USAT UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: Minutes REASON, IF JPM UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 2 of 12 I TQ-AA-106-0303 NAME: - DATE: SYSTEM: Eq u i p m en t Con tro I TASK: Authorize the Start of a Surveillance Test TASK NUMBER: 2990250302 INITIAL CONDITIONS: I. The plant is at 100% power, 3840 MWth. 2. Main Generator output is 1260 Mwe. 3. All 4.16KV 1 E Buses are in a Normal 2 Bus alignment.

4. The "A" EDG was just declared INOPERABLE.

INIl'IATING CUE: This is a Time Critical JPM with one Time Critical element. Initiate and authorize the performance of the HC.OP-ST.ZZ-0001 to satisfy the one hour requirement of T/S 3.8.1 .I action b. Page 3 of 12 TQ-AA-I 06-03t 13 En7@FA&py ATTACHMENT 1 Page 1 of 3 SMlCRS DATA AND SIGNATURE SHEET POWER DISTRIBUTION LINEUP - WEEKLY I .o PRETEST INFORMATION

1.1 Reason

for the Test 1 .I .I Regular Surveillance INITIALS 1.1.2 4.8.1.1.1.a ONLY JMB IN IT1 ALS 1.1.3 Retestlother INITIALS 1 .I .4 IF not performing the corriplete test, THEN LIST subsection(s) to be performed, as well as marking NIA on the applicable subsection(s) on the Attachment(s) that will not be performed, OR that do not require an independent verification IAW OP-AA-108-101-1002, Component Configuration Control. May list subsections in step 5.4 SUBS ECTION(S) - 1.2 Plant Conditions -. I .2.1 Operational Condition 1 - 1.2.2 Reactor Power Level I00%13840 MWth __ 1.2.3 MWe 1260 MWe 1.3 Permission to Perform the Test

1.3.1 Permission

granted to perform this test. Page 9 of 12 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power, 3840 MWth. 2. Main Generator output is 1260 Mwe. 3. All 4.1 6KV I E Buses are in a Normal 2 Bus alignment.

4. The "A EDG was just declared INOPERABLE.

INITIATING CUE: I TQ-AA-I 06-0: 03 This is a Time Critical JPM with one Time Critical element. Initiate and authorize the performance of the HC.OP-ST.ZZ-0001 to satisfy the one hour requirement of T/S 3.8.1 .I action b. Page 10 of 12 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: TASK NUMBER: 2990740302 Perform Leak Rate Measurement Data Sheet for W Or Steam Filled Piping te JPM NUMBER: 305H-JPM.ZZ032 REV#: 01 ***NRC ADMlN JPM SRO A4*** SAP BET: NOH05JPZZ32E ALTERNATE PATH: DEVELOPED BY: J. Berglund DATE: 1 1/9/08 Instructor REVIEWED BY: DATE: (I(\%[ Operations Rearesentative APPROVED BY: Train i ng De partme n t TQ-AA-106-0303 1 REV: 01 S TAT1 0 N : JPM NUMBER: 22032 SYSTEM: Radiation Control TASK NUMBER: 2990740302 Hope Creek TASK: Perform Leak Rate Measurement Data SI ,eet for Water Or Steam Fi red Piping -- KIA NUMBER: 2.3.1 I ALTERNATE PATH: 1x1 APPLICABILITY: RO SRO 4.3 _- IMPORTANCE FACTOR: 3.8 EO11 ROFI STAFI SROWI EVALUATION SETTING/METHOD: ClassroomPerform REFERENCES

HC. OP-G P .ZZ-0004 Rev 6 TOOLS, EQUIPMENT AND PROCEDURES:

Prepared copy of HC.OP-GP.ZZ-0004 (Attached) ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes JPM PERFORMED BY: - GRADE: USAT DUNSAT Mi n Utes ACTUAL COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF JPM UNSATISFACTORY: -- DATE: EVALUATOR'S SIGNATURE: Page 2 of 26 I TQ-AA-106-0303 NAME: DATE: SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping TASK NUMBER: 2990740302 IN ITlAL CON DlTlONS

1. The plant is Operational Condition 2 with a startup in progress following a Refuel Outage. 2. Pressure has been raised to 905 psig, and preparations are being made to transition to Operational Condition

1. 3. Leakage into the Core Spray Loop A Injection Header has resulted in loop pressurization above normal ECCS Jockey Pump discharge pressure as observed at 1 BEPISH-N654A (Panel 1 OC617) AND 1 BEPLR600A (Panel 1 OC650). LEAKAGE DETERMINATION was performed to determine the leakage rate. 4. HC.OP-GP.ZZ-0004 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE INITIATING CUE: PERFORM the CRS review of the completed HCOP-GP.ZZ-0004 AND DETERMINE any required actions.

Page 3 of 26 JPM: 22032 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Radiation Control Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping TASK. TQ -106-0303 NAME: DATE: STEP NO. CUE CUE ATT. 1 2. I ELEMENT PROVIDE the operator the initiating cue AND the attached prepared copy of HC. OP-GP.ZZ-0004. ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: POST TEST INFORMATION The data acquired during the performance of this test has been reviewed for completeness and compliance with Technical Specification 3.4.3.2, Reactor Coolant System Operational Leakage and the test is considered: (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. Operator reviews completed HC.OP-GP.ZZ-0004. COMMENTS SIU evaluation) EVAL (Required for UNSAT Page 4 of 26 JPM: 22032 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping EVAL SIU STEP NO. 5.1 .I 1 COMMENTS (Required for UNSAT evaluation) ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) I STANDARD CALCULATE the leak rate through by dividing the volume recorded in Step 5.1.9 by the elapsed time recorded in Step 5.1 .IO. RECORD leak rate in gpm on Attachment

2. 1 BE-VO07 (HV-F005A)

Operator recognizes a math error was made when calculating Leak Rate in step 5.1 .I 1. Actual leak rate is 6.3 gpm, NOT 0.63 gpm (6.25 gpm rounded up). data entered, CORRECT ACTUAL block as directed TQ -106-0303 NAME: DATE: 2 Page 5 of 26 JPM: 22032 ELEMENT Rev: 01 SYSTEM: TASK: (*Denotes a Critical Step)

• COMMENTS (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD ## SIU eva I ua t i on) STEP NO. Operator ensures 5.1 .I 1 SATWNSAT l block is corrected to UNSAT.

5.1 .I 1 CUE TQ .-I 06-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: Operator recognizes 5.1 .I 1 ACTUAL Leak Rate exceeds REQUIRED Leak Rate of 5 5 GPM.

• ll I I Examiner Note: Operator may correct , data or ca!! Performer to correct data. - IF directed as Performer to correct data entered, THEN ROLE PLAY as Performer and CORRECT SATNNSAT block as directed by Operator.

NIA Page 6 of 26 JPM: 22032 Rev: 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Radiation Control TASK. Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping STEP NO. TIS 3.4.3.2 ~~ ELEMENT Reactor coolant system leakage shall be limited to: d. 0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1, at rated pressure. APPLICABILITY: OPCON 1,2,3 ACT1 ON : c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one closed manual or deactivated automatic or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines TIS 3.4.3.2 Action c applies: With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one closed manual or deactivated automatic or check* valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. Examiner Note: Determining the SPECIFIC compensatory action is beyond the scope of the JPM. It is only necessary for the Operator to IDENTIFY the applicable Tech Spec Action. TQ ,-I 06-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation1 Page 7 of 26 JPM: 22032 Radiation Control Rev: 01 SYSTEM: TASK: STEP NO. CUE ' ATT. 1 2.1.2 TQ ,-I 06-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: Perform Leak Rate Measurement Data S.,eet for Water Or Steam Filled Piping AFTER the Operator determines the applicable Tech Spec Action statement, THEN INFORM the Operator Operator signs WIW block 2.1.2 of Attac, ,.. .-, UNSATISFACTORY AND - IF necessary the T.S. ACTION statement has been implemented. II I , . ' '"'SATISFACTORY hmnnt 1 WHEN operator informs you the task is complete, other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: the JPM has been terminated for NIA I r Page 8 of 26 I TQ-AA-I 06-03 13 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: JPM Number: 22032 TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping TASK NUMBER: 2990740302 __ QUESTION: -- RESPONSE: RESULT: SAT I I UNSAT i] -- QUESTION: _- _- ___ RESPONSE: RESULT: SAT I 1 UNSAT I) Page 9 of26 I TQ-AA-I 06-031 13 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. 2. 3. The plant is Operational Condition 2 with a startup in progress following a Refuel Outage.

Pressure has been raised to 905 psig, and preparations are being made to transition to Operational Condition

1. Leakage into the Core Spray Loop A Injection Header has resulted in loop pressurization above normal ECCS Jockey Pump discharge pressure as observed at 1 BEPISH-N654A (Panel 1 OC617 I AND 1 BEPLR600A (Panel 1 OC650). LEAKAGE DETERMINATION was performed to determine the leakage rate. 4. HC.OP-GP.ZZ-0004 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE INITIATING CUE: PERFORM the CRS review of the completed HC.OP-GP.ZZ-0004 AND DETERMINE any required actions.

Page 10 of 26 1 Page Ilof 1 PSEG Internal Use Only PSEG NIlJCLEAR L.L.C. HOPE CREEK GElNERATING STATION HC.OP-GP.ZZ-O004(Q) - Rev. 6 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION USE CATEGORY: I ~ ~~ ~ ~~ ~ NIA - - I- A. Biennial Review performed Yes No B. Change Package(s) and Affected Document Number(s) incorporated into this revision. - __ __ - CPNo. 80040594 CPRev.No. 0 ADNo. PO59 AD Rev. No. 0 or None C. OTSC(s) incorporated into this revision: OTSCNo(s) or None -- * - ' 1 .O REVISION

SUMMARY

1. 2. 3. 4. Changed title of Operations Superintendent (OS) to Shift Manager (SM) throughout procedure. These changes are based on changes made in Revision 9 to NC.NA-AP.ZZ-O002(Q), Organizatio 1, and can be considered editorial in nature.

,4ttachment 2 - the notation associated which address the asterisk and acceptance criterion have been re-worded for procedure clarity. These changes are considered editorial based on an allowance in NC.DM-AP.ZZ-000 1 (Q), for rewording or adding text for clarification. DCP 80040594 - the following changes have been incorporated to address the DCP associated \Y th the removal of the RPV head spray header: e Section 2.7 & 5.7 & Attachment 2 [Section 1.71 have been revised to delete the reference o RPV Head Spray Header. e Step 2.7.5 has been revised to delete the reference to RPV Spray Header 0 Step 5.7.1 1 has been revised to delete 1-HC-V020 (HV-F023). Attachment 2 has been revised to reflect this change. Section 4.0 has been changed to a bulleted list. Editorial IMPLEMENTATION REQUIREMENTS Pending closure of DCP 80040594 Effective date APPROVED: - Manager - Nope Creek Operations Date REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION TABLE OF CONTENTS Section Title Page 3 1 .o PURPOSE ....................................................................................... .......................... - 3 2.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 3 .O PRECAUTIONS & LIMITATIONS . ... . . . . . , . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... . . . . . . . . . . . . . 6 4.0 5 .O EQUIPMENT REQUIRED . . . . . .. ... .. . .". . . . . . .. , . . . . . . . . . . .. . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 8 5.1 Core Spray Loop A Injection Header ....................................................... 8 5.2 Core Spray Loop B Injection Header ... ..... .. ..... .. ............ . ... ... .. .... .. ...... ..... 10 5.3 RHR SDC Supply Header from B Recirc Loop ....................................... 12 5.4 RHR C LPCI Injection Header ......... .... ...... ............... ..... .......... ... .. . ..... ..... 13 5.5 RHR D LPCI Injection Header ... , ...... ................... ................. ..... . .. ... ...... . 15 5.6 RHR A LPCJ Injection Header 1' SDC Return Header to A Recirc Loop ..................................................... 18 5.7 RHR B LPCI Injection Header 1' SDC Return Header to B Recirc Loop ..................................................... 20 6.0 RECORDS ................................................ ................................................................ 22 22

7.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ATTACHMENTS Attachment 1 SM/CRS Data and Signature Sheet 

.......................................................... 23 Attachment 2 Inplant Data Sheet .................................................................................... 26 Hope Creek Page 1 of 34 Rev. 6 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE IETERMINATION

1.0 PURPOSE

This procedure can be used to determine if the leakage rate past the Reactor Coolant System Pressure Isolation Valves specified in Technical Specification Table 3.4.3.2-1 is in compliance with Technical Specification 3.4.3.2, Reactor Coolant System Operational Leakage. This procedure may also be used whenever an abnormal increase, or incident of high header pressure is observed at any of the following instruments: 1BEPISH-N654A / 1BEPI-R600A 1 BEPISH-N654B / 1 BEPI-R600B 1 BCPISH-N653A 1BCPISH-N653B 1BCPISH-N653C / IBCPI-N053C lBCPISH-N653D / 1BCPI-N053D 1 BCPISH-N657 2 .O PREREQUISITES 2.1 Core Spray Loop A Iniection Header Leak Rate Test 2.1.1 2.1.2 2.1.3 2.1.4 2.1.5 Permission to perform this test has been obtained fiom the SMKRS as indicated by the completion of Attachment 1, Section 1 .O. All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3 .O, prior to performing any part of ths procedure. No other testing or maintenance is in progress that will adversely affect the performance of this test. The Core Spray System is in a standby lineup. Leakage into the Core Spray Loop A Injection Header has resulted in loop pressurization above nortnal ECCS Jockey Pump discharge pressure as observed at 1BEPISH-N654A (Panel 1 OC6 17) Q& 1BEPI-R600A (Panel 1 OCti50). Hope Creek Page 2 of 34 Rev. 6 PSEG Internal Use Onlv HC.OP-GP.ZZ-0004( Q) 2.1.6 Radiation Protection should be contacted prior to perfoiming venting and/or draining in this procedure. The individual( s) performing the venting and or draining should obtain instructions AND approval from the Radiation Protection Shift Technician the Radiation Protection Supervisor. @@ 2.2 Core Spray Loop B Iniection Header Leak Rate Test 2.2.1 Permission to perform this test bas been obtained from the SM/CRS as indicated by the completion of Attachment 1, Section 1 .O. Nd 2.2.2 All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3.0, prior to performing any part of this procedure. NA 2.2.3 No other testing or maintenance is in progress that will adversely affect the performance of this test. N/A 2.2.4 The Core Spray System is in a standby lineup. N/A 2.2.5 Leakage into the Core Spray Loop B Injection Header has resulted in loop pressurization above normal ECCS Jockey Pump discharge pressure as observed at 1 BEPISH-N654B (Panel 1 OC618) 1BEPI-R600B (Panel 1 OC650). N/A 2.2.6 Radiation Protection should be contacted prior to performing venting and/or draining in this procedure. The individual(s) performing the venting and or draining should obtain instructions AND approval from the Radiation Protection Shift Technician - OR the Radiation Protection Supervisor. NA 2.3 RHR SDC Supply Header from B Recirc Loop 2.3.1 Permission to perform this test has been obtained from the SM/CRS as indicated by the completion of Attachment 1, Section 1 .O. N/A 2.3.2 All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3.0, prior to performing any part of this procedure. 2.3.3 No other testing or maintenance is in progress that will adversely affect the performance of this test. pl& 2.3.4 The RHR System is in a standby lineup. N/A Hope Creek Page 3 of 34 Rev. 6 2.7 RHR B LPCl Iniection Header / SDC Return Header to B Recirc Loop 2.7.1 Permission to perform this test has been obtained fiom the SM/CRS as indicated by the conipletion of Attachment 1, Section 1.0. N/A 2.7.2 All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3.0, prior to performing any part of this procedure.N/A 2.7.3 No other testing or maintenance is in progress that will adversely affect the performance of this test. N/A 2.7.4 The RHR System is in a standby lineup. N/A 2.7.5 Leakage into the RHR B LPCI Injection and SDC Return Header to B Recirc Loop Header has resulted in loop pressurization above normal ECCS Jockey Pump discharge pressure as observed at 1 BCPISH-N653B. (Panel 1 OC6 1 8) N/A 2.7.6 Radiation Protection should be contacted prior to performing venting and/or draining in this procedure. The individual(s) performing the venting and or draining should obtain instructions AND approval fiom the Radiation Protection Shift Technician - OR the Radiation Protection Supervisor. NIA 3.0 PRECAUTIONS AND LIMITATIONS

3.1 Precautions

3.1.1 IF at any time during the performance of this test a step cannot be completed or is observed to be unsatisfactory the NCO AND the SM/CRS should be immediately notified. [CD-927E] @E 3.1.2 This system contains potentially radioactive contaminated fluid. OBSERVE good radiological practices to prevent the spread of contamination. 9@ 3.1.3 - IF leak rate is excessive AND prevents depressurizing piping through any of the specified depressurization points, THEN the specified point should be closed AND the SM/CRS informed of the condition. Hope Creek Page 4 of 34 Rev. 6 HC. OP-GP.ZZ-0004

3.2 Limitations

Performance of all subsections may not be necessary. - IF not performing all subsections, the performer should determine which subsections are to be perfonned. All steps within each subsection are to be performed in sequence unless otherwise specified. 9@ The I&C Technician should install the Measuring and Test Equipment (M&TE) specified in this procedure. w 4.0 EQUIPMENT REQUIRED a Calibrated stop watch a One poly bottle a Two-way radios or equivalent e Pressure indicator (? 2% of full scale accuracy) for injection header pressure determination. Range of instrument must be 0 - 450 psig or less. One Graduated Cylinder ( or equivalent measuring device). e Hope Creek Page 5 of 34 Rev. 6 H C . OP-GP .ZZ-0004( Q) 5.0 PROCEDURE ___ NOTE 5.0 All operations are performed locally unless otherwise noted. 5.1 Core Spray Loop A Iniection Header Leak Rate Test 5. I .1 - IF this is the first subsection of the procedure to be performed, LOG test start time in the Contml Room log(s) E 5.1.2 ENSURE that all prerequisites have been satisfied IAW Section 2.1 of this procedure. E@ 5.1.3 this is the first subsection of the procedure to be performed. ENSURE Attachment 1, Section 1 .O of the SM/CRS Data and Signature Sheet has been completed, @ 5.1.4 RECORD M&TE identification numbers and calibration due dates on Attachment

2. @ 5.1.5 ENSURE 1AP-V041 Condensate Transfer Supply to A CS Loop is closed. (RE3 102' Rm 4331) E 5.1.6 ENSURE 1 -BE-V088 Jockey Pump Supply to A CS Loop is closed. (RJ3. 54' Rm 41 16B) B 5.1.7 OPEN P-BE-V9996 Instrument Root Valve for A Core Spray Pump Discharge Header Pressure Indicator BE-PI-4578A (RB 54' Rm 41 18A). INITIAL Attachment

2. E 5.1.8 RECORD on Attachment 2, the A Core Spray Pump Discharge Header Pressure Indication from BE-PI-4578A.

rn Hope Creek Page 6 of 34 Rev. 6 5.1.9 5.1.10 5.1.11 5.1.12 5.1.13 5.1.14 5.1.15 AND COLLECT leakoff as follJws: E A. B. C. D. REDUCE header pressure by draining into a poly bottle via P-BE-V9992 AND P-BE-V9992 DRI C CS Pump Discharge Pressure Indicator (BE-PI-4578C) Root and Drain Valves (RB 54' Rm 41 16). s WHEN Core Spray A Injection piping pressure as indicated on BE-PI-4578A reaches 100 psig, START the stopwatch and CLOSE AND CAP P-BE:-V9992 DRI. E@ CLOSE P-BE-V9992. s DETERMINE volume of fluid collected (use a graduated cylinder if necessary, AND TAKE into account any fluid dumped). RECORD volume on Attachment

2. Ee WHEN A Core Spray Pump discharge header pressure indication on BE-PI-4578A reaches the initial value recorded in Step 5.1.8, STOP the stop watch AND RECORD elapsed time in Attachment

2. CALCULATE the leak rate through 1 BE-V007 (HV-FOO5A) by dividing the volume recorded in Step 5.1.9 by the elapsed time recorded in Step 5.1.10.

RECORD leak rate in gpm on Attachment

2. Es CLOSE P-BE-V9996 Instrument Root Valve for A Core Spray Pump discharge header pressure indicator BE-PI-4578A.

INITIAL Attachment

2. e - IF required, OPEN Condensate Transfer Supply to A CS Loop AP-V041. (RB 102' Rm 433 1) EE OPEN Jockey Pump Supply to A CS Loop 1-BE-V088.

EE PERFORM independent verification that the A Core Spray System has been returned to normal by completing Attachment 2. RE2 Hope Creek Page 7 of 34 Rev. 6 5.1.16 this is the final subsection of the procedure to be performed, LOG test end time in the Control Room log(s) 5.1.17 this is the final subsection of the procedure to be performed, SUBMIT this procedure to the SM/CRS for review AND completion of Attachment 1. 5.2 Core Sprav Loop B Iniection Header Leak Rate Test 5.2.1 5.2.2 5.2.3 5.2.4 5.2.5 5.2.6 5.2.7 5.2.8 - IF this is the first subsection of the procedure to be performed, LOG test start time in the Control Room log(s) ENSURE that all prerequisites have been satisfied IAW Section 2.2 of this procedure. - IF this is the first subsection of the procedure to be performed, ENSURE Attachment 1, Section 1 .O of the SM/CRS Data and Signature Sheet has been completed,. RECORD stop watch M&TE identification number and calibration due date on Attachment

2. N/A N/A I , N/A ENSURE 1-AP-V062 Condensate Transfer Supply to B CS Loop is closed. (RB 102' Rm 4322B) N/A ENSURE 1-BE-V083 Jockey Pump Supply to B CS Loop is closed. (RB 54' Rm 4105A) N/A OPEN P-BE-V9986 Instrument Root Valve for B Core Spray Pump discharge header pressure indicator BE-PI-4578B (RB 54' Rm 41 04B). INITIAL Attachment

2. N/A RECORD on Attachment 2, the B Core Spray Pump discharge header pressure indication from BE-PI-4578B.

N/A Hope Creek Page 8 of 34 Rev. 6 M&TE as follows AND INITIAL Attachment 3: N/A A. CLOSE Test Connection Valve P-BC-V9958. N:A B. REMOVE MsLTE pressure indicator at test connection PP-NO58B. N/A C. CAP Test Connection PP-N058B. N/A 5.7.14 PERFORM independent verification that the RHR system has been returned to normal by completing Attachment 2. - NIA 5.7.15 this is the final subsection of the procedure to be performed, LOG test end time in the Control Room log(s). N/A 5.7.16 this is the final subsection of the procedure to be performed, SUBMIT this procedure to the SM/CRS for review completion of Attachment

1. N/A 6.0 RECORDS 6.1 RETAIN the following IAW NC.NA-AP.ZZ-0011 (Q); Records Management Program: 0 Procedure cover page 0 0 Attachment 1 - SMKRS Data and Signature Sheet Attachment 2 - Inplant Data Sheet

7.0 REFERENCES

7.1 P&ID: M-51-1 M-52-1 7.2 Procedures NC.NA-AP.ZZ-O005(Q) Station Operating Practices NC.NA-AP.ZZ-O012(Q) Technical Specification Surveillance Program NC.DE-AP.ZZ-O030(Q). Control of Temporary Modification

7.3 Commitment

Documents CD-927E NRC INFO 97-25 CD-358F Page 9 of 34 Rev. 6 Hope Creek ATTACHMENT 1 SM/CRS DATA AND SIGYATURE SHEET REACTOR COOLANT SYSTEM PRESSURE ISOLATION F'ALVE LEAKAGE DETERMINATION 1 .o PRETEST INFORMATION

1.1 Reason

for the Test 1.1.1 Regalar Surveillance INITIALS 1.1.2 Retest/Other Pv JNITIALS I. I .3 - IF not performing the complete test, THEN LIST subsection(s)/ valve(s) to be performed, as we11 as marking N/A on the applicable subsection(s)/ valve(s) on the Attachment(s) that will not be performed, OR that do not require an independent verification IAW ~\~~.NA-AP.ZZ-OOOS(Q); Station Operating Practices. 5.1 Core Spray Loop A Injection Header ONLY __ SLBSECTION(S)NALVES I .2 Plant Conditions _- 1.2.1 Operational Condition 2 -_ 1.2.2 Reactor Power Level 7 ?ho 1.2.3 Reactor Pressure 905 psig __ 1.3 Permission to Perform the Test 1.3.1 Permission granted to perform this test. Today13 hours age. __ DATE-TIME Pew SM/CRS 1.3.2 Order No. - Hope Creek Page 10 of 34 Rev. 6 PSEG Internal Use Only HC.OP-GP.ZZ-O004(Q) ATTACHMENT 1 SM/CRS DATA AND SIGNATURE SHEET REACTOR COOLANT SYSTEM PRESSURE ISOLATION VAL\'E LEAKAGE DETERhlINATION 2.0 POST TEST INFORMATION 2.1 The data acquired during the performance of this test has been reviewed for completeness and compliance with Technical Specification 3.4.3.2, Reactor Coolant System Operational Leakage and the test is considered:

2.1.1 SATISFACTORY

I SMiCRS DATE-TIME

2.1.2 UNSATISFACTORY

AND - IF necessary the T.S. ACTION statement has been implemented. i SMICKS DATE-TIME 2.1.3 Order No. 2.1.4 Remarks Hope Creek Page 11 of 34 Rev. 6 ATTACHMENT 1 SM/CRS DATA AND SIGNATURE SHEET REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION 3 .O PROCEDURE PERFORMER(S) AND VERIFIER(S) 3.1 I have read and understand the steps of this procedure that I am required to perform. (All Departments) PRINT NAME SIGNATURE IN IT1 ALS DATEITIME WY Today13 hrs ago Jim Berglund F# P= Today/Z hrs ago Archie Faulkner AS? Today12 hrs ago Joe Johnson *- - Hope Creek Page 12 of 34 Rev. 6 TQ-AA-106-031t3 JOB PERFORMANCE MEASURE ATTACHMEIVT 2 INPLANT DATA SHEET REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION STEP TEST EQUIPMENT INST. TAG/MTE NO. CAL DUE DATE 1.1 Core Spray Loop A Iniection Header Leak Rate Test - NOTES 5.1.4 - STOPWATCH LDC-1 4/30/09 STEP NOMENCLATURE REQ POSITION PERF IME FOR PRESSURE 5.1.7 P-BE-V9996 BE-PI-4578A ROOT VLV

• The asterisk indicates acceptance criteria - in order to satis@ the requirements of the acceptance criteria, the SATIUNSAT block must be marked SAT. OPEN IWi - STEP NOMENCLATURE REQ POSITION PERF VERIF I 1 1 -BE-V088 I nDEAT CLOSED P-BE-V9996 BE-PI-4578A ROOT VLV F AE7 VI Ll'I 5.1.15 CS LOOP A JOCK PMP TIE-IN ISLN CLOSED P-BE-V9992 BE-PT-4578C ROOT VLV Page 13 of 26 ps AS? p AS? ~~ ~ ~ CLOSED&CAPPED P-BE-V9992 DRT BE-PI-4578C DRAIN VLV As?

JOB PERFORMANCE MEASURE STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: Hope Creek Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition 2000500302/2000020505 305H-JPM.ECG006 REV#: 04 ***NRC ADMlN JPM SRO A5*** NOH05JPCLOGE APPLICABILITY: EO i] RO FI STA /XI SRO PI DEVELOPED BY: Jim Berglund DATE: 12/12/08 Instructor REVIEWED BY: DATE: z,[ (z( 8- Operations Representative APPROVED BY: ' '- Training Department TQ-AA-106-0303 STATION : Hope Creek JPM NUMBER: ECGOOG SYSTEM: Administrative DutieslReporting Requirements TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification ,nc Reportability Of An Event And/or Plant Condition ALTERNATE PATH: IC WA NUMBER: 2.4.38 IMPORTANCE FACTOR: 2.2 4.0 APPLICABILITY: RO SRC EVALUATION SETTINGIMETHOD: Classroom/Perform

REFERENCES:

Hope Creek Event Classification Guide, TOC Rev 81 TOOLS, EQUIPMENT AND PROCEDURES: ESTIMATED COMPLETION TIM E: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 1511 3 Minutes JPM PERFORMED BY: GRADE: USAT DUNSA ACTUAL COMPLETION TIME: Minutes I Minutes ACTUAL TIME CRITICAL COMPLETION TIME: REASON, IF U NSATlS FACTORY: - EVALUATOR'S SIGNATURE: DATE: TQ-AA-106-0303 - NAME: DATE: SYSTEM: Administrative DutiedReporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportabilitv Of An Event And/or Plant Condition TASK NUMBER: 2000500302/2000020505 INITIAL CONDITIONS: 1, With the plant operating at 100% power, Hope Creek experiences an earthquake which indicates a magnitude of > 0.lg. 2. Control Room Annunciator C6-C4 is in. 3. ON Panel lOC673: 1. The SMA-3 Event Indicator is White 2. The Strong Motion Accelerograph Tape Machines have advanced but are not currently running 3. The AMBER alarm light on the Seismic Switch Power Supply Drawer is lit 4. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer.

5. A LOCA results. The Reactor is successfully scrammed, with RPV level dropping rapidly to -250"; then stabilizing between -225" and

-205", being maintained using all available ECCS. 6. Drywell Pressure peaked at 44 psig, then dropped to e2 psig over the next 90 seconds. 7. Drywell Pressure is 1.95 psig and continuing to slowly drop.

8. The current 33 ft. elevation wind direction is from 275" at 7 mph. 9. Plant Effluent activity is 1.17E+01 pCi/sec Noble Gas and 1.17E-02 pCi/sec 1-131. INITIATING CUE: Based on this information, CLASSIFY this event AND MAKE the initial notifications.

This is a Time Critical Task, and has two Time Critical elements. Time zero for this event is now. Page 3 of 17 ECGOOG OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE SYSTEM: Administrative DutieslReporting Requirements

2. REFER to Section EALlRAL Flowchart diagram(s), and identify the Initiating Conditions that are re'ated to the event/condition that has occurred or is ongoing. TQ- a1 06-0303 NAME: Operator refers to Table 3.0 and Flowchart Diagrams and identifies that the Initial Conditions for Table 3.0 and EAL 9.5.2 are related to the event that has occurred.

DATE: TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition (*Denotes a Critical Step) COMMENTS NO. STANDARD # s/u evaluation)

• STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT PROVIDE the operator the initiating Operator repeats back initiating cue.

I CUE 1 cue. ENTER START TIME AFTER I CUE I OPERATOR REPEATS BACK I Operator obtains the correct procedure. Classification Guide. Operator obtains Hope Creek Event Section ECG I Classification: To use this ECG volume, follow this sequence: I. ASSESS the event andlor plant conditions and DETERMINE which ECG section(s) is most appropriate. Operator assesses the initial conditions, and determines that Table 3, Fission Product Barriers, and 9.0, Hazards- InternallExternal, are the appropriate ECG sections. ECG Section i.1V.C I I I I I Page 4 of 17 ECGOOG OPERATOR TRAINING PROGRAM TQ-. *I 06-0303 NAME: DATE: JOBPERFORMANCEMEASURE SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emerc STEP NO. ECG Section i.1V.C ELEMENT 3. REVIEW the associated EALs or RALs as compared to the event and SELECT the highest appropriate emergency or reportable action level. If identification of an EAL is questionable, refer to paragraph 1V.A above. If there is any doubt with regard to assessment of a particular EAL or RAL, the ECG Technical Basis Document should be reviewed. Words contained in an EAL or RAL that are bold face are either threshold values associated with that action level or are words that are defined in the basis for that specific EAL/RAL. icy Classification And/or Reportability Of An Event And/or Plant Condition (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator reviews the EALs in section 9.5, and determines that EAL #9.5.2 is the highest emergency action level met or exceeded (ALERT). EVAL s/u COMMENTS (Required for UNSAT evaluation) I - Page 5 of 17 ECGOOG SYSTEM: TASK: STEP NO. ECG Section. i.1V.C Table 3.0 1. TQ-b _.*-I 06-0303 NAME: JOB PERFORMANCE MEASURE DATE: OPERATOR TRAINING PROGRAM Administrative DutieslReporting Requirements (*Denotes a Critical Step) ELEMENT 4. If an EAL has been entered, then equal level EALs or lower level EALs and RALs are not required to be reported as long as the applicable information is communicated to the NRC using Attachment 5, NRC Data Sheet. If a RAL has already been reported and other conditions subsequently appear that meet the requirements for another ML, whether or not it is a consequence of the original RAL conditions, then a separate RAL report shall be made. However, multiple RALs may be reported in a single notification provided the time requirements for all the RALs beinn reported are met. In the table review the Emergency Action Levels of all columns and identify which need further review. (#Denotes a Sequential Step) STANDARD Examiner Note: Filling out the NRC Data Sheet is beyond the scope of this JPM. Operator reviews the EALs of all columns, and determines that all columns need further review. COMMENTS (Required for UNSAT evaluation) Page 6 of 17 ECGOOG 9,lO SYSTEM: TASK: STEP NO. Table 3.0 2. Table 3.0 3. Table 3.0 4. GENERAL ATT. 4 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Administrative DutiesIReporting Requirements Utilize The ECG To Determine The Emerc ELEMENT For each of the three barriers, determine the EAL with the highest point value, and circle the EAL # and point value. No more than one EAL should be selected for each barrier. Add the point values circled for the three barriers and enter the total below: Classify based on the point value sum as follows: r , I 1 TQ. -1 06-0303 NAME: DATE: icy Classification AndIOr Reportability Of An Event And/or Plant Condition (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines that the following EALs have been exceeded and represent the highest value met or exceeded for the respective column: 3.1.1.b; 3.2.2.b or 3.2.1.b; 3.3.2.b or 3.3.2.d. Operator circles the EAL numbers and point values for the EALs listed above. Operator adds the values (should be circled), and enters the value IO in the appropriate space. Operator determines that this classification is higher than the classification on EAL 9.5.2 and classifies the event as a General Emergency based on Table 3.0 EVAL SIU COMMENTS (Required for UNSAJ evaluation) 2 Page 7 of 17 TQ, .-I 06-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: ECGOOG SYSTEM: TASK: STEP NO. ECG Section i.1V.C CUE ECG Section i.1V.C Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emerc ~~ ELEMENT 5. The STA is responsible to perform an independent verification of the EAL classification. The STA verification does not alleviate the requirement of the SM to make a timely classification. Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO. - IF the Operator requests the STAllA to independently verify the EAL Classification, THEN INFORM the Operator the STAllA is not available. ~ 6. IDENTIFY and IMPLEMENT the referenced Attach men t under Action Required. ncv Classification And/or Reportability Of An Event And/or Plant Condition (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD COMMENTS (Required for UNSAT eva I u at i o n) IF time permits, THEN Operator requests STA/IA verification of classification. Examiner Note: Due to time spent assessing andlor nature of JPM administration, Operator may not request a verification. NIA Operator identifies and implements ECG Attachment

4. Page 8 of 17 EGG006 SYSTEM: TASK: EGG Att. 4 EGG Att. 4 CUE TQ -106-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition ELEMENT I. EMERGENCY COORDINATOR A. DECLARE A GENERAL EMERGENCY AT HOPE CREEK (EC) LOG SHEET EAL #(s) 1 3 DECLARED AT hrs on time date

6. NOTIFICATIONS

1. CALL the communicators to the Control Room AFTER 2 minutes, REPORT as the communicators and give your name as CMI and CM2. (*Denotes a Critical Step) (#Denotes a Sequential Step)

STANDARD Operator declares a General Emergency, places the EAL # s 3.1 .I .b, 3.2.2.b or 3.2.l.b, 3.3.2.b or 3.3.2.d, time and date in the appropriate spots in attachment 4, and initials the step as the EC. Examiners Note: ENTER the declaration time that the operator entered on Att. 4. The difference between the START TIME and the "DECLARED AT' TIME is the first critical time-(l5 rnin.) Initialing the step is not critical. Operator calls the communicator using the plant page. N/A - * # -

• COMMENTS (Required for UNSAT evaluation)

Page 9 of 17 ECGOOG * (*Denotes a Critical Step) (#Denotes a Sequential Step) EVAL STANDARD # s/u Operator activates the ERO. Examiner Note: This step cannot be simulated in the classroom. SYSTEM: TASK: COMMENTS (Required for UNSAT evaluation) STEP NO. ECG Att. 4 CUE ECG Att. 4 CUE TQ .-106-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emergencv Classification And/or Reportabilitv Of An Event And/or Plant Condition ELEMENT 2. ACTIVATE "ERO Emergency Callout" per posted instructions titled: "Emergency Callout Activation" (EP96-003) INFORM the operator the Emergency Callout System has been activated.

3. MAKE A PAR as follows: a. REFER to Predetermined PAR Flowchart on Pg. 3 and DETERMINE the appropriate PAR. b. a Radiologically Based PAR is IMMEDIATELY available, THEN COMPARE the two PARS and choose the most appropriate for inclusion on the ICMF. - IF asked, THEN INFORM the operator a Radiologically Based PAR is not available.

NIA Operator Refers to APPENDIX 1, determines that a GE Based 10 Points PAR is appropriate MILES, [EVACUATE ALL SECTORS 0-5 EVACUATE DOWNWIND +I SECTOR SHELTER ALL REMAINING 5-1 0 MILES(ENE-E-ESE), SECTORS, 5-10 MILES]. I

• NIA Page 10 of 17 ECGOOG OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ .-I 06-0303 NAME: DATE: SYSTEM: Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event AndlOr Plant Condition TASK: STEP NO. ECG Att. 4 CUE ELEMENT 4. COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment).

5. PROVIDE the ICMF to the Primary Communicator (CMI ) and DIRECT the Communicator to implement ECG Attachment

6. LOG the time the ICMF is provided to CMI. LOG TIME: ROLE-PLAY as CMI and REPEAT BACK the direction as given. (*Denotes a Critical Step) (#Denotes a Sequential Step)

STANDARD Operator Completes the ICMF. Examiners Note: See the attached ICMF for an example of what the form should look like when filled out properly. Note that the exact words do not have to be in the "DESCRIPTION OF EVENT, but the description must convey the sense of the Initiating Condition for EALs 3.1.1 .b, 3.2.2.bi3.2.1 .b, 3.3.2. bi3.3.2.d. The operator may place the Examiner's name as the Communicator or tell the Examiner to place hisiher name as the Communicator. Operator provides the ICMF to CMI and directs implementation of Att.6. Examiners Note: The difference between the "DECLARED AT" TIME and this LOG TIME is the second critical time (13 min.) EVAL SIU COMMENTS (Required for UNSAT evaluation) Page 11 of 17 TQ .-106-0303 ECGOOG SYSTEM: TASK: STEP NO. I ECG Att. 4 CUE CUE i OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition ELEMENT 6. DIRECT the Secondary Operator directs CM2 to implement Att.8 for a GENERAL EMERGENCY. ROLE-PLAY as CM2 and REPEAT BACK the direction as given. the JPM has been terminated for other reasons, THEN RECORD the STOP time. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". Page 12 of 17 TQ-AA-106-0: 03 JOBPERFORMANCEMEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ___ DATE: JPM Number: ECGOOG TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event AndlOr Plant Condition TASK NUMBER: 2000500302/2000020505 __ QUESTION: RESPONSE: RESULT: SAT UNSAT QUESTION: __ RESPONSE: RESULT: SAT 1 UNSAT Page 13 of 17 JOB PERFORMANCE MEASURE 1 NOTE: Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 1.20E+04 pCi/sec Noble Gas or 1.70E+01 pCi/sec 1-13 1. ECG ATT 4 Pg. 5 of 5 INITIAL CONTACT MESSAGE FORM I. THIS IS Inserts CMl's name , COMMUNICATOR r~ THE a0 CONTROL ROOM CNAME) 0 TSC c] EOF AT THE HOPE CREEK NUCLEAR GENE:RATING STATION. ____________________---------------------------------------------------..----------------------------------------------------- IIa. @ THIS IS NOTIFICATION OF A GENERAL EMERGENCY WHICH WAS DECLARED AT Todays Time ON Todays Date EAL #(s) 3.1 .I .b ?- 3.2.2.b or 3.2.1.b , 3.3.2.b or 3.3.2.d (TIME - 24 HOUR CLOCK) (DATE) DESCRIPTION OF EVENT; h Loss of Fuel Clad, Reactor Coolant Boundary, &\e t inment Barriers \ I\\\\ HCGS Rev. 07 Page 14 of 17 TQ-AA-106-031 3 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. With the plant operating at 100% power, Hope Creek experiences an earthquake which indicates a magnitude of > 0.lg. 2. Control Room Annunciator C6-C4 is in. 3. ON Panel 10C673:

a. The SMA-3 Event Indicator is White b. The Strong Motion Accelerograph Tape Machines have advanced but are not currently running

c. The AMBER alarm light on the Seismic Switch Power Supply Drawer is lit 4. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer.

5. A LOCA results. The Reactor is successfully scrammed, with RPV level dropping rapidly to

-250"; then stabilizing between -225" and -205", being maintained using all available ECCS. 6. Drywell Pressure peaked at 44 psig, then dropped to <2 psig over the next 90 seconds. 7. Drywell Pressure is 1.95 psig and continuing to slowly drop.

8. The current 33 ft. elevation wind direction is from 275" at 7 mph. 9. Plant Effluent activity is 1 .I 7E+01 pCi/sec Noble Gas and 1 .I 7E-02 pCi/sec 1-1 31. INITIATING CUE: Based on this information, CLASSIFY this event AND MAKE the initial notifications.

This is a Time Critical Task, and has two Time Critical elements. Time zero for this event is now. Page 15 of 17 JOB PERFORMANCE MEASURE STATION : Hope Creek SYSTEM: Conduct of Operations TASK: TASK NUMBER: 2990630301 JPM NUMBER: 305H-JPM.ZZO12 REV#: 02 ***NRC ADMlN JPM RO AI*** SAP BET: NOH05JPU12E Perform A Shift Turnover HS On-Coming/Off-Gcdg ALTERNATE PATH: APPLICABILITY: co EO I/ RO STA 1-1 SRO Ix/ DEVELOPED BY: J. Berglund DATE: 1 1/2/08 Instructor Operations Resresentative APPROVED BY: DATE: /$/d5 TQ-AA-106-0303 -- STATION: Hope Creek JPM NUMBER: ZZOl2 REV: 02 SYSTEM: Conduct of Operations TASK NUMBER: 2990630301 TASK: Perform A Shift Turnover As On-Coming/Off-Going NCO ALTERNATE PATH: m] KIA NUMBER:

2.1.3 APPLICABILITY

RO SRO IMPORTANCE FACTOR: 3.7 3.9 EOI ROIX] STAl-1 SROm EVALUATION SETTINGIMETHOD: Simulator/Perform

REFERENCES:

OP-AA-112-101 Rev 2 OP-HC-112-101-1001 Rev 3 TOOLS, EQUIPMENT AND PROCEDURES: 3lank OP-HC-112-101-1001 Attachment 6 with Control Room Key Audit initialed for Days. Red pen, ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes IPM PERFORMED BY: GRADE: USAT UUNSA ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF JPM UNSATISFACTORY: - EVALUATOR'S SIGNATURE: DATE: Page 2 of 19 TQ-AA-106-0302 NAME: DATE: SYSTEM: Conduct of Operations TASK: Perform A Shift Turnover As On-Coming10ff-Going NCO TASK NUMBER: 2990630301 INITIAL CONDITIONS:

1. The plant is at 100% power. 2. The 'D' SSW pump is C/T for scheduled maintenance.

3. The 1 OF1 04 and OOFl04 Instrument Air Dryers are in service and the 1AF104 Instrument Air Dryer is in Standby. 4. Salem Units 1 and 2 are in service, Salem Unit 3 is available but NOT in service. 5. Preparations for shift relief are in progress.

INITIATING CUE: You are the Off-Going Day Shift Reactor Operator of "A' Shift. Complete the Equipment Status Checklist, Attachment 6 of OP-HC-112-101-1001, with the exception of the Control Room Key Audit. The Control Room Key Audit has been performed by another operator. Page 3 of I9 JPM: 22012 Rev: 02 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Perform A Shift Turnover As On-Coming10ff-Going NCO NO. STEP I ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) I STANDARD CUE PROVIDE the operator the initiating cue AND a blank copy of OP-HC-112-101-1001 Attachment 6 WITH the Control Room Key Audit completed (initialed). Operator repeats back initiating cue. - * # - TQ-AA-1 06-0303 NAME: DATE: TQ-AA-1 06-0303 NAME: DATE: COMMENTS (Required for UNSAT I evaluation) Page 4 of 19 JPM: 22012 Rev: 02 4.2.3 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Utilize appropriate attachment from this document to document the turnover. SYSTEM: Conduct of Operations STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD 0 pe ra to r co m p I ete s OP-HC-112-101-1001 Attachment 6 with the exception of the Control Room Key Audit. Examiner Note: Refer to attached example of completed turnover sheet and the following critical aspects of co m p I e t io n . Operator circles andlor crosses out operating equipment with 2 80% accuracy. Examiner Note: There are 180 total opportunities, 5 36 errors is passing. Operator places an "X over the 'D' SSW pump. Operator recognizes HPCl Flow Controller is in MAN and should be in AUTO and reports to CRS. Examiner Note: Flow controller is failed and CANNOT be restored to AUTO. Page 5 of 19 TQ-AA-106-0303 NAME: DATE: EVAL SIU COMMENTS (Required for UNSAT evaluation) JPM: 22012 Rev: 02 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 NAME: DATE: SYSTEM: Conduct of Operations TASK: Perform A Shift Turnover As On-Coming10ff-Going NCO ELEMENT THEN INFORM Operator the mis-positioning will be investigated this document to document the THEN Operator signs in Off-Going OR the JPM has been terminated for THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is Page 6 of 19 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: I TQ-AA-106-0333 _- DATE: JPM Number: 22012 TASK: Perform A Shift Turnover As On-Coming10ff-Going NCO TASK NUMBER: 2990630301 QUESTION: RESPONSE: RESULT: QUESTION: SAT UNSAT RESPONSE: -- RESULT: SAT UNSAT Page 7 of 19 ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page I of 7) [ C D-42 I v] Shift On-Duty A Days X Nights Date TODAI - Ta be completed by the off-going RO/PO for turnover to the oncoming ROIPO. Circle designator for equipment in service, X over designator for INOP/Bypassed equipment. Coolinq Water ssws: SACS: TACS Loop: RACS: Condenser/Condensate cw: SJAE: Offgas Train: PCP: SCP: HWCI: Reactor Feedwater A RFP: B RFP: C RFP: Startup Valves Reactor RWCU Pump: RWCU Filter-Demin: Reactor Recirc Pumps: Recirc Control: CRD Pumps: CRD Stabilizer: CRD Flow Control: Nuclear Instrumentation APRM: IRM: SRM: FLOW UNITS: RBM: RWM: ma Common 8 STOP ANUAL ANUAL ANUAL AUTCXX@ANUA~OSE~ E A B @ma @a!3 ACEGBDFH AC BD Operable Inoperable Page 8 of 19 ULJ ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 2 of 7) Turbine: TIG Oil Pump OP111 Motor Suction Pump OP108 Emergency Bearing Oil Pump OP112 Remarks ABCD EHC Pumps: Lift Pumps: Seals: B EF G AUX HJ Main Generator: Voltage Regulator: Auto Track: Stabilizer: Stator Cooling: SALEM Units On-line: MANUAL OFF OFF B 3 C C C B B B B B a B 8 A 8 A A A A a a Diesel Generator: Chi I I ed War: Turbine Bldg (KI 1 I): TB CW Pumps: TSC Chiller (K403): Control Area Chiller (K400): Ventilation: CREF: FRVS Recirc: FRVS Vent: Fans In Lockout: C E F H2/02 Analyzers: B B No Fuel Pool Cooling Pumps: (Consistent With Plant Condition) BOP System Bmass: Feedwater Heaters: Air Systems: Instrument Air Dryers: Service Air: Emergency Instrument Air: PCIG: 1 AF104 w 00K107 1 OK1 00 , Aux Boiler: "A Boiler Removed Page 9 of 19 OP-HC-112-I01 -I 001 Revision 3 Eaam!mG;r @Dpy Page 16 of 22 ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 3 of 7) CORE SPRAY SYSTEM $ 41 Page 10 of 19 OP-HC-I 12-101-1001 Revision 3 EEmdrn(3r G@py Page 17 of22 ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 4 of 7) HPCl SYSTEM I/ Page 11 of 19 ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 5 of 7) HAHOM~ rnic --- RClC SYSTEM F059 00 tl-F045 + GO 1 Valve 1 C FO1914405 I YIX ' 4 ro31 x Ix Actuator I FIC-RfiOO f013 L x Ix ID ~-_______ - -- REMARKS, .~.- .. . . .- ....... Page 12 of 19 Eaam[ @@r @q-tiJy-llz;:;;la Page I9 of 22 ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 6 of 7) RHR "B" 1 REMARKS: ____ Page 13 of 19 ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 7 of 7) RHR "A" x FPOM 8'RCCIRC F065C w REMARKS - Control Key Audit Performed By: __ Checklist Performed By: . Initials L!kPez- __ Off-going Operator Page 14 of 19 I.C. r I -1 initial - _J ENSURE equipment alignment matches attached checklist. PLACE the HPCl Flow Controller in MANUAL. Initial ENSURE the 'B' SSW pump is in service. ET # Description EVENT ACTION: 1 COMMAND: PURPOSE: C/T 'D' SSW pump as follows: I. INSERT Malfunction CW05D 2 2. START the 'D' SSW pump and allow to trip EVENT ACTION: COMMAND: PURPOSE: _- 3. ACKNOWLEDGE alarms 4. PLACE HV-2198D in LOCKOUT 5. PLACE HV-2197D in LOCKOUT PREP FOR TRAINING (i.e., RMI 1 set points, procedures, bezel covers) r I 1 I lnifial I Description _i PLACE red bezel on DP502 SSW pump. PLACE red bezel cover on HV-2198D discharge valve. PLACE red bezel cover on HV-2197D backwash valve. I _- EVENT TRIGGERS: I I Page 15 of 19 Ramp Trigger lnit Val Final \ al of DP501 SSW pump -+ Delay --- NONE --- --- -i Initial I I I I Trigger lnit Val Final \ al i Description Delay Ramp 5A23 AI LO DP502 OVLD/PWR FAIL light --- --- NONE --- OFF REMOTElFI ELD FUNCTION

SUMMARY

I 7 5A23 A2 LO DP502 INOP light 5A23 F LO DP502 SSW pump STOP Delay Ramp Trigger lnit Val CW24 HV-2197D Backwash Valve breaker --- --- NONE --- OFF --- --- NONE --- --- NONE --- --- I/O OVERRIDE

SUMMARY

I I , I 1 --- --- 5A41 E DI HV-2198D OPEN PB 5A41 F LO HV-2198D CLOSE light --- NONE --- --_ NONE --- OFF I I 9A2 B DI HPCl FIC-R600 AUTO Pushbutton I NONE 1 --- I ON I I 5A41 A LO HV-2198D OVLD/PWR FAIL 1 --- 1 --- 1 --- I OFF --- --- Page 16 of 19 TQ-AA-106-03 33 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

I. The plant is at 100% power. 2. The 'D' SSW pump is CIT for scheduled maintenance.

3. The 10F104 and OOFl04 Instrument Air Dryers are in service and the 1 AF104 lnstrumen Air Dryer is in Standby.

4. Salem Units I and 2 are in service, Salem Unit 3 is available but NOT in service. 5. Preparations for shift relief are in progress.

INITIATING CUE: You are the Off-Going Day Shift Reactor Operator of "A Shift. Complete the Equipment Status Checklist, Attachment 6 of OP-HC-112-101-1001, with the exception of the Control Room Key Audit. The Control Room Key Audit has been performed by another operator. STATION : SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: JOB PERFORMANCE MEASURE Hope Creek Conduct of Operations Generate An SAP System Valve/Breaker Alignment 2990090301 305H-JPM.ZZ030 REV#: 01 ***NRC ADMIN JPM RO A2*** NOH05JPZZ30E ALTERNATE PATH: APPLICABILITY: DEVELOPED BY: J. Berglund DATE: 1 1/8/08 I tructor DATE: 17/12 /e Operations Representative DATE: /z/dg REVIEWED BY: > APPROVED BY: Training Department TQ-AA-I 06-0303 S TAT10 N : Hope Creek JPM NUMBER: 22030 REV: 01 SYSTEM: Conduct of Operations TASK NUMBER: 2990090301 TASK: Generate An SAP System Valve/Breaker Alignment ALTERNATE PATH: I) KIA NUMBER: 2.1.29 IMPORTANCE FACTOR: 4.1

4.2 APPLICABILITY

RO SRO EVALUATION SETTINGIMETHOD: ClassroomlPerform

REFERENCES:

HCOP-DL.ZZ-0015 Rev 21 SH.WM-DG.ZZ-0015 Rev 6 TOOLS, EQUIPMENT AND PROCEDURES: SAP Computer and accessible SAP printer. ESTIMATED COMPLETION TIME: 15 Minutes N/A Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: JPM PERFORMED BY: GRADE: USAT UUNSAl ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 2 of 12 I TQ-AA-106-0303 NAME: - DATE: SYSTEM: Conduct of Operations TASK: Generate An SAP System ValvdBreaker Alignment TASK NUMBER: 2990090301 INITIAL CONDITIONS:

1. The plant is at 100°/o power steady state. 2. The current time is 3:30 am. INITIATING CUE: You are the Tuesday Night Shift Plant Operator.

PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged) for the Shift Routine. Page 3 of 12 JPM: 22030 Rev: 01 SYSTEM: Conduct of Operations TASK. Generate An SAP System ValvelBreaker Alignment TQ-/+fi-lO6-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: STEP NO. CUE CUE CUE 3.6.1. A ELEMENT SETUP Logon to the SAP Training Client Using: User: TRAIN20 Password: WELCOME9 Ensure the "WCM: Area Menu" is open (Fast Path ZWCMM) PROVIDE the operator the initiating cue AND the following: 0 A prepared copy of HC.OP-DL.ZZ-0015 with an Attachment 1 completed for Dayshift (Attached) 0 SH.WM-DG.ZZ-0015 ~___ ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: HC.OP-DL.ZZ-0015 PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged) AND FILE in the Control Room - NIA Operator repeats back initiating cue. - Page 4 of 12 TQ-~fi-lO6-0303 NAME: DATE: JPM: 22030 Rev: 01 SYSTEM: Conduct of Operations OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK- Generate An SAP System Valve/Breaker Alignment - (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # COMMENTS (Required for UNSAT evaluation) ELEMENT EVAL s/u Operator obtains procedure Examiner Note: The procedure is only a desktop guide and the operator may be proficient at the task and NOT reference the desktop guide. SH. WM-DG.ZZ-0015. E necessary, THEN Operator obtains the correct procedure. 5.3.6 c SH.WM-DG.ZZ-0015 N/A PrintinglReviewing Off-Normal From the WCM: Area Menu A. Click "WCM Reports" menu, then click "Off Normal Report (Version 1 )'I. Operator Clicks: "WCM Reports" menu. Operator then clicks "Off Normal Report (Version 1 )'I. 6. Complete "Object Info" section for report to be obtained.

• Operator enters the following Object Info: Planning Plant:

NNUC Plant Section: HC * ~ Mode: 01 Type: F *

• Technical Object:
• OR H* OR HI*
• C. Select desired "Display Filter" either "Off Normal" or "Tagged" or both. * - Operator selects "Display Filter" for "Off Normal" ONLY.

Page 5 of 12 JPM: 22030 OPERATOR TRAINING PROGRAM Rev: 01 SYSTEM: TASK: JOB PERFORMANCE MEASURE Conduct of Operations Generate An SAP System ValvelBreaker Alianment TQ-,w.-I06-0303 NAME: DATE: STEP NO. CUE ELEMENT D. If printing report: 0 Under "Program" select "Execute and Print". - IF in the LDC, THEN PROVIDE the Operator with an accessible SAP printer number. PRINTER PROVIDED: Select output device then cl i c k To n t i nu e". E. If reviewing report, click "Execute". F. Click "Back". ~ (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Based on Initiating Cue, Operator determines printing the report required. Examiner Note: It is NOT critical in the following steps HOW the Operator prints the Report. For instance, may select preview mode and then use printer icon. It is also NOT critical to actually retrieve the printout. (Not all SAP printers work in the Training Client) Critical portion is to execute steps to generate a printout. I * # - Under "Program", Operator selects "Execute and Print". COMMENTS (Required for UNSAT evaluation) Operator Selects an output device then clicks "Continue". Based on Initiating Cue, Operator determines this step is not required. Operator clicks "Back" to exit.

• Page 6 of 12 JPM: 22030 Rev: 01 SYSTEM: Conduct of Operations TASK: Generate An SAP System 1 ,..re/Breaker STEP NO. CUE 3.6.1. A CUE ELEMENT HC.OP-DL.ZZ-0015 RETRIEVE printed Off-Normal AND INFORM the operator the Report has been filed. PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged)

AND FILE in the Control Room WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-t *~-106-0303 NAME: DATE: lignment N/A WHEN printed Off-Normal is filed, THEN Operator enters time (simulated to be 03:30) AND initials Attachment

1. - Page 7 of 12 I TQ-AA-I 06-03C 3 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION

-- NAME: DATE: __ JPM Number: 22030 TASK: Generate An SAP System ValvelBreaker Alignment TASK NUMBER: 2990090301 -- QUESTION: __ RESPONSE: RESULT: SAT UNSAT 1 QUESTION: __ RESPONSE: RESULT: SAT UNSAT Page 8 of 12 TQ-AA-106-030 3 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: I. The plant is at 100% power steady state. INITIATING CUE: You are the Tuesday Night Shift Plant Operator. PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged) for the Shift Routine. Page 9 of 12 JOB PERFORMANCE MEASURE 1 X Shift NOTE TQ-AA-I 06-0303 99 99 3.6.1 .B PERFORM lamp test on all possible Sections of 10C800. 3.6.3 MARK all Control Room strip charts (Date & Initial), NOTIFIED I&C if Memory Space digital reading 2 20%. VERIFIED status of Paperless Recorders. ATTACHMENT I (Page I of I) TUESDAY SHIFT ROUTINE LOG REQUIRED Date: TODAY ROUTINES REQUIRED I ROUTINES I 0600-1800 1800 - 0600 1800 - 0600 1800 - 0600 (Off-Normal and NOT Tagged) ANJ FILE in the Control Room 3.6.2 Control Room cleanup

3.6.4 Attachment

2 of SH.OP-DL.ZZ-O027(Z), has been completed and Temporary Log package for the next day has been prepared.

3.6.5 PLACE

the out-of-service TSC Chilled Water Pump l A(B>P-414 in-service (pump only) for a I-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-O002(Q), A(B)K403 1 E Panel Room Chilld Water System ODeration.. 1700360441 1800 - 0600 3.6.6 PLACE the out-of-service Control Area Chilled Water Pump 1A(B>P-400 in-service (pump only) for a I-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-0001 (Q), Control Area Chilled Water System Operation. [70086974] TIME COMPLETED 1800 - 0600 INITIALS Performed By: Y g9L Y g-.... Supervisor Review: 2ii7 gzA8A Y 0600-1 800 1800-0600 PSEG Internal Use Onlv PSEG NUCLEAR L.L.C. Page 1 of 1 HOPE CREEK GENERATING STATION HC.OP-DL.ZZ-O015(Q) - Rev. 21 TUESDAY SHIFT ROUTINE LOG USE CATEGORY: 11 0 Biennial Review Performed: Yes - No J NA - 0 Packages and Affected Document Numbers incorporated into this revision: CP No. CP Rev. - AD No. - Rev No. None J 0 The following OTSCs were incorporated into this revision: None REVlS IO N SUM MARY This revision adds Step 3.6.6 and instruction to Attachment 1 for a Control Area Chilled Water Pump IA(B)-P-400 - Weekly Run. This Step places the out-of-service Control Area Chilled Water Pump in-service (pump only) for a l-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-0001 (Q), A(B)K400 Control Area Chilled Water System Operation. Applicable References added to Section 5.0. [CRCA 700869741 IMPLEMENTATION REQUIREMENTS None Effective date 811 512008 I H C .O P -D L .ZZ-OO 1 5 (a) TUESDAY SHIFT ROUTINE LOG 1.0 PURPOSE The purpose of this log is to record completion and results or schedule the performance of activities required at a frequency of one week or less. 2 .O RES PONS1 81 LlTY 2.1 Shift ManagerlControl Room Supervisor - the SMlCRS is responsible to review this Log once per shift and note the review where indicated. CRS has primary responsibility for completion and documentation of log reviews. 2.2 Nuclear Control Operator (NCO) - NCO completes or directs completion of all sections applicable to the shift on duty. 2.3 Operations Staff - transmits the completed log to TDR for completion.

3.0 PROCEDURE

3.1 Attachment

1 is completed every Tuesday. Attachment 1 schedules activities or additional data sheets that the NCO must complete or direct completion. 3.2 The NCO performs and initials activities conducted at the NCO watch station. 3.3 The NCO directs performance and initials completion of activities performed outside the NCO area of responsibility. 3.4 The SM/CRS is notified when an activity is not completed or an entry is out-of-specification.

3.5 Completed

logs are filed at the end of the day in the Control Room file with the remainder of completed logs for that day. Hope Creek Page 1 of 6 Rev. 21 t HC.OP-DL.ZZ-O015(Q)

3.6 Procedures

for each routine are provided below listed by the corresponding routine number. 3.6.1. Shiftlv Routines 3.6.2 Hope Creek A. Once daily, GENERATE the WCM Off-Normal Report USING the REPORTWOFF-NORMAL REPORT function (Off-Normal and NOT Tagged) - AND FILE in the Control Room. PERFORM a lamp check on all possible Sections of 10C800. REPLACE all observed burned out bulbs. B. C. Once daily, FILE all closed WCDs in the marked file in the WCC. D. At the end of each month TRANSFER all closed tagouts from the current month file to the two year file in the Operations supply room. REMOVE and DISCARD all tagouts greater than two years old. Control Room Cleanup CLEAN the Control Room CRT screens. 0 DUST the Control Console. 0 TAKE out trash. 0 CLEAN UP unnecessary papers from the Control Room. Page 2 of 6 Rev. 21 NOTE Only recorders that are Operating or Operable need be checked in this section. 3.6.3. Control Room Strip Charts & Paperless Recorders A. Control Room Strip Charts The NCO shall use chart stamp or black ink pen on each Control Room chart, dating & initialing where required. RESET to correct time if required. B. Paperless Recorders On the recorder Status Bar PERFORM the following: VERIFY Memory Space Icon is illuminated "green." VERIFY PC Card Icon is illuminated "green." VERIFY Memory Space Indicator indicating "orange" if recording or "gray" if not recording. VERIFY Memory Space digital reading 20% - IF reading 2 20%, NOTIFY I&C. [REFERENCE VTD 325037, page 281 3.6.4. Temporary Loqs The Nuclear Control Operator (NCO) should ENSURE the completion of Attachment 2 of SH.OP-DL.ZZ-O027(Z); Temporary Reading Log & Log Supplements AND PREPARE the Temporary Log package for the next day. - IF it has been over a week since the out of service Chilled Water Pump has been started, it may trip due to air intrusion. [80077941] 3.6.5. TSC Chilled Water Pump 1A(B)-P-414 -Weekly Run [70036044] PLACE the out-of-service TSC Chilled Water Pump IA(B)-P-414 in-service (pump only) for a l-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-OOOZ(Q), A(B)K403 1 E Panel Room Chilled Water System Operation. Hope Creek Page 3 of 6 Rev. 21 NOTE - IF it has been over a week since the out of service Chilled Water Pump has been started, it mav trip due to air intrusion. [70086974]

3.6.6. Control

Area Chilled Water Pump IA(B)-P-400 - Weekly Run [ 700 869 741 I PLACE the out-of-service Control Area Chilled Water Pump 1A(B)-P-400 in-service (pump only) for a l-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-0001 (Q), A(B)K400 Control Area Chilled Water System Operation. Hope Creek Page 4 of 6 Rev. 21

4.0 ATTACHMENTS

4.1 Attachment

1, Tuesday Shift Routine Log

5.0 REFERENCES

P&ID; M-15-0, Sht. 1 Order 70036044 - 1A-P-414 Trips Due To Air Intrusion Order 70086974 - Control Area Chilled Water Pump Trip On Low Flow. 80077941 70086974 SH.OP-DL.ZZ-O027(Z); Temporary Reading Log & Log Supplements HC.OP-SO.GJ-0001 (Q), A(B)K400 Control Area Chilled Water System Operation. HC.OP-SO.GJ-O002(Q), A(B)K403 1 E Panel Room Chilled Water System Operation. I I I I Hope Creek Page 5 of 6 Rev. 21 HC.OP-DL.ZZ-O015(Q) REQUIRED ROUTINES 0600 - 1800 ATTACHMENT I 1800 - 0600 (Page 1 of I) TUESDAY SHIFT ROUTINE LOG 1 X Shift NOTE 3.6.1.B 3.6.3 PERFORM lamp test on all possible Sections of 10C800. MARK all Control Room strip charts (Date & Initial), VERIFIED status of PaDerless Recorders. REQUIRED 1800 - 0600 1800 - 0600 1800 - 0600 1800 - 0600 1800 - 0600 NOTIFIED I&C if Memory Space digital reading 2 20%. NOTE - Only recorders that are Operating or Operable need be checked. ROUTINES TIME COMPLETED INITIALS 3.6.1 .A PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged) AND FILE in the Control Room 3.6.2 Control Room cleanup 3.6.4 Attachment 2 of SH.OP-DL.ZZ-O027(Z), has been completed and Temporary Log package for the next day has been prepared.

3.6.5 PLACE

the out-of-service TSC Chilled Water Pump IA(B)-P-414 in-service (pump only) for a I-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-O002(Q), A(B)K403 1 E Panel Room Chilled Water System Operation.. [70036044] PLACE the out-of-service Control Area Chilled Water Pump IA(B)-P-400 in-service (pump only) for a I-hour run to purge any air from piping high points IAW HC.OP-SO.GJ-0001 (a), Control Area Chilled Water System Operation. [70086974]

3.6.6 REMARKS

Performed by: Supervisor Review: 0600 - 1800 1800 - 0600 Hope Creek Page 6 of 6 Rev. 21 I SH.WM-DG.ZZ-0025

5.3.2. Change

Current Position From the WCM: Area Menu A. Click "Work Clearance Management", go to "Current Positions", then double click "Create/Change". Enter functional location preceded by an "F" in the previous box, click "Enter" . B. NOTE Remark is required when changing position to off-normal or back to normal. C. Enter position in "Current Position" field and reason for change in "Comments" field. click "Save".

5.3.3. Display

Functional Location Current Position From the WCM: Area Menu A. Click "Work Clearance Management", go to "Current Positions", then double click "Display" B. Enter functional location preceded by an "F" in the previous box, click "Enter". C. After reviewing Blocking Point (item), click "Back".

5.3.4. Viewing

Information Page To view Information Page (IP) open another SAP Session A. Enter "ZCD2" in Fast Path screen. B. Enter Functional Location and Planning Plant data and click "Enter". C. Select "FLOCDet" icon. D. The Information Page (IP) is located under Blocking Points Comments section. SalemlHope Creek Page 48 of 61 Rev. 6 SH.WM-DG.ZZ-0015

5.3.5. Updating

Location details and IP page of Components To update Information Page (IP) open another SAP Session A. Enter "ZCDZ" in Fast Path screen. 8. Enter Functional Location and Planning Plant data and click "Enter". C. Select "FLOCDet" icon. D. Click "ChangeMode E. Type in desired special Location detail information in Location box. F. Type in desired special instructions into Blocking Point Comments boxes. G. Click "Save". H. Click "Back" I. Click "Back" again to exit the component data module and save all entries. 5.3.6. PrintingIReviewing Off-Normal From the WCM: Area Menu A. Click "WCM Reports" menu, then click "Off Normal Report (Version 1)" B. Complete "Object Info" section for report to be obtained. C. Select desired "Display Filter" either "Off Normal" or "Tagged" or both. D. If printing report: 0 Under "Program" select "Execute and Print". 0 Select output device then click "Continue". E. If reviewing report, click "Execute". F. Click "Back". SalemlHope Creek Page 49 of 61 Rev. 6 JOB PERFORMANCE MEASURE STAT1 ON : SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: ALTERNATE PATH: APPLICABILITY: Eo I DEVELOPED BY: Hope Creek Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator 299001 01 01 305H-JPM.ZZ035 REV#: 00 ***NRC ADMIN JPM RO A3*** NOH05JPZZ35E J. Berglund DATE: 1 1 /I 5/08 - Instructor Operations Representative APPROVED B DATE: /d%g Training Department rI TQ-AA-I 06-0303 STATION: Hope Creek JPM NUMBER: 22035 SYSTEM: Equipment Control TASK NUMBER: 2990010101 TASK: REV: 00 Perform the Watchstanc,,ig Duties of the Nuclear Control Room Operator - ALTERNATEPATH: 1 I KIA NUMBER: 2.2.23 IMPORTANCE FACTOR: 3.2 4.2 APPLICABILITY: - RO SRO EVALUATION SETTINGIMETHOD: Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0026 Rev 113 HC.IC-FTSK-0006 Rev 15 TOOLS, EQUIPMENT AND PROCEDURES: Blank HC.OP-DL.ZZ-0026 Attachment 5, Prepared HC.IC-FT.SK-0006 Ops Info Sheet ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes JPM PERFORMED BY: GRADE: USAT nUNSA- ACTUAL COMPLETION TIME: M in Utes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY: 1 DATE: - EVALUATOR'S SIGNATURE: Page 2 of 14 TQ-AA-I 06-0303 NAME: - DATE: SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator TASK NUMBER: 2990010101 INITIAL CON DlTlONS : 1. The plant is at 100% power. 2. I&C is performing scheduled functional test HC.IC-FTSK-0006, RWCU NSSSS Division 4 Steam Leak Detection.

3. I&C requires opening breaker 52-242081 for the RWCU BG-HV-FOO4 valve to perform the test.

4. Applicable OHAs have been flagged. INITIATING CUE:

You are the Reactor Operator. LOG the I&C functional test onto HC.OP-DL.ZZ-0026 (provided). The applicable Technical Specification is 3.6.3 (Active) and the Required Action time is four hours. Page 3 of 14 JPM: 22035 Rev: 00 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: TASK: l Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator ELEMENT PROVIDE the operator the initiating cue AND: 0 The attached Operations 0 A blank copy of information Sheet HC.OP-DL.ZZ-0026 Attachment 5 ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: OP-HC-108-115-1001 RESPONSIBILITIES Nuclear Control Operator (NCO): Complete HC.OP-DL.ZZ-O026(Q), Surveillance Log, Attachment 5 as required by Step 5.3.3. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. TQ-t 106-0303 NAME: DATE:

• COMMENTS # SIU evaluation)
• VAL (Required for UNSAT Page 4 of 14 JPM: 22035 Rev: 00 EVAL SIU OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE COMMENTS (Required for UNSAT evaluation)

SYSTEM: TASK: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator ELEMENT - COMPLETE Attachment 5 of HC.OP-DL.ZZ-O026(Q), to track allowable outage times before actions (either by Operations or other departments) are required. - COMPLETE Attachment 5 of HC . 0 P-DL .ZZ-0026( Q), to track allowable outage times before actions (either by Operations or other departments) are required. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator enters current date on Attachment. Operator enters Order 60001 11 1 in ORDER block of Attachment. Operator enters "HC.IC-FT.SK-0006" in SURVEILLANCE NUMBER(S) block of Attachment. ~ Operator enters surveillance title OR description of surveillance in DESCRIPTION/PROCEDURE TITLE block of Attachment. Operator enters "3.6.3" in TIS NUMBER(s) block of Attachment. Operator enters "ACTIVE" in LCO STATUS ACTIVE/TRACKING block of Attachment. - * # - *

• TQ-, 106-0303 NAME: DATE: Page 5 of 14 JPM: 22035 Rev: 00 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator I 1.1 I COMMENTS (*Denotes a Critical Step)

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD I ## I SIU I evaluation) STEP NO. TQ-r. :106-0303 NAME: DATE: 5.3.3 CUE 5.3.3 - COMPLETE Attachment 5 of HC.OP-DL.ZZ-O026(Q), to track block of Attachment. normally wait until the breaker was actually opened to enter a time, THEN DIRECT the Operator to HC.OP-DL.ZZ-O026(Q), to track Operator enters current date and REQUIRED TI MEIDATE. departments) are required. Page 6 of 14 JPM: 22035 Rev: 00 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Perform the Watchstandina Duties of the Nuclear Control Room ODerator STEP NO. CUE ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) I STANDARD WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: N/A TQ-, 106-0303 NAME: DATE:

• COMMENTS # SIU evaluation) EVAL (Required for UNSAT Page 7 of 14 TQ-AA-I 06-03113 JOB PERFORMANCE MEASURE OPERATOR TRAlNlNG PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: 22035 TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator TASK NUMBER: 2990010101

-- QUESTION: RESPONSE: -- RESULT: QUESTION: UNSAT SAT RESPONSE: RESULT: Page 8 of 14 UNSAT TQ-A' "6-0303 LOG ON TIME/DATE RO INlT JOB PERFORhi, E MEASURE ACTION REQUIRED TIMEDATE [NOTE 21 ATTACHMENT 5 Surveillance Log TIS Surveillance and Planned Evolution AOT Tracking Log HC.IC-FT.SK-0006 Date: TODAY RWCU Div 4 Leak Detection Pane I of 1 ORDER 60001 I I I NOTES: SURVEILLANCE NUMBERS(S) [NOTE I] DESCRIPTION/ PROCEDURE TITLE TIS NUMBER( s) 3.6.3 LCO STATUS ACTIVE/ TRACKING ACTIVE TODAYINOW TODAYINOW 1 +4hrs I LOG OFF TlMElDATE RO INlT I. ALL ENTRIES WHICH ARE NOT LOGGED OFF BY THE END OF THE DAY (i.e.: 0700), SHALL BE CARRIED OVER TO THE FOLLOWING DAY'S LOG.

2. THE ACTION REQUIRED TIME/DATE SHOULD BE DETERMINED BY THE SM/CRS IAW HC.OP-AP.ZZ-0108 (a), OPERABILITY ASSESSMENT AND EQUIPMENT CONTROL PROGRAM, AND FILLED IN. IF THE ACTION REQUIRED TIME IS REACHED, THE SM/CRS WILL IMPLEMENT THE REQUIRED ACTIONS IAW SH.OP-AP.ZZ-O108(Q).

Page 9 of 14 I TQ-AA-106-03[13 JOBPERFORMANCEMEASURE INITIAL CONDITIONS:

1. The plant is at 100% power. 2. I&C is performing scheduled functional test HC.IC-FT.SK-0006, RWCU NSSSS Division t Steam Leak Detection.

3. I&C requires opening breaker 52-242081 for the RWCU BG-HV-F004 valve to perform the test.

4. Applicable OHAs have been flagged.

INITIATING CUE: You are the Reactor Operator. LOG the I&C functional test onto HC.OP-DL.ZZ-0026 Attachment 5 (provided). The applicable Technical Specification is 3.6.3 (Active) and the Required Action time is four hours. Page 10 of 14 EXHIBIT 1 OPERATIONS INFORMATION SHEET (I of 2) Procedure Title: RWCU - DIVISION 4 (AMB T, dT) STEAM LEAK DETECTION TEMPERATURE MONITOR NSSSS - DIVISION 4 1 SKXR-11499 Order #: 60001 11 1 Performer Name : Mack Strong TODAY NOW Date Time -__ NOTE Technical Specification 3.3.2 is applicable for the following: RWCU Differential Temperature Trip Channels A2-I, A2-2, A2-3, A2-4, A2-5, AND A2-1.3 RWCU Ambient Trip Channels A3-1, A3-2, A3-3, A3-4, A3-5, AND A3-6 NSSSS Logic D trip channels AI-3, AI-4, A4-1, AND A4-2 Technical Specification 3.6.3 AND ACTION 3.3.7.5 is applicable when valve breaker for HI BG -BG-HV-F004 is opened. ~ ~ ~~~~~ ~~~ ~ Annunciators + + + D1 El, RRCS TROUBLE + + + Status Lights Cl C2, RWCU SYSTEM TROUBLE C8 A4, NSSSS MSlV LOGIC D INITIATED + C8 C4, NSSSS ISLN SIG-STM TNL TEMP HI D1 B3, CONTAINMENT ISOLATION VALVE O/PF D3 A3, MN STM/RWCU AREA LEAK TEMP HI D3 D3, LEAK DET SYSTEM TROUBLE MCP Location: D/B RRCS + MCP Location: NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM 6 CHANNEL B, RRCS LOGIC A TROUBLE TRIP LOGIC D, MSlV TRIP LOGIC TRIPPED i EXHIBIT 1 OPERATIONS INFORMATION SHEET (2 of 2) Computer Points + + + + D2088, MAIN STEAM LINE D LEAK DETECT D2393, STEAM LEAK DET CH D CARD AT4 D4675, CONTAINMENT ISOLATION MOV OPF D5868, RWCU/MAIN ST LEAK DET TMP CH Z + D3144, RWCU OUTBD ISLN HV-F004 OPF Functions + NSSSS Logic D Trip on High Steam Tunnel Temperature (Steam Leak Detectiort) + RWCU outboard isolation, valve 1-BG-V004 (HV-F004), on High Ventilation D/T (Steam Leak Detection); (function defeated by opening valve breaker) + RWCU outboard isolation, valve 1-BG-V004 (HV-F004), on Area High Temperatt ire (Steam Leak Detection); (function defeated by opening valve breaker) JOB PERFORMANCE MEASURE STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: Hope Creek Radiation Control Perform Alternate RCS Leakage Determination (Floor Drains) 3660020201 305H-JPM .ZZ036 ***NRC ADMlN JPM RO A4*** NOHOSJPZZ36E REV#: 00 ALTERNATEPATH: I I J. Berglund DATE: 1 1 /I 6/08 DEVELOPED BY: I s ctor REVIEWED BY: 4)J DATE: (2/p (f Operations Representative APPROVED BY: Y (= Training Department APPROVED BY: Y (= LLJ [[A, Training Department DATE: /& //s /t D TQ-AA-I 06-0303 -1 S TA TI 0 N : Hope Creek JPM NUMBER: 22036 REV: 00 SYSTEM: Radiation Control TASK NUMBER: 3660020201 TASK: Perform Alternate RCS Leakage Determination (Floor Drains) ALTERNATE PATH: KIA NUMBER: 2.3.1 1 IMPORTANCE FACTOR: 3.8 4.3 APPLICABILITY: RO SRO EVALUATION S ETTI N G/M ETHOD : Perfo rm/Cla ssroo m

REFERENCES:

HC.OP-ST.SK-0001 Rev 7 HC.OP-DL.ZZ-0026 Rev 1 13 Tech Spec 3.4.3.2.e and 4.4.3.2.1.b rooLs, EQUIPMENT AND PROCEDURES: Prepared copies of HC.OP-ST.SK-0001 and H6.OP-DL.ZZ-0026 Att 3z (Attached) ESTIMATED COMPLETION TIME: 12 Min Utes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: USAT UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY: _- EVALU AT0 R'S SIGNATURE: DATE: Page 2 of 34 TQ-AA-106-0303 NAME: DATE: SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains) TASK NUMBER: 3660020201 INITIAL CONDITIONS: 1. The plant at 100% power. 2. The Drywell Floor Drain RMS has failed and repairs are expected to take 48 hours. 3. Drywell Floor Drain inleakage is being determined manually IAW HC.OP-ST.SK-0001 with a multimeter and stopwatch once per hour. 4. I&C has just completed taking the 0700 Final Milliamp reading. INITIATING CUE: You are the Extra NCO. COMPLETE the hourly calculation of Drywell Floor Drain inleakage IAW HC.OP-ST.SK-0001 (Provided) AND RECORD the result on HC.OP-DL.ZZ-0026 Attachment 3z (Provided). The current time is 0700. Page 3 of 34 JPM: 22036 Rev: 00 (*Denotes a Critical Step)

• ELEMENT (#Denotes a Sequential Step)

STANDARD ## PROVIDE the operator the initiating cue AND: TQ. .-106-0303 NAME: OPERATOR TRAINING PROGRAM COMMENTS SIU evaluation) EVAL (Required for UNSAT JOB PERFORMANCE MEASURE DATE: SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains) STEP NO. CUE CUE A prepared copy of Operator repeats back initiating cue. HC.OP-ST.SK-0001 (Attached) A prepared DL.ZZ-0026 Att. 3z to record final reading on (Attached) II Operator repeats back the Initiating Cue; START TIME: Page 4 of 34 a JPM: 22036 Rev: 00 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains) ~ STEP NO. 5.1.10 5.1 .I 1 5.1 .I2 CALCULATE Differential Milliamp "Diff mA" AND Differential Time "Diff Time" AND RECORD on Attachment 2, Section 2.3. CALCULATE "Inleakage (GPM)", using formula at bottom of Attachment 2, Section 2.3 AND RECORD the rate, date, AND INITIALS on the Attachment. RECORD required leak rate readings from Attachments IAW HC.OP-DL.ZZ-O026(Q); Surveillance Log. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator calculates Differential Milliamps of 0.257 - 0.26 and records on Attachment

2. 12.393 - 12.1 36 = 0.257 Examiner Note:

Rounding to 0.26 mA is acceptable. ~ Operator calculates Differential Time of 60 minutes and records on Attachment

2. ~ Operator calculates inleakage of 0.0998 gpm and records 0.0998 - 0.101 on Attachment

2. 0.257 x 23.31 = 0.0998 gpm 60 minutes Examiner Note:

Rounding to 0.1 gpm is acceptable. Operator records leak rate on H C . OP-DL .ZZ-0026 Attachment 3z. T6 *106-0303 NAME: DATE: EVAL SIU COMMENTS 1 (Required for UNSAT evaluation) Page 5 of 34 JPM: 22036 Rev: 00 SYSTEM: TASK: STEP NO. CAUT 5.1 .I 3 5.1.13 CUE OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE Radiation Control Perform Alternate RCS Leakage Determination (Floor Drains) ELEMENT Allow for enough time when obtaining the next reading so that the calculated leak rate is obtained at least once every four hours IAW TIS 3.4.3.1 ACTION a.1. CONTINUE calculating inleakage rate using steps

5.1.7 through

5.1 .I 1 UNTIL the capability to obtain leak rate information from the RMS, for Drywell Floor Drain System has returned, THEN PROCEED to step 5.1.29 to exit this procedure. WHEN operator informs you the task is complete, the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME: TQ- -106-0303 NAME: DATE: NIA Operator determines capability to obtain leak rate information from RMS is not yet available and does NOT exit the procedure. Page 6 of 34 H C . 0 P- D L 7-0 02 6( Q) ATTACHMtdT 32 Page I of 1 Action Statement Surveillance SURVEILLANCE Generic Action Statement Surveillance Sheet Applicability: When entering a T/S Action Statement that requires increased surveillance. OPER ACCEPTABLE LIMITS COND MIN NORM MAX DAY EVE MID COMMENTS NIA NIA NIA NIA NIA NIA Action Statement Number LDC-I Date TODAY SURVEILLANCE OPER ACCEPTABLE LIMITS 1200 1300 1400 Drywell Floor Drain Flow STSK-0001 1,2,3 1500 1600 1700 Page 7 of 34 SURVEILLANCE 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 0000 0100 0200 0300 0400 0500 COMMENTS 0600 TQ-AA-I 06-03 33 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION -~ NAME: DATE: -~ JPM Number: 22036 TASK: Perform Alternate RCS Leakage Determination (Floor Drains) TASK NUMBER: 3660020201 -_ QUESTION: RESPONSE: RESULT: SAT TI UNSAT -1 __ QUESTION: -_ RESPONSE: RESULT: SAT UNSAT 1 I Page 8 of 34 TQ-AA-I 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant at 100% power.

2. The Drywell Floor Drain RMS has failed and repairs are expected to take 48 hours. 3. Drywell Floor Drain inleakage is being determined manually IAW HC.OP-ST.SK-0001 with a multimeter and stopwatch once per hour.

4. I&C has just completed taking the 0700 Final Milliamp reading.

INITIATING CUE: You are the Extra NCO. COMPLETE the hourlv calculation of Drvwell Floor Drain inleakage IAW HC.OP-STSK-0001 (Provided) AND RECORD the result on HC.OP-DL.ZZ-0026 Attachment 3z (Provided). The current time is 0700. Page 1 of 2 HOPE CREEK GENER4TING STATION HC.OP-ST.SK-OOOl(Q) - Rev. 7 ALTERNATE RCS LEAKAGE DETERMINATION USE CATEGORY: I REVISION

SUMMARY

Rev. 7 1. Note 1 .O of Attachment 2 stating the requirements of Independent Verification was deleted. The use of N/A is self explanatory. This change is generic and can be considered editorial based on allowance in NC.NA-AP.ZZ-000 1 (Q), for "Revising a procedure to include changes previously reviewed and approved".

2. This procedure has been converted from Professional Write to Microsoft Word. 3. The following changes were made in this revision to bring the procedure in line with the rules governing procedure format, content, and writerheviewer guidelines, as contained in NC.NA- WG.ZZ-OOOl(Q), Procedure Writers Guide and can be considered Editorial in nature. Due to the extensive changes, revision bars were omitted. Added "RECORDS" section

6.0 Capitalization

and Bolding of action verbs Added Recurring Task number to references Changed procedure Font from "Anal" to "Times New Roman" Revised Cautions and Note boxes format fi-om margin to margin Moved "Commitment Document" numbers from left margins to end of applicable steps Added PlacekeepingBtep completion signoffs throughout procedure Replaced "SIGN" with "INITIAL" throughout procedure. Replaced "REQUEST" with "DIRECT" throughout procedure.

4. Incorporates revision request OP-97-0176 (PR 970401160) by revising procedure to modify and add steps for the collection of M&TE data and the recording of M&TE removal. See changes to steps 5.1.29.A, and 5.2.16.A and the addition of steps 5.1.4 and 5.2.4. (Continued) IMPLEMENTATION REQUIREMENTS Effective Date APPROVED: Operations Manager Date HOPE CREEK GENERATING STATION Page 2 of 2 HC.OP-ST.SK-0001 (Q) - Rev. 7 ALTERNATE RCS LEAKAGE DETERMINATION USE CATEGORY:

I REVISION

SUMMARY

CONTINUATION SHEET Rev. 7 5. Organizational title changes were made in this revision to bring the procedure in line with guidelines, as contained in NC.NA-AP.ZZ-O002(Q), Nuclear Business Unit Organization, Attachment 1 and are considered editorial based on an allowance in NC.NA-AP.ZZ-OOOl(Q), Attachment 7 for "changing personnel titles to reflect organizational changes (without changing authority or responsibilities)." Due to the extensive changes, revision bars were omitted. 6. Based on comments the following changes were made: Removed Caution 5.0 as being redundant to Precaution 3.1; Removed Precaution 3.1.2 as being redundant to Cautions 5.1.6.A and 5.2.5.A. SECTION 1 .o 2.0 3.0 4.0 5.0 H C . 0 P-S T. S K-00 0 1 ( Q) ALTERNATE RCS LEAKAGE DETERMINATION TABLE OF CONTENTS TITLE PAGE PURPOSE ..................................................................................... PREREQUISITES ..................................................................................... PRECAUTIONS & LIMITATIONS ......... .. .... .......... ... ........ ......... . . . . .... .......... .. . ...... EQUIPMENT REQUIRED . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . PROCEDURE .....................................................................................

5.1 Determining

Drywell Floor Drain Leak Rate ..........................................

5.2 Determining

Drywell Equipment Drain Leak Rate ........ .. ..... .... .. . ........ .. .. 6.0 RECORDS .....................................................................................

7.0 REFERENCES

..................................................................................... ATTACHMENTS Attachment 1 - OS/CRS/WCCS Data and Signature Sheet .............................................................. Attachment 2 - Inplant Data Sheet ..................................................................................... Attachment 3 - Floor Drain Sump Pumpdown Intervals .................................................................. Attachment 4 - Drywell Equipment Drain Sump Curve ................................................................... 2 2 3 4 4 4 11 15 15 16 19 24 25 Hope Creek Page 1 of 20 Rev. 7 H C . 0 P-ST. S K-00 0 1 (a) ALTERNATE RCS LEAKAGE DETERMINATION

1.0 PURPOSE

The purpose of this procedure is to determine Reactor Coolant System leak rate in the event the normal Drywell Floor and/or Equipment Drain Sump Monitoring System is inoperable ~ICJ to satisfy Tech. Spec. 3.4.3.1 .a 4.4.3.2.1 .b. 2.0 PREREQUISITES

2.1 Determining

Drywell Floor Drain Leak Kate 2.1.1 2.1.2 2.1.3 2.1.4 2.1.5 2.1.6 Permission to perform this test has been obtained from the OS/CRS/WCCS as indicated by the completion of Attachment 1, Section 1 .O. All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3.0, prior to performing any part of this procedure. = The RO/PO has been informed that the following test is to be performed . No other testing maintenance is in progress that will adversely affect the performance of this test. E The ability to read Drywell Floor Drain inleakage on RMS modules 1 SKLI-4930 (Panel 1 OC604) Q& 1 SKLI-4930A (Control & Diesel Generator Bldg. El. 124') is lost. @@L P=- I&C personnel are available to connect multimeter and/or chart recorder at Panel 1DC695. Hope Creek Page 2 of 20 Rev. 6 HC.OP-ST.SK-0001 (Q: 2.2 Determining Drjwell Equipment Drain Leak Rate 2.2.1 2.2.2 2.2.3 2.2.4 2.2.5 2.2.6 Permission to perform this test has been obtained from the OS/CRS/WCCS as indicated by the completion of Attachment I, Section 1 .O. N/A All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3 .O, prior to performing any part of this procedure. The RO/PO has been informed that the following test is to be performed. NIA No other testing the performance of this test. maintenance is in progress that will adversely affect N/A The ability to read Drywell Equipment Drain inleakage on RMS modules 1SKLJ-4930 (Panel 10C604) QII ISKLI-4930A (Control & Diesel Generator Bldg. - El. 124') is lost. NIA I&C personnel are available to connect multimeter and/or chart recorder at Panel 1DC695. N/A 3 .O PRECAUTIONS AND LIMITATIONS 3.1 3.2 Precautions - IF at any time during the performance of this test, a step cannot be completed THEN IMMEDIATELY NOTIFY the RWPO is observed to be unsatisfactory; AND the OS/CRS/WCCS. [CD-927E] - Limitations 3.2.1 All steps within each section within the body of this procedure are to be completed in sequence unless otherwise specified. - 3.2.2 ENSURE leak rate is in compliance with T/S 3.4.3.2, during Conditions 1,2, and 3. 3.2.3 Section 5.1 and 5.2 may be performed concurrently. - Hope Creek Page 3 of 20 Rev. 6 HC.OP-ST.SK-0001 (Q) 4.0 EOUIPMENT REQUIRED a Keithly Model 197 Multimeter equivalent a Gould Model 2200s Chart Recorder equivalent a Calibrated Stopwatch

5.0 EROCEDURE

~- NOTE 5.0 A. All operations are performed locally at Junction Box I DC695 unless otherwise noted. Junction Box 1DC695 is located in the Control & Diesel Generator Bldg. - El. 124' -Room 5448. B. 5.1 Determining Drywell Floor Drain Leakage 5.1.1 this is the first subsection of the procedure to be performed THEN LOG test start time in the Control Room log(s). !BE- 5.1.2 5. I .3 ENSURE that all prerequisites have been satisfied IAW Section 2.1. ENSURE Attachment 1, Section I, of the OS/CRS/WCCS Data and Signature Sheet has been completed Regular Surveillance - or Retest is indicated. R R 5.1.4 RECORD the M&TE identification and calibration due dates for test equipment to be utilized for this test on Attachment

2. Hope Creek Page 4 of 20 , Rev. 6 1 HC.OP-ST.SK-0001 (Q) NOTE 5.1.5 - If failure to read Drywell Floor Drain Sump level at 1 SKLI-4930 and 1 SKLI-4930A was by power failure to the RM-80 Motherboard or failure of 1 SKLT-4931, proceed to step 5.1 .I4 5.1.5 Floor Drain Sump levels should be monitored AND a leak rate calculated using the time intervals between readings specified on Attachment

3. = 5.1.6 DIRECT I&C to CONNECT a Keithley Model 197 Multimeter set to read milliamps DC equivalent as follows:

m CAUTION 5.1.6.A The Action Pack Isolator is removed prior to connecting the Multimeter, as an accidental short circuit while disconnecting orconnecting wiring may cause a failure of the Action Pack Isolator. A. REMOVE A-2 Action Pack Isolator. A17 B. LIFT lead from 1 SKLT-493 1 //Drywell Floor Drain Sump Level Transmitter// at terminal 4. TB4 AND INITIAL Attachment 2, Section 2.1. Az&zL C. CONNECT one input of multimeter to lifted lead AND INITIAL Attachment 2, Section 2.1. A17 D. CONNECT the other input of multimeter to terminal 4, TB4 AND INITIAL Attachment 2, Section 2. I. d&zz Continued Next Page Hope Creek Page 5 of 20 Rev. 6 HC.OP-ST.SK-0001 (Q: 5.1.6 (Continued) ___. NOTE 5.1.6.E If multimeter indication is offscale high low, tdOTlFY OS/CRS/WCCS that the Drywell l- Floor Drain Sump level may be out of normal range possible failure of I SKLT-4931. E. ENSURE multimeter indicates 4 - 20 milliamps. AE7 F. INSERT A-2 Action Pack Isolator. RE7 ~- NOTE 5.1.7 The following steps will be performed to obtain data in order to calculate leak rate. A calibrated stop watch should be used for accuracy in timing reading intervals.

5.1.7 PRESS

START Pb on //DRWELL FLOOR DRAIN SUMP BT267 pump// C(D)P267 (1 OC65OD). 5.1.8 WHEN the sump pump stops automatically on low sump level, SIMULTANEOUSLY START the stopwatch. RECORD the "Initial Milliamp" reading on the Multimeter AND "Initial Time" on Attachment 2, Section 2.3. A17 NOTE 5.1.9 The initial time interval between taking the "Initial Milliamp" reading and the "Final Milliamp" reading should be obtained from Attachment 3, and based on the last recorded reading for HC.OP-DL.ZZ-O026(Q), Drywell Floor Drain leakage. Subsequent time intervals should be obtained from Attachment 3 and based on what the last calculated lnleakage reading was. Using the time interval between readings, allows for a continuous fill of the sump readings without an automatic start of the sump pump on level. This would prevent obtaining a valid calculated reading using this method. 5.1.9 At the interval specified in Attachment 3, AND using the running stopwatch for accuracy, RECORD "Final Time", AND "Final Milliamps" on Attachment 2, Section 2.3. RE7 Hope Creek Page 6 of 20 Rev. 6 5.1.10 5.1.1 1 5.1.12 H C . 0 P -ST. S K-00 0 1 (Q) CALCULATE Differential Milliainp "Diff mA" AND Differential Time "Diff Time" AND RECORD on Attachment 2, Section 2.3. CALCULATE "Inleakage (GPM)", using fonnula at bottom of Attachment 2, Section 2.3 AND RECORD the rate, date, AND INITIALS on the Attachment. RECORD required leak rate readings from Attachments IAW HC.OP-DL.ZZ-O026(Q); Surveillance Log. t ! i CAUTIO4 5.1 -13 Allow for enough time when obtaining the next reading so that the calculated leak rate is obtained at least once every four hours IAW TIS 3.4.3.1 ACTION a.1. i i 5.1.13 CONTINUE calculating inleakage rate using steps

5.1.7 through

5.1.1 1 UNTIL the capability to obtain leak rate information from the RMS, for Drywell Floor Drain System has returned, THEN PROCEED to step 5.1.29 to exit this procedure. DIRECT I&C to CONNECT a Gould Model 2200s Chart Recorder (I& equivalent as follows: N/A A. 5.1.14 CONNECT positive input of recorder to terminal 7, TB3 AND INITIAL Attachment 2, Section

2.1. CONNECT

negative input of recorder to terminal 8, TB3 AND INITIAL Attachment 2, Section 2.1. SET recorder pin to center scale with a gain of 5 VDC per major division. N/A D. SET recorder chart speed at 5 dmin. NIA PRESS START Pb on //DRYWELL FLOOR DRAIN SUMP BT267 pump// C(D)P267 (10C650D). NIA N/A B. NIA C. 5.1.15 Hope Creek Page 7 of 20 Rev. 6 HC.OP-ST.SK-0001 (Q] NOTE 5.1 .I6 The recorder pin will indicate 0 VDC when the Floor Drain Sump Pump(s) is running and 5 VDC when the pump is not running. 5.1.16 5.1 .I 7 5.1.18 OBSERVE recorder pin indicates 0 VDC while pump is running. ALLOM. pump to stop automatically on low sump level. RECORD on the chart the time, date and initials at point where pump stopped (chart should indicate 5 VDC). RECORD "Pump Stop Time" on Attachment 2, Section 2.2. NIA NIA NIA NIA 5.1.19 d -- NOTE 5.1.20 The recorder pin will indicate 0 VDC when the Floor Drain Sump Pump(s) is running and 5 VDC when the pump is not running. I 5.1 20 5.1.21 5.1.22 5.1.23 At the interval specified by Attachment 3, and based on the last recorded reading for HC.OP-DL.ZZ- 0026(Q), Drywell Floor Drain leakage, CONTINUE to observe the recorder at each interval for indication of a sump pumpout. NIA - IF there has not been a pumpout AND the required TIS 4 hour reading is due THEN GO TO step 5.1.27. NIA IF there was a sump pumpout, THEN CALCULATE "Pump Start Time" and "Pump Stop Time" from the chart by measurement from the previous stop time (5 dmin.), AND RECORD on Attachment 2, Section 2.2. NIA RECORD Differential Time "Diff Time" from the previous Pump Stop Time (auto shutdown) to the last Pump Start Time on Attachment 2, Section 2.2. NIA Hope Creek Page 8 of 20 Rev. 6 5.1.24 5.1.25 5.1.26 5.1.27 Time from Last Inleakage (GPM) Time from Last Pumpout Pumpout HC.OP-ST.SK-0001 (a) Using Equation on Attachment 2, Section 3.2, CALCULATE AND RECORD "Inleakage (GPM)", "Date" AND "Initials" on Attachment. NIA Inleakage (GPM) CONTINUE to monitor and calculate leak rates using steps 5.1.21 through 5.1.24 so that the leak rate is obtained at least once every four hours IAW TIS 3.4.3.1 ACTION a. 1. NIA RECORD required leak rate readings from Attachments IAW HC.OP-DL.ZZ-O026(Q); Surveillance Log. NIA there was NOT a pumpout, THEN RECORD the "Inleakage (GPM)" as less than the value specified in Table 5.1.27. NIA 5 Hours 4 Hours 3 Hours 2 Hours 1 Hour c 0.30 0.37 < 0.49 < 0.78 < 1.48 18 Minutes 15 Minutes < 4.94 < 5.92 5.1.28 WHEN the capability to obtain leak rate information from the RMS for Drywell Floor Drain System has returned, THEN CONTINUE with the next step. NIA Hope Creek Page 9 of 20 Rev. 6 H C . OP -ST. S K-0 0 0 1 (Q) 5.1.29 this is the final subsection of this procedure to be performed THEN: A. DIRECT I&C to REMOVE recorder and multimeter ($used) AND RETURN lifted lead to terminal 4 at TB4 AND INITIAL Attachment 2, Section 2.1. (I&C OPS). B. LOG test end time in the Control Room log(s). C. SUBMIT this procedure to the OSICRSNJCCS for review AND completion of Attachment

1. Hope Creek Page 10 of 20 Rev. 6 RECORDS H C . 0 P -ST. S K-0 00 1 (Q: 6.1 RETAIN the following IAW NC.NA-AP.ZZ-O003(Q);

Document Management Program: e Procedure cover page e Attachment 1 - OS/CRS/WCCS Data and Signature Sheet Attachment 2 - Inplant Data Sheet

7.0 REFERENCES

7.1 P&ID: M-25-1, Sht. 1 M-61-1, Sht. 1 M-61-1, Sht. 2 7.2 J-R 1000-0 7.3 5-3 73Q-87-4 7.4 DCP: 4HM-0323 4HC-0074, Pkg. 5 7.5 Commitment Document CD-927E (NRC INFO 87-25) Hope Creek Page 11 of 20 Rev. 6 HC.OP-ST.SK-0001 (Q) ATTACHMENT 1 OSlCRSNVCCS DATA AND SIGNATURE SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page I of 3 1 .o PRETEST INFORMATION

1.1 Reason

for the Test 1.1.1 Regular Surveillance INITIALS 1.1.2 Retest/Other PV INITIALS 1.1.3 - If not performing the complete test, list subsection(s)/valves to be performed, as well as marking N/,4 on the applicable subsection(s)/valves on the Attachment(s) that will not be performed, or, that do not require an independent verification IAW NC.NA-AP.ZZ-O005(Q); Station Operating Practices.

5.1 Floor

Drain Inleakage Determination with Multimeter SUBSECTION( S) - 1.2 Plant Conditions - 1.2.1 Operational Condition 1 1.2.2 Reactor Power Level 100% - 1.2.3 GMWe 1260 - 1.3 Permission to Perform the Test 1.3.1 Permission granted to perform this test. - Today/0400

• e OS/CRS/WCCS DATE-TIME 1.3.2 Work Order No. Hope Creek Page 12 of 20 Rev. 6 HC.OP-ST.SK-0001 (Q) ATTACHMENT I OSlCRSNVCCS DATA AND SIGNATURE SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page 2 of 3 2.0 POST TEST INFORMATION 2.1 The data acquired during the performance of this test has been reviewed for completeness and compliance with Technical Specification 3.4.3.2, Reactor Coolant System Operational Leakage and the test is considered:

2.1.1 SATISFACTORY

2.1.2 2.1.3 2.1.4 OSICRSIWCCS DATE-TIME UNSATISFACTORY AND necessary the T.S. ACTION statement has been implemented. I OSICRSIWCCS DATE-TIME Order No. Remarks Hope Creek Page 13 of 20 Rev. 6 H C .O P-ST. S K-0 0 0 1 (a) ATTACHMENT 1 OSICRSNVCCS DATA AND SIGNATURE SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page 3 of 3 3 .O PROCEDURE PERFORMER(S) AND \'ERIFIER(S) 3.1 I have read and understand the steps of this procedure that I am required to perform. (All Departments) PRINT NAME Joe Johnson Jim Berglund Archie Faulkner Kevin Faulk INITIALS PY DATElTlME To d a y/O 4 0 0 Todav/0500 Today10500 Today10500 Hope Creek Page 14 of 20 Rev. 6 HC.OP-ST.SK-0001 Q) STEP TEST EQUIPMENT INST. TAGlMTE NO. Stopwatch LDC-I Multimeter LDC-2 5.1.4 5.2.4 ATTACHMENT 2 INPLANT DATA SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page I of 5 CAL DUE DATE NCiTES -~ 4/30/09 4/30/09 1 .O TEST INFORMATION STEP NOMENCLATURE REQ POSITION PERF VERiF 5.1.6.B Lifted Lead from Term. 4, TB4 Lifted A# ;z;e7 5.1.6.C Multimeter connected to Lead Connected A# ;z;e7 5.1.6.D Multimeter connected to Term. 4, TB 4 Connected AS? xR7 5.1.14.A Positive Input connected to Term. 7, TB3 Connected NIA N /A. 5.1.14.B Negative Input connected to Term. 8, TB3 Connected NIA NIL 5.1 29.A Recorder and Multimeter (if used) Removed NIA N IC1 NIC 5.1.29.A Lifted Lead from Term. 4, TB4 Terminated NIA 5.2.5.B Lifted Lead from Term. 1, TB4 Lifted NIA NIP 5.2.5.C Multimeter connected to Lead Connected NIA NIJ! 5.2.5.D Multimeter connected to Term. 1, TBLT Connected NIA NIP NIF 5.2.6.A Positive Input connected to Term. 1, TB3 Connected NIA NIF. 5.2.6.B Negative Input connected to Term. 2, TB3 Connected NIA 5.2.1 6.A Recorder and Multimeter (if used) Removed NIA NIP 5.2.1 6.A Lifted Lead from Term. 1, TB4 Terminated NIA NIP -- -- _- 2.1 Alternate RCS Leakage - Determination Instrumentation Setup and Removal Hope Creek Page 15 of 20 Rev. 6 HC.OP-ST.SK-000' (a) ATTACHMENT 2 INPLANT DATA SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page 2 of 5 2.2 Determining; - Drywell Floor Drain Leak Rate Using: Chart Recorder Pump Stop Time NIA Pump Start Time NIA Diff. Time (Minutes) NIA - In leakage (GPM) NIA Date N/A Pump Start at Hiqh Level Alarm 97.7 Gallons = lnleakage (GPM) Diff. Minutes Initials Hope Creek Page I6 of 20 Rev. 6 HC.OP-ST.SK-0001t Q) Initial Time ATTACHMENT 2 INPLANT DATA SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page 3 of 5 Initial M il liam ps 2.3 Determining Drywell Floor Drain Leak Rate Using Multimeter 5.1.8 06:OO ~ 12.136 Hope Creek 5.1.9 Final M i lli am ps 12.393 Final Time 07:OO 5.1.10 D iff mA Diff Time (Min) 5.1 .I 1 [Diff. MA) x (23.31) = lnleakage (GPM) Diff. Time (Minutes) Page 17 of 20 - Init/ Date -- Rev. 6 Time N/A I HC.OP-ST.SK-000liQ) ATTACHMENT 2 INPLANT DATA SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page 4 of 5 2.4 Determining Drvwell Equipment Drain Leak Rate Using. Chart Recorder Pump Stop Time NIA Pump Start Time N/A Diff. Time (Minutes) NIA lnleakage (GPM) N/A Pump Start at Hinh Level Alarm 178.4 Gallons- = lnleakage (GPM) Diff. Minutes Date NIA -- - In i t i a i s -- - NIA Hope Creek Page 18 of 20 Rev. 6 H C . 0 P -S T. S K-0 0 0 I Q) ATTACHMENT 2 ALTERNATE RCS LEAKAGE DETERMINATION INPLANT DATA SHEET Page5of5 . 2.5 Determining Drwell Equipment Drain Leak Rate Using Multimeter Time NIA Mi I I iam ps NIA Hope Creek Volume (Gal Ions) NIA Diff Volume (Gallons) NIA Diff Time (Mi n Utes) NIA NIA Page 19 of 20 Date NIA 3iff. Volume (Gallons) = Inleakage (GPM) )iff. Time (Minutes) Rev. 6 I HC.OP-ST.SK-OOOl('2) ATTACHMENT 3 ISKLT-4931 OUTPUT (Ma) FLOOR DRAIN SUMP PUMPDOWN INTERVALS Page 1 of 1 Time Intervals between obtaining Sump Level Readings based on lnleakage Flow Ratc - Time Interval Inleakage Flow Rate (GPM) 1 Hour 30 Minutes 15 Minutes Hope Creek - -= 1.0 > 1 .O but 5 2.0 > 2.0 Page 20 of 20 Rev. 6 ATTACHMENT 32 Page 1 of 1 Action Statement Surveillance S U RVEl LLANCE Generic Action Statement Surveillance Sheet Applicability: When entering a TIS Action Statement that requires increased surveillance. OPER ACCEPTABLE LIMITS COND MIN I NORM I MAX DAY EVE MID Action Statement Number LDC-1 NIA NIA NIA ACCEPTABLE LIMITS MIN NORM MAX ! NIA I N/A 1 NIA 0700 I 0800 I SURVEILLANCE I Drywell Floor Drain Flow STSK-0001 I OPER COND 1,2,3 1800 1900 2000 2100 2200 2300 0000 0100 0200 0300 0400 0500 0600 COMMENTS Date TODAY S U RVE I LLAN CE OPER ACCEPTABLE LIMITS COND MIN NORM MAX 0700 0800 0900 1000 1100 1200 1300 1400 1500 1600 COMMENTS I 1700 1800 1900 2000 2100 2200 2300 0000 0100 0200 0300 0400 0500 0600 Hope Creek COMMENTS Page 95 of 99 Rev1 13}}