ML090360438
| ML090360438 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/04/2009 |
| From: | Public Service Enterprise Group |
| To: | D'Antonio J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML082600269 | List: |
| References | |
| 50-354/09-301, TAC U01693 50-354/09-301 | |
| Download: ML090360438 (405) | |
Text
SCENARIO TITLE: NRC SCENARIO 1 SCENARIO NUMBER: ESG-NRC-S1 EFFECTIVE DATE: Effective when approved.
EXPECTED DURATION: 80 minutes REVISION NUMBER: 02 PROGRAM: 1- L.O. REQUAL r l INITIAL LICENSE OTHER REVISION
SUMMARY
- 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 T I INITIAL LICENSE 1- OTHER ~
REVISION
SUMMARY
- 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. Raise Reactor Power with Control Rods B. lnerting the Containment C. Stuck Control Rod D. Main Steam Line RMS failure E. Loss of 1AD482 inverter F. Steam leak in the steam tunnel G. Small break LOCA/
H. RHR pump room flooding/ (Failure to isolate)
I. 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-482inverter 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-S1 Page 2 of 27 Re:!: 02
I c.
w -
Initial INITIALIZE the simulator to IC-94; 4% power, MOC. Pull step 259 INSERT control rods through step 234.
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 lnifial 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:
rr
~~~
Reactor Dower
~~
I WIR Reactor Water Level
~~~~ ~
I 0 W/R Reactor Pressure 0 Fuel Zone RPV Level
~~ ~~ ~
COMPLETE the Simulator Ready for Training/Examination Checklist.
PRE-BRIEF the crew for the power change and Containment lnerting ESG-NRC-S1 Page 3 of 27 Reti: 02
EVt IT TRIGGERS:
ET # Description EVENT ACTION LCPNEPOI >= 300 1 COMMAND DMF CD033843 PURPOSE Deletes malfunction when drive pressure is 300 psig -
EVENT ACTION ZLMS20A 5 COMMAND PURPOSE CLOSED light for A MSlV __
EVENT ACTION ZLRHPMR(4)
COMMAND: IMF RH07D PURPOSE: Inserts flooding malfunction when RHR D pump is running __
EVENT ACTION: ZDRHFOC(20)
COMMAND:
PURPOSE: HV-F004D Switch to CLOSE -
EVENT ACTION: ZDCWZPDM >= 1.O COMMAND:
PURPOSE: D SACS Pump MAN PB -
EVENT ACTION: ZDCWZPDA >= 1.O COMMAND: DMF CW15D PURPOSE: D SACS Pump AUTO PB -
EVENT ACTION: ZDCWZPDS >= 1.O COMMAND:
PURPOSE: D SACS Pump START PB -
EVENT ACTION:
COMMAND:
PURPOSE:
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 1E lnstr bus 1AD482 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
RR3182 Recirc loop B large break RHO'ID RHR leak via pump D suction PC06 Suppression Pool Break r i
- 1 REMOTE/FIELD FUNCTION
SUMMARY
I I I 7 lnitial Description Delay Ramp RH21D HV-F004 RHR pump D suction valve --- --- ET-7 ---
I lnitial I
1/0OVERRIDE
SUMMARY
Description 5A31 C OVLO DP210 MAN-LOOP B Pumps-Pump 5A31 D OVLO DP210 AUTO-LOOP B PUMPS-Pump I
Delay I
q-f Tri er I
ESG-NRC-SI Page 5 of 27 REX02
V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected PlantlStudent Response Comments Raise Reactor Power with CRS directs the RO to raise Control Rods: Reactor power with Control Rods in accordance with RE guidance.
NOTE: LPRM downscale 0 RO withdraws Control Rods in HPI USED:
alarms can be expected. As accordance with HC.OP-S0.S F- STAR RE, inform crew alarms are 0001 and CRS directions. PEER CHECK expected for this rod pattern. =, Selected rod PB comes ON OP BARRIERS (bright white).
z CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod position (1OC650C).
The associated Full Core Display (white) numbered rod identification light comes ON (1OC650C).
NOTE: Operator may single 0 At the ROD SELECT MODULE, notch withdraw the rods, as simultaneously press and hold necessary, in which case the both the WITHDRAW PB CONTINUOUS WITHDRAW AND the CONTINUOUS PB is NOT used. 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.
z CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod movement.
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.
ESG-NRC-SI Page 6 of 27 Rev: 02
I Event I Instructor Activity Expected PlantEtudent Response Camments
= The SETTLE (white) light comes ON for =. 6 seconds, then goes out.
3 CONTROL ROD POSITION 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-ST.BF-0001.
0 Perform the following while giving HPI USED:
the selected Control Rod a STAR continuous wit hdraw signal: PEER CHECK Observe the following as OP BARRIERS 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.
Indicates the completion of the movement on the Pull Listing.
Stuck Control Rod 38-43: RO determines that Control Rod Preinserted. 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 HC.OP-AB.IC-0001:
Condition I.
ESG-NRC-SI Page 7 of 27 Rev: 02
V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE I
Event / Instructor Activity Expected PlantlStudent Response Comments RO performs actions in HPI USED:
accordance with CRS directions: STAR 0 Verifies no Rod Blocks are PEER CHECK CI present. OP BARRIERS Attempts to operate the drive NOTE: Crew may request RE in both directions to guidance. Respond that a determine the exact condition withdraw signal then an insert of the Control Rod.
signal may be attempted.
Verifies drive water flow fluctuates normally.
Verifies proper operation of the SETTL.E, INSERT, AND WITHDRAW lights.
ENSURE ET-I triggers when Performs the following:
drive water pressure dp >300 Raises the drive water psid. This deletes stuck rod pressure in approximately 50 malfunction. 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: HPI USED:
HV-4978 STAR
= HV-5035 PEER CHECK 0 a P-KH-V9973, Liquid N2 To FLAGGING Vaporizer (local) OP BARRIERS 0 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 N2 RAISE SETPOINT PB to attain the desired nitrogen flow rate as indicated on FR-4971-1, N2 FLOW (UPto 150,000 scfh).
0 intermittently OPEN one of the PSV-4946A (B,C,D,E,F,G,H),
Torus to Drywell Vacuum Breakers, using the TEST OPEN push-button approximately every 15 minutes.
Main Steam Line RMS "A" 0 Crew recognizes MSL RMS Fails Upscale: Channel failure by:
3 OHA C6-A3 "MN STM LINE TRIGGER ET-2 when Control RADIATION HI" Rods have been withdrawn, R M l l 9RX511 High alarm containment inerting is in Other channels reading progress, or at the Lead normally.
Zxaminer's discretion.
e CRIDS Page 37 MSL Radiation C readings.
ESG-NRC-SI Page 9 of 27 Red: 02
I AND EXPE RE I
Event I Instructor Activity Expected PlantlStudent Response Comments CRS reviews AB.RPV-0008:
a Condition A Condition B Condition C and finds them not applicable.
CRS rec0gniz.eTech Specs action 3.3.2 action b.1) c) applies.
CRS contacts Maintenance to troubleshoot and repair the MSL RMS channel.
Crew identifies and communicates the loss of TACS to the CRS.
RO/PO informs CRS that RPV power, level and pressure are stable.
NOTE: HC.0P-AB.ZZ-000 I e CRS orders TACS placed on the may be referenced also for the B SACS loop IAW HC.OP-transfer of TACS. AB. COOL-0002:
Condition B.
e PO performs HC.OP-AB-COOL-0002 as directed by the CRS WHEN operator starts D SACS PO ensures the standby SACS HPI USED:
Pump, THEN DELETE pump starts. STAR 0 Overrides 5A31C and 5A31 D. OP BARRIERS 0 e Ensures BOTH pairs of TACS supply and return valves on the Standby loop open to supply TACS. (HV-2522/2496) e Ensures TACS supply AND return valves on the loop that WAS supplying TACS are CLOSED. (HV-2522/2496)
ESG-NRC-SI Page 10 of 27 Red: 02
Event / Instructor Activity Expected PiantlStudent Response Comments Determines that the HV-2522E HV-2522F are closed THEN re-opens them as follows:
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 PBs until the valves indicate open.
WHEN dispatched to the 1A-D- Crew identifies the loss of the 482 as an operator, THEN 1AD482 inverter REPORT the inverter output =) OHA D3-E3 120VAC UPS breaker CBIO is open, the AC TROUBLE Reg Output breaker CB302 is =) CRIDS open and the Static Switch cabinet is de-energized.
WHEN dispatched to the IA-D- CRS implements HC.OP-AB.ZZ-482 as maintenance, THEN 0136, Attachment 5.
REPORT there appears to be a fault in the Static Switch cabinet and you will need the inverter tagged.
NOTE: If dispatched to 0 Crew recognizes loss of RWCU investigate H2 Seal Oil System, via OHA and trip of both RWCU respond that alarm was due to pumps due to a loss of HV-F001 low pressure. Using Remote indication.
Function acknowledge alarm.
NOTE: If dispatched to the 0 RO/PO refers CRS to HC.OP-lsophase System, alarm was AB.RPV-0007 in accordance with due to high temperature. Using HC .0P-AR.ZZ-0008.
Remote Function acknowledge alarm.
0 CRS directs actions to be taken in accordance with HC.OP-AB.RPV-0007, Condition 6.
[DIRECT Chemistry to sample and analyze reactor coolant.]
ESG-NRC-S 1 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 a 3.8.3.1 .a.l.e and action A or post start checks are SAT. 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.
=, Monitor the following to determine the source of leak:
Main Steam Flow indication Feedwater Flow indication RWCU System
= Ensures TB Chilled Water Supply Temp is c55F.
a HV-9532-1 and HV-9532-2 are open.
ESG-NRC-S 1 Page 12 of 27 Rev: 02
h Event / Instructor Activity Expected PlantlStudent Response Comments WHEN dispatched to perform
= Ensure proper positioning of Steam Tunnel Supply AND BOP-0005 actions, REPORT:
Return Backdraft dampers Action A.3: Steam Tunnel =1 Ensure both Steam Tunnel supply and return back draft cooling Fans in-service at dampers - both sets are open. Dane1 1EC281.
Action A.5: Place Both Steam Ensure GlJ-HD9395A AND Tunnel cooling fans in service GU-HD9395B are closed.
by placing REMOTE FUNCTION H V I I 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: monitor Steam Tunnel temperature.
Action A.3: Steam Tunnel supply and return back draft dampers - both sets are open.
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 This alarm may not be Support Center ARM.
.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 Comments 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.
The CRS may take 0 CRS directs a manual Scram conservative action and scram when Steam Tunnel temperature before 145 degrees. >I45 degrees IAW the Retainment Override.
RO takes actions to manually HPI USED:
scram the reactor IAW HC.OP- STAR 0 AB .ZZ-000 1.
PO takes action to control, HPI USED:
restore and maintain RPV level STAR 0 with Feedwater. HARDCARD 0 CRS implements HC.OP-EO.ZZ-0101 based on entry condition of 4 2 . 5 RPV Level and directs actions to stabilize the plant.
=j RO performs scram actions HPI USED:
IAW HC .0P-AB .ZZ-000 1 STAR 0 HARDCARD 0 CRS may transfer level and pressure control to RClC and SRVs in anticipation of MSlV closure.
RO/PO coordinate transfer of Reactor Pressure and RPV level control .
Crew places B RHR in HPI USED:
Suppression Pool cooling to STAR 0 support RCIC/SRV operation HARDCARD 0 IAW HC.OP-AB .ZZ-000 1 Attachment 3 VOTE: CRS directs closing MSlVs and drains to isolate steam leak.
The MSIVs may automatically close on an isolation signal.
ESG-NRC-SI Page 14 of 27 Rev 02
0 RO closes the MSlVs and drains. HPI USED:
STAR 0 The CRS directs the PO to HPI USED:
restore and maintain RPV level / STAR 0 pressure with HPCl and/or RClC and SRVs.
CRS implements HC.OP-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.
Crew recognizes LOCA condition:
=) 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 perat ures 0 PO maximizes Drywell cooling HPI USED:
and checks proper operation of STAR 0 TB Chillers.
ESG-NRC-SI Page 15 of 27 Rev, 02
r Event I Instructor Activity Expected Plant'Student Response Comments Crew recognizes HI-HI Drywell pressure of 1.68 psig CRS reenters; HC.OP-EO.ZZ-0101, 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.
NOTE: At the discretion of the CREW determines leak to be in Lead Examiner, raise the RHR pump D room via SPDS severity of PC06. and/or CRlDS alarms D2971 and D2939.
As RBEO, two minutes after e RO/PO notifies RBEO to being dispatched, REPORT a investigate cause of RHR pump large leak at D pump suction room flooded alarm.
with approximately two inches of water on floor. You have exited the room and closed the watertight door.
e CRS enters and directs actions of HC.OP-EO.ZZ-O103/4, Reactor Building and Rad Release to isolate the leak.
e CRS directs actions to isolate RHR Pump D suction by closing HV-F004D.
WHEN operator places F004D PO attempts to close HV-F004D, HPI USED:
keyswitch in CLOSE, THEN observes that the OVLD/PWR STAR 0 ENSURE ET-7 Triggers. FAIL illuminates, and informs the CRS.
ESG-NRC-SI Page 16 of 27 Rev 02
I Event / Instructor Activity Expected Plant/Student Response Comments NOTE: 0 When Suppression Pool Level Role-play as the building drops below 74.5 inches, CRS EO to support reenters HC.OP-EO.ZZ-0102, implementation of EOP 300 Primary Con1.ainment Control, level procedures. and directs actions to restore suppression pool level using Do NOT implement EO- RCIC, Core Spray, or Service 315, use Remote Functions Water.
CS02 or CS04.
Although, REPORT completion of lineup to the MCR.
NOTE: 0 CREW closely monitors Torus level decrease and determines Once Crew determines a that a major failure of the Torus major failure of the Torus has occurred.
has occurred and level cannot be maintained, they may stop makeup efforts.
- 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 HPI USED:
CRS direction. STAR 0 HARDCARD 0 PO recognizes failure of SRV F013E to open via closed indication on 1OC650C and informs CRS.
CRS directs PO to open other SRV(s) until 5 SRVs are open.
PO opens additional SRV per CRS instructions ESG-NRC-S1 Page 17 of 27 Re\ : 02
I Event I Instructor Activity Expected PlantlStudent Response Comments NOTE: This task is completed
- Crew recognizes via acoustic satisfactorily if Emergency and temperature indications Depressurization occurs before that F013E, ADS SRV, has 38.5 of SPL is reached. failed to open and opens an additional SRV 0 PO maintainsh-estores RPV level
>-I85 inches in accordance with CRS instructions.
a PO initiates Suppression Pool HPI USED:
cooling IAW CRS direction. STAR 0 ESG-NRC-S 1 Page 18 of 27 Revr 02
A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid 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. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. OP-AA-101-111-1003 Use of Procedures K. HU-AA-1081 Fundamentals Toolkit L. HU-AA-1211 Briefing M. OP-AA-101-1 11-1004 Operations Standards N. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel
- 0. OP-AA-106-101-1001 Event Response Guidelines P. OP-AA-108-114 Post Transient Review Q. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program R. OP-HC-108-106-1001 Equipment Operational Control S. OP-AA-101-112-1002 On-Line Risk Assessment T. HC.OP-AB.BOP-0002 Main Turbine U. HC.OP-AB.BOP-0005 Main Steam Tunnel Temperature
- v. HC.OP-AB.CONT-0001 Drywell Pressure W. HC.OP-AB.CONT-0004 Radioactive Gaseous Release X. HC.OP-AB.COOL-0002 Safety Auxiliaries Cooling System Y. HC.OP-AB.IC-0001 Control Rod Z. HC.OP-AB.RPV-0007 Reactor Coolant Conductivity AA HC.OP-AB.RPV-0008 Reactor Coolant Activity BB. HC.0P-AB.ZZ-000 1 Trans ient PIant Conditions 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-0001 Feedwater System Operation JJ. HC.OP-SO.SF-0001 Reactor Manual Control KK. HC.OP-ST.BF-0001 Control Rod Drive Exercise - Weekly ESG-NRC-S1 Page 19 of 27 Rei: 02
ESG-NRC-S1 I 0 2 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 SRVs RO 4.4 SRO 4.4 The Minimum Number of SRVs required for Emergency Depressurization (MNSRED) is five.
The MNSRED is utilized to assure the RPV will depressurize and remain depressurized when Emergency Depressurization is required. When the PSV-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. SRVs are designed to open with a minimum differential pressure of 50 psid between the reactor vessel and the suppression chamber. Below this d/p, they may not open.
If the Crew does not attempt to open the fifth SRV before this minimum d/p is lost, they cannot validate its operation. This would prevent them from detecting the failure and pursuing the usca of the Alternate Depressurization Systems in HC.OP-EO.ZZ-0202.
ESG-NRC-S1 Page 20 of 27 R e i 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 Y Internal Flooding LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:
Turbine Trip Loss of ssw Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSlV Closure inadvertent SRV Opening Y Manual Scram COMPONENTlTRAlNlSYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Y/N KEY EQUIPMENT Hard Torus Vent SLC HPCl CRD 1E 4.16KV Bus 1E 125VDC SACS Hx/Pump EDG KEY SYSTEMS 120VAC 4811482 Inverter 500KV AC Power A/B RHR S RVs RClC Condensate/Feedwater SSW Pump 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 Page 1 of 1 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG HOURS TOTAL PREV. AUTH. AUTHORIZING THIS HOURS CLOSING THIS PERMIT INITIAL THIS PERMIT PREVIOUS (NOTE 1) PERMIT YEAR (NOTE 1) 24 Tom MacEwan s%z?
K I II NOTE 1: The previous year i :ludes the period from 2400 on todays 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, I N E F N G OR PRESSURE CONTROL VALVE PERMIT SECTION
~ _ _ _A_ -
Date: Todav NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: 2 0 0 9 - 0 1 SECTION
_ ____ B HOURS VALVESlLlNES OPEN PREVIOUS YEAR (Note 1)
Calculate Total Hours Open (1) Max. allowed for 365 days (Admin Limit) 452 hrs During Previous Year (NOTE I)
DATE NUMBER OF HOURS (2) Total previous year (NOTE 1) I-) 6 06/0112008 6 Hours available this date (line 1 minus line 2) [=) 446 Hours authorized this date (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 open or Condition 1, 2. Time at which valvelline was closed or Total number of hours valve/lir-?
or 3 was entered with valve/line open Condition 4 or 5 was entered with valve/line opened this cycle opened (NOTE 3 )
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 @ < I 5°/~/hour.
0 Commence inerting the containment IAW HC.OP-SO.GS-0001 step 5.1.9.
Protected Equipment:
None Heinhtened Awareness:
None Tanaed Equipment:
None Reactivitv:
Rod pull step 234.
Continuous rod withdraw is allowed.
RE-Some LPRM downscale and SRM Short Period alarms may occur during withdraw of rod Contact RE for guidance.
ESG-NRC-S1 Page 24 of 27 Rev
EXAMINATION SCENARIO GUIDE (ESG) REVlEW/VALIDATION Note: This form is used as guidance for an examination team to conduct a review for the propc sed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.
ESG- NRC-SI 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 doc s not cue crew into expected events.
Each event description consists of 0 The point in the scenario when it is to be initiated 0 The malfunction(s) that are entered to initiate the event 0 The symptoms/cues that will be visible to the crew 0 The expected operator actions (by shift position) 0 The event termination point The use of non-mechanistic failures (e g pipe break) should be limited to one or a credible precedin!:
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 7n appropriate time frame and implements procedures and/or corrective actions).
Sequencing/timing 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-SI Page 25 of 27 Rev : 02
EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cont)
Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates E range to be met for a set of two scenarios. Therefore, to complete this part of the review, the set of scenarios mu 4 be available. The section below should be completed once per scenario set.
ESG: NRC-SI SELF-CHECK 8 $-.Fr 1. Total malfunctions inserted: 5 8 G 93- 2. Malfunctions that occur after EOP entry: 1-2
$?-3. Abnormal Events: 2-4 2 2 4. Major Transients: 1-2 c57r 5. EOPs entered requiring substantive actions: 1-2 k 5y 6. EOP Contingency Procedures requiring substantive actions: G2 f? ?y7.Approximate scenario run time: 60-90 minutes
&57/8. Critical Tasks: 2-3 h G m . Technical Specifications are exercised during the test: 22 Comments:
ESG-NRC-SI Page 26 of 27 Rev., 02
Crew Validation Rev: 01 Date Validated: 11/20/2008 Validation Comments Disposition Need Containment purge Permit updated. Provided updated purge permit from OP-HC-103-105 Short Period alarm occurred but not mentioned in turnover sheet. UDdated TO sheet to reflect Short Period alarms mav occur.
Stuck rod trigger malfunctioned. Need to resnap. Validation stopped. ResnaDDed ESG. Need to re-validate ESG.
Crew Validation Rev: 02 Date Validated: 12/5/2006 Trouble alaim when 1AD482 inverter fails. TROUBLE on ET-3 Suppression Pool Leak too slow. Plant depressurizing faster than Modified PC06 to ramp leak from 25 to 5 0 % y e r 6 minutes. This is approaching ED on SPL. consistent with ESG-005 rates.
Validation time 80 minutes. Revised cover sheet. - ~~
ESG-NRC-S1 Page 27 of 27 Rev.: 02
TRAINING USE ONLY ONLINE RISK: GREEN WORK WEEK CHANNEL: B 1 Reactor Power: 4%
MWe (May vary slightly): 0 Activities Completed Last Shift:
Reactor Startup in progress to step 5.3.40 of 10-3 Containment inerting lineup in progress through step 5.1.8 of SO-GS-0001 Major Activities Next 12 Hours:
Continue with Startup by withdrawing Control Rods @ e l 5%/hour.
0 Commence inerting the containment IAW HC.OP-SO.GS-0001 step 5.1.9.
Heightened Awareness:
None Protected Equipment:
None Jagged Equipment:
None Reactivity:
0 Reactor Startup in progress. Continue Startup at 4 5 % power / hr Rod Pull Sheet Step 234 0 Continuous rod withdraw is allowed 0 Per R.E. Some LPRM Downscale and SRM Short Period alarms may occur during withdraw of rods.
SCENARIO TITLE: Loss of RBVS, Loss of EHC, ATWS SCENARIO NUMBER: ESG-NRC-S2 EFFECTIVE DATE: Effective when signed.
EXPECTED DURATION: 82 minutes REV1SlON NUMBER: 01 PROGRAM: 1- L.O. REQUAL T I INITIAL LICENSE 1-1 OTHER -
REVlSION
SUMMARY
- 1. Added 10-0006 step to turnover sheet based on validation comments.
- 2. Changed accumulator pressures to clear alarms earlier based on validation comments.
- 3. Added validation time to cover sheet.
PREPARED BY: Archie E. Faulkner 12/2/2008 -
Instructor DATE APPROVED BY: -
or Designee DATE 4PPROVED BY:
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 crews ability to safel) 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:
_I A. Place Dl Circ Water Pump in service B. Power Ascension C. A CRD Pump trips D. Loss of RBVS E. Trip of EHC Pump F. Lossof EHC G. ATWS w/Trip of B SLC Pump 111. SCENARIO
SUMMARY
The scenario begins with the plant at -51% power, 547 MWe, with D Circ Water Pump out of iervice. Following turnover, the crew starts Dl Circ Water Pump and raises reactor power with control rods. A CRD Pump will trip requiring B CRD Pump to be placed in-service to restore charging flow within 20 minute Tech Spec LCO time. The RBVS Return Damper 9414B fails closed, requiring manual placement of FRVS in service. The A EHC pump will trip. When the B EHC pump starts, foreign material in the sump near the BEHC pump suction will cause the B EHC pump discharge filter to clog. EHC pressure will drop until the turbine trips. When the plant is scrammed, a half core ATWS will occur. Post scram power level is about 20%. Initially bypass valves will control pressure. ADS is inhibited to prevent actuation during ATWS (Critic; Task). Ultimately, the B EHC pump will trip and bypass valves will be lost, requiring SRVs for pressure control. Torus temperature will approach I 1 0 degF. The B SLC pump will trip and cannot be recovered. The A SLC pump will not auto-start, but can be started by the Crew (Critical Task). Crew intentionally lowers RPV water level to reduce reactor power (Critical Task). If the Crew efficiently manages the power control leg of EOP-IOIA and takes advantage of available steam line drains and RFPTs to reject heat to the condenser, intentional lowering of RPV water level to -129 can be avoided. Crew inserts all control rods via CRD or EOP-320 (Critical Task). The scenario is terminated when level is being maintained above -185 inches and all control rods have been inserted.
ESG-NRC-S2 Page 2 of 28 Rev 01
I.C.
I /nitia/ I -
. i INITIALIZE the simulator to 97% power.
REDUCE reactor power to 73% using reactor Recirc.
INSERT control rods in sequence to 51YOpower REMOVE Crossflow from service.
REMOVE 'C' RFPT from feeding and place on recirc IAW SO.AE-0001 section 5.10.
REMOVE 'D' Circulating Water pump from service IAN SO.DA-0001 section 5.2.2.
PREP FOR TRAINING (i.e., RMI 1 set points, procedures, bezel covers)
I I 1 Initial Description J INITIAL l0.ZZ-0006 Section 5.1 up to and including step 5.1.5.8.
INITIAL SO.AE-0001 Section 5.10 up to and including step 5.10.6.A.
INITIAL SO.DA-0001 Section 5.2.2 up to and including step 5.2.2.H.
ENSURE Data Collection is trending the following parameters:
0 Reactor power 0 W/R Reactor Water Level WIR Reactor Pressure Fuel Zone RPV Level COMPLETE the Simulator Ready for Training/Examination Checklist.
PRE-BRIEF the crew for the power change and Circ Water Pump start (optional)
ESG-NRC-S2 Page 3 of 28 Rev. 01
EVE ET #
EVENT ACTION: et-array(5) 5 COMMAND: imf tc16 100 PURPOSE: Swaps B EHC filter and inserts filter plugging at 100%
EVENT ACTION: crqnmi c= 40 // Reactor PDwer 4 0 %
11 COMMAND: imf tc16 100 PURPOSE: Ensures Turbine BvDass valves fail shut.
EVENT ACTION: slnpmpb >= 0.50 // SLC Pump B Start 12 COMMAND:
PURPOSE: Triggers Failure of BP208 SLC pump EVENT ACTION: 1c:pbrun I/ B CRD pump in service.
13 COMMAND: dmf cd051855 PURPOSE: Deletes accumulator trouble alarm malfunction.
EVENT ACTION: 1c:pbrun I/ B CRD pump in service.
14 COMMAND: dmf cd054223 PURPOSE: Deletes accumulator trouble alarm malfunction.
EVENT ACTION: lcpdb >= 900 I! B CRD pump discharge pressure 15 COMMAND: set Icpaccx(171) 950 PURPOSE: Restores HCU accumulator pressure on rod 18-55.
EVENT ACTION: lcpdb >= 900 // B CRD pump discharge pressure 16 COMMAND: set Icpaccx(66) = 950 PURPOSE: Restores HCU accumulator pressure on rod 42-23.
EVENT ACTION:
COMMAND:
PURPOSE:
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 ---
REMOTE/FIELD FUNCTl0N
SUMMARY
I Initial 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 1OC382 Acknowledge 00:05 ET-3 --- NORM TC06 B EHC Pump Filter Replacement --- --- ET-5 --- REPLASE EPOI EOP-301 MSlV LVL 1 Isolation 6:OO --- ET-6 --- BYPASS EP02 EOP-311 Restoring PClG to MSlVs 8:OO --- ET-7 --- BYPA:;S EP38 EOP-319 Restoring lnst Air
~~
3:OO --- ET-8 --- EMERG EP09 EOP 320 ARI Fuses 4:OO --- ET-9 --- REMO /E EPIO EOP 320 ARI Fuses 4:OO --- ET-9 --- REMO /E EP11 EOP 320 RPS Div 1 6:OO --- ET-9 --- INSTA .L EP13 EOP 320 RPS Div 3 6:OO --- ET-9 --- INSTA -L EP12 EOP 320 RPS Div 2 8:OO --- ET-9 --- INSTA -L 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 CLOSE ESG-NRCS2 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 Expected PlantlStudent Response a CRS directs 'D' Circ Water Pump Crew starts 'D' Circ water to be placed in service.
Pump and opens all circ water a PO starts D Circ Water Pump as follows:
a OBSERVE CIRCULATING WATER PUMP DP501 STR ENBL is illuminated.
a PRESS PUMP DP501 START HPI USED:
push-button. STAR 0 PEER CHECK 0 OP BARRIERS 0 a OBSERVE AI-6325D ClRC WTR PUMP MOT AMP indicates 500 -
610 amps (running).
IF dispatched to respond to a OBSERVE DISCH VALVE HV-CW Panel 10C502 panel 2152D OPEN/CLOSE MID alarm, THEN REPORT the illuminates.
alarm was caused by momentary high discharge pressure on D pump and the alarm has cleared. TOGGLE Remote Function AN06 to NORM.
a OBSERVE CIRCULATlNG WATER PUMP DP501 START is illuminated.
a PRESS DISCH VALVE HV-2152D OPEN FULL push-button.
OBSERVE HV-2152D OPEN FULL illuminates.
PO opens remaining CW Pump discharge valves OPEN FULL as follows:
a PRESS DISCH VALVE HV-2152A(B,C) OPEN FULL push-button.
ESG-NRC-S2 Page 7 of 28 R e i 01
Event I Instructor Activity Expected PlantlStudent Response Comments OBSERVE HV/-2152A(B,C)
OPEN FULL illuminates.
Power Ascension: 0 CRS directs raising power to 80% using RE guidance.
Crew commences reactor power ascension after assuming the watch As RE PROVIDE the following 0 RO raises power with control HPI USED:
guidance: rods using provided Move Sheets STAR 0 0 SPRI and Enhanced as follows: PEERCHECKU Stability Guidance are valid OP BARRIERS 17 for the remainder of the maneuver.
0 Power has been steady for the last hour.
0 Raise power to 60% with control rods using 9E rods to position 48.
Select a control rod 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).
3 CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod position (1OC650C).
The associated Full Core Display (white) numbered rod identification light comes ON (1OC650C).
Approximately 6 gpm total flow through both the Insert AND Withdraw Stabilizing valves is indicated on CRlDs point B2117.
ESG-NRC-S2 Page 8 of 28 Rev: 01
V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE I
Event I Instructor Activity Expected PlantlStudent Response Cornments 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 CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod movement.
Full Core Display FULL IN (green) light goes OUT, as applicable.
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.
s CONTROL ROD POSITION 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 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 0 WHEN a control rod is withdrawn 48 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 ENTER time of CRD CRD pump by: Pump trip for beginning OHA C6-F2 CRD SYSTEM of 20 minute LCO time:
TROUBLE CRIDS D2244 CRD WATER Time:
PUMP A MOTOR TRBL OHA CI-F5 COMPUTER PT IN ALARM CRIDS D2926 RECIRC PUMP A SEAL STAGE FLOW HILO CRIDS D2927 RECI RC PUMP B SEAL STAGE FLOW HILO Flashing STOP light for AP207 Flashing OVLD/PWR FAIL for AP207 ESG-NRC-S2 Page 10 of 28 Rev: 01
r Event I instructor Activity Expected Piant/Student Response Comments IF dispatched to AP207, e RO dispatches N E 0 to inspect THEN REPORT the pump AP207 CRD pump.
inboard bearing oil bubbler is broken and the motor is hot to the touch.
E dispatched to AP207 e Crew dispatches N E 0 to inspect breaker, breaker for AP207 CRD pump.
THEN REPORT the breaker tripped on overcurrent.
e Crew recognizes potentially inoperable accumulators on withdrawn control rods by:
3 OHA C6-D4 CRD ACCUM TROUBLE 3 CRIDS D5268 CRD ACCUMULATOR TRBL Flashing amber ACCUM lights on Full Core Display for 18-55 and 42-23 WHEN dispatched to e Crew dispatches N E 0 to check investigate HCU accumulator HCUs 18-55 and 42-23.
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.
CRS enters AB.IC-0001 Condition A CRDM temperatures can be e CRS directs placing BP207 CRD checked with Monitor Item pump in service IAW either:
Ictcrd. 3 AR.ZZ-0011 s SO.BF-0001 ESG-NRC-S2 Page 11 of 28 Rev; 01
SUPPORT any directed RO place BP207 CRD pump in HPI USED:
manipulations of the BP207 service as directed by CRS. STAR 0 discharge valve (v008) using PEERCHECKO Remote Function CD02. FLAGGING OP BARRIERS 0 Record Time B 1 CRD Pump started TIME CRS recognize the following Restore charging wai Tech Specs apply: pressure within 20
= Control Rod Accumulators minutes or place the 3.1.3.5.a.2 mode switch in SHUTDOWN 1 Loss of RBVS: 10 Crew recognizes ~ o s ofs RBVS I After the Crew assumes the by:
watch and at the discretion o = RB DIP indication on the Lead Examiner, 1OC650E 3 SPDS RB PARAMETERS D/P indication.
2 OHA EI-F5 COMPUTER PT IN ALARM
= CRIDS B7164 REACTOR BLDG DlFF PRESS z OHA E6-C5 RBVS & WING AREA HVAC PNL 106382 z CRIDS D3960 RBVS EXH RMT PNL C382 TRBL 3 CRIDS D3961 RBVS SUPPLY RMT PNL C382 TRBL 0 CRS implements AB.CONT-003:
= Condition A a Condition D IF dispatched to 1OC382, Crew dispatches RBEO to THEN REPORT Low Flow Trip 1OC382 to investigate.
darms on all Reactor Bldg Supply and exhaust fans.
ESG-NRC-S2 Page 12 of 28 Re\
b Event / Instructor Activity Expected PlantlStudent R e s p o n s e Comments RO/PO recognize HD-9414B failed in mid position by 1OC651E indication and inform CRS.
IF directed to secure RBVS, RO/PO place FRVS in service HPI USED:
THEN TRIGGER ET-3. IAW SO.GU-0001. STAR 0 PEER CHECK Cl FLAGGING 0 OP BARRIERS IF dispatched
- to HD-9414B, Crew dispatches N E 0 and THEN REPORT there is no Maintenance to investigate obvious reason for the failure. closure of HD-9414B.
(GU-HD-9414B is located in Room 4624, on the Rx Bldg roof.)
CRS recognize the following Tech Specs apply: Restore Secondary Secondary Containment Containment within 4 Integrity hours.
3.6.5.1
=> Secondary Containment 8 Hour LCO Action tirie Automatic Isolation Dampers for damper.
3.6.5.2 action a or b or c Crew recognizes trip of API 16 If left in AUTO, the EHC pump by: B P I 16 EHC pump wii OHA D3-F5 TURB HYDR auto-start in about 10 PUMP TROUBLE seconds.
OHA D3-E5 TURB HYDR 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 ESG-NRC-S2 Page 13 of 28 Rev: 0 1
E dispatched to API 16, 0 ROlPO ensures start of the HPI USED:
THEN REPORT the pump BPI 16 EHC pump. STAR 0 outboard motor bearing is hot PEERCHECKO to the touch. Immediate Operator action IAW E dispatched to API 16 AB.BOP-0003.
breaker, THEN REPORT the breaker tripped on overcurrent.
Monitor Item: 0 CRS implements AB.BOP-0003. There are no subsequent actions in 0 EHC Header Pressure AB.BOP-0003 for a tri tupehchd of a pump.
0 EHC Pump Disch Pressure tupehc(2) - 15 0 EHC Pump Filter D/P tupehcdp(2)
BEHC Pump CloW:
Filter 0 Crew recognizes BPI 16 discharge filter clogging by:
With discharge filter swap, EHC pressure OHA D3-F5 TURB HYDR will reach 1100# in The BPI 16 discharge fi 3 begin clogging one min PUMP TROUBLE about 6 minutes after the pump starts. s CRlDS D3629 MAIN TURB the pump trip.
EHC PUMP B FILTER DP HI IF the
- discharge filters 3 HYDR FLUID PUMP B are swapped, flashing HI FILTER DIP light THEN EHC pressure
=) Lowering EHC header will reach 1100# abou pressure 4 minutes after the swap.
a Condition A IF directed to
- swap BPI 16 0 Crew directs TBEO to swap EHC header pressure discharge filters, BPI 16 pump discharge filters. will recover, then REFER to SO.CH-0001 continue to decay.
Section 5.20, THEN TRIGGER ET-5.
0 WHEN EHC pressure lowers to May direct earlier, 1200 psig, based on rate of THEN CRS directs locking the pressure drop and Mode Switch in SHUTDOWN. absence of any remaining compensatory actions 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 HPI USED:
AB.ZZ-0001 Attachment 1. HARD CARD 0 CRS implements EOP-IOIA.
PO stabilizes and maintains RPV level as directed by CRS.
CRS directs:
a Initiating SLC Verifying RWCU Isolates RO initiate SLC and verify HPI USED:
temperature reaches 7 70 pump is started:
degrees. Temp:
Crew recognizes trip of BP208 SLC pump by:
3 OHACI-91 SLC PUMPNALVE O/PF
=) OHA C1-F1 SLClRRCS I NIT1AT10N FA1LU RE 3 CRIDS D3023 SLC INJ PMP BP208 TROUBLE TRBL Flashing STOP light for BP208 IF dispatched
- to investigate trip 0 Crew dispatches NE0 and of BP208, Maintenance to investigate trip of
-HENREPORT the breaker is BP208 SLC pump.
tripped and will not reset.
(52-222101)
ESG-NRC-S2 Page 15 of 28 Rev. 01
CRS directs:
Verifying Recirc runback to minimum Tripping reactor recirc pumps 0 RO: HPI USED:
Verify Recirc runback to STAR minimum May already be tripped Trip reactor recirc pumps on EOC-RPT.
ROlPO inhibit ADS IAW HPI USED:
AB.ZZ-0001 Att. 13. STAR HARD CARD
- Crew prevents an uncontrolled This Critical Task is not depressurization during ATWS applicable if RPV level conditions by preventing ADS never reaches -1 29.
ACTUATION. See justification for failure criteria.
REFER to the appropriate EOP CRS directs performance of the The timing, order, and and SUPPORT Crew requests following EOPs: priority of the EOP for EOPs IAW with the EO.ZZ-0320 Defeating ARI performance may vat-).
following. Validated execution and RPS Interlocks time delays are built-in: EO.ZZ-0301 Bypassing EOP-301: ET-6 MSlV Isolation Interlocks EOP-311: ET-7 EO.ZZ-0311 Bypassing EOP-319: ET-8 Primary Containment EOP-320: ET-9 Instrument Gas Isolation EOP-322: ET-I 0 Interlocks EO.ZZ-0319 Restoring Instrument Air in an Emergency 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 ESG-NRCS2 Page 16 of 28 R e \ : 01
0 RO/PO terminate and prevent HPI USED:
injection IAW AB.ZZ-0001: STAR 0
=) Attachment 16 (1OC651) HARD CARD
= Attachment 17 (1OC650) 0 CRS directs maintaining RPV Typically, the lower er 3 water level between -50 and of the level band is se.*
-185. above -1 29.
0 PO control level as directed by HPI USED:
CRS with: STAR Feedwater IAW AB.ZZ-0001 HARD CARD I7 Att. 14 If the turbine trips 3 RClC IAW AB.ZZ-0001 Att. 6 before the reactor is 3 HPCl IAW EOP-322 scrammed, an RRCS feedwater runback may occur.
- 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 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 0 CRS directs stabilizing pressure When pressure control below 1037 psig with: swaps to SRVs, Main Steam Line Drains maintaining RPV water 3 SRVS level between -50 an3
-129 will be very challenging due to shrink and swell and changing reactor pressure with the RFPTs in MAN.
0 RO/PO control pressure as HPI USED:
directed by CRS with: STAR Main Steam Line Drains IAW HARD CARD R AB.ZZ-0001 Att. 15 OP BARRIERS R
= 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 1OC650C a RMI 1 9AX833/834 alarm Various Suppression Pool tem perature indicators 0 CRS implements EOP-102.
0 CRS directs placing RHR in Suppression Pool Cooling.
RO/PO place RHR in Supp Pool HPI USED:
Cooling IAW AB.ZZ-0001 Att. 3. STAR HARD CARD R FLAGGING ESG-NRC-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, HPI USED:
THEN RO/PO terminates and STAR 0 prevents injection from Core HARD CARD 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 THEN the Crew implements RP07 to allow full rod insertion EOP-320 Section 5.3 and resets on the next scram. RPS.
At the Lead Examiners WHEN OHA C6-E4 clears, HPI USED:
discretion, MODIFY Monitor THEN the Crew initiates a STAR 0 Item lclsdv to accelerate manual scram IAW EOP-320 draining of the SDV. Section 5.3.
- CREW fully inserts all control rods via RMCS and/or manual scram(s) IA W H C.0P-EO.ZZ-0320.
0 Crew recognizes the reactor is shutdown by:
5 SPDS ALL. RODS IN
=. RWM Confirm Shutdown CRIDS Rod positions 0 CRS directs terminating SLC injection.
0 RO/PO terminate SLC injection. HPI USED:
STAR 0 ESG-NRC-S2 Page 19 of 28 Rev: 01
Event I Instructor Activity Expected PiantlStudent Response Comments CRS exits EOP-IOIA, enters The scenario may be EOP-101.
terminated at the discre ained above -1 85 0
ESG-NRC-S2 Page 20 of 28 Rev: 01
A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid 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. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101Procedure Use and Adherence J. OP-AA-101-1 11-1003 Use of Procedures K. HU-AA-1081 Fundamentals Toolkit L. HU-AA-1211 Briefing M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001Event Response Guidelines
- 0. OP-AA-108-114 Post Transient Review P. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program Q. OP-HC-108-106-1001Equipment Operational Control R. OP-AA-101-112-1002On-Line Risk Assessment S. HC.OP-IO.ZZ-0006 Power Changes During Operation T. HC.OP-SO.AE-0001 Feedwater System Operation U. HC.OP-SODA-0001 Circulating Water System Operation V. HC.OP-SOSF-0001 Reactor Manual Control W. HC.OP-SO.SF-0003Rod Worth Minimizer Operation X. HC.OP-AB.IC-0001 Control Rod Y. HC.OP-AB.ZZ-0001Transient Plant Conditions Z. HC.OP-AB.CONT-0004Reactor Building AA. HC.OP-AB.BOP-0006Turbine Hydraulic Pressure BB. HC.RE-AB.ZZ-0001 Insertion of Control Rods in Response to an ATWS cc. HC.OP-AB.ZZ-000Reactor Scram DD. HC.OP-EO.ZZ-0101 RPV Control EE. HC.OP-EO.ZZ-0101A ATWS-RPV Control FF. HC.OP-EO.ZZ-0102Primary Containment Control GG. HC.OP-EO.ZZ-0301Bypassing MSlV Isolation Interlocks HH. HC.OP-EO.ZZ-0311Bypassing Primary Containment Instrument Gas Isolation Interlocks II. HC.OP-EO.ZZ-0319Restoring Instrument Air in an Emergency JJ. HC.OP-EO.ZZ-0320 Defeating ARI and RPS Interlocks KK. HC.OP-EO.ZZ-0322 Core Spray Injection Valve Override ESG-NRC-S2 Page21 of28 Re\:: 01
ES ESG-NRC-S2 I O 1 1.
- Crew starts AP208 SLC pump before Suppression Pool temperature reaches 1I O 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 r 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 110°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 -129 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 110°F will help reduce power and may prevent the need to lower level to -129.
2.
KIA 218000 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.
- Crew lowers RPV level to -50; and ensures adequate core cooling by maintaining o restoring RPV level above -185 without Emergency Depressurizing.
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 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 -185. 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.
ESG-NRC-S2 Page 22 of 28 01 Rev4v:
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 5.15 . 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 tXAMI NATION SC ENARI0 GUIDE (ES G) REVIEW/VA LIDATION I
- 4 I
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 point in the scenario when it is to be initiated The malfunction(s) that are entered to initiate the event The symptoms/cues that will be visible to the crew The expected operator actions (by shift position)
The event termination point 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 7 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\ 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 $71. Total malfunctions inserted: 5-8
(.; c,J-2. Malfunctions that occur after EOP entry: 1-2 0
'8 3. Abnormal Events: 2-4 6q /;- I 4. Major Transients: 1-2
[tL'$f 5. EOPs entered requiring substantive actions: 1-2 G . 5 2 6. EOP Contingency Procedures requiring substantive actions: 0-2
[I "3- 7. Approximate scenario run time: 60-90 minutes Gi-2 8. +
Critical Tasks: 2-3 fi k 9. Technical Specifications are exercised during the test: >2 Comments:
ESG-NRC-S2 Page 27 of 28 Re\ : 01
EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cont)
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. Added.
Simplfy Turnover sheet. Minimized wordina on TO sheet.
Validation time 82 minutes. Add validation time to cover sheet. Added.
Crew Validation Rev: Date Validated:
Crew Validation Rev: Date Validated:
ESG-NRC-S2 Page 28 of 28 Rev.: 01
I TRAINING WE ONLY ONLINE RISK: GREEN WORK WEEK CHANNEL: C 1 i
Reactor Power: -51 % Returning from power reduction for condenser water box cleaning.
MWe (May vary slightly): 547 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 1st alarm until scram sctpoint with no action taken.
- 2. Failed Fool to close manually and automatically based on validation comments.
I
- 3. Swapped to 8 TSC Chilled Water System in service for preps for TACS swap.
PREPARED BY: Archie E.Faulkner 12/5/08 ,-
Instructor DATE
/?
APPROVED BY: y J d hlw2 0 rations Training Manager or Designee APPROVED BY:
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 DSACS pump is in Standby.
ENSURE the BTSC Chilled Water System is in sewice and the A TSC Chilled Water Circ pump is in Standby in Auto.
ENSURE HC.OP-DL.ZZ-0026log 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 EVENT TRIGGERS:
I I
ET # Description EVENT ACTION: cufdelta >= 60 // RWCU Diff Flow in gpm COMMAND: irnf cu03 100 120 PURPOSE: Raises severity of RWCU leak after isolation setpoint is exceeded.
~ ~~ ~
EVENT ACTION: crqnrni <= 10 I1 Reactor power < 10%
COMMAND: drnf tcOl-IO PURPOSE: Deletes stuck closed bypass valves, fails Mode Switch and triggers LOCA.
EVENT ACTION: rnspeh <= 900 I/ Main Steam Line Header Pressure < 900 psig 10 COMMAND: irnf TC02-4 0 PURPOSE: Closes TCVM to prevent depressurization and MSIV isolation.
EVENT ACTION: rnspeh <= 890 /I Main Steam Line Header Pressure < 890 psig 11 COMMAND: irnf TC02-3 0 PURPOSE: Closes TCV#3 to prevent depressurization and MSlV isolation.
EVENT ACTION: mspeh <= 880 /I Main Steam Line Header Pressure < 870 psig 12 COMMAND: irnf TC02-2 0 PURPOSE: Closes TCV#2 to prevent depressurization and MSlV isolation.
EVENT ACTION: rnspeh <= 870 / I Main Steam Line Header Pressure < 860 psig 13 COMMAND: irnf TC02-I 0 PURPOSE: Closes TCV#I to prevent depressurization and MSlV isolation.
EVENT ACTION: pcpdw >= 16.4 // Drywell Pressure > 1.7 psig COMMAND:
PURPOSE: 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
ET019 GROUP 7A HV-F001 RWCU Supply Is01 --- NONE --- FAIL-OPEN 1 ESG-NRC-S3 Page 6 of 27 Rev.: 01
Event I Instructor Activity Expected PlantlStudent Response Comments Power Reduction: CRS directs continuing the power Crew continues reactor pow reduction to 84.5% using RE duction after assuming t guidance.
As RE PROVIDE the following 0 RO reduces power with control HPI USED:
guidance: rods using provided Move STAR q 0 SPRl and Enhanced Sheets. PEERCHECKU Stability Guidance are valid OP BARRIERS 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).
3 CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod position (1OC650C).
The associated Full Core Display (white) numbered rod identification light comes ON (1OC650C).
Approximately 6 gpm total flow through both the Insert AND Withdraw Stabilizing valves is indicated on CRIDs point B2117.
Continuous rod insertion 0 At the ROD SELECT MODULE, (Non-emergency) PRESS AND HOLD the INSERT PB AND OBSERVE the following:
The INSERT (white) light comes ON.
ESG-NRC-S3 Page 7 of 27 Rev.: 01
Event I instructor Activity Expected PiantlStudent Response 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 P6 AND OBSERVE the following:
The INSERT (white) light goes OUT.
a The SETTLE (white) light comes ON for = 6 seconds, THEN goes out.
r;, CONTROL ROD POSITION 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 PO swaps TACS after LOOPB IAW OP-SO.EG-0001.
e 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 EG-HV-2512B to ensure minimum flow requirements of =go00 g Pm.
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
~ 4 5 0 0gpm SACS flow through the 'A' RHR HX.
ESG-NRC-S3 Page 9 of 27 Re$(.:01
Event I Instructor Activity Expected PlantlStudent Response Comments 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 PERFORM the following to place the SACS Loop A in standby:
PRESS the AP210 STOP pushbutton.
3 PLACE SACS LOOPA Pump A in AUTO.
3 THROTTLE EG-HV-2512A to ensure minimum flow requirements of ~ 4 5 0 0 gpm.
Crew recognizes RRCS Failure PT-N403A output can by: be seen on the SPDS 3 OHA D1-E1 RRCS Reactor Pressure Poird TROUBLE Status display.
RRCS Channel A Logic A RRCS LOGIC A TROUBLE light
-IF dispatched to RRCS, 0 Crew dispatches ABEO and/or THEN REPORT there is an Maintenance to RRCS cabinets ATM CALI GROSS FAILURE 1OC601/602.
light lit on 1OC601 and PT-N403A is reading 0 psig.
IF dispatched to RRCS to perform DL-26 Attach 1b Form 1,
THEN PROVIDE DL-26 Attach I b 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.
ESG-NRC-S3 Page 10 of 27 Re\.: 01
Event / Instructor Activity Expected Plant/Student Response Comments a CRS recognize the following Place the inoperable Tech Spec action applies: channel in a tripped a ATWS Recirculation Pump condition within one Trip System Instrumentation hour.
3.3.4.1 action b RWCU Leak: a Crew recognizes rising offsite 9RX580 Rate of Rise After Tech Spec actions fo release rate by: will alarm 1-2 minute!
PT-N403A have been => SPDS indication after the leak starts.
identified, RMI 1 SPV Effluent 9RX580 This alarm is NOT OR
-1 programmed to be at the discretion of the Lead audible in the Control Examiner, Room TRIGGER ET-5 (RWCU with Auto Isolation failure)
AND two minutes after the RWCU leak has been in VERIFY South Plant Vent THEN CALL as Rad Pro 0 CRS implements AB.CONT-004:
Condition C Condition A Crew recognizes leak from Room temperatures v I1 Monitor Items: RWCU by: not provide conclusivc.
0 RWCU Diff Flow 3 Rising differential flows on evidence of leak.
cufdelta NUMAC and CRIDS page 61 RWCU differential floi 3 OHA D3-33RWCU STM LK will reach the alarm ISLN TIMER INITIATED setpoint about 7.5 CRIDS 05871 RWCU ISLN minutes after leak TIMER INITIATED CH D starts.
3 CRIDS 05873 RWCU ISLN TIMER INITIATED CH A If RWCU is isolated before differential flow*
setpoint is reached, alarms will not be received.
ESG-NRC-S3 Page 11 of 27 Re\ : 01
V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / instructor Activity Expected PlanVStudent Response Comments Monitor Items: 0 Crew recognizes failure of If RWCU is isolated 0 A Channel Isolation RWCU to isolate by: before differential flow cu:k6a09 =1 OHA CI-A2 RWCU DlFF setpoint is reached, 0 D Channel Isolation FLOW HI isolation will not be cu:k6d7 7 =. CRIDS D5870 RWCU DlFF received.
FLOW CH D c
=. CRIDS D5872 RWCU DlFF FLOW CH A Examiner Note: HV-F001 will not close manually or automatically. 3 RO close RWCU HV-F001 and HV-FOO4.
(May also close HV-F039)
Immediate Operator action IAW AB .CONT-0002.
HPI USED:
STAR 0 Monitor Items:
- Crew initiates closure of RECORD time betwecm HV-FOO4 RWCU HV-F004 within two C1-A2 and initiating cuvfOO4 minutes of receiving OHA d o sure.
C7-A2 RWCU DlFF FLOW HI. TIME:
(Closing HV-F004 prior to the isolation timer complefion satisfies this requirement.) Closing the RWCU HV-F004 prior to receiving OHA C1-A2 satisfies this Critical Task.
i0 RO reports the HV-F001 would not close manually or automatically.
=, Condition B 3 If crew isolated RWC!J prior to isolation signal,
=. Condition A Condition A will not be performed.
CRS directs placing FRVS in service.
IF directed to remove RBVS 0 PO place FRVS in service IAW HPI USED:
G m service, SO.GU-0001 Section 5.3. STAR 0 THEN REFER to SO.GU-0001 AND TRIGGER ET-6.
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 Need to restore valve:
Tech Spec action applies: to OPERABLE or Primary Containment deactivate the HV-FOC 1 Isolation Valves or HV-F004 in the nexi 3.6.3 action a four hours.
Primary Containment Integrity May also refer to T/S 3.6.1 .I 3.3.2, although both trip systems would already be tripped, and the valves already shut.
I MODIFY the initial severity of I Crew recognizes rising reactor pressure by:
Some alarms may no:
be received if the
=) OHA D3-D5 EHC UNIT pressure excursion is PANEL 1OC363 terminated before the r 3 OHA B3-E5 RPV setpoint.
PRESSURE HI 3 OHA C5-A5 RPV PRESSURE HI DEHC Bypass Valve Positioning Error alarms
=1 CRIDS D3372 MN TURB LOAD LIMIT LIMITING Various Reactor Pressure indicators 0 RO reduces reactor power to Immediate Operator maintain the RPV PRESSURE HI Action IAW overhead alarm clear. AB. RPV-0005.
HPI USED:
STAR D ESG-NRC-S3 Page 13 of 27 Rev.: 01
Event I Instructor Activity Expected PlantlStudent Response Comments 0 CRS implements AB.RPV-0005:
=z Condition A Condition D 0 WHEN reactor pressure cannot HPI USED:
be maintained <IO30 psig, STAR THEN Crew locks the Mode Switch in SHUTDOWN.
- Crew scrams the reactor within RECORD time when one minufe of reactor pressure Reactor Pressure goes exceeding 1037 psig. above 1037 psig.
(Scramming prior to reaching 1037 psis safisfies this TIME:
requirement.)
NOTE: If the crew is in the e -IF Reactor Pressure was above process of a manual scram 1037 psig when the reactor was when 1037 psig is reached, manually scrammed, failure of RPS may not be THEN Crew recognizes Scram
-ecognized. However, if it is Condition and Reactor Power qecognized that RPS did not Above 4% or Undetermined EOP automatically scram the reactor Entry Condition by:
at 1037 psig, EOP-IOIA should 3 OHA C 5 A 5 RPV be entered and exited. PRESSURE HI Various indications of reactor power e 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.
0 RO performs scram actions IAW HPI USED:
A6.ZZ-0001Att. 1. STAR HARD CARD 0 e Crew recognizes RPV Level May also have High Below 12.5 EOP entry condition Reactor Pressure ent*y by: condition.
=> OHA C5-A4 RPV WATER LEVEL LO 3 OHA A7-D5 RPV LEVEL 3 Various water level indicators 0 CRS implements EOP-101.
ESG-NRC-S3 Page 14 of 27 Re.:.: 01
0 PO maintains reactor water level HPI USED:
as directed by CRS IAW STAR AB.ZZ-0001 Att. 14. HARD CARD 0 Crew may recognize partial loss HPI USED:
of Mode Switch functions by STAR loss/absence of:
3 OHA C 5 A 3 MANUAL SCRAM 3 OHA C5-GI MODE SWITCH SHUTDOWN SCRAM BYP 3 OHA C5-C3 MSIV CLOSURE TRIP BYP Absence of SRMllRM status lights and alarms 0 Crew recognizes LOCA condition:
3 OHA C6-61 DLD SYSTEM ALA RMITRBL 5 RM11 9AX314 DLD FLOOR DRN FLOW alarm 3 OHA D3-C3 DRYWELL SUMP LEVEL HI/LO 5 OHA A4-F5 COMPUTER PT IN ALARM 3 OHA A7-E4 DRYWELL PRESSURE HVLO Rising Drywell Pressure 0 CRS implements AB.CONT-001:
Condition A 0 RO/PO ensures drywell cooling HPI USED:
maximized. STAR 0 0 Crew checks Recirc pump seal parameters SRV temperatures ESG-NRC-S3 Page 15 of 27 Rev.: 01
Crew recognizes Drywell Pressure Above 1.68# EOP entry condition by:
q OHA A7-D4 DRYWELL PRESSURE HI/HI q OHA C5-B5 DRYWELL PRESSURE HI Various system initiations and isolations.
CRS enters EOP-102, re-enters EOP-101.
e RO/PO verify automatic actions.
AIC Loaic Failures: 0 Crew recognizes failure of the Core Spray WILL auto The failure of Drywell Pressure AIC Core Spray logics to initiate initiate if RPV water transmitters N094E/G is by: level reaches -1 29.
already inserted. 3 N C INlT AND SEALED IN PClS isolations will lights extinguished occur due to the Pump STOPPED indication availability of NSSSS N C channel breaker status and the PT-NO94NC.
on 1OC650E NON CLASS 1E Only the Core Spray LOAD ISLN CIRCUIT logic fanout (EDG, BREAKER STATUS AND sequencer, etc) will bc C0NTROI- affected.
s N C EDGs not running Also, no drywell Various valve failures to pressure indicators are isolate affected by the failures.
RO/PO initiate N C Core Spray HPI USED:
logic IAW AB.ZZ-0001 Att 5. STAR 0 HARD CARD 0 Crew recognizes failure of the RHR WILL auto initia%
N C RHR logics to initiate by: if RPV water level 3 N C INlT AND SEALED IN reaches -1 29.
lights extinguished Pump STOPPED indication RO/PO initiate N C RHR logic HPI USED:
IAW AB.ZZ-0001 Att 4. STAR HARD CARD ESG-NRC-S3 Page 16 of 27 ReJ.: 01
Event I Instructor Activity Expected PlanffStudentResponse Comments Crew recognizes failure of HPCl HPCI WILL auto initiate to initiate by: if RPV water level HPCl INIT AND SEALED IN reaches -38 and is light extinguished capable of maintaining HV-F001 CLSD indication RPV water level by
= FV-4880 CLOSED indication itself.
I FV-4879 CLOSED indication
= SI-4919 Turbine Speed indicates zero rpm FIC-R600 Pump Flow indicates zero gpm 0 RO/PO manually initiate HPCI HPI USED:
IAW AB.ZZ-0001 Att. 6. STAR 0 HARD CARD 0 0 CRS directs maintaining RPV RFPTs will trip and level 12.5 to 54with any SULCV will fail closed combination of: when drywell pressure, 3 HPCI reaches I .7 psig and a RClC cannot be restored.
FeedwatedCondensate 0 RO/PO maintain RPV level as HPI USED:
directed by CRS with: STAR 0 HPCI JAW AB.ZZ-0001 Att. 6 HARD CARD 0 3 RCIC IAW AB.ZZ-0001 Att. 6 0 CRS implements AB.COOL-003:
Condition 8 0 RO/PO trips recirc pumps. HPI USED:
STAR n RRCS RPT trips are failed. Pumps must t 2 tripped manually.
May also be tripped JAW EOP-102 guidar :e for spraying the dtyw II.
0 WHEN Suppression Chamber Recirc pumps should pressure exceeds 9.5 psig, be tripped prior to THEN CRS directs initiating initiating drywell spray.
drywell spray.
ESG-NRC-S3 Page 17 of 27 Re&.: 01
V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE RO/PO place one loop of RHR in HPI USED:
drywell spray IAW AB.ZZ-0001 STAR 0 Att. 2. HARD CARD 0 IF 'A' RHR logic was NOT manually initiatl 1 THEN 'A' RHR canni spray the drywell.
Crew maintains Suppression PSP will by reached Chamber Pressure below the approximately elevei Action Required region of the minutes after the LO 4 PSP curve without Emergency starts with no mitigal 3 Depressurizing. action.
CRS directs placing RHR pump in Suppression Pool Cooling and Suppression Chamber Spray.
ROlPO place RHR pump in HPI USED:
Suppression Pool Cooling and STAR Suppression Chamber Spray HARD CARD IAW AB.ZZ-0001 Att. 3.
CRS directs restoring PClG to SRVs.
RO/PO restore PCIG to SRVs HPI USED:
IAW AB.=-0001 Att. 9. STAR 0 HARD CARD 0 If necessary, Crew prevents HPI USED:
injection from Low Pressure STAR ECCS not required for adequate HARD CARD core cooling.
ESG-NRCS3 Page 18 of 27 ' 01
I HC.OP-BL.ZZ-0026{Q]
ATTACHMENT I b Page Iof 5 FORM +I ATWS-RPT Channel Check [ f o r Surveillance Log Item 6)
T0da.y~ Date Operational Condition Date
)PER 1 ACCEPTABLE LIhllTS :
RPV LEVEL I I ilPV PRESSURE COMMENTS:
Hope Creek Page 4? of 99 Rev. 222
A. TQ-AA-106-0304Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Alarm Response Procedures (Various)
G. HU-AA-101 Performance Tools and Verification Practices H. HU-AA-104-101 Procedure Use and Adherence I. HU-AA-1081 Fundamentals Toolkit J. HU-AA-1211 Briefing K. OP-AA-101-111-1003Use of Procedures L. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel M. OP-AA-101-111-1004Operations Standards N. OP-AA-101-112-1002On-Line Risk Assessment
- 0. OP-AA-106-101-1001Event Response Guidelines P. OP-HC-108-106-1001 Equipment Operational Control Q. OP-AA-108-114 Post Transient Review R. OP-HC-108-115-1001Operability Assessment and Equipment Control Program S. HC.OP-DL.ZZ-0026 Surveillance Log T. HC.OP-SO.BB-0002Reactor Recirculation System Operation U. HC.OP-SO.BC-0001Residual Heat Removal System Operation V. HC.OP-SO.BE-0001Core 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-0005Reactor Pressure BB. HC.OP-AB.CONT-0001Drywell Pressure CC. HC.OP-AB.CONT-0002 Primary Containment DD. HC.OP-AB.CONT-0004Radioactive Gaseous Release EE. HC.OP-AB.ZZ-000Reactor Scram FF. HC.OP-EO.ZZ-0101 RPV Control GG. HC.OP-EO.ZZ-0102 Primary Containment Control HH. HC.CH-TI.ZZ-0012Chemistry Sampling Frequencies, Specifications, and Surveillances 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 I O 1 I.
- Crew initiates closure of RWCU HV-FO04 within two minutes of receiving OHA C 7 4 2 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 241000 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 t h e 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 ~ t y 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 I O 1 HOPE CREEK ESG PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE y
l b
J EVENT yJ EVENT Loss Of OfFsite PowerISBO Internal Flooding Y LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:
Turbine Trip Loss of ssw Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening Y Manual Scram COMPONENTlTRAINlSYSTEMUNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Y/N
__ KEY EQUIPMENT Hard Torus Vent SLC HPCI CRD 1E 4.16KV Bus 1E 125VDC SACS HxlPump EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power NB RHR SRVs RClC CondensatelFeedwater SSW Pump PClG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE ybJ OPERATOR ACTION Y 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): 1100 Work Week: A Risk Color: Green Activities Completed Last Shift:
0 Power reduction to 90% power.
0 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 The point in the scenario when it is to be initiated 0 The malfunction(s) that are entered to initiate the event 0 The symptoms/cues that will be visible to the crew 0 The expected operator actions (by shift position) 0 The event termination point 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. The section below should be complc ted for each scenario.
ESG: NRC-S3 SELF-CHECK 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-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 Failed Fool to close manually and automatically.
earlv. then the CRS will not aet TS call.
Slow down rate of rise of TCV failure. No real time to do anything Changed ramp time from 10 minutes to 15 minutes. Overall time to about it. respond is now about 2 minutes from 1st alarm until scram setpoint with no action taken.
Crew Validation Rev: Date Validated:
ESG-NRC-S3 Page 27 of 27 Rev.: 01
TRAINING USE ONLY E ONLINE RISK: GREEN 11 WORK WEEK CHANNEL: A ]
Reactor Power: 90%
MWe (May vary slightly): I 1 0 0 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.
- 3. Added driver guidance for I&C action for Flow Unit
- 4. Added that the light is extinguished for Seismic panel.
PREPARED BY: Archie E. Faulkner 12/6/2008 -
Instructor DATE APPROVED BY: fu 2 pJ C r bper4ions Training Manag& or Designee A
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 crews 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. Place B RFPT in service B. Power ascension C. SRV H Tailpipe temp sensor fails upscale D. C Recirc Flow Unit Summer fails downscale E. Seismic Event F. RClC Steam Leak G. Trip of Service Air Compressor H. Air Leak w/Multiple Rod Drift I. LOP w/ EDG failures J. 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 1OK107 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:
- 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.
- 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 PREP FOR TRAINING (Le., RMI 1 set points, procedures, bezel covers)
I 1 Initial Description PREPARE a Fire Alarm for FA016.
~ ~~ ~ ~~
i COMPLETE the Simulator Ready for TraininglExammation Checklist.
ENSURE Data Collection is trending the following datapool variables:
0 RClC Room Temp hvtr4110 0 W/R Reactor Water Level: rrlnO9la or equivalent 0 Fuel Zone Reactor Water Level: rrlfzcha or equivalent 0 Instrument Air Header Pressure: iapiarcaliapiarcb or equivalent ESG-NRC-S4 Page 3 of 29 Rt
ET # Description EVENT ACTION: et-array(6)
PURPOSE: imf COMMAND:
EVENT ACTION:
PC07B Initiates .
aftershock with LOP/LOCA -
7 COMMAND:
PURPOSE:
EVENT ACTION: et-array( 8) a COMMAND: dmf dg02a PURPOSE: Restores A EDG to service.
EVENT ACTION: ia:Oprun >= 1.0 /I OOKl07 running 9 COMMAND:
PURPOSE: Inserts air leak when OOKlO7 is started.
EVENT ACTION: iapiarca C= 75 // Instrument Air header pressure <= 75 psig 10 COMMAND: imf cdO11427 PURPOSE: Inserts drifting rods if pressure drops near 70 psig before delay times out.
~______ ~ ~
EVENT ACTION: iapiarca <= 75 /I Instrument Air header pressure <= 75 psig 11 COMMAND: imf cdOl1827 PURPOSE: Inserts drifting rods if pressure drops near 70 psig before delay times out.
EVENT ACTION: iapiarca <= 75 // Instrument Air header pressure C = 75 psig 12 COMMAND: imf cd012227 PURPOSE: Inserts drifting rods if pressure drops near 70 psig before delay times out.
EVENT ACTION: iapiarca C= 75 I/ Instrument Air header pressure c= 75 psig 13 COMMAND: imf cd062627 PURPOSE: Inserts drifting rods if pressure drops near 70 psig before delay times out.
L EVENT ACTION: rh:bkr(l) >= 1.0 // A RHK pump running 14 COMMAND:
PURPOSE: Trips the A EDG 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 --- ---
HP04 HPCl system fails to start --- --- NONE --- ---
DGOlC'C' EDG Failure to Start (Auto or Man) --- --- NONE --- ---
DG02B Failure of '6' EDG --- 1 --- NONE --- ---
I
~~~~ ~ ~~
DG02D Failure of 'D' EDG --- --- NONE --- ---
RH08C 'C' RHR Failure to AuteStarVlnject --- --- NONE --- - I-ADO1 Failure of ADS to Actuate --- --- NONE --- ---
AD04H SRV H Tailpipe Temp fails upscale --- --- ET-I --- 100' b NM12C Recirc Flow Summer failure --- --- ET-2 --- 0%
RC09 Steam Line Break in the RClC Room 1:oo 5100 ' ET-3 25% 809,)
AN-A2A5 Cry Wolf Fire Protection Panel Alarm 3:OO --- ET-3 --- ---
~~ ~ ~
IAOlA Trip of 10K107 Service Air Compressor --- --- ET-5 --- ---
IA02 Gradual Loss of Instrument Air --- --- ET-9 --- 60 CD011427 Control Rod Drift In 14-27 2:oo --- ET-9 --- -I -
CD011827 Control Rod Drift In 18-27 2:oo --- ET-9 --- ---
CD012227 Control Rod Drift In 22-27 2:oo --- ET-9 --- ---
CD062627 Control Rod Scram 26-27 2:oo --- ET-9 --- ---
EG12 Loss of Offsite Power --- --- ET-6 --- ---
~~ ~ ~~
RR31A2 Large Break LOCA 3:OO 500 ET-6 0Yo 3%
DG02A Failure of 'A' EDG 00:03 --- ET-I 4 --- ---
REMOTE/FIELD FUNCTION
SUMMARY
I I 1 Initial Description Delay Ramp Trigger Init Val HV06 CVH300 RBVS Fan --- --- ET-4 ---
-4
~
HV05 BVH300 RBVS Fan 1 sec E T-4 --- STC3 HV04 AVH300 RBVS Fan I sec --- ET-4 --- STC3 HV03 CV301 RBVE Fan HV02 BV301 RBVE Fan HVOI AV301 RBVE Fan 3 sec ET-4 ---
I HP08 HPCl Aux Oil Pump Breaker 1 --- 1 --- I ET-7 I --- I TAGGZD I rDG05 'A' EDG Shutdown Relay I 00:05 I --- I ET-8 I --- 1 RESET I
-rDGOl 'A' EDG Lockout Relay I 00:20 I --- I ET-8 I --- I RESt T I ESG-NRC-S4 Page 5 of 29 Rev: 02
Ramp Trigger lnit Val Final i
I 2 I I I -1 ESG-NRC-S4 Page 6 of 29 Rev: 02
Event I Instructor Activity Expected PlantlStudent Response Comments Place 6 RFPT in-service: e CRS directs PO to place B Crew places IB RFPT in RFPT in service IAW OP-SO.AE-0001.
PO opens HV-I769B, REACTOR HPI USED:
FEED PUMP B DlSCH STOP STAR q CHK VLV MOT OPER. PEER CHECK OP BARRIERS q 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 HPI USED:
DECREASE 1 push button on the STAR Pump being placed in-service as PEERCHECKU necessary, to equalize the OP BARRIERS D EMAND signa I s, WHILE MONITORING the following:
a RFPT Discharge Pressure a RFPT DEMAND 3 RFPT FLOW When flow and speed are HPI USED:
approximately equal, PO STAR I3 transfers RFPT B SPEED PEER CHECK q CTRLR to automatic by pressing OP BARRIERS I7 the A pushbutton AND observing A iI I u minat es.
CRS directs raising power to 90% using RE guidance.
ESG-NRC-S4 Page 7 of 29 REW:02
Event I Instructor Activity Expected Plant/Student Response Comments As RE PROVIDE the following 0 RO monitors the following when guidance: changing Recirc Pump speed:
0 SPRl and Enhanced 3 XR-R603A,B,C,D - C51 Stability Guidance are valid (NEUTRON MONITORING) for the remainder of the APRM maneuver 3 B31-FR-RG14 RECIRC LOOP 0 Power has been steady for A(B) FLOW the last hour. = FR-R61IA(B) RECIRC LOOP 0 Target rod line has been A(6) JET PUMP FLOW reached. 3 PDR-R613/FR- FR-R613 0 Raise power to 90% with CORE PLATE DlFF reactor recirculation and PRESS/JET PUMP FLOW hold for thermal limit checks.
0 RO raises Reactor Recirc Pump HPI USED:
speed by intermittently pressing STAR INCREASE pushbutton on SIC- PEERCHECK17 R621A(B) PUMP A(B) SPD OP BARRIERS CONT.
SRV Tailpipe Temperature 0 Crew recognizes SRV FOI 3H high tailpipe temp by:
After the Crew co OHA CI-A3 ADS/SAFETY RELIEF VLV NOT CLOSED Flashing red alarm light on TRR-6 14 0 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.
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 CRS recognize the following Must restore within 30 Tech Spec action applies: days or initiate actions a Accident Monitoring IAW TIS 6.9.2 Instrumentation Table 3.3.7.5-1 Action 80a RECIRC LOOP FLOW Crew monitors Reactor power, SUMMER C FAILURE: pressure, and level and ensure At the discretion o plant conditions are stable.
Examiner, Ensures no scram setpoints have
~ TRIGGER ET-2 (RECI been exceeded.
LOOP FLOW SUMME FAILURE to 0 percent a Crew recognizes RPS 1/2 scram by:
3 OHA C3-A3 REACTOR SCRAM TRIP LOGIC A2 s OHA C5-A1 NEUTRON M0NITOR ING SYSTEM RPS Trip Logic A2 NORMALIRESET status lights extinguished Pilot Scram Valve Solenoid LOGIC A NORMAL status lights for all four groups extinguished.
CRIDS D2127 NEUTRON MONITORING SYSTEM SCRAM Y TRIP 3 CRlDS D2132 REACTOR SCRAM Y TRIP ESG-NRC-S4 Page 9 of 29 Rev: 02
I Event I Instructor Activity Expected Plant/Student Response Comments 0 Crew recognizes A, C, and E APRMs Upscale by:
3 OHA C3-C4 APRM SYS A UPSCALE TRIP/INOP 3 C3-D4 APRM UPSCALE APRMs A,C, and E UPSC TR OR INOP status lights APRM A,C, and E UPSC ALARM status lights
=1 CRIDS D2143 APRM CHANNEL C UPSCALE TRIP YES 3 CRIDS D4306 APRM CH C UPSCALE THERMAL TRIP ALARM 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 0 CRS implements AB.IC-0004:
Condition F 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.
IF directed to place the Flow RO directs I&Cto place the Unit C MODE Switch in the MODE Switch, on the applicable unlabeled position, THEN flow unit, to the UNLABELED CHANGE Malfunction NM12C position between STANDBY and Final value to 100%. ZERO.
ESG-NRC-S4 Page 10 of 29 REK 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: Crew recognizes Seismic Event At the discretion by:
Examiner: 3 OHA C6-C4 SEISMIC MON PLAYtheEa PNL C673 Sound Effect (if available) a 3 CRlDS D3977 SEISMIC medium volume for about TROUBLE ALARM TRBL Response Spectrum Analyzer indications on 1OC650C Loud rumbling noise motion then it stops (if available)
TRIGGER ET-3 (Seismic Crew monitors criticaI parameters to determine if plant is stable.
-IF Crew calls National 0 CRS implements AB.MISC-0001: AB.MISC-0001 action:
Earthquake Center, Condition E provided for reference THEN REPORT a seismic Condition F only. Due to the pace event of 6.0 on Richter scale of the scenario, it is centered 12 miles east of unlikely they will be Wilmington, DE. implemented.
IF Crew
- calls Security, THEN REPORT the Security system is intact.
RO/PO implement AR.ZZ-0011 Attachment C4.
ESG-NRC-S4 Page 11 of 29 Rev 02
Event / Instructor Activity Expected PlantlStudent Response Comments dispatched to 106673, 0 Crew dispatches ABEO to THEN REPORT: 106673.
0 The Event Indicator is 0 Crew recognizes a seismic event WHITE
>0.1g has occurred The tape machines have advanced but are not running The Amber Alarm light on the Seismic Switch Power Supply drawer is lit.
The Amber SMA-3 Event Alarm Light is extinguished.
IF directed to reset 10C673, 0 RO/PO direct ABEO to reset THEN DELETE Malfunction IOC673 IAW SO.SG-0001.
PC07B and re-insert Malf PC07B with trigger ET-6.
RO/PO record Seismic Response Spectrum Analyzer lights on AR.ZZ-001 IAtt. C4-I.
RO/PO reset Seismic Response Spectrum Analyzer IAW SO.SG-0001.
Crew determines a shutdown IAW l0.ZZ-0004 is required.
Crew recognizes a steam line B1-A2 and ISLN INlT break in the RClC room by: status lights will be z OHA B1-A2 RCIC STEAM received if the leak LINE DlFF PRESSURE HI severity reaches 80%
3 OHA A2-A5 FIRE PROT before being isolated.
PANEL 1QC671 (about 5 minutes)
Fire Comp Pt FA016 ROOM A2-A5 Fire Alarm will 41 10 RClC PUMP AND be received two TURBINE ROOM minutes after the leak RClC room temperature starts.
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 ESG-NRC-S4 Page 12 of 29 Re\: 02
i I
Event I Instructor Activity Expected Plantistudent Response Comments 0 Crew announces steam leak in RClC room on plant page.
IF dispatched to
- RClC Room, Crew recognizes failure of RClC Only applicable if THEN REPORT the room is to isolate by: isolation signal filled with steam. HV-F007 valve position received.
HV-F008 valve position RClC room temperature trending up (Rm 41 IO)
PO closes HV-F007 AND HPI USED:
HV-F008 using Control Room STAR I7 keylock switches. PEER CHECK 0 Immediate Operator Action IAW AB .CONT-0002
- Crew closes the RCIC HV-FO07 RECORD RClC Room O R HV-F008 before RClC 41 10 temperature whc n Room temperature reaches HV-F007 F008 arc 250 degE closed.
Temperature:
0 RClC Room temperature reaches 115 degrees, THEN CRS implements EOP-I 03.
0 Crew recognizes abnormal gaseous radioactive release by:
3 OHAC6-C1 RADIATION MONITORlNG ALARM/TRBL RMI 1 9RX580 SPV Effluent alarm SPDS indication 0 CRS implements AB.CONT-004:
Condition A Condition C ESG-NRC-S4 Page 13 of 29 Reb 02
Event I Instructor Activity Expected PlantlStudent Response Comments IF
- dispatched to secure Rx 0 PO places FRVS in service IAW HPI USED:
BIdg Ventilation, SO.GU-0001 Section 5.3. STAR THEN: PEERCHECKCI REFER to SO.GU-0001 FLAGGING 0 Section 5.3 OP BARRIERS 0 TRIGGER ET-4 to secure fans 0 CRS recognize the following With RClC inoperable Tech Specs actions apply: operation may continue a Reactor Core isolation Clg provided HPCl is 3.7.4 operable. Must restore Primary Containment RClC in 14 days or be Isolation Valves in at least HOT 3.6.3 (Only if failure to isolate SHUTDOWN within the is observed) next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor pressure to 5 150 psig in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(Note that a shutdown is already required dut:
to the seismic event)
Crew recognizes loss of 1OK107 The primary purpose crf by: the air malfunctions is OHA A2-B2 COMPRESSED to exercise the AIR PANEL OOCI 88 immediate operator
= OHA A2-A1/A2 INST AIR actions for trip of the HEADER N B PRESS LO inservice service air
= CRIDS D4601 INSTR AIR compressor and SPLY HDR A PRESS LO multiple rods drifting ir.
= CRIDS D4602 INSTR AIR The pace may not allcw SPLY HDR B PRESS LO full implementation of OVLD/PWR FAIL light the abnormal.
Lowering Service and Instrument Air pressures PO places 00K107 in service Immediate Operator IAW AB.ZZ-0001 Attachment 7. Action IAW AB.COMP-0001.
HPI USED:
STAR CI HARD CARD CI PEER CHECK 0 0 CRS implements AB.COMP-001:
Condition A ESG-NRC-S4 Page 14 of 29 Re\: 02
IF dispatched
- to check status Instrument Air Header of RACS demins, Pressure reaches 85 psig, AND the EIAC is running, THEN CRS implements THEN REPORT the RACS AB.COMP-0001:
demins are isolated. =, Condition C 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 z p of 1OK107, Maintenance to investigate trip of THEN REPORT VIBRATION 1OK107.
ALARM and VIBRATION SHUTDOWN alarms were in.
I 9ir Leak: I Crew recognizes air leak by:
OHA AZ-A1/A2 INST AIR The air leak is aut =
inserted when the HEADER N B PRESS LO started 3 OHA A2-B2 COMPRESSED AIR PANEL OOCI 88 ENSURE ET-9 tri 00K107 is manua
= CRlDS D4601 INSTR AIR SPLY HDR A PRESS LO 3 CRIDS D4602 INSTR AIR SPLY HDR B PRESS LO 3 Lowering Service and Instrument Air pressures CRS implements AB.COMP-001:
Condition A IF dispatched
- to check status 0 IF Instrument Air
- Header of RACS demins, Pressure reaches 85 psig, AND the ElAC is running, THEN CRS implements THEN REPORT the RACS AB.COMP-0001:
demins are isolated. = Condition C IF dispatched
- to check status of HV-11416, AND Remote Function IAOI itatus is online, THEN REPORT the HV-11416 is open.
ESG-N RC-S4 Page 15 of 29 Rev 02
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 3 CRIDS C078 ROD DRIFT ALARM ALM
= Lowering reactor power and Main Generator output RO locks the Mode Switch in SHUTDOWN.
- Crew scrams the reactor within RECORD the time two minutes o f rod drifts. between OHA C6-E3 and reactor scrammec!,
TIME:
0 RO performs scram actions IAW HPI USED:
AB.ZZ-0001 Att 1. STAR 0 HARD CARD 0 0 Crew recognizes RPV Level Below 12.5 EOP entry condition by:
3 OHA C5-A4 RPV WATER LEVEL LO 3 OHA A7-D5 RPV LEVEL 3 Various water level indicators 0 CRS implements EOP-101.
0 PO controls RPV water level as directed by CRS IAW AB.ZZ-0001 Att 14.
ESG-NRC-S4 Page 16 of 29 Rev 02
I Event I Instructor Activity Expected Plant/Student Response Comments Afte rshock/LOP/LOCA : 0 Crew recognizes Loss of Offsite 5 minutes after the scram, Power by:
-0 R, =. OHA STA SERVICE at the Lead Examiners TRANSFORMER TROUBLE discretion, for all transformers PLAY the Earthquake =I TRIP indication for all 500 KV Sound Effect (if available) at breakers
=. Flashing TRIP lights for all previously closed bus infeeds.
Numerous OVLDlPWR FAIL lights.
motion then it stops TRIGGER ET-6 (LOP/LOCA) I Crew recognizes failure of the Only A EDG will start.
B/C/D EDGs to start and load by: A EDG will trip when Engine STOP lights the A RHR pump is Output breaker TRIP lights started.
OVLD/PWR lights on associated Channel components RO/PO attempt to start the B U D HPI USED:
EDGs. STAR PEERCHECKO Immediate Operator Action IAW AB.ZZ-O1:;5 CRS implements AB.ZZ-0135.
IF
- dispatched to investigate the Crew dispatches N E 0 and/or failure of BID EDGs to start, Maintenance to investigate THEN REPORT both EDGs failure of B/D EDGs to start.
have Lube Oil Low Pressure Shutdown alarms. There is oil on EDG room floors.
ESG-NRC-S4 Page 17 of 29 R e i 02
I Event I Instructor Activity Expected Plant/Student Response Comments
-IF dispatched to investigate the Crew dispatches NE0 and/or failure of the C EDG to start, Maintenance to investigate THEN REPORT there is a failure of C EDG to start.
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.
(AR.KJ-0005 Att. 37A)
-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)
IF dispatched
- to determine 0 Crew recognizes HPCI oil status of HPCI, problem by:
THEN REPORT =1 OHA BI-A4 HPCI TURBINE 0 HPCl is idle TRIP 0 HPCl Aux oil pump is 3 OHA BI-E5 HPCI PUMP running. DISCH FLOW LO
=3 HPCl Trip Throttle and 0 HV-F001 is closed Governor valves closed IF directed to open the breaker w/Aux Oil pump running and for the HPCl Aux Oil pump, TURB TRIP SOLENOID (72-251042) ENERGZ light not lit
=3 CRIDS D5435 HPCI BRG THEN TRIGGER ET-7.
OIL LO PWHVFOOI OPN IF directed
- to open HV-F001 by hand, REPORT HV-F001 will not move 0 CRS directs injecting with A Only available injection SLC pump. source.
0 RO/PO start the A SLC pump. 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 Given the lowering RFV Temp Above 95°F EOP entry water level, and A condition by: RHR being the only 3 OHA C8-F1 SUPPR POOL available RHR pump, TEMP HIGH the Crew may not plac,e Flashing 95 degree status A RHR in Suppression light on 1OC65OC Pool cooling at this RMI 1 9AX8331834 alarm time.
Various Suppression Pool temperature indicators 0 Crew recognizes Supp Pool Given the LOP and th.3 Level Above 78.5 In EOP entry unavailability of HPCl condition by: and RCIC, there is 2 OHA B1-C3 SUPPRESSION nothing the Crew can POOL LEVEL HIILO do to lower
= Various Suppression Pool Suppression Pool water level indicators 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 N E 0 and/or trip of the A EDG, Maintenance to investigate trips THEN REPORT you heard the of the A EDG.
EDG slow down, then speed up and trip. Alarm on local panel is ENGINE OVERSPEED.
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
-1 29, THEN CRS directs inhibiting ADS.
0 RO/PO inhibit ADS IAW HPI USED:
AB.ZZ-0001 Att. 13. STAR D HARD CARD 0 PEER CHECK 0 FLAGGING 0 0 WHEN RPV water level reaches
-ZOO, THEN CRS directs opening five ADS SRVs.
0 RO/PO open five ADS SRVs HPI USED:
IAW AB.ZZ-0001 Att. 13. STAR 0 HARD CARD PEER CHECK 0 NHEN at least five SRVs are
- Crew opens at least five SRWs open, before reactor water level has THEN DELETE Malfunction been below -200 for two DGOIC to restore the C EDG minutes.
to service AND REPORT the C EDG has been successfully started.
SUPPORT any requests to 0 Crew recognizes start of the C place ECCS pumps in PTL EDG by:
using Remote Functions: Diesel engine START light CSOSC for C Core Spray Generator breaker CLOSE RH23C for C RHR light OVLD/PWR FAIL lights extinguished on associated channel loads RO/PO starts the C RHR pump, The auto-start of the T i opens the HV-FOI7CI and RHR pump and restores RPV water level to auto-opening of the above -1 85 IAW AB.=-0001 FOI 7C are failed.
Att. 4.
ESG-NRC-S4 Page 20 of 29 Re\. 02
AFTER the Crew restores RPV
- WHEN the C EDG is restored, water level to above -1 85, THEN the Crew injects with the THEN REPORT you are ready C RHR pump and restores to restore the A EDG to and maintains RPV water level service. The governor oil level above -185.
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 0 Crew recognizes start of the A The restoration of the EDG to service, AND after level EDG by: AEDG makes the A has been restored with C Diesel engine START light Core Spray Loop EDG, Generator breaker CLOSE available for RPV watc r rHEN TRIGGER ET-8 AND light level control.
REPORT the A EDG has =, OVLDlPWR FAIL lights been successfully restarted. extinguished on associated channel loads CRS directs restoring PClG to The AK202 PClG the SRVs. compressor became available when the C EDG was restored.
RO/PO restores PClG to the HPI USED:
SRVS IAW AB.ZZ-0001 Att. 9. STAR HARD CARD CJ PEER CHECK FLAGGING CRS directs placing the A RHR pump in Drywell Spray.
0 RO/PO places A RHR pump in HPI USED:
The scenario should b Drywell Spray IAW AB.ZZ-0001 STAR 0 terminated at the discretion o Att. 2. HARD CARD 17 the Lead Examiner wh PEER CHECK FLAGGING
~~
ESG-NRC-S4 Page 21 of 29 Rev 02
A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid 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. HU-AA-101 PerformanceTools and Verification Practices I. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel J. OP-AA-101-1 11-1004 Operations Standards K. OP-AA-101-1 12-1002 On-Line Risk Assessment L. OP-AA-106-101-1001Event Response Guidelines M. OP-HC-108-106-1001Equipment Operational Control N. OP-AA-108-114 Post Transient Review
- 0. OP-HC-108-115-1001Operability Assessment and Equipment Control Program P. HC.OP-AB.ZZ-0001Transient Plant Conditions Q. HC.OP-AB.CONT-0002Primary Containment R. HC.OP-AB.CONT-0004Radioactive Gaseous Release S. HC.OP-AB.COMP-0001Instrument andlor Service Air T. HC.OP-AB.MISC-0001Acts of Nature U. HC.OP-AB.RPV-0006Safety/Relief Valve V. HC.OP-AB.ZZ-0135Station BlackoutlLoss of Offsite Power/Diesel Generator Malfunction W. HC.OP-AB.ZZ-000Reactor Scram X. HC.OP-EO.ZZ-0101RPV Control Y. HC.OP-EO.ZZ-0102Primary Containment Control Z. HC.OP-EO.ZZ-0103Reactor Building Control AA. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization BB. HC.OP-EO.ZZ-0206 RPV Flooding 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 I O 2 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; z r d (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 be restorec to service.
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
_ _ Y/N EVENT X Loss Of Offsite Power/SBO Internal Flooding X LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:
Turbine Trip Loss of ssw Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSlV Closure Inadvertent SRV Opening X Manual Scram COMPONENTfrRAINISYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Y/N KEY EQUIPMENT Hard Torus Vent s LC X HPCl CRD X 1E 4.16KV Bus 1E 125VDC SACS HdPump X EDG KEYSYSTEMS 120VAC 481/482 Inverter X 500KV AC Power N B RHR S RVs X RClC CondensatelFeedwater SSW Pump PClG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION X Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment X Emergency Depressurize RPV W/O High Pressure Injection X Initiating LP ECCS with No High Pressure Injection Available X 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 515%/ 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 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) a The event termination point 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 evaluation results commensuratewith 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-S4 Page 27 of 29 Rev.. 02
EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cont)
Note: The following criteria list scenario traits that are numerical in nature.
ESG: NRC-S4 SELF-CHECK 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 (7-I 9. Technical Specifications are exercised during the test 22 Comments:
ESG-NRC-S4 Page 28 of 29 Rev : 02
EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cont)
Crew Validation Rev: 01 Date Validated: 11/21/2009 Validation Comments Disposition Need RFPT Startup step on Turnover Sheet. Added to TO sheet. Return B RFPT to service IAW HC.OP-SO-AE-0001 Section 5.7.
Add guidance for placing Flow unit Mode Switch in unlabeled position. Added driver guidance for I&C action.
Add status of SMA-3 Event Alarm Light to ABEO report. Added that the light is extinguished.
Crew Validation Rev: Date Validated:
ESG-NRC-S4 Page 29 of 29 Rev.: 02
TRAINING 1JSE ONLY ONLINE RISK: GREEN 11 WORK WEEK CHANNEL: B 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 Equipment: -
None Reactivity:
0 Raise power to 90% using Reactor Recirc at (1 5%/ hr and hold for RE thermal limit checks.
SY s YEM : C ~ r i f r dArea Veniifati2i-I System TASK: Manually Isolate the Control Room Emergency Filter System TASK NUMBER: 48800601 01 JPM NUMBER: 305H-JPM.GKOO1 REV#: 05 SAP BET: NOH05JPGKOl E ALTERNATE PATH: I ]
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 ALTERNATE PATH: KIA NUMBER: 290003 A4.01 -
IMPORTANCE FACTOR: 3.2 3.2 APPLICABILITY: RO SRC?
EVALUATION SETTING/METHOD: Simulator/Petform
REFERENCES:
HC.OP-SO.GK-0001 Rev I 3 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: O S A T UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
Page 2 of 15
SYSTEW,: Contro i Are a \/e nr i Ia 'ii o i l Sys 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 *.
~
i GKOOI OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE.
1 SYSTEM: Control Area Ventilation System TASK: Manually Isolate the Control Room Emergency Filter System STEP ELEMENT NO.
CUE PROVIQE the operator the initiating cue. Operator repeats back initiating cue.
CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INiTIATING CUE: NIA START TIME:
~
I I I Operator obtains the correct Operator obtains procedure I / I procedure. HC.OP-SO.GK-000j. I -~
1
~
Operator reviews precautions and Operator reviews precautions and limitations. limitations. l l CUE if excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step Operator determines correct beginning of the procedure. 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 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.
Operator reviews Prerequisites.
I !
l .
"I.
l CUE I I f 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, Examiner Note: Section 5.2.3 may be RE-ESTABLISH normal Control used in error. The Steps are identical Room Ventilation by performing the to 5.3.5.
following steps: Operator dispatches NE0 to local panel A. DISPATCH an operator to Local 1EC485.
Panel 1EC485.
CUE Role-play as NE0 sent to lE-C48%.
Page 5 of 15
- - 1 I
GKOOI OPERATOR TRAINING PROGRAM NAME: ..
JOB PERFORMANCE MEASURE DATE. ~-
SYSTEM: Cmtrol Area Ventilation System TASK. Manual!y Isolate the Control Room Emergency Filter System ELEMENT I
- 9. PRESS HD-9598A NORMAL AND HD-9598B NORMAL PB. SPLYIEXH HD9598A NORMAL pushbutton.
Operator presses CONTROL AREA SPLY/EXH HD9598B NORMAL pushbutton. _ _ _ ~
C. STOP A(B) Control Room
- , Operator presses the A CREF Fan Emergency Filter Unit A(B)V400 STOP pushbutton.
by pressing the STOP PB. I- ~ -~
I illuminates and the AV400 START light extinguishes. 1 Page 6 of 15
GKOO 1 OPERATOR TRAINING PROGRAM JOBPERFORMANCEMEASURE SYSTEM: Control Area Ventilation System TASK: Manually Isolate the Control Room Emergency Filter System ELEMENT ! (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD D. E in RECIRC MODE, PLACE CONTROL ROOM EMER FILTER Operator determines that the system is UNIT A AND B OP MODE Switch in RECIRC MODE.
in OA MODE AND INITIAL Attachment I.
Operator depresses the CONTROL ROOM EMER FILTER UNIT A OP MODE switch O.A. MODE push button.
CONTROL ROOM EMER FILTER UNIT B OP MODE switch O.A. MODE push button and initials Attachment 1.
i Page 7 of 15
6 ."F._f?'>(] <
7, EL? _ . I GK001 OPERATOR TRAINING PROGRAM NAME. __________~
JOB PERFORMANCE MEASURE DATE. -
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 Operator directs placing one CAE fan in RUN and initials Attachment 1.
THEN to the RUN position 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 HS-9599B to STOP fan in AUTO and initials Attachment 1.
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 Operator directs inspecting drain doors. REPORT a n y water openings via port holes in doors for signs of water accumulation or flow.
Role-play as N E 0 sent to inspect drain openings via port holes in doors, and to report any water 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".
Page 9 of 15
JPM Number: GMOOI T A S K : Manually Isoia.2 the Control Room Emergency Filter System TASK NUMBER: 4880060101 QUESTION: _ _ . ~ --
RESPONSE: --
RESULT: §AT Ti UNSAT i l
QUESTION: --
RESPONSE: ____
RESULT: SAT UNSAT Page I O of 15 "j4
1 1,severe Marsh fire had beer1 mserved near tne siie I - G Cfire
~ , departments respmdec: to the fl re 2 Smoke was observed to be entering the Main Control R o x r from the Control Room Ventilation System.
- 3. 'A' CREF was placed in service in accordance with H~V.O?-AB.ML/AC-O~O~, Control 2oDm 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.
I. LNITPAL CONDITIONS:
1.c. -
INITIALIZE the simulator to 100% power, RlOL A'Control Room Ventilation train IS in service a d the 'B'Train
-1 ENSURE the __-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)
Initial Description ENSURE simulator IS reset -
I T
I lnitiai ET # Description -
EVENT ACTION:
COMMAND:
PURPOSE: -
EVENT ACTION:
COMMAND:
PURPOSE: -
MALFUNCTION
SUMMARY
I 1 initial Description __-- Delay 1 lnitial 1 Descrmtion Delay I Ramp Trigger lnit Val Final 'a1 1 1 HVD9 CAE Fan AV402 DlREC ED
! HVIO CAE Fan BV402 1/0OVERRIDE
SUMMARY
I Delay ~ Ramp I I
Trigger 1 Init Val I -1 Final Jal 1 Page 13 of I 5
_' 1i
Rev # Date Description Va I idati o 7
___.. _____._~ Reqlairec _ ?_
114 611 5/07 Sevision 11 of HC.OP-SO.GK-0001direction to initial N 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 performa nce data .
O5 I 8/26/08 Jpdated reference procedurs revisions only. No changes to sperator actions. No validation required.
s PATION : !-lope Creek SYSTEM: Core Spray TASK: Manually Start the Core Spray System TASK NUMBER: 20900301 01 JPM NUMBER: 305H-JPM.BE005 REV#: 06 SAP BET: NOHOSJPBEO5E ALTERNATE PATH:
APPLICABILITY:
EO n RO wl STA -1 SRO Fl DEVELOPED BY: -
Archie E. Faulkner DATE: 9/4/08 -
Instructor REVIEWED BY: DATE: 9- / Z-Og 0perations Representative APPROVED BY: CyjJ 1 DATE:
Training Department
TQ-AA-106-030 ,I STATION: Hope Creek JPM NUMBER: BE005 REV: 06 SYSTEM: Core Spray TASK NUMBER: 2090030101 TASK: Manually Start the Core Qpray System ALTERNATE PATH: ml K/A NUMBER: 209001 A4.01 - -
IMPORTANCE FACTOR: 3.8 3.7 APPLICABILITY: RO SRO EVALUAT10N SETTIN GIMETH0D: Si muIato r/Pe rform
REFERENCES:
HC.OP-AB.ZZ-0001 Attachment 5 Rev. 16 TOOLS, EQUIPMENT AND PROCEDURES: None EST1MATED COMPLET10N TIME: 13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes JPM PERFORMED BY: GRADE: U S A T UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:
EVALUATORS SIGNATURE: -- DATE:
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 LOCA.
- 2. A and C Emergency Diesel Generators have failed to start.
- 3. HPCl h a s just tripped
- 4. Reactor pressure is approximately 500 psig and lowering.
- 5. 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. T h e simulator is in FREEZE until you are ready to begin.
Page 3 of 12
TC 106-8383 JPM: BE005 OPERATOR TRAINING PROGRAM NAME:
Rev: 06 JOB PERFORMANCE MEASURE DATE: ___
SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP ELEMENT NO.
CUE PROVIDE the operator the initiating Operator repeats back initiating cue.
cue.
CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:
START TIME:
Operator obtainsllocates procedure Operator obtains the correct procedure.
HC.OP-AB.ZZ-0001, Attachment 5.
k
__ - ~-
IF required, ARM THEN PRESS B Operator determines that operation of MAN INlT PBs. the MAN lNlT PBs is not necessary based on overhead annunciators B3-AllA21A31A4, CORE SPRAY PUMP AUTO START are in alarm. -
2.0 ENSURE B Core Spray Pump is Operator observes the B Core Spray RUNNlNG. Pump is not running. _____ _ _ - - ~
Operator depresses the BP206 START push button. /*I I Operator observes that B Core Spray Pump is running. -
3.0 IF Required, ARM
- THEN PRESS D Operator determines that operation of MAN INlT PBs. the MAN INlT PBs is not necessary based on overhead annunciators B3-A1/AZ/AYA4, CORE SPRAY PUMP AUTO START are in alarm.
Page 4 of 12
7.0 WHEN flow is > 775 gpm, ENSURE Operator observes Core Spray System HV-F031B is CLOSED. B flow on FI-RGOIB to be >775 gprn. _____~
Operator observes HV-F031B is closed. -I_
JPM: BE005 OPERATOR TRAINING PROGRAM Rev: 06 JOBPERFORMANCEMEASURE DATE: ~-
SYSTEM: Core Spray TASK: Manually Start the Core Spray .
System
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.
STANDARD # SIU evaluation) - _ I _
CUE 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:
Page 6 of I 2
TQ-LA-7 OG-t:. 0 3 J0E ?E ?r 0I?Id k I\JCE blEA S UF:E 0P ER A T 3R TR k 1 NI NG PR 0GRAM 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 1 1 QUESTION:
RESPONSE
RESULT: SAT UNSAT Page 7 of 12
J 0E ?E RF0R M A I4C E MEA SURE I NI SIAL C0N D I TI014S :
- 1. The plant has experienced a Ixs of all ofi'site power coincident with ~t small break LOCA.
- 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.
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 JOB PERFOP~I~IAI\JZE iulEASilRE SIlvl ULATOR SETUP I I\JS:F: JCTI 014S (OFTIONAL)
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.,RM1Iset points, procedures, bezel covers)
I hbal Description COMPLETE Simulator Ready-for-TrainingiExnmination Checklist.
-i
- EVI NT TRIGGERS:
If Initial ET # Description COMMAND:
PURPOSE:
EVENT ACTION:
COMMAND, PURPOSE:
Page 9 of 12
MALFUNCTION
SUMMARY
(i!7rtiai>escrintion ' Ramp Trigger lnit Val I Final' I
EG12 Loss of all Offsite Power _-- None ,
DGO2A A Diesel Generator Failure To Start ~
1, _-- None DG02C C Diesel Generator Failure To S t a i --- --- None Recirc Loop small leak --_ --- None RR31A2 Recirc Loop large break MSOI Steam line break in the drywell -3:I I CSD3B Core Spray HV-FOO5B fails to auto open None None
--_ 3 CS04B Core Spray pump fails to auto start
--- None ---
CSO4D Core Spray Pump Fails To Auto Start 1 Inibal 1 Description lnit Val 1 Fins1
- 4 I/O OVERRIDE
SUMMARY
7- -
Page 10 of 12
JPIV N3MBER: BE005 Description Validatio rl Required_ -7 06 9/4/2008 This revision converts to HC LOR format, documents Y 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.
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Main Steam TASK: Open The MSlVs With The Reactor Pressurized (>200 PSQ)
TASK NUMBER: 2390020101 JPM NUMBER: 305H-JPM.AB006 REV#: 00 SAP BET: NOH05JPABOGE ALTERNATEPATH: I I DEVELOPED BY: Archie E. Faulkner DATE: 12/6/08 gAvV Instructor REVIEWED BY: DATE: !./iiiy perati ns M r e s e n t a t i v e APPROVED BY:
Training Department DATE: A-
/ L // fi
TQ-AA-I 06-030 STATION: Hope Creek JPM NUMBER: AB006 REV: 00 SYSTEM: Main Steam TASK NUMBER: 2390020101 TASK: Open The MS Vs With The Reactor Pressurized (>200 psig)
ALTERNATE PATH: KIA NUMBER: 239001 A4.01 - -
IMPORTANCE FACTOR: 4.2 4.0 Eo u APPLICABILITY:
RO[ X I S T A m S R O F ]
RO SRO 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: O S A T UUNSl ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:
EVALUATORS 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.
- 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 JPM: AB006 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Main Steam ELEMENT Operator repeats back initiating cue.
OPERATOR REPEATS BACK INITIATING CUE:
Page 4 of 16
1 \. .+-I 06-0303 JPM: AB006 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Main Steam
(*Denotes a Critical Step)
- COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. ELEMENT # evaluation)
STANDARD SIU Operator observes HV-F071 green close light illuminates and red open light extinguishes.
l l I 5.1.10.
HV-F033 DRN HDR OPR DRN VLV Operator presses HV-F033 CLOSE PB.
rves HV-F033 green tes and red open
, 1-5.1.11.
A SELECT I Pressure Controll I Operator uses the DEHC HMI touchscreen display to select then (PressureControll
, 1(
5.1 .I
- 1. SELECT Throttle Pressure Set -
B (Setpoinij Operator selects Throttle Pressure AND ENTER a pressure setpoint Set - F t J above reactor pressure.
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
1 \. e4-106-0303 JPM: AB006 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD ## s/u evaluation)
- 5.1 .I2 LINE DRAIN HDR ISLN OUTBOARD Operator presses HV-FO19 OPEN PB.
VALVE//.
Operator observes HV-FO19 red open light illuminates and green close light extinguishes.
3 5.1 .I OPEN HV-F016 //CNTMT INBD STM LINE DRAIN HDR ISLN INBOARD VALVEII.
Operator presses HV-FO16 OPEN PB.
- II Operator observes HV-FO16 red open light illuminates and green close light extinguishes.
I 5.1.14 I THROTTLE OPEN HV-F020 MAIN I
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.
Page 6 of 16
7 4-1 06-0303 JPM: AB006 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Main Steam TASK: Open The MSlVs With The Reactor Pressurized (>20O psig)
(*Denotes a Critical Step)
ELEMENT (#Denotes a Sequential Step) (Required for UNSAT STANDARD evaluation) 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.
5.1 .I5. HV-F022A INBD MSlV A Operator turns handswitch for HV-A F022A INBD MSIV A to OPEN position.-
Operator observes HV-F022A INBD MSlV A red open light illuminates and green closed light extinguishes.
I 5.lt;15. I HV-F022B INBD MSIV B Operator turns handswitch for HV-F022B INBD MSlV B to OPEN position.
Operator observes HV-F022B INBD MSIV B red open light illuminates and green closed light extinguishes.
i 5.1.15. HV-F022C INBD MSlV C 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.
Page 7 of 16
1 ~ .4-106-0303 JPM: AB006 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM:
TASK:
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # SIU evaluation) 5.1.15.
D HV-F022D INBD MSlV D Operator turns handswitch for HV-F022D INBD MSlV D to OPEN position. I*( I CUE 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 5.1.16 5.1.16.
A Operator presses HV-F020 CLOSE PB.
Operator observes HV-F020 green close light illuminates and red open 5.1.16.
B DRAIN HDR ISLN OUTBOARD Operator presses HV-FO19 CLOSE PB.
VA LVEll.
Page 8 of 16
1 ._4-106-0303 JPM: AB006 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 DATE:
SYSTEM:
TASK:
7 (*Denotes a Critical Step)
- COMMENTS STEP I ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. '
STANDARD ## SIU evaIuation)
~
Operator observes HV-FO19 green close light illuminates and red open light extinguishes.
5.1.16. HV-F016 //CNTMT INBD STM LINE C DRAIN HDR ISLN INBOARD Operator presses HV-F016 CLOSE PB.
VALVE//.
Operator observes HV-FO16 green close light illuminates and red open light extinguishes.
5.1.17 CONTROL reactor pressure IAW HC.OP-EO.ZZ-0101A(Q).
CUE 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:
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.
- 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 JOBPERFORMANCEMEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
- 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-0001Attachment 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., RMI 1 set points, procedures, bezel covers)
I Initial Description COMPLETE Simulator Ready-for-Training/ExaminationChecklist. i
-I
~ ~ - ~ ~
ENSURE copies of HC.OP-EO.ZZ-0301 are available and marked up to and including step 5.1.9.D. for 3re-briefing JPM.
ENSURE an extra instructor is available to control RPV level using HPCl and acknowlege unrelated a1 drms.
Approx 90 seconds after coming out of freeze, reduce HPCl AUTO flow setpoint to 1200 gpm.
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
TQ-AA-I 06-0 303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) lnitial Description Delay Ramp Trigger Init Val Fina Val RP06 Half Core ATWS - Left Side Isec. --- None --- __
EGII Main Generator Trip --- --- ET-1 --- __
TCOI-10 All TBV failed closed. --- --- None --- -. .
SLOIA SBLC Injection pump AP208 failure SLOIB SBLC Injection Pump BP208 failure REMOTE/FIELD FUNCTlON
SUMMARY
I I I I 1 Mia/ Description EP02 EOP-311 Bypass PClG (-129") isolation EP05 EOP-319 LOCA Level 2 interlock EP35 EOP-322 HV-FOO6 HPCl to CS Delay I
Ramp Trigger None None None lnit Val
-4 Fin2 Val BY F ASS EM; RG F-1 IL EPOI EOP-301 Bypass MSlV (-129") isolation --- --- None ---
MS04 AB HV-F020 --- --- None --- U N T 4GG MS05 AB HV-F021 --- --- None --- UNT 4GG E3 110 OVERRIDE
SUMMARY
I I I I I I 1 - 1 Initial Description Delay Ramp Trigger lnit Val 3838 A HV-F022D CLOSE SWITCH --- --_ None ---
I I3DS31 BHV-F022DCLOSED-INBD MSIVD I --- I --- 1 None 1 --- 1 CI N 1 I
1 I
3DS31 A HV-F022D OPEN-INBD MSlV D I
I None --- 1 CZF 1
Page 14 of 15
I TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AB006 Date Description Requirec?
11/10/2008 New JPM.
12/5/2008 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.
LQ;"%
a1 1qoN: Hope Creek sY sTEPA : 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
- YS TEM
- 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 LICAB1L I N : RO SRO -
f VA LUAT10N S ETTlNGIMETH0D : Si mu Iato r/ Perfo rm ZEFERENCES: HC .OP-AB.HVAC-0002 Rev 5 HC.OP-IO.ZZ-0008 Rev 28 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMP LET10N TIM E: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes JPM PERFORMED BY: GRADE: U S A T [7UNSA" ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF UNSATISFACTORY:
EVALUATOR'S SIGNATURE: -___ DATE: __
Page 2 of 14
sY STE1\1!: Residual Heat Removal TASK: 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.
7 . RClC has been initiated IAW HC.OP-AB.HVAC-0002 AND Section 5.2 of 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 BRHR.
Page 3 of 14
JPM: BC009 OPERATOR TRAINING PROGRAM NAME: ____.
Rev: 09 JOB PERFORMANCE MEASURE DATE. ___
SYSTEM: Residual Heat Removal TASK: Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP)
ELEMENT PROVIDE the operator the initiating cue. Operator repeats back initiating cue.
I !
ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:
START TIME:
Operator obtains the correct Operator obtains procedure I procedure. HC .OP- I0.ZZ-0008. I
- ~
i Operator reviews precautions and Operator reviews precautions and limitations. limitations.
If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.8.1.
Page 4 of 14
TQ, 186-0303 JPM: BC009 OPERATOR TRAINING PROGRAM NAME:
Rev: 09 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Residual Heat Removai TASK: Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) 1 STEP 1 ELEMENT NO. ~
NOTE 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 N/A 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.
5.8.1 IF necessary, THEN PLACE the B RHR loop in the Suppression Pool Cooling mode as Operator presses AND holds the fo IIOWs [C D-987X , C D-370XI HV2512B INCR OPEN pushbutton until A. ENSURE EG-HV-2512B RHR the green CLOSE DECR light HX SACS RTN ISLN MOV is extinguishes.
OPEN. PB must be held depressed to open.
B. ENSURE HV-F004B RHRPMP Operator observes the red HVF004B B SUPP POOL SUCT MOV is OPEN indicator is illuminated and OPEN. green CLSD indicator is extinguished.
C. ENSURE HV-F007B RHRPMP Operator observes the red HVFOO7B B MIN FLOW MOV is OPEN. OPEN indicator is illuminated and green CLSD indicator is extinguished.
Page 5 of 14
TQ 106-0303 JPM: BC009 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
Rev: 09 SYSTEM: Residual Heat Removal TASK:
D. START BP202 RHR PUMP. Operator presses the BP202 START pushbutton. # ____
~~
The following two steps should be performed concurrently.
E. THROTTLE OPEN HV-F024B RHR LOOP !3 TEST RET MOV pushbutton whiie observing Fi-4435.
UNTIL Fl-4435 RHR HEAT When Fl-4435 indicates = 10,000 gpm, EXCHANGER FLOW indicates the operator releases the INCR Pb.
= 10,000 gpm.
Operator observes the red HVF024B OPEN indicator illuminates. I I I F. WHEN Fl-4435 RHRHEAT When Fl-4435 indicates > 1400 gprn, EXCHANGER FLOW indicates the Operator presses the HVFOO7B
> 1400 gpm, CLOSE pushbutton and observes the THEN CLOSE HV-F007B RHR green CLSD indicator illuminates and PMP B MIN FLOW MOV. the red OPEN indicator extinguishes. - __ - __-
Page 6 of 14
TQ 106-0383 JPM: BC009 OPERATOR TRAINING PROGRAM NAME: -~
Rev: 09 JOBPERFORMANCEMEASURE DATE: -_
SYSTEM: Residual Heat Removal TASK: Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) ._-_--
STEP ELEMENT NO.
G. ENSURE HV-F047B RHRHX Operator observes the HVF0475 and INLET VALVE HVF003B red OPEN indicators are AND HV-F003B B RHR HX illuminated and green CLSD indicators are extinguished.
OUTLET MOV are OPEN AND CLOSE HV-F048B RHR HX B SHELL SIDE BYPASS VLV.
Operator presses and holds the HVF048B DECR Pb until the green CLSD indicator illuminates AND the red 0PEN indicator exting uishe s .
H. THWQTTLE HV-F024B RHR Operator presses HVF024B INCR LOOP B TEST RET MOV AS andlor DECR pushbuttons as necessary to re-establish loop flow necessary until Fl-4435 flow indicates of approx. 10,000 gpm on Fl-4435. 9,000 - I1,000 gpm.
I. OBSERVE TR-3647J( M)- Operator observes Suppression SUPPRESSION CHAMBER Chamber Water Temperature on WATER TEMP. 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.
I I REPEAT BACK any message from the 1 lj l operator on the status of the JPM, and then state "This JPM is complete".
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 i I UNSAT Page 9 of 14
1 . The control room has b e e n abandoned d u e to d e n s e s m o k e .
- 2. HC. 9P-AB. HVAC-0002, Control Room Environmeni, has b e e n implemented.
3 . The Reactor h a s been s c r a m m e d , all rods a r e full In.
- 4. The Turbine is tripped.
- 5. The MSlVs are closed.
- 6. Control of the plant h a s b e e n established at the RSP IAW HC.OP-AB.HVAC-00Q2AND Sectiori 5.1 of HC.OP-IO.ZZ-0008, Shutdown from Outside Control room.
7 . RClC h a s b e e n 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 t h e RSP.
You a r e responsible ONLY for B RHR.
Page 10 of 14
- 1. INITIAL COIWITI INITIALIZE the simulator to 100% power MOL 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 u p 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-0008up to the point of placing BRHR in service.
JOGGLE Control Room Horns to OFF.
ENSURE RSP Chart Recorders are ON.
ENSURE simulator reset.
EVENT TRIGGERS:
initial ET # Description EVENT ACTION.
1 COMMAND PURPOSE.
_ _ _ _ _ _ _ _ _ ~
EVENT ACTION:
2 COMMAND.
PURPOSE Page 11 of 14
HPOI HPCl Auto initiation Failure Dy;" 1 Rarmp ~ Trigger NONE 1
I lni;-;al I Fin;! \/a1 I I I II
_____ -I REMOTEFIELD FUNCTlON S UMMARY:
Delay Ramp Trigger I/O OVERRIDE
SUMMARY
1 Ramp Trigger NONE 1 lnit Val
-4 Final Jal Page 12 af 14
J 3E PE2 F3 RVIAN CE MEAS U F:E aEMs EON i4ISTO RY JPM NUMBER: EC039 Rev b: Date Description Val idat ion Required?--
, i 08 09 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.
JOB PERFORMANCE MEASURE STAT10N: Hope Creek SYSTEM: Primary Containment TASK: Respond To A Containment Isolation TASK NUMBER: 4000760401 JPM NUMBER: 305H-JPM.SM002 REV#: 00 SAP BET: NOH05JPSM02E ALTERNATE PATH:
APPLICABILITY:
DEVELOPED BY: Archie E. Faulkner DATE: 12/5/08 InstructQlr REVIEWED BY: flNfl- DATE: [I,/ I / / -
Operations epresentative APPROVED BY: DATE: &}I , / D e Y
Training Department
S TAT10N : 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 - -
IMPORTANCE FACTOR: 3.5 3.5_ _
APPLICABILITY: RO SRO E O I ] ROIFl S T A L S R O R EVALUATION SETTINGIMETHOD: Simulator/Perform
REFERENCES:
HC.OP-AB-CONT-0002 Rev. 7 HC.OP-SO.SM-0001Rev. 17 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 9 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: Minutes JPM PERFORMED BY: GRADE: U S A T UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: Minutes REASON, IF UNSATISFACTORY:
EVALUATORS SIGNATURE: -- DATE:
Page 2 of 16
I TQ-AA-106-0303 NAME:
DATE:
SYSTEM: Primary Containment TASK: Respond To A Containment Isolation TASK NUMBER: 4000760401 INITIAL CONDITIONS:
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 JPM: SM002 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Primary Containment TASK: Respond To A Containment Isolation I
I
(*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.
STEP CUE 1 ~~~~
cue.
~ ~
PROVIDE the operator the initiating STANDARD Operator repeats back initiating cue.
I 1 SIU evaluation)
CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:
START TIME:
Operator obtains procedure Operator obtains the correct procedure.
HC.OP-AB.CONT-0002 or Attachment 1 and 2 Hardcard.
Operator determines beginning step Operator determines correct beginning of the procedure. step to be Attachment 1.
OBSERVE the Valves listed in Attachment 1 have closed under the
-38" Automatic Isolation Signal.
~~
0 PClG MINOR Operator verifies that ALL of the listed valves/equipment in this group have KL-HV-5155, 5154, 5156A, 51568, responded correctly to the initiating SE-HV-5161 event.
TIPS Operator verifies that ALL of the listed valveslequipment in this group have SE-SVJ004Al-5 responded correctly to the initiating event.
Page 4 of 16
TL. .-I 06-0303 JPM: SM002 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Primary Containment TASK: Respond To A Containment Isolation
(*Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO. STANDARD evaluation)
Twcu Operator verifies that ALL of the listed EE-HV-4652,4679,4680,4681 valves/equipment in this group have responded correctly to the initiating event.
~
0 DWSUMPS Operator observes the HB-HV-FO19 DRYWELL EQPT DRAIN SUMP AT267 HB-HV-FO19, F020, F003, F004 ISLN VLV has failed to isolate and informs the CRS.
CUE 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 Operator PRESSES CLOSE PB for HB-HV-FOl9 DRYWELL EQPT DRAIN Primary Containment Isolation SUMP AT267 ISLN VLV.
Valve FAILS to automatically ISOLATE. PERFORM EITHER of the following:
0 CLOSE a redundant isolation valve 0 CLOSE the valve manually.
Page 5 of 16
TL .-106-0303 JPM: SM002 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Primary Containment TASK. Respond To A Containment Isolation
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD -
- SIU evaluation)
Operator observes the HB-HV-FO19 DRYWELL EQPT DRAIN SUMP AT267 ISLN VLV red OPEN light extinguishes and green CLSD light illuminates.
Immediate Operator Action Operator observes the HB-HV-F020 DRYWELL EQPT DRAIN SUMP AT267 Primary Containment Isolation ISLN VLV has failed to isolate and Valve FAILS to automatically informs the CRS.
ISOLATE. PERFORM EITHER of the following:
0 CLOSE a redundant isolation valve 0 CLOSE the valve manually. -
Operator PRESSES CLOSE PB for HB-
Operator observes the HB-HV-F020 DRYWELL EQPT DRAIN SUMP AT267 ISLN VLV red OPEN light extinguishes and green CLSD light illuminates.
~
HB-HV-F003 DRYWELL FLOOR Operator observes the HB-HV-F003 DRAIN SUMP BT267 ISLN VLV DRYWELL FLOOR DRAIN SUMP BT267 ISLN VLV has closed.
HB-HV-F004 DRYWELL FLOOR Operator observes the HB-HV-F004 DRAIN SUMP BT267 ISLN VLV DRYWELL FLOOR DRAIN SUMP BT267 ISLN VLV has closed.
Page 6 of 16
TL .-106-0303 OPERATOR TRAINING PROGRAM NAME:
JPM: SM002 JOB PERFORMANCE MEASURE DATE:
Rev: 00 SYSTEM: Primary Containment TASK: Respond To A Containment Isolation
(*Denotes a Critical Step) COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD SIU evaluation) 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 Operator verifies that ALL of the listed valveslequipment in this group have SK-HV-5018,4953,4957,4981, responded correctly to the initiating event.
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 Page 7 of 16
TL .-I 06-0303 JPM: SM002 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Primary Containment TASK: Respond To A Containment Isolation
(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD SIU evaI uat ion)
RBVS SUPPLYlEXH Operator verifies that ALL of the listed GU-HD-9370A, 93706 valveslequipment in this group have GR-HD-9414A, 9414B responded correctly to the initiating event.
~~
0 DW PURGE SUPlEXH Operator verifies that ALL of the listed GT-HD-9372A. 9372C valves/equipment in this group have responded correctly to the initiating event.
RECIRC SAMPLE Operator verifies that ALL of the listed BB-SV-4310,4311 valveslequipment in this group have responded correctly to the initiating event.
~~
RWCU Operator verifies that ALL of the listed BG-HV-F001, F004 valves/equipment in this group have responded correctly to the initiating event.
Page 8 of 16
T .I 06-0303 JPM: SM002 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Primary Containment TASK: Respond To A Containment Isolation I
NO.
STEP I ~~ ~
ELEMENT CUE 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:
I Page 9 of 16
I TQ-AA-I 06-03133 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: --
DATE:
JPM Number: SM002 TASK: Respond To A Containment Isolation TASK NUMBER: 4000760401 QUESTION: _-
RESPONSE: -
RESULT: SAT 1 UNSAT QUESTION:
RESPONSE: _-
RESULT: SAT UNSAT I I Page 10 of 16
TQ-AA-106-030 3 306 PERFORMANCE MEASURE INITIAL CONDITIONS:
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 lnifial INITIALIZE the simulator to 97% power.
TRIP all three RFPTs.
i CONTROL HPCllRClC such that RPV level recovers to the normal band.
IMPLEMENT EOP-101/102 for the transient.
A PREP FOR TRAINING (ie., R M l 1 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 l2of 16
TQ-AA-106-03 13 JOBPERFORMANCEMEASURE Si MULATOR SETUP INSTRUCTIONS (OPTIONAL)
/nit,a/ ET # Description _-
EVENT ACTION: et-array(1) 1 COMMAND: irf et023 normal PURPOSE: _-
EVENT ACTION: et-array(2) 2 COMMAND: irf et024 normal PURPOSE: _-
EVENT ACTION:
Page I 3 of 16
TQ-AA-I 06-0373 JOBPERFORMANCEMEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) lnitial Description Ramp Trigger Init Val FW26A Feedwater Pump Turbine AS105 Trip --- None ---
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 lnitial Description Delay Ramp Trigger lnit Val ET023 GROUP 9 B HV-FO19 DW Eqp Sump lsol --- --- None ---
ET024 GROUP 96 HV-F020 DW Eqp Sump lsol --- --- None --- FAIL 4s IS I/O OVERRIDE
SUMMARY
Page 14 of 16
TQ-AA-106-0323 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: SM002 Rev #
00 Date 9/6/08 New JPM.
Description I Va:ioln]
Required?
00 12/5/08 Validated with 2 ROs from C Shift. Avg validation time 9 minutes I
N a d d e d to page 2 I -
I I I i -2
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Emergency Diesel Generator TASK: Perform Non-Emergency Operation of the Diesel Generators TASK NUMBER: 2640030101 JPM NUMBER: 305H-JPM.KJ008 REV#: 01 SAP BET: NOH05JPKJ08E ALTERNATE PATH:
APPLlCABlLITY:
DEVELOPED BY: Archie E. Faulkner DATE: 12/7/08 nstructor REVIEWED BY: DATE: \L\ii[g perations 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: 2640030101 TASK: Perform Non-Emergency Operation of the Diesel Generators ALTERNATE PATH: 1- WA NUMBER: 264000A4.04 IMPORTANCE FACTOR: 3.7 -
3.7 -
APPLICABILITY: RO SRQ E O F I R O F i S T A I 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 TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: U S A T DUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:
EVALUATORS 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. 1OA401 bus had been shifted to the Alternate breaker 40101 in preparation for work on the NORMAL breaker 40108.
- 2. The improper tagout of the 40108 breaker caused the AG400 EDG to start and load onto the 10A401 bus.
- 3. All components have been restored to their normal condition.
- 4. Station Service Transformers 1AX501 and 1BX501 are in service to supply power to class IE 4.16Kv Busses.
- 5. Preparations are in progress to shutdown EDG A in accordance with HC.OP-SO.KJ-0001, Section 5.7.
- 6. 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 (40101) in accordance with HC.OP-SO.PB-0001, Step 5.7.5.
Page 3 of 16
1 .-I 06-0303 JPM: KJ008 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE 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 1 NO.
CUE I PROVIDE the operator the initiating cue.
STANDARD Operator repeats back initiating cue.
- SIU evaluation)
Operator obtains/locates procedure HC.OP-SO.PB-0001.
1 Operator locates the proper procedure.
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 Operator reviews Prerequisites and Section 2.7 have been satisfied. initials each Prerequisite in the space provided in the procedure.
Page 4 of 16
TL. ..~-106-0303 JPM: KJ008 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE 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. ..
I STANDARD SIU evaluation)
CUE: If excessive time is taken reviewing Prerequisites, inform operator that The operator then initials the all are satisfied. appropriate procedure step.
5.7.5 SHIFT breaker alignment on the desired Class IE 4160V 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. PRESS DIESEL ENG GOV INCR Operator presses the DIESEL ENG A push-button AND INCREASE GOV INCR push-button.
Generator frequency to 61 Hz.
Operator observes engine frequency rise to 61 Hz on FI-6393A.
5.7.5. PRESS DIESEL ENG GOV DROOP Operator depresses the DIESEL ENG B MODE push-button AND ENSURE GOV DROOP MODE push-button.
that the DROOP MODE light for EDG, is illuminated.
Operator observes the DROOP MODE light is illuminated.
Page 5 of 16
TL i- I 06-0303 JPM: KJ008 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 DATE:
SYSTEM:
TASK: -
75.7.5.
C ELEMENT IF required' ADJUST EDG frequency to 60 Hz by pressing the DIESEL ENG GOV INCR DECR push-buttons as applicable.
(*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD Operator adjusts frequency to 60 Hz by pressing the DIESEL ENG GOV INCR DECR push-buttons COMMENTS (Required for UNSAT evaluation)
Operator observes frequency at approximately 60 Hz on FI-6393A.
-~
5.7.5.
D PLACE the Normal (Alternate) FEED BRKR-SYNC KEYLOCK Switch in the 1, Operator places the Alternate FEED (40101) BRKR-SYNC KEYLOCK ON position. Switch in the ON position.
Operator observes the Alternate FEED (40101) BRKR-SYNC KEYLOCK Switch in the ON position.
Operator observes the Sync Scope rotating .
5.7.5. ENSURE the DROOP MODE light for Operator observes the DROOP MODE E the Diesel AND the SYNC indicator light for the Diesel is ON.
lights are ON.
~~
Operator observes the SYNC indicator lights are ON while the sync scope is off 12 O'clock position.
Page 6 of 16
1 - A-I 06-0303 JPM: KJ008 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Emergency Diesel Generator TASK: Perform Non-Emergencv Operation of the Diesel Generators -
STEP NO.
ELEMENT
(*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD EVAL SIU I COMMENTS (Required for UNSAT evaluation) 5.7.5. ENSURE that the Normal AND Operator presses the Normal (40108)
- F Alternate Feeder Breaker AUTO AUTO CLOSE BLOCK PB, and CLOSE BLOCK PB backlights are ensures that the Normal and Alternate Feeder Breaker AUTO CLOSE BLOCK OFF. PB backlights are OFF.
~
Operator observes that the Normal and Alternate Feeder Breaker AUTO CLOSE BLOCK PB backlights are OFF.
5.7.5. PERFORM the following to G synchronize across AND CLOSE the Normal (Alternate) FEED BRKR:
5.7.5. IF necessary,
- ADJUST the Running Operator ensures the Diesel Generator G.1. Voltage using the GEN VR RAISE Running Voltage and Bus Incoming LOWER PBs, to match Diesel Voltage are matched on VI-641 1A and VI-641 2A. (Adjustment using the GEN Generator Running Voltage WITH VR RAISE LOWER PBs may be Bus Incoming Voltage. required. Should be within half an increment .)
Page 7 of 16
TL . .A-106-0303 JPM: KJ008 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 DATE:
SYSTEM:
TASK: -
7
(*Denotes a Critical Step)
- COMMENTS ELEMENT (#Denotes a Sequential Step) (Required for UNSAT STANDARD -
5.7.5. ADJUST DG Speed UNTIL the G.2. SYNCHROSCOPE pointer is moving Operator presses the DIESEL ENG slowly in the SLOW (counter INCR or DECR PB.
clockwise) direction by pressing the DIESEL ENG INCR DECR PB.
Operator observes the synchroscope pointer rotating in the SLOW direction.
5.7.5. WHEN synchroscope pointer is at 3 When synchroscope pointer is G.3. minutes past 12 O'clock (before approximately 3 minutes past 12 pointer reaches 12 O'r,!ock in its O'clock, the operator closes the Alternate FEED BRKR (4010-1j by direction of travel), THEN CLOSE the pressing the 401 01 CLOSE PB.
Normal (Alternate) FEED BRKR.
Operator observes the Alternate FEED BRKR (40101) CLOSE light illuminates and the green TRIP light extinguishes.
~ _ _ ~ ~ ~
5.7.5. PRESS the AUTO CLOSE BLOCK
- H PB for the Normal(A1ternate) Feed Operator presses the AUTO CLOSE Breaker AND VERIFY that the AUTO BLOCK PB for 40101.
CLOSE BLOCK PI3 is illuminated.
[CD-056 HI Operator observes that the AUTO CLOSE BLOCK PB is illuminated.
Page 8 of 16
TL 4-1 06-0303 JPM: KJ008 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
I
(*Denotes a Critical Step)
- STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.
STANDARD # evaluation) 5.7.5.1 PLACE the Normal (Alternate) FEED Operator places the Alternate FEED
- BRKR -SYNC KEYLOCK Switch in BRKR-SYNC KEYLOCK Switch in the the OFF position. OFF position.
~ ~~ ~
Operator observes that the synchroscope de-energizes.
5.7.5. J As directed by the CRS, UNLOAD AND STOP the ~ iG~~~~~~~~
~ IAW
~ ~Operatorl informs the CRS of the status HC.OP-SO.KJ-0001(Q). o f the EDG.
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:
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 ,
I TASK: Perform Non-Emergency Operation of the Diesel Generators I
TASK NUMBER: 2640030101 I
QUESTION: --
RESPONSE: I
- -1 RESULT: SAT 1 1 UNSAT 1-QUESTION: -l RESP0NSE: -__
RESULT: SAT I ] UNSAT Page 10 of 16
I TQ-AA-I 06-01 03 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- 1. 10A401 bus had been shifted to the Alternate breaker 40101 in preparation for work on the NORMAL breaker 40108.
- 2. The improper tagout of the 401 08 breaker caused the AG400 EDG to start and load ontc the 10A401 bus.
- 3. All components have been restored to their normal condition.
- 4. Station Service Transformers 1AX501 and 16x501 are in service to supply power to clac s 1E 4.16Kv Busses.
- 5. Preparations are in progress to shutdown EDG A in accordance with HC.OP-SO.KJ-000 ,
Section 5.7.
- 6. 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 (40101) in accordance with HC.OP-SO.PB-0001, Step 5.7.5.
Page I 1 of 16
TQ-AA-2 06-0: 03 JOBPERFORMANCEMEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
I INITIALIZE the simulator to rated power, MOL. I i
TRANSFER 1OA401 to the ALTERNATE FEED BRKR.
START, parallel, and load EDG A.
ENSURE Isochronous light is ON.
OPEN breaker 40108.
ACKNOWLEDGE overhead and local alarms.
ADJUST generator voltage for bus voltage -4300 volts.
ADJUST bus frequency to 60 Hertz.
SWAP busses 1OA402, 403, and 404 to Alternate infeeds.
PREP FOR TRAINING (i.e., RMI Iset 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 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
EVENT TRIGGERS: -
initial ET # Description _-
EVENT ACTION:
1 COMMAND:
PURPOSE: _ _ .
EVENT ACTION:
2 COMMAND:
PURPOSE: _-
Page 13 of 16
I TQ-AA-106-0: 03 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTION S (OPTIONAL)
MALFUNCTION
SUMMARY
lnifial I
I 1 Description I Delay Ramp i
1 Trigger I
I Init Val I i
Final /a1 1 REMOTElFlELD FUNCTION
SUMMARY
I I I 1
I lnitial Description ' Delay Ramp Trigger lnit Val Final Val
~
I -
--- --- --- --- -I 110 OVERRIDE
SUMMARY
Page 14 of 16
TQ-AA-106-0203 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: KJ008 Rev # Date Description Validaticln Required? -
01 11/10/2008 This revision converts to HC LOR format, documents validation, Y 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.
01 12111/2008 Validated with 2 ROs from !3 Shift. Average completion time is N 14 minutes. Incorporated recommendation to swap other bus infeed breaker to alternate to prevent 311 lineup complications.
JDE; pEilr:Qg$&&cE pYJig4i,SuxE STATDO !4 : Hcqe ,Creek SYSTEM: Rea 320 I. Auxi Ii a ri e s Coo I in g Sy ste rn TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 JPM NUMBER: 305H-JPlVI.ED002 REV#: 01 SAP BET: NOH05JPED02E ALTERNATE PATH: IXI APP LICABILIITY:
EO n 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: F l K/A NUMBER: 29501 8 AA2.02 _ _
IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO_ _
E O I R O W 1 S T A m S R O F I 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: U S A T 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: R e s p n d 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 h a s been briefed arld is stationed at the BP209 RACS pump.
- 4. The BP209 h a s K T b e e n 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 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: 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 HC.OP-SO.ED-0001. I I I
Operator reviews precautions and Operator reviews precautions and limitations. limitations. I CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.3.1. .__- --
5.3.1 ENSURE all prerequisites have been Operator ensures that all prerequisites satisfied IAW Section 2.3. have been satisfied.
Operator then initials the appropriate Reactor Auxiliaries Cooling Water procedure step.
System is in service.
CUE if excessive time is taken reviewing prerequisites, inform operator that NIA all are satisfied.
Page 4 of 16
Ti. 4-106-0303 JPM: EDU02 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction
____I COMMENTS ELEMENT (Required for UNSAT eva I u ati o !I)
ENSURE that one of the following On 10C651A operator observes the HX valves are OPEN ( I OC651A): INLET VALVES:
ED-HV-2537A(B) HX INLET VLVS. HX AE217 INLET red HV2537A OPEN light is illuminated and green CLOSE light is extinguished e HX BE217 INLET red HV2537B OPEN light is illuminated and green CLOSE light is extinguished.
OBSERVE the following lights are off for the RACS Pumps Operator observes the REACTOR going in service: AlJXlLlARlES COOLING PUMPS e OVLDlPWR FAIL PUMP B amber OVLD/PWR FAIL, INOP, and white REMOTE lights are
- 8) INOP extinguished.
0 REMOTE 5.3.4 For the 1AP209 and/or IBP209, as applicable, On 1OC650E operator observes the ENSURE RACS PMP 1AP209 BKR RACS PMP BP209 BRKR 52-4201 1 52-4101 I, red CLOSED light is illuminated and andlor 1BP209 BKR 52-4201 1 green TRIPPED light is extinguished CLOSED is on. (10C650E)
Page 5 of 16
JPM: EDC02 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction STEP
(*Denotes a Critical Step)
(#Denotes a Sequential Step) 7 EVAL ELEMENT N0=
STANDARD -
- si w 5.3.5 -IF returning a pump to service that has been isolated and drained, PERFORM the following steps as Operator determines to proceed to Step necessary to correctlprevent air 5.3.6, since the Initiating Cue states binding, otherwise, PROCEED to that the pump was not isolated.
Step 0 for a normal start of a standby pump:
5.3.6 PRESS REACTOR AUXILIARIES Operator presses the REACTOR COOLING PUMP A(B)(C) #
AUXILIARIES COOLING PUMPS START PB (10C651A). START PUMP B BP209 START pushbutton.
comes on.
OBSERVE AI-6460 (Al-6461) Operator observes:
REACTOR AUXILIARIES COOLING 0 The red BP209 START light PUMP A(B)(C) MOT AMPS settles at illuminates and the green STOP
< 180 amps light extinguishes.
AND is approximately the same as e Al-6461 is < 180 amps and settles the other IIS RACS pumps motor at approximately the same value as amps. the A and CRACS pumps amps.
5.3.7 PRESS REACTOR AUXILIARIES Operator presses the REACTOR COOLING PUMP B(A)(C) AUXILIARIES COOLING PUMPS STOP PB. STOP comes on. PUMP A STOP pushbutton.
~~
Operator observes the green STOP light illuminates and the red AP209 START light extinguishes.
Page 6 of 16
T\ 4-f 06-8303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction
(*Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step) EVAL NO.
STANDARD siu NIA Operations Fundamental: 5 seconds after the A RACS pump has been secured, the Operator observes Control Board Awareness 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.
e Green STOP light is flashing.
o AI-6461 reads 0 amps NIA HC .0P-AR .ZZ-0 0 02 NIA ATT OPERATOR ACTION:
E2 1. REFER to HC.OP-AB .COOL-0003(Q); Reactor Auxiliary Cooling System.
- 2. ENSURE compliance with Operator refers to Technical Specifications 3.6.3 - HC.OP-AB.COOL-0003.
Containment Isolation Valves.
- 3. ENSURE compliance with Technical Specifications 3.6.5 -
Secondary Containment Integrity.
Page 7 of 16
6 .-a 06-0393 JPM: ED002 OPERATOR TRAINING PROGRAM NAME. .___-
Rev: 01 JOB PERFORMANCE MEASURE DATE. ~ __
SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction T--__I-.---
1 I ("Denotes a Critical Step) + c=OMMJ"sEIJrC I STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required io. !SPiSP,X NO.
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 Time Operator enters the current Time in the space provided.
A I I t-------------- - -
A. I PRESS the START P.B. for anv Operator presses the REACTOR available RACS pump in standby AUXILIARIES COOLING PUMPS PUMP A AP209 START pushbutton.
Operator observes:
o The red AP209 START light l l r remains extinguished and the green STOP light remains illuminated.
o Motor amps continue to indicate 0. I I I CUE Respond to any reports of the 'A' RACS pump failure to start by directing the operator to continue implementing Condition 'A' of HC .OP-AB.COO L-0003.
JPM: ED002 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliarv Coolinq Malfunction STEP NO.
ELEMENT I ("Denotes a Critical Step)
(#Denotes a Sequential Step) EWAL STANDARD siu A.2 E a second RACS Pump CANNOT be placed in service, Operator observes the OFFGAS THEN ISOLATE RACS to the out of RECOMB TRAIN SELECT:
service Off-Gas Train as follows: e COM TRAIN red OPEN light 0 E the Common Off-Gas Train illuminated and green CLOSE light is in service, extinguished.
THEN CLOSE HV-2577. e TRAIN 1 red OPEN light IF Unit 1 Off-Gas Train is in e __ extinguished and green CLOSE light service, illuminated.
THEN CLOSE HV-7712Al.
Operator presses the OFF GAS CLR CNDS COOLli\lG IOE306 Ui\ilT 7 1
- green CLOSE pushbutton Operator observes the green CLOSE light illuminates and red HV2577 OPEN light extinguishes.
CUE 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 NIA JPM.
Leaving the HV7712A1 closed andlor causing an isolation of the Common Offgas Train is failure criteria.
Page 9 of 16
JPM: ED002 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling - Malfunction ELEMENT STANDARD eval uatkon)
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:
Page 10 of 16
JPM Number: ED002 TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 QUESTION: -_
RESPONSE: -_
RESULT: I SAT , UNSAT QUESTION: -_
RESPONSE: -_
RESULT: SAT [-I UNSAT I]
I N IT I At. c 9N u i TI Q N s :
1 The RAGS System is in service with the AP209 and CP209 RACS pumps r u i i n i n ~
2 AP209 RACS pump is schedulec for an oil change 3 The Reactor Building EO has been briefed and IS stationed at the BP209 RACS pump 4 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 s f I 6
CW08B Trip of BP209 RACS pump JPM NUMBER: ED002 Rev# 1
______ Required'
Jag [ x/Fk,;':b$1A%"LSCE FL(&5*s;'LFLE STATION: plop6 Creel:
SYSTEM: Reactor Rest rculation TASK: Perform Scoop Tube Positioner Lock-Up Operation TASK NUMBER: 2020080401 JPM NUMBER: 305H-JPM.BB002 REV#: 16 SAP BET: NOH05JPBB02E ALTERNATE PATH: FI APPLICABILITY:
EO RO PI STA 1- SRO DEVELOPED BY: Archie E. Faulkner DATE: 9/4/08 Instructor REVIEWED BY:
/
f l i'r- BATE: fl .IC Operations Representative Training Department
- ?
STATION: ! l o p 3 wreck SPM NIblJIEEht?,: B3002 5 YSTE I\li: 2eactor Recirculation TASK NUMBER: 2020080401 TASK: Perform Scoop Tube Positioner Lock-Up Operation ALTERNATE PATH: FI WA NUMBER: 202002 A2.05 IMPORTANCE FACTOR: 3. I 3.1_ _
APP LlCABI LITY: RO SRO EO(( RO[XJ S T A m S R O R EVALUAT10 N S ETTlNGIMETHOD : S i muI ato r/Perfo rm
REFERENCES:
HC.OP-SO.BB-0002 Rev 72 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 17 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Vhx~tes JPM PERFORMED BY: - GRADE: O S A T UUNSAS.
ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: BABE:
Page 2 of 23
SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-Up Operation TASK NUMBER: 2020080401 lNfTIAL CONDITIONS:
- 1. The plant was at 80% Reactor Power with power ascension in progress.
- 2. The SPRVESG guidance is valid. Some rods may already be inserted.
- 3. A control signal failure caused the A Reactor Recirc Pump Motor/Generator Scoop Tube to lock-up.
- 4. The A Reactor Recirc pump was placed in Scoop Tube Positioner Lockup Operation IAW HC.OP-SO.BB-0002.
- 5. I&C has repaired the control signal failure.
- 6. An NCO is stationed at the A Reactor Recirc Pump Motor/Generator Scoop Tube Positioner.
- 7. Manual adjustment of the A Reactor Recit-c Scoop Tube has been terminated.
- 8. The A Reactor Recirc Scoop Tube Positioner Power Switch is ON.
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 JOB PERFORMANCE MEASURE SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-Up Operation
__rr_- - .-.-. 7 ELEMENT PROVIDE the operator the initiating cue. Operator repeats back initiating cue.
I ENTER START TIME AFTER Operator repeats back the Initiating Cue:
START TIME:
Operator obtains the correct Operator obtains procedure procedure. HC.OP-SO.BB-0002. __ ~. ~~-
0perato r reviews p re ca IJt io ns and 0perato r reviews p r e mutions and I / I limitations. limitations. I / I
-IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.
Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.9.1.
Improper reset of a Scoop Tube Positioner can result in a significant power transient, and possible Scram due to rapid changes in Recirculation Flow.
Page 4 of 13
JPM: BB002 OPERATOR TRAINING PROGRAM NAME Rev: 16 JOB PERFORMANCE MEASURE DATE: -
SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-Up Operation t
(*Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step)
NO.
STANDARD 5.9.1 ENSURE all prerequisites have been Operator ensures that all prerequisites satisfied IAW Section 2.9. have been satisfied.
CUE IF excessive time
- is taken reviewing prerequisites, NIA THEN INFORM operator that all are satisfied.
5.9.2 PRESS SIC-621A MAN AND SIC- Operator observes SIC-R621A/B MAN Y N Fiaygiriy 621B MAN push buttons. 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.
5.9.3 Operator observes OUTPUT A Y N Ffagging PRESS SIC-620 OUTPUT A(B)
SELECT push button, for the Pump SELECT light is illuminated.
that will be reset. Examiner Note: Operator may press button even with OUTPUT A already selected. If button is NOT pressed, T I M should be entered in place-keeping block.
Page 5 of 13
JPM: BB002 OPERATOR TRAINING PROGRAM NAME. ~-
Rev: 16 JOBPERFORMANCEMEASURE DATE __ ~-
SYSTEM: Reactor Recirculation TASK: Perform SCOODTube Pssitioner Lock-Ur, ,era t ion STEP ELEMENT NO.
NOTE 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 NIA conditions, it may be either above or I I
below the scoop tube position I corresponding to the actual speed.
This step determines the desired demanded scope tube position for the actual s p e e d .
5.9.4 Using Attachment 3, DETERMINE the Operator determines the desired desired SIC-621A(B) SPEED SIC-R621A SPEED DEMAND to be 58-DEMAND for the actual SPEED 62% IAW Attachment 3.
indicated on SIC-621A(B). Examiner Note: The target SPEED DEMAND is 60%. Some leeway has been added for meter readability and the potential interpolation of Attachment 3 data.
Page 6 of 13
JPM: BBOU2 OPERATOR TRAINING PROGRAM NAME: -
Rev: 16 JOB PERFORMANCE MEASURE SYSTEM: Reactor Rec,, culation TASK: Perform Scoop Tube Positioner Lock-Up Operation
(*Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step) EVAL NO.
STANDARD SIU 5.9.5 PRESS SIC-R621A(B) SPD CONT Operator presses the SIC-R621A INCREASE OR DECREASE LOOP A SPD INCR andlor DECR pb pushbutton as necessary to obtain the until SIC-R621A SPEED DEMND matches the SPEED DEMAND from desired SIC-621A(B) SPEED Step 5.9.4.
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.
NOTE 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. NIA Although a constant speed should be maintained when coming out of Lockup, a small speed change may be experienced.
CAUT When coming out of Scoop Tube Lockup, the potential exists for the Recirc Pump to Run Away, and the NIA operator should be prepared to take appropriate action.
Page 7 of 13
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 t h e JPM has been terminated for other reasons, THEN RECORD the STOP TIME. I REPEAT BACK any message from the i operator on the status of the JPM, and then state "This JPM is complete". 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',B11AlCONDITIONS:
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 5.5f ~ the r '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-800ZJPI6 _-91
Con'itr-ol Rod Drive Hyci:aulics Conduct Emergency I\/iat;eup To The RPV Using Two CKD P u m p s 2010200'104 REV #: 01 NQHOSJPBFI3E DEVELOPED BY: Archie E. Faulkner - DATE: 8/28/2008 lnstrueQoP REVIEWED BY:
APPROVED BY: /
Training Department
TQ-AA-106-0301 STATION: Hope Creek JPM NUMBER: BFOI 3 REV: 01 SYSTEM: Control Rod Drive Hydraulics TASK NUMBER: 2010200104 TASK: Conduct Emergency Makeup To The RPV Using Two CRD Pumps K/A NUMBER: 295031EA 1.08 IMPORTANCE FACTOR: 3.8 3.9 AP PLlCABlLITY: 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: U S A T DUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE: __
Page 2 of 12
sY s TEFir, : Control Rod Driv6 iiyaraulics TASU: Conduci Emergency Makeup To The EP'v'Using Two CEG Pumps TASK NUMBER: 2010200104 INITlAL co ND ITIONS:
- 1. The plant was scrammed d u e to a loss of condensate and feedwater.
- 2. HPCl and RClC are unavailable.
- 5. The BP207 CRD pump, BF201 Pump Suction Filter, 5F204 Drive Water Filter, a n d the 'B' FCV a r e currently in service.
- 6. The scram h a s not been reset.
You are the Reactor Building operator.
Perform steps 5.4.1 through 5.4.10 of HCOP-S0,BF-0001 t o lineup for two CRD pump injection.
Another operator will be assigned to perform the remaining steps a n d control injection.
Page 3 of f.2
JPM: BF013 OPERATOR TRAINING PROGRAM Fie\J: 01 JOB PERFORMANCE MEASURE SYSTEM: Control Rod Drive Hydrauiics TASK: Conduct Emergency Makeup To The WPV Using TWOCRD Pumps STEP ELEMENT NO.
STANDARD CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue. I I CUE ENTER START TIME AFTER I I
OPERATOR REPEATS BACK INITIATING CUE:
START TIME:
Operator obtains procedure Operator obtains the coi-rect procedure.
HC.OP-SO.BF-0001.
Operator reviews precautions and Operator reviews precautions and limitations. limitations.
CUE If excessive t h e is taken reviewing precautions and limitations, inform operator that all are satisfied.
4.0 EQUIPMENT REQUIRED Operator obtains hose and pipe QI Wrench to remove cap from wrench.
Stabilizing valve needle valve. Examiner Note: After operator has e Small adjustable wrench io demonstrated ability to obtain required equipment, ensure that the equipment position Stabilizing valve is returned to its appropriate storage r?eedlevalve stern location. 5ased on initial conditions, AND locknut Operator may NOT obtain hose to d Hoses (for filling & venting). direct venting and may vent to the floor.
Operator determines beginning step 0perato r determines correct beginning nf f h e ~ r n c e d i j r e ~ step to b e 5.4.1.
Page 4 sb 92
Tk -f OG-0303 JPM: BF013 OPERATOR TRAINII\!G PROGRAM NAME: .~
Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Control Rod Drive Hydraulics TASK: Conduct Emergency Makeup To The RPV Using Two CRD Pumps
(+Denotes 3 Critical Step)
ELEMENT (#Qenotes a Sequential Step)
STANDARD ENSURE all prerequisites of Section Operator ensures that ail prerequisites 2.4 are satisfied. have been satisfied.
If excessive time is taken reviewing prerequisites, inforan operator that dl are satisfied.
PERFORM the following to place AF201(BF201), A(B)
Pump Suction Filter, in-service:
Operator opens 1-BF-V078.
- A. OPEN l-BF-V078(I-BF-V029),
CRD Suct Fltr AF201 (BF201) Inlet Vlv. I 8 The valve you indicated is open. I I B. VENT filter using 1-BF-VO81(I - Operator uncaps 1-6F-VQ81
- BF-V036), CRD Suct Fltr AF201(BF2011 Vent Vlv. #
Operator connects a hose between valve 2-BF-VQ81 and a drain huh. ~___---
Operator unlocks I-BF-V081.
Ogeraior throttles open I-BF-VQ81.
- A steady stream of water flows from the vent line ~ I -
Page 5 of i2
JPM: BF013 OPERATOR TRAINING PROGRAM Rev: 07 J 0 5 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 SYSTEM: Control Rod Drive Hydraulics TASK: Conduct Emergency Makeup Bo The RPV Using Two CRD Prmps ELEMEN i CUE You hear flow n o i s e through the walve. The valve you indicated is spen.
I I A. OPEN 1-BF-VOOS( 1-BF-VOI 0),
CRD Drive Wtr Fltr Inlet Vlv.
CUE The valve you indicated is open. 1
- 6. OPEN 1-BF-VOI 1(1-BF-V012), Operator opens I -BF-VOl I .
CRD Drive Wtr Fltr Outlet Vlv.
CUE The vaive you indicated is open.
r 5.4.8 REQUEST the Main Control Room to Operator requests the Main Control open HV-F003, DRIVE WTR PC Room open HV-FGO3.
VLV.
1 5.4.9 I OPEN 1-5F-VO62, DRIVE WTR PC VLV BYPASS.
Operator unlocks and opens the 1-BF-V062.
Page 7 of 12
JPM: BS-013 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE DAT-E: -~
SYSTEM: Csntrcl Rod Drive Hydraulics TASK: Conduct Emergency Makeup To The RPV Using Two CRD Pumps 7
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 m e s s q e 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 0N :
RE§ PONSE: -
RESULT: UNSAT
I , 1-hc plant was scrammed due to B 1 3 s of condensm and feedwater.
- 2. HPZl and RClC are unavailable.
- 3. EOP-101: ReactorlPressure Vessel (E?V)Control, is Seing implemented.
- 5. The BP207 CRB pump, BF2Oi Pump Suction Filter, 6F204 Drive Water Fiker, a n d the E FCV are currently in service.
G. 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 i 01 81282008 Revised to new JPM formal Revalidated JPM time. Y I
i Updated reference procedure revision number. '3perator actions did not change. i y 7 -7 I
I I
I I
I I
-7
-4
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 Departtnent
c-*-,:
h
- -l,-JK
- ii3;je dr~~eI\
r \
&IWr KUM5ER: SEO32 REV: 08 SPSIEM: 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 TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: 17 SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:
EVALUATORS §leNATURE: DATE:
Page 2 of I 1
SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504 INITIAL CONDITIONS:
- 1. A leak on the 'D'RHK P u m p suction line has lowered suppression pool level to 73 inches.
- 2. The leak has been isolated and suppression pool level is stable.
INITIATING CUE:
Make-up to the Suppression Chamber from Core Spray Loop B IAW HC.OP-EO.ZZ-0315 Page 3 of I 1
,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 PROVIDE the operator the initiating cue. Operator repeats back initiating cue.
CUE OPERATOR REPEATS BACK INITIATING CUE:
CUE Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.
Page 4 of 11
JPM: BE002 OPERATOR TRAINING PROGRAM Rev: 08 JOB PERFORMANCE MEASURE SYSTEM: Core Spray TASK: Perform Torus MakeuD Via Core SDrav Svstem
("Denotes a Critical Step)
STEP NO.
ELEMENT (#Denotes a Sequential Step)
STANDARD 4.0 EQUIPMENT REQUIRED Operator obtains the following required equipment:
4.1 Key #9 for EOP Locker in OSC (obtain from OS office or break 1. Key #9 for EOP locker in OSC red key holder glass in OSC (obtain from OS office or break red key holder glass in O S C )
AND 2. EOP-315 implementation kit from EOP-315 lmplementation Kit EOP iocker in OSC (EOP Locker in OSC) Examiner Note: After operator has Contents: 1 Wire Cutter demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location.
5.7 .I ENSURE that all prerequisites have Operator ensures that all prerequisites been satisfied IAW Section 2.1. have been satisfied.
CUE 14 excessive time is taken reviewing prerequisites, inform operator that all are satisfied.
UNLOCK AND OPEN 1-AP-V068 Operator UNLOCIS and OPENS 1-AP-llCond Stor & Xfr to Core Spray Pump V068, Cond Stor and Xfr to Core Spray 5.1.2 B and D Suction Fill ti Flush lsln Vlvll. Pump B & D Suction Fill & Flush lsln (local, Room 4203 reactor building, Valve located on the 77 ft. elevation of elevation 77') the reactor building.
CUE The valve you indicated is unlocked and open.
Page 5 of 11
JPM: BE002 OPERATOR TRAINING PROGRAM Rev: 08 JOB PERFORMANCE MEASURE SYSTEM: Core Spray TASK. Perform Torus Makeup Via Core SDrav Si 'tern
("Denotes a Critical Step)
STEP (#Denotes a Sequential Step)
ELEMENT NO. STANDARD 5.1.3 ENSURE the following (PANEL C650) Operator contacts Control Room and are OPEN: directs Control Room Operator to verify OPEN HV-F001B and HV-F001D.
A. HV-F001B CS Pmp B Suct lsln MOV Examiner Note: Operator may verify these valves OPEN before leaving the B. HV-FOOID CS Pmp D Suct I s h Control Room Area.
MQV CUE Respond as the MCR, HV-FOOIB and HV-FO01D are open.
5.1.4 UNLOCK AND THRQTTLE OPEN Operator throttles open BE-V058 and/or one QR both of the following valves to BE-V059.
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 I s h Vlv B. BE-V059 CS Pmps B & D Suct X-Tie I s h Vlv CUE (As appropriate) The valve you indicated is throttled open. Flow can be heard past the valve(s).
Operator informs Control Room that Suppression Chamber makeup is in progress.
CUE If operator informs Control Room, provide Terminating Cue.
Page 6 of 11
JPM: BE032 OPERATOR TRAINING PROGRAM NAME Rev: 08 JOBPERFORMANCEMEASURE SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray S ;tern
(*Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step)
NO.
STANDARD 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:
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 1 ,.-$&-:I$-'
I-h ,; p f N i-mb.c 0 N DETi CSld s :
I A leak on the 'D'RHR P ~ l m psuWi-1 iine has lowered suppressim pool level to 7 3 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: ct Io rI S y 5;t2 rn Rea cto r Pr c )is TASK: Transfer RPS Bus klE Power FroITi Alternate Source 7-0 RPS IUG Set TASK NgMBER: 21 200501C 1 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 STATION: Hope Creek JPM NUMBER: SB015 REV: 02 SYSTEM: Reactor Protection System TASK NUMBER: 2 120050I01 TASK: Transfer RPS Bus A/B Power From Alternate Source To RPS MG S 3t ALTERNATEPATH: IX I KIA NUMBER: 212000 A2.01 IMPORTANCE FACTOR: 3.7 3.9 APP LlCABlLITY: 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: U S A T UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
~~ ~
Page 2 of 14
SYSTE!M: Ee 2 ct 0 r Prot e ciio n Sv s t e rr TAS 1;: Transfer RPS Bus hlE POWE;F r : 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.
- 4. Once the lvlG Set IS running, Maintenance n e e d s to checldadjust NIG S e t 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 HC.OP-SO .S B-0001.
Contact Maintenance when ready for MG s e t output voltage cheddadji-1st.
TL 106-0303 i JPM: SB015 OPERATOR TRAINING PROGRAM NAME: __
1 Rev: 02 JOB PERFORMANCE MEASURE DATE.
i SYSTEM: Reactor Protection System TASK: Transfer RPS Bus AIS Power From Alternate Source To RPS MG Set STEP ELEMENT NO.
PROVlDE the operator the initiating Operator repeats back initiating cue.
I ____
CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:
START TIME:
Operator obtains procedure HC .OP-SO.SB-0001. Operator obtains the correct procedure. l i I Operator reviews precautions and Operator reviews precautions and I I limitations. limitations.
l l CUE If excessive time is taken reviewing I precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step Operator determines correct beginning of the procedure. ster, to be 5.5.1 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.5 are satisfied. have been satisfied.
CUE If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.
Page 4 of 14
JPM: SBulS OPERATOR I KAlNlNG PROGRAM Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System 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 Operator observes the Red MOTOR The operator then initials the appropriate procedure step.
Page 5 ~t I 4
JPM: Si3015 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Transfer RPS Bus AI6 Power From Alternate Source TQ RPS M G Set ELEMENT B. VERIFY A-C VOLTS Generator Operator observes A-C VOLTS Output Voltage AND PERFORM Generator Output Voltage and expects a voltage increase to 115-1 25 volts
- 1. E voltage increases to 115 - which stabilizes for approximately 5 AND has been stabilized for approximately 5 seconds, THEN RELEASE the MOTOR The meter identified rises and stabilizes at approximately 100 to 115 - 125 volts, THEN PERFORM the following:
- a. RELEASE the MOTOR ON Dush-button. __.~ __
The operator then initials the appropriate procedure __ step. ___-___
- b. PRESS AND HBh5 Operator presses and holds the AG401 #
MOTOR OFF push-button. M O T O R OFF push-button.
- Page 6 of I 4
TC ?06-&i393 JPM: SBOls OPERATOR TkAINING PROGRAM NAME: - - ~
Rev: 02 JOB PERFORMANCE MEASURE DATE. ______~ ~-
SYSTEM: Reactor Protection System TASK. Transfer RPS B u s A B Power From Alternate Source To RPS MG Set __c- -- --
ce:B;r'FgF%! lr.
STEP $; ELEMENT (Required fon- IJNFAT NO. 8 S/W e 3B I i9ti 0 f 1)
I I
- c. WHEN the MOTOR ON When the AG401 MOTOR ON light light extinguishes, THEN extinguishes, the operator releases the RELEASE the MOTOR AG401 MOTOR OFF push-button.
OFF push-button.
CUE The Red MOTOR ON lamp is extinguished, and the Green MOTOR OFF lamp is illuminated.
I I The operator then initials t h e appropriate procedure step.
~ ~~
- d. REPEAT Step 5.5.2.A. Operator returns to 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 The operator then initials the appropriate procedure step. I Page I at 44
JPM: 33015 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Transfer RPS Bus Ah3 Power From Alternate Source To RPS M G Set
("Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step)
NO.
STANDARD 5.5.2 IF start
- of 1A(B)G401, RPS MG Set, Operator presses and holds the AG401 is necessary, THEN PERFORM the MOTOR ON push-button.
following (ACB] MG Set Local Panel):
A. PRESS AND HOLD the MOTOR ON push-button (Red MOTOR ON lamp illuminates).
Operator observes the Red MOTOR ON lamp illuminates.
CUE 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 Operator observes A-C VOLTS Output Voltage AND PERFORM Generator Output Voltage expecting an the following: increase to 'I 15-125 volts.
- 1. voltage increases to 115 -
125 volts AND has been stabilized for approximately 5 seconds, THEN RELEASE the MOTOR ON push-button.
Page 8 of 14
JPM: S5015 OPERATOR TRAINING PROGRAM Rev: 02 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,I5 - 125 vo!ts, THEN PERFORM the following:
iI Operator determines this step no longer C. ViHEN 1 minute of MG Set Operator waits one minute.
operation has elapsed, THEN PLACE RPS MG Set 1A(B)G401 GENERATOR OUTPUT breaker to ON AND IMlTlAb Attachment I .
Operator places the RPS M 6 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 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Transfer RPS Bus AI6 Power From Alternate Source To RPS M G Set
(*Denotes a Critical Step)
STEP (#Denotes a Sequential Step)
ELEMENT NO.
STANDARD The operator then initials the appropriate procedure step.
D. REQUEST Maintenance Operator requests maintenance io Department to CHECK AND check and adjust if necessary RPS MG ADJUST (as necessary), the Set A output voltage at t h e input to RPS MG Set(s) output voltage Electrical Protection Assembly (EPA) at the input to Electrical Circuit Breaker 1AN41 0 (unloaded)
Protection Assembly (EPA) IAW HC.MD-PM.S 5-000 1(Q),
Circuit Breaker IAN410 otherwise, verify A-C VOLTS at local (1AN41 1) (unloaded) IAW panel meter is 1I 5 to 'I 25 voIts.
HC.MD-PM.SB-000 I(a),
GTHERLYISE, VERIFY A-C VOLTS at local panel meter is 115 tc 125 volts.
CUE Respond as necessary and provide iie rrninating Cue.
CUE 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 W E Power From Alternate Source To RPS M E Set TkSK NUMBER: 2t20050101 QUE STION: -
RESPONSE: -.__I -
RESULT: UNSAT QUESTION:
RESPONSE
RES ULT: SATj-1 LINSA'T i Page 11 of14
- 7. The plant IS at 100% power.
- 2. RPS A is being powered from the ALTERNLTE A FEED.
- 4. Once the MG Set I S 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 HC.OP-SO. SB-0001.
Contact Maintenance when ready for MG set output voltage checkladjust.
I b
______ I I Bate I Descriptio 9: Validation LIT-----
i Updated reference procedure revisiori number. Operator actions did not change.
I
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
SAP BET: NOH05J PZZOSE ALTERNATE PATH: F I DEVELOPED BY: J. Berglund DATE: I1/9/08 Instructor REVIEWED BY: ax@ 0 erations Representative DATE: / >/f APPROVED BY:
/
/7A Iw' I " "Training
' Department DATE: / yl~/bfi-
TQ-AA-106-0303_ -
STATION: Hope Creek JPM NUMBER: 22009 REV: 01 SYSTEM: Conduct of Operations TASK NUMBER: 2990750302 TASK: Ensure the Operating Shift is Adequately 9annet ALTERNATEPATH: IX 1 KIA NUMBER: 2.1.5 --
IMPORTANCE FACTOR: 2.9 3.8 - -
APPLICABILITY: RO SRO 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 TIME PERIOD IDENTIFIED FOR TIME CRlTlCAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: U S A T UUNSAf ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: -- DATE: _-
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 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Dayshift from 0600-1800 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 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2/6 Dayshift watch tomorrow.
Page 3 of 16
TQ *I 06-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK:
Ensure the Operating Shift is Adequately Manned I
f
(*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.
STEP STANDARD evaluation)
CUE CUE 1 PROVIDE the operator the initiating cue AND a paper copy of LS-AA-119.
ENTER START TIME AFTER Operator repeats back initiating cue.
Operator repeats back the Initiating Cue: N/A START TIME:
4.1 .I An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight. Operator determines all work hours
- 1. Activities listed ic Step 1.4.4 may were applicable and no operator has or be excluded from time counted will exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight.
toward this time limitation.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than Operator determines all work hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven-day ( I 68 hr) were applicable and the RO will period. exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a seven-day period if 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2/6 Dayshift is worked.
- 1. Activities listed in Step 1.4.4 may be excluded from time counted toward these time limitations.
Page 4 of 16
TQ- .-I06-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned
_ _ _ _ ~
1 STEP NO.
ELEMENT I (;Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD
- I EVAL SIU COMMENTS (Required for UNSAT evaluation)
CUE asked whether another RO is available, THEN INFORM the operator that due NIA to a widespread illness, NO other ROs are available.
4.1.3 A break of at least eight hours should be allowed between work periods.
- 1. An eight hour break between work Operator determines CRS will meet the periods only becomes applicable if limitations in step 4.1.2 and the RO has one of the limitations in Steps 4.1 .I met and may exceed the limitations in and 4.1.2 has been met or exceeded. step 4.1.2, but each operator has had a break of at least eight hours between
- 2. Shift turnover time and casual work periods.
personal time noted in Step 1.4.4 may be included as part of the eight hour break between work periods.
Page 5 of 16
TQ. .-I 06-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOBPERFORMANCEMEASURE DATE:
SYSTEM: Conduct of Operations
(*Denotes a Critical Step)
STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.
STANDARD -
- evaluation) 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 Operator determines the RO deemed necessary by station watchstation is required to be staffed in management) requiring deviation from OPCON 1.
the above guidelines, such deviation (Tech Spec 6.2.2) 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 individuals name shall be listed).
-IF asked whether another RO is available, THEN INFORM the operator that due to a widespread illness, NO other ROs are available.
Page 6 of 16
TQ. -106-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned
(*Denotes a Critical Step)
- COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO.
STANDARD -
- SIU evaluation) 4.2.1 Consistent with GL 82-12, the paramount consideration in such authorization shall be that significant reductions in the effectiveness of Operator determines Attachment 1 is personnel would be highly unlikely. required to document exceeding work Authorized deviations to the working hour guidelines.
hour guidelines shall be documented on Attachment 1 (Le., each individuals name shall be listed).
4.2.2 In an emergency situation, it is acceptable to obtain a verbal overtime guideline deviation authorization prior Operator determines there is sufficient to an individual exceeding the above time to complete an Attachment 1.
guidelines and subsequently complete Attachment 1 when time allows.
4.2.3 Overtime hours worked for activities such as vacation coverage, normal shift coverage, do not constitute very Operator determines lack of operator unusual circumstances. Overtime availability due to widespread illness is worked for these types of activities unusual circumstance.
should not exceed the GL 82-12 limitations.
Page 7 of 16
TQ-. .-106-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK. Ensure the Operating Shift is Adequately Manned
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.
STANDARD -
- SIU evaluation) 4.2.4 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 Operator assesses workers for supervisor(s) will assess each alertness and signs of fatigue.
individual m e r 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.
CUE IF asked about the alertness of the operators, THEN INFORM the operator all three NIA operators appear alert and show no signs of fatigue.
Page 8 of 16
TQ .-I 06-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adeauatelv Manned
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. evaluation)
STANDARD # SIU 4.2.5 A single Overtime Guideline Deviation Authorization will be completed and Operator determines a single remain active for the entire time Attachment 1 is required to document period an individual exceeds a GL 82- exceeding work hour guidelines.
12 overtime guideline.
CUE AFTER the Operator demonstrates the ability to obtain an Attachment 1, NIA THEN PROVIDE a blank copy of Attachment 1.
4.3 When it has been determined that a deviation from the GL 82-12 overtime guidelines is necessary, then prior to Operator obtains blank Attachment 1, an individual exceeding the GL 82-12 Overtime Guideline Deviation overtime guidelines and performing Authorization.
safety-related work, initiate Examiner Note: This is included in the Attachment 1, Overtime Guideline provided copy of LS-AA-119.
Deviation Authorization. (cognizant supervisor or designee)
Page 9 of 16
TQ -106-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned
(*Denotes a Critical Step) COMMENTS STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO.
STANDARD -SIU evaluation) 4.3.1 COMPLETE columns one through Examiner Note: Refer to Exhibit Ifor four of Attachment 1. example of completed form.
- 1. If Attachment 1 is being completed Operator enters John Jones in for a large number of individuals, Column 1.
multiple forms will be required or a complete list of names may be Operator enters Operations in attached to a single Attachment 1. Column 2.
- 2. The Start Time/Date in column 4 Operator enters D in Column 3.
is the time at which an individual will (Long descriptions are also acceptable, exceed one of the overtime such as 72hrs in 7 days) guidelines, not the start of the shift GT work period. Operator enters 0600 and 2/6/09 in Column 4.
4.3.2 PROVIDE a description of the work to be performed verifying that the work Operator enters description of work.
is safety-related.
4.3.3 PROVIDE a justification describing Operator enters justification for needing why the safety-related work needs to overtime. Description may vary, but be performed on overtime. should convey unusual circumstance and not violate step 4.2.
4.3.4 SIGN Attachment 1 as the cognizant Operator signs and dates the supervisor of designee. attachment.
4.3.5 FORWARD the form to the Plant Operator seeks Plant Manager or Manager or designated manager for gpy-nvai designee approval.
- - ilI-_--
Page 10 of 16
TQ. 4 - 1 06-0303 JPM: 22009 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Ensure the Operating Shift is Adequately Manned STEP NO.
ELEMENT
(*Denotes a Critical Step)
(#Denotes a Sequential Step). I I
- EVAL I COMMENTS (RequiredforUNSAT CUE WHEN the operator forwards the Attachment for approval, THEN ROLE PLAY as the Plant Manager and approve the Attachment.
CUE 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 pIete ".
STOP TIME:
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- I06-0 3133 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 I 1 I I t -
I I I I Note 1: 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.
Note 2: The Plant Managers (or designated managers) approval shall be completed prior to an individua exceeding the overtime guidelines and performing safety related work. The Plant Managers appr wal may be received verbally by telephone. This, form is then forwarded back to the cognizant superv sor.
Note 3: The cognizant supervisor will perform an assessment of each individuals 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.
Note 4: The cognizant supervisor will complete colurnn 5 after the overtime deviation period is complete.
Note 5: GL 82-12 Overtime Guideline A - more than 16 consecutive hours to be exceeded: B - more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period C - more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period D - more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a seven day (168 hr) period E - less than an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> break between work periods 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 (ordesignated manager) Time Date Page 13 of 16
TQ-AA-106-03 33 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
The following Hope Creek Generating Station working hour history is given for an Operation:
1 crew. The hours worked are in the Main Control Room during Operational Condition 1.
Date PO JimCRS Smith JohEnes BobAdams 1/28/09 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 1/29/09 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Davs OFF
/2/2/09120urs-Davs I 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Daw 1 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 1 2/3/09 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 2/4/09 I 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 2/5/09 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-Days Today is 2/5/09.
The crew is scheduled to work a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2/6 Dayshift watch tomorrow.
Page 14 of 16
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 JPM NUMBER: 305H-JPM.ZZ017 REV#: 01
SAP BET: NOH05JPZZ17E J. Berglund DATE: A 1/8/08 DEVELOPED BY:
lnstryctor REVIEWED BY: DATE: I /L/P APPROVED BY:
STATION: Hope Creek JPM NUMBER: ZZOl7 REV: 01 SYSTEM: Conduct of Operations TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs ALTERNATE PATH: 1 KIA NUMBER: 2.1 . I 8 _-
IMPORTANCE FACTOR: 3.6 3.8 _ -
APPLICABILITY: RO SRO EVALUATION SETTINGIMETHOD: Classroom/Perform
REFERENCES:
HC.OP-DL.ZZ-0026 Rev 113 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: O S A T [7UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: -- DATE: _-
Page 2 of 11
TQ-AA- I06-030: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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 4. River temperature is 83 degF but is NOT expected to exceed 85 degF.
- 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
TQ 4-106-0303 JPM: 22017 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations ELEMENT Operator repeats back initiating cue.
HC.OP-DL.ZZ-0026( Q).
Page 4 of 11
TG t-106-0303 JPM: 22017 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Complete The Dailv Surveillance Logs
(*Denotes a Critical Step)
- COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO. # evaluation)
STANDARD SIU 2.1 Shift ManagerlControl Room Examiner Note: Examiner Copy Supervisor - the SMlCRS is Exhibit 1 is provided for reference.
responsible to implement, review, and Operator determines Attachment 1 is ensure completion of the log including required due to current Operational (CRS has primary responsibility for all Condition.
log reviews and documentation):
2.1 .IThe SM/CRS shall implement the log at the beginning of each Operator checks Attachment 1 on Attachment 1 Section A Log Initiation. I*
day by completing Attachment 1, Operator determined Attachment 3j is required due to Severe Storm Warning Section A; Log Initiation, listing that mav affect Artificial Island..
those Attachments that require performance due to present Operator checks Attachment 3j on conditions. Also, the present Attachment 1 Section A Log Initiation.
Operational Condition shall be Operator determines Attachment 3h is listed. required IAW Item 1 and T/S 4.7.1.3.b.l due to current River Water temperature.
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.
Operator places a I in the Operational Condition blank.
~
Page 5 of 11
TG &-I 06-0303 JPM: 22017 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOBPERFORMANCEMEASURE DATE:
SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs
(*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) (Required for UNSAT STANDARD evaluation) 2.1 .IThe SMlCRS shall implement Operator checks Attachment 5 on the log at the beginning of each Attachment 1 Section A Log Initiation.
day by completing Attachment Examiner Note: Although not 1, Section A; Log Initiation, specifically required by the current listing those Attachments that conditions, Attachment 5 is typically require performance due to used each day to track surveillance present conditions. Also, the procedures and would be needed the present Operational Condition first time a surveillance procedure with an action time is actually logged on.
shall be listed.
CUE 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 Page 6 of 11
TQ-AA-I 06-01 0 3 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 Pacie 1 of 1 Surveillance Log Date -___
A. LOG INITIATION I.Operational Condition 1 -
2.Check ( J ) Attachments to be performed 1 - 3c - 3g - 3m J
- 3s - 3w - 4a 2 - 3d - 3h - 3p J
- 3t J 3x - 4b 3e - 31 J 3q - 3u 3y - 4c 3f - 3k - 3r - 3v - J B. LOG PERFORMANCE
- 1. Ensure compliance with T/S by using procedure numbers and additional action.
Attachment l a Attachment 1 Auxiliary Bldg Attachment IC Reactor Bldg Attachment I d Turbine Bldg DAY EVE MID
- 3. Signature below indicates review of all required attachments checked ( 4 )above has bel A n 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
i TQ-AA-I 06-0: 03 JOBPERFORMANCEMEASURE 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-IO.ZZ-0003.
- 3. The National Weather Service has forecast a Severe Storm Warning for New Castle and Salem Counties for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 4. River temperature is 83 degF but is NOT expected to exceed 85 degF.
- 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.
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Equipment Control TASK: Authorize the Start of a Surveillance Test TASK NUMBER: 2990250302 JPM NUMBER: 305H-JPM.ZZ037 REV#: 00
SAP BET: NOH05JPZZ37E ALTERNATE PATH:
DEVELOPED BY: J. Berglund DATE: 11/7/08 Instructor REV1EWED BY:
Operations Representative APPROVED BY: I f IJd (13 I
V Training Department
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: 2.2.12 __
IMPORTANCE FACTOR: 3.7 4.1 - -
APPLICABILITY: RO SRO EO(I R o n S T A I I S R O m 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.
EST1MATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 50 Minutes JPM PERFORMED BY: GRADE: U S A T UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
-1 Page 2 of 12
I TQ-AA-106-0303 NAME: -
DATE:
SYSTEM: Eq u i p men t Contro 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 1E Buses are in a Normal 2 Bus alignment.
- 4. The A EDG was just declared INOPERABLE.
INIlIATING CUE:
This is a Time Critical JPM with one Time Critical element.
Initiate and authorize the performance of the HC.OP-ST.ZZ-0001to satisfy the one hour requirement of T/S 3.8.1 .Iaction b.
Page 3 of 12
En7@FA&py ATTACHMENT 1 TQ-AA-I 06-03t13 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 INIT1ALS 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 -
SUBSECTION(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
I TQ-AA-I 06-0: 0 3 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 IE Buses are in a Normal 2 Bus alignment.
- 4. The A EDG was just declared INOPERABLE.
INITIATING 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 .Iaction b.
Page 10 of 12
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for W te Or Steam Filled Piping TASK NUMBER: 2990740302 JPM NUMBER: 305H-JPM.ZZ032 REV#: 01
SAP BET: NOH05JPZZ32E ALTERNATE PATH:
DEVELOPED BY: J. Berglund DATE: 11/9/08 Instructor REVIEWED BY: DATE: (I(\%[
Operations Rearesentative APPROVED BY:
Train ing Department
TQ-AA-106-0303 STAT10N: Hope Creek 1
JPM NUMBER: 22032 REV: 01 SYSTEM: Radiation Control TASK NUMBER: 2990740302 TASK: Perform Leak Rate Measurement Data SI ,eet for Water Or Steam Fi red Piping ALTERNATE PATH: 1 x1 KIA NUMBER:
IMPORTANCE FACTOR: 3.8 2.3.1 I --
4.3_-
APPLICABILITY: RO SRO E O 1 1 R O F I S T A F I SROWI EVALUATION SETTING/METHOD: ClassroomPerform
REFERENCES:
HC.OP-GP.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: U S A T DUNSAT ACTUAL COMPLETION TIME: MinUtes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE: --
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 INITlAL CONDlTlONS:
- 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 1BEPISH-N654A (Panel 1OC617) AND 1BEPLR600A (Panel 1OC650).
- 4. HC.OP-GP.ZZ-0004 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION was performed to determine the leakage rate.
INITIATING CUE:
PERFORM the CRS review of the completed HCOP-GP.ZZ-0004 AND DETERMINE any required actions.
Page 3 of 26
TQ -106-0303 JPM: 22032 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Radiation Control TASK. Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping
(*Denotes a Critical Step) COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO. SIU evaluation)
STANDARD CUE PROVIDE the operator the initiating cue AND the attached prepared copy Operator repeats back initiating cue.
of HC.OP-GP.ZZ-0004.
CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue:
START TIME:
ATT. 1 POST TEST INFORMATION
- 2. I The data acquired during the performance of this test has been reviewed for completeness and Operator reviews completed compliance with Technical HC.OP-GP.ZZ-0004.
Specification 3.4.3.2, Reactor Coolant System Operational Leakage and the test is considered:
Page 4 of 26
TQ -106-0303 JPM: 22032 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping I
(*Denotes a Critical Step) COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO. SIU evaluation)
STANDARD 5.1 .I 1 CALCULATE the leak rate through 1BE-VO07 (HV-F005A) Operator recognizes a math error was by dividing the volume recorded in made when calculating Leak Rate in Step 5.1.9 by the step 5.1 .I1.
elapsed time recorded in Step 5.1 . I O . Actual leak rate is 6.3 gpm, NOT 0.63 RECORD leak rate in gpm on gpm (6.25 gpm rounded up).
Attachment 2.
data entered, CORRECT ACTUAL block as directed 2
Page 5 of 26
TQ .-I06-0303 JPM: 22032 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM:
TASK:
STEP
(*Denotes a Critical Step)
- COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.
STANDARD ## SIU eva Iuati on) 5.1 .I 1
Operator recognizes 5.1 .I 1 ACTUAL Leak Rate exceeds REQUIRED Leak Rate of 5 5 GPM.
Operator ensures 5.1 .I 1 SATWNSAT
- l block is corrected to UNSAT.
I Examiner Note: Operator may correct
, data or ca!! Performer to correct data. l l I CUE IF directed
- as Performer to correct data entered, THEN ROLE PLAY as Performer and NIA CORRECT SATNNSAT block as directed by Operator.
Page 6 of 26
TQ ,-I 06-0303 JPM: 22032 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Radiation Control TASK. Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping
~~
(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD SIU evaluation1 TIS Reactor coolant system leakage shall be limited to:
3.4.3.2 Operator determines TIS 3.4.3.2 Action
- d. 0.5 gpm leakage per nominal inch c applies:
of valve size up to a maximum of 5 gpm from any reactor coolant With any reactor coolant system system pressure isolation valve pressure isolation valve leakage greater specified in Table 3.4.3.2-1, at than the above limit, isolate the high rated pressure. pressure portion of the affected system APPLICABILITY: OPCON 1,2,3 from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed ACT1ON :
manual or deactivated automatic or
- c. With any reactor coolant system check* valves, or be in at least HOT pressure isolation valve leakage SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> greater than the above limit, isolate and in COLD SHUTDOWN within the the high pressure portion of the affected system from the low following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by Examiner Note: Determining the use of at least one closed manual SPECIFIC compensatory action is or deactivated automatic or check*
valves, or be in at least HOT beyond the scope of the JPM. It is only SHUTDOWN within the next 12 necessary for the Operator to hours and in COLD SHUTDOWN IDENTIFY the applicable Tech Spec within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Action.
Page 7 of 26
TQ ,-I 06-0303 JPM: 22032 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data S.,eet for Water Or Steam Filled Piping STEP NO.
CUE ' AFTER the Operator determines the applicable Tech Spec Action statement, THEN INFORM the Operator ATT. 1 2.1.2 UNSATISFACTORY AND Operator signs W' '"'SATISFACTORY IW IF necessary the T.S. ACTION
,.. .-, 1, .
block 2.1.2 of Attac,hmnnt statement has been implemented. I I I WHEN operator informs you the task is complete, the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.
NIA r REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".
STOP TIME: I Page 8 of 26
I TQ-AA-I 06-0313 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 06-03113 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- 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 1BEPISH-N654A (Panel 1OC617 I AND 1BEPLR600A (Panel 1OC650).
- 4. HC.OP-GP.ZZ-0004 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION was performed to determine the leakage rate.
INITIATING CUE:
PERFORM the CRS review of the completed HC.OP-GP.ZZ-0004 AND DETERMINE any required actions.
Page 10 of 26
1 PSEG Internal Use Only Page I l o f 1 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 U S E CATEGORY: I
~ ~~ ~ ~~ ~
A. Biennial Review performed Yes - No - NIA I -
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. 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.
- 2. ,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.
- 3. 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.
- 4. Section 4.0 has been changed to a bulleted list. Editorial IMPLEMENTATION REQUIREMENTS Effective date Pending closure of DCP 80040594 APPROVED: -
Manager Nope Creek Operations Date
REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION TABLE OF CONTENTS Section Title Page 1.o PURPOSE ....................................................................................... .......................... -3 2.0 PREREQUISITES ........................,........................................................................... -3 3 .O PRECAUTIONS & LIMITATIONS ........., .............................................................. 6 4.0 EQUIPMENT REQUIRED .............."........ ..............................................................
7 5 .O PROCEDURE ........................................................................................................... 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
7.0 REFERENCES
.......................................................................................................... 22 ATTACHMENTS SM/CRS Data and Signature Sheet .......................................................... 23 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 1BEPISH-N654B / 1BEPI-R600B 1BCPISH-N653A 1BCPISH-N653B 1BCPISH-N653C / IBCPI-N053C lBCPISH-N653D / 1BCPI-N053D 1BCPISH-N657 2 .O PREREQUISITES 2.1 Core Spray Loop A Iniection Header Leak Rate Test 2.1.1 Permission to perform this test has been obtained fiom the SMKRS as indicated by the completion of Attachment 1, Section 1.O.
2.1.2 All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3 .O, prior to performing any part of t h s procedure.
2.1.3 No other testing or maintenance is in progress that will adversely affect the performance of this test.
2.1.4 The Core Spray System is in a standby lineup.
2.1.5 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 1OC6 17)
Q& 1BEPI-R600A (Panel 1OCti50).
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. N d 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 1BEPISH-N654B (Panel 1OC618) 1BEPI-R600B (Panel 1OC650). 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. &lp 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 1BCPISH-N653B.
(Panel 1OC6 18) 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.
e One Graduated Cylinder ( or equivalent measuring device).
Hope Creek Page 5 of 34 Rev. 6
HC .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 AND COLLECT leakoff as follJws: E A. 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 B. 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@
C. CLOSE P-BE-V9992. s D. DETERMINE volume of fluid collected (use a graduated cylinder if necessary, AND TAKE into account any fluid dumped).
RECORD volume on Attachment 2. Ee 5.1.10 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.
5.1.11 CALCULATE the leak rate through 1BE-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 5.1.12 CLOSE P-BE-V9996 Instrument Root Valve for A Core Spray Pump discharge header pressure indicator BE-PI-4578A.
INITIAL Attachment 2. e 5.1.13 IF required, OPEN Condensate Transfer Supply to A CS Loop -
1-AP-V041. (RB 102' Rm 433 1) EE 5.1.14 OPEN Jockey Pump Supply to A CS Loop 1-BE-V088. EE 5.1.15 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 IF this
- is the first subsection of the procedure to be performed, LOG test start time in the Control Room log(s) 5.2.2 ENSURE that all prerequisites have been satisfied IAW Section 2.2 of this procedure. N/A 5.2.3 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,. N/A I 5.2.4 RECORD stop watch M&TE identification number and calibration due date on Attachment 2. N/A 5.2.5 ENSURE 1-AP-V062 Condensate Transfer Supply to B CS Loop is closed.
(RB 102' Rm 4322B) N/A 5.2.6 ENSURE 1-BE-V083 Jockey Pump Supply to B CS Loop is closed.
(RB 54' Rm 4105A) N/A 5.2.7 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 5.2.8 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 Attachment 1 - SMKRS Data and Signature Sheet 0 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 Hope Creek Page 9 of 34 Rev. 6
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 P v 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
~ \ ~ ~ . N A - A P . Z Z - O O O SStation
( Q ) ; 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.
P e w Today13 hours age.
SM/CRS DATE-TIME 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 INIT1ALS DATEITIME Joe Johnson Jim Berglund F#
- WY P=
Today13 hrs ago Today/Z hrs ago Archie Faulkner AS? Today12 hrs ago 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 1.1 Core Spray Loop A Iniection Header Leak Rate Test STEP TEST EQUIPMENT INST. TAG/MTE NO. CAL DUE DATE NOTES 5.1.4 STOPWATCH LDC-1 4/30/09 STEP NOMENCLATURE REQ POSITION PERF 5.1.7 P-BE-V9996 BE-PI-4578A ROOT VLV OPEN I W-i IME FOR PRESSURE
- The asterisk indicates acceptance criteria - in order to satis@ the requirements of the acceptance criteria, the SATIUNSAT block must be marked SAT.
STEP NOMENCLATURE REQ POSITION PERF VERIF P-BE-V9996 BE-PI-4578A ROOT VLV CLOSED F AE7 I 1 1-BE-V088 I nDEAT V I Ll'I ps AS?
5.1.15 CS LOOP A JOCK PMP TIE-IN ISLN P-BE-V9992 BE-PT-4578C ROOT VLV
~~ ~ ~
CLOSED p AS?
P-BE-V9992 CLOSED&CAPPED As?
DRT BE-PI-4578C DRAIN VLV Page 13 of 26
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition TASK NUMBER: 2000500302/2000020505 JPM NUMBER: 305H-JPM.ECG006 REV#: 04
SAP BET: NOH05JPCLOGE APPLICABILITY:
EO i ] RO F I 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 n,c IC Reportability Of An Event And/or Plant Condition ALTERNATE PATH: 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 TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15113 Minutes JPM PERFORMED BY: GRADE: U S A T DUNSA ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: I Minutes REASON, IF UNSATlSFACTORY:
EVALUATORS 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
TQ- a106-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOBPERFORMANCEMEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition
(*Denotes a Critical Step)
- COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # s/u evaluation)
I CUE 1 PROVIDE the operator the initiating cue. Operator repeats back initiating cue.
I CUE I ENTER START TIME AFTER OPERATOR REPEATS BACK I Operator obtains the correct Operator obtains Hope Creek Event procedure. Classification Guide.
ECG Section I Classification: To use this ECG volume, follow this sequence:
I. ASSESS the event andlor plant Operator assesses the initial conditions, and determines that Table 3, Fission conditions and DETERMINE Product Barriers, and 9.0, Hazards-which ECG section(s) is most InternallExternal, are the appropriate appropriate. ECG sections.
ECG 2. REFER to Section EALlRAL Flowchart diagram(s), and identify Operator refers to Table 3.0 and Section the Initiating Conditions that are Flowchart Diagrams and identifies that i.1V.C the Initial Conditions for Table 3.0 and re'ated to the event/condition that EAL 9.5.2 are related to the event that has occurred or is ongoing. has occurred.
I I I I I Page 4 of 17
TQ-. *I06-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOBPERFORMANCEMEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emerc i c y Classification And/or Reportability Of An Event And/or Plant Condition
(*Denotes a Critical Step) COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT ELEMENT NO. STANDARD s/u evaluation)
ECG 3. REVIEW the associated EALs or Section RALs as compared to the event i.1V.C and SELECT the highest appropriate emergency or reportable action level. If identification of an EAL is questionable, refer to paragraph 1V.A above. Operator reviews the EALs in section 9.5, and determines that EAL #9.5.2 is If there is any doubt with regard to the highest emergency action level met assessment of a particular EAL or or exceeded (ALERT).
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. I Page 5 of 17
TQ-b _.*-I 06-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK:
(*Denotes a Critical Step) COMMENTS STEP (#Denotes a Sequential Step) (Required for UNSAT ELEMENT NO. STANDARD evaluation)
ECG 4. If an EAL has been entered, then Section. equal level EALs or lower level i.1V.C 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 Examiner Note: Filling out the NRC Data Sheet is beyond the scope of this subsequently appear that meet JPM.
the requirements for another M L ,
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.
Table In the table review the Emergency Operator reviews the EALs of all 3.0 Action Levels of all columns and columns, and determines that all
- 1. columns need further review.
identify which need further review.
Page 6 of 17
TQ. -106-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutiesIReporting Requirements TASK: Utilize The ECG To Determine The Emerc icy Classification AndIOr Reportability Of An Event And/or Plant Condition
(*Denotes a Critical Step) COMMENTS STEP EVAL (Required for UNSAJ ELEMENT (#Denotes a Sequential Step)
NO. SIU evaluation)
STANDARD Table For each of the three barriers, Operator determines that the following 3.0 determine the EAL with the highest EALs have been exceeded and 2.
point value, and circle the EAL # and represent the highest value met or point value. No more than one EAL exceeded for the respective column:
should be selected for each barrier. 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.
Table Add the point values circled for the Operator adds the values (should be 3.0 three barriers and enter the total circled), and enters the value I O in the
- 3. appropriate space.
below:
Table Classify based on the point value sum Operator determines that this 3.0 as follows: classification is higher than the
- 4. r , I 1 classification on EAL 9.5.2 and classifies the event as a General Emergency based on Table 3.0 9,lO GENERAL ATT. 4 2
Page 7 of 17
TQ, .-I06-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emerc ncv Classification And/or Reportability Of An Event And/or Plant Condition
~~
(*Denotes a Critical Step) COMMENTS STEP (#Denotes a Sequential Step) (Required for UNSAT ELEMENT NO. STANDARD eva I uatio n)
ECG 5. The STA is responsible to Section perform an independent i.1V.C verification of the EAL IF time permits, classification. The STA THEN Operator requests STA/IA verification does not alleviate the verification of classification.
requirement of the SM to make a Examiner Note: Due to time spent timely classification. Should the assessing andlor nature of JPM SM fill the STA role, independent administration, Operator may not verification of the EAL request a verification.
classification will be delegated to another on-shift SRO.
CUE - IF the Operator requests the STAllA to independently verify the EAL Classification, NIA THEN INFORM the Operator the STAllA is not available.
~
ECG 6. IDENTIFY and IMPLEMENT the Operator identifies and implements Section referenced Attach ment under ECG Attachment 4.
i.1V.C Action Required.
Page 8 of 17
TQ -106-0303 EGG006 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK:
(*Denotes a Critical Step)
Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition
- COMMENTS ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EGG STANDARD -
evaluation)
I. EMERGENCY COORDINATOR Operator declares a General Att. 4 (EC) LOG SHEET Emergency, places the EAL # s 3.1.I .b, A. DECLARE A GENERAL 3.2.2.b or 3.2.l.b, 3.3.2.b or 3.3.2.d, EMERGENCY AT HOPE time and date in the appropriate spots CREEK in attachment 4, and initials the step as the EC.
EAL #(s) 1 3 Examiners Note: ENTER the DECLARED AT hrs on declaration time that the operator time date 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.
EGG 6. NOTIFICATIONS Att. 4
- 1. CALL the communicators to the Operator calls the communicator using Control Room the plant page.
AFTER 2 minutes, REPORT as the communicators CUE N/A and give your name as CMI and CM2.
Page 9 of 17
TQ .-106-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emergencv Classification And/or Reportabilitv Of An Event And/or Plant Condition
(*Denotes a Critical Step)
- COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT ELEMENT NO. STANDARD # s/u evaluation)
ECG 2. ACTIVATE ERO Emergency Att. 4 Operator activates the ERO.
Callout per posted instructions titled: Emergency Callout Examiner Note: This step cannot be Activation (EP96-003) simulated in the classroom.
INFORM the operator the CUE Emergency Callout System has NIA been activated.
ECG 3. MAKE A PAR as follows: Operator Refers to APPENDIX 1,
- Att. 4 determines that a GE Based 10 Points
- a. REFER to Predetermined PAR Flowchart on Pg. 3 and PAR is appropriate DETERMINE the appropriate [EVACUATE ALL SECTORS 0-5 PAR. MILES,
- b. a Radiologically Based EVACUATE DOWNWIND +SECTOR I PAR is IMMEDIATELY 5-10 MILES(ENE-E-ESE),
available, THEN COMPARE SHELTER ALL REMAINING the two PARS and choose SECTORS, 5-10 MILES].
the most appropriate for inclusion on the ICMF.
CUE IF asked, THEN INFORM the operator a NIA I
Radiologically Based PAR is not available.
Page 10 of 17
TQ .-I06-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event AndlOr Plant Condition
(*Denotes a Critical Step) COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO. SIU evaluation)
STANDARD ECG 4. COMPLETE the INITIAL Operator Completes the ICMF.
Att. 4 CONTACT MESSAGE FORM Examiners Note: See the attached (ICMF) (last page of this ICMF for an example of what the form attachment). 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 Examiners name as the Communicator or tell the Examiner to place hisiher name as the Communicator.
- 5. PROVIDE the ICMF to the Primary Communicator (CMI )
Operator provides the ICMF to CMI and DIRECT the Communicator and directs implementation of Att.6.
to implement ECG Attachment 6.
CUE LOG the time the ICMF is provided to CMI. Examiners Note: The difference between the DECLARED AT TIME LOG TIME:
and this LOG TIME is the second ROLE-PLAY as CMI and REPEAT critical time (13 min.)
BACK the direction as given.
Page 11 of 17
TQ .-106-0303 ECGOOG OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/or Reportability Of An Event And/or Plant Condition STEP ELEMENT NO.
I ECG 6. DIRECT the Secondary Att. 4 Operator directs CM2 to implement Att.8 for a GENERAL EMERGENCY.
CUE ROLE-PLAY as CM2 and REPEAT BACK the direction as given.
CUE the JPM has been terminated for other reasons, i
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 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 Todays Time ON Todays Date DECLARED AT (TIME - 24 HOUR CLOCK) (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 DESCRIPTION OF EVENT; h Loss of Fuel Clad, Reactor Coolant Boundary,
\
&\eI \ \ \ \
t inment Barriers 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 1-131 .
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.
7E+01 pCi/sec Noble Gas and 1. I 7E-02 pCi/sec 1-131.
- 9. Plant Effluent activity is 1.I 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: Perform A Shift Turnover HS On-Coming/Off-Gcdg co TASK NUMBER: 2990630301 JPM NUMBER: 305H-JPM.ZZO12 REV#: 02
SAP BET: NOH05JPU12E ALTERNATE PATH:
APPLICABILITY:
DEVELOPED BY: J. Berglund DATE: 11/2/08 Instructor Operations Resresentative APPROVED BY: DATE: /$/d5
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 IMPORTANCE FACTOR: 3.7 3.9 APPLICABILITY: RO SRO E O I ROIX] STAl-1 S R O m EVALUATION SETTINGIMETHOD: Simulator/Perform
REFERENCES:
OP-AA-112-101 Rev 2 OP-HC-112-101-1001 Rev 3 TOOLS, EQUIPMENT AND PROCEDURES: Red pen, 3lank OP-HC-112-101-1001 Attachment 6 with Control Room Key Audit initialed for Days.
ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Minutes IPM PERFORMED BY: GRADE: U S A T UUNSA ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: NIA Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS 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 1OF104 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 AShift.
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 I 9
TQ-AA-106-0303 JPM: 22012 OPERATOR TRAINING PROGRAM NAME:
Rev: 02 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Perform A Shift Turnover As On-Coming10ff-Going NCO -
NO.
STEP CUE I ELEMENT PROVIDE the operator the initiating I
(*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD
- I COMMENTS (Required for UNSAT evaluation) cue AND a blank copy of OP-HC-112-101-1001 Attachment 6 Operator repeats back initiating cue.
WITH the Control Room Key Audit completed (initialed).
Page 4 of 19
TQ-AA-106-0303 JPM: 22012 OPERATOR TRAINING PROGRAM NAME:
Rev: 02 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations
(*Denotes a Critical Step) COMMENTS STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO.
STANDARD SIU evaluation) 4.2.3 Utilize appropriate attachment from 0perato r compI ete s this document to document the OP-HC-112-101-1001 Attachment 6 turnover. 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 compI et ion.
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 JPM: 22012 OPERATOR TRAINING PROGRAM NAME:
Rev: 02 JOB PERFORMANCE MEASURE 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
I TQ-AA-106-0333 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:
DATE:
JPM Number: 22012 TASK: Perform A Shift Turnover As On-Coming10ff-Going NCO TASK NUMBER: 2990630301 QUESTION:
RESPONSE
RESULT: SAT UNSAT QUESTION:
RESPONSE
RESULT: SAT UNSAT Page 7 of 19
ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page Iof 7) [C D-42Iv]
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:
m a Offgas Train: Common PCP:
SCP:
HWCI:
8 STOP Reactor Feedwater A RFP: ANUAL B RFP: ANUAL C RFP: ANUAL Startup Valves AUTCXX@ANUA~OSE~
Reactor RWCU Pump:
RWCU Filter-Demin:
Reactor Recirc Pumps:
Recirc Control:
E A B
CRD Pumps:
CRD Stabilizer:
CRD Flow Control:
Nuclear Instrumentation APRM:
IRM:
@ma @a!3 A C E G B D F H SRM: A C B D FLOW UNITS:
RBM:
RWM: Operable Inoperable Page 8 of 19
U L J ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 2 of 7)
Turbine: Remarks TIG Oil Pump OP111 Motor Suction Pump OP108 Emergency Bearing Oil Pump OP112 EHC Pumps: B Lift Pumps: A B C D E F G H J Seals: AUX Main Generator:
Voltage Regulator: MANUAL Auto Track: OFF Stabilizer: OFF Stator Cooling: B SALEM Units On-line: a 3 Diesel Generator: A B C ChiIIed W a r :
8 8 Turbine Bldg (KI 1I ) : C TB CW Pumps: C TSC Chiller (K403): B Control Area Chiller (K400): B Ventilation:
CREF: A B FRVS Recirc: A C E B F FRVS Vent: A B Fans In Lockout:
H2/02 Analyzers: A B Fuel Pool Cooling Pumps: a B BOP System Bmass: a No (Consistent With Plant Condition)
Air Systems:
Instrument Air Dryers:
Service Air:
Emergency Instrument Air:
PCIG:
w 1OK100 1AF104 00K107 Aux Boiler: A Boiler Removed Page 9 of 19
Eaam!mG;r @Dpy ATTACHMENT 6 OP-HC-112-I01 -I001 Revision 3 Page 16 of 22 EQUIPMENT STATUS CHECKLIST (Page 3 of 7)
CORE SPRAY SYSTEM 41 Page 10 of 19
EEmdrn(3rG@py ATTACHMENT 6 OP-HC-I 12-101-1001 Revision 3 Page 17 of22 EQUIPMENT STATUS CHECKLIST (Page 4 of 7)
HPCl SYSTEM I/
Page 11 of 19
ATTACHMENT 6 EQUIPMENT STATUS CHECKLIST (Page 5 of 7)
RClC SYSTEM
+ tl-F045 x
f013 I x L ID 1 Valve Actuator 1 C I FIC-RfiOO H A H O M ~r n i c G O F059 0 0 4
FO1914405 I ro31 Y I X x I x REMARKS, ~-_______ - --
.~. .- . . .- .......
Page 12 of 19
Eaam[@@r @q-tiJy-lz;: la Page I 9 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 8RCCIRC w F065C REMARKS -
Control Key Audit Checklist Performed By: __ .
Performed By: L!kPez-Off-going Operator Initials Page 14 of 19
I.C.
r I -1 initial - _J ENSURE equipment alignment matches attached checklist.
PLACE the HPCl Flow Controller in MANUAL.
ENSURE the B SSW pump is in service.
C/T D SSW pump as follows:
I.INSERT Malfunction CW05D
- 2. START the D SSW pump and allow to trip
- 3. ACKNOWLEDGE alarms
- 4. PLACE HV-2198D in LOCKOUT
- 5. PLACE HV-2197D in LOCKOUT PREP FOR TRAINING (i.e., R M I 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.
EVENT TRIGGERS:
I I I Initial ET # Description EVENT ACTION:
1 COMMAND:
PURPOSE:
EVENT ACTION:
2 COMMAND:
PURPOSE:
Page 15 of 19
of DP501 SSW p u m p -+Delay I Ramp I
Trigger NONE I
lnit Val I
-i Final \ al REMOTElFIELD FUNCTION
SUMMARY
I 7 Delay Ramp Trigger lnit Val CW24 HV-2197D Backwash Valve breaker --- --- NONE ---
I/O OVERRIDE
SUMMARY
I I , I 1 Initial Description 5A23 A I 5A23 A2 LO DP502 OVLD/PWR FAIL light LO DP502 INOP light Delay Ramp Trigger NONE NONE lnit Val OFF i Final \ al 5A23 F LO DP502 SSW p u m p STOP --- --- NONE --- OFF I I 5A41 A LO HV-2198D OVLD/PWR FAIL 1 --- 1 --- 1 NONE 1 --- I ON I 5A41 E DI HV-2198D OPEN PB --- --- NONE ---
5A41 F LO HV-2198D CLOSE light --- --_ NONE --- OFF I I 9A2 B DI HPCl FIC-R600 AUTO Pushbutton --- --- --- 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 1AF104 lnstrumen Air Dryer is in Standby.
- 4. Salem Units Iand 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.
JOB PERFORMANCE MEASURE STATION : Hope Creek SYSTEM: Conduct of Operations TASK: Generate An S A P System Valve/Breaker Alignment TASK NUMBER: 2990090301 JPM NUMBER: 305H-JPM.ZZ030 REV#: 01
SAP BET: NOH05JPZZ30E ALTERNATE PATH:
APPLICABILITY:
DEVELOPED BY: J. Berglund DATE: 11/8/08 I tructor REVIEWED BY:
DATE: 17/12/e Operations Representative APPROVED BY: DATE: /z/dg Training Department
TQ-AA-I 06-0303 S TAT10N: 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 TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: U S A T UUNSAl ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
Page 2 of 12
I TQ-AA-106-0303 NAME: -
DATE:
SYSTEM: Conduct of Operations TASK: Generate An S A P 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
TQ-/+fi-lO6-0303 JPM: 22030 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK. Generate An SAP System ValvelBreaker Alignment STEP ELEMENT NO.
CUE SETUP Logon to the SAP Training Client Using:
User: TRAIN20 NIA Password: WELCOME9 Ensure the WCM: Area Menu is open (Fast Path ZWCMM)
CUE PROVIDE the operator the initiating cue AND the following:
0 A prepared copy of HC.OP-DL.ZZ-0015 with an Operator repeats back initiating cue.
Attachment 1 completed for Dayshift (Attached) 0 SH.WM-DG.ZZ-0015
~ _ _ _
CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue:
START TIME:
HC.OP-DL.ZZ-0015 3.6.1. PRINT a copy of the WCM Off-Normal A Report (Off-Normal and NOT Tagged)
AND FILE in the Control Room Page 4 of 12
TQ-~fi-lO6-0303 JPM: 22030 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK- Generate An SAP System Valve/Breaker Alignment
(*Denotes a Critical Step)
- COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # s/u evaluation)
Operator obtains procedure SH.WM-DG.ZZ-0015.
E necessary, THEN Operator obtains the correct Examiner Note: The procedure is only procedure. a desktop guide and the operator may be proficient at the task and NOT c
reference the desktop guide.
SH.WM-DG.ZZ-0015 N/A 5.3.6 PrintinglReviewing Off-Normal From the WCM: Area Menu Operator Clicks:
"WCM Reports" menu.
A. Click "WCM Reports" menu, Operator then clicks then click "Off Normal Report "Off Normal Report (Version 1 )'I.
(Version 1 )'I.
- 6. Complete "Object Info" section Operator enters the following Object
- for report to be obtained. Info:
Planning Plant: NNUC Plant Section: HC *
~
Mode: 01
- Type: F
- Technical Object:
- C. Select desired "Display Filter" Operator selects "Display Filter" for "Off either "Off Normal" or "Tagged" Normal" ONLY.
or both. -
Page 5 of 12
TQ-,w.-I06-0303 JPM: 22030 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Generate An SAP System ValvelBreaker Alianment
~
(*Denotes a Critical Step)
- COMMENTS STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO.
STANDARD -
- evaluation)
D. If printing report: 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 0 Under "Program" select Under "Program", Operator selects "Execute and Print". "Execute and Print".
CUE -IF in the LDC, THEN PROVIDE the Operator with an accessible SAP printer number.
PRINTER PROVIDED:
Select output device then Operator Selects an output device then cl ick T o nt inue". clicks "Continue".
E. If reviewing report, click Based on Initiating Cue, Operator "Execute". determines this step is not required.
F. Click "Back". Operator clicks "Back" to exit.
Page 6 of 12
TQ-t *~-106-0303 JPM: 22030 OPERATOR TRAINING PROGRAM NAME:
Rev: 01 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Conduct of Operations TASK: Generate An SAP System 1 ,..re/Breaker lignment STEP ELEMENT NO.
HC.OP-DL.ZZ-0015 CUE RETRIEVE printed Off-Normal AND INFORM the operator the Report has N/A been filed.
3.6.1. PRINT a copy of the WCM Off-Normal WHEN printed Off-Normal is filed, A Report THEN Operator enters time (simulated (Off-Normal and NOT Tagged) to be 03:30) AND initials Attachment 1.
AND FILE in the Control Room CUE 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:
Page 7 of 12
I TQ-AA-I 06-03C3 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
TQ-AA-I 06-0303 JOB PERFORMANCE MEASURE ATTACHMENT I (Page I of I)
TUESDAY SHIFT ROUTINE LOG Date: TODAY REQUIRED I ROUTINES I 0600-1800 -
1800 0600 1 X Shift 3.6.1.B PERFORM lamp test on all possible Sections of 10C800.
NOTE 3.6.3 MARK all Control Room strip charts (Date & Initial),
99 VERIFIED status of Paperless Recorders.
NOTIFIED I&C if Memory Space digital reading 2 20%.
99 REQUIRED ROUTINES TIME COMPLETED INITIALS (Off-Normal and NOT Tagged)
A NJ FILE in the Control Room 1800 - 0600 3.6.2 Control Room cleanup 1800 - 0600 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.
1800 - 0600 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 1E 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]
Performed By: g Y 9 Lg-....
Y Supervisor Review: 2ii 7gzA8A Y
0600-1800 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 REVlSION
SUMMARY
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 Effective date 811512008 None
I HC.OP-DL.ZZ-OO 15 (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 RESPONS181LlTY 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 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.
B. PERFORM a lamp check on all possible Sections of 10C800.
REPLACE all observed burned out bulbs.
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.
3.6.2 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.
Hope Creek 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 1E Panel Room Chilled Water System Operation.
Hope Creek Page 3 of 6 Rev. 21
NOTE I
-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 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. I 80077941 70086974 I
SH.OP-DL.ZZ-O027(Z); Temporary Reading Log & Log Supplements I HC.OP-SO.GJ-0001(Q), A(B)K400 Control Area Chilled Water System Operation.
I HC.OP-SO.GJ-O002(Q),A(B)K403 1E Panel Room Chilled Water System Operation.
Hope Creek Page 5 of 6 Rev. 21
HC.OP-DL.ZZ-O015(Q)
ATTACHMENT I (Page 1 of I)
TUESDAY SHIFT ROUTINE LOG REQUIRED ROUTINES -
0600 1800 1800 - 0600 1 X Shift 3.6.1.B PERFORM lamp test on all possible Sections of 10C800.
NOTE 3.6.3 MARK all Control Room strip charts (Date & Initial),
VERIFIED status of PaDerless Recorders.
NOTIFIED I&C if Memory Space digital reading 2 20%.
NOTE - Only recorders that are Operating or Operable need be checked.
REQUIRED ROUTINES TIME COMPLETED INITIALS 1800 - 0600 3.6.1 .A PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged)
AND FILE in the Control Room 1800 - 0600 3.6.2 Control Room cleanup 1800 - 0600 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.
1800 - 0600 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 1E Panel Room Chilled Water System Operation.. [70036044]
1800 - 0600 3.6.6 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]
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".
B. Enter functional location preceded by an "F" in the previous box, click "Enter" .
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 STAT1ON : Hope Creek SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator TASK NUMBER: 2990010101 JPM NUMBER: 305H-JPM.ZZ035 REV#: 00
SAP BET: NOH05JPZZ35E ALTERNATE PATH:
APPLICABILITY:
Eo I DEVELOPED BY: J. Berglund
- DATE: 11/I5/08 Instructor Operations Representative APPROVED B r I DATE: /d%g Training Department
TQ-AA-I 06-0303 STATION:
JPM NUMBER:
Hope Creek 22035 REV: 00 1
SYSTEM: Equipment Control TASK NUMBER: 2990010101 TASK: 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: U S A T nUNSA-ACTUAL COMPLETION TIME: MinUtes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE: -
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 CONDlTlONS:
- 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.
- 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 3 of 14
TQ-t 106-0303 JPM: 22035 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator
(*Denotes a Critical Step)
- COMMENTS ELEMENT (#Denotes a Sequential Step) VAL (Required for UNSAT STANDARD # SIU evaluation) l PROVIDE the operator the initiating cue AND:
0 The attached Operations Operator repeats back initiating cue.
information Sheet 0 A blank copy of 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.
Page 4 of 14
TQ-, 106-0303 JPM: 22035 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator
(*Denotes a Critical Step)
- COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD -
- SIU evaluation)
- COMPLETE Attachment 5 of HC.OP-DL.ZZ-O026(Q),to track allowable outage times before actions Operator enters current date on (either by Operations or other Attachment.
departments) are required.
Operator enters Order 60001 111 in ORDER block of Attachment.
- COMPLETE Attachment 5 of HC.0P-DL.ZZ-0026( Q), to track Operator enters HC.IC-FT.SK-0006 in allowable outage times before actions SURVEILLANCE NUMBER(S) block of (either by Operations or other Attachment.
departments) are required.
~
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.
Page 5 of 14
TQ-r. :106-0303 JPM: 22035 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator STEP NO.
ELEMENT I I (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD 1 . 1 I I EVAL SIU I
I COMMENTS (Required for UNSAT evaluation) 5.3.3 - COMPLETE Attachment 5 of HC.OP-DL.ZZ-O026(Q),to track block of Attachment.
CUE normally wait until the breaker was actually opened to enter a time, THEN DIRECT the Operator to 5.3.3 HC.OP-DL.ZZ-O026(Q), to track Operator enters current date and REQUIRED TI MEIDATE.
departments) are required.
Page 6 of 14
TQ-, 106-0303 JPM: 22035 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Equipment Control TASK: Perform the Watchstandina Duties of the Nuclear Control Room ODerator I
STEP
(*Denotes a Critical Step)
- COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.
STANDARD # SIU evaluation)
CUE 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 N/A the operator on the status of the JPM, and then state "This JPM is complete".
STOP TIME:
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: SAT UNSAT QUESTION:
RESPONSE
RESULT: UNSAT Page 8 of 14
TQ-A 6-0303 JOB PERFORhi, E MEASURE ATTACHMENT 5 Pane I of 1 Surveillance Log TIS Surveillance and Planned Evolution AOT Tracking Log Date: TODAY ORDER SURVEILLANCE DESCRIPTION/ TIS LCO STATUS LOG ON ACTION LOG OFF NUMBERS(S) PROCEDURE TITLE NUMBER(s) ACTIVE/ TIME/DATE REQUIRED TlMElDATE
[NOTE I] TRACKING RO INlT TIMEDATE RO INlT
[NOTE 21 60001III HC.IC-FT.SK-0006 RWCU Div 4 Leak Detection 3.6.3 ACTIVE TODAYINOW 1 TODAYINOW
+4hrs I
NOTES: I. ALL ENTRIES WHICH ARE NOT LOGGED OFF BY THE END OF THE DAY (i.e.: 0700), SHALL BE CARRIED OVER TO THE FOLLOWING DAYS 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.
- 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)
NSSSS - DIVISION 4 STEAM LEAK DETECTION TEMPERATURE MONITOR 1SKXR-11499 Order #: 60001111 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 H I BG -BG-HV-F004 is opened.
~ ~ ~~~~~ ~ ~~~
+ C l C2, RWCU SYSTEM TROUBLE
+ C8 A4, NSSSS MSlV LOGIC D INITIATED
+ C8 C4, NSSSS ISLN SIG-STM TNL TEMP HI
+ D1 E l , RRCS TROUBLE
+ D1 B3, CONTAINMENT ISOLATION VALVE O/PF
+ D3 A3, MN STM/RWCU AREA LEAK TEMP HI
+ D3 D3, LEAK DET SYSTEM TROUBLE Status Lights MCP Location: D/B RRCS
+ CHANNEL B, RRCS LOGIC A TROUBLE MCP Location: NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM 6 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
+ D3144, RWCU OUTBD ISLN HV-F004 OPF
+ D4675, CONTAINMENT ISOLATION MOV OPF
+ D5868, RWCU/MAIN ST LEAK DET TMP CH Z 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: Hope Creek SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains)
TASK NUMBER: 3660020201 JPM NUMBER: 305H-JPM.ZZ036 REV#: 00
SAP BET: NOHOSJPZZ36E ALTERNATEPATH: I I DEVELOPED BY: J. Berglund DATE: 11/I6/08 I s ctor REVIEWED BY: 4)J Operations Representative DATE: ( 2 / p(f APPROVED BY: Y Y
(=
(=
LLJ ((A, //s DATE: / & /t D Training Department
TQ-AA-I 06-0303 STA TI0N: Hope Creek -1 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 SETTING/METHOD: Perform/Classroo m
REFERENCES:
HC.OP-ST.SK-0001 Rev 7 HC.OP-DL.ZZ-0026 Rev 113 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 MinUtes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: U S A T UUNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:
EVALUA T 0 RS 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- 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 z (Provided).
The current time is 0700.
Page 3 of 34
TQ. .-106-0303 JPM: 22036 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains)
(*Denotes a Critical Step)
- COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)
NO. SIU evaluation)
STANDARD ##
CUE PROVIDE the operator the initiating cue AND:
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) I I CUE Operator repeats back the Initiating Cue; START TIME:
a Page 4 of 34
T6 *106-0303 JPM: 22036 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOB PERFORMANCE MEASURE DATE:
SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains) 1
~
(*Denotes a Critical Step) COMMENTS STEP EVAL (Required for UNSAT
(#Denotes a Sequential Step)
NO.
STANDARD SIU evaluation) 5.1.10 CALCULATE Differential Milliamp Operator calculates Differential Diff mA -
Milliamps of 0.257 0.26 and records AND Differential Time Diff Time on Attachment 2.
AND RECORD on Attachment 2, 12.393 - 12.136 = 0.257 Section 2.3.
Examiner Note: Rounding to 0.26 mA is acceptable.
~
Operator calculates Differential Time of 60 minutes and records on Attachment 2.
~
5.1 .I 1 CALCULATE Inleakage (GPM), Operator calculates inleakage of 0.0998 using formula at bottom of gpm and records 0.0998 - 0.101 on Attachment 2, Section 2.3 Attachment 2.
AND RECORD the rate, date, 0.257 x 23.31 = 0.0998 gpm AND INITIALS on the Attachment. 60 minutes Examiner Note: Rounding to 0.1 gpm is acceptable.
5.1 . I 2 RECORD required leak rate readings from Attachments IAW Operator records leak rate on HC.OP-DL.ZZ-O026(Q); Surveillance HC.OP-DL.ZZ-0026 Attachment 3z.
Log.
Page 5 of 34
TQ- -106-0303 JPM: 22036 OPERATOR TRAINING PROGRAM NAME:
Rev: 00 JOBPERFORMANCEMEASURE DATE:
SYSTEM: Radiation Control TASK: Perform Alternate RCS Leakage Determination (Floor Drains)
STEP ELEMENT NO.
CAUT Allow for enough time when obtaining the next reading so that 5.1 . I 3 the calculated leak rate is obtained NIA at least once every four hours IAW TIS 3.4.3.1 ACTION a.1.
5.1.13 CONTINUE calculating inleakage rate using steps 5.1.7 through 5.1 .I 1 UNTIL the capability to obtain leak Operator determines capability to rate information from the RMS, obtain leak rate information from RMS for Drywell Floor Drain System has is not yet available and does NOT exit returned, the procedure.
THEN PROCEED to step 5.1.29 to exit this procedure.
CUE 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:
Page 6 of 34
HC .0P- DL 7-0026(Q)
ATTACHMtdT 32 Page I of 1 Action Statement Surveillance Generic Action Statement Surveillance Sheet Applicability:
When entering a T/S Action Statement that requires increased surveillance.
Action Statement Number LDC-I Date TODAY SURVEILLANCE OPER ACCEPTABLE LIMITS COND MIN NORM MAX DAY EVE MID COMMENTS NIA NIA NIA NIA NIA NIA SURVEILLANCE OPER ACCEPTABLE LIMITS 1200 1300 1400 1500 1600 1700 Drywell Floor Drain Flow STSK-0001 1,2,3 SURVEILLANCE 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 0000 0100 0200 0300 0400 0500 0600 COMMENTS Page 7 of 34
TQ-AA-I 06-0333 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 T I 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- 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.
HOPE CREEK GENER4TING STATION Page 1of 2 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 EffectiveDate 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.
HC .0P-ST. S K-000 1( Q )
ALTERNATE RCS LEAKAGE DETERMINATION TABLE OF CONTENTS SECTION TITLE PAGE 1.o PURPOSE ..................................................................................... 2 2.0 PREREQUISITES ..................................................................................... 2 3.0 PRECAUTIONS & LIMITATIONS ......... ................ ........... ......... .................. ......... 3 4.0 EQUIPMENT REQUIRED ..................................................................................... 4 5.0 PROCEDURE ..................................................................................... 4 5.1 Determining Drywell Floor Drain Leak Rate .......................................... 4 5.2 Determining Drywell Equipment Drain Leak Rate .................................. 11 6.0 RECORDS ..................................................................................... 15
7.0 REFERENCES
..................................................................................... 15 ATTACHMENTS - OS/CRS/WCCS Data and Signature Sheet .............................................................. 16 - Inplant Data Sheet ..................................................................................... 19 - Floor Drain Sump Pumpdown Intervals .................................................................. 24 - Drywell Equipment Drain Sump Curve ................................................................... 25 Hope Creek Page 1 of 20 Rev. 7
HC .0P-ST.SK-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 JI~ to C
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 Permission to perform this test has been obtained from the OS/CRS/WCCS as indicated by the completion of Attachment 1, Section 1 .O.
2.1.2 All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3.0, prior to performing any part of this procedure. =
2.1.3 The RO/PO has been informed that the following test is to be performed .
2.1.4 No other testing maintenance is in progress that will adversely affect the performance of this test. E 2.1.5 The ability to read Drywell Floor Drain inleakage on RMS modules 1SKLI-4930 (Panel 1OC604) Q& 1SKLI-4930A (Control & Diesel Generator Bldg. El. 124') is lost. @@L 2.1.6 I&C personnel are available to connect multimeter and/or chart recorder at Panel 1DC695. P=-
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 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 2.2.2 All personnel involved in the performance of this procedure, should complete Attachment 1, Section 3 .O, prior to performing any part of this procedure.
2.2.3 The RO/PO has been informed that the following test is to be performed. NIA 2.2.4 No other testing maintenance is in progress that will adversely affect the performance of this test. N/A 2.2.5 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 2.2.6 I&C personnel are available to connect multimeter and/or chart recorder at Panel 1DC695. N/A 3.O PRECAUTIONS AND LIMITATIONS 3.1 Precautions IF at
- any time during the performance of this test, a step cannot be completed is observed to be unsatisfactory; THEN IMMEDIATELY NOTIFY the RWPO AND the OS/CRS/WCCS. [CD-927E]
3.2 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 IDC695 unless otherwise noted.
B. Junction Box 1DC695 is located in the Control & Diesel Generator Bldg. - El.
124' -Room 5448.
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 ENSURE that all prerequisites have been satisfied IAW Section 2.1.
- 5. I .3 ENSURE Attachment 1,Section I, of the OS/CRS/WCCS Data and Signature Sheet has been completed Regular Surveillance or Retest is indicated.
- 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. R 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 1SKLI-4930 and 1SKLI-4930A was by power failure to the RM-80 Motherboard or failure of 1SKLT-4931, proceed to step 5.1. I 4 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 1SKLT-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 l - If multimeter indication is offscale high low, tdOTlFY OS/CRS/WCCS that the Drywell Floor Drain Sump level may be out of normal range possible failure of ISKLT-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 / / D R W E L L 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
H C .0P-ST.S K-000 1(Q) 5.1.10 CALCULATE Differential Milliainp Diff mA AND Differential Time Diff Time AND RECORD on Attachment 2, Section 2.3.
5.1.1 1 CALCULATE Inleakage (GPM), using fonnula at bottom of Attachment 2, Section 2.3 AND RECORD the rate, date, AND INITIALS on the Attachment.
5.1.12 RECORD required leak rate readings from Attachments IAW HC.OP-DL.ZZ-O026(Q); Surveillance Log.
t CAUTIO4 5.1 -13 i
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.
5.1.14 DIRECT I&C to CONNECT a Gould Model 2200s Chart Recorder
( Iequivalent as follows:
& N/A A. CONNECT positive input of recorder to terminal 7, TB3 AND INITIAL Attachment 2, Section 2.1. N/A B. CONNECT negative input of recorder to terminal 8, TB3 AND INITIAL Attachment 2, Section 2.1. NIA C. SET recorder pin to center scale with a gain of 5 VDC per major division. N/A D. SET recorder chart speed at 5 d m i n . NIA 5.1.15 PRESS START Pb on //DRYWELL FLOOR DRAIN SUMP BT267 pump// C(D)P267 (10C650D). NIA Hope Creek Page 7 of 20 Rev. 6
HC.OP-ST.SK-0001 (Q]
NOTE 5.1 . I 6 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 OBSERVE recorder pin indicates 0 VDC while pump is running. NIA 5.1.I 7 ALLOM. pump to stop automatically on low sump level. NIA 5.1.18 RECORD on the chart the time, date and initials at point where pump stopped (chart should indicate 5 VDC). NIA 5.1.19 RECORD Pump Stop Time on Attachment 2, Section 2.2. NIA 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 5.12 0 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 5.1.21 IF there
- has not been a pumpout AND the required TIS 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reading is due THEN GO TO step 5.1.27. NIA 5.1.22 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 d m i n . ) ,
AND RECORD on Attachment 2, Section 2.2. NIA 5.1.23 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
HC.OP-ST.SK-0001 (a) 5.1.24 Using Equation on Attachment 2, Section 3.2, CALCULATE AND RECORD Inleakage (GPM), Date AND Initials on Attachment. NIA 5.1.25 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 5.1.26 RECORD required leak rate readings from Attachments IAW HC.OP-DL.ZZ-O026(Q); Surveillance Log. NIA 5.1.27 there was NOT a pumpout, THEN RECORD the Inleakage (GPM) as less than the value specified in Table 5.1.27. NIA Time from Last Inleakage (GPM) Time from Last Inleakage (GPM)
Pumpout Pumpout 5 Hours c 0.30 18 Minutes < 4.94 4 Hours 0.37 15 Minutes < 5.92 3 Hours < 0.49 2 Hours < 0.78 1 Hour < 1.48 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
HC .OP -ST.
SK-0 00 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
HC .0P-ST. SK-0 00 1(Q:
RECORDS 6.1 RETAIN the following IAW NC.NA-AP.ZZ-O003(Q); Document Management Program:
e Procedure cover page Attachment 1 - OS/CRS/WCCS Data and Signature Sheet e 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 5-373Q-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 Iof 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.
- e OS/CRS/WCCS Today/0400 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 OSICRSIWCCS DATE-TIME 2.1.2 UNSATISFACTORY AND necessary the T.S. ACTION statement has been implemented.
I OSICRSIWCCS DATE-TIME 2.1.3 Order No.
2.1.4 Remarks Hope Creek Page 13 of 20 Rev. 6
HC .OP-ST.SK-0 00 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 INITIALS DATElTlME Joe Johnson PY Today/O400 Jim Berglund Todav/0500 Archie Faulkner Today10500 Kevin Faulk Today10500 Hope Creek Page 14 of 20 Rev. 6
HC.OP-ST.SK-0001 Q)
ATTACHMENT 2 INPLANT DATA SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page Iof 5 1 .O TEST INFORMATION 2.1 Alternate RCS Leakage
- Determination Instrumentation Setup and Removal STEP TEST EQUIPMENT INST. TAGlMTE NO. CAL DUE DATE NCiTES
-~
Stopwatch LDC-I 4/30/09 5.1.4 Multimeter LDC-2 4/30/09 5.2.4 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 NCI1 5.1.29.A Lifted Lead from Term. 4, TB4 Terminated NIA NIC 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 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 NIF.
5.2.1 6.A Recorder and Multimeter (if used) Removed NIA NIP 5.2.16.A Lifted Lead from Term. 1, TB4 Terminated NIA NIP 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 Pump Start Diff. Time Inleakage Date Initials Time Time (Minutes) - (GPM)
NIA NIA NIA NIA N/A Pump Start at Hiqh Level Alarm 97.7 Gallons = lnleakage (GPM)
Diff. Minutes Hope Creek Page I 6 of 20 Rev. 6
HC.OP-ST.SK-0001t Q)
ATTACHMENT 2 INPLANT DATA SHEET ALTERNATE RCS LEAKAGE DETERMINATION Page 3 of 5 2.3 Determining Drywell Floor Drain Leak Rate Using Multimeter 5.1.8 5.1.9 5.1.10 5.1 . I 1 -
Initial Initial Final Final Diff Diff Init/
Time Mil liamps Milliam ps Time mA Time Date (Min) 06:OO ~ 12.136 12.393 07:OO
[Diff. MA) x (23.31) = lnleakage (GPM)
Diff. Time (Minutes)
Hope Creek Page 17 of 20 Rev. 6
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 Time Pump Stop Pump Start Diff. Time lnleakage Date Ini t ia i s Time Time (Minutes) (GPM) -- -
N/A NIA N/A NIA N/A NIA NIA Pump Start at Hinh Level Alarm 178.4 Gallons- = lnleakage (GPM)
Diff. Minutes Hope Creek Page 18 of 20 Rev. 6
HC .0P-ST. S K-000 IQ)
ATTACHMENT 2 ALTERNATE RCS LEAKAGE DETERMINATION INPLANT DATA SHEET Page5of5 .
2.5 Determining Drwell Equipment Drain Leak Rate Using Multimeter Time MiIIiamp s Volume Diff Diff Time Date (Gal Ions) Volume (Mi nUtes)
(Gallons)
NIA NIA NIA NIA NIA NIA NIA 3iff. Volume (Gallons) = Inleakage (GPM)
)iff. Time (Minutes)
Hope Creek Page 19 of 20 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 -= 1.0 30 Minutes > 1.O but 5 2.0 15 Minutes > 2.0 Hope Creek Page 20 of 20 Rev. 6
ATTACHMENT 32 Page 1 of 1 Action Statement Surveillance Generic Action Statement Surveillance Sheet Applicability:
When entering a TIS Action Statement that requires increased surveillance.
Action Statement Number LDC-1 Date TODAY I
I S URVElLLANCE SURVEILLANCE I OPER COND OPER COND ACCEPTABLE LIMITS MIN I NORM I MAX ACCEPTABLE LIMITS MIN NORM MAX DAY NIA NIA 0700 I I
0800 EVE NIA N/A 1 MID NIA NIA I COMMENTS Drywell Floor Drain Flow STSK-0001 1,2,3 1800 1900 2000 2100 2200 2300 0000 0100 0200 0300 0400 0500 0600 COMMENTS SURVEILLANCE OPER ACCEPTABLE LIMITS COND MIN NORM MAX 0700 0800 0900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 0000 0100 0200 0300 0400 0500 0600 COMMENTS Hope Creek Page 95 of 99 Rev1 13