ML030700330
| ML030700330 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/02/2003 |
| From: | Lanksbury R NRC/RGN-III/DRS/OLB |
| To: | Bakken A American Electric Power Co |
| References | |
| 50-315/02-301, 50-316/02-301 50-315/02-301, 50-316/02-301 | |
| Download: ML030700330 (117) | |
Text
INITIAL SUBMITTAL OF THE WALKTHROUGH JPMS FOR THE D. C. COOK EXAMINATION - NOV/DEC 2002
N02-0 1 TITLE RCCA Operability Checks NRC License Exam REVISION 0
TIME 15 Minutes DEVELOPING Name:
INSTRUCTOR(S):
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski T.Wrk_
t9/7E/0 9/7/02 91 c 1 7
-o Page 1 of 3 Revision 0
References 02-OHP-4030-STP-015 Rev 10 Full Length Control Rod Operability Test Task: 0120130201 Perform Full Length Control Rod Operability Test K/A CROSS
REFERENCE:
014 A4.02 K/A IMPORTANCE:
RO 3.4 SRO 3.2 Evaluation Setting Simulator Handouts N02-01-HO-1 Task Briefing Copy of 02-OHP-4030-STP-015 annotated to perform selected Control Rod Bank Copy of PMP-4010-job-001, Pre Job Brief Checklist (with predicted reactor response) 11 Attachments None SSimulator Setup Initialize the Simulator to an at power IC (IC 996) 100% power MOL Reset Control Rods, check Step Counters and verify Rod Bank Update is complete Page 2 of 3
Task Objectives/Standards Performs a Full Length Operability Test on Control Rod Bank 'A' lAW 02-OHP-4030-STP-01 5, observing all applicable precautions and limitations and procedural steps.
STask Brie1ng MTI has completed maintenance on the step counters for Control Bank A.
The Unit Supervisor directs you to perform a Full Length Operability test on Control Bank A in accordance with procedure 02-OHP-4030-STP-015 step 4.8.
Page 3 of 3
COURSE NUMBER N02-01 RCCA OPERABILITY CHECK REVISION: 0 AND TITLE:
Continuou-02-OHP-4030-STP-015 Rev. 10 Page 15 of 44 Full Length Control Rod Operability Test Control Rod Testing in Modes 1 and 2 Pages:
I I,,
6-22 4.8 Test Control Bank A positions as follows:
4,8.1 Record initial position of rods:
Group 1 Demand Group 2 Demand H6 HO F8K8 4.8.2 Place Full-Length Bank Selector Switch in the CONTROL BANK A position.
4.8.3 Monitor reactor power and RCS temperature during rod movement.
4.8.4 Insert Control Bank A while performing the following:
- a.
Verify the "Rods Inserting" lamp - IUT.
b:
Verify rod movement.
- c.
WHEN rod demand has moved at least 8 steps, THEN stop rod movement AND record position:
Group 1 Demand Group 2 Demand H6 Io F8 K8 4.8.5 Return rods to original position.
4.8.6 IF rods are inadvertently withdrawn past 231 steps, THEN perform Step 4.12 AND take appropriate actions specified in T/S 3.1.3.2.b.
General CUES:
- 1. Provide candidate annotated copies of:
02-OHP-4030-STP-015 Pre-Job Briefing Checklist.
- 2. If asked, all procedure prerequisites have been met.
-Correctly records position using step counters on Flux panel
-CT:
Places selector switch in correct position 7CT: Inserts all rods in the group at least 8 steps Monitors indications to verify expected results NOTE: Drop 31 "Rod Bank A low" on Panel 210 will alarm as Bank A rods are inserted, Drop 29 "Rod Sequence Violation" may alarm depending on the amount of steps rods are inserted.
Ensures each rod in group has moved a minimum of 8 steps
-Correctly records position using step counters on Flux panel
-CT:
Withdraws all rods in the group at least to original position NOTE: Drop 31 "Rod Bank A low" on panel 210 should clear
-Does not exceed 231 steps for any rod in group I Page 1 of 2 Revision 0
COURSE NUMBER N02-01 RCCA OPERABILITY CHECK REVISION: 0 AND TITLE:
Continuous 02-OHP-4030-STP-01S Rev. 10
- Pae 16 of 44 Full Length Control Rod Operability Test Control Rod Testing in Modes 1 and 2 Pages
T 6 -22 4.8.7 Record final position of rods:
Group 1 Demand Group 2 Demand H176_
H10 F8 IK8 4.8.8 Verify all rod positions are within the ARM of group demand.
4.8.9 Verify Annunciator 210, Drop 29, ROD SEQUENCE VIOLATION, is clear.
4-4.8,10 Acceptance Criteria:
Verify Control Bank A demand moved greater than or equal to 8 steps in any one direction AND all individual rod position indicators show rod motion (see Precaution 3.4 for an inoperable IR2P).
4.9 Test Control Bank B positions as follows:
4.9.1 Record initial position of rods:
Group I Demand Group 2 Demand F2 K14 B6 Plo Bl0 P6 F14 K2 4.9.2 Place Full-Length Bank Selector Switch in the CONTROL BANK B position.
4.9.3 Monitor reactor power and RCS temperature during rod movement.
Correctly records position using step counters on the Flux Panel Uses the Tech Data Book 2 Figure 13.1 or Operator Aid on Flux Panel to verify Allowed Rod Misalignment (ARM)
Verifies alarm clear Verifies test results are met Candidate reports Control Rod Bank A test is complete Evaluator: "JPM IS COMPLETE" Page 2 of 2 Revision 0
Task Briefing MTI has completed maintenance on the step counters for Control Bank A.
The Unit Supervisor directs you to perform a Full Length Operability test on Control Bank A in accordance with procedure 02-OHP-4030-STP-01 5 step 4.8.
N02-01.doc Page 1 of 1
iI N02.02IZ TITLE Raise SI Accumulator Level (with Faulted SPressure Relief Valve)
PROGRA NRC License Exam Note: JPM modified from RO-O-NO66 rev 4 REVISION 0
TIME 15 Minutes DEVELOPING Name:
INSTRUCTOR(S):
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski DAE:
9/7/02 q1 1 oz.
Page 1 of 3 Revision 0
COURSE NUMBER N02-02 Raise SI Accumulator Level (with REVISION: 0 AND TITLE:
Faulted Pressure Relief Valve)
RF REFERENCES 02-OHP-4021-008-004 Rev 10 Adjusting level of an Accumulator 02-OHP-4021-008-007, Operation of the Safety Injection Pump 02-OHP-4030-STP-030, Daily and Shift Surveillance Checks JPM: RO-O-NO66 Rev 4 Task: 0080240101: Increase an Accumulator level in Modes 1,2, or 3 K/A CROSS
REFERENCE:
006 A4.07 K/A IMPORTANCE: RO: 4.4 SRO: 4.4 EVALUATION SETTING Simulator HANDOUTS N02-02-HO-1 Task Briefing Copy of 02-OHP-4021-008-004 Attachment 3 annotated for #1 Accumulator fill w/ Lineup Sheet 2 ATTACHMENTS Caution Tag for West RHR Pump per 02-OHP-4021-008-004 Attachment 3, step 4.5.3 SIMULATOR SETUP Initialize to at power IC (IC 996) 100% power, MOL Drain #1 Accumulator until Panel 206 Drop 16 alarm is IN and NR level is 925 FT 3 Restore drain lineup to normal, adjust Accumulator pressure to 635 PSIG Fail #1 Accumulator Vent valve (2-IRV-112) closed with Override ZDI 101 IRV112 Note: Booth operator should be prepared to open 2-IRV-60 (MRF SIR 12) when requested.
Page 2 of 3 Revision 0
COURSE NUMBER N02-02 Raise SI Accumulator Level (with REVISION: 0 AND TITLE:
Faulted Pressure Relief Valve)
TASK OBJECTIVES/STANDARDS Performs a fill on #1 Accumulator, observing all applicable precautions and limitations and procedure steps.
In addition, due a faulted condition with the selected Accumulator Vent valve, the operator should recognize the inability to vent accumulator during fill evolution, determine the operational implications and mitigate system conditions by terminating the fill before accumulator exceeds the Tech Spec LCO.
TASK BRIEFING Given the following:
"* You are the "extra" RO brought in to perform this task.
"* Chemistry inadvertently drained #1 accumulator below the T.S. level limit.
"* The ACCUMULATOR 1 LEVEL HIGH OR LOW alarm is lit.
The US directs you to raise #1 accumulator level to 950 cu. Ft lAW 02-OHP-4021-008-004. The RO has completed steps 4.1 through 4.4. The South SI pump is running and the Starting Team reports all parameters are normal per 02-OHP-4021-008-004, Operation of the Safety Injection Pump. You are to begin at step 4.5.
Page 3 of 3 Revision 0
COURSE NUMBER N02-02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)
REVISION: 0 AND TITLE:
1 PURPOSE AND SCOPE 1.1 This attachment provides instructions to increase an Accumulator level with Reactor Coolant System (RCS) pressure greater than 1700 psig with the South Safety Injection (SI) Pump.
2 PREREQUISITES 2.1 Nitrogen is available to regulate the Accximulator pressure per 12-OHP 4021.030.001, Operation of the Reactor Nitrogen Gas System.
3 PRECAUTIONS AND LIMITATIONS 3.1 If during MODE 1, 2, or 3 an Accumulator level or pressure gets out of specifications, it must be returned to normal within one hour per Technical Specification (TS) 3.5. 1.
3.2 If during MODE 1, 2, or 3 an Accumulator boron concentration gets out of specifications, it must be returned to normal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per TS 3.5.1.
3.3 When adjusting Accumulator level during MODE 1, 2, or 3, the Accumulator is INOPERABLE. The level adjustment evolution shall be.
halted and the system restored per section 5.1 of this Attachment in the event that a SI signal is received during the evolution.
3.4 When adjusting Accumulator level during MODE 1, 2, or 3, care must be taken to ensure TS limits are not exceeded. Refer to 02-OHP 4030.STP.030, Daily and Shift Surveillance Checks, to ensure compliance with TS including instrument uncertainties.
3.5 If an Accumulator level is raised by 10 W or more in MODE 1, 2, or 3, it must be sampled within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> tov--tnfy boron concentration..
[Ref. 7.2. 1b.1 and 7.1.1]
3.6 A dedicated operator should be assigned to perform the Accumulator level adjustment to ensure the Reactor Operator assigned to the Control Boards is free to perform Immediate Actions of E-0 if required.
Continuous 02-ORP 4021.008.004 Rev. 10 T
Page 15 of 39 Page 1 of 5 Revision 0 Adjusting the Level of an Accumulator Raising an Accumulator Level with the RCS Pgs Pressure above 1700 psig with the South Safety Pages:
Injection Pump 15 -22 Notes To Evaluator This Alt Path JPM evaluates candidate's operational control during a routine evaluation. During refill of the accumulator, a failure of the vent valve to open prevents venting of the accumulator as level rises.
The candidate is successful if the task is performed lAW the procedure AND the fill evolution is stopped prior to exceeding the Accumulator Tech Spec LCO for level and pressure.
Operator should review limits in STP
COURSE NUMBER N02-02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)
REVISION: 0 AND TITLE:
Continuous 02-OHP 4021.008.004 Rev. 10 Page 16 of 39 Adjusting the Level of an Accumulator Raising an Accumulator Level with the RCS Pressure above 1700 psig with the South Safety Pages:
SInjection Pump 15-22 4
DETAILS INIT NOTE:
Only one Accumulator will be filled at a time in this attachment. In the event of an incident during filling requiring ECCS (e.g., Safety Injection actuation),
the evolution should be stopped and components aligned per the Corrective Actions section of this attachment.
4.1 Record Accumulator number that level is being raised:
Accumulator No.
4.2 Verify RCS pressure is greater than 1700 psig.
4.3 Verify the following valves - OPEN:
2-IMO-26 1, SI Pumps Suction from RWST 2-IMO-262, SI Pumps Recirc to RWST 2-IMO-263, SI Pumps Recirc to RWST 2-ICM-265, Safety Injection Discharge to Cold Legs 2 & 3 4.4 Start South Safety Injection Pump per 02-OHP 4021.008.007, Operation of the Safety Injection Pump.
NOTES:
If candidate stops procedure prior to completion, line-up sheet #2 provides method to secure evolution.
Operator reviews steps 4.1 through 4.4 are complete Page 2 of 5 Revision 0
COURSE NUMBER N02-02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)
TREVISION:
0 AND TITLE:
4.5 Perform the following to align the SI pump discharge flowpath:
4.5.1 Declare West RHR Pump INOPERABLE.
4.5.2 Place control switch for West RHR Pump in LOCKOUT.
4.5.3 Place a Caution Tag on the West RHR Pump control switch with the following wording:
"_Do NOT start W RHR pump in the event of SI initiation until the SI pump Cross-tie valves are open and RHR pump cross-tie valves are closed or RHR pump flows will prevent deadheading."
4.5.4 Open the following valves:
2-IMO-314, East RHR Pump Disch Xtie 2-IMO-324, West RH-IR Pump Disch Xtie I
IV A*.
IV I CAUTION:
When a Safety Injection Pump Crosstie valve is closed, Tech Spec 3.5.2.f is 7
entered and Action b is applicable.
4.5.5 Close one of the following valves:
2-IMO-270, Safety Injection Pump Disch Xtie
-OR 2-IMO-275, Safety Injection Pump Disch Xfie A
IV IV
- a.
TS 3.5.2.f (Action b): Time_
Date:
1_
4 CUE: US acknowledges West RHR Pump is INOPERABLE CT: Operator places control switch to lockout CUE: Independent verification is SAT CUE: Provide caution tag to Operator Operator places caution tag on west RHR control switch
- 27CT: Operator opens valves CUE: Independent verification is complete CUE: Acknowledge Tech Spec LCO when notified by Operator CT: Operator closes one valve.
CUE: Independent verification is complete Operator correctly records the time and date Page 3 of 5 Revision 0 Continuous 02-OHP 4021.008.004 Rev. 10 Page 17 of 39 Adjusting the Level of an Accumulator Raising an Accumulator Level with the RCS Pressure above 1700 psig with the South Safety Pages:
Injection Pump 15 - 22
COURSE NUMBER N02-02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)
REVISION: 0 AND TITLE:
Continuous 02-OH? 4021.008.004 Rev. 10 Page 18 of:
Adjusting the Level of an Accumulator Raising an Accumulator Level with the RCS Pressure above 1700 psig with the South Safety Pages:
Injection Pump 15-22 4.6 Open 2-IRV-60, SI Pumps Disch to Accumr Fill Line.
4.7 Declare the Accumulator, indicated in Step 4.1, INOPERABLE and enter Tech Spec 3.5.1 Action Item b.
Time entered:
n 4.8 Open fill valve for Accumulator to be filled AND record start time in Control Room Log:
CT Directs Aux Tour AEO to open 2-IRV-60 SIM Booth CUE: OPEN 2-IRV-60 (MRF SIR 12) and report to Operator it has been opened.
CUE: Acknowledge Tech Spec LCO when notified by Operator SOperator correctly records the time and date 2-IRV-1 11, Accum Fill Line 2-IRV-121, Accum Fill Line 2-IRV-131, Accum Fill Line 2-IRV-141, Accum Fill Line Positioni 4.9 IF regulating Accumulator pressure during fill, THEN perform the 4 following:
4.9.1 Open the nitrogen supply to the Accumulator being filled 2-IRV-112, Accum Nitrogen Supply 2-IRV-122, Accum Nitrogen Supply 2-IRV-132, Accum Nitrogen Supply 2-IRV-142, Accum Nitrogen Supply Position 4.9.2 Throttle 2-GRV-341, N2 Vent from Accumulator Tank, as necessary to regulate Accumulator pressure.
4.10 WHEN the required Accumulator level is reached, THEN perform Lineup Sheet 2.
4.11 Declare the Accumulator, indicated in Step 4. 1, OPERABLE and exit Tech Spec 3.5.1 Action Item b.
Time exited:
Date CT: Opens 2-IRV-1 11 for #1 Accumulator CUE: Acknowledge start time to be entered into the CR log by the RO Operator observes selected Accumulator level rise and level alarm clears on panel 206 Drop 16 Operators determines step is required during fill and attempts to open 2-IRV-1 12 N2 supply valve.
Operator determines 2-IRV-1 12 has failed Close, notifies US CUE: acknowledge 2-IRV-1 12 has failed closed.
CT: Operator closes 2-1RV-1 11 (on lineup sheet 2) when Accumulator level is within TS limits before Accumulator pressure is exceeds TS limit. (650 psig)
CUE: Provide Lineup Sheet 2 to Operator Operator correctly records the time and date.
TERMINATION CUE: JPM is complete Page 4 of 5 Revision 0 O
m ID Q
-4
COURSE NUMBER N02-02 Raise SI Accumulator Level (with Faulted Pressure Relief Valve)
REVISION: 0 AND TITLE:
DESCRIPTION Accum Fill Line Accum Fill Line Accum Fill Line Accum Fill Line Accum Nitrogen Supply Accum Nitrogen Supply Accum Nitrogen Supply Accum Nitrogen Supply N2 Vent from Accumulator Tank SI Pumps Disch to Accum Fill Line POSITION CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED INIT IV Record any comments during procedure use:
Verified Complete By:
Date:
/
/
Reviewed By:
Date:
/
/
Supervisor/Manager SiMature Operator correctly annotates the #1 Accumulator Fill Line and N2 Supply valves, 2-GRV-341 and 2-IRV-60 isolation valves CLOSED CUE: Independent verification is complete Page 5 of 5 Revision 0 NUMBER 2-IRV-1ii 2-IRV-121 2-IRV-131 2-IRV-141 2-ZRV 112 2-IRV-122 2-IRV-132 2-IRV-142 2-GRV-341 2-IRV-60
Task Briefing Given the following:
"* You are the "extra" RO brought in to perform this task.
"* Chemistry inadvertently drained #1 accumulator below the T.S. level limit.
"* The ACCUMULATOR I LEVEL HIGH OR LOW alarm is lit.
The US directs you to raise #1 accumulator level to 950 cu. Ft lAW 02-OHP-4021-008-004. The RO has completed steps 4.1 through 4.4. The South SI pump is running and the Starting Team reports all parameters are normal per 02-OHP-4021-008-004, Operation of the Safety Injection Pump. You are to begin at step 4.5.
N02-02 Page 1 of 1 Revision 0
N02103 TITLE Swap In-Service CCW Pump PORM NRC License Exam EVISION 0
TIME 15 Minutes DEVELOPING Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski yT. Werk 9/7/02 ec /oI2-Page 1 of 3 Revision 0
References 02-OHP-4021-016-003, Operation of the CCW System during System Startup and Power Operation Task: 0160140101: Switch operating CCW pumps K/A CROSS
REFERENCE:
008 A4.01 K/A IMPORTANCE:
RO 3.3 SRO 3.1 Evaluation Setting Simulator Handouts N02-03-HO-1 Task Briefing Copy of 02-OHP-4021-016-003 Attachment 2 Attachments None Simulator Setup Initialize at power IC (IC 996) 100% power, MOL (East CCW Pump - In Service / West CCW Pump - In Standby)
Verify prerequisites of controlling procedure are met Page 2 of 3
1 Task Objectives/Standards Performs switching of the CCW pumps, observing all applicable precautions and limitations and procedure steps.
Task Briefing The US directs you to swap the CCW pumps per 02-OHP-4021-16-003, Operation of the CCW System Startup and Power Operation.
Page 3 of 3
Reference 2,-OHP-4021-016-003 I
Rev. 13 I
Page 17 of 48 OPERATION OF THE COMPONENT COOLING WATER SYSTEM DURING SYSTEM STARTUP AND POWER OPERATION Switching CCW Pumps Pages:
14-19 4.1.10 Stop 2-PP-10W, West CCW Pump.
4.1.11 IF desired, THEN place 2-PP-10W, West CCW Pump control switch to - AUTO.
4.1.12 Verify the following valves - OPEN:
"* 2-CMO-412, CCW Pumps Discharge Crosstie Train A Shutoff Valve.
"° 2-CMO-414, CCW Pumps Discharge Crosstie Train B Shutoff Valve.
4.1.13 IF desired THEN CCW may be transferred to the West Hx by performing the following:
- a.
Open 2-CMO-420, West CCW Hx 2-HE-15W Outlet Valve.
- b.
Close 2-CMO-410, East CCW Hx 2-HE-15E Outlet Valve.
4.1.14 Verify CCW Pump flow requirements are met.
4.2 To transfer from East to West CCW Pump.
.4 4.2.1 Align ESW flow to the West CCW Hx as necessary.
"° 2-WMO-736, West CCW Hx 2-HE-15W ESW Inlet Valve OPEN.
"* 2-WMO-738, West CCW Hx 2-HE-15W ESW Outlet Valve
-THROTTLED as necessary.
4 4-General CUES:
- 1. Provide an annotated copy of 02-OHP-4021-016-003 to perform switch of CCW pumps.
- 2. Inform candidate the West CCW pump is operable Operator determines this is the correct step to begin
-Operator determines this step is necessary
-Verifies 2-WMO-736 is open (red light lit)
-CT: Throttles valve open (no specific initial intermediate position)
Evaluator Note: Initial (throttled) position of 2-WMO-738 is not critical however, this valve should be positioned in response to the high/low CCW temperature alarm (Annunciator #204, Drop 95).
Page 1 of 3 Revision 0
Reference I
'2-OHP-4021-016-003 I
Rev. 13 Pae 18 of 48 OPERATION OF THE COMPONENT COOLING WATER SYSTEM DURING SYSTEM STARTUP AND POWER OPERATION Switching CCW Pumps Pages 4.2.2 Verify the following valves - OPEN:
2-CMO-415, CCW to Misc Service Train A Shutoff Valve.
2-CMO-416, CCW to Misc Service Train B Shutoff Valve.
2-CMO-41 1, CCW Pumps Suction Crosstie Train A Shutoff Valve.
2-CMO-413, CCW Pumps Suction Crosstie Train B Shutoff Valve 4.2.3.
Verify 2-CMO-420, West CCW Hx 2-HE-15W CCW Outlet Valve - CLOSED.
4.2.4 Start 2-PP-OW, West CCW Pump.
4.2.5 Open 2-CMO-420, West CCW Hx 2-HE-15W CCW Outlet
.4 Valve.
4.2.6 Verify proper operation of 2-PP-10W, West CCW Pump.
4.2.7 IF the West CCW Pump is Operable, THEN verify at least one of the following valves - CLOSED:
"* 2-CMO-412, CCW Pumps Discharge Crosstie Train A Shutoff Valve.
-OR
"* 2-CMO-414, CCW Pumps Discharge Crosstie Train B Shutoff Valve.
4.2.8 IF the West CCW Pump is Inoperable, THEN verify the following valves - OPEN:
"* 2-CMO-412, CCW Pumps Discharge Crosstie Train A Shutoff Valve.
2-CMO-414, CCW Pumps Discharge Crosstie Train B Shutoff Valve.
Operator verifies each valve is OPEN in any order
-'Operator verifies valve is CLOSED
,-CUE: "Starting Team has verified West CCW pump is ready for start" CT: Operator starts West CCW pump
-CT: Operator opens 2-CMO-420 Operator verifies pump flow and amps have stabilized.
CUE: "Starting Team reports normal pump running parameters"
ý'CT: Operator closes one valve.
-Operator determines step - N/A (West CCW Pump is OPERABLE)
Page 2 of 3 Revision 0
Reference I '
02-OHP-4021-016-003 I
Rev. 13 1
Page 19 of 48 OPERATION OF THE COMPONENT COOLING WATER SYSTEM DURING SYSTEM STARTUP AND POWER OPERATION Switching CCW Pumps Pages:
14-19 4
4.2.9 Close 2-CMO-410, East CCW Hx 2-HE-15E Outlet Valve 4.2.10 Stop 2-PP-10E, East CCW Pump.
4.2.11 IF desired, THEN place 2-PP-10E, East CCW Pump control switch to - AUTO.
4.2.12 Verify the following valves - OPEN:
4 2-CMO-412, CCW Pumps Discharge Crosstie Train A Shutoff Valve..
2-CMO-414, CCW Pumps Discharge Crosstie Train B Shutoff Valve.
4.2.13 IF desired THEN CCW may be transferred to the East Hx by 4
performing the following:
- a.
Open 2-CMO-410, East CCW Hx 2-HE-15E Outlet Valve.
- b.
Close 2-CMO-420, West CCW Hx 2-HE-15W Outlet Valve.
4.2.14 Verify CCW Pump flow requirements are met.
FINAL CONDITIONS CCW Pumps have been switched to desired alignment.
Record any comments during procedure use:
,---CT: Operator closes valve 2-CMO-410 CT: Operator stops East CCW pump
.4 -CT: Operator places control switch to AUTO
-CT: Operator verifies valves OPEN Note: whichever valve was closed in step 4.2.7, must be manually reopened
-CUE:
US determines step is NOT desired
ý
ý-- -Operator verifies flow meets Precaution 3.2 Reports task completed.
JPM IS COMPLETE.
Page 3 of 3 Revision 0 5
5.1 C---
Task Briefing The US directs you to swap the CCW pumps per 02-OHP-4021-16-003, Operation of the CCW System Startup and Power Operation.
N02-03.doc Page 1 of 1
11: N02-04 TITLE Feed and Bleed of PRT to Lower Temperature PROGRAM:
NRC License Exam DEVELOPING Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski 0
15 Minutes 9/7/02 021o71 T/ T. Werk Page 1 of 3 Revision 0 I
COURSE NUMBER N02-04 Feed and Bleed of PRT to Lower REVISION: 0 AND TITLE:
Temperature References 02-OHP-4021-002-006, Pressurizer Relief Valve Tank Operation Task: 0020340101 Feed and Bleed PRT to reduce pressure or temperature K/A CROSS
REFERENCE:
007 A2.01 K/A IMPORTANCE:
RO 3.9 SRO 4.2 Evaluation Setting Simulator IIHandouts N02-04 Task Briefing Copy of 02-OHP-4021-002-006 Attachments 3 and 4 annotated to perform Feed and Bleed operation 1 Attachments None Simulator Setup Initialize the Simulator to at-power IC (IC 997) 100% power, MOL Insert malfunction for leaking PORV 2-NRV-151 (IMF RC 17B) at 10% severity, control leakage (using 2-NMO-151 as necessary) to raise PRT level to -86%, PRT pressure to -10 psig and PRT temperature to -127 °F.
Verify PRT level (Drop 26), PRT pressure (Drop 31) and PRT temperature (Drop 36) (Panel 210) alarms Shut 2-NMO-151 and allow RCS pressure to restore > 2200 psig Note: Booth Operator should be prepared to MRF (Waste Disposal) when requested.
Page 2 of 3
COURSE NUMBER N02-04 Feed and Bleed of PRT to Lower REVISION: 0 AND TITLE:
Temperature Task Objectives/Standards Perform Bleed and Feed on the PRT to reduce temperature from Pressurizer PORV leakage lAW 02 OHP-4021-002-006, Pressurizer Relief Valve Tank Operation, observing all applicable precautions and limitations and procedure steps.
Task Briefing 2-NRV-151 has just been identified as the leaking PORV and block valve 2-NMO-151 has been closed per 02-OHP-4022-002-009, Leaking Pressurizer Power Operated Relief Valve.
The US directs you to restore normal operating conditions in the PRT per 02-OHP-4021-002-006, Pressurizer Relief Tank Operation.
Using Attachment 3, drain the PRT to a level of 80 to 84% and using Attachment 4, perform a Feed and Bleed on the PRT to lower temperature to < 120 oF and pressure between 2 to 3 psig.
Page 3 of 3
COURSE NUMBER N02-04 Feed and Bleed of PRT to Lower Temperature REVISION: 0 AND TITLE:
LATEST REV. CHECKED Initial/Date NO. OF CS:
02-OHP 4021.002.006 ATTACHMENT NO. 3 General CUES:
DRAINING THE PRESSURIZER RELIEF TANK 1.0 PRECAUTIONS & LIMITATIONS 1.1 The hydrogen concentration must be maintained at less than 4% by volume or the oxygen concentration at less than 3% by volume to prevent occurrence of explosive mixtures in the PRT.
1.2 PRT pressure should not exceed 50 psig. The PRT rupture disc will burst at 100 psig.
2.0 INITIAL CONDITIONS 2.1 The Nitrogen System is available.
2.2 If the PRT oxygen Concentration is not within specification, the reactor coolant drain tank pumps are aligned to discharge to the 'M' CVCS holdup tanks or to the clean waste holdup tank.
2.3 PRT level and pressure instrumentation are available.
7 3.0 INSTRUCTIONS 3.1 Complete Data Sheet No, 1 if the PRT is being drained due to RCS leakage to the PRT. (Otherwise, N/A this step.)
CAUTION Positive pressure must be maintained on the PRT during draining.
3.2 Open 2-GCR-301, Nitrogen to PZR Relief TK, as necessary to maintain PAT pressure during draining.
3.3 Place Control Room switch for 2-DCR-205, RC Drain TK Outlet Train A Cntmt Isolation, to NORMAL position.
3.4 Open 2-DRV-1, Drain to RCDT.
3.5 Open 2-DCR-206, RC Drain Tank Pump Suction.
3.6 Open 2-DCR-205 to drain PRT.
3.7 If required to aid in RCDT level control, start RCDT pump(s).
INITIALS
__4
- CUE
- All initial conditions are met
- tCUE: Data Sheet No. 1 has been completed.
- -+Operator opens as needed 4
4 Operator verifies switch in Normal
-CT: Operator opens 2-DRV-1 Operator verifies 2-DCR-206 open
-CT: Operator directs AEO to open 2-DCR-205 Booth Operator Cue: Open 2-DCR-205 (MRF WDR 14)
-Operator directs AEO to start RCDT pumps as necessary Booth Operator Cue: Start pumps (MFR WDR 01 and 02)
Page 1 of 4 Revision 0
COURSE NUMBER N02-04 Feed and Bleed of PRT to Lower Temperature REVISION: 0 AND TITLE:
02-OHP 4021.002.006 ATTACHMENT NO. 3 INSTRUCTIONS INmALS 3.8 When PRT is drained to desired level, close the following valves:
4-3.8.1 2-DCR-205.
3.8.2 2-DRy-1.
Remarks Section-
-Operator stops draining PRT before reaching 78%
-Operator directs AEO to close 2-DCR-205 Booth Operator Cue: place 2-DCR-205 in auto (MRF WDR 14)
"-CT: Operator closes 2-DRV-1 Verified Complete By:
Reviewed By:
t 1
U.S./A.S.S.1S.S.
Page 2 of 4 Revision 0 Time:
Date:
I
/
Date:
/
I
COURSE NUMBER JlN02-04 Feed and Bleed of PRT to Lower Temperature AND TITLE:
SREVISION: 0 LATEST REV. CHECKED Initial/Date NO. OF CS:
02-OHP 4021-002.006 ATTACHMENT NO. 4 FEED AND BLEED OF PRT TO REDUCE PRESSURE OR TEMPERATURE 1.0 PRECAUTIONS & LIMITATIONS 1.1 PRT temperature should be maintained less than or equal to 120*F.
1.2 The hydrogen concentration must be maintained at less than 4% by volume or the oxygen concentration at less than 3% by volume to prevent occurrence of explosive mixtures in the PRT.
1.3 PRT pressure should not exceed 50 psig. The PRT rupture disc will burst at 100 psig.
1.4 PRT pressure should not exceed 10 psig when 2-RRV-103 is open.
1.5 When performing feed and bleed of PRT, nitrogen to the PRT should be available to compensate for decreases in PRT pressure due to level changes.
2.0 INITIAL CONDMONS 2.1 The Nitrogen System" is'avallable.
2.2 The Primary Water System is available.
2.3 Waste Gas Compressor is available, 2.4 If the PRT oxygen Concentration is not within specification, the reactor coolant drain tank pumps are aligned to discharge to the
'M' CVCS holdup tanks or to the clean waste holdup tank.
2.5 The Auto Gas Analyzer is in service or required actions of PMP-4030.EIS.001 are being performed.
2.8 PRT level and pressure instrumentation are available.
3.0 INSTRUCTIONS 3.1 If necessary, drain PRT per Attachment No. 3. (Otherwise, N/A this step.)
3.2 Verify running Primary Water Pump(s).
3.3 Open 2-NRV-251, Primary Water to PRT.
3.4 Place Control Room switch for 2-DCR-205, RC Drain TK Outlet Train A Cntmt Isolation, to NORMAL position.
3.5 Verify open 2-DCR-206, RC Drain Tank Pump Suction 3.6 Open 2-DCR-205.
INITIALS A
Ar r-CUE: All initial conditions are met Operator starts one or both PW pumps CT: Operator opens 2-NRV-251 Operator verifies 2-DCR-205 switch in normal Operator verifies 2-DCR-206 open CT: Operator directs AEO to open 2-DCR-205 Booth Operator Cue: Open 2-DCR-205 (MRF WDR 14)
Page 3 of 4 Revision 0
COURSE NUMBER N02-04 Feed and Bleed of PRT to Lower Temperature REVISION: 0 AND TITLE:
INSTRUCTIONS 3.7 Maintain PRT level during feed and bleed by performing the following:
Cycle 2-DRV-1, Drain to RCDT, as necessary to decrease PRT level.
If required to aid in RCDT level control, start RCDT pump(s).
Cycle 2-NRV-251 as necessary to Increase PRT level.
02-OHP 4021.002.006 ATTACHMENT NO. 4 INITIALS Operator cycles valves and pumps as necessary to lower PRT temperature to less than 120 F. The final PRT level should be between 80 to 84 %
Booth Operator Cue: MRF (WDRs) as requested NOTE 2-RRV-103 is interlocked to close when tank pressure reaches 10 psig.
3.8 Cycle 2-RRV-103, Relief Tank Vent to WDS Vent HDR, as necessary to maintain PRT pressure in normal operating range of 2 - 3 psig.
3.9 When PRT temperature or pressure has returned to desired 4
value, close 2-NRV-251.
3.10 If running, stop RCDT pump(s). (Otherwise, N/A this step.)
3.11 Close the following valves:
"- 2-DRV-1.
2-OCR-205.
3.12 Return Primary Water Pump(s) to original status.
Remarks Section:
Operator vents the PRT to maintain 2 to 3 psig SCT: Operator closes 2-NRV-251 Operator directs AEO to stop pumps Booth Operator Cue: return pumps to auto (MRF WDR 01 and 02)
CT: Operator closes 2-DRV-1
"* CT: Operator directs AEO to close 2-DCR-205 Booth Operator Cue: Place 2-DCR-205 in auto (MRF WDR14)
"Operator returns 1 PW to standby and other PW pump to auto Verified Complete By:____________________
Reviewed By:
Time:
U.S./A.S.S./S.S.
Date:
/
/
Date:
I I
Operator reports task complete JPM IS COMPLETE Page 4 of 4 Revision 0 Verified Complete By:
Reviewed By:
Task Briefing 2-NRV-151 has just been identified as the leaking PORV and block valve 2-NMO-151 has been closed per 02-OHP-4022-002-009, Leaking Pressurizer Power Operated Relief Valve.
The US directs you to restore normal operating conditions in the PRT per 02-OHP-4021-002-006, Pressurizer Relief Tank Operation.
Using Attachment 3, drain the PRT to a level of 80 to 84% and using Attachment 4, perform a Feed and Bleed on the PRT to lower temperature to < 120 oF and pressure between 2 to 3 psig.
N02-04.doc Page 1 of 1
SN0- N5 TITLE Synchronize and Load 2AB DG PROGRAM NRC License Exam REVISIONu0 TIME 20 Minutes DEVELOPING Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski S
T. Werk 9/7102
/ C/ /oZ Page 1 of 3
AB Diesel Generator Operability Test (Train B) Attachment 1 Task: 0320180201: Perform EDG Operability Test (STP-027 AB/CD)
K/A CROSS
REFERENCE:
064 A4.06 K/A IMPORTANCE:
RO 3.9 SRO 3.9 Simulator HANDOUTS NS02-05-HO-1 Task Brief Copy of Attachment 1 to 02-OHP-4030-STP-027AB with actions completed up to Step 4.18.
- 1.
NONE SIMULATOR. SETUP Initialize to at-Power IC (IC 997) 100% power, MOL Establish Trigger 1: linked to file "T21A11 Close" {ZLO101TA11(red)== 255)
Assign MALF EG07A @ 0.5 severity to Trigger 1 Start 2AB DG using the RUN control switch Adjust the DG speed to slightly less than 60 Hz Page 2 of 3 1.
- 2.
- 3.
- 4.
5.
S :::
REF E RENCE*S il 02-OHP 4030-STP-027AB, Rev 18
I,
.1 TASK OBJECTIVES/STANDARDS Synchronize and load the DG2AB to Bus T21A per 02-OHP-4030-STP-027AB.
Determine that a loss of Speed Control capability has occurred on the DG2AB, mitigate the condition by tripping or unloading and shutting down of the DG.
TASK BRIEFING You are an extra operator. The crew is performing the slow start surveillance test on the 2AB Diesel Generator. Attachment 1 of 02-OHP-4030-STP-027AB has been completed through Step 4.17. A dedicated operator is stationed locally at the 2AB Diesel Generator and is in direct communication.
The US directs you to synchronize and load the 2AB Diesel Generator, starting at Step 4.18 of.
11
COURSE NUMBER N02-05 Synchronize and Load 2AB DG REVISION: 0 AND TITLE:
Continuous I 02-OHFI-4030-STP-027AB I
Rev. 18 1
Page 25 of 144 AB DIESEL GENERATOR OPERABILITY TEST (TRAIN B)
DG2AB Slow Speed Start Pages:
1 10-35 4.15 Align one Jacket Water Pump for standby service as follows:
4,15.1 Place control switch for desired Jacket Water Pump in STOP.
4.15.2 Return control switch for desired Jacket Water Pump to AUTO.
4.16 Adjust DG Speed using DG2AB SPEED ADJUST to obtain 60 hertz AND-record the following data.
2-DGAB-SPD-IND-RB indication.
rpm 2-DGAB-SPD-IND-FB indication rpm Speed setting 4.16.1 IF Front and Rear bank speed are NOT between 500 to 530 rpm, THEN generate a Deficiency Tag to investigate..
(can be written anytime during procedure performance) 4.17 Record governor oil level.
CAUTI1ON:
Maximum phase current imbalance should not exceed 80 amps.
Maximum Current through any generator phase is 600 amps.
NOTE:
The local portions of steps 4.20 through 4.25 may be performed concurrently with step 4.18.
4.18 Load AB Diesel Generator to T21A bus, to 3500 kW as follows:
4.18.1 Place the following voltmeter selector switches in OFF position:
DG2AB Start Gen & 69/4KV Voltmeter Sel Potential DG2AB Run & Bus T21A & T21B Selector GENERAL CUE:
The 2 AB DG has been slow speed started and all actions through step 4.17 have been completed. A dedicated operator has been stationed in the 2AB DG room.
"ýOperator places both VOLTmeters to OFF position Page 1 of 3 Revision 0
Continuous 1 02-OHP-4030-STP-027AB I
Rev. 18 Page 26 of 144 AB DIESEL GENERATOR OPERABILITY TEST (TRAIN B)
Attachment I DG2AB Slow Speed Str Pages:
I 1
10-35 4.18.2 Parallel to bus T21A as follows:
- a.
Place DG2AB 4KV CB T2IAI Synch Selector in MAN position.
- b.
Adjust speed using DG2AB SPEED ADJUST so DG2AB synchroscope is rotating slowly in the FAST direction.
- c.
Adjust DG2AB Auto Volt Adjust so that diesel output, Start Gen & 69/4KV voltmeter, is 2 to 3 volts greater than Bus T21A, Run Bus T21A & T21B Volt, voltage.
d, WREN DG2AB synchroscope is between 5 minutes till 12 o'clock and 12 o'clock, THEN place DG2AB 4KV CB T21AI 1 Control switch in CLOSE position.
- e.
Check white light, Synch Permissives Met, illuminated for T21Al1.
- f.
WREN DG2AB synchroscope is between 5 minutes till 12 o'clock and 12 o'clock, THEN place DG2AB Synchronize Master Close switch to CLOSE position.
- g.
WHEN T21Al 1 closes, THEN without delay raise load with DG2AB SPEED ADJUST to 900-1100 kW load.
- h.
Place DG2AB 4KV CB T21AI I Synch Selector to OFF position.
- i.
IF running DG2AB for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> load run surveillance, THEN minimize circulating current by slowly adjusting Auto Volt Adjust until minimum amperage is obtained at the following:
"* DG2AB PH1 AMPS
"* DG2AB PH2 AMPS DG2AB PH3 AMPS
_4 CT: Operator places DG2AB 4KV CB T21A1 1 Synch Selector switch in MANUAL
-CT:
Operator adjusts speed so the Synchroscope is rotating SLOWLY in the FAST direction.
CT: Operator adjusts DG2AB run voltage is 2-3 volts higher than Bus T21A voltage.
CT: Operator closes DG2AB 4KV CB T21AI 1 control switch Operator verifies WHITE light permissive is LIT CT: Operator closes DG2AB Synchronize Master Close switch at 5 min to 12 o'clock position.
CT: Operator raises load to 900 -1100 kW DG2AB 4KV CB T21A1 1 synch selector switch in OFF CUE: The DG2AB will not be running greater than 30 minutes.
-This step is N/A Page 2 of 3 Revision 0
Continuous 02-OHP-4030-STP-027AB Rev. 18 Page 27 of 144 AB DIESEL GENERATOR OPERABILITY TEST (TRAIN B)
Attachment I DG2AB Slow Speed Start Pages:
1 10 - 35
- j.
Maintain 900-1100 kW load for approximately 10 minutes
- k.
Using DG2AB SPEED ADJUST, raise load to approximately 1750 kW
- 1.
Maintain 1750 kW load for approximately 10 minutes
- m. Using DG2AB SPEED ADJUST, raise load to approximately 2750 kW
- n.
Maintain 2750 kW load for approximately 10 minutes NOTE:
Maintain a continuous load of 3500kW on DG2AB throughout Diesel Load testing. Momentary load transients do not invalidate the diesel load test.
4.18.3 Using DG2AB SPEED ADJUST raise DG2AB load to 3500 kW.
4.18.4 Place the following voltmeter selector switches in the desired position:
"* DG2AB Start Gen & 69/4KV Voltmeter Sel Potential DG2AB Run & Bus T21A & T21B Selector 4.18.5 Record DG2AB maximum phase current imbalance:
Phase 1 Amps Phase 2 Amps Phase 3 Amps Current imbalance Amps
"-Operator monitors kW loading and reports uncontrolled load swing.
CUE: US acknowledges tripping open the T21A1 1 breaker and stopping the DG OR tripping of the 2CD DG with the Emergency Trip Pushbutton.
CT: DG2AB is unloaded/tripped by either:
"* Emergency trip pushbutton
"* Opening T21A11 Breaker and shutdown using normal control switch or emergency trip pushbutton TERMINATION CUE: DG2AB is unloaded/tripped JPM IS COMPLETE Page 3 of 3 Revision 0
TASK BRIEFING You are an extra operator. The crew is performing the slow start surveillance test on the 2AB Diesel Generator. Attachment 1 of 02-OHP-4030-STP-027AB has been completed through Step 4.17. A dedicated operator is stationed locally at the 2AB Diesel Generator and is in direct communication.
The US directs you to synchronize and load the 2AB Diesel Generator, starting at Step 4.18 of.
N02-05.doc Page 1 of 1
II
- 7 P-o6 TITLE Unit 2 CR Ventilation aligned for Unit 1 SI G
NRC License Exam DEVELOPING Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski T.Werk REV ISION TIME 15 Minutes JE:DATE 9/7/02 cl/e /o7z Page 1 of 3 Revision 0
COURSE NUMBER N02-06 Unit 2 CR Ventilation aligned for Unit 1 REVISION: 0 AND TITLE:.
Safety Injection References 02-OHP-4021-028-014, Operation of Control Room AC and Pressurization/Cleanup/Filter System Task: 0280210101: Align the Control Room Pressurization/Clean-up Filter system for standby.
K/A CROSS
REFERENCE:
072 K/A IMPORTANCE:
RO A3.01 2.9*
SRO 3.1 Evaluation Setting Simulator Handouts N02-06-HO-1 Task Briefing Copy of 02-OHP-4021-028-014 SAttachments None Simulator Setup Initialize at power IC (IC 997) 100% power, MOL Note: all Unit 2 controls will be left as-is, to require manipulation of controls during procedure implementation NOTE: Booth Operator should be prepared to initiate override for annunciator panel 201 drop 59, IAN AN01(059) with 30 second delay, when pressurization fan is started.
Page 2 of 3 Revision 0
COURSE NUMBER N02-06 Unit 2 CR Ventilation aligned for Unit 1 REVISION: 0 AND TITLE:
Safety Injection Task Objectives/Standards Align the Unit 2 CR AC and Pressurization system for a Unit 1 Sl signal, observing procedure steps and precautions and limitations of 02-OHP-4021-028-014.
In addition, due to a subsequent fire condition in the charcoal bed, the operator should respond and mitigate the conditions by implementing the actions of the Alarm Response Procedure, 02-OHP-4024 201, Drop 59.
Task Briefing A Safety Injection (SI) has occurred on Unit 1.
The US directs you to verify that the Unit 2 Control Room Ventilation system is aligned for the Unit 1 SI signal by performing 02-OHP-4021-028-014 Attachment 13.
Page 3 of 3
I REFERENCE I
02-OHP-4021-028-014 I
Rev. 14 1
Pape 55 of 68 1 Operation of the Control Room Air Conditioning and Pressuarzation/Cleanup Filter Systems I
m 3 "
Verifying Control Room Ventilation System Pages:
Attachmnent 13 Aligned For Unit I Safety Injection Signal 55 - 58 1
1.1 PURPOSE AND SCOPE Verify the Control Room ventilation/pressurization system is properly aligned following a safety injection signal from Unit 1.
2 PREREQUISITES None PRECAUTIONS AND LIMITATIONS This procedure attachment is referenced for use in the Emergency Operating Procedures. Use of this procedure as directed by the EOP series is subject to rules of usage found in OHI-4023, Abnormal.Emergency Operating Procedure User's Guide. lIRa. 7.1.21 DETAILS Verify only one pressurization fan running (circle running fan):
2-ffV-ACRF-1, West CTRL Room PRZN System OR 2-HV-ACRF-2, East CTRL Room PRZN System 4.2 Verify Control Room vent intake dampers - ISOLATED:
2-HV-ACR-DA-1, Control Room Vent Intake Damper 2-HV-ACR-DA-IA, Control Room Vent Intake Damper 4.3 Verify Control Room pressurization intake dampers - ONE PARTIAL OPEN AND ONE CLOSED:
2-HV-ACR-DA-2, CR PRZN CLN-UP Intake Damper 2-HV-ACR-DA-2A, CR PRZN CLN-UP Intake Damper INIT 4
Evaulator Information NOTE: the Unit 1 SI signal did not result in the expected realignment of the Unit 2 CR AC and Pressurization system.
The Operator will place all Unit 2 equipment in the required condition.
Shortly after the intake dampers are manually opened, a fire occurs in the control room pressurization charcoal filter bed.
CT: Operator starts nly 1 pressurization fan NOTE: Booth Operator initiates override for annunciator panel 201 drop 59, IAN AN01(059) with 30 second delay CT: Operator closes both intake dampers.
CT: Operator selects 1 damper to partial open (other damper remains closed)
Page 1 of 5 Revision 0 3
.3.1 4
4.1
REFERENCE 0o-oHP-4021-028-014 Rev. 14
.Page 56 of 68 Operation of the Control Room Air Conditioning and Pressurization/Cleanup Filter Systems Verifying Control Room Ventilation System Pages: 3 Aligned For Unit 1 Safety Injection Signal 55 - 58 4.4 Verify Control Room pressurization clean-up recirc damper - OPEN:
° 2-HV-ACR-DA-3, CR PRZN CLN-UP Recirc Damper 4.5 Verify Unit 2 Control Room cable vault hatch - CLOSED:
2-HATCH-A624-1, Aux Building El 633 U-2 Control Rm Cable "Vault Hatch Sh-Operator verifies damper open
-Operator verifies hatch closed by Panel 201 Drop 69 alarm clear OR simulates verifying hatch closed in back of Control Room Page 2 of 5 Revision 0
"*I-
02-OHP 4024.201 Level of Use: REFERENCE Drop 59 ANNUNCIATOR #201 RESPONSE: PLANT FIRE SYSTEM CTRL RM PRZN CHAR FILTER FIRE OR ABN 1.0 PROBABLE CAUSE(S):
1.1 Fire or overheating in Control Room pressurization charcoal filter.
1.2 Detection circuit trouble.
1.3 Pilot solenoid valve isolation switch in isolate position.
2.0 AUTOMATIC ACTION(S):
4 2.1 Actuation of the water deluge will:
Open isolation valve 12-ZMO-10, Yard Fire Hdr to Aux Bldg Open isolation valve 12-ZMO-20, Turb Bldg Fire Hdr to Aux Bldg Open water valve 2-ZRV-24, Fire Protection water to Control Room Ventilation Unit HV-ACRF Charcoal Filters control valve Actuate Annunciator 101, Drop 41 Actuate Annunciator 201, Drop 41 Operator reviews probable causes I Operator reviews automatic actions Page 3 of 5 Revision 0 INITIATING DEVICE(S)
NOMINAL AEP Alias SETPOINT Fire detection 2-ZTA-24 170 'F alarm 2-TMS-CF-ACRF, 400 'F operating LOCAL/CTRL CAB START Push
- Button, Selector switch 2-29-CPRF in ISOLATE
02-OHP 4024.201 Level of Use: REFERENCE Drop 59 3.0 OPERATOR ACTION(S):
3.1 Check Alison cabinet on 650 elevation of Auxiliary Building for cause of alarm.
3.2 Check filter housing in the Control Room ventilation equipment room.
3.3 IF amber PREALARM lamp is LIT, THEN:
3.3.1 Open 2-FP-283, Fire Protection water to Ventilation Unit 2-HV ACRF Charcoal Filter manual shutoff valve.
3.3.2 Open 2-DR-174 and 2-DR-198, Control Room Ventilation Unit 2 HV-ACRF Drains to Turbine Room Sump shutoff valves.
3.4 IF red System Operating lamp is lit, THEN:
S...
aaCAUTION IF a radiological emergency (LOCA, fuel handling accident) is in progress, then the Control Room pressurization fans shall not be sto~ped, unless fire or smoke is confirmed.
3.4.1 Place control switches for Control Room Pressurization Fans 2-HV-ACRF1 and 2-HV-ACRF2 in OFF.
3.4.2 Verify 12-ZMO-10, Yard Fire Hdr to Aux Bldg - OPEN.
3.4.3 Verify 12-ZMO-20, Turb Bldg. Fire Hdr to Aux Bldg - OPEN.
3.4.4 Verify 2-ZRV-24, deluge valve to Control Room Pressurization Fa%_
Filter - OPEN.
- a.
Monitor the ventilation unit to ensure the filter housing is draining as expected, to prevent overfilling and flooding of the ductwork to the Control Room.
3.4.5 Notify fire brigade:
- a.
Sound fire siren
- b.
Page fire brigade at pager #9999 3.4.6 Announce the location of the fire on PA and establish fire*
information line on extension I801.
Operator directs AEO to 650' of Aux Building IOperator directs another AEO to CR Ventilation Equipment Room CUE: Booth Operator reports as AEO that an amber PREALARM and red SYSTEM OPERATING lamp is lit NCT: Operator directs AEOs to open 2-FP-283, 2-DR-174 and 198 CUE: Booth Operator reports as AEO that smoke is observed in the CR ventilation filter housing CT: Operator places CR pressurization fans in stop CT: Operator opens 12-ZMO-10 and 20 with control switch
-Operator directs AEO to verify 2-ZRV-24 opens CUE: Booth Operator reports as AEOs that 2-ZRV-24 is open and the filter housing is draining properly
-Operator sounds the fire siren and simulates notifying the fire brigade.
Operator simulates PA announcement Page 4 of 5 Revision 0
02-OHP 4024.201 Level of Use: REFERENCE Drop 59 3.4.7 When the fire is extinguished;
- a.
Announce on the PA that the fire is out.
- b.
Ensure requirements of ATR# 2-FP-3 are met.
- c.
Close and seal 2-FP-283.
- d.
Reset fire system.
- e.
After filter housing is drained, close 2-DR-174 and 2-DR-198.
3.5 IF alarm is spurious, or no fire exists, THEN place control switches for both Control Room Pressurization Fans in.AUTO.
3.6 IF trouble condition exists, THEN:
"3.6.1 Check power supply to fire system.
3.6.2 Check isolation switch for charcoal filter fire detection system.
CUE: Fire is out JPM IS COMPLETE.
Page 5 of 5 Revision 0
Task Briefing A Safety Injection (SI) has occurred on Unit 1.
The US directs you to verify that the Unit 2 Control Room Ventilation system is aligned for the Unit 1 SI signal by performing 02-OHP-4021-028-014 Attachment 13.
N02-06.doc Page 1 of 1
NoN02-07 --j TITLE Energize SR Detectors and Audio Count Rate O
NRC License Exam REVISION 0
TIME 15 Minutes DEVELOPING Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski
~yT. Werk DATE.
917/02 C) / z Page 1 of 3 Revision 0
COURSE NUMBER N02-07 REVISION: 0 AND TITLE:
EnerizR toaAo u
a
- :Energize SR Detectors and Audio Count Rate References 02-OHP-4023-ES-1.2, Post LOCA Cooldown And Depressurization 02-OHP-4021-013-005, Visual Audio Count Rate Channel (NIS)
Task: 0130010501: Energize Source Range NIS 0130140101: Energize the Audio Count Rate Channel K/A CROSS
REFERENCE:
015 K/A IMPORTANCE:
Evaluation Setting Simulator IIHandouts N02-07 Task Briefing Field Copy of 02-OHP-4023-ES-i.2 I
Attachments None 11Simulator Setup Post Trip conditions with snap # IC 995 (-850 PSIG, -405 OF CETCs, ES 1.2 step 25)
Malfunction: NI07A (severity 0%) N-35 failed high due to under compensated.
RC10B (severity 50%) -750 GPM SBLOCA (run for - 90 minutes to be in ES 1.2)
Page 2 of 3 Revision 0
COURSE NUMBER N02-07 REVISION: 0 AND TITLE:
Energize S S.........
IEnergize SR Detectors and Audio Count Rate
- 'i Task Objectives/Standards 11 Manually energize the Source Range Detectors and Audio Count Rate, observing all applicable precautions and limitations and procedure steps.
Task Briefing 90 minutes ago a reactor trip and safety injection were actuated in response to a RCS leak (small break LOCA) inside containment.
The US has directed you to check if the Source Range detectors should be energized per ES 1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, step 29.
Page 3 of 3 Revision 0
COURSE NUMBER N02-07 AND TTLE:
Energize SR Detectors and Audio Count Rate REVISION:
STP ACTION/SxPECTED RESPONSE RESPONSE NOT OBTAINED
- 29.
Check If Source Range Detectors Should Be Energized:
- a. Intermediate range flux LESS THAN 6x10- 1 AMPS
- b. Source range detectors ENERGIZED
- c. Transfer SG-12 to source range scale
- d. Energize audio count rate channel:
- Refer to 02-OHP 4021.013.005, Visual Audio Count Rate Channel (NIS)
Section 4.1, Setup For Mode 6 Operation
- a. WEW flux is less than 6x10- 1 1 amps, THim do Steps 29.b through 29.d.
Continue with Step 30 (Page 38).
- b. Manually energize source range detectors.
14 4-Evaluator Information:
Since the Reactor tripped occurred -90 minutes ago, the operator should expect both Source Range detectors to have auto energized. The under compensation malfunction on N-35 IR results in the channel reading high, while the unaffected IR Channel will indicate <6 X 10-11 AMPS and the 2/2 (P-6) logic NOT satisfied.
-Operator determines N-36 IR Channel is < 6 X 10-11 AMPS (and that N-35 is reading erroneously high).
-CT: Operator determines the Source Range Detectors are NOT energized, momentarily places either "SOURCE RANGE TRIP BLK & RESET" switch to "UNBLOCK" position Operator places either or both Red pen and Blue pen Neutron Flux Recorder Selector Switches to "SRI" and/or "SR2" position(s)
-Operator obtains copy of 02-OHP-4021-013-005 CUE: Provide Operator with copy of 02-OHP-4021-013-005 Page 1 of 3 Revision 0 I.
--q
COURSE NUMBER N02-07 REVISION: 0 AND TITLE:
Energize SR Detectors and Audio Count Rate Reference I
Rev. 6 Page 4 of 16 VISUAL AUDIO COUNT RATE CHANNEL (NIS)
Setup of Audio Count Rate Channel Pages:
1 PURPOSE AND SCOPE 1.1 This attachment provides direction for setting up Audio Count Rate Channel. Upon completion there will be visual/audible indication in the control room and audible indication in containment.
2 PREREQUISITES 2.1 None.
3 PRECAUTIONS AND LIMITATIONS 3.1 Source assembly movement during core alterations may reduce audible count rate suddenly. Adjustment of audio multiplier setting may be needed to maintain audio count rate signal.
4 DETAILS 4.1 Place scaler timer POWER switch in ON position.
4.2 Check the following lights are lit on AUDIO COUNT RATE CHANNEL drawer:
AUDIO POWER ON SCALER POWER ON 4.3 Place CHANNEL SELECTOR switch to desired source range channel.
4 4.4 Place SAMPLING MODE selector switch in the following positions:
"* COUNT position on DISPLAY side SEC position on PRESET side 4.5 Volume control may be adjusted during sampling to any position that results in a comfortable volume for the audible count rate, Operator checks scaler timer "POWER" toggle switch in the "UP" position Operator checks lights lit
-Operator checks Channel Selector switch in "SRN31" or "SRN32" position
-Operator checks sampling mode switch in "COUNT/SEC" position Operator checks "VOLUME" switch in any position Page 2 of 3 Revision 0
COURSE NUMBER Ne02-07 REVISION:C0ta AND TITLE:ý Energize SR Detectors-and Audio Count Rate EIIN Reference 02-OHP-4021-013-005 Rev. 6 Page 5 of 16 VISUAL AUDIO COUNT RATE CHANNEL (NIS)
Setup of Audio Count Rate Channel Pages:
T4-5 NOTE In the current configuration, the thumbwheels enter time values to the nearest tenth of a second.
4.6 Position thumrbwheels to 00600 or other value as desired.
4.7 Place SAMPLING MODE toggle switch in AUTO.
4.8 Press the following pushbuttons:
4.8.1 STOP 4.8.2 RESET 4.8.3 START 4.9 Check GATE light is lit. "
q
] IF GATE light is NOT lit, THEN notify I&C.
4.10 Place AUDIO MULTIPLIER switch in a position that results in a distinguishable gap between counts. (This step N/A if source range detectors are deenergized,)
4.11 Verify count rate indication is audible in the following [Ref. 7.2.1a]:
° Control Room (This step N/A if source range detectors deenergized)
Containment (Mode 6 only)
Operator checks thumbwheels set to 00600 Operator checks sampling mode toggle switch in "AUTO" position Operator depresses the pushbuttons CT: "START" pushbutton is the critical portion of this step Operator checks gate light lit Operator adjusts audio multiplier switch to produce a distinguishable gap in audio output Operator determines Containment is N/A Reports task completed.
JPM IS COMPLETE.
Page 3 of 3 Revision 0 I
Task Briefing 90 minutes ago a reactor trip and safety injection were actuated in response to a RCS leak (small break LOCA) inside containment.
The US has directed you to check if the Source Range detectors should be energized per ES 1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, step 29.
N02-07.doc Page 1 of 1 Revision 0
08 Isolate SI Accumulators during Post LOCA Cooldown and Depressurization NRC License Exam DEVELOPING INSTRUCTOR:
Name:
Signature:
0 15 Minutes DATE0 9/7/02 R. Niedzielski OPERATIONS REVIEW:
Name:
Signature:
Page 1 of 7 C :ioz-T. Werk
,COURSE NUMBER N02-08 Isolate SI Accumulators during Post REV I ISION: 0 AND TITLE:
LOCA Cooldown and Depressurization/IF-IF RREFERENCES 02-OHP-4023.E-1, Loss of Reactor or Secondary Coolant Task: 0080020101: Isolate Accumulators K/A CROSS
REFERENCE:
006 A4.02 K/A IMPORTANCE:
RO 4.0*
SRO 3.8 VALUATION SETTINGS Simulator IF -
HANDOUTS_
- 1.
N02-08 Briefing Sheet
- 2.
Copy of 02-OHP 4023.E-1, Step 25 ATTACHMENTS
- 1.
NONE H
~SIMULATOR SETUP, Post Trip conditions with snap # IC 995 (-850 PSIG, -405 'F CETCs, ES 1.2 step 25)
Malfunction: RC10B (severity 50%) -750 GPM SBLOCA (run for - 90 minutes to be in ES 1.2)
- 1.
Insert Override ZDI101 IMO120 to OPEN
- 2.
Verify ALL Accumulators have injected then FREEZE the simulator Page 2 of 3 I1 I
COURSE NUMBER N02-08 Isolate SI Accumulators during Post REVISION:.
0 AND TITLE:
LOCA Cooldown and Depressurization TASK OBJECTIVES/STAND)ARDS Operator has successfully isolated or vented ALL four accumulators per procedure ES 1.2 step 25.
TASK BRIEFING You are an extra RO. The unit has experienced a small break LOCA. The crew has transitioned from E-A, Loss of Reactor or Secondary Coolant to ES-1.2, Post LOCA Cooldown and Depressurization.
The Unit Supervisor directs you to perform Step 25 of ES-1.2 to check if accumulators should be isolated.
11
COURSE NUMBER N02-08 Isolate SI Accumulators during Post LOCA Cooldown and AND TITLE:
Depressurization REVISION: 0 Number:
Title; Revielon Number:
02-OHP 4023 OST LOCA COO OWNA MUD ES-1.2 DEP SURIZA.TION 6
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25.
Check If Accumulators Should Be Isolatedt
GREATER THAN 36OF
- b. PRZ level -
GREATER THAN 19% 122% ADVERSE]
- a. XF.at least two RCS hot leg temperatures are less than 3550 F, THEN go to Step 25.c.
XR at least two RCS hot leg temperatures are NOT less than 355-F, TWE go to Step 26 (Page 35).
- b. Return to Step 13 (Page 15).
OBSERVE NOTES PRIOR TO Step 13.
- c. Locally restore power to accumulator outlet valves:
- 2-IMO-I10 (2-EZC-C-5C)
- 2-IMO-120 (2-EZC-B-IC)
- 2-IMO-130 (2-EZC-D-IC)
- 2-IMO-140 (2-EZC-A-SC)
(Step 25 Conriinued On Next Page)
Evaluator Information:
- 2 and #3 Accumulators isolation valves are faulted and will not close. The RNO column actions will be required to vent N2 pressurE to complete step 25.
Operator checks RCS subcooling >36 0F Operator checks Prz level >19%
CT: Operator directs Aux Operator to restore power CUE: Local Aux Operator will restore power as directed CUE: Booth Operator delete global malf 101IMO110, 101 IMO120 and 1011M0140.
CUE: Report back to Operator that all breakers are energized except 2EZC-D-1C (for 2-IMO-130) which tripped free (would not stay closed).
Page 1 of 2
COURSE NUMBER N02-08 Isolate SI Accumulators during Post LOCA Cooldown and REVISION: 0
. AND TITLE:
l*Depressurization IN ube r TeW is:e 02-oHP 4023 POIST LOCA COOLDOWNAMqDRv~o ubr ES-i.2 DERPflEURIZATION 6
(Step 25 Continued From Prevlou=
.Page
- d. Close all accumulator outlet valves 4---
- d. Vent any unisolated accumulator(s):
-CT: Operator closes 2-IMO-110 and 2-1M0140 (2-IMO-120 will not close)
-Operator determines RNO is needed for #2 and 3 Accumulators
- 1) Close 2-GCR-314, accumulators N2 supply
-- -CT: Operator CLOSES: 2-GCR-314
- 2) Open 2-GRV-341, N2 vent accumulators.
- 3) Open nitrogen supply valve for unisolated accumulator(s):
- 2-IRV-112
- 2-IRV-122
- 2-IRV-132
- 2-I1RV-142 IF.any accumulator can WA#r isolated or vented, Two consult Plant Evaluation Team to determine subsequent actions prior to any RCS depressurization below 800 paig.
Continue with Step 26 (Page 35).
CT: Operator OPENS 2-GRV-341 CT: Operator OPENS: 2-IRV-122 and 2-IRV-132 NOTE: Annunciator Panel 205 Drops 31 and 32 may alarm as the Accumulators are vented (containment pressure high alarms).
TERMINATE JPM: When Panel 206 Drops 22 and 23 are acknowledged (accumulator 2 & 3 low pressure alarms)
JPM IS COMPLETE.
Page 2 of 2
Task Briefing You are an extra RO. The unit has experienced a small break LOCA. The crew has transitioned from E-1, Loss of Reactor or Secondary Coolant to ES-1.2, Post LOCA Cooldown and Depressurization.
The Unit Supervisor directs you to perform Step 25 of ES-1.2 to check if accumulators should be isolated.
Page 1 of 1 NO2-O8.doc
1 09, TITLE Restore RCP Cooling during Post LOCA
[Cooldown and Depressurization P
GRAM NRC License Exam DEVELOPING, INSTRUCTOR:
Name:
Signature:
0 15 Minutes DATE:
917/02 R. Niedzielski OPERATIONS REVIEW:
Name:
Signature:
-&T.
Werk'A 9 17 0Z-Page 1 of 3 Revision 0
COURSE NUMBER N02-09 Restore RCP Cooling during Post LOCA REION0 AND TITLE:
Cooldown and Depressurization
[References 02-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization.
02-OHP-4023 SUP.007, Restoration of RCP cooling Task: 0020030501: Restore RCP support systems following containment isolation K/A CROSS
REFERENCE:
003 A4.08 K/A IMPORTANCE:
RO 3.2 SRO 2.9 I Evaluation Setting Simulator JIHandouts I
N02-09 Task Briefing Copy of 02-OHP-4023-ES1.2, Step 27 Attachments None Simulator Setup Post Trip conditions with snap # IC 995 (-850 PSIG, -405 0F CETCs, ES 1.2 step 25)
Malfunction: RC1 OB (severity 50%) -750 GPM SBLOCA (run for - 90 minutes to be in ES 1.2)
CCW isolated to RCPs Page 2 of 3 Revision 0
COURSE NUMBER',
N02-09 Restore RCP Cooling during Post LOCA REVISION: 0 AND TITLE:*
Cooldown and Depressurization 1 Task Objectives/Standards Establish normal cooling to RCPs in accordance with SUP.007, Restoration of RCP cooling.
Task Briefing The plant has responded to a Small Break LOCA and the actions of E-0, Reactor Trip or Safety Injection and E-1, Loss of Primary or Secondary Coolant have been completed. The US has transitioned to ES-1.2, Post LOCA Cooldown and Depressurization.
The US directs you to perform step 27, of ES-1.2 to check RCP cooling.
Page 3 of 3
02-HP 4023OT LOCA COOLDOWN AMn r
ES-1.2 DEPRESSURIZAON s
STEP ACTION/EXPECTED RESPONSE lIRESPONSE NOT OBTAINED I General CUES:
- 26.
Check If DGs Should Be Stopped:
- a. AC emergency buses ENERGIZED BY OFFSITE POWER
- 'T21A
- T21B
- T21C
- T21D
- b. Stop any unloaded DG and place in standby
- c. Locally stop jacket water pumps for shutdown DG(s) and place in AUTO
- 27.
Check ReP Cooling -
UOmL
"* CCW flow:
"* Lower bearing AT LEAST 5 GPM
"* Thermal barrier AT LEAST 35 GPM
"* Upper bearing AT LEAST 97.5 GPM
"* Seal injection flow 6 TO 12 GPM
- a. Try to restore offaite power to AC emergency buses using SUP.002, Restoration of Reserve Power to 4KV Buses.
Establish normal cooling to RCPs using SUP.007, Restoration of RCP Cooling.
-Operator determines the need to go to the RNO column and use SUP.007 to restore RCP cooling based on current plant conditions (No CCW flow).
CUE: Provide operator copy of SUP.007.
Page 1 of 4 Revision 0 COuRSE NUMBER N02-09 Restore RCP Cooling during Post LOCA Cooldown and Depressurization REVISION: 0 oAND TITLE:
'SE AGTION/EXPECTED RESPONSE. ý-
RESPONSE NT0RIE If RCP seal parameters have been exceeded, seal injection and CCW thermal barrier cooling should iYT be established to the RCPs.
- 1.
check RcW seal Performm the followi~
Temperaturzes -
NORURL
-C t Te.-
"RCP Seal 1 Outlet Te-p thermal barrier valves:
High" annunciators -
HAVE REMAINED CLEAR
- 2-CCM-453
"* Panel 207, Drop 14 (RCP 1)
"* Panel 207, Drop 34 (RCP 2)
"* Panel 207, Drop 74 (RCP 3)
- 2-CCM-454 IF at least one valve can Wr be manually closed, T
locally close one valve
- b. Return to procedure and step in effect,
- Panel 207, Drop 94 (RCP 4)
Lower bearing water temperatures -
HAVE REMAINED LESS THAN 225oF Indicator 2-QTI-210 2-OTI-220
-t 4
2-OTI-230 2-QTI-240 Point T0417A T0437A T04S7A T0477A Operator checks the annunciators clear CUE: Alarms have remained clear
-Operator checks the lower bearing water temperatures are less than 225 OF CUE: Temperatures have been stable at the observed values Page 2 of 4 Revision 0 RCP RCP 1 RCP 2 RCP 3 RCP 4
COURSE NUMBER N02-09 Restore RCP Cooling during Post LOCA Cooldown and Depressurization REVISION: 0 AND.TITLE:,
02-0HP 4023 SUP.007
-,S'TOIAnONOF RCOP COOLING
fl
N/EXPEcSPONSE
SE NOT
- 2.
Rstablixh CCI Flow To RflPs=
- a. Check -RCP Therm Barr Clg Wtr Temp High annunciators - HAVE REMAINED CLE.AR o Panel 207, Drop 8 (RCP 1)
- Panel 207, Drop 28 (RCP 2)
- Panel 207, Drop 68 (RCP 3)
- Panel 207, Drop 88 (RCP 4)
- a. Return to proced-sep in eff.
- 2-CCM-458
- 2-CCM-459
.S thermal barriers valves:
- 2-CCM-453
- 2-CCM-454
oil cooler valves:
- 2-CCM-451
- 2-CCM-452 Operator checks the annunciators are clear E: Annunciators have remained clear
- Operator OPENS both valves in any order Operator OPENS both valves in any order
-T-CT: Operator OPENS both valves in any order Page 3 of 4 Revision 0 Am
- --- CT:
COURSE NUMBER.
N02-09 Restore RCP Cooling during Post LOCA Cooldown and Depressurization REVISION: 0 AND TITLE:
STE ACTION/FXPECTE-D RESPO*E
- IPS*NENTOTI**
- 3.
Check Charging syat*:
Return to procedure and step in effect.
CCPs - AT LEAST ONE RUNNING
-OR CVCS crosstie ESTABLISHED'
- 4.
Establish Noinsal Seal Injection Flow To RCPu:
- a. Adjust 2-QRV-200, charging header pressure control valve as necessary to maintain:
0 RCP seal injection flow -
6 TO 12 GPM
- 5.
Return To Procedure And Step In Effect
-END-Operator checks at least one CCP running Operator verifies normal seal injection flow Reports task completed.
JPM IS COMPLETE.
Page 4 of 4 Revision 0
Task Briefing The plant has responded to a Small Break LOCA and the actions of E-0, Reactor Trip or Safety Injection and E-1, Loss of Primary or Secondary Coolant have been completed. The US has transitioned to ES-1.2, Post LOCA Cooldown and Depressurization.
The US directs you to perform step 27, of ES-1.2 to check RCP cooling.
N02-09.doc Page 1 of 1 Revision 0
N2'L3Z o TITLE Perform an Authorized Gaseous Release PROGRAM NRC License Exam
- REVISION, 0
TIME '-
.:'-: 25 Minutes DEVELOPING INSTRUCTOR:
OPERATIONS REVIEW:
Name:
Signature:
Name:
Signature:
R. Niedzielski T. Wer Page 1 of 3 DATE:
9/7/02
- q. C)107
COURSE NUMBER N02 Perform an Authorized Gaseous REVISION: 0 AND TITLE:
Release REFERENCES 12-OHP-4021.023.002, Release of Radioactive Waste From Gas Decay Tanks Task: 0230120104; Release a Gas Decay Tank to atmosphere K/A CROSS
REFERENCE:
071 A4.26 K/A IMPORTANCE:
RO 3.1 SRO 3.9 EvaluationSetting, In-Plant (573' elevation Aux Building)
Handouts' Task Briefing for N02-1 0 Gas Release Package (attachments listed below)
ATTACHMENTS
- 1. 12-OHP 4021.023.002, Attachment 2 completed through step 4.5.
- 2. 12-OHP 4021.023.002, Data Sheet 1, completed through Section 3.0
- 3. 12-OHP 4021.023.002, Figure 1 L
SIMULATOR SETUP.
N/A Page 2 of 3
COURSE NUMBER N02-1° - Perform an Authorized Gaseous REVISON 0
AND TITLE:
ReleaseRI VS.[N0 Task Objectives/Standards, Release the contents of #1 Gas Decay Tank to the vent header in accordance with the release procedure.
Task Briefing
- 1 Gas Decay Tank has been isolated, sampled, and approved for release. 12-OHP 4021.023.002, Release Of Radioactive Waste From Gas Decay Tanks, Attachment 2, Release of Radioactive Gaseous Waste From Gas Decay Tanks, has been completed up through step 4.5. Data Sheet 1, Gas Decay Tank Release Permit, is complete up through section 3.0. All support equipment and instrumentation required for this release is in service and properly calibrated.
The US has directed you to perform a Gaseous Waste Release from #1 Gas Decay Tank beginning with step 4.6.
All actions are to be simulated. Dual Concurrent Positioner and Independent Verifier actions are waived for performance of this JPM.
Page 3 of 3
Continuous 12-OHP-4021-023-002 Rev. 18a..
Page 15 of 70 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS Release of Radioactive Gaseous Waste From Gas f Pages:
SDecay Tanks[
9 - 34 Gas Decay Tank Dey Release 4.5 Obtain SM/ASS. permission to release appropriate Gas Decay Tank on Section 3 of Data Sheet 1, Gas Decay Tank Release Permit.
4.6 Align system for release:
NOTE:
Two operators (dual concurrent verification) simultaneously perform the process of lining up the valves to release the Gas Decay Tank contents (Section 4.6.1 through 4.6.6). Independent verification must occur separately from the initial positioner/dual concurrent positioner and must be completed prior to performing Step 4.6.7; 4.6.1 Verify the following CVCS HUT to Radioactive Gas Decay Tanks Vent Header Valves. - CLOSED:
12-CS-531 41 Dual concurrent positioner Independent verifier.
12-CS-532 IV IV General CUES:
Evaluator Note: Valves on this page located on 573' of Aux.
Bldg.
Operator verifies valves closed Cue: No chain (handwheel) movement when pulled in the closed direction.
NOTE: local valve position verification can be waived due to ALARA considerations 12-CS-533 Dual concurrent positioner Independent verifier.
IV Page 1 of 10
COURSE NUMBER N02-1
- Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
4.6.2 Verify applicable manual sample line isolation valve for GDT being released - CLOSED (./ valve verified CLOSED)
O 12-NS-440-1, Gas Decay Tank I Sample. Valve 12-RRV-310 Inlet Shutoff Valve O
12-NS-440-2, Gas Decay Tank 2 Sample Valve 12-RRV-320 Inlet Shutoff Valve O
12-NS-440-3, Gas Decay Tank 3 Sample Valve 12-RRV-330 Inlet Shutoff Valve O
12-NS-440-4, Gas Decay Tank 4 Sample Valve 12-RRV-340 Inlet Shutoff Valve O
12-NS-440-5, Gas Decay Tank 5 Sample Valve 12-RRV-350 Inlet Shutoff Valve o
12-NS-440-6, Gas Decay Tank 6 Sample Valve 12-RRV-360 Inlet Shutoff Valve 0
12-NS-440-7, Gas Decay Tank 7 Sample Valve 12-RRV-370 Inlet Shutoff Valve o
12-NS-440-8, Gas Decay Tank 8 Sample Valve 12-RRV-380 Inlet Shutoff Valve Dual concurrent positioner Independent verifier.
IV Evaluator Notes:
- Following valves located on 587' of Aux. Bldg.
- All valves for GDT #1 are initially closed Operator verifies 12-NS-440-1 Closed Checks and initials Cue: No handwheel movement when turned in the closed direction.
Page 2 of 10 Continuous 12-OHP-4021-023-002 Rev. 18a Page 16 of 70 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS Attac Ihment 2
Release of Radioactive Gaseous Waste From Gas[
Pages:
I Decay Tanks I
9-34 Gas Decay Tank #
I Release #
Continuous 12 P-4021-023-002 I
Rev. 18a I
Pae 17 of 70 4.6.3 Verify applicable isolation valve from compressors - CLOSED
(" valve verified CLOSED):
o 12-WD-227-1, Gas Decay Tank 1 Inlet Valve 12-RRV-311 Upstream Shutoff Valve Q
12-WD-227-2, Gas Decay Tank 2 Inlet Valve 12-RRV-321 Upstream Shutoff Valve o
12-WD-227-3, Gas Decay Tank 3 Inlet Valve 12-RRV-331 Upstream Shutoff Valve o
12-WD-227-4, Gas Decay Tank 4 Inlet Valve 12-RRV-341 Upstream Shutoff Valve o
12-WD-227-5, Gas Decay Tank 5 Inlet Valve 12-RRV-351 Upstream Shutoff Valve Q
12-WD-227-6, Gas Decay Tank 6 Inlet Valve 12-RRV-361 Upstream Shutoff Valve Q
12-WD-227-7, Gas Decay Tank 7 Inlet Valve 12-RRV-371 Upstream Shutoff Valve O
12-WD-227-8, Gas Decay Tank 8 Inlet Valve 12-RRV-381 Upstream Shutoff Valve Dual concurrent positioner Independent verifier.
"IV
/
Operator verifies 12-WD-227-1 Closed Checks and initials Cue: No handwheel movement when turned in the closed direction.
Page 3 of 10 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS Release of Radioactive Gaseous Waste From Gas Pages:
Decay Tanks I
9-34 Gas Decay Tank #
Release #
COURSE NUMBER N02 Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
Continuous I
52-OH1-4021-023-002 1
Rev. 18a 1
Pag e 18 of 70 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS I Release of Radioactive Gaseous Waste From Gas Pages:
I Decay Tanks 1
9-34 Gas Decay Tank # _
I I
Release #
Verify applicable isolation valve to recycle header - CLOSED
(/ valve verified CLOSED):
o 12-WD-231-1, Gas Decay Tank 1 to CVCS Cover Gas Header Shutoff Valve "O 12-WD-231-2, Gas Decay Tank 2 to CVCS Cover Gas Header Shutoff Valve "o
12-WD-231-3, Gas Decay Tank 3 to CVCS Cover Gas Header Shutoff Valve O3 12-WD-231-4, Gas Decay Tank 4 to CVCS Cover Gas Header Shutoff Valve ol 12-WD-231-5, Gas Decay Tank 5 to CVCS Cover Gas Header Shutoff Valve 13 12-WD-231-6, Gas Decay Tank 6 to CVCS Cover Gas Header Shutoff Valve O
12-WD-231-7, Gas Decay Tank 7 to CVCS Cover Gas Header Shutoff Valve U
12-WD-231-8, Gas Decay Tank 8 to CVCS Cover Gas Header Shutoff Valve 1
Operator verifies 12-WD-231-1 Closed Checks and initials Cue: No handwheel movement when turned in the closed direction.
Dual concurrent positioner Independent verifier.
IV Page 4 of 10 4.6.4
Continuous 12-OHP-4021-023-002 I
Rev. 18a I
Page 19 of 70 Release of Radioactive Gaseous Waste From Gas Pages:
IDecay Tanks 1
9-34 Gas Decay Tank #
I Release #
4.6.5 Open applicable gas decay tank isolation valve
(,1 valve OPENED):
Q 12-WD-229-l, Gas Decay Tank I Isolation Valve O
12-WD-229-2, Gas Decay Tank 2 Isolation Valve O
12-WD-229-3, Gas Decay Tank 3 Isolation Valve U
12-WD-229-4, Gas Decay Tank 4 Isolation Valve o
12-WD-229-5, Gas Decay Tank 5 Isolation Valve O
12-WD-229-6, Gas Decay Tank 6 Isolation Valve O
12-WD-229-7, Gas Decay Tank 7 Isolation Valve U
12-WD-229-8, Gas Decay Tank 8 Isolation Valve Dual concurrent positioner Independent verifier.
IV 4.6.6 Verify GDT to GDT release header shutoff valves - CLOSED 12-WD-230-1, Gas Decay Tank I to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
1CT:
Operator (simulates) opens 12-WD-229-1 Checks and initials Cue: Handwheel turns when operated in the open direction then stops when fully open.
Operator verifies 12-WD-230-1 Closed Cue: No handwheel movement when turned in the closed direction.
Page 5 of 10 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS
COURSE NUMBER N02-10 -Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
12-WD-230-2, Gas Decay Tank 2 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
12-WD-230-3, Gas Decay Tank 3 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
12-WD-230-4, Gas Decay Tank 4 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
12-WD-230-5, Gas Decay Tank 5 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
12-WD-230-6, Gas Decay Tank 6 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
IV IV 1 1 IV Evaluator Notes:
- All WD-230 valves are initially closed.
-Operator verifies 12-WD-230-2 Closed Cue: No handwheel movement when turned in the closed direction
-Operator verifies 12-WD-230-3 Closed Cue: No handwheel movement when turned in the closed direction
-Operator verifies 12-WD-230-4 Closed Cue: No handwheel movement when turned in the closed direction
-Operator verifies 12-WD-230-5 Closed Cue: No handwheel movement when turned in the closed direction
- Operator verifies 12-WD-230-6 Closed Cue: No handwheel movement when turned in the closed direction Page 6 of 10
COURSE NUMBER, N02 Perform an Authorized Gaseous Release AND TITLE:
Release of Radioactive Gaseous Waste From Gas Pages:
I Decay Tanks..
9-34 Gas Decay Tank # __
Release #
12-WD-230-7,. Gas Decay Tank 7 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
IV
.12-WD-230-8, Gas Decay Tank 8 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
IV IREV 0
- Operator verifies 12-WD-230-7 Closed Cue: No handwheel movement when turned in the closed direction
- Operator verifies 12-WD-230-8 Closed Cue: No handwheel movement when turned in the closed direction Page 7 of 10 Continuous 12-OtP-4021-023-002 I
Rev. 18a
- I Page 21 of 70 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS
4.6.7 Open applicable GDT to GDT release header shutoff valve (1' valve OPENED):
U 12-WD-230-1, Gas Decay Tank 1 to GDT Release Header Shutoff Valve
.0
.12-WD-230-2. Gas Decay Tank 2 to GDT Release Header Shutoff Valve "o 12-WD-230-3, Gas Decqay Tank 3 to GDT Release Header Shutoff Valve "O 12-WD-230-4, Gas Decay Tank 4 to GDT Release Header Shutoff Valve "0
12-WD-230-5, Gas Decay Tank.5 to GDT Release.
Header Shutoff Valve "O 12-WD-230-6, Gas Decay Tank 6 to GDT Release Header Shutoff Valve "O 12-WD-230-7, Gas Decay Tank 7 to GDT Release Header Shutoff Valve O3 12-WD-230-8, Gas Decay Tank 8 to GDT Release Header Shutoff Valve Dual concurrent positioner Independent verifier.
4.6.8 Open 12-WD-298, GDT Release Header Shutoff Valve 12-RRV-306 Outlet Valve.
Dual concurrent positioner Independent verifier.
CT: Operator (simulates) opens 12-WD-230-1 Checks and initials Cue: Handwheel turns when operated in the open direction then stops when fully open
-CT: Operator (simulates) opens 12-WD-298 and initials Cue: Handwheel turns when operated in the open direction then stops when fully open Page 8 of 10 Continuous 12-OHP-4021-023-002 I
Rev. 18a Page 22 of 70 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS Release of Radioactive Gaseous Waste From Gas Pages:
1 Decay Tanks 9-34 Gas Decay Tank #
I Release #
IV
Continuous I
2oHP-4021-o23-o2 Rev. 18a Pa RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANK Release of Radioactive Gaseous Waste From Gas j Pa IDecay Tanks 1 I Gas Decay Tank #__
Release #
4.6.9 Open 12-WD-297, GDT Release Header Pressure Reducing Valve 12-RRV-305 Inlet Valve.
Dual concurrent positioner Independent verifier.
4.7 Initiate release:
4.7.1 Record INITIAL DATA in Section 4 of Data Sheet 1.
4.7.2 Verify 12-RRV-305. GDT Release Header to Aux Bldg Vent
-Stack Pressure Reducing Valve, set at 4 - 5 psig.
4.7.3 Position 12-RRV-306:
- a. Determine valve position (% open) from Figure 1, 12-RRV-306 Flow Rate, for source flow rate specified in Data Sheet 1, Section 2.
12-RRV-306 position:
% OPEN
- b. While observing reading of RFR-300,Waste Gas to Vent Stack Flow Transmitter (12-MR-57) to ensure specified max source flow rate is NOT exceeded, OPEN 12-RRV-306 to the determined position.
Dual concurrent positioner Independent verifier.
e23 of 70 ges:
.34 IV IV IV' Page 9 of 10
,CT: Operator (simulates) opens 12-WD-297 Cue: Handwheel turns when rotated in the open direction
,Operator records Initial Data in Section 4 Cue: Wind Speed: 6.2 mph; Wind Direction: 200 9, Temp Diff:.
1; Vent Stack Flow: 9.25E4 scfm; Initial Tank Pressure: 97 psig
-Operator verifies 12-RRV-305 set for 4 - 5 psig Cue: Reducing valve set at 4.5
,,Operator determines 12-RRV-306 position (98 -100%)
,CT: Operator (simulates) opens 12-RRV-306 while observing flow on RFR-300 Cue: Flow is rising as valve is simulated being opened (red light lit). Flow is 120 scfm with valve fully open.
COURSE NUMBER N02-10 -Perform an Authorized Gaseous Release REVISION: 0 AND TITLE:
4.7.5 IF during the release, a high radiation alarm is received on VRS-1505 or VRS-2505, an in-service Unit 1 Auxiliary Building Exhaust Fan fails OR a flow alarm is received on. VFR-15 10, THEN Go to Step 4.10.
..4.7.6 Adjust system as necessary to ensure the following conditions are maintained until the release is complete:
- a.
Source flow rate.is less than the maximum dictated on Data Sheet 1, Section 2.
- b. GDT discharge pressure less than 5 psig as read on 12-RRV-305 controller.
- c.
Unit vent flow rate within + 10 % of value recorded in Step 4.3.4.
- d.
Gas Decay Tank pressure t 10 psig.
4.8 WHEN desired release is complete, THEN stop release by closing 12-RRV-306.
Dual concurrent positioner Independent verifier.
IV
/Operator determines that no adjustments are necessary Instructor Cues:
- Source flow rate: 120 scfm;
- GDT discharge pressure: 4.5 psig;
- Unit vent flow: 9.25E4 scfm;
- GDT #1 pressure 94 psig (and lowering 3 psig/min.)
Note: Time compression may be used to lower GDT pressure to desired value Cue: Gas Decay Tank #1 pressure is 12 psig
,CT: Operator stops release, by (simulates) closing 12-RRV 306, prior to lowering GDT pressure below 10 psig Cue: Flow is lowering as valve is simulated being closed (green light lit). Flow is 0 scfm with valve fully closed.
End of JPM Page 10 of 10 Continuous 12-OHP-4021-023-002 Rev. 18a Page 24 of 70 RELEASE OF RADIOACTIVE WASTE FROM GAS DECAY TANKS Release of Radioactive Gaseous Waste From Gas Pages:
Decay Tanks r
9-34 Gas Decay Tank #
"Release
Task Briefing
- 1 Gas Decay Tank has been isolated, sampled, and approved for release. 12-OHP 4021.023.002, Release Of Radioactive Waste From Gas Decay Tanks, Attachment 2, Release of Radioactive Gaseous Waste From Gas Decay Tanks, has been completed up through step 4.5. Data Sheet 1, Gas Decay Tank Release Permit, is complete up through section 3.0. All support equipment and instrumentation required for this release is in service and properly calibrated.
The US has directed you to perform a Gaseous Waste Release from #1 Gas Decay Tank beginning with step 4.6.
All actions are to be simulated. Dual Concurrent Positioner and Independent Verifier actions are waived for performance of this JPM.
N02-1 0.doc Page 1 of 1
.LI oIU1' TITLE Restore Unit 1 'N' Train Battery Charger PROGRAM NRC License Exam 0
14 Minutes DEVELOPING" I*NT*..RUCTOIR:,
OPERATIONS REVIEW:
Name:
Signature:
Name:
Signature:
1DATE 9/7/02 R. Niedzielski I
T. Werk
.9 1,,Z-IPage 1 of 3 7
/ 7.......
REFERENCES 01-OHP 4024.115 Drop 57, 01-OHP4021.082.01 5, Rev. 5 Trains A & B N Battery CHG De-energized Operation of the N Train Battery Charger Task: 0820080504: Reset the N-train Battery Charger 0820160104: Switch N-Train Battery Chargers 0000000000: Startup and Switch a Vital Battery Charger K/A IMPORTANCE:
K/A CROSS
REFERENCE:
APE 058 AA1.01 EVALUATION SETTING Auxiliary Building 633' HANDOUTS Task Briefing for N02-1 1 01-OHP 4024.115 Drop 57, Trains A & B N Battery CHG De-energized 01-OHP 4021.082.01 5, Operation of the N Train Battery System ATTACHMENTS None SIMULATOR SETUP None - in-plant JPM I Page 2 of 3
Task Objectives/Standards An N-Train Battery Charger is charging the N-Train battery following a SI and load shed condition.
Task Briefing Unit 1 is in Mode 3 following a reactor trip with a safety injection.
The Unit Supervisor gives you a working copy of the annunciator response procedure for annunciator panel 115 drop 57 (N-Train Battery Charger De-Energized).
You are to review the subsequent actions of this annunciator response procedure and restore a N-Train battery charger to service.
The Train B Charger is currently aligned for service on the Unit 1 N Train Battery system.
Page 3 of 3
COURSE NUMBER N02-11 II REVSION AND TITLE:
Reset an 'N' Train Battery Charger (Ul) 01-OHP 4024.1 IS DROP 57 ANNUNCIATOR PANEL NUMBER 115 FEED PUMP TURBINE SETPOINT: NIA TRAINS A & B N BATTERY CHG INITIATING DEVICE: 3OBC-A and 3OBC-B or 88XBC-A and (88XBC-B or DE-ENERGIZED Kl-l TR B1 or 88XBC-B and 88XBC.A or K1-t TR A] or K1-1 TR A and KI-ITR B or 49 device (thermal overload) open on both feeds.
1.0 PROBABLE CAUSE 1.1 Both N Train A and B battery charger de-energized simuolaneOunly.
1.2 Safety Injection signal actuated.
1.3 Load shedding on bus T-11B or T-I1D.
1.4 Thermal overload trip on both battery charger feeds.
2.0 IMMEDIATE ACTION 2.1 Automatic 2.1.1 None 2.2 Manual 2.2.1 None 3.0 SUBSEQUENT ACTION 3.1 If switching battery chargers in progress, ensure one battery charger left in service, 3.2 If safety injection signal actuated, or load shed occurred, then manually eset the in service battery charger by placing the charger's control switch to OFF and then returning it to AUTO.
3.3 Reset thermal overloads.
3.4 If the alarm is still standing upon completing the applicable checks from steps 3.1, 3.2, or 3.3, the operator should reference 01-OHP 4021.082.015, Operation of the N Train Battery System, to restore the N Train Battery Charger to service.
Page 67 of 118 Rev. 10 Operator recognizes that the N-Train battery charger must be manually reset following an SI and load shed on bus T-1 1 B or T 11D.
CT: Operator (simulates) resets the in-service battery charger by placing the control switch to "OFF" and then back to the "AUTO" position.
Cue: The control room reports that annunciator panel 115 drop 57 alarm has NOT cleared.
SPage 1 of 3
COURSE NUMBER N02-11 1EI A N D T IT L E :
R e s e a n N T rai nR E V IS IO N : 0 AND TIL:
3/4;i Reset an 'N" Train Battery Charger (Ul1)
Re'erence 0l-OHP-4021-082-015 Rev. 5 Pae*e3 ofIO OPER-ATION OF THE N TRAIN BATTERY SYSTEM 4
DETAILS NOTE:
This procedure is referenced for use in the Emergency Operating procedures.
Use of this procedure as directed by the EOP series is subject to rules of usage found in 11-14023, Abnomiai'Emergency Procedure Users Guide, 4, 1 Placing a Battery Charger in Service:
4.1.1 IF placing battery charger in service after an extended battery outage, THEN request Maintenance to be present to adjust charger voltage to prevent exceeding current limitations.
4.1.2 Verify AC Input breaker for selected charger in OFF:
I -BC-A-CBI Battery Charger AC Input From 1-AM-D-4A,4 St-.BC-B-CBI Battery Charger AC Input From I-ABD-B-2A 4.1.3 Verify green AC POWER TO CHARGER OFF light - LIT on battery charger control box (I -BC-A-PNL or I-.BC-B-PNL).
- a.
IF light is NOT LIT, [HEN close 'die selected AC supply breaker.
- I -AM-D-4A T'rain 'N Battery Distribution Train 'A' Battery Charger I-BC-A
- I-ABD-B-2A Train B N Train Battery Charger I-BC-B 4A1.4 IF the N Battery Charger will be powered from an EDG,.
T'HEN verify adequate diesel generator capacity is available.
4.1.5 Close the incoming Feed breaker for the selected battery charger:
I-DCN Ckt I Incoming Feed From Battery Char.
1-BC-A (Train A)
I -DCN Ckt 4 Incoming tFeed From Batter, Charuger 1-BC-B (Train B)
Evaluator Note: The operator should recognize that he must place the opposite train (A) charger in service. If not prompt operator as US to place Train A charger in service. Provide operator with copy of 01 -OHP 4021.082.015.
Prerequisites If asked, "MCCs 1-AM-D and 1-ABD-B are energized; one battery exhaust fan is operating" If asked, "The charger was in service yesterday with operating parameters within normal limits."
Operator verifies the 1-BC-A-CB-1 is "OFF" (not closed).
When checked, "The GREEN light on the standby battery charger control box is NOT LIT.
CT: Operator (simulates) closes 1-AM-D-4A breaker.
Cue: "The charger to be placed in service will not be powered from a diesel."
CT: Operator (simulates) closes I-DCN CKT I breaker LPage 2 of 3
COURSE NUM BER N02-11 1EIIN AND TITLE:.
Reset an 'N' Train Battery Charger (Ul)
-Reference L
t)-OHI-4021-082-015 Rev. 5 Pa'_e 4 of 10 OPERATION OF THE N TRAIN BATTERY SYSTEM CAUTION:
Float charge should be 260 to 265 VDC.
Battery charger must NOT exceed 25 amips when placing in service.
4.1.6 Close DC Output breaker on selected charger:
I-BC-A-CB2 Battery Charger DC..- pta oXfcr Cab I-DCN CKT 1 l-BC-B-CB2 Batten; Charger DC Output To Xfer Cab 1 -DCN CKT 4 4.137 Close AC Input breaker on selected charger, S
i -BC-A-CB I Battery Charger AC Input From i-AM-D-4A
.1-BC-B.CBI Bartery Charger AC Input From I-ABD-B-2A 4,1,8 Place control switch for selected charger in AUTO position:
N Traiin BatteryTrain A Charger I -BC-A Control Swite N Train Battery Train B Charger I-BC-B Control Switch 4.1.9 IF chargers are being switched, THEN:
- a.
Place the control switch lbr the charger being removed t'roin4 service to OFF,
- b.
Verify green AC POWER TO CHARGER OFF light - LIT for the charger being removed from service.
4.1.10 Verify red AC POWER TO CILARGER ON lighht - LIT for the charger being placed. in se-*vice.
4.2 Removing a Battery Charger from Service:
4.2.1 Verifi control switch for selected charger in OFF position:
N Traiin Battery Train A Charae:" I-BC-A Control Switch CT: Operator (simulates) closes 1-BC-A-CB2 breaker.
Cue: Breaker clicks into position.
CT: Operator (simulates) closes 1-BC-A-CB1 breaker.
Cue: Breaker clicks into position CT: Operator (simulates) places 1-BC-A control switch in AUTO.
Cue: Control switch is in the position selected CT: Operator (simulates) places 1-BC-B control switch in OFF.
CUE: "The GREEN lamp is LIT on the Train B charger control box."
CUE: "The RED lamp is LIT on the Train A charger control box."
JPM IS COMPLETE I Page 3 of 3
Task Briefing Unit 1 is in Mode 3 following a reactor trip with a safety injection.
The Unit Supervisor gives you a working copy of the annunciator response procedure for annunciator panel 115 drop 57 (N-Train Battery Charger De-Energized).
You are to review the subsequent actions of this annunciator response procedure and restore a N-Train battery charger to service.
The Train B Charger is currently aligned for service on the Unit 1 N Train Battery system.
N02-1.1.doc LPage 1 of 1
1[ElFN0.ý 1 2=
Establish ESW Cooling to CR Air Handling Units NRC License Exam DEVELOPING INSTRUCTOR:
Name:
Signature:
Name:
Signature:
0 13 Minutes R. Niedzielski j T7 Werk DATE:
9/7/02 491 Oz-.
Page 1 of 3
COURSE NUMBER N02-12 Establish ESW Cooling to CR Air REVISION: 0 AND TITLE:
Handling Units References 02-OHP-4023-ECA-0.O, Loss of All AC Power 02-OHP-4021-028-014 Attachment 6, Initiating or restoring from ESW Cooling to Air Handling units Task: 0280250104: Align. ESW to Control Room AC Air Handling Units K/A CROSS
REFERENCE:
076 A4.04 K/A IMPORTANCE:
RO 3.5* SRO 3.5 SEvaluation Setting In-plant, Unit 2 CR Ventilation Equipment Room, above 633' elevation Handouts Task Briefing for N02-1 2 Copy of 02-OHP-4021-028-014, Attachment 6 Attachments None Simulator Setup N/A Page 2 of 3
COURSE NUMBER N02-12 Establish ESW Cooling to CR Air REVISION: 0 AND TITLE:
Handling Units Task Objectives/Standards Align ESW cooling to Unit 2 Control Room AC Air Handling Units per 02-OHP-4021-028-014, Observing all applicable precautions and limitations and procedural steps.
Task Briefing A failure of both Unit 2 Control Room Chiller Packages has occurred.
The Control Room operator has directed you to establish ESW Cooling to the Unit 2 North Control Room AC Air Handling Unit using 02-OHP-4021-028-014 Attachment 6.
Page 3 of 3
I REFERENCE I
02-OHP-4021-028-014 I
Rev. 14 Page 24 of 68 Operation of the Control Room Air Conditioning and Pressurization/Cleanup Filter Systems Initiating Or Restoring From ESW Cooling To '
Air Handling Units Following A Failure Of Both Pages:
Chiller Packages 4
DETAILS INIT NOTE:
Due to Chemistry concerns ESW may be lined up to only one Chiller package.
at the direction of the Unit Supervisor. N/A any steps for the Chiller unit which is not lined up to ESW.
4.1 To initiate ESW to Chiller package perform the following:
4.1.1 Stop chilled water pumps:
"* 2-PP-82N, North Chilled Water Pump
"* 2-PP-82S, South Chilled Water Pump 4.1.2 Place chiller control switches in - OFF:
2-HV-ACR-1, North Chiller t
2-HV-ACR-2, South Chiller 4.1.3 Place first and second stage AHU heater control switches in OFF:
2-101-ACRH1l, North Coni Room AHU Elect HTR Heating Element #1 2-HV-ACR-H1-l 2-101-ACRH12, North Cont Room AHU Elect HTR Heating Element #2 2-HV-ACR-HI-2 2-101-ACRH21, South Cont Room AHU Elect HTR Heating Element #1 2-HV-ACR-H2-1 2-101-ACRH22, South Cont Room AHU Elect HTR Heating Element #2 2-HV-ACR-H2-2 General CUES:
ESW Supply temperature is 50 OF This JPM is simulated ONLY, no operation of plant equipment is permitted.
CUE: ESW should be lined up to North Chiller package only
.4-j--CT: Operator simulates placing North CW pump in STOP "l--tStep is "N/A" Ar
-CT: Operator simulates placing North Chiller in OFF
-Step is "N/A"
>CT: Operator simulates placing Electric Heating elements in OFF
>Steps are "N/A" Page 1 of 3 I
REFERENCE I
02 OHP-4021-02R-fl14 I
Rev 14 I
PcA
4.1.4 Close the following chill water valves:
"* 2-DW-166N, CRAC North Chill Water Circ Pump Discharge Valve
"* 2-DW-166S, CRAC South Chill Water Circ Pump Discharge Valve 2-DW-163N, CRAC Chill Water To North Liquid Chiller Inlet Isolation Valve 2-DW-163S, CRAC Chill Water To South Liquid Chiller Inlet Isolation Valve 4.1.5 Open the following ESW supply valves:
North CRAC AHU 2-ESW-168N, Emergency ESW Supply To North CRAC AHU 2-HV-ACRA-1 Shutoff Valve 2-ESW-171N, Emergency ESW Return From North CRAC AHU 2-HV-ACRA-1 Shutoff Valve 2-ESW-296, Emergency ESW Supply To North CRAC AHU 2-HV-ACRA-1 Shutoff Valve South CRAC AHU 2-ESW-168S, Emergency ESW Supply To South CRAC AHU 2-HV-ACRA-2 Shutoff Valve 2-ESW-171S, Emergency ESW Return From South CRAC AHU 2-HV-ACRA-2 Shutoff Valve 2-ESW-298, Emergency ESW Supply To South CRAC AHU 2-HV-ACRA-2 Shutoff Valve 77>CT: Operator simulates closing North Chiller valves
>Step is N/A
ýCT: Operator simulates opening North CRAC AHU ESW valves rStep is N/A Page 2 of 3 Operation of the Control Room Air Conditioning and Pressurization/Cleanup Filter Systems Initiating Or Restoring From ESW Cooling To Pages:
Air Handling Units Following A Failure Of Both 23 - 29 Chiller Packages T
RE'ERENCE2 I
02-AHP4 1-02
¶A I
Initiating Or Restoring From ESW Cooling To Air Handling Units Following A Failure Of Both Pages:
SChiller Packages 23 - 29 4.1.6 IF control air is not available or the regulating valves and circuitry are not functioning properly, THEN close the following valve(s) to isolate control air to chill water control valves and ensure bypass flow is isolated:
2-CA-3134, 50 PSI Control Air To CRAC Chilled Water Reg Valve 2-VRV-315 Shutoff Valve (North CRAC Unit) 2-CA-3129, 50 PSI Control Air To CRAC Chilled Water Control Valve 2-VRV-325 Shutoff Valve (South CRAC Unit) 4.1.7 Place desired CRAC control switch in - RUN:
2-HV-ACRA-1, North Ctrl Room Air Hdlg Unit 2-HV-ACRA-2, South Ctrl Room Air Hdlg Unit.
NOTE:
Due to Chemistry concerns ESW should have been lined-up to only one Chiller package at the direction of the Unit Supervisor. N/A any steps for the Chiller unit which was not lined up to ESW.
4.2 To restore chill water to the Air Handling Units perform the following:
4.2.1 Verify open the following valve(s) to restore control air to chill water control valves to ensure bypass flow is restored:
"* 2-CA-3134, 50 PSI Control Air To CRAC Chilled Water Reg Valve 2-VRV-315 Shutoff Valve (North CRAC Unit)
"* 2-CA-3129, 50 PSI Control Air To CRAC Chilled Water Control Valve 2-VRV-325 Shutoff Valve (South CRAC Unit) 4 -
CUE: Control Air is available
/
Operator determines step is N/A A-- CT: Operator notifies Unit 2 CR to start 2-HV-ACRA-1.
+--tStep is N/A Cue: Unit 2 reports that 2-HV-ACRA-1 is running.
Operator reports task is complete CUE: JPM IS COMPLETE Page 3 of 3 Operation of the Control Room Air Conditioning and Pressurization/Cleanup Filter Systems
TASK BRIEFING A failure of both Unit 2 Control Room Chiller Packages has occurred.
The Control Room operator has directed you to establish ESW Cooling to the Unit 2 North Control Room AC Air Handling Unit using 02-OHP-4021-028-014 Attachment 6.
N02-12.doc Page 1 of 1
Perform Local DG Trip and Isolation NRC License Exam
.REVISION 0
TIME 17 Minutes DEVELOPING INSTRUCTOR:
Name:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski T. Werk DATE 9/7/02 q /oz.
Page 1 of 3 Revision 0 11, I -. 7 N02-13
References 02-OHP-4025-LTI-3, Local Diesel Generator Isolation Task: 0320250604 Locally trip the Emergency Diesel Generator K/A CROSS
REFERENCE:
APE 068 AA1.31 K/A IMPORTANCE:
RO 3.9 SRO 4.0 Evaluation Setting In plant, Unit 2 591'elevation CD DG room and 609' elevation 4KV room Handouts Task Briefing for N02-13 Copy of 02-OHP-4025-LTI-3, Local Diesel Generator Trip and Isolation Attachments None Simulator Setup None Page 2 of 3 Revision 0
Task Objectives/Standards 1
Perform a local trip and isolation on Unit 2 CD Diesel Generator per 02-OHP-4025-LTI-3, observing applicable precautions and limitations and procedural steps.
11 Task Briefing 11 After a fire event on Unit 2, 2CD Diesel Generator started but failed to load.
The US directs you to locally trip and isolated the 2CD Diesel Generator per 02-OHP-4025-LTI-3-2 (page 5).
You are to simulate your actions on plant equipment and observe industrial safety requirements.
Page 3 of 3 Revision 0
COURSE NUMBER N02-13.Perform Local Diesel Generator Trip and Isolation REVISION: 0 AND TITLE:
Title wber LOCAL DIESEL GENERATOR TRIP AND ISOLATION 02-OHP 4025.LTI-3 STEP ACTION/EXPECTED RESPONSE
' RESPONSE NOT OBTAINED*
LTI-3-2 DG2CD LOCAL TRIP AND ISOLATION CAUTION:
THIS PROCEDURE SHOULD ONLY BE PERFORMED IF CD DIESEL GENERATOR IS CURRENTLY RUNNING AND HAS FAILED TO LOAD.
- 1.
Trip CD Diesel Generator Locally:
- a. At Diesel Generator 2CD subpanel, depress DG2CD local Emergency Trip pushbutton'n
- b. Check DG2CD -. TRIPPED
- b. If CD Diesel Generator does not trip, IHEN perform the following:
- 1) Close DG2CD starting air receiver outlet valves: DG-184C
- 2-DG-186C
- 2) Close control air dryer,4 inlet valves for DG2CD: DG-138C
- 2-DG-144C
- 3) Open the following control air dryer drain valves to depressurize 100 psi control air header to DG2CD:
2-DG-252C 2-DG-254C GENERAL CUES:
2CD Diesel Generator started but failed to load after a fire event on Unit 2.
-CT: Operator (simulates) depressing local EMERGENCY TRIP
-CUE: CD EDG is still Operating
_CT: Operator (Simulates) closing 2-DG-184C & 2-DG-186C CUE : Handwheel has stopped turning.
-CT: Operator (Simulates) closing 2-DG-138C & 2-DG-144C CUE : Handwheel has stopped turning.
_CT: Operator (Simulates) opening 2-DG-252C & 2-DG-254C CUE : Handwheel has stopped turning. Air is blowing from the drain valves and air receiver pressure is lowering to 0 psig.
CUE: 2 CD EDG has stopped running.
Page 1 of 2 Revison 0
Tit(*
LOCAL DIESEL GENERATOR TRIP AND ISOLATION 02-OHP 4025.LTI-3 STEP ACTION/EXPECTE
- 2.
Isolate CD Dies Buses T21D And
- a. Breaker T21DB Breaker To Bu ED RESPONSE LTI-3-2 DG2CD LOCAL TRIP AND ISOLATION el Generator From T21C:
8, DG2CD Output us T21D:
I) Remove breaker control power fuses h
' 10
- 2) Check breaker T21DB -
- 2) IFbreaker T21D8 is NOT TRIPPED TRIPPED, TJJE push mechanical trip pushbutton on lower front of breaker cubicle.
- b. Breaker T21C3, DG2CD Output Breaker To Bus T2lC:
- 1) Remove breaker control power fuses
- 2) Check breaker T21C3 -
- 0)
IF breaker T21C3 is NOT TRIPPED TRIPPED, THEN push mechanical trip pushbutton on lower front of breaker cubicle.
- 3.
Report 02-OHP 4025.LTI-3, LOCAL DIESEL GENERATOR TRIP AND ISOLATION, LTI-3-2, DGZCD LOCAL TRIP AND ISOLATION, Complete
- 4.
Stand By For Further Instructions
-END OF SECTION-NOTE: Operator leaves the 2CD DG room and proceeds to the 4KV Switchgear Room (609' TB)
NOTE: Operator (simulates) dons Full Flash Equipment
-CT: Operator locates T21 08 breaker and (simulates) removes control power fuses
-CT: Operator verifies breaker T21 D8 tripped CUE: Breaker T21 D8 indicates tripped
-CT: Operator locates T21 C3 breaker and (simulates) removes control power fuses
-CT: Operator verifies breaker T21 C3 tripped CUE: Breaker T21 C3 indicates tripped Reports task completed.
JPM IS COMPLETE.
Page 2 of 2 Revison 0
Task Briefing After a fire event on Unit 2, 2CD Diesel Generator started but failed to load.
The US directs you to locally trip and isolated the 2CD Diesel Generator per 02-OHP-4025-LTI-3-2 (page 5).
You are to simulate your actions on plant equipment and observe industrial safety requirements.
N02-13.doc Page 1 of 1 Revision 0
TITLE Modify, Relatch and Locally Start TDAFP
- PROGRAM, NRC License Exam TIME 20 Minutes DEVELOPIN 1G Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski T.Werk DATE:
9/7/02 Page 1 of 3 Revision 0 II::No2-1*4:
REFERENCES 01-OHP 4025.LS-2, Start-up AFW 01-OHP 4025.001.001,Emergency Remote Shutdown Task: APRO06061 2 Startup AFW using Local Controls K/A CROSS
REFERENCE:
APE 068 AA1.02 K/A IMPORTANCE:
RO 4.3 SRO EVALUATION SETTING In-Plant Simulate (Sequenced)
- 1. 633' Unit I AB
- 2. 587' Unit I AB
~~<HANDOUTS Task Briefing for N02-14 Copy of O1-OHP 4025.LS-2, Start-up AFW ATTACHMENTS*
None SIMULATOR SETUP None Page 2 of 3 Revision 0 I
I I
TASK OBJECTIVES/STANDARDS Unit 1 TDAFW running after being relatched and started locally per 01-OHP-4025-LS-2, observing applicable precautions and limitations and procedural steps.
TASK BRIEFING, 7
The Unit 1 Control Room has been evacuated due to heavy smoke from a fire in the control board panels. Neither Motor Driven AFW pump was capable of being started. You are a member of the Emergency Remote Shutdown (ERS) Team assembled in the Unit 2 Control Room.
You have -been directed to relatch and start the TDAFP locally in accordance with 01-OHP 4025.LS-2-3, Relatch TDAFP, and LS-2-4, Start TDAFP.
Page 3 of 3 Revision 0
COURSE NUMBER N02-14 Modify, Relatch and Locally Start TDAFP II ON AND TITLE:
REVISION: 0 "Eille Number START-UP AFW 01-OHP 4025.LS-2 LS-2 INDEX INDEX FOR PROCEDURE LS-2 PAGE#
LS-2-3 RELATCH TDAFP PURPOSE:
Manually resets TDAFP for restarting in the event normal remote control fails, and de-energizes the TDAFP turbine steam supply isolation valves to prevent spurious clol REQUIREMENTS:
Operators I
Special Tools and Equipment Fuse Pullers, Jumper, Diagon
- ers, Flat-Tip Screwdriver Security Keys AFW PP Room, N Battery Room, A-37 Key-Fo pendix R Toolbox A-2 Key -
r Safety Equipment Locker Protective Clothing Full h Equipment
/
Est, Tune to Completion nmn.
LS-2-4 START TDAFP9 PURPOSE:
Manually starts TDAFP in the event normal remote control fails.
REQUIREMENTS:
Operators Special Tools and Equipment NONE Security Keys AFW PP Room Protective Clothing NONE Est. Time to Completion 5 min.
General CUES:'
Operator reviews purpose and performing LS.2-3 and LS.2-4 equipment requirements for 7Operator obtains tools, keys, and protective clothing as specified NOTE: The evaluator may ensure the operator knows what protective equipment is required and where it is located in-lieu of actually obtaining the protective equipment.
Page 1 of 5 Revison 0
COURSE NUMBER N02-14 Modify, Relatch and Locally Start TDAFP AND TITLE:
REVISION: 0 II START-UP AFW 01-OBP 4025.LS-2 STEP ACTION/EXPECfED RESPONSE RESPONSE NOT OBTAINED LS-2-3 RELATCH TDAFP
- 1. Verify Valves - OPEN
- a. l-MCM-221, #12 SQ Supply To TDAFP
NOTE:
- Tools required to complete this procedure are stored in the Appendix R toolbox located in the Turbine Building on 591' elevation, in the hallway outside of the E MDAFP and TDAFP Rooms.
The following steps will be performed in Unit I auxiliary building on 633' elevation.
.2.
Open Circuit Breakers:
- a. I-DCN, Ckt#6, TDAFP Control Bus Feeder
- b. 1-AM-A-IB, I-MCM-221 (#12 SQ Supply To TDAFP)
- c. 1-AM-D-R6C, I-MCM-231 (#13 SQ Supply To TDAFP)
NOTE:
The following step will be performed in Unit 1 auxiliary building on 587' elevation.
- 3. Remove Control Power Fuses From 1-AB-N-3B, TDAFP Trip And Throttle Valve Control Circuit (1-QT-506)
-Operator verifies Valves open CUE: The US reports 1-MCM-221 and 231 are open at the Hot Shutdown Panel (HSD).
"Operator reviews notes prior to step 2 Cue: Initially breakers are in ON position (Evaluator may elect to locate panel at a different time to avoid multiple trips into the Aux Building)
-CT: Operator locates Panel 1-DCN and (simulates) places breake Ckt. 6 in OFF position
-CT: Operator locates MCC 1-AM-A and (simulates) places breake 1-AM-A-1B in OFF position
-CT: Operator locates MCC 1-AM-D and (simulates) places breake I -AM-D-R6C in OFF position r
r
- r Cue
- Breakers are in OFF position CT: Operator locates panel VCC-1-AB-N cubicle 1-QT-506, simulates opening cubicle door and describes process of pulling fuses for 2-AB-N-3B Cue: Door is open and fuses pulled Page 2 of 5 Revison 0 Jl REV 0
COURSE NUMBER N02-14 Modify, Relatch and Locally Start TDAFP REVISION: 0 AND TITLE:
START-UP AFW 01-OHP 4025.IS-2 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED LS-2-3 RELATCH TDAFP NOTE:
The following steps will be performed in the turbine building on 591' elevation, in the Unit I turbine driven auxiliary fecdwater pump room.
- 4. Lift Wires Inside Turbine Driven Auxiliary Feedwater Pump Subpanel 1-TFP:
- a. Terminal Block TCE:
TERMINAL CB BLOCK POINT TD+
9000BR-I TD-9000BR-I TDTV-3 9000BR-1 TDTV-4 9000BR-1 S
TDTV-5 9000BR-1 TDTV-6 9000BR-1
- b. Terminal Block TCF:
TERMINAL BLOCK POINT CABLE #
14A 9IDOIBR-I 15 9001BR-1
- CT: Operator locates Subpanel 1-TFP and identifies that this action is to be performed inside the subpanel.
Cue: The wires have been lifted on Terminal Block TCE and Terminal Block TCF Page 3 of 5 Revison 0
STARTUPAFW 01-OHP 4025.LS.2 S
ACTION/EXPECI'ED RESPONSE j
RESPONSE NOT OBTAINED LS-2-3
- 5. Establish Local TDAFP S Re Tna~telline T,,m~., nR.
RELATCH TDAFP peýd Indication and 15 On Terminal Block TCF NOTE:
The following step will be performed in Unit 1 auxiliary buildin elevation.
- 6. Close 1-DCN, Ckt #6, Turbine Driven Auxiliary Feedwater Pump Control Bus Feeder NOTE:
.The following step will be performed in turbine building on 591' elevation, in the Unit 1 turbine driven auxiliary feedwatr urn
- 7. Check 1-QT-506, Turbine Driven IF TDAFP TrV is UNLATCHED, THEN Auxiliary Feedwater Pump Trip And perform the following; Throttle Valve - LATCHED
- a. Engage hbadwheel clutch.
- b. Rotate handwheel CLOCKWISE until latching lever is in the RESET position.
- c. IF latching mechanism will NOT engage, THEN reset Mechanical Overspeed Trip Device per Operator Aid I-OA-MSTM-2-2 posted at TDAFP TTV.
-END OF SECTION-L1 Page 4 of 5 Revison 0
.Operator identifies that this action is to be performed inside subpanel TFP-1.
Cue: A Jumper has been placed between points 14A and 15 on Terminal Block TCF CT: Operator Returns to panel 1-DCN and (simulates) closes circuit 6 (NOTE: Evaluator may ask location of panel 1-DCN in-lieu of returning to the panel or locate the panel at a different time - same breaker as in step 2.a.)
Cue: Circuit 6 is in ON position
_.CT: Operator checks TTV latched Cue: Latching mechanism is not engaged
_CT: Operator (simulates) performs RNO: TTV Clutch pushed in downward direction to engage handwheel Cue: Clutch lever lowers and will not move any further
-CT: Operator (simulates) turns TTV handwheel clockwise until latching lever raises to RESET position Cue: Latching mechanism is engaged in the reset position Operator reports TDAFP is latched.
Cue: "1 understand that the TDAFP is latched, start the TDAFP in accordance with LS-2-4."
COURSE NUMBER N
Modify, Relatch and Locally Start TDAFP AND TITLE:REISONM Numbr[
01-OHP 4025.LS-2 RESPONSENOT OrTA AFP I. Verify 01-OHP 4025.LS-2, START-UP AFW, LS-2-3, RELATCH TDAFP-COMLETrE NOTE:
The following steps will be performed in turbine building on 591' elevation, in the Unit I turbine driven auxiliary feedwater pump room.
- 2. Start Turbine Driven Auxiliary Feedwater Pump:
- 3. Check Proper TDAFP Operation:
"* Unusual noise
"* Oil leakage Vibration
I Operator acknowledges that LS-2-3 is complete CT: Operator (simulates) slowly turns TTV handwheel counterclockwise until speed indications stops rising then fully opens TTV Cue: Provide rising speed indications until turbine speed is at 4110 rpm and then stops rising. After speed stabilizes, operator continues to turn TTV handwheel in CCW direction Operator Checks for proper operation Cue: No unusual noise, no excessive vibrations, and no oil leaks Reports task complete JPM IS COMPLETE Page 5 of 5 Revison 0
'*tle START-UP AFW STEP ACTION/EXPECTpD RES.PONSEP LS-2-4 STATiT START TD REVISION: 0
Task Briefing The Unit 1 Control Room has been evacuated due to heavy smoke from a fire in the control board panels. Neither Motor Driven AFW pump was capable of being started. You are a member of the Emergency Remote Shutdown (ERS) Team assembled in the Unit 2 Control Room.
You have been directed to relatch and start the TDAFP locally in accordance with 01-OHP 4025.LS-2-3, Relatch TDAFP, and LS-2-4, Start TDAFP.
N02-14.doc Page 1 of 1 Revision 0
Z1
-5 TITLE Local Control of RHR Valve for RCS Cooldown SPROGRA'Mi NRC License Exam TIME
,.12 Minutes DEVELOPING Name:
INSTRUCTOR:
Signature:
OPERATIONS REVIEW:
Name:
Signature:
R. Niedzielski
~/?T.
Wer DAT E 9/7/02 9/
oz.
Page 1 of 3 Revision 0
References 01-OHP-4025-LS-7, RCS Cooldown using RHR Task: APRO0 10604 Local Control of RHR and CVCS air operated regulating valves K/A CROSS
REFERENCE:
005 A2.04 K/A IMPORTANCE:
RO 2.9 SRO 2.9 Evaluation Settings In Plant Simulation Unit 1 609' elevation of Aux Building Handouts Task Briefing for N02-1 5 Copy of 01-OHP-4025-LS-7, RCS Cooldown using RHR, pages 25 and 26 Attach ments None Simulator Setup None Page 2 of 3 Revision 0
COURSE NUMBER AND TITLE:
Task Objectives/Standards Establish local control of RHR valves during RCS cooldown per 01-OHP-4025-LS-7, observing applicable precautions and limitations and procedural steps.
Jr Task Briefing Unit 1 is in Mode 4 with a cooldown to cold shutdown in progress using the west train of RHR.
A fire has impacted the operation of the West RHR HX Outlet Flow Control valve, 1-IRV-320.
Control Air is available.
The procedure for RCS cooldown using the West RHR Train (01-OHP-4024-LS-7-2) has been implemented and at step 4, the remote operation of 1 -IRV-320 is unavailable.
The US directs you to perform the step 4 RNO actions of 01-OHP-4025-LS-7-2 and verify proper operation of 1 -IRV-320.
There no hazardous conditions in route or at the local control stations and no tools are required to complete your task.
Page 3 of 3 Revision 0
COURSE NUMBER N02-15 Local Control of RHR Valve for RCS Cooldown AND TITLE:
REVISION: 0 01-OHP 4025.LS-7
"-ST-E,,ACTION/EXPECTE RSONSE RESPONSE NOT OBTA-INE-Dj LS-7-2 RCS COOLDOWN USING WEST RHR TIRAIN
- 4.
Check Remote Control Operation Of IF remote control operation is RHR Valves:
unavailable THEN modify valve(s) for local operation by performing
"* 1-1RV-320, 1W RHR Hx Outlet the following:
Flow Control Valve
- a. Go to appropriate local
" 1-IRV-311. RHR Hx Bypass Flow control station:
Control Valve C Located Aux Bldg. 609' elevation, outside of U-1 RHR Hx Rooms
- b. Locate flex hose and emergency control air connection for the affected valve:
Verify vaIve number on flex hose matches number on emergency air connection.
- c. Close normal control air supply valve to electro-pneumatic transducer (EPT),
- d. Disconnect flex hose from normal control air connection.
'e Connect flex hose to.emergency*
control air connection.
- f. Open emergency control air supply valve.
This Step continued on the next page.
RCS COOLDOWN USING RHR Page 1 of 2 Revision 0 General CUES:
Remote operation of 1-IRV-320 is unavailable Operator performs actions of RNO CT: Operator goes to Hallway by U-1 RHR HX rooms CT: Operator locates hose for 1-IRV-320, verifies number match
-CT: Operator (simulates) closes air supply to EPT for 1-IRV-320
-CT: Operator (simulates) disconnects air hose for 1-IRV-320 CT: Operator (simulates) connects emergency hose to emergency control air supply for 1 -IRV-320 CT: Operator (simulates) opens emergency control air supply for 1-IRV-320
COURSE NUMBER N02-15 Local Control of RHR Valve for RCS Cooldown RI AND TITLE:
Title RCS COOLDOWN USING RHR 01-OHP 4025.LS-7 STEP ACTION/EXPECTED RESPONSELW UN RESPONSE NOT OBTAINETD LS-7-2 SRCS COOLDOWN USING WEST RHR TRAIN
- g. Adjust pressure regulator and check regulator output gauge to verify proper valve operation:
" FULL OPEN - 3 psig
" FULL CLOSED - 15 pslg IF 1-IRV-320 OR 1-IRV-311 will NOT respond to local control station operation. THEN FAIL OPEN the applicable vTaves(s) by performing the following:
- 1) Verify closed the normal control air supply valve to electro-pneumatic transducer (EPT).
- 2) Close emergency control air" supply valve.
- 3) Disconnect flex hose from emergency control air connection.
- 4) Connect flex hose to normal control air connection.
- 5) Visually verify applicable valve(s) open: IRV-320 - Located in 1W RHR Hx Room
4-I-t CT: Operator (simulates) adjusts pressure regulator for 1-IRV 320 to verify valve opens and closes CUE: Another operator stationed at valve reports:
1-IRV-320 is open at 3 psig 1-IRV-320 is closed at 15 psig.
Reports task is complete JPM IS COMPLETE Page 2 of 2 Revision 0
TASK BRIEFING Unit 1 is in Mode 4 with a cooldown to cold shutdown in progress using the west train of RHR.
A fire has impacted the operation of the West RHR HX Outlet Flow Control valve, 1-IRV-320.
Control Air is available.
The procedure for RCS cooldown using the West RHR Train (01-OHP-4024-LS-7-2) has been implemented and at step 4, the remote operation of 1-IRV-320 is unavailable.
The US directs you to perform the step 4 RNO actions of 01-OHP-4025-LS-7-2 and verify proper operation of 1-IRV-320.
There no hazardous conditions in route or at the local control stations and no tools are required to complete your task.
N02-1 5.doc Page 1 of 1 Revision 0