ML101590081
| ML101590081 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/03/2010 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| References | |
| 50-324/10-301, 50-325/10-301 | |
| Download: ML101590081 (147) | |
Text
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN PLANT NRC Sim A LESSON TITLE: Bypass a LPRM LESSON NUMBER: LOT-SIM-JP-215-007 REVISION NO: 2 SIMULATOR SETUP: Recommended Initial Conditions IC-11, 100% Power, BOC Required Plant Conditions Triggers Malfunctions Overrides Remotes IMPORTANT NOTE: Bypassing a LPRM Resetting the simulator does not reset the PPC. The Scanning Enabled will have to be performed on PPC screen 861. This must be done after each performance of the JPM and prior to the next examinee starting this JPM. . To reset the PPC: Select the 861 screen. Select LPRM 04-21A and hit Control Point 10 Select Scanning Disabled Type E Press Enter Verify value returns (changes from cyan to green) Place PPC on the Main Menu LOT-SIM-JP-215-007 Page 2 of 10 Rev. 2 Bypassing a LPRM SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the performer.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1.LPRM 04-21A (APRM 1) operation has been erratic causing numerous upscale alarms but is currently reading normal. INITIATING CUE: You are directed by the Unit CRS to bypassLPRM 04-21A per 20P-09. Inform the CRS when all required actions have been completed.
LOT-SIM-JP-215-D07 Page 3 of 10 Rev. 2 Bypassing a LPRM PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain current revision of 20P-09, Section 8.4. Current revision of 20P-09, Section B.4 obtained.
SAT/UNSAT*
TIMESTART
___ _ Step 2 -Identify the number of LPRMs in average. The number of LPRMs is identified using the APRM Bar graph on panel P60B or the PPC. SAT/UNSAT
- PROMPT: If asked Inform the examinee as the UnitCRS that the minimum number of LPRM inputs will be maintained Jor the affected APRM and OPRM. Step 3 -Confirm that the minimum number of LPRM inputs can be maintained.
The minimum number of LPRM inputs is verified.
SATIUNSAT*
I PROMPT: If asked provide guidance as the Unit CRSto Bypass APRM 1. Step 4 -Place APRM 1 in BYPASS. APRM 1 is placed in BYPASS. SAT/UNSAT*
Step 5 -Confirm 'BYP' is indicated for APRM 1. APRM 1 BYP heading in inverse video is verified.
SAT/UNSAT*
LOT-SIM-JP-215-007 Page 4 of 10 Rev. 2 Bypassing a LPRM I NOTE: The ETC soft key will be toggledto display the BYPASS SELECTIONS soft key. Step 6 -Press ETC soft key to obtain BYPASS SELECTIONS soft key. Bypass Selections soft key is obtained.
SAT/UNSAT*
Step 7 -Press BYPASS SELECTIONS soft key. Bypass Selections soft key is pressed. **CRITICAL STEP**SAT/UNSAT*
NOTE: If ten (10) seconds expires before the password is accepted (ENT is pressed on the numeric keypad) the screen will revert to the Main APRM Bar Graph display. The examinee must repeat steps to access the correct screen. Step 8 -Enter password "1 234" and press ENT. Password is entered. **CRITICAL STEP**SAT/UNSAT*
NOTE: The right arrow key must be pressed repeatedly to obtain the correct LPRM. The down arrow key will not work. Step 9 -Select LPRM 04-21A AND PRESS BYPASS/HV OFF soft key.LPRM 04-21A is selected and bypassed.
- CRITICAL STEP**SAT/UNSAT*
Step 10 -Confirm LPRM status changes to BYPASS/HV OFF.LPRM 04-21A status is verified as BypasslHV Off. SAT/UNSAT*
Step 11 -Press EXIT soft key. Exit soft key is pressed. SAT/UNSAT*
LOT-SIM-JP-215-007 Page 5 of 10 Rev. 2 Bypassing a LPRM Step 12 -Verify that APRM GAFs are less than or equal to 1. GAF's are less than 1. SAT/UNSAT*
PROMPT: If notified, respond as the Reactor Engineer and/or Unit CRS as necessary.
Step 13 -Notify the Reactor Engineer that the LPRM is bypassed.
Reactor Engineer is notified.
SAT/UNSAT*
Step 14 -Ensure computer point for the bypassed LPRM has its scanning disabled AND a zero value inserted as follows SAT UNSAT a Move the curser to the poke point for the LPRM to be bypassed b Press the trackball
<SELECT> button c Confirm the point 10 for the LPRM appears in the message area at the bottom of the window d Press the <CONTROL POINT 10> hardkey e Confirm the DATA POINT display appears showing data associated with the desired point 10. f Place the curser on the green scanning "ENABLED" text and click g Type "0" to disable h Press keypad "ENTER" key i Confirm scanning text changes to "DISABLED" j Click on the value in the upper right hand area of the screen k Type "0" for the substitute value I Press keypad "ENTER" key m Confirm the point value entered appears in cyan Screen 861 indicates 04-21 value of zero and scanning diabled. SAT/UNSAT*
LOT-SIM-JP-215-007 Page 6 of 10 Rev. 2 Bypassing a LPRM Step 13 -Ensure APRM 1 is removed from BYPASS. APRM Bypass Joystick is returned to the center, OPERA TE, position.
SAT/UNSAT*
PROMPT: Notify the Performer that another Operator will make the log entry and initiate the Work Request. Step 14 -Notify the Unit CRS that LPRM 04-21A is bypassed.
Unit CRS is notified.
SAT/UNSAT*
TERMINATING CUE: When LPRM 04-21A is bypassed and the Unit CRS notified, this JPM is complete.
TIME COMPLETED
____ _ LOT-SIM-JP-215-007 Page 7 of 10 Rev. 2 Bypassing a LPRM LIST OF REFERENCES RELATED TASKS: 2152038401 Respond To A LPRM Failure Per APP A-06 1-7 or 1-8. KIA REFERENCE AND IMPORTANCE RATING: 215005 A2.02 (3.6/3.7).
Ability To Predict Impacts On APRM And Use Procedures To Correct, Control Or Mitigate Consequences
REFERENCES:
2APP A-06 1-8 20P-09 TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2) Safety Function 7, Instrumentation, APRM/LPRM REASON FOR REVISION:
Added steps for PPC. LOT-SIM-JP-215-007 Page 8 of 10 Rev. 2 Bypassing a LPRM Time Required for Completion: Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit: 2 Setting: Control Room Simulator X In-Plant:
Time Critical:
Yes No X Time Limit Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail ----Remedial Training Required:
Yes No __ Did Performer Verify Procedure?
Yes No __ (Each Student should verify one JPM per evaluation set) Comments:
Comments reviewed with Student Evaluator Signature:
Date: ____ _ LOT-SIM-JP-215-D07 Page 9 of 10 Rev. 2 TASK CONDITIONS:
- 1. LPRM 04-21 A (APRM 1) operation has been erratic causing numerous upscale alarms but is currently reading normal. INITIATING CUE: You are directed by the Unit CRS to bypassLPRM 04-21A per 20P-09. Inform the CRS when all required actions have been completed.
8.4 Bypassing a LPRM 8.4.1 1. 8.4.2 Initial Conditions Initials DatelTime Started -------LPRM is required to be bypassed (indication invalid, erratic, etc.). Procedural Steps NOTE: Bypassing an LPRM may cause an APRM, RBM, or OPRM Channel to be inoperable from too few inputs if additional LPRMs have been previously bypassed.
The minimum number of inputs to APRM and OPRM can be identified using numerous PPC Displays -Displays 863 (864, 865, 866), LPRM BAR CHART -APRM 1 (2, 3,4) and Displays 888 (889, 890,891) OPRM 1 (2, 3,4) STATUS/DATA, are examples.
- 1. IDENTIFY the number of LPRMs in average to APRM using the APRM BARGRAPH on Panel P608, or applicable PPC Display. 2. CONFIRM the LPRM can be bypassed and minimum number of LPRM inputs maintained to the affected APRM and OPRM. 3. PLACE applicable APRM in BYPASS. 4. PERFORM the following to bypass an LPRM at Panel P608: LPRM __ _ a. CONFIRM BYP is indicated for the selected APRM channel. b. PRESS ETC soft key to obtain BYPASS SELECTIONS soft key. c. PRESS BYPASS SELECTIONS soft key. C Continuous Use !20P-09 Rev. 28 Page 19 of 39/
8.4.2 Procedural Steps 120P-09 d. ENTER password "1 2 34" AND PRESS ENT. e. Using the cursor keys, SELECT the LPRM AND PRESS BYPASS/HV OFF soft key. f. CONFIRM LPRM status changes to BYPASS/HV OFF. g. PRESS EXIT soft key. 5. ENSURE APRM GAF is less than or equal to 1.00, by performing Section 8.1 to adjust APRM GAFs, if required.
- 6. NOTIFY Reactor Engineer LPRM is bypassed.
- 7. ENSURE the computer point for the bypassed LPRM, on PPC Screen 861, has its scanning disabled AND a zero value inserted as follows: a. MOVE the curser to the poke point for the LPRM to be bypassed.
- b. PRESS the trackball
<SELECT> button. c. CONFIRM the point 10 for the LPRM appears in the message area at the bottom of the window. d. PRESS the <CONTROL POINT 10> hardkey. e. CONFIRM the DATA POINT display appears showing data associated with the desired point 10. f. PLACE the curser on the green scanning "ENABLED" text AND CLICK. g. TYPE "0" to disable. h. PRESS keypad "ENTER" key. Rev. 28 Page 20 of 39/
8.4.2 Procedural Steps 12QP-09 i. CONFIRM scanning text changes to "DISABLED".
- j. CLICK on the value in the upper right hand area of the screen. k. TYPE "0" for the substitute value. I. PRESS keypad "ENTER" key. m. CONFIRM the point value entered appears in cyan. 8. ENSURE applicable APRM is removed from BYPASS. 9. ENSURE the Unit Status Database, LPRM Status, is updated to reflect the bypassed LPRM. 10. ENSURE a W/R is initiated for the bypassed LPRM. 11. NOTIFY Unit SCQ the LPRM has been bypassed.
DatelTime Completed
______ _ Performed By (Print) Reviewed By: __________
_ Unit SCQ Initials Rev. 28 Page 21 of 39/
LESSON TITLE: LESSON PLAN: REVISION NO: PROGRESS ENERGY -CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE CONTROL ROOM NRC Sim B SEP-04 -Restart RB HVAC with Failure to Isolate LOT-SIM-JP-300-K11 01 SEP-04 -Restart RB HVAC with Failure to Isolate SIMULATOR SETUP: A. Initial Conditions:
- 1. Recommended Initial Conditions IC Rx. Pwr. Core Age 11 100% BOC B. Required Plant Conditions A Secondary Containment leak that results in tripping the 012-R609A1B monitors on high radiation, which isolates RB HVAC. RPV water level is below LL2 or OW pressure is >1.7 psig and the Rx Bldg Rad Monitors are tripped. C. Malfunctions Event System Tag Title Value Activate Deactivate (ramp Time Time (sec) rate) (sec) A RW RH013F RWCU Break in Triangle 100%/4 00 NA Room mins A NB NB006F MSL D Break before flow 1%/0 00 NA restrictor mins O. Overrides Event Panel Tag Title Value Activate Deactivate (ramp Time Time (sec) rate) (sec) LOT-SIM-JP-300-K11 Page 2 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate E1: Q5625BRG (RB Supply Fan Red Light) G5B25G1 G to 0.7 over 1 minute Set up the RB Supply Fan A Red light ON to cause the following:
RB Rad Monitor A indication (g5b25g1g ) to start rising to 0.7 over a 1 minute time frame. RB Rad Monitor B indication (g5b25g2g ) to start rising to 0.7 over a 1 minute time frame. PROCESS RX BLDG VENT RAD HI Annunciator (ZUA345) to actuate after 50 sec. PROCESS RX BLDG VENT RAD HI-HI Annunciator (ZUA335) to actuate after 55 sec. E2: trc:2,aod:g5b25g1 9 Set up the RB Rad Monitor A meter override to be deleted on depressing the RB Isolation Dampers close switch (K5608JCV close is true). E3: trc:3,aod:g5b25g2g Set up the RB Rad Monitor B meter override to be deleted on depressing the RB Isolation Dampers close switch (K5608JCV close is true). E. Special Instructions
- 1. Place simulator in RUN and activate malfunctions.
- 2. When drywell pressure rises to cause a reactor scram, carry out the RO immediate actions. Make sure level set is at 187 inches (this will go back to 170 inches after coming out of freeze) Make sure that SEP-04 is cleaned. LOT-SIM-JP-300-K11 Page 3 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate SAFETY CONSIDERATIONS:
NONE. EVALUATOR NOTES: (Do not read to examinee)
- 1. The applicable procedure section WILL NOT be provided to the examinee.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the examinee.
Read the following to trainee. TASK CONDITIONS:
- 1. EOP-03-SCCP has been entered. 2. A high-radiation condition sensed by the RB Vent Radiation Monitors (D12-R609NB) resulted in the isolation of Reactor Building HVAC. 3. Reactor Building Exhaust temperature has not exceeded 135°F. 4. The leak has been isolated and EOP-03-SCCP directs restoring RB HVAC. 5. Instrument air pressure to the latch actuators for the reactor building ventilation isolation valves was never lost. INITIATING CUE: The Unit SCO directs you to restart Reactor Building HVAC per SEP-04 and inform him when your actions are complete.
LOT-SIM-JP-300-K11 Page 4 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain current revision of OEOP-SEP-04.
Current revision of OEOP-SEP-04 obtained.
SAT/UNSAT*
TIME START: ____ _ PROMPT: If asked, indicate the peak radiation levels on D12-RR-R605 at 4mr/hr and the Reactor Building Exhaust temperature has not exceeded 135°F . Step 2 -Verifies RB vent rad monitors have not been off-scale high as indicated on D12-RR-605 and that Reactor Building Exhaust temperature has not exceeded 135°F Peak radiation levels determined on D12-RR-R605 to be onscale. Verifies UA-03, 6-2 not in alarm. SAT/UNSAT*
PROMPT: When requested, install jumpers by modifying Remote Function EP _IAEOPJP6 to ON and inform the examinee.that jumpers have been installed to bypass reactor low water level and Drywell high pressure isolation interlocks.
Step 3 -Request jumpers be installed to bypass the low reactor level and high drywell pressure interlocks.
Jumpers are installed to bypass the interlocks.
- CRITICAL STEP ** SATIUNSAT*
Step 4 -Place the CAC PURGE VENT ISOL OVRD, CAC-CS-5519 switch to OVERRIDE.
CAC-CS-5519 switch in OVERRIDE.
- CRITICAL STEP ** SAT/UNSAT*
LOT-SIM-JP-300-K11 Page 5 of 11 REV. 1 NOTE: SEP-04 -Restart RB HVAC with Failure to Isolate When both Process RB Vent Exhaust Rad Monitors are reset, annunciators UA-033-5 (PROCESS RX BLDG VENT RAD HI-HI) clears and annunciators UA-05 3-5 (SBGT SYS B FAILURE) and 4-6 (SBGT SYS A FAILURE) alarm. Step 5 -Reset the Process Reactor Building Vent Exhaust Rad Monitors at Panel H12-P606.
D12-RM-K609A and o 12-RM-K609B are reset at Panel H12-P606.
- CRITICAL STEP ** SAT/UNSAT*
Step 6 -Reset the PCIS Group 6 Isolation on RTGB Panel P601. PCIS Group 6 Isolation reset by depressing pushbuttons S32 and S33 on P601. ** CRITICAL STEP ** SAT/UNSAT*
PROMPT: If asked, inform examinee that instrument air pressure to the Reactor Building ventilation isolation valve latch actuators was never lost, OR: PROMPT: If requested, inform the examinee as Reactor Building Auxiliary Operator that the latches for the Reactor Building Ventilation Isolation Dampers are in the unlatched position.
Step 7 -Open RB Vent Isol Vlvs: a. C-BFIV-RB and A-BFIV-RB C-BFIV-RB, A-BFIV-RB are open. ** CRITICAL STEP ** SAT/UNSAT*
- b. D-BFIV-RB and B-BFIV-RB D-BFIV-RB, B-BFIV-RB are open. ** CRITICAL STEP ** SAT/UNSAT*
LOT-SIM-JP-300-K11 Page 6 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate PROMPT: When RB HVAC Supply Fan A has been started (Red lamp on the fan) verify Event Trigger E1 actuates to cause REACTOR BLDG VENT RAD Monitor to start to rise and go above 4 mr/hr. Step 8 -Start as many Reactor Building Exhaust and Supply Fans as possible to provide maximum ventilation.
At least one Reactor Building Supply and Exhaust Fan Running. ** CRITICAL STEP ** SATIUNSAT*
Step 9 -Recognizes Reactor Building Vent Rad Monitor increasing.
NOTE: Radiation monitor readings are rising. SAT/UNSAT*
Closing the BFIV-RBs will cause the Reactor Building Vent and Supply fansto automatically trip. Step 10 -Manually stop the Reactor Building Supply and Exhaust Fans. NOTE: All Reactor Building Supply and Exhaust Fans are stopped. SAT/UNSAT*
Closing the BFIV-RBs will cause the RB Vent Rad Monitors overrides to be deleted and go to normal readings.
LOT-SIM-JP-300-K11 Page 7 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate Step 11 -Manually close RB Vent Isol Vlvs: a. C-BFIV-RB and A-BFIV-RB C-BFIV-RB, A-BFIV-RB are closed. ** CRITICAL STEP ** SAT/UNSAT*
- b. O-BFIV-RB and B-BFIV-RB D-BFIV-RB, B-BFIV-RB are closed. ** CRITICAL STEP ** SAT/UNSAT*
Step 12 -Ensure initiated SBGT system. Both SBGT trains are operating.
SAT/UNSAT*
Step 13 -Unit SCQ informed that SEP-04, RB HVAC Restart procedure cannot be performed at this time. Unit SCQ informed.
SAT/UNSAT*
I TERMINATING CUE: RB HVAC has been isolated and SBGT has been verified running.
- Comments required for any step evaluated as UNSAT. STOP TIME: ____ _ LQT-SIM-JP-300-K11 Page 8 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate LIST OF REFERENCES RELATED TASKS: 288205B501 Restart Reactor Building HVAC per EOP-01-SEP-04 KIA REFERENCE AND IMPORTANCE RATING: 288000 A3.01 3.8, 3.8 Ability to monitor Plant Ventilation System automatic isolation/initiation signals in the control room
REFERENCES:
OEOP-SEP-04 Rev. 11 TOOLS AND EQUIPMENT:
Plant Page SAFETY FUNCTION (from NUREG 1123, Rev 2): 9 -Radioactivity Release REASON FOR REVISION:
Changed to rad signal vs high temperature for the alternate path. LOT-SIM-JP-300-K11 Page 9 of 11 REV. 1 SEP-04 -Restart RB HVAC with Failure to Isolate Time Required for Completion:
20 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit: 2 Setting: Control Room Simulator--L (Not applicable to In-Plant JPMs) Time Critical:
Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Trainee: ____________
_ JPM: Pass Fail --Remedial Training Required:
Yes No __ Did Trainee Verify Procedure as Authorized Copy?: Yes No __ _ (Each Student should verify one JPM per evaluation set) Comments:
Comments reviewed with Student Evaluator Signature:
____________
_ Oate: ____ _ LOT-SIM-JP-300-K11 Page 10 of 11 REV. 1 TASK CONDITIONS:
- 1. EQP-03-SCCP has been entered. 2. A high-radiation condition sensed by the RB Vent Radiation Monitors (012-R609A1B) resulted in the isolation of Reactor Building HVAC. 3. Reactor Building Exhaust temperature has not exceeded 135°F. 4. The leak has been isolated and EQP-03-SCCP directs restoring RB HVAC. 5. Instrument air pressure to the latch actuators for the reactor building ventilation isolation valves was never lost. INITIATING CUE: The Unit SCQ directs you to restart Reactor Building HVAC per SEP-04 and inform him when your actions are complete.
Progress Energy BRUNSWICK NUCLEAR PLANT PLANT OPERATING MANUAL VOLUME VI EMERGENCY OPERATING PROCEDURE UNIT o OEOP-01-SEP-04 REACTOR BUILDING HVAC RESTART PROCEDURE REVISION 12 I OEOP-01-SEP-04 Rev. 12 Page 1 of 61 REACTOR BUILDING HVAC RESTART 1.0 ENTRY CONDITIONS As directed by Secondary Containment Control Procedure, EOP-03-SCCP OR As directed by Containment and Radioactivity Release Control, SAMG-02 2.0 OPERATOR ACTIONS NOTE: Manpower:
1 Control Operator 1 Auxiliary Operator 1 Independent Verifier Special equipment:
2 jumpers (10 and 11) CO: 2.1. IF the reactor building ventilation radiation monitors have been D off scale high as indicated on D12-RR-R605 OR the reactor building exhaust temperature has exceeded 135°F (UA-03, 6-2), THEN EXIT this procedure.
CAUTION Installation of the following jumpers will also inhibit the automatic start of SBGT on reactor low water level and on high drywell pressure.
CO: CO: 2.2 INSTALL the following jumpers to bypass the reactor low water level and drywell high pressure interlocks:
Jumper 10 in Panel XU-27, Terminal Board E, from the right side of Terminal 28 to the right side of Terminal 30 Jumper 11 in Panel XU-28, Terminal Board E, from the right side of Terminal 28 to the right side of Terminal 30 I OEOP-01-SEP-04 Rev. 12 D D Page 2 of 61 2.0 OPERATOR ACTIONS CO: 2.3 PLACE the affected unit's CAC PURGE VENT ISOL OVRD, CAC-CS-5519, switch to OVERRIDE.
2.4 IF necessary, THEN RESET the following reactor building ventilation radiation monitors at Panel H12-P606:
CO: PROCESS REACTOR BLDG VENTILA TlON RADIA TlON MONITOR A, D12-RM-K609A CO: PROCESS REACTOR BLDG VENTILA TlON RADIA TlON MONITOR B, D12-RM-K609B CO: 2.5 RESET the Group 6 isolation from the RTGB. NOTE: IF the green indicator tab is against the yellow bar, THEN the valve is unlatched and valve operation is permitted.
CAUTION D D D D Attempting to open reactor building ventilation isolation valves when the latches are engaged will damage the latch/damper assemblies.
AO: AO: AO: AO: 2.6 IF instrument air pressure to the latch actuators for the reactor building ventilation isolation valves has been lost and restored, THEN DISPATCH an AO to ensure the latches for the following valves are in the unlatched position prior to performing Step 2.7: RB VENT INBD SUPPLY ISOL VLV, A-BFIV-RB RB VENT OTBD SUPPL Y ISOL VL V, B-BFIV-RB RB VENT INBD EXHAUST ISOL VL V, C-BFIV-RB RB VENT OTBD EXHAUST ISOL VL V, D-BFIV-RB I OEOP-01-SEP-04 Rev. 12 D D D D Page 3 of 61 2.0 OPERATOR ACTIONS CO: CO: 2.7 OPEN the following valves: RB VENT INBD ISOL VALVES, EXHAUST C-BFIV-RB, SUPPL Y A-BFIV-RB RB VENT OTBD ISOL VALVES, EXHAUST D-BFIV-RB, SUPPL Y B-BFIV-RB o o NOTE: In order to start a reactor building supply or exhaust fan, the control switch should be held in START until the discharge damper is full open. CO: 2.8 START as many reactor building exhaust and supply fans as 0 possible to provide maximum ventilation (OP-37.1).
2.9 IF PROCESS RX BLDG VENT RAD HI-HI annunciator (UA-03 3-5) (alarm setpoint at 4 mR/hr) OR RX BLDG VENT TEMP HIGH annunciator (UA-03 6-2) (alarm setpoint at 135°F) is received, THEN: CO: a. ENSURE reactor building exhaust and supply fans are off. 0 b. ENSURE the following valves are closed: CO: RB VENT INBD ISOL VALVES, EXHAUST 0 C-BFIV-RB, SUPPL Y A-BFIV-RB CO: RB VENT OTBD ISOL VALVES, EXHAUST 0 D-BFIV-RB, SUPPL Y B-BFIV-RB CO: c. ENSURE the SBGT System has initiated (OP-10). 0 I OEOP-01-SEP-04 Rev. 12 Page 4 of 61 2.0 OPERATOR ACTIONS Initials 2.10 WHEN reactor low water level and drywell high pressure conditions have cleared, THEN REMOVE the following jumpers: CO: Jumper 10 in Panel XU-27, Terminal Board E, from the / right side of Terminals 28 and 30 Ind.ver. CO: Jumper 11 in Panel XU-28, Terminal Board E, from the / right side of Terminals 28 and 30 Ind.ver. CO: 2.11 WHEN PROCESS OG VENT PIPE RAO HI-HI annunciator
/ (UA-03 5-4) clears, THEN PLACE CAC PURGE VENT ISOL Ind.ver. OVRO, CAC-CS-5519, switch to OFF. CO: 2.12 OPERATE the Reactor Building Ventilation System and the SBGT System as directed by the Unit SCO (OP-37.1 and OP-10). CO: 2.13 EXIT this procedure AND CONTINUE in the procedure(s) in effect. Date/Time Completed Performed By (Print) Initials Reviewed By: _____________
_ Unit SCO I OEOP-01-SEP-04 Rev. 12 Page 5 of 61 REVISION
SUMMARY
Revision 12 converts the document and upgrades procedure format. Added independent verifier to manpower requirements.
Revision 11 incorporates changes required to support implementation of Severe Accident Management Guidelines.
Entry conditions have been revised to reflect possible entry from Containment and Radioactivity Release Control, OSAMG-02.
Allowances to restart ventilation when 135°F has been exceeded have been deleted due to Reactor Building EQ concerns.
I OEOP-01-SEP-04 Rev. 12 Page 6 of 61 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR NRC Sim C LESSON TITLE: Place BLoop RHR in Suppression Pool Cooling lAW Hard NSW Header Failure LESSON NUMBER: LOT-SIM-JP-017-A10 REVISION NO: 7 Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure A. Initial Conditions:
- 1. Recommended Initial Conditions IC Rx. Pwr. Core Age 11 100% BOC 2. Required Plant Conditions Suppression Pool Temperature>
95°. B. Malfunctions None required C. Overrides Switches Event Pane Tag Title I NA P601 K1705A RHR SW Pmps BID Nu SW-V105 D. Remote Function Event Panel Tag Title NA P601 ZVSW105M SW-V105 NSW to RHRSW E. Special Instructions Value Activate Deactivate (ramp rate) Time (sec) Time (sec) As Is 0 0 Value Activate Deactivate (ramp rate) Time (sec) Time (sec) Off 0 0 1. Open SRV(s) as necessary to raise Suppression Pool temperature above 95°. 2. Ensure Suppression Pool High Temperature alarm on Panel UA-12 is annunciated.
- 3. Place red caps on RHR Pump 2A and 2C. LOT-SIM-JP-017-A 10 Page 2 of 9 Rev.7 Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure SAFETY CONSIDERATIONS:
NONE EVALUATOR NOTES: (Do not read to examinee)
- 1. The applicable procedure section WILL be provided to the examinee, once it is demonstrated he/she knows the correct procedure.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the examinee.
Read the following to examinee.
TASK CONDITIONS:
- 1. Torus temperatures is >95°F due to SRV B failure. 2. SRV B fuses have been pulled which closed the valve. 3. Primary Containment Control Procedure requires Suppression Pool Cooling to be placed in service. 4. The standby NSW pump has been started. 5. RHR Loop A is under clearance.
INITIATING CUE: The Unit CRS has directed you to place B RHR Loop in suppression pool cooling per the Emergency Suppression Pool Cooling Hard Card (One RHRSW pump and one RHR pump). LOT-SIM-JP-017 -A 10 Page 3 of 9 Rev.7 Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
I PROMPT: If asked, another RO is not available to perform peer checks / IVs. Step 1 -Obtain current revision of Emergency Suppression Pool Cooling hard card for Loop B. Current revision of Emergency Suppression Pool Cooling hard card obtained.
SAT/UNSAT*
TIME START: ____ _ Step 2 -Attempt to open suction valve to RHR SW pump from NSW SW-V105. Recognize SW-V1 05 will not open. . SAT/UNSAT*
PROMPT: PROMPT: If requested to manually open SW-V105, report valve is mechanically bound and will not open by handwheel.
If requested to turn breaker OFF for SW-V105, activate REMOTE FUNCTION, ZVSW105M, SW-V105 NSW toRHRSW, OFF. If. Examinee informs Unit CRS RHR cannot be placed into service using NSW, direct the examinee that EOP flowcharts require RHR Loop B to be placed in Suppression Pool Cooling now. If asked, give permission to place B Loop in service using CSW header. Step 3 -Open CSW SW-V1 01, Conventional Service Water to RHRSW Pumps. CSW SW-V1 01 opened. ** CRITICAL STEP ** SAT/UNSAT*
Step 4 -Close SW-V143, RHR SW Well Water Supply Valve. SW-V143 Closed. SAT/UNSAT*
LOT-SIM-JP-017-A 10 Page 4 of 9 Rev.7 Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure Step 5 -Open SW-V102, Conventional-Nuclear Header Cross-tie valve. Crosstie valve SW-V102, opened. ** CRITICAL STEP ** SATIUNSAT*
Step 6 -If LOCA signal is present PLACE RHR SW Booster Pumps B & 0 LOCA Override Switch to Manual Override Recognize no LOCA signal is present and override is not required.
SAT/UNSAT*
Step 7 -Start 2B or 20 RHR SW pumps. 2B or 20 RHR SW pumps started. ** CRITICAL STEP ** SA TlUNSAT* Step 8 -Adjust RHR HX 2B SW Discharge Valve, E11-PDV-F068B to obtain desired RHR SW flow. Flow is adjusted using F06BB to obtain 2000 -4000 gpm. ** CRITICAL STEP ** SAT/UNSAT*
Step 9 -Supply cooling water to the Vital Header. SW-V111 or SW-V117 opened to supply cooling water to the Vital Header. SAT/UNSAT*
Step 10 -If LOCA signal is present, Verify Spray Logic is made up. Recognize Spray Logic not required.
SAT/UNSAT*
Step 11 -If EII-F015B is open, then close E11-F017B.
Recognize E11-F015B is not open and E11-F017B closure is not required.
SAT/UNSAT*
LOT-SIM-JP-01
?-A1 0 Page 5 of 9 Rev.?
Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure Step 12 -Start RHR Pump 2B or 2D. RHR pump 2B or 20 started. ** CRITICAL STEP ** SAT/UNSAT*
Step 13 -Open E11-F028B, Torus Discharge Isolation Valve. E11-F028B opened. ** CRITICAL STEP ** SAT/UNSAT*
Step 14 -Throttle open E11-F024B, Torus Cooling Isolation Valve, to establish desired flow. E11-F024B throttled open to obtain 6000-10,000 gpm (1 pump). ** CRITICAL STEP ** SAT/UNSAT*
Step 15 -Throttle closed E 11-F048B, HX Bypass Valve. E11-F048B throttled fully closed. SAT/UNSAT*
Step 16 -Inform Unit CRS that BLoop RHR Suppression Pool Cooling is in service with one pump operation and cooling is aligned to the Conventional Service Water header. Unit CRS notified.
SAT/UNSAT*
TERMINATING CUE: When the E11-F024B has been opened and 6,000 to 10,000 gpm flow has been established this JPM can be terminated.
- Comments required for any step evaluated as UNSAT. TIME STOP: ____ _ LOT-SIM-JP-01
?-A1 0 Page 6 of 9 Rev.?
Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure LIST OF REFERENCES RELATED TASKS: 205014 B1 01 Start Up RHR In Suppression Pool Cooling Mode Per OP-17 KIA REFERENCE AND IMPORTANCE RATING: 219000 A4.12 4.1,4.1 Ability to manually operate and/or monitor in the control room suppression pool temperature.
REFERENCES:
Emergency Suppression Pool Cooling hard card, S/1064. TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev 2): Safety Function 5, Containment Integrity REASON FOR REVISION:
Changed to one pump vs. maximizing due to PU&A concerns.
LOT-SIM-JP-017-A10 Page 7 of 9 Rev.7 Place BLoop RHR in Suppression Pool Cooling lAW Hard Card -NSW Header Failure Time Required for Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit: 2 Setting: Control Room Simulator L (Not applicable to In-Plant JPMs) Time Critical:
Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Examinee:
JPM: Pass __ Fail __ Remedial Training Required:
Yes No __ Did Examinee Verify Procedure?
Yes ____ No ___ _ (Each Student should verify one JPM per evaluation set) Comments:
___________________________________________________
_ Comments reviewed with Student Evaluator Signature:
Date: --------LOT-SIM-JP-01?-A10 Page 8 of 9 Rev.?
TASK CONDITIONS:
- 1. Torus temperatures is >95°F due to SRV B failure. 2. SRV B fuses have been pulled which closed the valve. 3. Primary Containment Control Procedure requires Suppression Pool Cooling to be placed in service. 4. The standby NSW pump has been started. 5. RHR Loop A is under clearance.
INITIATING CUE: The Unit CRS has directed you to place B RHR Loop in suppression pool cooling per the Emergency Suppression Pool Cooling Hard Card (One RHRSW pump and one RHR pump).
ATTACHMENT 8 Page 2 of 2 Emergency Suppression Pool Cooling START RHR SW BLOOP (NUC) RHR SW BLOOP (CONV) : OPEN SW-V105 : CLOSE SW-V143 : IF LOCA SIGNAL IS PRESENT PLACE RHR SW BOOSTER PUMPS B & D LOCA OVERRIDE SWITCH TO MANUAL OVERRIDE : START RHR SW PMP : ADJUST E11-PDV-F068B
- SUPPLY CLG WTR TO VITAL HDR START RHRLOOP B : OPEN SW-V101 : CLOSE SW-V143 : OPEN SW-V102 : IF LOCA SIGNAL IS PRESENT PLACE RHR SW BOOSTER PUMPS B & D LOCA OVERRIDE SWITCH TO MANUAL OVERRIDE : START RHR SW PMP : ADJUST E11-PDV-F068B
- SUPPLY CLG WTR TO VITAL HDR __ : IF LOCA SIGNAL IS PRESENT, VERIFY SPRAY LOGIC IS MADE UP 120P-17 __ : IF E11-F015B IS OPEN, THEN CLOSE E11-F017B
- THROTTLE E11-F048B Rev. 155 2/1063 S/1064 Page 288 of 2971 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR NRC Sim D LESSON TITLE: HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. LESSON NUMBER: LOT-SIM-JP-019-14 REVISION NO: 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. SIMULATOR SETUP Recommended Initial Conditions IC-11 100%, BOC Event Triggers E1 -Activates all malfunctions/overrides when F008 is opened. Malfunctions A, ES040F, HPCI Fail To Auto Start A, ES053F -E41-F002 Fail To Auto Close A, ES054F -E41-F003 Fail To Auto Close E1, ES047F -HPCI Stm Brk HPCI Room, 1 %, 0 SEC Overrides Lamps E1, P601, Q1112SWL, Auto Isol Sig A White, ON with 5 sec activation time E1, P601, Q1111 SWL, Auto Isol Sig B White, ON with 5 sec activation time Alarms E1, P601, ZA 135, HPCI Isol Trip Sig A, ON with 5 sec activation time E1, P601, ZA 145, HPCI Isol Trip Sig B , ON with 5 sec activation time E1, P601, ZA152, HPCI Turb Exh Diaph Press Hi, On Special Instructions
- 1. Scram the Reactor and close MSIV's 2. Perform scram immediate actions 3. Ensure RPV level is stable and >LL2 LOT-SIM-JP-019-14 Page 2 of 9 REV. 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. SAFETY CONSIDERATIONS:
None. EVALUATOR NOTES: (Do not read to trainee) 1. The applicable procedure section WILL NOT be provided to the trainee. 2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee. Read the following to trainee. TASK CONDITIONS:
- 1. The reactor has scrammed due to MSIV closure. 2. RPV water level is stable. 3. HPCI is not required for RPV level control. INITIATING CUE: You are directed by the Unit CRS to start HPCI for pressure control to lower pressure to 800 psig per the Hard Card and inform the Unit CRS when the actions are complete.
LOT-SIM-JP-019-14 Page 3 of 9 REV. 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain Hard Card for HPCI Pressure Control In EOPs. Hard Card for HPCI Pressure Control obtained.
SATIUNSAT Time Started: ____ _ Initial Reactor Pressure:
____ _ NOTE: Auto Initiation signal can be verified to be reset by observing the white light is not illuminated or by depressing the reset pushbutton.
Step 2 -Ensure HPCI auto initiation is reset. HPCI auto initiation is reset. SATIUNSAT Step 3 -Ensure Auxiliary Oil Pump is not running. Auxiliary Oil Pump verified not running. SAT/UNSAT Step 4 -Place HPCI Flow Control, E41-FIC-R600, in Manual (M), and adjust output demand to approximately midscale, using the Manual lever. Manual selected and lever (moved to the left) lowered output to midscale.
SAT/UNSAT Step 5 -Ensure E41-V8 and E41-V9 are closed. E41-V8 and E41-V9 indicate closed. SAT/UNSAT LOT-SIM-JP-019-14 Page 4 of 9 REV. 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. Step 6 -Open E41-F011.
E41-F011 indicates full open. Step 7 -Open E41-F059.
E41-F059 indicates full open. Step 8 -Start Vacuum Pump and leave in start Vacuum Pump is running Step 9 -Open E41-F001.
E41-F001 indicates full open. Step 10 -Start Auxiliary Oil Pump and Leave in START. ** CRITICAL STEP ** SAT/UNSAT
- CRITICAL STEP ** SAT/UNSAT SAT/UNSAT
- CRITICAL STEP ** SAT/UNSAT Auxiliary Oil Pump control switch in the START position.
- CRITICAL STEP ** SAT/UNSAT Step 11 -When speed stops increasing, then adjust speed to approximately 2100 RPM. Speed is adjusted to 2100 RPM. SAT/UNSAT LOT-SIM-JP-019-14 Page 5 of 9 REV. 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. SIMOP: Verify trigger E1 is activated when F008 is opened. Step 12 -Throttle open E41-F008 to maintain desired reactor pressure.
E41-F008 indicates dual indication.
SAT/UNSAT Step 14 -Determine HPCI has failed to auto isolate and manually isolate HPCI by closing E41-F002 and F003. E41-F002 or E41-F003 indicate full closed. ** CRITICAL STEP ** SAT/UNSAT Step 15 -Inform Unit CRS HPCI is isolated and unavailable for pressure control. CRS informed HPC/ is unavailable for injection.
SAT/UNSAT TERMINATING CUE: When HPClsteamleak is isolated by closing the E41-F002 or F003 this JPM is complete.
Comments required for any step evaluated as UNSA T. Time completed:
____ _ LOT-SIM-JP-019-14 Page 6 of 9 REV. 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. RELATED TASKS: 2062008401, Place HPCI in Reactor Pressure control from the standby lineup per OP-19 KIA REFERENCE AND IMPORTANCE RATING: 295025 EA 1.04 3.8/3.9 Ability to operate and/or monitor the following as they apply to High Reactor Pressure:
HPCI (plant specific)
REFERENCES:
20P-19, Section 8.2 Hard Card S/1019, HPCI Pressure Control In EOPs TOOLS AND EQUIPMENT:
None. SAFETY FUNCTION (from NUREG 1123, Rev 2.) 3 -Pressure Control (HPCI) REASON FOR REVISION:
Modified JPM to have exhaust diaphragm failure. LOT-SIM-JP-019-14 Page 7 of 9 REV. 0 HPCI Start in Pressure Control Per The Hard Card -Exhaust Diaphragm Failure. Vailidation Time: Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual l Unit: 2 Setting: Control Room Simulatorl( Not applicable to In-Plant JPMs) Time Critical:
Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Trainee: ________________
_ JPM: Pass Fail ----Remedial Training Required:
Yes No __ Did Trainee Verify Procedure?
Yes No __ _ (Each Student should verify one JPM per evaluation set.) Comments:
Comments reviewed with Student Evaluator Signature:
Date: ______ _ LOT-SIM-JP-019-14 Page 8 of 9 REV. 0 TASK CONDITIONS:
- 1. The reactor has scrammed due to MSIV closure. 2. RPV water level is stable. 3. HPCI is not required for RPV level control. INITIATING CUE: You are directed by the Unit CRS to start HPCI for pressure control to lower pressure to 800 psig per the Hard Card and inform the Unit CRS when the actions are complete.
ATTACHMENT 8 Page 1 of 1 HPCI Instructional Aid OP-19 HPCI PRESSURE CONTROL IN EOPs 1. ENSURE HPCI AUTO INITIATION IS RESET D 2. ENSURE AUXILIARY OIL PUMP IS NOT RUNNING D 3. PLACE HPCI FLOW CONTROL, E41-FIC-R600, IN MANUAL (M), D AND ADJUST OUTPUT DEMAND TO APPROXIMATELY MIDSCALE, USING THE MANUAL LEVER. 4. ENSURE E41-V8 AND E41-V9 ARE CLOSED D 5. OPEN E41-F011 D 6. OPEN E41-F059 D 7. START VACUUM PUMP AND LEAVE IN START D 8. OPEN E41-F001 D 9. START AUXILIARY OIL PUMP AND LEAVE IN START D 10. ENSURE E41-V8 AND E41-V9 ARE OPEN D 11. WHEN SPEED STOPS INCREASING, THEN ADJUST SPEED TO D APPROXIMATELY 2100 RPM 12. THROTTLE OPEN E41-F008, UNTIL FLOW IS BETWEEN 1000 D GPM AND 1500 GPM 13. ENSURE E41-F012 IS CLOSED WHEN FLOW HAS INCREASED D ABOVE 800 GPM 14. ENSURE E41-F025 AND E41-F026 ARE CLOSED D 15. ADJUST HPCI FLOW CONTROL, E41-FIC-R600, SETPOINT TO D MATCH SYSTEM FLOW, AND THEN PLACE E41-FIC-R600 IN AUTO (A) 16. START SBGT (OP-10) D 17. ENSURE BAROMETRIC CNDSR CONDENSATE PUMP IS D OPERATING
- 18. ADJUST HPCI AS NEEDED TO CONTROL REACTOR D PRESSURE 2/1020 S/1019 \20P-19 Rev. 124 Page 107 of 112\
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN PLANT NRC Sim E LESSON TITLE: Energize 230 kV Bus 2B. LESSON NUMBER: LOT-SIM-JP-050-A06 REVISION NO: 1 Energize 230 kV Bus 2B. SIMULATOR SETUP: Recommended Initial Conditions IC-11, 100% Power, BOC Required Plant Conditions Open PCB's 26B, 27B, 28B, 29B, 30B, and 31 B. Triggers Malfunctions Overrides Remotes SAFETY CONSIDERATIONS:
None LOT-SIM-JP-050-A06 Page 2 of 9 Rev. 1 Energize 230 kV Bus 2B. EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the performer.
- 2. Provide examinee with a copy of 20P-50, Section 5.1, marked complete through step 5.1.2.7 3. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. 230 kV Bus 2B tripped due to a lightning strike. 2. 230 kV Bus 2A is energized and supplying power to the SAT. 3. The bus has been inspected and determined to be ready for energizing.
- 4. The load dispatcher has directed energizing 230 kV Bus 2B by closing PCB 31 B. 5. 20P-50, Section 5.1 is in progress and is completed up to and including step 5.1.2.7. INITIATING CUE: You are directed to energize 230 kV Bus 2B in accordance with 20P-50, Section 5.1. Inform the Unit SCO when 230 kV Bus 2B is energized through PCB 31 B. LOT-SIM-JP-050-A06 Page 3 of 9 Rev. 1 Energize 230 kV Bus 2B. PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain current revision of 20P-SO, Section S.1. Current revision of 20P-50, Section 5. 1 obtained.
SAT/UNSAT*
TIME START ____ _ NOTE: The examinee should determine actions associated with 230 kV Bus 2A are not applicable.
PROMPT: If requested, as Unit SCO concur that all steps associated with 230 kV Bus 2A are not applicable.
Step 2 -Confirm the white indicating lights on Panel XU-S above the following are illuminated:
NOTE: a. Bus 2B Whiteville 230 kV Breaker 31 B synchronizing switch. 0 b. Bus 2B Delco West 230 kV Breaker 30B synchronizing switch. 0 c. Bus 2B Wallace 230 kV Breaker 28B synchronizing switch. 0 d. Bus 2B Wilmington Corning 230 kV Breaker 27B synchronizing switch. 0 White indicating lights confirmed to be illuminated. . SAT/UNSAT*
The supervisory switch must be in local before the PCB can be operated from control room panel XU-So Step 3 -Place Bus 2B Whiteville 230 kV Breaker 31 B PCB Supervisory Local/Remote switch in Local. Supervisory switch is in Local. **CRITICAL STEP**SATIUNSAT*
Step 4 -Place Bus 2B Whiteville 230 kV Breaker 31 B PCB Synchronizing switch in ON. Synchronizing switch is ON. **CRITICAL STEP**SAT/UNSAT*
LOT -SIM-J P-050-A06 Page 4 of 9 Rev. 1 Energize 230 kV Bus 2B. Step 5 -Place Bus 2B Voltmeter switch in ON. Voltmeter switch is ON. I NOTE: 230 kV Bus 2Bis deenergizedso only incoming volts will indicate voltage. Step 6 -Ensure incoming and running voltmeter values are equal. Marked up version of procedure has this marked as NA. NOTE: 230 kV Bus 2B is de-energized,so synchronization is not required.
Step 7 -Close the 230 kV breaker. This is energizing a dead bus, so synchronization is not required.
PCB 31 B is closed. SAT/UNSAT*
SAT/UNSAT*
- CRITICAL STEP**SATIUNSAT*
Step 8 -Confirm 230 kV breaker has closed by observing indicating light. PCB 31B confirmed closed. SAT/UNSAT*
Step 9 -Confirm running and incoming voltmeters indicate the same value. Voltmeters confirmed to be indicating approximately the same value. SAT/UNSAT*
Step 10-Place Bus 2B Voltmeter Switch in OFF. Voltmeter switch is in OFF. SAT/UNSAT*
LOT-SIM-JP-050-A06 Page 5 of 9 Rev. 1 Energize 230 kV Bus 2B. Step 11 -Place Bus 2B Whiteville 230 kV Breaker 31 B PCB Synchronizing switch in OFF. Synchronizing switch is OFF. SAT/UNSAT*
Step 12 -Place Bus 2B Whiteville 230 kV Breaker 31 B PCB Supervisory Local/Remote switch in Remote. Supervisory switch is in Remote. SAT/UNSAT*
Step 13 -Place Bus 2B Whiteville 230 kV Breaker 31B Auto Reclose Control Switch in AUTO. Auto Reclose control switch is in AUTO. SAT/UNSAT*
Step 11 -Informs Unit SCO that 230 kV Bus 2B is energized.
Unit seo is informed 230 kV Bus 2B is energized.
SAT/UNSAT*
TERMINATING CUE: When PCB 31 B is closed and the Unit seo has been informed that 230 kV Bus 2Bhas been energized this JPM is complete.
TIME STOP ____ _ LOT-SIM-JP-050-A06 Page 6 of 9 Rev. 1 LIST OF REFERENCES RELATED TASKS: 262201 81 01 Energize 230 kV Bus 2B. KIA REFERENCE AND IMPORTANCE RATING: 262001 A4.01 3.4/
3.7 REFERENCES
20P-50 TOOLS AND EQUIPMENT:
None. SAFETY FUNCTION (from NUREG 1123, Rev 2.): 6 -Electrical REASON FOR REVISION:
Removed actions for MOD 268. LOT -SIM-J P-050-A06 Page 7 of 9 Rev. 1 Energize 230 kV Bus 2B. Time required for Completion:
12 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit: 2 Setting: Control Room Simulator X In-Plant:
Time Critical:
Yes No X Time Limit Alternate Path: Yes No X EVALUATION Performer:
_______________
_ JPM: Pass __ Fail __ Remedial Training Required:
Yes No __ Did Performer Verify Procedure?
Yes No __ (Each Student should verify one JPM per evaluation set) Comments:
Comments reviewed with Student Evaluator Signature:
______________
_ Date: ____ _ LOT-SIM-JP-050-A06 Page 8 of 9 Rev. 1 TASK CONDITIONS:
- 1. 230 kV Bus 2B tripped due to a lightning strike. 2. 230 kV Bus 2A is energized and supplying power to the SAT. 3. The bus has been inspected and determined to be ready for energizing.
- 4. The load dispatcher has directed energizing 230 kV Bus 2B by closing PCB 31 B. 5. 20P-50, Section 5.1 is in progress and is completed up to and including step 5.1.2.7. INITIATING CUE: You are directed to energize 230 kV Bus 2B in accordance with 20P-50, Section 5.1. Inform the Unit SCO when 230 kV Bus 2B is energized through PCB 31 B.
5.0 STARTUP 5.1 Energizing the 230 KV Switchyard 5.1.1 Initial Conditions
- 1. 2. All applicable prerequisites as listed in Section 4.0 are met. The Switchyard Electrical Lineup is complete in accordance with Attachment 1 A. 5.1.2 Procedural Steps NOTE: Unless otherwise noted, the following steps are performed in the switchyard relay house. 1. RESET the following on the 230 KV Differential Panel 11 R, Node H14: a. Bus 2A Diff Lockout Relay, 86P/2A. [@ b. Bus 2A Diff Lockout Relay, 86B/2A. l6P c. Bus 2B Diff Lockout Relay, 86B/2B. lAb d. Bus 2B Diff Lockout Relay, 86P/2B. e. Bus 2A Diff Lockout Relay, 86P2/2A. l8b f. Bus 2A Diff Lockout Relay, 86B2/2A. l6P g. Bus 2B Diff Lockout Relay, 86B2/2B. l8b h. Bus 2B Diff Lockout Relay, 86P2/2B. C Continuous Use 120P-50 Rev. 113 Page 12 of 2021 5.1.2 2. 3. 4. 5. 120P-50 Procedural Steps CONFIRM the white indicating lights, above the following control switches on the 230 KV Differential Panel 11 R, Node H14, are on: a. Bus 2A Diff Lockout Relay, 86P/2A. b. Bus 2A Diff Lockout Relay, 86B/2A. c. Bus 2B Diff Lockout Relay, 86B/2B. d. Bus 2B Diff Lockout Relay, 86P/2B. ENSURE the following power switches on equipment rack Node HIO are in ON: a. 230 KV Feeder 30 Delco West carrier toggle switch ON. b. 230 KV Feeder 31 Whiteville carrier toggle switch ON. ENSURE the following power switches on equipment rack Node HI7 are in ON: a. 230 KV Feeder 27 Wilmington Corning carrier togg Ie switch ON. b. 230 KV Feeder 28 Wallace carrier toggle switch ON. CONFIRM the white indicating lights for the primary and backup DC supply relays are on for the following:
- a. 230 KV Feeder 27 Wilmington Corning. (Panel 9R, Node H12) b. 230 KV Feeder 28 Wallace. (Panel 10R, Node H13) c. 230 KV Feeder 30 Delco West. (Panel 12R, Node H15) d. 230 KV Feeder 31 Whiteville. (Panel 13R, Node H16) W [fJ) lAb tAb [6b [6b Rev. 113 Page 13 of 202 !
5.1.2 Procedural Steps 6. RESET the following: a. 230 KV Breaker 27A breaker failure lockout relay. lAb (Panel HH6) b. 230 KV Breaker 27B breaker failure lockout relay. [M) (Panel HH6) c. 230 KV Breaker 28A breaker failure lockout relay. [6p (Panel HH7) d. 230 KV Breaker 28B breaker failure lockout relay. (Panel HH7) e. 230 KV Breaker 30A breaker failure lockout relay. (Panel HH9) f. 230 KV Breaker 30B breaker failure lockout relay. (Panel HH9) g. 230 KV Breaker 31A breaker failure lockout relay. [6p (Panel HH10) h. 230 KV Breaker 31 B breaker failure lockout relay. [6p (Panel HH10) 7. CONFIRM the green indicating lights above the following control switches are on: a. 230 KV Breaker 31A Whiteville local control switch. (Panel HH1 0) b. 230 KV Breaker 31 B Whiteville local control [6p switch. (Panel HH1 0) c. 230 KV Breaker 30A Delco West local control [6b switch. (Panel HH9) d. 230 KV Breaker 30B Delco West local control switch. (Panel HH9) e. 230 KV Breaker 28A Wallace local control switch. (Panel HH7) 120P-50 Rev. 113 Page 14 of 2021 5.1.2 Procedural Steps f. 230 KV Breaker 2SB Wallace local control switch. [6p (Panel HH7) g. 230 KV Breaker 27 A Wilmington Corning local control switch. (Panel HH6) h. 230 KV Breaker 27B Wilmington Corning local control switch. (Panel HH6) i. 230 KV Breaker 26A Transformer Bus 2 local control switch. (Panel SF, Node HH5) j. 230 KV Breaker 26B Transformer Bus 2 local control switch. (Panel SF, Node HH5) NOTE: The following steps are performed from the Control Room. S. CONFIRM the white indicating lights on Panel XU-5 above the following are illuminated:
- a. BUS 2B WHITEVILLE 230 KV BREAKER 31B D synchronizing switch. b. BUS 2A WHITEVILLE 230 KV BREAKER 31A synchronizing switch. c. BUS 2B DELCO WEST LINE 230 KV BREAKER D 30B synchronizing switch. d. BUS 2A DELCO WEST LINE 230 KV BREAKER 30A synchronizing switch. e. BUS 2B WALLACE 230 KV BREAKER 28B D synchronizing switch. f. BUS 2A WALLACE 230 KV BREAKER 28A synchronizing switch. g. BUS 2B WILMINGTON CORNING 230 KV D BREAKER 27B synchronizing switch. h. BUS 2A WILMINGTON CORNING 230 KV BREAKER 27A synchronizing switch. 120P-50 Rev. 113 Page 15 of 2021 5.1.2 9. Procedural Steps IF the System Load Dispatcher has directed BUS 2B WHITEVILLE 230 KV BREAKER 31B to be closed, THEN PERFORM the following:
CAUTION PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. b. c. PLACE associated PCB Supervisory Local/Remote switch in LOCAL. PLACE associated Synchronizing Switch in ON. PLACE BUS 2B(2A) VOLTMETER SWITCH in ON. D D D NOTE: With the 230 KV bus deenergized, only "incoming volts" will indicate voltage. d. e. f. g. h. i. j. ENSURE incoming and running voltmeter values are equal. 'A41IEN !)I,el"ll'e!eepe il'leliefltes tRe lifle flflell3l:1S aFe SYfl8RF8f1iZ!eel wiiR iRe lTIateReel, N-1 THEN CLOSE the 230KV breaker. CONFIRM 230 KV breaker has closed by observing the indicating light. CONFIRM running and incoming voltmeters indicate the same value. PLACE BUS 2B(2A) VOL TMETER SWITCH in OFF. PLACE associated Synchronizing Switch in OFF. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. D D D D D D N-1: With bus de-energized, bus synchronization with voltages matched is not required.
PRR submitted.
120P-50 Rev. 113 Page 16 of 2021 5.1.2 Procedural Steps k. PLACE associated Auto Reclose Control Switch in AUTO. 10. IF the System Load Dispatcher has directed BUS 2A WHITEVILLE 230 KV BREAKER 31A to be closed, THEN PERFORM the following:
CAUTION D PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. PLACE associated PCB Supervisory D Local/Remote Switch in LOCAL. b. PLACE associated Synchronizing Switch in ON. D c. PLACE BUS 2A(2B) VOL TMETER SWITCH in D ON. E: With the 230 KV bus deenergized, only "incoming volts" will indicate voltage. d. ENSURE incoming and running voltmeter values D are equal. e. WHEN the synchroscope indicates the line and D bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. f. CONFIRM 230 KV breaker has closed by D observing the indicating light. g. CONFIRM running and incoming voltmeters D indicate the same value. h. PLACE BUS 2A(2B) VOLTMETER SWITCH in D OFF. i. PLACE associated Synchronizing Switch in OFF. D 120P-50 Rev. 113 Page 17 of 2021 5.1.2 Procedural Steps j. k. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. PLACE associated Auto Reclose Control Switch in AUTO. D D 11. IF directed by the System Load Dispatcher, THEN D PLACE LINE 31 CARRIER CONTROL SWITCH in ON. 12. IF the System Load Dispatcher has directed BUS 2B DELCO WEST LINE 230 KV BREAKER 30B to be closed, THEN PERFORM the following:
CAUTION PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. b. c. PLACE associated PCB Supervisory Local/Remote Switch in LOCAL. PLACE associated Synchronizing Switch in ON. PLACE BUS 2B(2A) VOL TMETER SWITCH in ON. D D D NOTE: With the 230 KV bus deenergized, only "incoming volts" will indicate voltage. d. e. f. g. 120P-50 ENSURE incoming and running voltmeter values are equal. WHEN the synchroscope indicates the line and bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. CONFIRM 230 KV breaker has closed by observing the indicating light. CONFIRM running and incoming voltmeters indicate the same value. D D D D Rev. 113 Page 18 of 2021 5.1.2 Procedural Steps h. i. j. k. PLACE BUS 2B(2A) VOL TMETER SWITCH in OFF. PLACE associated Synchronizing Switch in OFF. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. PLACE associated Auto Reclose Control Switch in AUTO. 13. IF the System Load Dispatcher has directed BUS 2A DELCO WEST LINE 230 KV BREAKER 30A to be closed, THEN PERFORM the following:
CAUTION o o o o PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. 120P-50 a. b. c. PLACE associated PCB Supervisory Local/Remote Switch in LOCAL. PLACE associated Synchronizing Switch in ON. PLACE BUS 2A(2B) VOL TMETER SWITCH in ON. o o o With the 230 KV bus deenergized, only "incoming volts" will indicate volta d. ENSURE incoming and running voltmeter values 0 are equal. e. WHEN the synchroscope indicates the line and 0 bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. f. CONFIRM 230 KV breaker has closed by 0 observing the indicating light. Rev. 113 Page 19 of 2021 5.1.2 Procedural Steps g. CONFIRM running and incoming voltmeters D indicate the same value. h. PLACE BUS 2A(2B) VOLTMETER SWITCH in D OFF. i. PLACE associated Synchronizing Switch in OFF. D j. PLACE associated PCB Supervisory D Local/Remote Switch in REMOTE. k. PLACE associated Auto Reclose Control Switch in D AUTO. 14. IF directed by the System Load Dispatcher, THEN D PLACE LINE 30 CARRIER CONTROL SWITCH in ON. 15. IF the System Load Dispatcher has directed BUS 2B WALLACE 230 KV BREAKER 28B to be closed, THEN PERFORM the following:
CAUTION PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. b. c. PLACE associated PCB Supervisory Local/Remote Switch in LOCAL. PLACE associated Synchronizing Switch in ON. PLACE BUS 2B(2A) VOL TMETER SWITCH in ON. D D D NOTE: With the 230 KV bus deenergized, only "incoming volts" will indicate volta d. /20P-50 ENSURE incoming and running voltmeter values are equal. D Rev. 113 Page 20 of 202/
5.1.2 Procedural Steps e. f. g. h. i. j. k. WHEN the synchroscope indicates the line and bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. CONFIRM 230 KV breaker has closed by observing the indicating light. CONFIRM running and incoming voltmeters indicate the same value. PLACE BUS 2B(2A) VOL TMETER SWITCH in OFF. PLACE associated Synchronizing Switch in OFF. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. PLACE associated Auto Reclose Control Switch in AUTO. 16. IF the System Load Dispatcher has directed BUS 2A WALLACE 230 KV BREAKER 28A to be closed, THEN PERFORM the following steps: CAUTION D D D D D D D PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. PLACE associated PCB Supervisory D Local/Remote Switch in LOCAL. b. PLACE associated Synchronizing Switch in ON. D c. PLACE BUS 2A(2B) VOLTMETER SWITCH in D ON. /20P-50 Rev. 113 Page 21 of 2021 5.1.2 Procedural Steps NOTE: With the 230 KV bus deenergized, only "incoming volts" will indicate voltage. d. e. f. g. h. i. j. k. ENSURE incoming and running voltmeter values are equal. WHEN the synchroscope indicates the line and bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. CONFIRM 230 KV breaker has closed by observing the indicating light. CONFIRM running and incoming voltmeters indicate the same value. PLACE BUS 2A(2B) VOL TMETER SWITCH in OFF. PLACE associated Synchronizing Switch in OFF. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. PLACE associated Auto Reclose Control Switch in AUTO. D D D D D D D D 17. IF directed by the System Load Dispatcher, THEN D PLACE LINE 28 CARRIER CONTROL SWITCH in ON. 18. IF the System Load Dispatcher has directed BUS 2B WILMINGTON CORNING 230 KV BREAKER 27B to be closed, THEN PERFORM the following:
CAUTION PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. 120P-50 PLACE associated PCB Supervisory Local/Remote Switch in LOCAL. Rev. 113 D Page 22 of 2021 5.1.2 Procedural Steps b. c. PLACE associated Synchronizing Switch in ON. PLACE BUS 2B(2A) VOL TMETER SWITCH in ON. D D NOTE: With the 230 KV bus deenergized, only "incoming volts" will indicate voltage. d. e. f. g. h. i. j. k. ENSURE incoming and running voltmeter values are equal. WHEN the synchroscope indicates the line and bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. CONFIRM 230 KV breaker has closed by observing the indicating light. CONFIRM running and incoming voltmeters indicate the same value. PLACE BUS 2B(2A) VOLTMETER SWITCH in OFF. PLACE associated Synchronizing Switch in OFF. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. PLACE associated Auto Reclose Control Switch in AUTO. 19. IF the System Load Dispatcher has directed BUS 2A WILMINGTON CORNING 230 KV BREAKER 27 A to be closed, THEN PERFORM the following:
CAUTION D D D D D D D D PCB supervisory switch must be in LOCAL before the associated PCB is operated from Control Panel XU-5. a. \20P-50 PLACE associated PCB Supervisory Local/Remote Switch in LOCAL. Rev. 113 D Page 23 of 202\
5.1.2 Procedural Steps b. c. PLACE associated Synchronizing Switch in ON. PLACE BUS 2A(2B) VOL TMETER SWITCH in ON. D D NOTE: With the 230 KV bus deenergized, only "incoming volts" will indicate voltage. ! 20P-50 d. e. f. g. h. i. j. k. ENSURE incoming and running voltmeter values are equal. WHEN the synchroscope indicates the line and bus are synchronized with the voltages matched, THEN CLOSE the 230 KV breaker. CONFIRM 230 KV breaker has closed by observing the indicating light. CONFIRM running and incoming voltmeters indicate the same value. PLACE BUS 2A(2B) VOL TMETER SWITCH in OFF. PLACE associated Synchronizing Switch in OFF. PLACE associated PCB Supervisory Local/Remote Switch in REMOTE. PLACE associated Auto Reclose Control Switch in AUTO. D D D D D D D D 20. IF directed by the System Load Dispatcher, THEN D PLACE LINE 27 CARRIER CONTROL SWITCH in ON. Rev. 113 Page 24 of 2021 PROGRESS ENERGY -CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE CONTROL ROOM NRC Sim F LESSON TITLE: Main Turbine Shutdown With PCB Failure LESSON NUMBER: LOT-SIM-JP-26.0-01 REVISION NO: 00 Main Turbine Shutdown SIMULATOR SETUP: A. Initial Conditions:
- 1. Recommended Initial Conditions IC 15 Rx. Pwr. 15% Core Age EOC 2. Required Plant Conditions None B. Overrides Tag 10 Description Position/
Actual Override Rmptime Actime Dactime Trig Target Value Value Q3101UR8 BUS 2A GEN 2 230 KV BKR ON ON/OFF ON ON RED Q3101DG8 BUS 2A GEN 2 230 KV BKR OFF ON/OFF ON OFF GREEN Q8182LG8 230 KV Bkr ON Red (XU-5 Panel) ON/OFF ON ON Q8182RR8 230 KV Bkr ON Green (XU-5 ON/OFF ON OFF Panel) D. Remote Function None E. Special Instructions E1 PCB 29A CS not in Normal will delete Q3101UR8 (trc:1,dod:q3101ur8)
E2 PCB 29A CS in TRIP will delete Q3101DG8 (trc:2,dod:q3101dg8).
E3 PCB 29A CS not in Normal will delete Q8182LG8 (trc:3,dod:
Q8182LG8)
E4 PCB 29A CS in TRIP will delete Q8182RR8 (trc:4,dod:
Q8182RR8).
LOT-SIM-JP-26.0-01 Page 2 of 10 Rev. 00 Main Turbine Shutdown SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to examinee)
- 1. The applicable procedure section WILL be provided to the examinee, once it is demonstrated he/she knows the correct procedure.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the examinee.
Read the following to examinee.
TASK CONDITIONS: 1 . Auxiliary power has been transferred to the SAT. 2. Load Dispatcher has been notified of impending grid separation.
- 3. OGP-05, Unit Shutdown, is complete up to Step 5.2.3. 4. Turbine load has been reduced to between 100 to 110 MWe. 5. Second stage reheat has been removed from service. 6. 20P-26 Section 7.1 has been completed through step 7.1.2.2. INITIATING CUE: You are directed to shutdown Main Turbine in accordance with 20P-26 and inform the Unit seo when the actions are complete.
LOT-SIM-JP-26.0-01 Page 3 of 10 Rev. 00 Main Turbine Shutdown PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain/provide a copy of 20P-26, Section 7.1. Procedure obtained.
SAT/UNSAT Time Started: ____ _ NOTE: NOTE: NOTE: Turbine load can be verified / monitored on PPC, ERFIS, Control Panel XU-01 (GEN-MW-727), .orXU-04 (GEN-WMR-760)
Steps 2-4 may be performed in any order prior to tripping the main turbine. TheMN STM LEAD AFTERCV-3 DRN, MVD-DV3, operates with the limit switch position of the CV-1/CV-2 drain valves and the position can be confirmed with the indicating light on Panel XU-3. Step 2 -0 )pen th f II d . t d P I XU 3 e 0 oWing rain va ves oca e on ane -Valve Position SAT UNSAT MN STM LN BEFORE SV DRNS, MS-V46/47/48/49 Open MAIN SV & CV ABOVE SEAT DRN, MVD-CV Open MN STM LEAD AFTER CV-1 DRN, MVD-CV2 Open MN STM LEAD AFTER CV-2 DRN, MVD-CV4 Open Drain valves open. SAT/UNSAT LOT-SIM-JP-26.0-01 Page 4 of 10 Rev. 00 Main Turbine Shutdown Step 3 -Perform the following to align the Turbine Lube Oil System: PROMPT: Inform examinee that the Turbine Building AO has rotated the Cuno filters handles. NOTE: NOTE: a. Rotate the five Cuno filter's T-handles clockwise two complete revolutions to clean the lift pumps' Cuno filters. TB A 0 communicates Cuno filters rotated. SATIUNSAT Alarm UA-02 (2-3) MOTOR SUCTION PUMP RUNNING will.annunciate when the MSP is started, examinee may review the alarm prior to starting the MSP. b. Start the motor suction pump. Motor suction pump running. SATIUNSAT Alarm UA-02 (4-2)TURNING GEAROIL PUMP RUNNING will annunciate when the TGOP is started, examinee.
may review the alarm prior to starting the TGOP. c. Start the turning gear oil pump and ensure the lift pumps start by observing all six amber PRESS NORM lights come on. Turning gear oil pump and all lift pumps running. SATIUNSAT Step 4 -Perform the following to test the operation of LOW CONDENSER VACUUM SWITCHES, OG-PS-110 and OG-PS-111, the pressure set control, and the bypass valves: a. Depress Bypass Valve Opening Jack INCREASE push button to open a bypass valve 12% to 18%. Turbine Bypass Valve opened 12% to 18%. SATIUNSAT LOT -SIM-JP-26.0-01 Page 5 of 10 Rev. 00 Main Turbine Shutdown b. Depress Bypass Valve Opening Jack DECREASE push button to fully close the bypass valve. Turbine Bypass Valve closed. SAT/UNSAT Step 5 -Monitor main generator megawatts using computer point B059 or Net Unit Megawatts 2-GEN-WMR-760.
NOTE: NOTE: Monitors main generator megawatts.
SAT/UNSAT This starts the alternate path portion to diagnose failure of PCB 29A. Steps 6 and 7 should be reviewed prior. to performing step 6. This happens in a very short time period. Step 6 -Depress the Emergency Trip System push button Emergency Trip System push button depressed.
- CRITICAL STEP ** SAT/UNSAT A d th f II n ensure e oowmg: Valve Position SAT UNSAT All four main stop valves Closed All four control valves Closed Bypass valves maintain reactor pressure constant at Throttled 928 psig All four intercept valves Closed Valve positions verified.
SATIUNSAT LOT-SIM-JP-26.0-01 Page 6 of 10 Rev. 00 NOTE: Main Turbine Shutdown Examinee may determine the PCB 29A failed to open and decide to implement 20P-50.0, Section 8.31 (Emergency Isolation of 230KV Bus 2A). Step 7 -When main generator MWe decrease to zero, then ensure both generator output breakers GENERA TOR 2 TO BUS 2A 230 KV PCB 29A and GENERA TOR 2 TO BUS 2B 230 KV PCB 29B, are open. Recognizes PCB 29A failed to open and takes control switch to trip. ** CRITICAL STEP ** SA T1UNSAT NOTE: Acknowledge PCB 29A failure and .direct examinee another operator will continue with Main Turbine shutdown.
Step 8 -Notifies SRO PCB 29A failed to automatically open and was manually opened. SRO notified of PCB 29A failure. SAT/UNSAT TERMINATING CUE: When both main generator output breakers (PCB 29A & 29B) are open, this JPM is complete.
Comments required for any step evaluated as UNSA T. Time completed:
____ _ LOT-SIM-JP-26.0-01 Page 7 of 10 Rev. 00 Main Turbine Shutdown RELATED TASKS: 245012B101, Shutdown the Main Turbine per20P-26 KIA REFERENCE AND IMPORTANCE RATING: 245000 A2.01 3.7/3.9 Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
REFERENCES:
GP-05 OP-26 TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2) 4, Heat Removal REASON FOR REVISION:
New LOT-SIM-JP-26.0-01 Page 8 of 10 Rev. 00 Main Turbine Shutdown Validation Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit: 2 Setting: Control Room Simulator X (Not applicable to In-Plant JPMs) Time Critical:
Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Examinee:
JPM: Pass Fail __ __ Remedial Training Required:
Yes No __ __ Did Examinee Verify Procedure?
Yes ___ No ___ _ (Each Student should verify one JPM per evaluation set) Comments:
Comments reviewed with Student Evaluator Signature:
Date: ____________
_ LOT-SIM-JP-26.0-01 Page 9 of 10 Rev. 00 TASK CONDITIONS:
- 1. Auxiliary power has been transferred to the SAT. 2. Load Dispatcher has been notified of impending grid separation.
- 3. OGP-05, Unit Shutdown, is complete up to Step 5.2.3. 4. Turbine load has been reduced to between 100 to 110 MWe. 5. Second stage reheat has been removed from service. 6. 2QP-26 Section 7.1 has been completed through step 7.1.2.2. INITIATING CUE: You are directed to shutdown Main Turbine in accordance with 2QP-26 and inform the Unit SeQ when the actions are complete.
7.0 SHUTDOWN 7.1 Normal Shutdown 7.1.1 Initial Conditions
- 1. 2. Turbine load has been reduced in accordance with OGP-05 to between 100 and 110 MWe. Second stage reheat has been removed from service in accordance with 20P-36. 7.1.2 Procedural Steps NOTE: Steps 7.1.2.1 through 7.1.2.5 may be performed in any order as long as they are completed prior to tripping the turbine. CAUTION Operation at less than 33% turbine load AND less than 25" Hg Vacuum (greater than 5" HGA backpressure) can cause damage to the last stage buckets and should be avoided. 1. 2. PLACE TURBINE SUPERVISORY INSTRUMENTS Trip/Disable switch to ON. CONFIRM TURB CV FAST CLOS/SV/RPT TRIP BYPASS (A-05, 6-7) is in alarm. NOTE: The MN STM LEAD AFTER CV-3 ORN, MVD-OV3, operates with the limit switch position of the CV-1/CV-2 drain valves and the position can be confirmed with the indicating light on Panel XU-3. 3. OPEN the following drain valves located on Panel XU-3: a. MN STM LN BEFORE SV ORNS, D MS-V46/47/48/49
- b. MAIN SV & CV ABOVE SEAT ORN, MVO-CV D 120P-26 Rev. 116 Page 52 of 1591 C Continuous Use 7.1.2 Procedural Steps c. d. MN STM LEAD AFTER CV-1 DRN, MVD-CV2 MN STM LEAD AFTER CV-2 DRN, MVD-CV4 4. PERFORM the following to align the Turbine Lube Oil System: a. b. c. ROTATE the five Cuno filter's T-handles clockwise two complete revolutions to clean the lift pumps' Cuno filters. START the motor suction pump. START the turning gear oil pump AND ENSURE the lift pumps start by observing all six amber PRESS NORM lights come on. CAUTION D D D D D IF the bypass valve does NOT open, THEN tripping the main turbine may result in a main turbine trip without bypass valves with resultant high reactor pressure and APRM upscale alarms or trips. 120P-26 5. PERFORM the following to test the operation of LOW CONDENSER VACUUM SWITCHES, OG-PS-110 and OG-PS-111, the pressure set control, and the bypass valves: a. b. DEPRESS Bypass Valve Opening Jack INCREASE push button to open a bypass valve 12% to 18%. DEPRESS Bypass Valve Opening Jack DECREASE push button to fully close the bypass valve. D D 6. MONITOR main generator megawatts using computer D point U2GENB059 OR Net Unit Megawatts 2-GEN-WMR-760.
Rev. 116 Page 53 of 1591 7.1.2 Procedural Steps 7. DEPRESS the Emergency Trip System push button AND D ENSURE the following:
- a. All four main stop valves go full closed. D b. All four control valves go full closed. D c. The bypass valves throttle open to maintain D reactor pressure constant at 928 psig. d. All four intercept valves go closed. D 8. WHEN main generator MWe decrease to zero, THEN D ENSURE both generator output breakers GENERA TOR 2 TO BUS 2A 230 KV PCB 29A AND GENERA TOR 2 TO BUS 2B 230 KV PCB 29B, are open. 9. PLACE REGULA TOR MODE SELECTOR, 43 CS, in D MAN. 10. OPEN EXCITER FIELD BREAKER, 41 CS. D 11. PLACE GEN MANUAL VOL T ADJ RHEO, 70 CS, in the D full lower position.
- 12. PLACE GEN AUTO VOL T ADJ RHEO, 90 CS, in the full D lower position.
- 13. NOTIFY System Operations Load Dispatcher that the D unit is separated from the system. 14. ENSURE the following extraction nonreturn valves on Panel XU-2, are closed: a. LP Turbine A 9th Stage Extraction Nonreturn D Valves, EX-V11 and EX-V13 b. LP Turbine B 9th Stage Extraction Nonreturn D Valves, EX-V12 and EX-V14 c. 7th Stage Extraction To FW Heater 4A Nonreturn D Valve, EX-V19 120P-26 Rev. 116 Page 54 of 1591 7.1.2 Procedural Steps d. 7th Stage Extraction To FW Heater 4B Nonreturn D Valve, EX-V20 e. 4th Stage Extraction To FW Heater 5A Nonreturn D Valve, EX-V23 f. 4th Stage Extraction To FW Heater 5B Nonreturn D Valve, EX-V24 15. ENSURE the following moisture removal valves, located on Panel XU-2, are open: a. LP Turbine A 11th Stage Extraction Moisture D Removal Valve, L V-262 b. LP Turbine A 11th Stage Extraction Moisture D Removal Valve, L V-263 c. LP Turbine B 11th Stage Extraction To Heater D Drains Deaerator Moisture Removal Valve, LV-264 d. LP Turbine B 11th Stage Extraction To Heater D Drains Deaerator Moisture Removal Valve, LV-265 e. LP Turbine A 9th Stage Extraction To Heater D Drains Deaerator Moisture Removal Valve, MVO-LV-266
- f. LP Turbine B 9th Stage Extraction To Heater D Drains Deaerator Moisture Removal Valve, MVO-LV-267
- g. 4th Stage Extraction to FW Heater 5A Moisture D Removal Valve, MVO-L V-268 h. 4th Stage Extraction to FW Heater 5B Moisture D Removal Valve, MVO-L V-269 i. FW Heater 1 A Moisture Removal Valve to D Condenser, HO-L V-216 1 2 0 P-2 6 Rev. 116 Page 55 of 1591 7.1.2 Procedural Steps j. FW Heater 1 B Moisture Removal Valve to D Condenser, HD-L V-217 k. HP TURB 7TH STAGE EXHAUST DRAIN VLVS, D MVD-MOV-CA-2/1/3/4
- 16. ENSURE the exhaust hood spray system maintains D exhaust hood temperatures less than 175°F on recorder TSI-TXR-638, Points 8 and 9. 17. MONITOR turbine bearing metal temperatures during D turbine coastdown for spikes greater than 50°F on recorder TSI-TR-642. 18. IF a turbine bearing metal temperature spike of greater than 50°F is indicated, THEN PERFORM the following:
- a. IF turbine speed is greater than 900 rpm, THEN D MANUALLY start the lift pumps. b. IF turbine speed is less than 900 rpm, THEN D ENSURE the lift pump associated with the high temperature bearing is operating.
- c. NOTIFY the Unit CRS of the condition.
D 19. WHEN turbine speed decreases to less than 900 rpm, D THEN ENSURE all six turbine bearing lift pumps are running. 20. IF turbine bearing metal temperature spikes greater than D 10°F/minute are detected, THEN NOTIFY the System Engineer to investigate.
- 21. MONITOR vibration of turbine bearings on recorder D TSI-XR-640 during turbine coastdown.
- 22. IF vibration greater than 10 mils is detected, THEN D NOTIFY the System Engineer.
- 23. ADJUST TBCCW TO MAIN TURB OIL COOLER D temperature controller to maintain bearing oil inlet temperature at 90°F. 120P-26 Rev. 116 Page 56 of 159) 7.1.2 Procedural Steps NOTE: Oil temperature should be maintained at 80-90°F. MAIN TURBINE OIL COOLER TBCCWOUTLET ISOLATION VALVE, TCC-V117, may require throttling to maintain this temperature.
!20P-26 24. IF required, THEN THROTTLE MAIN TURBINE OIL D COOLERS TBCCW OUTLET ISOLA TlON VAL VE, TCC-V117, to maintain oil temperature at 90°F. 25. WHEN turbine speed decreases to zero, as indicated by the TURBINE AT ZERO SPEED (UA-02 1-4) alarm, THEN ENSURE the following:
- a. The turning gear piggy back motor starts AND engages. b. Approximately 10 seconds after the piggy back motor starts, the turning gear main motor starts. 26. IF the turning gear will NOT remain engaged, THEN REMOVE lift pumps from service in accordance with Section 8.22. 27. WHEN the turbine is on the turning gear, THEN PERFORM the following actions once per hour: a. ENSURE the appropriate lift pumps are operating in accordance with Section 8.22. b. ENSURE all bearing metal temperatures, as indicated on recorder TSI-TR-642, are within 95°F to 110°F for turning gear operation.
- c. IF any bearing metal temperature exceeds 110°F, THEN NOTIFY the Unit CRS. 28. ENSURE either Bus Duct Fan 2A-1 or 2A-2 is in-service AND PLACE Isophase Bus Heater switch in ON at the equipment cabinet on Turbine Building 38' el. 29. WHEN the turbine is operating on the turning gear, THEN CLEAN the lift pumps' Cuno filters once per shift by rotating the five Cuno filters' T-handles clockwise two complete revolutions.
D D D D D D D D Rev. 116 Page 57 of 159/
7.1.2 Procedural Steps NOTE: The Main Lube Oil System should be operated continuously except for shutdowns required for Maintenance or inspection.
- 30. REMOVE the turbine from turning gear operation in D accordance with Section 8.1. !20P-26 Rev. 116 Page 58 of 1591 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR NRC Sim G LESSON TITLE: Place SULCV In Service Following a Reactor Scram LESSON NUMBER: LOT-SIM-JP-32A-07 REVISION NO: 01 Place SULCV In Service Following a Reactor Scram. SIMULATOR SETUP A. Initial Conditions
- 1. Recommended Initial Conditions IC 11 Rx. Pwr. 100% Core Age BOC 2. Required Plant Conditions RPV water level <170", RFP high-level trips sealed-in B. Malfunctions None C. Overrides None. D. Special Instructions
- 1. Trip the Main Turbine to insert a reactor scram and perform immediate actions with exception of tripping one RFP; allow RFPs to trip on high level. 2. 3. Lower RPV level to <170". Ensure RCIC is tripped and HPCI AOP is in PTL. Perform actions of the SULCV Hard card up to step 9. LOT-SIM-JP-03A2-A07 Page 2 of 9 Rev. 01 Place SULCV In Service Following a Reactor Scram. SAFETY CONSIDERATIONS:
NONE EVALUATOR NOTES: (Do not read to trainee) 1. The applicable procedure section WILL NOT be provided to the trainee. 2. If this is the first set of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee. Read the following to the trainee TASK CONDITIONS:
- 1. A reactor scram has occurred.
- 2. RPV water level has dropped below +170" and Feedwater is required to restore RPV water level to the normal band. 3. HPCI and RCIC are not available.
- 4. Feedwater Level Control Following A Reactor Scram Hard Card was started and completed up through step 8. INITIATING CUE: You are directed by the Unit CRS to: (1) restart Reactor Feed Pump A, (2) complete the actions to place the Startup Level Control. Valve in service, and (3) restore RPV water level to +170" -+200". Inform the Unit CRS when RPV water level has been restored above 170". LOT-SIM-JP-03A2-A07 Page 3 of 9 Rev. 01 Place SUlCV In Service Following a Reactor Scram. PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain Hard Card S/1205. Hard Card SI1205 obtained.
SAT/UNSAT*
TIME START ____ _ NOTE: The Operator needs to flip the hard card over to the other side for REACTOR FEED PUMP STARTUP instructions.
Step 2 -Open RFP A Recirc Valve FW-FV-V46.
RFP A Recirc Valve FW-FV-V46 indicates full open. ** CRITICAL STEP ** SAT/UNSAT*
Step 3 -Verify open RFP A Discharge Valve FW-V3. RFP A Discharge Valve FW-V3 indicates full open. SAT/UNSAT*
Step 4 -Place RFPT ASP CTl, C32-SIC-R601A in MANUAL at its lower limit. RFPT ASP CTL, C32-SIC-R601A indicates M with output at s:D%. SATIUNSAT*
Step 5 -Place MAN/DFCS Control Switch to MANUAL. MANIDFCS Control Switch in MANUAL. ** CRITICAL STEP ** SATIUNSAT*
lOT-SIM-JP-03A2-A07 Page 4 of 9 Rev. 01 Place SULCV In Service Following a Reactor Scram. NOTE: Step 14 may not be required based on plant conditions.
Step 6 -Reset RFP high level trip signal. At least 2 of 3 reset push buttons are depressed and amber high level trip amber lamps on P603 are extinguished.
SA TlU NSAT/N E* Step 7 -Depress RFP A RESET pushbutton.
RFPT A reset pushbutton on XU-2 depressed and RFP Tripped annunciator cleared. ** CRITICAL STEP ** SAT/UNSAT*
Step 8 -Ensure RFP A LP and HP Stop Valves are open. Verifies RFPT A LP and HP Stop Valves are open on XU-2. SAT/UNSAT*
Step 9 -Depress the RFP A START Pushbutton.
RFP A START Pushbutton depressed and RFP speed rises to 1000 rpm. ** CRITICAL STEP ** SATIUNSAT*
Step 10-Raise RFP A speed to 2550 rpm using the LOWER/RAISE Control Switch. RFP A speed 2550 rpm. ** CRITICAL STEP ** SAT/UNSAT*
LOT-SIM-JP-03A2-A07 Page 5 of 9 Rev. 01 Place SUlCV In Service Following a Reactor Scram. Step 11 -Depress the RFPT DFCS CTRl RESET Pushbutton and place MAN/DFCS Control Switch to DFCS. MANIDFCS Control Switch in DFCS, DFCS light is ON. ** CRITICAL STEP ** SAT/UNSAT*
Step 12 -Selects RFP DEMAND on RFPT ASP CTl, C32-SIC-R601A and raises RFP A speed, until discharge pressure is greater than or equal to 100 psig above reactor pressure.
NOTE: RFP A discharge pressure to :?100 psig above reactor pressure.
- CRITICAL STEP ** SAT/UNSAT*
The Operator needs to flip the hard card over to the other side for Feedwater Level Control Following a Reactor Scram and continue at step 10. Step 13 -Manually adjust the SUlCV, FW-LlC-3269, for desired reactor water level. SULCV is adjusted in manual to open the valve. Master controller verified to be at 187 inches. ** CRITICAL STEP ** SAT/UNSAT*
Step 14 -Place SUlCV, FW-LlC-3269, in AUTO. SULCV is in AUTO. SAT/UNSAT*
Step 15 -Inform Unit CRS that RPV water level is above +170". Unit CRS informed.
SAT/UNSAT*
II T_I::,R'VlIN,'!ATING CUE: RPV water level has been restored to >+170"using SUlCV. Comments required for any step evaluated as UNSAT. TIME COMPLETED
____ _ lOT-SIM-JP-03A2-A07 Page 6 of 9 Rev. 01 Place SULCV In Service Following a Reactor Scram. RELATED TASKS: 2592028101 Start the First Reactor Feed Pump per OP-32 KIA REFERENCE AND IMPORTANCE RATING: 295001 A4.02 3.9, 3.7 Ability to manually start/control a RFP in the control room.
REFERENCES:
ATTACHMENT 6 of 20P-32, Rev 165 TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2) Safety Function 2, Inventory Control REASON FOR REVISION:
Removed the steps prior to starting the feed pump .. LOT-SIM-JP-03A2-A07 Page 7 of 9 Rev. 01 Place SULCV In Service Following a Reactor Scram. Time required for Completion:
15 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit 2 Setting: Control Room Simulator1 (Not applicable to In-Plant JPMs) Time Critical:
Yes No X Alternate Path: Yes No X EVALUATION Trainee: ---------------------------
JPM: Pass __ Fail __ Remedial Training Required:
Yes No __ Did Trainee Verify Procedure as Authorized Copy? Yes __ No __ (Each Student should verify one JPM per evaluation set.) Comments:
Comments Reviewed With Trainee Time Limit N/A Evaluator Signature:
_________________________
Date: ____ _ LOT-SIM-JP-03A2-A07 Page 8 of 9 Rev. 01 TASK CONDITIONS:
- 1. A reactor scram has occurred.
- 2. RPV water level has dropped below +170" and Feedwater is required to restore RPV water level to the normal band. 3. HPCI and RCIC are not available.
- 4. Feedwater Level Control Following A Reactor Scram Hard Card was started and completed up through step 8. INITIATING CUE: You are directed by the Unit CRS to: (1) restart Reactor Feed Pump A, (2) complete the actions to place the Startup Level Control Valve in service, and (3) restore RPV water level to +170" -+200". Inform the Unit CRS when RPV water level has been restored above 170".
ATTACHMENT 6 Page 1 of 2 Feedwater Level Control Following a Reactor Scram -Reactor Feed Pump Startup NOTE: This attachment is also applicable to the Simulator.
NOTE: This attachment is NOT to be used for routine system operation.
FEEDWATER LEVEL CONTROL FOLLOWING A REACTOR SCRAM RO 1. IF NECESSARY, THEN DISPATCH AN OPERATOR TO RFP A(B) TO RESPOND TO ANY LOCAL ANNUNCIATOR PANEL ALARMS. RO 2. CLOSE (FW-V6 AND FW-V8) OR (FW-V118 AND FW-V119).
RO 3. ENSURE FW-FV-177 IS CLOSED. RO 4. OPEN FW-V10. RO 5. PLACE FEEDWATER CONTROL MODE SELECT TO 1 ELEM. RO 6. IF BOTH RFPs HAVE TRIPPED, THEN ENSURE MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, IS IN M (MANUAL) AND SET TO MAINTAIN 187 INCHES. RO 7. ENSURE SULCV, FW-LlC-3269, IN M (MANUAL) AND SULCV CLOSED. RO 8. ENSURE B21-F032A AND B21-F032B ARE OPEN. \20P-32 9. IF AN RFP IS RUNNING, THEN PLACE RFPT A (B) SP CTL, C32-SIC-R601A (B), IN M (MANUAL) AND ADJUST RFP A (B) SPEED LJNTIL DISCHARGE PRESSURE IS APPROXIMATELY 100 PSI GREATER THAN REACTOR PRESSURE.
- 10. ADJUST SULCV, FW-LlC-3269, FOR DESIRED REACTOR WATER LEVEL. 11. IF DESIRED, THEN PLACE SULCV, FW-LlC-3269, IN A (AUTO). 12. ADJUST FW-FV-177 TO MAINTAIN SULCV, FW-LlC-3269, OUTPUT DEMAND SIGNAL BETWEEN 25% AND 55%. 13. IF SULCV, FW-LlC-3269, FAILS TO CONTROL LEVEL, THEN USE ONE OR MORE OF THE FOLLOWING VALVES TO AID IN LEVEL CONTROL: FW-V120, (FW-V118 AND FW-V6), (FW-V119 AND FW-V8). 2/1204 S/1205 Rev. 166 Page 292 of 301 I ATTACHMENT 6 Page 2 of 2 Feedwater Level Control Following a Reactor Scram -Reactor Feed Pump Startup NOTE: This attachment is also applicable to the Simulator.
NOTE: This attachment is NOT to be used for routine system operation.
RO 1. RO 2. 3. 4. 5. 6. 7. 8. 9. 10. 11.
- 12.
- 13. !20P-32 REACTOR FEED PUMP STARTUP IF NECESSARY, THEN DISPATCH AN OPERATOR TO RFP A(B) TO RESPOND TO ANY LOCAL ANNUNCIATOR PANEL ALARMS. ENSURE A FEEDWATER FLOW PATH IS ESTABLISHED TO THE REACTOR VESSEL. OPEN RFP A (B) RECIRC VLV, FW-FV-46 (FW-FV-47).
ENSURE RFP A (B) DISCH VLV, FW-V3 (FW-V4) IS OPEN. PLACE RFPT A (B) SP CTL, C32-SIC-R601A (B), IN M (MANUAL) AT ITS LOWER LIMIT. PLACE RFPT A(B) MAN/DFCS CONTROL SWITCH IN MAN. ENSURE REACTOR WATER LEVEL IS LESS THAN +206 INCHES AND RFPT A&B HIGH LEVEL TRIP/RESET PUSHBUTTONS ARE RESET. DEPRESS RFPT A (B) RESET PUSHBUTTON ENSURE RFPT A (B) LP AND HP STOP VLVS ARE OPEN. ROLL RFPT A (B) TO 1000 RPM BY DEPRESSING RFP A(B) START PUSHBUTTON.
RAISE RFPT A(B) SPEED TO APPROXIMATELY 2550 RPM USING THE LOWER/RAISE CONTROL SWITCH. DEPRESS RFPT A(B) DFCS CTRL RESET AND PLACE MANIDFCS CONTROL SWITCH TO DFCS. RAISE RFPT A (B) SPEED WITH RFPT A (B) SP CTL, C32-SIC-R601A (B), UNTIL DISCHARGE PRESSURE IS GREATER THAN OR EQUAL TO 100 PSIG ABOVE REACTOR PRESSURE.
Rev. 166 2/1204 S/1205 Page 293 of 301 !
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR NRC Sim H LESSON TITLE: Restart CRD Following CRD Pump Trip LESSON NUMBER: LOT-SIM-JP-008-B01 REVISION NO: 1 Restart CRD Following CRD Pump Trip SIMULATOR SETUP Initial Conditions
- 1. Recommended Initial Conditions IC 11 Rx. Pwr. 100% Core Age BOC 2. Required Plant Conditions No CRD pumps in operation.
Special Instructions Turn off the operating CRD pump. Isolate Seal Purge to the Recirc Pumps LOT-OJT-JP-002-A01 Page 2 REV. 0 Restart CRD Following CRD Pump Trip SAFETY CONSIDERATIONS:
NONE EVALUATOR NOTES: (Do not read to trainee) 1. The applicable procedure section WILL NOT be provided to the trainee. When the trainee has identified the proper procedure and section to be used a working copy of the procedure WILL be given to the trainee. 2. If this is the first set of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee. Read the following to the trainee TASK CONDITIONS:
- 1. The operating CRD Pump tripped on low suction pressure.
- 2. OAOP-02.0 has been entered due to Control Rod Malfunction/Misposition.
- 3. The standby CRD Suction Filter has been placed in service. 4. Recirculation Pump seal purge has been isolated, and another operator has been assigned to perform 20P-02 actions for seal purge restoration.
INITIATING CUE: You are directed by the Unit CRS to restart the CRD system per 20P-08, and inform him when CRD has been returned to service. LOT -OJT -J P-002-A01 Page 3 REV. 0 Restart CRD Following CRD Pump Trip PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain current revision of 20P-08 section 8.17. Current revision of 20P-OB, Section B. 17 obtained.
SATIUNSAT*
TIME START: _____ _ Step 2 -Place CRD Flow Control, C12-FC-R600, in MAN and reduce potentiometer to minimum setting. C12-FC-R600 in MAN, manual output meter on controller indicates O. ** CRITICAL STEP ** SAT/UNSAT*
Step 3 -Open Drive Pressure control valve C12-PCV-F003.
C12-PCV-F003 indicates full open on P603. SAT/UNSAT*
PROMPT: If requested as AO, report cooling water valves to CRD pumps are'" ,.. Step 4 -Ensure RBCCW in operation to supply cooling water to CRD pumps. RBCCW checked in operation as indicated by pumps running and RBCCW discharge header pressure is normal as indicated on RCC-PI-671-1 on XU-2. SAT/UNSAT*
NOTE: After starting the pump, alarms A-5 (6-1) CRD PUMP INLET FILTER.6P HIGH will come in and clear and alarm A-05 (2-1) CRD CHARGING WTR PRESS HI will come in until the flow control valve is opened. This may be reviewed prior to starting the pump and announced as expected alarms. LOT-OJT-JP-002-A01 Page 4 REV. 0 Restart CRD Following CRD Pump Trip PROMPT: If requested as AO, report prestart checks completed SAT. Step 5 -Start non operating CRD Pump. CRD Pump A or 8 started and indicates running by red light on P603. ** CRITICAL STEP ** SAT/UNSAT*
Step 6 -Raise CRD flow rate to 30-60 GPM using manual potentiometer on CRD FLOW CONTROL, C12-FC-R600.
SIM OP: PROMPT: CRD flow raised using manual potentiometer and indicates between 30 and 60 GPM on flow controller C12-FC-R600.
SAT/UNSAT*
When asked to restore recirc pump seal purge perform the
- 1. Open SEAL INJECTION VALVE, 832-V22, for Recirc Pump A. 2. Open SEAL INJECTION VAL VE, 832-V30, for Recirc Pump B. When the Sim Op has opened the recirc seal purge valves, Inform examinee that recirc pump seal purge has been restored.
Step 7 -Null CRD FLOW CONTROL, C12-FC-R600, using the setpoint tape. C12-FC-R600 setpoint tape adjusted to bring red needle within green band of setpoint tape. SATIUNSAT*
Step 8 -Shift CRD FLOW CONTROL, C12-FC-R600 to Auto. Select switch on C12-FC-R600 is placed to AUTO. ** CRITICAL STEP ** SA TlUNSAT* LOT -OJT -JP-002-A01 Page 5 REV. 0 Restart CRD Following CRD Pump Trip Step 9 -Adjust setpoint tape on CRD FLOW CONTROL, C12-FC-R600, to maintain cooling water differential pressure between 1 0-26 psid as read on R603 on Panel P603. Cooling Water dp reads between 10 and 26 psid on C12-PDI-R603 on Panel P603. ** CRITICAL STEP ** SAT/UNSAT*
Step 10-Ensure CRD flow rate is between 30 and 60 gpm. C12-FC-R600 flow meter reads between 30-60 GPM. SATIUNSAT*
Step 11 -Establish drive water header differential pressure between 260 and 275 psid as read on C12-PDI-R602 on Panel P603 by throttling closed DRIVE PRESS VLV, C12-PCV-F003.
Drive water dp indicates 260-275 psid as indicated on C12-PDI-R602 on panel P603. ** CRITICAL STEP ** SATIUNSAT*
Step 12 -Monitor operation of CRD Hydraulic System in accordance with section 6.0. 20P-08, Section 6.0 referred to for proper operational parameters.
SAT/UNSAT*
Step 13 -Inform Unit CRS that CRD has been returned to service per 20P-OS. Unit CRS informed.
SAT/UNSAT*
TERMINATING CUE: CRD has been returned to service per 20P-OS. Comments required for any step evaluated as UNSAT. TIME STOP: _____ _ LOT -OJT -JP-002-A01 Page 6 REV. 0 Restart CRD Following CRD Pump Trip RELATED TASKS: 2010238101 Restart the CRD Hydraulic System Following a Loss of a CRD Pump Per OP-OB. KIA REFERENCE AND IMPORTANCE RATING: 201001 A2.01 3.2/3.2 Ability to predict the impact of a CRD pump trip on the CRD Hydraulic System and use procedures to correct, control or mitigate the consequences.
REFERENCES:
20P-OB, Section B.17, Rev. 7B TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2) Safety Function 1, Reactivity Control REASON FOR REVISION:
LOT-OJT-JP-002-A01 Page 7 REV. 0 Restart CRD Following CRD Pump Trip Time required for Completion:
10 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X Unit: 2 Setting: Control Room Simulator
-.X. (Not applicable to In-Plant JPMs) Time Critical:
Yes No X Alternate Path: Yes No X EVALUATION Trainee: --------------
JPM: Pass __ __ Fail __ Remedial Training Required:
Yes No __ Did Trainee Verify Procedure as Authorized Copy? Yes __ (Each Student should verify one JPM per evaluation set.) Comments:
Comments Reviewed With Trainee Time Limit N/A No __ _ Evaluator Signature:
____________
Date: ____ _ LOT -OJT -J P-002-AO 1 Page 8 REV. 0 TASK CONDITIONS:
- 1. The operating CRD Pump tripped on low suction pressure.
- 2. OAOP-02.0 has been entered due to Control Rod Malfunction/Misposition.
- 3. The standby CRD Suction Filter has been placed in service. 4. Recirculation Pump seal purge has been isolated, and another operator has been assigned to perform 20P-02 actions for seal purge restoration.
INITIATING CUE: You are directed by the Unit CRS to restart the CRD system per the Operating Procedure, and inform him when CRD has been returned to service.
8.17 Restarting CRD Hydraulic System Following Loss of CRD Pump 8.17.1 1. 2. 8.17.2 1. 2. 3. 4. 5. 6. Initial Conditions CRD System was in operation in accordance with Section 5.1. Operating CRD pump has stopped. Procedural Steps CLOSE SEAL INJECTION VALVE, 832-V22, for Recirc Pump A. CLOSE SEAL INJECTION VALVE, 832-V30, for Recirc Pump B. PLACE CRD FLOW CONTROL, C12-FC-R600, in MAN AND REDUCE potentiometer to minimum setting. ENSURE DRIVE PRESS VL V, C12-PCV-F003, is fully open. ENSURE RBCCW is in operation to supply cooling water to CRD pumps. START non-operating (desired)
CRD Pump A or B. NOTE: Following startup of the non-operating CRD pump, CRD accumulator recharge may momentarily delay the ability to perform CRD flow rate adjustments.
NOTE: IF a reactor scram is sealed in, THEN the following steps can NOT be performed until the scram is reset. D D D D 7. RAISE CRD flow rate to between 30 and 60 gpm, by D adjusting manual potentiometer on CRD FLOW CONTROL, C12-FC-R600.
- 8. RESTORE recirc pump seal purge in accordance with D 20P-02 concurrently with performance of this section. 120P-08 Rev. 78 Page 79 of 3351 R Reference Use 8.17.2 Procedural Steps 9. NULL CRD FLOW CONTROL, C12-FC-R600, by D adjusting the setpoint tape. 10. SHIFT CRD FLOW CONTROL, C12-FC-R600, to AUTO. D 11. ADJUST setpoint tape on CRD FLOW CONTROL, D C12-FC-R600, to maintain cooling water differential pressure between 10 and 26 psid on C12-PDI-R603 on Panel P603. 12. ENSURE CRD flow rate is between 30 and 60 gpm. D 13. ESTABLISH drive water header differential pressure D between 260 and 275 psid on C12-PDI-R602 on Panel P603, by throttling closed DRIVE PRESS VL \I, C12-PCV-FOO3.
- 14. MONITOR operation of CRD System in accordance with D Section 6.0. 120P-08 Rev. 78 Page 80 of 3351 6.0 SYSTEM OPERATION 6.1 During normal operation of the Control Rod Drive Hydraulic System, the following parameters should be routinely monitored:
CRD flow rate C12-FC-R600 PanelP603 Drive water differential pressure C12-POI-R602 PanelP603 Cooling water differential pressure C12-POI-R603 PanelP603 Charging water pressure C12-PI-R601 PanelP603 Drive water flow rate C12-FI-R604 PanelP603 Cooling water flow rate C12-FI-R605 PanelP603 CRD temperature C12-TR-R018 Panel H21-P007 Pressure control valve CO-PCV-4105 (outlet pressure)
CO-PI-4106 Radwaste Bldg. -23' EI. -Southwest 30 to 60 gpm during normal power operations; up to 199 gpm (max flow) during various other applications, such as vessel fill, accumulator charging, etc 260 to 275 psid 10 to 26 psid (may be less than 10 psid if reactor vessel temperature is less than 250°F) Less than 1510 psig Approximately 0 gpm (flow rate < 5.0 gpm during rod movement) 30 to 60 gpm (flow rates above 50 gpm must be obtained from C12-FC-R600 on Panel P603) Less than 250°F 15 to 35 psig Information Use 1 2 0 P-08 Rev. 78 Page 15 of 335 )
LESSON TITLE: CAROLINA POWER & LIGHT COMPANY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN PLANT NRC In-Plant I LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water LESSON NUMBER: AOT-OJT-JP-300-J11 REVISION NO: 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water SAFETY CONSIDERATIONS
- 1. Boron is a caustic substance.
Avoid contact with SLC solutions and precipitated sodium pentaborate salts. A portable eyewash station is present in the area and should be verified as being ready for use PRIOR to allowing trainee to potentially contact boron. 2. Radiation levels in this area are subject to rapid changes, especially during refuel outages. 3. Some areas may be inaccessible during CRD Rebuild evolutions.
- 4. Hearing protection may be required to access and then egress the plant locations associated with this JPM. EVALUATOR NOTES: (Do not read to trainee) 1. The applicable procedure section WILL be provided to the trainee. The trainee should be given a current copy of EOP-01-LEP-01, Section 1, with the applicable steps marked off as complete.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee. 3. The trainee may desire to open the LEP Toolbox on the Reactor Building 80' elevation, near the RWCU Panel. To open this toolbox the trainee must obtain an LSV key, obtainable from the SRO or the Work Control Center, or normally carried by the duty Auxiliary Operator.
If this toolbox is opened, Operations may require the toolbox to be inventoried.
- 4. All operations are conducted on the Reactor Building 80' elevation unless otherwise noted. AOT-OJT-JP-300-J11 Page 2 of 10 Rev. 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water Read the following to the trainee TASK CONDITIONS:
- 1. This task is to be performed on Unit __ . 2. The Reactor Vessel Control Procedure, EOP-01-RVCP, has been entered and is directing the crew to perform OEOP-01-LEP-01; Alternate Coolant Injection, (LEP-01) in order to maintain RPV water level above TAF. 3. ALL control rods are fully inserted.
- 4. The Fire Protection System is OPERABLE.
- 5. SLC Pumps are available to support LEP-01 activities.
- 6. The Demineralized Water System is damaged and is NOT available for use. INITIATING CUE: The Unit __ RO has directed you to perform the AO actions associated with lining up the SLC System to inject with Fire Protection Water per LEP-01 , Section 1, Coolant Injection With SLC Pumps. You are to notify the Control Room when the required steps of the procedure have been completed to allow the starting of the SLC Pumps. AOT-OJT-JP-300-J11 Page 3 of 10 Rev. 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
A marked up copy of LEP-01, Section 1, is to be provided to the trainee. Step 1 -Obtain marked up copy of LEP-01, Section 1 from Control Operator.
LEP-01, Section 1 obtained from the Control Operator.
SATIUNSAT*
TIME START: _______ _ PROMPT: IF asked, as the RO, inform the trainee that demineralized water is NOT available and fire protection water is available.
Step 2 -UNLOCK and CLOSE SLC Storage Tank Outlet Isolation Valve, C41-F001.
SLC Storage Tank Outlet Isolation Valve, C41-F001, is UNLOCKED and CLOSED. SAT/UNSAT*
NOTE: The procedure hasa note that informs the trainee of the location of Fire Hose Stations on the Reactor Building 80'elv. One station ison the south wall and the other station is on the north wall of the CRD Rebuild Room. NOTE: The trainee does not need to OPEN the LEP Toolbox, they should however explain what equipment is needed. IF THIS TOOLBOX IS OPENED, an inventory of the toolbox may be required by Operations.
The trainee will need an "LSV" Key for opening the toolbox which is normally carried by the duty Auxiliary Operator or is obtained from the SRO or the Work Control Center. No equipment should be removed from the toolbox for the performance of this JPM. PROMPT: A picture of the Fire Hose to SLC Connector is provided once obtained from the LEP toolbox Step 4 -Trainee determines which fire hose station to use. Fire hose station is selected for use. SAT/UNSAT*
AOT-OJT-JP-300-J11 Page 4 of 10 Rev. 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water Step 5 -REMOVE the fire hose nozzle for the fire hose to be used. Fire hose nozzle removed. ** CRITICAL STEP ** SAT/UNSAT*
Step 6 -CONNECT the Fire Hose to SLC Connector to the threaded connection upstream of SLC TEST TANK OUTLET DEMINERALIZED WATER SUPPL Y ISOLATION VALVE, C41-F014.
Fire Hose to SLC Connector connected to the piping. ** CRITICAL STEP ** SAT/UNSAT*
Step 7 -CONNECT the Fire Hose to SLC Connector to the selected fire hose. Fire hose connected to the Fire Hose to SLC Connector.
- CRITICAL STEP ** SA TlUNSAT* Step 8 -OPEN the hose reel angle valve for the fire hose. Opens angle valve counterclockwise (to the left). ** CRITICAL STEP ** SAT/UNSAT*
Step 9 -UNLOCK AND OPEN SLC TEST TANK OUTLET DEMINERALIZED WATER SUPPL Y ISOLA TlON VALVE, C41-F014.
C41-F014 is open. ** CRITICAL STEP ** SAT/UNSAT*
PROMPT: IF asked, air sparging is not in progress.
Or the examinee may ask the status of SLC STORAGE TANK SERVICE AIR STOP VALVE, C41-F012, at which time indicate that it is closed (or indicate that it looks as is if closed). AOT-OJT-JP-300-J11 Page 5 of 10 Rev. 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water Step 10 -Notify the Control Room that the required AO actions per LEP-01, Section 1, are complete and that the SLC Pumps may be started. Control Room notified that AO steps of LEP-01 are complete and the SLC. Pumps can be started. ** CRITICAL STEP ** SAT/UNSAT*
TERMINATING CUE: When the Auxiliary Operator actions are complete per LEP-01, Section 1 to allow the Control Operator to start the SLC Pumps, this JPM is complete.
TIME STOP: _______ _ Comments required for any step evaluated as UNSAT. AOT-OJT-JP-300-J11 Page 6 of 10 Rev. 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water RELATED TASK: 211 00685 Perform Alternate Coolant Injection With SLC Pumps Per EOP-LEP-01 KIA REFERENCE AND IMPORTANCE RATING: 295031 EA1.08 3.8/3.9 Ability To Operate/Monitor Alternate Coolant Injection Systems
REFERENCES:
20P-05, Standby liquid Control System operating Procedure SO-05, Standby Liquid Control System Description OEOP-01-LEP-01, Alternate Coolant Injection
-Rev. 23 P&IO 9527-0-25047, Unit 1 SLC System P&IO 9527-0-2547, Unit 2 SLC System TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2) Safety Function 2, Reactor Water Inventory Control REASON FOR REVISION:
Modified this JPM for use of the new connection piece. AOT-OJT-JP-300-J11 Page 7 of 10 Rev. 03 LEP-01; Alternate Coolant Injection
-SLC Pumps Using Fire Protection Water Time required for Completion:
15 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate X Actual Unit: Setting: Control Room Simulator_ (Not applicable to In-Plant JPMs ) Time Critical:
Yes No X Alternate Path: Yes No X EVALUATION Trainee: ________________
_ JPM: Pass Fail --Remedial Training Required:
Yes No __ Did Trainee Verify Procedure?
Yes __ No -:--__ (Each Student should verify one JPM per evaluation set.) Comments:
Comments Reviewed With Trainee Time Limit N/A Evaluator Signature:
_________________
Date: ____ _ AOT-OJT-JP-300-J11 Page 8 of 10 Rev. 03 Fire Hose to SLC Connector TASK CONDITIONS:
- 1. This task is to be performed on Unit __ . 2. The Reactor Vessel Control Procedure, EOP-01-RVCP, has been entered and is directing the crew to perform OEOP-01-LEP-01; Alternate Coolant Injection, (LEP-01) in order to maintain RPV water level above TAF. 3. ALL control rods are fully inserted.
- 4. The Fire Protection System is OPERABLE.
- 5. SLC Pumps are available to support LEP-01 activities.
- 6. The Demineralized Water System is damaged and is NOT available for use. INITIATING CUE: The Unit __ RO has directed you to perform the AO actions associated with lining up the SLC System to inject with Fire Protection Water per LEP-01 , Section 1, Coolant Injection With SLC Pumps. You are to notify the Control Room when the required steps of the procedure have been completed to allow the starting of the SLC Pumps.
Section 1 Coolant Injection with SLC Pumps NOTE: Manpower:
1 Reactor Operator 1 Auxiliary Operator RO: RO: RO: AO: AO: AO: 1 Independent Verifier Special equipment:
1 LEP toolbox key 1. 2. 3. 4. 80' Rx Bldg LEP Toolbox 3 locking tabs 1 pipewrench 1 Demineralized Water to SLC Jumper Hose 1 Fire Hose to SLC Connector INFORM the Unit CRS of the performance of this section. [@ IF directed by the Unit CRS to inject with SLC pumps [iA while aligned to the SLC storage tank, THEN GO TO Step 6, on page 7. IF it has been determined the reactor will remain [ffiJ shutdown under all conditions without boron, THEN CONTINUE in this procedure.
IF directed to inject demineralized water, THEN PERFORM the following steps: a. UNLOCK AND CLOSE SLC STORAGE TANK [ffi\ OUTLET ISOLATION VALVE, C41-FOO1.
- b. CONNECT one end of the DEMINERALIZED WATER TO SLC JUMPER HOSE to the threaded connection at SLC DEMINERALIZED WATER SUPPL Y ISOLA TlON VALVE, C41-V5000.
- c. CONNECT the other end of the DEMINERALIZED
[f;IA WATER TO SLC JUMPER HOSE to the threaded connection upstream of SLC TEST TANK OUTLET DEMINERALIZED WATER SUPPL Y ISOLA TlON VALVE, C41-F014.
IOEOP-01-LEP-01 Rev. 30 Page 5 of 381 Section 1 (Continued)
AO: AO: AO: d. OPEN SLC DEMINERALIZED WATER SUPPL Y ISOLA TlON VALVE, C41-V5000.
- e. UNLOCK AND OPEN SLC TEST TANK OUTLET DEMINERALIZED WATER SUPPL Y ISOLA TlON VALVE, C41-F014.
- 5. IF demineralized water is NOT available AND fire protection water is available, THEN PERFORM the following:
- a. UNLOCK AND CLOSE SLC STORAGE TANK OUTLET ISOLA TlON VALVE, C41-F001.
D NOTE: Fire hose stations are located on the north wall of the CRD rebuild room and the south wall of the SO' elevation.
AO: b. DISCONNECT the nozzle from the fire hose D selected for supplying SLC. AO: c. CONNECT one end of the FIRE HOSE TO SLC D CONNECTOR to the threaded connection upstream of SLC TEST TANK OUTLET DEMINERALIZED WATER SUPPLY ISOLATION VALVE, C41-F014.
AO: d. CONNECT the other end of the FIRE HOSE TO D SLC CONNECTOR to the fire hose selected in Step 5.b above. AO: e. ENSURE the temporary valve on the FIRE HOSE D TO SLC CONNECTOR is closed. AO: f. OPEN the hose reel angle valve for the fire hose D selected in Step 5.b above. AO: g. OPEN the temporary valve on the FIRE HOSE TO D SLC CONNECTOR until a stream of water issues from the valve, THEN CLOSE the temporary valve. AO: h. UNLOCK AND OPEN SLC TEST TANK OUTLET D DEMINERALIZED WATER SUPPL Y ISOLA TlON VALVE, C41-F014.
I OEOP-01-LEP-01 Rev. 30 Page 6 of 3s1 Section 1 (Continued)
AO: 6. IF sparging of the SLC tank is in progress, THEN CLOSE 0 SLC STORAGE TANK SERVICE AIR STOP VALVE, C41-F012.
RO: 7. START SLC Pumps A and B from the RTGB. 0 Initials 8. WHEN SLC pumps are NOT required for coolant injection, THEN PERFORM the following:
RO: a. PLACE SLC PUMPS A & B, C41-CS-S1, to STOP. AO: b. SECURE the fire protection water supply to SLC, if necessary.
- c. PERFORM the following for all valves that were operated:
AO: (1 ) ENSURE SLC STORAGE TANK SERVICE / AIR STOP VALVE, C41-F012, is locked Ind.ver. closed. AO: (2) CLOSE AND LOCK SLC TEST TANK / OUTLET DEMINERALIZED WATER Ind.ver. SUPPL Y ISOLA TlON VALVE, C41-F014.
AO: (3) CLOSE SLC DEMINERALIZED WATER / SUPPL Y ISOLA TlON VALVE, C41-V5000.
Ind.ver. AO: (4) OPEN AND LOCK SLC STORAGE TANK / OUTLET ISOLATION VALVE, C41-FOO1.
Ind.ver. AO: d. IF installed, THEN REMOVE the FIRE HOSE TO SLC CONNECTOR from the fire hose selected in Step 5.b above. AO: e. IF installed, THEN REMOVE the FIRE HOSE TO / SLC CONNECTOR from the threaded connection Ind.ver. upstream of SLC TEST TANK OUTLET DEMINERALIZED WA TER SUPPL Y ISOLA TlON VALVE, C41-F014, AND INSTALL the pipe cap. IOEOP-01-LEP-01 Rev. 30 Page 7 of 381 Section 1 (Continued)
Initials AO: f. AO: g. AO: h. AO: i. RO: j. AO: k. RO: I. 1 OEOP-01-LEP-01 IF removed, THEN INSTALL the fire hose nozzle removed in Step S.b on the fire hose used for supplying SLC. IF Step S.b was performed, THEN COORDINATE with Fire Protection personnel to perform an inspection of the fire hose station used for supplying SLC. IF installed, THEN REMOVE the DEMINERALIZED WATER TO SLC JUMPER HOSE and connections, AND INSTALL the pipe caps. RETURN any LEP tool box equipment to storage AND PERFORM inventory of LEP tool boxes. COORDINATE with E&RC to sample the SLC tank for proper concentration OR to refill the SLC tank in accordance with 1 (2)OP-OS.
INITIATE a WO to replace both squib valves. EXIT this section AND CONTINUE in this procedure at Step 2.1 on page 3. DatelTime Completed Performed By (Print) Reviewed By: ______ _ Unit CRS/SRO / IndVer. / IndVer. Initials Rev. 30 Page 8 of 381 PROGRESS ENERGY -CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT NRC In-Plant J LESSON TITLE: Manually transferring the Electric Fire Pump power supply. LESSON NUMBER: AOT-OJT-JP-041-A07 REVISION NO: 02 Manually transferring the Electric Fire Pump power supply. SAFETY CONSIDERATIONS:
Use caution in the vicinity of operating equipment.
Use caution in vicinity of energized electrical equipment.
EVALUATOR NOTES: (Do not read to trainee) 1. The applicable procedure section WILL be provided to the trainee. 2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee. Read the following to trainee. TASK CONDITIONS:
- 1. Off-Site Power is unavailable to either unit. DG2 is tripped, and Bus E2 is energized, and cannot be energized by cross-tie.
- 2. Buses E1, E3, and E4 are energized by their respective DGs. Buses E5 and E6 have been cross-tied.
- 3. The Diesel Driven Fire Pump is unavailable.
- 4. RVCP directs aligning all available alternate coolant injection per EOP-01-LEP-01.
Reactor pressure is 10 psig. 5. The Electric Fire Pump is aligned to its normal power supply. The Electric Fire Pump cannot be started from the control room. 6. The Electric Fire Pump Normal and Alternate Feed Breakers are open and indicate off on the XU-69 panel. 7. All applicable prerequisites listed in Section 4.0 of OP-41 are met. INITIATING CUE: You are directed by the Unit CO to transfer the Electric Fire Pump to its alternate power supply in accordance with OP-41 and inform the CO when your actions are complete.
AOT -OJT -J P-041-A07 Page 2 of 7 REV. 02 Manually transferring the Electric Fire Pump power supply. PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain a current revision of OP-41 , Section 8.58. Current Revision of OP-41, Section 8.58. SATIUNSAT*
PROMPT: Inform the examinee that the switches on XU-69 are tripped and breakers indicate OFF. Step 2 -Shift the Electric Fire Pump to the alternate supply at the 2-FP-P2-XFER-SW cabinet as follows: a. Confirm normal transfer switch operating oil level. Oil level is normal. SAT/UNSAT*
- b. Remove the transfer switch locking device. Locking device removed. ** CRITICAL STEP ** SATIUNSAT*
- c. Disengage position pin from position plate. Position pin is disengaged.
- CRITICAL STEP ** SAT/UNSAT*
- d. Place Transfer switch located on front of cabinet in position A. Transfer switch located on front of cabinet placed in position A. ** CRITICAL STEP ** SAT/UNSAT*
AOT -OJT -J P-041-A07 Page 3 of 7 REV. 02 Manually transferring the Electric Fire Pump power supply. e. Ensure position pin engages position plate. Position pin engaged. SAT/UNSAT*
- f. Install the transfer switch locking device. Locking device installed.
SAT/UNSAT*
PROMPT: When requested, Inform the examinee that the switches on XU-69 are closed and breakers indicate ON. PROMPT: As theSCO inform the examinee that another operator will perform Attachment
- 47. Step 3 -Inform CO that Fire Pump has been transferred to alternate power. CO informed actions for fire pump are complete.
SAT/UNSAT*
I TERMINATING CUE: Fire pump has been transferred to alternate power per OP-41.
- Comments required for any step evaluated as UNSAT. AOT -OJT -JP-041-A07 Page 4 of 7 REV. 02 Manually transferring the Electric Fire Pump power supply. RELATED TASKS: 2000758504, Perform Alternate Coolant Injection With Fire Water Per LEP-01 KIA REFERENCE AND IMPORTANCE RATING: 286000 A1.05 3.2/
3.2 REFERENCES
OP-41 TOOLS AND EQUIPMENT:
None. SAFETY FUNCTION (from NUREG 1123, Rev 2.): 8 -Fire Protection AOT-OJT-JP-041-A07 Page 5 of 7 REV. 02 Manually transferring the Electric Fire Pump power supply. Time Required for Completion: Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate X Actual Unit: _0_ Setting: Control Room Simulator
__ ( Not applicable to In-Plant JPMs ) Time Critical:
Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee: ----------------------------------------
JPM: Pass --Fail __ Remedial Training Required:
Yes No __ Comments:
Comments reviewed with Student Evaluator Signature:
______________________________
_ Date: -----AOT -OJT -JP-041-A07 Page 6 of 7 REV. 02 TASK CONDITIONS:
- 1. Off-Site Power is unavailable to either unit. DG2 is tripped, and Bus E2 is energized, and cannot be energized by cross-tie.
- 2. Buses E1, E3, and E4 are energized by their respective DGs. Buses E5 and E5 have been cross-tied.
- 3. The Diesel Driven Fire Pump is unavailable.
- 4. RVCP directs aligning all available alternate coolant injection per EOP-01-LEP-01.
Reactor pressure is 10 psig. 5. The Electric Fire Pump is aligned to its normal power supply. The Electric Fire Pump cannot be started from the control room. 5. The Electric Fire Pump Normal and Alternate Feed Breakers are open and indicate off on the XU-59 panel. 7. All applicable prerequisites listed in Section 4.0 of OP-41 are met. INITIATING CUE: You are directed by the Unit CO to transfer the Electric Fire Pump to its alternate power supply in accordance with OP-41 and inform the CO when your actions are complete.
8.58 Transferring the Electric Fire Pump P2 Power Supply 8.58.1 1. 2. 8.58.2 Initial Conditions All applicable prerequisites listed in Section 4.0 are met. The Unit SCO has determined the Electric Fire Pump power supply should be transferred.
Procedural Steps D D NOTE: Switch position B is the normal power supply source from Bus E2, Compt AH7. Switch position A is the alternate power supply source from Bus E4, Compt AL3. NOTE: IF plant conditions require the transfer switch to remain in alternate power supply position A, THEN an EC tag should be used for tracking until the transfer switch is restored to normal power supply position B. NOTE: Steps in this section will be performed at the 2-FP-P2-XFER-SW cabinet unless otherwise noted. NOTE: Performance of the followings steps will inop the Electric Fire Pump. 1. IF desired to transfer Electric Fire Pump power supply to the alternate source, THEN PERFORM the following:
- a. At Control Panel XU-69, MOMENTARILY PLACE the following switches to TRIP AND ENSURE the breaker indicates OFF: ELECTRIC FIRE PUMP P2 AL TERNA TE D FEED BREAKER CONTROL SWITCH (E4) ELECTRIC FIRE PUMP P2 NORMAL FEED D BREAKER CONTROL SWITCH (E2) b. CONFIRM normal transfer switch operating oil D level. c. REMOVE transfer switch locking device. D R Reference Use IOOP-41 Rev. 102 Page 133 of 271 I 8.58.2 Procedural Steps d. DISENGAGE position pin from position plate. D NOTE: The position pin should be released prior to the switch reaching position A to allow the pin to engage automatically.
- e. PLACE transfer switch on front of cabinet in D position A. f. ENSURE position pin engages position plate. D g. INSTALL transfer switch locking device. D h. At Control Panel XU-59, MOMENTARILY PLACE the following switches to CLOSE AND ENSURE breaker indicates ON: ELECTRIC FIRE PUMP P2 AL TERNA TE D FEED BREAKER CONTROL SWITCH (E4) ELECTRIC FIRE PUMP P2 NORMAL FEED D BREAKER CONTROL SWITCH (E2) 2. IF desired to transfer Electric Fire Pump power supply to the normal source, THEN PERFORM the following:
- a. At Control Panel XU-59, MOMENTARILY PLACE the following switches to TRIP AND ENSURE the breaker indicates OFF: ELECTRIC FIRE PUMP P2 NORMAL FEED D BREAKER CONTROL SWITCH (E2) ELECTRIC FIRE PUMP P2 AL TERNA TE D FEED BREAKER CONTROL SWITCH (E4) b. CONFIRM normal transfer switch operating oil D level. c. REMOVE transfer switch locking device. D IOOP-41 Rev. 102 Page 134 of 271 I 8.58.2 Procedural Steps d. DISENGAGE position pin from position plate. D NOTE: The position pin should be released prior to the switch reaching position B to allow the pin to engage automatically.
- e. PLACE transfer switch on front of cabinet in D position B. f. ENSURE position pin engages position plate. D g. INSTALL transfer switch locking device. D h. At Control Panel XU-69, MOMENTARILY PLACE the following switches to CLOSE AND ENSURE the breaker indicates ON: ELECTRIC FIRE PUMP P2 NORMAL FEED D BREAKER CONTROL SWITCH (E2) ELECTRIC FIRE PUMP P2 AL TERNA TE D FEED BREAKER CONTROL SWITCH (E4) 3. COMPLETE Attachment
- 47. D \OOP-41 Rev. 102 Page 135 of 271 I LESSON TITLE: PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT NRC In-Plant K Dual Unit Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels (Unit 2) LESSON NUMBER: AOT-OJT-JP-303-13 REVISION NO: 0 Station Blackout: Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels SAFETY CONSIDERATIONS:
- 1. Standard electrical precautions when working around energized electrical equipment.
- 2. Hard Hat, safety glasses, gloves and ear protection where posted. EVALUATOR NOTES: (Do not read to trainee) 1. The applicable procedure section WILL be provided to the trainee. 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee. Read the following to trainee. TASK CONDITIONS:
- 1. A complete Loss of Offsite Power has occurred in both Unit 1 and Unit 2. 2. Diesel Generators 1, 2, 3 and 4 cannot be started. 3. OAOP-36.2 section 3.2.24 has been entered and performed up to step 5. INITIATING CUE: You are directed by the Control Operator to complete the actions associated with aligning 2-SAMA-DIESEL-2 to Battery Chargers 2B-1/2B-2 in accordance with Section 3.2.24 steps 5 through 12. AOT -OJT -JP-303-012 Page 2 of 9 Rev.O Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain marked up copy of OAOP-36.2 Section 3.2.24. Current revision of OAOP-36.2 Section 3.2.24 obtained.
SAT/UNSAT TIME START ____ _ Step 2 -Ensure TRANSFER SWITCH 2-SAMA-DG2-XFER-SW is in MCC 2CB. 2CB selected **Critical Step** SAT / UNSAT PROMPT: Perform the following at 2-SAMA-OIESEL-2.
If asked, inform examinee that oil level is in the STOP ranae of the dinstick.
Step 3 -Check engine oil level is in the STOP range on the dip stick. Oil level verified in the stop region. SAT/UNSAT PROMPT: Perform the following at 2-SAMA-OIESEL-2.
Inform the examinee that OIESEL-2-52 is "as you see it". Step 4 -Ensure SAMA DIESEL GENERATOR 1 OUTPUT BREAKER, 2-SAMA-DIESEL-2-52, is OFF. 2-SAMA-O/ESEL-2-52 Output breaker off SAT/UNSAT PROMPT: Perform the following at 2-SAMA-OIESEL-2.
Inform the examinee that you hear noise from the diesel after "RUN" is depressed.
Step 5 -Press RUN to start the engine. Engine is running. **Critical Step** SAT / UNSAT AOT-OJT-JP-303-012 Page 3 of 9 Rev.O Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels Step 6 -Close SAMA DIESEL GENERATOR 1 OUTPUT BREAKER, 2-SAMA-DIESEL-2-52.
2-SAMA-DIESEL-2-52 Output breaker closed (up position).
- 2 SUPPLY, located on MCC 2CB, Compt. C60. MGG 2GB, Gompt. G60 closed. **Critical Step** SAT I UNSAT Step 8 -Close BATT CHARGER 2B-1 AC INPUT NORM FEED, located on MCC 2CB, Compt. C57. MGG 2GB, compt G57 closed **Critical Step** SAT I UNSAT Step 9 -Close BATT CHARGER 2B-2 AC INPUT NORM FEED, located on MCC 2CB, Compt. C56. MGG 2GB, compt G56 closed **Critical Step** SAT / UNSAT NOTE: Ensure that examinee adheres to all rules regarding fire doors when performing next step. Battery room to cable spread room door 2-CTB-DR-EL023-113 should be simulated tied open. Materials are located inSAMGtool box. Step 10 -Tie open the door between 2B Battery Room and Cable Spread, 2-CTB-DR-EL023-113. 2-GTB-DR-EL023-113 simulated tied open. SAT/UNSAT AOT -OJT -J P-303-0 12 Page 4 of 9 Rev.O Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels PROMPT: The following steps are performed in the battery rooms (28-1). Inform the examinee that the D.C. amperes on BAT-AM-6002 indicate 30 amps. Step 11 -Confirm the following for Battery Chargers 2B-1, D.C. AMPERES, BAT-AM-6002, indicates between 10 and 50 amps Verified to be between 10 -50 amps. SAT/UNSAT PROMPT: The following steps are performed in the battery rooms (28-2). Inform the examinee that the D.C. amperes on BAT-AM-6003 indicate 20 amps. Step 12 -Confirm the following for Battery Chargers (28-2), D.C. AMPERES, BAT-AM-6003, indicates between 10 and 50 amps Verified to be between 10 -50 amps SAT/UNSAT PROMPT: The following steps are performed in the battery rooms (28-1). Inform the examinee that the D.C. VOLTS,BAT-VM-6011, indicates 135.volts.
Step 13 -Confirm the following for Battery Chargers 2B-1, D.C. VOLTS, BAT-VM-6011, indicates between 130 and 140 volts Verified to be between 130 -140 volts SAT/UNSAT PROMPT: The following steps are performed in the battery rooms (28-2). Inform the examinee that the D.C. VOLTS, BAT-VM-6012, indicates 135 volts. Step 14 -Confirm the following for Battery Chargers 2B-2, D.C. VOLTS, BAT-VM-6012, indicates between 130 and 140 volts Verified to be between 130 -140 volts SAT/UNSAT AOT -OJT -J P-303-0 12 Page 5 of 9 Rev.O Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels Step 15 -Notify the TSC station batteries are charging using Battery Chargers 2B-1/2B-2 without battery room ventilation.
TSC notified (control room acceptable with comments)
SAT/UNSAT Termination Cue: When the TSC has been notified that the batterychargers have been enerQized from theSAMA Diesels this JPM may be terminated.
Time completed:
_____ _
- Comments required for any step evaluated as UNSAT. AOT-OJT-JP-303-012 Page 6 of 9 Rev.O Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels LIST OF REFERENCES RELATED TASKS: 200104B404 Perform AO actions to align diesel power to the battery chargers per OAOP-36.2.
KIA REFERENCE AND IMPORTANCE RATING: 295003 AA 1.02 4.2/4.3 Ability to Operate and/or Monitor Emergency Generators as it applies to a Station Blackout
REFERENCES:
OAOP-36.2, Section 3.2.21 TOOLS AND EQUIPMENT:
- 1. Plant page (or) 2. Radio 3. SAMG tool box SAFETY FUNCTION (from NUREG 1123, Rev 2): 6 (Electrical Distribution)
REASON FOR REVISION:
New for SAMA Diesels. AOT -OJT -J P-303-0 12 Page 7 of 9 Rev.O Station Blackout:
Energizing 2B-1/2B-2 Battery Chargers with SAMA Diesels Time Required for Completion:
18 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual Unit: 2 Setting: Control Room Simulator
__ (Not applicable to In-Plant JPMs) Time Critical:
Yes No X Time Limit Alternate Path: Yes No X EVALUATION Trainee: ________________
_ JPM: Pass --Fail __ Remedial Training Required:
Yes No Did Trainee Verify Procedure Revision?:
Yes No __ _ (Each Student should verify one JPM per evaluation set.) Comments:
Comments reviewed with Student Evaluator Signature:
_______________
_ Date: _____ _ AOT -OJT -J P-303-0 12 Page 8 of 9 Rev.O TASK CONDITIONS:
- 1. A complete Loss of Offsite Power has occurred in both Unit 1 and Unit 2. 2. Diesel Generators 1, 2, 3 and 4 cannot be started. 3. OAOP-36.2 section 3.2.24 has been entered and performed up to step 5. INITIATING CUE: You are directed by the Control Operator to complete the actions associated with aligning 2-SAMA-DIESEL-2 to Battery Chargers 2B-1/2B-2 in accordance with Section 3.2.24 steps 5 through 12.
3.2.24 1. Alignment of 2-SAMA-Diesel-2 to Battery Chargers 2B-1/2B-2 OBTAIN the SAMG Diesel Toolbox from the equipment gangbox located 23' Control Building stairwell, Unit 1. NOTE: Cross-tying E buses is the preferred method to energize battery chargers.
If cross-tying E buses is NOT possible, this section aligns the SAMA diesels to energize the battery chargers.
- 2. CONTACT the Control Room to determine if continuing with this section is desirable.
- 3. OPEN MCC 2CB, Compt A09, located on 480V Sub E8. W 4. ENSURE all breakers on MCC 2CB are off. W 5. ENSURE TRANSFER SWITCH 2-SAMA-DG2-XFER-SW D is in MCC 2CB. 6. PERFORM the following at 2-SAMA-DIESEL-2:
- a. CHECK engine oil level is in the STOP range on the D dip stick. b. ENSURE SAMA DIESEL GENERA TOR 2 OUTPUT D BREAKER, 2-SAMA-DIESEL-2-52, is OFF. c. PRESS RUN to start the engine. D d. CLOSE SAMA DIESEL GENERA TOR 2 OUTPUT D BREAKER, 2-SAMA-DIESEL-2-52.
- 7. CLOSE SAMA DIESEL GENERA TOR #2 SUPPL Y, D located on MCC 2CB, Compt. C60. 8. CLOSE BATT CHARGER 2B-1 AC INPUT NORM FEED, D located on MCC 2CB, Compt. C57. 9. CLOSE BA TT CHARGER 2B-2 AC INPUT NORM FEED, D located on MCC 2CB, Compt. C56. 10. TIE OPEN the door between 2B Battery Room and Cable D Spread, 2-CTB-DR-EL023-113.
IOAOP-36.2 Rev. 41 Page 128 of 1961 3.2.24 Alignment of 2-SAMA-Diesel-2 to Battery Chargers 2B-1/2B-2
- 11. CONFIRM the following for BA TTERY CHARGERS 2B-1 (2B-2): a. D. C. AMPERES, BA T-AM-6002, indicates between D 10 and 50 amps b. D. C. AMPERES, BA T-AM-6003, indicates between D 10 and 50 amps c. D.C. VOLTS, BAT-VM-6011, indicates between 130 D and 140 volts d. D.C. VOLTS, BAT-VM-6012, indicates between 130 D and 140 volts CAUTION Batteries generate hydrogen gas when being charged. IOAOP-36.2
- 12. NOTIFY the TSC station batteries are charging using D Battery Chargers 2B-112B-2 without battery room ventilation.
- 13. MONITOR SAMA diesel fuel level AND REQUEST D Maintenance to refuel as necessary.
END OF SECTION Rev. 41 Page 129 of 1961