ML102371241
| ML102371241 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/25/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-390/08-301 | |
| Download: ML102371241 (168) | |
Text
REV. 5 PAGE 1 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 LOCAL CONTROL MOTOR DRIVEN AFWP LCV FOR #1 S/G LEVEL PER SOI-3.02
REV. 5 PAGE 2 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF DATE PAGES PREPARED!
NUMBER REVISION AFFECTED REVISED BY:
0 Initial Issue. 8/28/92 ALL 1 DELETE KNOWLEDGE 4/7/93 3,5,6,8,9 QUESTIONS, CHANGE VAL TIME, OTHER MINOR CHANGES 2 CHANGE WORDING AND 12/06/9 7 SETPOINTS IN JPM STEPS 6,7 3 3 REFLECT PROCEDURE REV 20 11/1/95 4,6,7,8 Ed Knoblauch 4 Revised K/A values to Rev 2 of 11/7/99 ALL Albert V. White NUREG 1122, updated procedure references, revised initiating cues, converted format to NRC format.
Added step addressing SG #2 Level Control.
5 Incorporated previously made pen & 9/28/07 ALL D.L. Hughes ink changes to update procedure referenced, add gloves to equipment needed, correct typo in step 8.
Reworded Examiners Cues for steps 5, and 7 to provide more detail.
No change of intent
REV. 5 PAGE 3 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 Task: Local Control Motor Driven AFWP LCV For #1 SIG Level Per SOl-3.02.
Alternate Path: N/A.
Facility JPM #: 3-OT-JPMAO87 Rev 5 K/A Rating(s): 054-AK3.03 [3.8/4.1] 054-AA [4.5/4.4] 2.1.30 [3.9/3.4]
Task Standard: Establish communications with the Control Room Operator and assume local control of #1 S/G level using lA-A Motor-Driven AFWP LCV.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant X Perform Simulate X
References:
SOl-3.02 Auxiliary Feedwater System Rev. 45 Task Number:: AUO-003-SOI-3.02-008 APPLICABLE FOR: AUO/RO/SRO 10CFR55.45: 7, 8, 9 Validation Time: 13 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
REV. 5 PAGE 4 OF 10 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 Tools/Eguipment!Procedures Needed:
Hard Hat, Safety Glasses, Flashlight, Hearing Protection, Plant Approved Shoes, gloves, and radio.
Latest revision of SOl-3.02.
Ladder Safety since some valves require access from above floor elevation, and ALARA considerations. Auto Start capabilities of the AFW System.
NOTE: Start this JPM in the MCR.
EVALUATOR NOTE: Provide copy of SOI-3.02 Section 8.5 to performer with candidates cue sheet.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Unit is in Mode 3 with the RCS at 557 F and 2235 psig.
0 The TD AFW Pump is tagged for maintenance.
The Control Room Operator has been experiencing increasing difficulty in maintaining
- 1 S/G level.
You are the Auxiliary Building AUO and you have already checked out a radio.
INITIATING CUES:
The Unit Supervisor has directed you to establish radio communications with the MCR and then take local control of SG 1 level via lA-A MD AFWP, per S01-3.02 Section 8.5.
REV. 5 PAGE 5 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 START TIME:
STEP 1: Obtain a copy of the procedure.
SAT STANDARD: A copy of SOl-3.02 Sect. 8.5.1 has been obtained.
EXAMINERS CUE: Provide copy of SOI-3.02 Section 8.5 to performer.
UNSAT COMMENTS:
NOTE Direct radio communications with UO required to perform this section.
STEP 2: Establish communication with the UO.
STANDARD: Radio Communication with the MCR has been established.
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 6 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 STEP 3: [Step 1] ENSURE AFW Pump A-A running.
STANDARD: Performer determines that the lA-A MD AFWP is running by observation or MCR information. SAT
UNSAT
- CUE: If local indications checked, performer can hear/feel normal pump running soundMbration, discharge pressure 1150 psig COMMENTS:
Note: Performance steps 4 and 5 are part of the same instruction step and_must_be_performed_in_sequence.
STEP 4: [Step 2] PERFORM the following to fail CLOSED l-PCV CRITICAL 122, AUX FEEDWATER PMP lA-A DISCHARGE PRESS STEP CONTROL [A3S/71 3]:
[2.1] CLOSE O-ISV-32-460, ESSENT CNTL AIR ISOL VALVE TO 1-PCV-3-l 22: SAT STANDARD: O-ISV-32-460 is manually closed. Step is critical to allow isolation of air to fail valve closed.
UNSAT
- CUE: After performer describes how to close valve, state valve handle rotates clockwise until it is snug.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 7 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 STEP 5: [Step 2.2] DEPRESSURIZE air from regulator on 1 -PCV CRITICAL 122. STEP STANDARD: Petcock on local pressure regulator on 1-PCV-3-122 located and manually opened to de-pressurize regulator. Step is SAT critical to allow bleed of air to fail valve closed.
- CUE: After drain valve is opened, state that air is heard and felt coming from the drain, which then slows down and UNSAT stops completely.
IF ASKED about 1-PCV-3-122 response, state that as air was bled off, 1-PCV-3-122 stem moved down and is now completely down indicating closed.
COMMENTS:
Note: Performance steps 6 and 7 are part of the same instruction step and_must_be_performed_in_sequence.
STEP 6: [Step 3] IF MANUAL control of SG 1 level is necessary, CRITICAL THEN PERFORM the following to fail OPEN 1 -LCV-3-1 64, STEP MD AFW PUMP lA-A SG 1 LEVEL CONTROL [A3T/737 West Wall]:
[3.1] CLOSE 1-ISV-32-3765, ESSENT CONTROL AIR ISOL SAT VALVE TO 1-LCV-3-164.
STANDARD: 1 -ISV-32-3765 is manually closed. Step is critical to allow isolation of air to fail valve open. UNSAT
- CUE: After performer describes how to close valve, state valve handle rotates clockwise until it is snug.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 8 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 STEP 7: [Step 3.2] DEPRESSURIZE air from regulator on 1-LCV CRITICAL 164. STEP STANDARD: Petcock on local pressure regulator on 1-LCV-3-164 located and manually opened to de-pressurize regulator. Step is SAT critical to allow bleed of air to fail valve open.
- CUE: After drain valve is opened, air is heard and felt coming from the drain, which then slows down and stops UNSAT corn pletely.
IF ASKED about 1-LCV-3-164 response, state that as air was bled off, 1-LCV-3-164 stem moved up and is now completely up indicating open.
COMMENTS:
STEP 8: [Step 4] IF MANUAL control of SG 2 level is necessary, THEN PERFORM the following to fail 1-LCV-3-156, MD AFW PUMP lA-A SG 2 LEVEL CONTROL [A3T/737 West Wall]:
[4.11 CLOSE 1 -ISV-32-3761, ESSENT CONTROL AIR ISOL VALVE TO 1-LCV-3-156. SAT
[4.2] DEPRESSURIZE air from regulator on 1-LCV-3-156.
STANDARD: Performer determines that this step is N/A and proceeds to the UNSAT next step.
- CUE: If control room contacted, state that manual level control of SG 2 is not required.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 PAGE 9 OF1O WATTS BAR NUCLEAR PLANT 3-OT-J PMAO87 NOTE: Manual Handwheel on top of 1-PCV-3-122 must be turned CLOCKWISE to OPEN.
STEP 9: [Step 5] ADJUST 1-PCV-3-122, AUX FEEDWATER PMP 1A- CRITICAL A DISCHARGE PRESS CONTROL to establish approx 1200 STEP psid between 1-PI-3-117, AUX FEEDWATER PMP lA-A SUCTION PRESS, and 1-Pl-3-122B, AUX FEEDWATER PMP lA-A DISCHARGE PRESS [A3S/713]. SAT STANDARD: Manual hand wheel for 1-PCV-3-122 adjusted (clockwise to open) to establish approximately 1200 psid between 1-Pl 117 and 1 -P1-3-i 22B. .Step is critical to establish flow path UNSAT to SG 1.
- CUE: After adjustment of 1 -PCV-3-1 22, indicate that 1 -P1-3-117 reads 20 psig and 1-Pl-3-122B reads 1200 psig COMMENTS:
STEP 10: [Step 6] IF SG 1 level to be controlled, THEN UNLOCK and CRITICAL THROTTLE 1-ISV-3-828, MD AFW PUMP lA-A SG 1 LEVEL STEP CONTROL ISOL, per UO instruction [A3T/737 West Wall].
STANDARD: 1 -ISV-3-828 is unlocked and manually throttled clockwise to SAT 50%.. Step is critical to control flow path to SG 1.
- CUE: Inform the performer that the lock, if present, is a breakaway type lock. UNSAT
- CUE: Respond as control room and request 1-ISV-3-828 be throttled to 50% open position.
- CUE: After valve is throttled, then respond as control room and state that the Rad Waste AUO will be contacted if additional adjustments are needed.
COMMENTS:
END OF TASK TIME STOP:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 5 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DO NOT OPERATE ANY PLANT EQUIPMENT INITIAL CONDITIONS:
The Unit is in Mode 3 with the RCS at 557 F and 2235 psig.
0 The TD AFW Pump is tagged for maintenance.
The Control Room Operator has been experiencing increasing difficulty in maintaining
- 1 S/G level.
You are the Auxiliary Building AUO and you have already checked out a radio.
INITIATING CUES:
The Unit Supervisor has directed you to establish radio communications with the MCR and then take local control of SG 1 level via lA-A MD AFWP, per SOI-3.02 Section 8.5.
REV. 0 PAGE 1 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A lA-A DIESEL GENERATOR IDLE START FOR WARM UP PER SOI-82.Ol
REV. 0 PAGE 2 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A NUCLEAR TRAINING REVISION/USAGE LOG REV DESCRIPTION OF DATE PAGES REVIEWED BY NO. REVISION AFFECTED 0 Initial Issue. Used 3-OT-JPMAO49and 04/29/08 ALL modified
REV. 0 PAGE 3 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A EVALUATION SHEET Task: lA-A Diesel Generator Idle Start for Warm Up per SOI-82.01 Alternate Path: To Emergency Stop the EDG due to exceeding Lube Oil Temperature shutdown criteria.
Facility JPM #: 3-OT-JPMAO49 Rev 6 K/A Rating(s): 064-A4.01 [4.0/4.3] 064-A4.06 [3.9/3.9] 064-A3.06 [3.3/3.4]
2.1.30 [3.9/3.4]
Task Standard: lA-A DG is successfully started, brought to idle speed, and then emergency stopped due to excessive lube oil temperature, Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant X Perform Simulate X_
References:
SOl-82.O1 Diesel Generator lA-A Rev. 61 Task Number:: AUO-082-SOl-82.1-OO1 APPLICABLE FOR: AUO/RO/SRO AUO-082-SOl-82. 1-002 10CFR55.45: 8 VIit1tinn Time: 25 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS
REV. 0 PAGE 4 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A EVALUATOR INFORMATION SHEET Tools/EguipmentlProcedures Needed:
Hard Hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes.
Ear Muffs (simulate for double hearing protection required when DG in operation)
SOI-82.O1 INSERT EXTRA COPY OF APPENDIX B SOI-82.01 after page 10 of JPM.
Safety considerations: C02 Protected area; Potential for high noise if DG auto starts.
NOTE: Get Shift Managers Permission to enter the EDG lA-A Room Start this JPM in the MCR.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
All DGs are in standby alignment.
IA-A DG has been declared INOPERABLE, preventative maintenance on both Engines Jacket Water Systems has just been completed.
lA-A DG has been rolled one complete revolution four hours ago.
Maint. Crews are on hand to perform required surveillance testing of the lA-A DG.
You are an AUO assigned to work with Maint. on the 1 A-A DG.
INITIATING CUES:
The Control Room Operator directs you to use SOI-82.01 to locally perform an Idle Start for warm up followed by shutdown on the lA-A DG.
You are to notify the Control Room Operator when you have completed the task and the lA-A DG is returned to standby alignment.
REV. 0 PAGE 5 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO49A START TIME:
STEP 1: Obtain a copy of the instruction.
STANDARD: A copy of SOI-82.O1 section 8.1.1 and 8.1.2 has been SAT obtained.
EXAMINERS CUE: After the performer has identified correct instruction, the evaluator can provide a copy of UNSAT the instruction.
EVALUATOR NOTE: Section 8.1.1 contains prerequisite. Initial conditions for this JPM has the information to meet prerequisites. Prerequisite Steps 1 & 2 are met.
COMMENTS:
Note: The following steps are from Section 8.1.2 Idle Start STEP 2: [1] ENSURE 1-HS-82-18, DG MODE SELECTOR CRITICAL SWITCH, in (UNIT) PULL FOR LOCAL TRANSFER STEP
[O-M-26].
STANDARD: Performer contacts the MCR to ensure that 1 -HS-82-1 8 is SAT in PULL FOR LOCAL TRANSFER. This step is critical to enable local control of DG.
UNSAT
- CUE: When contacted, repeat back, then report that 1-HS-82-18 has been placed in PULL FOR LOCAL TRANSFER COMMENTS:
REV. 0 PAGE 6 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO49A STEP 3: [2] ENSURE VOLTAGE SHUT DOWN, red light LIT
[1-PNL-82-A, Diesel Engine 1A1I1A2 Control Panel].
SAT STANDARD: Performer ensures that voltage shutdown red light is LIT.
- CUE: When checked, state that light is LIT UNSAT COMMENTS:
STEP 4: [3] PRESS 1-HS-82-22, TRIP TO LOCAL GEN lA-A, to CRITICAL trip LRX1 A relay to LOCAL. [1 -ARB-82-A/3 Diesel STEP Generator lA-A Relay Board].
STANDARD: The performer presses 1-HS-82-22, TRIP TO LOCAL GEN SAT 1 A-A. This step is critical to enable local control of DG.
- CUE: It asked, state that an audible snap was heard when UNSAT hand switch was pressed.
COMMENTS:
STEP 5: [4] ENSURE 1-RLY-82-LRX1A, DG lA-A LOCALJ REMOTE CONTROL LOCKOUT, in LOCAL. [1 -ARB 82-All Diesel Generator lA-A Relay Board]. SAT STANDARD: The performer ensures that 1-RLY-82-LRX1A, DG lA-A LOCAL/REMOTE CONTROL LOCKOUT, in LOCAL UNSAT
- CUE: When LRX1A is checked, STATE that the relay handle is positioned to LOCAL.
COMMENTS:
REV. 0 PAGE 7 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A STEP 6: [5] PRESS AND HOLD 1 -HS-1 8-29/1, FUEL OIL CRITICAL PRIMING PUMPS DSL ENG 1A1 & 1A2 PB [1-PNL- STEP 82-A/2], until fuel press gauges indicate greater than 20 psig (1-IPl-18-1000/1, DG ENG 1A1 FUEL OIL PRESS, & 1-lPl-18-1001/1, DG ENG 1A2 FUEL OIL SAT PRESS)[1-PNL-82-AI1, Diesel Engine 1A1/1A2 Control Panel].
STANDARD: 1-HS-18-29/1, FUEL OIL PRIMING PUMPS DSL ENG 1A1 UNSAT
& 1A2 PB, is pressed and held until fuel press gauges are verified >20 psig (1 -IPI-1 8-1000/1 & 1 -IPI-1 8-1001/1).
This step is critical to provide proper prime to fuel injectors.
- CUE: When the pressure gauges are checked, use a pen to simulate that the pressure is 28 psig.
COMMENTS:
NOTE: DG-1 A-A should reach speed of 450+/-10 rpm and hold.
Speed indication is on 1-PNL-82-A.
STEP 7: [6] PRESS 1-HS-82-25, IDLE START GEN lA-A, CRITICAL
[1-PNL-82-A/2, Diesel Engine 1A1/1A2 Control Panel] STEP to start DG.
STANDARD: 1-HS-82-25, IDLE START GEN lA-A, is pressed. This SAT step is critical since it starts the DG.
- CUE: After switch is depressed is pushed, state that the diesel generator starts, and if checked engine is at UNSAT 445 RPM.
COMMENTS:
REV. 0 PAGE 8 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A STEP 8: [7] IF 1-FCV-67-66, DG HX 1A1/1A2 ERCW SUP HDR 1A ISOL, is NOT OPEN, THEN OPEN 1-FCV-67-68, DG HX 1A1/1A2 ERCW SUP HDR 2B ISOL, using 1-HS-67-68D, DSL GEN ENG 1A1!1A2 HTX ERCW SAT HEADER B SUPPLY. [1-PNL-82-AI1].
STANDARD: Performer verifies that 1 -FCV-67-66 is open.
UNSAT
- CUE: If MCR contacted, state that there are no indication lights on 1-FCV-67-66. Label indicates that it has power disconnected and is open. If local check is made, use a pen to simulate the local indicator points to open.
COMMENTS:
STEP 9: [8] IF DG startup is for testing, AND a thick black combustion product emits for more than 5 minutes, THEN PERFORM the following:
A. QUICKLY LOAD DG to 4.4MW to burn SAT excess oil.
B. IF smoke will NOT clear, THEN NOTIFY SRO to evaluate DG shutdown.
UNSAT STANDARD: Performer verifies combustion exhaust is normal.
- CUE: When performer checks exhaust, state that the combustion exhaust is grayish white in color and not excessive.
COMMENTS:
REV. 0 PAGE 9 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A NOTE TO EVALUATOR: The following step refers to intake dampers to the DG room located in the overhead by the north end of the DG.
These when checked (when simulating task performance) are normally closed. When performer checks them, asks what position they are in, then give the CUE below:
STEP 10: [9] MONITOR all 4 groups of the AIR Intake Damper to the outside plenum are full open, AND IF ANY of the 4 groups in the Air Intake Damper fails to fully OPEN, THEN SAT
[9.1] NOTIFY the Duty Engineering Manager to perform an evaluation to determine affect on DG operability.
[9.2] INITIATE WO to repair the failed group. UNSAT WO#_________
STANDARD: Performer verifies that Air Intake Damper 1 -FCO-3O-443 four groups are fully OPEN.
COMMENTS:
EVALUATOR NOTE: USE your copy of Appendix B (last page) to assist in indicating to performer the appropriate values.
REV. 0 PAGE 10 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A STEP 11: [10] MONITOR parameters listed on Appendix B during operation.
STANDARD: The performer locates and verifies the parameters as listed SAT in Appendix B.
- jJ If asked about a parameter AFTER IT IS CHECKED, indicate to performer (use of a pointer, laser, etc.)
that the parameter indicates the value listed for the UNSAT parameter when checked.
(Note: The Candidate may check these parameters in a different order than listed since doing them in sequence is not required. Give these readings on the first engine looked at. The appropriate cue is underlined.)
Lube Oil Pressure: 75 psig Lube Oil Tempfrom eng 255°F Evaluator Cue: If asked, the Lube oil pipe from the engine sump is too hot to touch.
If asked, rumbling, low frequency banging noise coming from engine Lube Oil Tempto eng 200°F Jacket Water Temp to Eng 175 F Evaluator Cue: If checking Jacket Water Temperature after checking Lube Oil Temperature, the value will be 195 °F and slowly rising, and the Jacket Water Temp Alarm will be in on local EDG alarm panel (buzzer may not be heard over the EDG Engine noise). Otherwise if checked first, it will be 180 °F and slowly rising Jacket Water Temp from Eng 195 °F
REV. 0 PAGE 11 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A Fuel Oil Pressure: 40 psici Pressure at outlet of strainers 38 psig Exhaust Cylinder Temps All 1200 °F Woodward Governor Oil Level As actually indicated (> Low Mark)
Coolant Expansion Tank Level 1/2 way between Low and Full Mark Engine Crankcase Lube Oil Level Cue: Indicates slightly greater than the 7MARK.
Day Tank Level As actually indicated (> 1/2 full)
JW Hx ERCW flow 900 qpm (to each engine)
COMMENTS:
REV. 0 PAGE 12 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A STEP 12: [11] IF any parameter not within specified limits, THEN CRITICAL NOTIFY SM/Unit SRO to evaluate removing D/G from STEP service.
STANDARD: 1-HS-82-17B, Emergency Stop DG lA-A Pushbutton is pressed.
This step is critical to the shutdown of the DG. SAT (The performer has determined that the lube oil temperature is beyond the limit and the lA-A Diesel Generator should be promptly secured.) UNSAT (If the Candidate attempts to radio the MCR to have them emergency stop the lA-A Diesel Generator. Do not respond to the radio call as if the MCR operators are too busy to answer.)
(If the Candidate simulates calling the MCR on the phone:
- Cue: The phone is busy.)
Once the Emergency Stop pushbutton has been depressed, then:
- CUE: The diesel can be heard shutting down and coming to a complete stop.
(If speed is checked on local panel 1 -PNL-82-A, indicate zero is speed)
COMMENTS:
Note: Go to JPM STEP 15 once the lA-A DG has been emergency stopped.
REV. 0 PAGE 13 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-J PMAO49A The candidate may use SOl-82.01, section 8.1.2 step 13 (listed below) to perform a local (non-emergency stop of the 1 A-A DG).
If the Emergency Stop Pushbutton was depressed, then go straight to STEP 15 of this JPM.
CAUTION: DG may accelerate for approximately 2 sec after actuating the normal stop handswitch due to the time delay inherent in the DG governor circuit which assumes a full speed condition when the normal stop handswitch is actuated. The time delay was added to allow the DG breaker to open before speed dropped to idle speed from full speed.
STEP 14: [13] IF Idle Start is used for warm up followed by shutdown, THEN PERFORM the following:
[13.1] PRESS 1-HS-82-26, LOCAL NORMAL STOP GEN lA-A, to initiate shutdown sequence [1 -PNL A12, Diesel Engine 1A1/1A2 Control Panel].
UNSAT STANDARD: 1-HS-82-26 is pressed.
- CUE: After switch is depressed is pushed, and if checked engine is at 450 RPM.
EVALUATOR NOTE: Speed indication is on 1-PNL-82-A.
If Candidate checks Lube oils temperature again,
- CUE: Lube Oil Temp indicates 265 °F and rising.
If the Candidate continues to attempt to contact the MCR, do not respond to the radio and/or inform them that the phone is still busy.
If after 5 minutes the Candidate still hasnt emergency stopped the diesel, then,
- CUE: The diesel can be heard seizing and coming to a sudden stop.
COMMENTS:
REV. 0 PAGE 14 OF 16 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO49A STEP 15: Notify the Control Room Operator that 1 A-A DG has been emergency stopped. SAT STANDARD: The performer notifies the MCR that lA-A DG has been emergency stopped due to lube oil temperatures being beyond limits. UNSAT
- CUE: When notified, acknowledge the report using repeat back.
COMMENTS:
END OF TASK TIME STOP:
REV. 0 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
INITIAL CONDITIONS:
All DGs are in standby alignment.
IA-A DG has been declared INOPERABLE, preventative maintenance on both Engines Jacket Water Systems has just been completed.
lA-A DG has been rolled one complete revolution four hours ago.
Maint. Crews are on hand to perform required surveillance testing of the lA-A DG.
You are an AUO assigned to work with Maint. on the lA-A DG.
INITIATING CUES:
The Control Room Operator directs you to use SOI-82.O1 to locally perform an Idle Start for warm up followed by shutdown on the lA-A DG.
You are to notify the Control Room Operator when you have completed the task and the lA-A DG is returned to standby alignment.
Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)
WBN Diesel Generator (OG) IA-A SOl-82.0I Unit I Rev. 0065 Page 79 of 88 Appendix B (Page I of I)
DG IA-A Operating Parameters (Idle)
PARAMETER MIN MAX SHUT DOWN Lube Oil Pressure 25 psig 120 psig 20 psig 75 psiq Lube Oil Temp (from engine) 85°F 230°F 250°F 1-ITI-82-309/IA1 ,1-lTl-82-307/1A2 255 °F Lube Oil Temp (to engine) 85°F 185°F 1 -lTl-82-31 0/1A1, 1-ITI-82-30811 A2 250 °F Jacket Water Temp (from engine) 100°F 190°F 1 205°F 1-ITI-82-304/1A1 ,1-ITI-82-301/1A2 180 °F
- Jacket Water Temp (to engine) 110°F 180°F 1-ITI-82-306/1A1 1 -ITI-82-303/1 A2 175 °F Fuel Oil Pressure 20 psig N/A 15 psig 40 psig Pressure at outlet of fuel oil strainers 1-Pl-18-6911 & 20 psig N/A 1-Pl-18-84/1 (Shaft Drive Pmps) 38 psig 1-Pl-18-68/1 & 1-Pl-18-83/1 (Priming Pmps)
Cylinder Exhaust Temp N/A 1100°F 1 1300°F 1000 °F 2
Woodward Governor Oil Level Low Mark --
> Low Mark Coolant Expansion Tank Level Run Mark Run Mark LOW FULL Mid Range Engine Crankcase Lube Oil Level 7 9 Day Tank Level 1/2 (-290 full Gals/tank) As indicated Jacket Water HX ERCW Flow 6SOgpm 1200 gpm
[1-Fl-67-69. EMERG DG HX IA1 ERCW (each engine) (each engine)
DISCH FLOW, 1-Fl-67-277, EMERG DG HX 1A2 1-FCV-67-66 900 gpm ERCW DISCH FLOW]. OPEN NOTE Parameters may NOT be achieved during initial 10 minute idle start.
Exceeding a shutdown parameter may cause extensive damage to the DG. If any parameter exceeds its shutdown limit, it should be immediately reported to the MCR and the DG should be shutdown immediately. Notify System Engineering for assistance.
2 Governor/Actuator oil level is at or above the indicator line for a single line sightglass or above the lower line of a two line sightglass. Addition/removal of oil should only be done based on oil level at idle.
A level above the 7 mark on engine lube oil dipstick ensures greater than 287 gallons of lube oil inventory. A level above the 6 mark on the engine lube oil dipstick ensures greater than 267 gallons of lube oil inventory. If oil level is less than 7, SRO must be notified immediately. REFER TO Tech Specs.
Unless the Candidate is checking this indication after identifying that the b& Lube Oil temp is elevated, then..
- CUE 195 °F and rising.
REV. 3 PAGE 1 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 TASK TITLE: LOCAL CONTROL OF 1 -FCV-62-93 (CHARGING FLOW CONTROL VALVE)
WRITTEN BY:
VALIDATED BY:
APPROVED BY:
(OPERATIONS TRAINING)
CONCURRENCE:
(OPERATIONS REPRESENTATIVE)
REV. 3 PAGE 2 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
0 INITIAL ISSUE REPLACES JPM #010, 9/12/97 All Revised to reflect procedure rev from Rev 17 to Rev 20 CN-1 of SO 1-62.01.
Added You are an AUO on shift to 09/23/98 All Albert V. White information sheet, revised K/As to Rev 2 NUREG 1122, updated procedure reference, reworded some cues.
2 Update procedure reference, revised K/A 10/30/01 All Albert V. White values to Rev 2 of NUREG 1122, JPM Technical content was not changed.
3 Incorporated pen & ink changes to that 07/31/07 All Albert V. White corrected handout sheet. Converted to new format, updated procedures referenced. Revised termination cue.
Task performance and evaluation were not changed.
REV. 3 PAGE 3 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 EVALUATION SHEET Task: LOCAL CONTROL OF FCV-62-93 (CHARGING FLOW CONTROL VALVE)
Alternate Path: None Facility JPM #: 3-OT-JPMAO1 0 Rev 3 K/A Rating(s): 004A2.22 [3.2/3.1] 004A1 .11 [3.0/3.0]
2.1.30 [3.9/3.4 2.1.23 [3.9/4.0]
TASK STANDARDS: 1 -HIC-62-93B has been placed in manual and Pressurizer Level has been raised to and stabilized at 60% in accordance with SOI-62.01 Section 8.5.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant X Perform Simulate X
References:
SOI-62.01, CVCS CHARGING AND LETDOWN, (Rev 55)
Task Number: AUO-062-SOI-62.1-006 APPLICABLE FOR: AUO/RO/SRO 10CFR55.45: 8, 9, 10 VIitItinq Time: 11 mm. Time Critical: No Candidate: Time Start:
NAME SSNIEIN Time Finish:
Performance Rating: SAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
REV. 3 PAGE 4 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Hard-hat, Safety Glasses, Hearing Protection Plant Approved Shoes Gloves ALARA considerations Note: Have a copy of SOl-62.01 to give to the performer.
Note: START THIS JPM AT THE RADWASTE AUO DESK IN THE AUX BLDG, READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
Unit at 100% RTP Centrifugal Charging Pump lA-A is in service.
Pressurizer level is being maintained by 1 -FCV-62-93, but the control system is malfunctioning.
Pressurizer level is stable at 55%.
The controller for 1 -FCV-62-93 is going to be repaired by IMs.
You are an AUC on shift.
INITIATING CUES:
The Unit Operator has directed you to check out a radio then take local control of 1-FCV-62-93 per procedure and slowly raise the pressurizer level to 60% while maintaining radio contact with the MCR operator (Allowing the MCR operator to adjust the seal flow with 1-FCV-62-89), then return charging flow to normal.
You are to notify the Unit Operator when local flow rate has returned to normal.
REV. 3 PAGE 5 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 START TIME:
STEP 1: Obtain a radio and the proper procedure STANDARD: The performer simulates check out of a radio and obtains a copy of SOI-62.1, section 8.5.
SAT (CUE: Inform the Performer not to actually check out a radio but discuss where/how to check out a radio.)
UNSAT COMMENTS:
EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
NOTE 1-FCV-62-93, CVCS CHARGING HEADER FLOW/PZR LEVEL CONTROL, fails OPEN (power or air.)
STEP 2: [1] ESTABLISH communication with UO before transfer to manual control.
STANDARD: Performer contacts control room prior to transfer control to SAT manual.
(CUE: When notified, acknowledge using repeat back.) UNSAT COMMENTS:
REV. 3 PAGE 6 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 STEP 3: [2] ADJUST 1-HIC-62-93B, CVCS CHARGING HEADER FLOW CTLR [PNL 1-L-1 12A, el. 692], so the Red Critical indicator (desired) and Black indicator (actual) are Step MATCHED. (0% is OPEN, 100% is CLOSED)
STANDARD: 1-HIC-62-93B has been located and the red indicator has been matched to the black indicator on 1 -HIC-62-93B. __SAT Step is critical to proper alignment for local control.
(CUE: When CHECKED indicate that the black indicator READS 34% and the red indicator UNSAT reads 0%. After ADJUSTED, indicate that the red is matched with the black indicator.)
COMMENTS:
NOTE Xl-62-93, MANUAL CHARGING FLOW CONTROL [1 -M-51, is LIT when HIC-62-93B is in MANUAL.
STEP 4: [3] PLACE 1-HIC-62-93B, CVCS CHARGING HEADER FLOW CTLR, in MANUAL. Critical Step STANDARD: The AUTO/MANUAL selector switch on 1 -HIC-62-93B has been placed in the MANUAL position.
Step is critical to proper alignment for local control.
(CUE: If UO contacted, State that Xl-62-93 red transfer SAT light is illuminated.)
COMMENTS: UNSAT
REV. 3 PAGE 7 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 NOTE Turning 1-HIC-62-93B clockwise reduces flow, counter-clockwise raises flow (UP is CLOSED, DOWN is OPEN on HIC)
STEP 5: [4] ADJUST 1-HIC-62-93B, CVCS CHARGING HEADER Critical Step FLOW CTLR, to vary charging flow and to balance Charging/Letdown flow per UO.
STANDARD: Charging flow has been adjusted per UO directions SAT (clockwise reduce flow / counterclockwise raise flow) with performer checking local indications for charging flow/pressurizer level or requesting Unit Operator feedback for appropriate parameters. UNSAT Note: Initial adjustment is CCW to raise level.
(CUE: When UO contacted, Direct the performer to slowly raise charging from 87 gpm to raise Pressurizer level.)
(CUE: When checked indicate that charging flow rising as CCW adjustment is made, or reducing as CW adjustment is made.)
Step is critical to proper control of flow path.
COMMENTS:
REV. 3 PAGE 8 0F9 WATTS BAR NUCLEAR PLANT 3-OT-JPMAO1 0 STEP 6: [5] MONITOR Charging flow:
[5.1] 1-LI-68-335B, PRESSURIZER LEVEL [1-L-369, A6T/692]
[5.2] 1-FI-62-93B, CVCS CHARGING HEADER FLOW [1-L-112A, A5T/692].
SAT STANDARD: Perlormer monitors pressurizer level and charging flow or has requested parameters from the control room.
(CUE: When checked, or if UO has been requested to _UNSAT report levels/flows inform the performer that PZR level is 60% and direct performer to slowly reduce charging flow back to 87 gpm.)
(CUE: When checked indicate that charging flow reducing as CW adjustment is made or rising if CCW adjustment is made and indicate flow is now 87 gpm.)
COMMENTS:
STEP 7: NOTIFY the control room that charging flow has been returned to normal.
STANDARD: The MCR operator has been notified that charging flow has been returned to normal.
SAT (CUE: When notified, acknowledge the report using repeat back.)
(CUE: Inform the performer that the Rad Waste AUO UNSAT will take over & maintain charging flow per UO directions. State This JPM has been completed. We will stop here.
COMMENTS:
END OF TASK TIME STOP:
REV. 3 WATTS BAR NUCLEAR PLANT CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
INITIAL CONDITIONS:
Unit at 100% RTP Centrifugal Charging Pump lA-A is in service.
Pressurizer level is being maintained by 1 -FCV-62-93, but the control system is malfunctioning.
Pressurizer level is stable at 55%.
The controller for 1 -FCV-62-93 is going to be repaired by IMs.
You are an AUC on shift.
INITIATING CUES:
The Unit Operator has directed you to check out a radio then take local control of 1-FCV-62-93 per procedure and slowly raise the pressurizer level to 60% while maintaining radio contact with the MCR operator (Allowing the MCR operator to adjust the seal flow with 1-FCV-62-89), then return charging flow to normal.
You are to notify the Unit Operator when local flow rate has returned to normal.
RevO. PAGE 1 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B1 PLACE MAIN GENERATOR IN SERVICE AND SYNCHRONIZE TO SYSTEM PER SOI-47.02
RevO. PAGE 2 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B1 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial Issue. 04/28/08 All D.L.Hughes
Rev 0. PAGE 3 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B1 EVALUATION SHEET Task: PLACE MAIN GENERATOR IN SERVICE AND SYNCHRONIZE TO SYSTEM PER SOI-47.02 Alternate Path: None Facility JPM #: 3-OT-JPMRO1 1 4B Rev 0 K/A Rating(s): A4.02 Ability to manually operate and/or monitor in the control room: T/G controls, including breakers [Importance RO/SRO 2.7 I 2.6]
TASK STANDARDS: Turbine Generator synchronized with Grid, generator voltage stable and MEGAVARS slightly outgoing, with voltage being controlled manually.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform _X Simulate
References:
SOl-47.02 Turbo-Generator Startup Operation Revision 0058 Task Number: RO-092-AOI-4-001 APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 4, 6, 12 Validation Time: 25 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
RevO. PAGE 4 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B1 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to IC # 252
- 2. Acknowledge all alarms.
- 3. Ensure MODs for PCBs 5088 and 5044 are OPEN
- 4. RESET Core Monitor Alarm, enable Core Monitor Alarm.
- 5. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
a) Initialize to IC- 46 b) Perform S01-47.02 section 5.4 Placing Generator in Service and Synchronizing with the Exciter Regulator On up to step [10.1] PLACE 1-HS-57-19, EXCITER FIELD BREAKER [1-M-1], in CLOSE.)
c) Acknowledge all alarms d) Place the Simulator in FREEZE.
- 7. After performer indicates understanding of task, place simulator in run.
SIMULATOR OPERATOR INSTRUCTIONS:
NONE
RevO. PAGE 5 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B1 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure to have a clean marked-up copy of SOl-47.02 Turbo-Generator Startup Operation to give to the performer prior to starting the JPM.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
AllI Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- A Unit Startup is in progress and is currently 14% RTP.
- SOI-47.02 Turbo-Generator Startup Operation is in progress and has been completed up thru Section 5.4 step [9].
- Switching Orders have been obtained from Northeast Area Dispatcher (NEAD) and Unit One is to be aligned with PCB 5088 & 5044.
- You are an extra RO.
INITIATING CUES:
Give performer a marked-up copy of SOI-47.02 Turbo-Generator Startup Operation.
The Unit Supervisor has directed you to synchronize the Main Generator with PCB 5088 lAW SOI-47.02 Turbo-Generator Startup Operation starting at section 5.4 step [10] and performing all applicable steps up thru step [28].
You are to notify the Unit Supervisor when step [28] is complete.
RevO PAGE 6 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B START TIME:
STEP 1:
[10] MONITOR 1-EI-57-15, GENERATOR VOLTS while performing the following: CRITICAL STEP
[10.1] PLACE 1-HS-57-19, EXCITER FIELD BREAKER [1-M-1], in CLOSE.
STANDARD: SAT 1-HS-57-l9 is placed in the CLOSED position.
COMMENTS:
UNSAT STEP 2: [10.2] Slowly JOG 1 -HS-57-23, EXCITER BASE CRITICAL ADJUSTER [1-M-1], until field flashes as STEP indicated by voltage rise..
STANDARD: 1 -HS-57-23 is adjusted to flash generator field as indicated SAT on 1 -El-57-1 5, Generator Volts.
COMMENTS:
UNSAT STEP 3: [10.3] ADJUST 1-HS-57-23, EXCITER BASE ADJUSTER [1 -M-1], to adjust voltage to 23.5 kV.
CRITICAL STANDARD: 1-HS-57-23, EXCITER BASE ADJUSTER [1-M-1], is STEP adjusted to produce a generator voltage to 23.5 kV.
COMMENTS: SAT UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0 PAGE 7 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 4: [11] VERIFY 3-phase GENERATOR VOLTS on 1-EI-57-15 using 1-XS-57-15.
SAT 1-XS-57-15 POSITION METER POT A-B METER POT B-C METER POT C-A VOLT REG POT A-B VOLT REG POT B-C VOLT REG POT C-A UNSAT STANDARD: 1-XS-57-15 has been selected to check voltages for meter pots and volt reg pots and voltages are 23.5 kV.
COMMENTS:
STEP 5: [12] PLACE SYNC SWITCH for selected PCB, to indicated CRITICAL position (N/A unused blank): STEP PCB HANDSWITCH POSITION 5088 1-HS-57-27, SYNC SWITCH SYNC CHK INTLK 500KV BUS_2 SAT 5044 2-HS-57-27, SYNC SWITCH SYNC CHK INTLK 500KV BUS_1 5064 SYNC SWITCH on ECB 5 for ON PCB_5064 STANDARD: I-HS-57-27 is placed in SYNC CHECK INTERLOCK position for PCB 5088. UNSAT COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 8 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 6: [13] Slowly JOG l-HS-57-23, EXCITER BASE ADJUSTER, CRITICAL to match INCOMING VOLTAGE (1-El-57-2), with STEP RUNNING VOLTAGE (1-EI-57-3) [1-M-1].
STANDARDS Generator running voltage is matched to incoming voltage with I-HS-57-23 as observed on 1-EI-57-2 & 1-EI-57-3.
COMMENTS: SAT UNSAT STEP 7: [14] VERIFY MAIN XFMR COOLER, Preferred Group IN SERVICE, by Red lights above l-HS-57106 [1-M-1].
SAT STANDARD: I-HS-57-1 06 is checked to verify Transformer Coolers (Preferred Group) in service.
Evaluator If asked as NAUO to verify which Transformer Coolers in service, respond Preferred Group in service.
Cue:
UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 9 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B
[15] PLACE I-HS-57-20, EXCITER REGULATOR [1-M-1], in TEST, and VERIFY Amber light LIT, and Green light OUT.
STANDARD: Voltage regulator l-HS-57-20 is placed in TEST, and amber light _SAT is verified LIT and green light OUT.
COMMENTS:
UNSAT STEP 9: [16] PERFORM the following:
CRITICAL STEP
[16.1] ADJUST l-HS-57-22, EXCITER VOLTAGE ADJUSTER, to obtain 0 on I-EI-57-12, V REG XFER BAL VOLTS.
SAT STANDARD: l-HS-57-22 is adjusted to null the regulator such that the output meter, l-El-57-12, reads 0.
COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 10 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 10: [162] PLACE I-HS-57-20, EXCITER REGULATOR to ON CRITICAL STEP SAT STANDARD: I-HS-57-20 is placed in the ON position and red light is verified ON and amber light OFF.
COMMENTS:
UNSAT STEP 11: [17] NOTIFY Northeast Area Dispatcher (NEAD) that generator is READY to SYNCHRONIZE.
STANDARD NOTIFY Northeast Area Dispatcher (NEAD) that generator is SAT READY to SYNCHRONIZE EXAMINER When notified, acknowledge the report CUE:
COMMENTS:
UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 11 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 12: [18] CHECK VALVE POSITION LIMIT set 15% OPEN.
SAT STANDARD: Performer checks/adjusts turbine Valve Position Limiter to 15% open. UNSAT COMMENTS:
STEP 13: [19] COORDINATE Turbine operation with Operator on feedwater and reactor controls.
_SAT STANDARD: Performer notifies ATC that the generator is about to be synchronized and loaded to grid. Monitor feedwater and UNSAT reactor controls COMMENTS:
STEP 14: [20] PUSH TURBINE MODES OPER AUTO SYNC button.
SAT STANDARD: OPER AUTO SYNC push button on EH panel is depressed & Oper Auto Sync light is checked illuminated COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 12 0F18 Watts Bar Nuclear Plant 3-OT-JPMR114B STEP 15: [21] ADJUST I-HS-57-21, GENERATOR SPEED OPER AUTO SYNC [l-M-l], to obtain SLOWLY moving SYNC-SCOPE (1 -XI-57-1 or SYNC PNL 1 on ECB 8 if using PCB 5064 to sync) in the FAST direction (one revolution every 10 -15 seconds). _SAT STANDARD: l-HS-57-21 is adjusted to obtain a SLOW SCOPE in the fast direction. Rotation of scope once every 10-15 seconds.
COMMENTS: UNSAT STEP 16: [22] ENSURE 1-El-57-2, INCOMING VOLTAGE, and 1-El-57-3, RUNNING VOLTAGE, are EQUAL SAT STANDARD: Incoming voltage is verified to be equal to running voltage.
COMMENTS:
UNSAT STEP 17: [23] IF Unit is to be synchronized using PCB 5044 (or 5064 spared out for 5044), THEN ENSURE MOD 6127 is OPEN and MOD 6117 is CLOSED.
SAT Performer determines step is not applicable, NAs step and STANDARD. proceeds to next step.
COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0 PAGE 13 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 18: [24] CLOSE MODs for PCB to be used to sync generator (N/A unused blank).
I MOD HANDSWITCH PCB SAT I 5087 & 5089 (ECB 6) 5088 I 5045 & 5043 (ECB 5) 5044 T 5065&5063(ECB5) 5064 STANDARD: Performer checks MOD 5087 and 5089 CLOSED position UNSAT by MOD red lights lit for respective MODs.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated..
RevO PAGE 14 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 19: [25] WHEN 1 -Xl-57-1, SYNC-SCOPE or SYNC PNL 1 on ECB 8) reaches 12:00, THEN PLACE [IS for CRITICAL selected PCB, in CLOSE (N/A unused blank):
STEP HANDSWITCH PCB 1 -HS-57-26 5088 2-HS-57-26 5044 PCB 5064 hand-switch on 5064 SAT ECB STANDARD: Generator PCB 5088 is CLOSED when synchroscope reaches 12:00 and all three phases are checked to verify loading.
UNSAT Evaluator If Performer attempts to close PCB 5088 exactly at Note: 12:00, the PCB may not close. The performer is allowed repeated attempts to close PCB 5088 providing closing attempt are within 5 minutes till noon EXAMINER If asked, cue performer that an additional attempt is to CUE: be performed.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 15 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 20: [261 ENSURE generator picks up some load on all 3 phases (DO NOT allow generator to motor):
INDICATOR LOCATION 1-El-57-9, A Phase AMPS 1-M-1 SAT 1-El-57-10, B Phase AMPS 1-N-i 1 -EI-57-i 1, C Phase AMPS 1 -M-i STANDARD: All three phases are checked to verify loading.
UNSAT COMMENTS:
STEP 21: [27] PLACE SYNC SWITCH used in Step [12] to OFF.
STANDARD: 1-HS-57-27, 500 kV Bus is placed in the OFF position.
SAT COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO PAGE 16 0F18 Watts Bar Nuclear Plant 3-OT-JPMR1 14B STEP 22: [28] ENSURE 1 -EI-57-8, MEGAVARS, is slightly outgoing SAT using 1-HS-57-22, EXCITER VOLTAGE ADJUSTER
[1 -M-1].
STANDARD: The performer should recognize that MEGAVARS, are slightly outgoing. .UNSAT COMMENTS:
TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- A Unit Startup is in progress and is currently 14% RTP.
- SOl-47.02 Turbo-Generator Startup Operation is in progress and has been completed up thru Section 5.4 step [9].
- Switching Orders have been obtained from Northeast Area Dispatcher (NEAD) and Unit One is to be aligned with PCB 5088 & 5044.
- You are an extra RO.
INITIATING CUES:
Here is the in-progress working copy of SOI-47.02 Turbo-Generator Startup Operation.
The Unit Supervisor has directed you to synchronize the Main Generator with PCB 5088 lAW SOI-47.02 Turbo-Generator Startup Operation starting at section 5.4 step [10] and performing all applicable steps up thru step [28].
You are to notify the Unit Supervisor when step [28] is complete.
REV. 0 PAGE 1 OF 24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB Establish Manual Makeup to Volume Control Tank (VCT) Per SOl-62
REV. 0 PAGE 2 OF 24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB
REV. 0 PAGE 3 OF 24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB REVISION LOG REVISION DATE DESCRIPTION OF CHANGES PAGES REVIEWED LOG AFFECTED BY 0 03/10/08 INITIAL ISSUE ALL D.L.Hughes
REV. 0 PAGE 4 OF 24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB Task: Establish Manual Makeup to Volume Control Tank (VCT) Per SOI-62 Alternate Path: When the Manual Makeup quanity has completed, the dilution valves will not close, requiring actions to secure the Primary Water pumps Facility JPM #: 3-OT-JPMRO5OB Rev 0 K/A Rating(s): 004 A4.13 Ability to manually operate and/or monitor in the control room:
VCT level control and pressure control [Importance: RO/SRO 3.3/2.9]
TASK STANDARDS:
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOl-62.02 Rev 0047 Boron Concentration Control AOl-03 Rev 0027 MALFUNCTION OF REACTOR MAKEUP CONTROL Task Number: RO-062-SOl-62-017 APPLICABLE FOR: RO/SRO 10CFR55.45: 2, 3, 5, 6, 8 Validation Time: 15 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
REV. 0 PAGE 5 OF 24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to preshot in IC # 258
- 2. Acknowledge all alarms.
- 3. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
Initialize to IC-40 Place 1-HS-62-140A in STOP Place 1 -HS-62-1 1 8A in divert until VCT level is 18%.
Insert IMF CVO9 to fail auto makeup to VCT.
Insert IOR ZD1HS62144 CLOSE Insert ICR ZD1HS62143 (el) OPEN Insert IOR ZD1HS62128 (el) OPEN Acknowledge alarms.
- 5. After performer indicates understanding of task, place simulator in run.
SIMULATOR OPERATOR INSTRUCTIONS:
- 1. When the performer is at JPM STEP 8, and Primary Water flow has been adjusted, insert Trigger 1 to fail 1-FCV-62-128, and 1-FCV-62-143 OPEN.
REV.O PAGE 6 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB Tools/EguipmentlProcedures Needed:
ENSURE clean copies of SOl-62.02 are in all the books on the simulator floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- The Unit is at 100% RTP.
- The RCS Cb is at 1020 ppm per Chem Lab report.
- VCT level is stable at 18%, Auto Make-up from the Blender has failed to operate.
- The STA has just completed a REACTW for the desired makeup.
INITIATING CUES:
The Unit Supervisor has directed you to perform a manual makeup to the VCT via 1 -FCV 128, MAKEUP TO VCT INLET, to increase VCT level to 29-31%.
Notify US when the procedure is complete.
REV.O PAGE 7 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB START TIME:
STEP 1: Obtain a copy of the procedure.
STANDARD: A copy of SOI-62.02 has been obtained COMMENTS:
SAT UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
(CUE:If asked, section 4.2, Field Preparations, have been completed)
CAUTION:
When maintaining VCT level using Manual, level must be monitored closely to avoid charging pump suction auto swapover to RWST.
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 8 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB Examiner Note: The following procedure note requires the batches to be performed in small batches (max 100 gallons at a time). There are 2 REACTW sheets in this JPM. If the performer fails to comply with the 100 gallon requirement and attempts to calculate batch for entire VCT change, give the performer the 232 gallon REACTW sheet. Otherwise give the performer the 97 gallon REACTW sheet.
NOTES:
- 1) Manual is used when auto makeup is unavailable or if desired due to special operating conditions. As RCS CB is changed during load follow, the Manual blended solution setpoints must be adjusted.
Controls are on 1-M-6.
- 2) RCS CB may be slightly changed during blended makeup because of the accuracy in flow controller settings. When this occurs small RCS temperature changes will be seen and control rod adjustments may be required to compensate for the temperature change.
- 3) Batches to the VCT should be done in several smaller batches rather than one large batch to allow time to evaluate possible reactivity effects between batches. A maximum batch of 100 gallons at a time is allowed.
STEP 2: [1] PERFORM Appendix C, Calculation Of Boric Acid And Primary Water Integrator Setting For Manual Makeup OR USE Appendix B for Blending at greater than 2500 ppm.
EXAMINERS SAT CUE: Give the Performer the appropriate REACTW SheeL (If the Candidate comments about the batch being STANDARD: greater than 100 gallon, then give them the 97 gallon UNSAT REACTW Sheet.)
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 9 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 3: [2] PLACE controllers in MANUAL, and CLOSE the following:
[a] 1-FC-62-139, BA TO BLENDER _SAT
[b] 1-FC-62-142, PWTO BLENDER STANDARD: 1-FC-62-139 and 1-FC-62-142 controllers placed in the MANUAL position and closed. _UNSAT COMMENTS:
STEP 4: [3] ADJUST Batch Counters for the desired quantity of CRITICAL boric acid and primary water using values from STEP Appendix B or C:
- a. 1-FQ-62-139, BA Batch Counter
- b. 1-FQ-62-142, PW Batch Counter SAT STANDARD: 1 -FQ-62-1 39 and 1 -FQ-62-1 42 have been reset and adjusted (by thumb wheel) to the desired quantity.
UNSAT If Candidate is using 232 Sheet, then:
- BA Batch Counter @ 35
- PW Batch Counter @ 197 If Candidate is using 97 Sheet, then:
- BA Batch Counter @ 14
- PW Batch Counter @ 83)
It is not a failure of the Critical Step if the wrong REACTW sheet is utilized. A failure of the Critical Step occurs if a value is used that is not on either REACTW sheet.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.0 PAGE 10 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 5: [4] PLACE 1-HS-62-140B, VCT MAKEUP MODE, in MAN.
SAT STANDARD: 1-HS-62-140B has been placed in the MANUAL position.
COMMENTS: UNSAT STEP 6: [5] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to CRITICAL START, and VERIFY Red light is LIT. STEP STANDARD: 1 -HS-62-1 40A, Make up Control Switch, has been placed SAT in the START position and Red Light has been verified LIT.
COMMENTS: UNSAT NOTE:
When blending to VCT through 1-FCV-62-128, Chemistry cannot get a representative sample of the blender outlet.
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 11 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 7: [6] IF Borating OR Blending, THEN PERFORM the CRITICAL following: STEP
[a] OPEN 1-FCV-62-128, MAKEUP TO VCT INLET SAT STANDARD:
1-HS-62-128, Makeup to VCT Inlet, has been placed in the OPEN position. .UNSAT COMMENTS:
STEP 8: [6] PERFORM the following: CRITICAL
[b] MANUALLY ADJUST 1 -FC-62-1 39, BA TO STEP BLENDER, and 1-FC-62-142, PW TO BLENDER, to desired flow(s) using blending flowrates from Appendix C, OR Appendix B for _SAT Blending at greater than 2500 ppm.
STANDARD:
- 1-FC-62-139 has been adjusted to approximately 12 (+/-0.5) gpm UNSAT
- 1-FC-62-142 has been adjusted to approximately 70 (+/-5.0) gpm SIMULA TOR OPERATOR When Primary Water flow has been adjusted, insert Trigger 1 to fail 1-FCV-62-128, and 1-FCV-62-143 OPEN.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 12 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB CAUTIONS:
- 1) 1-FC-62-142 should be maintained above 10% due to potential for controller oscillations.
- 2) If 1-FCV-62-128, MAKEUP TO VCT INLET and FCV 144, MAKEUP TO VCT OUTLET are NOT closed, boric acid will feed to the VCT through 1-FCV-62-140, BA TO BLENDER NOTE:
When blending to VCT through 1-FCV-62-128, Chemistry cannot get a representative sample of the blender outlet.
STEP 9: [7] IF Diluting, THEN PERFORM the following:
[a] OPEN 1-FCV-62-128, MAKEUP TO VCT SAT INLET.
[b] ADJUST 1-FC-62-142, PW TO BLENDER, to desired flow.
UNSAT STANDARD: The performer has determined that this step does not apply.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 13 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 10: [8] IF Alternate Diluting, THEN PERFORM the following:
[a] OPEN 1-FCV-62-144, MAKEUP TO VCT OUTLET, and 1-FCV-62-128, MAKEUP TO VCT INLET.
[b] ADJUST 1-FC-62-142, PW TO BLENDER, to UNSAT desired flow.
STANDARD: The performer has determined that this step does not apply.
COMMENTS:
STEP 11: [9] IF RCS CB is being changed, THEN PLACE 1 -HS 341H, BACKUP HEATER C [1-M-4], to ON to SAT equalize RCS-Pzr C .
8 STANDARD: The performer has determined that this step does not apply. UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 0 PAGE 14 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 12: [10] MONITOR parameters listed below:
Instrument Location Parameters SAT 1-Pl-62-122 1-M-6 VCT PRESS 1-Ll-62-129A 1-M-6 VCT LEVEL 1 -Fl-62-1 39 1 -M-6 BA TO BLENDER FLOW UNSAT 1-FQ-62-139 1-M-6 BA BATCH COUNTER 1-Fl-62-142 1-M-6 PW TO BLENDER FLOW 1-FQ-62-142 1-M-6 PW BATCH COUNTER 1 -Ll-62-238 1 -M-6 BAT A LEVEL 1 -Ll-62-242 1-M-6 BAT C LEVEL The above listed indicators have been checked periodically during VCT make-up operation.
STANDARD:
COMMENTS:
STEP 13: [11] IF 1-LI-62-129A, VCT LEVEL, increases to 63% THEN ENSURE 1 -FCV-62-1 1 8A, LETDOWN DIVERT TO SAT HUT, diverts to the HUT.
STANDARD: 1 -Ll-62-1 29A, VCT Level, is monitored periodically during VCT make-up operation and is not allowed to reach 63%. UNSAT COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 15 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 14: [12] WHEN 1-LI-62-129A, VCT LEVEL, is at desired level, THEN PERFORM the following:
[a] PLACE 1-HS-62-140A, VCT MAKEUP SAT CONTROL, to STOP.
[b] CLOSE 1-FCV-62-128, MAKEUP TO VCT INLET.
UNSAT STANDARD: 1 -Ll-62-1 29A has been checked at 29-31 %.
1-HS-62-140A has been placed in STOP position.
1-FCV-62-128 has been placed in the CLOSE postion.
Performer should realize that dilution flow did not stop and that 1-FCV-62-128 and 1-FCV-62-143 did not close.
COMMENTS:
Evaluator The Critical Task is to take actions to stop Primary Note Water flow in accordance with:
- ARI-1 12E PW to Blender Flow Deviation and AOl-3 Malfunction of Reactor Makeup Control, OR
- Tl-1204 Users Guide ForAbnormal And Emergency Operating Instructions (section2.7 Prudent Operator Actions)
(if Performer takes Prudent Operator action to Stop Primary Water flow, and does not perform ARI-1 12E, THEN N/A JPM steps 15 19 and complete JPM step 20)
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 16 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 15: AR! 112E actions:
Corrective Action: __SAT
[1] IF dilution controls in AUTO, THEN VERIFY 1-FCV-62-128 and 1-FCV-62-144 CLOSE.
[2] ENSURE VCT makeup control system lined up per SOI 62.02, BORON CONCENTRATION CONTROL. UNSAT
[3] IF manual operation of VCT makeup is required, THEN GO TO SOl-62.02 for system alignment and operation.
[4] IF Cause of alarm is Determined to be: Probable Cause #3.
Dilution/Boration in progress coincident with: THEN Re-N/A instate Dilution/Boration activity in progress.
[5] REFER TO AOI-3, MALFUNCTION OF REACTOR MAKEUP CONTROL STANDARD:
Performer attempts to perform step 1 above, ensures step 2 (lineup) above is correct, and then goes to AOl-3 COMMENTS:
- !talicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 0 PAGE 17 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB STEP 16: A 01-3 actions:
SAT OPERATOR ACTIONS Diagnostics UNSAT IF GO TO Subsection UNEXPLAINED rod insertion, SRM count rate RISING, or 3.2 T-avg RISING. N/A UNEXPLAINED rod withdrawal, SRM count rate DROPPING, or 3.3 T-avg DROPPING.
LOSS of one Demin Water Pump or 3.4 Header while the Primary Water System is in Bypass Mode.
STANDARD: Performer should go to Subsection 3.2 COMMENTS:
A 01-3 actions:
STEP 17:
l.a. CHECK PWST in normal alignment .SAT (PWST NOT Bypass Mode).
Evaluator If asked, inform performer that PWST is in normal UNSAT Que alignment STANDARD: Performer goes to step 1 b.
N/A COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 18 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB A 01-3 actions:
STEP 18:
1 .b. ENSURE standby primary water pump HS in MAN. __SAT STANDARD: Performer ensures that standby primary water pump HS in MAN. UNSAT COMMENTS:
N/A A 01-3 actions: CRITICAL STEP 19: STEP 1 .c. STOP the running primary water pump.
SAT STANDARD: Performer stops running PW Pump and then verifies that PW flow has stopped. The performer then notifies the SRO. UNSAT EVALUATOR If Performer completes JPM step 20, THEN N/A this NOTE JPM step. N/A COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.O PAGE 19 0F24 WATTS BAR NUCLEAR PLANT 3-OT-JPMRO5OB CRITICAL STEP 20: Prudent Operator Action JAW TI-12.04 STEP The Performer performs one or both of the following:
SAT STOPs both prima!y water pumps and verifies Primary Water STANDARD: flow has stopped on 1-Fl-62-142.
OR UNSAT Places 1-FC 142 in Manual and CLOSES 1-FCV 142 and verifies Primary Water flow has stopped on 1-FI 142.
The performer then notifies the SRO.
EVALUATOR If Performer has completed JPM step 19, THEN N/A this NOTE step.
COMMENTS:
Examiner Acknowledge report, notifiy performer that the task is cue: complete. End task TIME STOP:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev. 0 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The Unit is at 100% RTP.
- The RCS Cb is at 1020 ppm per Chem Lab report.
- VCT level is at 18%, Auto Make-up from the Blender has failed to operate.
- The problem has been found and a work request initiated by the previous shifts crew.
INITIATING CUES:
The Unit Supervisor has directed you to use the proper procedure to increase VCT level to 29-31%.
Notify US when the procedure is complete.
NRC Evaluator Sheet A REACTW - VERS WB3.2]
VCT MAKEUP INTEGRATOR SETTINGS CALCULATION WATTS BAR UNIT 1 CYCLE 9 WBN Boron Concentration Control SOI-62.02 Unit I Rev. 0047 Page 50 of 62 Appendix C (Page 1 of 4)
CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)
Date Today INITIALS NOTES 1> Use page 1 of this appendix when using VCT MAKEUP CALCULATION program in REACTINW, otherwise use pages 2 and 3 when performing Hand Calculations.
- 2) The computer code named REACTINW (VCT MAKEUP CALCULATION) when used from the Y: server is a verified and validated program. The methodology used is based on the equations:
V1C1 + V2C2 = V3C3 & VI + V2 = V3 Where: V is the volume flow rates of water and acid going into and out of the Boric Acid Blender and C is the boric acid concentration of the flow streams.
1.0 REACTINW VCT MAKEUP CALCULATION
[1] OBTAIN the following data for input to the REACTINW program:
Current RCS Boric Acid Concentration. 1020
[1.1] PPM
[1.2] Current BAT Boric Acid Concentration. 6820 PPM
[1 .3] B-i 0 Depletion Value from Reactivity Management Briefing Sheet 0 PPM
[1.4] Current VCT Level 18 %
[1 .5] Desired VCT Level 30 S7,
[2] RUN REACTINW calculation VCT Makeup Calculation. S7.I
[2A] PRINT the output file:
VCT MAKUP INTEGRATOR SETTINGS CALCUALTION S7,1
[3] SIGN and DATE output sheets. 57%
[4] OBTAIN independent verification by an SRO on output sheets. tS9
NRC Evaluator Sheet A REACTW - VERS WB3.2]
VCT MAKEUP INTEGRATOR SETTINGS CALCULATION WATTS BAR UNIT 1 CYCLE 9 INPUT DATA
[1] CURRENT RCS BORIC ACID CONCENTRATION 1020 PPM
[2] CURRENT BAT BORIC ACID CONCENTRATION 6820 PPM
[3] B-10 DEPLETION VALUE 0 PPM
[4] CURRENT VCT LEVEL 18 %
[5] DESIRED VCT LEVEL 30 %
CALCULATION OUTPUTS
[1] B-10 CORRECTED BORON CONCENTRATION 1020 PPM
[2] VCT ADDITION VOLUME 232 GALS
[3] TOTAL FLOW RATE 82.3 GPM CALCULATION CHECK QUANTITIES [1] AND [2] BELOW SHOULD BE APPROXIMATELY THE SAME
[1] VCT ADDITION VOLUME 232 GALS
[2] ( 35 + 197 )
(BA INTG SETTING + PW INTG SETTING)
TOTAL INTEGRATOR SETTING 232 GALS INPUT DATA
[1] BA BATCH COUNTER 35 GALS (1-FQ-62-139) [1-M-6j
[2] BA TO BLENDER 30.8 %
(1-FC-62-139) [1-M-61
[3] BA TO BLENDER FLOW 12.3 GPM (1-FI-62-139) [1-M-6]
[4] PW BATCH COUNTER 197 GALS (1-FQ-62-142) [1-M-6]
[5] PW TO BLENDER 35.0%
(1-FC-62-142) [1-M-6]
[6] PW TO BLENDER FLOW 70.0 GPM (1-FI-62-142) [1-M-6]
70d4, PERFORMER DATE 7
IV/SRO DATA
NRC Evaluator Sheet B REACTW - VERS WB3.2]
VCT MAKEUP INTEGRATOR SETTINGS CALCULATION WATTS BAR UNIT 1 CYCLE 9 WBN Boron Concentration Control SOl-62.02 Unit I Rev. 0047 Page 50 of 62 Appendix C (Page 1 of 4)
CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)
Date Toda INITIALS NOTES
- 1) Use page 1 of this appendix when using VCT MAKEUP CALCULATION program in REACTINW, otherwise use pages 2 and 3 when performing Hand Calculations.
- 2) The computer code named REACTINW (VCT MAKEUP CALCULATION) when used from the Y: server is a verified and validated program. The methodology used is based on the equations:
V1C1 + V2C2 V3C3 & Vi + V2 = V3 Where: V is the volume flow rates of water and acid going into and out of the Boric Acid Blender and C is the boric acid concentration of the flow streams.
1.0 REACTINW VCT MAKEUP CALCULATION
[1) OBTAIN the following data for input to the REACTINW program:
[1.1] Current RCS Boric Acid Concentration. 1020 PPM
[1.2] Current BAT Boric Acid Concentration. 6820 PPM
[1 .3] B-i 0 Depletion Value from Reactivity Management Briefing Sheet 0 PPM
[1 .4] Current VCT Level 18
[i .5] Desired VCT Level 23 %
[2] RUN REACTINW calculation VCT Makeup Calculation. S71
[2.1] PRINT the output file:
VCT MAKUP INTEGRATOR SETTINGS CALCUALTION SZ4
[3] SIGN and DATE output sheets.
[4] OBTAIN independent verification by an SRO on output sheets. IIS9V
NRC Evaluator Sheet B REACTW - VERS WB3.2J VCT MAKEUP INTEGRATOR SETTINGS CALCULATION WATTS BAR UNIT 1 CYCLE 9 INPUT DATA
[1] CURRENT RCS BORIC ACID CONCENTRATION 1020 PPM
[2] CURRENT BAT BORIC ACID CONCENTRATION 6820 PPM
[3] B-10 DEPLETION VALUE 0 PPM
[4] CURRENT VCT LEVEL 18 %
[5] DESIRED VCT LEVEL 23 %
CALCULATION OUTPUTS
[1] B-10 CORRECTED BORON CONCENTRATION 1020 PPM
[2] VCT ADDITION VOLUME 97 GALS
[3] TOTAL FLOW RATE 82.3 GPM CALCULATION CHECK QUANTITIES [1] AND [2] BELOW SHOULD BE APPROXIMATELY THE SAME
[1] VCT ADDITION VOLUME 97 GALS
[2] ( 14 + 83 )
(BA INTG SETTING + PW INTG SETTING)
TOTAL INTEGRATOR SETTING 97 GALS INPUT DATA
[1] BA BATCH COUNTER 14 GALS (1-FQ-62-139) [1-M-6]
[2] BATO BLENDER 30.8%
(1-FC-62-139) [1-M-6]
[3] BA TO BLENDER FLOW 12.3 GPM (1-FI-62-139) [1-M-6]
[4] PW BATCH COUNTER 83 GALS (1-FQ-62-142) [1-M-6]
[5] PW TO BLENDER 3 5.0%
(1-FC-62-142) [1-M-6]
[6] PW TO BLENDER FLOW 70.0 GPM (1-FI-62-142) [1-M-6]
9 7tda PERFORMER DATE
- 9 7oda IV/SRO DATA
Rev7 PAGE 1 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 TRANSFER CONTAINMENT SPRAY SUCTION TO RHR CONTAINMENT SUMP PER ES-1.3
Rev 7 PAGE 2 OF 13 Watts Bar Nuclear Plant 3-OT-J PM R070 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial Issue. Replaces JPM #ES-i .2-2 8/26/92 ALL 1 DELETE KNOWLEDGE QUESTIONS 4/2/93 3,4 REFLECT PROCEDURE REVISION 2 REFLECT PROCEDURE REVISION 11/20/95 4-10 3 Reflect procedure revision from Rev 6 9/25/97 ALL Albert V.
to Rev 8. Made time without spray White flow time critical. Added admin info, changed titles of ASOS to US, added cautions from procedure, provided step numbers from procedure.
4 Incorporated pen & ink changes which 11/20/99 ALL Albert V.
added information to turnover sheet White that RWST level has just reached 8%.
Made performance step 12 critical since one valve must be open.
Clarified when to begin 120 second time period for critical portion of this JPM. Revised K/A values to Rev 2 of NUREG 1122, updated procedure references, Revised simulator setup instructions.
5 Added procedure step numbers to 10/i 6/01 ALL Albert V.
Performance Steps, corrected step White number referenced on initial conditions, changed performance step 12 from critical to not critical. Revised procedure step numbers to reflect Rev 10 of ES-1.3.
6 Revised JPM to reflect rev 13 of ES- 08/05/03 ALL A. V. White 1.3 which deleted one step from JPM and added some step numbers.
7 Revised JPM to reflect rev of ES-i .3 03/i 3/08 D.L.Hughes and changed Time Critical step to begin when CTMT Spray Pumps are secured. Revised K/A reference.
Revised initial conditions to have RWST at i0%, this adds an additional critical ster
Rev 7 PAGE 3 OFi3 Watts Bar Nuclear Plant 3-OT-J PM R070 EVALUATION SHEET Task: TRANSFER CONTAINMENT SPRAY SUCTION TO RHR CONTAINMENT SUMP PER ES-1.3 Alternate Path: N/A Facility JPM #: 3-OT-JPMRO7O Rev 7 K/A Rating(s): 026A4.Oi CSS controls [Importance RO/SRO 4.5/4.3]
TASK STANDARDS: Steps 21 through 24 of ES-i .3 have been correctly performed Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
ES-1.3, Transfer to RHR Containment Sump (REV.17)
Task Number: RO-1 13-ES-i .3-001 APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 6, 7, 8 VIidtinri Time: 7 mm. Time Critical: YES Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME -- SIGNATURE DATE COMMENTS
Rev7 PAGE 4 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 SIMULATOR OPERATOR INSTRUCTIONS:
This JPM has been pre-shot in IC # 254. Should IC # 254 be erased or fail to perform as expected then use the following set-up instructions:
a) Initialize to IC-50.
b) Insert mfp thOib @ 100% Severity (Hot Leg Break Loop 2).
c) Acknowledge all alarms and clear motor trip-out white lights d) Stop RCPs.
e) Perform operator actions lAW E-0, and E-1 f) Insert iii sirl4 (Restore power to FCV-63-1).
g) When required, perform transfer to Containment Sump, steps 1 through 20 of ES-1.3 h) Open 1-FCV-70-153, and 156 (CCS to RHR Hx).
i) Close 0-HS-70-197A (SEP HT EXCH Supply) and 1-HS-70-207 (CDWE Supply from HDR 1B) j) Ensure CCS flows and pressures stabilize.
k) Insert ORP ZAOPDI3O42 @ 4 I) Insert ORP ZAOPDI3O43 @ 4 m) Insert ORP ZAOPDI3O44 @ 4 n) Insert ORP ZAOPDI3O45 © 4 o) Insert ORP ZAOPR3O45[1] @ 4 p) Insert ORP ZAOPR3O45[2] © 4 q) Acknowledge all alarms r) Ereeze simulator when RWST level reaches 12% (a minute remains until RWST gets below 8% after going to RUN).
- 2. After performer indicates understanding of task, place simulator in run.
Rev7 PAGE 5 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure clean copy ES-i .3, Transfer to RHR Containment Sump is available.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
AllI Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- A Large Break LOCA has occurred.
- E-0 was entered, transition made to E-1 and then to ES-i .3, where Step 20 has been completed.
- You are the RO.
- The BOP has commenced Appendix C (ES-i .3), ERCW Operation to aligned ERCW for sump recirc operation.
INITIATING CUES:
The Unit Supervisor directs you to transfer the Containment Spray Pumps to the Containment Sump by performing applicable steps 21 thru 24 of ES-i .3.
Notify Unit Supervisor when Containment Spray has been re-established.
NOTE: PART OF THIS TASK IS TIME CRITICAL.
Rev7 PAGE 6 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 START TIME:
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD STANDARD: A copy of ES-i .3, Transfer to RHR Containment Sump is obtained. _SAT COMMENTS:
UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
CAUTION STEP 2
- The containment spray pump MUST stay aligned to the RWST UNTIL the RWST level is less than 8% to ensure sufficient sump inventory for spray pump operation. .SAT
- If containment pressure is greater than or equal to 2.0 psig, the containment spray pump suction must be aligned and pump restarted within 120 seconds.
Performer reads cautions and abides by requirements. .UNSAT STANDARD:
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE7OF13 Watts Bar Nuclear Plant 3-OT-J PM R070 Simulator Operator Commence actions to:
Q ENSURE ERCW aligned for sump recirc operation:
[21] ALIGN cntmt spray RWST suction:
STEP 3:
[21.a] CHECK spray pumps RUNNING.
SAT Containment spray pumps verified to be running by red STANDARD:
indicating lights or amp meters.
COMMENTS:
UNSAT STEP 4:
[21 .b] CHECK RWST level less than 8%.
Performer observes that RWST level is not yet less than 8%, SAT STANDARD:
goes to E-1 .3 step 21 .b RNO.
COMMENTS: UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 8 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 5* [21 .b RNO]
Critical Ste I WHEN RWST level less than 8%, THEN PERFORM Substep 21c and ALIGN cntmt spray pumps to cntmt sump.
SAT GO TO Step 26.
Performer monitors RWST level (since it is so close may not go STAN DARD to Step 26), and when level is less than 8%, THEN PERFORM Substep 21c
_UNSAT Evaluator Note: Critical portion of this JPM step is that the performer waits until RWST level is less than 8% prior to performing Step 21.c COMMENTS:
STEP 6: Critical Step
[21 .c]
STOP both cntmt spray pumps, and PLACE in PULL TO LOCK.
STANDARD: Control Room Hand switches for A and B Cntmt Spray Pumps in SAT PU LL-TOLOCK position. (1 -HS-72-1 OA & 1 HS-72-27A).
Evaluator Note: When the 2 Cntmt Spray Pump is placed in PTL, begin 120 second timer Clock Time: mm/sec UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 9 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 7: Critical Step
[21 .d]
ISOLATE cntmt spray suction from RWST:
- CLOSE 1-FCV-72-22.
- CLOSE 1 -FCV-72-21.
SAT STANDARD: i-HS-72-2iA and i-HS-72-22A placed in the closed position and valves indicate closed.
COMMENTS: UNSAT STEP 8:
[22] ENSURE ERCW aligned for sump recirc operation:
REFER TO Appendix C (ES-i .3), ERCW Operation.
SAT Evaluator Que: STATE to the performer that the BOP operator has completed the ERCW system alignment per Appendix C.
Performer has verified Appendix C of ES-i .3 completed.
STANDARD: UNSAT COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 10 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 9: Critical Step
[23] ALIGN cntmt spray sump suction:
- a. OPEN i-FCV-72-44 cntmt spray suction from cntmt sump.
SAT STANDARD: i-HS-72-44A placed in open and valve indicates open.
COMMENTS:
UNSAT STEP 10: Critical Step
[23] ALIGN cntmt spray sump suction:
- b. OPEN i-FCV-72-45 cntmt spray suction from cntmt sump.
SAT STANDARD: i-HS-72-45A placed in open and valve indicates open.
COMMENTS:
UNSAT STEP 11:
[24] MONITOR cntmt press less than 2.0 psig.
Performer uses any of the following indications to determine SAT STANDARD:
that cntmt press is greater than 2.0 psig, and proceeds to the RNO column of ES-i .3. Step 24
- PDI-30-42
- 1-PDI-30-43
- i-PDI-30-44
- i-PDI-30-45 UNSAT
- i-PR-30-45 COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 11 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 12: Critical Step
[25 RNO] IF cntmt press greater than or equal to 2.0 psg, THEN:
- a. START cntmt spray pumps. __SAT STANDARD: Cntmt spray pumps started with 1-HS-72-27A and 1-HS-72-10A.
Evaluator Note: When the 1 Cntmt Spray Pump is started, stop the 120 second timer UNSAT Clock Time: mm/sec st 1
Critical Step is to have started the Cntmt Spray Pump prior to 120 seconds.
COMMENTS:
STEP 13:
[RNO 25.bJ OPEN discharge valves 1-FCV-72-2 and 1-FCV-72-39. SAT STANDARD: Discharge valves verified opened by RED lights on 1-HS-72-2A and 1 -HS-72-39A.
COMMENTS: UNSAT STEP 14:
[RNO 25.c] ENSURE spray flow on 1-Fl-72-34 and 1-Fl 13.
SAT STANDARD: Performer ensures spray flow indicated on 1 -Fl-72-34 and 1-Fl-72-13.
COMMENTS:
UNSAT
- Ita!icized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev7 PAGE 12 0F13 Watts Bar Nuclear Plant 3-OT-J PM R070 STEP 15: [13] Notify Unit Supervisor that Containment Spray has been transferred to Containment Sump..
EXAMINER When notified, acknowledge the report, notify performer that SAT CUE: the task is complete. End task COMMENTS:
UNSAT END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- A Large Break LOCA has occurred.
- E-0 was entered, transition made to E-i and then to ES-i .3, where Step 20 has been completed.
- You are the RO.
- The BOP has commenced Appendix C (ES-i .3), ERCW Operation to aligned ERCW for sump recirc operation.
INITIATING CUES:
The Unit Supervisor directs you to transfer the Containment Spray Pumps to the Containment Sump by performing applicable steps 21 thru 24 of ES-i .3.
Notify Unit Supervisor when Containment Spray has been re-established.
NOTE: PART OF THIS TASK IS TIME CRITICAL.
REV. 4 PAGE 1 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A RAISE COLD LEG ACCUMULATOR LEVEL PER SOI-63.O1
REV. 4 PAGE 2 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A NUCLEAR TRAINING REVISION/USAGE LOG Rev # Date Description of changes Pages Affected Reviewed By 0 10/16/01 Initial Issue. ALL A. V. White 11/01/01 Revised format, made changes to reflect rev ALL A. V. White 28 of SOI-63.01. Revised simulator setup instructions and turnover information.
2 11/04/02 Updated procedures referenced, corrected 2, 3, 5, 6, 13, 15 A. V. White typo, revised task assignment sheet, and removed cue from JPM step 3 which was not needed.
3 08/03/07 Incorporated pen & ink change that corrected ALL A. V. White minor wording change due to procedure revision. Added EIN to evaluation sheet.
Updated procedures referenced which changed substep numbers but did not change task performance or its evaluation.
4 03/20/08 Incorporated pen & ink change that corrected ALL D.L.Hughes minor wording issues. Changed substep numbers but did not change task performance or its evaluation.
REV. 4 PAGE 3 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A EVALUATION SHEET Task: Raise Cold Leg Accumulator Level Per SOl-63.O1 Alternate Path: N/A Facility JPM #: 3-OT-JPMRO27A Rev 4 K/A Rating(s): O06-A4.O1 [4.1/3.9] 006-A1.13 [3.5/3.7] 2.2.21 [3.1/3.2]
Task Standard: Cold Leg Accumulator #1 water level raised to normal level (Annunciator Window 131 -A Dark) and system lineup re-established per SOl-63.O1.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOI-63.O1 Safety Injection System Rev.42.
Task Number:: RO-063-SOI-63-OO1 APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 4, 6, 7 Validation Time: 14 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
REV. 4 PAGE 4 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to 259
- 2. Acknowledge all alarms. Ensure Source Range Audible Count is audible in horse shoe.
- 3. Place the Simulator in FREEZE.
- 4. Place the Simulator to RUN when the performer indicates an understanding of the task.
- 5. This JPM has been pre-shot in IC #259. Should IC # 259 be erased or fail to perform as expected then use the following set-up instructions:
Initialize to IC-i 29, go to RUN, cooldown the RCS in accordance with GO-6 to establish conditions where RCS is approximately 1400 psig and temperature 500 °F with CLAs in service.
Ensure Source Range Audible Count audible in horse shoe.
To lower level in CLA-1 to below level alarm setpoint:
- Enter REMOTE FUNCTION rfp sirlO to OPEN drain to RCDT 63-618.
- Manually OPEN 1-63-1 30A on 1 M6.
- When either the CLA #1 Low level alarm 131-A Alarms or CLA #1 Low pressure 131-B Alarms then CLOSE 1-63-130A.
Ensure 1-HS-63-23, 71A, 84, and 64A in the CLOSE position.
Freeze simulator until performer indicates understanding of task.
SIMULATOR OPERATOR INSTRUCTIONS:
NONE
REV. 4 PAGE 5 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A Tools/Equipment/Procedures Needed:
Ensure clean copy of SOl-63.O1 in the simulator copies on the Simulator Floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit is Mode 3, RCS Heatup is in progress.
Cold Leg Accumulator # 1 Pressure Hi/Lo and Level annunciation are lit.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor directs you to perform the proper instruction to return CLA #1 water level to normal, utilizing the 1A Safety Injection Pump.
SOI-63.O1 Section 5.1 to fill and vent 1A Safety Injection Pump is complete.
You are to notify the Unit Supervisor when the instruction is complete.
REV. 4 PAGE 6 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PMRO27A START TIME:
STEP 1: Obtain a copy of the procedure.
SAT STANDARD: A copy of SOI-63.01 Section 8.3.1 has been obtained.
EXAMINERS CUE: After the performer has demonstrated the method of obtaining the correct instruction, the evaluator can UNSAT provide a copy of the instruction.
COMMENTS:
CAUTION: Adding water to more than one CLA at a time while they are required to be operable places the plant outside design basis. This section is to be used to add water to any selected single CLA. If more than one CLA needs water, separate evolutions must be performed.
STEP 2: [STEP 1] ENSURE Sect 5.1, To Fill & Vent SI Pmps and Piping, COMPLETE. SAT STANDARD: No action required. (Performer proceeds to next step)
COMMENTS: Fill & Vent completion is identified on the candidate cue sheet. UNSAT STEP 3: [STEP 2] IF RCS pressure is 1000 psig, THEN ENSURE 1-FCV-63-118, CLACCUM 1 OUTLET, CLOSED. SAT STANDARD: Performer determines that step in Not Applicable and proceeds to the next step.
UNSAT COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 7 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A CAUTION If RCS is 1650 psig or less, ALL SIP injection flow paths must be disabled to prevent inadvertent RCS injection. If 1-FCV-63-152 is closed, then SI Pmp A is the only pump that can be used to fill CLA.
STEP 4: [STEP 3] IF RCS 1650 psig or less, AND SIP A is to be used CRITICAL to fill CLA 1, THEN CLOSE 1 -FCV-63-1 52, SI PMP A TO CL STEP 1-2-3-4 [1-M-6].
SAT STANDARD: 1-HS-63-152A is placed to the close position and green valve position indicating light is verified ON, red valve position light OFF on respective valve hand switch. Step is critical to prevent injection to RCS when SI pump is started. UNSAT COMMENTS:
CAUTION In Mode 4, 5, 6 with the Rx Vessel Head ON, before starting SI Pmp A, 1-FCV-63-1 52 and -156 must be closed, with Hold tags on the handwheels and breakers (Refer to T.S. 3.4.12).
STEP 5: [STEP 4] IF in Mode 4, 5, 6 with SIP lA-A is to be used with Rx Vessel Head ON, THEN
[4.1] ENSURE 1-FCV-63-156, SI PMP A TO HL 1 & 3 [1-M-6],i5CLOSED. SAT
[4.2] ENSURE 1-BKR-63-156, SI PUMP lA-A HOT LEG 1 &
3 INJECTION [1A1-A, C/13A], is OFF & TAGGED.
[4.3] ENSURE 1-BKR-63-152, SIP lA-A COLD LEG INJ FLOW CNTL [1A1-A, C/12E], is OFF & TAGGED. UNSAT
[4.4] ENSURE SAFETY INJECTION PUMP lA-A [6.9kV SD Bd lA-A/Cl 5], Breaker racked UP and Closing Spring CHARGED.
STANDARD: No action required. Unit is in Mode 3. The performer N/As the step.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 8 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A CAUTION 1-FCV-63-22, 156, 157 MUST be closed with HOLD Tags on handwheels and bkrs in Modes 4, 5, 6 with vessel head on when running SIP B. (See T.S.
3.4.12)
STEP 6: [STEP 5] IF in Mode 4, 5, 6 with SIP lB-B is to be used with Rx Vessel Head ON, THEN
[5.1] ENSURE i-FCV-63-22, SI PUMPS CL Injection is CLOSED. SAT
[5.2] VERIFY 1 -BKR-63-22, (1 B1 -B, C/il D) Tagged OPEN with Hold Tag.
[5.3] ENSURE l-FCV-63-156, SI PUMP 1A HL injection CLOSED. UNSAT
[5.4] VERIFY l-BKR-63-156, (1A1-A, C/13A) Tagged OPEN with Hold Tag.
[5.5] ENSURE 1-FCV-63-157, SI PUMP lB HL injection CLOSED.
[5.6] VERIFY i-BKR-63-l57, (lBl-B, C/13B) Tagged OPEN with Hold Tag.
[5.7] ENSURE 1-FCV-63-152, SI PUMP A TO CL 1-2-3-4 OPEN.
[5.8] ENSURE 1 -FCV-63-l 53, SI PUMP B TO CL 1-2-3-4 OPEN.
[5.9] ENSURE SAFETY INJECTION PUMP lB-B [6.9kV SD Bd lB-B/C15], Breaker racked UP and Closing Spring CHARGE.
STANDARD: No action required. Unit is in Mode 3. The performer N/As the step.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
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REV. 4 PAGE 10 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A STEP 9: [STEP 8] PERFORM the following (N/A pump not selected): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNI D SI PMP lA-A (ECCS) 1-M-6 START 1-HS-63-1OA SI PMP lB-B (ECCS) 1-M-6 START 1-HS-63-15A STANDARD: Hand switch 1-HS-63-1OA has been placed to START position SAT and lA-A pump started. Step is critical to provide flow to Accumulator.
EVALUATOR NOTE: Starting of the pump should be announced on P.A. UNSAT If asked as an AUO for local condition of the pump, state that the pump is ready for a start and all personnel are clear.
COMMENTS:
STEP 10: [Step 9] OPEN 1 -FCV-63-l 15, MAKEUP TO CL ACCUM 1, CRITICAL
[l-M-6]. STEP STANDARD: 1 -HS-63-l 1 5A has been placed in the OPEN position. Step is critical to establish flow path to accumulator. SAT COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 11 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A NOTE 1-Ll-63-129, CLA 1 LEVEL [1-M-6], is preferred to monitor level due to faster response than 1-Ll-63-119.
STEP 11: [STEP 10] WHEN CLA is at desired level (Alarm 131-A, CL CRITICAL ACCUM 1 LEVEL HI/LO, not LIT), THEN PERFORM the STEP following:
NOMENCLATURE LOCATION POSITION UNI D MAKEUP TO CL ACCUM 1 1-M-6 CLOSED 1-FCV-63-1 15 CKV TEST LINE TO HUT 1-M-6 CLOSED 1-FCV-63-71 TEST LINE (1 -XS-63-1 00) ISOL 1-M-6 CLOSED 1-FCV-63-187 CLA FILL FROM SI PMPS 1-M-6 CLOSED 1-FCV-63-23 STANDARD: The level has been increased until neither HI/LO alarm on SAT Annunciator 131 -A is LIT, THEN 1 -HS-63-1 1 5A, 1 -HS-63-71 A, 1-HS-63-187, & 1-HS-63-23 have been placed in the CLOSED position. This step is critical isolate flow path to accumulator UNSAT EVALUATOR NOTE: Annunciator level alarm setpoints are HI 7970 gal, LO 7660 gal and pressure alarms Hi 660 psig, Lo 610 psig COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 12 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A STEP 12: [STEP 11] ENSURE SI pump has operated for greater than CRITICAL 20 minutes, THEN PERFORM the following (N/A pump not STEP selected):
NOMENCLATURE LOCATION POSITION UNID SI PMP lA-A (ECCS) 1-M-6 STOP 1-HS-63-1OA SI PMP lB-B (ECCS) 1-M-6 STOP 1-HS-63-15A STANDARD: Hand switch 1 -HS-63-1 OA has been placed to STOP position SAT and lA-A SI pump is Stopped. This step is critical to return SI pump to normal after fill.
- CUE: After performer has determined time to take pump off, UNSAT state that the time period has elapsed.
COMMENTS:
NOTE Step 8.3.1[12] or 8.3.1[13] may be N/Ad based on SIPs operability requirements.
(JPM steps 13 & 14.)
STEP 13: [STEP 12] ENSURE the following (N/A pump NOT selected): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNI D SI PMP lA-A (ECCS) 1-M-6 A AUTO 1-HS-63-1OA SI PMP 1 B-B (ECCS) 1 -M-6 A AUTO 1 -HS-63-1 5A STANDARD: Hand switch 1-HS-63-1OA has been placed to A AUTO SAT position. This step is critical to assure ES Standby lineup.
COMMENTS:
UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 13 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A STEP 14: [STEP 13] PERFORM the following (NIA pump NOT selected):
NOMENCLATURE LOCATION POSITION UNID SI PMP lA-A (ECCS) 1-M-6 PULL-TO-LOCK 1-HS-63-1OA SI PMP lB-B (ECCS) 1-M-6 PULL-TO-LOCK 1-HS-63-15A STANDARD: Performer N/As this step. SAT COMMENTS:
UNSAT STEP 15: [STEP 14] IF 1-FCV-63-152, was closed in step 8.3.1[3], CRITICAL THEN OPEN 1-FCV-63-152, SI PMP A TOOL 1-2-3-4 [1-M-6] STEP (N/A in Mode 4, 5, 6.)
SAT STANDARD: 1-HS-63-152A is placed to the open position and red valve position indicating light is verified ON, green valve position indicating light is verified OFF. Step is critical to realign SI flow path to RCS. UNSAT COMMENTS:
STEP 16: [STEP 15] IF 1-FCV-63-1 18 was closed in step 8.3.1[2],
THEN OPEN 1 -FOV-63-1 18, CL ACCUM 1 OUTLET if desired.
STANDARD: No action required. Valve was not closed. The performer N/As the step. SAT COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 PAGE 14 OF 15 WATTS BAR NUCLEAR PLANT 3-OT-J PM R027A NOTE CLA 1 press can be read on 1-PI-63-126 or 128.
STEP 17: [STEP 16] VERIFY CLA pressure in desired range (Alarm 131-B, CL ACCUM 1 PRESS Hl/LO, not LIT).
STANDARD: The CLA pressure has been checked to be between > 610 psig AND < 660 psig. SAT
- CUE: If pressure >660 psig and performer mentions, acknowledge and state that the CLA will be vented following completion of this procedure. UNSAT EVALUATOR NOTE: Annunciator alarm setpoints are HI 660 psig, LO 610 psig)
COMMENTS:
STEP 18: Notifies Unit Supervisor that fill of CLA #1 has been completed.
SAT STANDARD: Performer notifies Unit Supervisor that CLA #1 has been filled.
- CUE: As Unit Supervisor acknowledge report using repeat back. UNSAT COMMENTS:
END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 4 WATTS BAR NUCLEAR PLANT CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Unit is Mode 3, RCS Heatup is in progress.
Cold Leg Accumulator # 1 Pressure Hi/Lo and Level annunciation are lit.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor directs you to perform the proper instruction to return CLA
- 1 water level to normal, utilizing the 1A Safety Injection Pump.
SOI-63.O1 Section 5.1 to fill and vent 1A Safety Injection Pump is complete.
You are to notify the Unit Supervisor when the instruction is complete.
REV7 PAGE 1 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 TASK TITLE: ESTABLISH RCS BLEED PATHS PER FR-H.1 WRITTEN BY:
VALIDATED BY:
APPROVED BY:
(OPERATIONS TRAINING)
CONCURRENCE:
(OPERATIONS REPRESENTATIVE)
REV.7 PAGE 2 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 NUCLEAR TRAINING REVISION/USAGE LOG Rev # Date Description of changes Pages Affected Reviewed By 0 10/11/96 Initial Issue. Initial issue replaces JPM ALL
- 093, reflects procedure rev 11 1 09/25/97 Added Cues and standard to Pert Step 6 2, 4, 7, 8 for removing Hold Notices from valves, updated procedure reference, removed termination cue.
2 11/08/99 Revised K/A Values to reflect Rev 2 of 2, 3, 4, 7, 8 A. V. White NUREG 1122, updated procedure references, corrected typos, reworded JPM Step 9 to reflect procedure wording.
No intent changes were made.
3 10/17/01 Minor changes to simulator setup A. V. White instructions to remove and reinstall hold order tags, added start/stop time slots, added caution statement prior to step 18 of FR-H.1, changed font.
4 03/26/02 Revised due to Rev 14 of FR-H.1 which All A. V. White added several steps. Revised Cue concerning HPFP Spool Pieces and when Cue is given. Shortened estimated completion time from 19 minutes to 15 minutes.
5 08/05/03 Revised to reflect Rev 15 of FRH.1. ALL A. V. White 6 07/17/06 Revised to current format. No change of All D. Rector intent made.
7 08/08/07 Revised to incorporate Rev 16 and 17 of All A. V. White FR-H.1 which changed order of task performance.
8 04/29/08 Revised to add Loss of Offsite and Loss of 1 B 6.9 Ky Shutdown Board to change to an Alternate Path JPM.
REV. 7 PAGE 3 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PMRO93 EVALUATION SHEET Task: Establish RCS Bleed path per FR-H.1 Alternate Path: Yes. Failure of one of the two PORVs to open requires use of the Reactor Vessel Head Vent System to create adequate vent of RCS as bleed path.
Facility JPM #: 3-OT-JPMRO93 Rev 7 K/A Rating(s): 054AK3.05 [4.6/4.7] 054AK3.04 [4.4/4.6]
E05 EA1.l [4.1/4.0] EO5EA2.2 [3.7/4.3]
TASK STANDARDS: Bleed and feed cooling of the RCS is established per Steps 18 through 20 of FR-Ri.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
FR-Ri Revision 17 Task Number: RO-1 13-FR-H.i-OOi APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 4, 6, 7, 8 VIidtinn Time: 15 mm. Time (ritirI No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
REV.7 PAGE 4 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 SIMULATOR OPERATOR INSTRUCTIONS:
Initialize to IC #269 and over ride switch check for Pzr PORV 68-340.
Acknowledge all alarms Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
When asked to restore power to RV Head Vents, rfp rcrO6 Note: This JPM had been preshot in IC #269. The following steps are the setup instructions if needed:
Initialize the simulator in IC #50.
Place 1 A-A and 1 B-B AFW pumps in P-T-L.
IMF FWO7A 1A MDAFW Pump Trip IMF FWO7B 1 B MDAFW Pump Trip IMF EDO1 Loss of Offsite Power IMF EDO6B 1 B 6.9 Ky Shutdown Board Trip mn fwr27 (Overspeed Trip of TDAFWP) ior zdihs68HS34OA CLOSE Keeps PZR PORV from opening.
Perform E-0 through Appendix A.
Stop one hotwell pump.
Close High Pressure Feedwater Heater Outlet Isolation Valves.
Perform FR-H.1 through step 17 Allow simulator to run until all S/G levels < 26% wide range.
Then freeze simulator.
After JPM performance Place Hold Order Tags on 1-HIC-68-394 & 395.
REV.7 PAGE 5 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 SIMULATOR OPERATOR INSTRUCTIONS:
Tools/EguipmentlProcedures Needed:
Clean copies of FR-Hi in all ERG books on simulator floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating cues and reports on other actions when directed by you.
Ensure you indicate to me when you understand your assigned task.
To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A Loss of Offsite Power has occurred.
The unit was at 100% RTP when a MEW line break caused a Rx trip.
A loss of 1 B 6.9Kv Shutdown Board also occurred.
All AFW pumps were removed due to cavitation, operators have been dispatched.
Wide range levels on all SGs are < 26%.
Maintenance has been notified to install spool pieces to #3 and #4 S/Gs per MI-i 7.18 and AOl-7.06 is in progress.
You are the Operator at the Controls INITIATING CUES:
The Unit Supervisor directs you to establish bleed and feed per FR-H.1 Step 18 through 20.
You are to notify the US when the steps have been completed.
REV.7 PAGE 6 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 START TIME:
STEP 1: Obtain the appropriate procedure.
STANDARD: FR-H.1 is obtained. SAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can UNSAT proWde a copy of the instruction COMMENTS:
CAUTION: Steps 18 through 20 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed.
STEP 2: 18. ACTUATE SI. CRITICAL STEP STANDARD: Safety Injection is initiated by 1-HS-63-133A or 1-HS-63-1331 Step is critical to ensure necessary equipment running SAT for inventory control of the RCS.
COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.7 PAGE 7 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PMRO93 STEP 3: 19. ESTABLISH at least one of the following RCS feed paths: .SAT
- At least one charging pump injecting thru BIT, OR UNSAT
- At least one SI pump running with its injection valves open.
STANDARD: At least one charging pump is checked to be running and 1-FI-63-170 is determined to indicate flow or At least one SI pump is checked to be running and injection valve open by red light on 1 -HS-63-22A COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 7 PAGE 8 OF 13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 CAUTION
- When the reactor vessel head vent block valve is opened, the throttle valve will cycle open and closed.
- Slowly opening (5 seconds stroke time) the head vent valve will prevent water hammer and pipe damage.
STEP 4: 20. ENSURE adequate RCS bleed path: Critical Step
STANDARD: PORV Block valves are verified to be open by observing red indicating lights lit on 1 -HS-68-332A and 1 -HS-68-333A AND Performer: SAT
- 1) opens PORV 1 334 with 1 -HS-68-334A
- 2) determines that PORV 1 340 will NOT open by green indicating light on 1-HS-68-340A and 3 transitions to the RNO column. UNSAT Step is critical because the relief capacity of one PORV is inadequate to pass sufficient fluid to depressurize the RCS and allow adequate core cooling via inventory addition. Transition to RNO establishes alternate!
additional depressurization path.
COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 7 PAGE 9 OF 13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 Note: RFP RCRO6 to ON must be inserted by simulator operator after request is made to place power on the Rx Head Vent valves in next step. Console operator must remove hold notices from 1-HS-68-394, -395, and 1-HIC-68-396, -397)
NOTE To Evaluator: The following steps 5 through 8 are RNO for Step 20.
CRITICAL STEP 5: RNO 20. PERFORM the following: STEP
- 1) RESTORE power to head vents:
- PLACE 1 -SW-68-394-A disconnect switch to ON
[1 25V Vital Batt Bd Rm I].
- PLACE 1 -SW-68-395-B disconnect switch to ON
[1 25V Vital Batt Bd Rm II].
STAN DARD: US/AUO is requested to place power on reactor vessel _SAT head vent valves.
Tagging Supervisor is contacted to lift hold notices from hand switches 1-HS-68-394 & 395, and from controllers 1-HIC-68-396 & 397. UNSAT CUE: Role play as Tagging Supervisor and acknowledge request to lift or pick up hold notice notices from Rx Vessel Head Vent Blocks and Controllers.
CUE: Role play as US/AUO and acknowledge request, then report back that power is restored to the head vents.
Step is critical because power will not be restored without the request being made. Unless power is restored, the valves cannot be opened and no bleed path can be established.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.7 PAGE 10 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 Critical Step STEP 6: 2) OPEN all reactor vessel head vent and block valves.
STANDARD: The performer opens the vent isolation valves by using 1 -HS-68-394 & 1 -HS-68-395 and the vent control valves by SAT using 1-HIC-68-396 & 1-HIC-68-397.
Opening the vent valves establishes the RCS bleed path and is therefore critical. UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.7 PAGE 11 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PM R093 NOTE TO EVALUATOR: Give the following cue before performer performs the next step:
CUE: Spool piece installation has been completed per MI-i 7.18 for SG SG #3 and SG #4.
Critical Step STEP 7: 3) OPEN ERCW valves to AFW pump suction, OR ALIGN HPFP to at least one Intact S/G USING the following:
- MI-17.18, Flood Preparation HPFP System Spool Pieces.
UNSAT STANDARD: 1-HS-3-116AIA, 1-HS-3-126A1A, and either 1-HS-3-136A1A, 1-HS-3-179A1A or both are turned to the open position or Performer refers to AOl-7.06 for alignment of HPFP water to the Steam Generators.
Step is critical to ensure a source of water is established to at least one intact S/G.
CUE: When performer refers to AOI-7.06, state that another operator will complete AOl-7.06 for establishing flow to SGs #3 and #4.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV.7 PAGE 12 0F13 WATTS BAR NUCLEAR PLANT 3-OT-J PMRO93 CRITICAL STEP 8: 4) DEPRESSURIZE at least one Intact S/G to STEP atmospheric press with S/G PORV.
SAT STANDARD: The PORV on at least ONE steam generator is opened by placing hand switch to open or PlC to 100% to depressurize the S/G to atmospheric pressure.
__UNSAT Step is critical because it ensures at least one SIG which can be filled from a low pressure source to supply a heat sink for the RCS.
COMMENTS:
STEP 9: Notify the Unit Supervisor that bleed and feed has been established. __SAT STANDARD: The Unit Supervisor is notified that bleed and feed has been established.
UNSAT Cue: Acknowledge the report using repeat back. State we will stop here.
COMMENTS:
END OF TASK TIME STOP:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
REV. 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
A Loss of Offsite Power occurred.
The unit was at 100% RTP when a MEW line break caused a Rx trip.
A loss of 1-B 6.9 Ky Shutdown Board Has also occurred.
All AFW pumps were removed due to cavitation, operators have been dispatched.
Wide range levels on all SG5 are < 26%.
Maintenance has been notified to install spool pieces to #3 and #4 S/Gs per MI-i 7.18 and AOl-7.06 is in progress.
You are the Operator at the Controls.
INITIATING CUES:
The Unit Supervisor directs you to establish bleed and feed per FR-Hi Step 18 through 20.
You are to notify the Unit Supervisor when the steps have been completed.
RevO Pagelofl5 Watts Bar Nuclear Plant 3-OT-JPMR1 74 CALIBRATE POWER RANGE NUCLEAR INSTRUMENTATION WRITTEN BY:
VALIDATED BY:
APPROVED BY:
(OPERATIONS TRAINING)
CONCURRENCE:
(OPERATIONS REPRESENTATIVE)
RevO Page2ofl5 Watts Bar Nuclear Plant 3-OT-JPMR1 74 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 New revision created from SQN JPM 04/25/08 All DW LeGrand 22-AP2.
RevO Page 3 of 15 Watts Bar Nuclear Plant 3-OT-JPMR1 74 EVALUATION SHEET Task: Calibrate Power Range Nuclear Instrumentation Alternate Path: None Facility JPM #: 3-OT-JPMR174 RevO K/A Rating(s): Al .01 (3.5 3.8); A4.02 (3.9 3.9)
TASK STANDARDS:
- 1) Each channel of Power Range instrumentation (on the respective Power Rang A /drawer) will indicate within acceptance criteria tolerances of the calorimetric.
- 2) The unit is not tripped by a Power Range neutron flux rate trip.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
1 -Sl-92-1, NIS Daily Comparison Task Number: APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 4, 6, 7, 8 IIr4tq Time: 25 mm. Time Cr.fii No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
RevO Page4ofl5 Watts Bar Nuclear Plant 3-OT-JPMR1 74 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to IC #271.
- 2. Acknowledge all alarms.
- 3. Ensure that all PRNIs are reading within the ranges prescribed in 4.c. and 4.d.
- 4. Ensure that all PRNIs potentiometers are locked.
- 5. NOTE: This JPM has been preshot in a 75% RTP IC. The following are the setup instructions if needed:
- c. Ensure PRNI-42 and 44 are between 75% and 75.5%.
- d. Ensure PRNI-41 and 43 are between 76.8% and 77.5%.
- e. Adjust the indications to ensure that the Power Range Channel Deviation annunciator is not lit.
- f. Acknowledge all alarms.
- 4. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.
- 5. After performer indicates understanding of task, place simulator in run.
SIMULATOR OPERATOR INSTRUCTIONS:
No specific instructions are provided.
RevO Page5ofl5 Watts Bar Nuclear Plant 3-OT-JPMR1 74 EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Provide a marked-up copy of 1 -SI-92-1 (NIS Daily Comparison) to pre-brief the Section 3.0 (Precautions and Limitations), Section 4.0 (Prerequisite Actions) and Section 5.0 (Acceptance Criteria) prior to entering the simulator. The candidate should return the marked-up copy to the evaluator. The copy will be provided to the candidate on entry to the simulator for the task performance.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The unit is at steady state conditions with all NIS channels and LEFM operable. Reactor power and RCS temperature have been stable for 30 minutes.
INITIATING CUES:
You are the CRC and the US has directed you to perform 1-51-92-i.
Section 4.0 of 1-51-92-1 has been completed.
Notify the US when the SI has been completed.
Rev#O PAGE 6 0F10 Watts Bar Nuclear Plant 3-OT-JPM1 74 START TIME:
STEP 1: Obtain the appropriate procedure
.SAT STANDARD: Operator goes to section 6.0 of 1-51-92-1.
COMMENTS:
UNSAT EXAMINERS The evaluator can provide a copy of the instruction.
CUE:
STEP 2: ENSURE Precautions and Limitations in Section 3.0 have been reviewed. SAT STANDARD: Operator reviews Section 3.0 and initials step [1].
COMMENTS:
UNSAT STEP 3: ENSURE Prerequisite Actions in Section 4.0 have been met. SAT STANDARD: Operator reviews Section 4.0 and initials step [2].
COMMENTS:
UNSAT STEP 4: ENSURE TAVG changing less than +/- 0.5 °F in a 15 minute period.
STANDARD: Operator verifies no change in last 15 minutes.
COMMENTS: Operator may use the turnover paper provided, or may use UNSAT a graph or ICS trend to verify TAVG has not changed.
Rev#O PAGE 7 OF1O Watts Bar Nuclear Plant 3-OT-JPM1 74 STEP 5: ENSURE TAVGITREF mismatch is less than +/- 0.5 °F (i.e., TAVG is
+/- 0.5 °F of program). _SAT STANDARD: Operator verifies mismatch is less than +/- 0.5 °F.
COMMENTS: Operator may use the turnover paper provided, or may use a graph or ICS trend to verify TAVG/TREF has not changed. UNSAT Evaluator NOTE: Procedure contains a Note that showed be reviewed for content. There may be some confusion over 1) that states to perform steps 6.2[1] through 6.2[4] concurrently. The intent is to perform the steps consecutively in a timely manner.
STEP 6: DETERMINE calorimetric power percent by ONE of the CRITICAL methods below: STEP A. U1127TM the 10 minute average calorimetric power (based on LEFM calorimetric and 3459 MWth). SAT Calorimetric power (%) = 74.65 %
B. U1254 the 10 minute average calorimetric power (based on Venturi calorimetric and 3411 MWth).
UNSAT Calorimetric power (%) = N/A %
C. Tl-6.0O1, Board Calorimetric performance.
Calorimetric power (%) = N/A %
D. RCS Delta Temperature (i.e. primary calorimetric) from the 10 minute average percent core thermal power Ui 1 27TM when below 15% RTP or from U0485TM.
Calorimetric power (%) = N/A %
AND RECORD as calorimetric power in STep 6.2[3].
STANDARD: Operator determines calorimetric power percent between 74.5% and 74.7% using Ui 127TM.
Operator N/A steps B., C., and D.
Operator records the calorimetric power in the appropriate column of Step 6.2[3] for each PRNI.
COMMENTS: Operator should use [1jA based on the information provided that the LEFM is operable. Operator may incorrectly choose [i]B, [i]C, or [1]D. This will lead to an erroneous adjustment of Power Range Nis.
P&L 3.OL. requires the use of Ui 127TM when LEFM is available.
Rev#O PAGE 8 OF1O Watts Bar Nuclear Plant 3-OT-JPM1 74 STEP 7: RECORD as-found NIS power from the A Channel CRITICAL drawers for each operable NIS Power Range Channel in STEP Step 6.2[3}.
OR USE the average reading each NIS PR Channel from SAT Tl-6.OO1. (N/A inoperable channel.)
STANDARD: Operator records the as-found NIS power in the appropriate column for each PRNI.
COMMENTS: Tl-6.OO1 would be used if a PRNI channel were UNSAT inoperable.
STEP 8: CALCULATE the as found difference AND CRITICAL CHECK whether or NOT the difference is within STEP 2% AND INDICATE by circling YES or NO below:
SAT STANDARD: Operator records the as found difference in the appropriate column for each PRNI.
Operator circles YES for the differences that are less than 2% and NO for the differences that are UNSAT greater than 2%.
COMMENTS: The operator should identify that N-41 and N-43 are greater than 2% and circle NO.
The operator should identify that N-42 and N-44 are less than 2% and circle YES.
POWER RANGE AS-FOUND CALORIMETRIC AS FOUND CHANNEL NIS POWER DIFFERENC CIRCLE ONE POWER (%) E
(%) (%)
N-41 (1-IDWR-92-N41A) YE 770 74.65 2.35 N-41 (1-IDWR-92-N41A) NO 75.5 74.65 0.85 N-41 (1-IDWR-92-N41A) YE NO 77.5 74.65 2.85 N-41 (1 -IDWR-92-N41 A) NO 74.65 0.85 Initials
Rev#O PAGE 9 OF1O Watts Bar Nuclear Plant 3-OT-JPM1 74 Evaluator NOTE: Procedure contains a Note that showed be reviewed by the candidate.
The Note requires an adjustment when an NIS indicated power is 2% greater than calorimetric indicated power. Two of the channels are required to be adjusted by the operator.
The Note allows adjustments when an NIS indicated power is greater than calorimetric indicated power. The channels less than 2% above calorimetric channel may be adjusted by the operator.
STEP 9: IF an adjustment is needed, THEN, PROCEED TO Section 6.3 to adjust the needed NIS Power SAT Range Channel(s); OTHERWISE, PROCEED TO Section 6.4 when no adjustments needed.
STANDARD: Operator determines adjustment is needed to N-41 and N- UNSAT 43.
COMMENTS: The operator may choose to adjust N-42 and N-44 based on Section 3.0 Precautions and Limitations, step 0.
Evaluator NOTE: Procedure contains a Note that showed be reviewed by the candidate. This note is exactly the same as the previous note with one additional note at the end.
STEP 10: OBTAIN SMs Approval to adjust the channels before CRITICAL adjusting: STEP N-41 n Adjust DO NOT Adjust o SAT N-42 o Adjust DO NOT Adjust o N-43 Adjust DO NOT Adjust N-44 Adjust DO NOT Adjust UNSAT EVALUATOR NOTE: When asked, provides cue to candidate that SM approves adjusting NIs as identified.
STANDARD: Operator obtains SMs approval prior to adjustment.
COMMENTS: The operator determines that adjustment shall be made on N-41 and N-42 and checks the Adjust boxes.
The operator may choose to adjust N-42 and N-44 and checks the Adjust boxes for them or may check the DO NOT Adjust boxes.
Rev#0 PAGE 10 0F10 Watts Bar Nuclear Plant 3-OT-JPM1 74 STEP 11: VERIFY reactor power has remained constant (+/- 0.5%) for at least 10 to 15 minutes AND __SAT NOTIFY the Unit Operator to maintain STABLE reactor power while adjusting NIS.
Operator verifies reactor power has remained constant and _UNSAT STANDARD*
notifies the unit operator.
COMMENTS:
STEP 12: PLACE ROD BANK SELECT switch (1 -RBSS), in MANUAL or BANK SELECT.
SAT STANDARD: Operator places rod bank select switch in manual or bank select.
UNSAT COMMENTS: Rod bank select switch should be removed from AUTO to prevent inadvertent control rod operation during NIS Power Range Channel adjustments.
Evaluator NOTE: Procedure contains a Note that showed be reviewed by the candidate. This note limits the operator actions to one NIS channel as a time.
The note ensures the operator reviews the caution prior to making adjustments that could cause a rate trip to occur.
STEP 13: IF rate trip exists on any NIS channel, THEN CRITICAL ATTEMPT TO CLEAR all channels rate trip signals STEP (momentarily set RATE MODE switch to RESET position) and the annunciator on panel 1-XA-55-6A-1 15E POWER RANGE FLUX RATE HI before proceeding to the next SAT step.
STANDARD: Operator resets any rate trip signals as necessary prior to proceeding. ..UNSAT COMMENTS: There are no rate trips present, requiring no action to reset rate trips. However, during NIS Power Channel adjustments, a rate trip may occur due to potentiometer sensitivity.
In the event a rate trip is caused on two NIS channels that are not reset and result in a reactor trip, then this task becomes a critical step.
Rev#O PAGE 11 OF1O Watts Bar Nuclear Plant 3-OT-JPM1 74 Evaluator NOTE: Procedure contains a Caution that showed be reviewed by the candidate. This caution warns that adjusting a channel too quickly may cause an inadvertent rate trip.
Evaluator NOTE: Procedure contains a Note that showed be reviewed by the candidate. This note directs the operator to ensure that the indicated NIS power is to remain equal to or above the calorimetric power.
STEP 14: UNLOCK AND ADJUST the gain potentiometer (on the CRITICAL Power Range B drawer) for the NIS channel being adjusted STEP to match calorimetric power AND LOCK the gain potentiometer. .SAT Adjustment Performed N/A Channel N-41: UNSAT Channel N-42: ii Channel N-43:
Channel N-44:
STANDARD: Operator adjusts the gain potentiometer to match calorimetric power and locks the gain potentionmeter on completion.
COMMENTS: This action is critical for each NIS channel that is being adjusted.
NIS channels that are not adjusted are marked N/A.
Rev#O PAGE 12 0F10 Watts Bar Nuclear Plant 3-OT-JPM1 74 STEP 15: IF the gain potentiometer does NOT provide enough gain to satisfy the adjustment requirements above, THEN SAT PERFORM Appendix A, COURSE GAIN ADJUSTMENT OF PR NIS.
Adjustment UNSAT Performed N/A Channel N-41:
Channel N-42:
Channel N-43:
Channel N-44:
STANDARD: Operator determines that gain potentiometer provides enough gain to satisfy the adjustment requirements.
COMMENTS: Each channel is marked N/A.
STEP 16: IF additional NIS channels require adjustment, THEN RETURN to Step 6.3[3]. SAT STANDARD: Operator determines that no additional adjustments are required.
COMMENTS:
UNSAT
Rev #0 PAGE 13 OF1O Watts Bar Nuclear Plant 3-OT-JPM1 74 STEP 17: WHEN NIS channel adjustments have been completed, CRITICAL THEN STEP ENSURE gain potentiometers have been LOCKED AND RECORD the current value of Calorimetric Power and the SAT power level from each NIS Power Range channel.
POWER LEVEL Calorimetric Power %
INDICATION UNSAT U11227TM OR U 1254 (Venturi) n 94.65 %
OR Tl-6.OO1 E POWER RANGE NIS POWER (%)
CHANNEL N-41 (1-IDWR-92-N41A) %
N-42 (1-IDWR-92-N42A) %
N-43 (1-IDWR-92-N43A) %
N-44 (1-IDWR-92-N44A) %
STANDARD: Operator records the current values for Ui 127TM and all NIS channels.
Operator ensures the gain potentiometers are locked.
COMMENTS: Indications should be read from U1127TM computer point and from each NIS Power Range channel.
STEP 18: CONTINUE to Section 6.4.
SAT STANDARD: Operator initials and continues.
COMMENTS:
UNSAT
Rev#O PAGE 14 OF1O Watts Bar Nuclear Plant 3-OT-JPM1 74 STEP 19: VERIFY all operable NIS Power Range Channels agree CRITICAL 6 4[1] within 2% of calorimetric power (%) recorded in 6.4[1 .1] OR STEP 6.4[1 .2] below:
[1.1] Step 6.2[3]
(Acc Crit A)
UNSAT
[1.2] Section 6.3[8]
(Acc Crit A & C)
STANDARD: Operator determines that acceptance criteria A and C are met.
COMMENTS: Operator N/As step [1.11 and initials step [1.2] that the four NIS Power Range Channels agree within 2% of calorimetric power (%).
Examiner Notify performer that the task is complete.
cue:
End task TIME STOP:
Rev #
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The unit is at steady state conditions with all NIS channels and LEFM operable.
INITIATING CUES:
You are the CRC and the US has directed you to perform 1 -SI-92-1.
Section 4.0 of 1-Sl-92-1 has been completed.
Notify the US when the SI has been completed.
Give marked up copy of 1 92-i to the candidate.
REV. 0 PAGE 1 OF 20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Restore Normal Charging and Letdown Per SOl-62.O1
REV. 0 PAGE 2 OF 20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR1O1a REVISION LOG REVISION DATE DESCRIPTION OF CHANGES PAGES REVIEWED LOG AFFECTED BY 0 03/9/08 Initial issue for NRC Exam ALL D.L.Hughes
REV. 0 PAGE 3 OF 20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Task: Restore Charging and Letdown Per SOl-62.O1 Alternate Path: 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, will malfunction and will not maintain temperature less than 127°F, after being placed in Auto, requiring operator action to take the controller to manual and control letdown temperature. In addition, the VCT Temperature Divert Valve, 1-TCV-62-79, will not auto divert, it will require manual action.
Facility JPM #: 3-OT-JPMR lOla RevO K/A Rating(s): A 4.05 Letdown pressure and temperature control valves(lmportance RO/SRO 3.6/ 3.1 TASK STANDARDS: Charging and Letdown in service with letdown temperature being controlled manually Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOI-62.01 Rev 0056 CVCS-Charging and Letdown Task Number: RO-062-SOI-62-006 APPLICABLE FOR: RO/SRO 10CFR55.45: 1,2,5 VIirItinn Time: 20 mm. Time CritI No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner:
NAME SIGNATURE DATE COMMENTS
REV. 0 PAGE 4 OF 20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla SIMULATOR OPERATOR INSTRUCTIONS:
Initialize to preshot in IC # 255 or perform the following:
- 1. Reset to any Mode 1 (recommend IC-40, 50, or 60) with PCS temperature >525° F.
- 2. All PCPs running.
- 3. Using SOt 62.01, remove Charging and Letdown per section 8.1 and place Excess Letdown in service per section 8.3.
- 4. ior zaihic6278A (el) 0.01 15 (insert overide for 1-HIC-62-78 to fail to 1% demand, ramped over 15 seconds from event trigger entry)
- 5. imf cv 60 VCT Temperature Divert Valve, 1-TCV-62-79, failure to auto divert
- 6. Allow PZR Level to stabilize and freeze the simulator.
- 7. Have a working copy of SOl 62.01 for examiner to provide.
After performer indicates understanding of task, place simulator in run.
When performer places 1-HIC-62-79A in P-Auto, (step 23 of JPM) insert Trigger 1 to fall the automatic temperature controL
REV. 0 PAGE 5 OF 20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Tools/Equipment/Procedures Needed:
ENSURE clean copies of SOI-62.O1 are in all the books on the simulator floor.
READ TO OPERATOR DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Excess letdown was placed in service 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to an air line fitting vibrating loose on 1PCV 81. The air leak was just repaired and 1 -PCV-62-81 has been tested.
Another Operator is being briefed to remove Excess Letdown from service when you have completed yor task.
INITIATING CUES:
The Control Room Supervisor has directed you to restore normal charging with the 1A CCP running, and 75 gpm Letdown Orifice B by performing Section 8.2 of SOI 62.01 CVCS- Charging and Letdown. (Consider the plant operating in Cycle 9)
Notify US when the procedure is complete.
REV. 0 PAGE 6 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla START TIME:
STEP 1: Obtain a copy of the procedure.
STANDARD: A copy of SOI-62.01 has been obtained COMMENTS:
SAT UNSAT EXAMINERS After the performer has demonstrated the method of CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
CAUTION:
Charging and Letdown must be in service together.
If Letdown isolates or Charging is lost, the other must be isolated.
STEP 2: [8.2.1]
[1] ENSURE all letdown orifices CLOSED:
PERF NOMENCLATURE LOCATION UNID INITIAL LETDOWN ORIFICE A 45 GPM 1-M-6 1-HS-62-72A (CIV-ØA) SAT LETDOWN ORIFICE 875 GPM 1-M-6 1-HS-62-73A (CIV-ØA)
LETDOWN ORIFICE C 75 GPM 1-M-6 1-HS62-74A (CIV-ØA)
LETDOWN ORIFICE 5 GPM 1-M-6 1-HS-62-76 UNSAT (CIV-ØA)
STANDARD:
All letdown orifices CLOSED:
COMMENTS:
REV.O PAGE 7 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 3: [2] CLOSE 1-HIC-62-89A, CHARGING HEADER RCP SEALS FLOW CONTROL.
SAT STANDARD: 1-FCV-62-89 is closed UNSAT COMMENTS:
STEP 4: [3] IF NO Charging Pump is IN SERVICE, THEN PERFORM the following:
SAT STANDARD: Step is N/A, since A CCP is operating UNSAT COMMENTS:
STEP 5: [4] ADJUST 1-HIC-62-93A, CHARGING FLOW PZR LEVEL CONTROL, to between 8 and 13 gpm per RCP.
SAT STANDARD: Seal flow is between 8 - 13 gpm per RCP UNSAT COMMENTS:
REV.O PAGE 8 0F20 WAI IS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 6: [5] ENSURE 1-HS-62-84A, AUX SPRAY TO PZR [1-M-6],
CLOSED.
SAT STANDARD:
1-FCV-62-84 is closed UNSAT COMMENTS:
STEP 7: [6] PLACE 1-HS-62-79A, LTDN HI TEMP DIVERT, in VCT.
SAT STANDARD: 1-HS-62-79A, LTDN HI TEMP DIVERT,is in VCT UNSAT SI MU LATOR OPERATOR COMMENTS:
CAUTION Pressure surges can cause 1 -RFV-62-662, CVCS LETDOWN HEADER RELIEF, to open. If relief sticks open or leaks after closing, the tailpipe temperature may alarm, and the Pzr Relief/Safety tailpipe temperature may rise and alarm.
REV. 0 PAGE 9 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 8: [7] ENSURE the following:
CRITICAL PERF STEP NOMENCLATURE LOCATION POSITION UNID INITIAL RCS LETDOWN FRM 1-M-6 OPEN 1-HS-62-69A LOOP 3 IN CNTMT RCS LETDOWN FRM 1-M-6 OPEN 1-HS-62-70A SAT LOOP 3 IN CNTMT LP LETDOWN SQL CIV-ØA 1-M-6 OPEN 1-HS-62-77A STANDARD: UNSAT 1 -FCV-92-69, 1 -FCV-92-70, 1 -FCV-92-77 are OPEN, COMMENTS:
STEP 9: [8] ENSURE 1-HIC-62-78A, LETDOWN HX OUTLET TEMP CRITICAL TCV-70-192 CNTL, in MANUAL and set between 20 and 25% STEP OPEN.
SAT STANDARD: TCV70-192 CNTL, is in MANUAL and set between 20 and 25%
OPEN.
UNSAT COMMENTS:
REV.O PAGE 10 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 10: [9] ENSURE CCS in service to LDHX (1-Fl-70-190)
[0-M-27B]. SAT UNSAT STANDARD: CCS is verified to be in service to LDHX on 1-Fl-70-190.
COMMENTS:
NOTES:
- 1) If 1-PCV-62-81 is unavailable, it may be necessary to use the bypass valve per Section 8.15.
- 2) It may be necessary to manually control 1-HIC-62-81A, LETDOWN PRESS CONTROL, to prevent letdown pressure from exceeding 600 psig and causing 1-RFV-62-662, CVCS LETDOWN HEADER RELIEF, to OPEN.
STEP 11: [10] ENSURE 1-HIC-62-81A, LETDOWN PRESS CONTROL, in CRITICAL MANUAL and set between 40 and 50% OPEN if using 75 STEP gpm orifice (20-30% OPEN if using 45 gpm orifice).
LETDOWN PRESS CONTROLLER, is in MANUAL and set SAT STANDARD: between 40 and 50% OPEN UNSAT COMMENTS:
REV. 0 PAGE 11 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 12: CRITICAL
[11] ENSURE the following:
STEP NOMENCLATURE LOCATION POSITION UNID PERF VERIFIER INITIAL INITIAL CHARGING LINE 1-M-6 OPEN 1-HS-62-90A ISOLATION IV CHARGING LINE 1-M-6 OPEN 1-HS-62-91A ISOLATION IV SAT STANDARD: 1 -FCV-62-90 and 1 FCV-62-91 are OPEN UNSAT COMMENTS:
NOTE:
To minimize possible transient effects on either RCS charging penetration, 1 -FCV-62-85 is preferred for use during odd numbered fuel cycles, and 1-FCV-62-86 is preferred for use during even numbered fuel cycIes 1-Sl-O-8 provides transient monitoring STEP 13: [12] OPEN one charging valve (N/A valve NOT opened>:
NOMENCLATURE LOCATION UNID PERF VERIFIER CRITICAL INITIAL INITIAL STEP NORM CHARGING TO 1-M-6 1-FCV-62-85A LOOP I IV ALT CHARGING TO 1-M-6 1-FCV-62-86A LOOP 4 IV SAT STANDARD:
Performer refers to Initial Conditions and determines that 1-FCV 85 is used during odd fuel cycles (cycle 9), therefore 1-FCV-62-85 is opened UNSAT COMMENTS:
REV.O PAGE 12 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla CAUTIONS:
- 1) 1-HIC-62-89A, CHARGING HEADER RCP SEALS FLOW CONTROL, must be opened slowly to avoid thermal shock to Regenerative HX.
- 2) When operating at a minimum charging flow rate, letdown flow must be cooled below 380°F. If NOT, charging and letdown flow should be raised by opening an additional letdown orifice flow path.
NOTE Letdown flow should be established promptly after Charging flow is established via 1-FCV-62-89.
STEP 14: [13] ADJUST 1-HIC-62-89A, CHARGING HEADER RCP SEALS CRITICAL FLOW CONTROL, and 1-HIC-62-93A, CHARGING FLOW STEP PZR LEVEL CONTROL, to establish charging flow greater than 55 gpm (to ensure cooling to Regen Hx), and MAINTAIN between 8 and 13 gpm RCP Seal flow. SAT Performer establishes Charging greater than 55 gpm with Seal STANDARD: injection flow 8 13 gpm per RCP and abides by Caution and Note prior to step. UNSAT COMMENTS:
REV.O PAGE 13 0F20 WA I I S BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 15: [14] MONITOR 1-TI-62-71, REGEN HX OUT LTDN TEMP, to maintain letdown temperature less than 380°F. _SAT STANDARD: Performer monitors Letdown temperature now and in subsequent _UNSAT steps.
COMMENTS:
STEP 16: [15] OPEN 1-HS-62-76A, LETDOWN ORIFICE (5 GPM).
SAT STANDARD: Performer OPENs 1-HS-62-76A, monitors Letdown flow and temperature.
UNSAT COMMENTS:
STEP 17: [16] IF Letdown was isolated for more than 8 hrs AND RCS is 350°F or more, THEN SAT Evaluator Cue: It the pertormer ask how long it has been since letdown has been isolated, inform them that it has been 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes UNSAT STANDARD: Performer determines that there is no need to hold in this configuration COMMENTS:
REV. 0 PAGE 14 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla CAUTION:
Pressure surges can cause 1-RFV-62-662, CVCS LETDOWN HEADER RELIEF, to open.
STEP 18: [17] WHEN letdown pressure and temperature stabilize, THEN CRITICAL OPEN 1-HS-62-72A, CVCS LETDOWN ORIFICE A STEP ISOLATION(45 GPM, CIV-ØA), OR IF 75 gpm letdown is desired, THEN SAT PERFORM the following:
[17.1] OPEN one of the following (NIA orifice NOT selectec UNSAT NOMENCLATURE LOCATION UNID LETDOWN ORIFICE B 75 GPM 1-M-6 1-HS-62-73A CIV-OA LETDOWN ORIFICE C 75 GPM 1-M-6 1-HS-62-74A CIV-ØA
[17.2] ENSURE 1-HS-6272A, LETDOWN ORIFICE A ISOLATION (45 GPM), is CLOSED.
STANDARD: Performer allows letdown pressure and temperature to stabilize, and then OPENS Letdown Ort ice B, Using 1 -HS-62-73A.
Performer also verifies 1-HS-62-72A, Letdown Ort ice A Isolation, CLOSED COMMENTS:
Critical step aspect is to open a 75 gpm orifice.
REV.O PAGE 15 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 19: [18] CLOSE 1-HS-62-76A, LETDOWN ORIFICE 5 GPM CIV-(A.
SAT STANDARD: 1-FCV-62-76 IS CLOSED UNSAT COMMENTS:
STEP 20: [19] ADJUST 1-HIC-62-81A, LETDOWN PRESS CONTROL, to CRITICAL maintain between 320 and 350 psig, AND PLACE in AUTO. STEP 1-HIC-62-81A, LETDOWN PRESS CONTROL, is in AUTO and STANDARD: controlling between 320 and 350 psig. SAT UNSAT COMMENTS:
NOTE:
During periods of high river water temperature, river water temperature will limit the ability of TCV-70-192 to control letdown temperature at lower temperatures. Refer to P & L 3.OC.
REV.O PAGE 16 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 21: [20] ADJUST 1-HIC-62-78A, LETDOWN HX OUTLET TEMP CRITICAL TCV-70-192 CNTL, to maintain less than 127°F, AND STEP MAINTAIN 1-TCV-70-192 less than full open.
STANDARD: LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, is less than SAT full open and Letdown Temperature is less than 127 F° COMMENTS:
UNSAT STEP 22: [21] PLACE 1-HIC-62-78A in AUTO.
SAT STANDARD: Performer places 1-HIC-62-78A in Auto, and monitors Letdown Temperature on 1-Tl-62-78 {1-M-6], UNSAT COMMENTS:
STEP 23: [22] PLACE 1-HS-62-79A, LETDOWN HI TEMP DIVERT, to DEMIN, then to P-AUTO. SAT STANDARD: 1-HS-62-79A, is in P-AUTO. UNSAT Simulator When performer places 1-HIC-62-79A in Auto, insert Trigger Operator CUE 1 to fail temperature control COMMENTS:
REV.O PAGE 17 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla Evaluator Note:
Performer should observe letdown temperature on i-Tl-62-78 [1-M-61, not being controlled, and that letdown flow is still going to the demineralizers.
The following steps are associated with alarm response ARI hOD LTDN TO DEMINS TEMP HI If the performer realizes the temperature control problem and takes the following 2 prudent actions, lAW TI-i 2.04, then the remaining Critical Steps would have been accomplished.
- 1. Take manual action to divert letdown flow from CVCS demineralizers with 1-HIS-62-79A.
- 2. Take manual control of 1-HIC-62-78A and control letdown temperature to less than 127°F.
STEP 24: ARI ii OD Step 1 CRITICAL STEP IF letdown temperature is greater than 137.5° Eon 1-TI-62-78 [1 M-6], THEN ENSURE CVCS demineralizers bypassed (lights above 1-HS-62-79 [1-M-6]).
SAT STANDARD:
Manual action is performed to place 1-HS-62-79A, in Divert, since letdown temperature got greater than 137.5° F UNSAT COMMENTS:
REV.O PAGE 18 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 25: ARI hOD Step 2 ENSURE letdown flow is 45 gpm to 120 gpm on 1-FI-62-82
[1-M-6]. SAT STANDARD:
Letdown Flow is 75 gpm UNSAT COMMENTS:
STEP 26: ARI hOD Step 3 ENSURE charging flow is 57 gpm to 132 gpm on 1-FI-62-93A [1-M-5]. SAT STANDARD: Charging Flow is 57 gpm to 132 gpm UNSAT COMMENTS:
REV.0 PAGE 19 0F20 WATTS BAR NUCLEAR PLANT 3-OT-JPMR lOla STEP 27: ARI hOD Step 4 CRITICAL STEP ADJUST 1-HIC-62-78A to maintain letdown temperature less than 127° F on 1-TI-62-78.
SAT STANDARD: 1-HIC-62-78A is placed in Manual and Letdown temperature controlled to less than 127°F __UNSAT COMMENTS:
STEP 28: Performer informs SRO that Charging and Letdown are in service with 1-HIC-62-78A is placed in Manual controlling __SAT Letdown temperature UNSAT Evaluator Cue Acknowledge report, notifiy performer that the task is complete. End task Inform performer that another operator will take the task from this point.
COMMENTS:
End of Task TIME STOP:
Rev. 0 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Excess letdown was placed in service 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to an air line fitting vibrating loose on 1-PCV 81. The air leak was just repaired and 1 -PCV-62-81 has been tested.
Another Operator is being briefed to remove Excess Letdown from service when you have completed yor task.
INITIATING CUES:
The Control Room Supervisor has directed you to restore normal charging with the 1A CCP running, and 75 gpm Letdown Orifice B by performing Section 8.2 of SOl 62.01 CVCS- Charging and Letdown. (Consider the plant operating in Cycle 9)
Notify US when the procedure is complete.
RevO. PAGE 1 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73A START UP UPPER CONTAINMENT PURGE PER SOI-30.02
RevO. PAGE 2 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73A NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Inhlial Issue. All D.L.Hughes
Rev 0. PAGE 3 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73A EVALUATION SHEET Task: START UP UPPER CONTAINMENT PURGE PER SOI-30.02 Alternate Path: N/A Facility JPM #: 3-OT-JPMR173A RevO K/A Rating(s):
- 029A2.03 Startup operations and the associated required valve lineups. [Importance:
RO/SRO 2.7/3.1]
- 029A4.01 Containment purge flow rate [Importance: RO/SRO 2.5 / 2.5]
- 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. [Importance: RO/SRO 4.6/4.1]
TASK STANDARDS: Upper Containment Purge is in service Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
SOI-30.02 Containment Purge System Rev 0051.
Task Number: RO-030-SOl-30-007 APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 3, & 7 Validation Time: 20 mm. Time Critical: No Candidate: Time Start:
NAME SSN/EIN Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS
RevO. PAGE 4 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73A SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Initialize to any Mode 1 IC that does not have Containment Purge in service.
- 2. Acknowledge all alarms.
- 3. After performer indicates understanding of task, place simulator in run.
- 4. There are no malfunctions, overrides, or booth communications needed for the administration of this JPM
RevO. PAGE 5 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73A EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Needed:
Ensure clean copy of SOl-30.02 Containment Purge System in the books on the Simulator Floor.
READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
AllI Control Room steps shall be performed for this task, including any required communications.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
The Unit is in Mode 1.
You are the BOP.
INITIATING CUES:
The Unit Supervisor has directed you to place B train Upper Containment Purge in service, utilizing 1-FCV-30-9 & 53 and 1-FCV-30-1O & 52.
Section 4.0, Prerequisite Actions are complete.
You are to notify the Unit Supervisor when your task is complete.
RevO. PAGE 6 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 START TIME:
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD: A copy of S0I-30.02 has been obtained.
_SAT COMMENTS:
EXAMINERS After the performer has demonstrated the method of UNSAT CUE: obtaining the correct instruction, the evaluator can provide a copy of the instruction.
STEP 2 [1] ENSURE Section 4.0, Prerequisite Actions, COMPLETE.
SAT STANDARD: Performer determines from turnover sheet that Section 4.0, Prerequisite Actions, COMPLETE UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 7 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 3: [2] PERFORM the following prior to moving irradiated fuel with containment open to ABSCE spaces: (N/A if SAT in Modes 1-4 or if in Modes 5 & 6 with containment isolated)
STANDARD: Performer determines that the step is N/A.
UNSAT COMMENTS:
STEP 4: [3] OBTAIN SRO approval.
STANDARD: Performer determines that Unit Supervisors permission was given in the initial conditions.
COMMENTS:
UNSAT STEP 5: [4] OBTAIN Release Permit from Chemistry Countroom.
EXAMINERS Inform performer that Unit Supervisor has obtained SAT CUE: Release Permit from Chemistry Countroom.
STANDARD: Performer determines that Release Permit from Chemistry Countroom is obtained.
UNSAT COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 8 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 6: [5] ENSURE appropriate heating/cooling water to Containment Purge Supply per SOI-44.01/SOI-31 .03 (N/A if NOT desired).
SAT EXAMINERS Inform performer that heating/cooling water to CUE: Containment Purge Supply is not desired.
UNSAT STANDARD: Step is N/Aed COMMENTS:
STEP 7 [6] ENSURE Section 5.10 of SOl-90.02, Gaseous Process Radiation Monitors, has been completed for specific train(s) of containment purge to be placed in service. SAT EXAMINERS If asked, inform performer that Section 5.10 of SOl CUE: 90.02, Gaseous Process Radiation Monitors, has been completed for B train of upper containment purge to be placed in service.
UNSAT STANDARD: Performer initials step as complete.
COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 9 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 8: [7] INDICATE which Train(s) will be used
- Train A Containment Purge
- Train B Containment Purge _SAT
- Both Trains A and B Containment Purge STANDARD: Performer reviews initiating cues, and selects train B.
UNSAT COMMENTS:
STEP 9: [8] IF Wafer Vlv, 1 -ISV-78-600, OPEN in Mode 6 WITH SFP & Rx Cavity Full, THEN...
STANDARD: Performer N/As step since plant is in Mode 1 SAT COMMENTS:
UNSAT STEP 1o [9] IF aligning for 2-Train operation, THEN CHECK A Train ABGTS is NOT running.
SAT STANDARD: Performer N/As step since plant is only 1 train operation is desired.
COMMENTS:
UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 10 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 11: [10] CLOSE Containment vent filter flowpath: CRITICAL STEP NOMENCLATURE LOCA11ON POSITION UNID LWR CNTMT PURGE EXH 1-M-9 CLOSED 1-HS-30-37 PRESS RLF LWR CNTMT PURGE EXH 1M-9 CLOSED 1-HS-30-40 PRESS RLF STANDARD: Performer closes: SAT
- 1-HS-30-37
- 1-HS-30-40 COMMENTS: UNSAT STEP 12: [11] OPEN Selected Supply Fan(s) Disch damper (NIA if NOT CRITICAL selected): STEP NOMENCLATURE LOCATION POSITION UNID PURGE SUP FAN 1A DISCH 1-M-9 OPEN 1-HS-3O2 PURGE SUP FAN lB DISCH 1-M-9 OPEN 1-HS-30-5 SAT STANDARD: Performer only OPENS:
- 1-HS-30-5 COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 11 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 13: [12.1] IF Train A will be run, THEN CRITICAL STEP PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN 1ATO 1-M-9 OPEN 1-HS-30-213 SHIELD BLDG VNT PURGE EXH FAN 1BTO 1-M-9 CLOSED 1-HS-30-216 SHIELD BLDG VNT SAT
[12.2] IF Train B will be run, THEN PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN 1ATO 1M-9 CLOSED 1-HS--30-213 UNSAT SHIELD BLDG VNT PURGE EXH FAN 1BTO 1-M-9 OPEN 1-HS-3O216 SHIELD BLDG VNT
[12.3] IF Both Train A and B will be run, THEN PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN 1ATO 1-M-9 OPEN 1-HS-30-213 SHIELD BLDG VNT PURGE EXH FAN 1BTO 1-M-9 OPEN 1-HS-30-216 SHIELD BLDG VNT STANDARD: The Performer (NA steps [12.11 &[12.3]) AND
. VERIFY CLOSED 1-HS-30-213
. OPENS 1 -HS-30-21 6 COMMENTS:
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 12 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 14: [13] OPEN the FCVs in 5.1[13.1] & 5.1[13.2], or 5.1[13.3] & CRITICAL 5.1[13.4] [1-M-9] (N/A set NOT used): STEP
[13.1] UPR CNTMT PURGE 1-FCV-30-7 & 51 with 1-HS-30-7.
[13.2] UPR CNTMT PURGE 1-FCV-30-8 & 50 with 1-.HS-30-8.
[13.3] UPR CNTMT PURGE 1-FCV-30-9 & 53 with 1-HS-30-9.
[13.4] UPR CNTMT PURGE 1-FCV-30-10 & 52 with 1 -HS-30-1 0.
STANDARD Performer reviews JPM initiating que and ONLY OPENS: UNSAT
- FCV-30-9 & 53 with 1 -HS-30-9
- 1-FCV-30-1O & 52 with 1-HS-30-1O COMMENTS:
STEP 15: [14] START Selected Purge Sup & Exh Fan(s) (N/A if NOT CRITICAL selected):
STEP NOMENCLATURE LOCATION POSITION UNID CNTMT PURGE SUP & EXH 1-M-9 START 1-HS-30-1A FANS 1AAND FCO-30-1A& lB CNTMT PURGE SUP & EXH 1-M-9 START 1-HS-30-4A FANS lB AND FCO-30-4A & 48 SAT STANDARD: Performer ONLY starts 1 B Fans and dampers with 1 -HS-30-4A.
COMMENTS:
UNSAT
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
Rev 0. PAGE 13 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 16: [15] PERFORM the following (N!A if NOT selected): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID PURGE EXH FAN ASUCT 1-M-9 OPEN 1-HS-30-61 PURGE EXH FAN B SUCT 1-M-9 OPEN 1-HS-30-62 STANDARD: The performer ONLY OPENS 1 -HS-30-62.
SAT COMMENTS:
UNSAT STEP 17: [16] ENSURE the following (NIA Train NOT used): CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID PURGE SUP SUCT ISOL 1-M-9 OPEN FCO-30-294 DAMPER 1-XI-30-294 PURGE SUP SUCT ISOL 1-M-9 OPEN FCO-30-295 DAMPER 1-Xl-30-295 Train A DAMPER 1-XI-30-1A 1-M-9 OPEN FCO-30-1A SAT DAMPER 1-XI-30-IB 1-M-9 OPEN FCO-30-1B Train B DAMPER 1-XI-30-4A 1-M-9 OPEN FCO-30-4A UNSAT DAMPER 1-XI-30-4B 1-M-9 OPEN FCO-30-4B STANDARD: The performer ENSURES OPEN:
- FCO-30-294
- FCO-30-295
- FCO-30-4A
- FCO-30-4B COMMENTS:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 14 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 18 [17] CHECK flow on 1-Fl-90-400, SHIELD BLDG VT FLOW [1-M-9] (N/A if Fl NOT available).
STANDARD: The performer verifies flow on 1 -Fl-90-400, SHIELD BLDG VT FLOW. SAT COMMENTS:
UNSAT STEP 19 [18] IF FI-90-400 is NOT available, THEN ENSURE Flow being estimated per 1 -Sl-O-2, Shift & Daily Log.
STANDARD: The performer N/As this step.
SAT COMMENTS:
UNSAT STEP 20 [19] NOTIFY the Chemistry Countroom of the purge start date and time.
STANDARD: The performer informs Chemistry Countroom of the purge start date and time. SAT EXAMINER When notified, acknowledge the report.
CUE:
COMMENTS: UNSAT
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
RevO. PAGE 15 0F16 Watts Bar Nuclear Plant 3-OT-JPMR1 73 STEP 2l [20] IF containment pressure approaches or exceeds Tech Spec value (+0.27 psid in Modes 1-4), THEN PERFORM Section 7.1, SHUT DOWN Upper Containment Purge.
SAT STANDARD: The performer monitors Containment pressure on 1-PDI-30-133 and verifies it is less than Tech Spec value.
Performer notifies Unit Supervisor that B train Upper Containment Purge in service _UNSAT EXAMINER When notified, acknowledge the report, notify CUE: performer that the task is complete. End task COMMENTS:
END OF TASK TIME STOP:
- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
EXAMINEE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Unit is in Model.
You are the BOP.
INITIATING CUES:
The Unit Supervisor has directed you to place B train Upper Containment Purge in service, utilizing 1-FCV-30-9 & 53 and 1-FCV-30-1O & 52.
Section 4.0, Prerequisite Actions are complete.
You are to notify the Unit Supervisor when your task is complete.