ML060830469
| ML060830469 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 11/14/2005 |
| From: | Palagi B NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| 50-305/05-301 50-305/05-301 | |
| Download: ML060830469 (82) | |
Text
Facility: Kewaunee Scenario No.: 1 Op-Test No.: 1 Exam iners: Operators:
Initial Conditions: IC-12, 100% power, Middle of Cycle (MOC)
Motor Driven AFW A Pump is in PULLOUT.
SI Pump A is in PULLOUT.
Turnover: The plant is at 100% power. AFW Pump A has been out of service for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to inboard bearing replacement. S I Pump A has been out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an inspection of the breaker cu bicle indicated the lugs on one of the supply line connectors is loose.
At turnover, the Equipment Operator reported Steam Traps 23 and 24 on the lines from the individual steam header supplies to the TD A FW Pump , and Steam Trap 25 and 26 on the common steam line to the Turbine-Driven AF W Pump are cold. The Shift M anager has just declared the T D A FW Pump inoperable and directs the crew to remove it from service as soon as turnover is complete. (No action taken yet.)
Event No. Malf. No. Event Event Type* Description Preload CC04B Failure to Auto Start CC Pump B 1 N BOP Pow er backdown to less than 1673 M Wt (~94% power) 3/4 SRO R RO Maintain DI and RCS Tave using rods and boron addition.
2 RX211, I BOP Con trolling SG A level channel (LT 461 ) fails high over 10 seconds.
100 SRO 3 SW05C, C BOP Running Service Water Pump 1B1 trips on overcurrent. Standby Pump 100 SRO auto starts. SW-3A header isolation valve closes im properly.
DI-46528-CLOSE ON 4 CC03B, C RO RXCP B Thermal Barrier leak with failure of automatic isolation of CC 1.0 SRO cooling from thermal barrier. This will eventually lead to a manual reactor DI-46332-OPEN ON trip directed due to RXC P parameters exceeding limits or the RXC P will RC03B trip. (EOP entry)
AI-4301-02-R1, 5 C BOP SG B POR V Controller fails giving POR V open signal. Manual control 0 SRO available.
6 SG 01B , 7 M BOP SG B tube rupture of ~ 250 gpm ramped in over 10 minutes starting 2:00 10:00 RO minutes after the reactor trip.
SRO 7 CC05A C RO Component Cooling Water Pump trips on overcurrent. Component CC04B SRO Cooling Pump B fails to auto start. Manual start available.
- (N)ormal, (R)eactivity (I)nstrument, (C)ompon ent, (M)ajor Scenario1-1.doc 1 03/24/06 Rev. A
Scenario1-1.doc 2 03/24/06 Rev. A
Event 1 - The plant is at 100% power. SI Pump A and AF W P ump A are inoperable. At turnover, the Turbine-Driven AFW Pump is determined to be inoperable due to the failure of steam traps on the steam lines to the TD AF W Pump. The CRS will direct rem oval from service (Placing TD AF W Pump in PUL LO UT , and possible closing the Steam Supply valves fro the SGs MS-10A and MS-10B). Technical Specification 3.4.b will be addressed and LCO 3.4.b.3 requires reactor power be reduced to less than or equal to 1673 M Wt within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Operations Management will inform the crew that power reduction needs to begin as soon as possible. 1673 MWt corresponds to 94.4% power. Crew will use N-O-03 and N-TB-54 to reduce load.
Event 2 - Following clearly observable plant response from the reactivity changes during the load reduction, the controlling level channel for SG A w ill fail high. The actual level will begin to lower due to FW-7A closing in response to the high level. The BOP will take FW-7A Con troller to MAN UA L and verify that SG level recovers toward program level. Procedure A-FW-5A and A-MI-87 will be used to address the failure. The failed instrument will be rem oved from service using A-M I-87. Th e SR O w ill address T echnical Specification 3.5.b to en sure continued plant operation is allowed w ith the failed channel.
Event 3 - After the operator actions are completed for removal of the failed SG Level channel from service, the running Service Water Pump 1B1 will trip on overcurrent. This will result in automatic start of the standby SW Pump1B2 when SW header pressure drops below 72 psig. Train B Header Isolation valve SW -3A will inadvertently close. It normally closes on SI signal or on sensed low pressure in the associated header. Train A pressure will remain above the closure setpoint. The crew will respond by taking actions directed in A-SW-02, and re-open SW -3A when SW Header A Operating is checked. The SR O w ill address T echnical Specification 3.3.e.2 for actions associated with the loss of the SW Pum p. Also by direction of N-SW-02 Precaution and Limitation 2.2, the SRO will determine in accordance with this item that with SI Pump B also inoperable, Technical Specification 3.0.c is applicable requiring plant shutdown.
Event 4 - Once the requirement for plant shutdown is reviewed , a leak will develop in RX CP B Thermal Barrier.
This will result in leakage of RCS water into the Component Cooling System. CC radiation levels will rise and be detected on process monitor R17, Com ponent Cooling Surge Tank level will rise and CC-610B , RXC P B Thermal Barr Comp Cooling Return, that normally closes on high flow, will fail to close. The crew will address the problem by entering A-RC -36C, A-RM -45, and/or A-CC-31. The actions are expected to identify RXCP B thermal barrier leakage and result in closing the isolation valve CC-61 0B. RX CP conditions deteriorate for bearing temperature and may require the RXCP be stopped. The CRS should then direct a manual reactor trip and stopping of RXCP B when the immed iate operator actions of E-0, Reactor Trip Or Safety Injection, are complete. If the actions to close CC-610B are completed prior to the parameters reaching a required trip condition, then RX CP B will trip (breaker opens) two minutes after the valve is closed.
Event 5 - At the time of the reactor trip (based on NI power) SG B PORV Controller will fail so that SD-2B, SG B PORV fully opens. Manual control is available and when the open SG PORV is identified by the BOP, the Controller will be placed to MAN.
Event 6 & 7 - Associated w ith the transient placed on SG B , a SG tube rupture w ill occur in SG B . The rate w ill increase to a value of 250 gpm over a ten-minute period. The crew will recognize conditions requiring a Safety Injection and manually initiate SI (if required). Five minutes following SI actuation, Component Cooling Pump A trips. Component Cooling Pump B fails to automatically start and should be manually started after verification that SI sequencer completes its sequence. The scenario ends following cooldown and depressurization of the RCS, and if possible, term ination of SI flow, O R at the discretion of the Chief Examiner.
Critical Tasks
- 1. E-0 K - Manually start at least one CCW pump required to provide adequate component cooling for the operating safeguards trains before transition out of E-0. [Event 7]
Scenario1-1.doc 3 03/24/06 Rev. A
- 2. E-3 A - Isolate feedwater flow into and steam flow from the ruptured S G before a transition to EC A-3.1 occurs [Even t 6]
- 3. E-3 B - Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions: [Event 6]
- Too high to maintain 50°F [85°F for adverse Containment] subcooling OR
- Below 270°F.
- 4. E-3 C - Depressurize RCS until either 1) PRZR level is > 74%, 2) RCS subcooling based on CETs is < 30°F
[65°F for adverse containment], or 3) RCS pressure is < S/G pressure and PRZR level is > 5% [30% for adverse containment] before 96% level is exceeded in the ruptured S/G. [Event 6]
Scenario1-1.doc 4 03/24/06 Rev. A
Scenario1-1.doc 5 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Page of 43 Power backdown to less than 1673 M Wt.
Event
Description:
Turnover indicates that Shift Manager has just declared TD AFW Pump inoperable due to failure of the steam line drains to operate properly. AFW Pump A is already OOS.
ACTION is based on LCO for AF W (TS 3.4.b . 3) with two of three AFW trains inoperable, within two ho urs, red uce reactor pow er to less than or equal to 16 73 M W t.
Additionally, another LCO (TS 3 .4.4.B) allows for two AFW trains to be inoperable for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when the RCS temperature is greater than 350ºF Time Position Applicant's Actions or Behavior CUE: Entry into LCO for two AFW Pum ps inoperable.
(If necessary (once the LCO is discussed) a cue may be provided to the crew that Op erations M anagement has directed an im mediate downpow er at norm al rate (1/4%/min) to the lower thermal rating as result of the Operational Decision-Making process.)
CRS Implement actions of N-0-03 Plant Operation Greater Than 35 % Power, step 4.2, Power Reduction:
CREW Review applicable Precautions, and Limitations and Actions.
CRS Determine that transition to A-O-03 is NOT required since power reduction rate is less than 1%/min.
CRS Direct that reactivity estimate be performed based on power reduction.
RO Perform reactivity estimate:
Current load: 100% (1772 MWt); Projected load: 94.4% (1673 MWt) [MINIMUM RE QU IRED]
NOT E: Load may be reduced further but given values are based on reduction to 94%
Comments:
Scenario1-1.doc 6 03/24/06 Rev. A
pow er.
Use the Reactivity Placard (or Reactor Data Manual) to perform reactivity balance:
Final Rod position: > 220 (226 is projected final position)
Given Borate: % pwr 7.5 gallons boron/%pwr Power decrease of 6% will require 45 gallons of boron with rods ending at 226 steps.
BOP Reduce load per N-TB-54, Turbine and Generator Operation, section 4.3, Shutdown:
- Review applicable Precautions & Limitations
- Determine m axim um load rate per Figures 2 & 3 and A ttachment C
- Take Turbine off VPL (preferred method)
§ Press RE FER EN CE CO NT RO L DOW N pushbutton until SETTER value reads less than 103%.
§ Set Loading Rate to value less than or equal to 5%/min.
§ Press GO button.
§ When the VALVE PO S LIMIT green light extinguishes, press HOLD button.
- Verify/set loading rate to 1/4%/min.
- Inform (telephone) Energy Supply & Control of rate and amount of load reduction.
- Depress GO
- Verify load increases
- Verify Reactive Load rem ains within Figure 5, G enerator C apability Curve, limits
§ If required, adjust Generator #1 Voltage Adjuster switch to change VARs (REACT PWR meter 4460104)
- When required load is reached, verify GO button not lit, or press HOLD pushbutton.
- If desired set V alve P osition Limit:
§ Adjust Valve Position Limit DOWN button in tiny increments until VALVE POS LIM IT light lit.
§ Press REFEREN CE CO NTRO L UP pushbutton to increase SETTER value by 3%.
§ Press GO button.
Comments:
Scenario1-1.doc 7 03/24/06 Rev. A
RO Perform reactivity adjustments:
Rod Con trol (outward motion at 1.5°F difference Tref-Tave)
AND/OR Boron Concentration Control per N-CV-35A, Boron Concentration Control, section 4.5, Normal Boration Du ring At P ower Evolutions:
- Review applicable Precautions & Limitations.
- Determine rate and magnitude of boration (total amoun t from above reactivity calculations)
- Adjust CV C-403/CV -31092, Blender Con trol BA Flow, to required flow rate.
- Set Rx M ake-up Totalizer to required quantity.
- Position Reactor Makeup Mode Selector to BORATE.
- Position Reactor Makeup Control switch to START
- Verify required change has been achieved by monitoring:
§ Rod Position
§ Boron Con centration
§ Tave Wh en boration is complete:
- At B oric Acid Totalizer:
§ Verify the correct quantity added.
§ Reset the BA Totalizer by pressing the black button.
§ Verify BA Totalizer indicating all ZEROs in window by black button.
- Place CVC-406/CV31094, BA Blender to VCT, to CLOSE position.
- Perform a 20-gallon Alternate Dilute (section 4.4).
RO § Set Rx M akeup Totalizer to 20.
(cont.) § Position Reactor Makeup Mode Selector to ALT DIL.
§ Position Reactor Makeup Control switch to START.
§ Wh en dilution is complete:
o Verify MU-1022/CV-31095, Blender Control Rx Mu Flow, is set to 60 gpm.
o Verify correct quan tity added at Rx Makeup Totalizer.
Comments:
Scenario1-1.doc 8 03/24/06 Rev. A
o Reset Rx Makeup Totalizer by pressing the black button.
o Verify BA Totalizer indicating all ZEROs in window by black button.
- Place CVC-406 to AUTO position.
- Position Reactor Makeup Mode Selector to AUTO.
- Position Reactor Makeup Control switch to START.
NOTE: Following the required reactivity change of ~ 5% power, Event 2 may be started.
Comments:
Scenario1-1.doc 9 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page of 43 Event
Description:
Controlling SG A level channel (LT 461) fails high over 10 seconds.
The controlling SG A level channel, LI-461, normally reading 44% will fail up to 100% over a 10-second ramp. The BOP will recognize the failure by comparing SG A level on the other channels LI-462 and LI463, which will show a lowering level. The actual level will be lowering due to the response of FW-7A, M ain FW Flow Control Valve, closing due to the controlling channel high level. The B OP will take manual contro l of FW -7A an d adjust as necessary to maintain SG A level within normal oper ating band (3 9% -49% ).
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47062-A, S/G A PROGRAM LEVEL DEVIATION 47062-B, S/G A BYPASS CV LEVEL DEVIATION 47064-B, S/G A LEVEL HIGH, (at > 67%)
TLA-10 SG TILTS PP CS A larms:
L0461A S/G A Chan 1 Level (H-4)
L0403D S/G A Lo Lo Level Chan 1 Trip [When bistable is tripped]
LI-461 S/G A level rising or at top of scale (100% ) with LI-462 and L I-463 lowering.
FW -7A Valve Po sition Dem and and Actual (Position) Indication lowering.
FI-466 and FI-467 , S/G A Feed Flow indications lowering.
BOP Identify and report LI-461 failed high.
Take FW-7A controller to MANUA L.
CREW Address Annunciator Response for 47062-A and/or 47062-B.
Report that if the alarm is due to a failed instrum ent:
Comments:
Scenario1-1.doc 10 03/24/06 Rev. A
- Verify the alarm was caused by failure of S/G A Level LI-461 AN D p osition FW -7A to MA NUA L.
- Go To A-MI-87 Go to A-FW-5A (NOTE: Addressing the Annun ciator Response is norm ally done by the off operator, but may b e perf orm ed by the involved op erator if con ditions dictate.)
CRS Direct the BOP to control SG A level with FW-7A in MAN UAL.
NOT E: Although AFW -05A is identified in the Alarm Response, the procedure only provides direction for restoring the F W-7A /B, F W Co ntrol Valves, to autom atic operation. N o action s would be directed from this procedu re in resp onse to this event.
CRS Direct actions of A-MI-87, B istable Tripping for Failed Reactor Protection or Safegu ards Inst.
CRS Check Technical Specifications for instruments with bistable tripping requirements [TS 3.5.b]:
TS Table 3.5-2, item No. 12 (Lo-lo SG water level reactor trip) - 3/loop with 2/loop required.
TS Table 3.5-3, item No. 4.a (M D A FW Pumps, Eith er SG lo-lo level) - 3/loop with 2/loop required.
TS Table 3.5-3, item No. 5.a (TD A FW Pump , Both SG lo-lo level) - 3/loop with 2/loop required.
TS Table 3.5-4, No. 4.a (Main FW Isol, Hi-hi SG level) - 3/loop with 2/loop required.
CRS Ensure I&C (Work Control/Work Week Coordinator) is notified of status of LT461.
CRS Declare LT461 channel out-of-service (OO S).
CRS Ensure bistables for LT461 are to be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of declaring OOS.
CRS Direct I&C to check for redundant channel bistable status by performing SP 47-316E , Channel Comments:
Scenario1-1.doc 11 03/24/06 Rev. A
1 (Red) R eactor Protection Logic Test.
NO TE: Time W arp m ay be used a t this point to have the check of redund ant bistables complete.
CUE: SP 47-316E is complete and no bistables were detected that would cause a reactor trip.
CRS Direct the crew to perform/verify Prerequisite Alignment of Attachment I for LT461.
BOP Ensure FW-7A, S/G A Main FW Flow Control Auto/Manual switch in MAN.
Ensure FW-10A, S/G A Bypass FW Flow Control Auto/Manual switch in MAN.
RO Act as SECOND OPER for verification of position for FW-7A and FW-10A in MAN.
CRS Direct I&C to trip bistables per Attachment I section 2.0 and 3.0 (NOTE : Th e COMMUN ICAT OR is set rep ort & to receive direction from CR S, and will perform action s for tripping b istables from the Simulator Booth.)
CRS Direct crew to verify control room indications per Attach ment I.
BOP Verify following lit:
§ Annunciator 47064-A, S/G A LEVEL LOW LOW
§ Annunciator 47064-B, S/G A LEVEL HIGH
§ Status Light 44907-1101, S/G A Low-Low Level
§ Status Light 44908-0801, S/G A Hi-Hi Level CREW Comp lete P ER FO RM ED BY and V ER IFC ATIO N BY sections of A ttach ment I.
CRS Direct status control for LI-461 indication (OO S sticker).
AT TH IS TIM E the crew w ill be inform ed that the Turbine Drive AFW Pum p steamline traps have been warm ed, and the T/D A FW Pump m ay b e returned to service. As S hift M anager, a cue is provided to th e crew to remove any S tatus Control and restore the T/D AFW Pum p to service.
Comments:
Scenario1-1.doc 12 03/24/06 Rev. A
NOTE: At Chief Examiner direction, Event 3 may be initiated.
Comments:
Scenario1-1.doc 13 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Page of 43 Event
Description:
Service Water Pum p 1B1 trips on overcurrent. SW-3A, SW header A Isolation inadv ertently closes.
Running SW Pump 1B1 trips, reducing the overall SW header pressure. When pressure drops to 78 psig, SW Pump 1B2 automatically starts. SW-3A and SW -3B, the SW Header Isolation valves are designed to close on a lowering header pressure at 72 psig on their associated header.
Pressure does no drop this low; however, SW-3A will go closed.
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47093-L, BUS 6 FEEDER BKR OVERLOAD 47092 -L, BUS 6 F EED ER B KR T RIP 47051-P, SW HEADER PRESSURE LOW 47052-Q, TURBINE BLDG SW ISOLATION ALERT The W HIT E light for SW Pum p 1B 1 will be lit.
SW W Pump 1 B2 auto starts (red light).
FW -3A green light lit and SW -3B red light lit.
BOP Identify and report trip of SW P ump 1B 1.
Report SW Pump 1B 2 start.
CREW Address Annunciator Response.
47092-L and 47093-L:
If alarm is activated by SW Pum p B1 Breaker 1-608 Overcurrent trip:
- Start additional SW Pumps as required.
- Refer to Tech nical Specification 3.3 Comments:
Scenario1-1.doc 14 03/24/06 Rev. A
- Dispatch NAO to investigate Timed Overcurrent relays on Bus 6.
- Notify Plant Electricians.
47051-P and 47051-Q:
- Go to A-SW-02 CREW When IPEOP s are N OT in effect:
(cont.)
- If Turbine Bldg S W header is isolated [SW -4A and SW -4B closed], restore SW headers to normal per A-SW-02.
- If Turbine Building S W header is not isolated AN D S W ESF Isolation signal is present, SER 839(840), THEN depress SW ESF Isol Reset pushbutton.
(NOTE: Addressing the Annunciator Response is normally done by the off operator, but may be perform ed by the involved operator if conditions dictate.)
(470 51-P AN D 4705 2-Q should reset after the stan dby SW Pum p starts.)
CRS Direct actions of A-SW-02, Abnormal Service Water System Operation.
BOP Check Forebay Level LI-41551 > 42%.
CREW Dispatch O perator to m onitor SW Loads (Check SW Pum ps and breakers).
BOP Check both SW header pressures > 72 psig on PI-41503 and PI-41506.
Check SW Header Isolation Valves SW-3A and SW-3b open.
- Report SW-3A closed.
- Verify all available SW Pumps running.
Comments:
Scenario1-1.doc 15 03/24/06 Rev. A
BOP Check if SW to Turbine Bldg should be isolated.
(cont.)
- An nunciator 47 051-N CW PU MPS FLOO D LEV EL TR IP not lit.
CREW Determine IPEO PS are not in affect.
BOP Check SW header pressure supplying Turbine Building > 60 psig on PI-41503 for header A.
Check SW-4A OPEN.
Check PI-41503 SW Header A pressure > 60 psig on PI-41503.
Check SW-10A, Aux Bldg SW H eader A Isol, open.
Check PI-41506 SW Header B pressure > 60 psig on PI-41506.
Check SW-10B, Aux Bldg SW H eader B Isol, open.
NOT E: The following indications are associated with the RO portion of then boards and may be addressed by either operator, although most likely by the RO.
CREW Check S W Header in Containment intact:
- Normal Containment sump levels
§ Annunciators for sump s OFF: 47031-P, 47031-Q and 47031-R
§ Containment Level Wide Range Channel A, 4131703 AND C ontainment Level Wide Range Channel B, 4131704 NORMAL at ZERO.
BOP Check Containment FCU outlet temperatures approximately equal on Omniguard 41507, points 15127 through 15130.
Check both SW header pressures > 86 psig on PI-41503 and PI-41506.
Comments:
Scenario1-1.doc 16 03/24/06 Rev. A
Check annun ciator 47052 -P off, and SER points 24 0 and 241 on Alarm Screen or Alarm Printer are off.
Crew Verify SI is reset (not active) [Annu nciators 4702 1-A and 47021B off].
BOP Open SW-3A.
BOP Verify SW Header B operating:
(cont.)
- Check SW-10B, Aux Bldg SW H eader B Isol, open.
- Turbine Bldg H eader intact.
- SW-4A open.
[END OF PROC EURE STE PS]
Comments:
Scenario1-1.doc 17 03/24/06 Rev. A
CRS Check T echnical Specifications for SW, TS 3.3.e.2 7 2-hour LCO w ith ONE SW Train inoperable.
Determine plant sh utdown is req uired due to inoperability of SI Pump B based on inoperable SW Train B. Entry into TS 3.0.c Standard Shutdown Sequence. (Reference TS 3.7.c for electrical equipment operability)
NO TE : Th e affect on SI P um p B and other equipment dep end ent on SW is addressed in N-SW-02, Service Wa ter System , Precautions and Limitations:
2.2 W HE N one train of Service Water is inoperable, com ponents supported by that train are inoperable. Apply T.S. LCO for Service Water System.
- 1. Test other Diesel Generator daily to ENSURE OPERABILITY.
- 2. VER IFY engineered safety features associated with other Diesel Generator OPERABLE.
CRS Inform Operations Management of plant conditions and Technical Specification requirement to shutdown.
If not contacted earlier, ensure Electrical Maintenance (Work Control/Work Week Coordinator) contacted to address overcurrent for beaker for SW Pump 1B1.
NOTE: At Chief Examiner direction, Event 4 may be initiated.
Comments:
Scenario1-1.doc 18 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Page of 43 Event
Description:
RXC P B T herm al Barrier leak reactor coolant into Com ponent Cooling (CC ) System.
CC Isolation va lve, CC-610B , fails to close. RXC P B trip (if req uired).
Leak of ~ 65 gpm from the RCS into the CC System initially. CC61 0B, RX CP B Thermal Barr Rtn, fails to close. Normally when the sensed CC return flow on FI609 exceeds 260 gpm, CC-610B will close isolating the cooling flow to the thermal barrier. RXCPB parameters degrade as the RCS coolant flows up the labyrinth seals feeding the thermal barrier leak. Component Cooling system shows indications of RCS leak with CC Surge Tank level rising and R-17, CC Ra diatio n M onito r upward trend. Ev entu ally w orsening condition s for th e RXC P should require a reactor trip so the RXCP can be stopped. If not stopped at the time the thermal barrier leak has been addressed, then RXCP B w ill trip.
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47014-L, RXCP B LABRYNTH SEAL DP LOW 47014-I, RXCP B LABRYNTH SEAL DP LOW 47024-H, CC SURGE TANK LEVEL HIGH/LOW 47012/11-B, RADIATION INDICATION ALERT; RADIATION INDICATION HIGH TLA-15 RMS ABO VE NO RMAL PP CS A larms:
P0129 RCP B Labyrinth Seal W ater D P L-1 P0429 A Przr pressure Channel 1 low L-1 P0430 A Przr pressure Channel 2 low L-1 P0431 A Przr pressure Channel 3 low L-1 P0449 A Przr pressure Channel 4 low L-1 G0 001 7A Rad iation M onitor R-17 H -1 RXC P B P I-131B Lab yrinth seal delta-P drops to ZE RO in.
RXCP B FI-116 #1 Seal Injection Flow rises to top of scale.
Charging Pump A speed increases (in AUTO ).
Pressurizer pressure and level drop.
Comments:
Scenario1-1.doc 19 03/24/06 Rev. A
CC Surge Tank level LI-618 rises R-17, CC R adiation Monitor value rising.
RO Identify and report RXC P prob lem (RXC P Labyrinth seal DP low; seal injection flow higher; CC Surge Tan k level rising).
CREW Address Annunciator Response.
For 47014-L and/or 47014-I:
- Go to A-RC-36C For 47024-H:
- If an increase in level is noted that is not attributable to system makeup or temperature increase, then go to A-CC-31.
For 47011-B or 47012-B:
- If alarm is NOT due to plann ed evolution, then inform Radiation Protection and request assistance in identifying and isolating radiation source.
- Go to A-RM-45 (NOTE: Addressing the Annunciator Response is normally done by the off operator, but may be perform ed by the involved operator if conditions dictate.)
NOT E: The crew m ay address one or more of the procedures in any order based on crew-determined priority.
Each of these procedures is addressed below.
CRS Direct the actions of A-RC-36C.
CREW If any RXCP m onitored parameter exceeds the allowed maximum value, then trip the reactor and got to E-0.
Comments:
Scenario1-1.doc 20 03/24/06 Rev. A
RO Check if RXC P should remain operating:
- #1 seal leakoff flow < 8.0 gpm on recorder 42588.
- #1 seal outlet temperature < 125ºF on TI-181/TI-182.
- Bearing Water temperature < 225ºF on T-132/T-125.
- Motor vibration < 5 mils on R XC P Vibration monitors.
- Pum p vibrations < 20 mils RXCP Vibration monitors.
- PPCS motor Bearing temperatures T0413A-T0416A/T0433A-T0436A < 195ºF.
- PPC S M otor stator temperature T0417A/T0437A < 155ºF (NOTE: Values m ay also be read from RX CP Graph ic Display on PPCS. The above is a Con tinuou s Action Step .)
RO Check CC flow to RXCPs Motor Bearing Oil Coolers;
- At least one CC pump running.
- Valves CC-600, CC-601A/B and CC-612A/B open.
- RX CP CC FLO W LOW annunciator 470 21-I off.
Check #1 seal DP greater than 200 psid on PI-173/PI-174.
RO Check R XC P Pump vibration < 15 mil.
(cont.)
Check #1 Seal leakoff flow < 6.0 gpm.
Verify CC flow to RXC P Therm al Barriers intact:
- CC-610A/B, RXCP Thermal Barrier CC Return open
- Component Cooling radiation levels R -17 norm al.
- CC Surge Tank level normal.
Report R-17 radiation levels elevated and/or CC Surge Tank level rising.
CREW Determine RXCP T hermal Barrier is leaking.
Comments:
Scenario1-1.doc 21 03/24/06 Rev. A
(NOTE: It is expected that the parameters will be sufficient to allow determination that RXCP B thermal barrier is leaking; how ever, the crew may elect to isolate both until an evaluation is perform ed.)
CRS Direct closing CC-610B and/or CC-610A.
RO Close CC-610B.
(NOTE: The closure of the valve will initiate 2-minute timer leading to trip of RXC P B.)
CREW Verify thermal barrier leak has been stopped:
- 1. Monitor R-17
- 2. Monitor CC Surge Tank level.
CREW
- Trend RXCP parameters on PPCS.
- Do not open CC-610 A/B on affected RX CPs during subsequent recovery steps.
If any thermal barrier is intact, reestablish CC flow to thermal barrier:
- Place CC-610A/CV31127, RXCP A Thermal Barr CC Alternate Control in OPEN position.
- Open CC-610A, if closed.
NOTE: It is expected that RXCP B conditions may require or may have required a reactor trip and RXCP B shutdown by this point. If not, RXCP B will trip at this point. A-CC-31 actions are covered below.
CRS Direct the actions of A-CC-31.
- At least one CC Pump running.
Comments:
Scenario1-1.doc 22 03/24/06 Rev. A
- Verify Comp Cooling Heat Exchanger A/B outlet, CC-6A AND/OR CC -6B, at least one open.
- Check CC Flow return normal (1000 - 1500 gpm) on FI-619.
Maintain CC System Inventory:
- Surge Tank Level < 52% on LI-618 Report CC Surge Tank level rising.
Isolate Surge Tank makeup:
- Verify SW-1400, Em ergency Makeup to CC, closed CREW
- Direct NAO to locally verify DW-161, makeup Supply from Demin Water, closed.
RO Check CC Surge tank level > 45% on LI-618.
Check both CC Pumps running Report CC Pum p A running.
- 1. Check CC Pump A discharge pressure > 90 psig on PI-4130202.
- 2. Monitor temperature and flow to components in operation.
RO Check if RXC P should remain operating:
Check RXCP operating Check RXC P parameters
- #1 seal outlet temperature < 125ºF on TI-181/TI-182.
- Bearing Water temperature < 225ºF on T-132/T-125.
Comments:
Scenario1-1.doc 23 03/24/06 Rev. A
- Motor vibration < 5 mils on R XC P Vibration monitors.
- Pum p vibrations < 20 mils RXCP Vibration monitors.
- PPCS motor Bearing temperatures T0413A-T0416A/T0433A-T0436A < 195ºF.
- PPC S M otor stator temperature T0417A/T0437A < 155ºF (NOTE: Values m ay also be read from RX CP Graph ic Display on PPCS. The above is a Con tinuou s Action Step .)
CREW If any RXCP m onitored parameter exceeds the allowed maximum value, then trip the reactor and got to E-0.
RO Stop the affected RX CPs and close its associated Spray valve.
RO Check CC flow to RXCPs Motor Bearing Oil Coolers; (cont.)
- At least one CC pump running.
- Valves CC-600, CC-601A/B and CC-612A/B open.
- RX CP CC FLO W LOW annunciator 470 21-I off.
Check CC Hx Outlet temperature on PPCT0 621A < 120ºF and stable.
If temperature is high or rising:
- Direct NAO to locally place SW -1306A/B controller in manual and operate to regain control of CC temperature.
- Cool down C C temperature:
§ Verify proper cooling established to C C heat exchanger.
§ Shut down unnecessary loads supplied by CC.
Comments:
Scenario1-1.doc 24 03/24/06 Rev. A
- At least one CC Pump running
- Letdown HX O utlet temperature stable or decreasing on TI-130.
- At least one CC Pump running
- VCT O utlet temperature stable or decreasing on TI-140.
RO Check if C C System is intact:
(cont.) 1. CC radiation level R-17 normal Report R-17 radiation level elevated.
CREW Try to identify location of leak:
- Ab normal CC flow throu gh compon ents
- Abnormal CC temperatures
- Ab normal temperatures on compon ents
- Abnormal Sump level changes
- Local visual inspection
- Selective isolation of H eat Exchangers Check C C H xs intact.
Check C C to RX CP s intact:
- Con tainment sum p alarms clear.
- RX CP motor bearing oil coolers intact.
RO Verify CC flow to RXCP Therm al Barriers:
- RXCP A /B Therm B arr temperature between 105-120ºF
- CC-610A/B, RXCP Thermal Barrier CC Return open
- RXCP T hermal Barrier Return flow, FI-614/FI-610 normal Comments:
Scenario1-1.doc 25 03/24/06 Rev. A
RO Report thermal barrier temperature on TI-610 elevated.
(cont.)
CREW If Thermal Barrier return flow is checked, direct NAO to locally read FI-614/FI-610.
When NA O resp onds, report elevated flow on FI-610.
RO Isolate any leaking thermal barrier:
- Close CC-610B.
(NOTE: The closure of the valve will initiate 2-minute timer leading to trip of RXC P B.)
CREW Place computer points for RXCP B on trend.
RO Maintain seal injection flow to RXCPs 6-13 gpm.
NOTE: It is expected that RXCP B conditions may require or may have required a reactor trip and RXCP B shutdown by this point. If not, RXCP B will trip at this point. A-RM-45 actions are covered below.
CRS Direct the actions or performance of A-RM-45.
CREW Check if personnel should be evacuated:
Determine m onitor indications for R-2 through R-10 are normal.
Check for radiation monitors failed downscale.
Go to step 18 for R-17 response.
Ch eck R-17 operating properly.
Comments:
Scenario1-1.doc 26 03/24/06 Rev. A
Check R-17 radiation levels elevated:
- Direct contact/Contact Chemistry to determine samp ling requirements.
- With indications of leakage into CC System, Go to A-CC-31.
NOTE: Actions of A-CC-31 are listed above.
NOTE: When the reactor is tripped (manual or automatic due to RXCP trip), Events 5, 6 & 7 are initiated.
Comments:
Scenario1-1.doc 27 03/24/06 Rev. A
1 Scenario No.: 1 Event No.: 5, 6 & 7 Page of 43 Op-Test No.:
Event
Description:
Reactor trip actions with failed SG B PORV controller. Steam Generator Tube Rupture. Trip of running Compon ent Cooling (CC) W ater Pum p (A) with failure of CC Pump B to auto start.
On the reactor trip, SG B PORV , SD-3B, setpoint input fails to ZERO resulting in SD-3A opening in AUTO . Manu al control of the POR V is available. The reduction in SG B pressure due to the open PORV results in initiation of SGTR. The 250 gpm rupture results in SI actuation. Dur ing the actions of E-0, the runn ing CC Pump trips, and the stand by pum p fails to auto start. The operator must manually start CC Pump B to ensure cooling to ECCS comp onen ts.
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
various SD-3B, SG B POR V, red light lit, green light out SG B pressure < 1000 psig and lowering.
Steam Flow indicated on FI474 & FI-475 for SG B, with steam dumps closed.
Przr pressure lowering.
Przr pressure and level dropping.
Charging flow increasing.
TLA-15 Alarm RMS ABOVE NORMAL Radiation trend rising for R-15, Air Ejector Exhaust, and R-19SG Blowdown Liquid.
Automatic SI actuation.
SG B level rising faster than SG A level / SG B level rising with feed isolated.
47103-F, BUS 51 FEEDER B KR TR IP (SER0746)
Various CC flow low annunciators CC Pump A green and white lights lit.
CC H eader pressure falling below 35 psig on 4130202 without start of CC Pump B RO [E-0, step 1]
Comments:
Scenario1-1.doc 28 03/24/06 Rev. A
Verify reactor trip:
- Reactor Trip and Bypass Breakers OPEN [Green lights lit for RTBs A & B]
- All Rod Position indicator £ 7.5 steps
- All R od B ottom (red) lights lit
- Neutron flux decreasing [4122601-4122604 or Power Range NIS Panel A drawers]
BOP [E-0 steps 2 & 3]
Verify turbine trip:
- Turbine Stop V alve green CLOS E indications lit.
Verify power to either Bus 5 or Bus 6 (W hite voltage lights lit).
CREW [E-0 step 4]
Check if SI is actuated:
An nunciator 47 021-A and 47021-B - SI Train A(B) A CT UA TE D - either lit.
If not, Check if SI is required:
Przr pressure < 1815 psig Przr level < 5%
RCS subcooling <30ºF SG pressure < 500 psig CNTM T pressure > 4 psig.
If SI is not required announce reactor trip.
RO Take Przr Spray Control LOOP B to MAN and verify closed.
Comments:
Scenario1-1.doc 29 03/24/06 Rev. A
CREW Identify steam release:
- Przr pressure lowering
- Steam flow indicated from SGs with steam dum ps closed
Take SD-3B controller to manual and verify SD-3B closed.
CRS Direct actions of E -0 Verify immediate actions.
If SI has not occurred or is not required, inform crew of transition to ES-0.1 NOTE: it is expected that the SGTR malfunction will be active before the crew does transition to ES-0.1 or performs actions in ES-0.1. If the transition is made to ES-0.1, then upon actuation of SI, transition to E-0 step 1 will be made and the immediate operator actions reperformed.
RO Report indications of RCS leak:
- Lowering R CS pressure
- Lowering Przr level
- Charging flow rising.
CREW Report secondary radiation indication.
CRS If SI has not occurred , direct SI actuation (E-0 QRF):
- Przr level cannot be maintained > 5%
(cont.) Przr pressure is trending toward 1815 psig and actions have not stabilized pressure.
RCS subcooling <30ºF RO If directed, actuate SI by p ressing both SI Train A and Train B INITIATE pushbutton s.
Comments:
Scenario1-1.doc 30 03/24/06 Rev. A
CREW Check both trains of SI actuated:
An nunciator 47 021-A and 47021-B - SI Train A(B) A CT UA TE D lit.
CRS Evaluate E-0 QRF, Ruptured SG Isolation Criteria.
CREW Wh en determined that SG B is ruptured, then apply ruptured SG Isolation Criteria:
If any SG level rises in an uncontrolled manner O R any SG has abnormal radiation AND Narrow range level in the affected SG [B] is > 4% ,
THEN feed flow may be isolated to SG B.
BOP When directed, isolate feed flow to SG B by closing AFW-2B and AFW-10B.
- FW-10A/B, SG A & B Bypass Flow Control valves, closed.
CREW Make plant announcement that Safety Injection has occurred.
CREW Dispatch EO/AO to Locally monitor AFW Pump operation:
BOP Check if steamline isolation is required:
- Containment pressure > 17 psig.
Comments:
Scenario1-1.doc 31 03/24/06 Rev. A
CREW Verify Containment Spray not required:
Check containment pressure (Cntmt Wide Range Pressure recorders 42597 & 42 598) have remained below 23 psig.
BOP Verify Containment Fan C oil Units running.
Verify SW-903 A, B, C & D CNTM T Fan Coil Unit SW Return valves open.
BOP Verify Aux Bldg Special Ventilation running:
- An nunciator 47 052-G NO T lit.
- Zone SV Fans A and B running.
Verify Service W ater alignment:
- Verify all SW Pumps running
Verify AFW Pump s running:
- 2. Check AFW Pump B running
- 3. Check TD AFW Pump running (red light lit for MS-102, T/D AFW Pump Main Steam Isol, and discharge pressure on 41040 Throttle AFW Pump Disch valves (AF W-2B):
Comments:
Scenario1-1.doc 32 03/24/06 Rev. A
- 1. Maintain running A FW Pump Disch Pressure > 1000 psig
- 2. Maintain either 1) Total AFW flow > 205 gpm OR 2) SG narrow range level in at least one SG > 4% [15% AD VE RSE].
NOTE: If SG B feed flow has been isolated IAW E-0 QRF for ruptured SG actions, then the TD AFW pump will be aligned and operated as necessary to feed SG A only.
RO Verify CI A ctive Status Panel Lights lit.
Verify ESF Equipm ent running:
- 2. RH R Pump s
CRITICAL Start CC Pump B.
TASK
(cont.)
Comments:
Scenario1-1.doc 33 03/24/06 Rev. A
Check RXCP cooling:
- CC valves to RXCPs open - CC-600, CC-601A/B, CC610A/B & CC-612A/B.
- RX CP Thermal B arrier temperatures normal, T614 & T610. [N ormal is 60ºF to 95ºF.]
- RX CP bearing temperatures normal, T132 & T125. [N ormal is Ambient to 150ºF.]
Report CC-610B closed.
CRS Direct starting one Charging Pump.
RO Ensure Charging Pump to be started is in MAN.
Rotate Charging Pump pot fully counter-clockwise to minimum.
Start one Charging Pump.
CREW Check RCS average temperature stable at or trending to 547ºF:
NOTE: If feed to SG B was isolated due to the action of the E-0 QRF, then the crew may not stop the TD AFW Pump since it is the only source of feed to SG A.
BOP If Tave is not stable or trending to 547ºF:
- Transfer Steam Dump s to Pressure Control Mode.
- Control feed flow. Maintain total feed > 205 gpm until narrow range in at least one SG >
4% [15% ADVERSE]
- If cooldown continues, close MS-1A & B.
RO Check Przr PORVS closed.
Comments:
Scenario1-1.doc 34 03/24/06 Rev. A
Check Przr Spray Valves closed.
Check CV-15, Aux Spray Valve closed.
Check if RXCPs should be tripped:
- RCS injection flow indicated on F925 AND
- RCS subcooling <15ºF [45ºF]
If both conditions exist, THEN stop both RXCPs and place the control switches in PULLOUT.
- Any SG pressure decreasing in uncontrolled manner.
CREW Check SG Tubes not ruptured:
- R-15 Air Ejector Exhaust monitor panel & recorder 45716 normal
- R-19 SG B lowdown liquid monitor panel & recorder 45716 normal
- R-31& R -33, Steamline monitors, on SPDS normal Report indications for secondary radiation (R-19 reading elevated).
CRS Inform crew of transition to E-3, Steam Generator Tube Rupture.
Comments:
Scenario1-1.doc 35 03/24/06 Rev. A
Direct monitoring of Critical Safety Function Status Trees.
CRS Direct actions of E -3 Refer to E-3 QRF.
Inform Shift Manager to contact personnel for initiating of surveys and sampling and to review EPIPs.
RO Check if RXCPs should be tripped:
- RCS injection flow indicated on F925 AND
- RCS subcooling <15ºF [45ºF]
If both conditions exist, THEN stop both RXCPs and place the control switches in PULLOUT.
CREW Dispatch an operator to locally monitor AFW Pump operation.
BOP Report SG B level rising faster than expected or rising with feed flow isolated.
Report secondary radiation indications that may identify the ruptured SG:
- R-33 on SPDS
- R-43 on recorder 42562 CREW Direct R adiation Protection/Chemistry to check for indications of radiation or secondary conductivity to confirm ruptured SG.
Identify ruptured SG B.
NOTE: It is expected SG B will be identified with narrow range level rising and feed stopped to SG.
Comments:
Scenario1-1.doc 36 03/24/06 Rev. A
- BT-2B and BT -3B closed
- SD -3B Controller set to 1 050 psig CRITICAL TASKs Report SG B PORV controller in M AN UA L and closed
CREW Direct AO to locally close TD-1-9 & TD-3-9, Main Steam Header B, Trap 9 Inlet and CRITICAL Bypass valves.
TASK BOP Close MS-1B, SG B MSIV, by pressing Main Steam Isolation Initiate Train B pushbutton.
CRITICAL Verify MS-2B, SG B MSIV Bypass, closed.
TASKs Check SG B level > 4% narrow range, and if so stop feed flow to SG B by closing AFW -2B and AFW-10B.
If < 4%, maintain feed flow to ruptured SG until narrow range level indicates > 4%, THEN stop feed flow to ruptured SG.
NOTE: The isolation of feed flow may have already occurred as directed by E-0 QRF.
Those actions also satisfy the Critical Task above for closing AFW-2B (or stopping AFW Pum p B) and closing AFW -10B.
BOP Check SG B pressure > 550 psig.
Reset SI by pressing SI Train A and Train B RESET pushb uttons.
RO Verify annunciators 4702 1-A and 47021-B clear.
CREW Determine required CET temperature based on SG B pressure.
Comments:
Scenario1-1.doc 37 03/24/06 Rev. A
NOTE: Value will be based on SG B at the time this step is performed. SG B press ________
CET desired temp _________
Maintain running A FW Pump Disch Pressure > 1000 psig BOP
- Direct NAO to locally throttle AF W-2C, T/D AF W Pump Discharge as necessary to maintain > 1000 psig discharge pressure.
BOP Dump steam to condenser or atmosphere from SG A.
If dumping steam to condenser:
- Set steam dump to STM PRESS m ode
- Du mp steam at maximum rate
§ Take Steam Dump Control to MAN and rotate pot clockwise to open dumps or
§ Rotate setpoint dial clockwise to lower setpoint until dumps fully open.
- When RCS falls below 540ºF, then take both Trains of Steam Dump Control to BYPASS (cont.) INTLK.
If dumping steam using SG A PORV:
- Take SD-3A controller to MAN and rotate pot clockwise to open valve.
or
- Rotate SD -3A setpoint dial clockwise to lower setpoint un til SD-3A fully opens.
NOTE: While the cooldown is in progress, the procedure directs continuing the actions with step 11 until the requ ired tem perature is rea ched . These steps that may b e perf orm ed during this tim e are noted below [STEP #].
CREW Cooldown R CS C ore Exit Thermocouples read less than CET value determined above.
Close steam dumps or SG A PORV.
Comments:
Scenario1-1.doc 38 03/24/06 Rev. A
Operate steam dumps or SG A PO RV to maintain RC S Tave less than CET value determined above.
BOP [11]
Check SG A level: > 4% narrow range.
If not, m aintain AFW feed > 205 gpm until narrow range level is > 4% , TH EN control feed to maintain SG A level between 4% and 50%.
RO [12]
Check Przr PO RV s and Block Valves:
- Power available to Block V alves by ind icating lights lit.
- POR Vs closed
- At least one PORV Block Valve open.
RO [13, 14, 15]
Place LD-4A to CLOSE.
If not performed earlier, reset SI.
Reset Containment Isolation by pressing CI Train A and Train B RESET pushb uttons.
- Verify annunciators 4702 1-C and 4702 1-D clear.
BOP [16]
Verify Instrument Air to Containment established:
- IA-101, Instr Air to Containment Isol, open
- Containment Air Pressure header > 40 psig on 4150103.
RO [17]
Check if RHR Pumps should be stopped:
- RC S pressure > 150 psig Comments:
Scenario1-1.doc 39 03/24/06 Rev. A
Stop RHR Pumps and place in AUTO.
RO [18]
Establish Charging flow:
If Charging Pump is running then continue with action. If no charging pump is running, check CC flow to RXCP B thermal barrier is isolated (CC-610-B closed), and then proceed to next step
- Open CVC-301, RWST Supply to Charging Pumps
- Close CVC-1, VCT Supply to Charging Pumps
- Start a second charging pump and establish maximum charging flow. (CVC-7 open and Charging Pumps demand > 90%)
CREW [19]
Check if cooldown should be stopped:
CET temperature __________
Close steam dumps or SG A PORV.
Operate steam dumps or SG A PO RV to maintain RC S Tave less than CET value determined above.
BOP Check SG B pressure stable or increasing.
CRITICAL TASK If SG B pressure continues to decrease to less than 250 psi above SG A pressure, then transition to ECA-3.1, SGTR W ith Loss of Reactor Coolant Subcooled Recovery Desired.
(See NOTE below for possible conditions that may affect this Critical Task)
Comments:
Scenario1-1.doc 40 03/24/06 Rev. A
CRS If conditions required, inform crew of transition to ECA-3.1.
NOTE: It is not expected that conditions for transition will occur here. However, with RXCP B stopped and cooler SI injection flow to loop B, the reduced loop flow m ay result in unanticipated reduction of SG B pressure.
If the conditions do warrant transfer, the Chief Examiner will terminate the scenario here. [Training has the shift.] This is done since ECA-3.1 provides no further additional actions for the crew to be evaluated on until step 14, which initiates the RCS coold own (already perform ed to the initial plateau). The critical task is valid for evalu ation if actions the operator took during the cooldown resulted in the plant conditions that require transition to ECA-3.1. Critical Task reads, Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature Post scenario review of this task would then be required.
CREW Check RCS subcooling > 50ºF.
CRITICAL TASK RO Depressurize the RCS to minimize break flow and refill Przr:
Determine normal Przr spray is available using PS-1A.
Energize/deenergize Przr heaters as necessary to maintain saturated con ditions in Przr.
- Fu lly open P S-1A to depressurize RCS until a stopping condition is m et:
(cont.) 1. Przr level >74%
CRITICAL OR TASK 2. RC S subcooling <30 ºF OR
When one of the conditions above is met, close PS-1A.
NO TE: The Contingency Action of step 22.c allows for faster depressurization to prevent SG overfill. The crew may evaluate conditions and chose to use more rapid depressurization using a Przr PO RV . If so the next section covers those actions.
Comments:
Scenario1-1.doc 41 03/24/06 Rev. A
RO Determine one Przr POR V is available.
Energize/deenergize Przr heaters as necessary to maintain saturated con ditions in Przr.
CRITICAL
TASK 1. Przr level >74%
- 2. RC S subcooling <30 ºF OR
When one of the conditions above is met, close the open Przr PORV.
RO If PORV was opened to reduce RCS pressure, check RCS pressure increasing.
RO Check if SI flow should be terminated:
- 1. RCS subcooling greater than 30ºF.
- 2. RCS pressure stable or increasing.
- 3. Przr level greater than 5%.
BOP Check if SI flow should be terminated:
- 4. Secondary heat sink:
- Total feed flow greater than 205 gpm available. [TD AFW P ump available]
- Narrow range level in SG A greater than 4%.
RO If the above conditions are met, stop SI Pump B and place in AUTO.
Comments:
Scenario1-1.doc 42 03/24/06 Rev. A
Following actions to terminate SI flow, the Chief Examiner will terminate the scenario. [Training has the shift.]
Comments:
Scenario1-1.doc 43 03/24/06 Rev. A
Facility: Kewaunee Scenario No.: 2 Op-Test No.: 1 Exam iners: Operators:
Initial Conditions: IC-10; 49% power, Beginning of cycle (BOC)
Ready to start Feedwater Pump B and continue power increase.
Motor Driven AFW A Pump is in PULLOUT.
SI Pump A is in PULLOUT.
Turnover: The plant is at 49% power. Currently at step 4.1.9.d of N-O-03, Plant Operation Greater Than 35%
Power and step 4.1.8.b (4.1.4.i) of N-FW-05A, Feedwater System Normal Operation. The EO is standing by at Feedwater Pu mp B, ready for pump starting. Once FW Pump B is started, the crew is directed to continue power increase to 100 % power. All fuel pre-conditioning requirements for normal power increase have been met. AFW Pump A has been out of service for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to inboard bearing vibration. SI Pump A has been out of service for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> due to failing to develop the minimum dP during IST surveillance.
Event No. Malf. No. Event Event Type* Description Preload RD11 Reactor T rip Breakers Fail to Open on T RIP Sign al RP03 AM SAC A ctuation Override DI-46624-CLOSE Preload ON Bkr 13301 Bus 33 Supply fails to trip. (CRD M G Set A p ower source)
DI-46624-TRIP &
PTL OFF DI-46621-CLOSE Preload ON Bkr 1-308 Bus 33 Sup ply fails to trip. (CRD M G Set A p ower source)
DI-46621-TRIP &
PTL OFF Preload SI05B SI Pump B fails to automatically start. Manual start is available.
D I- 40 0 15 -C LO S E ON Preload D I- 40 0 16 -C LO S E ON RBV-150C and RB V-150D fail to open on high containment pressure.
1 N BOP Start FW Pum p B and resume power increase.
3/4 SRO R RO Follow turbine load increase using rods and/or dilution.
2 RX217 100 I BOP SG B controlling steam flow channel fails high.
SRO 3 NI05D 100 I RO Power Range Nuclear Instrument channel fails high.
SRO D I- 46 1 55 -T R IP O N 4 M BOP Turbine trips without reactor trip . Op eration of (Rod D rive M G S et)
RO supply breakers to Bus 33 fails.
SRO 5 MS02A 75 M RO SG A steam line rupture inside containment. Delayed for 3 minutes BOP following opening of the reactor trip breakers, and ramped over 5 SRO minutes.
6 D I -4 0 01 5 -C L O SE O N C BOP Train B Containment Fan C oil Units Emergency Dampers fail to auto D I -4 0 01 6 -C L O SE O N SRO open. Manual control is available.
7 SI05B C RO SI Pump B fails to auto start. Manual start available. (Only SI Pump)
- (N)ormal, (R)eactivity (I)nstrument, (C)ompon ent, (M)ajor Transient
SCENARIO 1-2 OVERVIEW Event 1 - The plant is at 49% pow er during a startup. Feedwater Pump B is to be started using N-FW -05A, Feedwater System Normal Operation. The Equipm ent Operator (EO) is standing by following turnover and has completed local checks of the pump. O nce the FW Pump is started the crew should resume the normal power increase to 100% at the rate of 1/4 %/minute, as allowed by fuel pre-conditioning.
Event 2 - Following clearly observable plant response from the reactivity changes, the controlling channel for SG B steam flow will fail high. The BOP will take manual control of FW-7B, Main Feed Control Valve, and restore SG level to normal. The channel will be removed from service using A-MI-87. The CRS will address Technical Specification requirements for steam flow channels (TS 3.5.b) in Table TS 3.5-2 and Table TS 3.5-4 Event 3 - Following completion of the removal of service and Technical Specification review for the failed steam flow channel, Power Range N I channel N-44 will fail high. This will cause control rods to insert in AU TO, and will generate a rod withdrawal rod stop. The RO will respond, after identifying the failed channel, by taking rod control to MANUAL. A-NI-48 will be used to identify and respond to the failure, and A-M I-87 will be entered to remove the failed NI channel from service. The CRS will address Technical Specification requirement for the failed channel (TS 3.5.b) in Table TS 3.5-2.
Event 4 - Following completion of the removal of service and Technical Specification review for the failed NI channel, an inadverten t turbine trip signal will be generated. The turbine w ill trip; however, the reactor w ill not trip. The crew will enter E-0 and during the immediate operator actions take actions to manually trip the reactor and deenergize the buses supply the rod drive MG sets. Neither action will be successful, and the CRS will direct transition to FR-S.1. The imm ediate actions will be perform ed including dispatching the Au xiliary O perator (AO to locally trip the reactor trip breakers. Following the completion of step 2 (Verify Turbine Trip) and no sooner than 2 minutes after being notified, the AO will locally trip the reactor trip breakers and stop both MG sets. The AO will then inform the Control Room of actions completed. The crew will continue with actions of FR-S.1, including establishing charging flow and boration flow path.
The crew should transition to E-0 at step 19 of FR-S.1.
Event 5, 6 & 7 - Four minutes following the opening of the reactor trip breakers, a steam line break on SG A will initiate and worsen over the next 5 minutes. The crew should recognize the cond itions for Safety Injection and manually actuate SI, if it has not automatically occurred. The B OP will rep ort that RB V-150C and RB V-150D, Containment Fan C oil Unit Emergency Dampers (Train B), have not opened when Containment pressure has risen above 4 psig. The SRO will direct the dampers be opened manually (Control Room switch). The RO will recognize that no SI Pumps are running, and after SI sequencing is complete, start SI Pump B. The crew will recognize the conditions indicating SG A is faulted inside containment. (NO TE: Depending on the maximum value for containment pressure and transition time from E -0, entry may be mad e into FR-Z.1 Response to C ontainment High Pressure, on an OR AN GE path for Containment CSF.)
Transition will be made to E-2 to isolate the faulted SG. Following isolation and check of secondary radiation indication, transition will be made to E-1. The scenario terminates following transition to E-1 if SG A has completed blowdown, or after evaluation of SI termination criteria in step 12 of E-1, OR at the discretion of the Chief Examiner.
Critical Tasks
- 1. FR-S.1 C - Insert negative reactivity into the core by at least one of the following methods before completing the immediate-action steps of FR-S.1: [Event 4]
- Open the Bus 33 and Bus 43 supply breakers to de-energize the Rod Drive MG sets
- Manually insert Control Rods
- 2. E-0 I - Establish flow from at least one SI pump before transition out of E-0. [Event 7]
- 3. E-2 A - Isolate the faulted SG before transition out of E-2. [Event 5]
SCENARIO 1-2 OVERVIEW Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Page of 39 Start Feedwater Pump B and initiate load increase to 100%.
Event
Description:
Start FW Pum p B using N -FW -05, Feedwater S ystem N ormal Op eration. Crew directs EO to complete checks for pump when running. The crew will initiate a load increase to 100% power using N-O-03, Plant Op eration Greater Than 35% Power, N-T B-54, T urbine and Generator Op eration, and N-C VC -35A , Boron concentration Co ntrol.
Time Position Applicant's Actions or Behavior CUE: Provided in Turnover.
CRS Direct actions of N-0-03 Plant Operation Greater Than 35% Power, step 4.1.9.d.
BOP (Step 4.1.4.i of N-FW-05) Start of FW Pump B
- Take FW-2B, Feedwater Pump B and Discharge Valve, to START.
- Check PPCS FW Pump G roup Output parameters (Group 26 - Feedwater Pump B Temperatures or Graphic Display - Feedwater Pumps) stabilize.
- Check SG levels stable.
- Direct EO to locally verify proper F W conditions (step 4.1.4.k), and perform actions to ensure proper FW operation (step 4.1.4.l).
Comments:
Scenario1-2.doc 5 03/24/06 Rev. A
CRS Direct (Contin uou s Action Step) SG Blowdown be shifted to Mode II with cond ensate to Heater Drain Tank (HDT) per N-BT-07A.
CREW Direct EO to align SG blowdown with Condensate to HDT per N-BT-07A. (step 4.1.2.q)
CREW Contact Chemistry for instructions regarding chemical injection per N-CI-28, Chem ical Injection System.
CRS Direct that reactivity estimate be performed based on power loading RO Perform reactivity estimate for power increase:
Use the Reactivity Plan to plan dilutions and rod m ovem ent for pow er increase from 50% to 100 % power.
Final Rod position: 226 BOP Raise load per N-TB-54, Turbine and Generator Operation, section 4.1.19:
- Review applicable Precautions & Limitations
- Determine maximum load rate % per minute based on fuel performance limit: 40 Mw/hr
- Determine maximum load rate % per minute based on Turbine Operating Limits using figure 1 and Attachment A steps A.7 through A.10
- Take turbine off Valve Position Limiter:
§ Lower the SETTER to less than or equal to the value on the EH Panel Plaque [43.6]
using REFEREN CE CO NTRO L DOW N pushbutton.
§ Set Loading R ate to a rate less than or equal to 5% /min
§ Press GO pu shbutton
§ Wh en the VALVE POS LIMIT green light goes out, press the HOLD pushbutton
- Set valve Position Limit to 100%.
(~ 100%)
- Verify/set loading rate to 1/4%/min.
- Inform (telephone) ATC of rate and amount of load pickup.
Comments:
Scenario1-2.doc 6 03/24/06 Rev. A
- Depress GO
- Verify load increases BOP (N-TB-54 cont.)
(cont)
- Verify Reactive Load rem ains within Figure 5, G enerator C apability Curve, limits
§ If required, adjust Generator #1 Voltage Adjuster switch to change VARs (REACT PWR meter 4460104)
- Verify and maintain turbine and auxiliaries operating conditions:
§ Turbine Lube Oil Cooler outlet temperature 106-110ºF. (PPCS T2165A , Group 28 Turbine Bearings/Oil Temperatures)
§ Exciter air temperature 108-112ºF. (PPCS T2121A, T2122A, T2123A)
§ EH oil temperature 110-120ºF . (Local)
§ Hydrogen seal oil temperature 112-120ºF (Local)
§ Generator H ydrogen temperatures 30-35ºC; 86-95ºF on Gen Stator Temp recorder.
(PPCS T0397, Group 34 Generator Slot Temperatures 2; Recorder 42525)
RO Perform reactivity adjustments:
Rod Con trol (outward motion at - 1.5°F difference Tref-Tave)
AND/OR Boron Concentration Control per N-CV -35A, Boron Concentration Control, section 4.4, D ilute or Alternate Dilute:
Comments:
Scenario1-2.doc 7 03/24/06 Rev. A
- Review applicable Precautions & Limitations.
(cont.)
- Determine rate and magnitude of dilution(s) (total amount from above reactivity calculations)
- Adjust M U-1022/CV-3109 5, Blender Control Rx M u Flow, to required flow rate.
- Set Rx M akeup Totalizer to required quantity.
- Position Reactor Makeup Mode Selector to DILUTE or ALT DIL.
- Position Reactor Makeup Control switch to START
- Verify required change has been achieved by monitoring:
§ Rod Position
§ Boron Con centration
§ Tave Wh en dilution is complete:
- Use Oper Aid 96-3 to verify CVC-403/CV-3109 2, Blender Control BA Flow, set at current RCS boron concentration.
- Verify MU-1022/CV-31095, Blender Control Rx Mu Flow, is set to 60 gpm.
- Verify CVC-406 to AUTO position.
- Position Reactor Makeup Mode Selector to AUTO.
- Position Reactor Makeup Control switch to START.
- At R x M akeup Totalizer:
§ Verify correct quantity added.
§ Reset Rx Makeup Totalizer by pressing the black button.
§ Verify BA Totalizer indicating all ZEROs in window by black button.
- If RCS boron has been changed by > 50 ppm, the operate Przr heaters as necessary to equalize RCS and Przr boron.
NOTE: Following the required reactivity change of ~ 5% power, Event 2 may be started.
Comments:
Scenario1-2.doc 8 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Page of 39 Event
Description:
SG B controlling steam flow channel (FT-474) fails high.
The con trolling Steam Flow channel for SG B fails high indicating 4.5E6 P PH /HR flow . Input to the control circuit demands additional feedwater flow, so FW -7B, M ain Feed Control Valve, will open. SG B inventory will rise until the operator takes manual control of FW-7B. The other Steam Flow channel will ind icate normal flo w (~ 2.0 E6 PP H/H R) .T he operator w ill adjust FW -7B as nece ssary to maintain SG B level within norm al operating ban d (39% -49% ).
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47061-E, S/G B SF>FF 47061-F, S/G B FEEDFLOW EXCESSIVE 47062-D, S/G B PROGRAM LEVEL DEVIATION 47062-E, S/G B BYPASS CV LEVEL DEVIATION 47062-J, STEAM HEAD ER B ISOLATION ALERT 47063-J, MAIN STEAM HEADER B FLOW HI-HI TLA-10 SG TILTS PP CS A larms:
L0461A S/G A Chan 1 Level FI-474, S/G B Steam Flow at top of scale; FI-475, S/G B Steam Flow stable at ~2E6 PPB/HR LI-471, LI-472 and LI-473 S/G B level rising.
FW -7B Va lve Position Demand and A ctual (Position) Indication rising.
FI-476 and FI-477 , S/G B Feed Flow indications rising.
BOP Identify and report FI-474 failed high.
Take FW-7B controller to MANUAL.
CREW Address Annunciator Response for 47061-E, 47061-F, 47062-E and/or 47062-F.
Comments:
Scenario1-2.doc 9 03/24/06 Rev. A
Report that if the alarm is due to a failed instrum ent:
- Verify the alarm was caused by failure of S/G B Steam Flow FT-474 AND position FW-7B to MANU AL.
- Go To A-MI-87.
- Refer to A -FW -05, Ab normal Feedwater System Op eration , when returning F W-7B to AUTO.
(NOTE: Addressing the Annun ciator Response is norm ally done by the off operator, but may b e perf orm ed by the involved op erator if con ditions dictate.)
CRS Direct the BOP to control SG B level with FW-7B in MANU AL.
CRS Direct actions of A-MI-87, B istable Tripping for Failed Reactor Protection or Safegu ards Inst.
CRS Check Technical Specifications for instruments with bistable tripping requirements [TS 3.5.b]:
TS Table 3.5-2, item No. 16 (Steam Flow/Feedwater Flow Mismatch) - 2 with 1 required.
TS Table 3.5-4, No. 2.a (Hi-Hi Steam Flow with SI) - 2/loop with 1 required.
TS Table 3.5-4, No. 2.b (Hi Steam Flow and 2 of 4 Lo-Lo T avg with SI) - 2/loop with 1 required.
CRS Ensure I&C (Work Control/Work Week Coordinator) is notified of status of FT474.
CRS Declare FT 474 channel out-of-service (OO S).
CRS Ensure bistables for FT474 are to be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of declaring OOS.
CRS If desired, direct I&C to check for redundant channel bistable status by performing SP 47-316G , Channel 3 (B lue) R eactor Protection Logic Test.
NO TE : Time W arp may be used at this point to have the check of redundant bistables complete.
CUE: SP 47-316G is complete and no bistables were detected that would cause a reactor trip.
CRS Direct the crew to perform/verify Prerequisite Alignment of Attachment I for FT474.
Comments:
Scenario1-2.doc 10 03/24/06 Rev. A
BOP Position Steam Flow Channel Selector switch for S/G B 46549/HFC-475 to 475/YELLOW (Channel IV).
NOTE: The FW Flow Channel Selector switch for S/G B 46550/H FC-476 may also be placed to the 477/YELLOW (Channel IV) position, as it is standard practice that the corresponding control channels be powered from the same Instrument Bu s in the event of a bus failure.
RO Act as SECOND OPER for verification of position 46549/HFC-476 in 475/YELLOW.
CRS Direct I&C to trip bistables per Attachment I section 2.0 and 3.0 (NOTE : Th e COMMUN ICAT OR is set rep ort & to receive direction from CR S, and will perform action s for tripping b istables from the Simulator Booth.)
CRS Direct crew to verify control room indications per Attach ment I.
BOP Verify following lit:
§ Annunciator 47063-J, MAIN STEAM HEADER B FLOW HI-HI
§ Annunciator 47062-J, STEAM HEADER B ISOLATION ALERT
§ Annunciator 47061-F, S/G B FEED FLOW EXCESSIVE
§ Annunciator 47061-E, S/G B SF>FF
§ Status Light 44908-0507, M S Hdr B Hi Flow
§ Status Light 44908-0607, M S Hdr B Hi-Hi Flow
§ Status Light 44907-1003, S/G B SF> FF CREW Comp lete P ER FO RM ED BY and V ER IFC ATIO N BY sections of A ttach ment I.
CRS If desired, direct statu s control for FI-474 indication (OOS sticker) and switch 46549/HF C in 475 /YELLO W (CA UT ION tag).
NOTE: At Chief Examiner direction, Event 3 may be initiated.
Comments:
Scenario1-2.doc 11 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Page of 39 Event
Description:
Power Range Nuclear Instrument channel N44 fails high.
Power ra nge NIS outp ut fails to 10 0% of sca le or 1 20% indica ted p ow er for this chan nel.
Control Rods in AUTO w ill begin to step IN due to turbine power - auctioneered high nuclear pow er misma tch. The RO will be req uired to take ma nual co ntrol of rods.
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47031-L, POWER RANGE OVERPOWER ROD STOP 47031-M, POWER RANGE HIGH FLUX 47032-K, POWER RANGE PO SITIVE RATE CHANNEL ALERT 47033-K, POWER RANGE CHANNEL DEVIATION TLA-6, POWER RA NGE RAD IAL FLUX TILT Various PPCS Alarms associated with N44 channel Control Rods stepping IN in AUTO.
RO Identify and report trip failure of Power Range NI channel N44 high.
CREW Determine no valid signal for rods stepping (Tave-Tref within 1.5ºF initially and NO turbine runback in progress, load stable and RU NBACK V PL and R UN BACK REF lights not lit on Turbine C ontrol Panel Limits section.)
RO Place Control Rod Bank Selector in MAN.
Comments:
Scenario1-2.doc 12 03/24/06 Rev. A
CREW Address Annunciator Response.
47031-L and 47031-M: (The other AR Sheets also address the actions below)
- Stop any positive reactivity additions
- Reduce load until alarm clears CREW
- If alarm is caused by instrument failure:
(cont.) § Position Control Rod Bank Selector switch to MAN.
§ Go to A-NI-48
- If alarm is caused by boron dilution, Go To A-RC-36F.
(NOTE: Addressing the Annunciator Response is normally done by the off operator, but may be perform ed by the involved operator if conditions dictate.)
RO If Dilution is in progress, stop dilution by placing Reactor Makeup Control Switch to STOP.
CRS Direct actions of A-NI-48, Abnormal Nuclear Instrumentation.
RO Check Control rod motion stopped.
If NOT stopped and moving due to Power Range channel failure, position Control Rod Bank Selector in MAN.
RO Check 4 Power Range channels operable.
CREW Determine with a single Power Range chann el inoperable, remove the channel from service Comments:
Scenario1-2.doc 13 03/24/06 Rev. A
per A-MI-87.
CRS Direct actions of A-MI-87, B istable Tripping for Failed Reactor Protection or Safegu ards Inst.
CRS Check Technical Specifications for instruments with bistable tripping requirements [TS 3.5.b]:
TS Table 3.5-2, item No. 2 (Nuclear Flux Power Range)
(Low Setting) - 4 with 3 requ ired. Permissible B ypass - P -10 [Currently BYPA SSED ].
(High Setting) - 4 with 3 required.
(Positive Rate) - 4 with 3 required.
(Negative Rate) - 4 with 3 required.
TS Table 3.5-2, item No. 5 (Overtemperature DT) - 4 with 3 required.
CRS Ensure I&C (Work Control/Work Week Coordinator) is notified of status of N44.
CRS Declare N44 channel out-of-service (OO S).
CRS Ensure bistables for N44 are to be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of declaring OOS.
CRS Direct I&C to check for redundant channel bistable status by performing SP 47-316H , Channel 4 (Y ELLO W) Reactor P rotection Logic T est.
NO TE : Time W arp may be used at this point to have the check of redundant bistables complete.
CUE: SP 47-316G is complete and no bistables were detected that would cause a reactor trip.
CRS Direct the crew to perform/verify Prerequisite Alignment of Attachment I for Power Range N44.
- Position UPPER SEC TION switch on Detector Current Comparator to PR N44.
- Position UPPER SEC TION switch on Detector Current Comparator to PR N44.
Comments:
Scenario1-2.doc 14 03/24/06 Rev. A
- Position RO D S TO P BYP AS S switch on M iscellan eous Control and Indication Panel to (cont) BYPA SS PR N44.
- Position POWER M ISMA TCH BYPAS S switch on Miscellaneous Control and Indication Panel to BYPASS PR N44.
- Position N44A drawer CONTRO L POWER breaker to OFF.
BOP Act as SECON D O PER for verification of actions performed above.
CRS Direct I&C to trip bistables per Attachment I section 3.0 and 4.0 (NOTE : Th e COMMUN ICAT OR is set rep ort & to receive direction from CR S, and will perform action s for tripping b istables from the Simulator Booth.)
CRS Direct recover of rod control operation.
RO As directed by CRS, withdraw Control Bank D in 5 step increments to order to match Tave-Tref.
NOTE: The limit on 5-step w ithdrawals in M AN is specified in GNP -03.17.10, Reactivity Management.
CRS When conditions permit, direct positioning Control Rod Bank Selector to AUTO.
RO When directed and conditions perm it (Tave-Tref within 1ºF and no rod control step demand),
place Control Rod Bank Selector in AUTO.
Comments:
Scenario1-2.doc 15 03/24/06 Rev. A
CRS Direct crew to verify control room indications per Attach ment I.
BOP Verify following lit:
§ Annunciator 47033-C, OTDT HIGH
§ Annunciator 47041-R, OTDT CHANNEL RNBACK/RDSTP ALERT
§ Annunciator 47032-K, POWER RANGE POSITIVE RATE CHANNEL ALERT
§ Annunciator 47032-J, POWER RANGE NEGATIVE RATE CHANNEL ALERT
§ Annunciator 47031-M, POWER RANGE HIGH FLUX
§ Annunciator 47033-J, POWER RANGE DETECTOR VOLTAGE LOW
§ Status Light 44907-0404, PR N44 P8
§ Status Light 44907-0504, PR N44 P10
§ Status Light 44907-0604, PR N44 LOW RANGE HI FLUX
§ Status Light 44907-0704, PR N44 HI RANGE HI FLUX
§ Status Light 44907-0508, LOOP A OTDT
§ Status Light 44907-0804, PR N44 HI FLUX RATE
§ Status Light 44906-0602, N44 ROD STOP BYPASSED
§ Status Light 44904-0201, LOOP A CHAN 4 OTDT CREW Comp lete P ER FO RM ED BY and V ER IFC ATIO N BY sections of A ttach ment I.
CRS If desired, direct status control for N-44 indications (OOS stickers) and N44 drawer (power switch) (CA UT ION tag).
CRS Direct remaining actions of A-NI-48.
RO Verify annunciator 47032-L clear OR on D etector Current Comparator drawer, check under Up per S ection ALL CHA NN ELS BELOW 50% F.P. light lit.
Verify annunciator 47032-M clear OR on Detector Current Comparator drawer, check under Low er Section ALL CHA NN ELS BELOW 50% F.P. light lit.
Comments:
Scenario1-2.doc 16 03/24/06 Rev. A
Check both Intermediate Range channels operable.
Check both Source Range channels operable.
[END OF A-NI-48 PROCEU RE STEPS]
RO If dilution was secured due to N44 failure, restore Reactor makeup to AUTO per N-CVC-35A:
Obtain current RCS boron concentration.
If required use Oper A id 96-3 and adjust C VC -403/CV3 1092, Blender Control BA F low, to provide makeup at current RCS boron concentration.
Position Reactor Makeup Mode Selector to AUTO.
Position Reactor makeup Control Switch to START.
Observe VCT level to verify proper automatic control operation.
NOTE: At Chief Examiner direction, Event 4 may be initiated.
Comments:
Scenario1-2.doc 17 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Page of 39 Event
Description:
Turbine Trip with ATW S.
A turbine trip signal is generated and the turbine trips. The reactor trip does not occur and the manua l actuation of a reactor trip from the control room will also fail. The crew will attempt to remove power to the Rod D rive MG set buses, allowing the rods to drop; however, the breakers to Rod Drive MG Set A will not open (Bkr 13301 Bus 33 Supply Breaker and Bkr1-308 Bus 33 Supply fail to trip.). When an operator is dispatched to open the Reactor Trip Breakers locally, the reactor trip breakers will open.
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47051-S, TUR BIN E TR IP 47032 -A, TUR BIN E TR IP RE ACT OR T RIP [First Out Annunciator]
Turb ine trip indications:
HP Im pulse pressure trending to ZERO (PI-485 & P I-486).
Turbine Stop Valve green CLO SE indications lit.
Reactor T rip B reake r A and B red lights lit.
Power Range Instruments indicating above 5% power Control Rod Position indications at 226 for Shutdown Banks And Control Banks A & B and above ZERO for Control Banks C & D.
CREW Identify turbine trip.
Report failure of reactor to trip.
CRS Direct manual reactor trip.
CREW Perform Immediate A ctions of E -0 (first 4 steps are so designated):
Comments:
Scenario1-2.doc 18 03/24/06 Rev. A
RO Verify reactor trip.
Report failure of reactor to trip.
- Reactor trip breakers NO T open
- Rod Positions indications greater than 7.5 steps
- Rod Bottom lights NO T lit
- Neutron flux not less than 5%.
RO Manually trip the reactor (press the Reactor Trip button on panel with R od Controls)
(cont.)
BOP Manually trip the reactor (press the Reactor Trip button on panel with Turbine C ontrols)
RO Report failure of reactor trip.
Drive rods IN.
NOTE: Rods may be left in AU TO to drive in as long as inward rod motion is apparent. If rod motion stops rods are to be taken to MAN and inserted.
BOP Take the following breakers to TRIP position:
- BK R 13301, Bus 33 SU PPLY (Red label)
- BK R 14301, Bus 43 SU PPLY (red label)
Report failure of breakers to open and deenergize Bus 33.
Verify turbine trip:
- Turbine Stop V alve green CLOS E indications lit.
Verify pow er to either Bus 5 or Bus 6 (White voltage lights lit)
Comments:
Scenario1-2.doc 19 03/24/06 Rev. A
NOTE:
The above actions may be taken by the BOP as part of his immediate actions of E-0, prior to the determination of the need to go to FR-S.1.
NOTE: Depending on timing for performing the Immediate Actions, reactor power may be below 5% due to the operator driving in rods, if so transition to FR-S.1 is NOT required.
RO Report reactor power is GREA TER T HAN 5% .
CRS Verify actions of E-0.
Read step 1 and check actions taken.
If reactor power is greater than 5%, announce transition to FR-S.1, Response to Nuclear Power Generation/ATWS. (Sep 1.c CA)
CREW PERFOR M Immediate A ctions of FR-S.1 RO Verify reactor trip.
Report failure of reactor to trip.
- Reactor trip breakers NO T open
- Rod Positions indications greater than 7.5 steps
- Rod Bottom lights NO T lit
- Neutron flux not less than 5%.
Manually trip the reactor (press the Reactor Trip button on panel with R od Controls)
CRITICAL Manually insert Control Rods TASK (if in FR-S.1)
(NOT E: The insertion performed as directed in E-0, CA step 1.b.1) also counts for this Critical Task.)
Comments:
Scenario1-2.doc 20 03/24/06 Rev. A
NO TE : The steps for deenergizing Bus 33 and Bus 43 need not be performed again since the Breaker controls are in the TRIP position.
CREW Dispatch AO to locally open the Reactor Trip breakers and to Position the Rod D rive MG Set Motor and Generator Circuit Breaker Control Switches to TRIP.
(NOTE: The CO MM UN ICATO R is set receive direction from crew, and will perform actions above from the Simulator Booth 2 minutes after receiving direction AND FR-S.1.
step 3 is initiated.)
BOP Verify turbine trip:
- Turbine Stop V alve green CLOS E indications lit.
[This completes the Immediate Actions of FR-S.1]
BOP Check both MD A FW Pum ps running; if NOT, manually start pumps. [NOTE: AFW Pump A is OOS]
Check TD AFW Pump running OR start TD AFW Pump.
NOTE : The next malfunction (Steam line break in Containment) is set to occur 3 minutes following the opening of the reactor trip breakers. This may occur while still performing actions of FR-S.1. The actions here will also include those actions for the condition if SI is actuated.
(cont.)
If any SI Pump is running, open Przr PORVs to obtain SI flow greater than 100 gpm.
Starting the S I P um p here, if If SI flow is greater than 100 gpm AND additional charging flow is NOT desired then do NOT conditions establish charging flow & boration path, otherwise establish charging flow.
warran t, will satisfy NO TE : The C harging Pu mps are load shed when SI actuates.
Comments:
Scenario1-2.doc 21 03/24/06 Rev. A
the Critical Establish Charging flow:
Task
- Start charging pumps as necessary to establish 2 running.
iden tified in E-0 below.
- Verify CVC-11/CV31229, Charging Line Isolation open.
- Fully open CVC -7/CV-31103 , Charging Control Chg Line.
- Increase charging pump speed as necessary to establish maximum available charging flow
(~ 75 gpm indicated FI-128)
RO Align boration path:
(cont.)
- Start both Boric Acid Transfer Pumps in FA ST speed
- Open CVC-440, Em ergency Boration valve.
- Check P rzr pressure less than 2335 psig
- Verify charging flow greater then 40 gpm.
Continue boration until Cold Shutdown Boron Concentration is achieved (RD-6.7) [~1795 ppm @ 2000 M WD /MTU burnup)
BOP Verify Containment Ventilation Isolation:
- Cn mt Purge/Vent Supply & E xhaust closed - RBV -1, R BV -2, R BV -3, R BV -4, R BV -5 TAV-12.
Scenario1-2.doc 22 03/24/06 Rev. A
NO TE : If SI has actuated at this point, steps 3 through 16 of E -0 should be perform ed as time perm its. Th e CRS will usually direct the BOP to perform these actions while continuing in FR-S.1 with the RO.
The actions for the operator performing the steps of E-0 are located under the next event.
RO Check that reactor is tripped.
BOP (RO) Check that turbine is tripped.
BOP Check SG narrow range level in at least one SG greater than 4% [15% for ADVERSE Con tainment].
If NOT, verify total feed flow greater than 410 gpm (sum of indicated flow 414107 AFW H dr A Flow and 41042 02 A FW Hdr B Flow).
Control feed flow to maintain SG narrow range level between 4% [15%] and 50%.
N OTE : Adverse Containment occurs when containment pressure is above 4 psig or containment radiation is above 1E5 R/hr.
RO Verify all dilution paths isolated:
- MU -1022, Reactor makeup W ater to Blender
- Direct the AO to locally verify the following are closed: MU-1025, MU-1024, CVC-423, MU -1031A and MU-1031B CREW Check for reactivity insertion from uncontrolled cooldown:
- RCS temperature decreasing in uncontrolled manner
- Any SG pressure decreasing in uncontrolled manner If no uncontrolled cooldown, then stop any uncontrolled cooldown and continue actions for checking Core Exit TCs; otherwise continue with attempts to isolate cooldown source.
Comments:
Scenario1-2.doc 23 03/24/06 Rev. A
NO TE: These actions will be performed if the next event is active.
BOP (RO) Check Main Steamline Isolation and Bypass valves closed [MS-1A/B and MS-2A/B; MS-2A/B are normally closed at pow er].
If required, Actuate Main Steam Line Isolation train A and Train B to close MS-1A and MS-1B respectively.
Check if TD AFW should be stopped.
BOP (RO) Check if SGs are faulted:
- Any SG pressure decreasing in uncontrolled manner
Performing
- Verify BT-2A and BT-3A closed the actions here sa tisfy
- Verify BT-31 A and BT -32A, SG S ample Isol, closed [dual lights]
Verify Reactor subcritical:
- 1. Power Range channels (N41-N43) less than 5%.
Comments:
Scenario1-2.doc 24 03/24/06 Rev. A
- 2. Intermediate Range channels negative SUR.
CRS Ensure CA UT ION is read and understood by crew to continue boration to obtain C old Shutdown Boron Concentration.
Transition to E-0 step 1.
CREW Monitor Critical Safety Function Status Trees.
NOT E: Continued under Event 5, 6 & 7.
Comments:
Scenario1-2.doc 25 03/24/06 Rev. A
Op-Test No.: 1 Scenario No.: 2 Event No.: 5, 6 & 7 Page of 39 Event
Description:
SG A steam line ruptures inside containm ent.
Train B Containmen t Fan C oil Unit dam pers fail to shift to accident mode.
SI Pum p B fa ils to auto start on SI sequencer.
Three minutes following the opening of the reactor trip breakers, SG A steamline will rupture in containment result in full shear over a 5-minute ramp. Containment pressure will rise and Prz r pre ssure, Przr pre ssure and RC S tem perature w ill lower resulting in SI actua tion, M ain Steamline Isolation and Containment Spray actuation. During the event the Train B CFCU dampers which open on 4 psig pressure in Containment will fail to open, requiring the operator to manually open them. SI Pump B will fail to auto start and must be manually started.
Time Position Applicant's Actions or Behavior CU ES: Ann unciato r Alar ms:
47021-A, SI TRAIN A ACTUATED 47021-B, SI TRAIN B ACTUATED 47021-C, CI TRAIN A ACTUA TED 47021-D, CI TRAIN B ACTUA TED 47022-D, CONTAINM ENT H IGH PRESSU RE SI 47022-B, MAIN STEA M HEAD ER A LO W PR ESSURE SI S/G A pressure lowering.
Containment humidity and pressure rising.
RCS pressure, temperature and Przr level lowering.
ECCS/ESF equipment started.
Containment Fan Coil Unit (CFCU ) Emergency Damper position indication green light lit when Conta inment pressure is greater than 4 psig. (RBV 150C & R BV -150D ). RBV -10A/B red lights lit.
SI Pump B NOT running (green light lit / no SI flow indicated) following sequencing of ECCS
/ESFAS equipment. (Step 1 of SI sequence)
Comments:
Scenario1-2.doc 26 03/24/06 Rev. A
Note: If one of the operators w as assigned to perform E-0 steps 3-16 while performing F R-S.1, the CRS may choose to review the actions taken and conditions noted and begin actions where the operator stopped.
RO Verify reactor trip.
BOP Verify turbine trip:
- Turbine Stop V alve green CLOS E indications lit.
Verify pow er to either Bus 5 or Bus 6 (White voltage lights lit)
CREW Check both trains of SI actuated:
An nunciator 47 021-A and 47021-B - SI Train A(B) A CT UA TE D lit.
CREW NOTE: This action may be performed at any time based on judgment of CRS and CREW . (and earlier actions taken)
Implement E-0 QRF Item 3 FAULTED SG ISOLATION CRITERIA:
If any SG p ressure decreasing in an uncontrolled m anner OR any SG completely depressurized, AND remaining SG is intact, THEN the following may be performed:
- Maintain total feed flow greater than 205 gpm until narrow range level in at least one SG is greater than 4% [15% ADV ERSE] [4104202 AFW H DR B F LOW ]
- FW-10A/B, SG A & B Bypass Flow Control valves, closed.
Comments:
Scenario1-2.doc 27 03/24/06 Rev. A
CREW Make plant announcement that Safety Injection has occurred.
Dispatch EO/AO to Locally monitor AFW Pump operation:
BOP Check if steamline isolation is required:
- Containment pressure > 17 psig.
Verify MS-1A, SG A M ain Steam Isolation, closed.
If NOT and conditions required it closed, press Main Steam Line Isol Train A pushbutton.
Verify MS-2A, SG A M SIV Bypass, closed.
NOTE : If Containment pressure is > 17 psig, both steamlines should be isolated, so MS-1B and MS-2B will be verified closed.
CREW Verify Containment Spray not required:
Check containment pressure (Cntmt Wide Range Pressure recorders 42597 & 42 598) have remained below 23 psig.
If NOT, verify containment spray initiated. [Annunciator 47021-F CONTAINMENT SPRAY AC TU AT ED lit and Panel 44910, SI AC TIV E, R ow 10 Status Lights lit)
BOP Verify Containment fan Coil Units running Verify SW-903 A, B, C & D CNTM T Fan Coil Unit SW Return valves open.
When containm ent pressure exceeds 4 psig, verify RB V-150A, B, C & D , CN TM T Fan C oil Unit Emergency Dampers open Comments:
Scenario1-2.doc 28 03/24/06 Rev. A
Report RBV-150C & D NOT open.
Manually open RBV-150C & D.
Verify Aux Bldg Special Ventilation running:
- An nunciator 47 052-G NO T lit.
- Zone SV Fans A and B running.
BOP Verify Service W ater alignment:
(cont.)
- Verify all SW Pumps running
Verify AFW Pump s running:
- 2. Check AFW Pump B running
- 3. Check TD AFW Pump running (red light lit for MS-102, T/D AFW Pump Main Steam Isol, and discharge pressure on 41040.
Throttle AFW Pum p Disch valves:
- 1. Maintain running A FW Pump Disch Pressure > 1000 psig
- 2. Maintain either 1) Total AFW flow > 205 gpm OR 2) SG narrow range level in at least one SG > 4% [15% AD VE RSE].
Comments:
Scenario1-2.doc 29 03/24/06 Rev. A
RO Verify CI A ctive Status Panel Lights lit.
RO Verify ESF Equipm ent running:
(cont.) 1. SI Pumps Report SI Pump B NOT started. [SI Pump A not running - OOS]
CRITICAL Manually start SI Pump B.
TASK
- 2. RH R Pump s
- 3. CC Pumps
- 4. Check SI Active Panel lights lit [SI Pump A not lit.]
Verify SI flow on F92 5 if RC S pressure is < 2200 psig [20 00 psig AD VE RSE].
Check RXCP cooling:
- CC valves to RXCPs open - CC-600, CC-601A/B, CC610A/B & CC-612A/B.
- RX CP Thermal B arrier temperatures normal, T614 & T610. [N ormal is 60ºF to 95ºF.]
- RX CP bearing temperatures normal, T132 & T125. [N ormal is Ambient to 150ºF.]
CREW Check RCS average temperature stable at or trending to 547ºF:
NOTE : If blowdown of SG A is complete at this time, the RCS temperature may be trending up and the following action step w ould not be performed. A lso for the follow ing step, the PO RV s may be cycling and passing w ater due to heatup and injection refill of Przr.
Comments:
Scenario1-2.doc 30 03/24/06 Rev. A
- Transfer Steam Dump s to Pressure Control Mode.
- Control feed flow. Maintain total feed > 205 gpm until narrow range in at least one SG >
4% [15% ADVERSE]
- If cooldown continues, close MS-1A & B.
RO Check Przr PORVS closed Check Przr Spray Valves closed.
Check CV-15, Aux Spray Valve, closed.
Check if RXCPs should be tripped:
- RCS injection flow indicated on F925 AND
- RCS subcooling <15ºF [45ºF]
RO If both conditions exist, THEN stop both RXCPs and place the control switches in PULLOUT.
(cont.)
- Any SG pressure decreasing in uncontrolled manner.
Comments:
Scenario1-2.doc 31 03/24/06 Rev. A
NO TE: Transition may be made to F R-P.1 if the cooldow n is such that the INTEGR ITY status tree indicates a RE D or OR AN GE Path. The steps to be perf orm ed are covered further dow n after the E-2 & E-1 actions.
CRS Inform crew of transition to E-2, Faulted SG Isolation.
Direct actions of E-2.
Inform Shift Manager to review EPIPs.
Read CAUTIONS to crew:
Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown BOP Verify Steamline Isolation For SG A - M S-1A and MS-2 A Closed.
CRITCAL TASK CREW Dispatch Operator For AFW Operation.
BOP Check if any SG NO T faulted: Check pressure in SG any stable or increasing.
Report SG B pressure stable (or increasing).
[NO TE : Pressure in SG B may be decreasing, but is considered stable if the pressure is approximately the saturation pressure for the RCS Loop B cold leg temperature. Cold leg temperature may be depressed due to the SI injection water.]
Comments:
Scenario1-2.doc 32 03/24/06 Rev. A
(cont.)
- BT-2A & BT-3A, SG A Blowdown Isol, closed.
CRITCAL
TASK
- BT-31A & BT-31B, SG Sample Isol, closed.
Check CST level > 20% on 4102901 & 4102902.
CREW Check secondary radiation normal:
- Request Chem istry provide periodic activity samples and Radiation Protection conduct radiation surveys of both SGs
- Check unisolated secondary rad monitors - normal
§ R-31& R-33, Steamline monitors, on SPDS.
§ SG A & SG B N-16 monitors, recorders 42506 and 42562.
§ R-15, Condenser Air Ejector monitor, panel & recorder 45716.
§ R-19, SG Blowdown monitor, panel & recorder 45716.
BOP Set steam dump to minimize heatup:
If condenser steam dumps available, SG B MSIV (MS-1A) open and CDSR AVAIL DUPM PERM status light (44905-0301) lit, Then:
- Set Steam Dump Control Mode to STM PRESS.
- Verify Steam Dump Pressure Setpoint controller in AUTO.
- Set Steam Release Control Steam Dump Pressure to saturation pressure for RCS Loop B Comments:
Scenario1-2.doc 33 03/24/06 Rev. A
Cold Leg temperature.
- Wh en RCS temperature is less than 540ºF, set Main Steam Dum p Train A and B Interlock Selector to BYPASS INTLK.
If MS-1A and MS-1B closed OR steam dumps not available (as indicated above):
CRS Inform crew of transition to E-1, Loss of R eactor Or Second ary Coolan t.
Direct actions of E-1.
Refer to E-1 QRF.
RO Check if RXCPs should be tripped:
- RCS injection flow indicated on F925 AND
- RCS subcooling <15ºF [45ºF]
If both conditions exist, THEN stop both RXCPs and place the control switches in PULLOUT.
Check RWST level > 37% on LI-920 & LI-921.
- Any SG pressure decreasing in uncontrolled manner.
- Any SG completely depressurized If so, verify steamlines and feedlines isolated.
Comments:
Scenario1-2.doc 34 03/24/06 Rev. A
Check level in at least one SG > 4% [15% AD VE RSE].
- If so, control feed flow to maintain narrow range level between 4% [15% ADV ERSE] and 50%.
- If NOT, maintain total feed > 205 gpm until narrow range in at least one SG > 4% [15%
AD VE RSE].
CREW Check M ain Steamline rad monitors - normal
- R-31& R-33, Steamline monitors, on SPDS.
RO Check Przr PO RV s and Block valves:
- PR-1A and PR-1B, Przr PORV Block Valves have power available.
- PORV S closed.
- At least one Block Valve open.
Isolate letdown:
- Place LD-4A, Letdown Orifice Valve, switch in CLOSE ; verify LD-4B & LD -4C switches in CLOSE position.
RO Reset SI by pressing SI Train A and Train B RESET pushb uttons.
- Verify annunciators 4702 1-A and 47021-B clear.
Reset Containment Isolation by pressing CI Train A and Train B RESET pushb uttons.
- Verify annunciators 4702 1-C and 4702 1-D clear.
BOP Verify Instrument Air to Containment established:
Comments:
Scenario1-2.doc 35 03/24/06 Rev. A
- IA-101, Instr Air to Containment Isol, open
- Containment Air Pressure header > 40 psig on 4150103.
RO Establish Charging flow:
Report no charging pump running.
- Check that CC flow has not been lost the RXCP T hermal Barriers (CC-610A 7 B open)
- Reduce demand on charging pump to be started to ZERO
- Start the selected Charging Pump.
- Raise charging pump speed to establish charging flow.
- Monitor Przr level for > 5% [30% ADVERSE]
CREW Check if SI should be terminated
- 1. RC S subcooling > 30ºF [65ºF ADV ER SE].
- 2. RCS pressure > 2200 psig [2000 psig ADV ERS E] and stable or increasing.
- 3. Przr level > 5% [30% ADVERSE]
- 4. Secondary heat sink:
- Total flow to SG B > 205 gpm
Comments:
Scenario1-2.doc 36 03/24/06 Rev. A
CRS If all conditions for SI termination are met, inform crew of transition to ES-1.1, SI Termination.
If conditions not met then continue.
The Chief Examiner will terminate the scenario at this point. [Training has the shift.]
NOTE: The steps of FR-P.1 are included below, if CSFTs dictate transition for INTEGR ITY path.
CRS Inform crew of transition of FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.
Direct actions of FR-P.1.
CRS Check if FR-P.1 implementation required.
(cont.)
- Check RCS pressure > 150 psig on PI419 or PI420, or recorder 42556.
CREW Check Cold Leg temperatures stable or increasing on recorder 42555.
BOP If NOT, stop RCS cooldown:
- Verify MS-1A closed on faulted SG
- Close MS-100A from faulted SG
RO Check Przr PO RV s and Block valves:
- PR-1A and PR-1B, Przr PORV Block Valves have power available.
- PORV S closed.
- At least one Block Valve open.
Check if any SI Pump running.
Comments:
Scenario1-2.doc 37 03/24/06 Rev. A
Identify SI Pump B running.
CREW Check if SI should be terminated
- 1. RC S subcooling > 80ºF [115ºF A DV ER SE].
If so, Reset SI by pressing SI Train A and Train B RESET pushb uttons.
- Verify annunciators 4702 1-A and 47021-B clear.
Reset Containment Isolation by pressing CI Train A and Train B RESET pushb uttons.
- Verify annunciators 4702 1-C and 4702 1-D clear.
BOP Verify Instrument Air to Containment established:
- IA-101, Instr Air to Containment Isol, open
- Containment Air Pressure header > 40 psig on 4150103.
RO Stop SI Pump A and place in AUTO Stop RHR Pump A and B and place in AUTO.
RO Establish Charging flow:
Report no charging pump running.
- Check that CC flow has not been lost the RXCP T hermal Barriers (CC-610A 7 B open)
Comments:
Scenario1-2.doc 38 03/24/06 Rev. A
- Reduce demand on charging pump to be started to ZERO Start the selected Charging Pump.
Establish 20 gpm charging flow (FI-128).
If transition was mad e to FR-P.1, The Chief Examiner will terminate the scenario at this point. [Training has the shift.]
S Comments:
Scenario1-2.doc 39 03/24/06 Rev. A