ML033100055
| ML033100055 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 10/03/2003 |
| From: | Gosekamp M Entergy Nuclear Vermont Yankee |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-271/03-301 | |
| Download: ML033100055 (59) | |
Text
Appendix D Scenario Outline Form ES-D-1 Vermont Yankee Facility: (1999 NRC)Modified Scenario No.: 1 Op-Test No.:
Examiners: Operators: ACRO CRO CRS Objectives: Evaluate the crews ability to operate plant equipment to support a normal power ascension, respond to and evaluate (Technical Specification) a level instrument failure and the resultant reactivity addition transient. Recognize and take action for a Recirc Pump failure, recognize and limit the positive reactivity from a Recirc Pump speed transient. Determine the affect of a loss of a 480 VAC ECCS bus on plant operation, and to implement the EOPs to monitor and control plant parameters for a major primary containment steam leak resulting in emergency depressurization as well as recognizing the inability to spray the drywell Initial Conditions: lC-G7(Snapshot) 30% power, approaching conditions for second Feedwater Pump Start Turnover: See Attached Shift Turnover Sheet Malf. Event Event Type*
No. Description CRO Continue power ascension IAW OP 0105 CRS CRO Start the second Feedwater Pump CRS ACRO Key 1 Inadvertent RClC initiation (TS)
I CRO RC04 CRS 5 minutes after RFP start Key 2 CRO RR07B B Recirc Pump lower and upper seal failure CRS RR08B Key 3 RRIO CRO I CRS ARecirc Pump speed controller failure, pump speed increasing 100% @
3600 sec ACRO Key 4 ED05C c CRO 480 VAC ECCS Bus 8 fails CRS Key 5
.4% @
300 sec ACRO MS06 M CRO Steam line leak in the drywell - emergency depressurization Key 6 CRS 10% @
1000 sec RH03A c ACRO Drywell Spray Valve does not open (B valves have no power)
RFHP05 N/A HPCl aux oil pump ACB open - out of service for governor oil leak repair P
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor
SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#I)
GENERAL REQUIREMENTS 9 All chart recorders will be rolled forward, timed and dated.
9 Paper from selected chart recorders will be saved for the examination team as requested.
9 All procedures, flow charts, curves, graphs, etc., will be returned to their normal storage place and closed.
9 All markable procedures, boards, etc., will be erased.
9 All paper used by the previous crew will be removed and kept for the examination team as requested.
9 The simulator operator, or designated person, will keep a rough log of all communications into and out of the control room during the scenario as requested by the examination team.
INITIAL SETUP 9 IC- 67. setup for -30% power getting ready to start the C Feedwater Pump P Ensure the A Feedwater Pump is running with C in Standby P Place HPCl out of service (Preinsert RFHPO5, Aux oil pump ACB open) PTL aux oil pump switch 9 Preinsert RH03A (RHR A Cont Spray 26A fails to open) 9 Mark con-demin status board N B I C in service DURING THE SCENARIO The examination team will determine when each event is to be inserted and when to freeze and will inform the simulator operator.
> EVENT I Provide copy of VYOPF 2404.02 for rod withdraw sequence.
Support crew as Reactor Engineer as requested.
9 EVENT 2 If crew continues to raise power direct them to start the second feedpump at 40% power. When directed as A 0 to perform prestart checks for Feedpump start inform Control Room checks are completed. Seal water temperatures are normal after the feedwater pump start 9 EVENT 3 After conditions stable for 5 minutes insert RClC start.
Acknowledge request as I&C. They know of no reason why RClC started. Report that RClC initiation relays K-1 and K-2 are energized, and the investigation continues.
9 EVENT 4 Insert seal leak rate low and ramp up after recognized by crew.
Use RDRI2 to secure seal purge. Recirc cooling is SWR 58
9 EVENT 5 Insert malfunction after the A pump is on master control.
Attempt to provide a slow speed increase to allow operators to recognize it and take actions. Master Controller fails. If they place Ain Manual pump speed control will work.
Acknowledge request as I&C to respond to CR to investigate Recirc Flow Control trouble.
P EVENT 6 Insert malfunction as soon as plant stable following Event 5.
Allow crew time to discuss plant status, plans for continued operation/shutdown. Support crew as requested on bus failure.
It will not be available anytime soon.
P EVENT 7 Insert leak at the lower severity. After the scram insert the leak at the higher severity 9 EVENT 8 Acknowledge request to attempt manual opening of Outbd Drywell Spray Valve (RHR-26A). At Exam Team direction after ED is performed, remotely open requested valve to allow sprays.
Rf RH 46 (RHR26A)
TERMINATION After vessel depressurization and RHR 26A opened via local manual operation or as Exam Team directs.
SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#I)
(con?)
Event No. Malf. No.
EventType* I Event Description Verify RWM latched to GRP 64 RFHP05 Preinsert RH03A Preinsert I RHR CONT SPR VLV (26A) FAIL TO OPEN 1 CRo CRS 1 Continue power ascension IAW OP 0105 2 N CRO Start the second Feedwater Pump CRS ACRO 3 RC04 Key1 I CRO Inadvertent RClC initiation (TS)
CRS 4
RR07B Key2 RR08B Key2 CRo CRS 1 B Recirc Pump lower and upper seal failure 5
RR10 Key3 100% @ 3600 sec I
CRo CRS ACRO I After A pump is on the master controller A Recirc Pump speed controller failure, pump speed increasing ED05C Key4 6 C CRO 480 VAC ECCS Bus 8 fails CRS MS06 Key5 Steam line leak in the drywell - emergency depressurization 7 .4% @ 300 sec M CRO CRS After drywell RRUs started post loss of Bus 8 MS06 Key6 Steam leak will cause drywell temperature to exceed 280 degrees and require RPV-ED. After manual or auto scram on 10% @ 1000 sec high drywell pressure 8 RH03A Preinsert c
SHIFT TURNOVER (#I 1 PLANT CONDlTlONS:
Approximately 30% power Sequence A2 Group 64, Control rod 10-27 No rapid shutdown sequence is available INOPERABLE EQUIPMENTILCOS:
HPCl is out of service for repair of a governor oil leak SCHEDULED EVOLUTIONS:
0 OP 0105 Phase 4 step 24 page 82 0 Raise power to 40% CTP at 1%/ Imin Start C RFP at 40% power for PMT of seal replacement. Place A RFP in STBY At 45% speed transfer Recic pump speed control to master manual control SURVEILLANCES DUE THIS SHIFT:
None ACTIVE CLEARANCES:
0 N/A GENERAL INFORMATION:
CONTROL ROOM SHIFT TURNOVER CHECKLIST &mrb 1 Parameted Allowable Checks Component Condnimit 06 I 18 cs Am sys No Alarms/Opr # I CS-7 A/B cs PP Am AUTOIO r Closed G O O gpm RHR Sys No A l d O p r RHR PP AmIcID AUTO/Opr Open Open Open Open Closed RHR FI-10-139A/B A 5 0 0 gpm 250 - <87.3"F NoAldOpr In AUTO ON Open IHPCI-14.25.19.
. . . I 21,57,58 IClosed HPCI Flow I b v NOTE 1 : STA walkthrough to include status check of the Control Room Pyrotronics Panel.
NOTE 2: In the event minimum shift staffing levels cannot be met, actions to be initiated are specified in AP 0894.
VYAPF 0152.01 NOTE 3: Control Room staff shall contact VELCO whenever abnormal yard conditions exist. (CAR910370Pl) AP 0152 Rev. 22 Page 1 of 1 LPC #5
TECH. SPEC./TEC"ICAL REQUIREMENTS MANUAL, S Y S T E M S K O M P 0 " T S INOPERABLE OPERATIONS REQUIRED SWCRS TECH. DATE/TIME LOGGING, TESTING OR ALLOWABLE DATE/TIME , INITIALS SPEC./TRM DECLARED UNPLANNED OTHER ACTION TIME DECLARED SYSTEWCOMPONENT PARAGRAPH INOPERABLE LCO (ER970390-03) INOPERATIVE OPERABLE mop OF 3*SE, 2 uac & v ' f i o Q - F S /Yd+/5 @'
VYAPF 0152.02 AP 0152 Rev. 22 Page 1 of 1
ov ov ov oa3v oa3v VLS 0x3 sa3 xo H S WYS a=ds
CONTROL ROOM TURNOVER SHEET Date: %dCy Shift: @ Nights
~-
munciators (Existing, New, Nuisance, Disabled, Restored)
Mdue &+et& Afe4.d VYAPF 0152.04 AP 0152 Rev. 22 Page 1 of 1
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: I Page - I- of 10 Event
Description:
Increasing reactor power from 30% CTP to 40% with flow IAW OP 0105 P
Time Position Applicants Actions or Behavior CRS Perform crew brief for the Dower increase CRS Direct continued Dower ascension IAW OP 0105 Phase 4 step 24 Request a peer check for the reactivity increase if one is not assigned Raise reactor power with flow 1% CTP/I Min, For each flow increase:
Turns controller 2-184-16-1N1 B manual knob in the clockwise direction 0 Monitors recirc pumps for expected speed increase CRO 0 Directs RBAO to monitor MG lube oil temperatures Maintains pump speeds within 5% of each other 0 Monitors nuclear instrumentation for proper response Monitors feedwater level control system response to the power increase Monitor plant parameters/assist as necessary ACRO Make preparations for second Feedwater Pump start
~
CRO Report recirc speeds at 45% as indicated on controller 2-184-16-1NlB CRS Direct recirc flow control transferred to master manual control Transfer recirc flow control to master manual control as flows Verify N B speed > or equal to 45% on 2-184-16-1N!B 0 Ensure feedwater low flow interlock is clear (Alarms 9-4-B-6/F-6 Use D (Display) button on controllers 2-184-16-1NB to observe P and S values CRO Adjust master controller SC-2-184-14 to match the speed on the Individual controllers 0 If necessary adjust the Bias on the second controller to be shifted to match its speed to the master controllers speed 0 When speed signals are matched transfer to the master Controller by depressing the auto/manual push button on the Individual controllers A(B).
Appendix D Required Operator Actions Form ES-D-2 Event
Description:
Start second Feedwater pump prior to 40% CTP Position Applicants Actions or Behavior CRS Direct startup of C Feedwater Pump per Phase 4 section B of OP 0105 Start the second feedwater pump per OP 0105 Phase 4.B 0 Review Phase 2 & 4 Precautions and Administrative Limits 0 Verify both heater strings are in service 0 Verify Standby Lube Oil pimp in service Close feed pump discharge valve (FDW-4C) 0 Position C pump control switch to Start ACRO 0 Verify pump breaker closes, discharge valve opens and auxiliary lube oil pump stops 0 Check seal water temp 0 Monitor lube oil and bearing temps until stabilized 0 Monitor running current (max. 666 amps) 0 Check Bus 3 / 4 undervoltage relay targets CRO Request a peer checker if one is not assigned CRO Observe system flow and reactor level stabilizes Report C Feedwater Pump placed in service Place A Feedwater Pump in Standby ACRO 0 Control switch placed in Auto 0 Open Feedwater Pump Discharge Valve (FDW-4A)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Page 3 of I O Event
Description:
Inadvertent RClC start. Electrical short in low level sensing circuit (KI & K2 energize)
Initial Automatic Actions: RClC initiation and injection, No alarms, except for alarm typer Effects (General Sequence): Power and level increase. Very minor (positive reactivity addition)
Enteddirect actions IAW OT 31I O , Positive Reactivity Insertion.
CRS May refer to OT 3114, Reactor High Level Verifies by two or more independent indications that RClC initiation is spurious, informs CRS.
Secure RClC ACRO 0 Press RClC Turbine Trip pushbutton 0 Verify turbine trips and RPM decreasing 0 Report minimum flow valve open CRO I Verify reactor power and level return to normal.
HPCl is Inoperable. Declare RClC hoperable IAW 3.5.E.3 commence a CRS shutdown to 4 5 0 PSlG within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. May call 3.5.G.3 Same actions Direct I&C investigate cause of failure.
CRS I Informs Operations Management of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shutdown LCO
Appendix D Required Operator Actions Form ES-D-2
~ Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Page 4 of 1 0 Event
Description:
B Recirc Pump lower and upper seal failure Cause: Worn seals Initial Automatic Actions: Initially receive alarms 9-4 G-I & G-2 Effects (General Sequence): Both seals on the B Recirc pump fail requiring pump removal and isolation, increasing drywell temperature/pressure until isolated Position Applicants Actions or Behavior
_Ip -
Recognizehake action IAW 9-4 G-2 & G-I , inform CRS 0 Monitor B Recirc Pump parameters CRO / ACRO 0 Determine failure of both pump seals, inform CRS 0 Monitor Drywell equipment drain sump, temperature and drywell pressure Enteddirect actions IAW ON 3142, Recirc Pump Seal Failure 0 Direct B Recirc Pump shutdown and isolation Enteddirect actions IAW OT 3117, Rector Instability, and OT 3118, Recirc CRS Pump Trip 0 May direct monitoring for reactor instabilities Refer to Tech Spec 3.6.G and direct actions for single loop operation, inform RE Secure and isolate the B recirc pump IAW ON 3142 0 Open B Recirc Pump MG Set Drive Motor Breaker 0 Close suction valve RV-43B CRO 0 When suction indicates closed, close discharge bypass valve RV-54B and discharge valve RV-53B 0 Direct Aux Operator to secure seal purge IAW OP 2111 Determine operating point on COLR Figure 2.4-1 CRO Monitor LPRM readings by selecting STBLTY on ERFIS 0 May initiate stability monitoring
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Page 5
-- of 10 Event
Description:
A Recirc Pump speed controller failure, pump speed increasing Cause: Master Controller output failure high Initial Automatic Actions: Reactor power rise, alarms 9-5 D-2 810-3 Effects (General Sequence): Pump speed increasing, power rise Applicants Actions or Behavior Recognize/report rising reactor power, inform CRS Recognizelreport ARecirc Pump speed rising, inform CRS CRO Recognizehake actions IAW 9-5 0 Monitor flow and power to confirm control rod blocks Enteddirect actions IAW OT 31 IO, Positive Reactivity Insertion 0 Direct the manual control of A Pump controller When directed adjust speed of A Recirc Pump to 50-70%
0 Place pump controller in Manual by depressing the auto/manual I
controller push button on controller 2-184-16-1A CRO 0 adjust pump speed by turning the manual knob on 2-184-16-1A to adjust pump speed to 50-70% speed Do not exceed 1% CTP/min power change Contact I&C and inform them of the recirc flow controller failure 1 ACRO Monitor RPV level pressure and power for return to normal Assist as necessary
-+----
I
Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 1 Event No.: 6 P a g e L o f 10
- vent
Description:
Loss of 480 VAC Bus 8 2ause: Bus fault due to ground on 8 nitial Automatic Actions: Half scram, PClS Group 3 isolation, multiple alarms Time Position Amlicant's Actions or Behavior RecognizeAake actions IAW 9-5K-I, inform CRS CRO / ACRO 0 Recognize half scram and PClS GP 3 isolation 0 Recoanize loss of 480 VAC Bus 8 Take actions for loss of Bus 8 0 Direct identification of lost loads 0 Direct backup of PClS GP 3 Refer to Tech Spec 3.5.B Determine 7 day LCO required. B EDG INOP IAW OP 2143 CRS Precaution g Tech Spec 3.10.A.4. Buses 3,4, 8, 9, energized and operable 0 No action statement 0 Recommend a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cold shutdown IAW AP 0151 page 5 responsibility 23. As Time permits or by follow-up questions Direct troubleshooting/repair Determine the following loads lost on Bus 8, inform CRS 0 DrywellRRUs 0 A RPS half scram 0 PClS GP 3 isolation 0 B CRD pump loss 0 BRBCCWpump CRO / ACRO 0 ATBCCWpump BRHR 0 BCS 0 BSBGT Stack Flow Indicator FT-108-22 ODCM Table 3.1.2 CRO B SBLC pump Stack Gas I, II indication loss Loss of RWCU (CU-15 loss of power)
ACRO Vital MG Set swap to DC drive Loss of RClC (RCIC-15 loss of Dower)
Amendix D Reauired ODerator Actions Form ES-D-2 1.: 1 Scenario No.: 1 Event No.: 6 (contd) Page 7 of 10 Backup Group 3 isolation IAW posted Operator Aid CRP 9-3 CRP 9-26 AC-8, DRYWELL PURGE HVAC-9, RB VENT SUPPLY AC-7A, DRYWELL VENT HVAC-10, RB VENT SUPPLY AC-6A, DRYWELL 3 VENT HVAC-12, RB VENT EXHAUST AC-20, Nz MAKE-UP HVAC-I 1, RB VENT EXHAUST AC-10, TORUS PURGE RB supply/exhaust fans off AC-7B, TORUS VENT RSF-1A off REF-1A off AC-GB, TORUS 3 VENT RSF-1B off REF-1B off AC-9, AIR PURGE SUPPLY AC-22B, DRYWELL MAKE-UP CRP 9-25 SGT-6, VENT TO SBGT SBGT ACRO AC-23, N2 PURGE SUPPLY REF-2A on AC-7, VENT TO RTF-5 REF-2B on AC-22A, TORUS MAKE-UP CA-38A, CTMT COMPR SUCT CRP 9-47 CA-38B, CTMT COMPR SUCT VG-26, CAM SUPPLY INBD VG-76A, CAM RETURN INBD VG-23, CAM SUPPLY OUTBD VG-76B, CAM RETURN OUTBD CAD Panel A NG I I A , 12A, 13A VG 22A, 9A CRS Direct drywell RRUs restarted Restart drywell RRUs CRP 9-25 RRU 3NB control switch to A&B run ACRO CRP 9-25 RRU 4NB control switch to A&B run
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 P a g e L o f 10 Event
Description:
Steam leak in drywell - emergency depressurization Cause: AMSL 18 inch pipe rupture between reactor vessel and flow restrictor Initial Automatic Actions: High drywell pressure scram Effects (General Sequence): Slowly rising drywell pressure to scram setpoint then rapid increase Time Position Applicants Actions or Behavior Recognizing rising drywell pressure, inform CRS 0 Check backpanel indications Recognize/take actions IAW 9-5 G-I & F-I 0 Check for leaks CRO / ACRO Maximize drywell cooling MCA keylock to bypass on CRP 9-25 0 CRP 9-25 RRU 3NB control switch to A&B run. (already done)
CRP 9-25 RRU 4NB control switch to A&B run. (already done)
Enteddirect actions IAW OT 31 1I,High Drywell Pressure CRS Direct power reductiodtransfer house loads/manual scram Direct manual scram per OT 3100 and enterldirect actions IAW EOP-I and 3.
Insert manual scram when directed/recognize automatic scram on high drywell pressure, inform CRS.
0 Press manual scram pushbuttons 0 Depress PB 1 on feedwater master controller CRP 9-5 0 Reactor mode switch to shutdown CRP 9-5 0 Insert IRMs/SRMs on CRP 9-5 0 Select IRM recorders on CRP 9-5 CRO Report reactor power ~ 2 %
Report all control rods inserted 0 After verifying the RPV is recovering leave one RFP running, and place one in standby, and one in pull to lock CRP 9-6 0 Verify closed scram discharge vent and drain valves (6) on CRP 9-5 Recognize/report EOP-1 and 3 entries on high drywell pressure.
Monitor and report RHR, CS, EDG and SBGT initiations and PClS GROUP 2, 3, noting failures from previous power failure.
ACRO 0 Group II valve switches to the closed position 0 LRW 82/83/94/95 on CRP 9-4 CRO Maintain level in 127-177 using preferred system (Feedwater and RCIC)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (contd) Page 9 of 10 Time Position Applicants Actions or Behavior Close MSlVs to control cooldown rate if necessary due to steam flow from auxiliaries.
ACRO Attempt reactor pressure control below 1055 psig, report pressure lowering with MSIVs closed.
Report drywell/torus pressure trending up to 10 psig.
CRS Direct Torus Sprays on ARHR loop before torus pressure reaches 10 psig.
Spray the torus as directed Place 0 A and D RHR pumps in PULL TO LOCK.
OR 0 B and C RHR pumps in PULL TO LOCK.
Close/verify closed HX BYPASS RHR-65A 0 Verify adequate SW pumps are operating to handle RHRSW pump demand.
0 Verify no more than one SW pump is in standby mode.
IF a LPCl initiation signal is present, THEN place RHRSW PP A&C LPCl AUTOSTOP OVERRIDE SWITCH keylock switch to MANUAL OVERRD (3-M-2 will annunciate).
ACRO 0 Start RHRSW pump A or C When conditions permit, verify RHRSW pump cooling water flow is 3 - 6 gpm.
If necessary, adjust RHRSW DISCHARGE, RHR-89A as follows:
0 Maintain RHRSW heat exchanger flow 2950 to 3140 gpm.
Maintain RHRSW pressure greater than 20 psid above RHR pressure.
IF reactor water level is greater than TAF, THEN 0 turn the RHR A/C LOGIC CTMT SPRAY VLV LPCl SIG BYPASS to MAN.
0 Open TORUS SPRAYKLG RHR-39A 0 Open TORUS SPRAY RHR-38A Direct drywell sprays with ARHR loop before reaching Unsafe region of DWSIL graph CRS 0 Verify torus level c 22.8 ft and in Safe 0 Verify safe on DSlC 0 Verify RRUs tripped or order shutdown
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Page I O of 10 Event
Description:
Drywell spray valve does not open Cause: Containment spray valve mechanically binds in the closed position Initial Automatic Actions: N/A Effects (General Sequence): Valve will not open from Control Room
~
Time Position Applicant's Actions or Behavior Place " A RHR loop in Drywell spray per OP 2124, Appendix C 0 Open RHR-31A 0 Open RHR-26A ACRO 0 Recognize loss of valve position indication when drywell spray valve opened 0 Report inability to open RHR-26A Direct ACRO to coordinate with Aux Operator to locally open RHR-26A loop spray valve 0 Recognize RHR-26B not available due to bus loss CT CRS Recognize torus IeveVpressure cannot be maintained in the "safe" region of PSP graph or drywell temperature cannot be maintained below 280°F, Exits EOP-1, RPV pressure leg, enteddirect actions IAW EOP-5 0 Direct rapid depressurization with bypass valves. May go direct to Emergency Depressurization Open bypass valves by going to raise on the bypass opening jack on CRP 9-7 ACRO 0 Do not exceed 40% steam flow as indicated on CRP 9-5 steam flow indicators Perform an Emergency Depressurization when directed Prevent injection from CS and RHR Pumps:
0 Core spray AIB pump control switches pull to lock 0 RHR A/B/C/D pump control switches pull to lock Open all SRVs on CRP 9-3 0 RV-71A switch to open ACRO 0 RV-71C switch to open 0 RV-71B switch to open 0 RV-71D switch to open Report Aux Operator is able to manually open " A RHR Drywell Spray valve Recognize/report lowering drywell pressure once valve is open if RHR A loop pumps are running at that time.
Classify event IAW A 0 3125 CRS Alert per A-3-b/A-3-a
Appendix D Scenario Outline Form ES-D-1 acility: Vermont Yankee (new) Scenario No.: 2 Op-Test No.:
ixaminers: Operators: ACRO CRO CRS Dbjectives: Evaluate the crews ability to operate plant equipment in response to a loss of the startup transformers during closed cycle operation. Evaluate the Technical Specification for a loss of one off-site power source, and commence a plant shutdown to ensure NPDES compliance.
Recognize a stuck FWRV and take actions to avert a high reactor water level scram. Recognize and respond to an LPRM upscale failure. Recognize and respond to a loss of main condenser vacuum, ATWS, and SLC system failures.
nitial Conditions: IC-9, 100% power, preparing to chlorinate the Circ Water System rurnover: See Attached Shift Turnover Sheet Event Event Event Type*
No. Malf. No. Description ACRO 1 Place CW in Closed Cycle for chlorination CRS ACRO Key 1 2 C CRO Loss of Startup Transformers ED-02A CRS Preinsert FW-O9A R CRO Power Reduction with stuck Feedwater regulating valve 3 C CRS ANN Failure Soft panel FRV A lockup red light out 9-5-E-2 Key 2 ACRO LPRM upscale failure, APRM D upscale NM2-24-41B 4 I CRO APRM D failure is Automatically deleted when LPRM 24-41 B is NM5D 97%
CRS bypassed Key 3 ACRO 5 MC-8 c CRO Main Condenser air inleakage (minor) 7% CRS Key 3 modify ACRO After control rod insertion for event 5 has started.
MC-8 M CRO Main Condenser large air Leak 50%
CRS Loss of Vacuum Turbine Trip / LNP 120 See Preinsert ACRO RD 12A 69% M CRO Hydraulic ATWS / Level Power Control I RD 12B 74% CRS Preinsert CRO SLOl A SLC A Pump Failure / B Squib Failure CRS SL02 B Bypass APRM A Preinsert APRM A INOP, Bypass APRM A prior to insertion NM-O6A
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor
SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#2)
GENERAL REQUIREMENTS All chart recorders will be rolled forward, timed and dated.
Paper from selected chart recorders will be saved for the examination team as requested.
All procedures, flow charts, curves, graphs, etc., will be returned to their normal storage place and closed.
All markable procedures, boards, etc., will be erased.
All paper used by the previous crew will be removed and kept for the examination team as requested.
The simulator operator, or designated person, will keep a rough log of all communications into and out of the control room I during the scenario as requested by the examination team.
INITIAL SETUP
> IC-9 Summer Time IC-Hybrid Cycle P APRM A INOP and bypassed DURING THE SCENARIO The examination team will determine when each event is to be inserted and when to freeze and will inform the simulator operator.
> EVENT1 If asked, chemistry is chlorinating service water. When asked if weir is overflowing:
.. if level is > 225 ft, yes if level is 225 ft, no When directed report traveling screens in off and service water strainer breakers open P EVENT2 OSAO when asked - report MOD T-3 open on all 3 phases, and visible damage to the startup transformers. If chemistry is asked, no chlorine has yet been added to the circ water system
> EVENT3 If TBAO is sent to the A FWRV report no obvious damage is visible. If the crew recommends locking up the A FWRV direct them as Operations Management to transfer control to local manual and lock up the valve.
> EVENT 4 If reactor engineer is asked about bypassing LPRM 24-41 B, inform them that as long as Technical Specifications are satisfied it can be bypassed. When LPRM 24-41 B is bypassed verify that APRM D failure (NM05D) automatically deletes itself. If not delete it manually.
> EVENT 5 No cause for the main condenser air leak will be found
> EVENTS 7 & 8 There appears to be nothing wrong with SLC pump A or Squib valve B (this infers an SLC switch failure)
TERMINATION P SLC injecting 9 RPV level controlled > -19
> Control rod insertion in progress
> Containment parameters under control
> Exam Team directs
SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#2)
(con't)
Event Event Type*
Malf. No. Description ACRO Place CW in Closed Cycle for chlorination CRS ACRO Key 1 C CRO Loss of Startup Transformers ED-02 CRS Preinsert R FW-O9A c CRO Power Reduction with stuck Feedwater regulating valve ANN Failure CRS Soft panel A FRV lockup light out 9-5-E-2 Key 2 ACRO NM2 24-41B I CRO LPRM upscale failure, APRM upscale failure NM6D CRS Key 3 ACRO MC-8 C CRO Main Condenser air inleakage (minor) 7% CRS
~
Key 4 ACRO Main Condenser large air Leak MC-8 M CRO 50% 120 sec CRS Loss of Vacuum Turbine Trip / LNP Preinsert ACRO RD 12A 69% M CRO Hydraulic ATWS / Level Power Control RD12B 74% CRS Preinsert CRO SLOl A CRS SLC A Pump Failure / B Squib Failure SL02 B
SHIFT TURNOVER (#2)
PLANT CONDITIONS:
0 Approximately 100% power 0 Rapid shutdown sequence is latched INOPERABLE EQUIPMENTILCOS:
0 APRM A is INOP and bypassed SCHEDULED EVOLUTIONS:
0 Place Circ Water in closed cycle for chlorination after relieving the watch 0 Service water is to be chlorinated also SURVEILLANCES DUE THIS SHIFT:
0 None ACTIVE CLEARANCES:
0 NIA GENERAL INFORMATION:
3900-4500 v DG A/B BKR CONT SELECT Switches Bus 819 Bus 314 Other 4KV ACB's SAJ Transformer Aux Transformer Cond Backpress SW PPs A/B/CID Cond Sys Feed Sys CST Level (ER20001509-06)
Inst. Air Press Rx Water Level Rx Press Rx Power SLC sys SLC Tk Level ConriTapelFlow INORWAlt F'wr NOTE 1: STA walkthrough to include status check of the Control Room Pyrotronics Panel.
NOTE 2: In the event minimum shift staffing levels cannot be met, actions to be initiated are specified in AP 0894.
VYAPF 0152.01 NOTE 3: Control Room staff shall contact VELCO whenever abnormal yard conditions exist. (CAR910370Pl) AP 0152 Rev. 22 Page 1 of 1 LPC #5
TECH. SPEC./TEC"ICAL REQUIREMENTS M A N AL SYSTEMSKOMPONENTS INOPERABLE 2
a VYAPF 0152.02 AP 0152 Rev. 22 Page 1 of 1
SHIFT BRIEFING CHECKLIST Mode Switch Position: L Date: %%!!
Shift: 8Af Night Day Plant Status: Rx Power 106 % Rx Water Level: 166 'I Rx Pressure: h d r HP Clock (Note 3) /D Significant Equipment Out of Service (No e 1)-
APhWl A -2mPc?J q f N J e d Special Instructions or Considerations (Pertinent Night Orders, Unusual Conditions) (MOOID93010P2)
Briefing Conducted By:
Control Room Supervisor Previous twelve hour full power average during steady state operation >1592 MWt?
Yes 0No NIA If no and unplanned, notify the Supervisor, Operations Support.
Attendees:
Spare Shift SM OR CRS Shift Chem Tech.
CRO Rad. Prot. Tech.
ACRO ACRO A0 A0 A0 Approved by:
Duty Shift Manager Note 1: Include Tech. Spec. Systems/Components entered on VYAPF 0152.02 for which active measures by Operations must be taken and list those actions. (ER970390-01 & -02)
Note 2: Ensure evolutions that may affect radiological conditions such as HPCI, RCIC, Core Spray and RHR operations are brought to the attention of the Radiation Protection Technician.
Note 3: State I-P clock number. IF clock has been reset, discuss the event that resulted in the reset.
VYAPF 0152.03 AP 0152 Rev. 22 Page 1 of 1 LPC #2
CONTROL ROOM TURNOVER SHEET Date: irL;$aj\L_ Shift: @ Nights Annunciators (Existing, New, Nuisance, Disabled, Restored)
- O M CJ /qnt/*UNCl'&ddrs Surveillances DoneDue
/VONe/
volutions/Transients ,
p/a& cu '19 =
uipment Out ofmeturned to Service eel Other VYAPF 0152.04 AP 0152 Rev. 22 Page 1 of 1
Appendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 1 Page 2of 12 Event
Description:
Place CW in closed cycle for chlorination Time Position Applicants Actions or Behavior Direct traveling screens to off, service water strainer breakers opened and circ CRS water placed in closed cycle for chlorination CRO Review prerequisites and admin limits to ensure they are satisfied Verify all CW and CWB pumps running CRO Verify sufficient fans o to maintain condenser vacuum 1.O to 5.0 inches CRO Call Chemistry to determine if service water will also be chlorinated CRO Request a peer check Open recirc gate to > 70%
0 Recirc gate switch on CRP 9-6 positioned to open and held CRO (Throttle) 0 Position verified >70% on CRP 9-6 PI-104-3 0 Recirc gate switch released CRO Verify wier level c 225 ft (LI-104-10-1) on CRP 9-7 CRO Direct an A 0 to check CW-7 open sufficiently to ensure no flow over of weir Close/check closed all intake gates 0 A intake gate control switch positioned to closed on CRP 9-6 0 B intake gate control switch positioned to closed on CRP 9-6 0 C intake gate control switch positioned to closed on CRP 9-6 CRO Intake gates verified closed on CRP 9-6 POI-104-1A POI-104-1B POI-104-IC ACRO / CRO Verify backpressure < 5.0 (monitor backpressure)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Page 2of 2 Event
Description:
Loss of Startup Transformers
~
Time Position Applicant's Actions or Behavior
~ ~
ACRO Diagnose and report loss of startup transformers CRS Enter ON 3150, Loss of Startup Transformers Send an operator to the relay house to complete VYOPF 2141.01/02.
Visually inspect startup transformers.
Consult Technical Specifications 3.1O.A.4, 3.1O.B.3, 3.5.D.C Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify Main Transformer backfeed is available -
CRS observation of plant status Enter 7 day LCO IAW 3.10.B.C CRS Direct voltages checked on Bus 3, 4, 8, 9, on panel meters and ERFIS Check voltages on Bus 3, 4, 8, 9 as directed BUS8 El-9-8-27 ACRO BUS9 El-9-8-28 Bus3 Bus4 SE Check voltages on Bus 3,4, 8, 9, on ERFIS (ECCS status screen)
CRS Direct EDG availability checked ACRO Check CRP 9-8 for normal standby conditions (no EDG alarm)
CRS Direct Circ Water shifted to open cycle
Appendix D Required Operator Actions Form ES-D-2 1 Scenario No.: 2 Event No.: 2 (cont'd) Page 3 of 12 Shift Circ water to open cycle 0 Inform Chemistry proceeding to open cycle Open intake gates to 100%
0 A intake gate control switch positioned to open on CRP 9-6 B intake gate control switch positioned to open on CRP 9-6 0 C intake gate control switch positioned to open on CRP 9-6 Intake gates verified open on CRP 9-6 POI-104-1A POI-104-1B POI-104-IC ACRO Fully close the recirc gate 0 Recirc gate switch on CRP 9-6 positioned to closed and held (Throttle) 0 Position verified 0% on CRP 9-6 PI-104-3 Recirc gate switch released Fully lower bypass gates (A & B) 0 Bypass gate A control switch to open on CRP 9-6 0 Bypass gate B control switch to open on CRP 9-6 0 Monitor fore-bay level on LI-104-2A on CRP 9-6 0 Monitor fore-bay level on Ll-I 04-2B on CRP 9-6 0 Monitor ERFIS and report NPDES status CRS Notify DCO and Operations Manager CRS Direct power reduction to 25 CTP at I 1O%/minute to 27.0 to 27.5 mlbm/hr CREW Monitor river temperature points M036/M037 ACROKRO Notify IS0 New England of power reduction Brief crew on plant status 0 25% CTP as soon as possible 0 Hot shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CRS 0 Unusual Event on Loss of Startup Transformers Startup Transformer status Potential LNP on a reactor scram CRS Request maintenance point of contract assigned CREW Direct Chemistry technician notify stake holders of unplanned power reduction CREW Contact ISONELCO, inform them of power reduction CRS Direct stability monitor verified operable Reduce recirc pump speed to a core flow of 27.0 to 27.5 mlbms/hr at the rate directed by the CRS CRO 0 Turns controller 2-184-16-IN1B manual knob in the counterclockwise direction on CRP 9-5 ACRO Adjust speed load changer per Figure 2 of OP 0105
Amendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Page 4 of 12 Event
Description:
Power reduction with a stuck feedwater regulating valve P
Time Position Applicants Actions or Behavior CRO Report increasing reactor level CRS Direct power reduction stopped until reactor level can be stabilized Check actual FRV positions on ERFIS.
CREW Determine A FRV is not responding.
Contact Operations Management and recommend actions to deal with the CRS stuck FWRV CRS Brief crew on plans to deal with stuck feedwater regulating valve Direct the A FWRV transferred to individual manual and then to local manual CRS Control and locked up Transfer the A FWRV to individual manual control as follows:
Press the display push button on FDW 12A individual controller Compare the S and V signals Verify the 3and V signals are matched Depress the AIM push button on the FDW 12A controller CRO Verify the green auto Led goes out on the FDW 12A controller Verify the red manual Led comes illuminates on the FDW 12A controller Then direct an A 0 to establish communications with the control room and take local manual control of the A FWRV in accordance with OP 2172
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Page 5 of 12 Event
Description:
LPRM Upscale Failure, W scram RPS Time Position Applicants Actions or Behavior
_a P CRO Report LPRM 24-41 B upscale failure, APRM D hi hi, % scram CRS Direct ACRO check LPRM 24-41B on back panel May direct APRM D bypassed at this time and the W scram reset, if not it will CRS be done in the subsequent steps ACRO Check and report LPRM 24-41B failed upscale and APRM D reading 120%
Direct LPRM 24-41B bypassed in accordance with ARS-9-5-M-I/M-3/N-7 OP CRS 2456 Obtains OP 2456 0 Notifies Shift Manager of APRM Rod block specification in TRM Table 3.2.5 not satisfied with APRMs A & D bypassed 0 Record time of bypass ACRO/CRO 0 BypassLPRM 24-41B and verify bypass light on 0 Reports APRM D returned to normal 0 Determine APRM GAFs are/are not required Return APRM D to service 0 Record time APRM D returned to service CRS Enters control rod block LCO of TRM 3.2.5 CRS Directs 1/2 scram reset if not already done
~
Appendix D Required Operator Actions Form ES-D-2 Event
Description:
Minor Condenser Air lnleakage Position Applicants Actions or Behavior P
CREW Report increased AOG flow/lowering condenser vacuum CRS Enter ON 3120, High Condenser Backpressure, and direct actions Verify all circ water and circ water booster pumps running on CRP 9-6 0 Circ water pump A red light on Circ water pump B red light on ACRO 0 Circ water pump C red light on Circ water Booster pump A red light on Circ water Booster pump B red light on Circ water Booster pump C red light on ACRO Verify 516 A open/throttled ACRO Verify steam seal pressure > 1 psig on PI-101-7 on CRP 9-7 Direct core flow reduced t 29.5 to 29 mlbm @ less than or equal to 10%
CRS CTP/Min Reduce core flow to 27.5 to 29.0 mlbm as directed CRO 0 Master flow controller on CRP 9-5 rotated counter clockwise CRO Report increasing RPV level Diagnose/recalI the AFRV as stuck using ERFIS, hold power reduction until Crew RPV level is controlled CRS Direct ACRO to monitor reactor level due to stuck FRV ACRO Monitor and control RPV level as directed CRS Direct control rods inserted to maintain backpressure < 5 Insert control rods as directed (Rapid S/D seq)
Turn on select power 0 Depresses select button for control rod CRO 0 Drives control rod in with continuous insert to to insert limit of the rapid shutdown sequence 0 Selects next rod in sequence and repeats step Brief crew that if a scram is necessary and LNP will occur causing a Loss of CRS Feedwater/Condensate/MSIVs
Amendix D Reauired OPerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 7of 12 Event
Description:
Main Condenser large air inleakage, Loss of Vacuum, Turbine Trip, Loss of Normal Power Time I Position 1 Applicants Actions or Behavior 1 CRS I Direct manual scram prior to 6.5vacuum I CRO I Scram the reactor as directed CRO 1 Attempt manual scram, report partial rod motion, reactor power ~ 2 %
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Page 8of 12 Event
Description:
Hydraulic ATWS / Level power control Time Position Applicant's Actions or Behavior CRO Initiate ARVRPT Trip recirc pump drive motor breakers Scram response Depress PB Ion feedwater master controller CRP 9-5 Reactor mode switch to shutdown CRP 9-5 when steam flow <40%
Insert IRMs/SRMs on CRP 9-5 Select IRM recorders on CRP 9-5 CRO Report reactor power when RPV level reaches 9 0 Report when reactor power is <2%
After verifying the RPV is recovering leave one RFP running, and place one in standby, and one in pull to lock CRP 9-6 when reactor power/steam flow allows Verify closed scram discharge vent and drain valves (6) on CRP 9-5 Enter EOP-1 CRS 0 Direct Table A automatic action confirmed Enter EOP-2 and direct:
0 ADS inhibited CT CRS 0 Reactor mode switch to shutdown when steam,flow is < .5mlbm/hr 0 Confirm ARVRPT Inhibit ADS CT ACRO 0 Logic A inhibit collar depressed and rolled clockwise on CRP9-3 0 Logic B inhibit collar depressed and rolled clockwise on CRP9-3 STA Confirm Table A when directed CT CRS Direct injection into the RPV terminated IAW OE 3107 Appendix GG
Appendix D Required Operator Actions Form ES-D-2 3.: 1 Scenario No.: 2 Event No.: 7 (cont'd) Page 9 of 12 Terminate injection IAW OE 3107 Appendix GG 0 Inhibit HPCl by depressing and rotating the inhibit collar on CRP 9-3 clockwise Inhibit RHWCS by placing control switches on CRP 9-3 in pull to lock 0 RHRA 0 RHRC ACRO 0 RHRB 0 RHRD 0 CSA 0 CSB Inhibit feedwater and condensate by placing 0 RFP NBIC on CRP 9-6 pull to lock 0 FWRV A/B shut using feedwater master controller CRS Continue to lower RPV level until reactor power is 2%
CRS Direct boron injection before torus temperature is > 110°F
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Page 10 of 12 Event
Description:
SLC APump failure, B Squib failure, (ATWS Continuing)
Time Position Applicants Actions or Behavior Inject boron SLC control switch on CRP 9-5 to SYSl or SYS 2 0 Confirm pump start by red light for pump on CRP 9-5 Verify RWCU isolates on CRP 9- 4 0 CU 15 shut by green light only on CRP 9- 4 0 CU 18 shut by green light only on CRP 9- 4 0 CU 68 shut by green light only on CRP 9-4 Verify squib valve fires by 0 Amber light out of CRP 9-5 CRO 0 ANN 9-5-A-1 squib continuity loss 0 Discharge pressure on CRP 9-5 PI-I 1-65 do not indicate the pump deadheaded 0 Red flow light on on CRP 9-5 indicating flow >30 GPM 0 SLC tank level lowering as indicated on CRP 9-5 LI-I 1-66 0 If system fails start other system Diagnose the A SLC pump failed to start and the B squib valve failed to fire 0 Inject SLC with the B pump 0 Report to the CRS the SLC system failures of A SLC pump, B Squib CRO report SLC is injecting When reactor power is 2%, direct injection reestablished to maintain RPV CT CRS level > 1 9 and the level at which power went below 2% using HPCI/RCIC/CRD CT CRO Reestablish RPV injection to maintain RPV level in the ordered band CT CRS Direct control rods inserted IAW Appendix BB/G
Appendix D Required Operator Actions Form ES-D-2 Op-Test I I.: 1 Scen: I No.: 2 Event No.: 8 (contd) Page 11 of 12 Insert control rods as directed Start all available CRD pumps.
Position the RWM keylock bypass switch to BYPASS concurrently If necessary, perform the following to open the CRD flow control valve.
Place FIC 3-301 CRD Flow Control in manual.
Adjust. FIC 3-301 CRD Flow Control to restore drive water pressure.
Close CRD-56 CRD Charging Water Header Supply Adjust CRD-PCV-20 DRIVE WTR PRESS CONTROL VALVE to achieve drive water differential pressure to between 300 and 500 psid.
The appropriate rod select template (MI) may be used as an aid, if desired.
The operator may initial, checkoff, or comment in the space provided after each control rod as appropriate.
Continuously insert control rods, using the ROD MOVEMENT CT CRO CONTROL switch, to position 00 as follows:
Insert control rods using the sequence given on Figure I.
IF the sequence of Figure II is inadvertently started, THEN notify the CRS, insert all possible control rods in that sequence and proceed to the sequence given on Figure I.
IF, while inserting control rods, a control rod is mispositioned, THEN notify the CRS, insert that control rod to 00 and continue in the sequence.
IF, while inserting control rods, a control rod in the sequence is partially inserted, THEN insert that control rod to 00 and continue in the sequence.
IF, while inserting control rods, a control rod in the sequence cannot be moved or is at 00, THEN skip that control rod and continue in the sequence.
WHEN all possible control rods have been inserted per Figure 1(11),
THEN continue to insert control rods per Figure ll(1).
WHEN all control rods that can be inserted have been inserted, THEN inform the CRS.
APP BB Start all available CRD pumps.
Close CRD-56 CRD Charging Water Header Supply.
CRO Fully OPEN CRD-PCV-20 DRIVE WTR PRESS from CRP 9-5.
Adjust CRD-PCV-22 CLG WTR PRESS to achieve drive water differential pressure between 300 and 500 psid.
When all control rods that can be inserted have been inserted, Then inform the CRS
Appendix D Required Operator Actions Form ES-D-2 OD-Test No.: 1 Scenario No.: 2 Event No.: 8 (cont'd) Page 12 of 12 Enter and direct actions in EOP-3 0 Restart Drywell RRUs CRS 0 Initiate torus cooling 0 Before torus pressure reaches 10 psig, spray the torus Restart all drywell RRUs when directed.
0 MCA keylock to bypass on CRP 9-25 0 CRP 9-25 Blocking relay reset push button depressed ACRO 0 CRP 9-25 RRU I N B control switch to A&B run 0 CRP 9-25 RRU 2NB control switch to A&B run 0 CRP 9-25 RRU 3NB control switch to A&B run 0 CRP 9-25 RRU 4NB control switch to A&B run Initiate torus cooling when directed Place 0 A and D RHR pumps in PULL TO LOCK.
OR 0 B and C RHR pumps in PULL TO LOCK.
0 Close/verify closed HX BYPASS RHR-65NB 0 Verify adequate SW pumps are operating to handle RHRSW pump demand.
0 Verify no more than one SW pump is in standby mode.
IF a LPCl initiation signal is present, THEN place RHRSW PP A&C LPCl AUTOSTOP OVERRIDE SWITCH keylock switch to MANUAL OVERRD (3-M-2 will annunciate).
ACRO Start RHRSW pump A or C /B or D When conditions permit, verify RHRSW pump cooling water flow is 3 - 6 gpm.
If necessary, adjust RHRSW DISCHARGE, RHR-89NB as follows:
0 Maintain RHRSW heat exchanger flow 2950 to 3140 gpm.
0 Maintain RHRSW pressure greater than 20 psid above RHR pressure.
IF reactor water level is greater than TAF, THEN 0 turn the RHR A/C or B/D LOGIC CTMT SPRAY VLV LPCl SIG BYPASS to MAN.
0 Open TORUS SPRAYELG RHR-39N39B Open TORUS COOLING RHR-34N34B Spray the torus when directed.
ACRO 0 Open RHR 39NB After Freeze, determine EAL in accordance with AP 3125 as S-7-c.
Amendix D Scenario Outline Form ES-D-1 Op-Test Facility: Vermont Yankee New Scenario No.: 3R No.:
Examiners: Operators:
Objectives: Evaluate the crews response to a fault on 480 volt Bus 898 and to take the required Technical Specification actions for the bus loss. Recognize and take action for a trip of the running TBCCW pump with a failure of the automatic and manual start of the standby RBCCW pump. The complete loss of TBCCW will cause condensate and feedwater pump bearing temperatures to rise to the alarm set points. They will attempt to transfer house loads to the startup transformers but the breakers will not close. They will scram the reactor due to degrading conditions in the feed and condensate pump bearings. The fast and residual bus transfer to the startup transformers will fail when the turbine trips after the scram causing an LNP. The crew will enter OT 3100 / EOP 1 (scram) and OT 3122 (LNP).
After the plant is stabilized a steam leak will occur in the drywell compounded by a loss of high pressure feed. EOP 3 will be entered to control primary containment parameters. After drywell sprays are initiated HPCl will trip. RPV level will lower due to the loss of high pressure feed sources and an RPV-ED will be preformed to allow low pressure injection sources to restore RPV level above TAF.
Multiple injection valve auto open failures will occur requiring operator actions to restore RPV level above TAF IC-9 100% power. RClC is out of service Initial Conditions:
See Attached Shift Turnover Sheet Turnover:
Event No. I Malf. No.
Event Description RF RCR05 N/A RClC 15 ACB opened after RClC 15 is closed (RCIC 00s)
CS03A preinsert I Core Spray A injection valve auto open failure CS03B preinsert I Core Spray B injection valve auto open failure RH07A Preinsert 1 I 1 RHR A injection valve auto open failure 1 C 1 Failure of breaker 23 to close manually
Amendix D Scenario Outline Form ES-D-1 Failure of breaker 13 to close manually (Switch I/O) No C malfunction for this side is available ED12A ED12B Preinsert I Failure of Bus 1 and 2 to auto transfer to the startup transformers 1 1 1 ED19B C Loss of Bus 898 SW 14A Trip of A TBCCW pump and failure of auto and manual starts of 2 SWdiOGswl2b C the B TBCCW pump I 3 I N/A N Power reduction due to increasing component temperatures RROIA 5% @ 800 sec ramp M Recirc loop rupture C HPCl turbine trip, loss of all high pressure feed See above preinserts Failure of injection valves to auto open Q_
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor
SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#3R)
GENERAL REQUIREMENTS
> All chart recorders will be rolled forward, timed and dated.
9 Paper from selected chart recorders will be saved for the examination team as requested.
9 All procedures, flow charts, curves, graphs, etc., will be returned to their normal storage place and closed.
9 All markable procedures, boards, etc., will be erased.
9 All paper used by the previous crew will be removed and kept for the examination team as requested.
9 The simulator operator, or designated person, will keep a rough log of all communications into and out of the "control room during the scenario as
'I requested by the examination team.
INITIAL SETUP 9 IC-9,100% CTP, RClC 00s DURING THE SCENARIO The examination team will determine when each event is to be inserted and when to "freeze" and will inform the simulator operator.
P EVENT 1 If the Control Room sends maintenance or an A 0 to investigate the loss of RUPS "B"/Bus 89B, inform the crew that:
0 at RUPS 1B - the Gen overhnder voltage lite is on and BKR "CB" is open (AC output BKR).
at MCC 89B - breaker "feed from UPS IB" is open. If the crew attempts to close the maintenance tie, it will trip.
0 if requested maintenance should inform the crew that there appears to be a fault on MCC89B and a work order is being initiated.
9 EVENT 2 If sent to investigate the loss of TBCCW report the A TBCCW pump breaker tripped and no reason for the start failure of the B TBCCW pump.
> EVENT 3 When directed to control recirc lube oil temperatures insert SWR 58.
After the manual scram and LNP if VELCO/AO/Maintenance are asked to report a cause for the LNP no cause will be found.
> EVENT 5 When sent to investigate the cause for the HPCl trip report a large oil leak has caused a loss of hydraulic and bearing oil.
> EVENT 6 If sent to manually open RHR 27B it will not open.
TERMINATION:
Reactor water level restored to above TAF and controlled with low pressure ECCS pumps. Exam Team directs.
SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#3R)
Event Event Event No. Malf. No. Type* Description RC05 Preinsert NIA RCIC isolation (RCIC 00s)
RF RCRO5 NIA RCIC 15 ACB opened after RCIC 15 is closed (RCIC 00s)
CS03A preinsert I Core Spray A injection valve auto open failure CS03B preinsert I Core Spray B injection valve auto open failure RH07A Preinsert I RHR A injection valve auto open failure ED2 1 Preinsert C Failure of breaker 23 to close manually EDdi08swz Failure of breaker 13 to close manually (Switch VO) No malfunction for Preinsert C this side is available ED12A ED 12B Preinsert I Failure of Bus 1 and 2 to auto transfer to the startup transformers ED 19B C Loss of Bus 89B SW14A Trip of A TBCCW pump and failure of auto and manual starts of the 2 SWdiO6swl2b C B TBCCW pump 5 NIA N Power reduction due to increasing component temperatures RROlA
.5% @ 800 4 sec ramp M Recirc loop rupture
~
5 HPO1 C HPCI turbine trip, loss of all high pressure feed See above 6 preinserts Failure of injection valves to auto open
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor
SHIFT TURNOVER (#3R)
PLANT CONDITIONS:
0 Approximately 100% power.
Rapid shutdown sequence is latched RClC is 00s due to a failed steam flow D/P cell causing a rrious i latio I INOPERABLE EQUIPMENT/LCOS:
RClC 14 days Technical Specifications 3.5.G.2. Entered 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago SCHEDULED EVOLUTIONS:
I/C is working on the failed RCIC steam flow D/P cell SURVEILLANCES DUE THIS SHIFT:
0 None ACTIVE CLEARANCES:
0 N/A GENERAL INFORMATION:
CONTROL ROOM SHlFT TURNOVER CHECKLIST Parameter/ Allowable Checks Component Cond/Limit 06, I 18 CS A/B Sys No A l d O p r J, I cs-7 A/B IOpen 1 1 ' 1 cs PP An3 IAUTO/Opr I /.I CS-5 A/B, 11 A/B Open J CS-26 A/B, 12 A/B Closed CS FI-14-5OAlB RHR Sys 6 0 0 gpm I No AlarmdOpr 4..
I J-I RHR PP A/B/CID IAUTO/Opr 21,57,58 IClosed HPCI Flow I I /I I I
~~
ConVTapdFIow 1AUT0/4250/<100 INORWAlt Pwr I I RPS MG A/B Power Avail.
Off-Gas Act Norm Trend Stack Gas Act Norm Trend Ref-2 A/B SBGT 9KW Hbs EUH-2&4 SGT-2N3A SGT-lA/B, 2B, 3B, 4A/B, 5 I Closed 1-0.25 to -2.0 inches I v ./I Rx Bldg D P H20 TVS-86 Closed /.
DrywelUTorus DIP 21.8 psid TONSWater Level OP 21 15, Rg 1 t/
I I I I I I TIME REMARKS: m m -
00%
NOTE 1: STA walkthrough to include status check of the Control Room Pyrotronics Panel.
NOTE 2: In the event minimum shift staffing levels cannot be met, actions to be initiated are specified in AP 0894.
VYAPF 0152.01 NOTE 3: Control Room staff shall contact VELCO whenever abnormal yard conditions exist. (CAR910370Pl) AP 0152 Rev. 22 Page 1 of 1 LPC #5
TECH. SPEC./TECHNICAL REQUIREMENTS MANUAL SYSTEMSKOMPONENTS INOPERABLE x
OPERATIONS REQUIRED SWCRS TECH. DATE/TIME LOGGING, TESTING OR ALIBwABLE DATE/T1ME SPEC.iTRh4 DECLARED UNPLANNED OTHER ACTION TIME DECLARED SYSTEWCOMPONENT PARAGRAPH INOPERABLE LCO (ER970390-03) INOPERATIVE OPERABLE RcSC 3S*G.2 fjrpa: h& 8 l o p.--
'pp f&
VYAPF 0152.02 AP 0152 Rev. 22 Page 1 of 1
SHIFT BRIEFING CHECKLIST Mode Switch Position: &d Date: %day Shift: OM Night Day Special Instructions or Considerations (Pertinent Night Orders, Unusual Conditions) (MOOID9301OP2)
NO Briefing Conducted By:
Control Room Supervisor Previous twelve hour full power average during steady state operation >1592 MWt?
d y e s 0 No 0 N/A If no and unplanned, notify the Supervisor, Operations Support.
Attendees:
Spare Shift SM OR CRS Shift Chem Tech.
CRO Rad. Prot. Tech.
ACRO ACRO A0 A0 A0 Approved by:
Duty Shift Manager Note 1: Include Tech. Spec. Systems/Components entered on VYAPF 0152.02 for which active measures by Operations must be taken and Iist those actions. (ER970390-01 & -02)
Note 2: Ensure evolutions that may affect radiological conditions such as HPCI, RCIC, Core Spray and RHR operations are brought to the attention of the Radiation Protection Technician.
Note 3: State HP clock number. IF clock has been reset, discuss the event that resulted in the reset.
VYAPF 0152.03 AP 0152 Rev. 22 Page 1 of 1 LPC #2
Date:+ CONTROL ROOM TURNOVER SHEET Shift:
0 Days Nights Equipment Out ofmeturned to Service RGK-Other VYAPF 0152.04 AP 0152 Rev. 22 Page 1 of 1
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3R Event No.: 1 CRS Direct maintenance to investigate the loss of MCC 89B.
I CRS Review Tech Specs and determine per 3.10.B.4 and 3.5.A.4.b enter a 7-day LCO for "E" LPCI. I 1 ACRO Direct A 0 to document indicating lights at RUPS 1B and MCC 89B per OP 2143.
I CRS I Brief the Crew on the 7 day LCO, and the A LPCl loop will not inject if needed. I
Appendix D Required Operator Actions Form ES-D-2 scription: Respond to a IOSS Of TBCCW Position Applicant's Actions or Behavior
~
CRO Recognize a loss of running TBCCW pump CRO Attempt to start the standby TBCCW pump, recognize both TBCCW pumps have tripped.
CRS Direct maintenance and an A 0 to attempt to reset the breaker to restart a TBCCW pump CRS Direct the CRO to begin lowering recirc speed to 27.5-29 mlb/hr at a rate not to exceed 10% RTPlmin Begin lowering Recirc speed using the master controller at a rate directed by CRO the CRS 0 Adjusts master controller SC-2-184-14 in the counter clockwise direction CRS Direct the crew to monitor the Condensate and Feed pump bearing temperatures STA Report when ERFIS alarms for Feed and Condensate pump temperatures High CRS Direct the ACRO to transfer House Loads to the Startup Transformers ttem t to # ansfer house loads to the startup transformers and report that the treakgrs wih not close Insert sync key in 13 bkr Turn on sync scope 0 Place 13 bkr control switch to close ACRO Report 13 bkr close failure Insert sync key in 23 bkr Turn on sync scope 0 Place 23 bkr control switch to close 0 Report 23 bkr close failure CRS Direct a reactor scram and carry out actions in OT3100, and possible LNP.
Appendix D Required Operator Actions Form ES-D-2 Event
Description:
Respond to a Reactor Scram with a loss of Off Site Power.
~ -- -
Position Applicant's Actions or Behavior Report reactor scram. Take scram actions 0 Press manual scram pushbuttons 0 Depress PB 1 on feedwater master controller CRP 9-5 0 Reactor mode switch to shutdown CRP 9-5 when steam flow <40%
0 Insert IRMs/SRMs on CRP 9-5 0 Select IRM recorders on CRP 9-5 CRO 0 Report reactor power <2%
0 Report all control rods inserted 0 After verifying the RPV is recovering leave one RFP running, and place one in standby, and one in pull to lock CRP 9-6 0 Verify closed scram discharge vent and drain valves (6) on CRP 9-5 Recognize/report EOP-1 and 3 entries on high drywell pressure.
ACRO Recognize and inform CRS of Turbine Trip with Loss of Off Site Power 0 Report power on buses 3,4,8,9 from the Diesels CRS Enter and direct actions IAW OT 3122 LNP Respond to LNP IAW 3122.
0 Verify DG start ACRO SW pumps start 0 Station AC start Restart drywell RRUs 0 Depress blocking relay reset on CRP 9-25 ACRO Inform CRS that Buses 1 and 2 failed to transfer and the 13 and 23 breakers will not close.
CRS Enter and direct crew actions IAW OT 3100, Rx Scram and EOP-1, RPV Control CRS Direct reactor water level maintained 127" - 177" per EOP-1 with HPCI.
CRO Report feed and condensate is unavailable.
( I
Amendix D Reauired ODerator Actions Form ES-D-2 Op-Test 1.: Scenario No.: 3R Event No.: 3 (cont'd) Page 4 of 9 Maintain reactor water level as directed with HPCI.
e Open TEST RETURN HPCI-24.
e Close/check closed PUMP DISCHARGE HPCI-19.
e Throttle open FULL FLOW TEST HPCl21 8-10 seconds.
(BMO-200-7R-01) e Start HPCl GL SL VAC FN-2-IA.
e Verify both trains of SBGT start. (As time permits) e Open MINIMUM FLOW HPCI-25.
e Open STEAM SUPPLY HPClI4.
e As time permits, verify that STM LINE DRAIN HPCI-42 and HPCI-43 close.
e Start AUX OIL PUMP P-85-1A and monitor SI 23-2 TURBINE SPEED.
e As flow increases above 800 gpm, verify that MINIMUM FLOW HPCI-25 closes.
e Control recirc flow rate to the CST and turbine speed by:
- a. Adjusting HPCl FLOW CONTROLLER FIC 23-108, or
- b. Throttling FULL FLOW TEST HPCI-21 as necessary.
C. If HPCl FLOW CONTROLLER FIC 23-108 automatic CRO/ACRO feature fails:
- 1) Place HPCl PUMP FLOW CONTROLLER FIC 23-108 in MANUAL.
- 2) Control flow using the MANUAL knob.
Monitor the following HPCl parameters:
Parameters Normal Ranse Trip Point Exhaust Pressure 0-50 psig 130 psig Suction Pressure 6-30 psig 15 in. Hg Vac.
Stm Supply Pressure 150-1120 psig 270 psig Turbine Speed >2200-4000 rpm 5000 rpm Discharge Pressure < 250 I psig N/A If injection to vessel is required:
Open PUMP DISCHARGE HPCI-19.
Throttle FULL FLOW TEST HPCI-21 as necessary to control reactor water level.
ACRO Control reactor pressure as directed.(Expect the use of HPCI)
CRS Direct torus cooling.
Appendix D Required Operator Actions Form ES-D-2 Ou-Test No.: Scenario No.: 3R Event No.: 3 (cont'd) Page 5 of 9 Start torus cooling as directed.
Place 0 A and D RHR pumps in PULL TO LOCK.
OR 0 B and C RHR pumps in PULL TO LOCK.
0 Close/verify closed HX BYPASS RHR-65NB 0 Verify adequate SW pumps are operating to handle RHRSW pump demand.
0 Verify no more than one SW pump is in standby mode.
IF a LPCl initiation signal is present, THEN place RHRSW PP A&C LPCl AUTOSTOP OVERRIDE SWITCH keylock switch to MANUAL OVERRD (3-M-2 will annunciate).
ACRO 0 Start RHRSW pump A or C /B or D When conditions permit, verify RHRSW pump cooling water flow is 3 - 6 gpm.
If necessary, adjust RHRSW DISCHARGE, RHR-89NB as follows:
0 Maintain RHRSW heat exchanger flow 2950 to 3140 gpm.
Maintain RHRSW pressure greater than 20 psid above RHR pressure.
IF reactor water level is greater than TAF, THEN w turn the RHR A/C or B/D LOGIC CTMT SPRAY VLV LPCl SIG BYPASS to MAN.
0 Open TORUS SPRAY/CLG RHR-39N39B Open TORUS COOLING RHR-34N34B Declare UE due to loss of Offsite Power per AP 3125, U-6-a CRS May be performed after the freeze
Appendix D Required Operator Actions Form ES-D-2 Position Applicants Actions or Behavior Crew Report increasing drywell pressure.
CRS Enter EOP-3. Primary Containment Control CRS Direct ACRO to restart drywell RRUs.
Restart drywell RRUs.
MCA keylock to bypass on CRP 9-25 0 CRP 9-25 RRU I N B control switch to A&B run ACRO 0 CRP 9-25 RRU 2NB control switch to A&B run 0 CRP 9-25 RRU 3AIB control switch to A&B run CRP 9-25 RRU 4NB control switch to A&B run CRS Direct torus sprays before torus pressure reaches 10 psig.
Spray the torus, as directed.
Spray the torus as directed Place A and D RHR pumps in PULL TO LOCK.
OR B and C RHR pumps in PULL TO LOCK.
Closelverify closed HX BYPASS RHR-65A 0 Verify adequate SW pumps are operating to handle RHRSW pump demand.
0 Verify no more than one SW pump is in standby mode.
IF a LPCl initiation signal is present, THEN place RHRSW PP A&C LPCl AUTOSTOP OVERRIDE SWITCH keylock switch to MANUAL OVERRD (3-M-2 will annunciate).
ACRO/C RO Start RHRSW pump A or C / B or D When conditions permit, verify RHRSW pump cooling water flow is 3 - 6 gpm.
If necessary, adjust RHRSW DISCHARGE, RHR-89NB as follows:
Maintain RHRSW heat exchanger flow 2950 to 3140 gpm.
0 Maintain RHRSW pressure greater than 20 psid above RHR pressure.
IF reactor water level is greater than TAF, THEN 0 turn the RHR A/C LOGIC CTMT SPRAY VLV LPCl SIG BYPASS to MAN.
0 Open TORUS SPRAY/CLG RHR-39NB Open TORUS SPRAY RHR-38NB
Appendix D Required Operator Actions Form ES-D-2 Op-Test I 3.: Scenario No.: 3R Event No.:
- 4 Pa e 7 of 9 Prior to RPV-ED, when torus pressure exceeds the suppression chamber spray initiation pressure, initiate drywell containment spray while in the safe region of the drywell spray initiation limit CT CRS Standard:
Spray the drywell within I O minutes of exceeding 10 psig torus pressure AND RPV level not an overriding priority CRS Verify drywell pressure and temperature allow the drywell to be sprayed.
CRS Direct drywell RRUs secured.
Secure drywell RRUs.
ACRO 0 ON CRP 9-25 four RRU c ntrol switches positioned to OFF or MCA keylock returned to norma?
CRS Direct drywell sprays.
Spray the drywell as directed.
ACRO/CRO 0 CRP 9-30pen RHR 26NB 0 CRP 9-3 Open RHR 31 A/B
ADlsendix D Reauired Olserator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3R Event No.: 5 Page 8of 9 Event
Description:
Respond to a loss of high pressure feed.
Time Position Applicant's Actions or Behavior ACRO Report HPCl trip and contact maintenance.
CRS Direct CRD flow maximized to vessel.
Start both CRD pumps CRO 0 Pump A switch to start CRP 9-5 0 Pump B switch to start CRP 9-5 CRS Direct SLC tank injected for reactor water level control.
Inject SLC, as directed.
0 SLC control switch on CRP 9-5 to SYS1 or SYS 2 Confirm pump start by red light for pump on CRP 9-5 Verify RWCU isolates on CRP 9- 4 (already isolated on low RPV level) 0 CU 15 shut by green light only on CRP 9- 4 0 CU 18 shut by green light only on CRP 9- 4 0 CU 68 shut by green light only on CRP 9- 4 CRO Verify squib valve fires by 0 Amber light out of CRP 9-5 0 ANN 9-5-A-I squib continuity loss Discharge pressure on CRP 9-5PI-I 1-65 do not indicate the pump deadheaded 0 Red flow light on on CRP 9-5 indicating flow >30 GPM 0 SLC tank level lowering as indicated on CRP 9-5 LI-I 1-66 CRS Direct injection subsystems CS "A", CS "Boand RHR "A" lined up for injection.
Lineup injection subsystems, as directed.
ShutRHR34A ACRO Shut RHR39A 0 ShutRHR38A CRS Direct ADS inhibited.
Inhibit ADS ACROKRO 0 Logic A inhibit collar depressed and rolled clockwise on CRP9-3 0 Logic B inhibit collar depressed and rolled clockwise on CRP9-3
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3R Event No.: 5 (contd) Page 9 of 9 With the reactor shutdown and reactor pressure greater than the shutoff head of the low pressure systems, initiate RPV-ED BEFORE RPV level reaches -19 inches CT CRS Standard:
Initiate RPV-ED (begin opening valves) BEFORE RPV level reaches -48 inches I CRS Direct all SRVs opened.
Open all SRVs on CRP 9-3 0 RV-71A switch to open 0 RV-71C switch to open 0 RV-71B switch to open 0 RV-71D switch to open Action is taken to restore RPV water level above -1 9 inches by operating available low pressure ECCS system(@when RPV pressure decreases below the shutoff head of the low pressure systems Standard:
0 All available ECCS pumps are lined up for injection and running prior to RPV pressure reaching the injection valve open permissive pressure.
0 No pumps are secured until adequate core cooling is assured.
0 Initiate manual opening of injection valves within 1 minute of reaching valve open permissive pressure Report failure of RHR-27A, CS-12A and CS-I26 to AUTO open and start to ACRO/CRO open them.
CRS Direct RHR and CS injection valves opened.
~~~
AC RO/CRO Manually open RHR 27A and CS 12A and 128 injection valves as directed.
CRS Direct reactor level restored to > TAF and then > 127 using RHWCS.
Consult AP 3125 and determine an Alert EAL has been reached IAW AP CRS 3125, A-3-a and/or A-3-b.
May be performed after the freeze