ML082750410
| ML082750410 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/05/2008 |
| From: | Brian Larson Operations Branch IV |
| To: | Entergy Operations |
| References | |
| 50-313/08-301, 50-368/08-301, ES-301, ES-301-1 50-313/08-301, 50-368/08-301 | |
| Download: ML082750410 (335) | |
Text
Page 5 of 5 JPM ID: A1JPM-RO-PZR05 INITIAL CONDITIONS:
The Reactor is at 38% power with 3 RCPs running D RCP is secured.
INITIATING CUE:
The CRS/SM directs you to respond Annunciator K09-C1 RCS Pressure HI/LO alarm
Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 1-R5 Op-Test No.: 2008-1 Examiners: __________________________ Operators: __________________________
Initial Conditions:
90% power due to dispatcher direction for loss of 500KV.
C2A IA compressor is out of service for overhaul.
ULD is failed and will not lower power.
RPS is failed and will not initiate a RX trip.
Provide stop watch for surveillance.
Two rods will fail to insert on the RX trip.
Turnover:
Day shift normal working day.
90% power due to dispatcher direction for loss of 500KV line as a result of storm damage to the Mabelvale 500KV line. No storms are currently in the area.
C2A IA compressor is out of service for overhaul.
1104.005 Supplement 2 RB Spray Red Train Valves Quarterly Test is in progress complete through step 2.2.2. This is not the 18 month surveillance.
Crew will continue in surveillance after turnover.
Event Malf. No. Event Event No. Type* Description N (SRO, Perform 1104.005 Supplement 2 RB Spray Red Train 1 N/A BOP) Valves Quarterly Test N (SRO) Dispatcher directs power reduction to 700Mwe 2 DI_ICC0009L R (ATC) ULD is failed I (SRO, 3 AI_FIC1207 RCP total flow setpoint fails to high ATC)
C (SRO, 4 CV016 RCP seal failure BOP)
N (SRO) Power reduction 5 DI_ICC0009L R (ATC) ULD is failed DI_H24T M (ALL) Loss of H2 bus 6 If power <55%,
CO_P32A N/A Trip A RCP when H2 bus is lost (Contingency to ensure RPS trip setpoint is reached.)
C (SRO, RPS is failed 7 RP246,7,8,9 ATC) Manual RX trip (TS) (ATC-CT)
CONTINUED Page 1 of 19
Event Event Event Malf. No.
No. Type* Description RD362 C (SRO, Stuck rod (TS) 8 RD363 ATC) Stuck rod (ATC-CT)
CV020 B RCP seal failure RC006 M (ALL) ~700gpm RCS leak (TS) (BOP-CT) 9 ES259 C (BOP) ESAS Channel 1 fails to actuate (TS) (ATC-CT)
CV-1300 CV1300 Fails open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 19
Appendix D Scenario Outline Form ES-D-1 Scenario #1-R5 Objectives
- 1) Evaluate individual ability to perform the valve stroke test of the Engineered Safegaurds Reactor Building Spray Block Valve.
- 2) Evaluate individual ability to recognize and respond to a failed reactor coolant pump total seal injection flow controller setpoint.
- 3) Evaluate individual ability to recognize and respond a degraded reactor coolant pump seal.
- 4) Evaluate individual ability to perform a plant power reduction.
- 5) Evaluate individual ability to recognize and respond a failed unit load demand input to the integrated control system.
- 6) Evaluate individual ability to recognize and respond a loss of a 6900V H bus and resulting loss of a reactor coolant pump.
- 7) Evaluate individual ability to recognize and respond to a reactor trip condition where RPS fails to trip the reactor.
- 8) Evaluate individual ability to recognize and respond to two stuck control rods and initiate emergency boration.
- 9) Evaluate individual ability to recognize and respond a post trip reactor coolant pump seal failure.
- 10) Evaluate individual ability to recognize and respond a reactor coolant system leak inside the reactor building.
- 11) Evaluate individual ability to recognize when conditions require the entry into technical specifications conditions.
- 12) Evaluate individual ability to recognize and respond to a medium reactor coolant system leak.
- 13) Evaluate individual ability to recognize and respond to failure of an ES channel to actuate.
- 14) Evaluate individual ability to recognize and respond a failed open ES component.
Page 3 of 19
Appendix D Scenario Outline Form ES-D-1 SCENARIO #1-R5 NARRATIVE The crew will assume the watch at 90% power. The Mabelvale 500KV line is out of service due to storm related damage in south east Arkansas. The down power was completed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
Reactor engineering has directed that rods can be used to account for the xenon transient.
1104.005 Supplement 2 RB Spray Red Train Valves Quarterly Test is complete through step 2.2.2. The crew should brief the remaining steps of the surveillance. The BOP will perform the stroke test (BOP-N) (SRO-N).
The dispatcher will call and direct U1 power be reduced to ~700Mwe in the next 10 minutes.
The CRS should calculate the required rate and direct power reduction per 1203.045 Rapid Plant Shutdown. The ATC should recognize that the ULD is not responding and power is not lowering. The ATC should reduce power to ~700 Mwe using the SG/RX Master station in hand.
(ATC-R) (SRO-N)
The controlling RCP total seal injection flow setpoint will fail high. (ATC-I) (SRO-I). This will cause CV-1207 RCP Seal Injection Control Valve to fail open raising total seal injection flow to maximum. Annunciator K08-D7 RCP Seal Cavity Press HI/LO will alarm due to the high seal injection flow. The CRS should reference 1203.012G K08 Annunciator Corrective Action. The ACA will direct the CRS to 1203.031 Reactor Coolant Pump and Motor Emergency. The crew should recognize high seal injection flow on C04 and take manual control of CV-1207 to establish 8-10gpm individual seal injection flow.
The RCP seal injection transient will cause the B RCP lower seal to fail (BOP-C) (SRO-C). The CRS should implement 1203.031 Reactor Coolant Pump and Motor Emergency and reduce power to ~60% in order to stop the B RCP using 1103.006 (ATC-R) (SRO-N) The ATC should reduce power to ~60% using the SG/RX Master station in hand.
At ~65% power or as directed by the lead evaluator a loss of the H2 bus will occur resulting in a loss of two RCPs (B and D) (BOP-M) (SRO-M) (ATC-M). If reactor power is <55% then the A RCP will be tripped along with the H2 bus by the simulator instructor to create the condition for the recognition of an RPS failure. The ATC should recognize the reactor should have tripped and manually trip the reactor.
(ATC-C) (SRO-C) (ATC-CT) (TS).
TS 3.3.1 Condition C CT criteria - The reactor should be manually tripped within 2 minutes of the loss of the H2 bus.
Two control rods will fail to fully insert on the Rx trip. (SRO-C) (ATC-C) The ATC should recognize and report this condition during the immediate action report. The CRS will direct 1202.012, RT-12 Emergency Boration to be performed. (ATC-CT)
TS 3.1.4 Condition C CT criteria - Emergency boration should be started within 5 minutes of the RX trip.
CONTINUED Page 4 of 19
Appendix D Scenario Outline Form ES-D-1 SCENARIO #1-R5 NARRATIVE CONTINUED
~10 minutes post trip a ~700gpm leak will occur in the reactor building from the failed RCP seal (ALL-M) (TS). Subcooling margin will be lost requiring the BOP to trip all running RCPs within 2 minutes. (BOP-CT) All ESAS channels will auto actuate except ES Ch.1. The crew should recognize the leak and recognize ES Ch. 1 failed to actuate. The ATC should manually actuate ES Ch.1 from C04 (ATC-CT). CV-1300 on ES Ch.2 fails to close. The BOP should recognize the open valve and attempt to close it manually. The CRS will direct operation per either 1202.002 Loss of Subcooling Margin or 1202.010 ESAS. Either procedure is acceptable. If the CRS enters ESAS he will eventually be directed to 1202.002 Loss of Subcooling Margin.
TS 3.4.13 Condition A CT-Criteria RCP should be tripped within 2 minutes of the loss of SCM.
CT criteria - ESAS Ch. 1 should be manually actuated before RT-10 is reported complete.
Page 5 of 19
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 1-R5 Value/ Event Event Time Malf. No. Ramp Description No.
Time Recall IC 101 IMF RP246,7,8,9 RPS failed IRF CO_C2A off C2A IA compressor OOS IOR DO_C2ASLG C2A IA compressor OOS IRF B5106 OPEN Mabelvale 500KV switchyard breaker open IRF B5110 OPEN Mabelvale 500KV switchyard breaker open IMF RD362 OPEN Group 2 Rod 4 IMF RD363 OPEN Group 6 Rod 8 IMF ES259 ES Channel 1 fails to auto actuate IMF CV1300 Failed open Perform remaining steps of 1104.005 1 0 N/A N/A Supplement 2 RB Spray Red Train Valves Quarterly Test.
N/A N/A Dispatcher directs power reduction to 2 12 700Mwe IOR DI_ICC0009L False ULD is failed RCP total flow setpoint fails high. This 3 IOR 1.0 22 will result CV-1207 Seal Injection AI_FIC1207 control valve traveling full open.
4 Seal Inj. IMF CV016 N/A RCP seal failure requiring power 8-10 gpm reduction and securing of the RCP.
As IOR 5 directed False Power reduction to ~60%
DI_ICC0009L by SRO 65% or as directed by the IMF ED462 N/A Loss of H2 bus when RCP is secured.
6 Lead Evaluator If power IOR Trip of A RCP (Contingency to ensure True
<55% DI_HS1022SP RPS trip setpoint is reached.)
RPS is failed requiring a manual RX trip on a loss of two RCPs >55% power IMF 7 Initial (TS) (ATC-CT) criteria - The reactor RP246,7,8,9 N/A should be manually tripped within 2 minutes of the loss of the H2 bus.
Two control rods will fail to insert TS 3.1.4 Condition C IMF RD362 100 8 Initial CT criteria - Emergency boration IMF RD363 100 should be started within 5 minutes of the RX trip.
CONTINUED Page 6 of 19
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 1-R5 Value/ Event Event Time Malf. No. Ramp Description No.
Time B RCP seal failure IMF CV020 100 Rx trip IMF RC006 0.08 9 ~700gpm RCS leak (TS) (ATC-CT)
IMF ES259 N/A
+10 min criteria - ESAS should be actuated IMF CV1300 1 before RT-10 reported complete.
Page 7 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 1 Event
Description:
Perform remaining steps in 1104.005 Supplement 2 Red train Spray Valve Test.
Time Position Applicants Actions or Behavior 0 BOP Implement 1104.005 Supplement 2 step 2.2.2.
BOP Verify Makeup Tank pressure > 25 psig.
Verify one of the following valves closed:
RB Sump Line A Outlet (CV-1405)
BOP or RB Sump Line A Outlet (CV-1414)
BOP Open BWST T-3 Outlet (CV-1407).
BOP While timing stroke, open CV-2401 (modulating valve).
BOP Record stroke time in Table 1.
Close CV-2401 (modulating valve, hold control switch in CLOSE until BOP valve torques closed). Verify closed indication.
BOP Record closed stroke in Table 1.
BOP Close CV-1407.
EXAMINER NOTE This event is complete when Supplement 2 is complete OR As directed by the Lead Evaluator Page 8 of 19
Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 2 Event
Description:
Dispatcher directs a power reduction to 700Mwe.
ULD is failed Time Position Applicants Actions or Behavior EXAMINER NOTE Dispatcher will call requiring a power reduction to 700Mwe net output for unit 1 in the next 10 minutes.
12 CRS Direct operations per 1203.045 Rapid Plant Shutdown.
Commence a plant shutdown at 0.5 to 10% per minute.
Place ULD in manual.
ATC Attempt Toggle down to CRS directed megawatt setting
~700 Mwe.
BOP Recognize and report ULD not responding to a lowering command.
CRS Direct power reduction using SG/RX master.
BOP Place SG/RX master to hand.
BOP Lower plant power to <60%.
ATC Monitor ICS and EHC subsystems for proper integrated response.
BOP CRS Direct chemistry or the AO to secure Zinc Injection.
If the CRS intends to stop heater drain pumps then direct AO to CRS Removing MSR DI From Service.
At <75% stop Heater Drain Pumps (P8A and P8B)
(CRS may elect to keep the P8s running based upon P8 flow.)
If Heater Drain Pumps are secured then the CRS will direct:
Verify Hi Lvl Dump Isolations open:
- CV-3041A (at B-3252)
- CV-3037A (at B-4252)
Verify Low Level Condenser Spray CV-2907 and CV-2868 (HS-2907 on C02) open.
As time permits after the runback refer to "Contingency Reactivity Plans" and Exhibit A (Operation of APSR Group) of Power Operation (1102.004)
ATC (This may not occur depending on operator response time and scenario time line.)
EXAMINER NOTE This event is complete when plant power is at 700Mwe OR As directed by the Lead Evaluator Page 9 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 3 Event
Description:
RCP total flow setpoint fails high. This will result CV-1207 Seal Injection control valve traveling full open.
Time Position Applicants Actions or Behavior Recognize, acknowledge, and report Annunciator K08-B7 RCP Bleedoff 22 ATC Flow HI.
CRS Implement 1203.012G Annunciator K08 Corrective Action.
GO TO "Seal Degradation" section of Reactor Coolant Pump and Motor CRS Emergencies (1203.031).
Verify the following valves are open:
RCP Seal Bleed off (Normal) Return (CV-1274)
RCP Seal Bleed off (Normal) from P-32D (CV-1270)
BOP RCP Seal Bleed off (Normal) from P-32C (CV-1271)
RCP Seal Bleed off (Normal) from P-32B (CV-1272)
RCP Seal Bleed off (Normal) from P-32A (CV-1273)
ATC Verify RCP Seal INJ Block (CV-1206) open.
EXAMINER NOTE If directed the WCO will report nothing abnormal with CV-1207.
Manually adjust RC Pump Seals Total INJ Flow (CV-1207) to establish ATC 32 to 40 gpm by verifying individual seal injection flow rates 8 to 10 gpm.
Provide Attachment A of this procedure to a Control Board Operator to CRS aid in monitoring seal parameters.
EXAMINER NOTE This event is complete when RCS seal injection flow is 8 to10gpm.
OR As directed by the Lead Evaluator Page 10 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 4 & 5 Event
Description:
RCP seal failure Power Reduction Time Position Applicants Actions or Behavior RCP seal Inj. BOP Recognize and report B RCP seal failure.
8-10 gpm Direct operations per 1203.012G K08 Annunciator Corrective Action and CRS 1203.031 Reactor Coolant Pump and Motor Emergency ANY Determine Seal bleed off temp >40°F above 1st stage seal temp.
Implement Rapid Plant Shutdown (1203.045).
CRS Direct power reduction using SG/RX Master Reduce reactor power to within the capacity of the unaffected RCP ATC combination, using Rapid Plant Shutdown (1203.045) .
BOP Lower SG/RX master to hand.
BOP Lower plant power to <60%.
ATC Monitor ICS and EHC subsystems for proper integrated response.
BOP Direct chemistry or the AO to secure Zinc Injection.
CRS (If not already performed)
If the CRS intends to stop heater drain pumps then direct AO to perform CRS Removing MSR DI From Service.
(If not already performed)
At <75% stop Heater Drain Pumps (P8A and P8B)
(CRS may elect to keep the P8s running based upon P8 flow.)
If Heater Drain Pumps are secured then the CRS will direct:
Verify Hi Lvl Dump Isolations open:
- CV-3041A (at B-3252)
- CV-3037A (at B-4252)
Verify Low Level Condenser Spray CV-2907 and CV-2868 (HS-2907 on C02) open.
(If not already performed)
As time permits after the runback refer to "Contingency Reactivity Plans" and Exhibit A (Operation of APSR Group) of Power Operation (1102.004)
ATC (This may not occur depending on operator response time and scenario time line.)
EVENT 4 & 5 CONTINUED Page 11 of 19
Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 4 & 5 CONTINUED Event
Description:
RCP seal failure Time Position Applicants Actions or Behavior As time permits after the runback refer to "Contingency Reactivity Plans" and Exhibit A (Operation of APSR Group) of Power Operation ATC (1102.004).
(This may not occur depending on operator response time and scenario time line.)
EXAMINER NOTE This event is complete when plant power is <65%
OR As directed by the Lead Evaluator Page 12 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 6 & 7 & 8 Event
Description:
Loss of H2 bus when RCP is secured.
RPS is failed requiring a manual RX trip on a loss of two RCPs >55% power.
Two control rods fail to insert on Rx trip.
Time Position Applicants Actions or Behavior 65%
or as Recognize loss of H2 bus and two RCPs.
directed ANY Recognize RPS failed to complete an automatic trip.
by the TS 3.3.1 Condition C Lead Evaluator Direct operations per 1202.001 Reactor Trip Emergency Operating CRS Procedure.
Direct manual trip of the reactor and performance of immediate CRS actions.
(ATC may trip the reactor before the CRS direction.)
Manually Trip Rx.
Verify all rods inserted AND ATC Reactor power dropping.
CT criteria - The reactor should be manually tripped within 2 minutes of the loss of the H2 bus.
Direct the performance of RT-12 Emergency Boration.
TS 3.1.4 Condition C CRS CT criteria - Emergency boration should be started within 5 minutes of the RX trip.
Set Batch Controller for maximum batch size as follows:
a) Depress lower DISPLAY b) Depress TOTAL c) Depress TOTAL RESET ATC d) Depress BATCH SET e) Depress 9, six times f) Depress ENTER g) Depress lower DISPLAY Emer.
Boration ATC Verify Condensate to Batch Controller (CV-1251) closed.
Actions Open Batch Controller Outlet (CV-1250).
ATC ATC Verify both Letdown Filters in service (F-3A and B).
ATC Record initial BAAT (T-6) level ____________ in.
ATC Start available Boric Acid Pump(s) (P-39A or B or both).
ATC Start Batch Controller by depressing RUN key.
EVENT 6 & 7 & 8 CONTINUED Page 13 of 19
Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 6 & 7 & 8 CONTINUED Event
Description:
Loss of H2 bus when RCP is secured.
RPS is failed requiring a manual RX trip on a loss of two RCPs >55% power.
Two control rods fail to insert on Rx trip.
Time Position Applicants Actions or Behavior Adjust Batch Controller Flow CNTRL VLV (CV-1249) to 100% open as follows:
a) Depress VALVE SET ATC b) Depress numbers: 1, 0, 0 c) Depress ENTER d) Depress lower DISPLAY e) Depress RATE ATC Adjust Pressurizer Level Control Setpoint to 220".
ATC Open BWST Outlet to OP HPI Pump (CV-1407 or 1408).
ATC When PZR level is >100", Then establish maximum Letdown flow.
Perform the following as necessary to maintain MU Tank level 55 to 86":
a) Close Batch Controller Outlet (CV-1250).
b) Stop running Boric Acid Pump(s) (P-39A, P-39B).
c) Place 3-Way valve in BLEED.
Emer. d) When MU Tank level is lowered to desired level, Then ATC perform the following:
Boration Actions (1) Return 3-Way valve to LETDOWN.
(2) Start available Boric Acid Pump(s) (P-39A or B or both).
(3) Open Batch Controller Outlet (CV-1250).
(These steps may not be required)
As time permits, determine actual required boration as follows:
a) Obtain required boron concentration from the Plant Data Book b) Calculate batch add required using Plant Computer OR ATC Soluble Poison Concentration Control (1103.004),
Attachment A.3, "Calculation of Feed Volume For Batch Boration or Dilution".
c) Use 1103.004, Attachment D, "Volume of BAAT vs. Depth of Liquid to determine desired final BAAT level.
When required amount of boric acid has been added per step 14) as ATC determined by Reactor Engineering.
(LOCA will occur prior to completing boric acid addition)
Manually trip Turbine.
BOP Verify Turbine throttle and governor valves closed.
ATC or Check adequate SCM.
BOP Advise Shift Manager to implement Emergency Action Level CRS Classification (1903.010).
EVENT 6 & 7 & 8 CONTINUED Page 14 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 6 & 7 & 8 CONTINUED Event
Description:
Loss of H2 bus when RCP is secured.
RPS is failed requiring a manual RX trip on a loss of two RCPs >55% power.
Two control rods fail to insert on Rx trip.
Time Position Applicants Actions or Behavior Reduce Letdown by closing Orifice Bypass (CV-1223).
ATC (This is not performed due to emergency boration)
BOP Open BWST Outlet to OP HPI pump (CV-1407 or 1408).
ATC Pressurizer Level Control setpoint to 100".
BOP Check for proper electrical response.
ANY Check OP HPI pump supplying normal Makeup and Seal Injection.
ATC Check both SG levels remain <410".
ANY Check Instrument Air Header press >75 psig.
ANY Check all NNI power available.
ANY Check all ICS power available.
ANY Check MSSV OPEN alarm clear (K07-C5).
ANY Check MSIVs open.
ANY Check Turb BYP valves operate to maintain SG press 970 to 1020 psig.
ANY Place both Feedwater Demands in HAND AND verify demand at zero.
ANY Check Main Block valves closed (CV-2625 and 2675).
ANY Check Low Load Block valves closed (CV-2624 and 2674).
ANY Check Startup valves maintain SG levels 20 to 40".
Verify MFW pumps run back and then operate to maintain >70 psid ANY across Startup valves.
Check the following in service:
Two Service Water pumps (P4A, B, or C).
ICW pump supplying Nuclear loop (P33C or B).
ANY ICW pump supplying Non-nuclear loop (P33A or B).
RB Cooling Fans (VSF1A, B, C, D, and E)
Previously running Main Chiller(s) (VCH1A, B)
EVENT 6 & 7 & 8 CONTINUED Page 15 of 19
Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 6 & 7 & 8 CONTINUED Event
Description:
Loss of H2 bus when RCP is secured.
RPS is failed requiring a manual RX trip on a loss of two RCPs >55% power.
Two control rods fail to insert on Rx trip.
Time Position Applicants Actions or Behavior ANY Check ESAS Actuation alarms clear on K11.
ANY Check RCS press >1700 psig.
Check Pressurizer Level Control valve (CV-1235) maintains PZR level ATC >55".
ANY Check PZR steam space integrity.
Verify ERV, Pressurizer Spray, and Pressurizer Heaters operate to ATC control RCS press 2050 to 2250 psig.
ANY Check at least one RCP running.
ATC Check RCS T-cold remains >540 F.
ANY Check adequate SCM.
Check RCS temp remains either:
580 F T-hot with any RCP on ATC OR 610 F CET temp with all RCPs off.
ANY Check RCS integrity.
EXAMINER NOTE This event is complete when Emergency Boration is started OR As directed by the Lead Evaluator Page 16 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 9 Event
Description:
A ~700gpm RCS leak will develop in the RX building resulting in ESAS actuation.
Time Positi Applicants Actions or Behavior on Trip + Recognize and report lower PZR level and RCS pressure.
ANY 10 min ANY Diagnose RCS leak inside containment. TS 3.4.13 Condition A ANY Recognize and report ESAS Channels 2, 3, 4, 5, & 6 actuated.
ANY Recognize and report ES Channel 1 failed to actuate.
Manually actuate ES channel 1.
ATC CT criteria - ES channel 1 should be actuated before RT-10 is reported complete.
Direct operations per 1202.010 ESAS, or 1202.002 Loss of Subcooling CRS Margin.
ANY Check adequate SCM.
ANY Recognize and report a loss of SCM.
IF <2 minutes have elapsed, THEN trip all RCPs.
BOP CT-Criteria RCP should be tripped within 2 minutes of the loss of SCM.
ATC Verify Reflux Boiling setpoint selected for EFW.
BOP Verify proper ESAS actuation (RT 10).
BOP Recognize and report CV1300 failed to close.
If ESAS BOP Attempt to manually close CV1300.
is IF MU Tank level drops below 18", THEN close Makeup Tank Outlet entered ATC (CV-1275). (MUT not expected to go below 18.
Isolate Pressurizer Spray Line as follows:
A. Place Pressurizer Spray Control in HAND AND verify closed ATC (CV-1008).
B. Close Pressurizer Spray Isolation (CV-1009).
ATC Verify ERV Isolation (CV-1000) closed.
ANY Check Nuclear Loop ICW process monitor alarm clear.
ANY Check SG tube integrity.
Check RCS press stabilizes >150 psig.
ANY (RCS pressure will stabilize >150psig)
ANY Check adequate CET SCM.
EVENT 9 CONTINUED Page 17 of 19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 9 CONTINUED Event
Description:
A ~700gpm RCS leak will develop in the RX building resulting in ESAS actuation.
Time Positi Applicants Actions or Behavior on CRS Transition to 1202.002 Loss of Subcooling Margin.
Check elapsed time since loss of adequate SCM:
IF <2 minutes have elapsed, THEN trip all RCPs.
BOP CT-Criteria RCP should be tripped within 2 minutes of the loss of SCM.
N/A (ESAS will be actuated resulting in full HPI)
IF MU Tank level drops below 18", THEN close Makeup Tank Outlet ATC (CV-1275). (MUT not expected to go below 18.
ATC Verify proper EFW actuation and control (RT 5).
BOP (The BOP may perform RT-5 as part of RT-10)
Check ESAS Actuation alarms clear on K11.
ANY IF RCS press is >150 psig, THEN verify proper ESAS actuation (RT 10).
(RCS pressure will be >150 psig)
Isolate Pressurizer Spray Line as follows:
Actions A. Place Pressurizer Spray Control in HAND AND verify closed ATC (CV-1008).
for LOSM B. Close Pressurizer Spray Isolation (CV-1009).
EOP ATC Verify ERV Isolation (CV-1000) closed.
ANY Check Nuclear Loop ICW process monitor alarm clear.
ANY Check SG tube integrity.
CET SCM is adequate, THEN control RCS press low within limits of ANY Figure 3 (RT 14).
(SCM will not be adequate)
ANY Check RCS press remains >150 psig.
ANY Check SG levels at or approaching 370 to 410".
Check primary to secondary heat transfer in progress.
ANY (Primary to secondary heat transfer will not be in progress)
Raise primary to secondary T to 40 to 60°F by adjusting TURB BYP or ATC ATM Dump Control System to establish SG press within limits of Figure 5.
IF SG press drops below 720 psig, THEN bypass MSLI.
BOP a) On Initiate module in each EFIC cabinet, place each SG bypass toggle switch in BYPASS and release.
EVENT 9 CONTINUED Page 18 of 19
Op-Test No.: 2008-1 Scenario No.: 1-R5 Event No.: 9 CONTINUED Event
Description:
A ~700gpm RCS leak will develop in the RX building resulting in ESAS actuation.
Time Position Applicants Actions or Behavior Check primary to secondary heat transfer in progress.
ANY (Primary to secondary heat transfer will not be in progress)
IF RCPs cannot be run due to either inability to maintain adequate CET SCM OR H1 and H2 bus degraded voltage (<6900V), THEN bump RCPs Action to establish primary to secondary heat.
s for N/A Establish PZR level >180".
LOSM (Pressurizer level can not be established >180 therefore RCPs will not EOP be bumped)
ATC Verify SG levels at or approaching 370 to 410".
IF an uncontrolled RCS cooldown is occurring due to HPI/break flow, CRS regardless of SG status, THEN GO TO Small Break LOCA Cooldown (1203.041).
EXAMINER NOTE This scenario may be terminated when the CRS transitions to 1203.041 OR As directed by the Lead Evaluator Page 19 of 19
Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 2-R5 Op-Test No.: 2008-1 Examiners: __________________________ Operators: __________________________
Initial Conditions:
100% Power EFIC is failed and will not auto actuate.
C2A IA compressor is out of service for overhaul.
Provide picture of RS-4 Turnover:
Day shift normal working day.
C2A IA compressor is out of service for overhaul.
Currently under a severe thunderstorm warning for the next hour. All actions of 1203.025 Natural Emergencies are complete.
Swap ICW pumps to have P33A and P33B running to allow visual inspection of P33C. The Inside AO has been briefed and is standing by the ICW pumps. P33B had not been drained.
Event Malf. No. Event Event No. Type* Description N (SRO, 1 N/A Swap operating ICW pumps BOP)
Lightning Lightning strike strike N/A 2 DI-DG2S #2 EDG auto start K01A3 #2 EDG Auto Start Alarm C (SRO, #2 EDG SW valve fails to open (TS).
CV-3807 BOP) #2 EDG Shutdown N (SRO) Dispatcher directs a power reduction to 700Mwe in the 3 N/A R (ATC) next 15 minutes.
Lightning Lightning strike strike I (SRO, 4 ATC)
ED451 Loss of the NNI Y power supply.
5 ED183 M (ALL) Loss of Offsite Power/Degraded Power DG175 #1 EDG will not auto start (BOP-CT)
DI_DG1_VR-LW #1 EDG voltage low (<4100V)
C (SRO, 7 FW621 EFIC fails (ATC-CT) (TS)
ATC)
DG173 M (ALL) #1 EDG will trip (TS) 8 A901 N/A Alternate AC Generator available. (BOP-CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 15
Appendix D Scenario Outline Form ES-D-1 Scenario #2-R5 Objectives
- 1) Evaluate individual ability to perform the swapping of the operating ICW pumps.
- 2) Evaluate individual ability to recognize and respond to the false auto start of emergence diesel generator.
- 3) Evaluate individual ability to recognize and respond to the failure to open of the service water supply valve on an operating emergence diesel generator.
- 4) Evaluate individual ability to reduce plant power.
- 5) Evaluate individual ability to recognize and respond to the loss of the Y Non-Nuclear Instrumentation system.
- 6) Evaluate individual ability to recognize and respond to a loss of offsite power.
- 7) Evaluate individual ability to recognize and respond to failure of the emergence diesel generator to auto start.
- 8) Evaluate individual ability to recognize and respond to the failure of the Emergency Feedwater Initiation and Control system to automatically actuate emergency feedwater.
- 9) Evaluate individual ability to recognize and respond to the tripping of the remaining emergence diesel generator putting the plant in a blackout condition.
- 10) Evaluate individual ability to perform the energizing of a vital bus from the alternate AC generator.
- 11) Evaluate individual ability to recognize when conditions require the entry into technical specifications conditions.
Page 2 of 15
Appendix D Scenario Outline Form ES-D-1 SCENARIO #2-R5 NARRATIVE The crew will assume the watch at 100% power. C2A IA compressor is out of service for overhaul. It is a day shift normal working day. ANO is currently under a severe thunderstorm warning for the next hour. All actions of 1203.025 Natural Emergencies are complete.
The crew will start P33B and secure P33C per1104.028 ICW Operating Procedure step10.2 (BOP-N) (SRO-N). This is being performed in order to visually inspect the motor rotor. P33B had not been drained.
A lightning strike will cause the auto start of the #2 EDG. The CRS should direct operations per 1203.012A Annunciator K01 Corrective Actions. The crew should determine it is a spurious actuation. The #2 EDG SW valve CV-3807 will not open resulting in no cooling flow to the EDG (BOP-C) (SRO-C). The crew should take the #2 EDG to lockout to prevent an automatic trip of the EDG (TS).
TS 3.8.1. Condition B The dispatcher will call and direct U1 to reduce net generator output to 700Mwe (SRO-N)
(ATC-R).
A second lightning strike will result in the loss on NNI-Y power supply (ATC-I) SRO-I). The crew should recognize the loss of NNI-Y power. The CRS should implement 1203.047 Loss of NNI Power. The power supply breakers on RS-4 bkr 9 and Y01 bkr 39 will not reset. Breakers S-1 and S-2 on the NNI-Y power supply will not be tripped.
Letdown flow and pressure indication will be lost on C04. The letdown orifice bypass valve will fail to 50% reducing letdown flow. CFT pressure instrumentation will be lost along with NaOH tank temperature. All NNI-Y inputs to PMS/PDS will be lost or fail to mid scale.
A loss of offsite power will occur due to storm related grid instabilities (SRO-M) (ATC-M)
(BOP-M). The reactor will trip automatically. The CRS will direct operations per 1202.001 Rx Trip. After the immediate actions are complete the CRS will transition to either 1202.008 Blackout or 1202.007 Degraded Power depending on when the BOP manually starts the #1 EDG.
The #1 EDG will not auto start requiring the BOP to manually start the EDG (BOP-C) (BOP-CT).
The #1 EDG voltage will be <4100V requiring the BOP to raise EDG voltage.
CT criteria - The BOP should start the #1 EDG before the 15 minute criteria for declaring an SAE for a station blackout.
The EFIC system is failed and will not automatically actuate EFW on the Loss of Offsite Power (ATC-C) (SRO-C). The ATC should manually actuate EFW from the remote switch matrix (ATC-CT) (TS). The ATC will perform 1202.012 Repetitive Tasks RT-5 Verify proper EFW actuation and control. EFW may be manually actuated before the step in the EOP that directs verifying EFW actuated.
TS 3.3.11 Condition B CT - EFW should be manually actuated before the ERV opens in automatic.
CONTINUED Page 3 of 15
Appendix D Scenario Outline Form ES-D-1 SCENARIO #2-R5 NARRATIVE CONTINUED The #1 EDG will trip putting the plant into a blackout (SRO-M) (ATC-M) (BOP-M) (TS). The CRS will direct operations per 1202.008 Blackout.
TS 3.8.1 Condition E, 3.0.3 The alternate AC generator will become available. The BOP should energize the A3 bus from the AAC generator (BOP-CT).
CT criteria - The AAC generator should be placed in service within 20 minutes of regaining the AAC Generator.
Page 4 of 15
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 2-R5 Value/ Event Event Time Malf. No. Ramp Description No.
Time Recall IC 102 IMF FW621 EFIC failure IRF CO_C2A off C2A IA compressor OOS IOR DO_C2ASLG C2A IA compressor OOS IMF DG175 #1 EDG fails to auto start IMF CV3807 Off #2 EDG SW valve fails closed IRF K01E7 Off D01 Trouble off IOR DI_DG1_VR_LW 15sec #1 EDG voltage low Swap operating ICW pumps to have 1 0 N/A N/A P33A and P33B running.
T1 IRF Lightning True IOR DI-DG2S True Lightning strike will cause the auto start 10 IOR DI_DG2SP False of #2 EDG.
IRF K01A3 On 2
DRF Lightning
- 2 EDG SW valve will not open following the EDG auto start. This will Initial IMF CV-3807 0 require the operators to shutdown #2 EDG. (TS)
Dispatcher will call and direct a power 3 18 N/A N/A reduction to 700 Mwe in the next 15 minutes.
T2 True Another lightning strike will result in the 4 28 IRF Lightning N/A loss of the NNI Y power supply.
IMF ED451 A Loss of Offsite Power will occur 5 36 IMF ED183 N/A resulting in an automatic reactor trip.
The #1 EDG will not auto start requiring the operators to manually start the EDG.
6 Initial IMF DG175 N/A (BOP-CT) criteria - The BOP should start the #1 EDG before 15 minute criteria for declaring an SAE for a station blackout.
CONTINUED Page 5 of 15
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 2-R5 Value/ Event Event Time Malf. No. Ramp Description No.
Time EFIC is failed and will not automatically actuate EFW.
7 Initial IMF FW621 N/A (TS) (ATC-CT) criteria - EFW should be manually actuated before the ERV opens in automatic.
U2 will report ACC Generator is running slow. Maintenance has been dispatched.
N/A The #1 EDG will trip putting the plant 48 IMF DG173 into a blackout. (TS)
At T=52 U2 will report AAC Generator has been repaired and is running normally with 2A901 closed.
8 The Alternate AC Generator will become available.
Closed (BOP-CT) CT criteria - The AAC 52 IRF A901 generator should be placed in service within 20 minutes of regaining the AAC Generator.
Page 6 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 1 Event
Description:
Swap operating ICW pumps to have P33A and P33B running.
Time Position Applicants Actions or Behavior CRS Direct performance of 1104.028 ICW Operating Procedure step 10.2.
Open A/B crossconnect valves:
0 BOP
- ICW Pumps Suction Crossconnect (CV-2241)
- ICW Pumps Discharge Crossconnect (CV-2239)
Direct AO to vent P-33B as necessary by opening ICW Pump P-33B BOP Vent (ICW-1191).
BOP Start P-33B.
BOP When P-33B has run at least 3 minutes, Then stop P-33C.
Verify flow is normal (~2000 gpm) on ICW Coolers Inlet Flow Non-Nuc BOP (FI-2218) (CO9).
EXAMINERS NOTE:
This event is complete when ICW flows are verified normal OR As directed by the Lead Evaluator Page 7 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 2 Event
Description:
Lightning strike will cause the auto start of #2 EDG.
- 2 EDG SW valve will not open following the EDG auto start. This will require the operators to shutdown #2 EDG.
Time Position Applicants Actions or Behavior Acknowledge and report Annunciator K01A3 EDG 2 AUTO START 10 CRS COMMAND.
CRS Direct plant operation per K01A3 EDG 2 AUTO START COMMAND.
BOP Verify that DG2 auto start.
BOP Check bus A4 energized from bus A1.
BOP Check bus B6 energized.
Verify SERV WTR to DG2 CLRS (CV-3807) opens.
ANY Recognize and report CV3807 will not open.
EXAMINEERS NOTE If called the AO will report CV-3807 cannot be opened locally.
Direct #2 EDG be placed in lockout. (BOP may try to push stop P/B first.
CRS EDG will stop but then restart)
TS 3.8.1. Condition B EXAMINEERS NOTE If called U2 will report Alternate AC Generator is available.
CRS Contact work management to investigate cause of EDG start.
CRS Refer to TS 3.8.1 Condition B for operability requirements.
Verify proper MOD alignment for Service Water Pump (P-4B) and Makeup Pump (P-36B) per Makeup & Purification System Operation CRS (1104.002) AND Service Water and Auxiliary Cooling System (1104.029).
EXAMINERS NOTE:
This event is complete when #2 EDG is in lockout OR As directed by the Lead Evaluator Page 8 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 3 Event
Description:
Dispatcher will call and direct a power reduction to 700MWe in the next 15 minutes.
Time Position Applicants Actions or Behavior 18 CRS Direct operations per 1203.045 Rapid Plant Shutdown.
Commence a plant shutdown at 0.5 to 10% per minute.
ATC Place ULD in manual Lower ULD setpoint to ~730 MWe ATC Monitor ICS and EHC subsystems for proper integrated response.
BOP ATC Refer to "Contingency Reactivity Plans.
CRS At <90%, direct Zinc Injection be secured.
ATC Stabilize power ~700 Mwe.
EXAMINERS NOTE:
This event is complete when power is stable at ~700 Mwe OR As directed by the Lead Evaluator Page 9 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 4 Event
Description:
Another lightning strike will result in the loss of the NNI Y power supply.
Time Position Applicants Actions or Behavior Recognize the loss of NNI-Y power.
Recognize and report loss of letdown flow and pressure indication on 28 ANY C04.
Recognize and report CV-1223 at 50%.
CRS Direct operations per 1203.047 Loss of NNI Power.
Verify NNI X-powered instruments selected on C03, C04, and C13.
ATC (Green light on for each SASS parameter)
BOP (CRS may direct placing SASS selector switch to the X position)
ATC Check NNI Y AC power available.
EVALUATOR NOTE:
The BOP will go to back of control room to a picture of RS-4 to simulate resetting Breaker RS-4 bkr 9.
The evaluator will tell the BOP that bkr 9 will not reset.
BOP Reset AND close Normal supply breaker RS-4 bkr 9.
Dispatch an operator to reset AND close Alternate supply breaker Y01 CRS bkr 39, while continuing with this procedure.
EXAMINERS NOTE:
Report as AO that Y01 bkr 39 will not reset.
Dispatch an operator to reset NNI Y power supply using Reactor Coolant System NNI (1105.006), "Resetting NNI Power Supplies" section, while continuing with this procedure.
CRS The S-1 and S-2 switches are on the NNI power supply and will not be tripped. Time will not permit any operator actions to be accomplished by the outside control room operator.
EXAMINERS NOTE:
This event is complete when instruments are verified selected to NNI-X power and power supply breakers Y01 bkr 39 and RS-4 bkr 9 are reported as not closing OR As directed by the Lead Evaluator Page 10 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 5 Event
Description:
A Loss of Offsite Power will occur resulting in an automatic reactor trip.
Time Position Applicants Actions or Behavior 36 ANY Recognize and report a loss of offsite power.
CRS Direct operations per 1202.001 RX trip.
ATC Manually Trip Rx, Verify all rods inserted and Reactor power dropping.
BOP Manually trip Turbine, Verify Turbine throttle and governor valves closed.
ANY Check adequate SCM.
EXAMINERS NOTE:
This event is complete when the immediate actions of 1202.001 are complete OR As directed by the Lead Evaluator Page 11 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 6 & 7 Event
Description:
The #1 EDG will not auto start requiring the operators to manually start the EDG.
EFIC is failed and will not automatically actuate EFW.
Time Position Applicants Actions or Behavior LOOP ANY Recognize #1 EDG failed to auto start.
Manually start #1 EDG.
BOP (BOP-CT) CT criteria - The BOP should start the #1 EDG before the 15 minute criteria for declaring an SAE for a station blackout.
CRS Direct operations per 1202.007 Degraded Power.
Verify both EDGs supplying associated ES buses with proper voltage, frequency and loading:
- 4100 to 4200V
- 59.5 to 60.5 Hz
BOP Adjust #1 EDG voltage to ~4160V.
BOP Verify 480V MCC B55 and 56 power supply is selected to B5.
BOP Close ACW Isolation (CV-3643).
BOP Close CV-3640 BOP Close CV-3820 Recognize and report Service Water Pump discharge pressure high ANY alarm.
(CRS may elect to place additional SW loads in service)
Dispatch an operator to restore EDG. (May not be performed as #2 EDG CRS is known to be OOS.)
EXAMINERS NOTE:
U2 will report ACC Generator is running slow. Maintenance has been dispatched.
CRS Request U2 start AAC Generator.
BOP Verify P36B Bus Select MOD Control selected to A3.
BOP Verify P4B Bus Select MOD Control selected to bus A3.
EVENT 6 & 7 CONTINUED Page 12 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 6 & 7 CONTINUED Event
Description:
The #1 EDG will not auto start requiring the operators to manually start the EDG.
EFIC is failed and will not automatically actuate EFW.
Time Position Applicants Actions or Behavior BOP Verify SW to DG1 CLRs open (CV-3806).
BOP Verify a Service Water pump P4A on after 15-second time delay.
Actuate MSLI for both SGs AND verify proper actuation and control of EFW and MSLI (RT 6).
ATC TS 3.3.11 Condition B (ATC-CT) CT - EFW should be manually actuated before the Electromatic Relief Valve (ERV) opens in automatic.
Operate ATM Dump CNTRL valves in HAND to minimize cycling and ATC conserve Instrument Air.
(Crew may determine ADVs not cycling and leave in auto)
ANY Check RCS press remains >1700 psig PZR level remains >30".
BOP Isolate Letdown by closing Letdown Cooler Outlets (CV-1214 and 1216).
ANY Check OP and STBY HPI pumps off.
Place RCP Seals Bleedoff (Alternate Path to Quench Tank) controls in BOP CLOSE (SV-1270, 1271, 1272 and 1273).
Isolate RCP Seal Bleedoff (Normal) by closing CV-1270, 1271, 1272, BOP and 1273.
IF PZR level is >55", THEN verify Proportional Control Pressurizer ATC Heaters operating in AUTO.
Place the following breakers in handswitches in PULL-TO-LOCK.
ATC A1, A2, H1, H2 BOP Condensate pumps (P2A, B and C)
ICW pumps (P33A, B and C)
ATC Verify RCP Seal INJ Block closed (CV-1206).
BOP Close RCS Makeup Block (CV-1233 or 1234).
BOP Open BWST Outlet to OP HPI pump CV-1407.
EXAMINERS NOTE:
This event is complete when CV-1407 is open OR As directed by the Lead Evaluator Page 13 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 8 Event
Description:
The #1 EDG will trip putting the plant into a blackout.
The Alternate AC Generator will become available.
Time Position Applicants Actions or Behavior Recognize and report #1 EDG tripped.
48 ANY TS 3.8.1 Condition E, 3.0.3 CRS Direct operations per 1202.008 Blackout.
Verify proper EFW actuation and control (RT 5).
ATC (CRS may direct ATC to re-perform RT5. RT 5 was performed during the Degraded Power event.)
Dispatch an operator to restore EDG (May not be performed as #2 EDG CRS is known to be OOS.)
EXAMINERS NOTE:
U2 will report Maintenance is working on the ACC Generator CRS Request U2 start AAC Generator.
ATC Check adequate SCM is maintained.
ATC Place P7B handswitch in PULL-TO-LOCK.
BOP Check off-site power available.
Direct dispatcher to take emergency actions to restore power, including CRS system load shed if necessary.
CRS Transition to step 33.
Dispatch an operator to take manual control of EFW pump (P7A) using CRS Emergency Feedwater pump Operation (1106.006).
EXAMINEERS NOTE Call as U2 and report AAC Generator is running normally and 2A-901 is closed.
52 CRS Transition to step 2 of 1202.008 Blackout.
Direct BOP to energize A3 using ES Electrical System Operation (1107.002), Alternate AC Generator Operation" section.
CRS (BOP-CT) CT criteria - The AAC generator should be placed in service within 20 minutes of regaining the AAC Generator.
BOP Place DG1 Output Breaker (A-308) in PULL-TO-LOCK.
BOP Verify A1 to A3 Supply Breaker (A-309) open.
EVENT 8 CONTINUED Page 14 of 15
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R5 Event No.: 8 CONTINUED Event
Description:
The #1 EDG will trip putting the plant into a blackout.
The Alternate AC Generator will become available.
Time Position Applicants Actions or Behavior BOP Verify A3-A4 Tie Breakers open (A-310 and A-410).
BOP Verify no bus A3 Lockout.
BOP Turn Synchronize switch on for A3-A4 Tie Breakers (A-310 and A-410).
BOP Close A3-A4 Crosstie (A-310).
BOP Turn Synchronize switch off.
Coordinate with Unit 2 to ensure 2K9 is NOT overloaded when starting BOP loads on bus A3.
If desired, Then start Service Water Pump P-4A or B per Service Water BOP and Auxiliary Cooling System (1104.029).
CRS GO TO 1202.007, "DEGRADED POWER" procedure.
EXAMINERS NOTE:
This scenario is complete when A3 is powered from the AAC Generator OR CRS transitions back to 1202.007 Degraded Power OR As directed by the Lead Evaluator Page 15 of 15
ES-301 Transient and Event Checklist Rev 1 Form ES-301-5 Facility: ANO-1 Date of Exam: 9-8-2008 Operating Test No.: 2008-1 A E Scenarios P V 1 2 3 (Spare) M P E I N CREW POSITION CREW POSITION CREW POSITION T N L I I T O M
C A T U S A B S A B S B A T T A M(*)
R T O R T O R O Y C L N O C P O C P O P R I U T P E
RX 2, 5 3 2 1 1 0 NOR 1 1, 3 7 1 1 1 1 1 RO I/C 2, 4, 6, 2, 4, 5, 3, 7, 8 2, 6 4, 6, 9 5 4 4 2 1, 2, 3 9 6, 9 MAJ 6, 9 5, 8 6, 7 7, 6 6, 7 4 2 2 1 TS 6, 6, 7 0 0 2 2 RX 3 0 1 1 0 NOR 1, 2, 5 3 1 1 1 I/C 3, 4, 7, SRO-U 4, 7 5 4 4 2 2, 3, 5 8, 9 MAJ 6, 9 5, 8 2 2 2 1 TS 7, 8, 9, 4 0 2 2 9
RX 0 1 1 0 NOR 1 1, 3 2 1 1 1 SRO-U I/C 2, 4, 6, 4, 9 4 4 4 2 1, 4, 6 7 MAJ 6, 9 5, 8 2 2 2 1 TS 2, 7, 8 3 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Competencies Checklist Rev 1 Form ES-301-6 Facility: ANO-1 Date of Examination: 09/08/2008 Operating Test No.: 2008-1 APPLICANTS RO SRO-U Competencies SCENARIO SCENARIO 1 2 3 (Spare) 1 2 3 (Spare)
Interpret/Diagnose 2, 3, 6, 7, 2, 4, 5, 6, 8 2, 4, 5, 6, 2, 3, 4, 6, 7, 2, 4, 5, 6, 2, 4, 5, 6, Events and Conditions 8, 9 7, 9 8, 9 7, 8 7, 9 Comply With and 2, 3, 5, 6, 1, 2, 4, 5, 6, 1, 2, 3, 4, 1, 2, 3, 4, 5, 1, 2, 3, 4, 1, 2, 3, 4, Use Procedures (1) 7, 8, 9 8 5, 6, 7, 8, 6, 7, 8, 9 5, 6, 7, 8 5, 6, 7, 8, 9 9 Operate Control 2, 3, 5, 6, 1, 2, 4, 5, 6, 1, 3, 4, 6, N/A N/A N/A Boards (2) 7, 8, 9 8 7, 8, 9 Communicate 2, 3, 5, 6, 1, 2, 3, 4, 5, 1, 2, 3, 4, 1, 2, 3, 4, 5, 1, 2, 3, 4, 1, 2, 3, 4, and Interact 7, 8, 9 6, 8 5, 6, 7, 8, 6, 7, 8, 9 5, 6, 7, 8, 5, 6, 7, 8, 9 9 9 Demonstrate N/A N/A N/A 1, 2, 3, 4, 5, 1, 2, 3, 4, 1, 2, 3, 4, Supervisory Ability (3) 6, 7, 8, 9 5, 6, 7, 8 5, 6, 7, 8, 9
Comply With and N/A N/A N/A 7, 8, 9, 9 2, 7, 8 6, 6, 7 Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.