IR 05000313/2008301
| ML082750586 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/05/2008 |
| From: | Operations Branch IV |
| To: | |
| References | |
| Download: ML082750586 (339) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 1-R2 Op-Test No.: 2008-1 Examiners: __________________________ Operators: __________________________
__________________________ __________________________
__________________________ __________________________
Initial Conditions:
80% power due to dispatcher direction for loss of 500K C2A IA compressor is out of service for overhau ULD is failed and will not lower powe RPS is failed and will not initiate a RX tri Provide stop watch for surveillanc Turnover:
Day shift normal working da % power due to dispatcher direction for loss of 500KV line as a result of maintenance on the Mabelvale 500KV lin C2A IA compressor is out of service for overhau .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 surveillanc Crew will continue in surveillance after turnove Event Malf. N Event Event N Type* Description N (SRO, Perform 1104.005 Supplement 2 RB Spray Red Train 1 N/A BOP) Valves Quarterly Tes I (SRO, 2 AI_FIC1207 RCP total flow setpoint fails to hig ATC)
C (SRO, 3 CV016 RCP seal failur BOP)
N (SRO)
4 N/A Power reduction R (ATC)
DI_H24T C (ALL) Loss of H2 bu If power <55%,
CO_P32A N/A Trip A RCP (Contingency to ensure RPS trip setpoint is reached.)
C (SRO, RP246,7,8,9 RPS is failed 6 ATC)
Manual RX trip (TS) (ATC-CT)
M (ALL)
C (SRO, B RCP seal failure CV020 7 BOP)
RC006 ~200gpm RCS leak (TS) (BOP-CT)
M (ALL)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 10
Appendix D Scenario Outline Form ES-D-1 Scenario #1-R2 Objectives 1) Evaluate individual ability to perform the valve stroke test of the Engineered Safegaurds Reactor Building Spray Block Valv ) Evaluate individual ability to recognize and respond to a failed reactor coolant pump total seal injection flow controller setpoin ) Evaluate individual ability to recognize and respond a degraded reactor coolant pump sea ) Evaluate individual ability to perform a plant power reductio ) Evaluate individual ability to stop a running reactor coolant pump at powe ) Evaluate individual ability to recognize and respond a loss of a 6900V H bus and resulting loss of a reactor coolant pum ) Evaluate individual ability to recognize and respond to a reactor trip condition where RPS fails to trip the reacto ) Evaluate individual ability to recognize and respond a post trip reactor coolant pump seal failur ) Evaluate individual ability to recognize and respond a reactor coolant system leak inside the reactor buildin ) Evaluate individual ability to recognize when conditions require the entry into technical specifications condition ) Evaluate individual ability to recognize and respond to the need for high pressure injection as a result of increased reactor coolant system leakag Page 2 of 10
Appendix D Scenario Outline Form ES-D-1 SCENARIO #1-R2 NARRATIVE The crew will assume the watch at 80% power. The Mayflower 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.
There is a severe thunderstorm warning in effect for Pope and Yell counties for the next two hours. All Natural Emergency (1203.025) actions are complete for this notification.
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 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).
When the B RCP is stopped a loss of the H2 bus will occur resulting in a loss of two RCPs (B and D) (BOP-C) (SRO-C) (ATC-C). If reactor power is <55% then the A RCP will be tripped 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 reacto (ATC-C) (SRO-C) (ATC-CT) (ALL-M) (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.
~5 minutes post trip a ~300gpm leak will occur in the reactor building from the failed RCP seal (SRO-C) (BOP-C) (ALL-M) (TS). The crew should recognize the leak and the BOP should initiate HPI per RT-2 to maintain RCS inventory pressure and subcooling margin (BOP-CT).
TS 3.4.13 Condition A CT criteria - HPI should be started before the ESAS actuates on low RCS pressur Page 3 of 10
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 1-R2 Value/ Event Event Time Malf. N Ramp Description N Time Recall IC To be established during validation IMF RP246,7,8,9 Perform remaining steps of 1104.005 1 0 N/A N/A Supplement 2 RB Spray Red Train Valves Quarterly Tes RCP total flow setpoint fails high. This 2 IOR will result CV-1207 Seal Injection AI_FIC1207 control valve traveling full ope Seal Inj. IMF CV016 N/A RCP seal failure requiring power 8-10 gpm reduction and securing of the RC As 4 directed N/A N/A Power reduction to ~60%
by SRO RCP Stopped Or IMF ED184 N/A Loss of H2 bus when RCP is secure %
power 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 6 Initial N/A (TS) (ATC-CT) criteria - The reactor RP246,7,8,9 should be manually tripped within 2 minutes of the loss of the H2 bu IMF CV020 100 B RCP seal failure Rx trip IMF RC006 0.0016 ~300gpm RCS leak (TS) (BOP-CT)
120 200 criteria - HPI should be started
+5 min before the ESAS actuates on low RCS pressur Page 4 of 10
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R2 Event No.: 1 Event Description:
Perform remaining steps in 1104.005 Supplement 2 Red train Spray Valve Tes Time Position Applicants Actions or Behavior 0 BOP Implement 1104.005 Supplement 2 step 2.2.2. (BOP-N) (SRO-N)
BOP Verify Makeup Tank pressure > 25 psi 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 indicatio BOP Record closed stroke in Table 1 BOP Close CV-1407 This event is complete when Supplement 2 is complet Page 5 of 10
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R2 Event No.: 2 Event Description:
RCP total flow setpoint fails high. This will result CV-1207 Seal Injection control valve traveling full ope Time Position Applicants Actions or Behavior Recognize, acknowledge, and report Annunciator K08-B7 RCP Bleedoff 12 ATC Flow HI (ATC-I) (SRO-I)
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) ope 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 gp Provide Attachment A of this procedure to a Control Board Operator to CRS aid in monitoring seal parameter This event is complete when RCS seal injection flow is 8 to10 gp Page 6 of 10
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R2 Event No.: 3 & 4 Event Description:
RCP seal failure Time Position Applicants Actions or Behavior RCP seal In BOP Recognize and report B RCP seal failure. (BOP-C) (SRO-C)
8-10 gpm Direct operations per 1203.012G K08 Annunciator Corrective Action And 1203.031 Reactor Coolant Pump and Motor Emergency ANY Determine Seal bleed off temp >40°F above 1st stage seal tem CRS Implement Rapid Plant Shutdown (1203.045)
Reduce reactor power to within the capacity of the unaffected RCP ATC combination, using Rapid Plant Shutdown (1203.045)
CRS Direct power reduction using ULD ATC BOP Lower plant power to <60% (SRO-N) (ATC-R)
This event is complete when plant power is <60%
Page 7 of 10
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R2 Event No.: 5 & 6 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% powe Time Position Applicants Actions or Behavior Direct BOP to stop the affected RCP(s) per Reactor Coolant Pump CRS Operation (1103.006)
IF time permits, THEN contact predictive maintenance to install backup ANY indication of RCP zero speed prior to RCP sto Start HP Oil Lift Pump (P-63B)
BOP OR Emergency HP Oil Lift Pump (P-80B)
BOP Stop P-32 BOP Verify HP Oil Lift Pump (P-63B) remains o ANY Monitor affected RCP for reverse rotation Recognize loss of H2 bus and two RCPs (BOP-C) (SRO-C) (ATC-C)
Recognize RPS failed to complete an automatic trip. (ATC-C) (SRO-C)
ANY (TS)
TS 3.3.1 Condition C Direct manual trip of the reactor and performance of immediate action CRS (ATC may trip the reactor before the CRS direction.)
Manually Trip Rx. (ATC-CT) (BOP-M) (SRO-M) (ATC-M)
Verify all rods inserted AND ATC Reactor power droppin CT criteria - The reactor should be manually tripped within 2 minutes of the loss of the H2 bu Manually trip Turbin BOP Verify Turbine throttle and governor valves close ATC or Check adequate SC BOP Advise Shift Manager to implement Emergency Action Level CRS Classification (1903.010).
ATC Reduce Letdown by closing Orifice Bypass (CV-1223).
BOP Open BWST Outlet to OP HPI pump (CV-1407 or 1408).
BOP Check for proper electrical response Check OP HPI pump supplying normal ANY Makeup and Seal Injectio ATC Check both SG levels remain 410".
Check Instrument Air Header press ANY 75 psig ANY Check all NNI power available:
ANY Check all ICS power available:
EVENT 5 & 6 CONTINUED Page 8 of 10
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R2 Event No.: 5 & 6 CONTINUED Event Description:
Loss of H2 bus when RCP is secure RPS is failed requiring a manual RX trip on a loss of two RCPs >55% powe Time Position Applicants Actions or Behavior ATC Check SG press 900 psi ANY Check MSSV OPEN alarm clear (K07-C5).
ANY Check MSIVs ope ANY Check Turb BYP valves operate to maintain SG press 970 to 1020 psi ANY Place both Feedwater Demands in HAND AND verify demand at zer 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 across ANY Startup valve 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)
ANY Check ESAS Actuation alarms clear on K1 ANY Check RCS press 1700 psi Check Pressurizer Level Control valve ATC (CV-1235) maintains PZR level 55".
ANY Check PZR steam space integrit Verify ERV, Pressurizer Spray, and Pressurizer Heaters operate to ontrol ATC RCS press 2050 to 2250 psi ANY Check at least one RCP runnin ATC Check RCS T-cold remains 540 ANY Check adequate SC Check RCS temp remains either:
580 F T-hot with any RCP on ATC OR 610 F CET temp with all RCPs of BOP Check SG tube integrity ANY Check RCS integrity This event is complete when the CRS leak is starte Page 9 of 10
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 1-R2 Event No.: 7 Event Description:
An ~200gpm RCS leak will develop in the RX building requiring HP Time Position Applicants Actions or Behavior Trip +
ANY Recognize and report lower PZR level and RCS pressure 5 min Recognize and report additional seal failed on B RCP (BOP-C) (SRO-C)
Diagnose RCS leak inside containment (BOP-M) (SRO-M) (ATC-M) (TS)
ANY TS 3.4.13 Condition A ANY Determine leak rate >50 gpm (EAL consideration)
CRS Direct implementation of HPI per Repetitive Tasks 1202.012 RT-2 Isolate Letdown by closing either:
Letdown Coolers Outlet (CV-1221)
BOP OR Letdown Cooler Outlets (CV-1214 and 1216)
BOP Open BWST Outlet to OP or STBY HPI pump (CV-1407 or 1408).
ANY Place or verify RCP Seal INJ Block (CV-1206) in OVR Open HPI Block valve associated with OP or STBY HPI pump (CV-1220 or 1285) to maintain PZR level and RCS press (BOP-CT)
BOP CT criteria - HPI should be started before the ESAS actuates on low RCS pressur BOP Open additional HPI Block valves associated with OP HPI pump IF PZR level or RCS press continues to drop, THEN place ES HPI pump BOP in service BOP Open BWST Outlet to ES HPI pump (CV-1407 or 1408).
BOP Verify both HPI RECIRC valves open (CV-1300 and 1301)
BOP Start AUX Lube Oil pump for ES HPI pump BOP WHEN BWST Outlet is open, THEN start ES HPI pump BOP Stop AUX Lube Oil pump Open HPI Block valve associated with ES HPI pump (CV-1220 or 1285)
BOP to maintain PZR level and RCS press (modulating valves).
BOP Open additional HPI Block valves associated with ES HPI pump:
This scenario may be terminated when HPI is initiate Page 10 of 10
Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 2-R2 Op-Test No.: 2008-1 Examiners: __________________________ Operators: __________________________
__________________________ __________________________
__________________________ __________________________
Initial Conditions:
100% Power EFIC is failed and will not auto actuat C2A IA compressor is out of service for overhau Provide picture of RS-4 Turnover:
Day shift normal working da C2A IA compressor is out of service for overhau Currently under a severe thunderstorm warning for the next hour. All actions of 1203.025 Natural Emergencies are complet Swap ICW pumps for normal pump rotation to have P33A, and P33B running. The Inside AO has been briefed and is standing by the ICW pumps. P33B had not been draine Event Malf. N Event Event N Type* Description N (SRO, 1 N/A Swap operating ICW pumps BOP)
Lightning Lightning strike strike 2 N/A DI-DG2S #2 EDG auto start K01A3 #2 EDG Auto Start Command Annunciator C (SRO, 3 CV-3807 #2 EDG SW valve fails to open (TS).
BOP)
N (SRO) Dispatcher directs a power reduction to 700Mwe in the 4 N/A R (ATC) next 15 minute Lightning Lightning strike strike I (SRO, 5 ATC)
ED451 Loss of the NNI Y power suppl 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 8 FW621 C (ATC) EFIC fails (ATC-CT) (TS)
C (ALL)
9 DG173 #1 EDG will trip (TS)
M (ALL)
N (SRO, 10 A901 Alternate AC Generator available. (BOP-CT)
BOP)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 14
Appendix D Scenario Outline Form ES-D-1 Scenario #2-R2 Objectives 1) Evaluate individual ability to perform the swapping of the operating ICW pump ) Evaluate individual ability to recognize and respond to the false auto start of emergence diesel generato ) Evaluate individual ability to recognize and respond to the failure to open of the service water supply valve on an operating emergence diesel generato ) Evaluate individual ability to reduce plant powe ) Evaluate individual ability to recognize and respond to the loss of the Y Non-Nuclear Instrumentation syste ) Evaluate individual ability to recognize and respond to a loss of offsite powe ) Evaluate individual ability to recognize and respond to failure of the emergence diesel generator to auto star ) Evaluate individual ability to recognize and respond to the failure of the Emergency Feedwater Initiation and Control system to automatically actuate emergency feedwate ) Evaluate individual ability to recognize and respond to the tripping of the remaining emergence diesel generator putting the plant in a blackout conditio ) Evaluate individual ability to perform the energizing of a vital bus from the alternate AC generato ) Evaluate individual ability to recognize when conditions require the entry into technical specifications condition Page 2 of 14
Appendix D Scenario Outline Form ES-D-1 SCENARIO #2-R2 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 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 #1 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.
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 #1 EDG will not auto start requiring the BOP to manually start the EDG (BOP-C) (BOP-CT).
The #1 EDG voltage will be low 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 (ATC-C). The ATC should manually actuate EFW from the remote switch matrix (ATC-CT) (TS).
TS 3.3.11 Condition B CT - EFW should be manually actuated before the ERV opens in automatic.
The #1 EDG will trip putting the plant into a blackout (SRO-M) (ATC-M) (BOP-M) (SRO-C)
(ATC-C) (BOP-C) (TS).
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) (BOP-N) (SRO-N).
CT criteria - The AAC generator should be placed in service within 20 minutes of losing
- 1 ED Page 3 of 14
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 2-R2 Value/ Event Event Time Malf. N Ramp Description N Time Recall IC 2 IMF FW621, IRF CO_C2A off, IOR DO_C2ASLG 1 Swap operating ICW pumps to have 0 N/A N/A P33A and P33B runnin IRF Lightning True Lightning strike will cause the auto start 2 10 IOR DI-DG2S True of #2 ED #2 EDG SW valve will not open 3 0 following the EDG auto start. This will Initial IMF CV-3807 require the operators to shutdown #2 EDG. (TS)
Dispatcher will call and direct a power 4 18 N/A N/A reduction to 700 Mwe in the next 15 minute IRF Lightning True Another lightning strike will result in the 5 28 IMF ED451 N/A loss of the NNI Y power suppl N/A A Loss of Offsite Power will occur 36 IMF ED183 resulting in an automatic reactor tri The #1 EDG will not auto start requiring the operators to manually start the ED 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 blackou CONTINUED Page 4 of 14
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 2-R2 Value/ Event Event Time Malf. N Ramp Description N Time EFIC is failed and will not automatically actuate EF (TS) (ATC-CT) criteria - EFW should 8 Initial IMF FW621 N/A be manually actuated before the ERV opens in automati N/A The #1 EDG will trip putting the plant 48 IMF DG??? into a blackout. (TS)
U2 will report ACC Generator is running slow. Maintenance has been dispatche At T=52 U2 will report AAC Generator has been repaired and is running normally with 2A901 close The Alternate AC Generator will become availabl Closed (BOP-CT) criteria - The AAC 52 IRF A901 generator should be placed in service within 20 minutes of losing
- 1 ED Page 5 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 1 Event Description:
Swap operating ICW pumps to have P33A and P33B runnin Time Position Applicants Actions or Behavior Open A/B crossconnect valves: (BOP-N) (SRO-N)
0 BOP * ICW Pumps Suction Crossconnect (CV-2240)
- ICW Pumps Discharge Crossconnect (CV-2238)
Direct AO to vent P-33B as necessary by opening ICW Pump P-33B BOP Vent (ICW-1191).
BOP Start P-33 WHEN P-33B has run at least 3 minutes, BOP THEN stop P-33 Verify flow is normal (~2000 gpm) on ICW Coolers Inlet Flow Non-Nuc BOP (FI-2218) (CO9).
This event is complete when ICW flows are verified norma Page 6 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 2 & 3 Event Description:
Lightning strike will cause the auto start of #2 ED #2 EDG SW valve will not open following the EDG auto start. This will require the operators to shutdown #2 ED Time Position Applicants Actions or Behavior Acknowledge and report annunciator K01A3 EDG 2 AUTO START 10 CRS COMMAN CRS Direct plant operation per K01A3 EDG 2 AUTO START COMMAND BOP Verify that DG2 auto start BOP Check bus A4 energized from bus A BOP Check bus B6 energize Verify SERV WTR to DG2 CLRS (CV-3807) open ANY Recognize and report CV3806 will not open. (BOP-C) (SRO-C)
Direct #2 EDG be placed in lockout. (Crew may try to push stop P/B firs CRS EDG will stop but then restart) TS 3.8.1. Condition B CRS Contact work management to investigate cause of EDG star CRS Refer to TS 3.8.1 Condition B for operability requirement 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).
This event is complete when #2 EDG is in lockout Page 7 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 4 Event Description:
Dispatcher will call and direct a power reduction to 700MWe in the next 15 minute 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 minut (ATC-R) (SRO-N)
ATC Place ULD in manual Lower ULD setpoint to ~730 MWe ATC Monitor ICS and EHC subsystems for proper integrated respons BOP ATC Refer to "Contingency Reactivity Plans CRS At <90%, direct Zinc Injection be secured ATC Stabilize power ~700 Mwe This event is complete when power is stable at ~700 Mwe Page 8 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 5 Event Description:
Another lightning strike will result in the loss of the NNI Y power suppl Time Position Applicants Actions or Behavior 28 ANY Recognize the loss of NNI-Y power (ATC-I) (SRO-I)
CRS Direct operations per 1203.047 Loss of NNI Power ATC Verify NNI X-powered instruments selected on C03, C04, and C1 BOP ATC Check NNI Y AC power availabl 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 rese BOP Reset AND close Normal supply breaker RS-4 bkr Dispatch an operator to reset AND close Alternate supply breaker Y01 CRS bkr 39, while continuing with this procedur Report as AO that Y01 bkr 39 will not rese Dispatch an operator to reset NNI Y power supply using Reactor Coolant System NNI (1105.006), "Resetting NNI Power Supplies" section, while CRS continuing with this procedur This event is complete when NNI-X instruments are selected or verified SASS selected to NNI X power and NNI Y power supply breakers are reported as not closin Page 9 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 6 Event Description:
A Loss of Offsite Power will occur resulting in an automatic reactor tri Time Position Applicants Actions or Behavior 36 ANY Recognize and report a loss of offsite power (ATC-M) (BOP-M) (SRO-M)
CRS Direct operations per 1202.001 RX tri ATC Manually Trip Rx, Verify all rods inserted and Reactor power droppin BOP Manually trip Turbine, Verify Turbine throttle and governor valves closed ANY Check adequate SCM This event is complete when the immediate actions of 1202.001 are complet Page 10 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 7 & 8 Event Description:
The #1 EDG will not auto start requiring the operators to manually start the ED EFIC is failed and will not automatically actuate EF Time Position Applicants Actions or Behavior LOOP ANY Recognize #1 EDG failed to auto start. (BOP-C) (SRO-C)
Manually start #2 EDG. (CT-BOP) CT criteria - The BOP should start BOP the #1 EDG before the 15 minute criteria for declaring an SAE for a station blackou CRS Direct operations per 1202.007 Degraded Powe Verify both EDGs supplying associated ES buses with proper voltage, frequency and loading:
- 4100 to 4200V BOP
- 59.5 to 60.5 Hz
- <2750 kw BOP Recognize #1 EDG voltage is low BOP Adjust #1 EDG voltage to ~4160V BOP Verify 480V MCC B55 and 56 power supply is selected to B BOP Close ACW Isolation (CV-3643).
BOP Close CV-3640 BOP Close CV-3820 Dispatch an operator to restore EDG (May not be performed as #2 EDG CRS is known to be OO U2 will report ACC Generator is running slow. Maintenance has been dispatche CRS Request U2 start AAC Generato BOP Verify P36B Bus Select MOD Control selected to A BOP Verify P4B Bus Select MOD Control selected to bus A EVENT 7 & 8 CONTINUED Page 11 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 7 & 8 CONTINUED Event Description:
The #1 EDG will not auto start requiring the operators to manually start the ED EFIC is failed and will not automatically actuate EF 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 dela Actuate EFW and MSLI for both SGs AND verify proper actuation and control of EFW and MSLI (RT 6) (ATC-C) (CT-ATC)
ATC (TS) TS 3.3.11 Condition B CT - EFW should be manually actuated before the ERV opens in automati Operate ATM Dump CNTRL valves in HAND to minimize cycling and ATC conserve Instrument Ai ANY Check RCS press remains >1700 psigPZR level remains >30".
BOP Isolate Letdown by closing Letdown Cooler Outlets (CV-1214 and 1216).
ANY Check OP and STBY HPI pumps of 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 127 IF PZR level is >55", THEN verify Proportional Control Pressurizer ATC Heaters operating in AUT Place the following breakers in handswitches in PULL-TO-LOC 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-140 This event is complete when CV-1407 is open Page 12 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 9 Event Description:
The #1 EDG will trip putting the plant into a blackou Time Position Applicants Actions or Behavior Recognize and report #1 EDG tripped. (ATC-M) (BOP-M) (SRO-M)
48 ANY (ATC-C) (BOP-C) (SRO-C) (TS) TS 3.8.1 Condition E, 3. CRS Direct operations per 1202.008 Blackou Dispatch an operator to restore EDG (May not be performed as #2 EDG CRS is known to be OO U2 will report Maintenance is working on the ACC Generator CRS Request U2 start AAC Generato ATC Check adequate SCM is maintaine 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 necessar CRS Transition to step 3 Dispatch an operator to take manual control of EFW pump (P7A) using CRS Emergency Feedwater pump Operation (1106.006).
This event is complete when the WCO is dispatched or T=52 Page 13 of 14
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 2-R2 Event No.: 10 Event Description:
The Alternate AC Generator will become availabl Time Position Applicants Actions or Behavior Report as U2 that the AAC generator is running properly and 2A901 is close CRS Transition to step 2 Direct BOP to energize A3 using ES Electrical System Operation (1107.002), Alternate AC Generator Operation" sectio CRS (BOP-N) (SRO-N) (CT-BOP) CT criteria - The AAC generator should be placed in service within 20 minutes of losing #1 ED BOP Place DG1 Output Breaker (A-308) in PULL-TO-LOC BOP Verify A1 to A3 Supply Breaker (A-309) ope BOP Verify A3-A4 Tie Breakers open (A-310 and A-410).
BOP Verify no bus A3 Lockout Turn Synchronize switch on for A3-A4 Tie Breakers (A-310 BOP and A-410).
BOP Close A3-A4 Crosstie (A-310).
BOP Turn Synchronize switch of Coordinate with Unit 2 to ensure 2K9 is NOT overloaded when starting BOP loads on bus A 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" procedur This scenario is complete when A3 is powered from the AAC Generator Page 14 of 14
Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 3-R2 Op-Test No.: 2008-1 Examiners: __________________________ Operators: __________________________
__________________________ __________________________
__________________________ __________________________
Initial Conditions:
100% power C2A IA compressor is out of service for overhau RPS is failed RX trip P/B on C03 is failed Turnover:
C2A IA compressor is out of service for overhau Swap operating EH oil pumps for following maintenance on the standby pum Event Malf. N Event Event N Type* Description N (BOP, 1 N/A Swap the operating EH oil pumps SRO)
AO_PI2418 K10B5 I (BOP, B core flood tank pressure transmitter line breaks 2 DO_HS2420R SRO) (TS)
DO_HS2420G CV2420 C (SRO, 3 FW086 P8A heater drain pump winding failure and tri BOP)
N (SRO)
4 N/A Power reduction R (ATC)
CO_P14B Operating EH pump will trip 5 CO_P14A C (BOP)
Turbine trip >43%
DI_PB9201 C (ATC) RPS is failed (TS)
RP246,7,8,9 6 C (ATC) C03 manual trip P/B failed (TS)
DI_ICC0020 M (ALL) Manual reactor trip (ATC-CT)
7 RC001 M (ALL) ~150 GPM tube leak in the A SG (TS) (BOP-CT)
8 N/A N (ATC) Plant cooldown and depressurization
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 12
Appendix D Scenario Outline Form ES-D-1 Scenario #3-R2 Objectives 1) Evaluate individual ability to swap running EH oil pump ) Evaluate individual ability to recognize and respond to the failure of a core flood tank pressure indicatio ) Evaluate individual ability to recognize and respond to a heater drain pump tri ) Evaluate individual ability to perform a rapid plant power reductio ) Evaluate individual ability to recognize and respond to the loss of the operating EH oil pump and resultant turbine tri ) Evaluate individual ability to recognize and respond to a reactor protection system failure to complete an automatic tri ) Evaluate individual ability to recognize and respond to a steam generator tube lea ) Evaluate individual ability to commence a reactor coolant system cool down and depressurizatio Page 2 of 12
Appendix D Scenario Outline Form ES-D-1 SCENARIO #3-R2 NARRATIVE The crew will assume the watch with the plant at 100% power. C2A IA compressor is out of service for overhaul.
The turn over sheet will direct the crew to swap operating turbine electro-hydraulic pumps per 1106.012 Electro-Hydraulic Oil System Operation Section 14 (SRO-N) (BOP-N).
The B Core Flood Tank pressure instrument PT-2418 tube will fail resulting in a low pressure alarm and the slow venting of the B CFT. The CRS should implement 1203.012I Annunciator K10 Corrective Action (BOP-I) (SRO-I) (TS)
TS 3.5.1 Condition B P8A heater drain pump will experience a winding failure causing a high temperature alarm and P8A trip (SRO-C) (BOP-C). The CRS should reference 1203.012E Annunciator Corrective Action P8A/P8B FLOW LO and CONDENSATE PUMP AUTOSTART.
A plant power reduction is required to maintain suction pressure. The CRS should direct the power reduction per 1203.045 Rapid Plant Shutdown (ATC-R) (SRO-N).
After the power reduction the operating EH oil will trip. The standby pump will not start (BOP-C).
The loss of both EH pumps will result in a turbine trip. (Crew may complete a manual RX trip prior to the turbine trip) The reactor will fail to trip do to a failure of RPS (ATC-C) (TS). The manual RX trip pushbutton is failed (ATC-C). The ATC should manually trip the reactor using the shunt trip breakers (ATC-CT) (ATC-M) (BOP-M) (SRO-M).
TS 3.3.1 Condition C TS 3.3.2 Condition A CT criteria - The reactor should be manually tripped before the pressurizer goes solid.
A ~150gpm tube leak will occur in the A SG (ATC-M) (BOP-M) (SRO-M) (TS). The CRS should direct operation per 1202.006 Tube Rupture. The leak will be large enough to require HPI be initiated (BOP-CT). An RCS depressurization and cooldown should be started (ATC-N).
TS 3.1.13 Condition B CT criteria - HPI should be initiated before SCM is lost.
The scenario may be terminated when a controlled cooldown and depressurization is started or at the direction of the lead evaluato Page 3 of 12
Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 3-R2 Value/ Event Event Time Malf. N Ramp Description N Time Recall IC IMF RP246,7,8,9 IOR DI_ICC0020 IRF CO_C2A off IOR DO_C2ASLG 1 0 N/A N/A Swap the operating EH oil pumps IOR AO_PI2418 0 The B core flood tank pressure IRF K10B5 ON indication will fail to zero and the B 2 8 IOR DO_HS2420R OFF CFT actual pressure will slowly vent to IOR DO_HS2420G ON the RB atmosphere. (TS)
IMF CV2420 1 P8A heater drain pump will experience a winding failure causing it to heat up 3&4 19 IMF FW086 N/A and eventually trip requiring a power reduction to ~60%.
IRF CO_P14A OFF The operating EH pump will trip causing
IRF CO_P14B OFF a loss of EH flui Main turbine trip >43% power. (Crew 3 IOR DI_PB9201 True may complete a manual RX trip prior to the turbine trip)
RPS is failed and will not cause an automatic trip. (TS) Manual trip P/B is failed requiring the operators to IMF RP246,7,8,9 N/A manually trip the reactor using the 6 Initial IOR DI_ICC0020 False shunt trip P/B. (TS) (ATC-CT) criteria -
The reactor should be manually tripped before the pressurizer goes soli A ~150 GPM tube leak will develop in the A SG requiring initiation of HP IMF RC001 .2 (TS) (BOP-CT) criteria - HPI should be initiated before SCM is los A plant cooldown is required to allow for 8 N/A N/A N/A isolation of the bad S Page 4 of 12
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 1 Event Description:
Swap the operating EH oil pumps Time Position Applicants Actions or Behavior CRS, Dispatch operator to EH oil pumps to monitor for proper operatio BOP BOP Start P-14A by placing HS-9201 in STAR AO at the EH pumps will report EH pressure on PI-8534 is reading ~1850psi ANY Recognize P-14A Pressure is norma BOP Stop P-14B This event is complete when P-14B is secured Page 5 of 12
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 2 Event Description:
The B core flood tank pressure indication will fail to zero and the B CFT actual pressure will slowly vent to the RB atmosphere. (TS)
CFT Pressure transmitter failure ANY Recognize and report CFT Low pressure alarm CRS Direct operations per 1203.012I ANY Determine PI-2418 is failed causing CFT (T-2B) pressure to be low ANY Recognize that actual CFT pressure is lowerin Determine CFT inoperable, write a Condition Report and enter TS 3. CRS Condition Crew may begin 1104.001 Core Flood System Operating Procedure to CRS raise B CFT pressure or determine a leak has occurred and CFT pressure cannot be recovered.
This event is complete when the B CFT determined to be inoperabl Page 6 of 12
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 3 & 4 Event Description:
P8A heater drain pump will experience a winding failure causing it to heat up and eventually tri A power reduction is required to maintain feedwater suction pressur Time Position Applicants Actions or Behavior Recognize and report P8A winding temperature is going up. (Crew may ANY elect to stop P8A prior to the pump tripping.)
CRS Direct operations per 1203.012E Annunciator K06 Corrective actio CRS Initiate steps to determine cause of high temperature alarm Commence reducing power at ~ 10%/minute per Rapid Plant Shutdown (1203.045) to within the capacity of T-40 high level dump (~ 630 MW or ATC
~70% power) and secure affected pump. (The pump may trip before a power reduction can be started.)
ATC, Monitor ICS and EHC subsystems for proper integrated respons BOP CRS Direct securing Zinc Injectio As time permits instruct ATC to refer to "Contingency Reactivity Plans" CRS AND Exhibit A (Operation of APSR Group) of Power Operation (1102.004)
Contact AO to verify Htr Drn Tk T-40A Hi Lvl Dump Isol (CV-3041A) is ANY open at breaker (B-3252).
Report as AO that P8A is not rotating ANY Direct AO to check the tripped Heater Drain Pump for reverse rotatio ATC, Place Low Level Condenser Spray CV-2907 AND CV-2868 in service by BOP placing HS-2907 on C02 in OPEN.
This event is complete when plant power is stabilized at ~70%
Page 7 of 12
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 5 & 6 Event Description:
The operating EH pump breaker will trip causing a loss of EH fluid and a main turbine trip >43% powe RPS is failed and will not cause an automatic trip. (TS) The operators are required the manually trip the reacto Time Position Applicants Actions or Behavior ANY Recognize and report P14A tripped and P14B failed to star Dispatch operator to reset P-14A breaker (B-3225). (Crew may not have CRS time to dispatch this operator before the turbine trips)
ANY Recognize turbine valves closing ANY Recognize turbine tripped >43% powe Recognize RPS failed to automatically trip the reacto ANY TS 3.3.1 Condition C Recognize manual reactor trip push button is failed ATC TS 3.3.2 Condition A Trip the reactor using the shunt trip push button ATC CT criteria - The reactor should be manually tripped before the pressurizer goes soli CRS Direct operations per 1202.001 Reactor Trip ANY Recognize and report a loss of offsite power CRS Direct operations per 1202.001 RX tri ATC Manually Trip Rx, Verify all rods inserted and Reactor power droppin BOP Manually trip Turbine, Verify Turbine throttle and governor valves closed ANY Check adequate SCM Advise Shift Manager to implement Emergency Action Level CRS Classification ATC Reduce Letdown by closing Orifice Bypass BOP Open BWST Outlet to OP HPI pump CV-1407 EVENT 5 & 6 CONTINUED Page 8 of 12
Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 5 & 6 Continued Event Description:
The operating EH pump breaker will trip causing a loss of EH fluid and a main turbine trip >43% powe RPS is failed and will not cause an automatic trip. Manual trip P/B is failed requiring the operators to manually trip the reactor using the shunt trip P/ Time Position Applicants Actions or Behavior ATC Adjust Pressurizer Level Control setpoint to 100" BOP Check for proper electrical response ANY Check OP HPI pump supplying normal Makeup and Seal Injectio ATC Check both SG levels remain <410".
ANY Check Instrument Air Header press >75 ps ATC Check all NNI power available ATC Check all ICS power available ATC Check SG press >900 psi ATC Check MSSV OPEN alarm clear (K07-C5).
ATC Check MSIVs ope ATC Check Turb BYP valves operate to maintain SG press 950 to 1020 psi ATC Place both Feedwater Demands in HANDAND verify demand at zer ATC Check Main Block valves closed (CV-2625 and 2675)
ATC Check Low Load Block valves closed (CV-2624 and 2674).
ATC Check Startup valves maintain SG levels 20 to 40".
Verify MFW pumps run back and then operate to maintain >70 psid ATC across Startup Valve BOP Check Two Service Water pumps (P4A, B, or C).
EVENT 5 & 6 CONTINUED Page 9 of 12
Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 5 & 6 Continued Event Description:
The operating EH pump breaker will trip causing a loss of EH fluid and a main turbine trip >43% powe RPS is failed and will not cause an automatic trip. Manual trip P/B is failed requiring the operators to manually trip the reactor using the shunt trip P/ Time Position Applicants Actions or Behavior ANY Check ICW pump supplying Nuclear loop (P33C or B).
ANY Check ICW pump supplying Non-nuclear loop (P33A or B).
BOP Check RB Cooling Fans (VSF1A, B, C, D, and E)
BOP Check Previously running Main Chiller(s) (VCH1A, B)
ANY Check ESAS Actuation alarms clear on K1 ANY Check RCS press > 1700 psi Check Pressurizer Level Control valve (CV-1235) maintains PZR level >
ATC 55" BOP Check PZR steam space integrit Verify ERV, Pressurizer Spray, and Pressurizer Heaters operate to ATC control RCS press 2050 to 2250 psi ANY Check at least one RCP runnin ATC Check RCS T-cold remains >540° ANY Check adequate SC BOP Check SG tube integrity This event is complete when the operators recognize the SG tube lea Page 10 of 12
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 7 & 8 Event Description:
A ~150 GPM tube leak will develop in the A SG requiring initiation of HP Time Position Applicants Actions or Behavior Recognize SG tube leak on the A SG ANY TS 3.1.13 Condition B CRS Transition to 1202.006 Tube Rupture CRS Direct operations per 1202.006 Tube Rupture step 25 ATC Manually Trip Rx, Verify all rods inserted and Reactor power droppin BOP Manually trip Turbine, Verify Turbine throttle and governor valves closed ANY Check adequate SCM Advise Shift Manager to Notify Nuclear Chemistry to begin CRS off-site dose projections and Implement Emergency Action Level Classification (1903.010).
BOP Open BWST Outlet to OP HPI pump CV-1407 ATC Reduce Letdown by closing Orifice Bypass BOP Adjust Header Pressure Controller setpoint ATC Check TURB BYP valves controlling SG press 950 to 990 psi Operate Pressurizer Heaters AND Pressurizer Spray valve (CV-1008) to ATC maintain RCS press low within limits of Figure ATC, WHEN RCS press is <1700 psig, THEN bypass ESA BOP BOP Verify OTSG N-16 monitors selected to Gros ANY Recognize Lowering PZR level Initiate RT2 HPI BOP CT criteria - HPI should be initiated before SCM is los ANY Determine A as bad SG Direct AO to perform Control of Secondary System Contamination CRS (1203.014) in conjunction with this procedur EVENT 7 & 8 CONTINUED Page 11 of 12
Op-Test No.: 2008-1 Scenario No.: 3-R2 Event No.: 7 & 8 Continued Event Description:
A ~150 GPM tube leak will develop in the A SG requiring initiation of HP Time Position Applicants Actions or Behavior ATC Select A SG to indicate on Header press recorde Verify EFW pump Turbine (K3) Steam Supply CV-2667 from A SG in ATC MANUAL close ANY Check adequate SCM ANY Check ESAS Actuation alarms clear on K1 ANY Check at least one RCP per loop runnin BOP Trip P-32D ATC Establish RCS cooldown rate of <100°F/hr on B SG, ATC Control RCS press low within limits of Figure 3 (RT 14).
This scenario is complete when an RCS cooldown and depressurization have been started Page 12 of 12
ES-301 Transient and Event Checklist Rev 2 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 T M P E O I N CREW POSITION CREW POSITION CREW POSITION T N L I I T S A B S A B S A B A M R T O R T O R T O L C O C P O C P O C P U
A T M(*)
N Y R I U T P E
RX 4 1 1 1 0 NOR 1, 10 2 1 1 1 RO I/C 2, 5, 6 3, 7, 9 6 4 4 2 1, 2, 3 MAJ 6,7 6, 9 4 2 2 1 TS 0 0 2 2 RX 4 0 1 1 0 NOR 1, 4 2 1 1 1 SRO-U I/C 2, 3, 5, 8, 9 5 4 4 2 2, 3, 5 5,6,7 MAJ 6,7 6, 9 2 2 2 1 TS 6,7 2 0 2 2 RX 0 1 1 0 NOR 1 1, 4, 10 3 1 1 1 SRO-U I/C 3, 5, 7, 3, 5, 7 4 4 4 2
1, 4, 6 MAJ 6,7 6, 9 2 2 2 1 TS 3, 8, 9 3 0 2 2 Instructions: 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. 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. 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.