ML15167A344
| ML15167A344 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/29/2014 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML15167A344 (217) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 1 Op Test No.: ILC-14 Examiners: Operators: CRS -
RO -
BOP -
Initial Conditions: Mode 2 BOL, 150 MWD/MTU, 1564 PPM Boron.
Reactor startup in progress IAW GP-003 at step 8.2.23. Shutdown Banks A & B are at 225 steps.
No equipment is OOS Turnover: Continue reactor startup Critical Task: Start either A or B Safety Injection Pumps to provide adequate core cooling.
Open either SI-870 A or B to establish a flow path Manually isolate Excess Letdown Isolate C S/ G prior to S/G overfill Event Malf. No. Event Type* Event No. Description (R) RO, CRS GP-003 reactor startup 1 (N) BOP (C) RO, CRS Control Bank B rod K2 stuck 2 (TS) CRS (C) BOP, CRS South Service Water leak at intake 3 (TS) CRS 4 (C) BOP,CRS Loss of Condenser vacuum 5 (I) RO, CRS PT-145 fails Low / Place Excess Letdown in Service (M) ALL Control Bank B rod K2 ejected 6
(M) ALL C S/G ruptures 7
8 RO A & B SI Pumps fails to auto Start on SI 9 RO SI-870 A & B fail to auto open on SI
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 1
SUMMARY
DESCRIPTION The crew will assume the watch with the plant in mode 2 with reactor startup In progress.
Shutdown banks A&B are fully withdrawn. The crew will continue taking the reactor critical IAW GP-003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL. The crew will withdraw control rods to obtain their first doubling. The crew will perform a 1/M plot and proceed to withdraw rods to obtain their second doubling.
On cue from the Chief Examiner, Control Bank B rod K2 will not move. The crew will take actions IAW AOP-001, Malfunction of the Reactor Control System. The operator will perform immediate operator actions. The OAC will diagnose a stuck rod and the crew will transition to Section B, Immovable/Misaligned Rods. The crew will initiate boration of the RCS using OP-301 and borate to All Rods Out 1% Shutdown Boron Concentration to place the plant in mode 3 in preparation for tripping the rods. The CRS will review ITS 3.1.4, ROD GROUP ALIGNMENT LIMITS. For rod alignment the CRS will determine bank demand positions less than 200 steps if rod K2 is within 7.5 inches of the average of the individual rod positions in the bank. Entry to this will depend on how long the crew takes to identify rod K2 is stuck. Also, The CRS will need to determine if the rod is OPERABLE (trippable). The actions of the AOP will satisfy ITS 3.1.4 Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, the South Service Water Header will experience a break at the intake structure on the SW piping downstream of SW-6, SW Pump B Discharge Valve. The crew will take actions IAW AOP-022, Loss of Service Water, and will isolate the ruptured header and disable the service water pumps on the isolated header. This will result in the affected Emergency Diesel Generator being declared inoperable due to all the service water pumps supporting that EDG being disabled. The CRS will declare entry into ITS LCO 3.7.7, Condition A, due to one SW train inoperable. This LCO requires that the inoperable SW train be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The CRS will also declare entry into ITS LCO 3.8.1, Condition B, which requires the following: (1) Perform SR 3.8.1.1 for offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (OP-604, Section 8.4.9, Emergency Diesel Generator Inoperability), (2) Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s), (3) Determine Operable DG is not inoperable due to common cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and perform SR 3.8.1.2 for Operable DG within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and, (4) restore DG to Operable status within 7 days OR be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, a partial loss of vacuum will be initiated. The crew will enter AOP-012, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip. The crew will perform immediate operator actions and transition to Section A. Vacuum will stabilize with two vacuum pumps running. Leak location has been identified and determined to be a minor repair.
Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, Pressure Transmitter PT-145 for Letdown Line Pressure will fail LOW, causing PCV-145 to close and isolate letdown flow. AOP-025, RTGB Instrument Failure, Section A will be implemented to isolate the letdown line, reduce charging flow and Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 place Excess Letdown in service. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, Control Bank B rod K2 will be ejected. The crew will enter AOP-016, Excessive Primary Plant Leakage. PZR level and pressure will continue to lower and the crew will trip the reactor and enter EOP-E-0, REACTOR TRIP OR SAFETY INJECTION and perform immediate operator actions. During the Safety Injection both SI Pumps will fail to automatically start and will have to be manually started either by guidance in OMM-022 for automatic actions that should have taken place or IAW EOP-E-0 Attachment 1. SI-870 A & B, BIT OUTLET VALVES will fail to automatically open and will have to be manually opened either by guidance in OMM-022 for automatic actions that should have taken place or IAW EOP-E-0 . EOP-E-0 step 16 will have the crew transition to EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT. EOP-E-1 step 17 will have the crew transition to EPP-8, POST LOCA COOLDOWN AND DEPRESSURIZATION. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, C S/G will rupture. This will be initiated when the crew enters EPP-8. The S/Gs should have feed water isolated to them at this time by closing V2-16A/B/C to maintain the S/G level control band. Foldout B is in effect IAW EPP-8 and the crew will transition to EOP-E-3, STEAM GENERATOR TUBE RUPTURE. The crew will isolate C S/G and cooldown and depressurize the RCS. The crew will stabilize from the cooldown but will not meet minimum subcooling and will be required to transition to EPP-17, SGTR WITH A LOSS OF REACTOR COOLANT. There are several transition points to EPP-17 based on subcooling, PZR level, and RCS pressure stable or rising. The crew may meet SI termination criteria based on their progress through the procedure, however, if SI is terminated they will not be able to maintain PZR level and will transition to EPP-17.
The Chief Examiner may terminate the scenario at any time after entry to EPP-17.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Sat / Critical Task Critical Task Criteria Unsat Secure All RCPs due to STOP ALL RCPs within 6 minutes of reaching the EOP-E-0 Foldout Criteria following RCP trip criteria:
Both of the following satisfied:
o SI Pumps - At least one running and capable of delivering flow AND o RCS Subcooling based on Core Exit TCs
- Less than 30° F (50° F)
Start at least one Safety Start at least one SI Pump prior to completion of Injection Pump to provide EOP-E-0 Attachment 1.
adequate core cooling.
Open either SI-870A or SI- Open SI-870A OR SI-870B Prior to Completing 870B to establish SI flow. EOP-E-0 Attachment 1.
Manually isolate Excess Manually isolate Excess LetdownPrior to Letdown Completing EOP-E-0 Attachment 1.
Isolate Ruptured C S/G Isolate C S/G Prior to Transition from EOP-E-3 at Step 5 of EOP-E-3.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 1 SIMULATOR SETUP IC/SETUP:
IC-601, SCN 006_ILC_14_NRC_1.
Status board is provided to crew is IC-8.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip or triggered events following the reactor trip:
Event 8: A & B SI Pumps fail to Auto Start on SI.
Event 9: SI-870 A & B fail to open on SI.
EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
Event 1: GP-003 Reactor Startup Event 2: Control Bank B rod K2 stuck Event 3: South Service Water leak at intake Event 4: Loss of Condenser vacuum Event 5: PT-145 fails Low / Place Excess Letdown in Service Event 6: Control Bank B rod K2 ejected Event 7: C S/G ruptures EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
GP-003 AOP-001 AOP-022 AOP-012 AOP-025, Section A AOP-016 EOP-E-0 EOP-E-1 EPP-8 EOP-E-3 EPP-17 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 1 Page 6 of 64 Event
Description:
GP-003 Normal Plant Startup From Hot Shutdown to Critical Time Position Applicants Actions or Behavior EXAMINERS NOTE: The crew will assume the watch with the Shutdown Banks A & B at 225 steps performing a plant startup in accordance with GP-003, Normal Plant Startup From Hot Shutdown to Critical. The crew should be given adequate time to brief the evolution prior to entering the simulator. The crew will start at Section 8.2, Step 8.2.23.
GP-003 CRS Performs brief on Minimum of four inverse count rate ratio (1/M) data points are required on the approach to criticality..
NOTE: A minimum of four inverse count rate ratio (1/M) data points are required on the approach to criticality. The data points should be taken each time the count rate approaches a value that is approximately twice the previous stable data point. This is referred to as "doubling". The first data point, Reference Count Rate (CR0), is obtained after Shutdown Bank A and Shutdown Bank "B" have been fully withdrawn.
The Audio Count Rate VOLUME AND AUDIO MULTIPLIER should be adjusted as the count rate rises to maintain a distinguishable audible count rate.
WHEN Shutdown Bank A and Shutdown Bank B are fully withdrawn AND the count rate is stable, THEN RECORD the GP-003 BOP time and Reference Count Rate (CR0) on Attachment 10.2, Inverse Count Rate Ratio (1/M) Data and Plot Form.
Performs brief on step 8.2.24 through 8.2.27b being continuous action GP-003 CRS steps NOTE: The following FOUR steps, Steps 8.2.24 through 8.2.27.b, are continuous actions steps which remain in effect until the actions have been performed or plant conditions render the steps not applicable.
CAUTION A minimum of one decade overlap between Source Range and Intermediate Range Channels is required prior to blocking the Source Range Reactor Trip signals.
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 1 Page 7 of 64 Event
Description:
GP-003 Normal Plant Startup From Hot Shutdown to Critical Time Position Applicants Actions or Behavior WHEN Reactor power is indicating in the Intermediate Range, THEN PERFORM the following:
- a. SELECT the highest reading Intermediate Range GP-003 RO Channel on the Comparator and Rate Drawer.
- b. VERIFY one decade overlap between the Source Range and Intermediate Range indication.
NOTE: One Intermediate Range greater than 10-10 amps is required to satisfy the P-6 Permissive.
WHEN one Intermediate Range detector indicates greater than GP-003 RO 10-10 amps,THEN VERIFY the POWER ABOVE P-6 permissive light ILLUMINATES. (ITS SR 3.3.1.8)
WHEN both Intermediate Range channels indicate greater than 10-10 amps, THEN BLOCK the Source Range Reactor Trip by GP-003 RO depressing the SOURCE RANGE LOGIC TRIP DEFEAT TRAIN "A" AND the SOURCE RANGE LOGIC TRIP DEFEAT TRAIN "B" pushbuttons on the RTGB VERIFY the following:
GP-003
- a. All Source Range indication goes to zero.
- b. The SR DET LOSS OF DC Annunciator (APP-005-A1)
ILLUMINATED.
NOTE: The approach to criticality should take approximately four doublings of the Indicated Reference Count Rate (CR0) under ideal conditions. The target count rate is intended to serve as a known stable reactivity state suitable for data taking and criticality predictions.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 1 Page 8 of 64 Event
Description:
GP-003 Normal Plant Startup From Hot Shutdown to Critical Time Position Applicants Actions or Behavior It is NOT necessary to attempt to stabilize at exactly double the previous count rate, therefore the use of a "target count rate" (as applied to each doubling of the count rate) is intended to allow the Operator to stabilize the core as close as is practical to the "doubling" count rate without excessive rod motion.
APP-005-F2, ROD BOTTOM ROD DROP, will extinguish when Control Bank A is above 20 steps.
INPO SOER 07-1, Recommendation #2, makes the following statement: Reactivity changes during shift turnover or shift crew briefings are to be avoided. At RNP, this recommendation is implemented as follows:
- 1. Shift Turnover shall NOT be done unless the Reactor is stable AND EITHER (A) Shutdown Bank rod withdrawal has NOT commenced, OR (B) All Shutdown Bank rod withdrawal is complete with NO Control Bank rod withdrawal commenced or in progress.
WITHDRAW control rods to achieve the target count rate determined in Attachment 10.2, Inverse Count Rate Ratio (1/M)
GP-003 RO Data and Plot Form, as follows:
- a. SELECT "M" on the Rod Bank Selector switch.
NOTE: During Rod Withdrawal, the Operator at the Controls (OAC) is manipulating the Rod Withdrawal and monitoring applicable parameters. Simultaneously, a licensed RO other than the assigned OAC will assist in performing the Attachment 10.3, Control Rod Withdrawal Checklist.
WITHDRAW control rods to achieve the target count rate determined in Attachment 10.2, Inverse Count Rate Ratio (1/M)
Data and Plot Form, as follows:
GP-003 RO
- b. WITHDRAW Control Rods until count rate is approximately equal to the target count rate while performing the checks and verifications of Attachment Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 1 Page 9 of 64 Event
Description:
GP-003 Normal Plant Startup From Hot Shutdown to Critical Time Position Applicants Actions or Behavior 10.3, Control Rod Withdrawal Checklist.
WITHDRAW control rods to achieve the target count rate determined in Attachment 10.2, Inverse Count Rate Ratio (1/M)
Data and Plot Form, as follows:
GP-003 RO
- c. VERIFY the count rate stabilizes AND does NOT rise in an unexpected manner.
- d. IF criticality is indicated, THEN GO TO Section 8.3.
NOTE: Each successive reactivity addition will require less rod motion and a longer time for the count rate to stabilize. The NR-45 trace should be closely monitored and cross-checked against available instrumentation to determine when count rate has stabilized following each successive rod pull to double counts.
WHEN rod motion has been stopped AND count rate is stable, GP-003 RO THEN RECORD the required information on Attachment 10.2, Inverse Count Rate Ratio (1/M) Data and Plot Form.
WITHDRAW control rods to achieve the new target count rate GP-003 RO determined in Attachment 10.2, Inverse Count Rate Ratio (1/M)
Data and Plot Form, as follows:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 1
Op Test No.: ILC-14 NRC Scenario # 1 Event # 2 Page of 64 0
Event
Description:
Control Bank B rod K2 stuck Time Position Applicants Actions or Behavior BOOTH OPERATOR: Prior to withdrawing rods for second double insert Event 2, Control Bank B rod K2 stuck.
EVENT INDICATIONS:
Control Bank B rod K2 does not move during when demanded.
AOP-001, Malfunction of Reactor Control System Immediate Action Step:
AOP-001 RO Check Unexpected Rod Motion in Progress - (NO)
Go to step 7 AOP-001 CRS Enters AOP-001, Malfunction of Reactor Control System AOP-001 CRS Verifies immediate actions complete.
Determine If Multiple Rods Have Dropped As Follows:
- a. Analyze Indications For Multiple Rod Drop AOP-001 Prompt Drop PRESENT RO More than 1 Rod Bottom Light - ILLUMINATED More Than 1 IRPI INDICATES ON BOTTOM
- b. Check Multiple Dropped Rods PRESENT - (NO)
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 2 Page 11 of 64 Event
Description:
Control Bank B rod K2 stuck Time Position Applicants Actions or Behavior AOP-001 BOP Make PA Announcement for Procedure Entry.
AOP-001 RO Check Tavg - Trending to Tref (YES)
Determine The Status Of Rods As Follows:
- a. Analyze the below indications for a dropped rod:
APP 005 A3, PR DROP ROD ILLUMINATED APP 005 F2, ROD BOTTOM ROD DROP ILLUMINATED Rod Bottom Light for affected rod ILLUMINATED Indication of Prompt Drop AOP-001 RO PRESENT Quadrant Power Tilt indications PRESENT APP 005 F3, PR UPPER CH HI FLUX DEV/AUTO DEFEAT ILLUMINATED APP 005 F4, PR LOWER CH HI FLUX DEV/AUTO DEFEAT ILLUMINATED APP 005 C3, PR CHANNEL DEV ILLUMINATED Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 2 Page 12 of 64 Event
Description:
Control Bank B rod K2 stuck Time Position Applicants Actions or Behavior Power Range Drawer Indications
- b. Check Dropped Rod PRESENT - (NO)
NOTE IF there is any doubt as to IRPI failure OR actual rod misalignment, THEN assume rod misalignment is present.
Malfunctioning IRPI(s) may be identified by erratic or drifting IRPI indication when the associated Rod Bank is not being moved, or sudden large changes in IRPI indication with no corresponding change in nuclear power or motion of other rods in the associated bank.
ERFIS Rod Position Indication may be used for IRPI indication below.
Determine The Status Of IRPI As Follows:
- a. Analyze the below indications for an IRPI problem:
IRPI Indication Indicator drift with NO flux effects Erratic indicator movement with NO flux AOP-001 RO effects Indicator off scale High OR Low with NO flux Effects Dropped Rod Indication with no flux changes Rod Bottom Light for affected rod ILLUMINATED AND Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 2 Page 13 of 64 Event
Description:
Control Bank B rod K2 stuck Time Position Applicants Actions or Behavior APP 005 A3, PR DROP ROD EXTINGUISHED Simultaneous loss of ALL IRPI Indication (Power Supply Failure) PRESENT
- b. Check IRPI malfunction PRESENT - (NO)
Determine The Status Of Rods As Follows:
- a. Analyze below indications of A Immovable OR Misaligned Rod Rod CAN NOT BE MOVED APP 005 E2, ROD CONT SYSTEM URGENT FAILURE AOP-001 RO ILLUMINATED Rod Indication OUT OF ALIGNMENT WITH REMAINDER OF BANK
- b. Check Misaligned/Immovable Rod PRESENT (YES)
AOP-001 CRS Go To Section B, Immovable/Misaligned Rods AOP-001 Check current plant status - Mode 1 (NO)
RO RNO - Observe the NOTE prior to Step 49 and Go To Step 49.
NOTE Trip of the stuck rod(s) (RNO step below) is NOT considered a Reactor Trip for entry into the EOP Network since the plant is already in Mode 3.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 2 Page 14 of 64 Event
Description:
Control Bank B rod K2 stuck Time Position Applicants Actions or Behavior AOP-001 RO Check current plant status - Mode 2 (Yes)
AOP-001 RO Check Tavg WITHIN 1.5 TO +1.5°F OF TREF (YES)
Stop Any Evolutions That Change Reactor Power Except As Called For By This procedure AOP-001 CRS Steam demand changes Boron concentration changes Check APP 005 E2, ROD CONT SYSTEM URGENT FAILURE ILLUMINATED (NO)
RO AOP-001 RNO - Go to step 59 NOTE AOP 007, TURBINE TRIP BELOW P 8, is not applicable at this time.
AOP-001 RO Check malfunctioning Rod Status - Stuck (YES)
NOTE Trip of the rod(s) (step below) is NOT considered a Reactor Trip for entry into the EOP Network since the plant is already in Mode 3.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 2 Page 15 of 64 Event
Description:
Control Bank B rod K2 stuck Time Position Applicants Actions or Behavior Perform The Following.
- a. Initiate boration of the RCS using OP 301, Chemical and Volume Control System (CVCS), RCS Boration Quick Checklist.
AOP-001 c. Check Turbine ROLLING (NO)
- c. RNO Go To Step 60.e.
- e. WHEN the required 1% shutdown concentration has been achieved, THEN trip the Control Rods AND terminate boration AOP-001 CRS Implement The EALs Review Technical Specifications To Assure All Applicable LCO requirements Have Been Met:
ITS 3.1.4 Rod Alignment ITS 3.1.5 Shutdown Bank RIL AOP-001 ITS 3.1.6 Control Bank RIL CRS and overlap ITS 3.1.7 IRPI ITS 3.2.1 Fq(Z)
ITS 3.2.2 Fh ITS 3.2.3 AFD ITS 3.2.4 QPTR Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 3 Page 16 of 64 Event
Description:
Service Water Leak at the Intake Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #3 (South Service Water leak at intake) on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-008-E7, S SW HDR STRAINER PIT HI LVL APP-008-E8, N SW HDR STRAINER PIT HI LEVEL APP-008-F7, SOUTH SW HDR LO PRESS APP-008-F8, NORTH SW HDR LO PRESS SW Header Pressures on PI-1616 and PI-1684 reading 28 psig NOTE Step 1 is an immediate action step.
AOP-022, Loss of Service Water Immediate Action Step:
AOP-022 Check The Following Alarms - EXTINGUISHED: (NO)
BOP APP-OOB-E7, S SW HDR STRAINER PIT HI LEVEL APP-008-E&, N SW HDR STRAINER PIT HI LEVEL Perform the following:
- a. Close the following SW X-CONN Valves:
AOP-022 BOP V6-12B V6-12C Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 3 Page 17 of 64 Event
Description:
Service Water Leak at the Intake Time Position Applicants Actions or Behavior
- b. Go To Section F.
AOP-022 CRS Enters AOP-022, Loss of Service Water AOP-022 CRS Verifies immediate actions complete AOP-022 BOP Verify PA Announcement For Procedure Entry Performed Verify SW X-CONN Valves - CLOSED:
AOP-022 BOP V6-12B V6-12C NOTE The source of flooding in the Intake Structure may be Service Water, Fire Water, or Intake Structure leakage.
Evaluate Control Room Indications AND Perform Local Inspections To AOP-022 BOP Determine Source Of Flooding Prior To Continuing BOOTH OPERATOR: If / When contacted by the Control Room to investigate leakage at the intake, wait 5 minutes and then report that there is water in both SW pits and there appears to be a pipe break at the discharge tee of B SWP.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 3 Page 18 of 64 Event
Description:
Service Water Leak at the Intake Time Position Applicants Actions or Behavior AOP-022 BOP Check Source of Flooding - SERVICE WATER (YES)
AOP-022 BOP Check Service Water Leak Location - ON SOUTH HEADER (YES)
Verify the following:
- c. SW Pump A - Stopped
Check South SW Header Pressure on PI-1684 - Lowering (YES) (0 AOP-022 BOP psig)
Check North SW Header Pressure on PI-1616 - Stable OR Rising (YES) (46 psig)
NOTE With Service Water Pumps "A" AND "B" isolated, EDG "A" is inoperable. ITS 3.8.1 requires SR 3.8.1.1 to be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
AOP-022 BOP Close V6-12A, SW SOUTH HDR ISO NOTE SW-851 and SW-857, SOUTH SW HEADER CHEMICAL INJECTION, are located above the South SW Strainer Pit on the South side.
Verify The Following Valves At The Intake Structure - CLOSED:
AOP-022 BOP SW-851 SW-857 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 3 Page 19 of 64 Event
Description:
Service Water Leak at the Intake Time Position Applicants Actions or Behavior BOOTH OPERATOR: When dispatched, wait 2 minutes and report that SW-851 and SW-857 are closed. Valves are not modeled on Simulator.
CAUTION Confined Space entry requirements must be observed to access the South SW Strainer Pit.
NOTE SW-187, South HDR SUPPLY TO SCRN WASH & CW PMP GLAND SEAL, is located in the South SW Strainer Pit.
AOP-022 BOP Check Flooding Status - Stopped BOOTH OPERATOR: When requested to check flooding status, wait 30 seconds and then report that the flooding has stopped.
Check North SW Header Pressure On PI-1616 - GREATER THAN 40 AOP-022 BOP PSIG (YES, ~ 46 psig)
Remove Control Power Fuses From The Following Breakers At 480V Bus E-1:
AOP-022 SERVICE WATER PUMP A BOP (CMPT-20B)
SERVICE WATER PUMP B (CMPT-19C)
BOOTH OPERATOR: When dispatched to remove control power fuses, wait 5 minutes and then rack out breakers for SWP A and B IAW SCN file and report back to CR.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 3 Page 20 of 64 Event
Description:
Service Water Leak at the Intake Time Position Applicants Actions or Behavior Determine If A SW Booster Pump Should Be Started:
- a. Check SW Booster Pumps - ALL STOPPED (NO)
AOP-022 BOP RNO: Verify only ONE SW Booster Pump is running. (YES)
Go to Step 22.
AOP-022 BOP Check Circulating Water Pump Status - ANY RUNNING (YES)
Determine If Adequate Seal Water Is Available To Circulating Water Pumps As Follows: (YES to ALL)
AOP-022 BOP APP-008-E4, CW PMP A SEAL WTR LOST - EXTINGUISHED APP-008-E5, CW PMP B SEAL WTR LOST - EXTINGUISHED APP-008-E6, CW PMP C SEAL WTR LOST - EXTINGUISHED CAUTION CCW temperature is limited to 105°F when any of the following equipment is in service: Post Accident Sampling Heat Exchanger, and Excess Letdown Heat Exchanger Determine Maximum Allowable CCW Temperature As Follows:
AOP-022 RO RNO: Maintain CCW Heat Exchanger outlet temperature indicated on TI-607 less than or equal to 105°F.
Go To Step 29 Perform The Following AOP-022 BOP a. Inspect the area of the leak
- b. Report findings to the Control Room
- c. Identify and isolate the source of the SW leak BOOTH OPERATOR: If requested, report that the SW piping has a crack at B SWP Discharge Pipe Tee.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 3 Page 21 of 64 Event
Description:
Service Water Leak at the Intake Time Position Applicants Actions or Behavior Contact Maintenance To Install Temporary Pumps To Dewater AOP-022 CRS Service Water Pits Contact Engineering to perform the following:
CRS AOP-022 Evaluate operability of equipment affected by flooding Provide corrective actions for flooding Refer To Technical Specification 3.7.7, Service Water System (SWS)
ITS 3.7.7, One SWS train inoperable. Restore SWS train to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND be in MODE 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
ITS 3.8.1, One DG inoperable. Perform SR 3.8.1.1 for the offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. (OP-604 Section 8.4.9)
AND AOP-022 CRS Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of discovery of Condition B concurrent with inoperability of redundant required feature(s). Since A MDAFW pump is OOS, then the Crew has four hours to declare B MDAFW pump OOS.
AND Perform SR 3.8.1.2 for OPERABLE DG within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
AND Restore DG to OPERABLE status within 7 days AND 8 days from discovery of failure to meet LCO.
AOP-022 Implement the EALs CRS AOP-022 Return to procedure and step in effect.
CRS Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 4 Page 22 of 64 Event
Description:
Loss of Condenser Vacuum Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #4 (Loss of Condenser Vacuum) on cue from the Chief Examiner.
EVENT INDICATIONS:
PI-1310 Cond A Narrow Range inches HG ABS rising PI-1312 Cond A WR inches HG ABS rising PI-1311 Cond B Narrow Range inches HG ABS rising PI-1313 Cond B WR inches HG ABS rising APP-008-A5 Condenser Lo Vacuum illuminated NOTE Steps 1 and 2 are Immediate Action steps.
AOP-012, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip Immediate Action Step AOP-012 BOP Check Circulating Water Pump -
ANY TRIPPED Go To Section A, Partial Loss of Condenser vacuum.
AOP-012 Enters AOP-012, Partial Loss of Condenser Vacuum or Circulating CRS Water Pump Trip AOP-012 CRS Verifies immediate actions complete.
AOP-012 BOP Check Condenser Status - VACUUM PREVIOUSLY ESTABLISHED (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 4 Page 23 of 64 Event
Description:
Loss of Condenser Vacuum Time Position Applicants Actions or Behavior AOP-012 BOP Verify All Available Vacuum Pumps - RUNNING AOP-012 BOP Verify The Following VACUUM BREAKER Valves - CLOSED MS-70A MS-70B AOP-012 BOP Make PA announcement for procedure entry AOP-012 RO Check plant conditions - in Modes 1 OR 2 (YES)
NOTE The use of narrow range pressure ERFIS points CDP2500A and CDP2501A and wide range ERFIS points CDP2502A and CDP2503A may aid in observing condenser vacuum conditions. Narrow range pressure ERFIS points have a maximum range of 6" HG backpressure.
AOP-012 BOP Continuous Action Step Check Condenser Back Pressure On PI-1312 AND PI-1313 -
APPROACHES RESTRICTED REGION OF ATTACHMENT 3, CONDENSER BACKPRESSURE LIMIT CURVE (NO - Turbine is not latched)
Go To Step 9.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 4 Page 24 of 64 Event
Description:
Loss of Condenser Vacuum Time Position Applicants Actions or Behavior AOP-012 BOP Continuous Action Step Check Condenser Vacuum DEGRADING using the following: (NO - stabilized in hogging/jetting mode with vacuum pumps)
-1310
-1311
-CDP2500A
-CDP2510A Go to step 11 Check Condenser Nitrogen Addition - in service (NO)
AOP-012 BOP Go to step 13 AOP-012 BOP Verify All Available Circulating Water Pumps - RUNNING Check APP-008-F3, EXH HOOD HI TEMP Alarm - ILLUMINATED (NO)
AOP-012 BOP Go to step 17 Check TURBINE GENERATOR SUPERVISORY RECORDER -
ANY VIBRATION GREATER THAN 14.0 MILS (N) - Turbine is not AOP-012 BOP latched)
Go to step 20 AOP-012 BOP Check Status of Auxiliary Boilers - IN SERVICE (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 4 Page 25 of 64 Event
Description:
Loss of Condenser Vacuum Time Position Applicants Actions or Behavior Check Auxiliary Boiler Status As Follows:
AOP-012 BOP a. Check Auxiliary Boilers - TRIPPED/SHUTDOWN (NO)
Go to step 22 Determine If Low Vacuum Due To Blowdown:
- b. Check blowdown - LOST (NO)
Go to step 23 Check Cause Of Vacuum Loss - IDENTIFIED (NO)
Dispatch AO to locally perform Attachment 1 while continuing with this procedure.
AOP-012 CRS Monitor Condenser Backpressure during the performance of Attachment and Coordinate with personnel performing the attachment.
Notify Chemistry personnel to monitor secondary chemistry to ensure AOP-012 BOP compliance with CP-005, Secondary Chemistry Corrective Action Program.
Dispatch AO to measure condenser in-leakage using OP-504, Condenser Air Removal, Measuring Condenser In-leakage.
AOP-012 BOP Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 4 Page 26 of 64 Event
Description:
Loss of Condenser Vacuum Time Position Applicants Actions or Behavior BOOTH OPERATOR: Notify the Control Room the Miscellaneous Drains Collecting Tank Level is low out of band and that you will be performing adjustment IAW Attachment 1.step 23 RNO.
AOP-012 CRS Implement the EALs AOP-012 CRS Check cause of vacuum loss found (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 5 Page 27 of 64 Event
Description:
PT-145, Letdown Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert event #5 (PT-145, Letdown Pressure Transmitter, fails low) on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-001-E6 - LP LTDN RELIEF HI TEMP APP-003-C3 - PRT HI PRESS References APP-001 and informs SRO of need to refer to AOP-025, AOP-025 RO RTGB Instrument Failure.
AOP-025 CRS Enters AOP-025, RTGB Instrument Failure AOP-025 RO Place LCV-460A&B In The CLOSE Position Verify ONLY ONE Charging Pump is Running. (Lowers the speed on AOP-025 RO the Charging Pump in Manual and stops the pump.)
AOP-025 BOP Place Excess Letdown in Service Using Attachment 2.
Attachment 2 Verify Closed the following valves:
LCV-460A&B Att. 2 BOP CVC-200A/B/C Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 5 Page 28 of 64 Event
Description:
PT-145, Letdown Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior CVC-204A/B Att. 2 BOP Verify Open CC-739 Att. 2 BOP Position CVC-389 to the RCDT Position Att. 2 BOP Open CVC-387, Excess Ltdn Stop Slowly Open HCV-137, Excess Ltdn Flow, not to exceed 195°F as Att. 2 BOP indicated on TI-139, Excess Ltdn HX Outlet Temp.
Att. 2 BOP Notify the CRS that Excess Letdown is in service.
Update the ERFS Calorimetric program to reflect Excess Letdown is Att. 2 BOP in service.
IF required to control Pzr Level, THEN contact Chemistry to perform Att. 2 BOP the alignment for purging the PZR Liquid sample line with full flow to the VCT iaw CP-003.
BOOTH OPERATOR: IF requested to align sample line for purge, wait 5 minutes and implement IAW SCN File.
IF PZR Liquid sample line is used to control PZR Level, THEN Att. 2 BOP/CRS remove the calorimetric calculation from service and enter TRM 3.25 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 5 Page 29 of 64 Event
Description:
PT-145, Letdown Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior IF desired to align Excess Letdown to the VCT, THEN perform the following:
- a. Position CVC-389 to the VCT.
Att. 2 BOP
- b. Notify Rad. Control that Excess Letdown is in service through the Seal Water Filters and Heat Exchanger, which will result in RAISED radiation levels in those areas.
Attachment 2 complete AOP-025 BOP Step 4: Make PA Announcement for Procedure Entry.
Check RCP Seal Injection Flow - Between 8 and 13 gpm. (NO)
Locally throttle CVC-297A/B/C to obtain 8 to 13 gpm.
If required to maintain minimum flow, then throttle HIC-121 while maintaining Charging Pump Discharge pressure less than 2500 psig.
AOP-025 RO If the normal Seal Injection Range can NOT be maintained, then an expanded range of between 6 to 20 gpm may be used.
Check ITS LCO 3.4.17 for applicability. (ITS 3.4.17 SR 3.4.17.1 requires that seal injection flow remain 6 gpm to each RCP)
BOOTH OPERATOR: IF / WHEN requested, throttle CVC-297A/B/C as necessary using the P&ID function to obtain requested seal injection flows.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 5 Page 30 of 64 Event
Description:
PT-145, Letdown Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior AOP-025 CRS Contact Plant Operations Staff to Expedite Repair of PT-145.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 31 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #6 Control Bank B Rod K2 Ejected) on cue from the Chief Examiner.
EVENT INDICATIONS:
RR-1 Warning for R-11 APP-036-D8, Process Monitor HI Rad (R-11)
RCS Pressure Lowering PZR Level Lowering EXAMINERS NOTE: The crew may determine to trip the reactor prior to implementing AOP-016 Continuous Action Step Determine If Reactor Trip Needed As Follows:
- b. Check the following:
PZR level - less than 14% and lowering in an uncontrolled manner (NO)
AOP-016 RO / CRS OR RCS subcooling - less than 35° F (NO)
- b. RNO - IF PZR level coan NOT be maintained greater than 14% OR subcooling can NOT be maintained greater than 35° F THEN trip the reactor and go to EOP-E-0, Reactor Trip or Safety Injection.
Go to step 2 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 32 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior AOP-016 BOP Make a PA announcement for procedure entry CAUTION Charging Pump Discharge Pressure must be maintained less than 2500 psig to prevent lifting the Charging Pump Discharge Relief.
AOP-016 RO Control charging flow to maintain desired RCS level Continuous Action Step Check VCT level - less than 12.5 inches (NO)
RO RNO - IF VCT level lowers to less than 12.5 inches, THEN observe AOP-016 the Note prior to step 5 and perform step 5 Go to step 6 Check charging pump status - less than two running (YES)
AOP-016 RO RNO - Go to step 11 Place running charging pump speed controller(s) in MAN AND adjust AOP-016 RO output to maximum AOP-016 RO Check RCS level - lowering in an uncontrolled manner (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 33 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior AOP-016 RO Check any letdown - in service (YES)
Verify all letdown flowpaths isolated as follows:
LCV-460A&B, LTDN line stop valves - closed AOP-016 RO HIC-142, Purification flow controller - adjusted to 0%
HIC-137, Excess LTDN flow controller - adjusted to 0%
CVC-387, Excess LTDN stop - closed AOP-016 RO Check RCS level - lowering in an uncontrolled manner (YES)
AOP-016 RO Check RCS pressure - greater than 1000 psig (YES)
AOP-016 RO/CRS Trip the reactor and go to EOP-E-0, Reactor Trip or Safety Injection Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 34 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior EOP-E-0, Reactor Trip or Safety Injection Immediate Action Steps
- 1. Check Reactor Trip: (YES)
Reactor trip and bypass breakers - OPEN EOP-E-0 RO Rod position indicators - AT ZERO Rod Bottom lights - ILLUMINATED Neutron flux - LOWERING Immediate Action Steps Check Turbine Trip:
- a. Both turbine stop valves - Closed (YES)
- b. All MSR purge and shutoff valves - Closed (YES)
Immediate Action Steps Check Power to AC Emergency Busses:
- a. E1 or E2 - At least one energized (YES)
- b. E1 and E2 - Both energized (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 35 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Immediate Action Steps Check SI Status:
a) Check if SI is actuated:
SI annunciators - ANY ILLUMINATED (YES)
SI equipment - AUTO STARTED (YES)
EOP-E-0 RO b) Check BOTH trains of SI - ACTUATED SI pumps - BOTH RUNNING (NO)
RHR pumps - BOTH RUNNING (YES)
RNO: Manually actuate BOTH trains of SI by depressing BOTH SI pushbuttons (SI Pumps do not start - candidate may start pumps and open SI-870A & B once immediate actions have been verified)
EOP-E-0 CRS Verifies all immediate actions for EOP-E-0.
EXAMINERS NOTE: Crew may take early actions at this time to address items that did not function or operate as designed.
Manually start A and B SI Pumps Open SI-870 A and B NOTE FOLDOUT for EOP-E-0 is in effect Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 36 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior FOLDOUT for EOP-E-0 is in effect RCP Trip Criteria IF either condition listed below occurs, THEN trip all RCPs: (YES)
Containment Isolation Phase B - ACTUATED (NO)
OR Critical CRS Task BOTH of the following satisfied:
o SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW (YES, B SI Pump is running)
AND o RCS subcooling based on core exit TCs - LESS THAN 30°F [50°F] (NO)
CRITICAL TASK - STOP ALL RCPs within 6 minutes of Reaching the RCP Trip Criteria of less than 50°F subcooling.
Perform Attachment 1, Auto Action Verification, While continuing EOP-E-0 CRS with this procedure. (Should be assigned to BOP.) (Att. 1 steps are presented next followed by the remainder of EOP-E-0.)
Beginning of EOP-E-0 Attachment 1 (Remainder of EOP-E-0 Follows this Section)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 37 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Check ECCS Pumps Running:
Att. 1 Critical BOP SI pumps - BOTH RUNNING (NO, Starts A OR B SI Pump)
Task RHR pumps - BOTH RUNNING (YES)
CRITICAL TASK - START A OR B SI PUMP PRIOR TO ANNOUNCING COMPLETION OF EOP-E-0 ATTACHMENT 1 Att. 1 Check ECCS Valves - PROPER EMERGENCY ALIGNMENT (NO.
Critical BOP open SI-870A OR B)
Task Att. 1 BOP Check CCW Pumps - AT LEAST ONE RUNNING (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 38 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check Containment Isolation Phase A
- a. Phase A - Actuated (YES)
- b. Phase A valves - Closed (YES)
Att. 1 Critical BOP c. Excess letdown - Isolated (NO)
Task CVC-387 - Closed (NO)
HIC-137 - at 0% DEMAND (NO)
- c. Manually close valve(s) as necessary CRITICAL TASK - MANUALLY ISOLATE EXCESS LETDOWN PRIOR TO ANNOUNCING COMPLETION OF EOP-E-0 ATTACHMENT 1 Check Feedwater Isolation:
a) Main feed pumps - BOTH TRIPPED (YES) b) Main feedwater - ISOLATED Att. 1 BOP FRVs - Closed (YES)
Feedwater reg bypass valves - Closed (YES)
Feedwater header section valves - Closed (YES)
Check if Main Steamlines Should Be Isolated:
Att. 1 BOP a) Main steamline isolation - REQUIRED (NO)
Go to step 7 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 39 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check Proper Service Water System Operation:
- a. SW pumps - All running (YES)
- b. SW booster pumps - Both running (YES)
Extinguished (NO)
- c. Perform the following:
Att. 1 BOP 1. RNO - Isolate SW to the Turbine Building:
o Close V6-16C, SW turbine building isolation OR o Close V6-16A and V6-16B, SW turbine building supply
- 2. WHEN this attachment is complete, THEN perform Supplement M, Component alignment for a loss of SW to the Turbine Building, as time permits.
Att. 1 BOP Check Both EDGs - Running (YES)
Check ECCS Flow:
- a. RCS pressure - less than 1650 psig (NO)
Att. 1 BOP b. SI pumps- Flow Indicated (NO)
- c. RCS pressure - less than 275 psig. (NO)
- d. RHR - Flow Indicated (NO)
Att. 1 BOP Check CV Recirculation Fans - All Running (YES, all available)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 40 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check IVSW - Actuated (YES)
Att. 1 BOP PCV-1922A - Open (YES)
PCV-1922B - Open (YES)
Check CV ventilation isolation (YES)
Att. 1 BOP
- a. CV ventilation isolation valves - CLOSED (YES)
Check control room ventilation - aligned for pressurization mode (YES)
HVA-1A or HVA-1B - Running (YES)
HVE Stopped (YES)
Att. 1 HVE-19A or HVE-19B - Running (NO, starts HVE-19A or HVE-BOP 19B)
Control Room HVAC outside air damper A or B - Open (YES)
CR-D1A-SA - Closed (YES)
CR-D1B-SB - Closed (YES)
Att. 1 BOP Check DS Bus - Energized (YES)
Check Battery Chargers - Energized (YES)
Att. 1 BOP APP-036-D1 - Extinguished (YES)
APP-036-D2 - Extinguished (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 41 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Att. 1 BOP Stop R-11/12 Sample Pump Att. 1 BOP Locally Reset and Load IACs as necessary (N/A)
Perform Crew Update to include the following:
Attachment Completion Manual Actions Taken (Started A and B SI Pumps, opened SI-870A and B, closed HIC-137 and CVC-387)
Att. 1 BOP Failed Equipment status SW status SW to Turbine Building isolated Performing Supplement M End of EOP-E-0 Attachment 1 AOP-005 - Radiation Monitoring System (Concurrent AOP)
Attachment Number 12 AOP-005 BOP Check R-11/R-12 Selector Switch - Selected to CV (YES)
AOP-005 BOP Check RCS Temperature - Greater than 200°F (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 42 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check Channel R-11/R-12 Low Flow Alarm - Illuminated (YES, pump AOP-005 BOP off IAW Attachment 1 of EOP-E-0.)
AOP-005 BOP Verify R-11/12 Vacuum Pump - stopped (YES)
AOP-005 BOP Step 5: Check EOP Network Procedures - Implemented (YES)
AOP-005 BOP Return to procedure and step in effect End of AOP-005 Supplement M, Component Alignment for Loss of SW to Turbine Building Shutdown secondary as follows:
- a. Check S/Gs - ANY RUPTURED a. Go To Step 1.c
- d. Break vacuum to the Condenser as follows:
BOP 1) Depress AND hold the THINK Pushbutton.
- 2) Open VACUUM BREAKER VALVES:
MS-70A MS-70B
- 3) WHEN the valves are open, THEN release the THINK pushbutton.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 43 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior
- e. Verify the following equipment is stopped:
FW PUMP A FW PUMP B COND PUMP A COND PUMP B HEATER DRAIN PUMP A HEATER DRAIN PUMP B GOV FLUID PUMP A (Pull To Lock)
GOV FLUID PUMP B (Pull To Lock)
VACUUM PUMP A VACUUM PUMP B CRS Return to procedure and step in effect End Supplement M Continuation of EOP-E-0 Check AFW Pumps - Running (MDAFW Pumps are running)
- b. S/G levels - 2 less than 16 % (NO)
Check AFW Valves - Proper Emergency Alignment (YES)
AFW header discharge valves - Full Open (YES)
EOP-E-0 RO AFW header section valves - Full Open (YES)
Steam driven AFW pump discharge valves - Full open if pump is running. (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 44 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check Total AFW Flow:
Reset SI EOP-E-0 RO Control feed flow to maintain NON-faulted S/Gs narrow range level - Between 23% and 50%.
Check total AFW flow- Greater than 300 gpm (YES)
Check CV Spray NOT Required:
RO a. CV pressure - Has remained less than 10 psig. (YES)
- b. CV Spray - NOT actuated (YES)
Check RCP Seal Cooling:
CCW flow to RCP thermal barriers - Normal (YES) o APP-001-C1 / D1 - Extinguished (YES)
OR EOP-E-0 RO Seal injection flow - Normal (YES) o Seal injection flow - Greater than 6 gpm per RCP OR o Thermal barrier Ps - Greater than 5 inches water.
BOOTH OPERATOR: As requested, adjust CVC-297A,B,C as necessary to control RCP seal injection flow using the P&ID function.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 45 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check RCS Temperature With NO RCPs running, RCS cold leg temperatures - Stable at or trending to 547°F (NO)
RNO: IF temperature is less then 547°F AND lowering then perform the following: (YES)
- b. IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:
o Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% in at least one S/G.
- c. IF cooldown continues, THEN close MSIVs and MSIV bypass valves. (MSIVs automatically closed due to Large Break LOCA)
Check PZR PORVs and Spray Valves:
- a. PORVs - Closed (YES)
- b. Normal PZR spray valves - Closed (YES)
- c. Aux spray valve - Closed (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 46 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check If RCPs should be stopped:
- a. RCPs - Any Running (YES)
RNO: Go to Step 14 Step 14: Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs EOP-E-0 BOP o None lowering in an uncontrolled manner (YES) o None Completely depressurized (YES)
Check if S/G Tubes are Intact:
Secondary radiation monitors - Have Remained Normal (YES)
R-15 EOP-E-0 BOP R-19s R-31s S/G levels - None Rising in an Uncontrolled Manner. (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 47 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check if RCS is Intact: (NO)
CV radiation - Normal (NO) o R-2 o R-32A/B EOP-E-0 RO CV pressure - Normal (NO)
CV sump level - Normal (NO)
RNO: Reset SPDS and initiate monitoring of CSFSTs. Go to EOP-E-1, Loss of Reactor or Secondary Coolant, Step 1.
Beginning of EOP-E-1, Loss of Reactor or Secondary Coolant NOTE FOLDOUT for EOP-E-1 is in effect. (This foldout criteria will apply later in the scenario)
EOP-E-3 TRANSITION CRITERIA IF any S/G level rises in an uncontrolled manner OR has abnormal EOP-E-1 CRS radiation, THEN perform the following:
- b. Reset SPDS and Go To EOP-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 48 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check If RCPs should be stopped:
- a. RCPs - Any Running (YES)
Go to step 2 Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs EOP-E-1 BOP o None lowering in an uncontrolled manner (YES) o None Completely depressurized (YES)
Continuous Action Step Check Intact S/G Levels:
- a. Narrow range levels - Greater than 23% (YES)
- b. Control feed flow to maintain narrow range levels - between 23% AND 50%
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
EOP-E-1 RO Reset SI Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 49 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior EOP-E-1 RO Reset Containment Isolation Phase A Check Secondary Radiation:
- b. Perform the following:
- 1) Request periodic activity samples of all S/Gs
- 2) Secondary sample results - Normal (When results available)
Check PZR PORVs and Block Valves:
- a. Power to block valves - Available (YES)
- b. PORVs - Closed (YES)
- c. Block valves - At least one open. (YES)
Establish Instrument Air to CV:
- a. Check APP-002-F7 - Extinguished (YES)
- b. Reset IA PCV-1716
- c. Check IA PCV-1716 - OPEN (YES)
Check Power Supply to Charging Pumps - Offsite power available EOP-E-1 RO (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 50 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check if Charging Flow has been established:
- a. Charging pumps - At least one running. (YES)
- b. Establish desired charging flow:
o Start additional pump(s) as necessary EOP-E-1 RO o Adjust charging pump speed controllers as necessary to establish desired charging flow.
o Adjust HIC-121 as necessary to establish desired charging flow:
o Maintain seal injection flow - Between 6 gpm and 20 gpm per RCP unless seal injection isolated.
BOOTH OPERATOR: If the crew starts additional charging pumps then insert event 7 for C S/G rupture Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 51 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check if SI flow should be terminated:
- b. Secondary heat sink:
Total feed flow to intact S/G(s) - greater than 300 OR EOP-E-1 RO Narrow range level in at least one intact S/G greater than 8%
- c. RCS pressure:
Pressure - greater than 1650 psig (NO)
Pressure - stable or rising (NO)
Go to step 12 Continuous Action Step Step 12: Check if Containment Spray should be stopped:
- a. Spray pump - Any running (NO)
RNO - Observe caution prior to step 13 and go to step 13 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 52 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior CAUTION If RCS pressure lowers in an uncontrolled manner to less than 275 psig [350 psig], the RHR pumps must be manually restarted to supply water to the RCS.
Continuous Action Step Step 13: Check if RHR Pumps Should be Stopped:
- a. Check RCS pressure:
EOP-E-1 RO o Pressure - Greater than 275 psig (YES) o Pressure - stable or rising (NO)
Go to step 14 Check RCS And S/G Pressure:
RO Check pressure in all S/Gs - STABLE OR RISING (YES)
Check RCS pressure - STABLE OR LOWERING (YES)
EXAMINERS NOTE: The crew may transition to EOP-E-3. This will be based on the crews progression through the procedure. If they remain in EOP-E-1 they will transition to EPP-8 which will then transition them to EOP-E-3.
EOP-E-1 Continued Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 53 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Step 15: Check if Diesel Generators should be Stopped:
- b. EDG starting air annunciators - Extinguished (YES) o APP-010-B2 / B3
- c. Stop unloaded EDGs Initiate Evaluation of Plant Status:
EOP-E-1 RO a. Check Cold leg recirculation capability:
Train A and Train B (Recirc capability available)
Check Auxiliary building radiation - NORMAL (YES)
Contact Chemistry to obtain samples Consult Plant Operations Staff for assessing additional EOP-E-1 sampling requirements for fuel damage as necessary BOP Evaluate plant equipment to support long term recovery as necessary Start/align plant equipment to assist in recovery as necessary Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 6, 8, 9 Page 54 of 64 Event
Description:
Control Bank B Rod K2 Ejected, On the SI A&C SI Pumps Fail to Auto Start and SI-870 A&B Fail to Auto Open Time Position Applicants Actions or Behavior Check If RCS Cooldown And Depressurization Is Required:
RCS pressure - greater than 275 psig (YES)
EOP-E-1 RO Reset SPDS and go to EPP-8, Post LOCA Cooldown and Depressurization, step 1 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 55 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert event 7 for C S/G rupture if not done previously Beginning of EPP-8, Post LOCA Cooldown and Depressurization Open Foldout B EOP-E-3 TRANSITION CRITERIA IF EITHER condition below occurs, THEN Go To EOP-E-3, Steam EPP-8 CREW Generator Tube Rupture, Step 1:
Any S/G level rises in an uncontrolled manner. (YES)
Any S/G has abnormal radiation levels.
Beginning of EOP-E-3, Steam Generator Tube Rupture NOTE FOLDOUT for EOP-E-3 is in effect.
EOP-E-3 Chemistry should be available for sampling during this CRS procedure.
Step 1 RCP trip criteria applies until an operator controlled RCS cooldown is initiated.
CONTINUOUS ACTION STEP Check If RCPs Should Be Stopped:
- a. RCPs - ANY RUNNING (YES)
EOP-E-3 b. SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF RO DELIVERING FLOW (YES)
[50°F] (NO)
RNO: Go to Step 2 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 56 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior Identify Ruptured S/G(s): (B S/G is ruptured)
Unexpected rise in any S/G narrow range level (YES)
OR High radiation from any SG steamline (R-31s)
EOP-E-3 OR BOP High radiation from any SG blowdown line (R-19s)
OR High radiation from any S/G sample:
o Contact Chemistry to sample all S/Gs for activity as necessary CAUTION If the steam driven AFW pump is the only available source of EOP-E-3 feed flow, steam supply to the steam driven AFW pump should CRS be maintained from at least one S/G.
At least one S/G must be maintained available for RCS cooldown.
Isolate Flow From Ruptured S/G(s):
- a. Adjust ruptured S/G(s) steam line PORV controller setpoint to 1060 psig
- b. Check ruptured S/G steam line PORV - (RV1-2) CLOSED (YES)
- c. Close steam driven AFW pump steam shutoff valve for ruptured S/G: (V1-8C)
- d. Locally close the following valve for ruptured S/G(s) while continuing with this procedure:
EOP-E-3 MS-38, SG "C" BYPASS DRN & WARM-UP LINE TO BOP AFW PUMP (pipe jungle above/right of V1-8C)
- e. Check S/G blow down and blow down sample valves from ruptured S/G(s) - Closed SG2 Blowdown FCV-1932 A & B FCV-1935 A & B SHUT
- f. Check MSIV above and below seat drain valves for ruptured S/G - CLOSED (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 57 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior BOOTH OPERATOR: When requested, wait 3 minutes and then close MS-38 IAW SCN file.
CAUTION If any ruptured S/G is faulted, feed flow to that S/G should EOP-E-3 remain isolated during subsequent recovery actions unless CRS needed for RCS cooldown.
If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Continuous Action Step Check Ruptured S/G Level:
- a. Narrow range level - Greater than 8%. (YES)
- c. Stop feed flow to ruptured S/G:
Close steam driven AFW pump discharge valve: V2-14C Close AFW header discharge valve: V2-16C
- d. Perform Att. 4, Deenergizing AFW Valves For Ruptured S/Gs BOOTH OPERATOR: When requested, wait 3 minutes and then open the breakers for AFW valves as specified in Att. 4 IAW the SCN file.
CRITICAL TASK - ISOLATE S/G C PRIOR TO S/G OVERFILL CAUTION EOP-E-3 Major steam flow paths from the ruptured S/G(s) should be isolated CRS before initiating RCS cooldown. This includes MSIVs and MSIV bypass valves, steam line PORV, and AFW pump steam shutoff valve.
EOP-E-3 Check Ruptured S/G Pressure - Greater than 500 psig. (YES)
BOP Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 58 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior CAUTION EOP-E-3 IF RCPs are not running, the following steps may cause a false CSF-CRS 4, Integrity Status Tree, indication for the ruptured loop. Disregard the ruptured loop T-cold indication until after performing Step 28.
NOTE EOP-E-3 Main steamline isolation may occur if the high steam flow setpoint is CRS exceeded. The cooldown should be continued using the steam line PORV(s) if MSIV closure occurs.
Initiate RCS Cooldown:
- a. Determine required core exit temperature:
Ruptured SG Pressure (PSIG) Required Core Exit Temperature
(°F) 1150 and above 508 [488]
1100 to 1149 503 [483]
1050 to 1099 497 [477]
1000 to 1049 491 [471]
950 to 999 485 [465]
900 to 949 478 [458]
850 to 899 472 [452]
800 to 849 465 [445]
750 to 799 458 [438]
700 to 749 450 [430]
EOP-E-3 BOP 650 to 699 442 [422]
600 to 649 433 [413]
550 to 599 424 [404]
500 to 549 415 [395]
- b. Dump steam to condenser from intact S/G(s) at maximum rate:
maximum rate from intact
- 1) Check condenser - AVAILABLE FROM INTACT S/G(s)
(NO)
RNO: Manually dump steam at maximum rate from intact S/G using steam line PORVs.
- c. Core exit TCs - Less Than Required Temperature
- d. Stop RCS cooldown
- e. Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 59 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior BOOTH OPERATOR: When cooldown has commenced modify the SBLOCA to 800 gpm.
Continuous Action Step Check Intact S/G Levels EOP-E-3 BOP a. Narrow range levels - Greater than 8% (YES)
- b. Control feed flow to maintain narrow range levels - BETWEEN 21% and 50%.
CAUTION CRS If any PZR PORV opens because of high PZR pressure, Step 8.b should be repeated after pressure lowers to less than 2335 psig.
Continuous Action Step Check PZR PORVs And Block Valves:
EOP-E-3 RO a. Power to block valves - AVAILABLE (YES)
- b. PORVs - CLOSED (YES)
- c. Block valves - AT LEAST ON OPEN (YES)
CAUTION EOP-E-3 CRS If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
EOP-E-3 RO Reset SI EOP-E-3 RO Reset Containment Isolation Phase A Establish Instrument Air To CV:
EOP-E-3 a. Check APP-002-F7 - EXTINGUISHED (YES)
- b. Reset IA PCV-1716, instrument air isolation to CV
- c. Check IA PCV-1716 - OPEN (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 60 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior CAUTION EOP-E-3 If RCS pressure lowers in an uncontrolled manner to less than 275 CRS psig [350 psig], the RHR pumps must be manually restarted to supply water to the RCS.
Check If RHR Pumps Should Be Stopped:
EOP-E-3 a. RCS pressure - GREATER THAN 275 PSIG [350 PSIG] (YES)
- b. Stop RHR pumps
- c. Monitor RCS pressure Establish Charging Flow:
- a. Charging pumps- AT LEAST ONE RUNNING (YES)
- b. Align charging pump suction to RWST
- 1) Open LCV-115B
- 2) Close LCV-115C
- 3) Place RCS makeup system switch to STOP
- c. Establish charging flow:
EOP-E-3 Start charging pump(s) as necessary to establish at least RO one running Adjust charging pump speed controllers as necessary to establish maximum charging flow for running pump(s)
Adjust HIC-121, charging flow control valve, as necessary to establish desired charging flow:
o Maintain seal injection flow - BETWEEN 6 GPM AND 20 GPM PER RCP UNLESS SEAL INJECTION ISOLATED Check If RCS Cooldown Should Be Stopped:
- b. Stop RCS cooldown
- c. Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 61 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior Check Ruptured S/G Pressure - Stable or Rising (NO, depending on scenario timeline.)
(If answered NO) RNO: IF pressure continues to lower to within 250 EOP-E-3 BOP psi above the pressure of the intact S/G(s) used for cooldown, THEN reset SPDS and Go To EPP-17, SGTR WITH LOSS OF REACTOR COOLANT:
SUBCOOLED RECOVERY, Step 1 Check RCS Subcooling Based on Core Exit TCs - Greater than 55°F (YES) (This may be less than 55°F at this time. It will depend on EOP-E-3 scenario timeline)
RO If less than 55°F Reset SPDS and go to EPP-17, SGTR WITH LOSS OF REACTOR COOLANT:
SUBCOOLED RECOVERY, Step 1 Depressurize RCS to Minimize Break Flow and Refill the PZR:
- a. Normal PZR spray - AVAILABLE (YES)
- b. Spray PZR with maximum available spray until any of the following conditions are satisfied:
Both of the following:
OR PZR level - GREATER THAN 73%
OR RCS subcooling based on core exit TCs - LESS THAN 35°F
- c. Close spray valves when any condition above is satisfied
- d. Observe CAUTION prior to Step 20 and Go to Step 20 CAUTION EOP-E-3 CRS SI must be terminated when termination criteria are satisfied to prevent overfilling the ruptured S/G(s).
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 62 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior Check if SI Flow Should be Terminated:
- b. Secondary heat sink:
Total feed flow to S/Gs - AT LEAST 300 GPM AVAILABLE (YES)
OR EOP-E-3 RO Narrow range level in at least one intact S/G - GREATER THAN 8% (YES)
- c. RCS pressure - STABLE OR RISING (YES) (This may not be stable or rising at this time. It will depend on scenario timeline)
If not then Reset SPDS and go to EPP-17, SGTR WITH LOSS OF REACTOR COOLANT:
SUBCOOLED RECOVERY, Step 1
- d. PZR level - GREATER THAN 14% (YES)
EOP-E-3 RO Stop Both SI Pumps EOP-E-3 Foldout SI REINITIATION CRITERIA IF either condition listed below occurs, THEN manually start SI and RHR pumps as necessary to restore RCS subcooling and PZR level:
RCS subcooling based on core exit TCs - LESS THAN 35 F [55 F]
OR PZR level - CANNOT BE MAINTAINED GREATER THAN 14% [37%] IF SI reinitiation occurs after SI termination at Step 21, THEN reset SPDS and Go To EPP-17, SGTR WITH LOSS OF REACTOR COOLANT: SUBCOOLED RECOVERY, Step 1. (Unable to maintain greater than 14% PZR level)
Reser SPDS and go to EPP-17, , SGTR WITH LOSS OF REACTOR CRS COOLANT: SUBCOOLED RECOVERY Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 1 Event # 7 Page 63 of 64 Event
Description:
C S/G Rupture Time Position Applicants Actions or Behavior The Lead Examiner may terminate the scenario any time after entry into EPP-17 Appendix D NUREG-1021, Rev. 9, Supp. 1
ILC-14 NRC SCENARIO 1 TURNOVER SHEET
- 1. INITIAL CONDITIONS a) Time in Core Life: BOL b) Reactor Power: 0% Mode 2 c) Turbine Load: 0 MWe d) Boron Concentration: 1564 ppm e) Rod Height: 225 SDB B f) RCS Pressure: 2235 psig g) PZR Level: 22.8 %
h) Xenon: Equilibrium
- 2. TECHNICAL SPECIFICATION LCO ACTIONS STATEMENTS IN EFFECT T.S. # Description
- 3. CLEARANCES IN EFFECT a) None
- 4. CAUTION CAPS IN EFFECT a) None
- 5. PROTECTED EQUIPMENT a) None
- 6. DEGRADED EQUIPMENT a) None
- 7. SWITCHYARD ACCESS a) Unrestricted
- 8. PLANNED EVOLUTIONS a) Continue Reactor Startup IAW GP-003
- 9. TURNOVER INFORMATION a) High heat load has resulted in all planned maintenance being deferred to a later date.
b) SGBD is split between the Flashtank and Condenser
- 10. REACTIVITY INFORMATION a) Review the OST-947 BOL charts for BA and PW additions
- 11. RISK a) GREEN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 2 Op Test No.: ILC-14 Examiners: Operators: CRS -
RO -
BOP -
Initial Conditions: 75% RTP EOL, 17000 MWD/MTU, 124 ppm Boron SWBP A OOS for a seal replacement Turnover: Reduce power to 65% to support valve testing Critical Task: Isolate S/G B IAW EOP-E-2 Start Service Water Pump C OR D Start CV Spray Pump B Event Malf. No. Event Type* Event No. Description (R) RO, CRS Reduce turbine load IAW OP-105 to 65%
1 (N) BOP (I) RO, CRS IRPI failure 2
(TS) CRS (I) BOP, CRS Feedwater Flow Transmitter FT-477 will fail high 3
(TS) CRS 4 (I) RO, CRS PZR Pressure Transmitter PT-445 fails low 5 (TS) CRS A oil leak on EDG A will render the EDG inoperable Feedwater Regulating Valve FCV-478 fails open causing 6 (C) BOP, CRS the reactor to be tripped A fault inside Containment on S/G B will occur during 7 (M) ALL the reactor trip 8 (M) ALL A loss of the SUT after the trip 9 BOP EDG A trips due to a lack of oil from its leak Service Water Pumps C and D fail to start on the SI 10 BOP Sequencer(CT to start Pump C OR D since only EDG B is available) 11 RO CV Spray pump B does not automatically start 12
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 2
SUMMARY
DESCRIPTION The crew will assume the watch with the plant at 75% steady state power. Operations Management has directed the plant power be reduced to 65% power to support valve testing.
The crew will reduce reactor power and turbine load IAW OP-105 to 65% to support valve testing.
On cue from the Chief Examiner, Control Bank C Rod D6 will experience and IRPI failure. The crew will enter AOP-001 and diagnose this as an IRPI due to no prompt drop. Rod D6 is in close proximity to NI-44 and no effects of a dropped rod are seen. The crew will transition to Section D. The CRS will need to apply ITS 3.1.7, Rod Position Indication. Once the Chief Examiner is satisfied, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, Feedwater flow channel FT-477 fails High, affecting the automatic operation of Feedwater Regulating Valve FCV-478 for S/G A. The operator will have to take manual control of the FRV and restore the S/G to program level. The crew will perform the immediate actions for FT-477 failure IAW AOP-025, RTGB Instrument Failure, Section E.
The crew will perform the necessary transfer to the controlling channel and restore the FRV to automatic operation. The failed feedwater flow transmitter will be removed from service IAW OWP-026, FWF-2. The CRS will review ITS Table 3.3.1-1 Item 14 and determine it does not apply. Once the FRV returned to automatic and the Chief Examiner is satisfied, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, PZR Pressure Transmitter PT-445 will fail Low, causing APP-003-D8 to alarm. Immediate actions of AOP-025, RTGB Instrument Failure, Section C will be performed by the crew. The CRS will verify that there are no applicable Tech Specs, PCV-456 is still operable because it can be manually opened and closed. Once the Chief Examiner is satisfied, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, The Inside Auxiliary Operator(IAO) will report a large oil leak on EDG A. This will render the EDG inoperable and will cause it to trip later in the scenario.
The CRS will also declare entry into ITS LCO 3.8.1, Condition B, which requires the following:
(1) Perform SR 3.8.1.1 for offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (OP-604, Section 8.4.9, Emergency Diesel Generator Inoperability), (2) Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s), (3) Determine Operable DG is not inoperable due to common cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and perform SR 3.8.1.2 for Operable DG within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and, (4) restore DG to Operable status within 7 days OR be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Once the Chief Examiner is satisfied with the stability of the plant and ITS compliance he may cue the next event On cue from the Chief Examiner, Feedwater Regulating Valve FCV-478 fails Open, this will lead to a reactor trip. The BOP will take manual control of FCV-478 to control S/G A water level, however, it will not work which will lead to the reactor being manually tripped. Upon the reactor trip, S/G B will become faulted in containment and the SUT will be lost.
Because of the Faulted S/G, a Safety Injection(SI) must be initiated. During the SI sequence, Service Water Pumps C and D will not start. The starting of these pumps is a Critical Task Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 because only EDG B will be running. EDG A will have tripped due to the oil leak from before.
The crew will enter into EOP-E-0.
The Faulted S/G will cause CV pressure to rise above 10 psig which will cause an automatic CV Spray signal if the crew does not initiate one manually. Upon this CV Spray signal, CV Spray Pump A will not start. Critical Task to start A CV Spray pump to avoid a potential loss of containment fission product barrier.
The crew will transition from EOP-E-0 to EOP-E-2 for a faulted S/G. S/G B will be isolated and the crew will secure SI IAW EOP-E-2 or they may transition to EOP-E-1 before meeting SI termination criteria. EOP-E-1 will send the crew to EPP-7, SI Termination.
The chief examiner may terminate the scenario any time after SI is terminated.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Sat /
Critical Task Critical Task Criteria Unsat Start either C or D SW Start either C OR D SW Pump prior to pump to provide cooling to announcing completion of EOP-E-0 Attachment B EDG. 1.
Manually start a CV Spray Manually start a CV Spray Pump IAW EOP-E-0, Pump prior to leaving EOP-E-0 Step 9.
Isolate S/G B Stop feeding the faulted S/G IAW EOP-E-0, prior to exiting EOP-E-0 Foldout, Step 2 AND within 10 min. of S/G fault condition.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 2 SIMULATOR SETUP IC/SETUP:
IC-602, SCN 006_ILC_14_SIM_NRC_2 Status board is provided to crew is from IC-22.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip or triggered events following the reactor trip:
Event 7: A fault inside Containment on S/G B will occur during the reactor trip Event 8: A loss of the SUT after the trip Event 9: EDG A will trip 3 minutes after it starts from its oil leak.
Event 10: Service Water Pumps C and D fail to start on the SI Sequencer(CT to start
Event 11: CV Spray pump B does not automatically start EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
Event 1: Power Reduction to 65%
Event 2: IRPI Failure in Control Bank C Rod D6 Event 3: FW Flow Transmitter, FT-477 fails high Event 4: Pressurizer Pressure Transmitter, PT-445 Fails low Event 5: Large Oil Leak on EDG "A Event 6: Feedwater Regulating Valve, FCV-478 Fails Open EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
OP-105, Section 8.4.1 marked up through step 8.4.1.2.c AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM AOP-025, RTGB INSTRUMENT FAILURE OWP-026, FWF-2 EOP-E-0, REACTOR TRIP OR SAFETY INJECTION EOP-E-2, FAULTED S/G ISOLATION EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT EPP-7, SI TERMINATION Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 1 Page 6 of 38 Event
Description:
Power Reduction to 65% IAW OP-105 Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, go to run on the simulator NOTE: Unloading of the unit should NOT exceed 5%/minute. Unloading of the unit can be stopped at any time by pressing the HOLD pushbutton. The HOLD lamp should illuminate, the GO lamp should extinguish, and unloading of the unit should be stopped. The SETTER should NOT be set to 0.0. If the Turbine is allowed to go to this setting without operator attention, all the governor valves could close and cause a turbine trip after a one minute time delay. During the load changes, GS-36, MANUAL GLAND SEAL DUMP may require throttling to maintain Gland Seal Pressure in the normal operating band of 3 to 6 psig.
CAUTION Although it is preferred to observe the effects of the initial boric acid addition prior to lowering Turbine load, it may be necessary to commence a rapid power reduction before the observed effects of any boric acid additions. In these situations, with rod Control in AUTOMATIC, Rod Control will drive the Controlling Bank of Rods to maintain Tavg on Tref. This will cause the Reactor Flux profile to go in the negative direction.
IF Reactor Power is near 100% at the time the rapid power change is commenced, this may cause Reactor Flux to go outside the Operating Band while less than 90% Power (or less than0.9 APL). IF this condition is established, APP-005-D6, Flux Warning / Status, and APP-005-E4, Flux Alarm, will both alarm.
IF a valid APP-005-E4 alarm is received while less than 90% Reactor Power (less than 0.9 APL), power reduction to less than 50% power will be required per ITS LCO 3.2.3. (NCR 306775)
IF EH Turbine Control is in OPER AUTO, THEN REDUCE turbine load as follows:
(1) PLACE the EH Turbine Control in the desired position:
- IMP IN (preferred)
- IMP OUT (if required for plant conditions)
(2) SET the desired load in the SETTER.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 1 Page 7 of 38 Event
Description:
Power Reduction to 65% IAW OP-105 Time Position Applicants Actions or Behavior (3) SELECT the desired Load Rate.
OP-015 BOP (4) DEPRESS the GO pushbutton.
NOTE: The MSR Timer Valves are operated by manually rotating the "French Curve" cam on the MSR TIMER VALVE CONTROLLER.
VERIFY the toggle switch inside the MSR TIMER VALVE CONTROLLER is in the OFF position.
OP-105 BOP GRADUALLY CLOSE the MSR Timer Valves to limit the LPTurbine inlet steam temperature drop to 100F/hr or less.
VERIFY proper programming of the following:
- Tavg tracks within 5F of Tref.
- PZR level tracks within 5% of reference level.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 2 Page 8 of 38 Event
Description:
IRPI Failure on Rod D6 Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 2, IRPI Failure, on cue from the Chief Examiner EVENT INDICATIONS: Rod D6 will show on IRPI at a different height from all other control rods.
Immediate Action Step:
AOP-001 RO Check Unexpected Rod Motion- IN PROGRESS (NO)
Determine If Multiple Rods Have Dropped As Follows:
- a. Analyze Indications For Multiple Rod Drop Prompt Drop - PRESENT More than 1 Rod Bottom Light -
AOP-001 RO ILLUMINATED More Than 1 IRPI - INDICATES ON BOTTOM
- b. Check Multiple Dropped Rods - PRESENT (NO)
Go to step 10 AOP-001 BOP Make PA Announcement For Procedure Entry Check Tavg - TRENDING TO Tref May or may NOT be depending on where they are at with the AOP-001 RO power reduction. IF they answer NO, they will restore Tavg to within + 1.5°F IAW Attachment 1 of AOP-001 Determine The Status Of Rods As Follows:
- a. Analyze the below indications for a dropped rod:
APP-005-A3, PR DROP ROD - ILLUMINATED APP-005-F2, ROD BOTTOM ROD DROP - ILLUMINATED AOP-001 RO Rod Bottom Light for affected rod -ILLUMINATED Indication of Prompt Drop - PRESENT Quadrant Power Tilt indications - PRESENT APP-005-F3, PR UPPER CH HI FLUX DEV/AUTO Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 2 Page 9 of 38 Event
Description:
IRPI Failure on Rod D6 Time Position Applicants Actions or Behavior DEFEAT - ILLUMINATED APP-005-F4, PR LOWER CH HI FLUX DEV/AUTO DEFEAT - ILLUMINATED APP-005-C3, PR CHANNEL DEV -ILLUMINATED Power Range Drawer -Indications
- b. Check Dropped Rod - PRESENT (NO)
Go to step 14 NOTE:
IF there is any doubt as to IRPI failure OR actual rod misalignment, THEN assume rod misalignment is present.
Malfunctioning IRPI(s) may be identified by erratic or drifting IRPI indication when the associated Rod Bank is not being AOP-001 CRS moved, or sudden large changes in IRPI indication with no corresponding change in nuclear power or motion of other rods in the associated bank.
ERFIS Rod Position Indication may be used for IRPI indication below.
Determine The Status Of IRPI As Follows:
- a. Analyze the below indications for an IRPI problem:
IRPI Indication Indicator drift with NO flux effects Erratic indicator movement with NO flux effects Indicator off-scale High OR Low with NO flux AOP-001 RO effects Dropped Rod Indication with no flux changes Rod Bottom Light for affected rod ILLUMINATED AND APP 005 A3, PR DROP ROD EXTINGUISHED Simultaneous loss of ALL IRPI Indication (Power Supply Failure) PRESENT Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 2 Page 10 of 38 Event
Description:
IRPI Failure on Rod D6 Time Position Applicants Actions or Behavior
- b. Check IRPI malfunction PRESENT (YES)
AOP-001 RO Go To Section D, Individual Rod Position Indication Malfunction NOTE:
On a loss of PP-61, all IRPI indication is lost except that a green LED will be illuminated on each rod indicator.
On a loss of Instrument Bus 7 all IRPI indication is lost.
PP-61 is located on the second floor of the Auxiliary Building near the entrance to the VCT Room.
PP-61 is fed from MCC-15.
AOP-001 RO Check IRPI ENERGIZED (YES)
AOP-001 RO Check Current Plant Status-Modes 1 OR 2 (YES)
NOTE:
Voltage measurement may be used for determination of IRPI channel operability below. (0.015 volts per step)
ERFIS Rod Position Indication may be used for determination of IRPI channel operability below.
AOP-001 CRS Implement ITS LCO 3.1.7 Appendix D NUREG-1021, Rev. 9, Supp. 1
3Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 3 Page 11 of 38 Event
Description:
Feedwater Flow Transmitter FT-477 will Fail High Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #3(Feedwater Flow Transmitter FT-477 failing high) on cue from the Chief Examiner.
EVENT INDICATIONS:
FT-477 indicating high FRV-478 closing APP-006-A2 APP-006-A3 S/G A level lowering FI-477 rising AOP-025 Actions AOP-025 CRS Go to the Appropriate Section for the Failed Transmitter, Section E Immediate Action Step:
AOP-025 BOP Verify the Affected FRV In MAN FCV-478 (FRV A)
Immediate Action Step:
AOP-025 BOP Restore Affected S/G Level to between 39% and 52%
Continuous Action Step:
AOP-025 CREW Check Reactor Trip Setpoint - Being Approached RNO - IF a Reactor Trip Setpoint is approached, THEN trip the Appendix D NUREG-1021, Rev. 9, Supp. 1
3Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 3 Page 12 of 38 Event
Description:
Feedwater Flow Transmitter FT-477 will Fail High Time Position Applicants Actions or Behavior Reactor and Go to EOP-E-0.
Go to step 5 AOP-025 BOP Make PA Announcement For Procedure Entry Place the Affected S/G Feed Flow Selector Switch to the Alternate Channel Below:
S/G A Feed Flow FR-488 AOP-025 BOP Failed Channel Position FT-477 Ch 476 Continuous Action Step:
Restore Affected Controller To Automatic as Follows:
AOP-025 BOP Check S/G level within +/-1% of Programmed Level (When +/-1%) Place the Affected Controller in Auto Remove the Affected Transmitter From Service using OWP-026 AOP-025 BOP Channel OWP FT-477 FWF-2 OWP-026 FWF-2 OWP-26 BOP FR-478 Feedwater Flow Selector Switch selected to 476 OWP-26 BOP Delete Input FT-477 From CALO Processing (FWF0404A)
Appendix D NUREG-1021, Rev. 9, Supp. 1
3Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 3 Page 13 of 38 Event
Description:
Feedwater Flow Transmitter FT-477 will Fail High Time Position Applicants Actions or Behavior End OWP-026 Check the following ITS LCOs for applicability:
AOP-025 CRS 3.3.1 3.3.2 AOP-025 CRS Go To Procedure Main Body, Step 2 AOP-025 CRS Implement the EALs AOP-025 CRS Return to Procedure and Step in Effect Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 4 Page 14 of 38 Event
Description:
PT-145, Letdown Pressure Transmitter, fails low / Place Excess Letdown in Service (AOP-025)
Time Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Examiner, insert Event 4, Pressurizer Pressure Transmitter, PT-445 Fails Low.
EVENT INDICATIONS:
APP-003-D8 PZR CONTROL HI/LO PRESS AOP-025 Actions AOP-025 CRS Go to the Appropriate Section for the Failed Transmitter. Section C Immediate Action Step:
Determine If PZR PORVs should be closed:
AOP-025 RO a) Check PZR Pressure Less Than 2335 PSIG (YES) b) Verify Both PZR PORVs Closed Immediate Action Step:
AOP-025 RO Control the PZR Spray Valves AND PZR heaters to restore RCS Pressure to the desired control band.
AOP-025 BOP Make PA announcement for Procedure Entry Check PT-444 - Failed Transmitter (NO)
AOP-025 RO Go to step 6 Verify Selector Switch PM-444 - SELECTED TO THE OPERABLE AOP-025 RO CHANNEL REC 444 Check the following ITS LCOs for applicability:
AOP-025 CRS 3.3.4 3.4.1 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 4 Page 15 of 38 Event
Description:
PT-145, Letdown Pressure Transmitter, fails low / Place Excess Letdown in Service (AOP-025)
Time Position Applicants Actions or Behavior SRO Go to Procedure Main Body, Step 2.
SRO Implement the EALs SRO Return to Procedure and Step in Effect BOOTH OPERATOR: When directed by Chief Examiner, call the Control Room as the IAO and report that there is a large oil leak on EDG A. There is oil pooling up on the floor.
The CRS will also declare entry into ITS LCO 3.8.1, Condition B, which requires the following:
(1) Perform SR 3.8.1.1 for offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (OP-604, Section 8.4.9, Emergency Diesel Generator Inoperability (2) Declare required feature(s) supported by the inoperable DG CRS inoperable when its required redundant feature(s) is inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s)
(3) Determine Operable DG is not inoperable due to common cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and perform SR 3.8.1.2 for Operable DG within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and, (4) restore DG to Operable status within 7 days OR be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 16 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Examiner, insert Event 6, FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G A will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
EVENT INDICATIONS:
FCV-478 traveling open S/G A level rising S/G A Feed flow rising Immediate Action Step:
Check Feedwater Regulating Valves - OPERATING PROPERLY (MANUAL OR AUTO):
FCV-478, FRV "A" RNO:
- a. Verify FRV for affected S/G(s) in manual control.
AOP-010 BOP b. Attempt to stabilize S/G level using FRV and/or FRVBypass Valves by matching steam flow with feed flow.
- c. Stop any load change in progress.
- d. Restore affected S/G level to between 39% and 52%.
- e. IF unable to control S/G level, THEN trip the Reactor AND Go To EOP-E-0, REACTOR TRIP or SAFETY INJECTION. (The RO Should manually trip the reactor at this point)
EOP-E-0, Reactor Trip or Safety Injection Immediate Action Steps EOP-E-0 RO Check Reactor tripped (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 17 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Immediate Action Steps Check Turbine Trip:
- a. Both turbine stop valves - Closed (YES)
- b. All MSR purge and shutoff valves - Closed (YES)
Immediate Action Steps Check Power to AC Emergency Busses:
- a. E1 or E2 - At least one energized (YES)
- b. E1 and E2 - Both energized (YES)
Immediate Action Step:
- a. Check if SI is actuated:
SI annunciators - ANY ILLUMINATED OR SI equipment - AUTO STARTED (YES)
- b. Check BOTH trains of SI - ACTUATED (YES)
SI pumps - BOTH RUNNING RHR pumps - BOTH RUNNING NOTE FOLDOUT for EOP-E-0 is in effect.
EXAMINERS NOTE: Crew may take early actions at this time to address items that did not function or operate as designed.
Manually start Service Water Pumps C OR D Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 18 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Manually start CV Spray Pump B CRITICAL TASK Verifies all immediate actions for EOP-E-0. Announce Adverse EOP-E-0 CRS numbers are in effect due to CV Pressure Greater than 4 psig.
Perform Attachment 1, Auto Action Verification, While Continuing With EOP-E-0 BOP This Procedure Beginning of EOP-E-0 Attachment 1 (Remainder of EOP-E-0 Follows this Section)
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Check ECCS Pumps Running:
SI pumps - BOTH RUNNING (Could be running if checked prior to Att. 1 BOP loss of EDG A)
RHR pumps - BOTH RUNNING (Could be running if checked prior to loss of EDG A)
Att. 1 BOP Check ECCS Valves - PROPER EMERGENCY ALIGNMENT (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 19 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Att. 1 BOP Check CCW Pumps - AT LEAST ONE RUNNING (YES)
Check Containment Isolation Phase A
- a. Phase A - Actuated (YES)
- b. Phase A valves - Closed (YES)
Att. 1 BOP
- c. Excess letdown - Isolated (YES)
CVC-387 - Closed (YES)
HIC-137 - at 0% DEMAND (YES)
Check Feedwater Isolation:
a) Main feed pumps - BOTH TRIPPED (YES) b) Main feedwater - ISOLATED Att. 1 BOP FRVs - Closed (YES)
Feedwater reg bypass valves - Closed (YES)
Feedwater header section valves - Closed (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 20 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Check if Main Steamlines Should Be Isolated:
a) Main steamline isolation - REQUIRED (YES)
Containment pressure - Greater than 10 psig (YES)
OR Att. 1 BOP High steam flow with: (NO) o S/G pressure - less than 614 psig OR o Tavg - less than 543°F b) Check MSIVs and MSIV bypass valves - CLOSED (YES)
Check Proper Service Water System Operation:
- a. SW pumps - All running (NO, Candidate must start Service Water Pumps C OR D) Critical Task Att. 1 CRITICAL BOP
Extinguished ()
Check Both EDGs - Running (NO, EDG A has tripped due to its oil Att. 1 BOP leak)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 21 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior
- a. RCS pressure - less than 1700 psig (YES)
- b. SI pumps- Flow Indicated (YES)
- c. RCS pressure - less than 350 psig. (YES)
- d. RHR - Flow Indicated (YES)
Check CV Recirculation Fans - All Running (NO, A Train does not Att. 1 BOP have power)
Check IVSW - Actuated (YES)
Att. 1 BOP PCV-1922A - Open (YES)
PCV-1922B - Open (YES)
Check CV ventilation isolation (YES)
Att. 1 BOP
- a. CV ventilation isolation valves - CLOSED (YES)
Check control room ventilation - aligned for pressurization mode (YES)
HVA-1A or HVA-1B - Running (YES)
Att. 1 HVE Stopped (YES)
BOP HVE-19A or HVE-19B - Running (NO, starts HVE-19A or HVE-19B)
Control Room HVAC outside air damper A or B - Open (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 22 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior CR-D1A-SA - Closed (YES)
CR-D1B-SB - Closed (YES)
Att. 1 BOP Check DS Bus - Energized (YES)
Check Battery Chargers - Energized (YES)
Att. 1 BOP APP-036-D1 - Extinguished (YES)
APP-036-D2 - Extinguished (YES)
Att. 1 BOP Stop R-11/12 Sample Pump Att. 1 BOP Locally Reset and Load IACs as necessary (Yes, A)
BOOTH OPERATOR: When requested, wait approximately 2 minutes and restore IAC A IAW the SCN File IF you have already been dispatched to restore MCC-5 from the DS Bus. If you have not restored MCC-5 via the DS Bus, you cannot reset IAC A.
Perform Crew Update to include the following:
Attachment Completion Att. 1 BOP Manual Actions Taken (Started Service Water Pumps C AND D and started CV Spray Pump B)
Failed Equipment status (EDG A is tripped)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 23 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior SW status (B Train of Service water is operating, A train of Service water does not have power)
Critical Task to start SW Pump C OR D End of EOP-E-0 Attachment 1 EOP-E-0 IF MCC-5 is NOT energized, THEN perform the following:
ATT 3 a. Verify DS bus is energized.
(Directed b. Transfer power source to DS Bus using the posted instructions at BOP from the Kirk Key Interlocked Breakers.
EOP-E-0 c. Locally reset and load instrument air compressor A (MCC-5 CMPT Foldout) 7M).
BOOTH OPERATOR: When requested, wait 3 minutes and restore MCC-5 using the DS Bus IAW SCN file. When requested, wait approximately 2 minutes and restore IAC A IAW the SCN File IF not previously done with the Att 1.
Check AFW Pumps - Running
- a. Motor driven AFW pumps - Both Running (YES)
- b. S/G levels - Two S/Gs less than 16% (NO)
- c. Steam Driven AFW pump steam shutoff valves - ALL OPEN (YES.)
EOP-E-0 RO Check AFW Valves - Proper Emergency Alignment (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 24 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior AFW header discharge valves - Full Open (YES)
AFW header section valves - Full Open (YES)
Steam driven AFW pump discharge valves - Full open if pump is running. (YES)
Check Total AFW Flow:
Reset SI EOP-E-0 RO Control feed flow to maintain NON-faulted S/Gs narrow range level - Between 23% and 50%.
Check total AFW flow- Greater than 300 gpm (YES)
Check CV Spray NOT Required:
- a. CV pressure - Has remained less than 10 psig. (NO)
- a. Perform the following:
- 1) Check CV spray actuated.
IF CV spray is NOT actuated, THEN manually actuate BOTH trains of CV spray.
- 2) Verify the following:
EOP-E-0 a) Both CV spray pumps are running. (Start CV Critical RO Spray Pump B)
Task b) CV spray pump discharge valves are open:
SI-880A SI-880B SI-880C SI-880D c) CV spray additive tank discharge valves are open:
SI-845A SI-845B d) Spray additive tank flow is approximately 12 gpm:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 25 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Adjust SI-845C, SAT throttling valve, as necessary.
- 3) Verify Containment Isolation Phase B valves are closed.
- 4) Stop all RCPs.
- 5) Observe CAUTION prior to Step 10 and Go To Step 10.
Critical Task to start CV Spray Pump B Check RCP Seal Cooling:
CCW flow to RCP thermal barriers - Normal (YES)
APP-001-C1 / D1 - Extinguished (D1 may be Illuminated depending on what actions were taken EOP-E-0 RO earlier in the scenario)
IF all charging pumps are stopped, THEN perform the following:
- a. IF DS bus is energized, THEN start charging pump A at , minimum speed for seal injection.
BOOTH OPERATOR: As requested, adjust CVC-297A,B,C as necessary to control RCP seal injection flow using the P&ID function.
Check RCS Temperature With NO RCPs running, RCS cold leg temperatures - Stable at or trending to 547°F (NO, Depending on scenario timeline the RCPs could still be running.)
EOP-E-0 RO RNO: IF temperature is less than 547°F AND lowering then perform the following: (YES)
- a. Stop dumping steam.
- b. IF cooldown continues, THEN reduce total feed flow to minimum for decay heat Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 26 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [23%] in at least one S/G.
Check PZR PORVs and Spray Valves:
- a. PORVs - Closed (YES)
- b. Normal PZR spray valves - Closed (YES)
- c. Aux spray valve - Closed (YES)
Check If RCPs should be stopped:
- a. RCPs - Any Running (NO, stopped per FOLDOUT)
EOP-E-0 RO RNO: Go to Step 14 Step 14: Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs None lowering in an uncontrolled manner (NO)
EOP-E-0 BOP a. Reset SPDS and initiate monitoring of Critical Safety Functions Status Trees.
Go To EOP-E-2, Faulted Steam Generator Isolation, Step 1.
Beginning of EOP-E-2, Faulted Steam Generator Isolation Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 27 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior CAUTION At least one S/G must be maintained available for RCS cooldown.
Any faulted S/G or secondary break should remain isolated during Check MSIVs and MSIV Bypass Valves for Faulted S/G - Closed S/G B:
EOP-E-2 BOP V1-3B MS-353B Check if any S/G Secondary Pressure Boundary is Intact:
- a. Check pressures in all S/Gs - Any stable or rising. (YES)
Identify Faulted S/Gs:
- a. Check pressures in all S/Gs:
Any S/G pressure lowering in an uncontrolled EOP-E-2 BOP manner (YES, B S/G)
OR Any S/G completely depressurized CAUTION If the SDAFW pump is the only available source of feed flow, steam supply to the SDAFW pump should be maintained from at least one S/G.
If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 28 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Isolate Faulted S/Gs
- a. Check main feedwater to faulted S/Gs - Isolated S/G B valves - Closed o FCV-488 o FCV-489 o V2-6B
- b. Reset SI
- c. Isolate AFW flow to faulted S/Gs o Close SDAFW pump discharge valve - V2-14B o Close AFW header discharge valve - V2-16B
Critical BOP e. Close SDAFW pump steam shutoff valve for faulted S/G(s)
Task o V1-8B (S/G B)
- f. Perform Attachment 1, Deenergizing AFW Valves for Faulted S/G.
- g. Locally close the following valve for faulted S/G as necessary while continuing with this procedure.
o S/G C:
MS-29
- h. Check S/G blow down and blow down sample valves from faulted S/G - Closed o S/G B:
FCV-1931 A & B - Shut FCV-1934 A & B - Shut BOOTH OPERATOR: When requested close MS-29 IAW the SCN file after 4 minutes.
Critical Task to Isolate S/G B EOP-E-2 BOP Check CST Level - Greater than 10% (YES)
Check Secondary Radiation:
- a. Request periodic activity samples of all S/Gs Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 29 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior
- b. Unisolated secondary radiation monitors - Have remained normal (YES) o R-15, R-19s, R-31s
- c. Secondary sample results - Normal (When results available.)
Check If SI Flow Should Be Terminated:
- b. Secondary heat sink:
Total feed flow to intact S/G(s) - AT LEAST 300 GPM (YES)
OR Narrow range level in at least one intact S/G -
GREATER THAN 8% [23%] (YES)
- c. RCS pressure:
Pressure - GREATER THAN 1650 PSIG [1700 PSIG]
(May be met depending on scenario timeline and crew progression. If not then perform RNO)
Pressure - STABLE OR RISING Go to step 17 Reset SPDS and Go To EOP-E-1, Loss Of Reactor Or EOP-E-2 CRS Secondary Coolant, Step 1 Beginning of EOP-E-1, Loss of Reactor or Secondary Coolant Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 30 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior NOTE FOLDOUT for EOP-E-1 is in effect.
SI TERMINATION CRITERIA IF all conditions listed below occur, THEN reset SPDS and Go To EPP-7, SI TERMINATION, Step 1:
RCS subcooling based on core exit TCs -
Total feed flow to intact S/Gs - GREATER THAN 300 gpm OR Narrow range level in at least one intact S/G - GREATER THAN 8% [23%]
RCS pressure - GREATER THAN 1650 PSIG [1700 PSIG]
RCS pressure - STABLE OR RISING PZR level - GREATER THAN 14% [37%]
Termination criteria may be met at any time during EOP-E-1 and transition to EPP-7 would be performed. Scenario guide will proceed in EOP-E-1 until met.
Check If RCPs should be stopped:
EOP-E-1 RO b. RCPs - Any Running (NO)
RNO: Go to Step 2 Check if S/G Secondary Pressure Boundaries are Intact:
- b. Check pressures in all S/Gs None lowering in an uncontrolled manner (NO)
EOP-E-1 BOP None Completely depressurized (NO)
RNO: Check all faulted S/G(s) isolated (unless need for RCS cooldown) (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 31 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Check Intact S/G Levels:
- a. Narrow range levels - Greater than 23% (YES)
- b. Control feed flow to maintain narrow range levels -
between 23% AND 50%
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
EOP-E-1 RO Reset SI EOP-E-1 RO Reset Containment Isolation Phase A Check Secondary Radiation:
- b. Perform the following:
- 1) Request periodic activity samples of all S/Gs
- 2) Secondary sample results - Normal (When results available)
CAUTION If any PZR PORV opens because of high PZR pressure, Step 7.b should be repeated after pressure lowers to less than 2335 psig.
Check PZR PORVs and Block Valves:
- a. Power to block valves - Available (YES)
- b. PORVs - Closed (YES)
- c. Block valves - At least one open. (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 32 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Establish Instrument Air to CV:
- a. Check APP-002-F7 - Extinguished (YES)
- b. Reset IA PCV-1716
- c. Check IA PCV-1716 - OPEN (YES)
Check Power Supply to Charging Pumps - Offsite power available (NO)
Check adequate diesel capacity to run charging pumps (108 KW each). (YES)
Check if Charging Flow has been established:
- a. Charging pumps - At least one running. (YES)
- b. Establish desired charging flow:
o Start additional pump(s) as necessary o Adjust charging pump speed controllers as necessary EOP-E-1 RO to establish desired charging flow.
o Adjust HIC-121 as necessary to establish desired charging flow:
o Maintain seal injection flow - Between 6 gpm and 20 gpm per RCP unless seal injection isolated.
Check if SI flow should be terminated:
- b. Secondary heat sink:
o Total feed flow to intact S/Gs - At least 300 gpm (YES)
EOP-E-1 RO OR o Narrow range level in at least one intact S/G -
Greater than 8% (YES)
- c. RCS pressure:
o Pressure - Greater than 1700 psig (YES) o Pressure - Stable or Rising (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 33 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior
- d. PZR level - GREATER THAN 14% [37%]
- e. Reset SPDS and Go To EPP-7, SI Termination, Step 1 Begin EPP-7, SI Termination EPP-7 CREW Open Foldout I CAUTION If only one SW Pump is running, it is subject to runout until the following step is completed.
CHECK SW Header Pressure AND Transition To Steps Indicated By The Table Below:
EPP-7 BOP SW PRESSURE CONDITION Step BETWEEN 40 PSIG AND 50 5 PSIG Continuous Action Step EPP-7 CREW CHECK DC Busses A AND B - ENERGIZED (YES)
CHECK All The Following EDG Cooling Annunciators -
EXTINGUISHED (YES)
APP-010-E2, EDG A LUBE OIL HI/LO TEMP Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 34 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior APP-010-E3, EDG B LUBE OIL HI/LO TEMP APP-010-F2, EDG A COOL WTR HI/LO TEMP APP-010-F3, EDG B COOL WTR HI/LO TEMP CAUTION A loss of DC power may occur if the DC Busses are at maximum load and the Battery Chargers are not restarted within 60 minutes of a loss of all AC power.
CHECK Emergency Busses - ENERGIZED BY OFFSITE EPP-7 BOP POWER (NO)
CHECK PZR Heaters - POWER AVAILABLE (NO)
RNO:
EPP-7 BOP ENERGIZE 150 KW of PZR Heaters using EPP-21, Energizing Pressurizer Heaters From Emergency Busses, while continuing with this procedure.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 35 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior CHECK All Non-emergency AC Busses - ENERGIZED BY OFFSITE POWER (NO)
RNO:
PERFORM the following:
- a. VERIFY one of the following pumps are RUNNING:
TURNING GEAR OIL PUMP OR EMERG OIL PUMP
- b. VERIFY one of the following pumps are RUNNING:
SEAL OIL BACKUP PUMP OR AIR SIDE SEAL OIL BACKUP PUMP
- c. DETERMINE the cause of the loss of offsite power.
IF due to a failure within the plant, THEN RESTORE power using OP-603, Electrical Distribution, after repairs are completed.
OR IF due to a failure of the Startup Transformer or Switchyard, THEN REQUEST Load Dispatcher notify substation maintenance crews to restore power from either the Normal or Spare Startup Transformer.
OR IF due to a loss of the grid, THEN REQUEST Load Dispatcher to restore the grid using SORMC-EOP-070, Restoration of Service Follwing a System Shutdown.
DETERMINE If A SW Booster Pump Should Be Started:
EPP-7 BOP a. CHECK SW Booster Pumps - ALL STOPPED (NO)
RNO:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 36 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior Go to step 11 IF Offsite Power Is Lost After SI Reset, THEN Manually EPP-7 RO RESTART Safeguard Equipment EPP-7 RO RESET SAFETY INJECTION EPP-7 RO RESET CONTAINMENT ISOLATION PHASE A AND PHASE B RESET FEEDWATER ISOLATION Using ATTACHMENT 5, EPP-7 BOP RESETTING FEEDWATER ISOLATION In The Computer Room, RESET The IVSW System As Follows:
DEPRESS the IVSW RESET PCV-1922A Pushbutton in EPP-7 BOP Relay Cabinet ARP-1 DEPRESS the IVSW RESET PCV-1922B Pushbutton in Relay Cabinet ARP-2 ESTABLISH Instrument Air To CV As Follows:
EXTINGUISHED EPP-7 RO
- c. CHECK INST AIR VALVE TO CV PCV-1716 - OPEN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 2 Event # 6 - 12 Page 37 of 38 Event
Description:
FRV FCV-478 fails open causing the reactor to be manually tripped. Upon the Reactor trip, S/G B will fault inside containment. The SUT will be lost after the trip. EDG A will trip 3 minutes after it starts from its oil leak. Service Water Pumps C and D will fail to automatically start. CV Spray Pump B will not automatically start.
Time Position Applicants Actions or Behavior ESTABLISH Charging Flow As Follows:
- a. CHECK Charging Pumps - ALL STOPPED (NO)
EPP-7 RO RNO:
Go to step 17.h VERIFY charging flow on FI-122A - GREATER THAN 35 GPM VERIFY The Following:
EPP-7 RO SI PUMPs - ALL STOPPED
- ALL STOPPED The Lead Examiner may terminate the scenario anytime after SI is terminated Appendix D NUREG-1021, Rev. 9, Supp. 1
ILC-14 NRC SCENARIO 2 TURNOVER SHEET
- 1. INITIAL CONDITIONS a) Time in Core Life: EOL b) Reactor Power: 75%
c) Turbine Load: 564 MWe d) Boron Concentration: 124ppm e) Rod Height: 168 CBD f) RCS Pressure: 2235 psig g) PZR Level: 44%
h) Xenon: Equilibrium
- 2. TECHNICAL SPECIFICATION LCO ACTIONS STATEMENTS IN EFFECT T.S. # Description 3.7.7 Condition A
- 3. CLEARANCES IN EFFECT a) SWBP A OOS for seal replacement
- 4. CAUTION CAPS IN EFFECT a) None
- 5. PROTECTED EQUIPMENT a) None
- 6. DEGRADED EQUIPMENT a) None
- 7. SWITCHYARD ACCESS a) Unrestricted
- 8. PLANNED EVOLUTIONS a) Reduce power to 65% to support valve testing
- 9. TURNOVER INFORMATION a) None
- 10. REACTIVITY INFORMATION a) Review the OST-947 BOL/MOL/EOL charts for BA and PW additions
- 11. RISK a) GREEN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 3 Op Test No.: ILC-14 Examiners: Operators: CRS -
RO -
BOP -
Initial Conditions: 100% MOL, 9000 MWD/MTU, 768 PPM Boron.
Turnover: Maintain power at current level.
Critical Task: Tripping the reactor using the left reactor trip pushbutton Isolate B S/G Closing B S/G PORV Event Malf. No. Event Type* Event No. Description (I) RO, CRS LT-115 fails high 1
(TS) CRS (I) BOP, CRS PT-447, Turbine First Stage Pressure Transmitter, fails 2 (TS) CRS Low (C) RO, CRS B Charging Pump trip 3 (TS) CRS (C) BOP, CRS Tube leak B S/G 2.0 gpm 4
(TS) CRS (R) RO, CRS Downpower due to Tube Leak B S/G 5 (N) BOP (TS) CRS 6 (C) BOP, CRS FRV-498 fails high in automatic 7 (C) BOP, CRS Turbine Governor Valves fail closed 8 (C) RO, CRS Manual Reactor trip - First trip button does not work 9 (M) ALL B S/G faulted outside Containment 10 (M) ALL Tube Rupture B S/G Train A of SI fails to auto actuate. Must perform manual 11 RO actions to start and align equipment.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 3
SUMMARY
DESCRIPTION The crew will assume the watch with the plant at 100% RTP.
On cue from the Chief Examiner, VCT Level Transmitter LT-115 will fail high. This will cause LCV-115A to divert all letdown flow to the CVCS HUTs and will cause LC-112, VCT Level Controller, to go to full output. LT-115 edge meter on the RTGB will indicate high. This failure will result in an VCT lowering, however, with LT-115 failed high there will be no automatic makeup. With no operator action this would result in the loss of Charging Pump suction. AOP-003, Malfunction of Reactor Makeup Control, will be implemented and LCV-115A will be overridden to the VCT until the VCT level control can be restored on the alternate channel. This will require that the alternate channel (LT-112) be selected for all control functions of VCT level.
Once AOP-003 actions are completed and when the Chief Examine is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, PT-447, Turbine First Stage Pressure Transmitter, fails low.
The crew will perform the immediate actions of AOP-025, RTGB Instrument Failure, Section H, and verify S/Gs trending to 39% and place Rod Control in Manual. S/G levels will be restored to normal, alternate channel selected and feedwater regulating valves returned to automatic. Rod control will be returned to automatic once Tavg verified in the required band. PT-447 will then be removed from service in accordance with OWP-033, FSP-2. Failure of PT-447 will result in ITS Table 3.3.1-1, Item 17e, requirement to have 2 Turbine Impulse Pressure, P-7 inputs available for Reactor Protection System Interlocks to not be met. ITS LCO 3.3.1, Condition T, will be entered which requires that the P-7 interlock be verified in the required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR be in Mode 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. ITS Table 3.3.2-1, Items 1f, 1g, 4d, and 4e, requirement to have 2 High Steam Flow in Two Steam Lines for Safety Injection and Steam Line Isolation will not be met. ITS LCO 3.3.2, Condition D, will be entered which requires that the channel be placed in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND be in Mode 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. ITS Table 3.3.6.1 Item 4 will also be reviewed and determined to be applicable due to affecting Safety Injection ESFAS Instrumentation associated with Containment Ventilation Isolation Instrumentation. Once the Chief Examiner is satisfied with the crews actions and Tech Spec compliance, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, B Charging Pump will trip. The crew will start a charging pump IAW APP-003-F5, CHG PMP MOTOR OVLD/TRIP. The CRS should reference ITS 3.4.17 and determine that the crew still has two operable charging pumps so condition A does not apply. Condition E for Seal injection to any RCP not within limit AND At least on charging pump OPERABLE does apply while no charging pumps were running. The crew may enter AOP-018, Reactor Coolant Pump Abnormal Conditions Section C for Loss of Seal Injection. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, B S/G will develop an 2.0 gpm tube leak. The crew will enter AOP-035, S/G TUBE LEAK. The crew may first enter AOP-016, EXCESSIVE PRIMARY PLANT LEAKAGE. This procedure would direct entry to AOP-035. AOP-035 can be entered by confirmed R-24, MAIN STEAM LINE N-16 MONITORS, leakage greater than or equal to 30 gpd. This would need to be validated by other radiation monitors or sampling by chemistry as R-24 is not technically in service at this time and is only used for trending. The magnitude of the leak will be 2.0 gpm which equates to 2880 gpd. This will be seen on R-24B initially and R-15, CONDENSER AIR EJECTOR GAS will start to trend up shortly after. ITS 3.4.13 has a primary to secondary leakage limit of 75 gpd in any one S/G. IAW AOP-035 the crew will declare a Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 PSAL-3 event and initiate a downpower IAW AOP-038, Rapid Downpower. Be less than 50%
power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring PSAL-3 and be in mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of declaring PSAL-3.
When the Chief Examine is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, FCV-498 will fail high in automatic. The crew will enter AOP-010, Main Feedwater/Condensate Malfunction. Operator will perform immediate actions and take FCV-498 to manual to control level. Also, the crew will stop the load change IAW immediate operator actions. They will restore level to program level band and recommence the unit downpower with FCV-498 in manual control. When the Chief Examine is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner , The Turbine Governor valves fail closed. This will result in the crew initiating a manual reactor trip. The right trip button will not function but the left pushbutton will. Automatic reactor trip will not function if an automatic trip signal is received prior to initiation of the manual trip. On the reactor trip the B S/G PORV will fail 30% open. The crew will enter EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, perform immediate operator actions and exit to EOP-ES-0.1, REACTOR TRIP RESPONSE.
At step 5 of EOP-ES-0.1 a 1000 gpm tube rupture will be initiated. The crew will return to EOP-E-0 and initiate safety injection. EOP-E-0 will direct entry to EOP-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 4d checks the faulted S/G PORV closed and the RNO will direct locally isolating Instrument Air to the PORV. This will close the PORV and isolate the fault. Critical task due to impact on fission product barriers. Step 6 of EOP-E-2 will direct entry to EOP-E-3, STEAM GENERATOR TUBE RUPTURE. The crew will isolate B S/G, cooldown and depressurize the RCS and terminate safety injection.
The Chief Examiner may terminate the scenario at any time after safety injection has been terminated.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Sat /
Critical Task Critical Task Criteria Unsat Manually trip the Reactor Manually trip the reactor IAW EOP-E-0, prior to leaving step 1 of EOP-E-0.
Stop feeding S/G B Stop feeding the faulted S/G IAW EOP-E-0, prior to exiting EOP-E-0 Foldout, Step 2 AND within 10 min. of EOP-E-0 entry.
Isolate S/G B Isolate S/G B (pathway from affected S/G to atmosphere is isolated-affected S/G MSIV closed within 30 of event initiation)
Close S/G B PORV Close S/G B PORV EOP-E-2 step 4d RNO. CT due to fission product barrier Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:
IC-603, SCN 006_ILC_14_SIM_NRC_3 Status board is provided to crew is IC-13.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip or triggered events following the reactor trip:
Event 9: B S/G faulted outside Containment Event 10: Tube Rupture B S/G Event 11: Train A of SI fails to auto actuate. Must perform manual actions to start and align equipment.
EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
Event 1: LT-115 Fails High Event 2: PT-447 Fails Low Event 3: Charging Pump 'B' Trip Event 4: S/G 'B' Tube Leak Event 5: AOP-038 downpower Event 6: FRV-498 fails high in auto Event 7: Turbine Gov Valves fail closed Event 8: Rx trip. Auto trip and right pushbutton do not work EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
AOP-003, Malfunction of Reactor Makeup Control AOP-025, RTGB Instrument Failure, Section H OWP-033, FSP-2 APP-003-F5, CHG PMP MOTOR OVLD/TRIP AOP-035, S/G TUBE LEAK AOP-010, Main Feedwater/Condensate Malfunction EOP-E-0, REACTOR TRIP OR SAFETY INJECTION EOP-ES-0.1, REACTOR TRIP RESPONSE EOP-E-2, FAULTED STEAM GENERATOR ISOLATION EOP-E-3, STEAM GENERATOR TUBE RUPTURE Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 1 Page 6 of 50 Event
Description:
LT-115 VCT Level Transmitter Fails High Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 1, LT-115 fails high EVENT INDICATIONS:
APP-003-E3 LI-115 Edge meter reads high ERFIS indication for LI-115 High ERFIS indication for LI-112 lowering NOTE An oscillating level channel failure is a channel that is changing at a rate faster than the makeup system can change VCT level Check For Failure Of A Level Transmitter As Follows:
- c. Check VCT level indicators - OSCILLATING LEVEL DEVIATION OBSERVED (NO)
Go to step 1.e
- e. Check VCT level deviation between LT-112 and LT-115 -
GREATER THAN 8 INCHES (13%) (YES)
AOP-003 RO Check LT-115 - FAILED (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 1 Page 7 of 50 Event
Description:
LT-115 VCT Level Transmitter Fails High Time Position Applicants Actions or Behavior CAUTION With no operator action, LT-115 failed high will result in the loss of Charging Pump suction Note The selection of LT-112 in the Hagan Rack will return indicated level to LI-115 on the RTGB The VCT Level Transmitter Selector Switch should be operated swiftly to prevent prolonged loss of level signal from both loops. Loss of both signals could cause LCV-115B to open.
Stabilize The RCS Makeup System As Follows:
- a. Check LT-115 - FAILED HIGH (YES)
- c. Obtain Hagan Racks Key number 10
- d. Place VCT Level Transmitter Selector Switch located in Hagan Rack #19, IN LT-112 POSITION BOOTH OPERATOR: When requested swap to channel LT-112 in the Hagan room AOP-003 RO e. Check LT-115 - FAILED HIGH AOP-003 RO f. Place the LCV-115A Control Switch to AUTO Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 1 Page 8 of 50 Event
Description:
LT-115 VCT Level Transmitter Fails High Time Position Applicants Actions or Behavior
- g. Contact I&C to repair fail channel AOP-003 CRS Go to step 6 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 2 Page 9 of 50 Event
Description:
PT-447, Turbine First Stage Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #2, PT-447 Turbine First Stage Pressure Transmitter fails low, on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-003-D4 APP-005-F5 APP-006-A3 APP-006-B3 APP-006-C3 APP-006-D4 APP-006-E4 APP-006-F4 APP-006-F5 PI-447 lowering Tref lowering Rods stepping in Immediate Action Step Check Turbine Load Reduction -
o IN PROGRESS (NO)
AOP-025 BOP OR o HAS OCCURRED (NO)
Go to step 3 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 2 Page 10 of 50 Event
Description:
PT-447, Turbine First Stage Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior Immediate Action Step AOP-025 BOP Check S/G Level Trend - CONTROLLING IN AUTO TO 39% (YES)
Immediate Action Step Manually Control Reactor Power AND Tavg As Follows:
- a. Place the Rod Control Selector Switch in Manual
- b. Operate rods to maintain Reactor Power - LESS THAN 100%
AOP-025 BOP Make PA Announcement For Procedure Entry Perform The Following:
- a. Check S/G Level - STABILIZED AT BETWEEN 39% TO 52%
- b. Verify All FRV Controllers In MAN (YES)
AOP-025 BOP FCV-478 FCV-488 FCV-498 Place The 1ST STAGE PRESSURE Selector Switch To The AlternateChannel Below:
AOP-025 Failed Channel Switch Position BOP PT-446 PT-447 PT-447 PT-446 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 2 Page 11 of 50 Event
Description:
PT-447, Turbine First Stage Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior Restore Each S/G Level To Program Level Using FRVs OR Bypass AOP-025 BOP Valves Restore Each S/G FRVs To Automatic As Follows:
- a. Check S/G level - WITHIN +or -1% OF PROGRAMMED LEVEL (NO)
- a. WHEN S/G level is within + or -1% of programmed level, THENplace the affected Controller in AUTO.
- b. Place the affected Controller in AUTO Restore Rod Control To Automatic As Follows:
- a. Check Tavg - WITHIN - (If not then)
AOP-025 RO Adjust rods to restore Tavg - -0.5 to
- b. Check AFD - WITHIN TARGET BAND (YES)
AOP-025 RO Place the Rod Control Selector Switch in AUTO Remove The Affected Transmitter From Service Using OWP-033:
Channel OWP AOP-025 BOP PT-446 FSP-1 PT-447 FSP-2 OWP-033 BOP Perform OWP-033, FSP-2 actions to remove channel from service.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 2 Page 12 of 50 Event
Description:
PT-447, Turbine First Stage Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior Steam Dump Mode Selector Switch to Steam Pressure Control 1st stage pressure selector switch 446/447 selected to 446 B/S 447-2 70% Turbine Load Limit - tripped B/S 447-1 Permissive P tripped B/S 475 Loop 1 Hi Stm Flow - tripped B/S 485 Loop 2 Hi Stm Flow - tripped B/S 495 Loop 3 Hi Stm Flow - tripped AMSAC Bypass Switch POWER 2, Processor A AMSAC Bypass Switch POWER 2, Processor B BOOTH OPERATOR: When requested apply SCN file for OWP-033 ITS Table 3.3.1-1, Item 17e, requirement to have 2 Turbine Impulse Pressure, P-7 inputs available for Reactor Protection System Interlocks is determined not to be met.
ITS LCO 3.3.1, Condition T, will be entered which requires that the P-7 interlock be verified in the required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR be in Mode 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
ITS Table 3.3.2-1, Items 1f, 1g, 4d, and 4e, requirement to have 2 High Steam Flow in Two Steam Lines for Safety Injection and Steam AOP-025 CRS Line Isolation will not be met.
ITS LCO 3.3.2, Condition D, will be entered which requires that the channel be placed in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND be in Mode 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
ITS Table 3.3.6.1 Item 4 will also be reviewed and determined to be applicable due to affecting Safety Injection ESFAS Instrumentation associated with Containment Ventilation Isolation Instrumentation.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 3 Page 13 of 50 Event
Description:
Charging Pump B Trip Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #3, Charging Pump B Trip, on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-001-B2 APP-001-B4 APP-001-B6 APP-001-D6 APP-001-E6 APP-003-F5 FR-124 Seal injection flows read zero Charging Pump B indicating light is dual EXAMINERS NOTE: The crew may use APP-003-F5 to start another Charging Pump or they may use AOP-018. Below will be the flow path for either choice.
OBSERVATIONS
- 1. Charging Pump breaker indication APP-003 RO
- 3. Monitor the following ERFIS Points for BOTH Emergency Bus Voltages. ELV3020A for E-1 and ELV3021A for E-2 (Voltage less than 440 Volts may indicate a single-phase open circuit condition)
ACTIONS
- 2. DISPATCH Operator to check the Charging Pump breaker(s):
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 3 Page 14 of 50 Event
Description:
Charging Pump B Trip Time Position Applicants Actions or Behavior
- 1) "A" Charging Pump at 480V Bus DS
- 2) "B" Charging Pump at 480V Bus E1
- 3) "C" Charging Pump at 480V Bus E2
- 3. DISPATCH Operator to check the Charging Pump(s).
NOTE: If more than 15 minutes elapses without RCP Seal Cooling, then Seal Cooling must be isolated before starting CCW OR Charging to prevent Seal damage.
- 5. IF a single-phase open circuit condition is suspected THEN ENTER AOP-026, Grid Instability.
BOOTH OPERATOR: When requested to check the Charging Pump breaker and pump, wait 2 minutes and report that the pump has no abnormal indications and report that the breaker is warm to the touch and is tripped.
MAKE PA Announcement For Procedure Entry AOP-018 BOP NOTE The RCP malfunctions in the Table below are listed in order of priority This procedure is NOT applicable during implementation of EPP-1, Loss Of All AC OR any of its recovery procedures AOP-018 RO EVALUATE Plant Conditions AND Go To The Appropriate Section For RCP Malfunction Not Yet Addressed:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 3 Page 15 of 50 Event
Description:
Charging Pump B Trip Time Position Applicants Actions or Behavior Malfunction Section Reactor Coolant Pump Seal Section A Failure High Reactor Coolant Pmp Section B Vibration Loss of Seal Injection Section C AOP-018 CRS Go to Section C CHECK APP-001-D1, RCP THERM BAR COOL WTR LO FLOW alarm - ILLUMINATED (NO)
AOP-018 RO Go to step 11 NOTE A rupture is a leak of sufficient magnitude to require stopping the Charging Pumps or reduces Charging Pump Discharge Pressure to less than RCS Pressure.
Charging System piping is any piping where a leak prevents the Charging Pumps from delivering flow to the Charging Line OR Seal Injection Line.
DETERMINE If A Charging Pump Can Be Started:
AOP-018 RO a. CHECK Charging System Piping - RUPTURED (NO)
GO TO Step 12 AOP-018 RO CHECK SI - INITIATED (NO)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 3 Page 16 of 50 Event
Description:
Charging Pump B Trip Time Position Applicants Actions or Behavior GO TO Step 14 AOP-018 RO VERIFY At Least ONE Charging Pump - RUNNING CHECK Seal Injection To RCPs ANY Seal Injection flow - LESS THAN 6 GPM (NO)
AOP-018 RO AND ANY Thermal Barrier Delta P - LESS THAN 5 inches (NO)
Go to step 47 ESTABLISH Charging Flow On FI-122A, CHARGING LINE FLOW AOP-018 RO GREATER THAN 35 GPM AOP-018 RO CHECK Normal Letdown - IN SERVICE (YES)
CONTROL Charging And Letdown Flow To Maintain Pressurizer Level As Follows:
AOP-018 RO OR o PZR level between 30% and 40% with RCP C stopped.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 3 Page 17 of 50 Event
Description:
Charging Pump B Trip Time Position Applicants Actions or Behavior
- a. CHECK RCP Seal Injection - ALIGNED (YES)
- b. CHECK RCP Seal Injection Flow - BETWEEN 8 GPM AND 13 GPM (YES)
AOP-018 RO CHECK Seal Injection Flow - ESTABLISHED TO ALL RCPs (YES)
ITS 3.4.17 Condition E will be entered for the time the Charging Pump was off and seal injection was less than 6 gpm.
AOP-018 CRS Condition E.1 - Initiate action to restore seal injection to affected RCP(s) Immediately Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 4 Page 18 of 50 Event
Description:
S/G B Tube Leak (2.0 gpm)
Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #4, Tube leak on S/G B (2.0 gpm), on cue from the Chief Examiner.
EVENT INDICATIONS:
VCT level lowering Charging flow rising, PZR level lowering, Auto-makeups R-24 rising R-15 rising R-19B rising RR-1 warning for R-15/19B EXAMINERS NOTE: The crew may also enter AOP-005 for any alarming RMS channel and/or AOP-016, Excessive RCS Leakage.
Continuous Action Step:
Determine if Reactor Trip Needed as follows: (NO)
- a. Check the following:
PZR Level - Less than 7% (NO)
OR AOP-035 RO RCS Subcooling - LESS THAN 35°F (NO)
RNO:
- a. IF PZR level can NOT be maintained greater than 7% OR Subcooling can NOT be maintained greater than 35°F, THEN trip the Reactor and Go to EOP-E-0.
Go to Step 2 AOP-035 BOP Make PA Announcement For Entry into AOP-035.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 4 Page 19 of 50 Event
Description:
S/G B Tube Leak (2.0 gpm)
Time Position Applicants Actions or Behavior Continuous Action Step:
Check VCT Level - Less than 12.5 inches. (NO)
IF VCT level lowers to less than 12.5 inches, then perform Step 4.
Go to Step 5.
Check RCS Level lowering in an uncontrolled manner. (NO)
AOP-035 RO RNO: Go to Step 12.
AOP-035 RO Control Charging Flow to Maintain Desired RCS Level Continuous Action Step:
Check RCS leakage - Greater than running charging flow. (NO)
AOP-035 RO RNO: IF leakage exceeds Charging flow, Then go to step 6.
Go to Step 15.
Notify Chemistry personnel to periodically sample all S/Gs for Activity AOP-035 BOP and Boron concentration.
Check Assistance To Open S/G Sample Valves- REQUESTED (NO)
RNO: WHEN assistance to open S/G Sample valves is requested, AOP-035 BOP THEN observe the NOTE prior to Step 17 and perform Step 17.
Observe the NOTE prior to Step 18 and Go to Step 18.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 4 Page 20 of 50 Event
Description:
S/G B Tube Leak (2.0 gpm)
Time Position Applicants Actions or Behavior Determine Leak Rate Using At Least One Of The Following Methods:
R-24 Recorder Perform OST-051, Reactor Coolant System Leakage Evaluation Perform a Charging versus Letdown balance AOP-035 Notify Chemistry personnel to perform isotopic analysis of S/G BOP samples for leak rate determination Use R-15 to monitor for low level Primary-to-Secondary leakage using the OP-504, Condenser Air Removal section "Using R-15 to Monitor for Low Level Primary to Secondary Leakage" Use CP-014 Conversion Factors to correlate R-15 to leakage AOP-035 BOP Check Leak Rate Determination - Complete NOTE ITS LCO 3.4.13 provides a primary to secondary leakage limit of 75 gpd through any one S/G.
Total leakage is assumed to be coming from a single S/G when unable to determine leakage from the individual S/Gs.
Normally performed steps in GP-006-1 or AOP-038, Rapid Downpower, such as placing S/G Blowdown to the Flash Tank may require Release Permits.
Continuous Action Step:
AOP-035 RO/BOP Check Leak Rate - Greater than OR equal to 100 gpd for a single S/G. (YES, should be approximately 2880 gpd)
NOTE It is important to perform GP-006-1 or AOP-038, Rapid Downpower, and AOP-035 concurrently to the extent possible in order to minimize secondary contamination.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 4 Page 21 of 50 Event
Description:
S/G B Tube Leak (2.0 gpm)
Time Position Applicants Actions or Behavior Perform the following Power Reduction:
- Notify Chemistry that a PSAL-3 event has occurred.
- Check Reactor in MODE 1 OR MODE 2. (YES)
- Be less than 50% power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring PSAL-3.
- Be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of declaring PSAL-3.
Identify Leaking S/G Using At Least One Of The Following Methods:
- Evaluate indications on R-24 Recorder OR
- Evaluate indications on RI-19A, RI-19B, and RI-19C, STM GEN BLOW DN Radiation Monitors AOP-035 BOP OR
- Evaluate indications on R-31A, R-31B, and R-31C, STEAMLINE RADIATION MONITORs OR
- Chemistry analysis of S/G samples for boron and activity AOP-035 CRS Implement the EALs Review Technical Specification LCOs AOP-035 CRS ITS 3.4.13, Condition B, Be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND Be in Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 4 Page 22 of 50 Event
Description:
S/G B Tube Leak (2.0 gpm)
Time Position Applicants Actions or Behavior EVALUATOR NOTE: At the Lead Evaluators discretion the crew can be allowed to enter and perform a portion of the Rapid Downpower. The next event may be inserted at any time once the applicable LCO has been entered and the shutdown requirement has been determined.
The following steps are from AOP-038, Rapid Downpower NOTIFY Plant Personnel Of Procedure Entry Using The Plant Page AOP-038 RO/BOP System DETERMINE Corrected Boration And Target Rod Height For Target Power Level Using Most Recently Performed OST-947, OPERATIONS REACTIVITY PLAN AOP-038 RO Target Load Reduction Rate________ %/min Target Power Level ________
Target Rod Height _________Steps Corrected Boration _________Gallons PERFORM Brief Of Control Room Personnel To Include The Following:
Reason for downpower AOP-038 CRS Target Power Level Target Rod Height Rate of load reduction Amount of boric acid addition Check required Power Reduction Rate - Less than OR equal to AOP-038 RO 5%/minute. (YES)
ENERGIZE All Available PZR Heaters PZR HTR CONTROL GROUP AOP-038 RO PZR HTR BACK-UP GROUP A PZR HTR BACK-UP GROUP B Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 4 Page 23 of 50 Event
Description:
S/G B Tube Leak (2.0 gpm)
Time Position Applicants Actions or Behavior AOP-038 RO Check Rod Control - IN AUTO (YES)
INITIATE Boration Using Attachment 1, RCS Boration, While AOP-038 RO Continuing With This Procedure INITIATE Turbine Load Reduction While Continuing With This Procedure
- a. CHECK EH Turbine Control - IN OPER AUTO
- b. PREPARE For Turbine Load Reduction As Follows:
AOP-038 BOP 1) CHECK IMP IN - ILLUMINATED
- 2) SET desired load in the SETTER
- 3) SELECT the desired Load Rate
- c. DEPRESS the GO pushbutton to initiate Turbine Load reduction ADJUST Turbine Load To Control Tavg Within 5°F Of Tref Using One Of The Following:
AOP-038 BOP ADJUST Load Rate OR DEPRESS GO and HOLD pushbuttons NOTE Four hour NRC notification is only required if the Shutdown was required by ITS.
NOTIFY Plant Personnel Of Procedure Entry Using The Plant Page AOP-038 RO/BOP System AOP-038 CRS Initiate Notification of the Rapid Downpower iaw AOP-038 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 6 Page 24 of 50 Event
Description:
FRV-498 Fails Open Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #6, FRV-498 fails open, on cue from the Chief Examiner.
EVENT INDICATIONS:
FR-498 feedwater flow and S/G level rising APP-006-C1, S/G FW > STM Flow APP-006-C3, S/G C LVL DEV Immediate Action Step Check Feedwater Regulating Valves - OPERATING PROPERLY (MANUAL OR AUTO):
FCV-478, FRV "A" FCV-488, FRV "B" FCV-498, FRV "C" (NO)
RNO AOP-010 BOP Perform the following:
- a. Verify FRV for affected S/G(s) in manual control. ( FCV-498 placed in manual)
- b. Attempt to stabilize S/G level using FRV and/or FRV Bypass Valves by matching steam flow with feed flow.
- c. Stop any load change in progress.
- d. Restore affected S/G level to between 39% and 52%.
Check Reactor Trip Setpoint - BEING APPROACHED (NO)
AOP-010 BOP Go to step 4 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 6 Page 25 of 50 Event
Description:
FRV-498 Fails Open Time Position Applicants Actions or Behavior AOP-010 BOP Make a PA announcement for procedure entry Go to the appropriate step from the table AOP-010 CRS Other - step 24 Continuous Action Step Reduce Turbine Load At 1%/MIN To 5%/MIN To Match Feedwater AOP-010 BOP Flow AND Steam Flows As Follows: (Steam and feed are matched)
AOP-010 BOP Check S/G level - AT OR TRENDING TO PROGRAM (YES)
AOP-010 RO Check Tavg - AT OR TRENDING TO Tref (YES)
Contact maintenance to troubleshoot and correct the feedwater AOP-010 CRS problem.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 26 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #7, Turbine Governor Valves fail closed, on cue from the Chief Examiner.
EVENT INDICATIONS:
Governor valve indicators lowering Net MWs lowering S/G levels lowering PZR pressure rising PZR level rising Charging Pump speed lowering EOP-E-0, Reactor Trip or Safety Injection CRITICAL TASK Immediate Action Steps
- 1. Check Reactor Trip: (YES)
EOP-E-0 Reactor trip and bypass breakers - OPEN CRITICAL TASK RO Rod position indicators - AT ZERO Rod Bottom lights - ILLUMINATED Neutron flux - LOWERING Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 27 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Immediate Action Steps Check Turbine Trip:
- a. Both turbine stop valves - Closed (YES)
- b. All MSR purge and shutoff valves - Closed (YES)
Immediate Action Steps Check Power to AC Emergency Busses:
- a. E1 or E2 - At least one energized (YES)
- b. E1 and E2 - Both energized (YES)
EXAMINERS NOTE: The crew may decide to initiate SI base on High Steam Flow Bistables being in from the OWP and Tavg lowering due to partially open S/G PORV. If they do then they will perform step B below. If they do not then they will transition to EOP-ES-0.1 Immediate Action Steps Check SI Status:
a) Check if SI is actuated:
EOP-E-0 RO SI annunciators - ANY ILLUMINATED (NO)
SI equipment - AUTO STARTED (NO)
RNO
- a. Check if SI is required:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 28 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior PZR pressure less than 1715 psig OR Containment pressure greater than 4 psig OR OR High steam flow with low Tavg or low steam pressure bistables illuminated IF SI is required, THEN manually actuate BOTH trains of SI.
IF SI is NOT required, THEN perform the following:
- 1) Reset SPDS and initiate monitoring of Critical Safety Functions Status Trees.
- 2) Go To EOP-ES-0.1, Reactor Trip Response, Step 1.
b) Check BOTH trains of SI - ACTUATED SI pumps - BOTH RUNNING (YES)
RHR pumps - BOTH RUNNING (YES)
EOP-E-0 CRS Verifies all immediate actions for EOP-E-0.
EXAMINERS NOTE: Crew may take early actions at this time to address items that did not function or operate as designed.
Manually start A SI Pump Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 29 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Manually start A RHR Pump Manually start B SW Pump Align Phase A that did not reposition on Phase A due to SI Train A failure. (This can be done by Initiating CV isolation or manually)
BOOTH OPERATOR: If requested to realign Phase A valves as an AO ensure the control room has repositioned all valves that can be operated from the RTGB prior to initiating the SCN file. The SCN file will reposition all Phase A valves that did not change state.
Critical CRS FOLDOUT for EOP-E-0 is in effect Task FAULTED S/G AFW ISOLATION CRITERIA IF both conditions listed below are met, Any S/G pressure is lowering in an uncontrolled manner OR has completely depressurized (YES, S/G B lowering in an uncontrolled manner)
AND Any S/G is NOT faulted THEN perform the following: (YES, A and C not faulted)
- a. Reset SI.
- b. Close steam driven AFW pump discharge valve for faulted S/G(s):
V2-14A (S/G A)
V2-14B (S/G B)
V2-14C (S/G C)
V2-16A (S/G A)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 30 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior V2-16B (S/G B)
V2-16C (S/G C)
- d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/G(s).
- e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [23%] in at least one S/G.
CRITICAL TASK: Isolate AFW to faulted S/G by manual operator actions within 10 minutes of EOP-E-0 entry.
BOOTH OPERATOR: When requested perform CAN file for Attachment 2 of EOP-E-0 Perform Attachment 1, Auto Action Verification, While continuing EOP-E-0 CRS with this procedure. (Should be assigned to BOP.) (Att. 1 steps are presented next followed by the remainder of EOP-E-0.)
Beginning of EOP-E-0 Attachment 1 (Remainder of EOP-E-0 Follows this Section)
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Att. 1 BOP Check ECCS Pumps Running:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 31 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior SI pumps - BOTH RUNNING (NO, Starts A SI Pump)
RHR pumps - BOTH RUNNING (YES)
Att. 1 Check ECCS Valves - PROPER EMERGENCY ALIGNMENT (NO.
BOP open SI-744B)
Att. 1 BOP Check CCW Pumps - AT LEAST ONE RUNNING (YES)
Check Containment Isolation Phase A
- a. Phase A - Actuated (YES)
- b. Phase A valves - Closed (NO, CVC-200A/204A, RC-550, FP-248/249/256/258, WDS-1721/22/23/28/86/87/89/&94, and PCV-1922A)
Att. 1 BOP
- c. Excess letdown - Isolated (YES)
CVC-387 - Closed (YES)
HIC-137 - at 0% DEMAND (YES)
- c. Manually close valve(s) as necessary BOOTH OPERATOR: If requested to realign Phase A valves as an AO ensure the control room has repositioned all valves that can be operated from the RTGB prior to initiating the SCN file. The SCN file will reposition all Phase A valves that did not change state.
May not be required if the crew initiates CV Isolation using the RTGB pushbuttons Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 32 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Check Feedwater Isolation:
a) Main feed pumps - BOTH TRIPPED (YES) b) Main feedwater - ISOLATED Att. 1 BOP FRVs - Closed (YES)
Feedwater reg bypass valves - Closed (YES)
Feedwater header section valves - Closed (YES)
Check if Main Steamlines Should Be Isolated:
a) Main steamline isolation - REQUIRED (YES, if received low Att. 1 BOP Tavg Bistables due to Hi Stm Flow Bistables being in form the OWP for PT-477) b) Close MSIVs and MSIV Bypasses Check Proper Service Water System Operation:
Att. 1 BOP
- b. SW booster pumps - Both running (YES) o Both SW header low pressure alarms (APP-008-F7/F8) - Extinguished (YES)
Att. 1 BOP Check Both EDGs - Running (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 33 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior
- a. RCS pressure - less than 1650 psig (NO, but trending down)
- b. SI pumps- Flow Indicated (NO)
- c. RCS pressure - less than 275 psig. (NO)
- d. RHR - Flow Indicated (NO)
Att. 1 BOP Check CV Recirculation Fans - All Running (YES, all available)
Check IVSW - Actuated (YES)
Att. 1 BOP PCV-1922A - Open (YES)
PCV-1922B - Open (YES)
Check CV ventilation isolation (YES)
Att. 1 BOP
- a. CV ventilation isolation valves - CLOSED (YES)
Check control room ventilation - aligned for pressurization mode (YES)
HVA-1A or HVA-1B - Running (YES)
HVE Stopped (YES)
Att. 1 BOP HVE-19A or HVE-19B - Running (NO, starts HVE-19A or HVE-19B)
Control Room HVAC outside air damper A or B - Open (YES)
CR-D1A-SA - Closed (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 34 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior CR-D1B-SB - Closed (YES)
Att. 1 BOP Check DS Bus - Energized (YES)
Check Battery Chargers - Energized (YES)
Att. 1 BOP APP-036-D1 - Extinguished (YES)
APP-036-D2 - Extinguished (YES)
Att. 1 BOP Stop R-11/12 Sample Pump Att. 1 BOP Locally Reset and Load IACs as necessary (N/A)
Perform Crew Update to include the following:
Attachment Completion Manual Actions Taken (Started A SI Pump, B RHR PUMP, B SW Pump. Aligned Phase A valves - CVC-200A/204A, Att. 1 BOP RC-550, FP-248/249/256/258, WDS-1721/22/23/28/86/87/89/&94, and PCV-1922A), and opened SI-744A Failed Equipment status SW status Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 35 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior End of EOP-E-0 Attachment 1 Continuation of EOP-E-0 Check AFW Pumps - Running (MDAFW Pumps are running)
- b. S/G levels - 2 less than 16 % (May be less than at this point, however, the SDAFW Pump is running )
Check AFW Valves - Proper Emergency Alignment (YES)
AFW header discharge valves - Full Open (YES)
EOP-E-0 RO AFW header section valves - Full Open (YES)
Steam driven AFW pump discharge valves - Full open if pump is running. (YES)
Check Total AFW Flow:
Reset SI EOP-E-0 RO Control feed flow to maintain NON-faulted S/Gs narrow range level - Between 8% and 50%.
Check total AFW flow- Greater than 300 gpm (YES)
Check CV Spray NOT Required:
- a. CV pressure - Has remained less than 10 psig. (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 36 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior
- b. CV Spray - NOT actuated (YES)
Check RCP Seal Cooling:
CCW flow to RCP thermal barriers - Normal (YES)
APP-001-C1 / D1 - Extinguished (YES)
OR EOP-E-0 RO Seal injection flow - Normal (YES)
Seal injection flow - Greater than 6 gpm per RCP OR Thermal barrier Ps - Greater than 5 inches water.
Check RCS Temperature With NO RCPs running, RCS cold leg temperatures - Stable at or trending to 547°F (NO)
RNO: IF temperature is less then 547°F AND lowering then perform the following: (YES)
EOP-E-0 RO a. Stop dumping steam
- b. IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:
Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% in at least one S/G.
- c. IF cooldown continues, THEN close MSIVs and MSIV Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 37 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior bypass valves. (MSIVs automatically closed due to Large Break LOCA)
Check PZR PORVs and Spray Valves:
- a. PORVs - Closed (YES)
- b. Normal PZR spray valves - Closed (YES)
- c. Aux spray valve - Closed (YES)
Check If RCPs should be stopped:
- a. RCPs - Any Running (YES)
RNO: Go to Step 14 Step 14: Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs None lowering in an uncontrolled manner (NO)
EOP-E-0 BOP None Completely depressurized (YES)
RNO:
Reset SPDS and initiate monitoring of CSFSTs. Go to EOP-E-2, Faulted Steam Generator Isolation step 1.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 38 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Beginning of EOP-E-2 CAUTION At least one S/g must be maintained available for RCS cooldown.
Any faulted S/G or secondary break should remain isolated during Check MSIVs and MSIV Bypass Valves for Faulted S/G - Closed S/G C:
EOP-E-2 BOP V1-3B MS-353B Check if any S/G Secondary Pressure Boundary is Intact:
EOP-E-2 BOP a. Check pressures in all S/Gs - Any stable or rising. (YES)
Identify Faulted S/Gs:
- a. Check pressures in all S/Gs:
Any S/G pressure lowering in an uncontrolled manner (YES, B S/G)
EOP-E-2 BOP OR Any S/G completely depressurized CAUTION
- If the SDAFW pump is the only available source of feed flow, steam supply to the SDAFW pump should be maintained from at least one S/G.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 39 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior
- If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Isolate Faulted S/G(s):
- a. Check main feedwater to faulted S/G(s) - ISOLATED (YES)
S/G B valves - CLOSED:
FCV-488, feedwater reg valve FCV-489, feedwater reg bypass valve V2-6B, feedwater header section valve
- b. Reset SI
- c. Isolate AFW flow to faulted S/G(s):
EOP-E-2 Close steam driven AFW pump discharge valve:
Critical BOP Task V2-14B (S/G B)
Close AFW header discharge valve:
V2-16B (S/G B)
- d. Check faulted S/G(s) steam line PORV - CLOSED (NO)
RV1-2 (S/G B)
RNO:
- d. Manually close PORV by adjusting pot to 0.0. (NO)
IF affected PORV(s) can NOT be closed, THEN close BOTH instrument air isolation valves for the affected controller(s):
(Secondary Control Panel behind PIC)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 40 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior PIC-487 (S/G B):
IA-3271, IA TO PIC-487 UPPER I/P IA-3272, IA TO PIC-487 LOWER I/P
- e. Close steam driven AFW pump steam shutoff valve for faulted S/G(s):
V1-8B (S/G B)
- f. Perform Attachment 1, Deenergizing AFW Valves For Faulted S/G(s)
- g. Locally close the following valve for faulted S/G(s) as necessary while continuing with this procedure:
S/G B:
MS-29, SG "B" BYPASS DRN & WARM-UP LINE TO AFW PUMP (pipe jungle above/right of V1-8B)
- h. Check S/G blowdown and blowdown sample valves from faulted S/G(s) - CLOSED S/G B:
SG2 BLOWDOWN FCV-1931 A & B FCV-1934 A
& B SHUT BOOTH OPERATOR: When requested to close IA-3271 and IA-3272, acknowledge report.
After 5 minutes report the valves closed and the PORV is closed.
CRITICAL TASK - Close S/G B PORV. Critical due to EALs for Loss of Containment. No longer lost.
BOOTH OPERATOR: When requested open the breaker for V1-8B, V2-16B and V2-14B Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 41 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior IAW the SCN file after 4 minutes. Breakers for V2-16B and V2-14B may have been previously opened IAW EOP-E-0, Att. 2.
BOOTH OPERATOR: When requested close MS-29 IAW the SCN file after 4 minutes.
CRITICAL TASK - ISOLATE FAULTED B STEAM GENERATOR EOP-E-2 BOP Check CST level greater than 10% (YES)
Check Secondary Radiation:
- a. Request periodic activity samples of all S/Gs
- b. Unisolated secondary radiation monitors - Have remained normal (NO)
EOP-E-2 BOP R-15, R-19s, R-31s
- c. Secondary sample results - Normal (When results available.)
. Reset SPDS and Go To EOP-E-3, Steam Generator Tube Rupture, Step 1.
BEGINNING OF EOP-E-3 NOTE FOLDOUT for EOP-E-3 is in effect.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 42 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Chemistry should be available for sampling during this procedure.
Step 1 RCP trip criteria applies until an operator controlled RCS cooldown is initiated.
CONTINUOUS ACTION STEP Check If RCPs Should Be Stopped:
- a. RCPs - ANY RUNNING (YES)
EOP-E-3 RO b. SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW (YES)
[50°F] (NO)
RNO: Go to Step 2 Identify Ruptured S/G(s): (B S/G is ruptured)
Unexpected rise in any S/G narrow range level OR High radiation from any SG steamline (R-31s)
OR EOP-E-3 BOP High radiation from any SG blowdown line (R-19s)
OR High radiation from any S/G sample:
Contact Chemistry to sample all S/Gs for activity as necessary CAUTION If the steam driven AFW pump is the only available source of feed flow, steam supply to Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 43 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior the steam driven AFW pump should be maintained from at least one S/G.
At least one S/G must be maintained available for RCS cooldown.
Isolate Flow From Ruptured S/G(s):
- a. Adjust ruptured S/G(s) steam line PORV controller setpoint to 1060 psig
- b. Check ruptured S/G steam line PORV - (RV1-2) CLOSED (YES)
- c. Close steam driven AFW pump steam shutoff valve for ruptured S/G: (V1-8B)
- d. Locally close the following valve for ruptured S/G(s) while continuing with this procedure:
MS-29, SG "B" BYPASS DRN & WARM-UP LINE TO EOP-E-3 BOP AFW PUMP (pipe jungle above/right of V1-8B)
- e. Check S/G blow down and blow down sample valves from ruptured S/G(s) - Closed SG2 Blowdown FCV-1931 A & B FCV-1935 A & B SHUT
- f. Check MSIV above and below seat drain valves for ruptured S/G - CLOSED (YES)
BOOTH OPERATOR: When requested, wait 3 minutes and then close MS-29 IAW SCN file.
CAUTION If any ruptured S/G is faulted, feed flow to that S/G should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 44 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Continuous Action Step Check Ruptured S/G Level:
- a. Narrow range level - Greater than 8%. (YES)
- c. Stop feed flow to ruptured S/G:
Close steam driven AFW pump discharge valve: V2-14B Close AFW header discharge valve: V2-16B
- d. Perform Att. 4, Deenergizing AFW Valves For Ruptured S/Gs BOOTH OPERATOR: When requested, wait 3 minutes and then open the breakers for AFW valves as specified in Att. 4 IAW the SCN file.
CRITICAL TASK - ISOLATE S/G B PRIOR TO S/G OVERFILL CAUTION Major steam flow paths from the ruptured S/G(s) should be isolated before initiating RCS cooldown. This includes MSIVs and MSIV bypass valves, steam line PORV, and AFW pump steam shutoff valve.
EOP-E-3 BOP Check Ruptured S/G Pressure - Greater than 500 psig. (YES)
CAUTION IF RCPs are not running, the following steps may cause a false CSF-4, Integrity Status Tree, indication for the ruptured loop. Disregard the ruptured loop T-cold indication until after performing Step 28.
NOTE Main steamline isolation may occur if the high steam flow setpoint is exceeded. The cooldown should be continued using the steam line PORV(s) if MSIV closure occurs.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 45 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Initiate RCS Cooldown:
- a. Determine required core exit temperature:
Ruptured SG Pressure (PSIG) Required Core Exit Temperature
(°F) 1150 and above 508 [488]
1100 to 1149 503 [483]
1050 to 1099 497 [477]
1000 to 1049 491 [471]
950 to 999 485 [465]
900 to 949 478 [458]
850 to 899 472 [452]
800 to 849 465 [445]
750 to 799 458 [438]
700 to 749 450 [430]
650 to 699 442 [422]
EOP-E-3 BOP 600 to 649 433 [413]
550 to 599 424 [404]
500 to 549 415 [395]
- b. Dump steam to condenser from intact S/G(s) at maximum rate:
maximum rate from intact
- 1) Check condenser - AVAILABLE FROM INTACT S/G(s)
(NO)
RNO: Manually dump steam at maximum rate from intact S/G using steam line PORVs.
- c. Core exit TCs - Less Than Required Temperature
- d. Stop RCS cooldown
- e. Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE Continuous Action Step EOP-E-3 BOP Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 46 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Check Intact S/G Levels
- a. Narrow range levels - Greater than 8% (YES)
- b. Control feed flow to maintain narrow range levels - BETWEEN 21% and 50%.
CAUTION If any PZR PORV opens because of high PZR pressure, Step 8.b should be repeated after pressure lowers to less than 2335 psig.
Continuous Action Step Check PZR PORVs And Block Valves:
EOP-E-3 RO a. Power to block valves - AVAILABLE (YES)
- b. PORVs - CLOSED (YES)
- c. Block valves - AT LEAST ON OPEN (YES)
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
EOP-E-3 RO Reset SI EOP-E-3 RO Reset Containment Isolation Phase A Establish Instrument Air To CV:
- a. Check APP-002-F7 - EXTINGUISHED (YES)
- b. Reset IA PCV-1716, instrument air isolation to CV
- c. Check IA PCV-1716 - OPEN (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 47 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior CAUTION If RCS pressure lowers in an uncontrolled manner to less than 275 psig [350 psig], the RHR pumps must be manually restarted to supply water to the RCS.
Check If RHR Pumps Should Be Stopped:
EOP-E-3 RO a. RCS pressure - GREATER THAN 275 PSIG [350 PSIG] (YES)
- b. Stop RHR pumps
- c. Monitor RCS pressure Establish Charging Flow:
- a. Charging pumps- AT LEAST ONE RUNNING (YES)
- b. Align charging pump suction to RWST
- 1) Open LCV-115B
- 2) Close LCV-115C
Start charging pump(s) as necessary to establish at least one running Adjust charging pump speed controllers as necessary to establish maximum charging flow for running pump(s)
Adjust HIC-121, charging flow control valve, as necessary to establish desired charging flow:
o Maintain seal injection flow - BETWEEN 6 GPM AND 20 GPM PER RCP UNLESS SEAL INJECTION ISOLATED Check If RCS Cooldown Should Be Stopped:
- b. Stop RCS cooldown
- c. Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 48 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior EOP-E-3 BOP Check Ruptured S/G Pressure - Stable or Rising (YES)
Check RCS Subcooling Based on Core Exit TCs - Greater than 55°F EOP-E-3 RO (YES)
Depressurize RCS to Minimize Break Flow and Refill the PZR:
- a. Normal PZR spray - AVAILABLE (YES)
- b. Spray PZR with maximum available spray until any of the following conditions are satisfied:
Both of the following:
OR PZR level - GREATER THAN 73%
OR RCS subcooling based on core exit TCs - LESS THAN 35°F
- c. Close spray valves when any condition above is satisfied
- d. Observe CAUTION prior to Step 20 and Go to Step 20 CAUTION SI must be terminated when termination criteria are satisfied to prevent overfilling the ruptured S/G(s).
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 3 Event # 7-11 Page 49 of 50 Event
Description:
Turbine Governor Valves Fail Closed Resulting in a Reactor Trip, Right Reactor Trip Pushbutton does not work. S/G B Faults Outside of CV (PORV fails 30% open), Tube Rupture on S/G B, and Train A SI Fails to Auto Actuate.
Time Position Applicants Actions or Behavior Check if SI Flow Should be Terminated:
- b. Secondary heat sink:
Total feed flow to S/Gs - AT LEAST 300 GPM EOP-E-3 RO AVAILABLE (YES)
OR Narrow range level in at least one intact S/G - GREATER THAN 8% (YES)
- d. PZR level - GREATER THAN 14% (YES)
EOP-E-3 RO Stop Both SI Pumps The Lead Examiner may terminate the scenario anytime after the SI pumps have been secured IAW EOP-E-3 Appendix D NUREG-1021, Rev. 9, Supp. 1
ILC-14 NRC SCENARIO 3 TURNOVER SHEET
- 1. INITIAL CONDITIONS a) Time in Core Life: MOL b) Reactor Power: 100%
c) Turbine Load: 749 MWe d) Boron Concentration: 768 ppm e) Rod Height: 218 CBD f) RCS Pressure: 2235 psig g) PZR Level: 53%
h) Xenon: Equilibrium
- 2. TECHNICAL SPECIFICATION LCO ACTIONS STATEMENTS IN EFFECT T.S. # Description
- 3. CLEARANCES IN EFFECT a) None
- 4. CAUTION CAPS IN EFFECT a) None
- 5. PROTECTED EQUIPMENT a) None
- 6. DEGRADED EQUIPMENT a) None
- 7. SWITCHYARD ACCESS a) Unrestricted
- 8. PLANNED EVOLUTIONS a) Maintain current power level
- 9. TURNOVER INFORMATION a) None
- 10. REACTIVITY INFORMATION a) Review the OST-947 BOL/MOL/EOL charts for BA and PW additions
- 11. RISK a) GREEN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 4 Op Test No.: ILC-14 Examiners: Operators: CRS -
RO -
BOP -
Initial Conditions: 68% RTP EOL, 17400 MWD/MTU, 128 ppm Boron Turnover: Maintain current power level Critical Task: Tripping the turbine after the ATWS Inserting Control Rods during the ATWS Emergency Borating during the ATWS Isolate CV Phase A valves FP-248/249/256/258 Isolate CV Phase B valve CVC-381 Event Malf. No. Event Type* Event No. Description 1 (I) RO, CRS Loop 1 Thot fails Low (TS) CRS 2 (C) BOP, CRS C S/G PORV fails open (TS) CRS 3 (I) RO, CRS PC-444J has a pressure shift down 4 (C) BOP, CRS Main Feedwater Pump B trip 5 (R) RO, CRS Load reduction to <60% RTP (N) BOP 6 (C) RO, CRS RCS leak inside Containment (TS) CRS 7 (C) RO, CRS CCW Leak 8 (M) ALL Reactor does not trip(ATWS) 9 (M) ALL LBLOCA 10 BOP Phase A valves FP-248/249/256/ and 258 fail to auto close 11 BOP Phase B valve CVC-381 fails to auto close
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 4
SUMMARY
DESCRIPTION The crew will assume the watch with the plant at 68% power. Maintaining current power level.
On cue from the Chief Examiner, Loop 1 Thot will fail low. The OAC will be alerted to this failure by APP-003-A4 alarming. The crew will respond IAW APP-003-A4 and remove the instrument from service using OWP-028, TDeltaT1. The CRS will enter LCO 3.3.1-1 items 5 & 6, Condition E for the failed instrument. Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
LCO 3.3.2-1 Items 1.f, 4.d, Condition D. Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. LCO 3.3.2-1 item 6b, Condition H. Verify interlock is in required stat for existing unit condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND be in Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. LCO 3.3.6-1 Item 4. This Item refers to LCO 3.3.2.
"ESFAS Instrumentation," Functions 1.a- f, for all initiation functions and requirements.
Reference LCO 3.4.2 RCS Minimum temperature for Criticallty. Crew determines all loop Tavg temperatures are greater than 530° F. When the Chief Examiner is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, C S/G PORV will fail open. The crew will enter AOP-025 Section I. The BOP will close the PORV by adjusting the controller potentiometer towards 0%
demand (raises the setpoint). The PORV control will be transferred to local control using and OWP-024 MS-4 will be implemented. The CRS will reference ITS 3.3.4, table B3.3.4-1 and determine that this specification is met by having the S/G safety valves operable.
When the Chief Examiner is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, PC-444Js pressure control band will shift causing pressure to not be kept in band(2220-2250 psig). The OAC will perform Immediate Actions of AOP-019, Malfunction of RCS Pressure Control. The OAC will take manual control of PC-444J and control pressure manually between 2220-2250psig. LCO 3.4.1 for RCS pressure <2223 psig (Standing Instruction 13-007) may be entered depending on how low pressure gets. Pressure will be controlled manually the rest of the scenario. When the Chief Examiner is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, Main Feedwater Pump B will trip. The BOP will perform Immediate Actions of AOP-010, Main Feedwater/Condensate Malfunction. While performing the remaining actions of AOP-010 the crew will determine that Reactor Power is required to be lowered to less than 60% Reactor Power. The crew will perform the load reduction in accordance with AOP-010 and OP-301, RCS Boration Quick Checklist. Once the Chief Examiner is satisfied with the crews actions to perform a controlled reduction in power and stabilize the plant, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, an RCS leak in Containment will occur. The leak will start out at 30 GPM and gradually ramp up to 50 GPM. The crew will enter AOP-016, Excessive Primary Plant Leakage, and take prescribed actions to mitigate the RCS leakage. ITS 3.4.13 RCS Operational Leakage, Condition A, will be entered due to unidentified leakage. Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Condition B equires that the plant be placed in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Once the crew has determined the leak rate and the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 On cue from the Chief Examiner, a non-isolable CCW leak will occur. This will require the crew to enter AOP-014, Component Cooling Water System Malfunction. The crew will try to make up to the CCW Surge Tank, however, the makeup will not overcome the amount leaking out. CCW surge tank will lower to <5% in which they will have a continuous action step to return to and trip the reactor. Upon initiating the reactor trip, the reactor will not trip(ATWS) and the crew will enter EOP-E-0, Reactor Trip or Safety Injection, and then transition immediately to FRP-S.1, Response to Nuclear Power Generation/ATWS. A LBLOCA will occur when the crew completes FRP-S.1. The crew will continue on with FRP-S.1 until it transitions them back to EOP-E-0 and then transition to EOP-E-1, Loss of Reactor Coolant or Secondary Coolant. Upon the LBLOCA, Phase A valves FP-249/249/256 and 258 will fail to auto close and have to be closed manually.
Phase B valve CVC-381 will fail to auto close and have to be closed manually. The crew will also enter FRP-P.1 due to the LBLOCA but will immediately exit due to the LOCA. AOP-014 is a concurrent AOP and an operator will be assigned to continue on with it once EOP-E-0 is complete.
Because there is no CCW available (due to the leak from before) the crew will have to transition from EOP-E-1 to EPP-15, Loss of Emergency Coolant Recirculation.
The Chief Examiner may terminate the scenario at any time after the crew has initiated makeup to the RWST.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Sat /
Critical Task Critical Task Criteria Unsat Insert Control Rods Insert Control Rods IAW FRP-S.1 prior to exiting Step 1 of FRP-S.1 Trip the Turbine Trip the Turbine IAW FRP-S.1 prior to exiting Step 2 of FRP-S.1 Emergency Borate Establish Emergency Boration IAW FRP S.1 prior to exiting Step 4 of FRP S.1 Isolate CV Phase A valves Isolate CV Phase A valves FP-248/249/256/258 IAW EOP-E-0 prior to announcing to the crew that Att 1 is complete Isolate CV Phase B valves Isolate CV Phase B valve CVC-381 IAW EOP-E-0 prior to completing step 9 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP:
IC-604, SCN 006_ILC_14_SIM_NRC_4 Status board is provided to crew is IC-17.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip or triggered events following the reactor trip:
Event 8: Reactor does not trip(ATWS)
Event 9: Large Break LOCA Event 10: Phase A valves FP-248/249/256/ and 258 fail to auto close Event 11 :Phase B valve CVC-381 fails to auto close EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
Event 1: Loop 1 Thot fails low Event 2: S/G 'C' PORV fails open Event 3: PC-444J pressure shift down Event 4: MFP 'B' Trip Event 5: Load reduction to <60% power Event 6: RCS leak in CV Event 7: CCW leak EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
OWP-028, TDeltaT1 AOP-025, RTGB Instrument Failure,Section I OWP-024 MS-4 AOP-019, Malfunction of RCS Pressure Control AOP-010, Main Feedwater/Condensate Malfunction OP-301, RCS Boration Quick Checklist AOP-016, Excessive Primary Plant Leakage AOP-014, Component Cooling Water System Malfunction EOP-E-0, Reactor Trip or Safety Injection FRP-S.1, Response to Nuclear Power Generation/ATWS FRP-P.1, Response to Imminent Pressurized Thermal Shock EOP-E-1, Loss of Reactor Coolant or Secondary Coolant EPP-15, Loss of Emergency Coolant Recirculation Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 1 Page 6 of 51 Event
Description:
Loop 1 Thot Fails Low. The crew will diagnose using APP-003 and remove the channel with OWP-028 Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 1, Loop 1 Thot fails low EVENT INDICATIONS:
APP-003-A4 APP-003-A6 App-003-B4 OBSERVATIONS
- 2. IF an instrument has failed, THEN REMOVE the malfunctioning Channel from Service using OWP-028 (T delta T).
APP-003 RO Diagnosis Loop 1 Thot has failed low Trip the following bistables:
Bistable Switch B/S 412B-1 Rack #1 Bistable Switch B/S 412B-2 Rack #1 OWP-028 BOP Bistable Switch B/S 412C-1 Rack #1 Bistable Switch B/S 412C-2 Rack #1 Bistable Light OT )T ROD STOP TC-412C2 Bistable Light LO TAVG TC-412E Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 1 Page 7 of 51 Event
Description:
Loop 1 Thot Fails Low. The crew will diagnose using APP-003 and remove the channel with OWP-028 Time Position Applicants Actions or Behavior Enter LCO 3.3.1-1 items 5 & 6, Condition E for the failed instrument.
Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
LCO 3.3.2-1 Items 1.f, 4.d, Condition D.
Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
LCO 3.3.2-1 item 6b, Condition H.
CRS Verify interlock is in required stat for existing unit condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND be in Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
LCO 3.3.6-1 Item 4.
This Item refers to LCO 3.3.2. "ESFAS Instrumentation,"
Functions 1.a- f, for all initiation functions and requirements.
Reference LCO 3.4.2 RCS Minimum temperature for Criticallty.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 2 Page 8 of 51 Event
Description:
S/G C PORV fails open. The crew will enter AOP-025.
Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #2, S/G C PORV fails open, on cue from the Chief Examiner.
EVENT INDICATIONS:
Steam noise Steam flow on C S/G rising Reactor power rising Tavg lowering PZR level lowering Charging Pump speed rising Determine IF Steam Line PORV(s) Should Be Closed
- a. Check Affected S/G Pressure - LESS Than PORV Opening Setpoint. )YES)
- b. Attempt To CLOSE The Affected Steam Line PORV From The RTGB By Adjusting The Affected PORV Controller (RV-1, RV-2 OR RV-3) Potentiometer Towards 0% Demand(Increases the Setpoint). (wiii not close)
AOP-025 RO Check Reactor Power - LESS THAN OR EQUAL TO 100% (YES)
AOP-025 BOP Make PA Announcement For Procedure Entry AOP-025 BOP Transfer The Affected Steam Line PORV Control (PIC-477 / PIC-487/
PIC-497) To The Local Controller using Attachment 3, Transfer Of Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 2 Page 9 of 51 Event
Description:
S/G C PORV fails open. The crew will enter AOP-025.
Time Position Applicants Actions or Behavior Steam Line PORV Control To Local BOOTH OPERATOR: When directed to transfer PORV to local control, wait 2 minutes and perform action. Report that action complete and no change in PORV position.
AOP-025 CRS Implement OWP-024, MS-4 For The Affected Steam Line PORV BOP directs an AO to perform PIC-477 Manual Thumbwheel (White)
OWP-024 BOP PORV RV-1 Switch PIC-477 Transfer Switch (Orange)
Reference ITS 3.3.4, table B 3.3.4-1 Item 3d for operability requirements of S/G pressure instrumentation and controls for Remote CRS Shutdown LCO is met. S/G safety valves are operable.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 3 Page 10 of 51 Event
Description:
PC-444J Pressure Shifts Down, The crew will enter AOP-019 Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #3, PC-444J pressure shift down, on cue from the Chief Examiner.
EVENT INDICATIONS:
RCS pressure lowering APP-003-D8 APP-003-F3 Immediate Action Step AOP-019 RO CHECK Both LTOPP Arming Switches Selected To NORMAL (YES)
Immediate Action Step Determine If PZR PORVs Should Be Closed:
- a. Check PZR pressure LESS THAN 2335 PSIG (YES)
- b. Verify Both PZR PORVs CLOSED (YES)
Immediate Action Step AOP-019 RO Control The Normal PZR Spray Valves AND PZR Heaters To Restore RCS Pressure To The Desired Control Band AOP-019 BOP Make PA Announcement For Procedure Entry Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 3 Page 11 of 51 Event
Description:
PC-444J Pressure Shifts Down, The crew will enter AOP-019 Time Position Applicants Actions or Behavior Continuous Action Step AOP-019 RO Check PZR Pressure UNDER OPERATOR CONTROL (YES)
Continuous Action Step Check Pressurizer Pressure Transmitter PT 444 OR PT 445 AOP-019 RO FAILED. (NO)
Go To Step 8 Check PC 444J, PZR PRESS OPERATING PROPERLY IN AUTO (NO)
Perform the following:
- a. Place PC 444J, PZR PRESS, in MAN.
- b. IF PC 444J is operating properly in manual, THEN Go To Step
- 10. (YES)
Operate PC 444J As Follows:
- a. Check PZR SPRAY VALVE Controllers IN AUTO (YES)
- b. Check PZR Heaters IN NORMAL CONFIGURATION (YES)
- c. Manually adjust PC 444J to maintain PZR pressure.
- d. Check PZR pressure UNDER CONTROL (YES)
- e. Go To Step 30 AOP-019 CRS Contact I&C To Make Repairs To The PZR Pressure Control System Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 3 Page 12 of 51 Event
Description:
PC-444J Pressure Shifts Down, The crew will enter AOP-019 Time Position Applicants Actions or Behavior Refer To ITS For Applicable LCOs LCO 3.4.11, PZR PORV TRM 3.4, PZR Spray T AOP-019 CRS LCO 3.4.4 AND 3.4.5, RCS Loops LCO 3.4.1, RCS Pressure LCO 3.4.9, PZR Level Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 13 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #4, MFW Pump B Trip, on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-007-A4 MFW Pump Indicating lights off Immediate Action Step Check Feedwater Regulating Valves - OPERATING PROPERLY (MANUAL OR AUTO): (YES)
AOP-010 BOP FCV-478, FRV "A" FCV-488, FRV "B" FCV-498, FRV "C" Continuous Action Step Immediate Action Step Check Reactor Trip Setpoint - BEING APPROACHED (NO)
AOP-010 RO IF a Reactor Trip Setpoint is approached, THEN trip the Reactor and Go To EOP-E-0, REACTOR TRIP or SAFETY INJECTION.
Go To Step 4.
AOP-010 BOP Make PA Announcement For Procedure Entry Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 14 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior Go To The Appropriate Step from The Table Below:
AOP-010 CRS Event Step MFW Pump trip Step 6 AOP-010 RO Check Reactor Power - LESS THAN 70% (YES)
AOP-010 RO Check Reactor Power - GREATER THAN 60% (YES)
NOTE Rapid power reductions may result in the axial flux difference exceeding the operating band values and require a power reduction to less than 50% to comply with ITS 3.2.3 Condition C.
Reduce Turbine Load At 1%/MIN To 5%/MIN To Achieve Less Than 60% Reactor Power As Follows:
- a. Verify Rods in AUTOMATIC (YES)
- b. Check Turbine Control Mode - AUTOMATIC (YES)
- 2) Set The Desired Load In The SETTER
- 3) Set The Desired Load Rate
- 4) Depress the GO Pushbutton or the HOLD Pushbutton as Necessary to Reduce Turbine Load
- c. Borate Per OP-301, RCS Boration Quick Checklist, as necessary to maintain AFD within the operating band Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 15 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior Go to step 13 Evaluator Note: OP-301 Steps are located at the end of this section Check Main Feed Pumps - AT LEAST ONE RUNNING (YES)
AOP-010 BOP Go to step 38 AOP-010 BOP Check S/G Level - AT OR TRENDING TO PROGRAM (YES)
AOP-010 RO Check Tavg - AT OR TRENDING TO Tref Contact Maintenance To Troubleshoot And Correct The Feedwater AOP-010 CRS Problem AOP-010 CRS Implement the EALs Check current loading for the following pumps - LESS THAN MAXIMUM o Main Feedwater Pump - 0.710KILOAMPS AOP-010 BOP o Condensate Pumps - 370 AMPS o Heater Drain Pumps - 90 AMPS Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 16 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed to check current loading, report Condensate pumps are 340 amps, HDPs are 70 amps, and MFP A is 650 amps.
Determine Iodine Sampling Requirements As Follows:
- a. Check Power Change - GREATER THAN 15% IN ONE HOUR AOP-010 CRS
- b. Implement ITS SR 3.4.16.2 c. NOTIFY E&C To Shutdown The RCS Zinc Injection System Check APP-005-B5, ROD BANKS A/B/C/D LO LIMIT -
Monitor Axial Flux Difference To Ensure Compliance With ITS AOP-010 RO 3.2.3 AOP-010 CRS Notify Load Dispatcher Of The Unit's Load Capability NOTE OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power.
DETERMINE the amount of Boric Acid to add to the RCS and RO OBTAIN an independent check of the volume required RO OBTAIN permission from the CRS OR the SM to borate.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 17 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior RO PLACE the RCS MAKEUP MODE selector switch to BORATE.
RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.
IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO AND manually ADJUST controller FCV-113A using the UP and DOWN pushbuttons.
RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.
IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
RO Rod Motion is blocked OR is in the wrong direction TAVG goes up Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:
FCV-113A, BORIC ACID FLOW, closes.
RO FCV-113B, BLENDED MU TO CHG SUCT, closes.
IF in Auto, THEN the operating Boric Acid Pump stops.
The RCS MAKEUP SYSTEM is OFF.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 18 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior IF desired, THEN FLUSH the Boric Acid flow path as follows:
PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.
SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons.
PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.
Momentarily PLACE the RCS MAKEUP SYSTEM switch to the START position.
IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
RO o Unanticipated Rod Motion o Primary Water addition reaches the desired value WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:
o FCV-114A closes.
o FCV-113B closes.
o IF in Auto, THEN the operating PW Pump stops.
o The RCS MAKEUP SYSTEM is OFF.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 4 Page 19 of 51 Event
Description:
MFW Pump B Trip. The crew will enter AOP-010 and reduce power to less than 60%.
Time Position Applicants Actions or Behavior RETURN the RCS Makeup System to automatic as follows:
VERIFY FCV-114A is in AUTO.
PLACE FCV-114B to the AUTO position.
RO PLACE the RCS MAKEUP MODE switch in AUTO.
VERIFY FCV-113A is in AUTO.
Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.
RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added during the boration.
MONITOR parameters for the expected change in reactivity AND inform the CRS OR the SM of the results of the boration.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 6 Page 20 of 51 Event
Description:
RCS leak inside of CV. The crew will enter AOP-016 Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #6, RCS Leak Inside CV, on cue from the Chief Examiner.
EVENT INDICATIONS:
Charging Pump speed rising R-11 indication rising RR-1 alarm for R-11 VCT level lowering CV parameters on ERFIS rising (CV Sump level, CV Pressure, and CV Temperature)
Continuous Action Step Check RCS Pressure - Greater than 1000 psig. (YES)
Check the following:
PZR Level - Less than 10% AND lowering in an uncontrolled manner (NO)
AOP-016 RO OR RCS Subcooling - Less than 35°F (NO)
RNO:
IF PZR Level can NOT be maintained greater than 10% OR Subcooling can NOT be maintained greater than 35°F, THEN trip the Reactor and Go to PATH-1.
AOP-016 BOP Make PA Announcement for Procedure Entry Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 6 Page 21 of 51 Event
Description:
RCS leak inside of CV. The crew will enter AOP-016 Time Position Applicants Actions or Behavior Continuous Action Step Check VCT Level - LESS THAN 12.5 INCHES (NO)
- IF VCT level lowers to less than 12.5 inches, THEN perform Step 5.
Go To Step 6 Check Charging Pump Status -LESS THAN TWO RUNNING (NO)
- Go To Step 11.
Place running Charging Pump Speed Controllers in MAN AND adjust AOP-016 RO output to maximum Check RCS Level - LOWERING IN AN UNCONTROLLED MANNER AOP-016 RO (NO)
AOP-016 RO Control Charging Flow To Maintain Desired RCS Level Monitor Leakage As Follows:
AOP-016 RO a. Check RCS Level - LOWERING IN AN UNCONTROLLED MANNER: (NO)
Go to step 22 Implement ITS LCO 3.4.13 AOP-016 CRS RCS Operational Leakage, Condition A, will be entered due to unidentified leakage.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 6 Page 22 of 51 Event
Description:
RCS leak inside of CV. The crew will enter AOP-016 Time Position Applicants Actions or Behavior Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Condition B, Required Action and associated Completion Time of Condition A not met.
Place the plant be placed in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
NOTIFY E&C To Shutdown The RCS Zinc Injection System AOP-016 BOP Check For Primary-To-Secondary Leakage As Indicated By One Or More Of The Following:
R-15, CONDENSER AIR EJECTOR GAS - RISING OR IN ALARM (NO)
OR AOP-016RI-19A, B OR C, STM GEN BLOW DN - RISING OR IN ALARM (NO)
AOP-016 BOP OR R-31A, B OR C, STEAMLINE RADIATION MONITOR -
RISING OR IN ALARM (NO)
OR Secondary chemistry sample results - INDICATE S/G TUBE LEAKAGE Go to step 26 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 6 Page 23 of 51 Event
Description:
RCS leak inside of CV. The crew will enter AOP-016 Time Position Applicants Actions or Behavior NOTE OST-051, Reactor Coolant System Leakage Evaluation, is the preferred method of leak rate determination if plant conditions permit.
Initiate Leak Rate Determination Using One Or More Of The Following Methods:
OST-051, Reactor Coolant System Leakage Evaluation OR OST-901, HVH Condensate Measuring System OR Charging versus letdown flow balance AOP-016 CRS Implement The EALs Check R-17, COMPONENT COOLING WATER RADIOACTIVE LIQUID - RISING OR IN ALARM (NO)
AOP-016 BOP Go to step 30 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 7/8 Page 24 of 51 Event
Description:
CCW Leak in CV. Leak will lower CCW Surge Tank level to less than 5%
which will require a reactor trip. The reactor will not trip and the crew will enter FRP-S.1 for an ATWS Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #7, CCW leak, on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-001A4 CCW Surge Tank level lowering (Indications on RTGB and ERFIS)
AOP-014 CRS Implement The EALs AOP-014 BOP Make PA Announcement For Procedure Entry NOTE A loss of inventory may be indicated by a report of leakage or lowering of surge tank level.
CCW Pump discharge pressure less than 78 psig will cause an alarm.
CCW low flow is defined as less than 2200 gal per pump CCW high temperature is defined as greater than 105°F or greater than 125°F if in Mode 3.
Go To Appropriate Section For Indicated Malfunction:
AOP-014 CRS Loss Of CCW Inventory Go To Section A Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 7/8 Page 25 of 51 Event
Description:
CCW Leak in CV. Leak will lower CCW Surge Tank level to less than 5%
which will require a reactor trip. The reactor will not trip and the crew will enter FRP-S.1 for an ATWS Time Position Applicants Actions or Behavior Continuous Action Step Determine If Pump Cavitation Is Occuring OR Imminent As Follows:
o Check Surge Tank Level - LESS THAN 5% (NO, but lowering rapidly)
AOP-014 RO OR o Check CCW Pump Discharge Pressure (Local) AND Flow
- WIDE OSCILLATIONS RNO:
IF CCW Surge Tank level lowers to less than 5% OR CCW Pump Cavitation occurs, THEN Go To Step 2.
Verify at the RTGB, Primary Water Makeup To CCW As Follows:
- a. Primary Water Pump - RUNNING b. CC-832, MAKEUP - OPEN Check CCW Surge Tank level (LI-614B) - STABLE OR RISING (NO)
AOP-014 RO Go to step 11 AOP-014 RO Start A Second Primary Water Pump Check CCW Surge Tank level (LI-614B) - LOWERING (YES)
AOP-014 RO Return to step 2 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 7/8 Page 26 of 51 Event
Description:
CCW Leak in CV. Leak will lower CCW Surge Tank level to less than 5%
which will require a reactor trip. The reactor will not trip and the crew will enter FRP-S.1 for an ATWS Time Position Applicants Actions or Behavior AOP-014 RO Check Reactor - CRITICAL (YES)
AOP-014 RO Verify Reactor - TRIPPED (NO)
- 1. Check Reactor Trip: (NO)
Reactor trip and bypass breakers - OPEN Rod position indicators - AT ZERO Rod Bottom lights - ILLUMINATED EOP-E-0 RO Neutron flux - LOWERING RNO:
Manually trip reactor.
IF reactor power is greater than or equal to 5% OR intermediate range SUR is positive, THEN Go To FRP-S.1, Response To NuclearPower Generation/ATWS, Step 1.
FRP S.1 Immediate Action:
Check Reactor Trip as Follows:
Reactor Trip Main AND BYP Breakers - Open (NO)
- a. Depress both Reactor Trip Pushbuttons
- b. IF Reactor Trip Breakers will NOT open, THEN perform the FRP-S.1 following:
- 1) Insert Control Rods Critical RO/CRS 2) Dispatch an Operator to the MG Set Room to trip Task the following breakers:
Reactor Trip Breakers A & B Generator A & B Circuit Breakers
- 3) Dispatch an Operator to 480V Busses 2B and 3 to trip the following breakers:
Rod Drive Motor Generator Set A & B Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 7/8 Page 27 of 51 Event
Description:
CCW Leak in CV. Leak will lower CCW Surge Tank level to less than 5%
which will require a reactor trip. The reactor will not trip and the crew will enter FRP-S.1 for an ATWS Time Position Applicants Actions or Behavior Immediate Action:
Check Turbine Trip as Follows:
Both Turbine Stop Valves - Closed (NO)
OR All Governor Valves - Closed (NO)
FRP-S.1 a. Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons. (YES)
Critical BOP/CRS
- b. IF Turbine will NOT trip, THEN run back Turbine at Task maximum rate until the Governor Valves are closed.
- c. IF Turbine can NOT be run back, THEN verify CLOSED the following:
o All MSIVs o All MSIV BYPs CRITICAL TASK: Ensure Control Rods Driving In and Turbine Manually Tripped.
FRP-S.1 BOP Verify All AFW Pumps - Running Initiate Emergency Boration of RCS as follows:
- a. Verify Charging Flowpath established as follows:
- 1. CVC-310B, Loop 2 Cold Leg CHG - Open FRP-S.1 2. HIC-121, Charging Flow Controller - Demand Signal at Critical RO 0%
Task
- b. Verify Two Charging pumps - Running at full speed
- c. Verify Boric Acid pump aligned for Blend - Running
- d. Verify from the RTGB MOV-350, BA to Charging pump suction
- Open Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 7/8 Page 28 of 51 Event
Description:
CCW Leak in CV. Leak will lower CCW Surge Tank level to less than 5%
which will require a reactor trip. The reactor will not trip and the crew will enter FRP-S.1 for an ATWS Time Position Applicants Actions or Behavior
- e. Check flow on FI-110, Boric Acid bypass flow - Flow Indicated (YES)
- f. Verify Charging Flow to RCS on FI-122A (YES)
CRITICAL TASK: Initiate Emergency Boration FRP-S.1 RO Check Containment Ventilation Isolation - Initiated (YES)
Continuous Action Step:
Check SI - Initiated (NO)
FRP-S.1 RO
- IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L, while continuing with this procedure.
- Go To Step 8 Check IF the following Trips Have Occurred:
FRP-S.1 RO/BOP a. Reactor Trip (YES)
- b. Turbine Trip (YES)
Continuous Action Step:
Check if Reactor is Subcritical:
- a. Check power range indication - Less Than 5% (YES)
FRP-S.1 RO
- b. Check Intermediate Range Indication - Negative SUR (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 7/8 Page 29 of 51 Event
Description:
CCW Leak in CV. Leak will lower CCW Surge Tank level to less than 5%
which will require a reactor trip. The reactor will not trip and the crew will enter FRP-S.1 for an ATWS Time Position Applicants Actions or Behavior
- c. Go To Step 23 Continuous Action Step:
FRP-S.1 RO Check ARPI - Less than Two Rods Stuck Out (YES)
Stop the RCS Boration
- a. Verify closed MOV-350, BA to Charging pump suction
- b. Verify Control Switch for Boric Acid pump aligned for blend in Auto.
- c. Check Emergency Boration - Performed using MOV-350 flowpath (YES)
- d. Notify Engineering to Evaluate the Following to Determine if RCP Seal Inspection is Required:
FRP-S.1 RO RCP Bearing temperatures No. 1 Seal Leakoff temperatures No. 1 Seal Leakoff flowrates
- e. Check Emergency Boration performed using RWST flowpath AND it is desired to align Charging pump suction to the VCT. (NO)
Go to Step 24.i
- i. Reduce Charging pump speed as desired.
Perform the following:
- b. Initiate Monitoring of Critical Safety Function Status Trees
- c. Return to procedure and Step in effect. (Return to EOP-E-0)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 30 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #9, LBLOCA, on cue from the Chief Examiner.
EXAMINERS NOTE: CSFST will turn Red for Integrity due to the LBLOCA. The procedure steps for this are shown after EOP-E-0 Attachment 1 NOTE: FOLDOUT for EOP-E-0 is in effect.
RCP Trip Criteria IF either condition listed below occurs, THEN trip all RCPs: (YES)
Containment Isolation Phase B - ACTUATED (YES)
OR BOTH of the following satisfied:
o SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW (YES, once SI-870A or B are opened.)
AND o RCS subcooling based on core exit TCs - LESS THAN 30°F [50°F] (YES, eventually)
Faulted S/G AFW Isolation Criteria IF both conditions listed below are met, EOP-E-0 RO/BOP Any S/G pressure is lowering in an uncontrolled manner OR has completely depressurized (NO)
AND Any S/G is NOT faulted (NO)
THEN perform the following:
- a. Reset SI.
- b. Close steam driven AFW pump discharge valve for faulted S/G(s):
o V2-14A (S/G A) o V2-14B (S/G B) o V2-14C (S/G C)
o V2-16A (S/G A) o V2-16B (S/G B) o V2-16C (S/G C)
- d. Perform Attachment 2, Deenergizing AFW Valves for Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 31 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior faulted S/G(s).
- e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [23%] in at least one S/G.
Evaluator Note: Crew may take early actions at this time to address items that did not function or operate as designed.
Isolate CV Phase A valves FP-248/249/256/258 Isolate CV Phase B valve CVC-381 Perform Attachment 1, Auto Action Verification, While continuing with EOP-E-0 BOP this procedure. (Should be assigned to BOP.) (Att. 1 steps are presented next followed by the remainder of EOP-E-0.)
Beginning of EOP-E-0 Attachment 1 Check ECCS Pumps Running:
Att. 1 BOP SI pumps - BOTH RUNNING (YES)
RHR pumps - BOTH RUNNING (YES)
Check ECCS Valves - PROPER EMERGENCY ALIGNMENT Att. 1 BOP (YES)
Check CCW Pumps - AT LEAST ONE RUNNING (YES, however, Att. 1 BOP there is no level. Pumps will be stopped and locked out in AOP-014)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 32 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Check Containment Isolation Phase A
- a. Phase A - Actuated (YES)
- b. Phase A valves - Closed (NO, FP-248/249/256/ and 258 are open)
Att. 1 RNO:
BOP Critical Task Manually close valve(s) as necessary
- c. Excess letdown - Isolated (YES)
CVC-387 - Closed (YES)
HIC-137 - at 0% DEMAND (YES)
CRITICAL TASK: Close Phase A Valves FP-248/249/256/258 Check Feedwater Isolation:
a) Main feed pumps - BOTH TRIPPED (YES) b) Main feedwater - ISOLATED Att. 1 BOP FRVs - Closed (YES)
Feedwater reg bypass valves - Closed (YES)
Feedwater header section valves - Closed (YES)
Check if Main Steamlines Should Be Isolated:
Att. 1 BOP a) Main steamline isolation - REQUIRED (YES)
Containment pressure - Greater than 10 psig (YES)
OR Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 33 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior High steam flow with: (NO) o S/G pressure - less than 614 psig OR o Tavg - less than 543°F Check MSIVs and MSIV bypass valves closed (YES)
Check Proper Service Water System Operation:
- a. SW pumps - All running (YES)
- b. SW booster pumps - Both running (YES)
Att. 1 BOP
Extinguished (YES)
Att. 1 BOP Check Both EDGs - Running (YES)
Check ECCS Flow:
- a. RCS pressure - less than 170 psig (YES)
- b. SI pumps- Flow Indicated (YES.)
Att. 1 BOP
- c. RCS pressure - less than 350 psig. (YES)
- d. RHR Pumps - flow indicated (YES, initially may not have flow. Pressure is lowering and flow will be established)
Att. 1 BOP Check CV Recirculation Fans - All Running (YES)
Check IVSW - Actuated (YES)
Att. 1 BOP PCV-1922A - Open (YES)
PCV-1922B - Open (YES)
Check CV ventilation isolation (YES)
Att. 1 BOP
- a. CV ventilation isolation valves - CLOSED (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 34 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Check control room ventilation - aligned for pressurization mode (YES)
HVA-1A or HVA-1B - Running (YES)
HVE Stopped (YES)
HVE-19A or HVE-19B - Running (YES)
Att. 1 BOP Control Room HVAC outside air damper A or B - Open (YES)
CR-D1A-SA - Closed (YES)
CR-D1B-SB - Closed (YES)
Att. 1 BOP Check DS Bus - Energized (YES)
Check Battery Chargers - Energized (YES)
Att. 1 BOP APP-036-D1 - Extinguished (YES)
APP-036-D2 - Extinguished (YES)
Att. 1 BOP Stop R-11/12 Sample Pump Att. 1 BOP Locally Reset and Load IACs as necessary (N/A)
Perform Crew Update to include the following:
Attachment Completion Manual Actions Taken (Opened FP-248/249/256/258 Att. 1 BOP valves)
Failed Equipment status.
SW status.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 35 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior End of EOP-E-0 Attachment 1 Beginning of FRP-P.1 Check CST Level - LESS THAN 10% (NO)
FRP-P.1 BOP Go to step 3 Determine If RCS Cooldown Is Due To A Large Break LOCA As Follows:
- a. Check both of the following conditions exist:
RCS pressure - LESS THAN 275 PSIG [350 PSIG]
(YES)
AND RHR flow on FI-605 - GREATER THAN 1200 GPM (YES)
- b. Reset SPDS AND return to procedure and step in effect End of FRP-P.1 Continuation of AOP-014 Lockout CCW Pumps As Follows:
AOP-014 RO/BOP
- a. Place AND hold all CCW Pump switches in STOP position Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 36 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior
- c. Release CCW Pump Switches
- d. Go To Step 13 Dispatch Operator To Perform Attachment 3, CCW Leak Search,While AOP-014 BOP Continuing With Procedure Determine If RHR Must Be Stopped As Follows:
- a. Check CCW Pumps - ALL STOPPED (YES)
AOP-014 BOP b. Check RHR Pump status - ANY PUMP RUNNING IN CORE COOLING MODE (NO)
RNO:
Observe the NOTE prior to Step 18 and Go To Step 18.
NOTE IF the location of the leak is known AND isolation is possible, THEN leak isolation may be commenced immediately.
Check CV For CCW Break Using Control Room Indications AsFollows:
- a. Monitor the following CV indications:
ERFIS CV SUMP LEVEL Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 37 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior CV WATER LEVEL (White Sump Lights)
LI-801, CHANNEL I CV WATER LEVEL LI-802, CHANNEL II CV WATER LEVEL RCP Abnormal Conditions
- b. Check CV - LOCATION OF CCW BREAK
- c. Inform personnel performing leak search that the leak location is in the CV Determine RCP Alarm Status:
ILLUMINATED (YES)
- b. Check ANY RCP BEARING HI TEMP Alarm - ILLUMINATED APP-001-B3 AOP-014 BOP OR APP-001-D3 OR APP-001-F3 Go to step 20 Check Reactor - CRITICAL (NO)
AOP-014 BOP Go to step 24 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 38 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Close The Following Valves To Isolate CCW To The RCPs:
CC-716A, CCW TO RCP ISO CC-716B, CCW TO RCP ISO AOP-014 BOP CC-730, BRG OUTLET ISO CC-735, THERM BAR OUT ISO FCV-626, THERM BAR FLOW CONT Determine If Charging Pump(s) Should Be Stopped As Follows:
- a. Check Charging Pumps - ANY PUMP RUNNING (YES)
- b. Check RCS temperature - (YES)
Establish Alternate Cooling To Charging Pumps As Follows:
- a. Stop ALL but one Charging Pump b. Raise the speed of the running Charging Pump to at least 75% Demand Signal
- c. Dispatch an operator to perform Attachment 1, Emergency Cooling To Charging Pumps Continuation of EOP-E-0 EOP-E-0 RO Check AFW Pumps - Running (YES, all started in FRP-S.1)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 39 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Check AFW Valves - Proper Emergency Alignment (YES)
AFW header discharge valves - Full Open AFW header section valves - Full Open EOP-E-0 RO Steam driven AFW pump discharge valves - Full open if pump is running.
Caution If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Check Total AFW Flow:
Reset SI EOP-E-0 RO Control feed flow to maintain NON-faulted S/Gs narrow range level - Between 8% and 50%.
Check total AFW flow- Greater than 300 gpm (YES)
Check CV Spray NOT Required:
EOP-E-0 a. CV pressure - Has remained less than 10 psig. (NO)
Critical RO Task RNO:
- a. Perform the following:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 40 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior
- 1) Check CV spray actuated. (YES)
- 2) Verify the following:
a) Both CV spray pumps are running.
b) CV spray pump discharge valves are open:
o SI-880A o SI-880B o SI-880C o SI-880D c) CV spray additive tank discharge valves are open:
o SI-845A o SI-845B d) Spray additive tank flow is approximately 12 gpm:
o Adjust SI-845C, SAT throttling valve, as necessary.
- 3) Verify Containment Isolation Phase B valves are closed.
(NO, CVC-381 open)
- 4) Stop all RCPs.
- 5) Observe CAUTION prior to Step 10 and Go To Step 10.
CRITICAL TASK: Close CVC-381. It did not close on the Phase B Check RCP Seal Cooling:
EOP-E-0 RO CCW flow to RCP thermal barriers - Normal (NO)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 41 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior o APP-001-C1 / D1 - Extinguished (NO)
OR Seal injection flow - Normal (YES) o Seal injection flow - Greater than 6 gpm per RCP OR o Thermal barrier Ps - Greater than 5 inches water.
Check RCS Temperature With NO RCPs running, RCS cold leg temperatures - Stable at or trending to 547°F (NO)
RNO: IF temperature is less then 547°F AND lowering then perform the following: (YES)
- a. Stop dumping steam EOP-E-0` RO b. IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:
o Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/G.
Check PZR PORVs and Spray Valves:
- a. PORVs - Closed (YES)
- b. Normal PZR spray valves - Closed (YES)
- c. Aux spray valve - Closed (YES)
Check If RCPs should be stopped:
EOP-E-0 RO a. RCPs - Any Running (NO, stopped per FOLDOUT)
RNO: Go to Step 14 Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs EOP-E-0 BOP o None lowering in an uncontrolled manner (YES) o None Completely depressurized (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 42 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Check If S/G Tubes Are Intact:
Secondary radiation monitors - HAVE REMAINED NORMAL (YES)
Condenser air ejector radiation (R-15)
S/G blowdown radiation (R-19s)
S/G steamline radiation (R-31s)
S/G levels - NONE RISING IN AN UNCONTROLLED MANNER RNO:
Reset SPDS and initiate monitoring of Critical Safety Functions Status Trees.
Go To EOP-E-1, Loss Of Reactor Or Secondary Coolant, Step 1.
Beginning of EOP-E-1, Loss of Reactor or Secondary Coolant NOTE FOLDOUT for EOP-E-1 is in effect.
Check If RCPs should be stopped:
EOP-E-1 RO a. RCPs - Any Running (NO, stopped per EOP-E-0 FOLDOUT)
RNO: Go to Step 2 Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs EOP-E-1 BOP o None lowering in an uncontrolled manner (YES) o None Completely depressurized (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 43 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Continuous Action Step Check Intact S/G Levels:
- a. Narrow range levels - Greater than 18% (YES)
- b. Control feed flow to maintain narrow range levels - between 8% AND 50%
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
EOP-E-1 RO Reset SI EOP-E-1 RO Reset Containment Isolation Phase A Check Secondary Radiation:
- a. Secondary radiation monitors - Have remained normal (YES) o R-15, R-19s, R-31s EOP-E-1 BOP b. Perform the following:
- 1) Request periodic activity samples of all S/Gs
- 2) Secondary sample results - Normal (When results available)
Check PZR PORVs and Block Valves:
- a. Power to block valves - Available (YES)
- b. PORVs - Closed (YES)
- c. Block valves - At least one open. (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 44 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Establish Instrument Air to CV:
- a. Check APP-002-F7 - Extinguished (YES)
- b. Reset IA PCV-1716
- c. Check IA PCV-1716 - OPEN (YES)
Check Power Supply to Charging Pumps - Offsite power available EOP-E-1 RO (YES)
Check if Charging Flow has been established:
- a. Charging pumps - At least one running. (YES)
- b. Establish desired charging flow:
o Start additional pump(s) as necessary o Adjust charging pump speed controllers as necessary to EOP-E-1 RO establish desired charging flow.
o Adjust HIC-121 as necessary to establish desired charging flow:
o Maintain seal injection flow - Between 6 gpm and 20 gpm per RCP unless seal injection isolated.
Check if SI flow should be terminated:
b.
Continuous Action Step Step 12: Check if Containment Spray should be stopped:
- a. Spray pump - Any running (YES)
- b. Containment pressure - Less than 4 psig (YES)
- c. Reset containment spray signal: Place Containment Spray key EOP-E-1 RO switch to OVRD/RESET and return to NORMAL
- d. Reset containment isolation Phase B
- e. Stop containment spray pumps
- f. Close CV Spray Pump Discharge Valves: SI-880A / B / C / D
- g. Close CV Spray Additive Tank Discharge Valves: SI-845A / B Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 45 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior CAUTION If RCS pressure lowers in an uncontrolled manner to less than 275 psig [350 psig], the RHR pumps must be manually restarted to supply water to the RCS.
Continuous Action Step Check if RHR Pumps Should be Stopped:
- a. Check RCS pressure:
o Pressure - Greater than 350 psig (NO, go to step 15)
Step 15: Check if Diesel Generators should be Stopped:
- b. EDG starting air annunciators - Extinguished (YES) o APP-010-B2 / B3
- c. Stop unloaded EDGs Initiate Evaluation of Plant Status:
- a. Check Cold leg recirculation capability:
Train A and Train B:
Crew determines that they do not have any CCW Pumps EOP-E-1 BOP RNO:
IF at least one train of cold leg recirculation capability can NOT be verified, THEN reset SPDS and Go To EPP-15, Loss Of Emergency Coolant Recirculation, Step 1.
Beginning of EPP-15 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 46 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Check Emergency Coolant Recirculation Capability -
RESTORED (NO)
EPP-15 CREW RNO:
Go to step 3 Reset SPDS AND Initiate Monitoring Critical Safety Function EPP-15 RO Status Trees Foldout Pages Are Not Applicable During Performance Of This EPP-15 CREW Procedure Check Suction Source To Any Of The Following Pumps -
LOST (NO)
RNO:
Go to step 7 EPP-15 RO SI Pumps RHR Pumps CV Spray Pumps Check Emergency Recirculation Equipment - AVAILABLE EPP-15 BOP USING SUPPLEMENT D (NO) CCW Pumps are not available Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 47 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Verify The Following CV RECIRC FANs - RUNNING HVH-1 EPP-15 RO HVH-2 HVH-3 HVH-4 Continuous Action Step Check RWST Level - LESS THAN 9% (NO)
EPP-15 RO RNO:
Go to step 11 Place The CONTAINMENT SPRAY Key Switch To The EPP-15 RO OVRD/RESET Position Determine CV Spray Pump Requirements
- a. Determine Number Of CV Spray Pumps Required Using the Following Table:
RWST CONTAINMENT CV RECIRC SPRAY EPP-15 RO FANS PUMPS LEVEL PRESSURE RUNNING REQUIRED
> 27% < 4 psig 0 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 48 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Check CV Spray Pumps Running - EQUAL TO NUMBER EPP-15 RO REQUIRED (YES)
Makeup To RWST Using Supplement P While Continuing With EPP-15 BOP This Procedure Begin Supplement P, Emergency Makeup To The RWST In the CCW Heat Exchanger Room, near the top of BAST "B",
open the following valves:
CVC-365A, BORIC ACID BLENDER TO RWST.
AND CVC-365B, BORIC ACID BLENDER TO RWST.
BOOTH OPERATOR: Acknowledge request. No action necessary Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 49 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Set Makeup Control POTs as follows:
- a. FCV-113A, Boric Acid Flow Controller at 10 turns on the POT (9.25 gpm Boric Acid flow)
- b. FCV-114A, Primary Wtr Flow Dilute Mode Controller to 4.9 turns on the POT (75 gpm PW flow)
RECORD RWST level, as indicated by LI-948 OR LI-969.
Place the RCS Makeup Mode Selector Switch in the BORATE position.
Set the total amount of Boric Acid to 5000 gal be used to blend to the RWST using the Boric Acid Totalizer, YIC-113 as follows:
- a. Depress BUTTON "A".
- b. Depress "CLR" BUTTON. c. Key in the 5000.0 gal.
Supple-RO ment P d. Depress the "ENT" BUTTON.
Place the control switch for FCV-113B,BLENDED MU TO CHG SUCT in the CLOSED position.
Place the control switch for FCV-114B, BLENDED MU TO VCT, in the CLOSED position.
Start one of the available Primary Water Pumps.
Place the RCS Makeup System Start/Stop switch in the START position.
Place FCV-114A, PW TO BLENDER, in the OPEN position.
PLACE the Primary Wtr Flow Dilute Mode Controller, FCV-114A, in MANUAL AND adjust the Primary Water flow rate to achieve 75 gpm.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 4 Event # 9 Page 50 of 51 Event
Description:
LBLOCA. Procedures used EOP-E-0, FRP-P.1 (will enter and immediately exit due to LBLOCA), AOP-014 is a concurrent AOP and will be given to the BOP to continue after EOP-E-0 Attachment 1 is complete, EOP-E-1, and then exit to EPP-15 due to no recirculation capability. Phase A valves FP-248/249/256/ and 258 fail to auto close and Phase B valve CVC-381 fails to auto close Time Position Applicants Actions or Behavior Adjust the POT for FCV-113A, Boric Acid Flow Controller, toachieve a flow rate of 9.25 gpm Boric Acid flow.
The Lead Examiner may terminate the scenario any time after makeup to the RWST is started.
Appendix D NUREG-1021, Rev. 9, Supp. 1
ILC-14 NRC SCENARIO 4 TURNOVER SHEET
- 1. INITIAL CONDITIONS a) Time in Core Life: EOL b) Reactor Power: 68%
c) Turbine Load: 503 MWe d) Boron Concentration: 128 ppm e) Rod Height: 158 CBD f) RCS Pressure: 2235 psig g) RCS Level: 42 %
h) Xenon: Equilibrium
- 2. TECHNICAL SPECIFICATION LCO ACTIONS STATEMENTS IN EFFECT T.S. # Description
- 3. CLEARANCES IN EFFECT a) None
- 4. CAUTION CAPS IN EFFECT a) None
- 5. PROTECTED EQUIPMENT a) None
- 6. DEGRADED EQUIPMENT a) None
- 7. SWITCHYARD ACCESS a) Unrestricted
- 8. PLANNED EVOLUTIONS a) Maintain current power level
- 9. TURNOVER INFORMATION a) None
- 10. REACTIVITY INFORMATION a) Review the OST-947 BOL/MOL/EOL charts for BA and PW additions
- 11. RISK a) GREEN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 5 Op Test No.: ILC-14 Examiners: Operators: CRS -
RO -
BOP -
Initial Conditions: 50% BOL, 150 MWD/MTU, 1337 PPM Boron B MFP OOS for shaft repair Turnover: Hold power at current value for B MFP repair Critical Task: Close FRVs IAW EOP-E-0 Attachment 1 criteria Close FW HDR Section Valves IAW EOP-E-0 Attachment 1 criteria Stop A MFP IAW EOP-E-0 Attachment 1 criteria Reduce feed flow to all S/Gs to 80-90 gpm IAW EPP-8 OR FRP-P.1 Event Malf. No. Event Type* Event No. Description (C) BOP, HVH-5A Trips with HVH-5B failure to Auto Start 1
CRS (C) RO, CRS RCP B # 1 Seal Failure 2
(TS) CRS (C) RO, CRS HVH-1 Service Water leak in Containment 3
(TS) CRS (C) RO, CRS Loss of IB- 3 4
(TS) CRS (C) BOP, Steam leak 72 header 5
CRS (N) BOP Down power AOP-038 6
(R) RO, CRS 7 (M) ALL Steam break 72 header 8 BOP FRVs fail to automatically close 9 BOP FW HDR Section Valves failed open 10 BOP A MFP fails to Auto trip 11 BOP MSIVs failed open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 5
SUMMARY
DESCRIPTION The crew will assume the watch with the plant at 50% RTP. They will maintain the current power level while repairs are being made to B MFP. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.
On cue from the Chief Examiner, HVH-5A, CRDM Cooling Fan, trips and HVH-5B fails to Auto-Start. The operator will verify the standby fan starts by manually starting HVH-5B from the RTGB in accordance with APP-010-A6, HVH-5A/B AIR FLOW LOST/OVLD. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, RCP B will experience a #1 Seal Failure. The crew will enter AOP-018, Reactor Coolant Pump Abnormal Conditions. The crew will perform Attachment 2, RCP #2 Seal Leak Rate Calculation , monitor RCP Seal parameters, and inform Engineering of seal leakage. CRS will review ITS 3.4.17, CVCS, 3.4.13, RCS Operational Leakage, 3.4.4/3.4.5/3.4.6, RCS Loops, and 3.6.3, CV Isolation Valves. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, HVH-1 will develop a Service Water leak in containment. The crew will diagnose this by a rise in Containment sump level. They will receive APP-002-A8, HVH-1 WTR OUTLET LO FLOW alarm. They will also receive APP-002-E2, HVH CONDENSATE COLL alarm. APP-002-E2 requires an operator to acknowledge the alarm on the CMS panel or ITS 3.4.15 will apply. APP-002-A8 has a caution that an HVH unit may be operated up to 15 minutes without cooling water to the fan motor without damage. The APP will stop the fan and isolate cooling water. ITS LCO 3.6.6 Condition C applies and requires returning to operable within 7 days. The crew may refer to AOP-022 but this AOP does not address this event. When the Chief Examine is satisfied with the crew actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, a loss of Instrument Bus #3 will occur due to the normal supply breaker on Inverter B trips. The crew will perform the immediate actions for the loss of Instrument Bus #3 IAW AOP-024, LOSS OF INSTRUMENT BUS. Once the cause of the loss of Instrument Bus #3 is determined the bus will be re-energized from its alternate power supply, MCC-8. Various automatic controllers will be returned to auto control. Rod control and Turbine control will be placed back in auto. The CRS will identify that ITS LCO 3.8.7, Condition A, is in effect while the normal supply breaker to Instrument Bus #3 is open. This LCO requires that the AC Instrument Bus Power Source be restored to Operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Additionally, ITS LCO 3.8.9, Condition B, was in effect while Instrument Bus #3 was de-energized. This LCO requires that the AC instrument bus subsystem be restored to Operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ITS LCO 3.4.9, Condition A may be entered if pressurizer level is allowed to rise above 63.3%.
The LCO requires that the plant be in Mode 3 with reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ITS LCO 3.4.1, Condition A may be entered if pressurizer pressure is allowed to lower below 2223 psig (Standing Instruction 13-007). This LCO requires that pressurizer pressure be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in Mode 2 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
On cue from the Chief Examiner, a steam leak will develop on the 72 header. The crew will commence a unit shutdown IAW GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN OR AOP-038, RAPID DOWNPOWER. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 On cue from the Chief Examiner, the plant will experience a fault on the 72 inch Main Steam Header. The crew will determine that a reactor trip is required and transition to EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. An automatic safety injection signal will be initiated due to high steam line flow with low Tavg. A steam explosion on the 72 header has damaged the MSIVs and they will fail to automatically close and cannot be manually closed. On the safety injection the FRVs will fail to automatically close and EOP-E-0 Attachment 1 will direct these valves to be closed manually. EOP-E-0 will direct entry to EOP-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 2 of EOP-E-2 will direct entry to EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS. EPP-16 will isolate all S/Gs. The crew will throttle AFW flow to each S/G to 80-90 gpm. This will cause CSF for Heat Sink to turn red.
The crew will enter FRP-H.1 and transition back to procedure and step in effect due to the red path being caused by operator action. The crew will transition to FRP-P.1, Response to Imminent Pressurized Thermal Shock. This procedure also throttles AFW flow to a minimum of 80 gpm to each S/G so if the crew transitions to FRP-P.1 prior to throttling flow in EPP-16 it will still get done.
The Chief Examiner may terminate the scenario at any time after the SI pumps have been secured in FRP-P.1.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 Sat /
Critical Task Critical Task Criteria Unsat Manually trip MFP A Manually trip Main Feed Pump A IAW EOP-E-0, prior to exiting Step 5 of EOP-E-0, Attachment 1.
Manually close Main FW Close Main Feedwater Isolation Valves IAW Isolation Valves, The Feed EOP-E-0, prior to exiting Step 5 of EOP-E-0, Reg valves and the Header Attachment 1. Main Feedwater Regulating Section Valves Valves, Main Feedwater Regulating Bypass Valves, and Main Feedwater Header Section Valves.
Reduce Feed Flow to all Reduce Feed Flow to all S/Gs prior to exiting S/Gs to 80-90 gpm IAW step 6 of FRP-P.1 EPP-8 OR FRP-P.1 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Scenario Outline Form ES-D-1 ILC-14 NRC SCENARIO 5 SIMULATOR SETUP IC/SETUP:
IC-605, SCN 006_ILC_14_SIM_NRC_5 Status board is provided to crew is IC-20.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip or triggered events following the reactor trip:
Event 7: Steam break 72 header Event 8: FRVs fail to automatically close Event 9: FW HDR Section Valves failed open Event 10: A MFP fails to Auto trip Event 11: MSIVs failed open EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
Event 1: HVH-5A Trips with HVH-5B failure to Auto Start Event 2: RCP 'B' #1 Seal Failure Event 3: HVH-1 SW Leak in CV Event 4: Loss of IB-3 Event 5: 72" Header Leak Event 6: AOP-038 Down Power EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
APP-010-A6, HVH-5A/B AIR FLOW LOST/OVLD AOP-018, Reactor Coolant Pump Abnormal Conditions APP-002-A8, HVH-1 WTR OUTLET LO FLOW APP-002-E2, HVH CONDENSATE COLL AOP-024, LOSS OF INSTRUMENT BUS GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN AOP-038, RAPID DOWNPOWER EOP-E-0, REACTOR TRIP OR SAFETY INJECTION EOP-E-2, FAULTED STEAM GENERATOR ISOLATION EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 1 Page 6 of 50 Event
Description:
HVH-5B Trips with no Auto Start of HVH-5B Time Position Applicants Actions or Behavior BOOTH OPERATOR: : Insert Event #1, HVH-5A trips with no auto start of HVH-5B.
EVENT INDICATIONS:
APP-010-A6 HVH-5A/B AIR FLOW LOST/OVLD - Illuminated APP-009-E7 480V GRD FAULT - Illuminated Reviews APP-010-A6 CAUSES: 1. HVH-5A/B supply breaker open / tripped.
APP-010 (MCC-5(5M) / MCC-5(4M)
BOP 2. HVH-5A/B control power fuse blown.
- 3. HVH-5A/B low flow with associated fan running.
- 4. HVH-5A/B magnetic or thermal overload tripped.
- 5. Single-phase open circuit condition.
NOTE Voltage less than 440 Volts may indicate a single-phase open circuit.[C5]
- 1. EVALUATE CRDM indicating lights to determine affected fan:
- HVH-5A, CRDM COOLING FAN
- HVH-5B, CRDM COOLING FAN
- 2. MONITOR the following ERFIS points to determine if a single-phase APP-010 BOP open circuit is present:
- ERFIS point ELV3020A, BUS E1 VOLTAGE
- ERFIS point ELV3021A, BUS E2 VOLTAGE
- 3. IF a single-phase open circuit condition is suspected, THEN GO TO AOP-026, Grid Instability Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 1 Page 7 of 50 Event
Description:
HVH-5B Trips with no Auto Start of HVH-5B Time Position Applicants Actions or Behavior
- 5. DISPATCH Operator to evaluate affected CRDM COOLING FAN supply breaker status:
- Breaker MCC-5(5M), CONTROL ROD DRIVE MECHANISM COOLING FAN, HVH-5A
- Breaker MCC-6(4M), CONTROL ROD DRIVE MECHANISM COOLING FAN, HVH-5B BOOTH OPERATOR: When requested to inspect MCC-5 breaker for HVH-5A wait 3 minutes and report no abnormal indications at the breaker other than being tripped Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 2 Page 8 of 50 Event
Description:
RCP B #1 Seal Failure Time Position Applicants Actions or Behavior BOOTH OPERATOR: : Insert Event #2, RCP B #1 Seal Failure, cue from the Chief Examiner.
EVENT INDICATIONS:
APP-001-D2 RCP #1 SEAL LEAKOFF HI FLOW - Illuminated FR-154A WR Seal Leakoff Flow, A rising, B&C lowering FR-124 Seal Injection Flow, A rising Reviews APP-001-D2 CAUSE
AOP-018 BOP MAKE PA Announcement For Procedure Entry NOTE The RCP malfunctions in the Table below are listed in order of priority g implementation of EPP-1, Loss Of All AC OR any of its recovery procedures EVALUATE Plant Conditions AND Go To The Appropriate Section For RO/CRS RCP Malfunction Not Yet Addressed:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 2 Page 9 of 50 Event
Description:
RCP B #1 Seal Failure Time Position Applicants Actions or Behavior MALFUNCTION SECTION AOP-018 Reactor Coolant Pump Seal Section A Failure High Reactor Coolant Pump Section B Vibration Loss of Seal Injection Section C Continuous Action Step AOP-018 CHECK Any RCP #1 Seal Leakoff Flow - GREATER THAN 5.7 GPM RO (NO)
GO TO Step 10 Continuous Action Step CHECK Indicated RCP #1 Seal Leakoff Flow - LESS THAN 0.8 GPM AOP-018 RO (NO)
OBSERVE the NOTE prior to Step 16 AND GO TO Step 16 NOTE leak rate calculations assume negligible #2 Seal leakage prior to event Determine total RCP #1 seal flow rate as follows:
- 2 Seal Leakoff Flow from Attachment 2 for total RCP #1 Seal Leakoff AOP-018 Flow Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 2 Page 10 of 50 Event
Description:
RCP B #1 Seal Failure Time Position Applicants Actions or Behavior
_____5.27____ + ____.14______ = __5.41___
INDICATED CALCULATED TOTAL AOP-018 Attachment 2 NOTE RCDT level can be obtained from ERFIS point WDL5601A, ERFIS plot QP RCDT, or locally at LI-1003 The initial leak rate determination calculation can be calculated with only 5 minute trend data.
More data trending may be performed if desired. The same initial level may be used multiple times as long as the RCDT has not been pumped MONITOR RCDT level at 5 MINUTE intervals AND RECORD below RECORD RCDT level below:
Att 2 RO FORMULA FOR FLOW RATE CALCULATION IN STEP 3 Time RCDT level RCDT level RCDT
(%) start (%) stop (Start/Stop) level
/ 30 30.1 0.1 PERFORM the following to determine #2 Seal leak rate:
- a. SUBTRACT the START LEVEL from the STOP LEVEL.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 2 Page 11 of 50 Event
Description:
RCP B #1 Seal Failure Time Position Applicants Actions or Behavior
_____30.1_____ - _____30______ = ___0.1_____
Att 2
____0.1___ X 3.5 = ____.35____
GALLONS
- c. DIVIDE GALLONS by elapsed time to obtain leak rate.
___.35 5___ = ____.07_____ gpm GALLONS TIME LEAK RATE Att 2 BOP NOTIFY the CRS of LEAK RATE value obtained in Step 3 End Attachment 2 Continuous Action Step AOP-018 RO CHECK Total RCP #1 Seal Flow - GREATER THAN 8.0 GPM (NO)
Go to step 19 CHECK RCP #2 Seal Problem - Suspected (NO)
RO AOP-018 Go to step 24 CHECK Affected RCP #1 Seal Leakoff Flow - LESS THAN 5 GPM (NO)
AOP-018 RO PERFORM The Following:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 2 Page 12 of 50 Event
Description:
RCP B #1 Seal Failure Time Position Applicants Actions or Behavior
- a. Closely MONITOR RCP Seal parameters.
- b. NOTIFY Engineering of RCP Seal condition AND DIRECT them to contact Westinghouse for further instructions.
- c. REVIEW OP-101, Reactor Coolant System and Reactor Coolant Pump Startup and Operation, Precautions and Limitations relating to RCP Number 1 Seal Leakoff Flow and take appropriate actions.
- d. MAINTAIN Seal Injection flow between 8 gpm and 13 gpm.
- e. GO TO Step 41.
AOP-018 RO IMPLEMENT The EALs REFER TO Technical Specifications For Any Applicable LCOs 3.4.17 - CVCS AOP-018 CRS 3.4.13 - RCS Operational Leakage 3.4.4, 3.4.5, & 3.4.6 - RCS Loops 3.6.3 - CV Isolation Valves Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 3 Page 13 of 50 Event
Description:
HVH-1 Service Water Leak in CV Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #3, HVH-1 Service Water Leak in CV, on cue from the Chief Examiner.
EVENT INDICATIONS:
APP-002-E2 HVH Condensate Coll APP-002-A8 HVH-1 WTR Outlet Lo Flow ERFIS indication of CV sump level rising Reviews APP-002-E2 CAUSES: 1. RCS leakage to CV atmosphere.
- 2. Steam leakage to CV atmosphere.
- 3. SW leakage in HVH unit housings. (YES)
APP-002-E2
- 4. Clogged HVH drain lines to sump.
- 5. Performance of OST-901 (expected alarm)
NOTE When an alarm is received on the local Condensate Collection Panel and is acknowledged, another alarm from a different HVH Unit will cause the RTGB annunciator to reflash.
Per ITS 3.4.15 Basis, operability of CMS includes the HVH condensate collection alarm function on the RTGB. Therefore, if the local alarm is NOT promptly acknowledged to allow reflash capability for the RTGB annunciator, the ability to monitor RCS leakage from the Control Room via the CMS alarm is lost and may require placing the plant in a REQUIRED ACTION STATEMENT in accordance with ITS LCO 3.4.15 with the plant in Modes 1, 2, 3, or 4. (NCR 219670)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 3 Page 14 of 50 Event
Description:
HVH-1 Service Water Leak in CV Time Position Applicants Actions or Behavior OPERATOR ACTIONS APP-002- RO E2 Determine the source of water, from available indications or CV entry Reviews APP-002-A8 CAUSES: 1. Operating Service Water Booster Pump Tripped
- 2. V6-33A (SW Booster Pump 'A' Supply to HVH-1), closed or other service water valves misaligned.
- 3. Standby Service Water Booster Pump Check Valve Stuck Open.
APP-002- RO A8 4. Service Water System Leak.
OBSERVATIONS
- 1. Service Water Booster Pump Status Lights on RTGB.
- 2. V6-33A (SW Booster Pump 'A' Supply to HVH-1) position indication.
- 3. Service Water Header Pressure, PI-1616 (North) and PI-1684 (South).
CAUTION HVH Units may be operated up to 15 minutes without cooling water to the fan motor.
Continuous operation of the HVH Unit fan motor without cooling water may result in motor damage. (ESR 95-00700)
OPERATOR ACTIONS
APP-002- a. Stop the affected HVH Unit and remove the control power fuses.
RO A8
- b. Close the affected HVH Unit inlet and outlet valves:
HVH-1 V6-33A - SW INLET V6-34A - SW OUTLET Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 3 Page 15 of 50 Event
Description:
HVH-1 Service Water Leak in CV Time Position Applicants Actions or Behavior V6-35A - WTR SAMPLING APP-002-CRS Declare the affected HVH Unit inoperable and apply ITS LCO 3.6.6 A8 BOOTH OPERATOR: If requested to check flow, wait 2 minutes and report HVH-1 flow is 500 gpm Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 16 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #4, Loss of IB 3, on cue from the Chief Examiner.
EVENT INDICATIONS:
S/G C FRV shifts to manual Loss of indication on Bistable Status Panel A PR NI indication fails to zero Numerous alarms AOP-024, Loss of Instrument Bus Immediate Action Steps AOP-024 RO Place The Main Turbine in Manual Verify S/G(s) Maintained At Program Level Place Rods in M (Manual)
AOP-024 RO Maintain Reactor Power Less Than OR Equal To 100%
Continuous Action Step AOP-024 Determine if RCS Makeup needs to be stopped:
Check Auto Makeup, Boration OR Dilution - in progress (NO)
RO OR Check IB 2 AND IB 7 De-energized (NO)
Go to step 7 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 17 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior Control PZR Heaters And Sprays To Restore RCS Pressure To The AOP-024 RO Desired Control Band BOP Make PA Announcement For Procedure Entry AOP-024 AOP-024 RO Control Charging And Letdown Flow To Maintain PZR Level CAUTION Maintain Charging Pump Discharge Pressure less than 2500 psig while adjusting seal injection flow to prevent lifting Charging Pump Discharge Relief valves NOTE Flow recorder FR-124, Seal Injection, will NOT be available if Instrument Bus 2 is not available AOP-024 RO Check RCP Seal Injection Flow Between 8 GPM and 13 GPM (YES)
Determine Failed Instrument Bus (IB) From Any Of The Following:
AOP-024 Available indications OR BOP Table Below IB Indication to check 3 FR-498, "C" S/G Level Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 18 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior BOOTH OPERATOR: When dispatched to check the IB-3 breaker wait 4 minutes and then report that a person was cleaning in the area and bumped the normal supply breaker Continuous Action Step AOP-024 BOP Check Emergency Busses E-1 AND E energized from the 4160V busses (YES)
Continuous Action Step Check affected IB - energized (NO)
AOP-024 BOP WHEN affected Instrument Bus is Energized, THEN observe the NOTE prior to Step 14 and perform Step 14 Go To Step 15.
NOTE When a manual/auto control station is reenergized, 15 to 20 sec. is needed for the AUTO light to go out and the manual/auto station to revert to the manual mode Step 14 Restore Affected Controllers On The RTGB To AUTO Mode As Follows:
- a. Check the affected controller - REVERTED TO MANUAL
- b. Depress and release the AUTO pushbutton on the affected controller.
RO Check LCV-460A & B, LTDN LINE STOP - CLOSED (NO)
AOP-024 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 19 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior Go to step 19 NOTE IF the cause for the loss of Instrument Bus is known or is not due to a fault or suspected damage, THEN one attempt to reset and close the open breaker in the Instrument Bus Normal Supply should be attempted MCC-8 may only carry one Instrument Bus unless needed for nuclear safety concerns Check affected IB energized (NO)
AOP-024 IF the cause is known OR NOT a fault OR suspected damage, THEN RO attempt to reset and close the open Instrument Bus normal supply breaker AOP-024 BOP Stop All Radioactive Batch Releases AOP-024 Check Status Of Local Actions:
- a. Check Local Actions Of Step 19 RNO - REQUIRED (YES)
- b. Check Local Actions Of Step 19 RNO - ATTEMPTED (YES)
AOP-024 RO Check affected IB energized (YES)
Restore RCS Makeup Control To AUTO RO
- a. Place the RCS MAKEUP SYSTEM Switch in STOP AOP-024 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 20 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior
- b. Verify the RCS MAKEUP MODE Switch in AUTO
- c. Momentarily place the RCS MAKEUP SYSTEM Switch to START Restore Rod Control To Automatic As Follows:
- a. Check Power - GREATER THAN 15% (YES)
AOP-024 RO b. Check Automatic Rod Control - available (YES)
- c. Check Tavg - WITHIN - 1.5 to + 1.5 °F of Tref (YES)
- d. Place the Rod Control selector switch to A (Automatic)
AOP-024 BOP Check Emergency Busses E-1 AND E-2 energized (YES)
AOP-024 Check Emergency Busses E-1 AND E-2 energized from their 4160V BOP busses (YES)
AOP-024 CRS Implement the EALs AOP-024 RO Check status of IB-4 energized (YES)
AOP-024 BOP Place Turbine Controls in Automatic Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 21 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior Determine CCW Pump status as follows:
AOP-024 RO Check CCW Pumps - MORE THAN ONE RUNNING (NO)
Go to step 31 AOP-024 RO Check RMS-1, RMS-2, RMS-3, AND RMS ALL OPEN (YES)
AOP-024 RO Check affected IB energized (YES)
AOP-024 RO Check PZR heater status - de-energized (NO)
AOP-024 RO Check Normal Letdown - ISOLATED Check All Radiation Monitor Alarms - EXTINGUISHED (NO)
Reset Radiation Monitor alarms that are illuminated due to loss of Instrument Bus as follows:
For RMS 1-12, 15-18, 20-31, OR 33, momentarily depress AOP-024 BOP ALARM/RESET Pushbutton For RMS 14 OR 19, contact E&C personnel to reset the monitor(s)
For RMS-32, momentarily depress SAFE/RESET Pushbutton Check R-11 OR R in service (YES)
BOP RMS-1, RMS-2, RMS-3, and RMS OPEN AOP-024 AND Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 22 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior R-11 and R-12 Vacuum Pump Operating Check R-20, Fuel Handling Bldg Lower Level Low Range - in service (YES)
AOP-024 BOP Check R-21, Fuel Handling Bldg Upper Level Low Range - in service (YES)
Check Control Room Ventilation - aligned for pressurization mode AOP-024 BOP (NO)
Go to step 43 Check PZR PRV Safety Acoustic Monitor Lights - illuminated (NO)
AOP-024 RO Go to step 45 AOP-024 RO Check IBs 1-4 energized from their normal source (YES)
Check status of EDGs - start signal received (NO)
AOP-024 BOP Go to step 65 AOP-024 BOP Check all safety related electrical busses energized (YES)
Check Technical Specifications For Applicable LCOs ITS LCO 3.8.1, AC Sources - Operating AOP-024 CRS ITS LCO 3.8.7, AC Instrument Bus Sources - Operating ITS LCO 3.8.9, Distribution Systems - Operating Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 4 Page 23 of 50 Event
Description:
Loss of IB 3 Time Position Applicants Actions or Behavior Check Annunciator APP-005-A3, PR DROP ROD - ILLUMINATED AOP-024 RO (YES)
Reset Dropped Rod Alarm By Performing The Following:
- b. Place DROPPED ROD MODE switch for the affected Power RangeDrawer to NORMAL Position
- c. Check Annunciator APP-005-A3, PR DROP ROD -
EXTINGUISHED (YES)
Check APP-006-F5, STEAM DUMP ARMED - ILLUMINATED (NO)
AOP-024 BOP Go to step 71 AOP-024 RO Check APP-006-F5, Steam Dump Armed - Illuminated (YES)
Reset AMSAC TROUB/BYPD Alarm By Depressing The SYSTEM AOP-024 RO RESET Pushbutton On AMSAC Front Panel BOOTH OPERATOR: When contacted wait 3 minutes and then reset AMSAC Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 5/6 Page 24 of 50 Event
Description:
Steam Leak on 72 Header Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #5, Steam Leak on 72 Header, on cue from the Chief Examiner.
EVENT INDICATIONS:
Steam noise is heard in the Control Room Steam flow indication has risen on all S/Gs on flow recorder Tavg lowers BOOTH OPERATOR: When requested to investigate steam leak, wait 2 minutes and report steam coming from the 72 header Call Operations management to inform them of steam leak and that CRS the unit will be shutdown BOOTH OPERATOR: If the CRS does not call Operations management then call them and let them know that you heard steam noise and saw steam rising from the Turbine deck. If they discuss shutting the unit down using GP-006-1 prompt them to use AOP-038 in case the leak gets worse.
NOTIFY Plant Personnel Of Procedure Entry Using The Plant Page AOP-038 BOP System DETERMINE Corrected Boration And Target Rod Height For Target AOP-038 BOP Power Level Using Most Recently Performed OST-947, OPERATIONS REACTIVITY PLAN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 5/6 Page 25 of 50 Event
Description:
Steam Leak on 72 Header Time Position Applicants Actions or Behavior o Target Load Reduction Rate
________ %/min o Target Power Level ________
o Target Rod Height _________ Steps o Corrected Boration _________ Gallons PERFORM Brief Of Control Room Personnel To Include The Following:
Reason for downpower Target Power Level AOP-038 CRS Target Rod Height Rate of load reduction Amount of boric acid addition Continuous Action Step AOP-038 CRS CHECK Required Power Reduction Rate - LESS THAN OR EQUAL to 5%/MINUTE (YES)
ENERGIZE All Available PZR Heaters PZR HTR CONTROL GROUP AOP-038 RO PZR HTR BACK-UP GROUP A PZR HTR BACK-UP GROUP B AOP-038 RO Check Rod Control - in auto (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 5/6 Page 26 of 50 Event
Description:
Steam Leak on 72 Header Time Position Applicants Actions or Behavior INITIATE Boration Using Attachment 1, RCS Boration, While AOP-038 RO Continuing With This Procedure AOP-038 Attachment 1 RCS Boration Att 1 RO PLACE The RCS MAKEUP MODE Selector Switch In BORATE IF Frequent Boric Acid Transfer Pump Starts Are Anticipated, THEN Att 1 RO PLACE Boric Acid Transfer Pump Switch Aligned To BLEND To ON NOTE When the potentiometer setting for FCV-113A exceeds 9.0, FR-113 should be monitored closely. Based on system design characteristics, an indicated flow of 10 gpm may be greater than 10 gpm (actual) boric acid flow. This is past the range of indication available on FR-113.
Due to RCS leak rates, batch additions may NOT be possible. FCV-113A, BORIC ACID FLOW, may be adjusted to compensate for RCS leakage.
Att 1 SET YIC-113, BORIC ACID TOTALIZER to amount determined in RO Main Body Step 2 Att 1 RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START Continuous Action Step Att 1 RO IF Boric Acid flow is NOT achieving the desired effect, THEN PLACE Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 5/6 Page 27 of 50 Event
Description:
Steam Leak on 72 Header Time Position Applicants Actions or Behavior FCV-113A, BORIC ACID FLOW, in MAN AND manually Adjust controller FCV-113A, BORIC ACID FLOW, using the UP and DOWN pushbuttons WHEN the desired amount of Boric Acid has been added to the RCS OR the RCS MAKEUP SYSTEM Switch is placed in STOP, THEN VERIFY the following:
- a. FCV-113A, BA TO BLENDER, closes.
Att 1 RO
- b. FCV-113B, BLENDED MU TO CHG SUCT, closes.
- c. IF in AUTO, THEN operating Boric Acid Pump stops.
- d. RCS MAKEUP SYSTEM is OFF WHEN all Boric Acid additions are complete, THEN FLUSH the Boric Acid flow as follows:
- b. SET YIC-114, PRIMARY WTR TOTALIZER, to 15 to 20 gallons.
- c. PLACE FCV-114B, BLENDED MU TO VCT, to CLOSE
- d. Momentarily PLACE the RCS MAKEUP SYSTEM switch to START Att 1 RO e. WHEN the Primary Water addition is complete, THEN VERIFY the following:
FCV-114A, PW TO BLENDER, closes FCV-113B, BLENDED MU TO CHG SUCT, closes IF in AUTO, THEN operating Primary Water Pump stops RCS MAKEUP SYSTEM is OFF Att 1 RO RETURN the RCS Makeup System to automatic as follows:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 5/6 Page 28 of 50 Event
Description:
Steam Leak on 72 Header Time Position Applicants Actions or Behavior
- a. VERIFY FCV-114A, PRIMARY WTR FLOW DILUTE MODE, is in AUTO.
- b. PLACE FCV-114B, BLENDED MU TO VCT, in AUTO.
- c. PLACE the RCS MAKEUP MODE switch in AUTO.
- d. VERIFY FCV-113A, BORIC ACID FLOW, in AUTO.
- e. VERIFY Primary Water Pump switch in AUTO.
- f. VERIFY Boric Acid Transfer Pump switch aligned to BLEND in AUTO.
- g. Momentarily PLACE the RCS MAKEUP SYSTEM switch to START RECORD in AUTO LOG the total amount of Primary Water and Boric Att 1 RO Acid added during the boration End of Attachment 1 INITIATE Turbine Load Reduction While Continuing With This Procedure
- a. CHECK EH Turbine Control - IN OPER AUTO
- b. PREPARE For Turbine Load Reduction As Follows:
- 1) CHECK IMP IN - ILLUMINATED
- 2) SET desired load in the SETTER
- 3) SELECT the desired Load Rate
- c. DEPRESS the GO pushbutton to initiate Turbine Load reduction Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 5/6 Page 29 of 50 Event
Description:
Steam Leak on 72 Header Time Position Applicants Actions or Behavior ADJUST Turbine Load To Control One Of The Following:
ADJUST Load Rate AOP-038 BOP OR DEPRESS GO and HOLD pushbuttons INITIATE Notifications Load Dispatcher of load reduction E&C to control secondary chemistry RC for elevated radiation levels in CV Pump Bays and Pipe Alley AOP-038 CRS On-call Duty Manager to activate the Event Response Team E&C for impending 15% power change for I-131 sampling within 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> E&C for impending power reduction greater than 20%
terminate zinc injection NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 30 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior BOOTH OPERATOR: Insert Event #7, Steam Break on 72 Header, on cue from the Chief Examiner.
EVENT INDICATIONS:
Steam noise gets louder PZR level and pressure lowering rapidly RCS temperature lowering EOP-E-0, Reactor Trip or Safety Injection Immediate Action Steps EOP-E-0 RO Check Reactor tripped (YES)
Immediate Action Steps Check Turbine Trip:
- a. Both turbine stop valves - Closed (YES)
- b. All MSR purge and shutoff valves - Closed (YES)
Immediate Action Steps EOP-E-0 BOP Check Power to AC Emergency Busses:
- a. E1 or E2 - At least one energized (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 31 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior
- b. E1 and E2 - Both energized (YES)
Immediate Action Steps Check SI Status:
a) Check if SI is actuated:
SI annunciators - ANY ILLUMINATED (YES)
EOP-E-0 RO SI equipment - AUTO STARTED (YES) b) Check BOTH trains of SI - ACTUATED SI pumps - BOTH RUNNING (yes)
RHR pumps - BOTH RUNNING (YES)
EOP-E-0 CRS Verifies all immediate actions for EOP-E-0.
EXAMINERS NOTE: Crew may take early actions at this time to address items that did not function or operate as designed.
Stop MFP A Close FRVs Close FW HDR Section Valves Crew may also take a prompt and prudent action and attempt to close the MSIVs (will not close)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 32 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior BOOTH OPERATOR: If dispatched to attempt to close the MSIVs notify the Control Room that they are damaged from the steam explosion and will not close NOTE FOLDOUT for EOP-E-0 is in effect (Faulted S/G AFW Isolation Criteria does not apply due to no intact S/G)
Perform Attachment 1, Auto Action Verification, While continuing EOP-E-0 CRS with this procedure. (Should be assigned to BOP.) (Att. 1 steps are presented next followed by the remainder of EOP-E-0.)
Beginning of EOP-E-0 Attachment 1 (Remainder of EOP-E-0 Follows this Section)
CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
Check ECCS Pumps Running:
Att. 1 BOP SI pumps - BOTH RUNNING (YES)
RHR pumps - BOTH RUNNING (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 33 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Att. 1 BOP Check ECCS Valves - PROPER EMERGENCY ALIGNMENT (YES)
Att. 1 BOP Check CCW Pumps - AT LEAST ONE RUNNING (YES)
Check Containment Isolation Phase A
- a. Phase A - Actuated (YES)
- b. Phase A valves - Closed (YES)
Att. 1 BOP c. Excess letdown - Isolated (YES)
CVC-387 - Closed HIC-137 - at 0% DEMAND
- c. Manually close valve(s) as necessary Check Feedwater Isolation:
a) Main feed pumps - BOTH TRIPPED (NO)
RNO - Trip MFPs as necessary Att. 1 b) Main feedwater - ISOLATED Critical BOP Task FRVs - Closed (NO)
Feedwater reg bypass valves - Closed (YES)
Feedwater header section valves - Closed (NO)
RNO - Manually close valve(s) as necessary Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 34 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior CRITICAL TASK - MANUALLY ISOLATE FEEDWATER PRIOR TO ANNOUNCING COMPLETION OF EOP-E-0 ATTACHMENT 1 Check if Main Steamlines Should Be Isolated:
a) Main steamline isolation - REQUIRED (YES)
Att. 1 BOP b) Check MSIVs and bypass valves closed (NO)
RNO - Manually close valve (s) as necessary (MSIVs will not close)
Check Proper Service Water System Operation:
- a. SW pumps - All running (YES)
Att. 1 BOP
- b. SW booster pumps - Both running (YES)
Extinguished (YES)
Att. 1 BOP Check Both EDGs - Running (YES)
Check ECCS Flow:
- a. RCS pressure - less than 1650 psig (YES)
Att. 1 BOP b. SI pumps- Flow Indicated (YES)
- c. RCS pressure - less than 275 psig. (NO)
Go to step 10 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 35 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Att. 1 BOP Check CV Recirculation Fans - All Running (HVH-1 is unavailable)
Check IVSW - Actuated (YES)
Att. 1 BOP PCV-1922A - Open (YES)
PCV-1922B - Open (YES)
Check CV ventilation isolation (YES)
Att. 1 BOP
- a. CV ventilation isolation valves - CLOSED (YES)
Check control room ventilation - aligned for pressurization mode (YES)
HVA-1A or HVA-1B - Running (YES)
HVE Stopped (YES)
Att. 1 HVE-19A or HVE-19B - Running (NO, starts HVE-19A or HVE-BOP 19B)
Control Room HVAC outside air damper A or B - Open (YES)
CR-D1A-SA - Closed (YES)
CR-D1B-SB - Closed (YES)
Att. 1 BOP Check DS Bus - Energized (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 36 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Check Battery Chargers - Energized (YES)
Att. 1 BOP APP-036-D1 - Extinguished (YES)
APP-036-D2 - Extinguished (YES)
Att. 1 BOP Stop R-11/12 Sample Pump Att. 1 BOP Locally Reset and Load IACs as necessary (N/A)
Perform Crew Update to include the following:
Attachment Completion Manual Actions Taken (Manually isolated FW from te RTGB)
Att. 1 BOP Failed Equipment status SW status SW to Turbine Building isolated Performing Supplement M End of EOP-E-0 Attachment 1 Continuation of EOP-E-0 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 37 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Check AFW Pumps - Running (MDAFW Pumps are running)
- a. MDAFW Pumps - both running (YES)
EOP-E-0 RO b. S/G levels - 2 less than 16 % (YES)
- c. Steam driven AFW pump steam shutoff valves - ALL OPEN (YES)
Check AFW Valves - Proper Emergency Alignment (YES)
AFW header discharge valves - Full Open (YES)
EOP-E-0 RO AFW header section valves - Full Open (YES)
Steam driven AFW pump discharge valves - Full open if pump is running. (YES)
Check Total AFW Flow:
Reset SI EOP-E-0 RO Control feed flow to maintain NON-faulted S/Gs narrow range level - Between 8% and 50%.
Check total AFW flow- Greater than 300 gpm (YES)
Check CV Spray NOT Required:
EOP-E-0 RO a. CV pressure - Has remained less than 10 psig. (YES)
- b. CV Spray - NOT actuated (YES)
EOP-E-0 RO Check RCP Seal Cooling:
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 38 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior CCW flow to RCP thermal barriers - Normal (YES) o APP-001-C1 / D1 - Extinguished (YES)
OR Seal injection flow - Normal (YES) o Seal injection flow - Greater than 6 gpm per RCP OR o Thermal barrier Ps - Greater than 5 inches water.
Check RCS Temperature With NO RCPs running, RCS cold leg temperatures - Stable at or trending to 547°F (NO)
RNO: IF temperature is less then 547°F AND lowering then perform the following: (YES)
- b. IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:
o Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% in at least one S/G.
- c. IF cooldown continues, THEN close MSIVs and MSIV bypass valves. (MSIVs automatically closed due to Large Break LOCA)
Check PZR PORVs and Spray Valves:
- a. PORVs - Closed (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 39 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior
- b. Normal PZR spray valves - Closed (YES)
- c. Aux spray valve - Closed (YES)
Check If RCPs should be stopped:
- a. RCPs - Any Running (YES)
RNO: Go to Step 14 Step 14: Check if S/G Secondary Pressure Boundaries are Intact:
- a. Check pressures in all S/Gs o None lowering in an uncontrolled manner (NO) o None Completely depressurized (NO)
EOP-E-0 BOP RNO - a. Reset SPDS and initiate monitoring of Critical Safety Functions Status Trees.
Go To EOP-E-2, Faulted Steam Generator Isolation, Step 1.
Beginning of EOP-E-2 CAUTION CRS EOP-E-2 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 40 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior At least one S/G must be maintained available for RCS cooldown.
Any faulted S/G or secondary break should remain isolated during Check MSIVs and MSIV Bypass Valves for Faulted S/G - Closed (ALL Faulted, MSIVs will not close)
EOP-E-2 BOP Manually close vlaves (will not close)
EOP-E-2 Check if any S/G Secondary Pressure Boundary is Intact:
- a. Check pressures in all S/Gs - Any stable or rising. (NO)
BOP RNO - IF all S/G pressures are lowering in an uncontrolled manner, THEN reset SPDS and Go To EPP-16, Uncontrolled Depressurization Of All Steam Generators, Step 1.
EXAMINERS NOTE: SPDS has been reset and may be indicating either an Orange or Red condition on RCS Integrity. The crew may have entered FRP-P.1 prior to entering EPP-16 Beginning of EPP-16 EPP-16 CREW Open foldout D Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 41 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Perform The Following:
- b. Initiate monitoring of Critical Safety Function Status Trees CAUTION Maintain one steam supply to the SDAFW available if the SDAFW Pump is the only available source of feed flow Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 42 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Isolate All S/Gs As Follows:
- c. Verify STEAM SHUTOFFS Valves - CLOSED EPP-16 BOP V1-8A V1-8B V1-8C
- e. Verify STEAM LINE PORVs - CLOSED RV-1 RV-2 RV-3 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 43 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Locally Open The Breakers For The Following Valves:
V1-8A, SDAFW PUMP STEAM ISOLATION (MCC-5, CMPT-16F)
EPP-16 BOP V1-8B, SDAFW PUMP STEAM ISOLATION (MCC-6, CMPT-16M)
V1-8C, SDAFW PUMP STEAM ISOLATION (MCC-6 CMPT-18M)
BOOTH OPERATOR: If requested to open the breakers for V1-8A/B/C use the P&ID function S/G button and rack out the breaker - V1-8A EPSMCC5_189, V1-8B EPSMCC6_226, V1-8C EPSMCC6_227 Check The S/G Blowdown Isolation AND Sample Valves - CLOSED EPP-16 RO (YES)
EPP-16 Locally Verify The Following Valves - CLOSED
- b. STEAM LINE BEFORE SEAT DRAIN ROOT ISOL
- c. STEAM LINE AFTER SEAT DRAIN ROOT ISOL Check Cooldown Rate In RCS Cold Legs - GREATER THAN EPP-16 RO LAST 60 MINUTE (YES)
EPP-16 BOP Check MDAFW Pump Status - AT LEAST ONE AVAILABLE (YES)
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 44 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Control Feed Flow To Minimize RCS Cooldown As Follows:
Throttle feed flow to between 80 gpm and 90 gpm to each S/G using MDAFW FLOW CONTROLLER:
EPP-16 FIC-1424, AFW Pump A Dischh Flow Critical BOP Task OR FIC-1425, AFW Pump B Disch Flow RNO - Open breakers for V2-16A/B/C and locally throttle valves to establish 80-90 gpm to each S/G CRITICAL TASK - Throttle feed flow to each S/G to 80-90 gpm BOOTH OPERATOR: When requested wait 3 minutes and then throttle V2-16A/B/C Beginning of FRP-H.1 EXAMINERS NOTE: This FRP may be entered after FRP-P.1 is implemented if AFW flow is throttled IAW FRP-P.1 CAUTION Feed flow is not re established to any faulted S/G if an intact S/G is available Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 45 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Check Total Feed Flow LESS THAN 300 GPM DUE TO FRP-H.1 BOP OPERATOR ACTION (YES)
FRP-H.1 CRS Reset SPDS And Return To Procedure And Step In Effect End of FRP-H.1 Beginning of FRP-P.1 EXAMINERS NOTE: Remove malfunctions for FW/OVRD RESET and alarm block using the SCN file FRP-P.1 BOP Check CST level less than 10% (NO)
Determine If RCS Cooldown Is Due To A Large Break LOCA As Follows:
- a. Check both of the following conditions exist:
RCS pressure - LESS THAN 275 PSIG [350 PSIG] (NO)
FRP-P.1 RO AND RHR flow on FI-605 - GREATER THAN 1200 GPM (NO)
Go to step 4 Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 46 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior FRP-P.1 RO Check RCS Cold Leg Temperature - lowering (YES)
Attempt To Stop RCS Cooldown As Follows:
- a. Verify STEAM LINE PORVs - CLOSED (YES)
FRP-P.1 BOP b. Verify COND DUMPs - CLOSED (YES)
- c. Check RHR System - ALIGNED FOR CORE COOLING (NO)
Go to step 6 Check S/G Status - ANY INTACT (NO)
RNO - Perform the following:
- b. IF the MDAFW Pumps are NOT available, THEN maintain steam supply to the SDAFW Pump from at least one S/G.
V1-8A V1-8B V1-8C
- d. Maintain feed flow to each S/G between 80 gpm and 90 gpm.
- e. Go To Step 11.
Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 47 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Check PORV BLOCK Valves As Follows:
FRP-P.1 RO a. Power to PORV BLOCK Valves - available (YES)
- b. PORV BLOCK Valves - AT LEAST ONE OPEN (YES)
Check LTOPP - IN SERVICE (NO)
FRP-P.1 RO Go to step 12.d Check PZR pressure - Less than 2335 psig (YES)
FRP-P.1 RO Verify PZR PORVs closed (YES)
FRP-P.1 RO Check SI PUMPs - ANY RUNNING (YES)
Determine If SI Can Be Terminated As Follows:
- a. Check RCS subcooling - (YES)
- b. Determine required RVLIS indication from Table:
Rcp Status Required RVLIS Indication FRP-P.1 RO None Running 69% Full Range One Running 40% Dynamic Range Two Running 57% Dynamic Range Three Running 85% Dynamic Range Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 48 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Check RVLIS Indication - GREATER THAN REQUIRED VALUE FROM TABLE FRP-P.1 RO Observe CAUTION prior to step 17 and go to step 17 CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment Perform The Following:
- a. Reset SAFETY INJECTION FRP-P.1 RO
- b. Momentarily place the CONTAINMENT SPRAY Key Switch to the OVRD/RESET position AND return to the NORMAL position Reset The Following Containment Isolations:
FRP-P.1 RO PHASE A PHASE B Establish Instrument Air To CV As Follows:
EXTINGUISHED FRP-P.1 RO
- c. Check IA PCV-1716, INSTRUMENT AIR ISO TO CV - OPEN Appendix D NUREG-1021, Rev. 9, Supp. 1
Appendix D Operator Action Form ES-D-2 Op Test No.: ILC-14 NRC Scenario # 5 Event # 7-11 Page 49 of 50 Event
Description:
Steam Break on 72 Header, On the SI FRVs Fail to Auto Close, FW Header Section Valves Fail to Auto Close, MFW Pump A Fails to Auto Trip, and MSIVs Fail to Close Time Position Applicants Actions or Behavior Verify The Following:
FRP-P.1 RO SI Pumps - ALL STOPPED RHR Pumps - ALL STOPPED The Lead Examiner may terminate the scenario anytime after THE Safety Injection Pumps are stopped Appendix D NUREG-1021, Rev. 9, Supp. 1
ILC-14 NRC SCENARIO 5 TURNOVER SHEET
- 1. INITIAL CONDITIONS a) Time in Core Life: BOL b) Reactor Power: 50%
c) Turbine Load: 353 MWe d) Boron Concentration: 1537 ppm e) Rod Height: 171 CBD f) RCS Pressure: 2235 psig g) RCS Level: 36 %
h) Xenon: Equilibrium
- 2. TECHNICAL SPECIFICATION LCO ACTIONS STATEMENTS IN EFFECT T.S. # Description
- 4. CAUTION CAPS IN EFFECT a) None
- 5. PROTECTED EQUIPMENT a) None
- 6. DEGRADED EQUIPMENT a) None
- 7. SWITCHYARD ACCESS a) Unrestricted
- 8. PLANNED EVOLUTIONS a) Maintain current power level
- 9. TURNOVER INFORMATION a) None
- 10. REACTIVITY INFORMATION a) Review the OST-947 BOL/MOL/EOL charts for BA and PW additions
- 11. RISK a) GREEN Appendix D NUREG-1021, Rev. 9, Supp. 1