ML101520379
| ML101520379 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/04/2010 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-269/10-301, 50-270/10-301, 50-287/10-301 | |
| Download: ML101520379 (78) | |
Text
Appendix 0 Scenario Outline Form ES-D-1 3/10 Facility:
Oconee Scenario No.: I Op-Test No.:
Examiners:
Operators:
Initial Conditions:
65% Reactor Power Turnover:
Place the 1A Main FDW Pump on Handjack Event Maif. No.
Event Type*
Event No.
Description Oa Pre-lnsert Switch will not stop 1B2 RCP when directed by Rule 2 AOR Ob Pre-Insert 1 HP-3 fails to close on ES AOR Oc Pre-lnsert All turbine trips bypassed AOR 1
Override N, BOP, SRO Place 1A Main Feedwater Pump on Handjack 2
MSS 200 C, BOP, SRO Vacuum Leak 3
MPS 247 C, BOP, SRO 1 Bi RCP lower seal fails (Requires pump shutdown) 4 MPI 281 I, OATC, SRO ICS fails to re-ratio Feedwater 5
MPS 248 C, ALL RCS Leak (1 B1 RCP middle and upper seals fail) (TS)
MPS 249 6
R, OATC, SRO Manual plant shutdown 7
Pre-Insert C, OATC, SRO Turbine fails to trip requiring EHC pumps lockout 8
MPS 400 M, ALL SBLOCA (LOSCM to LOCA CD) 1 HP-3 fails to close on ES Switch will NOT stop 1B2 RCP when directed by Rule 2 (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Page 1 of 19 Appendix D Scenario Outline Form ES-D-1 3/10 Facility: Oconee Scenario No.: 1 Op-Test No.:
1 Examiners:
Operators:
SRO OATC BOP Initial Conditions:
65% Reactor Power Turnover:
Place the 1 A Main FDW Pump on Handjack Event Malf. No.
Event Type*
Event No.
Description Oa Pre-Insert Switch will not stop 1 B2 RCP when directed by Rule 2 AOR Ob Pre-Insert 1 HP-3 fails to close on ES AOR Oc Pre-Insert All turbine trips bypassed AOR 1
Override N, BOP, SRO Place 1 A Main Feedwater Pump on Handiack 2
MSS 200 C, BOP, SRO Vacuum Leak 3
MPS 247 C, BOP, SRO 1 B1 RCP lower seal fails (Requires pump shutdown) 4 MPI281 I, OATC, SRO ICS fails to re-ratio Feedwater 5
MPS 248 C,ALL RCS Leak (1 B1 RCP middle and upper seals fail) (TS)
MPS 249 6
R, OATC, SRO Manual plant shutdown 7
Pre-Insert C, OATC, SRO Turbine fails to trip requiring EHC pumps lockout 8
MPS 400 M, ALL SBLOCA (LOSCM to LOCA CD) 1 HP-3 fails to close on ES Switch will NOT stop 1 B2 RCP when directed by Rule 2 (N)ormal, (R)eactivity, (I)nstrument (C)omponent (M)ajor Page 1 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: I Event No.: I Page 1 of 1 Event
Description:
Place IA Main Feedwater Pump on Handjack: (N; BOP, SRO)
Time Position Applicants Actions or Behavior Crew response:
BOP OP/I/Ni 106/002 B Enclosure 4.10 (Placing IA FDWPT On Handjack)
Ensure 1A MAIN FDW PUMP (ICS) in HAND.
NOTE:
Control of 1A FDWPT with 1A FDWPT Motor Speed Changer indicated when 1A FDWPT speed and/or suction flow decreases.
Two successful decreases should be achieved to ensure control.
Run 1A FDWPT Motor Speed Changer down to control 1A FDWPT.
NOTE:
Handjack ON simulates Motor Gear Unit at high speed stop.
When Handjack switch is placed to on FDWPT speed may increase 40 rpm.
Turn FDWPT 1A HANDJACK switch to ON.
1A FDWPT speed now controlled with 1A FDWPT Motor Speed Changer.
Record on Turnover Sheet control of 1A FDWPT on Motor Speed Changer.
Place Tb SHEET CR tag on 1A MAIN FDW PUMP (ICS) station.
When the IA Main FDW pump is on Handjack or when directed by the Lead Examiner this event is completed.
Page2ofl9 Appendix 0 Scenario Outline Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Page 1 of 1 Event
Description:
Place 1A Main Feedwater Pump on Handjack: (N; BOP, SRO)
Time Position Applicant's Actions or Behavior Crew response:
BOP OP/1/A/1106/002 B Enclosure 4.10 (Placing 1A FDWPT On Handjack)
Ensure 1A MAIN FDW PUMP (ICS) in "HAND".
NOTE:
Control of 1A FDWPT with 1A FDWPT Motor Speed Changer indicated when 1A FDWPT speed and/or suction flow decreases.
Two successful decreases should be achieved to ensure control.
Run 1 A FDWPT Motor Speed Changer down to control 1 A FDWPT.
NOTE:
Handjack "ON" simulates Motor Gear Unit at high speed stop.
When Handjack switch is placed to on FDWPT speed may increase -40 rpm.
Turn FDWPT 1A HANDJACK switch to "ON".
1A FDWPT speed now controlled with 1A FDWPT Motor Speed Changer.
Record on Turnover Sheet control of 1 A FDWPT on Motor Speed Changer.
Place "T/O SHEET" CR tag on 1A MAIN FDW PUMP (ICS) station.
When the 1 A Main FDW pump is on Handjack or when directed by the Lead Examiner this event is completed.
Page 2 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: I Event No.: 2 Page 1 of 1 Event
Description:
Time Position Applicants Actions or Behavior Plant response:
1SA-031A-6, COND VACUUM LOW OAC alarm, Main Condenser Vacuum LOW Crew response:
Refer to the ARG and AP127, Loss of Condenser Vacuum.
BOP Refer to AP/27:
SRO BOP Announce AP entry using PA system.
IAAT condenser vacuum is 22 Hg, THEN trip RX.
Dispatch operators to perform End. 5.1 (Main Vacuum Pump Alignment) and look for vacuum leaks.
Booth cue: Notify CR that USING TIME COMPRESSION, Main Vacuum Pumps are aligned per End. 5.1.
Start all Main Vacuum Pumps.
Ensure 1V-186 is closed.
Ensure Stm to Stm Air Eject A, B, C > 255 psig.
Verify Stm Seal Hdr Press> 1.5 psig.
Start 1 D CCW pump to ensure all CCW pumps operating.
Booth cue: Call Control Room as the NEO and report that a leak was found on the lB Main FDW Pump pumping trap sight glass and has been isolated.
Verify Condensate flow 2300 gpm.
WHEN condenser vacuum is stable, AND End 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure.
When vacuum has been recovered or when directed by the Lead Examiner, the event is complete.
Page 3 of 19 Appendix D Op-Test No.: 1 Event
Description:
Time Position BOP SRO BOP Scenario Outline Scenario No.: 1 Event No.: 2 Vacuum Leak: (C; BOP, SRO)
Applicant's Actions or Behavior Plant response:
1SA-03/A-6, COND VACUUM LOW OAC alarm, Main Condenser Vacuum LOW Crew response:
Refer to the ARG and AP/27, Loss of Condenser Vacuum.
Refer to AP/27:
Announce AP entry using PA system.
IAAT condenser vacuum is s; 22" Hg, THEN trip RX.
Form ES-D-2 Page 1 of 1 Dispatch operators to perform Enc!. 5.1 (Main Vacuum Pump Alignment) and look for vacuum leaks.
Booth cue: Notify CR that USING TIME COMPRESSION, Main Vacuum Pumps are aligned per Encl. 5.1.
Start all Main Vacuum Pumps.
Ensure 1V-186 is closed.
Ensure Stm to Stm Air Eject A, B, C > 255 psig.
Verify Stm Seal Hdr Press> 1.5 psig.
Start 1 D CCW pump to ensure all CCW pumps operating.
Booth cue: Call Control Room as the NED and report that a leak was found on the 1 B Main FDW Pump pumping trap sight glass and has been isolated.
Verify Condensate flow;:: 2300 gpm.
WHEN condenser vacuum is stable, AND Encl 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure.
When vacuum has been recovered or when directed by the Lead Examiner, the event is complete.
Page 3 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 3 Page 1 of 2 Event
Description:
IBI RCP lower Seal Failure: (C, BOP, SRO)
Time Position j
Applicants Actions or Behavior Plant response:
1SA-06/C-5, RC PUMP IBI CAVITY PRESS HI/LOW 1SA-06/C-6, RC PUMP 1B1 SEAL RETURN FLOW HI/LOW Crew response:
BOP Refer to the ARGs; Refer to AP/1 6 SRO Refer to AP/1 6
, Abnormal RCP Operations Check if any RCP Immediate Trip Criteria (ITC) met. RNO- (Go to step 4.12)
SRO Announce AP entry on plant page BOP Notify OSM to request evaluation by RCP Component Engineer.
IAAT the failure is identified, THEN GO TO the applicable section: (GO TO Section 4A-Seal Failure)
IAAT
- Check for ITC.
RNO- (Go to step 12 of Section 4A)
IAAT fly of the following indicate external RCP seal leakage:
RB RIAs increasing or in alarm (RIA-4, 43
- 46)
RCS Tave constant with LDST level decreasing more than normal Quench Tank level rate increasing RB Normal Sump rate increasing THEN initiate AP/02 (Excessive RCS Leakage).
Verify the following are open:
1HP-20 1HP-21 Verify 1HP-232 is open IAAT Based on #1 seal delta P; Go To Step 16 to shutdown 1B1 RCP.
Verify Mode 1 or 2 Verify three RCPs will remain operating after affected RCP is tripped Page4ofl9 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 3 Page 1 of 2 Event
Description:
1 B1 RCP lower Seal Failure: (C, BOP, SRO)
Time Position BOP SRO SRO Applicant's Actions or Behavior Plant response:
1SA-06/C-5, RC PUMP 1B1 CAVITY PRESS HI/LOW 1SA-06/C-6, RC PUMP 1B1 SEAL RETURN FLOW HI/LOW Crew response:
Refer to the ARGs; Refer to AP/16 Refer to AP/16, Abnormal RCP Operations Check if any RCP Immediate Trip Criteria (ITC) met. RNO- (Go to step 4.12)
Announce AP entry on plant page BOP Notify OSM to request evaluation by RCP Component Engineer.
IAAT the failure is identified, THEN GO TO the applicable section: (GO TO Section 4A-Seal Failure)
IAAT - Check for ITC. RNO- (Go to step 12 of Section 4A)
IAAT any of the following indicate external RCP seal leakage:
~ RB RIAs increasing or in alarm (RIA-4, 43 - 46)
~ RCS Tave constant with LOST level decreasing more than normal
~ Quench Tank level rate increasing
~ RB Normal Sump rate increasing THEN initiate AP/02 (Excessive RCS Leakage).
Verify the following are open:
~ 1HP-20
~ 1HP-21 Verify 1 HP-232 is open IAAT Based on #1 seal delta P; Go To Step 16 to shutdown 1B1 RCP.
Verify Mode 1 or 2 Verify three RCPs will remain operating after affected RCP is tripped Page 4 of 19
Verify Rx power is <70%
Verify jy SG not on Low Level Limits Verify FDW masters in Auto StopIBIRCP Verify ICS re-ratios feedwater Initiate End 4.3 (Special Instructions for < 4 RCP Operation) of OP/i/Ni 102/004 IAAT RCP has been shut down for >30 minutes, THEN close the associated RCP motor cooler inlet/outlet valve (1 LPSW-9 & 10)
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 3 Page 2 of 2 Event
Description:
IBI RCP lower Seal Failure: (C, BOP!SRO)
Time Position Applicants Actions or Behavior BOP When the I BI RCP has been secured or when directed by the Lead Examiner, the event is complete.
Page 5 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 3 Page 2 of 2 Event
Description:
1 B1 RCP lower Seal Failure: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior BOP Verify Rx power is ~ 70%
Verify any SG not on Low Level Limits Verify FDW masters in Auto Stop 1B1 RCP Verify ICS re-ratios feedwater Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 IAAT RCP has been shut down for >30 minutes, THEN close the associated RCP motor cooler inlet/outlet valve (1 LPSW-9 & 10)
When the 1 B1 RCP has been secured or when directed by the Lead Examiner, the event is complete.
Page 5 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 4 Page 1 of 2 Event
Description:
ICS fails to re-ratio Feedwater (I, OATC, SRO)
Time Position Applicants Actions or Behavior Plant response:
When the 1 Bi RCP is secured the TC controller will fail at
+35 Feedwater flow will continue to increase to the 1A SG and decrease to the I B SG causing the actual \\Tc to become increasingly negative.
Crew response:
OATCISRO API16 (Continued)
Verify ICS re-ratios feedwater to establish 0°F NOTE: ATC controller will fail in auto Place DELTA Tc station in HAND.
Manually adjust DELTA Tc station to achieve 0° i2k Tc.
CAUTION:
Total feedwater flow should be maintained constant to prevent changes in core reactivity.
IF DELTA Tc station does NOT control, THEN perform the following:
o Place lAand lB FDW MASTERs in HAND:
Manually adjust FDW masters to achieve 0° tiTc.
o Initiate AP128 (lOS Instrument Failure).
Note: FDW Master toggle switches will have to be used to adjust ATc.
Decrease the IA and Increase the lB Initiate End 4.3 (Special Instructions for < 4 RCP Operation) of OP/i/All 102/004 (Operation at Power).
IAAT any of the following indicate external RCP seal leakage:
o RB RIAs increasing or in alarm o
RCS Tave constant with LDST level decreasing more than normal o
Quench Tank level rate increasing o
RB Normal Sump rate increasing o
Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage).
Verify 1 HP-20 and 1 HP-21 are open:
Verify 1HP-232 is open.
Page 6 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 4 Page 1 of 2 Event
Description:
les fails to re-ratio Feedwater (I, OATC, SRO)
Time Position Applicant's Actions or Behavior Plant response:
When the 1 B 1 RCP is secured the ATC controller will fail at - +3.5 Feedwater flow will continue to increase to the 1A SG and decrease to the 1 B SG causing the actual ATc to become increasingly negative.
Crew response:
OATC/SRO AP/16 (Continued)
Verify ICS re-ratios feedwater to establish::::: O°F b. Tc.
NOTE: ATC controller will fail in auto aHa flUll'tlal~
Place DELTA Tc station in HAND.
Manually adjust DELTA Tc station to achieve::::: 0° b. Tc.
CAUTION:
Total feedwater flow should be maintained constant to prevent changes in core reactivity.
IF DELTA Tc station does NOT control, THEN perform the following:
o Place 1A and 1 B FDW MASTERs in HAND:
Manually adjust FDW masters to achieve::::: 0° b.Tc.
o Initiate AP/28 (ICS Instrument Failure).
Note: FDW Master toggle switches will have to be used to adjust aTc.
Decrease the 1A and Increase the 18 Initiate Ene! 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power).
IAAT any of the following indicate external RCP seal leakage:
o RB RIAs increasing or in alarm oRCS Tave constant with LDST level decreasing more than normal o
Quench Tank level rate increasing o
RB Normal Sump rate increasing o
Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage).
Verify 1 HP-20 and 1 HP-21 are open:
Verify 1 HP-232 is open.
Page 6 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 4 Page 2 of 2 Event
Description:
ICS fails to re-ratio Feedwater (I, OATC, SRO)
Time Position Applicants Actions or Behavior Crew response: (Continued)
OATC/SRO AP128 BOP Verify entry into AP128:
o Power>3%
o PTR actions taken and TPB the pre-transient power level AND Delta Tc has failed.
Verify that current thermal power best is pre-transient thermal power best and that the plant is stable.
Notify Rx Engineering to provide Control Room with a maneuvering plan.
GO TO the applicable section (4F Delta Tc) per the following table:
4F Delta Tc Ensure the following in HAND:
1AFDW MASTER 1BFDWMASTER DELTATc Re-ratio feedwater flow, as required, to establish 0°F DELTA Tc while maintaining total feedwater flow constant.
Notify SPOC to perform the following:
Investigate and repair the failed Delta Tc controller.
WHEN notified by SPOC that Delta Tc controller has been repaired, THEN GO TO End 5.1 (Placing lCS in AUTO).
When the plant is stable and SPOC has been notified, or when directed by the Lead Examiner this event is completed.
Page 7 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 4 Page 2 of 2 Event
Description:
les fails to re-ratio Feedwater (I, OATC, SRO)
Time Position OATC/SRO BOP Applicant's Actions or Behavior Crew response: (Continued)
AP/28 Verify entry into AP/28:
o Power> 3%
o PTR actions taken and TPB :s; the pre-transient power level AND Delta Tc has failed.
Verify that current thermal power best is :s; pre-transient thermal power best and that the plant is stable.
Notify Rx Engineering to provide Control Room with a maneuvering plan.
GO TO the applicable section (4F - Delta Tc) per the following table:
4F -
Delta Tc
~ Ensure the following in HAND:
1 A FDW MASTER 1 B FDW MASTER DELTA Tc
~ Re-ratio feedwater flow, as required, to establish:::: OaF DELTA Tc while maintaining total feedwater flow constant.
~ Notify SPOC to perform the following:
Investigate and repair the failed Delta Tc controller.
~ WHEN notified by SPOC that Delta Tc controller has been repaired, THEN GO TO Ene! 5.1 (Placing ICS in AUTO).
When the plant is stable and SPOC has been notified, or when directed by the Lead Examiner this event is completed.
Page 7 of 19
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 5 Page 1 of 2 Event
Description:
RCS Leak
- I BI RCP middle and upper seals fail, (C, All) (TS)
Time Position Applicants Actions or Behavior Plant response:
1 SA-6/C-5, RC Pump 1 Bi Seal Cavity Press Hi/Low 1 SA-61C-6, RC Pump 1 B1 Seal Return Flow Hi/Low 1 BI RCP lower pump cavity pressure will equal upper seal cavity pressure.
LDST level will decrease as -. 80 gpm will leak out of the RCS through the failed pump seals.
Reactor Building Normal Sump level will increase.
Crew response:
AP16 SRO/
Per IAAT (Section 4A
- Step 12), indication of external seal leakage, OATC/ BOP THEN initiate AP/2 (Excessive RCS Leakage).
AP2 Verify HPI operating.
IAAT RC makeup flow is> 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5.
IAAT RCS leakage> NORMAL MAKEUP CAPABILITY with letdown isolated, AND Pzr level decreasing, THEN trip Rx.
Initiate makeup to LDST using EOP End 5.5 (Pzr and LDST Level Control), as necessary EOP End 5.5 (Pzr and LDST Level Control)
BOP Utilize the following as necessary to maintain Pzr level >100 [180 acc]:
o Standby HPI pump o
1HP-26 o
1HP-7 o
IHP-5 o
1 HP-i 20 setpoint or valve demand IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
o Obtain SRO concurrence to reduce running HPI pumps.
o Secure the desired HPI pumps.
o Place secured HPI pump switch in AUTO, if desired.
IAAT LDST level CANNOT be maintained, o
Open 1HP-24.
o Open 1HP-25.
o Close 1HP-16.
Page 8 of 19 Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 5 Page 1 of 2 Event
Description:
RCS Leak - 1 B1 RCP middle and upper seals fail, (C, All) (TS)
Time Position SRO/
OATC/BOP BOP Applicant's Actions or Behavior Plant response:
1 SA-6/C-5, RC Pump 1 B1 Seal Cavity Press Hi/Low 1 SA-6/C-6, RC Pump 1 B1 Seal Return Flow Hi/Low 1 B1 RCP lower pump cavity pressure will equal upper seal cavity pressure.
LDST level will decrease as - 80 gpm will leak out of the RCS through the failed pump seals.
Reactor Building Normal Sump level will increase.
Crew response:
AP16 Per IAAT (Section 4A - Step 12), indication of external seal leakage, THEN initiate AP/2 (Excessive RCS Leakage).
AP2 Verify HPI operating.
IAAT RC makeup flow is > 100 gpm, AND Pzr level is decreasing, THEN close 1 HP-5.
IAAT RCS leakage> NORMAL MAKEUP CAPABILITY with letdown isolated, AND Pzr level decreasing, THEN trip Rx.
Initiate makeup to LDST using EOP Encl 5.5 (pzr and LDST Level Control), as necessary EOP Encl 5.5 (pzr and LOST Level Control)
Utilize the following as necessary to maintain Pzr level >100" [180" acc]:
o Standby HPI pump o
1 HP-26 o
1 HP-7 o
1 HP-5 o
1 HP-120 setpoint or valve demand IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
o Obtain SRO concurrence to reduce running HPI pumps.
o Secure the desired HPI pumps.
o Place secured HPI pump switch in AUTO, if desired.
IAAT LDST level CANNOT be maintained, o
Open 1 HP-24.
o Open 1 HP-25.
o Close 1HP-16.
Page 8 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 5 Page 2 of 2 Event
Description:
RCS Leak
- I BI RCP middle and upper seals fail, (C, All) (TS)
Time Position Applicants Actions or Behavior Crew response:
AP2 (Continued)
BOP/SRO Announce AP entry using the PA system.
Make notifications to OSM, STA, & RP Monitor OAC for leak trends/data Initiate End 5.1 (Leak Rate Determination).
Calculation of RCS Volume Loss:
LeakRate=
+
=
MU SI LD TSR Where: MU = Makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown Flow TSR = Total Seal Return Flow Go To Step 4.145 based on leakage from RCP seal failure Discontinue pumping RBNS since leak> 10 gpm IAAT leak rate > TS, THEN initiate shutdown by one of the following:
AP/29 (Rapid Unit Shutdown)
OP/11A111021004 (Operation At Power)
OP/i/All 102/010 (Controlling Procedure For Unit Shutdown).
NOTE: Crew will use AP129 NOTE: LCO 3.4.13 (RCS operational LEAKAGE)
RCS operational LEAKAGE shall be limited to:
No pressure boundary LEAKAGE; I gpm unidentified LEAKAGE; 10 gpm identified LEAKAGE; and 150 gallons per day primary to secondary LEAKAGE When plant shutdown has been directed or when directed by the Lead Examiner this event is completed.
Page 9 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 5 Page 2 of 2 Event
Description:
RCS Leak - 1 B1 RCP middle and upper seals fail, (C, All) (TS)
Time Position BOP/SRO Applicant's Actions or Behavior Crew response:
AP2 (Continued)
Announce AP entry using the PA system.
Make notifications to OSM, STA, & RP Monitor OAC for leak trends/data Initiate Ene! 5.1 (Leak Rate Determination).
Calculation of RCS Volume Loss:
Leak Rate =
+
- ___ - ___ = __ _
MU SI LD Where: MU = Makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown Flow TSR = Total Seal Return Flow TSR Go To Step 4.145 based on leakage from RCP seal failure Discontinue pumping RBNS since leak> 10 gpm IAAT leak rate> TS, THEN initiate shutdown by one of the following:
AP/29 (Rapid Unit Shutdown)
OP/1/A/1102/004 (Operation At Power)
OP/1/A/11 02/01 0 (Controlling Procedure For Unit Shutdown).
NOTE: Crew will use AP/29 NOTE: LCO 3.4.13 (RCS operational LEAKAGE)
RCS operational LEAKAGE shall be limited to:
No pressure boundary LEAKAGE; 1 gpm unidentified LEAKAGE; 10 gpm identified LEAKAGE; and 150 gallons per day primary to secondary LEAKAGE When plant shutdown has been directed or when directed by the Lead Examiner this event is completed.
Page 9 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 6 Page 1 of 2 Event
Description:
Manual Reactor power decrease: (R, OATC, SRO)
Time Position Applicants Actions or Behavior Crew response:
AP/29 (Rapid Unit Shutdown)
NOTE SRO The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.
BOP Initiate End 5.1 (Support Actions During Rapid Unit Shutdown).
Announce AP entry using the PA system.
Verify ICS in AUTO.
NOTE: ICS is in MANUAL. The OATC will use the Reactor Diamond and the FDW masters to reduce power.
OATC RNO: Initiate manual power reduction to desired power level.
Verify both Main FDWPs operating.
Verify 1 B FDWP to be shut down first.
Adjust the FWP bias counterclockwise to lower 1 B FDWP suction flow 1 x 106 lb/hr < 1A FDWP suction flow.
WHEN core thermal power is <65% FP, THEN continue.
IAAT any of the following statalarms are received:
1SA-16/A-1 (FWPA FLOW MINIMUM) 1SA-16/A-2 (FWP A FLOW BELOW MIN) 1SA-16/A-3 (FWP B FLOW MINIMUM) 1 SA-16/A-4 (FWP B FLOW BELOW MIN),
THEN trip the lB Main FDWP.
Verify Turbine-Generator shutdown is required.
Start the TURBINE TURNING GEAR OIL PUMP.
Start 1A through 1 E TURBINE BRNG OIL LIFT PUMPS.
Start the TURBINE MOTOR SUCTION PUMP.
WHEN NI power 18%,
THEN depress turbine TRIP pushbutton.
Page 10 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 6 Page 1 of 2 Event
Description:
Manual Reactor power decrease: (R, OATC, SRO)
Time Position Applicant's Actions or Behavior Crew response:
AP/29 (Rapid Unit Shutdown)
NOTE SRO The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.
BOP Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown).
OATC Announce AP entry using the PA system.
Verify ICS in AUTO.
NOTE: ICS is in MANUAL. The OATC will use the Reactor Diamond and the FDW masters to reduce power.
RNO: Initiate manual power reduction to desired power level.
Verify both Main FDWPs operating.
Verify 1 B FDWP to be shut down first.
Adjust the FWP bias counterclockwise to lower 1 B FDWP suction flow -
1 x 106 Ib/hr < 1 A FDWP suction flow.
WHEN core thermal power is < 65% FP, THEN continue.
IAAT any of the following statalarms are received:
1SA-16/A-1 (FWP A FLOW MINIMUM) 1SA-16/A-2 (FWP A FLOW BELOW MIN) 1SA-16/A-3 (FWP B FLOW MINIMUM) 1SA-16/A-4 (FWP B FLOW BELOW MIN),
THEN trip the 1 B Main FDWP.
Verify Turbine-Generator shutdown is required.
Start the TURBINE TURNING GEAR OIL PUMP.
Start 1A through 1 E TURBINE BRNG OIL LIFT PUMPS.
Start the TURBINE MOTOR SUCTION PUMP.
WHEN NI power::; 18%,
THEN depress turbine TRIP pushbutton.
Page 10 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 6 Page 2 of 2 Event
Description:
Manual Reactor power decrease: (R, OATC, SRO)
Time Position Applicants Actions or Behavior Crew response:
BOlD End 5.1 (Support Actions During Rapid Unit Shutdown).
Notify WOO SRO to initiate End 5.2 (WOO SRO Support During Rapid Unit Shutdown).
Start the following pumps:
1A and lB FDWP SEAL INJECTION PUMP 1A and lB FDWP AUXILIARY OIL PUMP Stop 1 El and I E2 HTR DRN PUMPs. (already off)
Verify Turbine-Generator shutdown is required.
Place the following transfer switches to MAN:
1TA and 1TB AUTO/MAN Close ITA SU 6.9 KV FDR and verify 1TA NORMAL 6.9 KV FDR opens.
Close 1TB SU 6.9 KV FDR and verify 1TB NORMAL 6.9 KV FDR opens.
Place the following transfer switches to MAN:
MFB1 and MFB2 AUTO/MAN Close El 1 MFB1 STARTUP FDR and verify Ni 1 MFB1 NORMAL FDR opens.
Close E2 1 MFB2 STARTUP FDR and verify N2 1 MFB2 NORMAL FDR opens.
Notify OR SRO that Unit auxiliaries have been transferred.
WHEN CTP 65%,
THEN place 1 FDW-53 and 1 FDW-65 in MANUAL and close:
Ensure lA and lB MSRH DRN PUMP is stopped.
Place 1 HD-37 and 1 HD-52 in DUMP.
WHEN CTPis60%,
THEN ensure 1SSH-9 closed.
When the OATC has reduced power 10%, or when directed by the Lead Examiner this event is completed.
Page 11 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 6 Page 2 of 2 Event
Description:
Manual Reactor power decrease: (R, OATC, SRO)
Time Position BOP Applicant's Actions or Behavior Crew response:
Encl 5.1 (Support Actions During Rapid Unit Shutdown).
Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid Unit Shutdown).
Start the following pumps:
1A and 1 B FDWP SEAL INJECTION PUMP 1A and 1 B FDWP AUXILIARY OIL PUMP Stop 1 E1 and 1 E2 HTR DRN PUMPs. (already off)
Verify Turbine-Generator shutdown is required.
Place the following transfer switches to MAN:
1 T A and 1 TB AUTO/MAN Close 1TA SU 6.9 KV FOR and verify 1TA NORMAL 6.9 KV FOR opens.
Close 1TB SU 6.9 KV FOR and verify 1TB NORMAL 6.9 KV FOR opens.
Place the following transfer switches to MAN:
MFB1 and MFB2 AUTO/MAN Close E11 MFB1 STARTUP FOR and verify N11 MFB1 NORMAL FOR opens.
Close E21 MFB2 STARTUP FOR and verify N21 MFB2 NORMAL FOR opens.
Notify CR SRO that Unit auxiliaries have been transferred.
WHEN CTP :s; 65%,
THEN place 1 FDW-53 and 1 FDW-65 in MANUAL and close:
Ensure 1A and 1 B MSRH DRN PUMP is stopped.
Place 1 HD-37 and 1 HD-52 in DUMP.
WHEN CTP is:s; 60%,
THEN ensure 1 SSH-9 closed.
When the OATC has reduced power - 10%, or when directed by the Lead Examiner this event is completed.
Page 11 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 7 Page 1 of 1 Event
Description:
Main Turbine Fails to trip (Lockout EHC Pumps) (C, OATC)
Note: Reactor will trip as a result of the SBLOCA in event 8.
Time Position Applicants Actions or Behavior Plant response:
1 SA-9/A-6, RB Reactor Building Normal Sump Level High/Low iSA-i/A-i, B-i, C-i, D-1, RP Channel Trip 1 SA-2/D-3, RC Press High/Low A SBLOCA will result in a reactor trip.
The Main Turbine should trip but does not. This will result in a reduction of steam pressure in both SGs until actions are taken to trip the turbine. This will result in RCS overcooling until the turbine is tripped.
Crew response:
OATC will perform Immediate Manual Actions OATC Depress REACTOR TRIP pushbutton Verify reactor power < 5% FP and decreasing Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed Note: The OATC should diagnose that the turbine did not trip and then perform the RNO step which will stop and lock out both EHC pumps. This will cause the turbine to trip. (CT-18)
Verify RCP seal injection available.
BOP will perform a symptom check.
BOP Event is complete when EHC pumps have been tripped or when directed by the Lead Examiner.
Page 12 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: 7 Page 1 of 1 Event
Description:
Main Turbine Fails to trip (Lockout EHC Pumps) (C, OATC)
Note: Reactor will trip as a result of the SBLOCA in event 8.
Time Position SRO OATC BOP Applicant's Actions or Behavior Plant response:
1 SA-9/A-6, RB Reactor Building Normal Sump Level High/Low 1 SA-1/A-1, B-1, C-1, D-1, RP Channel Trip 1 SA-2/D-3, RC Press High/Low A SBLOCA will result in a reactor trip.
The Main Turbine should trip but does not. This will result in a reduction of steam pressure in both SGs until actions are taken to trip the turbine. This will result in RCS overcooling until the turbine is tripped.
Crew response:
OATC will perform Immediate Manual Actions Depress REACTOR TRIP pushbutton Verify reactor power < 5% FP and decreasing Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed Note: The OATC should diagnose that the turbine did not trip and then perform the RNO step which will stop and lock out both EHC pumps. This will cause the turbine to trip. (CT-18)
Verify RCP seal injection available.
BOP will perform a symptom check.
Event is complete when EHC pumps have been tripped or when directed by the Lead Examiner.
Page 12 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 8 Page 1 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicants Actions or Behavior Plant response:
Statalarms:
1SA-91A-6, RB Reactor Bldg Norm Sump Level High/Low 1SA-81B-9, Process Radiation Monitor High Control board indications:
RBNS level increases PZR level will decrease very slowly due to the leak and 1 HP-5 being closed.
Crew response:
SRO The SRO will refer to EOP Subsequent Actions; Parallel Actions page.
The SRO will receive Symptoms Check/Report from one of the ROs.
The SRO will direct one of the ROs to perform EOP End. 5.1 (ES Actuation)
Note: The RCS will eventually saturate with all HPI injecting.
The SRO will provide concurrence to the other RO to perform Rule 2 Loss of Subcooling Margin.
Verify all control rods fully inserted.
Verify Main FDW in operation.
Verify Main FDW controlling properly.
Verify TBVs controlling SG pressure 1010 psig.
Verify 1 RIA-40 operable.
Dispatch an operator with End 5.29 (MSRV Locations) to verify all MSRVs have reseated.
Verify ES is required.
Ensure ES 5.1 (ES Actuation) is in progress Page 13 of 19 Appendix D Op-Test No.: __
Event
Description:
Time Position SRO Scenario Outline Form ES-D-2 Scenario No.: 1 Event No.: 8 Page 1 of 6 Small Break LOCA: (M, ALL)
Applicant's Actions or Behavior Plant response:
Statalarms:
1SA-9/A-6, RB Reactor Bldg Norm Sump Level High/Low 1 SA-8/B-9, Process Radiation Monitor High Control board indications:
RBNS level increases PZR level will decrease very slowly due to the leak and 1 HP-5 being closed.
Crew response:
The SRO will refer to EOP Subsequent Actions; Parallel Actions page.
The SRO will receive Symptoms Check/Report from one of the ROs.
The SRO will direct one of the ROs to perform EOP Enc!. 5.1 (ES Actuation)
Note: The RCS will eventually saturate with all HPI injecting.
The SRO will provide concurrence to the other RO to perform Rule 2 - Loss of Subcooling Margin.
Verify all control rods fully inserted.
Verify Main FDW in operation.
Verify Main FDW controlling properly.
Verify TBVs controlling SG pressure::::: 1010 psig.
Verify 1 RIA-40 operable.
Dispatch an operator with End 5.29 (MSRV Locations) to verify all MSRVs have reseated.
Verify ES is required.
Ensure ES 5.1 (ES Actuation) is in progress Page 13 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 8 Page 2 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicants Actions or Behavior OATC/
When ES Channels 1 and 2 actuate, an operator should inform the SRO that ES BOP Channels 1 and 2 have actuated.
The SRO should direct initiation of EOP End. 5.1, ES Actuation per the Parallel SRO Actions page of Subsequent Actions section or of the LOSCM Tab.
When running End. 5.1, the operator will:
OATC/
BOP Determine which ES channels should have actuated and verify all Blue Lights and White Lights are lighted for the appropriate channels.
Place HPI in Manual.
Verify Rule 2 in progress or complete.
Determine NO RCPs operating and GO TO Step 8.
Note: ES Channels 1-thru-6 may actuate due to High Reactor Building Pressure; therefore the ES Actuation Checklist may be performed in a staggered fashion as the various ES Channels are actuated.
Place LPI pumps and 1LP-17/18 in manual control.
CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head.
IAAT y LPI pump is operating against a shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps Ensure A & B and 3A & 3B Outside Air Booster Fans are operating. (CT-27)
Verify ICF-1/2 open.
Verify IHP-410 closed.
Secure makeup to the LDST.
Verify all ES Channel 1-4 components are in the ES position.
Note: I HP-3 will not close. The operator should diagnose this and perform the RNO and close IHP-I located on IUBI.
Close 1LPSW-139 Fail Open 1LPSW-251/252 Open I LPSW-4/5 Dispatch an operator to perform End. 5.2 (Placing RB Hydrogen Analyzers In Service)
Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open.
The operator must get SRO approval to exit this enclosure.
Page 14 of 19 Appendix 0 Scenario Outline Form ES-O-2 Op-Test No.: __
Scenario No.: 1 Event No.: 8 Page 2 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicant's Actions or Behavior OATC/
When ES Channels 1 and 2 actuate, an operator should inform the SRO that ES BOP Channels 1 and 2 have actuated.
The SRO should direct initiation of EOP Encl. 5.1, ES Actuation per the Parallel SRO Actions page of Subsequent Actions section or of the LOSCM Tab.
When running Encl. 5.1, the operator will:
OATC/
BOP Determine which ES channels should have actuated and verify all "Blue Lights" and White Lights" are lighted for the appropriate channels.
Place HPI in Manual.
Verify Rule 2 in progress or complete.
Determine NO RCPs operating and GO TO Step 8.
Note: ES Channels 1-thru-6 may actuate due to High Reactor Building Pressure; therefore the ES Actuation Checklist may be performed in a staggered fashion as the various ES Channels are actuated.
Place LPI pumps and 1 LP-17/18 in manual control.
CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head.
IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps Ensure A & Band 3A & 3B Outside Air Booster Fans are operating. (CT-27)
Verify 1CF-1/2 open.
Verify 1 HP-41 0 closed.
Secure makeup to the LDST.
Verify all ES Channel 1-4 components are in the ES position.
Note: 1 HP-3 will not close. The operator should diagnose this and perform the RNO and close 1 HP-1 located on 1 UB1.
Close 1 LPSW-139 Fail Open 1 LPSW-251/252 Open 1 LPSW-4/5 Dispatch an operator to perform Encl. 5.2 (Placing RB Hydrogen Analyzers In Service)
Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open.
The operator must get SRO approval to exit this enclosure.
Page 14 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 8 Page 3 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicants Actions or Behavior Plant response:
RCS subcooling margin (y) will = 0°F.
Crew response:
SRO The BOP/OATC should inform the SRO that the RCS has saturated and obtain SRO concurrence to perform Rule #2, Loss of SCM.
BOP/
Verify that reactor power is < 1 %.
OATC Stop all RCPs (within 2 mm of LOSCM)
(CT-I)
Note: 1B2 RCP will not trip from the switch. RNO will be performed to de energize ITA and ITB (6.9KV switchgear).
Step 2 RNO Place 1TA AUTO/MAN switch in MAN.
Place 1TB AUTO/MAN switch in MAN.
Open 1TA SU 6.9 KV FDR.
Open 1TB SU 6.9 KV FDR.
Verify that HPI is performing as required and notify CR SRO of HPI status.
Verify that LPI flow in both headers is <3400 gpm.
Verify that TBVs are available.
Select OFF for both digital channels on AFIS HEADER A and B.
Start both MD EFDW pumps and establish 300 gpm to each SG. Feed to LOSCM SP per Rule 7 (SG Feed Control). (CT-b)
Verify both MDEFDWPs operating.
Ensure TDEFDWP is in PULL TO LOCK.
Trip both MFDWPs and close the FDW block valves (FDW-33, 31, 42, 40)
Maintain SG pressure < RCS pressure using TBVs.
Ensure Rule 3 is in progress or complete.
Page 15 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __
Scenario No.: 1 Event No.: 8 Page 3 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicant's Actions or Behavior Plant response:
RCS subcooling margin (§!JY) will = OaF.
Crew response:
SRO The BOP/OATC should inform the SRO that the RCS has saturated and obtain SRO BOP/
OATC concurrence to perform Rule #2, Loss of SCM.
Verify that reactor power is < 1 %.
Stop all RCPs (within 2 min of LOSCM)
(CT-1)
Note: 1 B2 RCP will not trip from the switch. RNO will be performed to de-energize 1T A and 1TB (6.9KV switchgear).
Step 2 RNO Place 1TA AUTO/MAN switch in MAN.
Place 1TB AUTO/MAN switch in MAN.
Open HA SU 6.9 KV FDR.
Open 1 TB SU 6.9 KV FDR.
Verify that HPI is performing as required and notify CR SRO of HPI status.
Verify that LPI flow in both headers is < 3400 gpm.
Verify that TBVs are available.
Select OFF for both digital channels on AFIS HEADER A and B.
Start both MD EFDW pumps and establish 300 gpm to each SG. Feed to LOSCM SP per Rule 7 (SG Feed Control). (CT-10)
Verify both MDEFDWPs operating.
Ensure TDEFDWP is in PULL TO LOCK.
Trip both MFDWPs and close the FDW block valves (FDW-33, 31,42,40)
Maintain SG pressure < RCS pressure using TBVs.
Ensure Rule 3 is in progress or complete.
Page 15 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 8 Page 4 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
Rule 3:
BOP/
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
OATC AND any of the following exist:
o RCS pressure reaches 2300 psig OR NDT limit o
Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 Start EFDW pumps to feed all intact SGs.
Verify any EFDW pump operating.
IAAT Unit I EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation).
End 5.9 (Extended EFDW Operation Monitor EFDW parameters on EFW graphic display.
Perform the following as required to maintain UST level > 7.5:
o Makeup with demin water.
o Place CST pumps in AUTO.
IAAT all the following exist:
o Rapid cooldown NOT in progress o
MD EFDWP operating for each available SG o
EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.
Notify CR SRO to set priority based on the NOTE above and EOP activities.
Page 16 of 19 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __
Scenario No.: 1 Event No.: 8 Page 4 of 6 Event
Description:
Time Position BOP/
OATe Small Break LOCA: (M, ALL)
Applicant's Actions or Behavior Crew response:
Rule 3:
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
AND any of the following exist:
oRCS pressure reaches 2300 psig OR NDT limit o
Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 Start EFDW pumps to feed all intact SGs.
Verify any EFDW pump operating.
IAAT Unit 1 EFDW is in operation, THEN initiate Ene! 5.9 (Extended EFDW Operation).
Encl 5.9 (Extended EFDW Operation Monitor EFDW parameters on EFW graphic display.
Perform the following as required to maintain UST level> 7.5':
o Makeup with demin water.
o Place CST pumps in AUTO.
IAAT all the following exist:
o Rapid cooldown NOT in progress o
MD EFDWP operating for each available SG o
EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.
Notify CR SRO to set priority based on the NOTE above and EOP activities.
Page 16 of 19
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 8 Page 5 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicants Actions or Behavior SRO The SRO should GO TO the LOSCM Tab per the Parallel Actions page of the EOP Subsequent Actions section. LOSCM Tab will:
Ensure that Rule #2 is in progress or complete.
Verify that station ASW is NOT feeding any SG.
Verify that the LOSCM is NOT caused by excessive heat transfer.
Verify transfer to LOCA CD tab not required due to no LPI flow.
Verify that the SSF is NOT activated.
Verify all the following conditions exist:
NO RCPs are operating HPI flow exists in both HPI headers Adequate Total HPI flow per figure 1 (Total Required HPI Flow)
Open 1AS-40 while closing I MS-47.
Control steaming and feed rates on all intact SGs to maintain cooldown rate within Tech Spec limits:
Tc>280°F
<5O°F/4hour Tc<280°F
<25°F/1/4 hour Utilize TBVs GO TO Step 92.
Close 1 RC-4 (No HPI forced cooling in progress)
Close 1GWD-17, 1HP-1, 1HP-2, 1RC-3.
Maintain SG pressure < RCS pressure utilizing either TBVs or ADVs (TBVs).
Verify primary to secondary heat transfer exists.
Initiate End 5.16 (SG Tube-to-Shell iT Control).
Verify CETCs increasing.
Verify required RCS makeup flow NOT within normal makeup capability.
GO TO LOCA CD tab.
Page 17 of 19 Appendix D Op-Test No.: __
Event
Description:
Time Position SRO Scenario Outline Form ES-D-2 Scenario No.: 1 Event No.: 8 Page 5 of 6 Small Break LOCA: (M, ALL)
Applicant's Actions or Behavior The SRO should GO TO the LOSCM Tab per the Parallel Actions page of the EOP Subsequent Actions section. LOSCM Tab will:
Ensure that Rule #2 is in progress or complete.
Verify that station ASW is NOT feeding any SG.
Verify that the LOSCM is NOT caused by excessive heat transfer.
Verify transfer to LOCA CD tab not required due to no LPI flow.
Verify that the SSF is NOT activated.
Verify all the following conditions exist:
~ NO RCPs are operating
~ HPI flow exists in both HPI headers
~ Adequate Total HPI flow per figure 1 (Total Required HPI Flow)
Open 1 AS-40 while closing 1 MS-47.
Control steaming and feed rates on all intact SGs to maintain cooldown rate within Tech Spec limits:
~ Tc ~ 280°F
- 50°FI y; hour
~ Tc < 280°F
- 25°FI Y; hour Utilize TBVs GO TO Step 92.
Close 1 RC-4 (No HPI forced cooling in progress)
Close 1GWD-17, 1HP-1, 1 HP-2, 1 RC-3.
Maintain SG pressure < RCS pressure utilizing either TBVs or ADVs (TBVs).
Verify primary to secondary heat transfer exists.
Initiate Encl 5.16 (SG Tube-to-Shelll1 T Control).
Verify CETCs increasing.
Verify required RCS makeup flow NOT within normal makeup capability.
GO TO LOCA CD tab.
Page 17 of 19
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: I Event No.: 8 Page 6 of 6 Event
Description:
Small Break LOCA: (M, ALL)
Time Position
[
Applicants Actions or Behavior Crew response:
SRO LOCACD tab:
Ensure all RBCUs in low speed.
Open 1LPSW-18.
Open 1 LPSW-21.
Open 1 LPSW-24.
Initiate End 5.35 (Containment Isolation).
Start all RB Aux fans.
Initiate End 5.36 (Equipment Alignment For Plant Shutdown).
Select OFF for both digital channels on AFIS HEADER A and B.
Notify Chemistry to sample the RCS boron hourly Initiate determination of minimum required boron concentration for MODE 5 using either of the following:
Reactor Engineer PT/i/A/i 103/015 (Reactivity Balance Procedure)
Initiate steaming all intact SGs to cooldown to cooldown plateau at 50°F/Y 2 hr using either of the following:
TBVs ADVs Event and exam is complete when directed by the Lead Examiner.
Page 18 of 19 Appendix D Op-Test No.: __
Event
Description:
Time Position SRO Scenario Outline Form ES-D-2 Scenario No.: 1 Event No.: 8 Page 6 of 6 Small Break LOCA: (M, ALL)
Applicant's Actions or Behavior Crew response:
LOCA CD tab:
Ensure all RBCUs in low speed.
Open 1LPSW-18.
Open 1 LPSW-21.
Open 1 LPSW-24.
Initiate Ene! 5.35 (Containment Isolation).
Start all RB Aux fans.
Initiate Ene! 5.36 (Equipment Alignment For Plant Shutdown).
Select OFF for both digital channels on AFIS HEADER A and B.
Notify Chemistry to sample the RCS boron hourly Initiate determination of minimum required boron concentration for MODE 5 using either of the following:
Reactor Engineer PT/1/A/1103/015 (Reactivity Balance Procedure)
Initiate steaming all intact SGs to cooldown to cooldown plateau at ~ 50°F/Yz hr using either of the following:
TBVs ADVs Event and exam is complete when directed by the Lead Examiner.
Page 18 of 19
Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS 1.
CT-18, Turbine Trip 2.
CT-I, Trip All RCPs
CT-27, Implementation of Control Room Habitability Guidance Page 19 of 19 Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS
- 1. CT-18, Turbine Trip
- 2. CT-1, Trip All RCPs
- 4. CT-27, Implementation of Control Room Habitability Guidance Page 19 of 19
Simulator BrieflTurnover SAFETYIPRA RISK (OSM)
SAFETY: Take a Minute PRA Risk Status: GREEN F
UNIT 0 (OSM)
SSF Operable: Yes KHUs Operable: UI
- OH, U2
- UG LOTs Operable: 2 Fuel Handling: None L
UNIT STATUS (CR SRO)
Mode: 1 Unit I Simulator Reactor Power: 65%
Gross MWE: 586 RCS Leakage:.025 gpm Mode: 1 Unit 2 Other Units 100% Power EFDW Backup: Yes Mode: 1 Unit 3 100% Power EFDW Backup: Yes Technical SpecificationslSLC Items (CR SRO)
Corn ponentlTrain OOS DatelTime Restoration Required DatelTirne TSISLC #
Reactivity Management (CR SRO)
RCS Boron: 30 ppmB I Gp 7 Rod Position: 79%
II Batch additions as required for volume control.
Human Performance Emphasis (OSM)
Procedure Use and Adherence Shift Turnover Items (CR SRO)
Primary 492 EFPD Two hours ago power was decreased from 100% for possible work on the 1A Main FDW pump.
Rx Engineering is developing a maneuvering plan to maintain current power level.
Secondary 1SSH-1, 1SSH-3, 1SD-2, 1SD-5,1SD-140,ISD-303,1SD-355,ISD-356 and ISD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 PR-i, 1 PR-6, 1 LPSW-i, 1 LPSW-2, I LPSW-3, I FDW-80, I CF-5, 1 CF-6, I LP-i and 1 LP-2 breakers open per the appropriate system operating procedures.
Unit 3 has the Aux Steam Header OP/i/Ni 102/004 Operation at Power in progress. Enc. 4.2 is complete up through step 2.19.
After shift turnover, place the IA Main FDW pump on Handjack per 0P111A111061002 B.10 (Placing IA FDWPT On Handjack)
Scenario 1 RO Simulator BrieflTurnover SAFETY/PRA RISK (OSM)
I 3Ar~"1 : Take a Minute I PRA Risk Status: GREEN UNIT 0 (OSM SSF 0 II II 's Operable: U1 - OH, U2 - UG LeTs Operable: 2 II Fuel Handling: None II UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 65%
Mode: 1 Mode: 1 Gross MWE: 586 100% Power 100% Power RCS Leakage:.025 gpm EFOW Backup: Yes EFOW Backup: Yes Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration Required TS/SLC #
Date/Time Date/Time Shift Turnover Items (CR SRO)
Primary 492 EFPO Two hours ago power was decreased from 100% for possible work on the 1A Main FOW pump.
Rx Engineering is developing a maneuvering plan to maintain current power level.
Secondary 1 SSH-1, 1 SSH-3, 1 SO-2, 1 SO-5, 1 SO-140, 1 SO-303, 1 SO-355, 1 SO-356 and 1 SO-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 PR-1, 1 PR-6, 1 LPSW-1, 1 LPSW-2, 1 LPSW-3, 1 FOW-80, 1 CF-5, 1 CF-6, 1 LP-1 and 1 LP-2 breakers open per the appropriate system operating procedures.
Unit 3 has the Aux Steam Header OP/1/A/1102/004 Operation at Power in progress. Enc. 4.2 is complete up through step 2.19.
After shift turnover, place the 1A Main FDW pump on Handjack per OP/1/Al1106/002 B.10 (Placing 1A FDWPT On Handjack)
Reactivity Management (CR SRO)
RCS Boron: 30 ppm B I Gp 7 Rod Position: 79%
1/ Batch additions as required for volume control.
Human Performance Emphasis (OSM)
Procedure Use and Adherence Scenario 1 RO
Appendix D Scenario Outline Form ES-D-1 3/10 Facility:
Oconee Scenario No.: 2 Op-Test No.:
I Examiners:
Operators:
Initial Conditions:
100% Reactor power Turnover:
SASS in Manual CS in manual and ready to return to Auto Event Maif. No.
Event Type*
Event No.
Description Oa Pre-Insert SASS in Manual Ob ICS in Manual 1
N, OATC, SRO Place ICS in Auto 2
Override C, BOP, SRO Operating LPSW Pump trips and Standby fails to start (TS)
Updater MPIO21 C, BOP, Inadvertent ES Channels 2 actuation (TS)
OATC, SRO 4
MCS 004 I, OATC, SRO Controlling Tave fails high 5
Override C, BOP, SRO 1A CBP Trip and lB CBP fails to Auto Start.
MSS 460 6
MSS 010 M, ALL Loss of Main and Emergency Feedwater MSS 020 MSS 260 LOHT Tab MSS 270 CBP feed 7
Override ALL CBPs trip I HPI Forced cooling I HP-26 fails to open HPI CD Tab (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 3/10 Facility: Oconee Scenario No.: 2 Op-Test No.:
1 Examiners:
Operators:
SRO OATC BOP Initial Conditions:
1 00% Reactor power Turnover:
SASS in Manual ICS in manual and ready to return to Auto Event Malf. No.
Event Type*
Event No.
Description Oa Pre-Insert SASS in Manual Ob ICS in Manual 1
N, OATC, SRO Place ICS in Auto 2
Override C, BOP, SRO Operating LPSW Pump trips and Standby fails to start (TS)
Updater 3
MPI021 C, BOP, Inadvertent ES Channels 2 actuation (TS)
OATC, SRO 4
MCS 004 I, OATC, SRO ControllinQ Tave fails hiQh 5
Override C, BOP, SRO 1 A CBP Trip and 1 B CBP fails to Auto Start.
MSS 460 6
MSS 010 M,ALL Loss of Main and Emergency Feedwater MSS 020 LOHT Tab MSS 260 MSS 270 CBP feed 7
Override ALL CBPs trip / HPI Forced cooling 1 HP-26 fails to open HPI CD Tab (N)ormal (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: I Page 1 of 2 Event
Description:
Place ICS in AUTO: (C; OATC, SRO)
Time Position Applicants Actions or Behavior Crew response:
OATC/SRO OP/i/Ni 102/004 A End. 4.4 will direct the OATC to:
Ensure RATE SET thumbwheels at 0.0.
IF TURBINE MASTER is in HAND, perform Section 3 (Placing Turbine To Auto).
Turbine is in AUTO IF either TBV is in HAND, perform Section 4 (Placing TBV To Auto).
TBVsareinAUTO IF REACTOR MASTER OR DIAMOND is in manual, perform Section 5 (Placing Rx To Auto).
IF Rx Master is in HAND, perform the following:
Ensure DIAMOND is in MANUAL.
Place REACTOR MASTER to AUTO.
IF selected Tave (01 E2086) is different from Tave setpoint (01 E2087) by more than +/- 0.3°F, perform the following:
o Simultaneously ensure 1A and 1 B FDW MASTER in HAND o
On REACTOR MASTER adjust Tave setpoint (01 E2087) towards selected Tave (01 E2086).
o Verify selected Tave is within +/- 0.3°F of Tave setpoint.
o Place DIAMOND in AUTO.
o Return to Section 2 (Procedure).
IF DELTA Tc is in HAND, perform Section 6 (Placing DELTA Tc To Auto).
DELTA Tc is in AUTO Page 2 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Page 1 of 2 Event
Description:
Place ICS in AUTO: (C; OATC, SRO)
Time Position Applicant's Actions or Behavior Crew response:
OATC/SRO OP/1/A/1102/004 A Encl. 4.4 will direct the OATC to:
Ensure "RATE SET" thumbwheels at 0.0.
IF TURBINE MASTER is in "HAND", perform Section 3 (Placing Turbine To Auto).
Turbine is in AUTO IF either TBV is in "HAND", perform Section 4 (Placing TBV To Auto).
TBVs are in AUTO IF REACTOR MASTER OR DIAMOND is in manual, perform Section 5 (Placing Rx To Auto).
IF Rx Master is in "HAND", perform the following:
Ensure DIAMOND is in "MANUAL".
Place REACTOR MASTER to "AUTO".
IF selected Tave (01 E2086) is different from Tave setpoint (01 E2087) by more than +/- 0.3°F, perform the following:
o Simultaneously ensure 1A and 1 B FDW MASTER in "HAND" o
On REACTOR MASTER adjust Tave setpoint (01 E2087) towards selected Tave (01 E2086).
o Verify selected Tave is within +/- 0.3°F of Tave setpoint.
o Place DIAMOND in "AUTO".
o Return to Section 2 (Procedure).
IF DELTA Tc is in "HAND", perform Section 6 (Placing DELTA Tc To Auto).
DELTA Tc is in "AUTO" Page 2 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: I Page 2 of 2 Event
Description:
Place ICS in AUTO: (C; OATC, SRO)
Time Position Applicants Actions or Behavior Crew response:
OATC/SRO IF STM GENERATOR MASTER or either FDW MASTER is in HAND, perform Section 7 (Placing FDW To Auto).
IF SG Master is in HAND, perform the following:
SG Master is in AUTO.
IF either 1A OR lB FDW Master is NOT in AUTO, perform the following:
Select 1A and lB FDW MASTER to MEAS VAR IF both 1A and lB FDW Master Measured Variables are on the caret:
o Select 1A and lB FDW MASTER to POS o
Simultaneously ensure 1A and lB FDW MASTER in AUTO IF any FDW valves are in HAND, perform Section 8 (Placing FDW Valves To Auto).
All FDW valves are in AUTO IF either Main FDW Pump is in HAND, perform Section 9 (Placing Main FDW Pumps To Auto).
Both FDW pumps are in AUTO.
NOTE: 105 must be in full auto before adjusting any setpoint to minimize possible CTP changes. (R.M.)
The SRO will verify lOS in full Auto.
When the ICS has been placed in AUTO, or when directed by the Lead Examiner this event is completed.
Page3of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Page 2 of 2 Event
Description:
Place ICS in AUTO: (C; OATC, SRO)
Position Applicant's Actions or Behavior Crew response:
OATC/SRO IF STM GENERATOR MASTER or either FDW MASTER is in "HAND",
perform Section 7 (Placing FDW To Auto).
IF SG Master is in "HAND", perform the following:
SG Master is in AUTO.
IF either 1A OR 1 B FDW Master is NOT in "AUTO", perform the following:
Select 1 A and 1 B FDW MASTER to "MEAS VAR" IF both 1A and 1B FDW Master Measured Variables are on the caret:
o Select 1A and 1 B FDW MASTER to "POS" o
Simultaneously ensure 1A and 1 B FDW MASTER in "AUTO" IF any FDW valves are in "HAND", perform Section 8 (Placing FDW Valves To Auto).
All FDW valves are in AUTO IF either Main FDW Pump is in "HAND", perform Section 9 (Placing Main FDW Pumps To Auto).
Both FDW pumps are in AUTO.
NOTE: ICS must be in full auto before adjusting any setpoint to minimize possible CTP changes. (R.M.)
The SRO will verify ICS in full Auto.
When the ICS has been placed in AUTO, or when directed by the Lead Examiner this event is completed.
Page 3 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 2 Page 1 of 1 Event
Description:
Operating LPSW pump trips, Standby fails to auto start:
Time Position ApplicanVs Actions or Behavior Plant response:
1 SA-91A-9 (LPSW Header A Press Low)
LPSW Header A/B Pressure Low - gauge B LPSW pump trips Crew response:
Refer to ARG for 1 SA-9/A-9 (LPSW Header A/B Press Low)
Refer to AP124 (Loss of LPSW)
AP/24 (Loss of LPSW)
SRO/BOP Verify Unit 1 is going to handle LPSW system operations.
Determine no LPSW pump is cavitating Start available (NOT previously cavitating) LPSW pumps, as necessary, to raise LPSW header pressure.
Verify normal LPSW System operation is restored.
SRO Note: The SRO should direct a call to SPOC to troubleshoot the reason for the LPSW pump tripping and the Auto Start failure.
The SRO should refer to TS:
TS 3.7.7 (Low Pressure Service Water System) Condition A applies.
Restore required LPSW pump to operable status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time.
TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition A. Restore Auto-Start Circuitry to operable. 7 day completion time.
Event is complete when SRO has referred to TS or when directed by the Lead Examiner.
Page4ofl6 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Page 1 of 1 Event
Description:
Operating LPSW pump trips, Standby fails to auto start:
Time Position SRO/BOP Applicant's Actions or Behavior Plant response:
1 SA-9/A-9 (LPSW Header A Press Low)
LPSW Header AlB Pressure Low - gauge B LPSW pump trips Crew response:
Refer to ARG for 1 SA-9/A-9 (LPSW Header AlB Press Low)
~ Refer to AP/24 (Loss of LPSW)
AP/24 (Loss of LPSW)
Verify Unit 1 is going to handle LPSW system operations.
Determine no LPSW pump is cavitating Start available (NOT previously cavitating) LPSW pumps, as necessary, to raise LPSW header pressure.
Verify normal LPSW System operation is restored.
SRO Note: The SRO should direct a call to SP~C to troubleshoot the reason for the LPSW pump tripping and the Auto Start failure.
The SRO should refer to TS:
TS 3.7.7 (Low Pressure Service Water System) Condition "A" applies.
Restore required LPSW pump to operable status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time.
TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition "A". Restore Auto-Start Circuitry to operable. 7 day completion time.
Event is complete when SRO has referred to TS or when directed by the Lead Examiner.
Page 4 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 3 Page 1 of 3 Event
Description:
Inadvertent ES Channels 2 actuation: (C, OATC/BOPISRO)
Time Position j
Applicants Actions or Behavior Plant response:
Statalarms:
iSA-i/B-iC, ES CHANNEL 2 TRIP Control Board indications:
ES Channel 2 actuate HPI Injection in B header Letdown isolated Keowee emergency start Crew response:
Determine that ES actuation was NOT valid and inform the SRO.
BOP Crew may perform Plant Transient Response.
ALL The SRO should enter AP/42 (Inadvertent ES Actuation)
SRO AP/42 (Inadvertent ES Actuation) Actions:
Place HPI in MANUAL on RZ Modules BOP Throttle HPI Secure the 1C HPI pump Close 1HP-25 Direct the BOP to perform End. 5.1 (Side Board Action)
Notify the OSM and STA Direct the OATC to perform End. 5.2 (Letdown Restoration)
Page 5 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Page 1 of 3 Event
Description:
Inadvertent ES Channels 2 actuation: (C, OATC/BOP/SRO)
Time Position BOP ALL SRO BOP Applicant's Actions or Behavior Plant response:
Statalarms:
1SA-1/B-10, ES CHANNEL 2 TRIP Control Board indications:
ES Channel 2 actuate HPI Injection in "B" header Letdown isolated Keowee emergency start Crew response:
Determine that ES actuation was NOT valid and inform the SRO.
Crew may perform Plant Transient Response.
The SRO should enter AP/42 (Inadvertent ES Actuation)
AP/42 (Inadvertent ES Actuation) Actions:
Place HPI in MANUAL on RZ Modules Throttle HPI Secure the 1 C HPI pump Close 1 HP-25 Direct the BOP to perform End. 5.1 (Side Board Action)
Notify the OSM and STA Direct the OATC to perform End. 5.2 (Letdown Restoration)
Page 5 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 3 Page 2 of 3 Event
Description:
Inadvertent ES Channels 2 actuation: (C, OATCIBOP/SRO)
Time Position Applicants Actions or Behavior Crew response:
BOP BOP will perform End. 5.1 (Side Board Action)
Open 1 HP-20 and 1 HP-21 (Seal Return)
Open 1 HP-228, 226, 232, and 230 (Seal Return Stop)
Place the following in MANUAL on the RZ Module and OPEN:
1 PR-7, 1 PR-9 (RB RIAs) 1PR-8, 1PR-10 (RB RIAs)
Start the 1 RIA-47 RB RIA sample pump from the ENABLE CONTROLS screen on the RIA View Node.
NOTE: Must select OFF on sample pump before it can be restarted.
OATC End. 5.2 (Letdown Restoration)
Verify CC pump operating Verify letdown is isolated Close 1HP-5 (LETDOWN ISOLATION)
Open 1HP-1, 1HP-2, 1HP-3, and 1HP-4 (lAand lB Letdown Cooler Inlet and Outlet)
Close 1HP-6 (LETDOWN ORIFICE STOP)
Close *1HP-7 (LETDOWN CONTROL)
Open 1HP-5 (LETDOWN ISOLATION)
Adjust 1 HP-7 for 20 gpm letdown Open 1HP-6 (LETDOWN ORIFICE STOP)
Adjust 1 HP-7 to control desired letdown flow (75 gpm)
Page 6 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Page 2 of 3 Event
Description:
Inadvertent ES Channels 2 actuation: (C, OATC/BOP/SRO)
Time Position BOP OATC Applicant's Actions or Behavior Crew response:
BOP will perform Enc!. 5.1 (Side Board Action)
Open 1 HP-20 and 1 HP-21 (Seal Return)
Open 1 HP-228, 226, 232, and 230 (Seal Return Stop)
Place the following in MANUAL on the RZ Module and OPEN:
1 PR-7, 1 PR-9 (RB RIAs) 1 PR-8, 1 PR-1 0 (RB RIAs)
Start the 1 RIA-47 RB RIA sample pump from the ENABLE CONTROLS screen on the RIA View Node.
NOTE: Must select "OFF" on sample pump before it can be restarted.
Encl. 5.2 (Letdown Restoration)
Verify CC pump operating Verify letdown is isolated Close 1HP-5 (LETDOWN ISOLATION)
Open 1HP-1, 1 HP-2, 1 HP-3, and 1HP-4 (1Aand 1B Letdown Cooler Inlet and Outlet)
Close 1 HP-6 (LETDOWN ORIFICE STOP)
Close 1HP-7 (LETDOWN CONTROL)
Open 1 HP-5 (LETDOWN ISOLATION)
Adjust 1 HP-7 for::::: 20 gpm letdown Open 1 HP-6 (LETDOWN ORIFICE STOP)
Adjust 1 HP-7 to control desired letdown flow (75 gpm)
Page 6 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 3 Page 3 of 3 Event
Description:
Inadvertent ES Channels 2 actuation: (C, OATCIBOPISRO)
Time Position Applicants Actions or Behavior Crew response:
SRO AP142 (Inadvertent ES Actuation) Actions (Continued)
Verify ICS in AUTO Initiate a power decrease to maintain control rods within the desired band by adjusting rate set as necessary and decrease CTP demand setpoint.
Notify Chemistry for RCS and LDST boron sample Notify Rx Engineering to develop a maneuvering plan Place LOAD SHED & STBY BKR 1 and 2 in MANUAL on the RZ Module Dispatch an operator to perform End. 5.3 (SSF Restoration)
Notify SPOC to investigate and repair the failed ES components IAAT Rx power is stable THEN initiate evaluation of NI operability in accordance with OP/1/AJ1IO2/004 (Operation At Power) Limits and Precautions.
Initiate logging TS/SLC Entry/Exit as applicable, lAW End. 5.4 (TSISLC Requirements)
(TS) o TS 3.3.7 ESPS Digital Automatic Actuation Logic Channels Condition A; Place associated component(s) in ES configuration OR Declare the associated component(s) inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
o TS 3.3.6 ESPS Manual Instrumentation Condition A; Restore channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o TS 3.4.15 RCS Leakage Detection Instrumentation Condition B; Analyze grab samples of the containment atmosphere once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (can be exited once End. 5.1, Side Board Actions completed) o TS 3.4.9 Pressurizer Condition A; Restore level within limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Note: Should enter ONLY if Pzr level exceeds 260 inches WHEN all the following exist:
o Cause of inadvertent ES resolved o
ES Channel reset is desired o
OSM concurs THEN continue.
When plant is stable and Letdown has been restored, or when directed by the Lead Examiner the event is completed.
Page 7 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Page 3 of 3 Event
Description:
Inadvertent ES Channels 2 actuation: (C, OATC/BOP/SRO)
Time Position SRO Applicant's Actions or Behavior Crew response:
AP/42 (Inadvertent ES Actuation) Actions (Continued)
Verify ICS in AUTO Initiate a power decrease to maintain control rods within the desired band by adjusting rate set as necessary and decrease CTP demand setpoint.
Notify Chemistry for RCS and LDST boron sample Notify Rx Engineering to develop a maneuvering plan Place LOAD SHED & STBY BKR 1 and 2 in MANUAL on the RZ Module Dispatch an operator to perform End. 5.3 (SSF Restoration)
Notify SPOC to investigate and repair the failed ES components IAAT Rx power is stable THEN initiate evaluation of NI operability in accordance with OP/1/A/11 02/004 (Operation At Power) Limits and Precautions.
Initiate logging TS/SLC Entry/Exit as applicable, lAW Encl. 5.4 (TS/SLC Requirements)
(TS) o TS 3.3.7-ESPS Digital Automatic Actuation Logic Channels Condition A; Place associated component(s) in ES configuration OR Declare the associated component(s) inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
o TS 3.3.6 - ESPS Manual Instrumentation Condition A; Restore channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o TS 3.4.15 - RCS Leakage Detection Instrumentation Condition B; Analyze grab samples of the containment atmosphere once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (can be exited once End. 5.1, Side Board Actions completed) o TS 3.4.9 - Pressurizer Condition A; Restore level within limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Note: Should enter ONLY if Pzr level exceeds 260 inches WHEN all the following exist:
o Cause of inadvertent ES resolved o
ES Channel reset is desired o
OSM concurs THEN continue.
When plant is stable and Letdown has been restored, or when directed by the Lead Examiner the event is completed.
Page 7 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
Controlling Tave fails HIGH (I, OATC, SRO)
Time_j Position Applicants Actions or Behavior Plant response:
1SA-02/A-12, lOS Tracking, will actuate due to neutron and feedwater cross-limits.
Controlling Tave will indicate 596.4° F. (Failed HIGH)
Actual loop A & B Tave will decrease until operator stops transient.
RCS pressure and temperature will decrease.
Crew response:
SRO/OATC SRO OATC Statalarms; candidates perform Plant Transient Response process to stabilize the plant.
Verbalize to the SRO reactor power level and direction of movement.
Place the Diamond and both FDW Masters in manual and adjust.
FDW should be decreased to below pre-transient level and Control Rods may be inserted to stop RCS pressure increase The SRO should:
Refer to AP!28, CS Instrument Failures Contact SPOC to repair controlling Tave.
Note: The ICS remains in manual for the rest of scenario.
AP128 (lOS Instrument Failures)
Verify plant conditions are controlled or stable as indicated by the following:
NI power change <2% from current NI power indication AND thermal power best pre-transient power level Tave change < 2°F from current Tave indication THP/SG Outlet Press. change <30 psig from current THP/SG Outlet Press.
RCS pressure change < 150 psig from current RCS pressure Provide control bands see Placard (OMP 1-18)
Verify a power transient has occurred Notify Rx Engineering to discuss need for a power maneuvering plan GO TO section 4A (RCS Temperature Failure)
Notify SPOC to repair failed instrument PERFORM an instrumentation surveillance using applicable table in End 5.3 (ICS Instrument Surveillances) for the failed instrument.
When The SRO Directs Performing End. 5.3 Or At The Discretion Of The Lead Examiner this event is completed.
BOP Page 8 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
Controlling Tave fails HIGH (I, OATC, SRO)
Time Position SROIOATC SRO OATC BOP Applicant's Actions or Behavior Plant response:
1SA-02/A-12, ICS Tracking, will actuate due to neutron and feedwater cross-limits.
Controlling Tave will indicate== 596.4° F. (Failed HIGH)
Actual loop A & B Tave will decrease until operator stops transient.
RCS pressure and temperature will decrease.
Crew response:
Statalarms; candidates perform "Plant Transient Response" process to stabilize the plant.
Verbalize to the SRO reactor power level and direction of movement.
Place the Diamond and both FDW Masters in manual and adjust.
FDW should be decreased to below pre-transient level and Control Rods may be inserted to stop RCS pressure increase The SRO should:
Refer to AP/28, ICS Instrument Failures Contact SP~C to repair controlling Tave.
Note: The ICS remains in manual for the rest of scenario.
AP/28 (ICS Instrument Failures)
Verify plant conditions are controlled or stable as indicated by the following:
NI power change < 2% from current NI power indication AND thermal power best::; pre-transient power level Tave change < 2°F from current Tave indication THP/SG Outlet Press. change < 30 psig from current THP/SG Outlet Press.
RCS pressure change < 150 psig from current RCS pressure Provide control bands - see Placard (OMP 1-18)
Verify a power transient has occurred Notify Rx Engineering to discuss need for a power maneuvering plan GO TO section 4A (RCS Temperature Failure)
Notify SP~C to repair failed instrument PERFORM an instrumentation surveillance using applicable table in Encl 5.3 (ICS Instrument Surveillances) for the failed instrument.
When The SRO Directs Performing Encl. 5.3 Or At The Discretion Of The Lead Examiner this event is completed.
Page 8 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 5 Page 1 of 2 Event
Description:
IA CBP Trip and lB CBP fails to AUTO Start: (C, BOPISRO)
Time Position Applicants Actions or Behavior Plant Response:
1SA-2/A-11 ICSRUNBACK BOPISRO 1SA-8/A-1 FDW SUCTION PRESSURE LOW Powdex Bypasses at 360 psig FDWP Suction Pressure.
1 C-61 opens bypassing the Hydrogen Coolers © 235 psig (on either FDWP/ 2 out of 3 logic) FDWP Suction Pressure Crew Response:
Crew will take one of two paths:
Path #1 SRO!BOP Crew will manually start the 1 B CBP
/OATC Refer to ARG Path #2 Crew will perform Plant Transient Response (PTR)
BOP should determine that a valid ICS runback signal is present but the runback is NOT in progress (for C/FDW suction pressure) due to ICS in MANUAL.
SRO will enter AP/1 (Unit Runback) and go to section 4D Direct the OATC to manually reduce power with FDW and the Diamond until the runback clears. ( 85%)
When the plant is stable/controllable OR as directed by ARG 1 SA-8/A-1 FDW SUCTION PRESSURE LOW the team should elect to manually start the lB CBP (standby).
Manual Actions IF standby Condensate Booster Pump has NOT started, start any available CBP manually Note: If the unit trips initiate event 6.
The event is complete when the reactor trips, the plant is stabilized at 85% power, or when determined by the Lead Examiner.
Page 9 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Page 1 of 2 Event
Description:
1A CBP Trip and 1B CBP fails to AUTO Start: (C, BOP/SRO)
Time Position BOP/SRO SRO/BOP
/OATC Applicant's Actions or Behavior Plant Response:
1 SA-2/A-11 ICS RUNBACK 1 SA-8/A-1 FDW SUCTION PRESSURE LOW Powdex Bypasses at 360 psig FDWP Suction Pressure.
1 C-61 opens bypassing the Hydrogen Coolers @ 235 psig (on either FDWP/2 out of 3 logic) FDWP Suction Pressure Crew Response:
Crew will take one of two paths:
Path #1 Crew will manually start the 1 B CBP Refer to ARG Path #2 Crew will perform Plant Transient Response (PTR)
BOP should determine that a valid ICS runback signal is present but the runback is NOT in progress (for C/FDW suction pressure) due to ICS in MANUAL.
SRO will enter AP/1 (Unit Runback) and go to section 4D Direct the OATC to manually reduce power with FDW and the Diamond until the runback clears. (=== 85%)
When the plant is stable/controllable OR as directed by ARG 1SA-8/A-1 FDW SUCTION PRESSURE LOW the team should elect to manually start the '1 B' CBP (standby).
Manual Actions IF standby Condensate Booster Pump has NOT started, start any available CBP manually Note: If the unit trips initiate event 6.
The event is complete when the reactor trips, the plant is stabilized at
- 85% power, or when determined by the Lead Examiner.
Page 9 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 5 Page 2 of 2 Event
Description:
IA CBP Trip and lB CBP fails to AUTO Start: (C, BOPISRO)
Time Position Applicants Actions or Behavior Crew Response:
Note: If the plant does NOT trip, the crew may reset I C-61 and restore the SRO/BOP Powdex as described below.
/OATC Reset 10-61 when FDWP suction pressure 235 psig (OP/i/Ni 106/002 Condensate and Feedwater, Enclosure 4.22-Resetting 10-61 Controller) as follows:
Ensure 10-61 is in Manual Manually adjust 1C-6i controller demand to 85-95%
Verify 01D1417 (Generator Water Cooler Condensate Duff) value FALSE Throttle closed 10-61 to establish 5-16 ft H20 LP Ensure adjusted 10-61 setpoint to match actual AP Ensure 10-61 to AUTO Restore Powdex to service per (OP/I/Ni 106/002 Condensate and Feedwater; Enclosure 4.19-Placing Powdex In/Out of Service)
When FDWP suction pressure is > 360 psig place the Powdex In Service by slowly throttling closed on iC-14/15 while maintaining CBP suction pressure 70 psig.
Note: If the unit trips initiate event 6.
The event is complete when the reactor trips, the plant is stabilized at 85% power, or when determined by the Lead Examiner.
Page 10 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Page 2 of 2 Event
Description:
1A CBP Trip and 1B CBP fails to AUTO Start: (C, BOP/SRO)
Time Position SRO/BOP
/OATC Applicant's Actions or Behavior Crew Response:
Note: If the plant does NOT trip, the crew may reset 1 C-61 and restore the Powdex as described below.
Reset 1 C-61 when FDWP suction pressure ;::235 psig (OP/1/A/11 06/002 Condensate and Feedwater, Enclosure 4.22-Resetting 1 C-61 Controller) as follows:
Ensure 1C-61 is in Manual Manually adjust 1 C-61 controller demand to 85-95%
Verify 0101417 (Generator Water Cooler Condensate Diff) value "FALSE" Throttle closed 1 C-61 to establish 5-16 ft H20 L\\P Ensure adjusted 1 C-61 setpoint to match actual L\\P Ensure 1 C-61 to "AUTO" Restore Powdex to service per (OP/1/A/11 06/002 Condensate and Feedwater; Enclosure 4.19-Placing Powdex In/Out of Service)
When FDWP suction pressure is > 360 psig place the Powdex In Service by slowly throttling closed on 1C-14/15 while maintaining CBP suction pressure;:: 70 psig.
Note: If the unit trips initiate event 6.
The event is complete when the reactor trips, the plant is stabilized at
- 85% power, or when determined by the Lead Examiner.
Page 10 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 6 Page 1 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position Applicants Actions or Behavior Plant Response:
When directed by the Lead Examiner, a Loss of Main and Emergency Feedwater will occur.
Crew Response:
Perform Immediate Manual Actions (IMAs)
Depress REACTOR TRIP pushbutton.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
SRO/OATC Verify all turbine stop valves closed.
Verify RCP seal injection available.
BOP will perform a Symptom Check and initiate Rule 3 (Loss of Main and I or Emergency Feedwater)
SRO will transfer to the Loss Of Heat Transfer Tab BOP Rule 3 IAAT NO SGs can be fed with FDW (MainlCBPlEmergency), AND any of the following exist:
o RCS pressure reaches 2300 psig OR NDT limit o
Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Start EFDW pumps to feed all intact SGs.
Place the following in MANUAL and close:
1FDW-315 1FDW-316 Verify both of the following:
Any CBP operating TBVs available on an intact SG Select OFF for both digital channels on AFIS HEADER A.
Select OFF for both digital channels on AFIS HEADER B.
Page 11 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 1 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position SRO/OATC Applicant's Actions or Behavior Plant Response:
When directed by the Lead Examiner, a Loss of Main and Emergency Feedwater will occur.
Crew Response:
Perform Immediate Manual Actions (IMAs)
Depress REACTOR TRIP pushbutton.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed.
Verify RCP seal injection available.
BOP will perform a Symptom Check and initiate Rule 3 (Loss of Main and /
or Emergency Feedwater)
SRO will transfer to the Loss Of Heat Transfer Tab BOP Rule 3 IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
oRCS pressure reaches 2300 psig OR NOT limit o
Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Start EFDW pumps to feed all intact SGs.
Place the following in MANUAL and close:
1FDW-315 1FDW-316 Verify both of the following:
Any CBP operating TBVs available on an intact SG Select OFF for both digital channels on AFIS HEADER A.
Select OFF for both digital channels on AFIS HEADER B.
Page 11 of 16
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 6 Page 2 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position Applicants Actions or Behavior Crew Response:
Rule 3 (Continued)
BOP Place 1 FDW-33 and I FDW-42 control switches in OPEN:
Simultaneously position Startup Control valves (1 FDW-35 1 FDW-44) 10
- 20% open on all intact SGs:
Perform the following:
Place 1 FDW-31 switch in CLOSE.
Place 1 FDW-40 switch in CLOSE.
Close 1 FDW-32.
Close 1FDW-41.
Lower SG pressure in available SGs to 500 psig.
Control FDW flow to stabilize RCS P/T by throttling the Startup Control valves and TBVs as necessary:
Place 1 FDW-38 and 1 FDW-47 switches to OPEN Place 1 FDW-36 and 1 FDW-45 switches to CLOSE Dispatch an operator to perform End 5.26 (Manual Start of TDEFDWP).
Verify cross-tie with Unit 2 is desired.
Dispatch an operator to open 2FDW-313 and 2FDW-314 Dispatch an operator to 1 FDW-31 3 and have them notify the CR when in position.
NotifyUnit2to:
Manually Close 2FDW-315 & 316.
Start their U2 TDEFWP WHEN, either of the following exists:
1 FDW-31 3 Operator in position OR Unit 1 TDEFWP has been manually started; THEN continue.
Page 12 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 2 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position BOP Applicant's Actions or Behavior Crew Response:
Rule 3 (Continued)
Place 1 FDW-33 and 1 FDW-42 control switches in OPEN:
Simultaneously position Startup Control valves (1 FDW-35 1 FDW-44) 10
- 20% open on §l! intact SGs:
Perform the following:
Place 1 FDW-31 switch in CLOSE.
Place 1 FDW-40 switch in CLOSE.
Close 1 FDW-32.
Close 1FDW-41.
Lower SG pressure in available SGs to::::: 500 psig.
Control FDW flow to stabilize RCS PIT by throttling the Startup Control valves and TBVs as necessary:
Place 1 FDW-38 and 1 FDW-47 switches to OPEN Place 1 FDW-36 and 1 FDW-45 switches to CLOSE Dispatch an operator to perform Ene! 5.26 (Manual Start of TDEFDWP).
Verify cross-tie with Unit 2 is desired.
Dispatch an operator to open 2FDW-313 and 2FDW-314 Dispatch an operator to 1 FDW-313 and have them notify the CR when in position.
Notify Unit 2 to:
Manually Close 2FDW-315 & 316.
Start their U2 TDEFWP WHEN, either of the following exists: 1 FDW-313 Operator in position OR Unit 1 TDEFWP has been manually started; THEN continue.
Page 12 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 6 Page 3 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position Applicants Actions or Behavior Crew Response:
Loss Of Heat Transfer Tab SRO IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND jy of the following exist:
o RCS pressure reaches 2300 psig OR NDT limit o
Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
NOTE: IAI RCP provides the best Pzr spray.
Reduce operating RCPs to one pump/loop.
WHEN y of the following exists:
BOP o
Unit 1 EFDW available o
EFDW aligned from another unit THEN GO TO Step 48 BOP/OATC EOP Enclosure 5.5 Utilize the following as necessary to maintain Pzr level >1OQ[18Qacc]:
o Standby HPI pump o
1HP-26 o
1HP-7 o
1HP-5 o
1 HP-i 20 setpoint or valve demand IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
o Obtain SRO concurrence to reduce running HPI pumps.
o Secure the desired HPI pumps.
o Place secured HPI pump switch in AUTO, if desired.
IAAT LDST level CANNOT be maintained, o
. Open 1HP-24.
o
. Open 1HP-25 o
Close 1HP-16.
When RCS temperature is stabilized on Condensate Booster Pump feed, or when directed by the Lead Examiner this event is completed.
Page 13 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 3 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position SRO BOP BOP/OATC Applicant's Actions or Behavior Crew Response:
Loss Of Heat Transfer Tab IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
oRCS pressure reaches 2300 psig OR NDT limit o
Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
NOTE: 1A1 RCP provides the best Pzr spray.
Reduce operating RCPs to one pump/loop.
WHEN any of the following exists:
o Unit 1 EFDW available o
EFDW aligned from another unit THEN GO TO Step 48 EOP Enclosure 5.5 Utilize the following as necessary to maintain Pzr level >10Q"[18Q"acc]:
o Standby HPI pump o
1 HP-26 o
1 HP-7 o
1 HP-5 o
1 HP-120 setpoint or valve demand IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
o Obtain SRO concurrence to reduce running HPI pumps.
o Secure the desired HPI pumps.
o Place secured HPI pump switch in AUTO, if desired.
IAAT LDST level CANNOT be maintained, o. Open 1 HP-24.
o. Open 1 HP-25 o
Close 1HP-16.
When RCS temperature is stabilized on Condensate Booster Pump feed, or when directed by the Lead Examiner this event is completed.
Page 13 of 16
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 7 Page 1 of 2 Event
Description:
CBPs Trip, HPI Forced Cooling, Spray Valve Fails Closed (ALL)
Time Position Applicants Actions or Behavior Plant Response:
CBP5 trip Feedwater flow decreases RCS temperature increases Crew Response:
SRO SRO may direct RO to re-perform Rule 3 At 2300 psig RCS pressure, direct performance of Rule 4 (HPI Forced Cooling).
BOP/OATC Rule 4 (CT-14) (Within 5 minutes of meeting criteria)
Start aM available HPI pumps.
Open 1HP-26 and 1HP-27 Note: IHP-26 will NOT open (IHP-4I0 must be opened; per Step below)
Open 1RC-4.
Verify flow exists in y HPI header.
Open PORV. (Switch to OPEN, depress OPEN permit)
Verify at ast two HPI pumps operating.
Verify flow in both HPI headers is in the acceptable region of Figure 1 Open IHP-410 (Flow is unacceptable in IA HPI Header)
Stop all but one RCP (1A1 RCP provides the best Spray flow)
De-energize all Pzr heaters.
Close 1HP-5.
Verify HPI Forced Cooling initiated due to a loss of CBP feed.
Close TBVs, 1 FDW-35 and 1 FDW-44.
Page 14 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Page 1 of 2 Event
Description:
CBPs Trip, HPI Forced Cooling, Spray Valve Fails Closed (ALL)
Time Position Applicant's Actions or Behavior Plant Response:
CBPs trip Feedwater flow decreases RCS temperature increases Crew Response:
SRO SRO may direct RO to re-perform Rule 3 BOP/OATC At 2300 psiq RCS pressure, direct performance of Rule 4 (HPI Forced Cooling).
Rule 4 (CT-14) (Within 5 minutes of meeting criteria)
Open 1 HP-24 and 1 HP-25.
Start ill! available HPI pumps.
Open 1 HP-26 and 1 HP-27 Note: 1HP-26 will NOT open (1HP-410 must be opened; per Step below)
Open 1 RC-4.
Verify flow exists in any HPI header.
Open PORV. (Switch to OPEN, depress OPEN permit)
Verify at least two HPI pumps operating.
Verify flow in both HPI headers is in the acceptable region of Figure 1 Open 1HP-410 (Flow is unacceptable in 1A HPI Header)
Stop all but one RCP (1A 1 RCP provides the best Spray flow)
De-energize all Pzr heaters.
Close 1 HP-5.
Verify HPI Forced Cooling initiated due to a loss of CBP feed.
Close TBVs, 1 FDW-35 and 1 FDW-44.
Page 14 of 16
PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Verify all the following:
At least two HPI pumps operating Acceptable HPI flow exists in both HPI headers per Rule 4 PORV open 1RC-4 open GO TO HPI CD tab.
Verify all of the following exist:
PORV open 1 RC-4 open Two HPI trains injecting CETCs 640°F Ensure all RBCUs in low speed.
Open 1LPSW-18, 1LPSW-21 and 1LPSW-24.
Initiate End 5.35 (Containment Isolation)
Start A & B Outside Air Booster Fans (CT-27)
Notify Unit 3 to start 3A and 3B Outside Air Booster Fans When SRO transfers to HPI CD tab, or when directed by the lead examiner this event is completed.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 7 Page 2 of 2 Event
Description:
CBPs trip, HPI Forced Cooling, Spray Valve Fails Closed (ALL)
Time Position j
Applicants Actions or Behavior Crew Response:
LOHT tab SRO SRO/OATC/
BOP HPI CD tab Page 15 of 16 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Page 2 of 2 Event
Description:
CBPs trip, HPI Forced Cooling, Spray Valve Fails Closed (ALL)
Time Position Applicant's Actions or Behavior Crew Response:
SRO LOHT tab PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Verify all the following:
At least two HPI pumps operating Acceptable HPI flow exists in both HPI headers per Rule 4 PORVopen 1 RC-4 open GO TO HPI CD tab.
SROIOA TCI HPI CD tab BOP Verify.§ll of the following exist:
PORVopen 1RC-4 open Two HPI trains injecting CETCs :s 640°F Ensure all RBCUs in low speed.
Open 1LPSW-18, 1 LPSW-21 and 1 LPSW-24.
Initiate Ene! 5.35 (Containment Isolation)
Start A & B Outside Air Booster Fans (CT-27)
Notify Unit 3 to start 3A and 3B Outside Air Booster Fans When SRO transfers to HPI CD tab, or when directed by the lead examiner this event is completed.
Page 15 of 16
Appendix 0 Scenario Outline Form ES-D-2 CRITICAL TASKS 1.
CT-14, Initiate HPI Cooling 2.
CT-27, Implementation of Control Room Habitability Guidance (Optional if crew progresses this far)
Page 16 of 16 Appendix D Scenario Outline CRITICAL TASKS
- 1. CT-14, Initiate HPI Cooling
- 2. CT-27, Implementation of Control Room Habitability Guidance (Optional if crew progresses this far)
Page 16 of 16 Form ES-D-2
Simulator BrieflTurnover SAFETYIPRA RISK (OSM)
SAFETY: Take a Minute PRA Risk Status: GREEN UNIT 0 (OSM)
SSF Operable: Yes KHUs Operable: UI
- OH, U2
- UG LCTs Operable: 2 Fuel Handling: None Mode: 1 Unit I Simulator Reactor Power: 100%
Gross MWE: 897 RCS Leakage:.01 gpm RBNS Rate: 0 gpm Technical Specifications/SLC Items (CR SRO)
Shift Turnover Items (CR SRO)
Primary 420 EFPD SASS in Manual Secondary 1SSH-1, 1SSH-3, 1SD-2, 1SD-5,1SD-140,1SD-303,1SD-355,ISD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 PR-i, 1 PR-6, 1LPSW-i, 1LPSW-2, 1LPSW-3, 1FDW-80, 1CF-5, ICF-6, 1LP-1 and ILP-2 breakers open perthe appropriate system operating procedures.
ComponentlTrain OOS DatelTime Restoration Required DatelTime TSISLC #
Unit 3 has the Aux Steam Header Last shift ICS was placed in MANUAL for l&E testing After shift turnover, place ICS in AUTO per 0P111A111021004 A End. 4.4.
o Initial Conditions are complete Reactivity Management (CR SRO)
RCS Boron: 30 ppmB I Gp 7 Rod Position: 87%
II Batch additions as required for volume control.
Human Performance Emphasis (OSM)
Procedure Use and Adherence UNIT STATUS (CR SRO)
Other Units Unit 2 Mode: I 100% Power Unit 3 Mode:
EFDW Backup: Yes 1
100% Power EFDW Backup: Yes Scenario 2 RO Simulator Brief/Turnover SAFETY/PRA RISK (OSM)
I y: Take a Minute
- .. r
,~" '... a.... S: GREEN UNITO (OSM SSF Operable: Yes II KHU's Operable: U1 - OH, U2 - UG I LeTs Operable: 2 II Fuel Handling: None UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100%
Mode: 1 Mode: 1 Gross MWE: 897 100% Power 100% Power RCS Leakage:.01 gpm EFOW Backup: Yes EFOW Backup: Yes RBNS Rate: 0 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration Required TS/SLC #
Date/Time Date/Time Shift Turnover Items (CR SRO)
Primary 420 EFPO SASS in Manual Secondary 1SSH-1, 1SSH-3, 1S0-2, 1S0-5,1S0-140,1S0-303,1S0-355,1S0-356 and 1S0-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 PR-1, 1 PR-6, 1 LPSW-1, 1 LPSW-2, 1 LPSW-3, 1 FOW-80, 1 CF-5, 1 CF-6, 1 LP-1 and 1 LP-2 breakers open per the appropriate system operating procedures.
Unit 3 has the Aux Steam Header Last shift ICS was placed in MANUAL for I&E testing After shift turnover, place ICS in AUTO per OP/1/Al1102/004 A Encl. 4.4.
0 Initial Conditions are complete Reactivity Management (CR SRO)
RCS Boron: 30 ppmB I Gp 7 Rod Position: 87%
II Batch additions as required for volume control.
Human Performance Emphasis (OSM)
Procedure Use and Adherence Scenario 2 RO
Appendix D Scenario Outline Form ES-D-1 3/10 Facility:
Oconee Scenario No.: 3 Op-Test No.:
Examiners:
Operators:
Initial Conditions:
Reactor power = 100%
Turnover:
Intermittent LPSW leak in RB requires frequent RBNS pumping Event Maif. No.
Event Type*
Event No.
Description Oa Pre-SASS in Manual Insert 1
MPS 290 C, BOP, SRO 1A CC pump trips and lB CC pump fails to auto start Override 2
Override C, OATC, SRO 1HP-120 (RC Volume Control) fails Closed 3
Override I, BOP, SRO Pump RBNS and RBNS Pumps do not auto stop at 6 4
Override C, OATC, SRO 1A HPI Pump trips and standby HPI pump fails to start (TS) 5 Override C, BOP, SRO 1A RBCU cooler rupture (TS) 6 Override I, ALL Turbine trips to hand for unknown reason 7
MCRO21 C, OATC, SRO Dropped Control Rod and manual Power Reduction (TS)
MCRO22 8
MEL 120 M, ALL 1TA Lockout
- causes Rx trip due to loss of 2 RCPs eLr,d 8
CT-i Lockout I Keowee Unit 1 ELO (Blackout)
Regain power manually from CT-5.
9 MSS 380 All SGTR requires transfer to SGTR tab to end scenario TDEFWP fails requiring MDEFWPs (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 3110 Facility: Oconee Scenario No.: 3 Op-Test No.:
1 Examiners:
Operators:
SRO OATC BOP Initial Conditions:
Reactor power = 1 00%
Turnover:
Intermittent LPSW leak in RB requires frequent RBNS pumping Event Malf. No.
Event Type*
Event No.
Description Oa Pre-SASS in Manual Insert 1
MPS 290 C, BOP, SRO 1A CC pump trips and 1 B CC pump fails to auto start Override 2
Override C, OATC, SRO 1 HP-120 (RC Volume Control) fails Closed 3
Override I, BOP, SRO Pump RBNS and RBNS Pumps do not auto stop at 6" 4
Override C, OATC, SRO 1A HPI Pump trips and standby HPI pump fails to start (TS) 5 Override C, BOP, SRO 1A RBCU cooler rupture (TS) 6 Override I, ALL Turbine trips to hand for unknown reason 7
MCR021 C, OATC, SRO Dropped Control Rod and manual Power Reduction (TS)
MCR022 8
MEL 120 M, ALL 1TA Lockout - causes Rx trip due to loss of 2 RCP's MEL 180 CT-1 Lockout / Keowee Unit 1 ELO (Blackout)
Override Regain power manually from CT-5.
9 MSS 380 All SGTR requires transfer to SGTR tab to end scenario TDEFWP fails requiring MDEFWP's (N)ormal (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: I Page 1 of 3 Event
Description:
IA CC Pump trips, lB CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position__I Applicants Actions or Behavior Plant response:
1SA-9/B-1, CC CRD RETURN FLOW LOW 1SA-9/C-1, CC COMP COOLING RETURN FLOW LOW 1SA-21C-1, LETDOWN TEMPERATURE HIGH I HP-5 (Letdown Isolation) will close due to high letdown temperature CC Total Flow Low Component Cooling Pressure Low Crew Response:
Refer to ARG 1 SA-9/B-1 OR I SA-9/C-1 BOP Determine low flow is due to CC Pump failure AND Standby CC Pump did NOT start and perform the following:
Verify CC Surge Tank level> 12 Start Standby CC Pump SRO Note: The SRO may not initiate API2O if the Standby Pump is started per the ARG.
Initiate AP/20 (Loss of Component Cooling)
IAAT two CRD stator temperatures 180°F, BOP THEN trip RX. ( 4 minutes)
Open 1CC-7 and 1CC-8 Verify CC Surge Tank level 12.
Manually start the Standby CC Pump Verify CC TOTAL FLOW > 575 gpm If Letdown> 130 °F, THEN:
Close 1HP-5, Initiate AP!032 (Loss of Letdown)
Page 2 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Page 1 of 3 Event
Description:
1A CC Pump trips, 1B CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position BOP Applicant's Actions or Behavior Plant response:
1 SA-9/B-1, CC CRD RETURN FLOW LOW 1 SA-9/C-1, CC COMP COOLING RETURN FLOW LOW 1SA-2/C-1, LETDOWN TEMPERATURE HIGH 1 HP-5 (Letdown Isolation) will close due to high letdown temperature CC Total Flow Low Component Cooling Pressure Low Crew Response:
Refer to ARG 1SA-9/B-1 OR 1SA-9/C-1 Determine low flow is due to CC Pump failure AND Standby CC Pump did NOT start and perform the following:
Verify CC Surge Tank level> 12" Start Standby CC Pump SRO Note: The SRO may not initiate AP/20 if the Standby Pump is started per the ARG.
Initiate AP/20 (Loss of Component Cooling)
BOP IAAT ~ two CRD stator temperatures ~ 180°F, THEN trip RX. (- 4 minutes)
Open 1 CC-7 and 1 CC-8 Verify CC Surge Tank level;:: 12".
Manually start the Standby CC Pump Verify CC TOTAL FLOW> 575 gpm If Letdown> 130 of, THEN:
Close 1 HP-5, Initiate AP/032 (Loss of Letdown)
Page 2 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: I Page 2 of 3 Event
Description:
IA CC Pump trips, lB CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicants Actions or Behavior Crew Response:
SRO SRO Directs AP/32 (Loss of Letdown) entry; AP/32 will:
BOP/
Place 1 HP-120 in HAND and reduce demand to zero.
OATC Initiate makeup to LDST as required (EncI.5.5 or OP/i/Ni 103/004.
BOP Notify Chemistry of the following:
Current RCS boron sample is needed for possible unit shutdown.
Normal letdown line is isolated.
IAAT Pzr level
- 260, AND letdown CANNOT be established, THEN initiate unit shutdown at 20%/mm per AP/29 (Rapid Unit Shutdown).
IAAT Pzr level
- 375, THEN trip Rx.
Position the standby HPI pump switch to OFF.
Throttle IHP-31 to establish 12-15 gpm SEAL INLET HDR FLOW.
Verify HPI pump flow 65 gpm. ( gpm Recirc + SI +
MU)
Verify loss of letdown is due to L/D temperature high and then GO TO Step 4.29.
Notify SPOC to initiate repairs on failed equipment.
IAAT letdown can be re-established, THEN perform Steps 4.31 4.46.
Place CC system in operation Close 1HP-6 and 1HP-7.
Open the following:
IHP-i 1HP-2 1HP-3 1HP-4 Page 3 of 21 Appendix D Scenario Outline Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
1A CC Pump trips, 1B CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicant's Actions or Behavior Crew Response:
SRO SRO Directs AP/32 (Loss of Letdown) entry; AP/32 will:
BOPI OATC BOP Place 1 HP-120 in HAND and reduce demand to zero.
Initiate makeup to LOST as required (EncI.5.5 or OP/1/A/11 03/004.
Notify Chemistry of the following:
Current RCS boron sample is needed for possible unit shutdown.
Normal letdown line is isolated.
IAAT Pzr level ~ 260",
AND letdown CANNOT be established, Form ES-D-2 Page 2 of 3 THEN initiate unit shutdown at::::: 20%/min per AP/29 (Rapid Unit Shutdown).
IAAT Pzr level ~ 375",
THEN trip Rx.
Position the standby HPI pump switch to OFF.
Throttle 1HP-31 to establish 12 -15 gpm SEAL INLET HDR FLOW.
Verify HPI pump flow ~ 65 gpm. (30 gpm Recirc + _
SI +_ MU)
Verify loss of letdown is due to LID temperature high and then GO TO Step 4.29.
Notify SPOC to initiate repairs on failed equipment.
IAAT letdown can be re-established, THEN perform Steps 4.31 - 4.46.
Place CC system in operation Close 1 HP-6 and 1 HP-7.
Open the following:
1 HP-1 1 HP-2 1 HP-3 1 HP-4 Page 3 of 21
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: I Page 3 of 3 Event
Description:
IA CC Pump trips, lB CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicants Actions or Behavior Crew Response:
SRO!
Verify letdown temperature < 135°F (it is not; RNO Step 4.34)
Close the following:
IHP-8 1HP-9&11 Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Open I HP-5.
Throttle open 1 HP-7 to establish 20 gpm.
WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.
Open 1HP-6.
Adjust 1 HP-7 to control desired (75 gpm) letdown flow.
Re-establish normal makeup through 1HP-120.
Re-establish normal RCP seal injection flow.
Position the standby HPI pump switch to AUTO.
NOTE: If pressurizer level exceeds 260 inches, TS 3.4.9 Condition A should be entered requiring level be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> This event is complete when Seal Flow is returned to normal (32 gpm) or when directed by the Lead Examiner.
Page4of2l Appendix 0 Scenario Outline Form ES-O-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Page 3 of 3 Event
Description:
1A CC Pump trips, 1 B CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicant's Actions or Behavior Crew Response:
SRO/
Verify letdown temperature < 135°F (it is not; RNa Step 4.34)
BOP Open 1 HP-13.
Close the following:
1 HP-8 1 HP-9&11 Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Open 1 HP-5.
Throttle open 1 HP-7 to establish'" 20 gpm.
WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.
Open 1 HP-6.
Adjust 1 HP-7 to control desired (75 gpm) letdown flow.
Re-establish normal makeup through 1 HP-120.
Re-establish normal RCP seal injection flow.
Position the standby HPI pump switch to AUTO.
NOTE: If pressurizer level exceeds 260 inches, TS 3.4.9 Condition A should be entered requiring level be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> This event is complete when Seal Flow is returned to normal (32 gpm) or when directed by the Lead Examiner.
Page 4 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 2 Page 1 of 2 Event
Description:
IHP-120 (RC Volume Control) Fails closed (C, OATCISRO)
Time Position Applicants Actions or Behavior Plant response:
OATC RCS makeup flow goes to 10 gpm (HP lnj Warming Flow)
PZR level begins to decrease.
LDST level begins to increase.
Valve position demand for 1HP-120 begins to increase to the 100%
demand value and valve position indication will indicate closed (green light).
The OATC should diagnose the failure and notify the SRO.
Crew response:
Refer to APII4 (Loss of Normal Makeup and/or RCP Seal Injection.
IAAT Determine Seal Injection is lost...
IAAT loss of suction to HPI pumps is indicated...
SRO Announce AP entry using PA system.
OATC Verify y HPI pump operating Verify RCP seal injection or HPI makeup line leak is NOT indicated.
Report of line leak Abnormal LDST level decrease 1 RIA-32 (AUX BLDG GAS) 1RIA-45 (NORM VENT GAS)
RB RIAs in alarm Abnormal RBNS level increase Abnormal LAWT or HAWT level increase Verify RCP seal injection flow exists.
Verify 1HP-120 has failed in AUTO and perform the RNO and determine it will also not work in MANUAL. GO TO Step 4.129.
Perform the following as necessary to maintain Pzr level > 200:
Close 1HP-6 (Letdown Orifice Stop)
Throttle 1HP-7 (Letdown Control)
Throttle 1HP-26 (1A HP Injection)
Place 1HP-120 to HAND and closed Contact SPOC to repair 1HP-120.
Note: IHP-120 will remain failed for the duration of the scenario.
When PZR level is being controlled manually or when directed by the Lead Examiner this event is completed.
Page 5 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __
Scenario No.: 3 Event No.: 2 Page 1 of 2 Event
Description:
1 HP-120 (RC Volume Control) Fails closed (C, OATC/SRO)
Time Position OATC SRO OATC Applicant's Actions or Behavior Plant response:
RCS makeup flow goes to -10 gpm (HP Inj Warming Flow)
PZR level begins to decrease.
LOST level begins to increase.
Valve position demand for 1HP-120 begins to increase to the 100%
demand value and valve position indication will indicate closed (green light).
The OATC should diagnose the failure and notify the SRO.
Crew response:
Refer to AP/14 (Loss of Normal Makeup and/or RCP Seal Injection.
IAAT Determine Seal Injection is lost...
IAAT loss of suction to HPI pumps is indicated...
Announce AP entry using PA system.
Verify any HPI pump operating Verify RCP seal injection or HPI makeup line leak is NOT indicated.
Report of line leak Abnormal LOST level decrease 1 RIA-32 (AUX BLDG GAS) 1 RIA-45 (NORM VENT GAS)
RB RIAs in alarm Abnormal RBNS level increase Abnormal LAWT or HAWT level increase Verify RCP seal injection flow exists.
Verify 1HP-120 has failed in AUTO and perform the RNO and determine it will also not work in MANUAL. GO TO Step 4.129.
Perform the following as necessary to maintain Pzr level> 200":
Close 1 HP-6 (Letdown Orifice Stop)
Throttle 1 HP-7 (Letdown Control)
Throttle 1 HP-26 (1A HP Injection)
Place 1HP-120 to HAND and closed Contact SPOC to repair 1HP-120.
Note: 1 HP-120 will remain failed for the duration of the scenario.
When PZR level is being controlled manually or when directed by the Lead Examiner this event is completed.
Page 5 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 2 Page 2 of 2 Event
Description:
IHP-120 (RC Volume Control) Fails closed (C, OATCISRO)
Time Position Applicants Actions or Behavior Crew response:
BOP/OATC Crew may use EOP Enclosure 5.5 (Pzr and LDST Level Control) for primary inventory control Utilize the following as necessary to maintain Pzr level >100 [180 acc]:
Standby HPI pump 1HP-26 1HP-7 1HP-5 I HP-I 20 setpoint or valve demand IAAT> I HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
Obtain SRO concurrence to reduce running HPI pumps.
Secure the desired HPI pumps.
Place secured HPI pump switch in AUTO, if desired.
IAAT LDST level CANNOT be maintained, THEN Open IHP-24 and Open IHP-25; Close IHP-I6.
IAAT 1C HPI PUMP is required, THEN Open I HP-24 and 1 HP-25 Start IC HPI Pump Throttle 1HP-26 and 1HP-27 as required to maintain desired Pzr level:
IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.
IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close ICS-48 (1A BHUT RECIRC)
IAAT it is desired to secure makeup to LDST, THEN secure makeup from IA BHUT.
When PZR level is being controlled manually or when directed by the Lead Examiner this event is completed.
Page 6of21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __
Scenario No.: 3 Event No.: 2 Page 2 of 2 Event
Description:
1 HP-120 (RC Volume Control) Fails closed (C, OATC/SRO)
Time Position BOP/OATC Applicant's Actions or Behavior Crew response:
Crew may use EOP Enclosure 5.5 (pzr and LDST Level Control) for primary inventory control Utilize the following as necessary to maintain Pzr level >100" [180" acc]:
Standby HPI pump 1 HP-26 1 HP-7 1 HP-5 1 HP-120 setpoint or valve demand IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
Obtain SRO concurrence to reduce running HPI pumps.
Secure the desired HPI pumps.
Place secured HPI pump switch in AUTO, if desired.
IAAT LDST level CANNOT be maintained, THEN Open 1 HP-24 and Open 1 HP-25; Close 1 HP-16.
IAAT 1 C HPI PUMP is required, THEN Open 1 HP-24 and 1 HP-25 Start 1 C HPI Pump Throttle 1 HP-26 and 1 HP-27 as required to maintain desired Pzr level:
IAAT makeup to the LOST is desired, THEN makeup from 1A BHUT.
IAAT additional makeup flow to LOST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT RECIRC)
IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.
When PZR level is being controlled manually or when directed by the Lead Examiner this event is completed.
Page 6 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 3 Page 1 of 1 Event
Description:
Pump RBNS, RBNS pumps do NOT auto stop at 6 inches (I, BOP, SRO)
Time Position Applicants Actions or Behavior Plant response:
Statalarms:
1SA-9/A-6 (REACTOR BUILDING NORMAL SUMP LEVEL HIGH/LOW)
Crew response:
BOP/SRO Refer to 1 SA-91A-6 ARG.
High Level:
Align normal sump pump and lower level in sump per OP/1/A/1104/007 (Liquid Waste Disposal System), End. 4.1 (Ui RBNS Transfer Mode 1)
Verify MWHUT level adequate to receive waste volume.
Open 1LWD-i and 1LWD-2 (RB NORMAL SUMP ISOLATION)
Start one or both of the following:
Investigate possible RCS leakage per OP/0/B/1 106/033 (Primary System Leak Identification) or PT/1/A/0600/0i0 (Reactor Coolant Leakage). (Leakage is known from turnover-LPSW)
Monitor RB RIAs, CC Surge Tank level, CFT Level and LPSW flow to and from RB and sample RB Normal Sump to determine source.
Calculate RB Normal Sump Rate from Digital Trend (Use 15 gal/inch conversion factor).
Refer to AP/11A11700/002 (Excessive RCS Leakage). (Not needed due to knowing the source of the leakage into the RB).
Low Level:
Verify sump pump(s) stopped, and realign valves per OP/i/A/l 104/007 (Liquid Waste Disposal System), End. 4.1. (Ui RBNS Transfer Mode 1)
Note: The RBNS pumps will not stop on the low level cutoff. The BOP should recognize this and stop the pumps per procedure.
WHEN RBNS level is at desired level or at 6 (low level alarm),
THEN ensure pump(s) stopped.
Close 1LWD-1 and 1LWD-2(RB NORMAL SUMP ISOLATION)
Contact SPOC to repair RBNS pump low level cutoff.
When RBNS pumps have been stopped or when directed by the Lead Examiner this event is completed.
Page7of2l Appendix 0 Scenario Outline Form ES-O-2 Op-Test No.: __
Scenario No.: 3 Event No.: 3 Page 1 of 1 Event
Description:
Pump RBNS, RBNS pumps do NOT auto stop at 6 inches (I, BOP, SRO)
Time Position BOP/SRO Applicant's Actions or Behavior Plant response:
Statalarms:
1 SA-9/A-6 (REACTOR BUILDING NORMAL SUMP LEVEL HIGH/LOW)
Crew response:
Refer to 1 SA-9/A-6 ARG.
High Level:
Align normal sump pump and lower level in sump per OP/1/A/1104/007 (Liquid Waste Disposal System), Encl. 4.1 (U1 RBNS Transfer Mode 1)
Verify MWHUT level adequate to receive waste volume.
Open 1 LWD-1 and 1 LWD-2 (RB NORMAL SUMP ISOLATION)
Start one or both of the following:
Investigate possible RCS leakage per OP/0/B/11 06/033 (Primary System Leak Identification) or PT/1/A/0600/01 0 (Reactor Coolant Leakage). (Leakage is known from turnover-LPSW)
Monitor RB RIAs, CC Surge Tank level, CFT Level and LPSW flow to and from RB and sample RB Normal Sump to determine source.
Calculate RB Normal Sump Rate from Digital Trend (Use 15 gal/inch conversion factor).
Refer to AP/1/A/1700/002 (Excessive RCS Leakage). (Not needed due to knowing the source of the leakage into the RB).
Low Level:
Verify sump pump(s) stopped, and realign valves per OP/1/A/1104/007 (Liquid Waste Disposal System), Encl. 4.1. (U1 RBNS Transfer Mode 1)
Note: The RBNS pumps will not stop on the low level cutoff. The BOP should recognize this and stop the pumps per procedure.
WHEN RBNS level is at desired level or at 6" (low level alarm),
THEN ensure pump(s) stopped.
Close 1 LWD-1 and 1 LWD-2(RB NORMAL SUMP ISOLATION)
Contact SPOC to repair RBNS pump low level cutoff.
When RBNS pumps have been stopped or when directed by the Lead Examiner this event is completed.
Page 7 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 4 Page 1 of 2 Event
Description:
A HPI Pump trips and the Standby HPI pump fails to auto start:
(C, OATC, SRO)
(TS)
Time Position Applicants Actions or Behavior Plant response:
Statalarms:
1SA-2/B-2 (HP RCP Seal Injection Flow High/Low) 1SA-2/C-2 (HP Injection Pump Disch. Header Pressure High/Low)
Board indications:
RC Makeup Flow = 0 gpm 1A HPI Pump OFF PZR level will begin to decrease and LDST level will begin to increase.
BOP Crew response:
SRO Refer to ARG for above Statalarms SRO should refer to APII4 (Loss of Normal Makeup and/or RCP Seal BOP Injection)
IAAT RCP seal injection flow is lost...
IAAT loss of suction to operating HPI pumps is indicated...
Announce AP entry using PA system.
Verify NO HPI pump operating Close 1HP-5 (Letdown Isolation)
Place 1HP-120 (RC Volume Control) in HAND and closed Place 1HP-31 (RCP Seal Flow Control) in HAND and closed Start standby HPI pump (lB HPI pump)
Place in HAND and slowly open 1 HP-31 in small increments until 8 gpm/RCP is achieved.
Re-establish normal makeup through 1HP-120. (failed closed)
Ensure proper operation of the CC system.
Reduce 1 HP-7 demand to 0%.
Close 1HP-6 Ensure the following open:
1HP-1, 1HP-2, 1HP-3, 1HP-4 Page 8 of 21 Appendix D Op-Test No.: __
Event
Description:
Time Position Scenario Outline Scenario No.: 3 Event No.: 4 "A" HPJ Pump trips and the Standby HPJ pump fails to auto start:
(C, OATC, SRO) (TS)
Applicant's Actions or Behavior Plant response:
Statalarms:
1 SA-2/B-2 (HP RCP Seal Injection Flow High/Low)
Form ES-D-2 Page 1 of 2 1 SA-2/C-2 (HP Injection Pump Disch. Header Pressure High/Low)
Board indications:
RC Makeup Flow = 0 gpm 1A HPI Pump OFF PZR level will begin to decrease and LOST level will begin to increase.
BOP Crew response:
SRO Refer to ARG for above Statalarms SRO should refer to AP/14 (Loss of Normal Makeup and/or RCP Seal BOP Injection)
IAAT RCP seal injection flow is lost...
IAAT loss of suction to operating HPI pumps is indicated...
Announce AP entry using PA system.
Verify NO HPI pump operating Close 1 HP-5 (Letdown Isolation)
Place 1 HP-120 (RC Volume Control) in HAND and closed Place 1 HP-31 (RCP Seal Flow Control) in HAND and closed Start standby HPI pump (1 B HPI pump)
Place in HAND and slowly open 1 HP-31 in small increments until :::::
8 gpm/RCP is achieved.
Re-establish normal makeup through 1 HP-120. (failed closed)
Ensure proper operation of the CC system.
Reduce 1 HP-7 demand to 0%.
Close 1 HP-6 Ensure the following open:
~ 1 HP-1, 1 HP-2, 1 HP-3, 1 HP-4 Page 8 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 4 Page 2 of 2 Event
Description:
A HPI Pump trips and the standby HPI pump fails to auto start:
(C, OATCISRO)
Time Position Applicants Actions or Behavior Open 1HP-5 Throttle open 1 HP-7 for 20 gpm letdown flow.
Open IHP-6 Adjust 1 HP-7 for desired letdown flow (75 gpm).
Open 1HP-228, 1HP-226, 1HP-232, 1HP-230.
Open 1HP-21 Place 1HP-31 in auto.
Refer to Tech Spec 3.5.2 High Pressure Injection SRO Condition A Required Action: Restore HPI pump to OPERABLE status Completion Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency.
Event is complete when normal makeup and letdown is established or when directed by the Lead Examiner.
Page 9 of 21 Appendix D Op-Test No.: __
Event
Description:
Time Position SRO Scenario Outline Form ES-D-2 Scenario No.: 3 Event No.: 4 Page 2 of 2 "A" HPI Pump trips and the standby HPI pump fails to auto start:
(C, OATC/SRO)
Applicant's Actions or Behavior Open 1HP-5 Throttle open 1 HP-7 for:== 20 gpm letdown flow.
Open 1 HP-6 Adjust 1 HP-7 for desired letdown flow (75 gpm).
Open 1 HP-228, 1 HP-226, 1 HP-232, 1 HP-230.
Open 1 HP-21 Place 1 HP-31 in auto.
Refer to Tech Spec 3.5.2 High Pressure Injection Condition "A" Required Action: Restore HPI pump to OPERABLE status Completion Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency.
Event is complete when normal makeup and letdown is established or when directed by the Lead Examiner.
Page 9 of 21
Plant Response:
1SA-9/B-9, LPSW RBCU A Cooler Rupture 1SA-91A-6, RB Normal Sump Level High/Low RB normal sump level will increase Crew Response:
BOP ARG for 1 SA-91B-9 Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A delta flow (327 gpm Delta Flow).
Verify 1LPSW-18 (RBCU 1A Outlet) open Verify adequate LPSW flow is available; check LPSW pump operation and 1LPSW-16 (1A RBCU INLET PENE) is open.
Monitor RBNS Level for any unexplained increase Diagnose a Cooler Rupture is indicated and Isolate the 1A RBCU Cooler.
Close 1LPSW-16 (1A RBCU INLET PENE).
Close 1LPSW-18 (RBCU 1A OUTLET).
Perform TS 3.6.3 Condition C for closed containment system.
SRO Requires isolating penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Enter TS 3.6.5 for RBCU inoperable. (TS 3.6.5 Condition B).
Requires restoring RBCU to OPERABLE within 7 days Refer to SLC 16.9.12 (Additional LPSW and Siphon Seal Water System Operability Requirements) (Not applicable after ILPSW-16 is closed)
When the RBCU has been isolated, or at the direction of the Lead Examiner this event is completed.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 5 Page 1 of 1 Event
Description:
IA RBCU rupture (C, BOP, SRO) (TS)
Time Position Applicants Actions or Behavior Page 10 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __
Scenario No.: 3 Event No.: 5 Page 1 of 1 Event
Description:
1A RBCU rupture (C, BOP, SRO) (TS)
Time Position Applicant's Actions or Behavior Plant Response:
1 SA-9/B-9, LPSW RBCU A Cooler Rupture 1 SA-9/A-6, RB Normal Sump Level High/Low RB normal sump level will increase Crew Response:
BOP ARG for 1 SA-9/B-9 SRO Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A delta flow (327 gpm Delta Flow).
Verify 1LPSW-18 (RBCU 1A Outlet) open Verify adequate LPSW flow is available; check LPSW pump operation and 1 LPSW-16 (1A RBCU INLET PENE) is open.
Monitor RBNS Level for any unexplained increase Diagnose a Cooler Rupture is indicated and Isolate the 1A RBCU Cooler.
Close 1LPSW-16 (1A RBCU INLET PENE).
Close 1 LPSW-18 (RBCU 1A OUTLET).
Perform TS 3.6.3 Condition C for closed containment system.
Requires isolating penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Enter TS 3.6.5 for RBCU inoperable. (TS 3.6.5 Condition B).
Requires restoring RBCU to OPERABLE within 7 days Refer to SLC 16.9.12 (Additional LPSW and Siphon Seal Water System Operability Requirements) (Not applicable after 1 LPSW-16 is closed)
When the RBCU has been isolated, or at the direction of the Lead Examiner this event is completed.
Page 10 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 6 Page 1 of 1 Event
Description:
Turbine trips to HAND (I, ALL)
Time Position Applicants Actions or Behavior Plant Response:
Statalarms:
SRO 1SA-2/A-12, lOS Tracking 1 SA-2/C1 2, los H/A Station on Man Crew Response:
BOP Refer to ARG for above alarms.
IF Turbine Master Trips to Hand for unknown reason, refer to AP/lIAJl700/028 (105 Instrument Failure).
SRO AP128 GO TO Section 40 Simultaneously place the 1A and 1 B FDW MASTERs to HAND:
OATC Place the DIAMOND in MANUAL.
Notify SPOC to investigate the cause of the Turbine Master tripping to Hand.
When FDW Masters and Diamond are in MANUAL, or when directed by the Lead Examiner this event is completed.
Page 11 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __
Scenario No.: 3 Event No.: 6 Page 1 of 1 Event
Description:
Turbine trips to HAND (I, ALL)
Time Position Applicant's Actions or Behavior Plant Response:
Statalarms:
SRO 1SA-2/A-12, ICS Tracking 1SA-2/C-12, ICS H/A Station on Man Crew Response:
BOP Refer to ARG for above alarms.
IF Turbine Master Trips to Hand for unknown reason, refer to AP/1/A/17001028 (ICS Instrument Failure).
SRO AP/28 OATC GO TO Section 40 Simultaneously place the 1A and 1 B FDW MASTERs to HAND:
Place the DIAMOND in MANUAL.
Notify SP~C to investigate the cause of the Turbine Master tripping to Hand.
When FDW Masters and Diamond are in MANUAL, or when directed by the Lead Examiner this event is completed.
Page 11 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No. :7 Page 1 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATC, SRO) (TS)
Time_J Position Applicants Actions or Behavior Plant Response:
Stat alarm ISA2IA1O (CRD GLOBAL TROUBLE)
Stat alarm 1SA2/B1O (CRD ASYMMETRIC ROD ALARM)
Stat alarm 1SA2/D9 (CRD OUT INHIBIT)
Crew Response:
SRO SRO should enter APII (Unit Runback)
APII Section 4H IAAT more than one control rod is dropped or misaligned >6% (>9) from the group average, THEN trip the Rx.
Verify Rx is critical.
Verify Rx runback to 55% FP in progress.
Note: Runback will not be occurring due to ICS in MANUAL.
R OATC RNO: Initiate manual power reduction to 55% CTP at 1%Imin.
OATC will reduce power with FDW Masters, Diamond, and Turbine BOP Initiate End 5.1 (Control of Plant Equipment During Shutdown).
Notify SPOC to investigate cause of dropped or misaligned control rod and rreare to reduce the following trip setpoints:
o RPS Flux/Flow-Imbalance o
RPS High Flux Notify the OSM to ensure the requirements of the following Tech Specs are met:
o TS 3.1.4 (Control Rod Group Alignment Limits)
Previously discussed o
TS 3.1.5 (Safety Rod Position Limits)
Condition A -
1 hr Completion Time o
TS 3.2.3 (Quadrant Power Tilt)
IF QPT exceeds steady state limit, Condition A required. First action has 2 hr Completion Time NOTE: OSM will be unavailable to make the TS determination and it will be the responsibility of the SRO Page 12 of2l Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event NO.:7 Page 1 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATC, SRO) (TS)
Time Position Applicant's Actions or Behavior Plant Response:
Stat alarm 1 SA2/A 10 (CRD GLOBAL TROUBLE)
Stat alarm 1SA2/B10 (CRD ASYMMETRIC ROD ALARM)
Stat alarm 1 SA2/D9 (CRD OUT INHIBIT)
Crew Response:
SRO SRO should enter AP/1 (Unit Runback)
AP/1 Section 4H R,OATC BOP IAAT more than one control rod is dropped or misaligned >6% (> 9")
from the group average, THEN trip the Rx.
Verify Rx is critical.
Verify Rx runback to 55% FP in progress.
Note: Runback will not be occurring due to ICS in MANUAL.
RNO: Initiate manual power reduction to 55% CTP at ~ 1%/min.
OATC will reduce power with FDW Masters, Diamond, and Turbine Initiate Encl 5.1 (Control of Plant Equipment During Shutdown).
Notify SPOC to investigate cause of dropped or misaligned control rod and prepare to reduce the following trip setpoints:
o RPS Flux/Flow-Imbalance o
RPS High Flux Notify the OSM to ensure the requirements of the following Tech Specs are met:
o TS 3.1.4 (Control Rod Group Alignment Limits)
Previously discussed o
TS 3.1.5 (Safety Rod Position Limits)
Condition A - 1 hr Completion Time o
TS 3.2.3 (Quadrant Power Tilt)
IF QPT exceeds steady state limit, Condition A required. First action has 2 hr Completion Time NOTE: OSM will be unavailable to make the TS determination and it will be the responsibility of the SRO Page 12 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 7 Page 2 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATCISRO) (TS)
Time Position Applicants Actions or Behavior Crew Response:
SRO should refer to TS for the dropped control rod.
SRO Enter TS 3.1.4 (Control Rod Group Alignment Limits)
Condition A: (One trippable CR inoperable or not aligned to within 6.5% of its group average height or both).
- 1. Restore Control Rod Alignment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR
- 2. Verify SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR Initiate Boron to restore SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Reduce Thermal Power to < 60% of allowable thermal power within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND Reduce nuclear overpower trip setpoints (flux/flow/imb) to 65.5%
of the allowable thermal power within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> AND Verify the potential ejected rod worth is within assumptions of rod ejection analysis within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> BOP Verify> 1% SDM with allowance for the inoperable control rod per PT/i IA/i 103/015 (Reactivity Balance Calculation).
USE COLR curve for 4 RCPs and 1 inoperable rod.
Ensure requirements of TS 3.1.5 (Safety Rod Position Limits)
Ensure requirements of TS 3.2.3 (Quadrant Power Tilt) are met.
Reduce power and ensure <55% on all Nls when the power decrease is complete.
When TS have been addressed, or when directed by the lead examiner this event is completed.
Page 13 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event No.: 7 Page 2 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATC/SRO) (TS) e Position SRO Applicant's Actions or Behavior Crew Response:
SRO should refer to TS for the dropped control rod.
Enter TS 3.1.4 (Control Rod Group Alignment Limits)
Condition A: (One trippable CR inoperable or not aligned to within 6.5% of its group average height or both).
- 1. Restore Control Rod Alignment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR
- 2. Verify SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR Initiate Boron to restore SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Reduce Thermal Power to ~ 60% of allowable thermal power within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND Reduce nuclear overpower trip setpoints (fluxlflow/imb) to ~ 65.5%
of the allowable thermal power within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> AND Verify the potential ejected rod worth is within assumptions of rod ejection analysis within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> BOP Verify> 1 % SDM with allowance for the inoperable control rod per PT/1/A/11 031015 (Reactivity Balance Calculation).
USE COLR curve for 4 RCPs and 1 inoperable rod.
Ensure requirements ofTS 3.1.5 (Safety Rod Position Limits)
Ensure requirements of TS 3.2.3 (Quadrant Power Tilt) are met.
Reduce power and ensure <55% on all Nls when the power decrease is complete.
When TS have been addressed, or when directed by the lead examiner this event is completed.
Page 13 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 8 Page 1 of 5 Event
Description:
ITA Lockout and Unit Blackout: (M, ALL)
Time j Position J
Applicants Actions or Behavior Plant response:
ITA Lockout (6900 Volt Switchgear)
IAI and I BI RCPs trip causing a reactor trip KHU #1 Emergency Lockout CT-i Lockout MFBs will de-energize Crew response:
OATC/SRO Perform Immediate Manual Actions (IMAs)
Depress REACTOR TRIP pushbutton.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed.
Verify RCP seal injection available.
IF CC is unavailable, THEN immediately perform the following:
Stop all RCPs.
Notify CR SRO to initiate AP125 (Standby Shutdown Facility Emergency Operating Procedure).
BOP AP125 Obtain the Vital area access key ring, Flashlight and Proceed to the SSF.
NOTE: Examiner should stop the BOP before leaving the control room and informed that Unit 2 RO will perform SSF actions.
OATC/BOP Perform Symrtom Check Power Range Nis ARE <5% and decreasing NOSCMs<0°F Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)
- TDEFWP is oeratinq Uncontrolled Main Steam line(s) pressure decrease is NOT occurring SGTR does NOT exist CSAE Offgas alarms Process monitor alarms (RIA-40, 59, 60)
Area monitor alarms (RIA-i 6/17)
Page 14 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event No.: 8 Page 1 of 5 Event
Description:
1TA Lockout and Unit Blackout: (M, ALL)
Time Position OATC/SRO BOP OATC/BOP Applicant's Actions or Behavior Plant response:
1TA Lockout (6900 Volt Switchgear) 1A1 and 1B1 RCPs trip causing a reactor trip KHU #1 Emergency Lockout CT -1 Lockout MFBs will de-energize Crew response:
Perform Immediate Manual Actions (IMAs)
Depress REACTOR TRIP pushbutton.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed.
Verify RCP seal injection available.
IF CC is unavailable, THEN immediately perform the following:
Stop all RCPs.
Notify CR SRO to "initiate AP/25" (Standby Shutdown Facility Emergency Operating Procedure).
AP/25 Obtain the Vital area access key ring, Flashlight and Proceed to the SSF.
NOTE: Examiner should stop the BOP before leaving the control room and informed that Unit 2 RO will perform SSF actions.
Perform Symptom Check Power Range Nls ARE < 5% and decreasing NO SCMs < O°F Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) - TDEFWP is operating Uncontrolled Main Steam line(s) pressure decrease is NOT occurring SGTR does NOT exist CSAE Offgas alarms Process monitor alarms (RIA-40, 59, 60)
Area monitor alarms (RIA-16/17)
Page 14 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 8 Page 2 of 5 Event
Description:
ITA Lockout and Unit Blackout: (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
Rule 3 (Loss of Main or Emergency Feedwater)
BOPIOATC IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
RCS pressure reaches 2300 psig OR NDT limit Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Start EFDW pumps to feed all intact SGs. (Only the TDEFDFW pump will be operating)
Verify any SCM 0°F. RNO IF overcooling, THEN throttle EFDW as necessary.
IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation).
BOP/OATC End 5.9 (Extended EFDW Operation)
Monitor EFDW parameters on EFW graphic display.
Perform the following as required to maintain UST level > 7.5:
Makeup with demin water.
Place CST pumps in AUTO.
Verify I TD EFDW PUMP operating and Start TD EFDWP BEARING OIL COOLING PUMP.
Notify CR SRO to set priority based on the NOTE above and EOP activities.
SRO SRO will transfer to the BLACKOUT tab.
Page 15 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event No.: 8 Page 2 of 5 Event
Description:
1TA Lockout and Unit Blackout: (M, ALL)
Time Position BOP/OATC Applicant's Actions or Behavior Crew response:
Rule 3 (Loss of Main or Emergency Feedwater)
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
RCS pressure reaches 2300 psig OR NDT limit Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Start EFDW pumps to feed all intact SGs. (Only the TDEFDFW pump will be operating)
Verify any SCM ~O°F. RNO - IF overcooling, THEN throttle EFDW as necessary.
IAAT Unit 1 EFDW is in operation, THEN initiate Ene! 5.9 (Extended EFDW Operation).
BOP/OA TC Encl 5.9 (Extended EFDW Operation)
Monitor EFDW parameters on EFW graphic display.
Perform the following as required to maintain UST level> 7.5':
Makeup with demin water.
Place CST pumps in AUTO.
Verify 1 TD EFDW PUMP operating and Start TD EFDWP BEARING OIL COOLING PUMP.
Notify CR SRO to set priority based on the NOTE above and EOP activities.
SRO SRO will transfer to the BLACKOUT tab.
Page 15 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 8 Page 3 of 5 Event
Description:
ITA Lockout and Unit Blackout: (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
SRO will transfer to the BLACKOUT tab.
SRO/BOP
/OATC Direct an RO to announce plant conditions using the plant page and notify the OSM to reference EP and NSD 202 (reportability).
Verify two ROs available to perform Control Room activities.
SRO will direct an RO to perform End. 5.38 (Restoration of Power)
Position the following to OFF:
1AMDEFDWP 1BMDEFDWP Feed and steam available SGs as necessary to stabilize RCS P/T.
NOTE:
Feeding SGs with EFDW is desired above HPI Forced Cooling. Step 6 should be performed prior to re-performing Rule 3.
IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 or another unit) becomes available, THEN perform the following:
Establish 100 gpm to each intact SG. (Feeding to 240 XSUR)
Perform one of the following:
Tc> 550°F-Initiate cool down to Tc 540°F
- 550°F by feeding and steaming intact SGs at a rate that prevents RCS saturation.
Tc < 550°F Feed and Steam intact SGs to stabilize Tc < 550°F IAAT EFDW from any source is insufficient to maintain stable RCS P/T, THEN notify SSF operator that feeding SGs with SSF ASW is required.
IAAT power is restored to jy of the following:
1TC.1TD,1TE THEN Initiate AP/1 1 (Recovery from Loss of Power).
GO TO Subsequent Actions Tab SRO NOTE: Once power is restored to any 41 60V bus, the SRO will transfer to the Subsequent Actions tab per the above IAAT step.
Verify all control rods fully inserted.
Verify Main FDW in operation.
Verify Main FDW controlling properly.
IAAT Main FDW is operating...
Verify TBVs controlling SG pressure at desired setpoint.
Verify 1 RIA-40 operable with CSAE OFF-GAS BLOWER operating.
Page 16 of 21 Appendix D Scenario Outline Form ES*D*2 Op-Test No.: __ Scenario No.: 3 Event No.: 8 Page 3 of 5 Event
Description:
1TA Lockout and Unit Blackout: (M, ALL) ime Position SRO/BOP IOATC SRO Applicant's Actions or Behavior Crew response:
SRO will transfer to the BLACKOUT tab.
Direct an RO to announce plant conditions using the plant page and notify the OSM to reference EP and NSD 202 (reportability).
Verify two ROs available to perform Control Room activities.
SRO will direct an RO to perform Encl. 5.38 (Restoration of Power)
Position the following to OFF:
1A MD EFDWP 1B MD EFDWP Feed and steam available SGs as necessary to stabilize RCS PIT.
NOTE:
Feeding SGs with EFDW is desired above HPI Forced Cooling. Step 6 should be performed prior to re-performing Rule 3.
IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 or another unit) becomes available, THEN perform the following:
Establish 100 gpm to each intact SG. (Feeding to 240" XSUR)
Perform one of the following:
Tc> 550°F-Initiate cool down to Tc 540°F - 550°F by feeding and steaming intact SGs at a rate that prevents RCS saturation.
Tc ~ 550°F - Feed and Steam intact SG's to stabilize Tc ~ 550°F IAAT EFDW from any source is insufficient to maintain stable RCS PIT, THEN notify SSF operator that feeding SGs with SSF ASW is required.
IAAT power is restored to any of the following:
1TC. 1TD, 1TE THEN Initiate AP/11 (Recovery from Loss of Power).
GO TO Subsequent Actions Tab NOTE: Once power is restored to any 4160V bus, the SRO will transfer to the Subsequent Actions tab per the above IAAT step.
Verify all control rods fully inserted.
Verify Main FDW in operation.
Verify Main FDW controlling properly.
IAA T Main FDW is operating...
Verify TBVs controlling SG pressure at desired setpoint.
Verify 1 RIA-40 operable with CSAE OFF-GAS BLOWER operating.
Page 16 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 8 Page 4 of 5 Event
Description:
ITA Lockout and Unit Blackout: (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
AP/1 1 (Recovery from Loss of Power).
to be performed after completion of OATC/BOP EOP End. 5.38 (Restoration Of Power; from CT-5)
Announce AP entry using the PA system.
Verify load shed has initiated Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 1 or 2).
Close the following breakers:
1TC INCOMING FDR BUS 1/2 lTD INCOMING FDR BUS 1/2 1TE INCOMING FDR BUS 1/2 Verify a 230KV Switchyard Isolation has occurred. (It has NOT)
Verify ES has occurred. (It has NOT)
Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
MFB UNDERVOLTAGE CHANNEL 1/2 RESET Verify all condensate flow has been lost for < 25 minutes and condensate operation is desired.
Place all HWP control switches to OFF.
Place all CBP control switches to OFF.
Place 1 FDW-53/65 in MANUAL and close.
Place iC-iC FAIL SWITCH in MANUAL.
Close iC-b.
Using a plant page, clear TB Basement and TB third floor of non essential personnel.
Start one HWP.
Throttle 1 C-iC controller 10% open to satisfy 25 minute restart criteria.
WHEN FWP SUCT HDR PRESS is 100 psig, THEN open iC-iC.
Page 17 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event No.: 8 Page 4 of 5 Event
Description:
1TA Lockout and Unit Blackout: (M, ALL)
Time Position OATC/BOP Applicant's Actions or Behavior Crew response:
AP/11 (Recovery from Loss of Power). - to be performed after completion of EOP Enc!. 5.38 (Restoration Of Power; from CT-5)
Announce AP entry using the PA system.
Verify load shed has initiated Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 1 or 2).
Close the following breakers:
1TC INCOMING FOR BUS 1/2 1TD INCOMING FOR BUS 1/2 1TE INCOMING FOR BUS 1/2 Verify a 230KV Switchyard Isolation has occurred. (It has NOT)
Verify ES has occurred. (It has NOT)
Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
MFB UNDERVOL TAGE CHANNEL 1/2 RESET Verify all condensate flow has been lost for < 25 minutes and condensate operation is desired.
Place all HWP control switches to OFF.
Place all CBP control switches to OFF.
Place 1 FDW-53/65 in MANUAL and close.
Place 1C-10 FAIL SWITCH in MANUAL.
Close 1C-10.
Using a plant page, clear TB Basement and TB third floor of non-essential personnel.
Start one HWP.
Throttle 1 C-1 0 controller 10% open to satisfy 25 minute restart criteria.
WHEN FWP SUCT HDR PRESS is;::: 100 psig, THEN open 1C-10.
Page 17 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 8 Page 5 of 5 Event
Description:
ITA Lockout and Unit Blackout: (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
OATC/BOP RO will perform End. 5.38 (Restoration of Power) (CT-8) (Not met if End.
5.38 completed with power NOT restored.)
Place 1HP-31 in HAND and reduce demand to 0.
Close 1HP-21.
Verify MFB1/2 energized (NOT)
Verify CT-i indicates 4i60v (NO)
Verify both Standby Bus #1 and Standby Bus #2 are de-energized.
Emergency start Keowee units Notify Keowee Operator to place all operating Keowee units in Oconee Control.
IAAT CT-S indicates 4160 volts, THEN GO TO Step 50. (It does; from Central Swyd)
Place the following switches in MAN:
MFB1 and MFB2 AUTO/MAN STANDBY I and STANDBY 2 AUTO/MAN Open the following breakers:
Ni 1 and N2 1 MFB1 NORMAL FDR El 1 and E2 1 MFB1 STARTUP FDR Place the following switches in MAN:
CT4 BUS 1 and CT4 BUS 2 AUTO/MAN CT5 BUS I and CT5 BUS 2 AUTO/MAN Open the following breakers:
Ski and SK2 CT4 STBY BUS i FEEDER Close SL1 and SL2 CT5 STBY BUS 1 FEEDER Place the following switches in AUTO:
CT5 BUS i and CT5 BUS 2 AUTO/MAN Verify Standby Bus #1 energized.
Notify CR SRO in each unit where a blackout exists that Standby Bus #1 is energized.
Close Si 1 and S2 1 STBY BUS 2 TO MFB2 (power is restored)
Verify iTC, 1TD, or iTE energized.
Notify Unit i CR SRO of status of 4i60V SWGR.
When the SRO has transferred to Subsequent Actions tab, or when directed by the Lead Examiner this event is completed.
Page 18 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 8 Page 5 of 5 Event
Description:
1TA Lockout and Unit Blackout: (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
OATe/BOP RO will perform End. 5.38 (Restoration of Power) (CT-8) (Not met if Enc!.
5.38 completed with power NOT restored.)
Place 1 HP-31 in HAND and reduce demand to O.
Close 1 HP-21.
Verify MFB1/2 energized (NOT)
Verify CT-1 indicates 4160v (NO)
Verify both Standby Bus #1 and Standby Bus #2 are de-energized.
Emergency start Keowee units Notify Keowee Operator to place all operating Keowee units in Oconee Control.
IAAT CT-5 indicates== 4160 volts, THEN GO TO Step 50. (It does; from Central Swyd)
Place the following switches in MAN:
MFB1 and MFB2 AUTO/MAN STANDBY 1 and STANDBY 2 AUTO/MAN Open the following breakers:
N11 and N21 MFB1 NORMAL FOR E11 and E21 MFB1 STARTUP FOR Place the following switches in MAN:
CT4 BUS 1 and CT4 BUS 2 AUTO/MAN CT5 BUS 1 and CT5 BUS 2 AUTO/MAN Open the following breakers:
SK1 and SK2 CT4 STBY BUS 1 FEEDER Close SL 1 and SL2 CT5 STBY BUS 1 FEEDER Place the following switches in AUTO:
CT5 BUS 1 and CT5 BUS 2 AUTO/MAN Verify Standby Bus #1 energized.
Notify CR SRO in each unit where a blackout exists that Standby Bus #1 is energized.
Close S1 1 and S21 STBY BUS 2 TO MFB2 (power is restored)
Verify 1TC, 1TD, or 1TE energized.
Notify Unit 1 CR SRO of status of 4160V SWGR.
When the SRO has transferred to Subsequent Actions tab, or when directed by the Lead Examiner this event is completed.
Page 18 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 9 Page 1 of 2 Event
Description:
SGTR: (M, ALL)
Time Position Applicants Actions or Behavior After the SRO transfers to the Subsequent Actions tab and when directed by the Lead Examiner a SG tube rupture will occur in the I B SG.
Plant Response:
I SA-8/B-9 RM Process Monitor Radiation High 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH)
PZR level decreasing Crew response:
SRO The SRO should use the Parallel Actions page and transfer to the SGTR tab.
SGTR tab will:
Maintain Pzr level 14Q-180 [17-21acc] by initiating End 5.5 (Pzr and LDST Level Control).
Start A and B OUTSIDE AIR BOOSTER FAN (CT-27)
Notify Unit 3 to start the 3A and 3B OUTSIDE AIR BOOSTER FAN Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.
Dispatch an operator to open A and B TURB BLDG SUMP PUMP BKR)
Notify RP to survey both MS lines for radiation.
OATC/BOP Note: When RP is directed to survey MS lines the TD EFDW pump will trip; requiring either Rule 3 to be performed OR performing a symptoms check to start the MDEFWPs. (CT-b)
Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector (1MS-46), etc.).
Verify Main FDW or EFDW controlling properly.
Open 1HP-24 and 1HP-25 Secure makeup to LDST. (Close 1HP-16, if open)
Maintain both SG pressures < 950 psig using either of the following:
TBVs Dispatch two operators to perform End 5.24 (Operation of the ADV5)
Page 19 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event No.: 9 Page 1 of 2 Event
Description:
SGTR: (M, ALL)
Time Position Applicant's Actions or Behavior After the SRO transfers to the Subsequent Actions tab and when directed by the Lead Examiner a SG tube rupture will occur in the 1 B SG.
Plant Response:
1 SA-8/8-9 RM Process Monitor Radiation High 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH)
PZR level decreasing Crew response:
SRO The SRO should use the Parallel Actions page and transfer to the SGTR tab.
OATC/BOP SGTR tab will:
Maintain Pzr level 14Q"- 180" [17Q"- 21Q"acc] by initiating Encl 5.5 (pzr and LDST Level Control).
Start A and B OUTSIDE AIR BOOSTER FAN (CT-27)
Notify Unit 3 to start the 3A and 3B OUTSIDE AIR BOOSTER FAN Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.
Dispatch an operator to open A and B TURB BLDG SUMP PUMP BKR)
Notify RP to survey both MS lines for radiation.
Note: When RP is directed to survey MS lines the TD EFDW pump will trip; requiring either Rule 3 to be performed OR performing a symptoms check to start the MDEFWP's. (CT -10)
Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector (1 MS-46), etc.).
Verify Main FDW or EFDW controlling properly.
Open 1 HP-24 and 1 HP-25 Secure makeup to LDST. (Close 1HP-16, if open)
Maintain both SG pressures < 950 psig using either of the following:
TBVs Dispatch two operators to perform Encl 5.24 (Operation of the ADVs)
Page 19 of 21
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Scenario No.: 3 Event No.: 9 Page 2 of 2 Event
Description:
SGTR: (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
- ...SGTR tab continued:
ALL IAAT all the following exist:
All SCMs> 0°F ES Bypass Permit satisfied RCS pressure controllable THEN bypass ES as necessary.
Verify any RCP operating. (NOT)
Minimize core SCM using any/all of the following methods:
De-energize all Pzr heaters Use Pzr spray Maintain Pzr level 140
- 180 [175
- 215 acc]
NOTE: With no RCPs operating, the above methods will be unsuccessful at reducing SCM.
IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 36
- 38. (CT-7) a.
Verify Pzr spray nozzle liT 410°F.
b.
Cycle PORV as necessary.
When crew takes action to minimize SCM or when directed by the Lead Examiner, the scenario is complete.
Page 20 of 21 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: __ Scenario No.: 3 Event No.: 9 Page 2 of 2 Event
Description:
SGTR: (M, ALL)
Time Position ALL Applicant's Actions or Behavior Crew response:
.... SGTR tab continued:
IAAT all the following exist:
All SCMs > OaF ES Bypass Permit satisfied RCS pressure controllable THEN bypass ES as necessary.
Verify any RCP operating. (NOT)
Minimize core SCM using any/all of the following methods:
De-energize all Pzr heaters Use Pzr spray Maintain Pzr level 140" - 180" [175" - 215" acc]
NOTE: With no RCP's operating, the above methods will be unsuccessful at reducing SCM.
IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 36 - 38. (CT-?)
- a. Verify Pzr spray nozzle LlT;::: 410°F.
- b. Close 1 LWD-1 and 1 LWD-2
- c. Cycle PORV as necessary.
When crew takes action to minimize SCM or when directed by the Lead Examiner, the scenario is complete.
Page 20 of 21
Appendix 0 Scenario Outline Form ES-D-2 CRITICAL TASKS 1.
CT-8, Electrical Power Alignment 2.
CT-27, Implementation of Control Room Habitability Guidance 3.
CT-7, Minimize SCM (optional) 4.
CT-1O, Establish FDW Flow and Feed Steam Generators Page 21 of 21 Appendix 0 Scenario Outline Form ES-O-2 CRITICAL TASKS
- 1. CT -8, Electrical Power Alignment
- 2. CT-27, Implementation of Control Room Habitability Guidance
- 3. CT-7, Minimize SCM (optional)
- 4. CT-10, Establish FDW Flow and Feed Steam Generators Page 21 of 21
Simulator BrieflTurnover SAFETYIPRA RISK (OSM)
SAFETY: Take a Minute PRA Risk Status: GREEN UNITO(OSM)
SSF Operable: Yes KHUs Operable: UI
- OH, U2
- UG LCTs Operable: 2 Fuel Handling: None UNIT STATUS (CR SRO)
Mode: 1 Unit I Simulator Reactor Power: 100%
Gross MWE: 897 RCS Leakage:.01 gpm RBNS Rate: 0 gpm Mode: I Unit 2 100% Power Other Units EFDW Backup: Yes Mode: 1 Unit 3 100% Power EFDW Backup: Yes Technical SpecificationslSLC Items (CR SRO)
Shift Turnover Items (CR SRO)
Primary 492 EFPD Intermittent LPSW leak in RB requires frequent RBNS pumping Secondary 1SSH-1, 1SSH-3, ISD-2, 1SD-5,1SD-140,1SD-303,1SD-355,1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 PR-i, 1 PR-6, 1 LPSW-1, 1 LPSW-2, 1 LPSW-3, 1 FDW-80, 1 CF-5, 1 CF-6, 1 LP-1 and 1 LP-2 breakers open per the appropriate system operating procedures.
Unit 3 has the Aux Steam Header ComponentlTrain OOS DatelTime Restoration Required DatelTime TSISLC #
Reactivity Management (CR SRO)
RCS Boron: 30 ppmB Gp 7 Rod Position: 91%
II Batch additions as required for volume control.
II Two Human Performance Emphasis (OSM)
Procedure Use and Adherence Scenario 3 RO Simulator BriefITurnover I
SAFETY/PRA RISK (OSM)
I SAFETY: Take a Minute PRA Risk Status: GREEN UNITO (OSM SSF Operable: Yes II L<'UI I'" f"l""""hl,,: U1 - OH, U2 - UG LeTs Op II c.
ndling: None II UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100%
Mode: 1 Mode: 1 Gross MWE: 897 100% Power 100% Power RC8 Leakage:.01 gpm EFOW Backup: Yes EFOW Backup: Yes RBN8 Rate: 0 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration Required TS/SLC #
Date/Time Date/Time Shift Turnover Items (CR SRO)
Primary 492 EFPO Intermittent LP8W leak in RB requires frequent RBN8 pumping Secondary 188H-1, 188H-3, 180-2, 180-5,180-140,180-303,180-355,180-356 and 180-358 are closed with power supply breakers open per the 8tartup Procedure for 88F Overcooling Event. 1 PR-1, 1 PR-6, 1 LP8W-1, 1 LP8W-2, 1 LP8W-3, 1 FOW-80, 1 CF-5, 1CF-6, 1 LP-1 and 1 LP-2 breakers open per the appropriate system operating procedures.
Unit 3 has the Aux 8team Header Reactivity Management CRSRO)
RC8 Boron: 30 ppmB Gp 7 Rod Position: 91 %
II Batch additions as required for volume control.
Two Human Performance Emphasis (OSM)
Procedure Use and Adherence Scenario 3 RO
Appendix 0 Scenario Outline Form ES-D-1 3/10 Facility:
Oconee Scenario No.: 4 Op-Test No.:
Examiners:
Operators:
Initial Conditions:
Reactor power = 0.02%; below POAH Turnover:
Unit I Startup in progress; BOL; not after refueling LDST pressure low, requires H2 addition Startup procedure at step 3.29 (1 102/02 End 4.7)
Event Malf.No.
EventType*
Event No.
Description Oa Override AFIS does not auto actuate Ob Override 1FDW-316 failed closed 1
Override N, BOP, SRO Pressurize LDST with H2, H2 supply valve (1 H-i) fails OPEN (TS) 2 R, OATC, SRO Increase power to 3% and place ICS in AUTO 3
MPS 1 10 C, BOP, SRO 1 HP-5 (Letdown Isolation) fails CLOSED (TS) 4 Override C, OATC, SRO 1 RC-i (Pzr Spray Valve) fails open 5
MCSO12 M, ALL 1A Turbine bypass valve and its block valve fail open due to instrument failure Excessive Heat Transfer 1FDW-316 failed closed requiring feed through the startup header Transfer to FCDtab (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 3/10 Facility: Oconee Scenario No.: 4 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions:
Reactor power = 0.02%; below POAH Turnover:
Unit 1 Startup in progress; BOL; not after refueling LDST pressure low, requires H2 addition Startup procedure at step 3.29 (1102/02 Encl 4.7)
. Event Malf. No.
Event Type*
Event No.
Description Oa Override AFIS does not auto actuate Ob Override 1FDW-316 failed closed 1
Override N, BOP, SRO Pressurize LDST with H2, H2 supply valve (1 H-1) fails OPEN (TS) 2 R,OATC,SRO Increase power to 3% and place ICS in AUTO 3
MPS 110 C, BOP, SRO 1 HP-5 (Letdown Isolation) fails CLOSED (TS) 4 Override C, OATC, SRO 1 RC-1 (pzr Spray Valve) fails open 5
MCS012 M, ALL 1 A Turbine bypass valve and its block valve fail open due to instrument failure Excessive Heat Transfer 1 FDW-316 failed closed requiring feed through the startup header Transfer to FCD tab N)ormal, (R)eactivity, (I)nstrument, (C)omf'onent, (M)ajor
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: I Page 1 of 2 Event
Description:
Pressurize LDST with H2, H2 supply valve (IH-1) fails OPEN (N, BOP, SRO)
(TS)
Time Position Applicants Actions or Behavior Crew response:
SRO Direct the BOP to add H2 to the LDST using OP/i/A/1106/017 (Hydrogen System) Enclosure 4.5 (Unit 1 LDST H2 Addition).
- .5 (Unit 1 LDST H2 Addition) will:
Notify Chemistry of hydrogen addition prior to adding hydrogen.
NOTE:
OP/C/All 108/001 (Curves And General Information) and computer may be referred to for LDST Pressure vs. Level curve.
LDST Maximum Pressure vs Indicated Level Curve should NOT be exceeded when pressurizing LDST.
Immediately prior to pressurization determine lowest reading of diverse LDST level indications:
inches.
For existing LDST level determine LDST Pressure allowable per LDST Pressure vs. Level curve:
psig.
Notify Operator at H2 Cage to pressurize primary hydrogen.
NOTE:
Operator should be in constant communication with CR to close 1H-26 if 1H-l fails open.
Direct Operator to open 1 H-26 (LDST Block).
Direct Operator to monitor explosive detector.
Cycle 1 H-i (LDST SUPPLY) as required to pressurize LDST per LDST Pressure vs Level curve.
Note: IH-I (LDST SUPPLY) will fail open.
WHEN Hydrogen addition complete, ensure closed 1 H-1(LDST SUPPLY).
Page 2 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Page 1 of 2 Event
Description:
Pressurize LDST with H2, H2 supply valve (1 H-1) fails OPEN (N, BOP, SRO)
(TS)
Time Position Applicant's Actions or Behavior Crew response:
SRO Direct the BOP to add H2 to the LOST using OP/1/A/11 06/017 BOP (Hydrogen System) Enclosure 4.5 (Unit 1 LOST H2 Addition).
- .5 (Unit 1 LOST H2 Addition) will:
Notify Chemistry of hydrogen addition prior to adding hydrogen.
NOTE:
OP/O/A/1108/001 (Curves And General Information) and computer may be referred to for LOST Pressure vs. Level curve.
LOST Maximum Pressure vs Indicated Level Curve should NOT be exceeded when pressurizing LOST.
Immediately prior to pressurization determine lowest reading of diverse LOST level indications:
inches.
For existing LOST level determine LOST Pressure allowable per LOST Pressure vs. Level curve:
psig.
Notify Operator at H2 Cage to pressurize primary hydrogen.
NOTE: Operator should be in constant communication with CR to close 1 H-26 if 1 H-1 fails open.
Direct Operator to open 1 H-26 (LOST Block).
Direct Operator to monitor explosive detector.
Cycle 1 H-1 (LOST SUPPLY) as required to pressurize LOST per LOST Pressure vs Level curve.
Note: 1 H-1 (LDST SUPPLY) will fail open.
WHEN Hydrogen addition complete, ensure closed 1 H-1 (LOST SUPPLY).
Page 2 of 15
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: I Page 2 of 2 Event
Description:
Pressurize LDST with H2, H2 supply valve (IH-I) fails OPEN (N, BOP, SRO)
(TS)
Time Position Applicants Actions or Behavior Plant response:
LDST pressure will continue to increase.
1 SA-02/D-2, HP Approaching LDST Operating Limits, actuates Crew response:
BOP BOP should determine that 1 H-i has failed open and direct the NLO to close 1 H-26.
Refer to the ARG.
Verify LDST pressure/level are within the acceptable operating region of the LDST PRESSURE vs. LEVEL enclosure in OP/C/Ni 108/001 (Curves and General Information).
SRO IF necessary, vent LDSTt0 GWD per OP/1!N1104/002 (HPI System).
LDST PRESSURE vs. LEVEL enclosure in OP/O/N1 108/001 (Curves and General Information) directs the following:
If LDST Pressure vs. Level is above and to the left of Curve 1, then declare BOTH trains of HPI INOPERABLE.
o Immediately depressurize LDST below Curve 1.
o Refer to TS 3.0.3 for shutdown requirements.
o Make notifications as required by OMP 1-14 (Notifications).
BOP Direct the ROs to vent LDST to GWD per OP/i/Ni 104/002 (HPI System), End. 4.16, (Lowering LDST Pressure)
Review Limits and Precautions Direct Operator to Close 1 GWD-20 (LDST Vent Bik).
Open IGWD-i9 (LDST VENT).
Direct Operator to throttle open I GWD-20 (LDST Vent BIk) until LDST pressure begins to slowly decrease and GWD system can maintain vent header.
WHEN desired LDST pressure obtained, close 1GWD-i9 (LDST VENT)
Event is complete when vent of LDST is complete or when directed by the Lead Examiner.
Page 3 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Page 2 of 2 Event
Description:
Pressurize LDST with H2, H2 supply valve (1H-1) fails OPEN (N, BOP, SRO)
(TS)
Time Position Applicant's Actions or Behavior Plant response:
LDST pressure will continue to increase.
1 SA-02/D-2, HP Approaching LDST Operating Limits, actuates Crew response:
BOP BOP should determine that 1 H-1 has failed open and direct the NLO to close 1 H-26.
Refer to the ARG.
Verify LDST pressure/level are within the acceptable operating region of the LDST PRESSURE vs. LEVEL enclosure in OP/0/A/1108/001 (Curves and General Information).
SRO IF necessary, vent LDST to GWD per OP/1/A/1104/002 (HPI System).
BOP LDST PRESSURE vs. LEVEL enclosure in OP/0/A/11 081001 (Curves and General Information) directs the following:
If LDST Pressure vs. Level is above and to the left of Curve 1, then declare BOTH trains of HPI INOPERABLE.
o Immediately depressurize LDST below Curve 1.
o Refer to TS 3.0.3 for shutdown requirements.
o Make notifications as required by OMP 1-14 (Notifications).
Direct the ROs to vent LDST to GWD per OP/1/A/1104/002 (HPI System), Enc!. 4.16, (Lowering LDST Pressure)
Review Limits and Precautions Direct Operator to Close 1 GWD-20 (LDST Vent Blk).
Open 1GWD-19 (LDST VENT).
Direct Operator to throttle open 1 GWD-20 (LDST Vent Blk) until LDST pressure begins to slowly decrease and GWD system can maintain vent header.
WHEN desired LDST pressure obtained, close 1GWD-19 (LDST VENT)
Event is complete when vent of LDST is complete or when directed by the Lead Examiner.
Page 3 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 2 Page 1 of 1 Event
Description:
Increase reactor power to 3% and place ICS in AUTO: (R, OATC, SRO)
Time Position Applicants Actions or Behavior Crew response:
OP/i/Ni 102/001 (Controlling Procedure for Unit Startup)
NOTE:
POAH is normally achieved from 0.05 to 0.15% power on Wide Range Indications.
When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, & SUR will decrease with negative Moderator SRO/OATC Temperature Coefficient.
BOP Begin reactor power increase to 0.5%
- 1.0% at 0.5 DPM SUR.
WHEN above POAH, begin reactor power increase to 2.5 -3.5%.
WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215 to 225 PZR Level WHEN at 2.5%
- 3.5% Power, perform the following:
Place REACTOR MASTER to AUTO.
Place DIAMOND to AUTO.
Ensure TURBINE MASTER Setpoint to 880
- 890 psig.
Event is complete when ICS is placed in AUTO or when directed by the Lead Examiner.
Page 4of15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Page 1 of 1 Event
Description:
Increase reactor power to 3% and place ICS in AUTO: (R, OATC, SRO)
Time Position SROIOATC BOP Applicant's Actions or Behavior Crew response:
OP/1/A/1102/001 (Controlling Procedure for Unit Startup)
NOTE:
POAH is normally achieved from 0.05 to 0.15% power on Wide Range Indications.
When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, & SUR will decrease with negative Moderator Temperature Coefficient.
Begin reactor power increase to 0.5% - 1.0% at :5 0.5 DPM SUR.
WHEN above POAH, begin reactor power increase to 2.5 -3.5%.
WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215" to 225" PZR Level WHEN at 2.5% - 3.5% Power, perform the following:
Place REACTOR MASTER to "AUTO".
Place DIAMOND to "AUTO".
Ensure TURBINE MASTER Setpoint to::::: 880 - 890 psig.
Event is complete when ICS is placed in AUTO or when directed by the Lead Examiner.
Page 4 of 15
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 3 Page 1 of 2 Event
Description:
IHP-5 (Letdown Isolation) fails CLOSED (TS) (C, BOP, SRO)
Time Position Applicants Actions or Behavior Plant Response:
OATC 1HP-5 green closed light is lit Pzr Level slowly increases LDST Level slowly decreases Crew Response:
Enters AP/32, Loss of Letdown OATC/S Place 1HP-120 in HAND and reduce demand to zero.
RO Initiate makeup to LDST as required.
Initiate notification of the following:
OSM to reference OMP 1-14 (Notifications) and Emergency Plan STA Notify Chemistry of the following:
Current RCS boron sample is needed for possible unit shutdown.
Normal letdown line is isolated IAAT either of the following exist:
Pzr level > 260, AND letdown CANNOT be established Plant conditions exist such that letdown will NOT be restored THEN initiate unit shutdown at 20%/mm per AP/29 (Rapid Unit Shutdown).
IAAT Pzr level
- 375, THEN trip Rx.
Position the standby HPI pump switch to OFF.
Step 4.8, Throttle 1HP-31 to establish 12-15 gpm SEAL INLET HDR FLOW.
Verify HPI pump flow 65 gpm. (If less than 65 gpm, log beginning time for HLP pump flow below minimum).
GO TO Step 4.11 per Table in AP/32 Close 1HP-6.
Close 1HP-7.
Open 1 HP-5. (will not open from control room)
Page 5 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page 1 of 2 Event
Description:
1HP-5 (Letdown Isolation) fails CLOSED (TS) (C, BOP, SRO)
Time Position OATC OATC/S RO Applicant's Actions or Behavior Plant Response:
1 HP-5 green closed light is lit Pzr Level slowly increases LOST Level slowly decreases Crew Response:
Enters AP/32, Loss of Letdown Place 1 HP-120 in HAND and reduce demand to zero.
Initiate makeup to LOST as required.
Initiate notification of the following:
OSM to reference OMP 1-14 (Notifications) and Emergency Plan STA Notify Chemistry of the following:
Current RCS boron sample is needed for possible unit shutdown.
Normal letdown line is isolated IAAT either of the following exist:
Pzr level> 260",
AND letdown CANNOT be established Plant conditions exist such that letdown will NOT be restored THEN initiate unit shutdown at::::: 20%/min per AP/29 (Rapid Unit Shutdown).
IAAT Pzr level;::: 375",
THEN trip Rx.
Position the standby HPI pump switch to OFF.
Step 4.8, Throttle 1 HP-31 to establish 12 - 15 gpm SEAL INLET HDR FLOW.
Verify HPI pump flow;::: 65 gpm. (If less than 65 gpm, log beginning time for HLP pump flow below minimum).
GO TO Step 4.11 per Table in AP/32 Close 1 HP-6.
Close 1 HP-7.
Open 1 HP-5. (will not open from control room)
Page 5 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 3 Page 2 of 2 Event
Description:
IHP-5 (Letdown Isolation) fails CLOSED (TS) (C, BOP, SRO)
Time Position Applicants Actions or Behavior BOPISRO Open 1 HP-5 RNO actions as follows:
o Dispatch NEO in continuous communications with control room to manually open 1 HP-5 Booth cue: Using TIME COMPRESSION report that IHP-5 is manually open.
Note: Continuous communication can be accomplished using either plant radio or telephone o
IF 1 HP-5 is manually open, THEN enter TS 3.6.3 (Condition A, 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> completion time)
Note: I HP-5 is allowed to be manually opened by Note I.
WHEN 1 HP-5 is open, THEN continue.
Place CC system in operation.
Verify letdown temperature < 135°F.
Throttle 1 HP-7 to establish 20 gpm WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.
Open 1HP-6 Adjust 1 HP-7 to control desired letdown flow.
Re-establish normal makeup through 1HP-120.
Notify SPOC to initiate repairs on I HP-5.
Verify seal injection flow reduced in Step 4.8.
Re-establish normal RCP seal injection flow.
Position the standby HPI pump switch to AUTO.
WHEN repairs are complete on 1HP-5 (LETDOWN ISOLATION)
THEN perform the following:
o Locally turn 1 HP-S handwheel fully clockwise.
o EXITTS3.6.3.
Note: IHP-5 will not be repaired during this scenario Note: If Pzr level exceeds 260 inches, TS 3.4.9 Conditions A should be entered requiring level to be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
When I HP-5 is manually opened and NEO is stationed locally or when directed by Lead Examiner then this event is complete.
Page 6 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page 2 of 2 Event
Description:
1 HP-5 (Letdown Isolation) fails CLOSED (TS) (C, BOP, SRO)
Time Position BOP/SRO Applicant's Actions or Behavior Open 1 HP-5 RNO actions as follows:
o Dispatch NEO in continuous communications with control room to manually open 1 HP-5 Booth cue: Using TIME COMPRESSION report that 1 HP-5 is manually open.
Note: Continuous communication can be accomplished using either plant radio or telephone o
IF 1 HP-5 is manually open, THEN enter TS 3.6.3 (Condition A, 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> completion time)
Note: 1 HP-5 is allowed to be manually opened by Note 1.
WHEN 1 HP-5 is open, THEN continue.
Place CC system in operation.
Verify letdown temperature < 135°F.
Throttle 1 HP-7 to establish -20 gpm WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.
Open 1 HP-6 Adjust 1 HP-7 to control desired letdown flow.
Re-establish normal makeup through 1 HP-120.
Notify SPOC to initiate repairs on 1 HP-5.
Verify seal injection flow reduced in Step 4.8.
Re-establish normal RCP seal injection flow.
Position the standby HPI pump switch to AUTO.
WHEN repairs are complete on 1HP-5 (LETDOWN ISOLATION)
THEN perform the following:
o Locally turn 1 HP-5 handwheel fully clockwise.
o EXIT TS 3.6.3.
Note: 1 HP-5 will not be repaired during this scenario Note: If Pzr level exceeds 260 inches, TS 3.4.9 Conditions A should be entered requiring level to be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
When 1 HP-5 is manually opened and NEO is stationed locally or when directed by Lead Examiner then this event is complete.
Page 6 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 4 Page 1 of 1 Event
Description:
PZR Spray Valve Fails OPEN: (C, OATCISRO)
Time Position Applicants Actions or Behavior Booth cue:
Call as RP and ask BOP to report the pressure in the GWD gas tanks.
Plant response:
RCS pressure will decrease 1SA-21D-3, RC PRESS HIGH/LOW Crew response:
Refer to ARG SRO/OATC Refer to 1AP/44, Abnormal Pzr Pressure Control Note: If the block valve is not closed, the reactor will trip on variable low pressure and ES actuation will occur.
If the operator identifies 1 RC-1 has failed open, he should immediately close the block valve (1 RC-3) per IMAs of AP/44 Evaluate reducing or isolating letdown flow Increase makeup flow as required SRO enters to 1AP/44, Abnormal Pzr Pressure Control IAAT all of the following conditions exist:
RC pressure < 2155 psig RC pressure decreasing without a corresponding decrease in PZR level PZR heaters are on THEN close the following:
1RC-1 1RC-3 Verify Pzr heaters maintaining RCS pressure w/in bands Notify SPOC to repair failed 1 RC-1 Ensure TS requirements met WHEN repairs are complete, THEN place 1 RC-1 and 1 RC-3 in the desired positions.
Note: The PZR spray valve will remain failed for the remainder of the scenario.
When RCS pressure decrease has been stopped, or when directed by the Lead Examiner this event is completed.
Page 7of15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Page 1 of 1 Event
Description:
PZR Spray Valve Fails OPEN: (C, OATC/SRO)
Time Position Applicant's Actions or Behavior Booth cue: Call as RP and ask BOP to report the pressure in the GWD gas tanks.
Plant response:
RCS pressure will decrease 1 SA-21D-3, RC PRESS HIGH/LOW Crew response:
Refer to ARG SRO/OATC Refer to 1 AP/44, Abnormal Pzr Pressure Control Note: If the block valve is not closed, the reactor will trip on variable low pressure and ES actuation will occur.
If the operator identifies 1 RC-1 has failed open, he should immediately close the block valve (1 RC-3) per IMAs of AP/44 Evaluate reducing or isolating letdown flow Increase makeup flow as required SRO enters to 1AP/44, Abnormal Pzr Pressure Control IAAT all of the following conditions exist:
RC pressure < 2155 psig RC pressure decreasing without a corresponding decrease in PZR level PZR heaters are on THEN close the following:
1 RC-1 1 RC-3 Verify Pzr heaters maintaining RCS pressure w/in bands Notify SPOC to repair failed 1 RC-1 Ensure TS requirements met WHEN repairs are complete, THEN place 1 RC-1 and 1 RC-3 in the desired positions.
Note: The PZR spray valve will remain failed for the remainder of the scenario.
When RCS pressure decrease has been stopped, or when directed by the Lead Examiner this event is completed.
Page 7 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 1 of 7 Event
Description:
IA TBV fails OPEN (I: OATC, SRO)
Time Position Applicants Actions or Behavior Plant response:
OAC alarm 1A Turbine Bypass Valve fails open.
1A Main Steam line pressure decreases Reactor Coolant Temperature decreases causing reactor power to increase.
SRO/OATC Crew response Crew will perform Low Power Plant Transient Response.
Place lCS Diamond Panel to MAN Place ICS Feedwater Loop Masters 1A &1B to HAND OATC Insert Control Rods to reduce power to below pre-transient level As 1A SG pressure continues to decrease, the OATC should trip the reactor due to the anticipated affects of the excessive heat transfer.
When the reactor is tripped or when directed by the Lead Examiner, this event is completed Page 8 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 1 of 7 Event
Description:
1A TBV fails OPEN (I: OATC, SRO)
Time Position Applicant's Actions or Behavior Plant response:
OAC alarm 1 A Turbine Bypass Valve fails open.
1A Main Steam line pressure decreases Reactor Coolant Temperature decreases causing reactor power to increase.
SRO/OA TC Crew response OATC Crew will perform Low Power "Plant Transient Response".
Place ICS Diamond Panel to MAN Place ICS Feedwater Loop Masters 1A &1 B to HAND Insert Control Rods to reduce power to below pre-transient level As "1A" SG pressure continues to decrease, the OATC should trip the reactor due to the anticipated affects of the excessive heat transfer.
When the reactor is tripped or when directed by the Lead Examiner, this event is completed Page 8 of 15
Plant response:
Reactor is manually tripped 1A SG pressure continues to decrease AFIS fails to initiate automatically Crew response:
Perform Immediate Manual Actions (IMAs)
Depress REACTOR TRIP pushbutton.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed.
Verify RCP seal injection available.
Perform Symptom Check Power Range NIs <5%
Power Range Nis decreasing SCMs are > 0°F NO Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) exists Uncontrolled Main steam line(s) pressure decrease NOSGTR CSAE Offgas alarms Process monitor alarms (RIA-40, 59, 60)
Area monitor alarms (RIA-16/17)
An RO will recognize indications of a steam line break on the 1A MS Line and initiate Rule 5 (Excessive Heat Transfer).
Rule 5 (CT-17)
On AFIS HEADER A, depress CH. 1 IN IT.
On AFIS HEADER A, depress CH. 2 INIT.
NOTE: AFIS will not work Select OFF for 1A MD EFDWP.
Trip both Main FDWPTs.
Close 1FDW-315.
Place 1 FDW-33 switch to CLOSE.
Place 1 FDW-31 switch to CLOSE.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 2 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicants Actions or Behavior OATC/SRO BOP BOP/OATC Page9ofl5 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 2 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicant's Actions or Behavior Plant response:
Reactor is manually tripped 1 A SG pressure continues to decrease AFIS fails to initiate automatically Crew response:
OATC/SRO Perform Immediate Manual Actions (IMAs)
BOP BOP/OATC Depress REACTOR TRIP pushbutton.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed.
Verify RCP seal injection available.
Perform Symptom Check Power Range N Is < 5%
Power Range Nls decreasing SCMs are> O°F NO Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) exists Uncontrolled Main steam line(s) pressure decrease NO SGTR CSAE Offgas alarms Process monitor alarms (RIA-40, 59, 60)
Area monitor alarms (RIA-16/17)
An RO will recognize indications of a steam line break on the 1A MS Line and initiate Rule 5 (Excessive Heat Transfer).
Rule 5 (CT -17)
On AFIS HEADER A, depress CH. 1 INIT.
On AFIS HEADER A, depress CH. 2 INIT.
NOTE: AFIS will not work Select OFF for 1A MD EFDWP.
Trip both Main FDWPTs.
Close 1FDW-315.
Place 1 FDW-33 switch to CLOSE.
Place 1 FDW-31 switch to CLOSE.
Page 9 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 3 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Position Applicants Actions or Behavior Crew response:
BOP/OATC Rule 5 Continued.
Verify 1 TD EFDW PUMP operating.
Verify 1 TD EFDW PUMP is feeding affected SGs. (NOT)
IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5.
Verify lB SG is an affected SG. (NOT)
WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either of the following:
o TBVs o
Dispatch two operators to perform End 5.24 (Operation of the ADVs).
CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.
WHEN aM the following exist:
CoreSCM>OF Rxpowerl%
Pzr level BOP/OATC THEN perform the following to stabilize RCS P/T:
Throttle HPI.
Reduce 1HP-120 setpointto control at >100 [180acc}.
Adjust steaming of unaffected SG as necessary to maintain CETCs constant.
Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete.
Rule 3 (Loss of Main or Emergency Feedwater)
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND y of the following exist:
o RCS pressure reaches 2300 psig OR NDT limit o
Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Page 10 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 3 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Position Applicant's Actions or Behavior Crew response:
BOP/OATC Rule 5 Continued.
BOP/OATC Verify 1 TO EFDW PUMP operating.
Verify 1 TO EFDW PUMP is feeding affected SGs. (NOT)
IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5.
Verify 1 B SG is an affected SG. (NOT)
WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either of the following:
o TBVs o
Dispatch two operators to perform Encl 5.24 (Operation of the ADVs).
CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.
WHEN ill! the following exist:
~ Core SCM> 0 F
~ Rx power:::;; 1%
~ Pzr level THEN perform the following to stabilize RCS PIT:
~ Throttle HPI.
~ Reduce 1 HP-120 setpoint to control at >100" [180"acc].
~ Adjust steaming of unaffected SG as necessary to maintain CETCs constant.
Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete.
Rule 3 (Loss of Main or Emergency Feedwater)
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
oRCS pressure reaches 2300 psig OR NOT limit o
Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Page 10 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 4 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
BOP/OATC Rule 3 continued Start EFDW pumps to feed all intact SGs.
Verify y EFDW pump operating.
IAAT both of the following exist:
An EFDW valve will NOT control in AUTO The same EFDW control valve will NOT respond in MANUAL THEN perform Steps 33 and 34.
Notify CR SRO that End. 5.27 (Alternate Methods for Controlling EFDW Flow) is being initiated due to IFDW-316 failed closed.
Initiate End. 5.27, (Alternate Methods for Controlling EFDW Flow)
BOP/OATC End. 5.27 Identify the failure: (CHART; 1 FDW-31 6 CLOSED) Step 39 Stop lB MD EFDWP.
Verify IA MD EFWP is operating. (RNO)
Close 1 FDW-369; GO TO Step 43.
Place 1 FDW-44 in HAND and set demand to 0%.
OATC/SRO Close 1 FDW-42 Verify 1 B MD EFDWP will be used.
Open 1 FDW-384.
Verify the following:
1 FDW-45 closed 1FDW-47 open Start1BMDEFDWP.
Throttle 1FDW-44 to establish 100 gpm. (100 gpm is the Rule 7 limit for initial feeding a dry SG. After heat transfer is established the limit is 600 gpm per rule 7).
Throttle 1 FDW-44 to obtain desired SG level per Rule 7 (SG Feed Control). (CT-b)
IAAT proper SG level is reached (25) and level permits auto level control, THEN place 1 FDW-44 in AUTO.
Page 11 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 4 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
I Time Position Applicant's Actions or Behavior Crew response:
BOP/OATC Rule 3 continued BOP/OATC OATC/SRO Start EFDW pumps to feed all intact SGs.
Verify any EFDW pump operating.
IAAT both of the following exist:
An EFDW valve will NOT control in AUTO The same EFDW control valve will NOT respond in MANUAL THEN perform Steps 33 and 34.
Notify CR SRO that Encl. 5.27 (Alternate Methods for Controlling EFDW Flow) is being initiated due to 1 FDW-316 failed closed.
Initiate Encl. 5.27, (Alternate Methods for Controlling EFDW Flow)
Encl. 5.27 Identify the failure: (CHART; 1 FDW-316 - CLOSED) Step 39 Stop 1 B MD EFDWP.
Verify 1A MD EFWP is operating. (RNO)
Close 1 FDW-369; GO TO Step 43.
Place 1 FDW-44 in HAND and set demand to 0%.
Close 1 FDW-42 Verify 1 B MD EFDWP will be used.
Open 1 FDW-384.
Verify the following:
1 FDW-45 closed 1 FDW-47 open Start 1 B MD EFDWP.
Throttle 1 FDW-44 to establish 100 gpm. (100 gpm is the Rule 7 limit for initial feeding a dry SG. After heat transfer is established the limit is 600 gpm per rule 7).
Throttle 1 FDW-44 to obtain desired SG level per Rule 7 (SG Feed Control). (CT-10)
IAAT proper SG level is reached (25") and level permits auto level control, THEN place 1 FDW-44 in AUTO.
Page 11 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 5 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position
]
Applicants Actions or Behavior Crew response:
SRO Transfer to EOP Subsequent Actions tab then to the Excessive Heat Transfer tab per the Parallel Actions page of Subsequent Actions Verify any SG pressure < 550 psig.
Ensure Rule 5 (Main Steam Line Break) in progress or complete.
Place the following in HAND and decrease demand to zero on ji affected SGs:
1FDW-32 1FDW-35 SRO/BOP Close the following on all affected SGs:
/OATC 1 FDW-372
1MS-17 1MS-79 1MS-35 1M5-82 1FDW-368 Verify level in both SGs <96% O.R.
SRO/BOP
/OATC IAAT core SCM is > 0°F, Throttle HPI per Rule 6 (HPI).
Verify letdown in service.
Verify any SG has an intact secondary boundary (intact SG).
Open the following on all intact SGs:
1FDW-382 1 FDW-369 Start1BMDEFDWP Feed and steam aM intact SGs to stabilize RCS P/T using either of the following:
TBV5 Dispatch two operators to perform End 5.24 (Operation of the ADVs).
Page 12 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 5 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
SRO Transfer to EOP Subsequent Actions tab then to the Excessive Heat Transfer tab per the Parallel Actions page of Subsequent Actions SRO/BOP IOATC SRO/BOP IOATC Verify any SG pressure < 550 psig.
Ensure Rule 5 (Main Steam Line Break) in progress or complete.
Place the following in HAND and decrease demand to zero on ill!
affected SGs:
1 FDW-32 1 FDW-35 Close the following on all affected SGs:
1FDW-372 1MS-17 1 MS-79 1MS-35 1 MS-82 1FDW-368 Verify level in both SGs < 96% O.R.
IAAT core SCM is > OaF, Throttle HPI per Rule 6 (HPI).
Verify letdown in service.
Verify any SG has an intact secondary boundary (intact SG).
Open the following on all intact SGs:
1 FDW-382 1 FDW-369 Start 1 B MDEFDWP Feed and steam ill! intact SGs to stabilize RCS PIT using either of the following:
TBVs Dispatch two operators to perform Encl 5.24 (Operation of the ADVs).
Page 12 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 6 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)
/BOP Verify y of the following:
HPI has operated in the injection mode while NO RCPs were operating A cooldown below 400 °F at> 100 °FIhr has occurred Verify both of the following are closed:
Close the following 1 SSH-9.
Notify Chemistry to determine RCS boron concentration IAAT all the following exist:
ES Bypass Permit satisfied AIISCMs>OLIF RCS pressure controllable THEN bypass ES as necessary.
Verify any SG is dry.
Minimize SCM using the following methods as necessary:
De-energize all Pzr heaters Use Pzr spray Throttle HPI to maintain Pzr level 1OQ[18Qacc]
Use PORV Verify any RCP operating. Maintain RCP NPSH.
OAC End 5.18 (P/T Curves)
Initiate End 5.16 (SG Tube-to-Shell T Control).
IAAT all the following exist:
RBS actuated RB pressure < 10 psig 1 RIA-57 NOT in alarm 1 RIA-58 NOT in alarm THEN stop both RBS pumps.
Page 13 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 6 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Position Applicant's Actions or Behavior Crew response:
OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)
IBOP Verify any of the following:
HPI has operated in the injection mode while NO RCPs were operating A cooldown below 400 of at > 100 °F/hr has occurred Verify both of the following are closed:
1 MS-24 1 MS-33 Open 1AS-8.
Close the following 1 SSH-9.
Notify Chemistry to determine RCS boron concentration IAA T all the following exist:
ES Bypass Permit satisfied All SCMs > ODF RCS pressure controllable THEN bypass ES as necessary.
Verify any SG is dry.
Minimize SCM using the following methods as necessary:
De-energize all Pzr heaters Use Pzr spray Throttle HPI to maintain Pzr level 10Q"[18Q"acc]
Use PORV Verify any RCP operating. Maintain RCP NPSH.
OAC Encl 5.18 (PIT Curves)
Initiate Encl 5.16 (SG Tube-to-Shelll1 T Control).
IAAT all the following exist:
RBS actuated RB pressure < 10 psig 1 RIA-57 NOT in alarm 1 RIA-58 NOT in alarm THEN stop both RBS pumps.
Page 13 of 15
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 7 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicants Actions or Behavior Crew response:
OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)
/BOP Verify any RCP operating. Maintain RCP NPSH.
OAC End 5.18 (P/T Curves)
Initiate End 5.16 (SG Tube-to-Shell T Control).
IAAT all the following exist:
RBS actuated RB pressure < 10 psig 1 RIA-57 NOT in alarm 1 RIA-58 NOT in alarm THEN stop both RBS pumps.
IAAT Tcold approaches 350° F, AND all RCPs are operating, THEN ensure <four RCPs are operating.
IAAT BWST level is 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES).
Verify all SCMs> 0°F.
Verify indications of SGTR exist.
Verify required RCS makeup flow within normal makeup capability Verify either of the following:
Any SG isolated Any SG has an unisolable steam leak GO TO FCD tab.
When transfer to the FCD tab is made or when directed by the Lead Examiner this event is completed Page 14 of 15 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 7 of 7 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position OATC/SRO IBOP Applicant's Actions or Behavior Crew response:
Excessive Heat Transfer tab of the EOP (Continued)
Verify any RCP operating. Maintain RCP NPSH.
OAC Ene! 5.18 (PIT Curves)
Initiate Ene! 5.16 (SG Tube-to-Shell f1 T Control).
IAAT all the following exist:
RBS actuated RB pressure < 10 psig 1 RIA-57 NOT in alarm 1 RIA-58 NOT in alarm THEN stop both RBS pumps.
IAAT Tcold approaches 350°F, AND all RCPs are operating, THEN ensure < four RCPs are operating.
IAAT BWST level is::; 19',
THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).
Verify all SCMs > OaF.
Verify indications of SGTR exist.
Verify required RCS makeup flow within normal makeup capability Verify either of the following:
Any SG isolated Any SG has an unisolable steam leak GO TO FCD tab.
When transfer to the FCD tab is made or when directed by the Lead Examiner this event is completed Page 14 of 15
Appendix 0 Scenario Outline Form ES-D-2 CRITICAL TASKS 1
CT-i 7, Isolate Overcooling 2.
CT-10, Establish FDW Flow and Feed SGs Page 15 of 15 Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS
- 1. CT-17, Isolate Overcooling
- 2. CT-10, Establish FDW Flow and Feed SGs Page 15 of 15
Simulator BrieflTurnover SAFETYIPRA RISK (OSM)
SAFETY: Take a Minute PRA Risk Status: GREEN UNIT 0 (OSM)
SSF Operable: Yes KHUs Operable: UI
- OH, U2 - UG LCTs Operable: 2 Fuel Handling: None UNIT STATUS (CR SRO)
Unit I Simulator Other Units Mode:2 Unit2 Unit3 Reactor Power: 02%
Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.1 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0 gpm Technical Specifications!SLC Items (CR SRO)
ComponentlTrain OOS Restoration Required TSISLC #
DatelTime DatelTime Shift Turnover Items (CR SRO)
Primary Unit 1 was started up following a RFO and operated at power for 1 week. Turbine vibration problems required the unit to be shutdown. Turbine vibration problems have been fixed.
LDST pressure is low and requires H2 make up. After turnover is complete, perform a H2 make up to the LDST using OPII/A11106/017, End. 4.5.
Unit 1 Startup procedure in progress. OP/i/Ni 102/001 Enclosure 4.7 (Unit Startup From 532°F and 2155 psig) is complete up through step 3.28.
OP/i/Ni105/0i9 (Control Rod Drive) in progress. Initial Conditions completed Rx power 0.01%; below the POAH. After turnover is complete continue with the startup at step 3.29.
Secondary 1 SSH-i, 1 SSH-3, 1 SD-2, 1 SD-5, 1 SD-i 40,1 SD-303, 1 SD-355,1 SD-356 and 1 SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. iPR-i, iPR-6, 1LPSW-1, 1LPSW-2, 1LPSW-3, 1FDW-80, 1CF-5, 1CF-6, 1LP-i and I LP-2 breakers open per the appropriate system operating procedures.
Reactivity Management (CR SRO)
RCS Boron: 11 64ppmB Gp 6 Rod Position: 48%
Batch additions as required for volume control.
Human Performance Emphasis (OSM)
Procedure Use and Adherence Scenario 4 RO Simulator BrieflTurnover SAFETY/PRA RISK (OSM)
SAFETY: Take a Minute PRA Risk Status: GREEN UNIT 0 (OSM)
~~~ ~
/0
." I1na."hla: U1 - OH, U2 - UG II LeTs Oper~~.~. - j:.-.
.. ~: Mone UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power:.02%
Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.1 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration Required TS/SLC #
DatelTime Date/Time Shift Turnover Items (CR SRO)
Primary Unit 1 was started up following a RFO and operated at power for 1 week. Turbine vibration problems required the unit to be shutdown. Turbine vibration problems have been fixed.
LOST pressure is low and requires H2 make up. After turnover is complete, perform a H2 make up to the LOST using OP/1 /A/11 06/017, Encl. 4.5.
Unit 1 Startup procedure in progress. OP/1/A/1102/001 Enclosure 4.7 (Unit Startup From 532°F and 2155 psig) is complete up through step 3.28.
OP/1/A/11 05/019 (Control Rod Orive) in progress. Initial Conditions completed Rx power = 0.01 %; below the POAH. After turnover is complete continue with the startup at step 3.29.
Secondary 1 SSH-1, 1 SSH-3, 1 SO-2, 1 SO-5, 1 SO-140, 1 SO-303, 1 SO-355, 1 SO-356 and 1 SO-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 PR-1, 1 PR-6, 1 LPSW-1, 1 LPSW-2, 1 LPSW-3, 1 FOW-80, 1 CF-5, 1 CF-6, 1 LP-1 and 1 LP-2 breakers open per the appropriate system operating procedures.
Reactivitv Management (CR SRO)
RCS Boron: 1164ppmB I Gp 6 Rod Position: 48%
II Batch additions as required for volume control.
Human Performance Emphasis OSM)
Procedure Use and Adherence Scenario 4 RO