ML101520517
| ML101520517 | |
| 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: ML101520517 (75) | |
Text
Appendix D Scenario Outline Form ES-D-1 3/10 Facility: Oconee Scenario No.: 1 I Op-Test No.: 1 Examiners: Operators:
Initial Conditions:
- . 65% Reactor Power
- . Place the 1A Main FDW Pump on Handjack Event Maif. No.
Malf. Type*
Event Type* Event No. Description Oa Pre-Insert Switch will not stop 1 1B2 B2 RCP when directed by Rule 2 AO AOR R Ob Pre-Insert 1 1 HP-3 fails to close on ES AOR Oc Pre-Insert All turbine trips bypassed AOR 1
1 Override N, BOP, SRO Place 1 1A A Main Feedwater Pump on Handjack 2 MSS 200 C, BOP, SRO Vacuum Leak 3 P8D58ZW C, SRO C,SRO Safety shutdown of chiller (TS) 4 MPS 247 C, BOP, SRO 1 B1 RCP lower seal fails (Requires pump shutdown) 1 5 MPI 281 MPI281 I, OATC, SRO CS fails to re-ratio Feedwater ICS 6 MPS 248 C, ALL RCS Leak (1 B1 BI RCP middle and upper seals fail) (TS)
MPS 249 7 R, OATC, SRO Manual plant shutdown 8 Pre-Insert C, OATC, SRO C,OATC,SRO Turbine fails to trip requirin~
requiring EHC pumps lockout 9 MPS 400 M, ALL M,ALL SBLOCA (LOSCM to LOCA CD) 1 1 HP-3 fails to close on ES Switch will NOT stop 1 I B2 RCP when directed by Rule 2
- (N)ormal, (R)eactivity, (l)nstrument, (I)nstrument (C)omponent, (C)omponent (M)ajor DR Page 11 of 18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Op-Test No.: 11 Scenario No.: 1I Event No.: 11 Page 11 of 11 Event
Description:
Event
Description:
Place 1A IA Main Main Feedwater Pump on Handjack:
Feedwater Pump Handjack: (N; (N; BOP, BOP, SRO)
Time Position Applicants Actions or Behavior Applicant's Crew response:
BOP OP/I/Ni 106/002 B Enclosure 4.10 (Placing 1A FDWPT On Handjack)
OP/1/A/1106/002
- 1. Ensure 1A MAIN FDW PUMP (ICS) in "HAND".
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.
- 2. Run 1A FDWPT Motor Speed Changer down to control1Acontrol 1A FDWPT.
NOTE:
ON simulates Motor Gear Unit at high speed stop.
Handjack "ON" When Handjack switch is placed to on FDWPT speed may increase -40 40 rpm.
- 3. HAN DJACK switch to "ON".
Turn FDWPT 1A HANDJACK ON.
- 4. 1A FDWPT speed now controlled with 1A FDWPT Motor Speed Changer.
- 5. Record on Turnover Sheet control of 1A FDWPT on Motor Speed Changer.
- 6. T/O SHEET" Place "T/O SHEET CR tag on 1A MAIN FDW PUMP (ICS) station.
When the IA1A Main FDW pump is on Handjack or when directed by the Lead Examiner this event is completed.
Page 22 of of 18 18
Appendix D Scenario Outline Scenario Form ES-D-2 Op.Test No.:
Op-Test No.: 11 Scenario No.:
Scenario No.: 11 Event No.: 22 Event No.: Page Page 11 of of 11 Event
Description:
Event
Description:
Leak: (C; Vacuum Leak: BOP, SRO)
(C; BOP, Time Position
[ Plant response:
Applicant's Applicants Actions or Behavior
- 1SA-031A-6, COND VACUUM LOW 1SA-03/A-6,
- OAC alarm, Main Condenser Vacuum LOW Crew response:
AP!27, Loss of Condenser Vacuum.
Refer to the ARG and AP/27, BOP Refer to AP/27:
SRO BOP 1. Announce AP entry using PA system.
- 2. 22 Hg, THEN trip RX.
IAAT condenser vacuum is :::; 22"
- 3. End. 5.1 (Main Vacuum Pump Alignment) and look Dispatch operators to perform Enc!.
for vacuum leaks.
Cue: Notify CR that USING TIME COMPRESSION, Main Vacuum Pumps are End. 5.1.
aligned per Encl.
- 4. Start all Main Vacuum Pumps.
- 5. Ensure 1V-186 is closed.
- 6. Ensure Stm to Stm Air Eject A, B, C > > 255 psig.
- 7. Verify Stm Seal Hdr Press> 1.5 psig.p51g.
Start 1
- 9. flow 2300 gpm.
Verify Condensate flow;::
- 10. WHEN condenser vacuum is stable, AND Encl 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.
Appendix D Scenario Outline Form ES-D-2 No.: 11 Op-Test No.: No.: 1I Scenario No.: Event Event No.:
No.: 3 Page Page 11 of 11 Event
Description:
Event
Description:
Safety shutdown of Chiller: (TS, SRO)
Time Position j Applicants Actions or Behavior Applicant's Plant response:
BOP Crew response:
- 11SA-06/E-10, SA-06/E-1 0, AH CHILLER COMPRSSR PNL AlB A/B TROUBLE, actuates.
o AP/1 -2/A/i 700/036 (Degraded Control Room Area Cooling)
Refer to AP/1-2/Al1700/036 o Refer to Unit 2 OAC for computer alarm points and the following graphic displays:
~ 2CHILA
~ 2CHILB SRO/BOP Note: If asked Unit 2 will report that the "A" A chiller has experienced a safety shutdown signal and has tripped on Low Evaporator Pressure.
o Contact Mechanical Maintenance HVAC Group, as required.
- AP!1 -2/A/i 700/036 AP/1-2/Al1700/036 o Notify HVAC to monitor and report status of Temporary Chiller designated for CRACS to CR SRO.
o Dispatch Operator to perform EnclEnd 5.1 (Chiller Assessment and Restart).
Cue: USING TIME COMPRESSION you have found the "A" A chiller tripped on a Safety Shutdown and have started the B chiller o IAAT Control Room temperature exceeds 78°F, THEN initiate Encl End 5.2 (Actions For High Control Room Temperature).
o WHEN status of all Chillers is known, THEN continue procedure.
SRO Note: NEO will report that he found the A "A" chiller tripped on aa Safety Shutdown and has started the B "B" chiller.
o Enter TS 3.7.16 (Control Room Area Cooling System) Condition B B (Restore in 30 days)
Event is complete when TS entry or when directed by the Lead Examiner.
Appendix D0 Scenario Outline Form ES-D-2 ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 4 Page 11 of 2 Page Event
Description:
1IBI Failure: (C, B1 RCP lower Seal Failure: BOP, SRO)
(C, BOP, Time Position j Applicants Actions or Behavior Applicant's Plant response:
- 1SA-06/C-5, RC PUMP 1B1 1B1 CAVITY PRESS HI/LOW
- ISA-061C-6, RC PUMP 1B1 SEAL RETURN FLOW HI/LOW 1SA-06/C-6, Crew response:
BOP AP/1 6 Refer to the ARGs; Refer to AP/16 AP/1 6 , Abnormal RCP Operations Refer to AP/16 ,
- Check if any Immediate Trip Criteria (ITC) met. RNO- (Go to step 4.12)
SRO SRO
- Announce AP entry on plant page
BOP ** 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 y any of the following indicate external RCP seal leakage:
~ RB RIAs increasing or in alarm (RIA-4, 43 - 46)
~ RCS Tave constant with LOSTLDST 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-20
~ 1HP-21
- Verify 11HP-232 HP-232 is open
- IAAT Based on #1 seal delta P; Go To Step 16 to shutdown 1B1 RCP.
- Verify Mode 1 1 or 2
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1 I Event No.: 4 Page 2 of 2 IBI Event
Description:
1 B1 RCP lower Seal Failure: (C, BOP/SRO)
Time Position Applicants Applicant's Actions or Behavior BOP
- is < 70%
Verify Rx power is.:::
- Verify gjy any SG not on Low Level Limits
- Verify FDW masters in Auto
- Stop 1B1IBI RCP
- End 4.3 (Special Instructions for <
Initiate Encl < 4 RCP Operation) of OP/i/A/i 102/004 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 181 Examiner, the event is complete.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 5 Page 11 of 2 Event
Description:
ICS fails to re-ratio Feedwater (I, OATC, SRO)
Time Position Applicants Actions or Behavior Applicant's Plant response:
When the 11 B BI1 RCP is secured the LlATC TC controller will fail at - +3.8 Feedwater flow will continue to increase to the 1A SG and decrease to the 11 B SG causing the actual LlTc ATc to become increasingly negative.
Crew response:
OATC/SRO OATC!SRO API16 (Continued)
AP/16
establish O°F0°F b.Tc.
LiTc.
NOTE: LlTC ATC controller will fail in auto and manual
- Place DELTA Tc station in HAND.
- Manually adjust DELTA Tc station to achieve::::
achieve 0° b. 1 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 the following in HAND:
>-> 11AFDW A FDW MASTER
>-> 11BFDWMASTER B FDW MASTER
- Manually adjust FDW masters to achieve::::
achieve 0° IXTc.
00 b.Tc.
o Initiate AP/28 (lOS(lCS Instrument Failure).
- End 4.3 (Special Instructions for << 4 RCP Operation) of Initiate Encl OP/1/A11102/004 OP/1/A/11021004 (Operation at Power).
AP/28
- Verify entry into AP/28:
SRO/OATC SROIOATC o Power> 3%
BOP o PTR actions taken and TPB s; the pre-transient power level AND Delta TO TC has failed.
When the plant is stable and SPOC has been notified, or when directed by the lead examiner this event is completed.
Appendix D Scenario Outline Scenario Form ES-D-2 No.: _ _
Op-Test No.: Scenario No.: 1I Event No.: 5 Page 2 of 2 Page Event
Description:
ICS fails ICS fails to re-ratio Feedwater to re-ratio Feedwater (I, OATC, SRO)
SRO)
Time Position Applicants Actions or Behavior Applicant's Crew response:
OATC/SRO AP128 (Continued)
AP/28 BOP
- 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 4F DeltaTcTc
~ Ensure the following in HAND:
- 1AFDW 1A FDW MASTER
- 11BFDWMASTER B FDW MASTER
- DELTATc DELTA Tc
~ Re-ratio feedwater flow, as required, to establish::::
establish OaF 0°F DELTA Tc while maintaining total feedwater flow constant.
~ Notify SP~C SPOC to perform the following:
- Investigate and repair the failed Delta Tc controller.
~ WHEN notified by SP~C SPOC that Delta Tc controller has been repaired, THEN GO TO Encl End 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.
Appendix D Appendix 0 Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 1I Event No.:
Event No.: 66 Page 11 of Page of 22 Event
Description:
Event
Description:
- IBI RCP RCP middle middle and and upper upper seals seals fail, fail, (C, All) (TS)
(C, All) (TS)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- Bi RCP lower pump cavity pressure will equal upper seal cavity 11 B1 pressure.
- LDST level will decrease as - 80 gpm will leak out of the RCS through LOST 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 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 1 1HP-5.
HP-5.
- IAAT RCS leakage> NORMAL MAKEUP CAPABILITY with letdown isolated, AND Pzr level decreasing, THEN trip Rx.
- LDST using EOP Encl Initiate makeup to LOST End 5.5 (pzr (Pzr and LOST LDST Level Control), as necessary
- Monitor OAC for leak trends/data
- Initiate End Encl 5.1 (Leak Rate Determination).
Calculation of RCS Volume Loss:
Leak Rate =
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 Step 4.145 4.145 based onon leakage from RCP seal failure When plant plant shutdown shutdown has has been been directed directed or or when when directed directed by by the Lead Lead Examiner Examiner this event is is completed.
0 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 6 Page 2 of 2 Event
Description:
I B1 RCS Leak - 1
- BI RCP middle and upper seals fail, (C, All) (TS)
Time Position j Applicants Actions or Behavior Applicant's Crew response:
AP2 (Continued)
BOP/SRO
- Discontinue pumping RBNS since leak> 10 gpm
- rate > TS, THEN initiate shut down by one of the following:
IAAT leak rate>
- AP129 (Rapid Unit Shutdown)
AP/29
- OP/i/All 102/004 (Operation At Power)
OP/1/A/1102/004
- OP/1/A/1102/01O OP/1/A/11 02/01 0 (Controlling Procedure For Unit Shutdown).
AP129 NOTE: Crew will use AP/29 When plant shutdown has been directed or when directed by the Lead Examiner this event is completed.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 7 Page Page 11 of 3 Event
Description:
Manual Reactor power decrease: (R, OATC, SRO)
Time Position Applicants Actions or Behavior Applicant's Crew response:
AP!29 (Rapid Unit Shutdown)
AP/29 NOTE SRO The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.
BOP BOP
- End 5.1 (Support Actions During Rapid Unit Shutdown).
Initiate Encl
- lOS in AUTO.
Verify ICS OATC NOTE: ICS CS 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 1 B FDWP to be shut down first.
- Adjust the FWP bias counterclockwise to lower 1 1 B FDWP suction flow -
1 1066 Ib/hr 1 x 10 lb/hr < 1 1A A FDWP suction flow.
- IAAT any of the following statalarms are received:
- 1 1SA-16/A-1 SA-16/A-1 (FWPA(FWP A FLOW MINIMUM)
- 1SA-16/A-2 iSA-i 6/A-2 (FWP A FLOW BELOW MIN)
- 1SA-16/A-3 iSA-i 6/A-3 (FWP B B FLOW MINIMUM)
- Maintain Pzr level between 220 250.
220" - 250".
When the OATC has reduced power -10%, 10%, or when directed by the Lead Examiner this event is completed.
Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 1I Event No.:
Event No.: 88 Page Page 11 of of 11 Event
Description:
Event
Description:
Main Turbine Main Turbine Fails Fails to to trip trip (Lockout (Lockout EHC EHC Pumps)
Pumps) (C,(C, OATC)
OATC)
Note: Reactor will trip as a result of the SBLOCA in event 8.
Time Position Applicants Actions or Behavior Applicant's Plant response:
- 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 overcooling until the turbine is tripped.
RCS overc?oling Crew response:
- 2. 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.
- 3. BOP will perform a symptom check and Rule 3 (Loss of Main or Emergency Feedwater) for aa loss of Main Feedwater only.
BOP Event Event is is complete complete whenwhen EHCEHC pumps pumps have have been been tripped tripped oror when when directed directed by by the the Lead Lead Examiner.
Appendix DD Scenario Scenario Outline Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 1I Event No.:
Event No.: 99 Page 11 of Page of 55 Event
Description:
Event
Description:
Small Break Small Break LOCA:
LOCA: (M, (M, ALL)
ALL)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- 1. Statalarms:
- 2. Control board indications:
- RBNS level increases
- PZR level will decrease very slowly due to the leak and 11 HP-5 being closed.
Crew response:
SRO FOP Subsequent Actions; Parallel Actions page.
The SRO will refer to EOP The SRO will receive Symptoms Check/Report from one of the ROs.
End. 5.1 (ES Actuation)
The SRO will direct one of the ROs to perform EOP Encl.
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.
- 1. Verify all control rods fully inserted.
- 2. Verify Main FDW in operation.
- 3. Verify Main FDW controlling properly.
pressure 1010 psig.
- 5. Verify 11 RIA-40 operable.
- 7. Verify ES is required.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1 I Event No.: 9 Page 2 of 5 Event
Description:
Small Break LOCA: (M, ALL)
Time Position Applicants Applicant's Actions or Behavior OATCI OATC/ 1..
1 When ES Channels 1 1 and 2 actuate, an operator should inform the SRO that ES BOP Channels 11 and 2 have actuated.
SRO Actions page of Subsequent Actions section or of the LOSCM Tab.
- 3. When running Encl.
End. 5.1, the operator will:
OATC/
- Determine which ES channels should have actuated and verify all "Blue Blue Lights" Lights White 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.
CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head.
- B and 3A & 3B Outside Air Booster Fans are operating. (CT Ensure A & Band -27)
(CT-27)
- Verify 1CF-1/2 open.
- Verify 11HP-410 HP-41 0 closed.
- Secure makeup to the LOST.LDST.
Note: 1 I HP-3 will not close. The operator should diagnose this and perform the RNO and close 1HP-1 IHP-1 located on 1UB1.
IUBI.
- Close 1 1 LPSW-139 LPSW-1 39
- Fail Open 1 1LPSW-251/252 LPSW-251/252
- Open 1 1 LPSW-4/5
- Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open.
- The operator must get SRO approval to exit this enclosure.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 1I Event No.:
Event No.: 99 Page 33 of Page of 55 Event
Description:
Event
Description:
Small Break Small Break LOCA:
LOCA: (M, (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Behavior Plant response:
- RCS subcooling margin (SillY)
(gy) will = 0°F.
= O°F.
Crew response:
SRO 1.
- 1. BOP/QATC should inform the SRO that the RCS The BOP/OATC RCS has saturated and obtain SRO concurrence to perform Rule #2, Loss Loss of SCM.
BOP/ ** Verify that reactor power is << 11%.
OATC aM RCPs (within 2 min
- Stop all mm of LOSCM) (CT-I)
(CT-1)
Note: 11B2 B2 RCP will not trip from the switch. RNO will be performed to de- de ITA energize 1T ITB (6.9KV switchgear).
A and 1TB
Verify that HPlis
- Verify that TBVs are available.
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) 31, 42, 40)
- Ensure Rule 3 is in progress or complete.
Appendix 0D Scenario Outline Form ES-O-2 ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 11 Event No.:
Event No.: 99 Page 4 of Page of 55 Event
Description:
Event
Description:
Small Break Small Break LOCA:
LOCA: (M, ALL)
Time Position Applicants Actions or Behavior Applicant's SRO 3. 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 is NOT feeding any SG.
- Verify that the LOSCM is NOT caused by excessive heat transfer.
- Verify that the SSF is NOT activated.
- a the following conditions exist:
Verify all
>- NO RCPs are operating
>-> HPI flow exists in both HPI headers
>-> Adequate Total HPI flow per figure 11 (Total Required HPI Flow)
MS-47.
- Control steaming and feed rates on all intact SGs to maintain cooldown rate within Tech Spec limits:
>-> ~ 280°F Tc>280°F Tc ~ 50°FI ~ hour
<50°F!Y2hour
>-> Tc<280°F Tc < 280°F ~ 25°FI ~
<25°F! Y2 hour
- Utilize TBVs
- GO TO Step 92.
- Close 11RC-4RC-4 (No HPI forced cooling in progress)
RC-3.
- Verify primary to secondary heat transfer exists.
- Initiate Encl End 5.16 (SG Tube-to-ShelllJ.
Tube-to-Shell LT T Control).
- Verify CETCs increasing.
- Verify required RCS makeup flow NOT within normal makeup capability.
- GOTOLOCACDtab.
GO TO LOCA CD tab.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.:
Scenario No.: 1I Event No.: 99 Page 5 of 55 Event
Description:
Event
Description:
Break LOCA:
Small Break LOCA: (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Crew response:
- 1. Ensure all RBCUs in low speed.
- Open 11LPSW-18.
LPSW-18.
- Open 11 LPSW-21.
- Open 1 1 LPSW-24.
- 2. End 5.35 (Containment Isolation).
Initiate Encl
- 3. Start all RB Aux fans.
- 4. End 5.36 (Equipment Alignment For Plant Shutdown).
Initiate Encl
- 7. Initiate determination of minimum required boron concentration for MODE 5 using either of the following:
- Reactor Engineer
- PT/I /AIl 103/015 (Reactivity Balance Procedure)
PT/1/A/1103/015
- 8. Initiate steaming all intact SGs to cooldown to cooldown plateau at:::;
at 50°FM 2 hr 50°F/Y using either of the following:
- ADVs ADVs Event and exam is complete complete when directed by the Lead Examiner.
Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS
- 1. CT-18, Turbine Trip CT-i, Trip All RCPs
- 3. CT-10,
- 4. CT-27, Implementation of Control Room Habitability Guidance
Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 3/10 3110 Facility: Oconee Facility: Oconee Scenario No.:
Scenario No.: 22 Op-Test Op-Test No.:
No.: 1 Examiners:
Examiners: Operators:
Operators:
Initial Conditions:
Initial 100% Reactor power
- . 100%
Turnover:
- . SASS in Manual
- . ICS in manual and ready to return to Auto Event MaIf. No.
Malf. Type*
Event Type* Event No. Description Oa Pre-Insert SASS in Manual Ob CS in Manual ICS 11 N, OATC, SRO Place ICS in Auto 2 Override C, BOP, SRO Operating LPSW Pump trips and Standby fails to start (TS)
Updater MPIO21 MPI021 C, BOP, SRO Inadvertent ES Channels 11 and 2 actuation (TS) 3 MPS36O MPS360 C, OATC, SRO 1 HP-31 (RCP Seal Flow Control) fails OPEN in AUTO 1
4 5 Override C, BOP, SRO 1A 1 A CBP Trip and 1 B CBP fails to Auto Start.
lB MSS 460 6
6 MCS 004 I, OATC, SRO Controlling Tave fails high 7
7 MSS 010 M, ALL M,ALL Loss of Main and Emergency Feedwater MSS 020 MSS 260 LOHT Tab MSS 270 CBP feed 8 Override ALL CBPs trip I/ HPI Forced cooling 11HP-26 fails to open HPI CD Tab
- (N)ormal, (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (M)ajor DRAF]r
Appendix 0D Scenario Outline ES-D-2 Form ES-O-2 Op-Test No.: 1I Scenario No.: 2 Event No.: 1I Page 11 of 2 Event
Description:
Place ICS in AUTO: (C; OATC, SRO)
Time Position Applicant's Applicants Actions or Behavior Crew response:
OATC/SRO OP/i/All 102/004 OP/1/A/11 021004 A Encl.
End. 4.4 will direct the OATC to:
- 1. RATE SET" Ensure "RATE SET thumbwheels at 0.0.
- 2. IF TURBINE MASTER is in "HAND",HAND, perform Section 3 (Placing Turbine To Auto).
3.1 IF THP (01 E2088) is different from THP Setpoint (01 E2089) by more than +/- +/-
2 psig, perform the following:
- Simultaneously ensure 11A A and 1lB HAND B FDW MASTER in "HAND"
- MANUAL.
Ensure DIAMOND in "MANUAL".
- Ensure TURBINE MASTER in "HAND" HAND
- Ensure 1A and 1BlB TURBINE BYPASS VALVES in "HAND" HAND
- On TURBINE MASTER adjust THP Setpoint (01 E2089) to:::: to selected THP (01 E2088).
- AUTO.
Place TURBINE MASTER in "AUTO".
- Verify TURBINE MASTER controlling THP.
- Return to Section 2 (Procedure).
- 3. HAND, perform Section 4 (Placing TBV To Auto).
IF either TBV is in "HAND",
- TBVs are in AUTO
- 4. IF REACTOR MASTER OR DIAMOND is in manual, perform Section 5 (PlaCing (Placing Rx To Auto).
HAND, perform the following:
IF Rx Master is in "HAND",
- Ensure DIAMOND is in MANUAL.
"MANUAL".
- Place REACTOR MASTER to AUTO. "AUTO".
- IF selected Tave (01 E2086) is different from Tave setpoint (01 E2087) by more than +/-+/- 0.3°F, perform the following:
- Simultaneously ensure 1A 1A and 1lBB FDW MASTER in HAND "HAND"
- On REACTOR MASTER adjust Tave setpoint (01 E2087) towards selected Tave (O1E2086).
(01 E2086).
- Verify selected Tave is within +/-+/- 0.3°F of Tave setpoint.
- Place DIAMOND in AUTO.
"AUTO".
- Return to Section 22 (Procedure).
- 5. IF DELTA Tc is in HAND, "HAND", perform Section 66 (Placing DELTA Tc To Auto).
- DELTA Tc is in AUTO "AUTO" When the ICS has been placed in AUTO, or when directed by the Lead Examiner this event is completed.
Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 22 Event No.:
Event No.: 1I Page 22 of Page of 22 Event
Description:
Event
Description:
Place Place ICS ICS inin AUTO: (C; (C; OATC, OATC, SRO)
SRO)
Time
=Time Position Applicants Actions or Behavior Applicant's Crew response:
OATC/SRO 6. IF STM GENERATOR MASTER or either FDW MASTER is in "HAND", HAND, perform Section 7 (Placing FDW To Auto).
HAND, perform the following:
IF SG Master is in "HAND",
- SG Master is in AUTO.
IF either 1A OR 1lB B FDW Master is NOT in "AUTO",
AUTO, perform the following:
- Select 11A A and 1lBB FDW MASTER to "MEAS MEAS VAR" VAR
- IF both 1A and 1lB B FDW Master Measured Variables are on the caret:
- Select 11A A and 11 B FDW MASTER to "POS" POS
- Simultaneously ensure 1A and 1lB AUTO B FDW MASTER in "AUTO"
- 7. IF any FDW valves are in "HAND", HAND, perform Section 8 (Placing FDW Valves To Auto).
- All FDW valves are in AUTO
- 8. IF either Main FDW Pump is in "HAND", HAND, perform Section 9 (Placing Main FDW Pumps To Auto).
- Both FDW pumps are in AUTO.
NOTE: ICS lOS must be in full auto before adjusting any setpoint to minimize possible CTP changes. (R.M.)
When the ICS ICS has has been been placed in in AUTO, or when when directed directed by the Lead Lead Examiner this event is is completed.
completed.
Appendix D Scenario Outline Form ES-D-2 I
Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Page 11 of 11 Event
Description:
Operating LPSW pump trips, Standby fails to auto start:
Time_J Time Position Applicants Actions or Behavior Applicant's Plant response:
>- Refer to AP/24 (Loss of LPSW)
AP/24 (Loss of LPSW)
SRO/BOP
- Verify Unit 1 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 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 "An 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. "An. 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.
Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 22 Event Event No.:
No.: 33 Page 11 of Page of 33 Event
Description:
Event
Description:
Inadvertent Inadvertent ES and 22 actuation:
Channels 1I and ES Channels actuation: (C,(C, BOP/SRO)
BOPISRO)
Time Time j Position Position Applicants Actions Applicant's Actions oror Behavior Behavior Plant response:
Plant response:
Statalarms:
- 1. ES Channel 11 and 2 actuate
- 2. HPI Injection
- 3. Letdown isolated
- 4. Keowee emergency start Crew response:
BOP ALL 2. Crew may perform Plant Transient Response.
SRO 3. The SRO should enter AP/42 (Inadvertent ES Actuation)
- 4. API1IA/1700/042 AP/1/A/17001042 (Inadvertent ES Actuation) Actions:
- Place HPI in MANUAL on RZ Modules
- Throttle HPI
- Direct the BOP to perform End.Encl. 5.1 (Side Board Action)
- Direct the OATC to perform End.Encl. 5.2 (Letdown Restoration)
Appendix D D Scenario Outline Form ES-D-2 I
Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Page 2 of 3 Event
Description:
Inadvertent ES Channels 1 I and 2 actuation: (C, BOP/SRO)
BOPISRO)
Time Position Applicants Actions or Behavior Applicant's Crew response:
- 5. BOP will perform Encl.
End. 5.1 (Side Board Action)
- Open 1 1 HP-228, 226, 232, and 230 (Seal Return Stop)
- Place the following in MANUAL on the RZ Module and OPEN:
- Start the 11 RIA-47 RB RIA sample pump from the ENABLE CONTROLS screen on the RIA View Node.
- 6. End. 5.2 (Letdown Restoration)
Encl.
OATC
- Verify CC pump operating
- Verify letdown is isolated
- Close 1HP-5 (LETDOWN ISOLATION)
- Close 1HP-6 (LETDOWN ORIFICE STOP)
- Close 1HP-7 (LETDOWN CONTROL)
- Open 1HP-5 (LETDOWN ISOLATION)
- Adjust 11 HP-7 for == 20 gpm letdown
- Open 1 IHP-6 HP-6 (LETDOWN ORIFICE STOP)
- Adjust 11 HP-7 to control desired letdown flow (75 gpm)
Appendix D Scenario Outline Form ES-D-2 No.: 1I Op-Test No.: Scenario No.: 2 Event No.: 4 Page 3 of 3
Description:
Inadvertent ES Channels 1I and 2 actuation: (C, BOP/SRO)
Event
Description:
BOPISRO)
Time Position Applicants Actions or Behavior Applicant's Behavior Crew response:
- 7. AP/42 (Inadvertent ES Actuation) Actions (Continued)
- 105 in AUTO Verify ICS
- Initiate a power decrease to maintain control rods within the desired band by adjusting rate set as necessary and decrease CTP demand setpoint.
- Notify Rx Engineering to develop a maneuvering plan
- Place LOAD SHED & STBY BKR 1 1 and 2 in MANUAL on the RZ Module
- Dispatch an operator to perform End. 5.3 (SSF Restoration)
- IAAT Rx power is stable THEN initiate evaluation of NI operability in accordance with OP/1/
OP!1!A11102/004 Al11 02/004 (Operation At Power) Limits and Precautions.
- End. 5.4 Initiate logging TS/SLC Entry/Exit as applicable, lAW Encl.
(TS/SLC Requirements) (TS) o TS 3.3.7 3.3.7- ESPS Digital Automatic Actuation Logic Channels o TS 3.3.6 - ESPS Manual Instrumentation o TS 3.4.15 - RCS Leakage Detection Instrumentation (can be exited once End. 5.1, Side Board Actions completed) o TS 3.10 3.10 - SSF due to SSF power loss (ES Ch. 1)1)
- 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 directed by the Lead Examiner the event is completed.
0 Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 2 No.: 4 Event No.: Page 11 of 11 Event
Description:
1IHP-31 Event Fails Open: (C; OATC, SRO)
HP-31 Fails Time Position Applicants Actions or Behavior Applicant's Note: This event is run in parallel with Event 4 after Letdown has been re- re established.
Plant response:
11SA2/B-2 SA2/B-2 (HP RCP Seal Inlet Header Flow High/Low) (42 gpm)
Crew response:
ARG for 1 1 SA2/B-2:
SA2IB-2: High Alarm OATC/SRO
- Verify high seal flow conditions with individual RCP seal indications
- 1 HP-31 may have failed open/mid-position. Take manual control of 1I HP-1 HP 31 and throttle to maintain 32 gpm.
- IF flow CANNOT be reduced in above manner, adjust 11 HP-31 (RCP OP!1/A/1104/002 Seal Flow Control) per OP/1/A/11 041002 (HPI system)
When flow is reduced manually to - 32 gpm or when directed by the Lead Examiner this event is completed.
D Appendix D Scenario Outline Form ES-D-2 I
Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Page 1 1 of 11 Event
Description:
Seismic event IA CBP Trip and 1B 1A lB CBP fails to AUTO Start: (C, BOP/SRO)
Time Position Applicants Actions or Behavior Applicant's Plant Response:
- 20%/mm due to C/FDW Suction Pressure Runback Unit runback at 20%/min (should clear - 85% power)
- Powdex Bypasses at 360 psig FDWP Suction Pressure.
- 110-61 C-61 opens bypassing the Hydrogen Coolers @ © 235 psig (on either FDWP/ 2 out of 3 logic) FDWP Suction Pressure FDWP/2 Crew Response:
- 1. Crew should perform Plant Transient Response (PTR)
SRO/BOP
/OATC pressure pressure"
- 3. When the plant is stable/controllable OR as directed by ARG 1SA-8/A-1 1 SA-8/A-1 FDW SUCTION PRESSURE LOW the team should elect to manually start 1 B' the '1 B CBP (standby).
- 4. Manual Actions
- IF standby Condensate Booster Pump has NOT started, start any available CBP manually
- 5. Reset 1C-61 when FDWP suction pressure 2:235 235 psig (OP/1/A/11061002 (OP/1/A/1106/002 Condensate and Feedwater, Enclosure 4.22- Resetting 1 1C-61 C-61 Controller) as follows:
- Ensure 1 1C-61 C-61 is in Manual
- Manually adjust 1 1C-61 C-61 controller demand to 85-95%
- Verify 0101417 O1D1417 (Generator Water Cooler Condensate Diff) Duff) value FALSE "FALSE"
- Ensure adjusted 1 10-61 LiP C-61 setpoint to match actual LlP
- Ensure 110-61 toAUTO C-61 to "AUTO"
- 6. (OP/1/AJ11O6/002 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 iC-i 4/15 while maintaining CBP Service by slowly throttling closed on 1C-14/15 suction pressure 2: 70 psig.
F The event is complete when the plant stabilizes - 85% power or when determined by the Lead Examiner.
Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 22 Event No.:
Event No.: 66 Page 11 of Page of 11 Event
Description:
Event
Description:
Controlling Controlling Tave Tave fails fails HIGH HIGH (I, (I, OATC, OATC, SRO)SRO)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- 1SA-021A-12, ICS Tracking, will actuate due to neutron and feedwater 1SA-02/A-12, cross-limits.
- indicate 596.4° F. (Failed HIGH)
Controlling Tave will indicate::::
- Actual loop A & B Tave will decrease until operator stops transient.
- RCS pressure and temperature will decrease.
Crew response:
- Statalarms; candidates perform "PlantPlant Transient Response" 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 position as necessary to stabilize the plant.
S RO/OATC SROIOATC
- The SRO should:
>- Refer to AP/28, AP128, ICS Instrument Failures
>-> Contact SPOC to repair controlling Tave.
Note: The ICS remains in manual for the rest of scenario.
AP/28 (lCS (ICS Instrument Failures)
- 1. Verify plant conditions are controlled or stable as indicated by the following:
- NI power change < <2%
2% from current NI power indication AND thermal best pre-transient power level power best:::;
OATC
- Tave change < <2°F 2°F from current Tave indication
- THP/SG Outlet Press. change < <30 30 psig from current THP/SG Outlet Press.
- 2. Provide control bands - see Placard (OMP 1-18)
- 4. Verify a power transient has occurred
- 5. Notify Rx Engineering to discuss need for a power maneuvering plan
- 6. GO TO section 4A (RCS Temperature Failure)
- 7. Notify SPOC to repair failed instrument
- 8. PERFORM an instrumentation surveillance using applicable table in End 5.3 (ICS (ICS Instrument Surveillances) for the failed instrument.
instrument.
When the SRO SRO reaches the WHEN Step (6) (6) of of Section Section 4A 4A or or when directed directed by by the Lead Examiner Lead Examiner this event is is completed.
D Appendix D Scenario Outline Form ES-D-2 Form ES-D-2 No.: 1I Op-Test No.: Scenario No.:
Scenario No.: 2 Event No.:
Event No.: 7 Page Page 11 of 3 Event
Description:
Loss of Main and Emergency FDW, LOHT, CBP Feed (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Plant Response:
When directed by the Lead Examiner, a Loss of Main and Emergency Feedwater will occur.
Crew Response:
- Immediate Manual Actions (IMAs)
Perform Immediate
- 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 (MainlCBPlEmergency), AND any
- 1. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
of the following exist:
- 3. Pzr level reaches 375" [340 acc]
375 [340" THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
- 4. Start EFDW pumps to feed all intact SGs.
- 5. Place the following in MANUAL and close:
- 6. Verify both of the following:
- 7. Any CBP operating
D Appendix D Scenario Outline Form ES-D-2 I
Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Page 2 of 3 Event
Description:
Loss of Main and Emergency FOW, FDW, LOHT, CBP Feed (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Crew Response:
Rule 3 (Continued)
BOP 11. Place 11 FDW-33 and 11 FDW-42 )) control switch SGs in OPEN:
(1 FDW-35 1 FDW-44)
- 12. Simultaneously position Startup Control valves (1FDW-351FDW-44) 10 - 20% open on .ill!
- aM intact SGs:
- 13. Perform the following:
- Place 1 1 FDW-31 switch in CLOSE.
- Place 1 1 FDW-40 switch in CLOSE.
- Close 11 FDW-32.
- Close 1 1FDW-41.
FDW-41.
- 15. Control FDW flow to stabilize RCS PIT P/T by throttling the Startup (CT-IO)
Control valves and TBVs as necessary: (CT-10)
- Place 1 1 FDW-38 and 11 FDW-47 switches to OPEN:
- Place 1 1 FDW-36 and 1I FDW-45 switches to CLOSE:
End 5.26 (Manual Start of
- 16. Dispatch an operator to perform Encl TDEFDWP).
- 17. Verify cross-tie with Unit 2 is desired.
- 19. Dispatch an operator to 1 1 FDW-313 FDW-31 3 and have them notify the CR when in position.
- 20. Notify Unit 2 to: 1) Manually Close 2FDW-315 & 316. 2) Start their U2 TDEFWP
- 21. WHEN, either of the following exists: 1 1FDW-313 FDW-313 Operator in position OR Unit 1 1 TDEFWP has been manually started; THEN continue.
Appendix D D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 22 Event No.:
Event No.: 77 Page Page 33 of of 33 Event
Description:
Event
Description:
Loss Loss of of Main Main and and Emergency Emergency FDW, FDW, LOHT, LOHT, CBP CBP Feed (M, ALL)
Feed (M, Time Position Applicants Actions or Behavior Applicant's Crew Response:
Loss Of Heat Transfer Tab
o RCS pressure reaches 2300 psig OR NDT limit oRCS o Pzr level reaches 375" 375 [340"
[340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
IAI RCP provides the best Pzr spray.
NOTE: 1A1
- Reduce operating RCPs to one pump/loop.
- WHEN jy any of the following exists:
o Unit 1 1 EFDW available BOP o EFDW aligned from another unit THEN GO TO Step 48 When RCS temperature is stabilized on Condensate Booster Pump feed, or when directed by the Lead Examiner this event is completed.
Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 22 Event No.:
Event No.: 88 Page Page 11 of of 22 Event
Description:
CBPs Event
Description:
CBPs Trip, HPI HPI Forced Forced Cooling, Cooling, Spray Spray Valve Fails Fails Closed Closed (ALL)
(ALL)
Time Position Applicants Actions or Behavior Applicant's Plant Response:
- CBPs trip
- Feedwater flow decreases
- RCS temperature increases Crew Response:
SRO SRO SRO may direct RO to re-perform Rule 3 psig RCS pressure, direct performance of Rule 4 (HPI Forced At 2300 psiq Cooling).
BOP/OATC Rule 4 (CT-14) (Within 5 minutes of meeting criteria)
- 1. Open 1 IHP-24 HP-24 and 11HP-25.
HP-25.
aN available HPI pumps.
- 2. Start all
- 3. Open 1 1HP-26 HP-26 and 1 1HP-27 HP-27 Note: 1 IHP-26 HP-26 will NOT open (1 (IHP-410 HP-410 must be opened; per Step below)
- 4. Open 1 1 RC-4.
- 6. Open PORV. (Switch to OPEN, depress OPEN permit)
- 7. Verify at astleast two HPI pumps operating.
- 10. De-energize all Pzr heaters.
11.
- 11. Close 1HP-5.
1HP-5.
12.
13.
1FDW-44.
Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 22 Event No.:
Event No.: 88 Page Page 2 of 22 Event
Description:
Event
Description:
CBPs CBPs trip, HPI HPI Forced Forced Cooling, Cooling, Spray Spray Valve Fails Fails Closed Closed (ALL)
(ALL)
Time [ Position Crew Response:
Applicants Actions or Behavior Applicant's SRO LOHT tab
- 1. PERFORM Rule 4 (Initiation of HPI Forced Cooling).
aB the following:
- 2. Verify all
- At least two HPI pumps operating
- PORVopen
- 11RC-4 RC-4 open
- 3. GO TO HPI CD tab.
- 4. Verify.ill!
Verify aM of the following exist:
PORV open
- PORVopen
- Two HPI trains injecting
- CETCs ~ 640°F
- 5. Ensure all RBCUs in low speed.
LPSW-24.
End 5.35 (Containment Isolation)
- 7. Initiate Ene!
- 8. Start A & B B Outside Air Booster Fans (CT-27)
- 9. Notify Unit 3 to start 3A and 3B Outside Air Booster Fans When SRO SRO transfers to HPI HPI CD tab, or when directed directed by the lead lead examiner this event is is completed.
Appendix D D Scenario Outline Form ES-D-2 CRITICAL TASKS
- 2. CT-14, CT-i4, Initiate HPI Cooling
- 3. CT-27, Implementation of Control Room Habitability Guidance
Appendix 0 D Scenario Outline Form ES-O-1 ES-D-1 3/10 3110 Facility: Oconee Scenario No.: 3 Op-Test No.: 1I Examiners: Operators:
Initial Conditions:
- . Reactor Power =100%
Turnover:
- . Keowee Unit 2 OOS for unplanned reasons
- . Keowee Unit 11 Aligned to Underground
- . Operability test of Keowee Unit 11 is to be performed per PT/6201009 PT/620/009 (Keowee Hydro Operation) after turnover and before startup continues, ONS to perform remote Keowee start. Begin at Encl. End. 13.1 at Step 2.2 Event Maif. No.
Malt. Type*
Event Type* Event No. Description Oa Pre- SASS in Manual Insert Ob Pre- Keowee Unit 2 Emergency Lockout Insert MEL18O MEL 180 i
1 N, BOP, SRO Operability Test Keowee Unit 11 2 Override C, OATC, SRO C,OATC,SRO 1 HP-120 1 HP-i 20 (RC Volume Control) fails Closed 3 Override I, BOP, SRO Pump RBNS and RBNS Pumps do not auto stop at 6" 6 4 Override C, OATC, SRO 1A HPI Pump trips and standby HPI HP! pump fails to start (TS) 5 Override C, BOP, SRO 1A RBCU cooler rupture (TS) 1A 6 Override I, ALL Turbine trips to hand for unknown reason 7 MCRO21 MCR021 C, OATC, SRO C,OATC,SRO Dropped Control Rod and manual Power Reduction (TS)
MCRO22 MCR022 8 MEL 120120 M, ALL 1TA 1 T A Lockout - causes Rx trip due to loss of 2 RCP's
- RCPs MEL 180 eLreO CT-1 Lockout I Keowee Unit 1 CT-i 1 ELO (Blackout)
Override Regain power manually from CT-5.
ReQain 9 MSS 380 All SGTR requires transfer to SGTR tab to end scenario TDEFWP fails requiring Rule 3 to start MDEFWP's MDEFWPs
- (N)ormal, (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (M)ajor AF
Appendix 0D Appendix Scenario Outline Scenario Outline Form ES-O-2 Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 33 Event No.: 1I Event No.: Page Page 11 of of 33 Event
Description:
Event
Description:
Operability Operability test test Keowee Keowee UnitUnit 1I (N, BOPISRO)
(N, BOP/SRO)
Time Position Position Applicants Actions or Behavior Applicant's SRO PT/620!009 (Keowee Hydro Operation) Encl.
Direct BOP to perform PT/620/009 End. 13.1 13.1 (KHU-1 Operability Verification" Verification Step 2.2 to operability test Unit 11 Keowee Underground.
- 1. Verify various Statalarms NOT in alarm (lockouts and SU inhibit)
- 2. Ensure the following:
- PERMISSIVE AUTO START light on.
- UNIT 11 MASTER SELECTOR switch in "AUTO". AUTO.
- EXCITER MANUAL/AUTO Red AUTO light ON, Green MANUAL light OFF.
- EXCITER STOP/START Green STOP light ON, Red START light OFF.
- 3. Notify Keowee Operator to perform the following:
- On CB2, verify all required PREREQ lights are lit.
- Position MASTER TRANSFER switch for KHU-1 to "REMOTE". REMOTE.
- 4. Ensure UNIT 11 SYNC 230 KV selector in "MAN". MAN.
- 5. Place AND hold UNIT 11 LOCAL MASTER switch in "START" START position for> 10 seconds until KHU-1 starts.
- 6. Verify EXCITER STOP/START Red START light ON, Green STOP light OFF.
- 7. Perform the following:
- 8. After 60 seconds steady operation, record the following:
- KHU-1 OUTPUT VOLTS __ KV (Oconee Control Room Indication-2AB3) lndication-2AB3)
- KHU-1 digital speed _ _ RPM (KHU-1 Control Room Indication - CB-3) -
When requested, Simulator Operator will notify Oconee that:
Keowee RPMs = 128.
- 9. Verify CT4 energized by 13.8 KV Underground Power Path:
- Verify ACB-3 closed
- Verify 4.16
-4.16 KV on CT4 Volts (2AB3).
Page Page 22 of of 20 20
Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 33 Event No.:
Event No.: 1I Page Page 22 of of 33 Event
Description:
Event
Description:
Operability Operability test test Keowee Keowee UnitUnit 1I (N, (N, BOP/SRO)
BOPISRO)
Time Position Applicants Actions or Behavior Applicant's
- 10. Step 2.4.2 IF both Standby Buses are NOT energized, perform the following:
10.
- IF test is being performed to satisfy TS 3.8.1 one hour requirement, record time for later TSAIL entry: _ _ _ __
- 11. Step 2.4.3 IF Standby Bus 11 NOT energized 11.
- Verify - 4.16 KV on CT4 Volts
- Ensure CT5 BUS 1I AUTO/MAN transfer switch in MAN
- Ensure CT CT44 BUS 11 AUTO/MAN transfer switch in MAN
- Place STBY BUS 11 SYNCHRONIZING switch to ON
- SKi CT4 STBY BUS 11 FEEDER Close SK1
- Verify - 4.16 KV on Standby Bus 11 Volts
- SKi CT4 STBY BUS 11 FEEDER Open SK1
- Place STBY BUS 11 SYNCHRONIZING switch to OFF
- Place CT4 BUS 1 1 AUTO/MAN transfer switch to AUTO
- 12. Step 2.4.4 IF Standby Bus 2 NOT energized
- Verify4.16 KVon Verify - 4.16 KV on CT4 Volts
- Ensure CT5 BUS 2 2 AUTO/MAN transfer switch in MAN
- Ensure CT4 BUS 2 AUTO/MAN transfer switch in MAN
- Place STBY BUS 2 SYNCHRONIZING switch to ON
- Close SK2 CT4 STBY BUS 22 FEEDER
- Verify - 4.16 KV on Standby Bus 22 Volts
- Open 5K2 SK2 CT4 STBY BUS 22 FEEDER
- Place STBY BUS 22 SYNCHRONIZING switch to OFF
- Place CT4 CT4 BUS 22 AUTO/MAN transfer switch to AUTO 13.
- 13. Step 2.4.5 IF either Standby Bus is NOT energized and test is being performed to satisfy TS 3.8.1 one hour requirement perform the following:
o Ensure TS 3.8.1 Condition D D has been entered for UG path at Time in Step 2.4.2, Step 2.4.2.
o IfIf Overhead Overhead Power Power Path Path is is inoperable, ensure ensure TS TS 3.8.1 3.8.1 Condition Condition II has has been been entered entered at at the time time in in Step Step 2.4.2.
2.4.2.
Page Page 33 of 20 of 20
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _
Op-Test Scenario No.: 3 Scenario Event No.: 1I Page 3 of 33 Event
Description:
Event
Description:
Operability test Keowee Keowee Unit Unit 1I (N, BOPISRO)
(N, BOP/SRO)
Time Position Applicants Actions or Behavior Applicant's BOP
- 14. Step 2.4.6 IF CT4 Bus 11 AND Bus 2 AUTO/MAN transfer switches are in AUTO, perform the following:
"AUTO",
- Evaluate exiting TS 3.8.1 Condition D for Underground Power Path.
- IF Overhead Power Path is inoperable, evaluate exiting TS 3.8.1 Condition I.
3.8.lCondition
- 15. Step 2.5.1 Synchronize KHU-1 to the switchyard; position Keowee UNIT 11 SYNC 230 KV switch to "AUTO".AUTO. (Oconee Control Room) o Verify ACB 1 1 KEOWEE 11 GENERATOR BKR closed.
o Perform one of the following:
- Verify acceptance criteria met.
- IF acceptance criteria NOT met, ensure SRO notified.
- 16. Step 2.7.1 IF KHU-1 was started from Oconee Control Room, perform the following:
CAUTION: Do NOT lower MVARS to less than zero (0) before taking the KHU off line. This will prevent excitation current from burning the contacts on the generator breakers when KHU-1 is shut down.
o Perform the following concurrently as required:
- Adjust load to zero (0) MWs with UNIT 1 1 SPEED CHANGER MOTOR.
- Adjust MVARS to zero (0) with UNIT 1 1 AUTO VOLTAGE ADJUSTER.
o Place UNIT 1 1 LOCAL MASTER switch to "STOP"STOP AND hold in "STOP" STOP position for> 10 seconds.
NOTE: Placing UNIT 1 1 MASTER SELECTOR to AUTO "AUTO" shuts off the AC H.P. Lift Pump and closes the Generator Cooling Water valve. This action prevents KHU-1 from creeping.
o Ensure UNIT 1 1 MASTER SELECTOR to "AUTO".
AUTO.
o Verify TURBINE 1 1 GATE POSITION indicator is at zero (0).
o Notify Keowee to place KHU-1 MASTER TRANSFER switch in LOCAL.
"LOCAL".
o Ensure UNIT 1 1 SYNC 230 KV selector in AUTO.
"AUTO".
Event is complete when operability test is finished, or when directed by the lead examiner.
Page 44 of Page of 20 20
Appendix D Appendix 0 Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 33 Event No.:
Event No.: 22 Page 11 of Page of 11 Event
Description:
Event
Description:
1IHP-120 (RC Volume Control)
HP-120 (RC Control) Fails Fails closed OATCISRO)
(C, OATC/SRO) closed (C, Time Position Position Applicants Actions or Behavior Applicant's OATC Note: 1I HP-120 fails closed during Keowee #1 Operability test. This will allow OATC diagnoses offailure. of failure.
Plant response:
- PZR level begins to decrease.
- LDST level begins to increase.
- Valve position demand for 11HP-120HP-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:
SRO Refer to APII4 AP/14 (Loss of Normal Makeup and/or RCP Seal Injection.
OATC
- 1. Determine Seal Injection is not lost
- 2. Determine loss of suction to HPI pumps has not occurred.
- 4. Verify y any HPI pump operating
- 6. Verify RCP seal injection flow exists.
- 7. Verify 1HP-120 has failed in AUTO and perform the RNO and determine it will also not work in MANUAL. GO TO Step 4.176.
- 8. Perform the following as necessary to maintain Pzr level level> 200":
> 200:
- Close 1HP-61HP-6 (Letdown Orifice Stop)
- Throttle 1HP-7 1HP-7 (Letdown Control)
- 9. Place 1HP..120 1HP-120 to HANDHAN D and closed 10.
- 10. Contact SPOCSPOC to repair 1HP-120.
1HP-120.
Note:
Note: IHP-120 1 HP-120 will remain failed for the duration duration of of the scenario.
When PZR PZR level level is is being controlled controlled manually manually or or when when directed directed by by the Lead Lead Examiner Examiner this event event isis completed.
Page Page 55 of of 20 20
Appendix D Appendix 0 Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 33 Event No.:
Event No.: 33 Page Page 11 of of 11 Event
Description:
Event
Description:
Pump Pump RBNS RBNS andand RBNS RBNS pumps pumps do NOT auto do NOT auto stop stop at at 66 inches inches (I, (I, BOP, BOP, SRO)
SRO)
Time Position Position Applicants Actions or Applicant's Behavior or Behavior Plant response:
Plant response:
Statalarms:
Statalarms:
HIGH/LOW)
Crew response:
BOP/SRO Refer to 1I SA-9/A-6 ARG.
- 1. High Level:
Align normal sump pump and lower level in sump per OP/1/A/11 04/007 OP/i/Ni 104/007 (Liquid Waste Disposal System), Encl. End. 4.1 (U1 (Ui RBNS Transfer Mode 1)
- 2. Investigate possible RCS leakage per OP/0/B/11 06/033 (Primary OP/0/B/i 106/033 System Leak Identification) or PT/1/A/0600/01 PT/1/A10600/010 0 (Reactor Coolant Leakage). (Leakage is known from turnover-LPSW)
- 3. Monitor RB RIAs, CC Surge Tank level, CFT Level and LPSW flow to and from RB and sample RB Normal Sump to determine source.
- 5. Refer to AP/1/N1 AP/1/A/1700/002 700/002 (Excessive RCS Leakage). (Not needed due to knowing the source of the leakage into the RB).
- 6. Low Level:
Verify sump pump(s) stopped, and realign valves per OP/i/Ni OP/1/A/1104/007 i04/007 (Liquid Waste Disposal System), End. Encl. 4.1. (Ui(U1 RBNS Transfer Mode 1) 1)
Note: The RBNS pumps will not stop on the low level cutoff. The BOP should recognize this and stop the pumps per procedure.
7.
- 7. Contact SPOCSPOC to repair RBNS RBNS pumppump low low level level cutoff.
When When RBNS pumps have RBNS pumps have been been stopped stopped or or when when directed directed by by the the Lead Lead Examiner Examiner thisthis event event is is completed.
completed.
Page6of2O Page 6 of 20
Appendix D Appendix 0 Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 33 Event No.:
Event No.: 44 Page 11 of Page of 22 Event
Description:
Event
Description:
A HPI "A" HPI Pump Pump trips trips and and the the Standby Standby HPI HPI pump pump fails fails to to auto auto start:
start:
OATC, SRO)
(C, OATC, (C, SRO) (TS)(TS)
Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior Plant response:
PJant response:
Statalarms:
Board indications:
- RC Makeup Flow == 0 gpm
- 1A HPI Pump OFF
- PZR level will begin to decrease and LOST LDST level will begin to increase.
BOP Crew response:
SRO 1. Refer to ARG for above Statalarms
- Verify no HPI pump operating
- Close 1 1 HP-5 (Letdown Isolation)
- Place 1HP-120 (RC Volume Control) in HAND and closed
88 gpm/RCP is achieved.
- Re-establish normal makeupmakeup through 1HP-120.
1HP-120.
- Ensure Ensure proper operation operation of the CC system.
- Reduce 11HP-7 demanddemand to 0%. 0%.
- Close Close 11HP-6 HP-6
- Ensure Ensure thethe following open:
open:
>~ 1HP-1 1HP-1
>~ 1HP-2 1HP-2
~ 1HP-3 1HP-3
>~ 1HP-4 1HP-4 Page Page 77 of of 20 20
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 Event No.: 4 2 Page 2 of 2 Event
Description:
A HPI Pump trips and the standby HPI pump fails to auto start:
"A" OATCISRO)
(C, OATC/SRO)
Time Position Applicants Applicant's Actions or Behavior
- Open 1HP-5
- Throttle open 11 HP-7 for == 20 gpm letdown flow.
- Open 1HP-6
- Adjust 11 HP-7 for desired letdown flow (75 gpm).
HP-230.
- Open 1 1HP-21 HP-21
- Place 11HP-31 HP-31 in auto.
- 3. Refer to Tech Spec 3.5.2 High Pressure Injection SRO
- A Condition "A"
- 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 88 of 20
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 Event No.: 5 1 of 11 Page 1 Event
Description:
IA RBCU rupture (C, BOP, SRO) (TS) 1A Time Position Applicants Actions or Behavior Applicant's Plant Response:
BOP BOP SA-91B-9 ARG for 11 SA-9/B-9
- 1. Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A delta flow (327 gpm Delta Flow).
- 2. Verify 1LPSW-18 (RBCU 1A Outlet) open
- 3. Verify adequate LPSW flow is available; check LPSW pump operation and 1LPSW-16 (1A RBCU INLET PENE) is open.
- 4. Monitor RBNS Level for any unexplained increase
- 5. 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).
- 6. Perform TS 3.6.3 Condition C for closed containment system.
SRO 7. Enter TS 3.6.5 for RBCU inoperable. (TS 3.6.5 Condition B).
When the RBCU has been isolated, or at the direction of the Lead Examiner this event is completed.
Page 9 of 20
Appendix DD Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 6 Event No.: 6 Page 1 1 of 11 Event
Description:
Turbine trips to HAND (I, ALL)
Time
~.
Position Applicants Applicant's Actions or Behavior Plant Response:
Statalarms:
- 1 SA-2/A-12, 1 los Tracking SA-2/A-1 2, ICS
BOP BOP 1. Refer to ARG for above alarms.
- IF Turbine Master Trips to Hand for unknown reason, refer to AP/1/AJ1 700/028 (ICS AP/1/A/17001028 (lOS Instrument Failure).
SRO 2. AP/28
- 3. GO TO Section 40
- Simultaneously place the 1A and 1 lB B FDW MASTERs to HAND:
OATC
- Place the DIAMOND in MANUAL.
- SP~C to investigate the cause of the Turbine Master tripping Notify SPOC to Hand.
When FDW Masters and Diamond are in MANUAL, or when directed by the Lead Examiner this event is completed.
Page 10 of 20
Appendix D D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 No. :7 Event NO.:7 Page 11 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATC, SRO) (TS)
Time Position ApplicanVs Applicant's Actions or Behavior Plant Response:
1SA2IA1O (CRD GLOBAL TROUBLE)
Stat alarm 1SA2/A10 15A2/B1O (CRD ASYMMETRIC ROD ALARM)
Stat alarm 1SA2/B10 Stat alarm 11SA2/D9 SA21D9 (CRD OUT INHIBIT)
Crew Response:
SRO SRO SRO should enter APII AP/1 (Unit Runback)
APII AP/1 Section 4H
- 1. IAAT more than one control rod is dropped or misaligned >6% (> (>9) 9")
from the group average, THEN trip the Rx.
- 2. Verify Rx is critical.
- 3. Verify Rx runback to 55% FP in progress.
Note: Runback will not be occurring due to ICS in MANUAL.
- 4. RNO: Initiate manual power reduction to 55% CTP at ~ 1%Imin.
1%/min.
R,OATC
- 5. OATC will reduce power with FDW Masters, Diamond, and Turbine BOP End 5.1 (Control of Plant Equipment During Shutdown).
- 6. Initiate Ene!
- 7. 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
- 8. Notify the OSM to ensure the requirements of the following Tech Specs are met:
o TS 3.1.4 (Control Rod Group Alignment Limits) o TS 3.1.5 (Safety Rod Position Limits) o TS 3.2.3 (Quadrant Power Tilt)
NOTE: OSM will be unavailable to make the TS determination and it will be the responsibility of the SRO of2O Page 11 of 20
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.:No.: 3 Event No.:
Event No.: 7 Page 2 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction Reduction (C, OATC/SRO)
OATCISRO) (TS)
Time Position Applicants Actions or Behavior Applicant's 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 OR
60% of allowable thermal power AND (flux/flow/imb) to Reduce nuclear overpower trip setpoints (fluxlflow/imb)
<65.5%
.::: 65.5% of the allowable thermal power AND Verify the potential ejected rod worth is within assumptions of rod ejection analysis.
NOTE: Tech Spec 3.1.4 requires verification of SDM SDM>1%> 1% flklk AkIk or initiation of boration to achieve SDM within limits within an hour of the misaligned or dropped control rod.
- Verify> 11% % SDM with allowance for the inoperable control rod per BOP PT/1/A11103/015 PT/1/A/11 03/015 (Reactivity Balance Calculation).
USE COLR curve for 4 RCPs and 1 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% <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 12 12 of 20
Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
No.: 33 Event No.:
Event No.: 88 Page 11 of Page of 55 Event
Description:
Event
Description:
1TA ITA Lockout Lockout andand Unit Unit Blackout:
Blackout: (M,(M, ALL)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- 11TA TA Lockout (6900 Volt Switchgear)
- 1IAI A 1 and 1IBI B 1 RCPs trip causing a reactor trip
- KHU #1 Emergency Lockout
- CT-I CT -1 Lockout
- MFBs will de-energize Crew response:
Perform Immediate Manual Actions (IMAs)
OATC/SRO
- 1. Depress REACTOR TRIP pushbutton.
- 2. Verify reactor power < < 5% FP and decreasing.
- 3. Depress turbine TRIP pushbutton.
- 4. Verify all turbine stop valves closed.
- 5. Verify RCP seal injection available.
- 6. IF CC is unavailable, THEN immediately perform the following:
- Stop all RCPs.
- Notify CR SRO to "initiate initiate AP125 AP/25" (Standby Shutdown Facility Emergency Operating Procedure).
BOP AP125 AP/25 Obtain the Vital area access key ring, Flashlight and Proceed to the SSF.
NOTE: BOP will be stopped before leaving the control room and informed that Unit 22 RO will perform SSF actions.
OATC!BOP OATC/BOP Perform Symptom Check 1.
- 1. Power Range Nis Nls ARE <5%< 5% and decreasing
- 2. NO SCMs <0°F < O°F
- 3. Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) - TDEFWP is operating
- 4. Uncontrolled Main Steam line(s) pressure decrease is NOT occurring
- 5. SGTR does NOT exist
- CSAE Offgas alarms
- Process monitor alarms (RIA-40, 59, 60)
- Area monitor alarms (RIA-16/17)
Page Page 13 13 of of 20 20
Appendix 0 D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 33 Event No.: 88 Page 22 of 55 ITA Lockout and Unit Blackout: (M, ALL)
Event
Description:
1TA Time Position Applicant's Actions or Behavior Applicants Crew response:
Rule 33 (Loss of Main or Emergency Feedwater)
BOP/OATC
- 1. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
- NOTNDT limit _ Pzr level reaches 375
[340 acc]
375" [340" THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
- 2. Start EFDW pumps to feed all intact SGs. (Only the TDEFDFW pump will be operating)
- 3. Verify any SCM ;:;ooF.
0°F. RNO -IF IF overcooling, THEN throttle EFDW as necessary.
- 4. IAAT Unit 1 1 EFDW is in operation, THEN initiate Encl End 5.9 (Extended EFDW Operation).
BOP/OATC BOP/OATC End 5.9 (Extended EFDW Operation)
Encl
- 1. Monitor EFDW parameters on EFW graphic display.
- 2. Perform the following as required to maintain UST level>level > 7.5':
7.5:
- Makeup with demin water.
- Place CST pumps in AUTO.
- 3. Verify 1 TD EFDW PUMP operating and Start TO 1 TO TD EFDWP BEARING OIL COOLING PUMP.
SRO will transfer to the BLACKOUT tab.
SRO Page 14 of 20
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 Event No.: 8 Page 3 of 5 Page
Description:
1TA Event
Description:
Lockout and Unit Blackout: (M, ALL)
ITA Lockout Time Position j Crew response:
Applicants Actions or Behavior Applicant's SRO will transfer to the BLACKOUT tab.
SRO/BOP
- 1. Direct an RO to announce plant conditions using the plant page and
/OATC IOATC notify the OSM to reference EP and NSD 202 (reportability).
- 2. Verify two ROs available to perform Control Room activities.
- 4. Position the following to OFF:
- 1A1AMDEFDWP MD EFDWP
- 1B1BMDEFDWP MD EFDWP
NOTE:
Feeding SGs with EFDW is desired above HPI Forced Cooling. Step 6 should be performed prior to re-performing Rule 3.
- 6. IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 1 or another unit) becomes available, THEN perform the following:
- Establish 100 gpm to each intact SG. (Feeding to 240"240 XSUR)
- 7. 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.
- 8. IAAT EFDW from any source is insufficient to maintain stable RCS PIT, P/T, THEN notify SSF operator that feeding SGs with SSF ASW is required.
- 9. IAAT power is restored to jy any of the following:
- 1TC 1TC
- lTD 1TD
- 1TE 1TE THEN Initiate AP/1 AP/111 (Recovery from Loss of Power).
GO TO Subsequent Actions Tab SRO NOTE: Once power is restored to any 4160V bus, the SRO will transfer to the Subsequent Actions tab per the above IAAT step.
Page 15 15 of 20
Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 3 Event No.:
Event No.: 8 Page 44 of Page of 55 Event
Description:
Event
Description:
1TA ITA Lockout Lockout and and Unit Unit Blackout:
Blackout: (M, (M, ALL)
Time Position 1 Crew response:
Applicants Actions or Behavior Applicant's AP/1 1 (Recovery from Loss of Power). - to be performed after completion of AP/11 OATC/BOP EOP Ene!.
End. 5.38 (Restoration Of Power; from CT-5)
- 2. Verify load shed has initiated
- 3. Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 11 or 2).
- 4. Close the following breakers:
- 1TC INCOMING FOR FDR BUS 1/2 lTD INCOMING FOR
- iTO FDR BUS 1/2
- 1TE INCOMING FOR FDR BUS 1/2 Switchyard Isolation
- 5. Verify a 230KV SWitchyard soIation has occurred. (It has NOT)
- 6. Verify ES has occurred. (It has NOT)
- 7. Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
- 8. MFB UNDERVOL UNDERVOLTAGE TAGE CHANNEL 1/2 RESET
- 9. Verify all condensate flow has been lost for < 25 minutes and condensate operation is desired.
- 10. Place all HWP control switches to OFF.
- 11. Place all CBP control switches to OFF.
12.
- 13. Place iC-iC 1C-10 FAIL SWITCH in MANUAL.
14.
- 14. Close iC-iC.
15.
16.
- 16. Start one HWP.
17.
- 17. Throttle 11C-iC C-1 0 controller 10%
10% open to satisfy 25 minute restart criteria.
18.
is;:: 100 1C-10.
Page Page 16of20 16 of 20
Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.: _ _
Op-Test No.: Scenario No.:
Scenario No.: 33 Event No.:
Event No.: 88 Page 55 of Page of 55 Event
Description:
Event
Description:
1TA ITA Lockout Lockout and and Unit Blackout: (M, Unit Blackout: (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Crew response:
OATC/BOP RO will perform Ene!.
End. 5.38 (Restoration of Power) (CT-8) (Not met if Enc!.
End.
5.38 completed with power NOT restored.)
- 1. Place 11 HP-31 in HAND and reduce demand to O. 0.
- 2. Close 11HP-21.
HP-21.
- 3. Verify MFB1/2 energized (NOT)
- 4. Verify CT-1 CT-i indicates 4160v (NO)
- 5. Verify both Standby Bus #1 and Standby Bus #2 are de-energized.
- 6. Emergency start Keowee units
- 7. Notify Keowee Operator to place all operating Keowee units in Oconee Control.
- 8. IAAT CT-5 CT-S indicates::::
indicates 4160 volts, THEN GO TO Step 50. SO. (It does; from Central Swyd)
- 9. Place the following switches in MAN:
- MFB1 and MFB2 AUTO/MAN
- STANDBY 1 1 and STANDBY 2 AUTO/MAN
- 10. Open the following breakers:
1 and N21 Ni
- N11 1 MFB1 NORMAL FOR N2 FDR 1 and E21 El
- E11 1 MFB1 E2 MFBI STARTUP FOR FDR ii. Place the following switches in MAN:
11.
- CT5 12.
- 12. Open the following breakers:
- SKi SK1 and 5K2 SK2 CT4 STBY BUS 11 FEEDER 13.
- 13. Close SLI SL 1 and 5L2 SL2 CT5 STBY BUS 11 FEEDER 14.
- 14. Place the following switches in AUTO:
- CT5 BUS 11 and CT5 BUS 2 AUTO/MAN 15.
- 15. Verify Standby Bus #1 energized.
16.
- 16. Notify Notify CR SRO in each unit where aa blackout exists that Standby Bus #1 is energized.
17.
- 17. Close Si S1 1 and S2 1 S2 1 STBY BUS 22 TO MFB2 MFB2 (power is is restored) 18.
- 18. Verify 1TC, 1TC, 1TD, 1TD, or 1TE 1TE energized.
19.
SWGR.
When the SRO has has transferred to Subsequent Actions tab, or or when directed by by the Lead Lead Examiner this event is is completed.
Page Page 1717 of of 20 20
Appendix D0 Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: _ _ Scenario No.:
Scenario No.: 33 Event No.:
Event No.: 99 Page 11 of Page of 2 Event
Description:
Event
Description:
SGTR:
SGTR: (M, (M, ALL)
Time Position Applicants Actions or Behavior Applicant's After the SRO transfers to the Subsequent Actions tab and when directed by the Lead Examiner a SG tube rupture will occur in the 1I B SG.
Plant Response:
- 11 SA-8/B-9 RM Process Monitor Radiation High
- 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH) 1SAS/D10
- PZR level decreasing Crew response:
SRO The SRO should use the Parallel Actions page and transfer to the SGTR tab.
SGTR tab will:
14Q- 180 [17Q"-
- 1. Maintain Pzr level 14Q"-1S0" [17- 21Q"acc]
21acc] by initiating Enc15.5 End 5.5 (pzr (Pzr LDST Level Control).
and LOST
- 2. Start A and B B OUTSIDE AIR BOOSTER FAN (CT-27)
- 3. Notify Unit 3 to start the 3A and 3B OUTSIDE AIR BOOSTER FAN
- 4. Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.
- 5. Dispatch an operator to open A and B B TURB BLDG SUMP PUMP BKR)
- 6. Notify RP to survey both MS lines for radiation.
OATC/BOP Note: At step 66 the TD EFDW pump will trip; requiring either Rule 33 to be performed OR performing a symptoms check to start the MDEFWPs.
MDEFWP's. (CT-1O)(CT-10)
- 7. Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector, etc.).
8.
S. Verify Main FDW or EFDW controlling properly.
- 10. Secure makeup to LDST.LOST.
11.
- 11. Maintain Maintain both SG pressures <950< 950 psig using using either of the following:
- Dispatch Dispatch two operators to perform perform End Encl 5.24 (Operation of the ADV5)
ADVs)
Page Page 18 of 20 18 of 20
Appendix 0D Scenario Outline Form ES-O-2 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 Applicant's Crew response:
.. ....SGTR SGTR tab continued:
ALL 12. IAA IAAT T all the following exist:
- All SCMs > O°F 0°F
- ES Bypass Permit satisfied
- 13. Verify any RCP operating. (NOT)
- 14. Minimize core SCM using any/all of the following methods:
- De-energize all Pzr heaters
- Use Pzr spray
- Maintain Pzr level 140" 140 - 180"
- 180 [175"
[175 - 215"
- 215 acc]
NOTE: With no RCP's RCPs operating, the above methods will be unsuccessful at reducing SCM.
- 15. IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 36 - 38. (CT-7)
- a. Verify Pzr spray nozzle b. liT T ;::: 410°F.
- c. Cycle PORV as necessary.
When crew takes action to minimize SCM or when directed by the Lead Examiner, the scenario is complete.
Page 19 19 of 20 20
Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS CT-8,
- 1. CT -8, Electrical Power Alignment
- 2. CT-27, Implementation of Control Room Habitability Guidance
- 3. CT-7, Minimize SCM
- 4. CT-10, CT-i 0, Establish FDW Flow and Feed Steam Generators Page 20 of 20
Appendix D D Scenario Outline Form ES-D-1 3/10 Facility: Oconee Scenario No.: 4 Op-Test No.: I 1
Examiners: Operators:
Initial Conditions:
- . Reactor power =
= 0.02%; below POAH Turnover:
- . Unit 11 Startup in progress; BOL; not after refueling
- . LOST LDST pressure low, requires H2 2 addition H
- . Startup procedure at step 3.29 (1102/02 Encl4.7)
End 4.7)
Event Maif. No.
Malf. Type*
Event Type* Event No. Description Oa Override STBY CC pump fails to Auto start Ob Override AFIS does not auto actuate Oc Override 1 FDW-31 6 failed closed 1FDW-316 1
1 Override N, BOP, SRO LDST with H2, H2 supply valve (1 H-1)
Pressurize LOST H-i) fails OPEN (TS) 2 R, OATC, SRO R,OATC,SRO Increase power to 3% and place ICS lCS in AUTO 3 MPS 290 C, BOP, SRO 11CC A CC pump trips and 1lBB CC pump fails to auto start Override 4 MPS 1101 10 C, BOP, SRO 11 HP-5 (Letdown Isolation) fails CLOSED (TS) 5 Override C, OATC, SRO C,OATC,SRO 1I RC-1 (pzr (Pzr Spray Valve) fails open 6 MCSO12 MCS012 I, OATC, SRO 1iAA Turbine bypass valve and its block valve fail open due to instrument failure 7 Override M, ALL Excessive Heat Transfer 11FDW-316 FDW-316 failed closed requiring feed through the startup header Transfer to FCD tab
- (N)ormal, N)ormal, (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (M)ajor ir
D Appendix D Scenario Outline Form ES-D-2 I
Op-Test No.: 1 Scenario No.: 4 Event No.: 1I 1 of 2 Page 1 Event
Description:
Pressurize LDST with H2, H2 supply valve (1 (IH-I)
(TS)
Time Position Applicants Actions or Behavior Applicant's Crew response:
SRO 1. Direct the BOP to add H2 to the LOST LDST using OP/1 IA/11 06/017 0P111A111061017 (Hydrogen System) Enclosure 4.5 (Unit 1 LDST H2 Addition).
I LOST
- 2. Enclosure 4.5 (Unit 1 LDST H2 Addition) will:
1 LOST BOP
NOTE:
- OP/o/A/110S/001 OPIOIAI11O8IOO1 (Curves And General Information) and computer may LDST Pressure vs. Level curve.
be referred to for LOST LDST Maximum Pressure vs Indicated Level Curve should NOT be
- LOST exceeded when pressurizing LOST. LDST.
- Immediately prior to pressurization determine lowest reading of diverse LDST level indications:
LOST inches.
- LDST level determine LOST For existing LOST LDST Pressure allowable per LOST 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 1 H-26 if 11 H-1 1 H-i fails open.
- Direct Operator to open 1 1 H-26 (LOST (LDST Block).
- Direct Operator to monitor explosive detector.
- Cycle 11 H-1 (LDST SUPPLY) as required to pressurize LOST H-i (LOST LDST per LOST LDST Pressure vs Level curve.
Note: 1I H-1 H-I (LDST (LOST SUPPLY) will fail open.
- WHEN Hydrogen addition complete, ensure closed 1 iH-1(LDST H-1 (LOST SUPPLY).
Page 2 of 18
Appendix 0 D Scenario Outline ES-D-2 Form ES-O-2 I
Op-Test No.: 1 Scenario No.: 4 Event No.: 1 I Page 2 of 2 Event
Description:
Pressurize LOST LDST with H2, H2 supply valve (1H-1) (IH-I) fails OPEN (N, BOP, SRO)
(TS)
Time Position Applicant's Actions or Behavior Applicants Plant response:
LDST pressure will continue to increase.
- LOST
- 1 1SA-021D-2, SA-02/0-2, HP Approaching LOST LDST Operating Limits, actuates Crew response:
BOP 1. BOP should determine that 1 1 H-1 H-i has failed open and direct the NLO to 1 H-26.
close 1 RefertotheARG.
- 2. Refer to the ARG.
- 1. Verify LOST LDST pressure/level are within the acceptable operating LDST PRESSURE vs. LEVEL enclosure in region of the LOST OP/C/Ni 108/001 (Curves and General Information).
OP/O/A/1108/001 LDST to GWO IF necessary, vent LOST GWD per OP/1/A/1104/o02 OP/i/Ni 104/002 (HPI System).
SRO LDST PRESSURE vs. LEVEL enclosure in OP/o/A/1108/001
- 3. LOST OP/O/Nii08/OOi (Curves and General Information) directs the following:
LDST Pressure vs. Level is above and to the left of Curve 1, then
- If LOST declare BOTH trains of HPI INOPERABLE.
o Immediately depressurize LOST 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 LDST to GWO
- 4. Direct the ROs to vent LOST GWD per OP/1/A/1104/002 OP/i/Ni i04/002 (HPI End. 4.16, System), Encl. 4.i6, (Lowering LOSTLDST Pressure)
- Review Limits and Precautions
- Direct Operator to Close 1 1 GWO-20 GWD-20 (LOST (LDST Vent Blk).
BIk).
- iGWD-i9 (LOST Open 1GWO-19 (LDST VENT).
- Direct Operator to throttle open 1 i GWO-20 GWD-20 (LOST (LDST Vent Blk)
BIk) until LDST pressure begins to slowly decrease and GWO LOST GWD system can maintain vent header.
Event is complete when vent of LOST is complete or when directed by the Lead Examiner.
Page3ofl8 Page 3 of 18
Appendix D0 Scenario Outline Form ES-D-2 Op-Test No.: 1I No.: 4 Scenario No.: Event No.:
Event No.: 2 Page 11 of 11 Page Event
Description:
Event Increase reactor power
Description:
Increase power to 3% and place ICSICS in AUTO: (R, OATC, SRO)
Time Position I Crew response:
Applicants Actions or Behavior Applicant's OPI1/A11102!001 (Controlling Procedure for Unit Startup)
OP/1/A/1102/001 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 SROIOATC Temperature Coefficient.
BOP 1. Begin reactor power increase to 0.5% - 1.0% at :s: 0.5 DPM SUR.
- 2. WHEN above POAH, begin reactor power increase to 2.5 -3.5%.
- 3. WHILE power increases, begin increasing 11 HP-120 HP-i 20 (RC VOLUME 225 PZR Level 215 to 225" CONTROL) setpoint to establish 215"
- 4. WHEN at 2.5% - 3.5% Power, perform the following:
- Place REACTOR MASTER to "AUTO".AUTO.
- AUTO.
Place DIAMOND to "AUTO".
- Ensure TURBINE MASTER Setpoint to =:: 880 - 890 psig.
Event is complete when ICS CS is placed in AUTO or when directed by the Lead Examiner.
Page 4 of 18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.:
Op-Test No.: 1I No.: 4 Scenario No.: Event No.:
Event No.: 3 Page 11 of 3 Page IA CC Pump trips, 1B Event
Description:
1A lB CC CC Pump Pump Fails Fails to Auto Start: (C; BOP, SRO)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- 1SA-2/C-1, LETDOWN TEMPERATURE HIGH
- 11 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 1SA-9/C-1 ARC 1SA-9/B-1 1 SA-91C-1 BOP BOP 1. Determine low flow is due to CC Pump failure AND Standby CC Pump did NOT start and perform the following:
- 2. Verify CC Surge Tank level> 12" 12
- 3. Start Standby CC Pump Note: The SRO may not initiate AP/20 API2O if the Standby Pump is started per the ARG.
SRO API2O (Loss of Component Cooling)
Initiate AP/20
- a. THEN trip RX. (- (- 4 minutes)
- 3. Verify CC Surge Tank level ~ 12.
12".
- 4. Manually start the Standby CC Pump
- 5. Verify CC TOTAL FLOW> FLOW > 575 gpm
- 6. If Letdown> 130 of, °F, THEN:
- Close 1 1HP-5, HP-5,
- Initiate AP!032 AP/032 (Loss of Letdown)
Page 5 of 18
Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 4 Event No.:
Event No.: 33 Page 22 of Page of 33 Event
Description:
Event
Description:
1A IA CC Pump Pump trips, 1B lB CC CC Pump Pump Fails Fails to to Auto Start:
SRO)
Time Position_J Position Applicants Actions or Behavior Applicant's Crew Response:
SRO SRO Directs AP/32 (Loss of Letdown) entry; AP/32 will:
SOP!
BOPI 1. Place 11 HP-120 HP-i 20 in HAND and reduce demand to zero.
OATC
- 2. Initiate makeup to LDST as required (Encl.5.5 or OP/1/A/11 03/004.
OP/i/All 103/004.
- 3. Notify Chemistry of the following:
BOP 4. Current RCS boron sample is needed for possible unit shutdown.
- 5. Normal letdown line is isolated.
260,
- 6. IAAT Pzr level 2: 260",
AND letdown CANNOT be established, at 20%/min THEN initiate unit shutdown at::::: 20%/mm per AP/29 (Rapid Unit Shutdown).
375,
- 7. IAAT Pzr level 2: 375",
THEN trip Rx.
- 8. Position the standby HPI pump switch to OFF.
÷ MU) ii. Verify loss of letdown is due to LID
- 11. L/D temperature high and then GO TO Step 4.28.
- 12. Notify SPOC to initiate repairs on failed equipment.
13.
- 13. IAAT letdown can be re-established, THEN perform Steps 4.30 - 4.45.
- 14. Place CC system in operation 15.
1HP-7.
- 16. Open the following:
16.
- 1HP-1 1HP-1
- 1HP-2 1HP-2
- 1HP-3 1HP-3
- 1HP-4 1HP-4 Page Page 66 of of 18 18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 4 Event No.: 3 Page 3 of 3 Event
Description:
1A Event Pump trips, 1B IA CC Pump lB CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position j Crew Response:
Crew Response:
Applicants Actions or Behavior Applicant's SRO/ 17. Verify letdown temperature < < 135°F (it is not; RNO Step 4.34)
- 18. Open 1HP-13.
- 19. Close the following:
- 11HP-8 HP-8
- 1HP-9&11
- 20. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
- 21. Open 11HP-5.
HP-5.
- 22. Throttle open 11 HP-7 to establish:::::
establish 20 gpm.
- 23. WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.
- 24. Open 1 1HP-6.
HP-6.
- 25. Adjust 11 HP-7 to control desired (75 gpm) letdown flow.
- 26. Re-establish normal makeup through 1 1HP-120.
HP-120.
- 27. Re-establish normal RCP seal injection flow.
- 28. Position the standby HPI pump switch to AUTO.
This event is complete when Seal Flow is returned to normal (32 gpm) or when directed by the Lead Examiner.
Page 77 of 18 18
Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 44 Event No.:
Event No.: 44 Page 11 of Page of 22 Event
Description:
Event
Description:
1IHP-5 (Letdown Isolation)
HP-5 (Letdown Isolation) fails CLOSED CLOSED (TS) (TS)
Time Position Applicants Actions or Behavior Applicant's Plant Response:
OATC
- 11 HP-5 green closed light is lit
- Pzr Level slowly increases
- LDST Level slowly decreases Crew Response:
- AP/32,, Loss of Letdown Enters AP/32
- Place 11HP-120 HP-120 in HAND and reduce demand to zero.
OATC/S RO
- Initiate makeup to LDST as required.
- Position the standby HPI pump switch to OFF.
- GO TO Step 4.10 per Table in AP/32
- Close 11HP-6.
HP-6.
- Close 1 1HP-7.
HP-7.
- Open 1HP-5.
- Open 1 1 HP-5 RNO actions as follows:
o Dispatch NEO in continuous communications with control room to manually open 11 HP-5
- NEO manually opens 1 1 HP-5 Cue: Using TIME COMPRESSION report that IHP-5 1HP-5 is manually open.
NOTE: Continuous communication can be accomplished using either plant radio or telephone o Enter TS 3.6.3
- When 1HP-5 1HP-5 is open, THEN continue.
- Place CC system in operation.
- Verify letdown temperature << 135°F.
135°F.
- Throttle 1HP-7 1HP-7 to establish 20
-20 gpm
- Open 1HP-6 1HP-6 Page Page 88 of of 18 18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 4 Event No.: 4 Page 2 of 2 Event
Description:
1IHP-5 HP-5 (Letdown Isolation) fails CLOSED (TS)
Time Position Applicants Actions or Behavior Applicant's OATC/SRO OATC/SRO ** Re-establish normal makeup through 1HP-120.
- Notify SPOC to initiate repairs on 1 1 HP-5.
- Verify seal injection flow reduced in Step 4.7.
- Re-establish normal RCP seal injection flow.
- Position the standby HPI pump switch to AUTO.
- WHEN repairs are complete on 1HP-5 (LETDOWN ISOLATION) (East Pen Rm), THEN perform the following:
A. _ Locally turn 1 1 HP-5 handwheel fully clockwise.
B. 3.63.
EXIT TS 3.6.3.
NOTE: 1 I HP-5 will not be repaired during this scenario When 1 I HP-5 is manually opened and NEO is stationed locally or when directed by Lead Examiner then this event is complete.
Page 99 of 18 18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 4 Event No.: 5 Page 11 of 11 Event PZR Spray Valve Fails Event
Description:
PZR OATCISRO)
Fails OPEN: (C, OATC/SRO)
Note: This event will occur during Event 4.
Time Position Applicants Actions or Behavior Applicant's Cue: Call as Secondary Chemistry request SU (AS) steam flow to the E Heaters. (If needed to remove the BOP from the front board)
HE" Plant response:
- RCS pressure will decrease
- 11SA-2/D-3, SA-2/D-3, RC PRESS HIGH/LOW Crew response:
- 1. 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.
- 1 RC-1 has failed open, he should If the operator identifies 1 AP!44 immediately close the block valve (1 RC-3) per IMAs of AP/44
- Evaluate reducing or isolating letdown flow
- Increase makeup flow as required
- 2. SRO enters to 11AP/44, AP/44, Abnormal Pzr Pressure Control
- 3. 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 1 RC-1
- 1RC-3 1 RC-3
- 4. Verify Pzr heaters maintaining RCS pressure w/in bands
- 5. Notify SPOC SP~C to repair failed 11 RC-1
- 6. Ensure TS requirements met
- 7. WHEN repairs are complete, THEN place 1 1 RC-1 and 11 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 10 10 of 18
Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
No.: 4 Event No.:
Event No.: 66 Page 11 of Page of 11 Event
Description:
Event
Description:
1A IATBV OPEN (I:
TBV fails OPEN (I: OATC, OATC, SRO)
SRO)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- OAC alarm OAC alarm
- 1A Turbine Bypass Valve fails open.
- 11A A Main Steam line pressure decreases
- Reactor Coolant Temperature decreases causing reactor power to increase.
S RO!OATC SRO/OA TC Crew response Crew will perform Low Power "PlantPlant Transient Response".
Response.
- 1. Place ICS Diamond Panel to MAN
- 3. Insert Control Rods to reduce power to below pre-transient level lA SG pressure continues to decrease, the OATC should trip the
- 4. As "1A" reactor due to the anticipated affects of the excessive heat transfer.
When the reactor is is tripped or when directed by the Lead Examiner, this event isis completed completed Page 1111 of of 18 18
Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 44 Event No.:
Event No.: 77 Page 11 of Page of 55 Event
Description:
Event
Description:
Excessive Heat Excessive Heat Transfer (M, (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Plant response:
- Reactor is manually tripped
- 1A SG pressure continues to decrease
- AFIS fails to initiate automatically Crew response:
OATC/SRO OATC/SRO 1. Perform Immediate Manual Actions (IMAs) (IMA5)
- 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.
- 2. Perform Symptom Check
- Power Range Nls NIs <<5%
5%
- Power Range Nls NIs decreasing
- SCMs are NOT < 0° 0°FF
- NO Loss of Main and Emergency FDW (including unsuccessful BO P/OATC manual initiation of EFDW) exists BOP/OATC
- Uncontrolled Main steam line(s) pressure decrease
- NO NOSGTRSGTR
- CSAE Offgas alarms
- Process monitor alarms (RIA-40, 59, 60)
- Area monitor alarms (RIA-16/17)
(RIA-16117)
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)
INIT.
NOTE: AFIS will not work
- Select OFF for 1A 1A MD EFDWP.
- Trip both Main FDWPTs.
- Close 1FDW-315.
1FDW-315.
- Place 11FDW-33 switch to CLOSE. CLOSE.
- Place 1FDW-31 1FDW-31 switch to CLOSE.
CLOSE.
Page Page 1212 of of 18 18
Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
No.: 1I Scenario No.:
Scenario No.: 4 Event No.:
Event No.: 7 Page 2 of Page of 55 Event
Description:
Event
Description:
Excessive Heat Excessive Heat Transfer Transfer (M, (M, ALL)
Position Applicants Actions or Behavior Applicant's Crew response:
BOP/OATC 3. Rule 5 Continued.
- Verify 11 TO TD EFDW PUMP operating.
- Verify 11 TOTD EFDW PUMP is feeding affected SGs. (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 EnclEnd 5.24 (Operation of the ADVs).
ADV5).
CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.
- WHEN illl
[ the following exist:
> Core
~ CoreSCM>OF SCM> 0 F
~ RxRxpower1%
power:::; 1%
~ Pzr level THEN perform the following to stabilize RCS PIT:
P/T:
~ Throttle HPI.
BOP/OATC 1 HP-i 20 setpoint to control at >100"
~ Reduce 1HP-120 >100 [180"acc].
[1 80acc].
~ 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.
- 4. Rule 3 (Loss of Main or Emergency Feedwater)
- IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND y any of the following exist:
ooRCSRCS pressure reaches 2300 psig OR NDT NOT limit o Pzr level reaches 375 375" [340
[340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Page Page 1313 of 18 18
Appendix DD Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
No.: 4 Event No.:
Event No.: 77 Page 33 of Page of 4 Event
Description:
Event
Description:
Excessive Heat Excessive Heat Transfer (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Crew response:
BO P/OATC BOP/OATC 4. Rule 3 continued
- Start EFDW pumps to feed all intact SGs.
- Verify any jy EFDW pump operating.
- Verify any SCM s; 0 of. °F.
- 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 Enc!. End. 5,27 (Alternate Methods for Controlling EFDW Flow) is being initiated due to 1FDW-316 IFDW-316 failed closed.
- Initiate Encl.End. 5.27, (Alternate Methods for Controlling EFDW Flow) 80 P/OATC BOP/OATC End. 5.27
- 3. Encl.
- Identify the failure: (CHART; 11 FDW-316 FDW-31 6 - CLOSED) Step 39
- Stop 1 18B MD EFDWP.
- Verify 1A MD EFWP is operating. (RNO)
>-> Close 11 FDW-369; GO TO Step 43.
OATC/SRO
- Place 1 1 FDW-44 in HAND and set demand to 0%.
- Close 1 1 FDW-42
- Verify 1 1B B MD EFDWP will be used.
- Open 1 1 FDW-384.
- Verify the following:
>- 11FDW-45 closed
>- 11FDW-47 open
- Start1BMDEFDWP.
Start 1B MD EFDWP.
- Throttle 1FDW-44 1FDW-44 to establish 100 100 gpm.
Control). (CT-b)
(CT-10)
- IAAT IAAT proper SG level is is reached and level level permits permits auto level control, THEN place 11FDW-44 in in AUTO.
Page 14 14 of 18 18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 4 Event No.: 7 Event Page 3 of 4 Event
Description:
Event
Description:
Excessive Heat Transfer (M, ALL)
Excessive
_Time Time Position Applicants Actions or Behavior Applicant's Crew response:
SRO Transfer to EOP Subsequent Actions tab then to the Excessive Heat Transfer tab per the Parallel Actions page of Subsequent Actions
- 1. Verify any SG pressure < <550 550 psig.
- 2. Ensure Rule 5 (Main Steam Line Break) in progress or complete.
- 3. Place the following in HAND and decrease demand to zero on .ill[ jj affected SGs:
- 1FDW-32 1 FDW-32
/OATC IOATC ** 11FDW-372 FDW-372
- 11MS-79 MS-79
- 11MS-35 MS-35
- 11MS-82 MS-82
- 1FDW-368 1 FDW-368
- 5. Verify level in both SGs < < 96% O.R.
SRO/BOP 6. IAAT core SCM is > 0°F,
> O°F,
/OATC IOATC
- 7. Verify letdown in service.
- 9. Open the following on all intact SGs:
- 1 FDW-382 1
- 1 FDW-369 1
10.
- 10. Start 1 lB B MDEFDWP
- 11. Feed and steam .ill[
- Dispatch two operators to perform End Encl 5.24 (Operation of the ADV5).
ADVs).
Page 15 15 of 18 18
Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:
Op-Test No.: 1I Scenario No.:
Scenario No.: 4 Event No.:
Event No.: 77 Page 4 of Page of 4 Event
Description:
Event
Description:
Excessive Heat Excessive Heat Transfer (M, (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Crew response:
OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)
/BOP IBOP y of the following:
- 12. Verify any
- A cooldown below 400 of at>
°F at °FIhr has occurred
> 100 °F/hr
- 13. Verify both of the following are closed:
- 11MS-24 MS-24
- 11MS-33 MS-33
- 14. Open 11AS-8.
AS-8.
- 15. Close the following 11SSH-9.
SSH-9.
- 17. IAAT all the following exist:
- ES Bypass Permit satisfied
- All AIISCMs>OIIF SCMs > OOF
- 18. Verify any SG is dry.
- 19. Minimize SCM using the following methods as necessary:
- De-energize all Pzr heaters
- Use Pzr spray
- Throttle HPIHP! to maintain Pzr level 10Q"[18Q"acc]
1OQ[18Qacc]
- Use Use PORV PORV
- OACOAC
- End Encl 5.18 (P/T (PIT Curves)
- 21. Initiate End Encl 5.16 (SG Tube-to-Shell T !J. T Control).
- 22. IAAT IAAT all the following exist:
- 23. RBS actuated
- RB pressure << 10 10 psig
- 11RIA-57 NOT in alarm
Page 16 of 18 Page160f18
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 4 Event No.: 7 Page 4 of 4 Event
Description:
Excessive Heat Transfer (M, ALL)
Time Position Applicants Actions or Behavior Applicant's Crew response:
OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)
/BOP IBOP 24. Verify any RCP operating. Maintain RCP NPSH.
- OAC OAC
- End 5.18 (PIT Encl (P/T Curves)
- 25. Initiate Encl End 5.16 (SG Tube-to-Shell f:1tT T Control).
- 26. IAAT all the following exist:
- RBS actuated
- RB pressure < < 10 psig
- 11 RIA-57 NOT in alarm
- 11 RIA-58 NOT in alarm THEN stop both RBS pumps.
- 27. IAAT Tcold approaches 350°F,
- AND all RCPs are operating,
- THEN ensure < <four four RCPs are operating.
- IAAT BWST level is ~ 19', 19, End 5.12 (ECCS Suction Swap to RBES).
THEN initiate Encl 0°F.
- 28. Verify all SCMs > O°F.
- 29. Verify indications of SGTR exist.
- 30. Verify required RCS makeup flow within normal makeup capability
- 31. Verify either of the following:
- Any SG isolated
- Any SG has an unisolable steam leak
- 32. GO TO FCD tab.
When transfer to the FCD tab is made or when directed by the Lead Examiner this event is completed Page 17 17 of 18 18
Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS
- 1. CT-17, Isolate Overcooling
- 2. CT- 10, Establish FDW Flow and Feed SGs 18 of 18 Page 18of18