ML13025A049
| ML13025A049 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/22/2013 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML13025A049 (87) | |
Text
Appendix D Scenario Outline Form ES-D-1 ILT42 December 17, 2012 Facility: Oconee Scenario No.: 2 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions:
e Reactor Power = 75%
Unit 2: 100%,
Unit 3: 100%
Turnover:
1 B FDWP on Handjack SASS in manual for l&E e
Voltage Regulator is in MANUAL for l&E Reduce VARs to 150 +/- 10 MVARs lAW OP/1/A/1106/001, Enclosure 4.8 (Changing Generator MVAR)
Event F
Malfunction Event No.__[
No.
Event Type*
Description Oa Override SASS in Manual Ob Override AFIS Disabled Oc 1
Place Voltage Regulator Mode in AUTO and decrease N: BOP, SRO VARs.
2 M
C: BOP, SRO 1 B2 RCP seal failure 3
MSS47O C: BOP, SRO Re-occurring Hi Vibration on 1C RBCU degrades to (TS)
Cooler Rupture 4
MPI121 C: OATC, SRO 1HP-120 (RC Volume Control) Fails OPEN 5
MCRO21 C: OATC, SRO Dropped control rod with failure of auto runback circuit (TS)
(requires 1 B FDWP adjustment) 1TB 6900v lockout trips 2nd RCP (1A2) requiring 6
MCRO22 C: OATC, SRO manual Rx trip 1 B MSLB outside the reactor building (EHT tab) with MSS39O, 14%
7 M: ALL Auto AFIS actuation blocked MSS26O 1A MDEFWP fails 8
Override M: ALL LOHT to intact SG requiring transfer to LOHT
- (N)ormal, (R)eactivity, (I) nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
1 Page 1 of 1 Event
Description:
Place Voltage Regulator Mode in AUTO and Decrease VARs Time Position Applicants Actions or Behavior Crew Response:
SRO The SRO will direct the BOP to reduce Generator MVARs to 150 +/- 10 MVARs in accordance with OP/i IA/i 106/001, enclosure 4.8.
OP/1/A11106/OO1 Enclosure 4.8 CAUTION Do NOT exceed limits as shown on Enclosure 4.5 (Capability Curve).
NOTE Minimum of 18.05 Generator kV must be maintained.
Operation with leading PF is acceptable.
2.1.
Notify other online units of VAR change.
SRO/BOP 2.2. Select VARS on WATTNAR TRANSFER Switch.
2.3.
Ensure MVARS are indicated on MWATT/MVAR meter.
2.4.
IF VOLTAGE REGULATOR MODE will be swapped between AUTO &
MANUAL, notify System Operating Center (SOC) that VOLTAGE REGULATOR MODE will be swapped.
2.5.
IF AUTO adjustment is required, perform the following:
NOTE:
VOLTAGE REGULATOR MODE Ready Light (Amber light) should be ON.
CRD AC Power Fault A and/or B alarms along with CRD Global System Fault may be received during generator voltage changes.
2.5.1.
Ensure VOLTAGE REGULATOR MODE in AUTO.
2.5.2.
Use VOLTAGE ADJUST to slowly modify Generator voltage to increase/decrease MVARS.
2.6.
IF MANUAL adjustment is required, perform the following: N/A This event is completed when MVARs have been adjusted to 150 +/- 10 MVARs, or when directed by the lead examiner.
Page 2 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
2 Page 1 of 3 Event
Description:
1B2 RCP lower seal failure (requires pump shutdown) (C: BOP, SRO)
Time Position Applicants Actions or Behavior Plant response:
1 SA-06/D-5, RC PUMP 1 B2 SEAL CAVITY PRESS HI/LOW OAC Alarm RCP 1B2 LOWER SEAL CAVITY PRESSURE HI HI OAC Alarm RCP 1B2 UPPER SEAL CAVITY PRESSURE HI HI Crew response:
Refer to the ARGs BOP 3.1 Upper/Lower Seal Cavity Pressure High 3.1.1 Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action 3.2 Upper/Lower Seal Cavity Pressure Low 3.2.1 IF in Mode 1 or 2, Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action Refer to AP/1/A/1700/016 (Abnormal RCP Operation) 4.1 IAAT y RCP meets immediate trip criteria of End 5.1 (RCP SRO Immediate Trip Criteria), THEN perform Steps 4.2
- 4.11.
RNO:
GO TO Step 4.12.
4.12 IAAT either of the following apply:
It is desired to secure a RCP THEN perform Steps 4.13 -4.15.
RNO:
GO TO Step 4.16 (next page)
E)(AMINER Note:
It is acceptable for the SRO to take either procedure path to secure the 1B2 RCP. Step 4. 161$ on the next page.
4.13 Verity Rx Power > 70%
4.14 Initiate End 5.2 (Rapid Power Reduction) (see page 5) 4.15 WHEN Rx Power is 70%,
THEN GO TO Step 4.2 4.2 Verify MODE 1 or 2 4.3 Verity Rx power is 70% as indicated on all NIs 4.4 Verify three RCPs will remain operating after affected RCP is tripped 4.5 Verify jjy SG on Low Level Limits RNO:
GO TO Step 4.8 4.8 Verify FDW masters in Auto 4.9 Stop affected RCP 4.10 Verify ICS re-ratios feed water to establish desired This event is complete when Rx power is reduced to 70% and the 1B2 RCP is secured, or as directed by the Lead Examiner.
Page 3 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
2 Page 2 of 3 Event
Description:
1 B2 RCP lower seal failure (requires pump shutdown) (C: BOP, SRO)
Time Position Applicants Actions or Behavior Crew response:
SRO AP/1 IA/i 700/016 (Abnormal POP Operation) 4.16 Announce AP entry using the PA system 4.17 Notify OSM to request evaluation by POP Component Engineer 4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:
1 Section Failure 4A Seal Failure 4B Abnormal Vibration 40 High or Low Oil Pot Level 4D Loss of Seal Return 4E Abnormal RCP Temper tures AP/1/A/1700/016 Section 4A, POP Seal Failure SRO 1.
IAAT jjy POP meets immediate trip criteria of End 5.1, THEN perform Steps 2-1 1 RNO: GOTOStepl2 12.
IAAT y of the following indicate external POP seal leakage:
RB RIAs increasing or in alarm PbS Tave constant with LDST level decreasing more than normal Quench Tank level rate increasing RB Normal Sump rate increasing Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage) 13.
Verify the following are open:
1HP-20 1HP-21
- 14. Verify the following is open for the affected POP:
1 HP-230 (1 B2 POP)
This event is complete when Rx power is reduced to 70% and the 182 RCP is secured or as directed by the Lead Examiner.
Page 4 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: IL.T42 Scenario No.:
2 Event No.:
2 Page 3 of 3 Event
Description:
1B2 RCP lower seal failure (requires pump shutdown) (C: BOP, SRO)
Time Position
[
Applicant 1
s Actions or Behavior Crew response:
SPO AP/l/1V1700/016 Section 4A, RCP Seal Failure 15.
IAAT either of the following conditions apply to an operating RCP:
q RCS Pressure AP across y seal
> 1000 psig 100 psid 1000 psig S 35 psid THEN GO TO Step 16 to shut down the affected POP since shut down of the RCP is desired due to a seal failure.
16 IAAT shut down of an POP is desired, THEN perform Steps 17-27
- 17. VerifyMODElor2
- 18. Verify three POPs will remain operating after affected POP is tripped
- 19. Verify Rx power is 5 70% as indicated on aM NIs RNO:
1.
Direct an RD to initiate End 5.2 (Rapid Power Reduction) (see below)
OATO 2.
WHEN Rx power is 5 70% on
- Nls, THEN continue this procedure
- 20. Verify jjy SG on Low Level Limits RNO: GO TO Step 23
- 23. Verify FDW masters in Auto
- 24. Stop affected POP
- 25. Verify lOS re-ratios feedwater to establish desired \\Tc AP/16 Enclosure 5.2, Rapid Power Reduction 1.
VerifylOSinAUTO 2.
Initiate MAXIMUM RUNBAOK to 5 70% as indicated by all NIs 3.
WHEN Rx Power is 70% as indicated by i! NIs, THEN press MAXIMUM RUNBAOK to stop runback 4.
Notify OR SRO that Rx Power is 5 70%
5.
Adjust OTPD SET to match OTP DEMAND 6.
Stop the following pumps:
_1E1 HTRDRN PUMP 1E2 HTR DRN PUMP 7.
Verify Rx Power was reduced 15% within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period 8.
Notify Primary Ohemistry to perform Tech Spec SR 3.4.11.2 as required 9.
EXIT this enclosure This event is complete when Rx power is reduced to 70% and the 1B2 RCP is secured, or as directed by the Lead Examiner.
Page 5 of 46
Appendix D Required Operator Actions Form ES-D-2 lLT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
3 Page 1 of 4 Event
Description:
Reoccurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position
[
Applicants Actions or Behavior Plant response:
QAC alarm 01D1363, RBCU Fan lCVib Crew response:
SRO/BOP BOP will pull up the QAC alarm response guide E)(AMINER NOTE: The first time this OAC alarm comes in, it will reset and clear when the alarm reset pushbutton is depressed. 3 minutes after the initial alarm, there will be another High Vibration alarm. The second time it will not clear when reset.
BOOTH CUE: The first time the high Wbration timer is fired, Timer 15 will automatically fire 5 seconds later to allow the Hi Vib alarm to be reset by the operator. Three minutes after the initial Hi Vib alarm, a second Hi Vib alarm will occur that cannot be reset.
OAC Alarm Response for 01 Dl 363 (RBCU FAN 1C VIB) 1 Depress the RBCU DAC Vibration Alarm Reset Pushbutton.
2 If the alarm does not clear, STOP the RBCU 3
Notify Engineering for an evaluation.
BOOTH CUE: Using time compression, Engineering requests the crew to start the lB RBCU in HIGH speed in accordance with OP/i/A/i 104/015, Reactor Building Cooling System, Enclosure 4.3 Section 4 (Starting RBCU5)
OP/1/A/1104/015, Enclosure 4.3, Section 4 NOTE: When starting RBCUs or changing LPSW flows, RB pressure will change as RB temperature changes. {8}
4.1 Verify RB pressure within limits of PT/1/N0600/001 (Periodic Instrument Surveillance).
4.2 Begin monitoring RB absolute pressure. (OAC Turn On Code: 1 RBPA) 4.3 IF personnel inside containment, announce over plant page that starting RBCU lB.
NOTE: Starting RBCUs can affect the following: RBCU bearing temperatures, RBCU vibration, RBNS level, 1 RIA-47 level, RB pressure/temperature.
This event is complete when the 1 C RBCU rupture is isolated, or as directed by the lead examiner.
Page 6 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
3 Page 2 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position Applicants Actions or Behavior OP/1/A/1104/015, Enclosure 4.3, Section 4 (continued)
SRO/BOP 4.4.
Place desired switch to HIGH or LOW:
1ARBCU lB RBCU 1CRBCU NOTE:
When changing LPSW flows, RB pressure will change as RB temperature changes.
Each RBCU must have 550 gpm Inlet Flow or 750 gpm Outlet Flow to meet flow requirements of SLC 16.9.12.
4.5 Position valves as required for RB cooling:
1 LPSW-1 8 (1 A RBCU OUTLET) 1LPSW-21 (lB RBCU OUTLET) 1 LPSW-24 (10 RBCU OUTLET)
Examiner/Booth Note: When the 1C RBCU is stopped, Timer 15 will automatically fire and insert a IC RBCU cooler rupture. See next page for actions related to the 1C RBCU cooler rupture)
This event is complete when the IC RBCU rupture is isolated, or as directed by the lead examiner.
Page 7 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
3 Page 3 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position ApplicanVs Actions or Behavior Plant Response:
1SA-9/D-9, LPSW RBCU C Cooler Rupture 1SA-91A-6, RB Normal Sump Level High/Low RB normal sump level will increase 1 C RBCU LPSW flow indicator indicates low on VB2 Crew Response:
SRO/BOP ARG for 1 SA-9/D-9 (Manual Actions) 3.1 Verify alarm is valid by checking RBCU 1C Inlet Flow and RBCU 1C delta flow.
3.2 Verify 1 LPSW-24 (RBCU 1 C Outlet) open 3.3 Verify adequate LPSW flow is available; check LPSW pump operation 3.3.1 Verify 1LPSW-22 (1C RBCU INLET) is open.
3.3.2 IF 1 LPSW-22 (1 C RBCU INLET) is NOT open, refer to Technical Specifications and Selected Licensee Commitments 3.4 Monitor RBNS Level for any unexplained increase 3.5 IF RBNS Level is increasing AND ES has actuated, notify Chemistry to sample RBNS for boron to determine if a cooler rupture has occurred.
3.6 IF RBCU 1C Cooler rupture or line break is indicated, then:
NOTE: This sequence prevents having to call LPSW and Containment inoperable per SLC 16.9.12.
BOOTH CUE: As BOP performs step 3.6.1, fire timer #4 to initiate PZR Level #1 failure.
SROJBOP 3.6.1 Isolate the 1 C RBCU Cooler as follows:
A. Close 1LPSW-22 (1C RBCU INLET).
B. Close 1 LPSW-24 (RBCU 1 C OUTLET). (may already be closed)
C. Perform TS 3.6.3 Condition C (C.1
= 4 hrs & C.2 = 31 days) for closed containment system (as required).
D. Enter TS 3.6.5 Condition B (7 days and 14 days from discovery of failure to meet LCO) for RBCU inoperable.
E. Continue to monitor RBNS level for increase.
F. IF RBNS level is still increasing, notify TSC to evaluate further isolation of 1C RBCU.
This event is complete when the IC RBCU rupture is isolated, or as directed by the lead examiner.
Page 8 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
3 Page 4 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position Applicants Actions or Behavior Crew Response (cont.):
EXAMINER NOTE: The crew may decide to pump the RB Normal Sump. If so, see the steps below from OP/i/A/i 104/007 LWD System, Enclosure 4.1 Pumping RBNS to 6
SRO 3.6.2 Refer to Technical Specifications 3.6.3 RefertoSLC 16.9.12 OP/1/A/1104/007 Enclosure 4.1 SRO/BOP 3.1 Verify MWHUT level adequate to receive waste volume.
3.2 Position the following:
Ensure open 1LWD-1 (RB NORMAL SUMP ISOLATION)
Ensure open 1LWD-2 (RB NORMAL SUMP ISOLATION) 3.3 Start one or both of the following:
1A RB NORM SUMP PUMP lB RB NORM SUMP PUMP NOTE:*
Changes in LAWT levels may occur during pumping.
RIA Alarms may be indicative of gas leakage.
If RBNS level was above 14 when pumps were started, a level increase following securing the RBNS pumps may occur. {7}
3.4 WHEN RBNS is at desired level OR at 6 (low level alarm), ensure the following:
3.5 IF required to close the valves, position the following:
EXAMINER NOTE: The SRO should identify that the inoperability of the 1C RBCU results in entry into TS 3.6.5 Condition B (7 days and 14 days from discovery of failure to meet LCO). Also, as required, the crew may need to perform the required actions for TS 3.6.3 Condition C (C. 1 =4 hrs
& C.2 =31 days). SRO refers to SLC 16.9.12, but it is not entered because of the sequence by which step 3.6.1 above was performed.
This event is complete when the 1 C RBCU rupture is isolated, or as directed by the lead examiner.
Page 9 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
4 Page 1 of 1 Event
Description:
1HP-120 (RC Volume Control) Fails OPEN (C: OATC, SRO)
Time Position Applicants Actions or Behavior Plant Response:
OAC alarm for 01 E21 75 (lOS PZR Level Setpoint) Hi PZR level will increase on all channels LDST level will decrease OAC alarms for all 4 POP seal injection flow low 1 SA-2/C-3 (Pressurizer Level HIGH/LOW)
BOP Crew Response:
EXAMINER NOTE:
The crew may notice the increase in PZR level prior to receiving statalarm 1SA-2/C-3. If so, they may (lAW OMP 1-18) take manual control of 1 HP-120 to restore PZR level to the desired band. If not, they will SRO use the direction of the ARG below to restore PZR level. Either is acceptable.
Alarm Response Guide 1SA-2/C-3 (Pressurizer Level HIGH/LOW))
3.1 Oheck alternate PZR level indications.
3.2 Oheck for proper Makeup/Letdown flows and adjust to restore proper level.
3.3 Refer to the following procedures as required:
AP!l /AJ1 700/002 (Excessive ROS Leakage)
AP/i/A/1700/014 (Loss of Normal HPI Makeup and/or POP Seal Injection)
AP/i/A/1700/032 (Loss of Letdown).
EXAMINER NOTE:
Above statalarm is at 260. If action is not taken until the statalarm actuates, TS 3.4.9 Condition A would be entered with a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time to restore level to within limit (because this 260 indicated is equivalent to the 285 TS limit).
3.4 Refer to Technical Specification 3.4.9. (see above examiner note) 3.5 Refer to Technical Specification 3.3.8.(N/A) 3.6 Refer to OP/i/A/i i05/0i4 (Oontrol Room Instrumentation Operation And Information)
This event is complete when Pressurizer Level has been restored to its normal band, or as directed by the lead examiner.
Page 10 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
5 Page 1 of 5 Event
Description:
Dropped Control Rod, Auto Runback Circuit Fails (TS)
Time Position Applicants Actions or Behavior Plant Response:
Group 2 Rod 6 drops into the core Statalarm 1SA-2/A-10 (CRD GLOBAL TROUBLE)
Statalarm 1 SA-2/B-1 0 (CRD ASYMMETRIC ROD POSITION ERROR)
Statalarm 1SA-2/D-9 (CRD OUT INHIBIT)
Statalarm 1 SA-4/C-1 (QUADRANT POWER TILT) (in at 2 minutes)
Statalarm 1 SA-5/A-5 (1 A RPS TROUBLE)
Statalarm 1 SA-5/B-5 (1 B RPS TROUBLE)
Statalarm 1 SA-5/D-5 (1 D RPS TROUBLE)
Crew Response:
OATC/BOP/
Crew should perform Plant Transient Response (PTR)
OATC OATC reports to the SRO reactor power level and direction of movement.
The BOP reports expected AUTO Runback did not occur, and monitors RCS pressure and inventory and inserts Control Rods as needed.
The OATC will adjust FDW and/or control rods as necessary to restore reactor power to the desired control band.
SRO should enter AP/1/A/1 700/001 (Unit Runback)
AP/1 /A/1 700/001 4.1 GO TO the most limiting section per the following table:
i Section Runback 4H Asymmetric Control Rod (1%/mm to 55%power)
Section 4H 1
IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1.
2 IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx.
NOTE Nls should NOT be calibrated per guidelines contained in OP/1/A/1102/004 (Operation at Power) due to actual power re-distribution within the core as a result of a dropped/misaligned rod.
3 Verify Rx is critical.
4.
Verify power> 55% when the rod was dropped or misaligned.
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 11 of46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
5 Page 2 of 5 Event
Description:
Dropped Control Rod, Auto Runback Circuit Fails (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/OO1 Section 4H (continued)
EXAMINER NOTE: Malfunction set to fail Auto runback. Candidate will proceed to RNO SRO/OATC 5
Verify Rx runback to 55% core thermal power in progress.
CTPDsetat55%
ASYMETRIC RODS Runback Light lit CTP Demand decreasing Reactor power will decrease when the runback catches up with the initial power decrease from the dropped rod.
RNO:
- 1. Initiate power reduction to 55% core thermal power at 1%/mm.
- 2. IF control rods will not insert manually, THEN perform the following:
A. Trip reactor.
B. GO TO Unit 1 EOP.
6 Initiate End 5.1 (Control of Plant Equipment During Shutdown). (see page 14)
NOTE The following actions should be performed as quickly as possible due to the complexity of resetting RPS trip setpoints and Tech Spec time limits.
7 Notify SPOC to perform the following:
Investigate cause of dropped or misaligned control rod.
Prepare to reduce the following trip setpoints:
o RPS Flux/Flow-Imbalance o
Notify the OSM to ensure the requirements of the following Tech Specs are met:
TS 3.1.4 (Control Rod Group Alignment Limits)
TS 3.1.5 (Safety Rod Position Limits)
TS 3.2.3 (Quadrant Power Tilt)
Booth Cue: When OSM is contacted, inform the team that the OSM is occupied on Unit 3 and cannot verify TS requirements at this time.
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiners Page 12 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
5 Page 3 of 5 Event
Description:
Dropped Control Rod, Auto Runback Circuit Fails (TS)
Time Position ApplicanVs Actions or Behavior AP/1/A/1700/001 Section 4H (continued)
SRO/OATC/
9 Notify OSM to make notifications as required per OMP 1-14 BOP (Notifications).
10 Verify> 1% SDM with allowance for the inoperable control rod per PT/i IA/i 103/015 (Enclosure 13.18, Reactivity Balance Calculation) within one hour.
11 Reduce core thermal rower the following limits, based on the number of RCPs operating, within two hours:
RCPs Allowable Thermal Power (% FP) 3 45 L
4 60 NOTE:
The following ensures adequate margin in preparation for resetting RPS trip setpoints.
12 IAAT the power decrease is complete, AND any NI is > the following:
RCPs Maximum NI Power (% FP) 3 40 4
55 THEN reduce power until all NIs are the Maximum NI Power limit for the operating RCP combination per End 5.4 (Power Reduction).
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiners Page 13 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
5 Page 4 of 5 Event
Description:
Dropped Control Rod, Auto Runback Circuit Fails (TS)
Time Position
[
Applicants Actions or Behavior AP/1/A/1700/OO1 Enclosure 5.1 SRO/BOP 1
IAAT SRO determines all appropriate actions have been taken, AND the runback is complete, THEN EXIT this Enclosure.
2 Notify the WOO SRO to initiate Enclosure 5.2 (WOO SRO Support During Unit Runback; E)(AMINER NOTE: This scenario was snapped at 75% so steps 3 &4 have already been accomplished.
3 Start the following pumps:
1A FDWP SEAL INJEOTION PUMP 1A FDWP AUXILIARY OIL PUMP 1 B FDWP AUXILIARY OIL PUMP 1 B FDWP SEAL INJECTION PUMP.
4 WHEN CTP is 80%,
THEN stop the following pumps 1E1HTRDRNPUMP 1E2HTRDRNPUMP 5
WHEN OTP 65%,
THEN continue this Enclosure.
6 Place the following in MANUAL and close:
1FDW-53 1FDW-65 NOTE:
lB FDWP is the preferred pump to shut down first.
7 Verify both Main FDWPs operating.
8 Verify 1 B FDWP to be shut down first.
9 Adjust the FWP bias counter-clockwise to lower 1 B FWP suction flow 1 x 106 lb/hr < 1A FWP suction flow.
10 GOTOStepl2.
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 14 of46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
5 Page 5 of 5 Event
Description:
Dropped Control Rod, Auto Runback Circuit Fails (TS)
Time Position Applicants Actions or Behavior AP/1 IA/i 700/001 Enclosure 5.1 (continued)
SRO/BOP 12 IAAT both Main FDW pumps running, AND both of the following exist:
1 B Main FDW pump is first pump to be shut down Any of the following alarms occur:
o iSA-i 6/A-3 (FWP B FLOW MINIMUM) o 1SA-16/A-4 (FWP B FLOW BELOW MIN),
THEN trip 1 B Main FDW Pump.
13 IAAT both Main FDW pumps running, AND both of the following exist:
1A Main FDW pump is first pump to be shut down Any of the following alarms occur:
o 1SA-16/A-1 (FWPA FLOW MINIMUM) o 1 SA-16/A-2 (FWP A FLOW BELOW MIN),
THEN trip 1A Main FDW Pump.
14 IAAT the operating FDWP suction flow < 1.5 x 1 6 Ib/hr, THEN slowly throttle the associated recirc control valve to establish 2300
- 6000 gpm total Condensate flow:
1FDW-53 1FDW-65 15 Maintain Pzr level between 22Q-250.
EXAMINER NOTE: The SRO should refer to Tech Specs and make the following determinations:
TS 3.1.4 (Control Rod Group Alignment Limits), Condition A applies.
TS 3.1.5 (Safety Rod Position Limits), Condition A applies (Safety rods are in Groups 1 4)
TS 3.2.3 (Quadrant Power Tilt), Condition A applies (due to misaligned control rod) (If the highest Incore QPT exceeds +7.11 then Condition B would apply)
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 15 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
6 Page 1 of 1 Event
Description:
1TB Lockout causes a loss of 1A2 and 1B2 RCP requiring a Manual Reactor Trip Time__[
Position Applicants Actions or Behavior Plant Response:
1TB lockout will occur. This will cause a loss of 6900V power to the 1A2 and 1 B2 RCP (1 B2 already tripped). RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power.
Crew Response:
OATC Recognizes the reactor should have tripped (<3 RCPs operating with Reactor power >2%. (OMP 1-18 Att. A), therefore manually trips the Reactor and then perform Immediate Manual Actions of the EOP.
3.1 Depress REACTOR TRIP pushbutton.
3.2 Verify reactor power < 5% FP and decreasing.
3.3 Depress turbine TRIP pushbutton.
3.4 Verify all turbine stop valves closed.
3.5 Verify RCP seal injection available.
EXAMINER NOTE: The steam line break is automatically fired when the rods hit the bottom from the manual Ax trip. With an Excessive Heat Transfer in progress the SRO should not get an opportunity to take any of the Subsequent actions in the SA Tab.
BOP The BOP will perform a symptom check. See Event #7 (next page) for expected results of symptom check.
This event is complete when an operator has manually tripped the Reactor and the IMAs have been performed, or as directed by the lead examiner Page 16 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 1 of 15 Event
Description:
1 B MSLB outside the reactor building fl_Time_[
Position Applicants Actions or Behavior Plant response:
iSA-i/A-i, B-i, C-i, D-i RP Channel Trip iSA-2/D-3, RC Press High/Low iSA-02/A-9 (MS PRESS HIGH/LOW)
ES Channels i & 2 will actuate Crew response:
BOP will perform a Symptoms Check (per OMP i-lB Attachment C)
SROBOP e
Reactivity Control o
Power Range NIs <5% and decreasing ICC/Loss of Subcooling Margin (SCM) o If any SCM 0°F, perform Rule 2 Loss of Heat Transfer (LOHT) o Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)
Excessive Heat Transfer (EHT) o Uncontrolled Main Steam Line(s) pressure decrease Steam Generator Tube Rupture o
CSAE off-gas alarms, process RIAs (RIA-40, 59, 60), area RIAs (RIA 16/i 7)
OATC/BOP Perform Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO (details on page 21)
If SCM reaches 0°F at the beginning of the MSLB, Rule #2 will be performed (details on page 18)
SRO will direct performance of EOP Enclosure 5.i (ES Actuation) (details begin on page 26)
SRO refers to Parallel Actions page of the Subsequent Actions Tab and if SCM > 0°F transfers to the Excessive Heat Transfer Tab (page 30) if SCM = 0°F transfers to LOSCM tab (page 29)
The SRO will direct an RO to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202 This event is complete when step 32 complete in El-IT Tab or as directed by the lead examiner Page 17 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 2 of 15 Event
Description:
1 B MSLB outside the reactor building
[_Time Position Applicant 1
s Actions or Behavior EOP Rule 2 OATC!BOP 1.
i&r all exist:
ySCM0°F Rxpower1%
2 minutes elapsed since loss of SCM THEN perform Steps 2 and 3 2.
Stop all POPs GT-i) (Within 2 minutes of LOSCM) 3.
Notify CR SRO of POP status 4.
Verify Blackout exists RNO:
GO TO Step 6 6.
Open 1 HP-24 and 1 HP-25 7.
Start all available HPI pumps 8.
GOTOStepl3
- 14. Verify at least two HPI pumps are operating using two diverse indications 15.
IAAT 2 HPI pumps operating, AND HPI flow in y header is in the Unacceptable Region of Figure 1 THEN perform Steps 1621.
RNO: GOTOStepl7 17.
IAAT flow limits are exceeded Pump Operation Limit 1 HPI pump!hdr 475 gpm (md. seal injection for hdr) 1A& lB HPI Total flow of 950 pumps operating gpm (md. seal with 1 HP-409 injection) open THEN perform Steps 18-20 RNO: GO TO Step 21 This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 18 of 46
Appendix D Required Operator Actions Form ES-D-2 LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 3 of 15 Event
Description:
1 B MSLB outside the reactor building jJ__Time Position ApplicanVs Actions or Behavior Rule 2 (cont.)
OATC/BOP 21.
- 22. Verify RCS pressure > 550 psig.
23.
IAAT either exists:
LPI FLOW TRAIN A LLPl FLOW TRAIN B 3400 gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 24 RNO:
GO TO Step 35
- 35. IAAT TBVs are unavailable, THEN A Dispatch two operators to perform End 5.24 (Operation of ADV5)
B Notify CR SRO the ADVs are being aligned for use.
RNO: Select OFF for both digital channels on AFIS HEADER A.
RNO: Select OFF for both digital channels on AFIS HEADER B.
- 38. Verify any EFDW pump operating.
1AMDEFDWP 40; Verify any EFDW pump operating.
- 43. Verify both MD EFDWPs operating.
RNO: If 1 TDEFWP is operating, OR NO Main FDW Pumps are operating THEN GO TO step 45.
- 45. Trip both Main FDW pumps.
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 19 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 4 of 15 Event
Description:
1 B MSLB outside the reactor building Time__[
Position Applicant 1
s Actions or Behavior Rule 2 (cont.)
OATC!BOP
- 46. Place FDW block valve switches in CLOSE:
1FDW-33 1FDW-31 1FDW-42 1FDW-40 NOTE SQ levels must continue to increase until SG Lvl Control Point is reached.
If Main FDW is feeding y SG, Rule 7 provides a different SG Level Control Point.
TS cooldown rates are 50°F/1/2 hr when TCOjd > 280°F and 25°F/1/2 hr when T 0
jd 280°F.
- 47. Begin feeding all intact SGs to the appropriate SG Level Control Point in Rule 7 (SQ Feed Control) using available feed sources;
- 48. IAAT SQ Level Control Point is reached, Then maintain SQ Level Control Point by feeding and steaming as necessary.
- 49. Notify CR SRO of SQ feed status.
CAUTION If 1 TD EFDW PUMP is being used for SQ feed and Unit us supplying the Auxiliary Steam header, reducing SG pressure below 250 psig can result in reduced pumping capability.
TBVs Dispatch two operators to perform End 5.24 (operation of the ADVs)
- 51. Verify any Main FDW pump operating.
RNO: GO TO Step 58.
- 58. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete.
- 59. WHEN directed by CR SRO, THEN EXIT this rule.
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 20 of 46
Appendix D Required Operator Actions Form ES-D-2 ILT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 5 of 15 Event
Description:
1 B MSLB outside the reactor building Tim Position Applicants Actions or Behavior e
EOP Rule 5 OATC/BO P 1.
Perform the following on affected headers:
EXAMINER NOTE: AFIS did not auto actuate because a malfunction is preventing it, but the manual initiation below does work.
Initiate AFIS 1 B SG Digital Channels 1 and 2 (CT-17)
Select OFF for 1 B MDEFDW Pump EXAMINER NOTE:
Overcooling must be stopped prior to violating NDT limits. The critical task is to stop feeding the affected 8G.
Trip both Main FDW pumps Close 1 FDW-31 6, 1 FDW-42, and 1 FDW-40 EXAMINER NOTE: TD EFDW Pump tripped by AFIS and IA MD EFDWP did not start and will not manually start.
2.
Verify 1 TD EFDW PUMP operating.
RNO:
1 IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5
- 2. Start 1 TD EFDW Pump 3.
Verify 1 TD EFDW Pump is feeding affected SG.
RNO: GOTOStep5 5.
Verify 1 B SG is an affected SG.
6.
Open 1AS-40 while closing 1 MS-47.
7.
WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either:
TBVs Send two operators to perform End 5.24 (Operation of ADVs)
This event is complete when step 32 complete in El-IT Tab or as directed by the lead examiner Page 21 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 6 of 15 Event
Description:
1 B MSLB outside the reactor building f Tim Position Applicants Actions or Behavior e
EOP Rule 5 (continued)
OATC!BO P CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.
8.
WHEN !i of the following exist:
Core SCM >00 F RxPwr1%
Pzr Level increasing, THEN continue 9.
Place Diverse HPI in BYPASS 11.
Place ES CH 1 and ES CH 2 in MANUAL 12.
Perform the following to stabilize RCS P/T:
Throttle HPI Reduce 1HP-120 setpointto> 100 (180 ACC)
Adjust steaming of unaffected SG (1 B SG) to maintain CETCs constant 13.
WHEN CETCs have stabilized, THEN resume use of T for RCS temperature control 14.
Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (see next page) 15.
Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete (see page 25) 16.
WHEN directed by CR SRO, THEN EXIT this rule This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 22 of 46
Appendix D Required Operator Actions Form ES-D-2 ILT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 7 of 15 Event
Description:
1 B MSLB outside the reactor building Time f
Position Applicants Actions or Behavior EOP Rule 3 (as directed by Rule 5)
OATC!BOP
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding.
RNO: GO TO Step 3
- 3. 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).
- 5. Verify any EFDW pump operating.
- 6. GOTO Step 37.
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42.
RNO: GO TO Step 43
- 43. Verify any SCM 0°F.
RNO:
IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control),
THEN throttle EFDW, as necessary.
- 44. IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation). (see next page)
- 45. WHEN directed by CR SRO, THEN EXIT this rule.
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 23 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 8 of 15 Event
Description:
1 B MSLB outside the reactor building
[Time Position Applicants Actions or Behavior OATC/BOP End 5.9 (Extended EFDW Operation) as directed by Rule 3
- 1. Monitor EFDW parameters on EFW graphic display.
- 2. IAAT UST level is <4, THEN GO TO Step 120
- 8. Perform the following as required to maintain UST level > 7.5:
Makeup with demin water.
Place CST pumps in AUTO.
- 9. IAAT afl the following exist:
Rapid cooldown NOT in progress MD EFDWP operating for each available SG EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.
- 10. Verify 1 TD EFDW PUMP operating.
- 11. Start TD EFDWP BEARING OIL COOLING PUMP.
NOTE Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs.
If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and iC-b is 10% open.
If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 24 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 9 of 15 Event
Description:
1 B MSLB outside the reactor building Time__[
Position Applicants Actions or Behavior OATC/BOP Rule 8 (as directed by Rule 5)
E)(AMINER NOTE: Neither of the criteria in the note below are met so no actions are required in RuleS. If the crew pulls Rule 8 as directed by Rule 5, they should immediately EXIT back out based on the note at the beginning.
NOTE This rule is invoked under either of the following conditions:
A cooldown below 400° F T at> 100 °F/hr has occurred.
HPI has injected through an open or throttled open 1 HP-26, 27, 409, 410 with all RCPs OFF.
SCM must be minimized. The following methods may be used at the discretion of the CR SRO:
- IDe-energizing Pzr heaters
- Using Pzr normal spray
- Using Pzr aux spray
- Using PORV
- Throttling LPI
{22}
Once RCS temperature is stable, a 1-hour hold of RCS temperature must be performed unless a LOCA or SGTR is in progress. Use T in loop with an operating POP or use CETCs if NO RCPs are operating.
Once invoked, SCM shall remain minimized until Engineering has performed an evaluation and determined that PTS restrictions NO longer apply. Starting RCPs and/or restoring cool down rates to normal values do NOT negate the need for this evaluation.
This event is complete when step 32 complete in EKT Tab or as directed by the lead examiner Page 25 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 10 of 15 Event
Description:
1 B MSLB outside the reactor building
_Time Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation)
OATC/BOP 1.
Determine afi ES channels that should have actuated based on RCS pressure and RB pressure.
RCS 1600 psig: Channels 1,2 2.
Verify all ES digital channels associated with actuation setpoints have actuated.
3.
IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1-2.
4.
Place Diverse HPI in BYPASS 5.
Place ES CH 1 and ES CH 2 in MANUAL 6.
Verify Rule 2 in progress or complete.
RNO:
GO TO Step 73 73.
Ensure at least two HPI pumps are operating 75.
Verify 1 HP-26 and 1 HP-27 are open NOTE TO EXAMINER: Conditions not met to require opening 1HP-410 or 1HP-409. No operator action required at this time by step 76.
76.
IAAT at least two HPI pumps are operating, AND HPI flow in y header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header:
q 1 A Header q
1 B Header 1HP-410 1HP-409 77.
Verify jy RCP operating 78.
Open 1 HP-20 and 1 HP-21 79.
IAAT aH exist:
Voter associated with ES channel is in OVERRIDE An ES channel is manually actuated Components on that channel required manipulation THEN depress RESET on the required channel This event is complete when step 32 complete in EKT Tab or as directed by the lead examiner Page 26 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 11 of 15 Event
Description:
lB MSLB outside the reactor building Time__[
Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation) (continued)
OATC!BOP 80.
IAAT jj.y RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 81
- 84 RNO: GO TO Step 85 85.
IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 86 RNO: GO TO Step 123.
123. Start A & B Outside Air Booster Fans.
124. Notify Unit 3 to Start 3A & 3B Outside Air Booster Fans.
125. Verify open 1CF-1 and 1CF-2.
126. Verify 1HP-410 closed.
127. Secure makeup to the LDST.
128. Verify all ES channel 1 & 2 components are in the ES position.
129. Verify Unit 2 turbine tripped.
RNO: GOTO Step 132 132. Close 1LPSW-139.
133. Place in FAIL OPEN:
1 LPSW-251 FAIL SWITCH 1 LPSW-252 FAIL SWITCH 134. Start all available LPSW pumps.
135. Verify either:
Three LPSW pumps operating Two LPSW pumps operating when Tech Specs only requires two operable 136. Open 1 LPSW-4 and 1 LPSW-5 137. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES).
138. Dispatch an operator to perform End 5.2 (Placing RB Hydrogen Analyzers In Service).
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 27 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 12 of 15 Event
Description:
1 B MSLB outside the reactor building
_Time Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation) (continued)
OATC/BOP 139. Notify U2 CR SRO that SSF is inoperable due to OTS1 -1 open.
140. Ensure jjy turnover sheet compensatory measures for ES actuation are complete as necessary.
141. I6AT conditions causing ES actuation have cleared, THEN initiate End 5.41 (ES Recovery).
142. WHEN CR SRO approves, THEN EXIT.
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 28 of 46
Appendix D Required Operator Actions Form ES-D-2 lLT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 13 of 15 Event
Description:
1 B MSLB outside the reactor building Time__f Position Applicant 1
s Actions or Behavior EOP LOSCM tab SRO The SRO will direct an PC to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202
- 1. Ensure Rule 2 in progress or complete
- 2. Verify Station ASW feeding SG (it is not).
RNO: GO TO step4
- 4. Verify LOSCM caused by Excessive Heat Transfer
- 5. Verify EHT tab has been performed (it has not been).
RNO: GO TO EHT tab (details begin on next page)
This event is complete when step 32 complete in El-IT Tab or as directed by the lead examiner Page 29 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 14 of 15 Event
Description:
1 B MSLB outside the reactor building Time Position ApplicanVs Actions or Behavior EOP Excessive Heat Transfer Tab (EHT)
SRO The SRO will direct an Rb to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202 1.
Verify jy SG pressure < 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 ll affected SGs:
o 1FDW-41 andlFDW-44(forlBSG) 4.
Close the following on afl affected SGs:
1 FDW-382, 1 MS-26, 1 MS-76, 1 MS-36, 1 MS-84, 1 FDW-369 5.
Verify level in both SGs < 96% O.R.
6.
IAATcoreSCMis>0°F, THEN perform Steps 7 and 8 7.
Throttle HPI per Rule 6 (H P1) (CT-5)
Note: HPI flow must be throttled and RCS temperature controlled to prevent a solid Pzr and subsequent operation of the PORV.
8.
Verify letdown in service.
RNO:
IF desired to restore letdown, THEN initiate End 5.5 (Pzr and LDST Level Control) (see page 37) 9.
Verify y SG has an intact secondary boundary (intact SG)
NOTE If only one SG is intact and has been isolated for SGTR, the following steps will unisolate and use it for heat removal.
10.
Open the following on intact SGs 1 FDW-372, 1 FDW-368, and 1 MS-i 7 11.
Start MDEFDWP associated with aM intact SGs 1AMDEFDWP RNO: Start TDEFDWP 12.
Feed and steam aM intact SGs to stabilize RCS PIT using either of the following:
TBVs Dispatch two operators to perform End 5.24 (Operation of the ADV5)
This event is complete when step 32 complete in EHT Tab or as directed by the lead examiner Page 30 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
7 Page 15 of 15 Event
Description:
1 B MSLB outside the reactor building j_Time Position ApplicanVs Actions or Behavior EHT Tab (continued)
SPO 13.
GO TO Step 32 32.
Verify y of the following:
HPI has operated in the injection mode while NO RCPs were operating A cooldown below 400° F at> 100°F/hr has occurred RNO:
GO TO Step 34 BOOTH CUE: Fire TimerS after step 32 to trip pumps required to initiate LOHT 34.
Verify 1 MS-24 and 1 MS-33 are closed 35.
Open 1AS-8 36.
Close 1 SSH-9 37.
Perform the following notifications:
Notify Chemistry to determine RCS boron concentration and to sample RBES for boron.
Notify Secondary Chemistry to check for indications of SGTR Notify RP to check for indications of a SGTP This event is complete when step 32 complete in El-IT Tab or as directed by the lead examiner Page 31 of 46
SRO will direct to re-perform symptoms check and notes a loss of Main and Emergency Feedwater. SRO enters LOHT Tab.
LOHT Tab (Loss Of Heat Transfer)
Examiner Note: If RCS pressure reaches 2300 psig and no SG can be fed, the SRO should ensure Rule 4 is initiated. The PZR spray valve is failed closed. Details of Rule 4 are on page #35 1.
Ensure Rule 3 in progress or complete. (SRO will direct Rule 3 to be re-run. See next page for Rule 3 steps).
NOTE: Transfer to LOSCM tab is NOT required if RCS heats to the point where core SCM = 0°F 2.
IAAT the RCS heats to the point where core SCM = 0°F, THEN GO TO Step 4.
3.
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
AND J2Y 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) see page #35.
I NOTE: 1A1 RCP provides the best Pzr spray.
RNO:
1.
Reduce operating RCPs to one pump/loop.
2.
WHEN y of the following exists:
EFDW flow has been re-established by existing Rules/Enclosures EFDW aligned from another unit Operator performing Rule 3 (Loss of Main or Emergency FDW) or End 5.27 (Alternate Methods for Controlling EFDW Flow) reports EFDW available THEN GO TO Step 48 EXAMINER NOTE: The SRO will hold here at this WHEN statement until one of the above EFDW flowpaths is successfully established.
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: ILT42 Scenario No.:
2 Event No.:
8 Page 1 of 5 Event
Description:
LOHT II_Time Position Applicants Actions or Behavior SRO This event is complete when either the SRO is waiting at the WHEN statement at step 3 RNO in the LOHT Tab, Rule 4 is complete, or as directed by the lead examiner Page 32 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 Op-Test No.: lLT42 Scenario No.:
2 Event No.:
8 Page 2 of 5 Event
Description:
LOHT Time__[
Position Applicants Actions or Behavior Rule 3 OATC!BOP 1.
Verify loss of Main FDW/EFDW is due to Turbine Building Flooding.
RNO: GO TO Step 3.
3.
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).
4.
Start operable EFDW pumps, as required, to feed all intact SGs.
5.
Verify any EFDW pump operating.
RNO:
GO TO Step 7.
7.
Place the following in MANUAL and close:
1FDW-315 1FDW-316 8.
Verify both of the following:
Any CBP operating TBVs available on an intact SG RNO:
GO TO Step 16 16.
Verify 1 TD EFDW PUMP is operable and available for manual start.
RNO:
GOTOStep18 18.
Verify cross-tie with Unit 2 is desired.
19.
Dispatch an operator to open 2FDW-313 and 2FDW-314 20.
Dispatch an operator to 1 FDW-313 and have them notify the CR when in position.
21.
Notify Unit 2 to:
Manually Close 2FDW-31 5 & 316.
Start their U2 TDEFWP This event is complete when either the SRO is waiting at the WHEN statement at step 3 RNO in the LOHT Tab, Rule 4 is complete, or as directed by the lead examiner Page 33 of 46
Appendix D Required Operator Actions Form ES-D-2 ILT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
8 Page 3 of 5 Event
Description:
LOHT
_Time Position Applicants Actions or Behavior Rule 3 (continued)
OATCIBOP 22.
WHEN, either exists:
1 FDW-31 3 Operator in position Unit 1 TDEFWP has been manually started; THEN continue.
23.
IAAT an operator is in position at 1 FDW-313, AND Unit 1 TD EFDW PUMP is NOT operating, THEN notify the operator to open:
1 FDW-313 (1A EFDW Line Disch To 1A S/G X-Conn) 1 FDW-31 4 (1 B EFDW Line Disch To 18 S/G X-Conn) 24.
Verify either exists:
HPI Forced Cooling is maintaining core cooling CBP feed providing SG feed NOTE Begin opening EFDW control valve when this step is reached. Flow to the SG will begin as soon as alternate unit valve is off closed seat. 100 gpm could cause overcooling if adequate decay heat levels do NOT exist RNO:
- 1. Establish a maximum of 100 gpm to each available intact SG using:
1FDW-315 1FDW-316 This event is complete when either the SRO is waiting at the WHEN statement at step 3 RNO in the LOHT Tab, Rule 4 is complete, or as directed by the lead examiner Page 34 of 46
Verify any HPI pump can be operated.
Open:
1HP-24 1HP-25 3.
Start afl available HPI pumps.
4.
Open:
1HP-26 1HP-27 5.
Open 1 RC4.
6.
Verify flow exists in any HPI header.
7.
Perform the following:
A. Place 1 RC-66 SET POINT SELECTOR to OPEN.
B. Depress 1 RC-66 OPEN PERMIT pushbuffon.
8.
Verify at least two HPI pumps operating.
9.
Verify flow in both HPI headers is in the acceptable region of Figure 1 (Required HPI Flow Per Header).
Figure 1 Reqnired HPI Flew Per Header Appendix D Required Operator Actions Form ES-D-2 lLT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
8 Page 4 of 5 Event
Description:
LOHT Time Position
[
Applicants Actions or Behavior OATC/BO P Rule 4 1.
2.
lb I
2600 2400 2200 2000 1800 1600 I 400 1200 1000 800 600 400 200 C
0 100 200 300 400 Required HPI Flow Per Header (gpxn)
This event is complete when either the SRO is waiting at the WHEN statement at step 3 RNO in the LOI-IT Tab, Rule 4 is complete, or as directed by the lead examiner 500 00 Page 35 of 46
(continued)
Verify flow exists in any HPI header.
Perform the following:
A. Place 1 RC-66 SET POINT SELECTOR to OPEN.
B. Depress 1 RC-66 OPEN PERMIT pushbutton.
EXAMINER NOTE: 3 RCPs will likely be running unless Rule 2 was run earlier, in which case 0 RCPs will be running.
12.
Verify> one RCP operating.
NOTE 1A1 RCP provides the best Pzr spray and is preferred to be left running in case recovery from HPI forced cooling is performed and a Pzr bubble drawn.
Pump Operation Limit 1 HPI pump/hdr 475 gpm (md. seal injection for A hdr) 1A & 1 B HPI pumps Total flow of 950 gpm operating with 1HP-409 (md. seal injection) open TBVs 1FDW-35 1FDW-44 18.
IAAT all HPI is lost, THEN:
A. Stop all RCPs.
B. Position 1 RC-66 SETPOINT SELECTOR to HIGH.
19.
WHEN directed by CR SRO, THEN EXIT.
Appendix D Required Operator Actions Form ES-D-2 lLT42 December 17, 2012 Op-Test No.: 1LT42 Scenario No.:
2 Event No.:
8 Page 5 of 5 Event
Description:
LOHT Time Position Applicants Actions or Behavior OATC/BOP Rule 4 10.
11.
Stop all but one RCP.
IAAT the following limits are exceeded, 13.
14.
15.
16.
17.
THEN throttle HPI to maximize flow flow limit.
De-energize all Pzr heaters.
Close 1 HP-5.
Close:
This event is complete when either the SRO is waiting at the WHEN statement at step 3 RNO in the LOHT Tab, Rule 4 is complete, or as directed by the lead examiner Page 36 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 EXAMINER NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See excerpt below.
ENCLOSURE 5.5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.
1.
Utilize the following as necessary to maintain IF 1 HP-26 will NOT open, desired Pzr level:
THEN throttle 1 HP-41 0 to maintain
- 1A HPI Pump desired Pzr level.
- lB HPI Pump
- 1HP-7 o
1 HP-i 20 setpoint or valve demand
- 1HP-5 2.
IAAT makeup to the LDST is desired, THEN makeup from 1ABHUT.
3.
IAAT it is desired to secure makeup to
- LDST, THEN secure makeup from iA BHUT.
4.
IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:
A. Open:
1CS-26 1CS-4i B. Position 1HP-l4to BLEED.
C. Notify SRO.
5.
IAAT letdown bleed is NO longer desired, THEN position 1 HP-i4 to NORMAL.
Page 37 of 46
Appendix D Required Operator Actions Form ES-D-2 ILT42 December 17, 2012 ENCLOSURE 5.5 (cont.)
Page 2 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.
IAAT 10 HPI PUMP is required, GO TO Step 10.
THEN perform Steps 7-9.
7.
Open:
1._ IF BWST suction valves
- 1 HP-25 THEN perform the following:
A.
Start 1A LPI PUMP.
B.
Start lB LPI PUMP.
C. Open:
1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D.
IF two LPI Pumps are running çpjy to provide HPI pump suction, THEN secure one LPI pump.
E.
Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Pm, N end).
F.
GO TO Step 8.
2.
IF only one BWST suction valve (1 HP-24 or 1 HP-25) is open, THEN perform the following:
A.
IF three HPI pumps are operating, THEN secure 1 B HPI PUMP.
B.
IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C._ GOTOStep9.
Page 38 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 ACTION/EXPECTED RESPONSE 8.
Start 1C HPI PUMP.
IF at least two HPI pumps are operating, THEN throttle 1 HP-409 to maintain desired Pzr level.
9.
Throttle the following as required to 1
. IF at least two HPI pumps are operating, maintain desired Pzr level:
AND 1 HP-26 will NOT open, THEN throttle 1 HP-41 0 to maintain 1HP-26 desired Pzr level.
1HP-27 2._ IF 1A HPI PUMP and 1 B HPI PUMP are operating, AND 1 HP-27 will NOT open, THEN throttle 1 HP-409 to maintain desired Pzr evel.
RESPONSE NOT OBTAINED ENCLOSURE 5.5 (cont.)
Page3of8 Page 39 of 46
ENCLOSURE 5.5 (cont.)
Page 4 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOTOBTAINED 10.
IAAT LDST vel CANNOT be maintained, THEN perform Step 11.
11.
Perform the following:
.Open 1HP-24.
eOpen 1HP-25.
- Close 1HP-16.
1
. IF both BWST suction valves (1 HP-24 and 1 HP-25) are closed, THEN perform the following:
LPI PUMP.
LPI PUMP.
Start 1A Start lB 1LP-15 1LP-16 1LP-10 1LP-6 1LP-7 D.
IF two LPI Pumps are running pjy to provide HPI pump suction, THEN secure one LPI pump.
E.
Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Pm, N end).
F.
GO TO Step 12.
2._ IF only one BWST suction valve (1 HP-24 or 1 HP-25) is open, AND three HPI pumps are operating, THEN secure lB HPI PUMP.
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 GO TO Step 12.
A.
B.
C. Open:
1LP-9 Page 40 of 46
Appendix D Required Operator Actions Form ES-D-2 ILT42 December 17, 2012 ENCLOSURE 5.5 (cont.)
Page 5 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
12.
IAAT additional makeup flow to LDST is
- desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-i -1 07, Unit 1 RC Bleed Transfer Pump Rm.).
13 IAAT two Letdown Filters are desired, THEN perform the following:
Open 1HP-17.
Open 1HP-18 14 IAAT afl of the following exist:
GO TO Step 34.
Letdown isolated LPSW available Letdown restoration desired THEN pertorm Steps 1.5-33
{4 15 Open:
1.
Notify CR SRO that letdown CANNOT be 1 CC-7 restored due to inability to restart the CC 1 CC-8 system.
2._ GO TO Step 34.
16 Ensure only one CC pump running.
17 Place the non-running CC pump in AUTO.
18 Verify are open:
1 IF 1 HP-i is closed due to 1 HP-3 failing to 1HP-i
- close, 1 HP-2 THEN GO TO Step 20.
2._ IF 1 HP-2 is closed due to 1 HP-4 failing to
- close, THEN GO TO Step 20.
19 GOTOStep22.
NOTE Verification of leakage requires visual observation of East Penetration Room.
20.
Verify letdown line leak in East GO TO Step 22.
Penetration Room has occurred.
21.
GOTO Step 34.
Page 41 of 46
Appendix D Required Operator Actions Form ES-D-2 ILT42 December 17, 2012 ENCLOSURE 5.5 (cont.)
Page 6 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22.
Monitor for unexpected conditions while restoring letdown.
23.
Verify both letdown coolers to be placed in service.
24.
Open:
Verify at least one letdown cooler is aligned.
26.
Close 1HP-6.
27.
Close 1HP-7.
28.
Verify letdown temperature < 125°F.
1.
IF 1A letdown cooler is to be placed in
- service, THEN open:
1HP-1 1HP-3 2._ IF lB letdown cooler is to be placed in
- service, THEN open:
1HP-2 1HP-4 3._ GOTO Step 25.
Perform the following:
A.
Notify CR SRO of problem.
B. _GOTOStep34.
1._ Open 1HP-13.
- 2. Close:
1HP-8 1 HP-9&1 1 3._ IF y deborating IX is in service, THEN perform the following:
A.
Select 1HP-l4to NORMAL.
B.
Close 1HP-16.
4.
Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Page 42 of 46
Appendix D Required Operator Actions Form ES-D2 1LT42 December 17, 2012 Page 7 of 8 ENCLOSURE 5.5 (cont.)
I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
29.
Open 1HP-5.
30.
Adjust 1 HP-7 for 20 gpm letdown.
31.
WHEN letdown temperature is <125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.
32.
Open 1HP-6.
33.
Adjust 1 HP-7 to control desired letdown flow.
NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.
34.
IAAT it is determined that letdown is unavailable due to equipment failures letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).
35.
IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
A.
Obtain SRO concurrence to reduce running HPI pumps.
B.
Secure the desired HPI pumps.
C.
Place secured HP! pump switch in AUTO, if desired.
36.
IAAT aM the following conditions exist:
Makeup from BWST NOT required LDST level > 55 All control rods inserted Cooldown Plateau NOT being used THEN close:
1HP-24 1HP-25 Page 43 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 ENCLOSURE 5.5 (cont.)
Page 8 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37.
Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 39.
been closed to provide additional makeup flow to LDST.
38.
WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:
A.
Stop 1A BLEED TRANSFER PUMP.
B.
Locally position 10S-48 (1 A BHUT Recirc) one turn open (A 1-107, Unit 1 RC Bleed Transfer Pump Rm.).
C.
Close 1 CS-46.
D.
Start 1A BLEED TRANSFER PUMP.
E.
Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90
- 110 psig discharge pressure.
F.
Stop 1A BLEED TRANSFER PUMP.
39.
Verify two Letdown Filters in service, GO TO Step 41.
AND only one Letdown filter is desired.
40.
Perform Qj3 of the following:
Place 1 HP-i 7 switch to CLOSE.
Place 1 HP-i 8 switch to CLOSE.
41.
WHEN directed by CR SRO, THEN EXIT this enclosure.
END.
Page 44 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 CRITICAL TASKS
- 1. CT-i, Stop all RCPs (Within 2 minutes of LOSCM). page 18 (contingent on LOSCM due to overcooling)
CT-5, Throttle HPI per Rule 6. page 30 Page 45 of 46
Appendix D Required Operator Actions Form ES-D-2 1LT42 December 17, 2012 SAFETY: Take a Minute UNIT 0 (OSM)
SSF Operable: Yes N KHUs Operable: Ui
- OH, U2
- UG N LCTs Operable: 2 N Fuel Handling: No UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 75%
Mode: 1 Mode: 1 Gross MWE: 685 100% Power 100% Power RCS Leakage:.024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate:.01 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration TS/SLC #
Date/Time Required Date/Time Shift Turnover Items (CR SRO)
Primary SASS in Manual for I&E Secondary 1 SSH-1, 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.
Holding power at 75% to facilitate work on 18 FDWP.
iBFWPTonHandjack Voltage Regulator in Manual for maintenance. l&E ready to return it to Auto and reduce VARs to approximately 150 (+/- 10) using OP/i/Ni 106/001, End 4.8 (Changing Generator MVAR) to verify proper operation. SOC is already notified the Voltage Regulator will be swapped to AUTO Reactivity Management CR SRO)
R2 Reactivity management controls RCS Boron:
6 ppmB Gp 7 Rod Position: 70%
established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)
Procedure Use and Adherence
Appendix D Scenario Outline Form ES-D-1 ILT42 December 17, 2012 Facility: Oconee Scenario No.: 3 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions:
Reactor Power = 3%
Unit 2: 100%,
Unit 3: 100%
Turnover:
Holding power at 3% at step 3.42 of OP/i/A/i 102/001 (Unit Startup from 532°F/2155 psig to Mode 1) while.PT/i/AJ0630/00i (Mode Change Verification) Enclosure 13.10 Prior To Entry Into MODE 1 is being performed.
Swap CBPs to the 1A CBP running and lB HWP running using OP/1/A/1106/002 C Enclosure 4.3 Event Malfunction E
T Event No.
No.
yen ype Description Oa Override Auto start of HPIP on low seal injection flow is blocked Ob Oc 1
N: BOP, SRO Swap running CBPs and HWPs 2
Override C: OATC, SRO (TS)
Inadvertent DLPIS 3
MP5270,i C: BOP, SRO High Oil Level on 1A2 RCP 4
Override C: BOP, SRO (TS) pump trips and standby HPI pump fails to auto 5
Override C: OATC, SRO, PZR Spray Valve (1RC-l) Fails OPEN 6
MCRO61 C: OATC, SRO, Continuous Control Rod Withdrawal MEL17O M: ALL Blackout Requiring Manual Alignment From CT-5 7
MEL1SO CT-i Lockout KHU-i Emergency Lockout MELO2O KHU-2 Emergency Lockout 8
MSS55O,i00 M: ALL Turbine Building Flood
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
1 Page 1 of 2 Event
Description:
Swap running CBPs and HWPs Time Position Applicants Actions or Behavior OP/1/A/1106/002 C, Enclosure 4.3 (Swapping CBPs)
SRO/BOP 2.1 Position any of the following: (N/A)
IF desired ensure closed 1XGC-F1B (1ACBPAuxO1I Pump Bkr)
IF desired ensure closed 1 XGC-F1 C (1 B CBP Aux Oil Pump Bkr)
IF desired ensure closed 1 XGC-Fi D (1 C CBP Aux Oil Pump Bkr) 2.2 Position any of the following: (N/A)
IF desired ensure Racked-In 1TC-7 (1A CBP Mtr)
IF desired ensure Racked-In 1TD-5 (1 B CBP Mtr)
IF desired ensure Racked-In 1TE-5 (10 CBP Mtr) 2.3 IF desired bypass Powdex per OP/i/A/i 106/002 (Condensate And FDW System). N/A NOTE Number of operating HWP(s) is normally number of operating CBP(s).
During FDW system startup an additional HW pump is required prior to starting CBP until Condensate and FDW systems have been filled by high flow flushes.
BOOTH CUE: If directed to dispatch NEO to HWP & CBP to clear the area, inform the CR that using time compression the lB HWP and the 1A CBP breaker and pump areas are cleared and parameters are normal for start of the lB HWP and the lA CBP.
2.4 IF desired, start standby j HWP.
2.5 Start desired 1A CBP.
2.6 Stop desired 1C CBP.
2.7 IF desired, stop standby j HWP.
2.8 Ensure CBP LOAD SHED DEFEAT switch is positioned to running CBP.
2.9 Ensure HWP LOAD SHED DEFEAT switch is positioned to running HWP.
NOTE: If one or two HWP(s) are operating, standby HWP CR switch should be in AUTO. Required pump maintenance may prevent having a standby pump available.
2.10 IF desired, place standby 1A HWP switch in AUTO NOTE: If one or two CBP(s) are operating, standby CBP CR switch should be in AUTO. Required pump maintenance may prevent having a standby pump available.
2.11 IF desired, place standby 1C CBP switch in AUTO.
This event is complete when the 1A I-IWP and the IC CBP are in AUTO or as directed by the Lead Examiner.
Page 2 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
1 Page 2 of 2 Event
Description:
Swap CBPs Time
[
Position Applicant 1
s Actions or Behavior SRO/BOP OP/1/A/1106/002 C, Enclosure 4.3 (Swapping CBPs) (continued) 2.12 IF desired, place Powdex in service per OP/l/A/1106/002 (Condensate And FDW System). N/A 2.13 IF Unit 1 is in Model, perform the following: (T-5-Heater Panel) N/A Ensure closed 1 HD-298 (Htr 1 Fl Drain Lvl Control Byp)
Ensure closed 1 HD-303 (Htr 1 F2 Drain Lvl Control Byp)
Ensure closed 1 HD-308 (Htr 1 F3 Drain Lvl Control Byp).
This event is complete when the 1A HWP and the lB CBP are in AUTO or as directed by the Lead Examiner.
Page 3 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: lLT42 Scenario No.:
3 Event No.:
2 Page 1 of 4 Event
Description:
Inadvertent DLPIS (TS)
Time Position
[
Applicants Actions or Behavior Plant Response:
1SA-01/E-1i, Diverse LPI Trip 1SA-07/D-3, ES ODD VOTERS TROUBLE o
1 SA-07/E-3, ES EVEN VOTERS TROUBLE DLPIS red pushbutton Illuminated LPI Pumps start LPI injection aligned LPSW Pumps start Crew Response:
OATC/BOP ARG: 1SA-O1/E-11, Diverse LPI Trip 3.1 Determine if DLPIAS condition exists (RCS pressure 462 psig).
3.2 IF RCS pressure is 462 psig, Go To EP/i/A/i 800/001 (Emergency Operating Procedure).
3.3 IF ES condition does NOT exist, Initiate AP/i/AJ1700/042 (Inadvertent ES Actuation).
3.4 Refer to OP/i/A/i 105/014 (Control Room Instrumentation Operation And Information).
AP/1/N1700/042 (Inadvertent ES Actuation) 4.1 Verify any of the following have inadvertently actuated:
Diverse HPI ES Channel 1 ES Channel 2 RNO: GO TO Step 4.4 4.4 Verify any of the following have inadvertently actuated:
ES Channel 5 ES Channel 6 RNO: 1. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently
- actuated, AND it is desired to restore letdown, THEN initiate AP/42 End 5.2 (Letdown Restoration).
- 2. GO TO Step4.i0.
This event is complete when ILP-17 & 18 are closed and TS1SLCs have been addressed, or as directed by the Lead Examiner.
Page 4 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
2 Page 2 of 4 Event
Description:
Inadvertent DLPIS (TS)
Time Position Applicants Actions or Behavior AP/1 IA/i 700/042 (Inadvertent ES Actuation) (continued) 4.10 Close the following:
1HP-24 1HP-25 NOTE If personnel are available, progression should continue while End 5.1 (Required Operator Actions) is in progress.
SRO/BOP 41 1 Ensure AP/42 End 5.1 (Required Operator Actions) is in progress. (see page 7)
SRO/OATC 4.12 Verify any of the following have inadvertently actuated:
Diverse LPI ES Channel 3 ES Channel 4 4.13 Verify Diverse LPI has inadvertently actuated.
EXAMINER NOTE: Placing Diverse LPI in BYPASS will give you 1SA-Ol E 10 statalarm. This is an expected alarm.
4.14 Ensure DIVERSE LPI BYPASS is in BYPASS 4.15 Perform the following on all inadvertently actuated system(s):
Ensure ES CH-3 is in MANUAL Ensure ES CH-4 is in MANUAL 4.16 Verify LPI was aligned in decay heat removal mode prior to ES actuation.
RNO:
- 1. Stop the following:
1ALPIPUMP 1BLPIPUMP
- 2. Simultaneously close the following:
1LP-17 1LP-18 4.17 Verify the Rx is critical.
This event is complete when 1LP-17 & 18 are closed and TS/SLCs have been addressed, or as directed by the Lead Examiner.
Page 5 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
2 Page 3 of 4 Event
Description:
Inadvertent DLPIS (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/042 (Inadvertent ES Actuation) (continued)
CAUTION Do NOT add demin water to counter the boration until RCS boron concentration stabilizes to prevent a positive reactivity event.
NOTE ICS in Auto means lOS is in control of Tave and Rx power.
SRO/OATC 4.18 Verify lOS in Auto 4.19 Verify control rods are outside the desired control band.
RNO: GO TO Step 4.21 4.21 Verify any of the following have inadvertently actuated:
ES Channel 1 Diverse HPI RNO: GO TO Step 4.24 4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary.
SRO 4.25 Initiate logging TS/SLC Entry/Exit, as applicable, in accordance with End 5.4 (TS/SLC Requirements).
EXAMINERS NOTE: If OAC alarm is received for LPSW leakage accumulator level, TS 3.7.7 CONDITION B (7 days) will apply due to LPSW leakage accumulator alarm.
SLC 16.7.6 (Diverse Actuation Systems) will apply due to the automatic actuation logic being blocked if any Diverse Actuation system in OVERRIDE or BYPASS.
CONDITION A (7 days)
IT the RB RIAs isolated during this event TS.3.4.15 Condition B would be entered until unisolated in AP/42 End 5.1 at step 9 This event is complete when 1 LP-17 & 18 are closed and TS/SLC5 have been addressed, or as directed by the Lead Examiner.
Page 6 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
2 Page 4 of 4 Event
Description:
Inadvertent DLPIS (TS)
Time Position Applicants Actions or Behavior SRO/BOP AP/1/A1l700/042 Enclosure 5.1 (Required Operator Actions) 1 Initiate announcement of AP Entry using the PA system.
2 Verify any of the following have inadvertently actuated:
Diverse HPI ES Channel 1 ES Channel 2 RNO: GOTOStep5 5
Verify any of the following have inadvertently actuated:
ES Channel 7 ES Channel 8 RNO: GOTOStep9 9
Perform the following:
A. Open the following to restore RB RIAs:
1PR-7 1PR-8 1PR-9 1PR-10 B. From the ENABLE CONTROLS screen on the RIA View Node, perform the following:
- 1) Select OFF for RB RIA sample pump.
- 2) Start the RB RIA sample pump.
10 Verify any of the following have inadvertently actuated:
Diverse HPI ES Channel 1 RNO: GOTOStep12 12 EXIT this enclosure.
EXAMINER NOTE: If time permits, the BOP may refer to the ARGs for 1SA-07/D-3 and 1SA-07/E-3. Both ARGs will lead him to go to the ES Cabinets to see if there are any flashing lights or abnormal indications on the Even or Odd Voters.
EXAMINER CUE: There are no flashing lights or abnormal indications on either the Even or Odd Voters. (Both of those alarms have cleared by this point in the event)
This event is complete when 1LP-17 & 18 are closed and TSJSLCs have been addressed, or as directed by the Lead Examiner.
Page 7 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
3 Page 1 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position
[
Applicants Actions or Behavior Plant Response:
OAC alarm 01D1036 (RCP 1A2 MTR LOWER OIL POT LEVEL HI)
Crew Response:
SRO/BOP Refer to Alarm Response Guide for 01 D1036 (RCP 1A2 MTR LOWER OIL POT LEVEL HI) 1)
Display RCP parameters and closely monitor oil levels and bearing temperatures.
2)
Refer to AP/1/A/1 700/016 (Abnormal Reactor Coolant Pump Operation) 3)
Notify OSM and RCP Component Engineer of the alarm.
AP/1/A/1 700/01 6, Abnormal RCP Operation 4.1 IAAT any RCP meets immediate trip criteria of End 5.1 (RCP Immediate Trip Criteria),
THEN perform Steps 4.2
- 4.11.
RNO: GOTOStep4.12 EXAMINER NOTE: In step 4.12, the crew may conservatively decide to secure the RCP because the oil pot level is threatening to go offscale high. If so, they will proceed to step 4.13 and will not end up in Section 4C. This path is on page 11. This path or the path below are acceptable 4.12 IAAT either of the following apply:
Any RCP approaching immediate trip criteria of End 5.1 (RCP Immediate Trip Criteria)
It is desired to secure a RCP THEN perform Steps 4.13 -4.15.
RNO: GO TO Step 4.16 4.16 Announce AP entry using the PA system.
4.17 Notify OSM to request evaluation by RCP Component Engineer.
4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:
Section Failure 4A Seal Failure 4B Abnormal Vibration 4C High or Low Oil Pot Level 4D Loss of Seal Return 4E Abnormal RCP Temperatures This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 8 of 41
Appendix D Scenario Outilne Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
3 Page 2 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position
(
Applicants Actions or Behavior AP/1/A/1700/016, Section 4C SRO/BOP 1
IAAT any POP meets immediate trip criteria of End 5.1 (POP Immediate Trip Criteria),
THEN perform Steps 2
- 11.
RNO: GO TO Step 12 12 Start trending POP oil pot levels. (Turn-on Code unitpumpRCPT3, example 1A2RCPT3)
NOTE RCP oil pot level indication range is +1.5 to -1.5 inches.
POP motor oil pot temperatures and POP motor guide bearing temperatures may be used to validate low oil pot level. {4}
13 IAAT oil pot level threatens to go off scale high or low for an operating
- POP, THEN perform Steps 14-24.
14 Verify MODE 1 or 2.
15 Verify three POPs will remain operating after affected POP is tripped.
16 Verify Rx power is 70% as indicated on all NIs.
17 Verify any SG on Low Level Limits.
EXAMINER NOTE: STATALARMS 1SA-07/D-8 (1A2 RCPMP Trip), ISA 02/A-3 (RC Loop A Flow Low), & 1SA-02/A-5 (RC Total Flow Low) will alarm when the 1A2 RCP is stopped.
18 Stop the affected POP.
19 GO TO Step 23.
23 Initiate End 4.3 (Special Instructions for < 4 POP Operation) of OP/i/A/i 102/004 (Operation at Power)..
24 Make the following notifications:
Notify OSM to make required notifications of OMP 1-14 (Notifications).
Notify Rx Engineering and request a power maneuver plan, if needed.
Notify SOC if load reduction was required.
Notify Chemistry to take POS boron samples on a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> frequency.
This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 9 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
3 Page 3 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position
[
Applicants Actions or Behavior SRO/BO P AP/1 IA/i 700/016, Section 4C (continued) 25 IAAT an RB fire exists, THEN perform Steps 26
- 29.
RNO: GO TO Step 30 30 IAAT either of the following conditions is met:
a RCP with low oil level has been shut down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, {9}
a RCP with high oil level has been shut down THEN close the associated RCP motor cooler inlet/outlet valve:
1LPSW-7&8 (1A1 POP) 1LPSW-9&10(1B1 POP) 1LPSW-13&14 (1A2 RCP) 1LPSW-11&12(1B2RCP) 31 IAAT a POP has been tripped due to exceeding Immediate Trip Criteria on a POP motor, THEN contact RCP engineer prior to restart. {8}
32 WHEN conditions permit, THEN EXIT this procedure.
This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 10 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
3 Page 4 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position Applicants Actions or Behavior AP/1 IA/i 700/016, (continued)
SRO/BOP 4.13 Verify Px Power > 70%.
RNO: GO TO Step 4.15 4.15 WHEN Rx Power is 70%,
THEN GO TO Step 4.2.
4.2 Verify MODE 1 or 2.
4.3 Verify Rx power is 70% as indicated on all Nls.
4.4 Verify three RCPs will remain operating after affected RCP is tripped.
4.5 Verify any SG on Low Level Limits.
4.6 Stop the affected RCP.
4.7 GOTOStep4.26.
4.26 Initiate End 4.3 (Special Instructions for < 4 RCP Operation) of OP/i IA/i 102/004 (Operation at Power).
4.27 IAAT an RCP has been shut down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, {9}
THEN close the associated POP motor cooler inlet/outlet valves:
1 LPSW-7&8 (1 Al POP) 1 LPSW-9&l 0 (1 Bi POP) 1LPSW-13&14 (1A2 POP) 1LPSW-ll&12(1B2POP)
This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 11 of4l
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
4 Page 1 of 3 Event
Description:
1A HPI pump trips and standby HP! pump tails to auto start (TS)
Time Position
[
Applicants Actions or Behavior Plant response:
Statalarms:
1 SA-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 = o gpm POP SI flow = -0 gpm 1A HPI Pump amps low = 15 amps PZR level will begin to decrease and LDST level will begin to increase.
Crew response:
Refer to ARGs: Refer to AP/1 4 AP/1/A/1700/014, Loss of Normal HPI Makeup and/or RCP Seal Injection SRO/OATC 3.1 IAAT POP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:
A. Trip the Rx.
B. Stop all RCPs.
C. Initiate AP/25 (SSF EOP).
3.2 IAAT loss of suction to operating HPI pumps is indicated:
- Motor amps low or cycling
- Discharge pressure low or cycling
- Abnormal LDST level trend THEN GO TO Step 3.3.
RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System.
4.8 Verify any HPI pump operating.
RNO
- 1. Close 1HP-5
- 2. Place 1HP-120 in HAND and closed
- 3. Place 1 HP-31 in HAND and closed
- 5. IF standby HPI pump started, THEN GOTO Step 4.111.
This event is complete when 1 HP-31 is placed in AUTO, or as directed by the Lead Examiner.
Page 12 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
Page 2 of 3 Event
Description:
1A HPI pump trips and standby HPI pump fails to auto start (TS)
Time Position Applicants Actions or Behavior AP/14, Loss of Normal HPI Makeup and/or RCP Seal Injection (continued)
OATC/BOP 4.111 Place 1 HP-31 in HAND 4.112 Slowly open 1 HP-31 until 8 gpm/RCP is achieved.
4.113 Re-establish normal makeup through 1HP12O.
4.114 Ensure proper operation of the Component Cooling System.
4.115 Reduce 1HP-7 demand to 0%.
4.116 Close 1HP-6 4.117 Open the following:
1HP-1 1HP-2 1HP-3 1HP-4 BOOTH NOTE: Crew may direct NEO to open & rack out the l HPIP breaker. (Use Quick Strike to remove fuses) 4.118 Open 1HP-5 4.119 Throttle open 1HP-7for 20 gpm letdown flow.
4.120 Open 1HP-6 4.121 Adjust 1 HP-7 for desired letdown flow.
4.122 Open the following:1 HP-228, 1 HP-226,1 HP-232, 1 HP-230 4.123 Open 1HP-21.
4.124 IAAT SEAL INLET HDR FLOW 32 gpm, THEN place 1 HP-31 in AUTO 4.125 Monitor RCP seal parameters.
4.126 Maintain RCP seal injection flows as required.
4.127 Log thermal cycle of 1A HPI header.
4.128 WHEN conditions permit, THEN EXIT this procedure.
Note: Crew may enter AP/16 (Abnormal RCP Operation) as a result of high seal return temperatures. Steps are on the next page.
This event is complete when I HP-31 is placed in AUTO, or as directed by the Lead ExaminerS Page 13 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
Page 3 of 3 Event
Description:
1A HPI pump trips and standby HPI pump tails to auto start (TS)
Time__[
Position Applicants Actions or Behavior AP/16 (Abnormal RCP Operation)
OATC/BOP 4.1 IAAT any RCP meets immediate trip criteria... (does not)
RNO: GOTOStep4.12 4.12 IAAT all of the following apply:
Any RCP approaching immediate trip criteria of End 5.1.
It is desired to secure a POP THEN perform Steps 4.134.15:
RNO: GOTOStep4.16 4.16 Announce AP entry using the PA system.
4.17 Notify OSM to request evaluation by RCP Component Engineer.
4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:
4D Loss of Seal Return AP/16 (Abnormal RCP Operation) Section 4D
- 1. IAAT any RCP meets immediate trip criteria... (does not)
RNO: GOTO Step 12
- 15. Verify either of the following... (not met)
RNO GO TO Step 17.
- 17. Verify RCP seal return low flow alarms off.
RNO: Request that RCP Component Engineer provide the following:
Immediate evaluation Additional monitoring requirements EXAMINER CUE: If candidate attempts to monitor the Loose part Monitor, indicate that the noise is normal.
EXAMINER 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. 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 /> This event is complete when 1 HP-31 is placed in AUTO, or as directed by the Lead Examiner.
Page 14 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
5 Page 1 of 3 Event
Description:
PZR Spray Valve (1 RC-1) Falls OPEN Time Position
[
Applicants Actions or Behavior Booth Cue: Call control room as Secondary Chemist and request position of 1AS-35 (Stm to E Heaters) and steam flow to E heaters. While BOP is at vertical boards, fire Timer 5 to initiate event.
Plant Response:
RCS pressure will decrease 1 SA-2/D-3 (RC PRESS HIGH/LOW)
Crew Response:
EXAMINER NOTE: The crew may perform Plant Transient Response (PTR)
Refer to Alarm Response Guide 1 SA-2/D-3 (RC PRESS HIGH/LOW) 3.2 Low Alarm 3.2.1 Refer to AP/1/N1 700/044 (Abnormal Pressurizer Pressure Control)
AP/1 IA/i 700/044 (Abnormal Pressurizer Pressure Control)
SRO/OATC 3.
Immediate Manual Actions 3.1 IAAT ll of the following conditions exist:
PORV open RC pressure <2300 psig (HIGH) or 480 psig (LOW)
PZR level 375 THEN close 1 RC-4 EXAMINER NOTE: The crew may perform Immediate Manual Action Step 3.2 from memory prior to the SRO entering AP/44.
3.2 IAAT a the following conditions exist:
PC pressure <2155 psig RC pressure decreasing without a corresponding decrease in PZR level PZR heaters unable to maintain RCS pressure THEN close the following:
1RC-1 1RC-3 EXAMINER NOTE: If the block valve (1RC-3) is not closed, the Reactor will trip on variable low pressure and ES actuation will occur This event is complete when 1RC3 is re-opened and 1RC-i is in Auto, or as directed by the Lead Examiner.
Page 15 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
5 Page 2 of 3 Event
Description:
PZR Spray Valve (1 RC-i) Fails OPEN Time Position
[
Applicants Actions or Behavior AP/l IA/i 700/044 (Abnormal Pressurizer Pressure Control) (continued)
SRO/OATC 4.1 Announce AP entry using the PA system 4.2 GO TO the applicable per the following table:
q Failure Caused Step RCS Pressure Decrease 4.3 Increase 4.19 4.3 Verify the following:
1 P0-4 failed to close PORV open RNO:
GO TO Step 4.5 4.5 Verify 1 nc-i failed OPEN 4.6 Position the following to maintain RC pressure within desired band, as required:
1R0-1 1RC-3 4.7 Verify PC pressure decreasing uncontrollably RNO:
GO TO Step 4.14 4.14 Verify PZR heaters maintaining P05 pressure within desired band 4.15 Notify SPOC to repair malfunctioning component SRO 4.16 Ensure requirements of following are met: (no TS should apply)
TS 3.4.1 (RCS Pressure, Temperature, and Flow DNB Limits)
TS 3.4.9 (Pressurizer)
SLC 16.5.1 (IRCS Vents)
This event is complete when 1 RC-3 is opened and 1 RC-1 is in Auto, or as directed by the Lead Examiner.
Page 16 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
5 Page 3 of 3 Event
Description:
PZR Spray Valve (1 RC-1) Fails OPEN Time Position
[
Applicant 1
s Actions or Behavior SRO/OATC AP/l/AJ1700/044 (Abnormal Pressurizer Pressure Control) (continued)
BOOTH CUE: Fire Timer 14 to repair 1RC-1 then call control room as SPOC and inform the crew that (using Time Compression) the control module for IRC-1 had failed. It has been replaced and IRC-lcan be returned to normal operation 4.17 WHEN repairs complete, THEN place the following components in desired position for current plant conditions as determined by CR SRO.
1RC-1 1RC-3 1RC-4 PZR heater bank #1 PZR heater bank#2 PZR heater bank #3 PZR heater bank #4 4.18 When directed by the CR SRO, THEN EXIT this procedure.
This event is complete when 1 RC-3 is opened and 1 RC-1 is in Auto, or as directed by the Lead Examiner.
Page 17 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
6 Page 1 of 1 Event
Description:
Continuous Control Rod Withdrawal Time Position
[
Applicants Actions or Behavior Plant response:
Control Rods withdrawing without operator action NI-5 thru NI-9 indicate increasing reactor power SURs on Wide Range NIs increasing Crew response:
The candidates should utilize the Plant Transient Response process to stabilize the plant and recognize that control rods are withdrawing without a valid signal.
Verbalize to the SRO reactor power level and direction of movement.
Place the Diamond and both FDW Masters in MANUAL to stabilize the plant.
SRO/OATC The crew should insert control rods and monitor reactor power and wide range startup rate to stabilize the plant Report no valid (ICS) Runback and monitor RCS pressure and inventory Contact SPOC to investigate the continuous rod withdrawal.
Note: The OATC may elect to trip the Rx during this transient per SOMP 01-02 and OMP 1-18 Attachment J (Plant Transient Response).
6.3.3 During abnormal operating conditions a manual reactor trip shall be initiated if any of the following conditions occur:
Reactor power level approaches any operating limit Reactor power level exceeds the pre-transient power level by greater than 5% AND the cause of the power change is NOT understood, OR is NOT controllable Any time plant conditions are considered uncontrollable or unsafe EXAMINER/BOOTH NOTE: When the Rx is tripped Timer 7 will auto initiate Blackout (event 7-next page)
This event is complete when the plant is stabilized using PTR, the reactor is tripped, or as directed by the Lead Examiner.
Page 18 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No:3 Event No.: 7 Page 1 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5 Time__{
Position Applicants Actions or Behavior Plant Response Reactor will trip (if not already tripped)
MFBs will de-energize CT-i Lockout KHU-i Emergency Lockout KHU-2 Emergency Lockout Crew Response:
SRO directs OATC to perform Immediate Manual Actions (IMAs):
SRO/OATC Depress REACTOR TRIP pushbutton Verify Reactor Power < 5% FP and decreasing Depress turbine TRIP pushbutton Verify turbine stop valves closed Verify RCP seal injection available EXAMINER NOTE: The OATC should determine that RCP Seal Injection and CC are not available and inform the SRO to initiate AP/25. The SRO will then direct an RO to initiate AP/25. When the RO attempts to leave the Control Room, inform him/her that a Unit 2 RO will perform AP/25 actions at the SSF.
SRO directs BOP to perform Symptoms Check:
SRO/BOP Power Range NIs <5% and/or decreasing
- AnySCM0°F Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)
Uncontrolled Main Steam Line(s) pressure decrease Steam Generator Tube Rupture o
CSAE Offgas alarms o
Process Monitor alarms (RIA-40) o Area monitor alarms (RIA-i6/i7)
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 19 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.: 3 Event No.:7 Page 2 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5 U_Time Position Applicants Actions or Behavior Crew Response:
SRO will transfer to Subsequent Actions Tab of the EOP after documenting IMA5 and will refer to the Parallel Actions Page which will require a transfer to the Blackout Tab due to ALL 41 60V switchgear being de-energized.
Blackout Tab SRO/OATC/
1.
Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or BOP complete. (page 22) 2.
Verify two ROs available to perform Control Room actions NOTE:
During performance of End 5.38 (Restoration of Power), progression through the Blackout Tab should continue.
SRO/BOP 3.
Notify one P0 to perform End 5.38 (Restoration of Power)
(see page 24) 4.
Verify any SG is being fed SRO/OATC 5.
Verifyy MD EFDWP operating using diverse indication.
RNO: Position to OFF:
1AMDEFDWP 1BMDEFDWP 6.
Verify either:
Blackout occurred during Mode 3 Blackout occurred while in mode 4 with SGs removing decay heat.
RNO: 1. Feed and steam available SGs as necessary to stabilize RCS PIT in bands prescribed by Rule 7 (SG Feed Control)
- 2. GO TO step 8.
NOTE:
Feeding SGs with EFDW is desired over HPI Forced cooling. Step 8 should be performed prior to re-performing Rule 3.
100 gpm could cause overcooling if decay heat levels do NOT exist.
8.
IAAT NO SGs are being fed, AND y source of EFDW (Unit 1 or another unit) becomes available, THEN perform steps 9 11.
RNO: GOTOstepl2 This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 20 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:3 Event No.:7 Page 3 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5
[_Time Position Applicants Actions or Behavior Blackout Tab (continued)
SRO/OATC
- 12. IAAT EFDW from any source is insufficient to maintain stable RCS PIT, THEN notify SSF operator that feeding SGs with SSF ASW is required.
- 13. IAAT power is restored to jy of the following:
iTO 1 TD 1 TE THEN GO TO Step 14 RNO: GOTO Step 19
- 19. Verify End 5.38 (Restoration of Power) in progress or complete EXAMINER NOTE: When power is restored using End 5.38, return to Blackout Tab here.
- 13. IAAT power is restored to y of the following:
1TC o
lTD 1TE THEN GO TO Step 14
- 14. Ensure Step 8 dispositioned appropriately.
- 15. Verify SSF activated.
NOTE AP/i 1 (Recovery From Loss of Power) will transition seal injection from SSF to HPI.
- 16. Communicate status of SG feed and seal injection to SSF operator using x-2766, radio, or plant page.
- 17. Initiate AP/i 1 (Recovery from Loss of Power) (see page 26)
- 18. GO TO Subsequence Actions Tab.
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 21 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:3 Event No. :7 Page 4 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5
[ Time__[
Position Applicants Actions or Behavior SRO/BOP/
EOP Rule 3 OATC
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GO TO Step3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency)
AND jjy 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)
- 5. Verifyy EFDW pump operating
- 6. GO TO Step 37
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO Step 43
- 43. Verify ay SCM 0°F RNO: IF overcooling, OR exceeding limits in Rule 7 (50 Geed Control),
THEN throttle EFDW, as necessary
- 44. IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation) (see next page)
- 45. WHEN directed by CR SRO, THEN EXIT this rule This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 22 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.3 Event No. :7 Page 5 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5
_Time Position Applicants Actions or Behavior SRO/BOP/
End 5.9 (Extended EFDW Operation) as directed by Rule 3 OATC
- 1. Monitor EFDW parameters on EFW graphic display.
- 2. IAAT UST level is < 4, THEN GO TO Step 120
- 8. Perform the following as required to maintain UST level > 7.5:
Makeup with demin water.
Place CST pumps in AUTO.
- 9. IAAT all the following exist:
Rapid cooldown NOT in progress MD EFDWP operating for each available SG EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.
- 10. Verify 1 TD EFDW PUMP operating.
- 11. Start TD EFDWP BEARING OIL COOLING PUMP.
NOTE Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs.
If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 10-10 is 10% open.
If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiners Page 23 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:3 Event No.7 Page 6 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5
_Time Position Applicants Actions or Behavior SRO/BOP/
EOP Enclosure 5.38 (Restoration of Power)
OATC Verify power has been restored RNO: GO TO Step 3
- 3. Place 1 HP-31 in HAND and reduce demand to 0
- 4. Close 1HP-21
- 5. Verify any of the following energized:
MFB1 MFB2 RNO: GO TO Step 8
- 8. Verify CT-i indicates 4160 volts RNO: GOTO Step 18
- 18. Verify both Standby Bus #1 and Standby Bus #2 are de-energized
- 19. Verify both Keowee units operating RNO: 1. Emergency Start Keowee units:
KEOWEE EMER START CHANNEL A KEOWEE EMER START CHANNEL B (not modeled on simulator)
- 2. IF NO Keowee units are operating, THEN GO TO Step 36
- 36. IAAT CT-5 indicates 4160 volts, THEN GO TO Step 51
- 51. Place the following switches in MAN:
MFB1 AUTO/MAN (already in manual)
MFB2 AUTO/MAN (already in manual)
STANDBY 1 AUTO MAN STANDBY 2 AUTO MAN
- 52. Open the following breakers:
Ni 1 MFB1 NORMAL FDR (already open)
N2 1 MFB2 NORMAL FDR (already open)
El 1 MFB1 STARTUP FDR (already open)
E2 1 MFB2 STARTUP FDR (already open)
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 24 of 41
- 54. Open the following breakers:
SKi CT4 STBY BUS 1 FEEDER (already open)
SK2 CT4 STBY BUS 2 FEEDER (already open)
- 55. Close the following breakers: (CT-B> (*Critical Steps to regain power.
Only one set of breakers is required to regain power)
SL1 CT5 STBY BUS 1 FEEDER*
SL2 CT5 STBY BUS 2 FEEDER*
- 56. Place the following switches in AUTO:
CT5 BUS 1 AUTO/MAN CT5 BUS 2 AUTO/MAN
- 57. Verify Standby Bus #1 energized
- 58. Notify CR SRO in each unit where a blackout exists that Standby Bus #1 is energized Note: The Blackout exists on Unit 1 only.
- 59. Close the following breakers:
_S1 1 STBY BUS 1 TOMFB1*
S2 STBY BUS 2 TO MFB2*
- 60. Verify jjy of the following energized:
- 1TC, 1TD, 1TE
- 61. Notify Unit 1 CR SRO of status of 41 60V SWGR EXAMINER NOTE: When power is restored to 1TC, 1TD, or 1TE, IAAT Step 13 (B/O Tab) will apply.
Return to the Blackout Tab on page 21 for further actions.
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:3 Event No.:7 Page 7 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5 Time Position Applicants Actions or Behavior SPO/BOP!
OATC EOP Enclosure 5.38 (continued)
- 53. Place the following switches in MAN:
CT4 BUS 1 AUTO/MAN CT4 BUS 2 AUTO/MAN CT5 BUS 1 AUTO/MAN (already in manual)
CT5 BUS 2 AUTO/MAN (already in manual)
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 25 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.3 Event No.7 Page 8 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5 Time Position
[
Applicants Actions or Behavior 1
SRO/BOP/
AP/1 1 (Recovery From Loss of Power)
OATC 4.1 Announce AP entry using OMP 1-18 placard.
4.2 IAAT Pzr level > 80[180acc],
AND Pzr heaters are desired, THEN position Pzr heaters to AUTO.
4.3 Verify load shed of inverters was performed per Unit 1 EOP End (Load Shed of Inverters During SBO).
RNO: GO TO Step 4.9 4.9 Verify load shed has initiated as indicated by either of the following statalarms on:
1SA-15/D-4 (EL LOAD SHED CHNLA LOGIC INITIATE) 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.10 Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 1 or 2).
4.11 Close the following breakers:
1TC INCOMiNG FDR BUS 1 1TC INCOMING FDR BUS 2 lTD INCOMING FDR BUS 1 lTD INCOMING FDR BUS 2 1TE INCOMING FDR BUS 1 1TE INCOMING FDR BUS 2 4.12 Verify iSA-i 5/E-6 (EL SWYD ISOLATION CONFIRMED CHNL A LOGIC) is OFF.
RNO: GOTOStep4.15 4.15 Verify any Oconee unit receiving power from its normal source (iT, 2T, 3T).
4.16 Place transfer switches in MAN for all Oconee units receiving power from the normal source (iT, 2T, 3T):
MFB1 AUTO/MAN MFB2 AUTO/MAN TA AUTO/MAN TB AUTO/MAN This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 26 of 41
Appendix 0 Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:3 Event No.:7 Page 9 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5 Time Position Applicants Actions or Behavior 1
SRO/BOP/
AP/1 1 (Continued)
OATC 4.17 Verify load shed was initiated as indicated by either of the following statalarms on:
iSA-i 5/D-4 (EL LOAD SHED CHNLA LOGIC INITIATE) iSA-i 4/0-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.18 Verify ES has occurred.
RNO: GOTO Step 20 4.20 Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
MFB UNDERVOLTAGE CHANNEL 1 RESET MFB UNDERVOLTAGE CHANNEL 2 RESET 4.21 Verify load shed signal reset as indicated by both of the following statalarms off:
iSA-i 5/D-4 (EL LOAD SHED CHNLA LOGIC INITIATE) iSA-i 4/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.22 IAAT electrical loads are added, AND any MFB is powered from a Lee Gas Turbine, N/A THEN notify Lee Steam Station to adjust frequency as necessary.
4.23 Verify both:
Condensate flow has been lost for < 25 minutes Condensate system operation desired 4.24 Place all HWP control switches to OFF.
4.25 Place all CBP control switches to OFF.
4.26 Place in MANUAL and close:
o 1FDW-53 1FDW-65 4.27 Place iC-b FAIL SWITCH in MANUAL.
4.28 Close iC-b.
4.29 Make plant page to clear basement and third floor of non-essential personnel.
4.30 Start one HWP.
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 27 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:3 Event No. :7 Page 10 of 10 Event
Description:
Blackout Requiring Manual Alignment From CT-5
_Time Position Applicant t
s Actions or Behavior SRO/BOP/
API1 1 (Continued)
OATC 4.31 Verify < 25 minutes elapsed since loss of condensate.
4.32 Throttle 10-10 controller 10% open to satisfy 25 minute system restart criteria.
4.33 WHEN FWP SUCT HDR PRESS (1VB3) is 100 psig, THEN open 10-10.
4.34 Place 10-10 FAIL SWITCH in FAIL OPEN.
4.35 Maximize total recirc flow < 1200 gpm with one of the following:
1FDW-53 1FDW-65 This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 28 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
8 Page 1 of 3 Event
Description:
Turbine Building Flood Time Position Applicants Actions or Behavior Plant Response:
25A-18/B-11 (TURBINE BSMT WATER LEVEL ALERT)
Notification from Unit 2 that Turbine Building flooding exists as indicated by the following:
o 2SA-1 8/A-il (TURBINE BSMT WATER EMERGENCY HIGH LEVEL)
EXAMINER NOTE: The B-il ALERT will alarm before the A-il EMERGENCY HIGH alarms. Entry Conditions for AP-lO are not met until the A-il Emergency High statalarm is received. 2SA-18/B-l I actuation is the start time for TCA #4 (on page 3 of 3)
Crew Response:
ARG 2SA-18/B-11 (TURBINE BSMT WATER LEVEL ALERT)
SRO/OATC 3.1.
Dispatch operator to T.B. Water Level Monitoring Panel, located
/BOP outside #2 CR in order to determine which level switches are in alarm.
3.2.
Investigate and correct reason for water in T.B. Basement.
ARG 2SA-18/A-11 (TURBINE BSMT WATER EMERGENCY HIGH LEVEL) 3.1.
Notify Unit 3 Control Room.
3.2.
All units immediately refer to AP/1,2,3/A/i 700/i 0 (UNCONTROLLABLE FLOODING TURBINE BUILDING).
OATC/BOP performs AP-lO (Turbine Building Flood) after receiving direction from the SRO (details on page 31)
SRO enters the EOP TBF (Turbine building Flood) Tab and proceeds through it in parallel with the BOP performing AP-i 0. (see next page)
This event is complete when Close 1/Close 2 pushbuttons have been depressed, control of RCS cooldown has been demonstrated, and Pzr level is being maintained >100 or as directed by the lead examiner Page 29 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
8 Page 2 of 3 Event
Description:
Turbine Building Flood f_Time Position Applicants Actions or Behavior EOP TBF Tab NOTE Feeding to 95% O.R. in Step 1 supersedes guidance in Rule 7 (SG Feed Control), Table 4 (SG Level Control Points).
1.
Initiate feeding SGs to 95% OR. at maximum allowable rate using all available feedwater sources while maintaining the following:
Initial Tave 532°F maintain Tave 532°F during SG fill.
Initial Tave <532°F minimize cooldown during SG fill utilizing TBVs as required.
2.
Minimize Pzr level> 100 [180 acc].
NOTE POP 1A1 provides the best Pzr spray.
3.
Reduce operating RCPs to one NOTE Turbine Building flooding will result in loss of condenser vacuum, rendering TBVs unavailable.
4.
Stabilize temperature determined in Step 1 by performing the following:
A. Dispatch two operators to perform End 5.24 (Operation of the ADVs)
B. Adjust SG pressure as necessary using:
TBVs while available ADVs after TBVs are lost 5.
IAAT LPSW is lost, THEN stop all RCPs.
6.
Verify SSF-ASW available.
- 7. Dispatch operators to SSF with a copy of End 5.34 (Aligning SSF-ASW for SG feed).
Examiner Note: If Unit 1 RO attempts to go to SSF, inform them that a Unit 2 RO will staff the SSF 8.
Dispatch an operator to perform End 5.10 (Station ASW Pump Alignment). (PS)
This event is complete when Close 1/Close 2 pushbuttons have been depressed, control of RCS cooldown has been demonstrated, and Pzr level is being maintained >100 or as directed by the lead examiner Page 30 of 41
Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1LT42 Scenario No.:
3 Event No.:
8 Page 3 of 3 Event
Description:
Turbine Building Flood Tim Position Applicants Actions or Behavior e
AP/lO (Turbine Building Flood)
SROIBC P/
4.1.
Trip the Rx.
OATC NOTE Tripping the CCW pumps will cause loss of condenser vacuum which will result in TBVs failing closed and trip of the Main FDW pumps.
4.2.
Ensure all COW pumps are shutdown.
4.3.
Press both of the following on the TURB BLDG FLOOD EMER CLOSING ALL CCWP DISCH VALVES control switch: TCA#4 (Press Close 1/Close 2 within 20 minutes of CCW break OR within 11.3 minutes of receiving TB Emergency High Level alarm)
CLOSE 1 CLOSE 2 4.4.
Verify all CCW pump discharge valves are closed.
4.5.
Dispatch operators to ensure all three flood doors are closed and in the SECURED position from the AB side (A-i, at Unit 1, 2, and 3 stairwell entrances to TB): {2}
Unit 1 Flood Door Unit 2 Flood Door Unit 3 Flood Door 4.6.
Verify LPI decay heat removal is in progress.
RNO: GO TO Step 4.8 4.8.
Dispatch an operator to position the waterbox discharge valve switches (T-3, East of condenser catwalk):
1CCW-20 (iAi) switch to HAND 1CCW-20 (iAi) switch to CLOSE 1 CCW-2i (1 A2) switch to HAND 1CCW-2i (iA2) switch to CLOSE 1CCW-22 (1B1) switch to HAND 1CCW-22 (iBi) switch to CLOSE 1 CCW-23 (1 B2) switch to HAND 1 CCW-23 (1 B2) switch to CLOSE 1 CCW-24 (1 Ci) switch to HAND 1CCW-24 (iCi) switch to CLOSE 1 CCW-25 (102) switch to HAND 1 CCW-25 (1 C2) switch to CLOSE This event is complete when Close 1/Close 2 pushbuttons have been depressed, control of RCS cooldown has been demonstrated, and Pzr level is being maintained >100 or as directed by the lead examiner Page 31 of 41
Appendix D Scenario Outline Form ES-D-2 Page 1 of 8 NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See below.
ENCLOSURE 5.5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.
1.
Utilize the following as necessary to maintain IF 1 HP-26 will NOT open, desired Pzr level:
THEN throffle 1 HP-41 0 to maintain
- 1A HPI Pump desired Pzr level.
- 1BHPI Pump
- 1HP-7 1 HP-i 20 setpoint or valve demand
- 1HP-5 2.
IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.
3.
IAAT it is desired to secure makeup to
- LDST, THEN secure makeup from 1A BHUT.
4.
IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:
A. Open:
1CS-26 1CS-41 B. Position 1HP-l4to BLEED.
C. Notify SRO.
5.
IAAT letdown bleed is NO longer desired, THEN position 1HP-l4to NORMAL.
Page 32 of 41
Appendix D Scenario Outline Form ES-D-2 ENCLOSURE 5.5 (cont.)
Page 2 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOTOBTAINED 6.
IAAT 1C HPI PUMP is required, THEN perform Steps 7-9.
7.
Open:
- 1HP-24
- 1HP-25 GOTO Step 10.
IF both BWST suction valves (1 HP-24 and 1 HP-25) are closed, THEN perform the following:
A.
Start 1A LPI PUMP.
B.
Start lB LPI PUMP.
C. Open:
1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D.
IF two LPI Pumps are running jjjy to provide HPI pump suction, THEN secure one LPI pump.
E.
Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Pm, N end).
F.
GO TO Step 8.
2._ IF only one BWST suction valve (1 HP-24 or 1 HP-25) is open, THEN perform the following:
A.
IF three HPI pumps are operating, THEN secure 1 B HPI PUMP.
B.
IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C.
GO TO Step 9.
Page 33 of 41
Appendix D Scenario Outline Form ES-D-2 ENCLOSURE 5.5 (cont.)
Page3of8 I
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8.
Start 10 HPI PUMP.
IF at least two HPI pumps are operating, THEN throttle 1 HP-409 to maintain desired Pzr level.
9.
Throttle the following as required to 1.
IF at least two HPI pumps are operating, maintain desired Pzr level:
AND 1 HP-26 will NOT open, 1 HP 26 THEN throttle 1 HP-41 0 to maintain desired Pzr level.
1HP-27 2.
IF 1A HPI PUMP and lB HPI PUMP are operating, AND 1 HP-27 will NOT open, THEN throttle 1 HP-409 to maintain desired Pzr level.
Page 34 of 41
Appendix D Scenario Outline Form ES-D-2 ENCLOSURE 5.5 (cant.)
Page 4 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOTOBTAINED 10.
IAAT LDST vel CANNOT be maintained, THEN perform Step 11.
11.
Perform the following:
- Open 1 HP-24.
- Open 1 HP-25.
- Close 1HP-16.
GO TO Step 12.
1
. IF both BWST suction valves (1 HP-24 and 1 HP-25) are closed, THEN perform the following:
A.
Start 1A LPI PUMP.
B.
Start lB LPI PUMP.
C. Open:
1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D.
IF two LPI Pumps are running Qfljy to provide HPI pump suction, THEN secure one LPI pump.
E.
Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Pm, N end).
F.
GOTO Step 12.
2._ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure lB HPI PUMP.
Page 35 of 41
Appendix D Scenario Outline Form ES-D-2 ENCLOSURE 5.5 (cont.)
Page 5 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
12.
IAAT additional makeup flow to LDST is
- desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-i -1 07, Unit 1 RC Bleed Transfer Pump Rm.).
13.
IAAT two Letdown Filters are desired, THEN perform the following:
Open 1HP-17.
Open 1HP-18 14 IAAT aN of the following exist:
Letdown isolated LPSW available Letdown restoration desired TH EN p orm Steps
.- 3
{4 15.
Open:
100-7 100-8 16.
Ensure only one CC pump running.
17.
Place the non-running CC pump in AUTO.
18.
Verify both are open:
1._ Notify CR SRO that letdown CANNOT be restored due to inability to restart the CC system.
2._ GO TO Step 34.
1._ IF 1 HP-i is closed due to 1 HP-3 failing to
- close, THEN GO TO Step 20.
GOTO Step 34.
1HP-i 1HP-2 19.
GOTO Step 22.
- close, THEN GO TO Step 20.
2._ IF 1 HP-2 is closed due to 1 HP-4 failing to NOTE Verification of leakage requires visual observation of East Penetration Room.
20.
Verify letdown line leak in East GO TO Step 22.
Penetration Room has occurred.
21.
GOTOStep34.
Page 36 of 41
Appendix D Scenario Outline Form ES-D-2 ENCLOSURE 5.5 (cont.)
Page 6 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22.
Monitor for unexpected conditions while restoring letdown.
23.
Verify jq letdown coolers to be placed in service.
24.
Open:
Verify at least one letdown cooler is aligned.
26.
Close 1HP-6.
27.
28.
Close 1 HP-7.
Verify letdown temperature < 125°F.
i._ IF 1A letdown cooler is to be placed in
- service, THEN open:
1HP-1 1HP-3 2._ IF 1 B letdown cooler is to be placed in
- service, THEN open:
1HP-2 1HP-4 3._ GO TO Step 25.
Perform the following:
A.
Notify CR SRO of problem.
B. _GOTOStep34.
1._ Open 1HP-13.
- 2. Close:
1HP-8 1HP-9&11 3._ IF y deborating IX is in service, THEN perform the following:
A.
Select 1 HP-i 4 to NORMAL.
B.
Close 1HP-i6.
4._ Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Page 37 of 41
ENCLOSURE 5.5 (cont.)
Page 7 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29.
Open 1HP-5.
30.
Adjust 1 HP-7 for 20 gpm letdown.
31.
WHEN letdown temperature is
< 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.
32.
Open 1 HP-6.
33.
Adjust 1 HP-7 to control desired letdown flow.
NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.
34.
IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).
35.
IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
A.
Obtain SRO concurrence to reduce running HPI pumps.
B.
Secure the desired HPI pumps.
C.
Place secured HPI pump switch in AUTO, if desired.
36.
IAAT aM the following conditions exist:
Makeup from BWST NOT required LDST level > 55 AM control rods inserted Cooldown Plateau NOT being used THEN close:
1HP-24 1HP-25 Appendix D Scenario Outline Form ES-D-2 Page 38 of 41
Appendix D Scenario Outline Form ES-D-2 ENCLOSURE 5.5 (cont.)
Page 8 of 8 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37.
Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 39.
been closed to provide additional makeup flow to LDST.
38.
WHEN 1 CS-48 (1 A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:
A.
Stop 1A BLEED TRANSFER PUMP.
B.
Locally position 1CS-48 (1A BHUT Recirc) one turn open (A 1-107, Unit 1 PC Bleed Transfer Pump Pm.).
C.
Close 1 CS-46.
D.
Start 1A BLEED TRANSFER PUMP.
E.
Locally throttle 1 CS-48 (1A BHUT Recirc) to obtain 90
- 1 10 psig discharge pressure.
F.
Stop 1A BLEED TRANSFER PUMP.
39.
Verify two Letdown Filters in service, GO TO Step 41.
AND only one Letdown filter is desired.
40.
Perform one of the following:
Place 1 HP-i 7 switch to CLOSE.
e Place 1 HP-i 8 switch to CLOSE.
41.
WHEN directed by CR SPO, THEN EXIT this enclosure.
- .. END.
Page 39 of 41
Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS CT-8, Restore Power from CT-5 Standby BUS 1 or 2 Feeder (Page 25)
TCA #4, Press Close 1/Close 2 wIthin 11.3 minutes of receiving TB Emergency High Level alarm. (Page 31)
Page 40 of 41
Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 SAFETY: Take a Minute UNIT 0 (OSM)
SSF Operable: No I) KHUs Operable: Ui
- OH, U2
- UG 1 LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: 3%
Mode: 1 Mode: 1 Gross MWE: N/A 100% Power 100% Power RCS Leakage: 0.024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration Required TS/SLC #
Date/Time Date/Time Shift Turnover Items (CR SRO)
Primary Tave=543°F Secondary 1SSH-1, 1SSH-3, 1SD-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.
1AS-35 throttled per Secondary Chemist to provide steam to E heaters for secondary 02 removal.
Swap CBPs to the 1A CBP running and lB HWP running using OP/i/Ni 106/002 C Enclosure 4.3.
Chemistry has been consulted and bypassing the Powdex is not desired..
Reactivity Management CR SRO)
RCS Boron 1756 R2 Reactivity management controls mb
Rod position Gp 7 5% WD established in the Control Room per SOMP pp 01-02 Human Performance Emphasis (OSM)
Procedure Use and Adherence