ML022460364

Final - Section C Operating

ML022460364
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	08/15/2002
From:	Gosekamp M Entergy Nuclear Vermont Yankee
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-271/02301, ES-D-1 50-271/02301
Download: ML022460364 (10)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: Vermont Yankee Scenario No.: I Op-Test No.: I Examiners: Operators:

Initial Conditions: Reactor power - 85%, all equipment is operable.

Turnover: A reactor downpower is underway, utilizing OP-0105 Phase 5A step 6.b., for a rod pattern exchange. Reactor power is to be reduced to 80% using recirc. Reactor Engineering is to be notified at 80% power and will provide further guidance at that time.

Event Malf. Event Event No. No. Type* Description 1- N-SRO Continue power reduction R-SRO 2 NM05A I-SRO APRM fails upscale 3 ED03A C-SRO Loss of Bus 1 due to bus fault R-SRO 4 RR01A M-SRO Small break LOCA 5 FW08C M-SRO Scram, Loss of FW,HPCI failure, RCIC flow controller failure HP01 C-SRO RC03 6 RC01 M-SRO RCIC trip, RPV-ED on low level kry)ormal, tm)eactlvity, (I)nstrument, (C)omponent, (M)ajor

Objectives: To evaluate the applicants' ability to reduce reactor power in accordance with plant procedures; to respond to an APRM failure with TS implications; to respond to a loss of bus one; to respond to a small break LOCA with a loss of feedwater and HPCI failure controlling water level with RCIC; to implement EOP 1, RPV Control and EOP-3, Containment Control, to RPV-ED following RCIC trip with water level below TAF.

SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up: I.C. No.: 9 Discretionary Distractor Malfunctions/RFs/IOs:

1. Reduce power to 85% using recirc, check recirc lube oil temperatures rfSW_58

2. Verify Master Recirc controller in operation No MF/RF/IO # Severity Ramp REM # Activation Description 1 HP01 - PI HPCI Failure 2 NM05A 100 1 Following "A7 APRM upscale failure initiation of power reduction 3 ED03A - 2 Following Loss of Bus 1 due to bus bypass of fault APRM 4 RR01A 0.06 600 s 3 Following exit of Recirc Break buffer and exclusion regions of P-F 5 FW08C - 4 Immediately "C" RFP trip following scram 6 RR01A 0.11 120s 4 Recirc Break 7 RC03 0 4 RCIC Controller fails downscale 8 RC01 - 5 Following DW RCIC trip spray initiation 9 RR01A 0.6 120s 5 Recirc Break Additional Instructions:

1. The examination team will determine when each event is to be inserted, and when to FREEZE, and will inform the simulator console operator;

2. When AO is directed to maintain recirc lube oil temperatures, insert rfSW_58

3. If RE is contacted for additional guidance for downpower, inform control room RE will be available with the rod pattern adjustment.

4. When I&C is contacted to investigate the failed APRM, I&C will initiate troubleshooting efforts. The APRM can be bypassed prior to troubleshooting.

5. When electrical maintenance is contacted to investigate the loss of bus 1, there are indications of a fault on bus 1. Further troubleshooting is required. If requested, bus 6 and 7 cross c6nnect is not recommended. A detailed troubleshooting plan is being developed.

6. When requested to investigate the "C" RFP trip, report an instantaneous overcurrent trip on all three phases on the breaker.

7. When requested to investigate the failure of HPCI to start, report no apparent cause is evident. Further troubleshooting is required.

8. When requested to investigate the failure of the RCIC controller, report no apparent cause is evident. Further troubleshooting is required.

9. When requested to investigate the trip of RCIC, report no apparent cause is evident.

Further troubleshooting is required.

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 1 Page 4 of 10 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior SCRO Brief crew on power reduction Direct continued power reduction IAW OP 0105 Phase 5 Step A.6.b.

CRO Reduce reactor power using recirc at directed rate Direct AOs to monitor recirc lube oil temperatures SCRO Contact RE at 80% power for additional guidance on power reduction and control rod pattern exchange L

___ I______ I__________________________

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page 5 of 10 Event

Description:

APRM Failure Time Position Applicant's Actions or Behavior CRO Recognize and report APRM failure Verifies Alarm Response Procedures (5-M-1), reports to SCRO

• Verify Tech Spec actions

• Contact I&C

• If INOP bypass failed APRM Reports status of other APRM readings and power status SCRO Verify status of other operable APRMs and their readings Direct CRO/ACRO to contact I&C to investigate Verify Tech Specs (Table 3.1.1-scram and Table 3.2.5-rod block)

Log APRM inoperable status in LCO log Direct CRO to bypass failed APRM Direct CRO to reset half scram CRO Bypass failed APRM Reset half scram and verify half scram reset (standing order tag)

I I

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page 6 of 10 Event

Description:

Loss of Bus 1 Time Position Applicant's Actions or Behavior ACRO Recognize and report loss of Bus 1 SCRO Enter and direct actions IAW ON 3169, Loss of Bus 1 Direct auxiliary oil pump placed in PTL Enter and direct actions in OT3118, Recirc Direct recirc discharge valve RV-53A shut Verify "B" recirc speed <70%

Verify power-to-flow status Enter and direct actions in OT 3117, Direct operators to monitor for instabilities Direct rod insertion to exit buffer and exclusion regions Enter and direct actions in ON 3171, Loss of Bus 3 Verify "B" D/G status SE Report entry into exclusion region of power-to-flow map Initiate SOLOMON program to evaluate decay ratios Report exit from buffer and exclusion regions following power reduction CRO Report RPV water level has recovered on the "C" RFP, "A" and "B" have tripped on loss of power Reports trip of"A" recirc Shuts RV-53A as directed Reports "B" recirc speed Monitors for reactor instability while operating in exclusion region Inserts control rod to exit buffer and exclusion region ACRO Backup Group III isolation Report power is unavailable to the "A" AOG train SCRO Direct AOG restored using "B" AOG train ACRO Restore AOG using "B" AOG train L___ I _____ I I I___ _ __ I__

I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 4 Page 7 of 10 Event

Description:

Small Break LOCA Time Position Applicant's Actions or Behavior CRO/ACRO/SE Recognize and report rising DW pressure SCRO Enter and direct actions IAW OT 3111, "High Drywell Pressure" Direct power reduction Transfer house loads (bus 2 only)

Maximize DW cooling Manual Scram Direct Manual Scram per OT-3 100 ACRO Transfer house loads (bus 2 only)

Maximize DW cooling CRO Insert scram SCRO Enter and direct actions IAW EOP-1 Direct verification of Table A initiations and isolations Direct RPV water level control 127-177 using feedwater Direct RPV pressure control 800-1000 psig using TBVs Shift RPV pressure control to SRVs/RCIC (Aux Oil pump unavailable for TBV operation following turbine coastdown)

Enter and direct actions IAW EOP-3 Direct restart of all available RRUs Direct torus sprays prior to 10 psig torus pressure Spray the DW when torus pressure is greater then 10 psig Verify RRUs off, Recirc secured, Verify DWSIL Crew Critical When torus pressure exceeds the suppression chamber spray initiation Task pressure, initiate drywell containment spray while in the safe region of the drywell spray initiation limit Standard:

Spray the drywell within 10 minutes of exceeding 10 psig torus pressure and

_RPV level is not an overriding priority CRO Maintain RPV water level 127-177" using feedwater, perform post scram level control IAW DP-0 166 Maintain RPV pressure 800-1000 psig using TBVs/SRVs/RCIC

Op Test No.: 1 Scenario No.: 1 Event No.: 4 Page 8 of 10 Event

Description:

Small Break LOCA Time Position Applicant's Actions or Behavior ACRO Restart DW RRUs Initiate torus sprays Initiate DW sprays

Operator Actions ES -D -2 Op Test No.: I Scenario No.: 1 Event No.: 5 Page 9 of 10 Event

Description:

Loss of High Pressure Injection (HPCI/Feedwater), RCIC controller failure Time Position Applicant's Actions or Behavior ACRO Recognize and report the failure of HPCI to automatically initiate on high DW pressure signal CRO Recognize the loss of FW on "C" RFP trip (A & B RFP powered from Bus 1)

SCRO Direct RPV water level control 127-177 using Table C systems CRD - Maximize flow OP 2111 RCIC- OP 2121 CRO Maximize injection using CRD OP 2111 ACRO Inject with RCIC using mini procedure Report RCIC failed to control in automatic control SCRO Direct ACRO to control RCIC using manual control ACRO Report RPV water level and trend SCRO Direct maintenance to investigate the HPCI failure, "C" RFP trip, and RCIC controller failure

ES-D-2 Operator Actions Event No.: 6 Page 10 of 10 Op TestNo.: 1 Scenario No.: 1 Event

Description:

RCIC Tri, RPV-ED Time Position Applicant's Actions or Behavior ACRO Recognize and report RCIC trip ACRO/CRO Report RPV water level and trend Report low-low water level (+82.5")

Inhibit ADS as directed to +6 to 177 SCRO When RPV water level is < 127" expand RPV water level band Direct RPV water level control +6 to 177 inches Direct use of alternate systems Maximize CRD flow SBLC injection Direct ADS inhibited CRO/ACRO Report RPV water level and trend Report RPV water level at TAF (+6")

SCRO Lineup all available systems for injection Verify two systems are available With RPV water level < TAF, Enter EOP-5 RPV-ED than the shutoff head Crew Critical With the reactor shutdown and reactor pressure greater RPV level reaches -22 Task of the low pressure systems, initiate RPV-ED BEFORE inches Standard:

RPV level reaches -48 Initiate RPV-ED (begin opening valves) BEFORE inches.

Direct 4 SRV opened systems to 127-177" band Direct RPV water level recovery using low pressure ACRO Open 4 SRVs Recover RPV water level using low pressure system Report RPV water level and trend