ML17142A448

2016 Monticello Nuclear Generating Plant Initial License Examination Outline ES-D-1

ML17142A448
Person / Time
Site:	Monticello
Issue date:	05/18/2017
From:	David Reeser NRC/RGN-III/DRS/OLB
To:	Nuclear Management Co
Shared Package
ML15274A421	List: ML17142A436 ML17142A437 ML17142A439 ML17142A442 ML17142A446 ML17142A448 ML17156A029
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Download: ML17142A448 (4)

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Appendix D Scenario Outline Form ES-D-1 Facility:

MONTICELLO Scenario No.:

1 Op-Test No.:

2016-301 Examiners:

Operators:

Initial Conditions: 100% Power; There are 4 control rods with "slow" scram times (38-47, 42-43, 46-39, and 50-31); HPCI is in PTL due to inadvertent initiation on the previous shift.

Turnover: 12 EDG Monthly Surveillance test in progress, ready to unload.

Event No. Malf. No. Event Type* Event Description 1 N (BOP) EDG 1 2 Shutdown at completion of Surveillance Test 2 C (BOP) Main Seal Oil Pump (MSOP) trip with Emergency Seal Oil Pump (ESOP) Auto Start Failure.

3 TS (SRO) #10 Transformer Lockout/Loss of 1AR 4 I (OATC) CRD Flow Control Valve

- Fails Open; One Control Rod will partially insert; Place standby FCV in service.

Alarm 5-A-27 (ROD DRIFT)

Ops Man B.01.03

-05 Ops Man C.4

-B.01.03.C 5 R (SRO, OATC) Reduce power by 2-3% with Recirc Flow per Nuclear Engineer Instructions to restore control rod to original position

. 6 C (OATC) TS (SRO) Uncoupled Control Rod (TS 3.1.3; TS 3.1.6

) ARP 5-A-11 (ROD OVERTRAVEL)

Ops Man B.01.03

-05 Ops Man B.05.05

-05 7 M (CREW) Loss of 345KV Lockout of 345KV (Loss of 2R)

Loss of RR Pumps and Circ Water Pumps requiring SCRAM C (SRO, OATC)

RPS Failure; ARI Inserts control rods

[CT1] 8 M (BOP) HPCI Steam Line Break in Reactor Building (Auto Isolation Failure; Approximately 5 minutes post SCRAM)

[CT2] 9 M (CREW) Loss of 115KV with EDG 12 Auto Start Failure (approximately 10 minutes post SCRAM)

Lockout of 115KV Bus 1 (Loss of 1R)

Loss of Feedwater C (BOP) 12 EDG Auto Start Failure

[CT 3] C (BOP) 11 ESW Pump Auto Start Failure

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

MONTICELLO Scenario No.:

2 Op-Test No.:

2016-301 Examiners:

Operators:

Initial Conditions: Plant Start

-up in progress (38% power) following a forced outage. There are 4 control rods with "slow" scram times (38-47, 42-43, 46-39, and 50

-31)

Turnover: Continue the start

-up, raise power to 40% using control rod withdrawal stating at step 30 of ASR5. At 40%, place 12 Condensate Pump in service. Once 12 Condensate Pump is in service, raise power to 45% using recirculation pumps

. Event No. Malf. No. Event Type*

Event Description 1 R (OATC) Raise Power with Control Rods I (OATC) Stuck control rod; raise drive pressure. 2 N (BOP) Place second Condensate pump in service.

3 R (OATC) Raise power from 40% to 45% with Recirc Flow C (OATC) TS (SRO) 12 Recirc Pump speed control failure 4 C (BOP) TS (SRO) Loss of MCC

-131 5 C (BOP) SRV 'D' seat leakage ARP 3-A-9 (AUTO BLOWDOWN RELIEF VLV LEAKING) C.4-B.03.03.B (RELIEF VALVE LEAKING) 6 C (BOP) SRV 'D' fails open ARP 5-A-46 (SRV OPEN)

C.4-B.03.03.A (STUCK OPEN RELIEF VALVE

) M (CREW) Efforts to close SRV 'D' will be unsuccessful requiring a Manual Reactor SCRAM [CT1 - Manual Reactor SCRAM prior to Torus Temp of 110F] 7 M (CREW) Main Steam Line break inside Containment C (BOP) LPCI Initiation Bypass fails for 1 st Division of Drywell Spray/Alignment to 2 nd Division will be successful

. [CT2 - Emergency Depressurization (DW Temp/Pressure)]

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

MONTICELLO Scenario No.:

3 Op-Test No.:

2016-301 Examiners:

Operators:

Initial Conditions: 100% Power; There are 4 control rods with "slow" scram times (38-47, 42-43, 46-39, and 50-31); 1AR Transformer OOS

.

Turnover: OATC to perform Part A and B of 0010 (RX SCRAM Functional)

Event No. Malf. No. Event Type*

Event Description 1 03-S37-01 03-S37-02 N (OATC) Perform 0010 (Reactor SCRAM Functional) -- Manual SCRAM Only 2 RW01 & C-05-A03 I (OATC) TS (SRO) RWM Self-Test Failure 3 HP01 C (BOP) TS (SRO) HPCI Inadvertent Initiation/Reactor Power > 100%

4 MC03 & MC04B C (BOP) R (OATC) SJAE Failure resulting in degrading vacuum and power reduction.

5 ED12 M (Crew) Feedwater Line Break inside the Drywell (trip of both FW Pumps and Reactor SCRAM

) 6 RC01 C (OATC) RCIC Auto Initiation Failure 7 C (Crew) RCIC injection is in

-effective; Restore HPCI [CT - RCIC injection is in

-effective due since RCIC is aligned to the same line as where the feed line break is located. Failure to restore HPCI will cause RPV level to drop below TAF.]

CONTIGENCY

- If crew fails to restore HPCI and RPV drops to TAF, then BEFORE RPV level drops to

-149" Emergency Depressurize (Blowdown) and restore RPV level above TAF using Low Pressure ECCS.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

MONTICELLO Scenario No.:

4 (SPARE) Op-Test No.:

2016-301 Examiners:

Operators:

Initial Conditions: 100% Power; There are 4 control rods with "slow" scram times (38-47, 42-43, 46-39, and 50-31); HPCI OOS.

Turnover: Restore HPCI to service

. Event No. Malf. No. Event Type*

Event Description 1 N (SRO, BOP) Return HPCI to Standby 2 C-05-B20 I (OATC) TS (SRO) Condenser Vacuum Switch Failure with failure of 1/2 SCRAM to actuate (TS LCO 3.3.1.1) 3 AP07 C (BOP) TS (SRO) ADS Timer Failure (TS LCO 3.3.5.1 & 3.5.1) 4 04-A2S70-04 C (BOP) TS (SRO) R (OATC) EPR Fails High with MPR Locked necessitating a power reduction.

5 NI14C I/C (OATC)

TS (SRO) APRM Upscale 6 04-A2S59-02 M MPR lowers pressure, requiring SCRAM 7 CH22A/B M Torus water leak requiring Emergency Depressurization 8 AP08D C (BOP) Failure of one ADS Valve to Open.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor