ML17142A448
| 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: |
| References | |
| Download: ML17142A448 (4) | |
Text
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 12 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
[CT3]
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 110°F]
7 M (CREW)
Main Steam Line break inside Containment C (BOP)
LPCI Initiation Bypass fails for 1st Division of Drywell Spray/Alignment to 2nd 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
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
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