ML24120A165
| ML24120A165 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-024, DPR-027) |
| Issue date: | 10/23/2023 |
| From: | NRC/RGN-III |
| To: | Point Beach |
| B. Bergeon | |
| References | |
| Download: ML24120A165 | |
Text
Scenario #:
Op. Test #:
Applicants/
Event No.
Malf.
No.
N BOP N
ATC C
ATC R
BOP R
SRO M
Crew C/MC BOP C
SRO C
ATC C
SRO 1-2 2-4 1-2 1-2 1
2 Form 3.3-1 Scenario Outline Facility:
Point Beach Nuclear Plant 1
Scenario Source:
Modified from 2019 Scenario 2 Examiners:
Operators:
Initial Conditions:
Reactor power is 75%
1W-3B, Control Rod Shroud Fan and 1P-29 TDAFW Pump is OOS Turnover:
P-32B Service Water pump has a small oil leak. After turnover Maintenance will be working P-32B, so start P-32F, and secure P-32B per 0-SOP-SW-107 Service Water Pump Operation.
Event Type*
Event Description 1
P-32B, SW pump oil leak, shift SW Pumps (ILT NRC 2019 3/1) 2 1TE-402B, CH 2 (White) T(Cold) Loop A Temp Sensor RTD fails HIGH (ILT NRC 2015 2/1) 3 1HX-1A, SG Tube Leak approximately 10 gpm IAW AOP-3 (ILT NRC 2019 2/2) 4 Rapid Power Reduction IAW AOP-17A (ILT NRC 2019 2/2) 5 SG Tube Leak increases requiring trip and becomes a Tube Rupture post trip (CT-20)
(ILT NRC 2019 2/6) 6 1AF-4074A and 1AF-4074B: 1P-53 AFP to 1HX-1A/B fail to automatically open (CT-04)
(New) 7 Spray valves fail causing use of the PORV to depressurize the RCS (ILT NRC 2019 2/8)
Termination Criteria:
- Critical Tasks have been evaluated
- At the discretion of the Lead Evaluator 2
2 1
1 N/A 2
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Critical Tasks:
CT-04: Establish AFW Flow to S/Gs.
CT-20: Depressurize RCS to E-3 SI Termination Criteria
- Events after EOP entry
- Abnormal events
- Major transients
- EOPs entered/requiring substantive actions
- Entry into a contingency EOP with substantive actions
- Preidentified CTs
Scenario #:
Op. Test #:
Applicants/
Event No.
Malf.
No.
N ATC N
BOP N
ATC C
BOP C
SRO R
ATC R
BOP R
SRO M
Crew C
ATC C
SRO C
BOP C
SRO 1-2 2-4 1-2 1-2 1
2 4B Rapid power reduction IAW AOP-17A (New)
Form 3.3-1 Scenario Outline Facility:
Point Beach Nuclear Plant 2
Scenario Source:
New Examiners:
Operators:
Initial Conditions:
Reactor power is 100%
1W-3B, Control Rod Shroud Fan is OOS Turnover:
Chemistry has requested that Operations fill the Unit 1 PRT per OP-4C Section 5.1 Event Type*
Event Description 1
Fill PRT approximately 2% per OP-4C (New) 2 Component Cooling Pump trip with failure to start standby pump AOP-9B (ILT NRC 2023 2/5) 3 1P-53 Critical control power failure (New) 4A Lowering Condenser Vacuum (ruptured boot) AOP-5A (New) 5 1HC-110, Boric Acid Flow Controller fails in auto during the down power (ILT NRC 2019 2/3) 6 Loss of Vacuum requiring Plant Trip / Reactor Trip Button Malfunction EOP-0 (CT-2)
(New / ILT NRC 2023 1/8) 7 Multiple (4) Stuck Rods Post Trip, requires boration (manual)
(ILT NRC 2021 1/6) 8 1P-29 Turbine Driven Auxiliary Feedwater Pump Trips on Overspeed (CT-43)
(New)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Critical Tasks:
CT-02: Manually trip the reactor prior to Step 4 of CSP-S.1 CT-43: Establish Feedwater flow to S/Gs before bleed and feed is required Termination Criteria:
- Critical Tasks have been evaluated
- EOP-0.1 Step 9
- At the discretion of the Lead Evaluator
- Events after EOP entry
- Abnormal events
- Major transients
- EOPs entered/requiring substantive actions
- Entry into a contingency EOP with substantive actions
- Preidentified CTs 2
2 1
1 1
2
Scenario #:
Op. Test #:
Applicants/
Event No.
Malf.
No.
I ATC I
BOP TS SRO N/R ATC N/R BOP N/R SRO C/MC ATC C
SRO C
Crew C/MC ATC C
SRO C
ATC C
BOP C
SRO 1-2 2-4 1-2 1-2 1
2 Form 3.3-1 Scenario Outline Facility:
Point Beach Nuclear Plant 3
Scenario Source:
New Examiners:
Operators:
Initial Conditions:
Reactor power is 60%
1W-3B, Control Rod Shroud Fan is OOS due to motor failure.
Turnover:
The crew is directed to single up feed trains and continue a normal down power from 60% in accordance with OP 3A Unit 1, Power Operation to Hot Standby Unit 1.
Event Type*
Event Description 1
1PT-485 Turbine First Stage Pressure Fails Low, Rods work in Manual AOP-6C (New) 2A/B (A) Single up Feed Trains and (B) Down Power using normal procedure (ILT NRC 2017 5/1-5/2) 3 1CV-200A Ltdn Orifice Outlet CV closes causing loss of letdown flow.
(ILT NRC 2021 4/1) 4 1X-03 transformer lockout (New) 5 Steam leak from A SG in containment and B SG Safety fails open post trip, depressurization BOTH SGs (CT-17) (CT-33)
(New) 6 Turbine Fails to Trip 7
Containment accident cooling unit 1W-1A1 fails to auto start (ILT NRC 2023 SPARE 5/7) 8 B SG Safety valve reseats after crew controls cooldown (CT-17)
(New)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Critical Tasks:
CT-17: Isolate faulted steam generator CT-33: Control AFW flow to minimize RCS cooldown Termination Criteria:
- Critical Tasks have been evaluated
- EOP-1 Step 1
- At the discretion of the Lead Evaluator
- Events after EOP entry
- Abnormal events
- Major transients
- EOPs entered/requiring substantive actions
- Entry into a contingency EOP with substantive actions
- Preidentified CTs 2
2 1
1 1
2
Scenario #:
Op. Test #:
Applicants/
Event No.
Malf.
No.
N ATC N
BOP N
ATC C
ATC R
BOP R
SRO M
Crew C/MC ATC C
SRO 1-2 2-4 1-2 1-2 1
2 Form 3.3-1 Scenario Outline Facility:
Point Beach Nuclear Plant 4
Scenario Source:
New Examiners:
Operators:
Initial Conditions:
Reactor power is 75%
1W-3B, Control Rod Shroud Fan is OOS due to motor failure.
1P-10A RHR Pump in pullout to support PMT on 1SI-852A Low Head Core Deluge Valve per IT-03.
Turnover:
The crew is directed to perform Stroke open test 1SI-852A Low Head SI Core Deluge IAW IT-03 Event Type*
Event Description 1
Stroke test 1SI-852A Low Head SI Core Deluge Valve (New)(P005.012.COT) 2 1NI-41 PR NI fails low causing outward rod motion (ILT NRC 2017 4/3) 3 1W-3A CRDM Shroud Fan trips requiring Rapid Power Reduction (ILT NRC 2017 5/5) 4 RCS Bypass loop approx 20 gpm leak (ILT NRC 2021 3/5) 5 SBLOCA (CT-16)
(ILT NRC 2021 3/5) 6 SI fails to automatically actuate (CT-6)
(ILT NRC 2021 4/7) 7 RCS Hot Leg Containment Isolation valve fails open (ILT NRC 2012 1/8)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Critical Tasks:
CT-06: Establish flow from at least one Charging/SI pump (high-head SI pump for LP plants)
CT-16: Manually trip RCPs Termination Criteria:
- Critical Tasks have been evaluated
- Step 14 of EOP-1, Loss of Reactor or Secondary Coolant
- At the discretion of the Lead Evaluator
- Events after EOP entry
- Abnormal events
- Major transients
- EOPs entered/requiring substantive actions
- Entry into a contingency EOP with substantive actions
- Preidentified CTs 2
2 1
1 NA 2