ML17158B455
| ML17158B455 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/03/2017 |
| From: | David Reeser NRC/RGN-III/DRS/OLB |
| To: | FirstEnergy Nuclear Operating Co |
| Shared Package | |
| ML16242A222 | List: |
| References | |
| Download: ML17158B455 (8) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 1 - 100% Op-Test No.: 2017-1 Examiners: Operators: (SRO)
(ATC)
(BOP)
Initial Conditions: Plant is at 100% power. Motor Feed Pump and CRD B pump are tagged out due to oil leaks. eSOMS Narrative Log is down. Risk is Green and the Grid is Normal.
Turnover: Start HPCS ESW pump for vibration testing. Page Jeff Reeves when HPCS ESW is running. Personnel have been briefed and are on station to support field activities. When contacted by SCC lower Rx power to 93% per the Reactivity Plan and IOI-3 Power Maneuvering, for upcoming surveillances. Make any Narrative Log entries on your note pads.
Event Malf. Event Event No. No. Type* Description 1 N-(BOP) Start HPCS ESW for vibration testing.
2 R-(ATC) 6A Feedwater Heater isolation.
Lower Rx power 96%
3 I-(ATC) APRM A fails upscale - lockup FCVs I-(SRO) TS 3.3.1.1 & ORM 6.2.1 4 C-(BOP) HPCS ESW pump trips.
C-(SRO) TS 3.7.1 & 3.8.1 5 C-(ATC) Earthquake <OBE &Trip RFPT A on high vibrations 6 M-(Crew) Scram Rx on lowering RPV level. Enter EOP-1 C-(BOP) RCIC fails to auto start at L2 7 M(Crew) Earthquake aftershock >OBE Loss of RPV level - enter E0P-4-4 C-(BOP) ADS SRV B21-F041E fails to open on ED
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile
Narrative Summary - Initial Scenario 1 100%
Event
- 2. Feedwater heater 6A drain valves fail causing a high heater water level resulting in isolation of extraction steam to the FW heater. The SRO will enter ONI-N36. The ATC will immediately lower Rx power to 96% with Recirc Flow and maintain Rx power 96% as FW temperature decreases causing Rx power to increase. The SRO will also enter ONI-C51 for the unexpected Rx power change.
- 3. APRM A fails upscale requiring the ATC to lockup Recirc Flow Control Valves. APRM A will them be bypassed. SRO evaluates T.S 3.3.1.1 & ORM 6.2.1
- 4. The HPCS ESW pump will trip due to a heat damaged control power transformer in the MCC bucket. The SRO enters T.S. 3.7.1 & 3.8.1. The SRO will direct the BOP to place Div. 3 diesel generator and HPCS system in secured status.
- 5. An earthquake (<OBE) causes lowering flow on RFPT B and high vibrations on RFPT A. The vibration level exceeds the ARI setpoint for the operator to trip the pump. If the operator fails to trip the RFPT, it will trip after several minutes resulting in a Recirc FCV runback and a slow downward trend on RPV water level as flow continues to degrade on RFPT B.
- 6. As RPV water level approaches L3, the ATC will scram the Rx. If the crew allows RPV water level to go <L3, RPS will not automatically scram the Rx. However, if the crew allows RPV water level to lower to L2, ARI will insert rods. If RCIC has not been manually initiated before RPV level lowers to L2, RCIC will not auto start. The operator must manually initiate RCIC to recover RPV level.
- 7. After RCIC has been started and is recovering RPV level, a second and larger earthquake (>OBE) will occur. This will result in a sequential loss of all RPV level indication. This will require the crew to Emergency Depressurize the Rx and flood the RPV up to the Main Steam Lines. While performing ED, SRV B21-F041E will fail to open, requiring operator to open additional SRV.
EOPs:
ARI for APRM A ONI-N36 ONI-C51 ONI-C34 ONI-D51 Critical tasks:
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 2 - 90% Op-Test No.: 2017-1 Examiners: Operators: (SRO)
(ATC)
(BOP)
Initial Conditions: Last shift, power was reduced to 90% IAW IOI-3, Attachment 3 per SCC request. Service Water Pump A is out of service for planned maintenance. eSOMS Narrative Log is down.
Turnover: Planned activities; raise reactor power to 100% when directed by SCC; shift Service Water Pumps from C to D, an NLO has been briefed and is on station. Make any Narrative Log entries on your note pads. Risk is Green and the Grid is Normal.
Event Malf. Event Event No. No. Type* Description 1 N-(BOP) Shift Service Water Pumps from C to D running N-(SRO) 2 R-(ATC) Raise Rx power using Rx Recirc flow R-(SRO) 3 C-(SRO) SLC B Pump Suction Valve blown fuse, TS 3.1.7 4 I-(BOP) RCIS lock-up I-(SRO) ORM 6.1.2 5 C-(ATC) RFBP C pressure degrades 6 M-(Crew) Loss of IA in DW, Scram on Inboard MSIVs closure, EOP-1 7 M-(crew) ATWS >4% EOP-01A & EOP-02 C-(BOP) ESW A fails auto start, manually start ESW A
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile
Narrative Summary - Initial Scenario 2 90%
Event
- 1. The BOP shifts Service Water Pumps from C to D running.
- 2. The ATC will raise Rx power to 100% IAW the reactivity plan and IOI-3. The SRO will provide reactivity oversight.
- 3. Standby Liquid Control B pump suction valve will lose power due blown main-line fuses in the MCC bucket. The SRO enters T.S. 3.1.7.
- 4. RC&IS will become inoperable by locking up on a control rod. The crew will enter ONI-C11-1, Inability to Move Control Rods and will need to reset RC&IS IAW SOI-C11(RC&IS). The SRO will evaluate Tech Specs and ORM and enter ORM 6.1.2.
- 5. The Reactor Feed Booster Pump C discharge pressure will begin to degrade but the standby RFBP will not auto start. The operator must manually start the standby RFBP.
- 6. A loss of Instrument Air to the Drywell will result in the inboard MSIVs shutting. This will result in an automatic Rx scram and an ATWS >4%. This will challenge HCL. The US will enter EOP-1 and transition to EOP-1A. Also enter EOP-2. The crew will need to inhibit ADS, Terminate injection into the RPV, manually insert control rods, and maintain margin to HCL. Emergency Service Water pump A will not auto start on T&P and must be manually started.
EOPs:
EOP-1, EOP-1A & EOP-2 ABNORMALs:
ARI for RC&IS.
ARI for RFBP ONI-C11-1 Critical tasks:
- 1. Inhibit ADS.
- 2. Insert Control Rods
- 4. Maintain RPV pressure/Suppression Pool temperature below HCL
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 3 - 40% Op-Test No.: 2017-1 Examiners: Operators: (SRO)
(ATC)
(BOP)
Initial Conditions: Plant S/D in progress due to leaking SRV following an earthquake. RWCU F/D A is in Hold awaiting backwash. ESW B and ECC B running to support RHR run. In IOI-3, Step 4.7.30. I&C Tech has just completed adjusting APRM gains. eSOMS Narrative Log is down.
Turnover: Place RHR B in SP cooling then, transfer Recirc Pumps to slow speed and continue with plant S/D. Make your Narrative Log entries on your note pads.
Event Malf. Event Event No. No. Type* Description 1 N-(BOP) Place RHR B in Suppression Pool Cooling N-(SRO) TS 3.5.1 2 I-(SRO) LLS Instrument fails high on 1 channel TS 3.3.6.4 3 C-(BOP) TBCC pump trip C-(SRO) 4 C-(BOP) ECC B Temperature Controller fails in AUTO C-(SRO) TS 3.7.10 5 C-(ATC) RWCU Pump B Gland Seal Temp High C-(SRO) 6 R-(ATC) Shift Rx Recirc pumps from Fast to Slow speed R-(SRO) 7 M-(Crew) Multiple SRVs fail open. Enter EOP-2 8 M-(Crew) Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 9 C-(ATC) Feed pump turbine fails on scram - Start Motor Feed Pump
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile
Narrative Summary - Initial Scenario 3 40%
Event
- 2. A Low-Low-Set instrument will fail high (1 channel). The SRO will enter Tech Spec 3.3.6.4.
- 3. One of the running TBCC pumps will trip. The SRO enters ONI-P44, Loss of TBCC. The BOP will start an additional TBCC pump.
- 4. Nuclear Closed Cooling flow will degrade to RWCU pump B resulting in a high gland seal temperature. The ATC will shutdown the B RWCU pump IAW SOI-G33 and adjust RWCU inlet flow.
- 5. Emergency Closed Cooling temperature controller will fail in AUTO. The BOP will take manual control of ECC B temperature controller and restore ECC B temperature. The SRO will enter TS 3.7.10 if ECC B temperature exceeds 95°F.
- 7. Two SRVs fail open. The SRO enters ONI-B21-1, SRV Inadvertent Opening/Stuck Open and EOP-2, Primary Containment Control. The SRO will direct scramming the Rx prior to reaching 110°F in the Suppression Pool.
- 8. The Rx scram will result in an ATWS<4% and a steam leak in the Drywell with bypass leakage into Containment. The SRO will enter ONI-C71-1, Rx Scram and re-enter EOP-2 on high DW temperature. Control rods will need to be manually inserted in order to depressurize the Rx and stop the steam leak.
- 9. Feedwater is lost on the scram. Motor Feed Pump must be manually initiated in order to recover RPV level.
EOPs:
EOP-2 ABNORMALs:
ARI for RWCU ARI for ECC B ONI-P44 ONI-B21-1 Critical tasks:
- 2. Insert Control Rods
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 4 - 15% Op-Test No.: 2017-1 Examiners: Operators: (SRO)
(ATC)
(BOP)
Initial Conditions: Plant S/U in progress; Main turbine @ 1800 rpm. Ready for Main Generator synch per IOI-3, Step 4.3.35. RFPT A is out of service; installing insulation.
TBCC Pump C is out of service for bearing replacement. eSOMS Narrative Log is down.
Turnover: Planned activities; synchronize to the grid, raise reactor power per IOI-3. Reactor Engineering concurs with gang rod withdrawal where not prohibited. Make any Narrative Log entries on your note pads. Risk is Green and the Grid is Normal.
Event Malf. Event Event No. No. Type* Description 1 R-(ATC) Raise Reactor power to establish approximately 2 1/2 Bypass Valves open.
R-(SRO) 2 N-(BOP) Synchronize the Main Generator to the grid N-(BOP) 3 I-(SRO) Control Room Ventilation Rad Monitor sample pump fails; TS 3.3.7.1 4 C-(ATC) High vibration main turbine bearing manually trip turbine, C-(SRO) 5 C-(ATC) ONI-N32 - Main Turbine Trip, generator output breaker S610 fails to trip.
C-(SRO) 6 C-(BOP) LPCS Room sump alarm, enter EOP-3 ; SP Level <17.8 feet, enter EOP-2; C-(SRO) Closes LPCS Suction Valve prior to SP lowering < 14.25 feet 7 M-(Crew) TB/HB Vent Hi Rad, Turbine Area Temperature High C-(BOP) MSIVs fail to close
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile
Narrative Summary - Initial Scenario 4 15%
Event
- 1. The ATC increases Rx power by control rod withdrawal to obtain 2 and 1/2 bypass valves open. The SRO provides reactivity oversight.
- 2. The BOP will synchronize the main generator to the grid.
- 3. The Control Room radiation monitor sample pump fails. The SRO evaluates Tech Specs - 3.3.7.1.
- 4. Vibration develops on main turbine bearing #5. The auto trip of the main turbine fails requiring the ATC to manually trip the main turbine.
- 5. The crew enters ONI-N32 for trip of the main turbine. One of the generator output breakers fail to open requiring the ATC to manually open the generator output breaker.
- 6. A Suppression Pool leak in the LPCS pump room requires entry into EOP-3. As suppression pool level lowers, EOP-2 is entered. The leak is stopped by shutting the LPCS suction valve.
- 7. A steam leak in the Turbine Building at the Bypass Valve manifold results in turbine building high temperature and high radiation level. ONI-N11 is entered. The MSIVs receive an isolation signal, but only one line isolates. This requires the ATC to scram the Rx and the BOP to manually isolate all main steam lines to stop the radiation release.
EOPs:
ARI for Main Turbine vibration ONI-N32 ONI-N11 Critical tasks:
- 1. Isolate Suppression Pool Leak.
- 2. Isolate main steam lines