ML14211A287

Initial Exam 2014-301 Final Simulator Scenario No 4

ML14211A287
Person / Time
Site:	Browns Ferry
Issue date:	07/30/2014
From:	NRC/RGN-II/DRS/OLB
To:
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Download: ML14211A287 (56)

Text

NRC Scenario 4

( aci1ity: Browns Ferry NPP Scenario No.: NRC 4 Op-Test No.: 1404 Operators: SRO:______________________

ATC:_______________

BOP:________________

Initial Conditions: 80% power, RFPT 3B and A3 RHRSW Pumps are tagged out.

Turnover: Alternate Refuel and Reactor Zone Fans JAW 3-OI-30A and 30B. Raise power to 85% with flow and hold for RFPT 3B repairs.

Event Maif. No. Event Type* Event Description No.

N-BOP Alternate Refuel and Reactor Zone Fans lAW 3-OI-30A and 1 30B, Refuel damper 64-9 fails in mid position when Refuel Fans TS-SRO are in Off and is Open when Refuel Fans operating 2 Commence power increase with flow to 85%

R-SRO C-ATC 3 edlOb C-BOP Loss of 480V SD BD 3B

___ TS-SRO C-BOP 4 Batch File Stator Water Cooling Pump 3A trip C SRO 5 fw30a RFPT 3A Governor fails low 6 tcl0b EHC Pressure Transducer failure, with MSIV closure failure 7 Batch File M-ALL ATWS 8 Batch File M-ALL LOCA Loss of RPV Water Level 9 hpO7 C Loss of HPCI 120 VAC Power Supply

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

NRC Scenario 4 Critical Tasks Six CT 1 With reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS.

1. Safety Significance:

Precludes core damage due to an uncontrolled reactivity addition.

2. Cues:

Procedural compliance.

3. Measured by:

ADS logic inhibited prior to an automatic initiation unless all required injection systems are Terminated and Prevented.

4. Feedback:

RPV pressure trend.

RPV level trend.

ADS ADS LOGIC BUS A/B INHIBITED annunciator status.

CT 2 With a reactor scram required and the reactor not shutdown, initiate action to reduce power by injecting boron (If still critical with challenge to BuT) and inserting control rods.

1. Safety Significance:

Shutting down reactor can preclude failure of containment or equipment necessary for the safe shutdown of the plant.

2. Cues:

Procedural compliance.

Suppression Pool temperature.

3. Measured by:

Observation If operating JAW EOI-l and C-5, US determines that SLC is required (indicated by verbal direction or EOI placekeeping action) before exceeding 110 degrees in the Suppression Pool.

AND RO places SLC A / B Pump control switch in ON, when directed by US.

AND Control Rod insertion commenced in accordance EOI Appendixes.

4. Feedback:

Reactor Power trend.

Control Rod indications.

SLC tank level.

2

NRC Scenario 4 Critical Tasks Six CT 3 During an ATWS, when conditions with Emergency Depressurization required, Terminate and Prevent RPV injection (except for CRD, SLC and RCIC) from ECCS and Feedwater until reactor pressure is below the MARFP as directed by US.

1. Safety Significance:

Prevention of fuel damage due to uncontrolled feeding.

2. Cues:

Procedural compliance.

3. Measured by:

Observation No ECCS injection prior to being less than the MARFP.

AND Observation Feedwater terminated and prevented until less than the MARFP.

4. Feedback:

Reactor power trend, power spikes, reactor short period alarms.

Injection system flow rates into RPV.

CT 4 With RPV pressure <MARFP, slowly increase and control injection into RPV to restore and maintain RPV level above TAF as directed by US.

1. Safety Significance:

Maintaining adequate core cooling and preclude possibility of large power excursions.

2. Cues:

Procedural compliance.

RPV pressure indication.

3. Measured by:

Observation Injection not commenced until less than MARFP, and injection controlled such that power spikes are minimized, level restored and maintained greater than TAF.

4. Feedback:

RPV level trend.

RPV pressure trend.

Injection system flow rate into RPV.

3

NRC Scenario 4 Critical Tasks Six CT 5 When Suppression Chamber Pressure exceeds 12 psig, initiate Drywell Sprays while in the safe region of the Drywell Spray Initiation Limit (DSIL) curve and prior to exceeding the PSP limit.

1. Safety Significance:

Precludes failure of containment

2. Cues:

Procedural compliance High Drywell Pressure and Suppression Chamber Pressure

3. Measured by:

Observation US directs Drywell Sprays lAW with EOI Appendix 1 7B AND Observation RO initiates Drywell Sprays

4. Feedback:

Drywell and Suppression Pressure lowering RHR flow to containment OR Before Drywell temperature rises to 280°F, initiate Drywell Sprays while in the safe region of the Drywell Spray Initiation Limit (DSIL) curve.

1. Safety Significance:

Precludes failure of containment

2. Cues:

Procedural compliance High Drywell Pressure and Suppression Chamber Pressure

3. Measured by:

Observation US directs Drywell Sprays JAW with EOJ Appendix 1 7B AND Observation RO initiates Drywell Sprays

4. Feedback:

Drywell and Suppression Pressure lowering RHR flow to containment 4

NRC Scenario 4 Critical Tasks Six CT 6 After RPV water level drops to (-) 50 inches, when RPV level cannot be restored and maintained above (-) 180, RO initiates Emergency Depressurization as directed by US.

1. Safety Significance:

Maintaining adequate core cooling.

2. Cues:

Procedural compliance.

RPV level indication.

3. Measured by:

At least 6 SRVs are opened when RPV level cannot be restored and maintained above -180.

4. Feedback:

RPV pressure trend.

Suppression Pool temperature trend.

SRV open status indication.

5

NRC Scenario 4 Events

1. BOP operator will alternate Refuel and Reactor Zone Fans JAW 3-OI-30A and 30B. Refuel damper 64-9 fails in mid position when Refuel Fans are in off and is open when Refuel Fans operating. Tech Spec 3.6.4.2 Condition A, required action A.1 and A.2.

2. ATC commences power increase 85% using recirculation flow.

3. The Crew will respond to a loss of 480V SD BD 3B, this will cause a loss of RPS B, loss of 480V RMOV BDs 3B and 3C. The Inboard MSIV A will have inadvertently closed. The crew will need to lower power to meet the main steam line flow guidance lAW 3 -AOI-3 -1. The crew will need to restore power to 480V SD BD 3B, reset RPS, reset PCIS and restore systems. The SRO will also have to enter the following AOIs; 3-AOl- 1-3, 3 -AOI 1, and 3 -AOI 1. SRO will refer to the TRM and determine Technical Surveillance Requirement 3.4.1.1 to monitor Reactor Coolant Conductivity continuously cannot be met and samples must be drawn every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. SRO will refer to Tech Spec 3.6.1.3 for failed closed MSIV and enter condition A. SRO will refer to Tech Spec 3.4.5 and determine Condition B is required for inoperable containment atmospheric monitoring equipment.

4. The running Stator Water Cooling Pump will trip and the standby pump will fail to AUTO start.

The BOP operator will be required to start the standby Stator Water Cooling pump to restore system flow and prevent an automatic Turbine Trip/Reactor scram.

5. RFPT 3A flow controller will slowly fail low, RFPT 3A speed will continue to decrease until the ATC or Crew notices. The controller will fail to respond until the ATC takes manual control with handswitch. The Operator will be able to restore RFPT 3A speed in manual. SRO should direct entry into 3-AO1-3-1.

6. The EHC pressure transducer will slowly fail causing reactor pressure to slowly lower, the crew will enter 3-AOI-47-2. With RPV pressure lowering and the mode switch in RUN the MSIVs will fail to automatically close. The ATC will scram the reactor and verify MSIVs closed.

7. An ATWS will occur on the scram and the power supply to HPCI will fail, leaving RCIC as the only source of high pressure makeup besides SLC and CRD. The crew will insert control rods manually, and maintain reactor level.

8. With RCIC, CRD and SLC as the only source of high pressure makeup as the LOCA degrades RPV Level will continue to lower. The SRO will determine Emergency Depressurization is required to restore RPV Level. The crew will ED and restore RPV Level with available systems.

Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner:

Control Rods are being inserted Emergency Depressurization complete Reactor Level is restored 6

NRC Scenario 4 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: 4 9 Total Malfunctions Inserted: List (4-8) 2 Malfunctions that occur after EOI entry: List (1-4) 4 Abnormal Events: List (1-3) 2 Major Transients: List (1-2) 2 EOIs used: List (1-3) 2 EOI Contingencies used: List (0-3) 75 Validation Time (minutes) 6 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) 7

NRC Scenario 4 Scenario Tasks TASK NUMBER KIA RO SRO Alternate Reactor and Refuel Zone Fans RO U-30A-NO-02 288000A4.01 3.1 2.9 Raise Power with Recirc Flow RO U-000-NO-06 202002A4.07 3.3 3.3 SRO S-000-AD-3 1 Loss of 480V SD BD 3B RO U-57B-AL-06 26200 1A2.04 3.8 4.2 SRO S-57B-AL-09 Reactor Feed Pump Turbine Governor Failure RO U-003-AL-09 259002A4.01 3.8 3.6 SRO S-003-AB-01 Stator Water Cooling Pump Trip RO U-35A-AL-02 245000A4.03 2.7 2.8 SRO S-070-AB-01 EHC Pressure Transducer Failure RO U-047-AB-02 241000A2.03 4.1 4.2 SRO S-047-AB-02 LOCA/Low Level ED RO U-003-AL-24 29503 1EA2.04 4.6 4.8 RO U-000-EM-01 SRO S-000-EM-14 SRO S-000-EM-15 SRO 5-000-EM-Ol ATWS RO U-000-EM-03 295015AA2.01 4.1 4.3 RO U-000-EM-22 RO U-000-EM-28 SRO S-000-EM-03 SRO S-000-EM-18 8*

NRC Scenario 4 Procedures Used/Referenced:

Procedure Number Procedure Title 3-O1-30A Refuel Zone Ventilation System 3-01-30B Reactor Zone Ventilation System 3-GO1-100-12 Power Maneuvering 3-01-68 Reactor Recirculation System 3-ARP-9-8B Panel 9-8 3-XA-55-8B 3-ARP-9-8C Panel 9-8 3-XA-55-8C 3-ARP-9-4C Panel 9-4 3-XA-55-4C 3-AO1-99-i Loss of Power to One RPS Bus 3-AO1-i-3 Main Steam Isolation Valve Closure at Power 3-AOI-70-i Loss of Reactor Building Closed Cooling Water 3-01-99 Reactor Protection System 3-A0I-64-2D Group 6 Ventilation System Isolation Technical Specifications Technical Requirements Manual 3-ARP-9-7A Panel 9-7 3-XA-55-7A 3-ARP-9-8A Panel 9-8 3-XA-55-8A 3-ARP-9-5A Panel 9-5 3-XA-55-5A 3-AOI-3-1 Loss Of Reactor Feedwater or Reactor Water Level High/Low 3-ARP-9-7B Panel 9-7 3-XA-55-7B 3-A0I-47-2 Turbine EHC Control System Malfunctions 3-A0I-lOO-l Reactor Scram 3-EOI-i RPV Control 3-C-5 Level/Power Control 3-EOI Appendix-iD Insert Control Rods Using Reactor Manual Control System 3 -EO1 Appendix-i F Manual Scram 3 -EOI Appendix-2 Defeating AR! Logic Trips 3-EOI Appendix-i i A Alternate Pressure Control Systems MSRVs 3-EOI Appendix-5C Injection System Lineup RCIC 3-EOI-2 Primary Containment Control 3-E0I Appendix-i7A RHR System Operation Suppression Pool Cooling 3 -EOI Appendix-i 7C RHR System Operation Suppression Chamber Sprays 3-EOI Appendix-i 7B RI-IR System Operation Drywell Sprays 3-AOI-85-3 CRD System Failure 3 -EO1 Appendix-7B Alternate RPV Injection System Lineup SLC System 3 -EOI Appendix-4 Prevention of Injection 3-C-2 Emergency RPV Depressurization 3-EO1 Appendix-6B Injection Subsystems Lineup RHR System 1 LPCI Mode 3-EOI Appendix-6C Injection Subsystems Lineup RHR System II LPCI Mode EPIP- i Emergency Classification 9

NRC Scenario 4 Batch File

1. RFPT 3B and EECW Pump A3 tagout ior ypobkrrhrswpa3 fail_ccoil ior zlohs2385a[1j off ior ypomtreopb3 fail_control_power ior ypobkrmopb 1 fail_ccoil ior ypobkrmopb2 fail_ocoil ior ypomtrtgmb fail_control_power ior ypovfcv03 12 fail_power now ior ypovfcv0295 fail_power_now ior ypovfcv0l 129 fail_power_now ior ypovfcvO 1133 fail_power_now

1. Refuel Zone Damper 64-9 fails in Mid position ior zlohs649[2] on

1. Loss of 480V SD BD B imfedlOb (el 0) ior zdihs0l 14a[i] (el 0) close mrfrp09 (e3 0) reset trg e3 bat restorerpsb ior zdixs577l[iJ (e4 0) normal

1. B stator water pump trip irf egO2 (e5 0) off ior ypobkrscwpa (e5 0) fail_ccoil ior zdihs3535a[2] (e5 0) stop ior zlohs3535a[1] (e5 0) off

1. rfpt governor drift imffw3Oa (elO 0)02500 72 trg eli nrcrfptA trgell =dmffw30a

1. B EHC Pressure transducer failure ior zdihs0i l6[1] (e14 0) select ior zdihs472O4[i] (e14 0) null iorzlohs0ll6[l] off ior zlohs472O4{l] on imftcl0b (el4 0) 82 3000 79 imf ms06b imf ms06c imf ms06d imf ms06e imf ms06f imf ms06g imf ms06h 10

NRC Scenario 4

1. major trg el 8 nrcmodesw bat nrcstickquad Imfth22 (e18 1:00)

Imfth2l (e18 10:00) 1 15:00 imfhp07 (e18 0) trg e23 bat appOif trg e24 = bat app02 trg e25 = bat nrcstickquad-1 mrfrd06 (e26 0) close mrf rdO6 (e27 0) open trg e28 bat nrcatws95 t1g e 18 = bat nrcmsiv Trigger Files nrcrfptA zdihs468a[4] .ne. 1 Scenario 4 DESCRIPTION/ACTION Simulator Setup manual Reset to IC 203 Simulator Setup Load Batch bat nrcl4O4-4 Simulator Setup manual Tag RFPT 3B and EECW Pump A3 Simulator Setup Verify file loaded. Log in to EHC System to ensure when operators try to access they_are_able_to.

RCP required (80% 85% with flow) and RCP for Urgent Load Reduction Provide marked up copy of 3-GOI-100-12 11

NRC Scenario 4 Simulator Event Guide:

Event 1 Component: Alternate Refuel and Reactor Zone Fans lAW 3-01-3 OA and 3 OB SRO Direct Refuel and Reactor Zone Fans alternated BOP 6.1 Alternating Refueling Zone Supply and Exhaust Fans 3-0l-30A

[1] NOTIFY Unit 1 and Unit 2 Operators that the Refuel Zone fans are being alternated.

[2] VERIFY the Refueling Zone supply and exhaust fans are operating. REFER TO Section 5.1.

[3] REVIEW precautions and limitations in Section 3.0.

NOTES

1) The preferred method to start the alternate Refueling Zone supply and exhaust fans is to use the common control Switch, 3-HS-64-3A, on Panel 3-9-25.

2) Refueling Zone supply and exhaust dampers, 3-FCO-064-0005,0006,0009, and 0010 will open or close automatically as necessary when fans are stopped and started.

3) Refueling Zone supply and exhaust fans are alternated every six weeks.

PLACE REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A, in OFF.

[4]

[5] CHECK that the two red lights A(B) extinguish and the two green lights A(B) illuminate above REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A.

NOTE BOP If any damper does not meet the requirements of step 6.1 [6] IMMEDIATELY notify the Unit supervisor to evaluate SCIV damper operability (refer to TRM appendix A). If any listed damper indicates not full closed, it should be considered inoperable for its SCIV function, and the required actions of Tech Spec LCO 3.6.4.2 entered for all units.

[6] CHECK the red (open) damper position indication lights extinguish and the green (closed) lights illuminate above the following control switches:

• REFUEL ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-5

• REFUEL ZONE SPLY INBD ISOL DMPR, 3-HS-64-6

• REFUEL ZONE EXH OUTBD ISOL DMPR, 3-HS-64-9

• REFUEL ZONE EXH 1NBD ISOL DMPR, 3-HS-64-10

[7] PLACE REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A, in SLOW 3A (SLOW 3B) to start alternate fans.

BOP Report Failure of REFUEL ZONE EXH OUTBD ISOL DMPR, 3-HS-64-9 12

NRC Scenario 4 Simulator Event Guide:

Event 1 Component: Alternate Refuel and Reactor Zone Fans JAW 3-01-3 OA and 3 OB BOP [8] CHECK that the two green lights A(B) extinguish and the two red lights A(B) illuminate above REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A.

[9] CHECK the red (open) damper position indication lights illuminate and green (closed) lights extinguish above the following control switches:

• REFUEL ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-5

• REFUEL ZONE SPLY INBD ISOL DMPR, 3-HS-64-6

• REFUEL ZONE EXH OUTBD ISOL DMPR, 3-HS-64-9

• REFUEL ZONE EXH INBD ISOL DMPR, 3-HS-64-10 NOTE A five minute time delay should be observed following Refuel Zone Supply and Exhaust Fan SLOW Start. The time delay allows the discharge dampers to fully open after SLOW start.

[10] IF Refueling Zone Supply and Exhaust Fan FAST speed operation is necessary, THEN: PERFORM the following:

[10.1] PLACE REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A, in FAST 3A (FAST 3B).

[10.2] CHECK that the two green lights A(B) remain extinguished and the two red 1 lights A(B) remain illuminated above REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A.

[11] CHECK the following conditions:

• SUPPLY FANS FILTER DLFF PRESS Indicator, 3-PDI-064-0022, indicates less than 0.6 inches H20 at the Reactor Building/Refuel Floor Supply fan intake room at El 565.

• REFUELING ZONE STATIC PRESS INTLK, 1-PDS-064-006 lA/C, on refuel floor Panel 25-220 indicates between (negative) -0.25 inches to -0.40 inches.

BOP Contacts AUO for the above information Driver When contacted wait 4 minutes and repox licates 0.4 inches H20 and that 1-PDS-064-0061A/C, indicates -0.3 13

NRC Scenario 4 Simulator Event Guide:

Event 1 Component: Alternate Refuel and Reactor Zone Fans JAW 3-OJ-30A and 30B SRO Direct Refuel and Reactor Zone Fans alternated BOP 6.1 Alternating Reactor Zone Supply and Exhaust Fans 3-OI-30B

[1] VERIFY the Reactor Zone supply and exhaust fans are operating. REFER TO Section 5.1.

[2] REVIEW all Precautions and Limitations in Section 3.0.

NOTES

1) The preferred method to start the standby Reactor Zone supply and exhaust fans is to use the common control switch (3-HS-64-1 1A) on Panel 3-9-25.

2) Reactor Zone supply and exhaust dampers, 3-FCO-064-0013, 0014, 0042, and 0043 will open or close automatically as necessary when fans are stopped and started.

3) The Steam Vault Exhaust Booster Fan should normally be in service whenever the Unit is operating with Reactor Building Ventilation in service and fans in fast speed. Operation of the Steam Vault Exhaust Booster Fan with Reactor Zone Exhaust fans out of service is an ALARA concern due to backflow into the Reactor Building lower level ventilation ductwork. However, the Steam Vault Exhaust fan may remain in service with Reactor Zone Exhaust fans out of service to cool the steam tunnel for short durations such as alternating fans, cycling reactor Booster zone dampers, or RPS power transfers.

[3] IF Reactor Zone Ventilation is to remain Out of Service for an extended period (?3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) and it is desired to leave the Steam Vault Exhaust Booster Fan in service, THEN (Otherwise N/A): Step is NA

[4] IF required, THEN SHUT DOWN Steam Vault Exhaust Booster Fan. REFER TO Section 7.4. (Otherwise N/A). Step is NA

[5] PLACE REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-1 1A, in OFF.

[6] VERIFY dampers close and fans stop as indicated by illuminated green lights above the following switches:

• REACTOR ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-13

• REACTOR ZONE SPLY INBD ISOL DMPR, 3-HS-64-14

• REACTOR ZONE EXH INBD ISOL DMPR, 3-HS-64-42

• REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

• REACTOR ZONE FANS AND DAMPERS, 3-HS-64-1 1A

\

[7] PLACE REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-1 1A, in SLOW A (SLOW B) to start alternate fans.

14

NRC Scenario 4 Simulator Event Guide:

Event 1 Component: Alternate Refuel and Reactor Zone Fans JAW 3-OI-30A and 30B BOP [8] VERIFY dampers open and fans start as indicated by illuminated red lights above the following switches:

• REACTOR ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-13

• REACTOR ZONE SPLY INBD ISOL DMPR, 3-HS-64-14

• REACTOR ZONE EXH INBD ISOL DMPR, 3-HS-64-42

• REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

• REACTOR ZONE FANS AND DAMPERS, 3-HS-64-1 1A

[9] IF fast speed Reactor Zone Supply and Exhaust Fan operation is required, five minutes should be allowed after slow start for the discharge dampers to FULLY OPEN, THEN

[9.1] PLACE REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-1 1A, in FAST A (FAST B).

[9.2] VERIFY that the two green lights A(B) remain extinguished and the two red lights A(B) remain illuminated above REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-1 1A.

[10] VERIFY the following conditions:

[10.1] VERIFY REACTOR ZONE PRESS DIFFERENTIAL Indicator, 3-PDIC-064-0002, on 3-LPNL-925-0213, located at R17-P El 639, indicates between -0.25 inches and -0.40 inches H20.

[10.2] IF REACTOR ZONE PRESS DIFFERENTIAL Indicator, 3-PDIC-64-2, is not between -0.25 inches and -0.40 inches H2O, THEN REFER TO 3-AOl-30B-1, Reactor Building Ventilation Failure.

[11] IF required, THEN START Steam Vault Exhaust Booster Fan. REFER TO Section 5.4. NOT Required BOP Contacts AUO for the above information Driver When contacted wait 4 minutes and report 3-PDIC-064-0002, indicates -0.35 inches H20.

15

NRC Scenario 4 Simulator Event Guide:

Event 1 Component: Alternate Refuel and Reactor Zone Fans lAW 3-OI-30A and 30B 3.6.4.2 Secondary Containment isolation Valves (SC1Vs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel (OPDRVs).

SRO ACTIONS NOTES

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

Condition A. One or more penetration flow paths with one SCIV inoperable.

Required Action A. 1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

Completion Time: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND Required Action A.2 Verify the affected penetration flow path is isolated.

Completion Time: Once per 31 days Call Work Control for a clearance on the REFUEL ZONE SPLY OUTBD ISOL DMPR, SRO 3-FCV-64-1 0 TRM Appendix A Power Operated Secondary Containment Isolation Valves 3-DMP-64-9 REFUELING ZONE EXH DUCT OUTBD ISOL DMPR < 10 SEC 16

NRC Scenario 4 Simulator Event Guide:

Event 2 Reactivity: Power increase with Recirc Flow SRO Notifies ODS of power increase.

Directs Power increase using Recirc Flow, per 3-G0I-100-12.

[20] IF desired to raise power with only two(2) Reactor feedpumps in service, THEN RAISE Reactor power, as desired, maintaining each Reactor feedpump less than 5050 RPM.

ATC Raise Power w/Recirc, lAW 3-01-68, Section 6.2 D. Individual pump speeds should be mismatched by 60 RPM during dual pump operation between 1200 and 1300 RPM to minimize harmonic vibration (this requirement may be waived for short time periods for testing or maintenance).

[1] IF desired to control Recirc Pumps 3A and/or 3B speed with Recirc Individual Control, THEN PERFORM the following;

• Raise Recirc Pump 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B).

AND/OR

• Raise Recirc Pump 3B using, RAISE SLOW (MEDIUM), 3-HS-96-16A(16B).

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A &3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-3 1 RAISE MEDIUM, 3-HS-96-32 NRC At RR Pump Speeds of 1260rpm and 1200 rpm, power will be 85% and RT RPMs will be just below 5025 Driver When directed by NRC, Trigger 1 Loss of 480V SD BD 3B, If crew attemts to close alternate supply breaker or is going to close alternate supply breaker delete ED 1 OB in order to allow the crew to energized the Board Driver Wait 2 minutes and report license class 1404 was in the field, a trainee accidently tripped the normal feeder breaker. No problems indicated on Board.

17

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B Crew Responds to numerous alarms, diagnoses a loss of 480V SD BD 3B and 480V RMOV Bds 3Band3C Responds to the following alarms; 8B-30, 8C-l7, 24, 29, 31, 4C-12 and 3D -32.

SRO Enters 3-AO1-99-l, 3-AO1-1-3 and 3-AO1-70-l.

BOP Alarm 8B-30: 480V SHUTDOWN BD 3B UV OR XFR A. CHECK for indication of 480V Shutdown Bd 3B loss:

• RWCU Pump 3B shutdown

• Fuel pool cooling Pump 3B shutdown

• 480V Shutdown Bd 3B voltage (3-EI-57-30)

B. IF 480V Shutdown Bd 3B is lost, THEN MANUALLY TRANSFER to alternate source by placing CS in ALTERNATE position on Panel 3-9-8.

C. IF manual transfer is accomplished, THEN REFER TO O-O1-57B, 3-01-99, and appropriate Ols for recovery or realignment of equipment.

D. IF manual transfer is NOT accomplished, THEN REFER TO Tech Spec Section 3.8.1.

Dispatches personnel to Breaker, may attempt to energize 480V SD BD 3B triver If crew attempts to close alternate supply breaker or is going to close alternate supply breaker delete ED 1 OB in order to allow the crew to energized the Board Driver DO NOT Call until requested to investigate. Wait 2 minutes and report license class 1404 was in the field, a trainee accidently tripped the normal feeder breaker. No problems indicated on Board. If the crew directs you to restore 480V SD BD 3B to Normal supply trigger 4, ior zdihs577 1 [1] normal, if directed to restore Board on alternate supply change normal to ALT (alternate) 18

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B BOP Alarm 8C-24: 480V REACTOR MOV BD 3B OR 3E UV OR XFR A. CHECK light indications for loss of any 480V equipment.

B. CHECK 480V Rx MOV Bd 3B & 3E for abnormal conditions: relay targets, smoke, burned paint, breaker position, etc.

C. IF Normal or Alternate feeder breaker tripped, THEN MANUALLY DEPRESS mechanical trip/reset mechanism on breaker face to reset Bell Alarm lockout device.

D. IF undervoltage or transfer has occurred:

1. REFER TO TS Section 3.8.7.

2. RESET possible half-scram. REFER TO 3-01-99 BOP Alarm 8C-29: 1&C BUS B VOLTAGE ABNORMAL A. VERIFY the Alarm by checking:

• Loss of instrument power and remote position indication to Core Spray Div II and RI-JR Div 11 (Panel 3-9-3)

• RWCU Filter Demin 3B Isolation Reactor Zone/Refuel Zone Ventilation Isolation Verifies I&C Bus B Auto transferred to alternate feeder Alarm 8C-29: 480V REACTOR MOV BD 3C UV OR XFR A. VERIFY automatic action.

B. CHECK light indications for loss of 480V equipment.

C. CHECK board for abnormal conditions: relay targets, smoke, burned paint, breaker position, etc.

D. IF Normal or Alternate feeder breaker tripped, THEN MANUALLY DEPRESS mechanical trip/reset mechanism on breaker face to reset Bell Alarm lockout device.

E. REFER TO O-0I-57B to re-energize or transfer the board.

Driver When requested to restore steam tunnel booster fan wait two minutes and mrf PC 14 start 19

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B

=

ATC Alarm 4C-12: RBCCW PUMP DISCH. HDR PRESS LOW A. VERIFY 3-FCV-70-48 CLOSING/CLOSED.

B. VERIFY RBCCW pumps A and B in service.

C. VERIFY RBCCW surge tank low level alarm is reset.

E. REFER TO 3-AO1-70-l for RBCCW System failure and 3-01-70 for starting spare pump.

When 480V RMOV BD 38 is restored should VERIFY 3-FCV-70-48 CLOSING Report Alarm 3D-32: Reactor Zone Differential Pressure Low BOP EOI-3 Entry Condition.

SRO Enters EOI-3 Secondary Containment Control When requested to restore RPS B, if requested to place on alternate trigger 3, mi-f rpO9 reset Driver and bat restorerpsb, if requested to restore to normal then bat rpsreset and mrf rpO9 reset. If place back on normal ensure to reset alternate supply circuit protectors mrf rpO3 reset.

20

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B ATC Announces Power, Pressure and Level stable on Board loss Crew 3-AOl-99-1, Loss of Power to One RPS Bus 4.1 Immediate Actions

[1] STOP all testing with potential RPS half-scrams or PCIS logic isolation signals.

NOTES

3) Loss of RPS will isolate 3-RM-90-256, Drywell Air Monitor, and TS LCO 3.4.5 Condition B should be entered.

4.2 Subsequent Actions

[1] VERIFY automatic actions occur.

[2] VERIFY Steam Tunnel Booster Fan Operation by observation of MAIN STEAM LINE TUNNEL TEMPERATURE, 3-TIS- 1 -60A.

[3] IF desired to place RPS Bus A on Alternate Supply, (N/A)

[4] IF desired to place RPS Bus B on Alternate Supply, THEN PERFORM Step 4.2[9]. (Otherwise N/A)

[5] IF desired to Startup and Load RPS MG Set 3A, ( N/A)

[6] IF desired to Startup and Load RPS MG Set 3B, THEN PERFORM Step 4.2[l 1].

(Otherwise N/A)

When requested to restore RPS B, if requested to place on alternate trigger 3, mrf rpO9 reset Driver and bat restorerpsb, if requested to restore to normal then bat rpsreset and niif rpO9 reset. If place back on normal ensure to reset alternate supply circuit protectors mrf rpO3 reset.

21

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 313 Crew 3-AO1-99-1, Loss of Power to One RPS Bus

[9] RESTORE Alternate Power to RPS Bus B as follows:

[9.1] VERIFY memory lights inside the RPS Circuit Protector Cabinets are RESET.

• RPS CIRCUIT PROTECTOR RESET PB CAB 3d, 3-HS-099-0003C1.

• RPS CIRCUIT PROTECTOR RESET PB CAB 3C2, 3-HS-099-0003C2.

[9.2] VERIFY circuit Protectors 3C1 and 3C2 are RESET.

• RPS CIRCUIT PROTECTOR 3C1, 3-HS-099-0003C1/1.

• RPS CIRCUIT PROTECTOR 3C2, 3-HS-099-0003C2/1.

[9.5] NOTIFY Unit 3 Operator that RPS Bus 3B is on Alternate Supply.

[9.6] PROCEED to Step 4.2[12].

[11] STARTUP and Load RPS MG Set 3B as follows:

[11.1] VERIFY RPS MG Set 3B available to be placed in service.

[11.3] IF RPS MG Set 3B is still running and resetting of the circuit protectors is desired, THEN PERFORM steps 4.2[1 1.7] thru 4.2[1 1.14].

[11.7] RESET memory lights inside RPS Circuit Protector Cabinets, as follows:

[11.7.1] DEPRESS RPS CIRCUIT PROTECTOR 3B1 RESET pushbutton, 3-HS-099-0003B 1.

[11.7.2] DEPRESS RPS CIRCUIT PROTECTOR 3B2 RESET pushbutton, 3-HS-099-0003B2.

[11.8] RESET or VERIFY Reset CIRCUIT PROTECTORS 3B1 and 3B2 as follows:

[11.8.1] DEPRESS RPS CKT PROTECTOR 3B 1 RESET, 3-HS-099-0003B 1/1.

[11.8.2] DEPRESS RPS CKT PROTECTOR 3B2 RESET, 3-FIS-099-0003B2/1 When requested to restore RPS B, if requested to place on alternate trigger 3, mrfrpO9 reset Driver and bat restorerpsb, if requested to restore to normal then bat rpsreset and mrf rpO9 reset. If place back on normal ensure to reset alternate supply circuit protectors mrf rpO3 reset.

22

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B Crew 3-AOI-99-1, Loss of Power to One RPS Bus

[12] RESET the RPS trip logic half SCRAM at Panel 3-9-5 as follows:

[12.1] MOMENTARILY PLACE SCRAM RESET, 3-HS-99-5A/S5, as follows:

[12.2] RESET FIRST. (Group 2/3)

[12.3] RESET SECOND. (Group 1/4)

[12.4] NORMAL

[13] CHECK the following conditions:

[13.1] All eight SCRAM SOLENOID GROUP A/B LOGIC RESET lights ILLUMINATED.

[13.2] The following four lights ILLUMINATED:

[13.2.1] SYSTEM A BACKUP SCRAM VALVE, 3-IL-99-5A/AB

[13.2.2] SYSTEM B BACKUP SCRAM VALVE, 3-IL-99-5A/CD

[13.3] Scram Discharge Volume vent and drain valves indicate OPEN.

[13.4] Points S0E033 (Channel A3 manual scram) and SOEO35 (Channels A1&A2 Auto Scram) on ICS computer or on the First Out Printer reads NOT TRIP for RPS A.

Points SOEO34 (Channel B3 manual scram) and SOEO36 (Channels B1&B2

[13.5] Auto Scram) on ICS computer or on the First Out Printer reads NOT TRIP for RPS B.

[14] RESET PCIS trip logic at Panel 3-9-4 as follows:

[14.1] MOMENTARILY PLACE PCIS DIV I RESET, 3-HS-64-16A-532, to left and right RESET positions.

[14.2] CHECK the following red lights ILLUMINATED:

[14.2.1] MSIV GROUP Al, 3-IL-64-A1

[14.2.2] MSIV GROUP Bi, 3-IL-64-B1

[14.3] MOMENTARILY PLACE PCIS DIV II RESET, 3-HS-64-16A-S33, to left and right RESET positions.

[14.4] CHECK the following red lights ILLUMINATED:

[14.4.1] MSIV GROUP A2, 3-IL-64-A2

[14.4.2] MSIV GROUP B2, 3-IL-64-B2 23

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B Crew 3-AO1-99-1, Loss of Power to One RPS Bus

[16] RESET the secondary containment isolation logic at Panel 3-9-25, as follows:

[16.1] PLACE the REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-1 1A, to OFF.

[16.2] PLACE REFUEL ZONE FANS AND DAMPERS Switch, 3-HS-64-3A, to OFF.

[16.3] VERIFY only one SBGT trains operating.

[17] START the Refuel Zone supply and exhaust fans, at Panel 3-9-25, as follows:

[17.1] PLACE REFUEL ZONE FANS AND DAMPERS Switch, 3-HS-64-3A, in SLOW A (SLOW B) position.

[18] START the Reactor Building supply and exhaust fans, at Panel 3-9-25, as follows:

18.1] PLACE the REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-1 1A, to the SLOW A(B) position.

[19] SECURE remaining SBGT train per 0-01-65 section 7.1.

[20] IF fans transfer to fast speed is required after five minutes, THEN:

PLACE the REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-1 1A, to the FAST A(B) position.

[21] IF fans transfer to fast speed is required after five minutes, THEN:

PLACE the REFUEL ZONE FANS AND DAMPERS switch, 3-HS-64-3A, to the FAST A(FAST B) position.

[22] REFER to 3-01-99 to restore remaining affected systems to operation following RPS Bus Power loss and RETURN to Step 4.2[23]

24

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B ATC/BOP Reports MSIV A Inboard Valve shut on loss of board.

SRO Enters 3-AOI-1-3, Main Steam Isolation Valve Closure at Power ATC 4.2 Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s).

[2] LOWER reactor power with recirc flow and insert control rods as directed by the Reactor Engineer/Unit Supervisor as necessary to ensure that rated steam line flow 3.54 x 106 lb/hr is not exceeded as indicated on Main Steam Line Flow Indicators.

REFER TO 3-GOI-100-12 or 3-GOI-100-12A for the power reduction.

[6] IF Drywell control air pressure is normal, THEN IMTIATE trouble-shooting of the MSIV. (Otherwise N/A) Step is NA

[7] EVALUATE Technical Specification 3.6.1.3, Primary Containment Isolation Valves.

SRO Directs ATC to lower power to less than 3.54 x 106 lb/hr on Main Steam Line Flow Indicators. Directs recirc pump speeds matched when outside of the 1200 to 1300 rpm band.

(

BOP Places MSIV A Inboard Valve handswitch in the close position Lowers power as directed by SRO Lower Core flow to 74% or as directed by the RCP Insert control rods lAW with shove sheet, until the desired power level is reached or load ATC line is below 90%

Control Rods 14-31, 30-47, 46-31, 30-15 16 to 00 Control Rods 22-3 1, 30-39, 38-31, 30-23 48 to 00 25

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B SRO Enters 3-AOI-70-1, Loss of Reactor Building Closed Cooling Water ATC 4.1 Immediate Actions

[1] IF RBCCW Pump(s) has tripped, THEN Perform the following (Otherwise N/A):

• SECURE RWCU Pumps.

• VERIFY RBCCW SECT1ONALIZING VLV, 3-FCV-70-48 CLOSED.

Verifies RWCU Tripped, cannot verify sectionalizing valve at this time NO Power 4.2 Subsequent Actions

[1] IF Reactor is at power AND Drywell Cooling cannot be immediately restored, AND core flow is above 60%,THEN:

[2J IF any EO1 entry condition is met, THEN ENTER appropriate EOI(s) (otherwise N/A).

One RBCCW Pump is in service with sectionalizing valve open due to loss of power IF RBCCW Pump(s) has tripped and it is desired to restart the tripped RBCCW

[3] pump, THEN PERFORM the following (otherwise N/A):

[3.1] INSPECT the tripped RBCCW pump and its associated breaker for any damage or abnormal conditions.

[3.2] IF no damage or abnormal conditions are found, THEN ATTEMPT to restart tripped RBCCW pump(s).

ATC When power is restored to 480V SD BD 3B RBCCW Pump will auto start 26

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B SRO Directs 3-01-99 actions to restore from loss of RPS B Crew NOTE Steps 8.5[5] through 8.5[22] can be performed in any order.

[5] CHECK the green lights are ILLUMINATED on all 5 of the QLVPS located at bottom of Panel 9-14.

[6] RESTORE Reactor and Refuel Zone Ventilation to normal operation. REFER TO 3-AOI-64-2D, Group 6 Ventilation System Isolation.

[7] RESTORE Standby Gas Treatment System to standby readiness. REFER TO 0-01-65.

[8] At Panel 3-9-3, PLACE PSC head tank pumps in service as follows:

• PLACE PSC PUMP SUCTION 1NBD ISOL VALVE, 3-HS-75-57A, in AUTO After OPEN.

PLACE PSC PUMP SUCTION OUTBD ISOL VALVE, 3-HS-75-58A, in AUTO After OPEN.

[10] At Panel 3-9-3, RESTORE Drywell DP Compressor to automatic operation as follows:

[10.1] DEPRESS DRYWELL DP CPRSR SUCT VLV RESET pushbutton,

[10.2] DEPRESS DRYWELL DP CPRSR DISCH VLV RESET pushbutton, 3-HS-64-139A.

3-HS-64-1 40A.

[10.3] VERIFY OPEN DW TO SGT IIJBD ISOL VALVE using 3-HS-64-31.

[10.4] VERIFY OPEN SLJPPR CHBR SGT INBD ISOL VALVE using 3-HS-64-34.

27

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B SRO Directs 3-01-99 actions to restore from loss of RPS 13 Crew [13] IF DW Radiation Monitor CAM, 3-RM-90-256, isolated due to loss of RPS, THEN MOMENTARILY DEPRESS the following RESET pushbuttons on Panel 3-9-2.

• DW RAD MON UPPER INBD SUPPLY ISV RESET, 3-HS-90-254A-A (opens FCV-90-254A)

• DW RAE MON LOWER INBD SUPPLY ISV RESET, 3-HS-90-254B-A (opens FCV-90-254B)

• DW RAD MON OUTBD RETURN ISV RESET, 3-HS-90-257A-A (opens FCV-90-257A)

• DW RAD MON OUTBD SUPPLY ISV RESET, 3-HS-90-255A (opens FCV-90-255)

• DW RAD MON INBD RETURN ISV RESET, 3-HS-90-257B-A (opens FCV-90-257B)

[14] At Panel 3-9-54, PLACE H2/02 Analyzer in service per 3-01-76.

[15] At Panel 3-9-55, VERIFY DRYWELL OR SUPPRESSION CHAMBER EXHAUST TO SGTS, 3-FIC-84-20, in AUTO with setpoint at 100 scfim

[19] At Panels 3-9-10 and 3-9-1 1, RESTORE Radiation Monitoring System as follows:

[19.1] DEPRESS applicable RESET pushbuttons.

[19.2] RESTORE Radiation Monitoring System to normal. REFER TO 3-01-90.

28

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B BOP 3-AOI-64-2D, Group 6 Ventilation System Isolation

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s).

[2] VERIFY Group 6 isolation valves penetrating Primary Containment are closed.

UTILIZE Panel 3-9-3 mimic or Containment Isolation Status System on Panel 3-9-4.

[3] IF Refuel Zone Isolation is due to high radiation, as indicated on 3-RM-90-140 and/or 3-RM-90-141, Panel 3-9-10, and/or associated recorder on Panel 3-9-2, THEN. (Otherwise N/A) Step is NA

[7] CHECK the following to confirm condition:

• REACTOR & REFUEL ZONE EXHAUST RADIATION, 3-RR-90-144

• RX & REFUEL ZONE EXH CH A RAD MON RTMR, 3-RM-90-140/142

• RX & REFUEL ZONE EXH CH B RAD MON RTMR, 3-RM-90-141/143

[13] WHEN initiating signal has been corrected AN]) necessary repairs are made, THEN

[13.1] VERIFY PCIS RESET:

• RESET PCIS DIV I RESET, 3-HS-64-16A-S32.

RESET PCIS DIV II RESET, 3-HS-64-16A-S33.

[13.2] RESET Reactor/Refuel isolation logic, as required:

• PLACE REFUEL ZONE FANS AND DMPRS, 3-HS-64-3A, in OFF.

PLACE REACTOR ZONE FANS AND DMPRS, 3-HS-64-1 1A, in OFF.

[13.3] START Reactor/Refuel zone ventilation, as required:

• PLACE REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-1 1A, in SLOW A (SLOW B).

PLACE REFUEL ZONE FANS AND DAMPERS Switch, 3-HS-64-3A, in SLOW 3A (SLOW 3B).

[13.4] For the fans started, VERIFY that the dampers open and fans start as indicated by illuminated red lights above the following switches:

• The two green lights A(B) above REACTOR ZONE FANS AND DAMPERS Switch 3 -HS 11 A, extinguish and the two red lights A(B) illuminate.

• The two green lights A(B) above REFUEL ZONE FANS AND DAMPERS Switch 3-HS-64-3A, extinguish and the two red lights A(B) illuminate.

Driver when directed by NRC trigger 5 for Stator water pump trip 29

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B SRO Tech Spec Actions from loss of 480V SD BD 3B Evaluate TRM 3.4A TSR 3.4.L1 Monitor reactor coolant conductivity.

Continuously OR 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when the continuous conductivity monitor is inoperable and the reactor is not in MODE 4 or 5 OR 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the continuous conductivity monitor is inoperable and the reactor is in MODE 4 or 5 Informs Chemistry have lost Continuous reactor coolant conductivity monitoring SRO Evaluate Tech Spec 3.4.5 3.4.5 RCS Leakage Detection Instrumentation

()

LCO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Drywell floor drain sump monitoring system; and

b. One channel of either primary containment atmospheric particulate or atmospheric gaseous monitoring system.

APPLiCABILITY: MODES 1,2, and 3.

Condition B: Required primary containment atmospheric monitoring system inoperable.

Required Action B. 1: Analyze grab samples of primary containment atmosphere.

Completion Time: Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action B.2: Restore required primary containment atmospheric monitoring system to OPERABLE status.

Completion Time: 30 days Driver when directed by NRC trigger 5 for Stator water pump trip 30

NRC Scenario 4 Simulator Event Guide:

Event 3 Component: Loss of 480V SD BD 3B SRO Tech Spec Actions from loss of 480V SD BD 3B SRO Evaluate Technical Specification 3.6.1.3.

3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, Primary Containment Isolation Instrumentation.

Condition A: NOTE Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with one PCIV inoperable except due to MSIV leakage not within limits Required Action A. 1: Iso late the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

Completion Time: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for main steam lines Action A.2: NOTE Isolation devices in high radiation areas may be verified by Required use of administrative means.

Verify the affected penetration flow path is isolated.

Completion Time: Once per 31 days for isolation devices outside primary containment Driver when directed by NRC trigger 5 for Stator water pump trip 31

NRC Scenario 4 Simulator Event Guide:

Event 4 Component: Stator Water Cooling Pump trip BOP Responds to alarms 7A-22 and 8A-1 BOP Announces trip of Stator Water Cooling Pump 3A 7A-22, GEN STATOR COOLANT SYS ABNORMAL A. IF while performing the action of this ARP 3-XA-55-9-8A Window 1 alarms THEN,

1. VERIFY all available Stator Cooling Water Pumps running.

2. Attempt to RESET alarm

3. IF alarm fails to reset, AND reactor power is above turbine bypass valve capability THEN SCRAM the Reactor B. VERIFY a stator cooling water pump is running and CHECK stator temperature recorder, 3-TR-5 7-59, Panel 3-9-8.

C. CHECK alarm by dispatching personnel to check the Stator Coolant Control Cabinet.

8A-1, TURBINE TRIP TIMER INITIATED CHECK Stator Cooling Water Flow and Temperature and Generator Stator A. temperatures using ICS.

B. VERIFY all available Stator Cooling Water Pumps running.

NOTE The full capacity of the Turbine Bypass valves with all nine valves open is 25% reactor power. To determine the capacity of the bypass valves, subtract 3% for each out of service bypass valve from the 25%. (Example, one bypass valve out of service, [25% 3% = 22%],

therefore, the capacity of the bypass valves with one bypass valve out of service is 22%.)

C. IF all of the following conditions exist:

• Alarm fails to reset,

• Low Stator Cooling Water flow OR High Generator or Stator Cooling temperatures are observed on ICS,

• Reactor Power is above turbine bypass valve capability, THEN, SCRAM the reactor. (Otherwise N/A)

BOP Starts Stator Water Cooling Pump 3B Driver When dispatched wait two minutes and report pump is extremely hot to touch, at breaker breaker is tripped no other indications Driver When directed by NRC to insert RFPT 3A governor failure, verify start value is between 71 and 72. If not modify start value to the current value and ensure final severity is set to zero and ensure ramp time remains unchanged and then insert trigger 10 mf fw3 Oa (e 10 0) 0 1300 72, When operator takes manual control of RFPT 3A ensure trigger 11 goes active to allow the operator to control. Be prepared to insert the next event if the crew decides to scram, see next page driver instructions.

32

NRC Scenario 4 Simulator Event Guide:

Event 5 Instrument: RFPT 3A Governor slowly fails low ATC Notices lowering speed on RFPT 3A or rising speed on RFPT 3C, or responds alarm 5A-8.

SRO Direct Actions JAW OPDP-1 ATC OPDP-1 Actions Manual Control of Automatic Systems A. If an automatic control or an automatic action is confirmed to have malfunctioned, take prompt actions to place that control in manual or to accomplish the desired function. (e.g. Establishment of manual level control following automatic FCV failure to control level or manual start of an EDG that failed to auto start.)

B. When operating in manual mode, the responsible operator shall coordinate with the Unit Supervisor to specif the frequency of monitoring, control bands and trigger values, as appropriate.

C. When manual operation is no longer required or the automatic function is restored, return systems to automatic or standby mode.

.N D. When practical, before placing controls in manual for activities which require 4 manual control, review system response and actions to be taken during potential off normal events.

Driver when directed by NRC or if the crew decides to scram, verify start value is between 79 and

80. If not modify start value to the current value and ensure final severity is set to 82 and ensure ramp time remains unchanged and then insert trigger 14.

imftcl0b (e14 0) 82 1600 79 33

NRC Scenario 4 Simulator Event Guide:

Event 5 Instrument: RFPT 3A Governor slowly fails low ATC Notices lowering speed on RFPT 3A or rising speed on RFPT 3C, or responds alarm 5A-8.

5A-8, REACTOR WATER LEVEL ABNORMAL A. VERIFY Reactor water level hi/low using multiple indications including Average Narrow Range Level on 3-XR-3-53 recorder, 3-LI-3-53, 3-L1-3-60, 3-LI-3-206, and 3-LI-3-253 on Panel 3-9-5.

B. IF alarm is valid, THEN REFER TO 3-AO1-3-1_or 3-01-3.

ATC Report Reactor level less than 27 inches and lowering, reports RFPT 3A flow has lowered.

Takes manual control of RFPT 3A to attempt to control RPV Level SRO Directs entry 3-A01-3-1, Loss Of Reactor Feedwater or Reactor Water Level High/Low ATC [1] VERIFY applicable automatic actions.

[2] IF level OR Feedwater flow is lowering due to loss of Condensate, Condensate Booster, or Feedwater Pump(s), THEN REDUCE Recirc flow as required to avoid scram on low level.

[4] IF Feedwater Control System has failed, THEN D [4.1] PLACE individual RFPT Speed Control Raise/Lower switches in Manual Governor (depressed position with amber light illuminated).

[4.2] ADJUST RFP Discharge flows with RFPT Speed Control Raise/Lower switches as necessary to maintain level.

[24] IF unit remains on-line, THEN PERFORM the following:

• RETURN Reactor water level to normal operating level of 33(normal range).

• REQUEST Nuclear Engineer check core limits.

Driver when directed by NRC or if the crew decides to scram, verify start value is between 79 and

80. If not modify start value to the current value and ensure final severity is set to 82 and ensure ramp time remains unchanged and then insert trigger 14.

imftcl0b (e14 0) 82 1600 79 34

NRC Scenario 4 Simulator Event Guide:

Q Event 6 Instrument: EHC Pressure Transducer Failure Responds to alarm 7B-6, EHC/TSI SYSTEM A. On EHC Workstation computer on Panel 3-9-7, Alarm Summary screen, ATC/BOP ATTEMPT to RESET alarm input.

B. IF necessary, THEN REQUEST assistance from Site Engineering.

ATC Recognizes lowering Reactor Pressure and generator megawatts.

SRO Directs entry into 3-AOI-47-2.

3-AOI-47-2 Turbine EHC Control System Malfunctions 4.1 Immediate Actions

[11 IF Reactor Pressure lowers to or below 900 psig, THEN MANUALLY SCRAM the Reactor and CLOSE the MSIVs.

4.2 Subsequent Actions

[3] IF a Group 1 isolation has occurred, THEN PLACE EHC PUMP 3A and 3B, 3-HS-47-1A and 3-HS-47-2A, to PULL TO LOCK.

BOP Places EHC Pumps 3A and 3B in Pull to Lock

(

SRO Directs manual scram, closing of the MSIVs, and entry into 3-AO1-100-1.

ATC Manually scrams the reactor.

35

NRC Scenario 4 Simulator Event Guide:

Event 7 Major: ATWS

= ATC 3-AOI-100-1, Reactor Scram 4.1 Immediate Actions

[1] DEPRESS REACTOR SCRAM A and B, 3-HS-99-5AJS3A and 3-HS-99-5AJS3B, on Panel 3-9-5.

[2] IF scram is due to a loss of RPS, THEN PLACE REACTOR MODE SWITCH, 3-HS-99-5A-S1, in START & HOT STBY AND PAUSE for approximately 5 seconds (N/A)

[3] Refuel Mode One Rod Permissive Light check

[3.1] PLACE REACTOR MODE SWITCH, 3-HS-99-5A-S1, in REFUEL.

[3.2] CHECK illuminated REFUEL MODE ONE ROD PERMISSIVE light, 3 -XI-85-46.

[3.3] IF REFUEL MODE ONE ROD PERMISSIVE light, 3-XI-85-46, is NOT illuminated, THEN CHECK all control rod positions at Full-In Overtravel, or Full-In. (N/A)

[4] PLACE REACTOR MODE SWITCH, 3-HS-99-5A-S1, in SHUTDOWN.

[5] REPORT the following status to the US:

• Reactor Scram

• Mode Switch is in Shutdown

• All rods in or rods out

• Reactor Water Level and trend (recovering or lowering).

• Reactor pressure and trend

• MSIV position (Open or Closed)

• Power level 4.2 Subsequent Actions

[2] IF all control rods CAN NOT be verified fully inserted, THEN PERFORM the following:

[2.1] INITIATE ARI by Arming and Depressing BOTH of the following:

ARI Manual Initiate, 3-HS-68-1 19A

• ARI Manual Initiate, 3-HS-68-119B

[2.2] VERIFY the Reactor Recirc Pumps (if running) at minimum speed at Panel 3-9-4.

[2.3] REPORT ATWS Actions Complete and power level.

[3] DRIVE in all IRMs and SRMs from Panel 3-9-5 as time and conditions permit.

[3.1] DOWNRANGE IRMs as_necessary to follow power_as it lowers.

36

NRC Scenario 4 Simulator Event Guide:

Event 7 Component: ATWS SRO Enters EO1- I on Reactor Level SRO EO1-1 (Reactor Pressure)

Monitor and Control Reactor Pressure IF Drywell Pressure Above 2.4 psig? NO IF Emergency Depressurization is Anticipated and the Reactor will remain subcritical without boron under all conditions, THEN Rapidly depressurize the RPV with the Main Turbine Bypass Valves irrespective of cooldown rate? NO-IF Emergency Depressurization is or has been required THEN exit RC/P and enter C2 Emergency Depressurization? NO -

IF RPV water level cannot be determined? NO -

Is any MSRV Cycling? YES, but MSIVs closed IF Steam cooling is required? NO Suppression Pool level and temperature cannot be maintained in the safe area of Curve 3?-NO IF IF Suppression Pool level cannot be maintained in the safe area of Curve 4? NO-IF Drywell Control air becomes unavailable? NO -

IF Boron injection is required? NO SRO Directs a Pressure Band with SRVs lAW APPX hA SRO EOI-l (Reactor Level)

Monitor and Control Reactor Water Level.

Directs_Verification_of PCIS_isolations.

ATC/BOP Verifies PCIS isolations.

SRO IF It has NOT been determined that the reactor will remain subcritical without boron under all conditions THEN Exit RC/L and Enter C5, Level/Power control.

SRO Exits RC/L and Enters 3-C-5, Level/Power Control 37

NRC Scenario 4 Simulator Event Guide:

Event 7 Major: ATWS ATC/BOP Commence pressure control with Appendix hA, Alternate RPV Pressure Control Systems MSRVs IF Drywell Control Air is NOT available, THEN EXECUTE EOI Appendix 8G, CROSSTIE CAD TO DRY WELL CONTROL AIR, CONCURRENTLY with this procedure.

2. IF Suppression Pool level is at or below 5.5 ft, THEN CLOSE MSRVs and CONTROL RPV pressure using other options.

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

a. 1 3-PCV-1-179 MN STM LiNE A RELIEF VALVE.

b. 2 3-PCV-1-180 MN STM LiNE D RELIEF VALVE.

c. 3 3-PCV-1-4 MN STM LiNE A RELIEF VALVE.

d. 4 3-PCV-1-31 MN STM LINE C RELIEF VALVE.

e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALVE.

f. 6 3-PCV-1-42 MN STM LINE D RELIEF VALVE.

g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALVE.

h. 8 3-PCV-1-19 MN STM LINE B RELIEF VALVE.

i. 9 3-PCV-1-5 MN STM LINE A RELiEF VALVE.

10 3-PCV-1-41 MN STM LINED RELIEF VALVE.

k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALVE.

1. 12 3-PCV-1-18 MN STM LINE B RELiEF VALVE.

m._13_3-PC V-1-34 MN_STM LINE C RELIEF VALVE.

38

NRC Scenario 4 Simulator Event Guide:

Event 7 Major: ATWS SRO EO1- I (Power)

Monitor and Control Reactor Power Verify Reactor Mode Switch in shutdown Yes Initiate ARI completed Will tripping Recirc Pumps cause trip of main turbine, RFP, HPCI or RCIC No Is reactor power above 5% or unknown No -

SLC Leg When periodic APRM oscillations greater than 25% peak to peak persist continue OR Before Suppression Pool temperature rises to 110°F continue CT 2 Direct SLC injection (APPX 3A)

CT 1 Inhibit ADS Verify RWCU system isolation completed earlier CT 2 Insert Control Rods Leg Reset ARI and defeat ARI logic trip (APPX 2)

CT 2 lisert Control Rods using any of the following methods:

APPX-1A Deenergize scram solenoids No APPX-1B Vent the scram air header No APPX-1C Scram individual control rods No APPX-1D Drive Control Rods Yes APPX-1E Vent control rod over piston No -

APPX-1F - Reset scram/RE-SCRAM - Yes APPX-1G Raise CR1) cooling water dp No -

39

NRC Scenario 4 c Simulator Event Guide:

Event 7 Major: ATWS ATC Inserting Control Rods CT 2 Calls for 3-EOI Appendix-2 and the field portion of 3-EOI Appendix-iF 3-EOI Appendix-iF

2. WHEN RPS Logic has been defeated, THEN RESET Reactor Scram.

3. VERIFY OPEN Scram Discharge Volume vent and drain valves.

4. DRAIN SDV UNTIL the following annunciators clear:

WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (Panel 3-9-4, 3-XA-55-4A, Window 1)

EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (Panel 3-9-4, 3-XA-55-4A, Window 29).

5. DISPATCH personnel to VERIFY OPEN 3-SHV-085-0586, CHARGING WATER ISOL.

6. WHEN CRD Accumulators are recharged, THEN INITIATE manual Reactor Scram and ARI.

CT 2 3-EOI Appendix-iD

1. VERIFY at least one CRD pump in service.

2. IF Reactor Scram or AR! CANNOT be reset, THEN DISPATCH personnel to CLOSE 3-SHV-085-0586, CHARGING WATER SOV.

3. VERIFY REACTOR MODE SWITCH in SHUTDOWN.

4. BYPASS Rod Worth Minimizer.

5. REFER to Attachment 2 and INSERT control rods in the area of highest power as follows:

a. SELECT control rod.

b. PLACE CRD NOTCH OVERRIDE switch in EMERG ROD IN position UNTIL control rod is NOT moving inward.

c._REPEAT_Steps_5.a_and_5.b_for_each_control_rod to_be_inserted.

Driver When called for Appendix 2 wait 2 minutes and trigger 24, Appendix-iF wait 3 minutes and trigger 23, when SCRAM is reset trigger 25 to unstick rods. Before the crew scrams or the insert trigger 28 for bat nrcatws95 if requested to close 85-5 86 trigger 26 to close and trigger27 to open 40

NRC Scenario 4 Simulator Event Guide:

Event 9 Component: Loss of HPCI 120 VAC Power Supply SRO Enters C-5, Level/Power Control CT 1 Inhibit ADS CT 1 ATC/BOP Inhibits ADS SRO Is any main steam line open No-Is reactor power above 5% or unknown No -

Maintain RPV water level between -180 inches and +51 inches with the following injection sources:

CRD - APPX 5B, RCIC - APPX 5C, SLC - APPX 7B SRO Directs a Level Band maintained by RCIC ATC Initiate RCIC lAW Appendix-SC and maintains level in directed band, if possible BOP Reports Loss of HPCI 120 VAC Power Supply, HPIC NOT available for Level Control Crew Calls for investigation and repair in order to use HPCI for Level control r

41

NRC Scenario 4 Simulator Event Guide:

Event 7 Component: ATWS ATC/BOP Maintain Directed Level Band with RCIC, Appendix 5C.

1. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIP/THROT VALVE RESET.

2. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller in AUTO with setpoint at 600 gpm.

5. OPEN the following valves:

• 3-FCV-71-39, RCIC PUMP INJECTION VALVE

. 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

. 3-FCV-71-25, RCIC LUBE OIL COOLING WTR VLV.

6. PLACE 3-HS-71-3 1A, RC1C VACUUM PUMP, handswitch in START.

7. OPEN 3-FCV-71-8, RC1C TURBINE STEAM SUPPLY VLV, to start RCIC Turbine.

8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rpm.

b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gpm.

c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated.

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE, closes as flow rises above 120 gpm.

9. IF BOTH of the following exist? NO

10. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller as necessary to control injection.

42

NRC Scenario 4 Simulator Event Guide:

Event 7 Component: ATWS Crew Report rising Drywell Pressure SRO Enters EOI-2 on High Drywell Pressure Pc/P Monitor and control PC pressure below 2.4 psig using the Vent System (AOi-64-1),

PC pressure above 2.4 psig unable to vent When PC pressure CANNOT be maintained below 2.4 psig, Continues Before suppression chamber pressure rises to 12 psig Continues Initiate suppression chamber sprays using only those pumps NOT required to assure adequate core cooling by continuous injection (App 17C), Direct Appendix 1 7C When suppression chamber pressure exceeds 12 psig, Stops the first time through when the LOCA worsens will continue at that time is Suppression Pool Level below 19 Feet, YES is Drywell Temperatures and Pressures within the safe area of curve 5, YES CT 5 Directs Shutdown of Recirc Pumps and Drywell Blowers initiate DW Sprays using only those pumps NOT required to assure adequate core cooling by continuous injection (App 17B)

When Suppression chamber pressure CANNOT be maintained in the safe area of Curve 5 Continue, Does not continue 43

NRC Scenario 4 Simulator Event Guide:

Event 7 Component: ATWS Crew Report rising Drywell Pressure SRO Enters EOI-2 on High Drywell Pressure PC/H Verify H202 analyzer in service (APP 19)

When 1-12 is detected in PC (2.4% on control room indicators continue, does not continue SRO Enters EOI-2 on High Drywell Pressure SP/T MONITOR and CONTROL suppr p1 temp below 95°F using available suppr p1 cooling (APPX 17A), Pool Temp below 95° WHEN suppr p1 temp CANNOT be maintained below 95°F, directs RHR Pumps in Pool Cooling Enters EOI-2 on High Drywell Pressure SP/L and CONTROL suppr p1 lvl between -1 in. and -6 in. (APPX 18)

MONITOR Can suppr p1 lvi be maintained above -6 in., YES Can suppr p1 lvi be maintained below -1 in., YES 44

NRC Scenario 4 Simulator Event Guide:

Event 7 Component: ATWS ATC/BOP 3-EOI APPE?DIX-l7A, RHR System Operation Suppression Pool Cooling iF Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN BYPASS LPCI injection valve open interlock AS NECESSARY:

• PLACE 3-HS-.74-155A, LPCI SYS I OUTBD 1NJ VLV BYPASS SEL in BYPASS.

• PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VLV BYPASS SEL in BYPASS.

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

• 3-FCV-23-34, RHR lix 3A RHRSW OUTLET VLV 3-FCV-23-46, RHR lix 3B RHRSW OUTLET VLV

• 3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

• 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

d. IF Directed by SRO, THEN PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE.

e. IF LPCI INITIATION Signal exists, THEN MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT.

f. IF 3-FCV-74-53(67), RHR SYS 1(11) LPCI INBD INJECT VALVE, is OPEN, THEN VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBRJPOOL ISOL VLV.

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.

CAUTION RHR System flows below 7000 gpm or above 10000 gpm for one-pump operation may result in excessive vibration and equipment damage.

ATC/BOP Aligns directed RHR Pumps in Pool Coolmg 45

NRC Scenario 4 Simulator Event Guide:

Event 7 Component: ATWS ATC/BOP 3-EOI APPENDIX-17A, RHR System Operation Suppression Pool Cooling

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11) SUPPR POOL CLG/TEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11) FLOW:

• Between 7000 and 10000 gpm for one-pump operation.

OR

• At or below 13000 gpm for two-pump operation.

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE

k. MONITOR RI-JR Pump NPSH using Attachment 1.

1. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

m. IF Additional Suppression Pool Cooling flow is necessary, THEN PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1.

ATC/BOP . . .

Aligns directed RHR Pumps in Pool Coolmg 46

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA ATC/BOP 3-EOI APPENDIX-17C, RI-JR System Operation Suppression Chamber Sprays

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6.

2. IF Adequate core cooling is assured, OR Directed to spray the Suppression Chamber irrespective of adequate core cooling, THEN BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

3. IF Directed by SRO to spray the Suppression Chamber using Standby Coolant Supply, THEN CONTINUE in this procedure at Step 7.

4. IF Directed by SRO to spray the Suppression Chamber using Fire Protection, THEN CONTINUE in this procedure at Step 8.

5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF EITHER of the following exists:

• LPCI Initiation signal is NOT present, OR

• Directed by SRO, THEN PLACE keylock switch 3-XS-74-122(130), RHR SYS 1(11)

LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRiDE.

c. MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF 3-FCV-74-53(67), RHR SYS 1(11) INBD INJECT VALVE, is OPEN, THEN VERIFY CLOSED 3-FCV-74-52(66), RF{R SYS 1(11) OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBR/POOL ISOL VLV.

g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

ATC/BOP Aligns directed RHR Pumps in Suppression Chamber Sprays 47

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA ATC/BOP 3-EOI APPENDIX-17C, RHR System Operation Suppression Chamber Sprays

h. IF RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN CONTINUE in this procedure at Step 5.k.

i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) M1N FLOW VALVE.

j. RAISE system flow by placing the second RHR System 1(11) pump in service as necessary.

k. MONITOR RHR Pump NPSH using Attachment 2.

1. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

• 3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

• 3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

• 3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

• 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

ATC/BOP Aligns directed RHR Pumps in Suppression Chamber Sprays 48

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA CT 5 ATC/BOP 3-EOI APPENDIX-17B, RHR System Operation Drywell Sprays

1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure at Step 7.

2. IF Adequate core cooling is assured, OR Directed to spray the Drywell irrespective of adequate core cooling, THEN BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11) OUTBD 1NJ VLV BYPASS SEL in BYPASS.

3. VERIFY Recirc Pumps and Drywell Blowers shutdown.

4. IF Directed by SRO to spray the Drywell using Standby Coolant supply, THEN CONTINUE in this procedure at Step 8.

5. IF Directed by SRO to spray the Drywell using Fire Protection, THEN CONTINUE in this procedure at Step 9.

6. INITIATE Drywell Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

• Directed by SRO, THEN PLACE keylock switch 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF 3-FCV-74-53(67), RHR SYS 1(11) LPCI INBD INJECT VALVE, is OPEN, THEN VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired System 1(11) R}IR pump(s) for Drywell Spray.

f. OPEN the following valves:

• 3-FCV-74-60(74), RHR SYS 1(11) DW SPRAY OUTBD VLV

• 3-FCV-74-61(75), RHR SYS 1(11) DW SPRAY INBD VLV.

CT 5 ATC/BOP . .

Aligns directed RHR Pumps in Drywell Sprays 49

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA CT 5 ATC/BOP 3-EOI APPENDIX-17B, RI{R System Operation Drywell Sprays

g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

h. IF Additional Drywell Spray flow is necessary, THEN PLACE the second System II Ri-IR Pump in service.

i. MONITOR RHR Pump NPSH using Attachment 2.

j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

k. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

• 3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

• 3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

• 3-FCV-23-40, RHR FIX 3C RHRSW OUTLET VLV

• 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

1. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

7. WHEN EITHER of the following exists:

• Before drywell pressure drops below 0 psig, OR

• Directed by SRO to stop Drywell Sprays, THEN STOP Drywell Sprays as follows:

a. VERIFY CLOSED the following valves:

• 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE

• 3-FCV-74-60(74), RHR SYS 1(11) DW SPRAY OUTBD VLV

• 3FCV-74-61(75), RHR SYS 1(11) DW SPRAY 1NBD VLV.

b. VERIFY OPEN 3-FCV-74-7(30), RHR SYSTEM 1(11) MEN FLOW VALVE.

c. IF RHR operation is desired in ANY other mode, THEN EXIT this EOI Appendix.

d. STOP RHR Pumps.

CT 5 ATC/BOP Aligns directed RHR Pumps in Drywell Sprays 50

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA SRO C5 Level/Power Control SRO As Level continues to lower with RCIC injection, directs use of SLC APPX-7B CT 2 ATC Initiates SLC lAW APPX 7B

2. IF RPV injection is needed immediately ONLY to prevent or mitigate fuel damage, THEN CONTINUE at Step 10 to inject SLC Boron Tank to RPV.

10. UNLOCK and PLACE 3-HS-63-6A, SLC PUMP 3A13B, control switch in START PUMP 3A or START PUMP 3B (Panel 3-9-5).

11. CHECK SLC injection by observing the following:

. Selected pump starts, as indicated by red light illuminated above pump control switch.

• Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights extinguished,

. SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm (3-XA-55-5B, Window 20).

3-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

• System flow, as indicated by 3-IL-63-11, SLC FLOW, red light illuminated,

• SLC INJECTION FLOW TO REACTOR Annunciator in alarm (3-XA-55-5B, Window 14).

12. IF Proper system operation CANNOT be verified, THEN RETURN TO Step 10 and START other SLC pump.

CT As RPV Level continues to lower, CAN RPV water level be restored and maintained above 6 SRO

-180 inches -No Are at least 2 MSRVs open No -

CT 3 Emergency Depressurization is Required 3-C-2 and 3-C-5 Will the reactor remain subcritical without boron under all conditions NO When all injection into the RPV is stopped and prevented except from RCIC, CRD, and CT 3 SLC_per_CS,_LevellPower_control_Step_CS-22 CT 3 Stop and Prevent ALL injection into RPV Except from RCIC, CRD, and SLC (APPX 4) 51

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA CT 3 BOP/ATC Stop and Prevent ALL injection into RPV Except from RCIC, CRD, and SLC (APPX 4)

3. PREVENT injection from CORE SPRAY following an initiation signal by PLACING ALL Core Spray pump control switches in STOP.

4. PREVENT injection from LPCI SYSTEM I by performing the following:

a. Following automatic pump start, PLACE RI-IR SYSTEM I pump control switches in STOP.

OR

b. BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in BYPASS.

AN])

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

5. PREVENT injection from LPCI SYSTEM II by performing the following:

a. Following automatic pump start, PLACE RHR SYSTEM II pump control W switches in STOP.

OR

b. BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155B, LPCI SYS II OUTBD 1NJ VLV BYPASS SEL in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD iNJECT VALVE.

6. PREVENT injection from CONDENSATE and FEEDWATER by performing the following:

a. IF Immediate injection termination from a reactor feedwater pump is required, THEN PERFORM step 6.d for the desired pump.

c. CLOSE the following valves BEFORE RPV pressure drops below 450 psig:

• 3-FCV-3-19, RFP 3A DISCHARGE VALVE

• 3-FCV-3-12, RFP 3B DISCHARGE VALVE

• 3-FCV-3-5, RFP 3C DISCHARGE VALVE

• 3-LCV-3-53, RFW START-UP LEVEL CONTROL 52

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA CT 6 SRO C2 Emergency Depressurization and C5 Level/Power Control Is suppression pool level above 5.5 feet Yes Open all ADS Valves CT 6 BOP/ATC Opens all 6 ADS Valves SRO Can at least two MSRVs be opened per C2 Emergency RPV Depressurization Yes -

CT 4 When RPV pressure is below MSCP Table 1A 190 psig 4 Start and Slowly raise RPV injection with the following injection sources to restore and CT maintain RPV water level above -180 inches Directs injection with LPCI APPX 6B and 6C to restore RPV Level to directed band CT 4 BOP/ATC Injects with LPCI JAW APPX 6B and/or 6C to restore RPV water level SRO Emergency Classification EPIP-1 1.1-S 1 Reactor water level can NOT be maintained above -162 inches. (TAF)

OR 1.2-S Failure of automatic scram, manual scram, and ARI to bring the reactor subcritical.

53

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA CT 4 BOP/ATC Injects with LPCI JAW APPX 6B to restore RPV water level

1. IF Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in BYPASS.

2. VERIFY OPEN 3-FCV-74-l, RHR PUMP 3A SUPPR POOL SUCT VLV.

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VLV.

4. VERIFY CLOSED the following valves:

• 3-FCV-74-61, RHR SYS I DW SPRAY INBD VLV

• 3-FCV-74-60, RHR SYS I DW SPRAY OUTBD VLV

• 3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VLV

• 3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

• 3-FCV-74-59, RI-IR SYS I SUPPR POOL CLG/TEST VLV

5. VERIFY RHR Pump 3A and/or 3C running.

6. WI-lEN RPV pressure is below 450 psig, THEN VERIFY OPEN 3-FCV-74-53, RHR SYS 1 LPCI INBD INJECT VALVE.

7. IF RPV pressure is below 230 psig, THEN VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE.

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD iNJECT VALVE, as necessary to control injection.

9. MONITOR RHR Pump NPSH using Attachment 1.

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV.

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

• . 3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

• . 3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV.

54

NRC Scenario 4 Simulator Event Guide:

Event 8 Major: LOCA CT 4 BOP/ATC Injects with LPCI LAW APPX 6C to restore RPV water level

1. IF Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VLV BYPASS SEL in BYPASS.

2. VERIFY OPEN 3-FCV-74-24, RHR PUMP 3B SUPPR POOL SUCT VLV.

3. VERIFY OPEN 3-FCV-74-35, RHR PUMP 3D SUPPR POOL SUCT VLV.

4. VERIFY CLOSED the following valves:

• 3-FCV-74-75, RHR SYS II DW SPRAY 1NBD VLV

• 3-FCV-74-74, RHR SYS II DW SPRAY OUTBD VLV

• 3-FCV-74-71, RHR SYS II SUPPR CHBR/POOL ISOL VLV

• 3-FCV-74-72, RHR SYS II SUPPR CHBR SPRAY VALVE

• . 3-FCV-74-73, RHR SYS II SUPPR POOL CLG/TEST VLV

5. VERIFY RHR Pump 3B and/or 3D running.

6. WHEN RPV pressure is below 450 psig, THEN VERIFY OPEN 3-FCV-74-67, RHR SYS II LPCI 1NBD INJECT VALVE.

7. IF RPV pressure is below 230 psig, THEN VERIFY CLOSED 3-FCV-68-3, RECIRC PUMP 3A DISCHARGE VALVE.

8. THROTTLE 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE, as necessary to control injection.

9. MONITOR RHR Pump NPSH using Attachment 1.

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV.

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

• . 3.-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

• 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

55

NRC Scenario 4 SHIFT TURNOVER SHEET Equipment Out of Service[LCOs:

RFPT 3B and EECW Pump A3 Operations/Maintenance for the Shift:

Alternate Reactor Zone Fans and then Refuel Zone Fans lAW 3-OI-30B and 30A.

Commence a power increase to 85% in accordance with the RCP Unit 1 and 2 are at 100% Power Unusual Conditions/Problem Areas:

The following Control Rods are identified as SLOW: 30-19, 34-23, 14-51, 02-19, 46-51, and 06-43.

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