ML101610660

301 Final Simulator Scenarios (Section 10)

ML101610660
Person / Time
Site:	Summer
Issue date:	03/28/2010
From:	NRC/RGN-II
To:
References
2005-301, 50-395/05-301
Download: ML101610660 (62)

Text

Appendix 0 Facility:

V. C. Summer Examiners:

Initial Conditions:

100% IC, AT MOL. Scenario Outline Final Scenario No.: 1 Operators:

Op-Test No.: Form ES-O-1 2005-301 CRS RO PO Turnover:

Thunder storms in the area, severe weather check list being implemented. "A 1" train maintenance week. S/G A Small tube leak, approx. 8 gpd; MAL-RCS002A.

Motor Driven EFW Pump 'A' Impeller replacement in progress with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to complete, have done 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> so far. B S/G rad monitor (RMG-19B) is OOS. Event Event Type*

Event Description No. 1 RO (I) Turbine Impulse Pressure Transmitter PT-446 Fails Low. 2 BOP (I) Steam Generator Steam Flow Transmitter Failure, 474 fails LOW. RO (C) VCT suction valve 115C fails closed (hot short at motor). This will cause the 3 SRO (TS) running Charging pump to cavitate and fail requiring entry into AOP-1 02.2 BOP(N) and TS evaluation of loss of one CCP. SRO(TS) The building operator calls the control room and reports that, while on his 4 rounds, he discovered a significant amount of oil on the floor in the TDEFP room and it appears that the governor may have leaked all its oil onto the floor. RO (R) Reduce power to take the unit off line. In accordance with GOP-4B Power 5 BOP (N) Operation Mode 1 (Descending Power). MDS calls and requests that due to approaching severe thunderstorm he would like to increase the power descension rate to 1 %/min. BOP (C) During the Down power, the 0 FRV fails as is, this will cause the operator to 6 have to place the 0 FRV in manual and control the A SG in manual during the Shut Down. (AOP-21 0.1). 7 RO(C) SG Tube Leak on the "c" SG, ramping to approximately the output of the SRO(TS) existing charging pump(s). Ramp up over a 5 minute period. (AOP-112.2).

M (All) S/G tube rupture on the C SG to full flow of a tube (600 gpm ramped in over 3 8 min), requires reactor trip. The Reactor will not trip (ATWS) (EOP-13.0, Entry, Response to Abnormal Nuclear Power Generation).

BOP (C) When the reactor trips there is a Loss of power on the lOB emergency bus 9 due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 1 Page --L of 2Q.. Event

Description:

Turbine Impulse Pressure Transmitter PT-446 Fails Low. Time Position Applicant's Actions or Behavior AOP-401.7 RO Operator acknowledges annunciator 6152-5 (RCS TAVG-TREF DEV HI/LO), recognizes IPT0446 failure, and responds lAW AOP-401.7 RO Place ROD CNTRL BANK SEL Switch in MAN. RO Ensure TREF 1 ST STG PRESS Switch is positioned to the operable channellPT0447, CH IV). RO Adjust Control Rods until Tavg is within I.O°F of Tref. RO Check if Main Turbine load Is GREATER THAN 10%. Within one hour, verify the following permissives are dim: RO P13. 1ST STG PRESS. P7. REACTOR TRIP BLOCKED. Restore automatic rod control: a. Check if automatic rod control is desired. b. Verify reactor power is GREATER THAN 15% (C-5 status light dim). RO c. Verify Tavg is within I.O°F of Tref. d. Place ROD CNTRL BANK SEL Switch in AUTO (Crew may choose to return the rods to 230 steps prior to returning rods to auto but this is considered a good practice, not a requirement).

BOP Place STM DUMP MODE SELECT in STM PRESS. BOP Notify I&C to place AMSAC in BYPASS Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, place the failed channel bistables in a tripped condition.

SRO SRO evaluation of Tech Spec Table 3.3.3 (allow crew to fill out bistable trip sheet before moving on to next event Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page 3 of ..1.2.--Event

Description:

Steam Generator Steam Flow Transmitter Failure, 474 fails LOW. Time Position Applicant's Actions or Behavior AOP-401.3 BOP The BOP operator acknowledges annunciator 624 4-4 in alarm, recognizes the failure of IFT0474 and responds lAW AOP-401.3 BOP Depending on response time, annunciator 6241-5 (SG A LVL DEV) may also alarm. BOP Verify the failed channel is the controlling channel. Select the operable flow channel: BOP Place FW CONTROL CHANNEL SEL Switch to the operable channel. Place STEAM CONTROL CHANNEL SEL Switch to the operable channel. Verify Turbine Load is LESS THAN 950 MWe. Preferred is % turn on limiter. Using any method available, reduce Turbine Load by 40 MWe to 50 BOP MWe. (The preferred method is Yz turn on the load limiter) (The crew may decide to borate to avoid RAOC concerns and, if so, would likely turn on BU heaters for improved mixing. This would not be required for such a small load decrease but would be a good practice).

Expected plant response = rods step in and Group 1 steam dumps open. BOP Verify only one SG is AFFECTED.

BOP Adjust the Feedwater Flow Control Valve as necessary to restore feed flow to the AFFECTED SG. BOP Restore Narrow Range level in all SGs to between 60% and 65%. Check if Feedwater Pump speed control is operating properly:

a. Feedwater Header pressure is GREATER THAN Main Steam BOP pressure.

b. Feed flow is normal for flow and power level. c. All operating Feedwater Pump speeds and flows are balanced BOP Verify Narrow Range level in all SGs is normal. Restore the AFFECTED SG control systems to normal: BOP Place the Feedwater Flow Control Valve in AUTO. Place the Feedwater Pump Speed Control System in AUTO. REFER TO SOP-210, FEEDWATER SYSTEM. SRO Within six hours, place the failed channel protection bistables in a tripped condition:

SRO evaluates Tech Spec Table 3.3-3 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page of .2Q.. Event

Description:

VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior AOP*102.2 Operator acknowledges that annunciators 614 4-2 (CHG PP B/C TRIP), RO 6145-1 (CHG LINE FLO HI/LO), 6172-2,6182-2, & 619 2-2 (RCP A, B, C #1 SEAL INJ FLO LO) are all in alarm, recognizes the "B" Charging Pump has tripped, and responds lAW AOP-102.2 Check if Charging Pump flow is normal: IF Charging Pump has tripped or flow is abnormal, THEN perform the following:

o Ensure the Charging Pump is secured. o Close all Letdown Isolation Valves: PVT-8149A(B)(C), LTDN ORIFICE A(B)(C) ISOL. PVT-8152, LTDN LINE ISOL. RO LCV-459, L TDN LINE ISOL. LCV-460, L TDN LINE ISOL. (Expected plant response = RML*1 alarm on Letdown Isolation.)

o Close FCV-122, CHG FLOW. o Verify CCW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), THERM BARR FLOW GPM. n Display Dedicated Display ZZRCPBRG on the IPCS to monitor RCP temperatures. (RML-1 expected alarm -letdown isolation.)

CRS/SE o Contact Electrical and Mechanical Maintenance to investigate.

Verify Charging System valve lineup: RO o IF Charging Pump suction is aligned to the VCT, THEN ensure both LCV-115C(E), VCT OUTLET ISOL, are open. CRS/SE Send someone to locally open the breaker for valve 115C and then to manually open the valve. SRO SRO evaluates Tech Spec 3.5.2 and determines 72 hr. action statement.

o Ensure the following valves are open: MVG-81 06, CHG PP. MVT-8109A(B)(C), CHG PP A(B)(C). RO MVG-8130A(B), LP A SUCT TO CHG PP c. MVG-8131A(B), LP B SUCT TO CHG PP c. MVG-8132A(B), CHG PP C TO LP A DISCH. MVG-8133A(B), CHG PP C TO LP B DISCH o Check the Charging header valve lineup as follows: RO Ensure MVG-81 07, CHG LINE ISOL, is open. Ensure MVG-8108, CHG LINE ISOL, is open. Ensure FCV-122, CHG FLOW, is in MAN and CLOSE. RO Ensure the following valve is open:

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page 5 of .22-Event

Description:

VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior PVT-8147, ALT CHG TO RCS LP A. D Locally verify Charging Pump suction pressure is between 50 psig BOP and 100 psig as indicated on the following (building operator to report 52 psig): PI-151A, SUCTION PRESS, for Charging Pump A. With Shift Supervisor's permission, start a Charging Pump, while RO monitoring RCP temperatures.

REFER TO SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM. (SEE SOP 102 section III.B below) WHEN a Charging Pump is operating, THEN place Charging and RO Normal Letdown in service .. REFER SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM. (SEE SOP-102 Section IV.M below) SOP-102 Section III.B Crew instructs the building operator to perform Attachment VB (Floor instructor to provide copy of Attachment VB if requested by crew) to mechanically and electrically align "C" charging pump to "B" Train. (If SRO the crew chooses, they might start "A" CCW pump and "A" charging pump to get a charging pump back while they are waiting to get "C" charging pump racked up on "B" Train. If so the steps below are nearly identically except for "A" Train component numbers) RO To start XPP-0043C, PUMP C, on miniflow, complete Attachment VB if Charging Pump C is to be aligned to Train B. Following the completion of Attachment VA(B), Chilled Water Expansion Tank levels should be monitored for indications of equalization:

Building 1) L9004A, CHILLED WATER EXPANSION TNK A LV, or ILl09004-VU, CHILL WATER EXP TK A LEVEL IND (IB-412).

2) L9006A, CHILLED WATER EXPANSION TNK B LV, or ILl09006-VU, CHILL WATER TK B LEVEL IND (IB-412).

Verify PI-121, CHG PRESS PSIG, is between 2650 psig and 2850 psig. Monitor the following for proper pump operation:

RO a. LR-459, PZR % LEVEL & LEVEL SP. b. FI-130A, RCP A INJ FLO GPM. c. FI-127A, RCP B INJ FLO GPM. d. FI-124A, RCP C INJ FLO GPM. RO Ensure the B train of Component Cooling is operating per SOP-118. RO Ensure the B train of Chill Water is operating per SOP-501. RO Ensure XPP-43C-PP1, CHG PP C AUX OIL PP, is running. Building Verify IP100153A, CHG PUMP C SUCT HDR PRESS IND, indicates Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page 6 of 2Q.. Event

Description:

VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior pump suction pressure is greater than 15 psig (AB-388).

RO Start XPP-0043C, PUMP C. (PEER D) RO Verify XPP-43C-PP1, CHG PP C AUX OIL PP, stops automatically when the Charging Pump comes up to full speed. Building Verify IP100153A, CHG PUMP C SUCT HDR PRESS IND, indicates pump suction pressure is greater than 15 psig (AB-388).

Monitor the following to verify proper pump operation:

1) Charging Pump C running current is between 30 amps and RO 50 amps. 2) PI-121, CHG PRESS PSIG, is between 2650 psig and 2850 psig. 3) XVG-9684C-CC, CCW TO CHG PP C, is open. SOP-102 Section IV.M RO Place FCV-122, CHG FLOW, in MAN and close. RO Place PCV-145, LO PRESS LTDN, in MAN and open to 70%. (PEER D) RO Place TCV-144, CC TO L TDN HX, in MAN and open to 100%. RO Place TCV-143, LTDN TO VCT OR DEMIN, in VCT. RO Open PVT-8152, LTDN LINE ISOL. Open the following:

RO a. LCV-459, L TDN LINE ISOL. b. LCV-460, L TDN LINE ISOL. Ensure the following Charging Line Isolation Valves are open: RO a. MVG-8107, CHG LINE ISOL. b. MVG-8108, CHG LINE ISOL. RO Slowly open FCV-122, CHG FLOW, to establish 60 gpm flow as indicated on FI-122A, CHG FLOW GPM. Open Orifice Isolation Valves to obtain the desired Letdown flow rate (60 gpm to 120 gpm): RO a. PVT-8149A, LTDN ORIFICE A ISOL (45 gpm). b. PVT-8149B, LTDN ORIFICE B ISOL (60 gpm). C. PVT-8149C, LTDN ORIFICE C ISOL (60 gpm). Adjust FCV-122, CHG FLOW, as required to maintain TI-140, REGEN RO HX OUT TEMP of, between 250°F and 350°F while maintaining Pressurizer level. RO Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS L TDN PRESS PSIG, between 300 psig and 400 psig.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page --1-of .22..-----Event

Description:

VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior RO Place PCV-145, LO PRESS LTON, in AUTO. Adjust TCV-144, CC TO LTON HX, potentiometer as necessary to RO maintain the desired VCT temperature and place in AUTO. Refer to VCS Curve Book, Figure V11.15. RO When Pressurizer level matches reference level, place FCV-122, CHG FLOW, in AUTO per Section IV. RO After the Letdown temperatures have stabilized, place TCV-143, L TON TO VCT OR OEMIN, in OEMIN/AUTO.

Can move on to next event when chg and letdown restored (no need to wait until level deviation cleared).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 4 Page --L of 2Q.. ---Event

Description:

The building operator calis the control room and reports that, while on his rounds, he discovered a significant amount of oil on the floor in the TDEFP room and it appears that the governor may have leaked ali its oil onto the floor. Time Position Applicant's Actions or Behavior Building Building operator reports oil leak on TDEFP governor (FCV now). Crew determines TDEFP is inoperable and decides to remove it from service by taking both 2030 valve switches to the closed position.

Both SRO/BOP annunciators 623 2-3 and 622 2-3 (TD EFP AUTOSTART DEFEATED) alarm as the 2030 valves close. (May also choose to disable the TDEFP by tripping the Trip & Throttle valve or by closing and removing power from 2802A & 2802 B). SRO SRO evaluates Tech Spec 3.7.1.2 and determines that a plant shutdown is necessary (Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page 9 of 2Q.. ------Event

Description:

Reduce power to take the unit off line. In accordance with GOP-4B Power Operation Mode 1 (Descending Power). MDS calls and requests that due to approaching severe thunderstorm he would like to increase the power descension rate to 1 %/min. Time Position Applicant's Actions or Behavior GOP-4B Reduce load by one of the following methods: BOP 1) By use of the DEC LOAD RATE circuit 2) By use of the load limiter SRO MDS calls and requests that the load decrease be raised to 1 %/min because of approaching severe thunderstorm.

As load decreases, adjust Megavars using GEN FIELD VOL T ADJ as BOP requested by the Load Dispatcher and within the Estimated Generator Capability Curve (Enclosure A). RO Maintain Tavg within the control band by Control Rod motion or boron concentration changes. Borate per SOP-106, Reactor Makeup Water System, to maintain the following parameters: (Good practice to turn on Backup heaters during RO boration to improve mixing but not procedurally required)

1) within limits. 2) Control Rods above the Rod Insertion Limit.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 6 Page...:!.Q...

of ..lQ.. -Event

Description:

During the Down power, the 0 FRV fails as is, this will cause the operator to have to place the 0 FRV in manual and control the A SG in manual during the Shut Down. (AOP-21 0.1). Time Position Applicant's Actions or Behavior AOP-210.1 As load decreases, BOP operator notices that FCV-0478 is failed as is and takes manual control of the valve lAW AOP-21 0.1. (Could possibly BOP receive annunciator 624 1-5 SG A L VL DEV.) Crew may also decide to conservatively stop the load reduction until they can determine that they have manual control of the valve but this would not be required because it is not in the procedure.

Manually adjust the AFFECTED Feedwater Flow Control Valve as necessary to maintain Narrow Range SG level between 60% and 65%: BOP o PVT-478, SG A FWF. o PVT-488, SG B FWF. o PVT-498, SG C FWF. SRO Dispatch I&C to determine cause of auto control failure.

Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 7 Page 11 of 20 -Event

Description:

SG Tube Leak on the "e" SG, ramping to approximately the output of the existing charging pump(s). Ramp up over a 5 minute period. (AOP-112.2).

Time Position Applicant's Actions or Behavior RO RO acknowledges that annunciator 6462-1 (MN STM LINE RMG-19 HI RAD) is in alarm and pulls the ARP. RO Verify the alarm is valid and identify the Main Steam line affected by observing RM-G19A, B, and C and RlR-8. SRO Request Health Physics perform radiological surveys around the Main Steam lines. SRO Direct Chemistry to sample all Steam Generators for activity.

Align the condenser exhaust to the Auxiliary Building Charcoal Exhaust as follows: Building a. Open XVB0011O-AR, MN&AUX COND VAC PP CHAR EXH DISCH VALVE (TB-436).

b. Close XVB00109-AR, MN&AUX COND VAC PUMP ATMOS DISCH VALVE (TB-436).

BOP Reduce all Steam Generator blowdown flows to minimum. SRO If the alarm is valid, refer to AOP-112.2.

AOP-112.2 (approx 90% power) If they have not already done so in previous event, the crew may elect to Note stop the load reduction and stabilize power at this point (but not required by procedure).

Check if PZR level can be maintained:

a. Open FCV-122, CHG FLOW, as necessary to maintain PZR level RO this will cause annunciator 614 5-1 (CHG LINE FLO HI/LO) to alarm -expected alarm). b. Verify PZR level is at or trending to program level. BOP The tube leak may eventually cause annunciator 624 3-5 (SG C LVL DEV) to alarm (expected alarm). Reduce Letdown to one 45 gpm orifice. a) Set PCV-145, LO PRESS LTDN, to 70%. b) Ensure PVT-8149A, LTDN ORIFICE A ISOL, is RO c) Close both PVT-8149B(C), LTDN ORIFICE B(C) ISOL. d) Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS L TDN PRESS PSIG, between 300 psig and 400 psig. e) Place PCV-145, LO PRESS LTDN, in AUTO. IF PZR level continues to decrease, THEN perform the following RO Close PVT-8149A, LTDN ORIFICE A ISOL. RML-1 should alarm due to letdown isolation (expected alarm) SRO Check if 51 is required At some point near this step Pressurizer Pressure will drop below the Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 7 Pag e...1L of .22.. --Event

Description:

SG Tube Leak on the "C" SG, ramping to approximately the output of the existing charging pump(s). Ramp up over a 5 minute period. (AOP-112.2).

Time Position Applicant's Actions or Behavior Tech Spec 3.2.5 DNB value of 2206#. The SRO should evaluate and verbalize the 2 hr. LCO RO Verify VCT level is being maintained between 20% and 40%. Estimate the RCS leak rate using IPCS CHGNET. Calculate the RCS leak rate. lAW STP-114.002, OPERATIONAL LEAK SRO/SE TEST. Comply with Tech Spec 3.4.6.2 action statement.

Determines that shutdown to mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is required Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 8 Page.....:!1...

of 2Q.. Event

Description:

S/G tube rupture on the C SG to full flow of a tube (600 gpm ramped in over 3 min), requires reactor trip. The Reactor will not trip (ATWS) (EOP -13.0, Entry, Response to Abnormal Nuclear Power Generation).

Time Position Applicant's Actions or Behavior Tube rupture 600 gpm ramp over 3 min after Tech Spec eval. Acknowledges annunciator 616 1-5 (PZR LCS DEV HIILO and responds lAW direction of CRS or if time allows lAW ARP. SRO CRS directs the RO to insert a manual reactor trip and that they will actuate SI when directed by EOP-1.0 EOP-13.0 RO Verify Reactor Trip: Trip the Reactor using both Reactor Trip Switches.

RO IF the Reactor will NOT trip OR is NOT subcritical, THEN insert Control Rods at the fastest control rod insertion rate CRITICAL SRO Direction given to trip the reactor locally using Attachment 1 Follow-up question -may ask SRO to classify this emergency event (Site Area Emergency)

Verify Turbine/Generator Trip: BOP Verify all Turbine STM STOP VLVs are closed. Depress Emerg Trip Sys TRIP. Ensure Generator Trip I (after 30 second delay) BOP 1) Ensure the GEN BKR is open. 2) Ensure the GEN FIELD BKR is open. 3) Ensure the EXC FIELD CNTRL is tripped. Ensure EFW Pumps are running: BOP starts "B" EFW Pump (It has BOP not auto started because SG level is not yet below 35% and SI has probably not yet actuated.)

Initiate emergency boration of the RCS: Ensure at least one Charging Pump is running. Verify PZR pressure is LESS THAN 2335 psig. RO Verify SI ACT status light is NOT lit. Verify SI flow on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. GO TO Step 5. Observe the CAUTION prior to Step 5. (Emergency boration is not required if SI has actuated by this point and SI flow is verified)

Building Operator locally trips the RTBs at this point. Building Verify all Reactor Trip and 'Bypass Breakers are open. Verify all Rod Bottom Lights are lit. Verify Reactor Power level is decreasing.

5 Verify Containment Ventilation Isolation Valves closed by RO verifying the Safety INJECTION monitor lights are dim, (Time permitting, perform EOP-1.0 steps 1 -8 in conjunction with this Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 8 Page --2i. of 22.. ----Event

Description:

S/G tube rupture on the C SG to full flow of a tube (600 gpm ramped in over 3 min), requires reactor trip. The Reactor will not trip (ATWS) (EOP -13.0, Entry, Response to Abnormal Nuclear Power Generation).

Time Position Applicant's Actions or Behavior procedure)

Appendix 0 Required Operator Actions Form ES-O-2 Op Test No.: --L Scenario No.: 1 Event No.: 9 Page ....:!.?.

of 2Q.. Event

Description:

When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

Time Position Applicant's Actions or Behavior BOP operator notes that there is no power on IDB and that the diesel did BOP not start. He notes that there is a lockout on XFMR-XTF31 (by recognizing annunciator 639 4-2 in alarm). BOP operator also notes that annunciator 6376-1 (DG B ENG START FAIL) is in alarm BOP operator depresses the "B" DG Emergency Start Pushbutton and BOP notes that the diesel does start and the DG breaker does close to energize 1 DB. Verify the Reactor is subcritical:

Power Range channels indicate RO LESS THAN 5%. Intermediate Range channels indicate a negative startup rate SRO GO TO Step 15. Observe the CAUTION prior to Step 15. SRO RETURN TO the Procedure and Step in effect (EOP-1.0).

EOP-1.0 Verify Reactor Trip: Trip the Reactor using either Reactor Trip Switch. RO Verify all Reactor Trip and' Bypass Breakers are open. Verify all Rod Bottom Lights are lit. Verify Reactor Power level is decreasing.

Verify Turbine/Generator Trip: Verify all Turbine STM STOP VLVs are closed. BOP Ensure Generator Trip (after 30 second delay): Ensure the GEN BKR is open. Ensure the GEN FIELD BKR is open. Ensure the EXC FIELD CNTRL is tripped. BOP Verifies Power on both ESF busses At some point after the reactor trip Hi Rad on RMA-09. 645 1-3 CNDSR EXH RM-A9 HI RAD should come in and is an expected alarm with a tube rupture. Check if 51 is actuated:

RO Check if either SI ACT status light is bright on XCP-6107 1-1 or Any red first-out SI annunciator is lit on XCP-626 top row. Actuate SI using either SI ACTUATION Switch. Complete ATTACHMENT 3,51 EQUIPMENT VERIFICATION. (If not BOP already done, the BOP operator should be throttling EFW flow to zero to the "C" SG because it has been identified as the ruptured SG).OAP-103.4 SRO Announce plant conditions over the page system. RO Verify RB pressure has remained LESS THAN 12 psig on PR-951, '

Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 9 Page of 2Q... Event

Description:

When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

Time Position Applicant's Actions or Behavior RB PSIG (P-951), red pen. Check RCS temperature:

With any RCP running, RCS Tavg is stable at OR trending to 55rF. BOP WHEN Narrow Range SG level is GREATER THAN 30% [50%] in at least one SG, THEN control EFW flow as necessary to stabilize RCS temperature at 55rF. Check PZR PORVs and Spray Valves: PZR PORVs are closed. PZR Spray Valves are closed. RO Verify power is available to at least one PZR PORV Block Valve. MVG-8000A, RELIEF 445 A ISOL. MVG-8000B, RELIEF 444 B ISOL. MVG-8000C, RELIEF 445 B ISOL. Verify at least one PZR PORV Block Valve is open Check if RCPs should be stopped: RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on RO FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. Note: RCS pressure should be about 1800 psig so no RCP trip should be required.

Verify no SG is FAULTED: BOP No SG pressure is decreasing in an uncontrolled manner. No SG is completely depressurized.

Verify Secondary radiation levels indicate SG tubes are NOT RUPTURED:

RO RM-G19A(B)(C), STMLN HI RNG GAMMA. RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR. RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR. RM-L 10, SG BLOWDOWN CW DISCHARGE LIQUID MONITOR. CRITICAL SRO GO TO EOP-4.0, STEAM GENERATOR TUBE RUPTURE, Step 1. Check if RCPs should be stopped: Check if either of the following criteria is met: Annunciator XCP-612 4-2 is lit (PHASE B ISOL). RO OR RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. Note: RCS pressure should be about 1800 psig so it should not be necessary to secure any RCPs SRO Identify the RUPTURED SG(s):

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: ......L. Scenario No.: _1_ Event No.: ..L Page ..JL of .2Q.. Event

Description:

When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

Time Position Applicant's Actions or Behavior Narrow Range level in any SG increasing in an uncontrolled manner, OR High Radiation on any of RM-G19A(B)(C), STMLN HI RNG GAMMA, OR Local hand held radiation monitor readings taken by Health Physics on the blowdown lines at following penetrations:

XRP0326, SG A Blowdown Line (AB-412 West Pen). XRP0224, SG B Blowdown Line (IB-412 East Pen XRP0219, SG C Blowdown Line (IB-412 East Pen), OR As determined by Chemistry ample analysis for abnormal activity using a frisker. Isolate flow from each RUPTURED SG: Place the Steam line PWR RELIEF A(B)(C) SETPT Controller(s) in MAN and closed. BOP Adjust the PWR RELIEF A(B)(C) SETPT Controller(s) to 8.85 (1150 psig). Place the Steamline Power Relief A(B)(C) Mode Switch(s) in PWR RLF. Place the PWR RELIEF A(B)(C) SETPT Controller(s) in AUTO. BOP WHEN RCS Tavg is LESS THAN P-12 (552°F), THEN place both STM DUMP INTERLOCK Switches to BYP INTLK. BOP Verify the Steamline PORV closed. BOP IF at least one MD EFW Pump is running, THEN isolate the TD EFW Pump by placing PVG-2030, STM SPL Y TO TD EFP to CLOSE. Open XMC1DB2Y 05EH, EMERG FEEDWATER PUMP MAIN STEAM BOP/Bldg BLOCK XVG2802B-MS (AB-463).

Close XVG02802B-MS, MS HEADER C EF PUMP TURBINE SUPPL Y VLV Close the following for each RUPTURED SG: BOP SG Blowdown, PVG-503A(B)(C).

MS Drain Isolation, PVT-2843A(B)(C).

MS Drain Isolation, PVT-2877B for SG C. Close the following for each RUPTURED SG: BOP MS Isolation Valve, PVM-2801A(B)(C AND MS Isolation Bypass PVM-2869A(B)(C).

Verify Narrow Range level in each RUPTURED SG is GREATER THAN 30% [50%]. BOP a. Stop EFW flow to each RUPTURED SG: 1) Close FCV-3551, MD EFP TO SG C. 2) Close FCV-3556, TD EFP TO SG C. 3) Maintain Narrow Range level in C SG GREATER THAN 40% [50%]. BOP/SRO Verify each RUPTURED SG pressure is GREATER THAN 350 psig. SRO Determine the required core exit TC temperature for RCS cooldown.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page ---2!L of 22-Event

Description:

When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

Time Position Applicant's Actions or Behavior SRO/RO Check if any RCP is running (all running).

Dump steam from each INTACT SG: WHEN RCS Tavg is LESS THAN P-12 (552"F), THEN: Place both STM DUMP INTERLOCK Switches to BYP INTLK. Place both STMLN SI TRAIN A(B) Switches to BLOCK. BOP Verify PERMISV C-9 status light is bright on XCP-6114 1-3. Verify the MS Isolation to open.Valves, PVM-2801A & B are open Place the STM DUMP CNTRL Controller in MAN Place the STM DUMP MODE SELECT Switch in STM PRESS. Adjust the STM DUMP CNTRL Controller to fully open the Bank 1 Steam Dump Valves. RO While cooling down, a high vibration on "C" RCP may occur. If so, secure RCP "C" a required by SOP*101 BOP Verify Narrow Range level in SGs A & B 30% [50%]. BOP Control EFW flow to maintain in SGs between 40% [50%] and 60%. RO Verify power is available to the PZR PORV Block Valves: RO Verify all PZR PORVs are closed. RO Verify at least one PZR PORV Block Valve is open. RO Reset both SI RESET TRAIN A{B) Switches.

Reset Containment Isolation:

RO RESET PHASE A -TRAIN A(B) CNTMT ISOL. RESET PHASE B -TRAIN A(B) CNTMT ISOL. Place both ESF LOADING SEQ A{B) RESETS to: BOP a. NON-ESF LCKOUTS. b. AUTO-START BLOCKS. Establish Instrument Air to the RB: RO a. Start one Instrument Air Compressor and place the other in Standby. b. Open PVA-2659, INST AIR TO RB AIR SERVo C. Open PVT-2660, AIR SPLY TO RB. RO Stop both RHR pumps SRO Verify core exit TC temperature is LESS THAN the value determined in Steps 8 through 10 Stop the RCS cooldown:

BOP a. Ensure Step 10 is completed.

b. Adjust steam dump setpoints as necessary to maintain desired core exit TC temperature.

BOP Verify each RUPTURED SG pressure is stable OR increasing.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page ...:!2.. of 2Q.. Event

Description:

When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

Time Position Applicant's Actions or Behavior RO/SRO Verify RCS subcooling on TI-499A(B), A(B) TEMP is GREATER THAN 50°F. Depressurize the RCS using Normal PZR Spray at the maximum rate: (PCV-444C should not be opened if "c" RCP has been secured in a previous step) CRITICAL Using RCP A: 1) Open PCV-444D, PZR SPRAY. RO 2) Close PCV-444C, PZR SPRAY, if RCP C is NOT running Using RCPs BAND C: 1) Open PCV-444C, PZR SPRAY. 2) Close PCV-444D, PZR SPRAY, if RCP A is NOT running. Use maximum available spray until anyone of the following criteria is met: PZR level is GREATER THAN 68% [54%]. OR RCS subcooling on TI-499A(B), A(B) TEMP "F, is LESS THAN 30"F. OR RCS pressure is LESS THAN RUPTURED SG(s) pressure AND PZR level is GREATER THAN 18% [38%]. Upon meeting one of the above criteria, Stop RCS depressurization:

RO 1) Close both PCV-444C(D), PZR SPRAY. 2) Close PVT-8145, PZR SPRAY FR CVCS. Check if SI flow should be terminated:

a. RCS subcooling on TI-499A(B), is GREATER 30"F b. Secondary Heat Sink is adequate:

RO/BOP (Total EFW flow available to INTACT SGs is GREATER THAN 450 gpm. OR Narrow Range SG level is GREATER THAN 30% [50%] in at least one INTACT SG.) c. RCS pressure is stable OR increasing.

d. PZR level is GREATER THAN 18% [38%]. RO Stop all but one Charging Pump and place in Standby. Establish Normal Charging:

a. Close FCV-122, CHG FLOW. RO b. Open both MVG-8107 and MVG-81 08, CHG LINE ISOL. c. Adjust FCV-122, CHG FLOW, to obtain 60 gpm Charging flow. d. Close both MVG-8801A(B), HI HEAD TO COLD LEG INJ. RO Control FCV-122, CHG FLOW, to maintain PZR level. Verify SI flow is NOT required:

RO a. RCS subcooling on TI-499A(B), is GREATER THAN '30"F. b. PZR level is GREATER THAN 18% [38%]. This is the endpoint of this JPM or as directed by the NRC.

Appendix D Required Operator Actions Form ES*D*2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page -2.£.. of 22------Event

Description:

When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.

The Emergency Diesel generator does not start automatically.

Time Position Applicant's Actions or Behavior

Appendix D Facility:

V. C. Summer Examiners:

Scenario Outline Final Scenario No.: 2 Operators:

Form ES-D-1 Op-Test No.: 2005-301 CRS RO PO Initial Conditions:

At approximately 39% power and increasing.

Turnover:

Thunder storms in the area, severe weather check list being implemented. "A 1" train maintenance week. S/G A Small tube leak, approx. 8 gpd; MAL-RCS002A.

Motor Driven EFW Pump 'A' Impeller replacement in progress with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to complete, have done 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> so far. B S/G rad monitor (RMG-19B) is OOS. At the point of the GOP-4 Step 3.11.J when the second feed water pump is going to be placed in service. The crew is to place the B Main Feed Water Pump in service lAW SOP-210,Section III. Step 2.7.k Event Event Type*

Event Description No. 1 BOP (N) The BOP will place the second feed water pump in service lAW SOP-210. 2 BOP (I) Feedwater Flow transmitter (477) Failure, fails HIGH, with a slow ramp at SRO (TS) approximately 3 minutes from current position.

3 BOP (C) Running EH pump trips. (Must manually start other pump) 4 RO (I) Pressurizer pressure channel 444 gradual failure high. Control severity to SRO (TS) prevent a trip. 5 RO (I,R) Power Range Channel N44 failure high with the failure of the rods to move. SRO (TS) The rods will not move in any direction in Manual or Automatic.

RO (R) Small steam leak occurs allowing determination of a required reactor shut 6 BOP (N) down. The crew may initiate a Rx Trip since Rods already will not move. SRO (N) When a trip Signal is inserted, the reactor will not trip. Large Steam Line Break occurs on the C Steam Generator upstream of the 7 All (M) MSIVs. "C" MSIV fails to shut automatically.

The "c" feed water isolation valve does riot isolate automatically.

8 BOP (C) A Reactor Building Cooling Unit fails to start automatically.

9 RO (C) 'B' Train Containment Spray pump fails to start automatically.

10 RO (I) Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: _1_ Scenario No.: 1 Event No.: 1 Page 2 of L Event

Description:

The BOP will place the second feed water pump in service lAW SOP-210. Time Position Applicant's Actions or Behavior SOP-210 Place B FPT SPEED CONTROL in Cascade Mode as follows: 1) Increase the MASTER SPEED CNTRL (MCB mla station) in MAN until the Feed Pump speed demand, as indicated on SCY-509C, is between 4100 rpm and 5000 rpm (indicated on GRAPHIC 310 BOP screen only). (PEER D) 2) Adjust the SP value (up and down arrows) on B FPT SPEED CONTROL until turbine RPM is within 25 rpm of SCY-509C rpm (indicated on GRAPHIC 310 screen only). 3) Click on the C icon on the B FPT SPEED CONTROL (S icon) face plate. BOP Stop TPP22B-PP2, AUX OIL PP, and return the switch to AUTO. (PEER D) BOP Stop Feedwater Pump B TURN GEAR and return switch to AUTO. (PEER D) If more than one Main Feedwater Pump is operating, perform the following for the pump being placed in service: a. Adjust the setpoint potentiometer dials on PUMP B SPEED BOP CNTRL (MCB MIA station) as necessary to maintain all operating Feedwater Pumps within 120 RPM of each other. b. When plant load is greater than 15%, close MOV-1-5(B)

TURB DRN VLV (MCB). End of placing 2 nd FWP in service event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page _3_ of 2.L Event

Description:

Feedwater Flow transmitter (477) Failure, fails HIGH, with a slow ramp at approximately 3 minutes from current position.

Time Position Applicant's Actions or Behavior AOP 401.3 FT-477 STEAM FLOW FAILURE. Enter AOP-401.3.

First 7 steps are Immediate Operator Actions. FCV-478 will travel closed. Alarm XCP-624, 4-4 SG A FWF>STF MISMA TCH BOP 1 Verify the failed channel is the controlling channel. 2 Select the operable flow channel: BOP

• Place FW CONTROL CHANNEL SEL Switch to the operable channel.

• Place STEAM CONTROL CHANNEL SEL Switch to the operable channel CRS/BOP 3 Verify Turbine Load is LESS THAN 950 MWe. CRS/BOP 4 Verify only one SG is AFFECTED.

CRS/BOP 5 Adjust the Feedwater Flow Control Valve as necessary to restore feed flow to the AFFECTED SG. CRS/BOP 6 Restore Narrow Range level in all SGs to between 60% and 65%. 7 Check if Feedwater Pump speed control is operating properly:

• Feedwater Header pressure is GREATER THAN Main Steam CRS/BOP Header pressure

• Feed flow is normal for steam and flow and power level

• All operating Feedwater Pump speeds and flows are balanced CRS/BOP 8 Verify Narrow Range level in all SGs is normal. 9 Restore the AFFECTED SG control systems to normal: CRS/BOP

• Place the Feedwater Flow Control Valve in AUTO

• Place the Feedwater Pump Speed Control System in AUTO. REFER' TO SOP-210, FEEDWATER SYSTEM 10 Within six hours, place the failed' channel protection bistables in a ' tripped condition:

a. Identify the associated bistables for the failed channel. REFER TO ' Attachment

1. b. Record the following for each associated bistable on SOP-401, REACTOR PROTECTION AND CONTROL SYSTEM, CRS Attachment I:

• Instrument.

• Associated Bistable.

• Bistable Location.

• STPs. c. Notify the I&C Department to ' place the identified bistables in trip.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page --L of .1.1.... ---Event

Description:

Feedwater Flow transmitter (477) Failure, fails HIGH, with a slow ramp at approximately 3 minutes from current position.

Time Position Applicant's Actions or Behavior TS 3.3.1, Table 3.3-1, item 14 11 Determine and correct the cause of the channel failure. CRS/SE No repair will occur for this event. End of FT-477 failure event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 3 Page 5 of .1.:!....

Event

Description:

Running EH pump trips. (Must manually start other pump) Time Position Applicant's Actions or Behavior ARP 6311-2 Running EHC pump trips event BOP A EHC Pump trips, Receives alarm XCP 631,1-2, EHC FLUID PRESS LO, BOP reviews ARP and hands to CRS. Crew mayor may not reference SOP-222 SWITCHOVER OF THE EHC PUMPS for starting the idle EHC pump. BOP/CRS Start the idle EHC pump. Verify the following:

• Starting amps decay off within 30 seconds.

• The started pump discharge pressure is greater than 1550 psig BOP/CRS as indicated at the EHC unit by HFPM-A OUTPUT PRESSURE or HFPM-B OUTPUT PRESSURE.

• EHC header pressure is greater than 1550 psig as indicated by PI-5676, EHC FLUID PRESS PSIG. Place the previously running EHC pump switch in After-Stop.

BOP/CRS CRS may direct placing pump in PTL due to apparent motor failure. End of running EHC pump trips event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: _1_ Scenario No.: 1 Event No.: 4 Page --L of 2L Event

Description:

Pressurizer pressure channel 444 gradual failure high. Control severity to prevent a trip. I Time Position Applicant's Actions or Behavior AOP-401.5 Receives annunciators XCP 616 2-3 PZR PRESS HI/LO, 6162-5 PZR RO CNTRL PRESS HI, 6164-4 PRT LVL LOI TEMP/PRESS/LVLlHI Verifies PT-444 is failing high CRS Enters AOP-401.5, Pressurizer Pressure Control Channel Failure. Verifies first 3 steps are completed which are immediate actions. 1. Verify the PZR PORVs are closed:

• PCV-445A.

PWR RELIEF RO

• PCV-445B.

PWR RELIEF (did not close; requires closing block valve)

• PCV-444B.

PWR RELIEF 2. Compare the PZR control channel indication to the protection channel indications:

RO

• PI-455. PRESS PSIG

• PI-456. PRESS PSIG

• PI-457. PRESS PSIG RO 3. Check if PI-444. CNTRL CHAN PRESS PSIG is NORMAL 3. IF PT-444 failed, then perform the following:

CRS/RO a) Ensure the PZR Spray Valves are closed:

• PCV-444C.

PZR SPRAY

• PCV-4440, PZR SPRAY b) Control PZR PRESS MASTER CONTROL in MAN. RO c) Operate the PZR Heaters and Spray Valves in manual to control RCS pressure between 2220 psig and 2250 psig. CRS Will probably reach the 2206 psig ONB Tech Spec 3.2.5 at which point the CRS should verbalize the 2 hr LCO requirement.

d) Within one hour; close MVG-8000B.

RELIEF 444 B ISOL. CRS Per TS 3.4.4.b, must also remove power from block valve, XVG-8000B because it would not. CRS/RO 4. Check If PI-445. CNTRL CHAN PRESS PSIG, indication is NORMAL CRS/RO 5. Ensure ROD CNTRL BANK SEL Switch is In AUTO. CRS/RO 6. Maintain RCS pressure between 2220 pslg and 2250 psig. CRS/SE 7. Determine and correct the cause of the channel failure. CRS Reference TS 3.4.4.b. for PORV failure. Must remove power from block valve in this case.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page 7 of 21 --Event

Description:

Power Range Channel N44 failure high with the failure of the rods to move. The rods will not move in any direction in Manual or Automatic.

Time Position Applicant's Actions or Behavior AOP-401.10 Start of N-44 Failure and Rods Fail To Move event. Crew should enter:

• AOP-401.10 for N-44 Failure (steps 1&2 are immediate actions) .

• AOP-403.4 for Stuck Control Rods (steps 1&2 are immediate actions).

RO should notice rods did not move when N-44 failed. N-44 starts failing hi, the following alarms are received:

XCP 620 1-1 PR HI SETPT FLUX HI XCP 620 1-4 PR CHAN DEV RO XCP 6201-5 PR UP DET FLUX HI DEV AUTO DEFEAT XCP 620 5-1 ROD CNTRL SYS FAIL URGENT XCP 6201-6 PR LO DET FLUX HI DEV AUTO DEFEAT 1. Verify normal indication on Power Range Channel N-44. ROfCRS IF Power Range Channel N-44 has failed, THEN place the ROD CNTRL BANK SEL Switch in MAN. (Should be a discussion of GOP Appendix A requirement to have rods in AUTO if any PZR PORV is isolated.)

RO 2. Stabilize any plant transients in progress.

CRSfRO 3. Maintain stable plant conditions CRS/RO 4. Verify no testing .is in progress on the operable Power Range channels.

CRSfRO 5. Place ROD STOP BYPASS Switch for the failed Power Range channel in BYPASS. CRS/RO 6. Verify the appropriate Rod Stop Bypass status light is lit:

• For N-44, B2 OP ROD STOP BYP (XCP-6111 4-4). CRS/RO 7. Adjust Control Rods to maintain Tavg within I.O°F of Tref. The empty fuse holders should NOT be reinstalled as this will allow a small amount of current flow through the blown fuse indicator

8. Deenergize the failed Power Range channel:

• Remove the CONTROL POWER fuses from the POWER CRS/RO RANGE A drawer of N-44.

• Remove the INSTR POWER fuses from the POWER RANGE B drawer of N-44. 9. Align the Power Range channel comparator circuits:

a. Place the following switches to the failed Power Range channel (N-44) position:

CRS/RO

• COMPARATOR CHANNEL DEFEAT Switch (on the COMPARATOR AND RATE drawer)

• UPPER SECTION Switch (on the DETECTOR CURRENT COMPARATOR drawer)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page --L of 21 -Event

Description:

Power Range Channel N44 failure high with the failure of the rods to move. The rods will not move in any direction in Manual or Automatic.

Time Position Applicant's Actions or Behavior

• LOWER SECTION Switch (on the DETECTOR CURRENT COMPARATOR drawer). CRS/RO 10. Ensure NR-45 is selected to the appropriate operable channels.

11. Within six hours, place the failed channel protection bistables in a tripped condition:

a. Identify the associated bistables for the failed channel (N-44). REFER to Attachment

1. b. Record the following for each associated bistable on SOP-401. CRS/SE REACTOR PROTECTION AND CONTROL SYSTEM, Attachment I:

• Instrument

• Associated Bistable

• Bistable Location.

• STPs. c. Notify the I&C Department to place the identified bistables in trip. CRS/RO 12. Verify Reactor Power is LESS THAN 75%. CRS 13. Refer to Tech Spec 3.3.1. {Trip bistables within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.} CRS/SE 14. Determine and correct the cause of the Power Range channel failure. Cause of failure will not be determined for this event. AOP-403.4 Following are the actions for Failure of Control Rods to Move. Steps 1& CRS 2 are immediate actions. This event will be occurring simultaneously with the N44 failure so the crew will be forced to prioritize between the two AOPs. RO 1. The ROD CNTRL BANK SEL Switch is already in MAN RO 2. Main Turbine load is already stabilized CRS/RO 3. Stop any boration or dilution in progress 1. Adjust Control Rods to maintain Tavg within 1.0 degrees of Tref. NOTE -Step 4: If Tavg has remained within 1.5°F of Tref , Control Rods should be moved one or two steps in or out to verify proper operation.

CRS/RO Since Control Rods will NOT move, THEN perform the following:

• Adjust Main Turbine load until Tavg is within 5°F of Tref

• Initiate GTP-702, Attachment IV.A. INOPERABLE CONTROL ROD CRS CRS evaluates Tech Specs 3.1.3.1.C which will require a plant Appendix 0 Required Operator Actions Form ES-O-2 Op Test No.: 1 --Scenario No.: 1 Event No.: 5 Page 9 of 21 -Event

Description:

Power Range Channel N44 failure high with the failure of the rods to move. The rods will not move in any direction in Manual or Automatic.

Time Position Applicant's Actions or Behavior shutdown, then performs the following:

Building operator (if dispatched) reports that the urgent failure is from power cabinet 2BD a. Notify the following plant personnel:

SE

• Management Duty Supervisor

• Reactor Engineering

b. Decrease Main Turbine Load to 50 MW at a rate determined by BOP the Shift Supervisor. (Refer to GOP-4B, POWER OPERATION, MODE 1 -DESCENDING, starting with Step 3.3) c. Maintain Tavg within 5 degrees of Tref using the following:

BOP/RO

• Main Turbine Load adjustment

• RCS Boration.

Refer to SOP-1 06, REACTOR MAKEUP WATER SYSTEM Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: --L Event No.: -L Page...1.2..

of 21.. Small steam leak occurs allowing determination of a required reactor shut down. The crew may Event

Description:

initiate a Rx Trip since Rods already will not move. When a trip signal is inserted, the reactor will not trip. Time 1 Position 1 Applicant's Actions or Behavior NOTE While attempting to lower load, the SMALL STEAM LEAK will initiate.

NOTE to over 1 min IE 5 instantaneous

-then increase as necessary until decision is made to Booth trip Rx and SI Operator Increase break to IE7 on Rx trip. Operator will respond to below annunciators by pulling ARPs and RO following CRS directions:

XCP 6062-2 RBCU 1A12A DRN FLO HI XCP 607 2-2 RBCU 1 BI2B DRN FLO HI CRS SRO will evaluate Tech Spec for DNB TS 3.2.5 for low PZR Pressure when it occurs. (2206 psig) CRS/RO As the leak escalates and conditions deteriorate, the crew is expected to trip the reactor prior to automatic actuation.

CRITICAL Directs the RO to trip the reactor. CRS/RO RO manually trips the reactor.

Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: ----1-Scenario No.: 1 Event No.: 7 Page 11 of 21 --Event

Description:

Large Steam Line Break occurs on the C Steam Generator upstream of the MSIVs. "C n MS IV fails to shut automatically.

The "C n feed water isolation valve does not isolate automatically.

Time Position Applicant's Actions or Behavior EOP-1.0 NOTE Large Steam Break should occur at this time. An AUTO SI may occur prior to MANUAL actuation due to size of steam break. 1. Verify Reactor Trip: (Reactor did not trip automatically.

Isolate EFW flow to "C" S/G)

• Trip the Reactor using either Reactor Trip Switch RO

• Verify all Reactor Trip and Bypass Breakers are open.

• Verify all Rod Bottom Lights are lit.

• Verify Reactor Power level is decreasinQ.

2. Verify Turbine/Generator Trip: (Secure RCPs Hi 3) a. Verify all Turbine STM STOP VLVs are closed. BOP b. Ensure Generator Trip (after 30 second delay): 1) Ensure the GEN BKR is open. 2) Ensure the GEN FIELD BKR is open. 3) Ensure the EXC FIELD CNTRL is tripped. BOP 3. Verify both ESF buses are energized.

4. Check if SI is actuated:

a. Check if either:

• SI ACT status light is bright on XCP-61 07 1-1. OR ALL

• Any red first-out SI annunciator is lit on XCP-626 top row. b. Actuate SI using either SI ACTUATION Switch. GO TO Step 6. 5. Check if SI is required:

a. Check if any of the following conditions exist:

• PZR pressure LESS THAN 1850 psig. OR

• RB pressure GREATER THAN 3.6 psig. ALL OR

• Steamline pressure LESS THAN 675 psig. OR

• Steamline differential pressure GREATER THAN 97 psid. b. Actuate SI using either SI ACTUATION Switch. RO At some point after the Rx Trip, a High-3 should have occurred and the RO will secure all RCPs CRS/BOP 6. Complete ATTACHMENT 3, SI EQUIPMENT VERIFICATION.

BOP operator manually closes "C" MSIV and "C" FWIV.

Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 8 Page 12 of 21 -Event

Description:

A Reactor Building Cooling Unit fails to start automatically.

Time Position Applicant's Actions or Behavior RO Notes that RBCU XFN-0064B did not auto start in SS on the SI and manually starts XFN-0064B CRS/SE 7. Announce plant conditions over the page system. CRS/RO 8. Verify RB pressure has remained LESS THAN 12 psig on PR-951, RB PSIG (P-951), red pen. 8 Perform the following:

a) Verify both the following annunciators are lit: XCP-612 3-2 (RB SPR ACT). XCP-612 4-2 (PHASE B ISOL). RO IF either annunciator is NOT lit, THEN actuate RB Spray by placing the following switches to ACTUATE: Both CS-SGA 1 and CS-SGA2. OR Both CS-SGB1 and CS-SGB2. MVG-3003A(B}, SPRAY HDR ISOL LOOP A(B). RO b) Verify Phase B Isolation by ensuring RB PRA Y/PHASE B ISOL monitor lights are bright on XCP-61 05. c) Ensure the following are open: RO MVG-3001A(B), RWST TO SPRAY PUMP A(B) SUCT. MVG-3002A(B), NAOH TO SPRAY PUMP A(B) SUCT.

Appendix 0 Required Operator Actions Form ES-O-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page ---1l. of ..1.:!...

---Event

Description:

'8' Train Containment Spray pump fails to start automatically.

Time Position Applicant's Actions or Behavior d) Ensure both RB Spray Pumps are running Of the RO has not RO alread'l.

done SOl at this l2.oint the RO manuall'l.

starts the "B" RB Sl2.ra'l.l2.uml2.

that did not auto start on the Phase B isolation signal.l Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 10 Page 14 of 21 ----Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position Applicant's Actions or Behavior e) Verify RB Spray flow is GREATER THAN 2500 gpm for each operating train on FI-7368, SPR PP A DISCH FLOW GPM. RO FI-7378, SPR PP B DISCH FLOW GPM. (At this point the RO notes that there is no flow indicated on FI-7368 but that all other indications are normal and diagnoses it as a failed indicator. ) RO f) Stop all RCPs (if not already stopped on Phase B). CRS/RO BOP CRS/RO CRS/RO 9. Check RCS temperature:

• With no RCP running, RCS Tcold is stable at OR trending to 557"F. IF RCS temperature is LESS THAN 557"F AND decreasing, THEN: a) Place the STM DUMP CNTRL Controller in MAN and closed. b) Place the STM DUMP MODE SELECT Switch in STM PRESS. c) Ensure all Steamline PORVs and Condenser Steam Dumps are closed. d) IF RCS cooldown continues, THEN: (Could get red path on EOP-15.0 if throttle too much) (1) IF Narrow Range SG level is LESS THAN 30% [50%] in all SGs, THEN reduce EFW flow as necessary to stop the cooldown, while maintaining total EFW flow GREATER THAN 450 gpm. (2) WHEN Narrow Range SG level is GREATER THAN 30% [50%] in at least one SG, THEN control EFW flow as necessary to stabilize RCS temperature at 557"F. (3) IF RCS cooldown continues, THEN close:

• MS Isolation Valves, PVM-2801A(B)(C).

• MS Isolation Bypass Valves, PVM-2869A(B)(C).

By step 9 in EOP-1.0 the faulted SG should have been diagnosed as "C" and EFW to "C" SG should be secured (FCV closed) (OAP-103.4)

10. Check PZR PORVs and Spray Valves: a. PZR PORVs are closed. b. PZR Spray Valves are closed. c. Verify power is available to at least one PZR PORV Block Valve:

• MVG-8000A, RELIEF 445 A ISOL.

• MVG-8000B, RELIEF 444 B ISOL.

• MVG-8000C, RELIEF 445 B ISOL. d. Verify at least one PZR PORV Block Valve is open. OPEN one Block Valve unless it was closed to isolate an open PZR PORV. 11. a. Check if RCPs should be stopped: Check if either of the following criteria is met:

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page 15 of 2.1 -------Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position Applicant's Actions or Behavior

• Annunciator XCP-612 4-2 is lit (PHASE B ISOL) . OR

• RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. b. Stop all RCPs (already stopped).

12. Verify no SG is FAUL TED:

• No SG pressure is decreasing in an uncontrolled manner .

• No SG is completely depressurized . CRS/BOP GO TO EOP-3.0, FAULTED STEAM GENERATOR ISOLATION, Step 1. Crew will leave this procedure and transition to EOP-3.0, step 1. EOP-3.0 1. Ensure all the following are closed: CRS/BOP

• MS Isolation Valves, PVM-2801A(B)(G).

• MS Isolation Bypass Valves, PW-2869AIB)(Cl-

2. Check if any SG is NON-FAULTED:

ALL

• Pressure in any SG is stable or increasing.

• Any SG is not completely depressurized

3. Identify any FAULTED SG(s): ALL

• Any SG pressure decreasing in an uncontrolled manner. OR

• Any SG is NOT completely depressurized

4. Close the following valves for each FAULTED SG:

• FW Flow Control FCV-498 CRS/BOP

• FW Isolation, PVG-1611 C

• SG Blowdown.

PVG-503C

• FW Flow Control Bypass FCV-3341 5. Complete the isolation of each FAULTED SG: a. Close SG Chemical Feed Isolation, MVK-1633C

b. Close MS Drain Isolation PVT -2843C c. Close MS Drain Isolation, PVT-2877B for SG C. d. Place the Steam line PWR RELIEF C SETPT Controller in MAN and closed. ALL e. Place the Steamline Power Relief C Mode Switch in PWR RLF f. Close FCV-3551 MD EFP TO SG C g. Close FCV-3556 TD EFP TO SG C h. Locally unlock and close XVG01 017C-EF SG C MTR DR EF PUMP SUPPLY HEADER VALVE (IB-423).

i. Locally unlock and close XVK01 019C-EF SG C MTR DR EF PUMP SUPPL Y STOP CHK VLV (IB-423).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page of .1.:!... Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position CRITICAL BOP j. k. I.

• 1 ) 2) Applicant's Actions or Behavior Locally unlock and close XVG01 018C-EF SG C TURB DR EF PUMP SUPPLY HDR VALVE (IB-423).

Locally unlock and close XVK01020C-EF SG C TURB DR EF PUMP SUP STOP CHK VALVE (IB-423) Close and locally deenergize the appropriate valve for SG C FAULTED: For SG C: Open XMCIDB2Y 05EH. EMERG FEEDWATER PUMP MAIN STEAM BLOCK XVG2802B-MS (AB-463).

Close MVG-2802B MS LOOP C TO TD EFP Faulted SG is Isolated 6. Check if Secondary radiation levels are normal: a. Check radiation levels normal on all un isolated radiation monitors:

• RM-G19C STMLN HI RNG GAMMA.

• RM-L3, STEAM GENERATOR ALL BLOWDOWN LIQUID MONITOR.

• RM-LiO. SG BLOWDOWN CW DISCHARGE LIQUID MONITOR.

• RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR. b. Notify Chemistry to sample all SG secondary sides and screen samples for abnormal activity using a frisker. 7. Check if SI flow should be reduced: a. RCS subcooling on TI-499A(B), A(B) TEMP OF is GREATER THAN 30"F. b. Secondary Heat Sink is adequate:

• Total EFW flow to INTACT SGs is GREATER THAN 450 gpm. ALL OR CRS/RO CRS/RO CRS/BOP

• Narrow Range level is GREATER THAN 30% [50%] in at least one INTACT SG. c. RCS pressure is stable OR increasing.

d. PZR level is GREATER THAN 18% [38%] (IF PZR LEVEL

< 18%[38%], THEN transition to EOP-2.0, see attachment of EOP-2.0 steps) 8. Reset both SI RESET TRAIN A(B) Switches.

9. Reset Containment Isolation:

• RESET PHASE A TRAIN A(B) CNTMT ISOL.

• RESET PHASE B TRAIN A(B) CNTMT ISOL. 10. Place both ESF LOADING SEQ A(B) RESETS to: a. NON-ESF LCKOIJTS.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 10 Page 17 of 21 --Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position Applicant's Actions or Behavior b. AUTO-START BLOCKS. 11. Establish Instrument Air to the RB: a. Start one Instrument Air Compressor and place the other in CRS/RO Standby. b. Open PVA-2659, INST AIR TO RB AIR SERVo c. Open PVT-2660.

AIR SPLY TO RB CRS 12. GO TO EOP-1.2, SAFETY INJECTION TERMINATION, Step 1. If previously entered EOP-2.0, EOP-2.0 will transition back to EOP-1.2. EOP-1.2 CRS/RO Stop all but one Charging Pump and place in Standby. (Stop A Chg Pump) CRS/RO Verify RCS pressure is stable OR increasing.

Establish Normal Charging:

a. Close FCV-122, CHG FLOW. CRS/RO b. Open both MVG-8107 and MVG-8108, CHG LINE ISOL. c. Adjust FCV-122, CHG FLOW, to obtain 60 gpm Charging flow. d. Close both MVG-8801A(B), HI HEAD TO COLD LEG INJ CRS/RO Control FCV-122, CHG FLOW, to maintain PZR level. Note SI terminated and normal charging restored.

CRS/RO Stops both RHR pumps 6. Verify SI flow is NOT required:

CRS/RO a. RCS subcooling on TI-499A(B), is GREATER THAN 30°F c. PZR level is GREATER THAN 18% r38%]. 7. Check if RB Spray should be stopped: a. Check if any RB Spray Pumps are running. b. Verify RB pressure is LESS THAN pressure is LESS THAN 11 psig. CRS/RO c. Depress both RESET TRAIN A(B) RB SPRAY. d. Verify EOP-14.0, RESPONSE TO INADEQUATE CORE COOLING, has NOT been implemented.

e. Stop both RB Spray Pumps and place in Standby. f. Close MVG-3003A(B), SPRAY HDR ISOL LOOP A(B). 9. Check if Letdown can be established:

a. Verify PZR level is GREATER THAN 30% [50%] b. Establish Normal Letdown: CRS/RO 1) Adjust FCV-122, CHG FLOW, to obtain 60 gpm Charging flow. 2) Set PCV-145, LO PRESS LTDN, to 70%. 3) Open TCV-144, CC TO LTDN HX. 4) Open PVT-8152, LTDN LINE ISOL.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 10 Page 18 of 21 ---...;.. Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position Applicant's Actions or Behavior 5) Open both LCV-459 and LCV-460, L TDN LINE ISOL. 6) Open desired Orifice Isolation Valve(s) to obtain 60 gpm to 120 gpm:

• PVT-8149A, L TDN ORIFICE A ISOL (45 gpm).

• PVT-8149B, LTDN ORIFICE B ISOL (60 gpm).

• PVT-8149C, LTDN ORIFICE C ISOL (60 gpm). 7) Adjust FCV-122, CHG FLOW, to maintain TI-140, REGEN HX OUT TEMP "F, between 250"F and 350"F while maintaining PZR level. 8) Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS LTDN PRESS PSIG, between 300 psig and 400 psig. 9) Place PCV-145, LO PRESS LTDN, in AUTO. 10) Place TCV-144, CC TO LTDN HX, in AUTO. 9. Check the Reactor Makeup System: CRS/RO a. Set FCV-113 A&B, BA FLOW, Controller to 8.6. j. Ensure the Reactor Makeup System is in AUTO. 10. Transfer Charging Pump suction to the VCT: CRS/RO a. Open both LCV-115C(E), VCT OUTLET ISOL. k. Close both LCV-115B(D), RWST TO CHG PP SUCT. Examiners should end scenario at this point as SI is now secured and charging and letdown are restored.

EOP-2.0 {if The following are applicable steps of EOP-2.0, Loss of Reactor or Secondary Coolant. This would be entered if PZR Level was too low for EOP-1.2 transition.

1. Check if RCPs should be stopped: a. Check if either of the following criteria is met:

• Annunciator XCP-612 4-2 is lit (PHASE B ISOL). OR ALL

• RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. b. Stop all RCPs. 2. Verify no SG is FAUL TED: CRS/BOP No SG pressure is decreasing in an uncontrolled manner. *

• No SG is completely depressurized.

3. Check INTACT SG levels: CRS/BOP a. Verify Narrow Range level in INTACT SGs is GREATER THAN 30% [50%].

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: ----L-Scenario No.: 1 Event No.: 10 Page 19 of 21 --Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position CRS/RO CRS/RO ALL Applicant's Actions or Behavior e. Control EFW flow to maintain Narrow Range level in each INTACT SG between 40% [50%] and 60%. 4. Reset both SI RESET TRAIN A(B) Switches.

5. Reset Containment Isolation:

• RESET PHASE A -TRAIN A(B) CNTMT ISOL.

• RESET PHASE B -TRAIN AJB) CNTMT ISOL. 6. Check if Secondary radiation levels are normal: a. Check radiation levels normal on:

• RM-G19A(B)(C), STMLN HI RNG GAMMA.

• RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR.

• RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR.

• RM-L 10, SG BLOWDOWN CW DISCHARGE LIQUID MONITOR. b. Place SVX-9398A(B)(C), SG A(B)(C) SMPL ISOL, in AUTO. m. Notify Chemistry to sample all ' SG secondary sides and screen' samples for abnormal activity using a frisker.

7. Check PZR PORVs and Block Valves: a. Verify power is available to the PZR PORV Block Valves: 1) MVG-8000A, RELIEF 445 A ISOL. 2) MVG-8000B RELIEF 444 B ISOL. 3) MVG-8000C, RELIEF 445 B ISOL. CRS/RO If any PZR PORV opens because of high PZR pressure, Step 7.b should be repeated after pressure decreases to LESS THAN 2300 psig, to ensure the PORV recloses.

b. Verify all PZR PORVs are closed. c. Verify at least one PZR PORV Block Valve is open. 8. Place both ESF LOADING SEQ A(B) RESETS to: CRS/BOP a. NON-ESF LCKOUTS. CRS/RO b. AUTO-START BLOCKS. 9. Establish Instrument Air to the RB: a. Start one Instrument Air Compressor and place the other in Standby.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page 20 of 21 --Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position ALL ALL CRS/RO Applicant's Actions or Behavior b. Open PVA-2659, INST AIR TO RB AIR SERVo C. Open PVT-2660, AIR SPLY TO RB. 10. Check if SI flow should be reduced: a. RCS subcooling on TI-499A(B), A(B) TEMP "F, is GREATER THAN 30"F. b. Secondary Heat Sink is adequate:

• Total EFW flow to INTACT SGs is GREATER THAN 450 gpm. OR

• Narrow Range level is GREATER THAN 30% [50%] in at least one INTACT SG. C. RCS pressure is stable increasing.

NOTE -Step 10.d If PZR level is LESS THAN 18% [38%], the PZR should refill from SI flow after pressure is stabilized.

n. PZR level is GREATER THAN 18% [38%] (IF PZR still less than 18%[38%], then go to Step 11), if not then continue)

GO TO Step 11. o. GO TO EOP-1.2, SAFETY INJECTION TERMINATION, Step 1. 11. Check if RB Spray should be stopped: a. Check if any RB Spray Pumps are running b. Verify RB pressure is LESS THAN 11 psig c. Depress both RESET TRAIN A(B) , RB SPRAY. NOTE -Step 11.d

• RB Spray must run for a minimum of two hours.

• Anytime RB Spray Pumps are stopped, MVG-3003A(B), SPRAY HOR ISOL LOOP (B), should be closed for containment isolation.

d. Consult with TSC personnel concerning RB Spray System operation.

12. Check if RHR Pumps should be stopped: a. Check RCS pressure:

1) RCS pressure is GREATER THAN 250 psig 2) RCS pressure is stable OR increasing.

b. Check if any RHR Pump is running with suction aligned to the Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page 21 of 21 -----Event

Description:

Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.

Time Position Applicant's Actions or Behavior RWST c. Stop any RHR Pump which is running with suction aligned to the RWST and place in Standby. 13. Check if RCS pressure is stable OR decreasing.

This would be a "do loop" back to step1 until PZR Level was greater CRS/RO than 18% [38%] RETURN TO Step 1. This is end of EOP-2.0 for this scenario.

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

I vc Summer I Scenario No.: 3 (SPARE) Op-Test No.: 2005-301 Examiners:

Operators:

Initial Conditions:

The Unit is in Mode 2 with a MOL reactor startup in progress.

Turnover:

The previous crew has initiated the reactor startup per GOP-3. Source range counts are stable and Control bank '0' is presently at 100 steps. 11M data now projects criticality at 116 steps on Control bank '0'. Continue with the reactor startup beginning with step 3.11.q of GOP-3, and stabilize reactor power between 1-3%. "A 1" maintenance week S/G "A," Small tube leak, approx. 8 gpd. Event Malf. No. I Event Event Description No. Position Type* 1 RO R Pull control rods to establish critical reactor. BOP C Train 'A' Service Water Pump A trips and spare "c" pump needs to be aligned and 2 SRO (TS) started. RO I Controlling channel Pressurizer Level Transmitter (IL T-459) fails low and LID 3 isolates.

AOP-401.6 BOP N Re-establish letdown. 4 (SOP-102)

BOP I Steam Generator B PORV Pressure Transmitter (IPT-2010) fails high. BOP 5 operator takes manual control and closes PCV-201 O. BOP/RO C Letdown line break inside Containment.

AOP isolates letdown which terminates the 6 SRO (TS) leak. Crew places excess letdown in service. AOP-101.1

& SOP-102 RO C RCP "A" High Vibration (discussion about PZR spray) and seal failure when 7 secured. (AOP-101.2) (SOP-101)

ALL M Small break LOCA (approx 400 gpm). Ramp leak in over a 5 minute period to allow 8 entry into AOP-1 01.1 again. (vary ramp rate as necessary to give operators time to make "manual" reactor trip decision in AOP-101.1 prior to getting auto trip and time to manual SI in EOP-1.0 prior to auto SI). BOP or C Safety injection Train 'A' fails to automatically or manually actuate (troubleshooting 9 RO this event for the rest of the scenario).

and 'B' Charging pump fails to automatically start when safety injection is initiated but will manual start. The reactor fails to automatically trip & fails to trip from RO*side MCB switch but will trip from BOP side .. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior I I I GOP-3.0 I q. Within 15 minutes before achieving criticality, verify Tavg greater than or equal to 551°F. r. Announce criticality over the page system. s. Verify critical rod position is above the Rod Insertion Limit per Tech Spec 3.1.3.6. t. At the AUDIO COUNT RATE CHANNEL drawer, place the following switches in OFF: 1) AUDIO MULTIPLIER.

2) CHANNEL SELECTOR.

3.11 Increase Reactor Power to 10-3% as follows: / a. Establish a stable Startup Rate of less than one decade per minute. b. At 7.5x1 0-6%, perform the following:

1) Verify P6 Permissive energizes to bright. 2) Verify a minimum of one decade overlap between Source Range Channels and Intermediate Range Channels.

c. Prior to 10 0 CPS, perform the following:

1) Momentarily place SR TRAIN A Switch in BLOCK. 2) Verify SR A TRIP BLCK Permissive energizes to bright. 3) Momentarily place SR TRAIN B Switch in BLOCK. 4) Verify SR B TRIP BLCK Permissive energizes to bright. d. Select one Intermediate Range Channel and one Power Range Channel on NR-45, NIS RECORDER.

e. Stabilize Reactor Power at 10-;)%. This ends the pull to criticality event. RO A SWP trips. RO responds to various alarms and references the ARP: XCP-604 1-2: SWP A/C TRIP Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior XCP-604 3-3: SW CCW HX A FLO LOITEMP HI XCP-604 3-4: DG A CLR SW FLO LO TEMP HI CRS/RO ARP is handed to CRS, the IB operator is dispatched to SW PP house to investigate.

Electricians may also be notified.

CRS Decision should be made to place C SWP on A Train CORRECTIVE ACTIONS: I. Place the spare Service Water Pump in service per SOP-117. ALL 2.1 Shift from Service Water Pump A to Service Water Pump C in service, as follows: a. With the exception of racking down XSW1 EA 04, SERVICE WATER PUMP XPP0039A-SW, complete Attachment V. ALL b. Start XPP-0039C, PUMP C TRAIN A. (PEER D) RO c. Verify MVB-3116C, SWP C DISCH, automatically opens. ALL/Building

d. Ensure sufficient Service Water Pump C cooling water flow, by throttling the following (SW-436):

1) XVT03157C-SW, sw PP C MTR UPPER BRG CLG WTR SUP VALVE, to obtain upper bearing flow between 10 gpm and 12 gpm. 2) XVT03158C-SW, sw PP C MTR LOWER BRG CLG WTR SUP VALVE, to obtain lower bearing flow between 3 gpm and 4 gpm. ALL/Building

e. At XPN-13, C SERVICE WATER SCREEN Control Panel (SW-436), verify proper traveling screen operation, as follows: 1) Place the Screen Selector Switch, in HAND. 2) Verify proper screen operation and screen wash flow. 3) Place the Screen Selector Switch, in AUTO. RO f. Stop XPP-0039A, PUMP A, and place the control switch, in PULL TO LK NON-A. RO g. Verify MVB-3116A, SWP A DISCH, automatically closes. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior ALL/Building

h. Re-verify Service Water Pump C cooling water flow and adjust as necessary, by throttling the following (SW-436):

1) XVT03157C-SW, SW PP C MTR UPPER BRG CLG WTR SUP VALVE, to obtain upper bearing flow between 10 gpm and 12 gpm. 2) XVT03158C-SW, SW PP C MTR LOWER BRG CLG WTR SUP VALVE, to obtain lower bearing flow between 3 gpm and 4 gpm. ALL/Building I. Rack down XSW1EA 04, SERVICE WATER PUMP XPP0039A-SW (SW-425).

ALL/Building

j. At XPN-11, A SERVICE WATER SCREEN, Control Panel (SW-436), place the Screen Selector Switch, in OFF. ALL/Building

k. Complete Attachment V. ALL I. Ensure proper Service Water flow through the operable Train A Chiller per SOP-501. This ends the A SWP trip event. The following event is the L T-459 Failure, PZR Level Controlling channel. L T-459 Fails low and Letdown isolates.

The following alarms are received:

XCP-614 5-1: CHG LINE FLO HIILO XCP-616 1-3: BLCK HTRS ISOL LTDN PZR LCS LO XCP-616 1-5: PZR LCS DEV HIILO XCP-616 3-1: PZR HTR CNTRL OR BU GRP 1/2 TRIP XCP-616 4-6: SCR OUTPT LOSS Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior I Crew enters AOP-401.06 PZR Level Control and Protection Channel Failure. Step 1 is an immediate action. AOP-401.6 RO 1 Place PZR LEVEL CNTRL Switch to the position with two operable channels.

RO 2 Select an operable channel on PZR LEVEL RCDR. RO 3 Control the PZR Heaters as necessary to maintain PZR pressure:

CNTRL GRP Heaters. BU GRP 1 Heaters. BU GRP 2 Heaters. RO 4 Verify Letdown is in service. 4 Re-establish Letdown. REFER TO SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM. IF Letdown can NOT be established, THEN REFER TO AOP-102.1, LOSS OF LETDOWN, while continuing with this procedure.

RO 2.1 Place FCV-122, CHG FLOW, in MAN and close. RO 2.2 Place PCV-145, LO PRESS LTDN, in MAN and open to 70%. (PEER D) RO 2.3 Place TCV-144, CC TO LTDN HX, in MAN and open to 100%. RO 2.4 Place TCV-143, LTDN TO VCT OR DEMIN, in VCT. RO 2.5 Open PVT-8152, LTDN LINE ISOL. RO 2.6 Open the following:

a. LCV-459, L TON LINE ISOL. b. LCV-460, L TON LINE ISOL. Appendix 0, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior RO 2.7 Ensure the following Charging Line Isolation Valves are open: a. MVG-81 07, CHG LINE ISOL. b. MVG-81 08, CHG Llt:-JE ISOL. RO 2.8 Slowly open FCV-122, CHG FLOW, to establish 60 gpm flow as indicated on FI-122A, CHG FLOW GPM. RO 2.9 Open Orifice Isolation Valves to obtain the desired Letdown flow rate (60 gpm to 120 gpm): a. PVT-8149A, LTDN ORIFICE A ISOL (45 gpm). b. PVT-8149B, LTDN ORIFICE B ISOL (60 gpm). c. PVT-8149C, LTDN ORIFICE C ISOL (60 gpm). RO 2.10 Adjust FCV-122, CHG FLOW, as required to maintain TI-140, REGEN HX OUT TEMP of, between 250°F and 350°F while maintaining Pressurizer level. RO 2.11 Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS L TDN PRESS PSIG, between 300 psig and 400 psig. RO 2.12 Place PCV-145, LO PRESS LTDN, in AUTO. RO 2.13 Adjust TCV-144, CC TO L TDN HX, potentiometer as necessary to maintain the desired VCT temperature and place in AUTO. Refer to VCS Curve Book, Figure V11.15. RO 2.14 When Pressurizer level matches reference level, place FCV-122, CHG FLOW, in AUTO per Section IV. RO 2.15 After the Letdown temperatures have stabilized, place TCV-143, LTDN TO VCT OR DEMIN, in DEMIN/AUTO.

RO 5 Check if PZR LVL MASTER CONTROLLER is responding appropriately:

• Verify Charging flow is normal and responding to PZR level error.

• Verify PZR level is stable at OR trending to program level. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior CRS/SE 6 Within six hours, place the failed channel protection bistables in a tripped condition:

a. Identify the associated bistables for the failed channel REFER TO Attachment 1 . b. Record the following for each associated bistable on SOP-401, REACTOR PROTECTION AND CONTROL SYSTEM, Attachment I:

• Instrument.

• Associated Bistable.

• Bistable Location.

• STPs. c. Notify the I&C Department to place the identified bistables in trip. 7 Determine and correct the cause of the channel failure This concludes the L T-459 failure event. The next event is IPT-2010 slowly failing high which results in SG PORV IPV-2010 (8 Loop) slowly going full open. Valve controller can be taken to Manual and closed. No alarms are associated with this event. ALL Crew should notice some excess RCS cooling, increased steam flow and finally notice IPV-201 0 is going open. CRS/BOP CRS and/or BOP should recommend placing 2010 controller in Manual and attempting to close. BOP IPV-2010 placed in Manual and closed. CRS/SE MWR should be written and work order generated to repair transmitter.

This concludes the 2010 failing open event. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior The Letdown leak inside containment is the next event. The following alarms are received as leak progresses:

XCP-642 3-3: RB ACC AREA RM-G5 HI RAD XCP-642 3-4: RB ACC AREA RM-G5 TRBL XCP-642 3-5: INCOR INSTR AREA RM-G14 HI RAD XCP-642 3-6: INCOR INSTR AREA RM-G14 TRBL AOP-101.1 RO 1 Verify PZR level is at or trending to program level. IF PZR level is decreasing.

THEN perform the following:

a) Open FCV-122. CHG FLOW as necessary to maintain PZR level b) IF PZR level continues to decrease, THEN reduce Letdown to one 45 gpm orifice: 1)Set PCV-145, LO PRESS LTDN. To 70% 2) Ensure PVT-8149A.

LTDN ORIFICE A ISOL. is open. 3) Close both PVT-8149B(C).

LTDN ORIFICE B(C) Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior ISOL. 4) Adjust PCV-145. LO PRESS LTDN. to maintain PI-145. LO PRESS LTDN PRESS PSIG. between 300 psig and400 psig. 5) Place PCV-145, LO PRESS LTDN. in AUTO. CRS/RO 2 Check if 51 is required:

a. Check if any of the following criteria are met:

• PZR level is decreasing with Charging maximized and Letdown minimized.

• PZR level is approaching 12%.

• PZR pressure is approaching 1870 psig.

• VCT level is approaching 5%. SI should NOT be required, crew should follow AL TERNA TlVE ACTION of step 2 which is to GO TO STEP 3 CRS/SE 3 Determine RCS leak rate: a. Estimate the RCS leak rate. REFER TO IPCS CHGNET. b. Calculate the RCS leak rate. REFER TO STP-114.002.

OPERATIONAL LEAK TEST. c. Check if the RCS leak rate is GREATER THAN Tech Spec 3.4.6.2 d. Comply with the applicable Tech Spec 3.4.6.2 action statement.

RO 4 Verify RCS pressure is GREATER THAN 2210 psig. a) Ensure all PZR Heaters are on. b) the PZR Spray Valves are closed c) Ensure the PZR PORVs are closed. IF any PORV fails to close, THEN close its Siock Valve. BOP/CRS 5 Verify no SG tubes are leaking: a. Narrow Range level in no SG is increasing with feed flow LESS THAN steam flow. b. Radiation levels on all of the following are normal:

• RM-G19A(S)(C).

STMLN HI RNG GAMMA.

• RM-A9. CNDSR EXHAUST GAS ATMOS MONITOR.

• RM-L3. STEAM GENERA TOR SLOWDOWN Appendix 0, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: -----------Page __ of __ Event

Description:

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_ Time Position RO RO RO Applicants Actions or Behavior LIQUID MONITOR.

• RM-LiO. SG BLOWDOWN CW DISCHARGE LIQUID MONITOR. c. No steam flowlfeed flow mismatch (feed flow low). d. As determined by Chemistry sample analysis of ALL SG secondary sides for activity.

6 Check the PZR PORVs: a. Check if RCS pressure is LESS THAN 2335 psig. b. Verify all PZR PORVs are closed. c. Check if PRT conditions are normal by verifying PRT LVL LO ITEMP/LVLlPRESS HI (XCP-616 4-4). is not lit. d. Verify at least one PZR PORV Block Valve is open. 7 Check If Reactor Building conditions are normal: a. RB radiation levels are normal on the following:

• RM-GS. RB PERSONNEL ACCESS AREA GAMMA.

• RM-G6. 17 RB REFUEL BRIDGE AREA GAMMA.

• RM-A2. RB SAMPLE LINE PARTICULATE(IODINE)(GAS)

ATMOS MONITOR. b. RB Sump levels are normal c. RB pressure is LESS THAN 1.5 psig d. The following annunciators are NOT lit:

• RBCU IAl2A DRN FLO HI (XCP-606 2-2).

• RBCU IB/2B DRN FLO HI (XCP-607 2-2). Conditions are not normal, so the alternative action of isolating letdown will be performed.

7 Attempt to isolate leakage as follows: a) Close all Letdown Isolation Valves: 1) PVT-8149A(B)(G)

L TDN ORIFICE A(B)(C) ISOL. 2) LCV-459. L TDN LINE ISOL 3) LCV-460, L TDN LINE ISOL b) Check RCS parameters for indications of leakage. Leakage should be isolated by the above actions. Crew should wait and verify no further leakage occurs. Since Normal Letdown will remain isolated, crew should place EXCESS LETDOWN in service. REFER TO SOP-102. CHEMICAL AND VOLUME CONTROL SYSTEM Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior I The following is from SOP-102: RO 2.1 Ensure HCV-137, XS LTDN HX, is closed. RO 2.2 Place PVM-8143, XS LTDN TO VCT(PEER D) RO 2.3 If required, reset Phase A Isolation by depressing the following:

a. RESET PHASE A -TRAIN A CNTMT ISOL. b. RESET PHASE A -TRAIN B CNTMT ISOL. RO Open the following:

a. MVT-81 00, SEAL WTR RTN ISOL. b. MVT-8112, SEAL WTR RTN ISOL. RO 2.5 Ensure MVG-9583, FROM XS L TDN HX, is open. RO 2.6 Open PVT-8153, XS LTDN ISOL. RO 2.7 Open PVT -8154, XS L TDN ISOL. RO 2.8 Establish Excess Letdown flow as follows: a. Slowly throttle open HCV-137, XS LTDN HX. b. Monitor TI-139, XS LETDOWN HX OUT TEMP of, to maintain less than 165°F. c. Monitor the following to ensure flow between 0.2 gpm and 5.0 gpm: 1) FR-154A, RCP SL LKOFF HI RANGE. 2) FR-154B, RCP SL LKOFF LO RANGE. This concludes establishing Excess Letdown. More steps do remain from AOP-101.1 for determining if leakage is isolated, but can commence the A Rep high vibration event at this time. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior Crew receives annunciator XCP-617 1-3: RCPA VIBR HI RO should notice frame and shaft vibration levels are escalating.

A RCP should be secured based on increasing levels. The following steps would apply from SOP-101 for securing the RCP. RO 2.1 Place the Pressurizer Spray Valve for the affected Reactor Coolant Pump in MAN and close: a. PCV 444D, PZR SPRAY, for Reactor Coolant Pump A. RO 2.2 If the Reactor Coolant System is solid, place PCV-145, LO PRESS L TDN, in MAN. RO 2.3 Secure one of the following Reactor Coolant Pumps as required:

a. XPP-0030A, PUMP A. RO 2.4 If the Reactor Coolant System is solid, return PCV-145, LO PRESS L TDN, to AUTO, if desired. RO 2.5 Verify Seal Injection to the secured Reactor Coolant Pump using the applicable following indicator:

a. FI-130A, RCP A INJ FLO GPM. RO 2.6 Maintain Component Cooling Water to the secured Reactor Coolant Pump thermal barrier until RCS temperature is less than 150°F. BOP 2.7 Place the following controllers in MAN, as required for the affected RCS loop and maintain Narrow Range Steam Generator level between 60% and 65%: Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior a. PVT-478, SG A FWF. b. FCV-3321, LOOP A MAIN FW BYP. CRS 2.8 If not already in Hot Standby, proceed to Hot Standby lAW GOP-5, Reactor Shutdown From Startup To Hot Standby (Mode 2 To Mode 3). The following steps are from GOP-5, Reactor Shutdown from Mode 2 to Mode 3. These steps will place the Reactor below 7. 5x1 0-5% power. Prior to commencing shutdown, should go ahead and begin Small Break LOCA Event. CRS/SE 3.1 Complete GTP-702 Attachment II.K, Operational Mode Change Plant Shutdown -Entering Mode 3 Or Plant Trip To Mode 3 From Modes 1 Or 2. RO 3.2 Select both Intermediate Range Channels on NR-45, NIS RECORDER.

3.3 Insert Control Rods with a manual Reactor trip as follows: CRS a. Perform a Pre-job brief per OAP-100.3, Human Performance Tools. RO b. Select one Intermediate Range and one Source Range Channel on NR-45, NIS RECORDER BOP c. Ensure both Motor Driven Emergency Feedwater Pumps are running. RO d. (Optional)

If desired, commence RCS boration prior to performing a manual Reactor trip: 1) Open MVT-81 04, EMERG BORATE. 2) Ensure XPP-13A(B), BA XFER PP A(B), is running. 3) Verify greater than 30 gpm flow on FI-11 0, EMERG BORATE FLOW GPM. 4) Refer to STP-134.001, Shutdown Margin Verification, to determine the required boron concentration needed for the anticipated Plant Mode and temperature:

Anticipated Mode: Anticipated RCS temperature:

OF Required Boron: ppm 5) When boration is no longer desired, perform the following:

a) Close MVT-81 04, EMERG BORATE. b) Verify no flow on FI-110, EMERG BORATE Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: __ _ Scenario No.: ____ Event No.: __ _ Page __ of __ Event

Description:

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_ Time Position RO Applicants Actions or Behavior FLOW GPM. e. Place RX TRIP Switch CS-CR01 in TRIP. f. Verify all Reactor Trip and Bypass Breakers are open. g. Verify all Rod Bottom lights are lit. h. If two or more Control Rods are not fully inserted, then emergency borate as follows: 1) Open MVT-8104, EMERG BORATE. 2) Verify greater than 30 gpm flow on FI-110, EMERG BORATE FLOW GPM. 3) If required, refer to AOP-1 06.1, Emergency Boration, to establish greater than 30 gpm flow. 4) Borate 2500 gallons if two Control Rods are not fully inserted.

5) Borate 5800 gallons if greater than two Control Rods are not fully inserted.

i. Verify Reactor Power level is decreasing.

j. Ensure RCS temperature is being maintained between 555°F and 559°F using the Steam Dump System or Steam line PORVs. k. Place both SOURCE RANGE HIGH FLUX AT SHUTDOWN Switches in BLOCK. I. When Reactor Power decreases below 7.5 x 10-6%, complete the following:

1) Verify P6 Permissive de-energizes to dim. 2) When on scale indication is observed, select both Source Range Channels on NR-45, NIS RECORDER.

This concludes the high vibration on A RCP event. The Small Break LOCA event can now commence if not already performed earlier. The following steps would again be the repeat of AOP-101.1 until the size of the leak would require EOP-1.0 entry for TRIP and SI. Appendix D, Page 39 of 39 Scenario Event Oescription VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior The following annunciators should come into alarm: XCP 606 2-2: RBCU 1A12A DRN FLO HI XCP 607 2-2: RBCU 1 B/2B DRN FLO HI XCP 616 3-6:PZR PCS LO BU HTRS ON AOP-101.1 1 Verify PZR level is at or trending to program level. 1 IF PZR level is decreasing.

THEN perform the following:

a) Open FCV-122. CHG FLOW. as necessary to maintain PZR level b) IF PZR level continues to decrease, THEN reduce Letdown to one 45 gpm orifice: 1) Set PVT-145, LO PRESS LTON. To 70% 2) Ensure PVT-8149A.

LTON ORIFICE A ISOL. is open. 3) Close both PVT-8149B(C).

LTON ORIFICE B(C) ISOL. 4) Adjust PCV-145. LO PRESS LTON. to maintain PI-145. LO PRESS LTON PRESS PSIG. Between 300 psig and 400 psig. 5) Place PCV-145, LO PRESS LTON. in AUTO. 2 Check if 51 is required:

a. Check if any of the following criteria are met:

• PZR level is decreasing with Charging maximized and Letdown minimized.

• PZR level is approaching 12%.

• PZR pressure is approaching 1870 psig.

• VCT level is approaching 5% b. Perform the following:

1) Trip the Reactor.

2) GO TO EOP-1.0. REACTOR TRIP/SAFETY INJECTION ACTUATION.

WHEN EOP-1.0 Immediate Actions are complete, THEN actuate SI. Appendix 0, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior Crew should transition to EOP-1. O. The first 5 steps are immediate operator actions. A Train of SI will fail to actuate in BOTH Manual and Automatic.

Individual components can be manually started. Reactor will NOT trip in Automatic.

Reactor can be tripped manually from the BOP side MCB Switch. 1 Verify Reactor Trip:

• Trip the Reactor using either Reactor Trip

• Verify all Reactor Trip and Bypass Breakers are open.

• Verify all Rod Bottom Lights are lit.

• Verify Reactor Power level is decreasing.

2 Verify Turbine/Generator Trip: a. Verify all Turbine STM STOP VL Vs are closed. b. Ensure Generator Trip (after 30 second delay): 1) Ensure the GEN BKR is open. 2) Ensure the GEN FIELD BKR is open. 3) Ensure the EXC FIELD CNTRL is tripped. 3 Verify both ESF buses are energized.

4 Check if SI is actuated:

SI may have actuated by this time. Step 5 is the final immediate action. a. Check if either:

• SI ACT status light is bright on XCP-61 07 1-1 . OR

• Any red first-out SI annunciator is lit on XCP-626 top row. (If no SI then: GO TO Step 5.) b. Actuate SI using either SI ACTUATION Switch. c. GO TO Step 6. 6 Initiate ATTACHMENT 3, SI EQUIPMENT VERIFICATION.

The "B" Charging pump fails to automatically start on S/. The operator is expected to attempt to manually start "B" Charging pump and it will start. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: ---Scenario No.: Event No.: -------Page __ of __ Event

Description:

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_ Time Position Applicants Actions or Behavior 7 Announce plant conditions over the page system. 8 Verify RB pressure has remained LESS THAN 12 psig on PR-951, RB PSIG (P-951), red pen. 8 Perform the following:

a) Verify both the following annunciators are lit:

• XCP-612 3-2 (RB SPR ACT).

• XCP-612 4-2 (PHASE B ISOL). IF either annunciator is NOT lit, THEN actuate RB Spray by placing the following switches to ACTUATE:

• Both CS-SGA 1 and CS-SGA2. OR

• Both CS-SGB1 and CS-SGB2. b) Verify Phase B Isolation by ensuring RB SPRAY/PHASE B ISOL monitor lights are bright on XCP-61 05. c) Ensure the following are open:

• MVG-3001A(B), RWST TO SPRAY PUMP A(B) SUCT.

• MVG-3002A(B), NAOH TO SPRAY PUMP A(B) SUCT.

• MVG-3003A(B), SPRAY HDR ISOL LOOP A(B). d) Ensure both RB Spray Pumps are running. e) Verify RB Spray flow is GREATER THAN 2500 gpm for each operating train on:

• FI-7368, SPR PP A DISCH FLOW GPM.

• FI-7378, SPR PP B DISCH FLOW GPM. f) Stop all RCPs. 9 Check RCS temperature:

• With any Rep running, RCS Tavg is stable at OR trending to 557:F. Appendix D, Page 39 of 39 I Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: -----------Page __ of __ Event

Description:

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_ Time Position Applicants Actions or Behavior OR

• With no RCP running, RCS Tcold is stable at OR trending to 557"Fc) 9 IF RCS temperature is LESS THAN 557"F AND decreasing, THEN: a) Place the STM DUMP CNTRLControlier in MAN and Closed b) Place the STM DUMP MODE SELECT Switch in STM PRESS. c) Ensure all Steamline PORVs and Condenser Steam Dumps are closed. d) IF RCS cooldown continues, THEN: 1) IF Narrow Range SG level is LESS THAN 30% [50%] in all SGs, THEN reduce EFW flow as necessary to stop the cooldown, while maintaining total EFW flow GREATER THAN 450 gpm. 2) WHEN Narrow Range SG level is GREATER THAN 30% [50%] in at least one SG, THEN control EFW flow as necessary to stabilize RCS temperature at 557"F. e) IF RCS cooldown continues, THEN close:

• MS Isolation Valves, PVM-2801A(B)(C).

• MS Isolation Bypass Valves, PVM-2869A(B)(C).

• IF RCS temperature is GREATER THAN 557"F AND increasing, THEN: a) Verify PERMISV C-9 status light is bright on XCP-6114 1-3. b) IF the Condenser is available, THEN ensure Condenser Steam Dump Valves are open. c) IF the Condenser is NOT available, THEN open the Steam line PORVs, PCV-2000(2010)(2020):

1) Place the PWR RELIEF A(B)(C) SETPT Controllers in MAN and closed. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event

Description:

Time Position Applicants Actions or Behavior 2) Place the Steamline Power Relief A(B)(C) Mode Switches in PWR RLF. 3) Adjust the PWR RELIEF A(B)(C) SETPT Controllers as necessary to reduce RCS temperature.

10 Check PZR PORVs and Spray Valves: a. PZR PORVs are closed. b. PZR Spray Valves are closed. c. Verify power is available to at least one PZR PORV Block Valve:

• MVG-8000A, RELIEF 445 A ISOL.

• MVG-8000B, RELIEF 444 B ISOL.

• MVG-8000C, RELIEF 445 B ISOL. d. Verify at least one PZR PORV Block Valve is open .. 11 Check if RCPs should be stopped: a. Check if either of the following criteria is met:

• Annunciator XCP-612 4-2 is lit (PHASE B ISOL) . OR

• RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. b. Stop all RCPs. Conditions are probably not met for securing any RCPs. GO TO Step 12. Examiners may end exam at this point. Appendix D, Page 39 of 39