Text

Initial Examination 05000259-08-301, 05000260-08-301 and 05000296-08-301 Draft Simulator Scenarios
	ML091130444
Person / Time
Site:	Browns Ferry
Issue date:	01/19/2008
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	Download: ML091130444 (201)
	v • d • e

HLTS-3-1 Revision 0 Page 1 of 41 SIMULATOR EXERCISE GUIDE TITLE : SLOW LOSS OF HP FEEDWATER HEATING ON B STRING, 3A FPC PUMP TRIP, RFP TRIP, LOSS OF ALL FEEDWATER, UNISOLABLE RCIC STEAM LINE BREAK, 2 OR MORE AREA RAD LEVELS ABOVE MAX SAFE.

REVISION : 0 DATE : January 19, 2008 PROGRAM : BFN Hot License Training PREPARED BY: \

(Operations Instructor) Date REVIEWED BY: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee) (Required for Exam Scenarios only) Date VALIDATION \

BY: (Operations SRO) (Required for Exam Scenarios only) Date

HLTS-3-1 Revision 0 Page 2 of 41 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION DATE PAGES REVIEWED NUMBER OF CHANGES AFFECTED BY 0 Initial 01/19/2008 All csf

HLTS-3-1 Revision 0 Page 3 of 41 PROGRAM: BFN Licensed Operator Requalification Training I COURSE: License Requalification Training (Simulator Exercise Guide)

III. TITLE: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING, FPC PUMP TRIP, RFP TRIP, LOSS OF ALL FEEDWATER, UNISOLABLE RCIC STEAM LINE BREAK, 2 OR MORE AREA RAD LEVELS ABOVE MAX SAFE.

I LENGHT OF LESSON: 1 1/2 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Training Objectives Terminal Objectives Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedure . Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment/unit from operation. (SOER 94-1) Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedure . Use step text procedural complianc Enabling Objectives The operating crew will alternate stator coolant pumps as directed by 3-OI-35A section . The operating crew will recognize and respond to a high pressure heater string isolation as directed by 3-ARP-9-6A and 3-AOI-6-1 . The operating crew will recognize and respond to a spurious FPC system trip and will place the 3B pump I/S in accordance with 3-ARP-94 win 1 and 3-AOI-78- . The operating crew will recognize and respond to a RFP Trip with 3-AOI-3- . The operating crew will recognize and respond to a loss of feedwater event and Rx SCRA . The operating crew will recognize and respond to unisolable RCIC steam line break, 2 or more area rad levels above max safe requiring Emergency Depressurizatio HLTS-3-1 Revision 0 Page 4 of 41 V References: The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulato A. SOER 94-01 B. SOER 96-01 VII. Training Materials: Calculator (If required) Control Rod Insertion Sheet (If required) Stopwatch (If required) Hold Order / Caution tags (If required) Annunciator window covers (If required) Steam tables (If required)

HLTS-3-1 Revision 0 Page 5 of 41 VIII. Console Operator Instructions Scenario File Summary File: bat HLTS3-1 MF/RF/IOR# Description a) ior zlofcv712[2] on Fails 71-2 and 71-3 open b) ior zlofcv713[2] on c) ior zlohs712a[2] on d) ior zlohs713a[2] on e) ior ypovfcv712 fail_now f) ior ypovfcv713 fail_now g) imf rm10h (e1 :25) 30 HCU-East rad 30 mr/hr h) imf rm10j (e1 :25) 25 HCU-West rad 25 mr/hr i) imf rm10p (e1 2:00) 50 CS/RCIC area rad 50mr/hr j) imf DG01D D D/G Fails to Start k) imf DG02D D D/G Trip Protective Relay Operation l) ior zlo3hS2113ed10a[1] OFF 1836 Green Light Off m) mrf DG01D open Opens logic breaker n) imf rp08a Auto scram failure o) imf rp08b Auto scram failure p) imf rp14b Bypass valve failure q) ior zdihs47130b null BPV jack null File: bat HLTS3-1-1 MF/RF/IOR# Description a) mmf rm10p 1000 6:00 RCIC rad to max in 6 min b) mmf rm10h 1000 13:00 HCU-West to Max in 13 min c) mmf rm10j 1000 14:00 HCU- East to Max in 14 min d) imf rc09 100 7:00 RCIC steam leak e) imf ad01b 0 MSRV 1-19 fails closed f) imf ad01f 0 MSRV 1-34 fails closed g) Imf ad03b MSRV 1-19 Stuck Closed h) Imf ad03f MSRV 1-34 Stuck Closed File: bat HLTS3-1-2 MF/RF/IOR# Description i) imf fw08b 30 RFP 3B Discharge Check Valve Sticks j) imf fw13b (none, :10) 3B RFPT trips on Thrust Brng Wear

HLTS-3-1 Revision 0 Page 6 of 41 I Console Operator Instructions Console Operators Manipulations ELAP TIME PFK DESCRIPTION/ACTION Sim. Setup rst 28 100% power MOC Sim. Setup restorepref Establishes Preference Keys HLTS3-1 Sim. Setup setup Verify Preference Keys Sim. Setup esc Clears Popup Window Sim. Setup F3 trg e1 MODESW Assigns trigger Sim. Setup F4 bat HLTS3-1 see file summary Sim. Setup manual Tag D D/G with Hold notices ROLE PLAY:

(After Stator coolant pumps alternated) As AUO, report 3-FIS-035-0065 reading 610 gp PI-035-0064 is reading 47 psi HS-035-0040 selected for A-RES Stator Coolant pump on panel 25-114.

When requested to reset local Stator F5 mrf an01b reset Allows resetting MCR alarm Coolant panel alarm then:

ROLE PLAY: As an IM report that HPCI rupture diaphragm pressure switch PS-73-20B has failed low.

When directed from the Floor then: F6 imf fw05b 100 8:00 'B HP heater string isolation ROLE PLAY: If sent to investigate which valve is open, wait 2 minutes and report 3-LCV-22B light is out (B2 high level dump)

ROLE PLAY: At 79% power, as the Reactor Engineer, recommend inserting the first group of Emergency Insert Control Rods.

If asked to reset local Cond Demin F7 mrf an01d reset allows reset of control room alarm alarm After conditions stabilized or as F8 imf sw10a Trips 3A FPC pump directed by Floor Instr.

ROLE PLAY: (If asked) As AUO, report 3-78-506, 511, & crosstie 507 are open & 3-78-510 (B hx outlet) is closed ROLE PLAY: (If asked) As RW UO, 3-FRC-78-24 is in manual & set to 0%

If asked to throttle 3-FCV-78-66 F9 ior zlohs7866a[2] on If asked to close 3-FCV-78-66 F10 dor zlohs7866a[2]

ROLE PLAY: (If asked) As Rx Bldg AUO, report 3B pump discharge pressure is 140 psig (PI-78-16 on 9-25-16)

HLTS-3-1 Revision 0 Page 7 of 41 ROLE PLAY: If sent to inspect breaker on 3A FPC pump, report bkr was found tripped and will not test After FPC restored and as directed by F11 bat HLTS3-1-2 Trips 3B RFP on thrust brng Floor Inst wear with check valve failure at 30%.

ROLE PLAY: If sent to check 3B RFP report that there is no apparent cause but you will continue to check NOTE: Mark the time when RPV level reaches +2 inches to ensure Critical Task completion of inserting a manual scram within 60 seconds of reaching +2 inches.

When directed by Lead Examiner F12 imf fw13a Trips 3A RFP on thrust brng wear If doesnt start on low level <shift>F1 imf rc02 Start of RCIC After HPCI is in manual control and <shift>F2 imf hp07 HPCI 120V failure injecting up to -50 or directed by Lead Examiner then:

After 10 minutes of RCIC operations or <shift>F4 bat HLTS3-1-1 Max. Rad (2 areas in 13 mins.)

directed by Lead Examiner then:

ROLE PLAY: If directed to close RCIC valves 71-2 & 3 locally, respond that you are waiting on RadCon to enter the Reactor building.

If decided to attempt to close valves mrf rc05k emer 71-2 to emerg locally: mrf rc05s emer 71-3 to emerg To return transfer switch to normal mrf rc05k norm 71-2 to norm mrf rc05s norm 71-3 to norm Terminates the scenario when the following conditions are satisfied or upon request of the Lead Examiner: All rods are fully inserte . Reactor water level is in the normal ban . Emergency Depressurization has been complete HLTS-3-1 Revision 0 Page 8 of 41 X. Scenario Summary With the unit operating at 100%, the crew will alternate Stator Cooling Water Pumps per 3-OI-35A. Then the operating crew will experience a slow loss of FW HTR level control on the B high pressure heater string. Once the heater is isolated and power reduced, a trip of 3A FPC pump will require the operator to start 3B FPC pump per 3-OI-78. When plant conditions are stable the 3B Reactor Feedwater Pump will trip, the crew will respond per 3-AOI-3-1. After conditions stabilize, The crew will experience a loss of the remaining RFPs which will require the crew to scram and utilize RCIC for level control. The reactor will NOT scram automatically. When RCIC is initiated it develops a steam leak which cannot be isolated forcing the crew to emergency depressurize based on 2 Area Rad Monitors above maximum safe. If HPCI is used for water level control the crew will experience a problem with the flow controller to respond in automati Eventually, HPCI will experience a failure of the 120V AC power supply and HPCI will no longer functio HLTS-3-1 Revision 0 Page 9 of 41 Information to Floor Instructors:

A. Ensure recorders are inking and recording and ICS is active and updatin B. Assign Crew Positions based on the required rotatio . SRO: Unit Supervisor ATC: Board Unit Operator BOP: Desk Unit Operator C. Terminate the scenario when the following conditions are satisfied or at the direction of the Lead Examiner: All rods fully inserted Reactor Water level normal Emergency Depressurize on 2 area RADS above max safe value

HLTS-3-1 Revision 0 Page 10 of 41 X Simulator Event Guide Event 1a: NORMAL OPERATIONS TIME POSITION EXPECTED ACTIONS ATC/BOP Alternate Stator Cooling Pumps IAW 3-OI-35A, sect. [1] START the Standby Stator Cooling Water Pump A(B) by placing GEN STATOR CLG WATER PUMP 3A(B), 3-HS-35-35A(36A) on Panel 3-9-8 to STAR [2] STOP the Stator Cooling Water Pump B(A) by placing GEN STATOR CLG WATER PUMP 3B(A), 3-HS-35-36A(35A) on Panel 3-9-8 to STO [3] VERIFY the STATOR COOLING WATER GEN INLET FLOW, 3-FIS-035-0065, indicates Min. 595 to Max. 732 gpm on Panel 25-11 [4] VERIFY the STATOR COOLING WATER GEN INLET PRESS, 3-PI-035-0064, indicates 42 (22 psig and 20 psig head) to 52 psig on Panel 25-11 [5] VERIFY the pump control switch for the stator cooling water pump stopped in Step [2] above, (3A), is returned to AUTO on Panel 3-9- [6] SELECT STATOR COOLING WATER PUMPS SEL, 3-HS-035-0040 (A-RES-CO-B-RES) on Panel 25-114 to the non-operating pum ATC/BOP Identify the improper lens configuration on Stator Cooling Water pumps and swap the lenses or informs the SR HLTS-3-1 Revision 0 Page 11 of 41 X Simulator Event Guide Event 1b: HPCI PRESSURE SWITCH FAILURE TIME POSITION EXPECTED ACTIONS ATC/BOP Responds to Report by IMs of HPCI rupture diaphragm pressure switch failure (3-PS-73-20B), by relaying information to SR SRO Consults Tech Spec 3.3.6.1 Function 3c and determines only three pressure switches are require SRO Determines an INFORMATION ONLY LCO must be written for HPCI pressure switch 3-PS-73-20 HLTS-3-1 Revision 0 Page 12 of 41 X Simulator Event Guide Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING TIME POSITION EXPECTED ACTIONS ATC/BOP Announces BYPASS VALVE TO CONDENSER NOT CLOSED and refers to 3-ARP-9-6A, win 1 ATC/BOP A. CHECK heater high or low level or moisture separator high or low level alarm window illuminated on Panel 3-9-6 or 3-9-7 to identify which bypass valve is openin B. DISPATCH personnel to check which valve's light is extinguished on junction box 34-21, Col T-13 J-LINE, elevation 565'.

SRO Direct an Upper Power Runback due to RFP speed above 5050 rp ATC Initiates an Upper Power Runback of Recirc Pump ATC/BOP Announces HEATER B2 LEVEL HIGH and refers to 3-ARP-9-6A, win VERIFY Automatic action - Drain valve to condenser 3-LCV-6-22B open A. CHECK the following indications:

Condensate flow recorder 2-29, Panel 3-9-6. Rising flow is a possible indication of a tube lea Heater B2 shell pressure, 3-PI-5-22 and drain cooler B5 flow, 3-FI-6-34, Panel 3-9-6. High or rising shell pressure or drain cooler flow is possible indication of a tube lea HLTS-3-1 Revision 0 Page 13 of 41 X Simulator Event Guide Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING TIME POSITION EXPECTED ACTIONS ATC/BOP B. CHECK drain valve 3-FCV-6-95 ope C. CHECK level on ICS screen, FEEDWATER HEATER LEVEL(FWHL).

IF the 3B2 heater indicates HIGH (Yellow), THEN VERIFY proper operation of the Drain and Dump valve DISPATCH personnel to local Panel 3-LPNL-925-562C to VERIFY and MANUALLY control the leve D. IF a valid HIGH HIGH level is received, THEN GO TO 3-AOI-6-1A or 3-AOI-6-1 ATC/BOP Announces B1 and B2 HP htr. Extraction isolation SRO DIRECTS Crew to enter 3-AOI-6-1A Contacts Reactor Engineer

HLTS-3-1 Revision 0 Page 14 of 41 X Simulator Event Guide Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING TIME POSITION EXPECTED ACTIONS ATC/BOP 3-AOI-6-1A Performs immediate actions; REDUCE Core Thermal Power to 5% below initial power level to maintain thermal margi ATC/BOP Performs subsequent actions

[1] REFER TO 3-OI-6 for turbine/heater load restriction [2] REQUEST Reactor Engineer EVALUATE and ADJUST thermal limits, as require [3] ADJUST reactor power and flow as directed by Reactor Engineer/Unit Supervisor to stay within required thermal and feedwater temperature limits. REFER TO 3-GOI-100-12 or 3-GOI-100-12A for the power reductio SRO Directs isolating FW to B HP heater string Directs power reduction to < 79% power (Mid-power runback) per 3-OI-6, Ill 1 HEATERS OUT (Tube and Shell Side)** One HP string 920 MWe (79%)

Enters 3-GOI-100-12, Power Maneuvering Notifies Rx Eng. And ODS of Feedwater Heater isolation and power reduction

HLTS-3-1 Revision 0 Page 15 of 41 X Simulator Event Guide Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING TIME POSITION EXPECTED ACTIONS ATC/BOP Closes the following FW valves (Attachment 1)

3-FCV-3-31, HP HTR 3B2 FW INLET ISOL VALVE 3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VALVE Performs a mid-power runback ~79%

ATC/BOP [4] ISOLATE heater drain flow from the feedwater heater string that isolated by closing the appropriate FEEDWATER HEATER A-2(B-2) or (C-2) DRAIN TO HTR A-3(B-3) or (C-3), 3-FCV-6-94(95) or (96). (Closes 3-FCV-6-95)

[5] VERIFY automatic actions occur. REFER TO Attachment VERIFY automatic actions The High Pressure Heater Extraction Isolation Valves and Moisture Separator Level Control Isolation valves clos FCV-5-9, HP HEATER 3B1 EXTR ISOL VLV 3-FCV-5-21, HP HEATER 3B2 EXTR ISOL VLV 3-FCV-6-74, MOISTURE SEP LC RES B1 ISOL VLV 3-FCV-6-172, MOISTURE SEP LC RES B2 ISOL VLV

HLTS-3-1 Revision 0 Page 16 of 41 X Simulator Event Guide Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING TIME POSITION EXPECTED ACTIONS Crew [6] MONITOR TURB THRUST BEARING TEMPERATURE, 3-TR-47-23, for rises in metal temperature and possible active/passive plate reversa [7] DETERMINE cause which required heater isolation and PERFORM necessary corrective action. i.e. Recognizes HTR level lowers as a result of isolating the Condensate side of 3B HP HTR string (i.e. tube leak)

SRO Direct ATC to insert the first group of control rods on the Emergency Shove Sheet per Reactor Engineer recommendatio ATC Insert the first group of rods on the Emergency Shove Sheet using a peer check as directed by Rx Engineer & Unit Supervisor

HLTS-3-1 Revision 0 Page 17 of 41 X Simulator Event Guide Event 3: Trip of 3A FPC pump TIME POSITION EXPECTED ACTIONS Crew Recognizes 3A FPC pump trip, responds per the ARP ATC/BOP Resets MOTOR TRIPOUT 3-ARP-9-8C (W33)

ATC/BOP Performs the following:

Responds to alarm FPC system abnormal 3-ARP-9-4C (W 1)

A. DISPATCH personnel to Panels 25-15 and 25-16 to determine the cause of the alar H. IF Fuel Pool Cooling System failure has occurred, THEN REFER TO 3-AOI-78- Enters 3-AOI-78-1 to start the standby FPC pump Immediate Actions - None Subsequent actions 4.2[3] IF fuel pool cooling system failure is from loss of cooling, THEN:

(Otherwise N/A) PERFORM the following:

[3.1] START idle FUEL POOL COOLING PUMP 3B(3A).

HLTS-3-1 Revision 0 Page 18 of 41 X Simulator Event Guide Event 3: Trip of 3A FPC pump TIME POSITION EXPECTED ACTIONS Coordinates with Rx Bldg AUO and Radwaste UO to start 3B FPC pump Verifies discharge pressure >120 psig with AUO Directs RW UO and Rx Bldg AUO to place demin in service SRO/BOP Dispatch AUO/EMs to check breaker for 3A FPC pump SRO Directs restoration of system after cause is determined SRO Evaluate Tech. Spec. (TRM 3.9.2/3.9.3)

SRO Determine TRM 3.9.2 Action (A) applies to maintain FP temperature below 150O HLTS-3-1 Revision 0 Page 19 of 41 X Simulator Event Guide Event 4: 3B RFPT Trip TIME POSITION EXPECTED ACTIONS ATC/BOP Announces "RFPT Abnormal" alarm and trip of RFPT 'B'.

ATC/BOP Recognize that RFPT B speed still indicates ~4000 rpm after the tri ATC/BOP Recognize that RFPT A and C are running at the upper speed limite ATC/BOP Diagnose the possibility that the discharge check valve on RFPT B has not SRO close HLTS-3-1 Revision 0 Page 20 of 41 X Simulator Event Guide Event 4: 3B RFPT Trip TIME POSITION EXPECTED ACTIONS ATC/BOP Refers to ARP 9-6C and take required action A. VERIFY reactor power is within the capacity of operating RFP B. CHECK core limit C. WHEN RFPT coasts down to zero speed, unless RFPT is rolling on minimum flow, THEN VERIFY turning gear motor starts and engage D. REFER TO 3-AOI-3-1 or 3-OI-3, Section HLTS-3-1 Revision 0 Page 21 of 41 X Simulator Event Guide Event 4: 3B RFPT Trip TIME POSITION EXPECTED ACTIONS ATC/BOP Enters 3-AOI-3-1

[1] VERIFY applicable automatic action C. Recirc Pumps receive run back signal to 75% speed at 27" (normal range) if the discharge flow of a RFP is less than 889,000 lb/hr 19% (rated flow).

[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 leve HLTS-3-1 Revision 0 Page 22 of 41 X Simulator Event Guide Event 4: 3B RFPT Trip TIME POSITION EXPECTED ACTIONS

[9] IF RFPs are in automatic control, THEN VERIFY 3-LIC-46-5 raises flow of operating RFP [12] IF a RFPT has tripped and is NOT required to maintain level, THEN SECURE tripped RFPT. REFER TO 3-OI- [14] IF unit remains on-line, THEN RETURN Reactor water level to normal operating level of 33 (normal range).

SRO Dispatches AUO to RFP to determine cause of trip ATC/BOP Verifies that unit stable Verifies Rx Thermal limits SRO Contacts maintenance to check reason for RFPT trip NOTE: LEAD EXAMINER notify Console Instructor when ready to trip the next RFP (i.e. next event)

HLTS-3-1 Revision 0 Page 23 of 41 X Simulator Event Guide Event 5: 3A and 3C RFP Trip TIME POSITION EXPECTED ACTION ATC/BOP Recognizes 3A RFP trip and need for reactor scram ATC/BOP Recognize Auto scram failure (If not manually scrammed prior)

(Critical Task)

SRO Directs Reactor scram (Critical Task)

ATC Manually scrams the reactor and performs 3-AOI-100-1 actions-mode switch in S/D-checks power lowering-reports all rods in-recognizes trip of 3C RFP and informs SRO all RFPs are tripped BOP Trip Turbine / verify isolations SRO Enters 3-EOI-1 on low reactor water level Directs level be controlled by:

-RCIC-CRD-HPCI-Enter AOI-100-1

HLTS-3-1 Revision 0 Page 24 of 41 X Simulator Event Guide Event 5: 3A and 3C RFP Trip TIME POSITION EXPECTED ACTION ATC/BOP Utilizes RCIC for reactor water level control-RCIC (App 5C)

1. IF .. BOTH of the following exist:

RPV Pressure is at or below 50 psig, AND Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN EXECUTE EOI Appendix 16A concurrently with this procedur . IF .. BOTH of the following exist:

High temperature exists in the RCIC area, AND SRO directs bypass of RCIC High temperature Isolation interlocks, THEN PERFORM the following:

a. EXECUTE EOI Appendix 16K concurrently with this procedur b. RESET auto isolation logic using RCIC AUTO-ISOL LOGIC A(B) RESET 3-XS-71-51A(B) pushbutton HLTS-3-1 Revision 0 Page 25 of 41 X Simulator Event Guide Event 5: 3A and 3C RFP Trip TIME POSITION EXPECTED ACTION BOP 3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIP/THROT VALVE RESE . VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller in AUTO with setpoint at 600 gp . 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 VL . PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in STAR . OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbin HLTS-3-1 Revision 0 Page 26 of 41 X Simulator Event Guide Event 5: 3A and 3C RFP Trip TIME POSITION EXPECTED ACTION 8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rp b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gp c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminate d. 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE, closes as flow rises above 120 gp SRO Enters 3-EOI-3 on Rx Bldg Hi Rad

HLTS-3-1 Revision 0 Page 27 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP If HPCI is used, recognizes auto control failure and places HPCI controller in manual ATC/BOP Recognizes and reports high area temperature for RCIC room Recognizes RCIC failure to isolate and attempts to manually isolate it SRO Directs RCIC be isolated locally Crew Monitors area radiation levels SRO Determines has two area radiation levels above max safe IAW 3-EOI-3 and directs emergency depressurization by opening 6 ADS valves (C2)

(Critical Task)

EXAMINER NOTE: Of the 6 ADS valves, 2 will fail to open and the candidate will have to open additional valves (any two) until six are ope ATC/BOP Opens 6 ADS valves and recognizes 2 valves failed to open and opens 2 additional valves (Critical Task)

Verifies RFP discharge valves closed before uncontrolled injection on lowering Rx pressure

HLTS-3-1 Revision 0 Page 28 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS SRO Directs RPV level be maintained between +2" and +51" with one or more of the following: (After emergency depressurization.)

(Critical Task)

-LPCI-Core Spray-Condensate ATC/BOP After emergency depressurization maintains RPV water level TAF and restores level +2" to +51" with one or more of the following:

(Critical Task)

-LPCI-Core Spray-Condensate App 6A Condensate 1. VERIFY CLOSED the following Feedwater heater return valves:

3-FCV-3-71, HP HTR 3A1 LONG CYCLE TO CNDR 3-FCV-3-72, HP HTR 3B1 LONG CYCLE TO CNDR 3-FCV-3-73, HP HTR 3C1 LONG CYCLE TO CND HLTS-3-1 Revision 0 Page 29 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP 2. VERIFY CLOSED the following RFP discharge valves:

3-FCV-3-19, RFP 3A DISCHARGE VALVE 3-FCV-3-12, RFP 3B DISCHARGE VALVE 3-FCV-3-5, RFP 3C DISCHARGE VALV . VERIFY OPEN the following drain cooler inlet valves:

3-FCV-2-72, DRAIN COOLER 3A5 CNDS INLET ISOL VLV 3-FCV-2-84, DRAIN COOLER 3B5 CNDS INLET ISOL VLV 3-FCV-2-96, DRAIN COOLER 3C5 CNDS INLET ISOL VLV 4. VERIFY OPEN the following heater outlet valves:

3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VLV 3-FCV-2-125, LP HEATER 3B3 CNDS OUTL ISOL VLV 3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VL HLTS-3-1 Revision 0 Page 30 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP 5. VERIFY OPEN the following heater isolation valves:

3-FCV-3-38, HP HTR 3A2 FW INLET ISOL VLV 3-FCV-3-31, HP HTR 3B2 FW INLET ISOL VLV 3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV 3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV 3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VLV 3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV 6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-83, RFP 3A SUCTION VALVE 3-FCV-2-95, RFP 3B SUCTION VALVE 3-FCV-2-108, RFP 3C SUCTION VALV . VERIFY at least one condensate pump runnin . VERIFY at least one condensate booster pump runnin . ADJUST 3-LIC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5).

10. VERIFY RFW flow to RP HLTS-3-1 Revision 0 Page 31 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP App 6D Core Spray Sys I (Loop II similar)

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV 3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VLV 3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALV . VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALV . VERIFY CS Pump 3A and/or 3C RUNNIN . WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS I INBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pum . MONITOR Core Spray Pump NPSH using Attachment HLTS-3-1 Revision 0 Page 32 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP App 6B RHR Sys I (Loop II similar)

1. IF ..... Adequate core cooling is assured AND It becomes necessary to bypass LPCI Injection Valve Timers to control injection, THEN ...

EXECUTE EOI Appendix 16F concurrently with this procedur . VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL . VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VL . 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 CHBR/POOL ISOL VLV 3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE 3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VL . VERIFY RHR Pump 3A and/or 3C runnin . WHEN ... RPV pressure is below 450 psig, THEN ... VERIFY OPEN 3-FCV-74-53, RHR SYS I LPCI INBD INJECT VALV . IF ..... RPV pressure is below 230 psig, THEN ... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALV HLTS-3-1 Revision 0 Page 33 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP 8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injectio . MONITOR RHR Pump NPSH using Attachment . PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RP . 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 VL . NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchanger HLTS-3-1 Revision 0 Page 34 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS SRO After 3-EOI-2 entered on high SP water level or temperature directs the following:

- H 2 O 2 analyzers placed in service ATC/BOP Places H 2 O 2 analyzers in service SRO Directs all available Suppression Pool cooling be placed into service due to Suppression Pool water temperature ATC/BOP App 17A 1. IF ..... Adequate core cooling is assured, THEN ... BYPASS LPCI Injection Valve Timers as necessary using EOI Appendices 16F and 16 Calls for App 16F&G 2. PLACE RHR SYSTEM I(II) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW heade HLTS-3-1 Revision 0 Page 35 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP 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 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 VL d. IF ..... Directed by SRO, THEN ... PLACE the following keylock switches in MANUAL OVERRIDE:

3-XS-74-122, RHR SYS I LPCI 2/3 CORE HEIGHT OVR XS-74-130, RHR SYS II LPCI 2/3 CORE HEIGHT OVR e. IF ..... LPCI INITIATION Signal exists, THEN ... MOMENTARILY PLACE the following in select:

3-XS-74-121, RHR SYS I CTMT SPRAY/CLG VLV SELEC XS-74-129, RHR SYS II CTMT SPRAY/CLG VLV SELEC HLTS-3-1 Revision 0 Page 36 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP f. IF ..... 3-FCV-74-53(67), RHR SYS I(II) LPCI INBD INJECT VALVE, is OPEN, THEN ... VERIFY CLOSED 3-FCV-74-52(66), RHR SYS I(II) LPCI OUTBD INJECT VALV g. OPEN 3-FCV-74-57(71), RHR SYS I(II) SUPPR CHBR/POOL ISOL VL h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operatin i. THROTTLE 3-FCV-74-59(73), RHR SYS I(II) SUPPR POOL CLG/TEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64),

RHR SYS I(II) FLOW:

Between 7,000 and 10,000 gpm for one-pump operation. OR At or below 13,000 gpm for two-pump operatio HLTS-3-1 Revision 0 Page 37 of 41 X Simulator Event Guide Event 6: RCIC STEAM LEAK/LOSS OF HPCI TIME POSITION EXPECTED ACTIONS ATC/BOP j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM I(II) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

k. MONITOR RHR Pump NPSH using Attachment l. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchanger m. IF ..... Additional Suppression Pool Cooling flow is necessary, THEN

... PLACE additional RHR and RHRSW pumps in service using Steps through 2.l.

Terminate scenario when emergency depressurization has occurred and Rx water level is under contro HLTS-3-1 Revision 0 Page 38 of 41 XII. Crew Critical Tasks (If an evaluated scenario)

Task SAT/UNSAT Maintains reactor water level above TAF Emergency depressurize based on 2 areas radiation above maximum safe with a primary system discharging to secondary containment (within 5 minutes) Recognize auto scram failure within one minute. (If not manually scrammed)

HLTS-3-1 Revision 0 Page 39 of 41 XII Scenario Verification Data EVENT TASK# K/A RO SR CONTROL MANIPULATION O

1. Loss of HP Feedwater Heating 295014 3.7 3.9 B17 U-068-NO-10 U-006-AB-01 S-006-AB-01 T-000-AD-17 2. 3A FPC pump trip 3. RFPs Trip 295001A2.01 3.7 3.7 B3 U-003-AB-01 S-003-AB-01 U-003-NO-08 295001A4.02 3.9 G12 3.8 T-000-AD-17 4. HPCI Pressure Switch Failure U-073-AL-19 206000A2.09 3.5 3.7 B5 S-000-AD-27 2.1.12 2.9 4.0 5. RCIC Leak/MSL Leak U-000-EM-10 295033 3.6 3.9 A7,B14,A12, U-000-EM-11 B15,I4,I20 S-000-EM-10 295032 3.5 S-000-EM-12 U-000-EM-01 3.8 U-000-EM-02 U-000-EM-03 3.6 S-000-EM-01 3.5 S-000-EM-02 3.9 S-000-EM-03 3.9 U-000-EM-14 2.4.38 2.2 S-000-EM-15 295026 3.6 S-000-EM-24 T-000-AD-04 T-000-EM-09 T-000-EM-11 T-000-EM-16

HLTS-3-1 Revision 0 Page 40 of 41 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS 3-1 5 Total Malfunctions Inserted; List: (4-8)

1) High Pressure Heater Isolation 2) 3A FPC pump trip 3) RFPT trip 4) RCIC steam leak 5) RCIC failure to isolate (auto or manual)

6) HPCI 120V Failure 7) RPS Auto Scram Failure 8) BPV Failure 9) ARI Automatic Failure 3 Malfunctions That Occur After EOI Entry; List: (1-4)

1) RCIC steam leak 2) RCIC isolation failure (auto or manual)

3) Two ADS valve failures 3 Abnormal Events; List (1-3)

1) HP Heater Isol. (ARPs)

2) 3A FPC pump trip. (AOI & ARP)

3) RFPTs trip (ARP, AOI)

1 Major Transients; List: (1-2)

1) RCIC Steam Line Break 3 EOIs used; List: (1-3)

1) EOI-1 2) EOI-2 3) EOI-3 1 EOI Contingencies Used; List: (0-3)

1) C2 90 Run Time (minutes)

29 EOI Run Time (minutes); 30 % of Scenario EOI Run Time 3 Crew Critical Tasks yes Technical Specifications Exercised (yes/no)

XI SHIFT TURNOVER INFORMATION Equipment out of service/LCOs: Unit 3 has been operating for 193 days, Unit 2 has been operating for 56 days. Unit 1 has been operating for 290 days.

3ED Diesel Generator is tagged for water jacket leakage repair. Day 2 of LCO, will be returned to service this shift.

Operation/Maintenance for the Shift: Support scheduled maintenance and testing activities Alternate Stator Cooling Water Pumps per 3-OI-35A, Sect 6.4 for scheduled maintenance on 3A Stator Cooling Water Pump. HPCI SR in progress for rupture disk pressure switches by IMs.

Unusual Conditions/Problem Areas: Fuel leakers on U3 are currently @ RFI 60,000.

Storms passing through the region, No Watches in effect for the immediate area.

3C RFP was oscillating approximately 30 RPM during the last shift, but currently working properly and being monitored. 3C RFP is operating in automatic to collect data for next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . A trouble shooting plan is being develope Appendix D Scenario Outline Form ES-D-1 Facility: BFN Scenario Number: HLTS-3-1 Op-Test Number: HLT0610 Examiners:__________________ Operators: _________________

__________________ _________________

Initial Conditions:

Unit 3 has been operating for 192 days. Unit 2 has been operating for 56 days. Unit 1 has been operating for 274 days. 3ED Diesel Generator is tagged for water jacket leakage repair. Day 2 of the LCO. Expected to be returned to service this shift. Fuel leakers on U3 are currently at RFI 60,000. Thunderstorms are passing through the region, but no watches are in effect for the immediate area. The 3C RFP was oscillating approximating 30 RPM during last shift, but is now working properly and being monitored. The 3C RFP Pump is operating in automatic in order to collect data for the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . A trouble shooting plan is being developed.

Turnover:

Support scheduled maintenance and testing activities. Alternate Stator Cooling Water Pumps per 3-OI-35A, Sect 6.3 per scheduled OP Event Malfunction Event Event Number Number Type* Description 1 mrf an01b reset N-ATC The crew will alternate Stator Cooling Water Pumps using 3-N-BOP OI-35 N-SRO 1 N/A I-BOP The crew will respond to a HPCI Rupture Diaphragm pressure TS-SRO switch PS-73-20B failur imf fw05b 100 R-ATC The crew will respond to a 3B HP FW heater isolation using 8:00 C-BOP 3-AOI-6- R-SRO The crew will reduce power to ~91% using a recirc flow reductio The crew will isolate feedwater to the 3B FW heater strin The crew will further reduce power to <79% using a recirc flow reductio imf sw10a C-BOP The crew will respond to a trip of the 3A Fuel Pool Cooling C-SRO pump using 3-AOI-78- imf fw13b C-ATC The crew will respond to a trip of the 3B Reactor Feedwater C-BOP Pump (RFP) using 3-AOI-3-1 and 3-OI- C-SRO 5 bat M The crew will respond to a total loss of feedwater and reactor NRCrfpactrip All scra bat M The crew will respond to a RCIC steam leak into secondary HLTS04-1 All containmen The crew will anticipate Emergency Depressurization or perform Emergency Depressurization due to secondary containment high radiation.

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

HLTS-3-2 REV 0 PAGE 1 OF 63

-

SIMULATOR EVALUATION GUIDE TITLE : HPCI STEAMLINE BREAK, SRV FAILURE, RECIRC PUMP TRIP, DRYWELL LEAK ,

EMERGENCY DEPRESSURIZATION ON LEVEL (C1)

REVISION : 0 DATE : January 19, 2008 PROGRAM : BFN Operator Training - Hot License PREPARED BY: \

(Operations Instructor) Date REVIEWED BY: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee) (Required for Exam Scenarios only) Date VALIDATION BY: \

(Operations SRO) (Required for Exam Scenarios only) Date Requires copy of 3-SR-3.5.1.7 (current rev.) completed up to step 7.11 to be provided to crew at turnover

HLTS-3-2 REV 0 PAGE 2 OF 63 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF DATE PAGES REVIEWED BY NUMBER REVISION AFFECTED 0 INITIAL 1/19/08 All csf

HLTS-3-2 REV 0 PAGE 3 OF 63 Program: BFN Operator Training I Course: Hot License Training III. Title: HPCI STEAMLINE BREAK, SRV FAILURE, RECIRC PUMP TRIP, DRYWELL LEAK , EMERGENCY DEPRESSURIZATION ON LEVEL (C1)

I Length of Scenario: 1 to 1 1/2 hours Examination Objectives: Terminal Objective 1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedure . Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, abnormal, annunciator and emergency procedure B. Enabling Objectives:

1. The operating crew will alternate EHC pump . The operating crew will continue power ascension from 79% powe . The operating crew will experience a HPCI steam line break during performance of 3-SR-3.5.1.7 , HPCI Flow Rate, with a failure of HPCI to auto isolat . The operating crew will recognize and respond to a safety-relief valve failed ope . The operating crew will recognize and respond to a high vibration and trip of 3A Recirc pum . The operating crew will recognize and respond to reactor power oscillations by scramming the reacto . The operating crew will recognize and respond to a high drywell pressure conditio . The operating crew will Emergency De-pressurize when in C1 before reactor water level reaches -18 HLTS-3-2 REV 0 PAGE 4 OF 63 V References: The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: Calculator Control Rod Insertion Sheet Stopwatch Hold Order/Caution tags Annunciator window covers Steam tables

HLTS-3-2 REV 0 PAGE 5 OF 63 VIII. Console Operators Instructions Scenario File Summary File: bat HLTS3-2 MF/RF/1OR# Description a) trg e1 MODESW Sets trigger b) trg e2 adssrv1-22 Sets trigger c) ior zlohs7416a[1] off Tag Out 3C RHR d) imf rh01c 3C RHR Pump trip e) ior ypobkrpmpcrh fail_power Control power for RHR 3C breaker f) mrf hw01 fast Advances all charts g) imf th33b (e1 0) 1 2:00 B MSL break in DW h) imf th21 (e1 5:00) 0.5 10:00 Recirc. line break i) imf rd01a (e1 10:00) 3A CRDP trip j) imf rd01b 3B CRDP trip k) imf hp09 Failure of HPCI to auto isolate l) ior zdihs718a close Fails RCIC m) ior ypovfcv718 fail_power Keeps the 71-8 valve closed n) imf rp11 (e1 1:00) MSIV logic fuse failure File: bat RRPAVIB MF/RF/1OR# Description 1) imf th12a Inserts Vibration Alarm 2) imf th10a (none 1: ) Fails Recirc Pump A Inboard Seal 3) imf th11a (none 2: ) Fails Recirc Pump A Outboard Seal)

4) ior zdihs681 open Prevents Recirc Pump A Suction Valve Closure

HLTS-3-2 REV 0 PAGE 6 OF 63 B. Console Operators Manipulations ELAP. TIME PFK# DESCRIPTION/ACTION Simulator setup rst 28 78 %Power MOC, use mid-power runback push button Simulator setup restorepref Establishes Function Keys HLTS3-2 Simulator setup setup Verify Function Keys Simulator setup esc Clears Function Key Popup Simulator setup F3 bat HLTS3-2 See Scenario File Summary Simulator setup manual Place suppression pool cooling in service (Loop II)

Simulator setup manual Place HO tags on 3C RHR pump Simulator setup manual Place TESTING/MAINT frames on Panel 9-3F, Windows 5, 11, 26 for HPCI 3-SR-3.5.1.7 complete up to step 7.11 Simulator setup manual Provide a copy of 3-SR-3.6.2.1.1, Suppression Chamber Water Temperature Check Simulator setup manual Verify lens covers on EHC pumps are correct ROLE PLAY: When asked for local EHC pressure, (3-PI-047-0001(0002)) indicates 1625 psig. (3-OI-47A section step [4].

ROLE PLAY: When asked, EHC pump 3B EHC PUMP SUCTION FILTER and EHC AUX PUMP SUCTION FILTERS, indicate CLEAN, (3-OI-47A section 6.3 step [11].

ROLE PLAY: When asked, MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at 2.0 turns clockwise. (3-OI-47A section 6.3 step [12].

ROLE PLAY: If asked, state that the anti-rotation collar markings are aligne When HPCI is at rated pressure and F4 imf hp08 Steam leak into HPCI room flow ROLE PLAY: AUO at HPCI quad. Reports a large steam leak on HPCI and present location is elev. 565 Rx.Bld When directed by Lead Instructor F6 imf ad01c 40 Fails SRV-1-22 open When RO cycles SRV then: F7 dmf ad01c SRV-1-22 closes When directed by Lead Instructor F8 bat RRPAVIB Recirc Pump A high vibration, seal failure, suction valve fails to close and power oscillations.

ROLE PLAY: When dispatched to check 3A Recirc Vibration, wait 2 minutes and report back swinging 10 to 14 mil HLTS-3-2 REV 0 PAGE 7 OF 63 C. Console Operators Manipulations ELAP. TIME PFK# DESCRIPTION/ACTION When A Recirc trips F9 dmf th12a Deletes vibration high alarm 4 min. after 3A recirc. pump trip F10 imf cr02a 75 3:00 Core power oscillations then: and F11 imf th22 (none 1:30) 100 Bottom head leak When requested, wait 3 minutes F12 bat app16fg Defeats RHR injection valve timers Terminate the scenario when the following conditions are satisfied are at the direction of the Lead Examine . RPV water level +2 to +51 2. Drywell sprayed 3. Emergency Depressurizarion completed

HLTS-3-2 REV 0 PAGE 8 OF 63 I Scenario Summary Given Unit 3 at 79% power, the crew will alternate EHC pumps and resume power ascension to 100%. As 3-SR-3.5.1.7, HPCI Flow Rate, is continued the crew will experience a ruptured HPCI steam line with a failure of HPCI to automatically isolate. Manual HPCI isolation will be possible. As power ascension is continued, an SRV fails open but can be closed as steps of 3-AOI-1-1 are performed. The crew experiences high vibration with a subsequent trip and seal leakage on the 3A Recirc Pump resulting in high drywell pressure. When the diesel generators automatically start the 3ED diesel generator fails to auto start but can be manually started.

Finally, the crew will Emergency Depressurizes before reactor water level reaches -20 HLTS-3-2 REV 0 PAGE 9 OF 63 X. Information to Floor Instructors: Ensure recorders are inking and recording and ICS is active and updatin Assign Crew Positions based on the required rotatio . SRO: Unit Supervisor ATC: Board Unit Operator BOP: Desk Unit Operator Conduct a shift turnover with the Unit Superviso Direct the shift crew to review the control board and take note of present conditions, alarms, et Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluato . RPV water level +2 to +51 2. Emergency Depressurizarion completed

HLTS-3-2 REV 0 PAGE 10 OF 63 X Simulator Event Guide Event 1: Alternate EHC Pumps TIME POSITION EXPECTED ACTION(S)

ATC/BOP Receive crew briefing and walk boards down SRO Directs BOP to alternate EHC pumps BOP Alternates EHC Pumps in accordance with 3-OI-47A section [1] VERIFY EHC Sys is in service. REFER TO Section [2] REVIEW Precautions & Limitations listed in Section [3] START the non-operating EHC PUMP 3B(3A) using EHC HYD FLUID PUMP 3B(3A), 3-HS-47-2A(1A).

[4] CHECK the started EHC pump EHC HYD PUMP A(B) DISCH PRESS, 3-PI-047-0001(0002), indicates between 1550 psig and 1750 psig, locally at the EHC skid. (AUO reports 1625 psig)

[5] IF the started EHC pump discharge pressure is NOT between 1550 psig and 1750 psig, THEN ADJUST the pressure compensator for the started EHC pump to adjust pump discharge pressure. REFER TO Step 8.6[1].

[6] STOP EHC PUMP 3A(3B) using EHC HYD FLUID PUMP 3A(3B), 3-HS-47-1A(2A).

HLTS-3-2 REV 0 PAGE 11 OF 63 X Simulator Event Guide Event 1: Alternate EHC Pumps TIME POSITION EXPECTED ACTION(S)

[7] CHECK EHC HEADER PRESSURE, 3-PI-47-7, indicates between 1550 psig and 1650 psi [8] IF EHC header pressure is NOT between 1550 psig and 1650 psig, THEN ADJUST the pressure compensator for the operating EHC pump to adjust EHC header pressure. REFER TO Step 8.6[2].

[9] IF there are any disagreement flags, THEN RESET disagreement flags by placing the operating pump handswitch, EHC HYD FLUID PUMP 3A(3B), 3-HS-47-1A(2A), to STAR [10] CHECK the started EHC PUMP 3B(3A) MTR AMPS, 3-EI-47-2(1), indicates less than 140 amp [11] VERIFY EHC Pump 3B(3A), EHC PUMP SUCTION FILTER and EHC AUX PUMP SUCTION FILTERS, indicate CLEAN, locally at the EHC ski [12] [NER/C] VERIFY MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at 2.0 turns clockwise. [INPO SOER 84-006]

BOP Swaps lens covers for EHC pumps based on new lineup

HLTS-3-2 REV 0 PAGE 12 OF 63 X Simulator Event Guide (Continued)

Event 2: Power Ascension TIME POSITION EXPECTED ACTION(S)

SRO Directs power ascension per 3-GOI-100-12 step 6.2 and 3-OI-68 ATC Raises reactor power in accordance with 3-GOI-100-12 and 3-OI-68

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM) 3-HS-96-17A(17B), push-buttons, to achieve balanced jet pump flows. AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-6A(16B) /LOWER SLOW(MEDIUM)

3-HS-96-18A(18B), pushbuttons, to achieve balanced jet pump flow [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-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 BOP Performs as peer checker for recirc flow changes

HLTS-3-2 REV 0 PAGE 13 OF 63 X Simulator Event Guide (Continued)

Event 3a: HPCI Surveillence TIME POSITION EXPECTED ACTION(S)

SRO Directs BOP to continue with 3-SR-3.5.1.7 at step 7[11]

BOP [11] ALIGN HPCI System for a manual start by performing the following steps:

[11.1] CHECK HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 is in AUTO and SET to control at 500 (5,000 gpm).

IF required, THEN DEPRESS AUTO operation mode transfer switch and ADJUST setpoint using Setpoint up/down key [11.2] PLACE HPCI STEAM PACKING EXHAUSTER by placing 3-HS-73-10A to STAR [11.3] VERIFY 3-FCV-73-36, using HPCI/RCIC CST TEST VLV 3-HS-73-36A, is OPE [11.4] OPEN 3-FCV-73-35, using HPCI PUMP CST TEST VLV, 3-HS-73-35 [12] START the HPCI turbine by performing the following:

[12.1] [NER] VERIFY communication is established with Operations personnel in HPCI Room. [IE 93-67]

[12.2] [NER] REQUEST Operations personnel in HPCI Room, to ensure that all unnecessary personnel have exited HPCI Room. [IE 93-67]

[12.3] [NER] ANNOUNCE HPCI turbine startup over plant public address system. [IE 93-67]

HLTS-3-2 REV 0 PAGE 14 OF 63 X Simulator Event Guide (Continued)

Event 3a: HPCI Surveillence TIME POSITION EXPECTED ACTION(S)

BOP [12.4] PLACE HPCI AUXILIARY OIL PUMP 3-HS-73-47A to STAR [12.5] OPEN 3-FCV-73-30, using HPCI PUMP MIN FLOW VALVE, 3-HS-73-30 [12.6] ENSURE personnel are ready to monitor 3-FCV-73-18 for smooth operation. AND NOTIFY the personnel monitoring that the next step will open 3-FCV-73-1 [12.7] OPEN 3-FCV-73-16, using HPCI TURBINE STEAM SUPPLY VLV, 3-HS-73-16 [12.8] OBSERVE that the following actions occurs:

HPCI AUXILIARY OIL PUMP start [NRC/C] HPCI TURBINE STOP VALVE 3-FCV-73-18 opens by observing 3-ZI-73-18 position indicating lights. [Appendix R]

HPCI TURBINE CONTROL VALVE 3-FCV-73-19 partially or fully opens by observing 3-ZI-73-19 position indicating light HLTS-3-2 REV 0 PAGE 15 OF 63 X Simulator Event Guide (Continued)

Event 3a: HPCI Surveillence TIME POSITION EXPECTED ACTION(S)

[NRC/C] HPCI PUMP MIN FLOW VALVE 3-FCV-73-30 closes when HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 indicates approximately 125 (1250 gpm) flow. [Appendix R]

HPCI turbine speed rises to greater than 2400 rpm as indicated on HPCI TURBINE SPEED 3-SI-73-5 HPCI STM LINE CNDS INBD/OUTBD DR VLVS 3-FCV-73-6A and 3-FCV-73-6B close by observing 3-ZI-73-6A and 3-ZI-73-6B position indicating light HPCI AUXILIARY OIL PUMP stops as turbine speed rise [12.9] VERIFY Smooth operation of 3-FCV-73-18 and mark results belo Yes ________No ________

IF the Answer above is NO, THEN NOTIFY System Engineer to initiate a WO and proceed with test. (Otherwise N/A)

[12.10] VERIFY RESET the following annunciators:

HPCI PUMP DISCH FLOW LOW 3-FA-73-33 (3-XA-55-3F, window 5)

HPCI TURBINE TRIPPED 3-ZA-73-18 (3-XA-55-3F, window 11)

HPCI TURBINE GLAND SEAL DRAIN PRESSURE HIGH 3-PA-73-46 (3-XA-55-3F, window 14)

HPCI TURBINE BEARING OIL PRESSURE LOW 3-PA-73-47 (3-XA-55-3F, window 19)

[12.11] VERIFY system flow, discharge pressure, and turbine speed are stable prior to performing the next ste HLTS-3-2 REV 0 PAGE 16 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP Responds to Reactor Bldg Hi Rad alarm per 3-ARP-9-3A window 22 A. DETERMINE area with high radiation level on Panel 3-9-11. (Alarm on Panel 3-9-11 will automatically reset if radiation level lowers below setpoint.)

Determines HPCI area source of hi rad

B. IF the alarm is from the HPCI Room while Flow testing is being performed, THEN REQUEST personnel at the HPCI Quad to validate condition C. NOTIFY RADCO D. IF the TSC is NOT manned and a VALID radiological condition exists.,

THEN USE public address system to evacuate area where high airborne conditions exist

E. IF the TSC is manned and a VALID radiological condition exists, THEN REQUEST the TSC to evacuate non-essential personnel from affected area HLTS-3-2 REV 0 PAGE 17 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

F. MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed i G. IF a CREV initiation is received, THEN 1. VERIFY CREV A(B) Flow is 2700 CFM, and 3300 CFM as indicated on 0-FI-031-7214(7213) within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of the CREV initiation. [BFPER 03-017922]

2. IF CREV A(B) Flow is NOT 2700 CFM, and 3300 CFM as indicated on 0-FI-031-7214(7213) THEN PERFORM the following: (Otherwise N/A) [BFPER 03-017922]

a. STOP the operating CREV per 0-OI-3 b. START the standby CREV per 0-OI-3 SRO Enters EOI-3 on High Rad. / High Tem HLTS-3-2 REV 0 PAGE 18 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP Responds to HPCI Leak Detection Temp Hi alarm per 3-ARP-9-3F window 10 A. CHECK HPCI temperature switches on LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29 on Panel 3-9-2 B. IF high temperature is confirmed, THEN ENTER 3-EOI-3 Flowchar C. CHECK following on Panel 3-9-11 and NOTIFY RADCON if rising radiation levels are observed:

1. HPCI ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-24 . RHR WEST ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-25 D. DISPATCH personnel to investigate for leaks consistent with ALARA considerations in HPCI Turbine Area (El 519) and HPCI Steam Supply Area (El 550).

Recognizes HPCI not isolated when isolation lights are illuminated Notifies Unit Supervisor HPCI failed to isolate and 3-FCV-73-2 and 3-FCV-73-3 are still ope HLTS-3-2 REV 0 PAGE 19 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

SRO Directs HPCI manually isolated (Critical step)

BOP Manually isolates HPCI steam supply by closing 3-FCV-73-2 and 3-FCV-73-3 (Critical step)

ATC Receives EOI-3 entry on flood level in HPCI room 3-ARP-9-4c window 10 A. DISPATCH personnel to VISUALLY CHECK the HPCI roo B. IF possible, THEN DETERMINE the source of the leak and the leak rat SRO Re-enters EOI-3 on flood level BOP Notifies Rad Con and Fire Protection Monitors for lowering temperature and radiation levels in HPCI area (after successful isolation)

HLTS-3-2 REV 0 PAGE 20 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

SRO Directs entry into 3-AOI-64-2B BOP Immediate Actions

[1] VERIFY automatic actions occu HPCI Turbine TRIP HPCI STEAM LINE INBD ISOL VALVE, 3-FCV-73-2 CLOSE HPCI STEAM LINE OUTBD ISOL VALVE, 3-FCV-73-3 CLOSE HPCI STEAM LINE WARM-UP VALVE, 3-FCV-73-81 CLOSE HPCI PUMP MIN FLOW VALVE, 3-FCV-73-30 CLOSE HPCI SUPPR POOL INBD SUCT VLV, 3-FCV-73-26 CLOSE HPCI SUPPR POOL OUTBD SUCT VLV, 3-FCV-73-27 CLOSE HPCI TURBINE STOP VALVE, 3-FCV-73-18 CLOSE HLTS-3-2 REV 0 PAGE 21 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP Subsequent Actions

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

[2] DISPATCH an operator to the HPCI Turbine room to investigat [3] CHECK the following monitors for a rise in activity or area temperature:

AREA RADIATION, 3-RR-90-1, Point 23 (RM-90-24), Panel 3-9-2

AIR PARTICULATE RAD MON, 3-MON-90-50, Address 024 (3-RM-90-58),

Panel 3-9-2

RB & TB REFUELING ZONE EXH RAD MONITOR, 0-CONS-90-362, Address 08, 3-RM-90-250, Panel 1-9-44

LEAK DET SYS, TI-69-29, Panel 3-9-21, DEPRESS pushbutton to read TS-73-55A through 55 HLTS-3-2 REV 0 PAGE 22 OF 63 X Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP [4] VERIFY the following valves OPEN to drain the HPCI steam line MN STM LINE DRAIN INBD VLV, 3-FCV-1-55 OUTBD ISOLATION VLV, 3-FCV-1- -56,

[5] IF the HPCI TURBINE EXH DRAIN POT LEVEL HIGH 3-LA-73-8 (3-XA-55-3F, Window 33) annunciator is in alarm, THEN PERFORM the following:

[5.1] OPEN the HPCI TURB EXH CNDS POT LCV, 3-LCV-73- [5.2] WHEN the annunciator HPCI TURBINE EXH DRAIN POT LEVEL HIGH resets, THEN CLOSE the HPCI TURB EXH CNDS POT LCV, 3-LCV-73- SRO Determines unit in 14 day LCO (TS 3.5.1.C - HPCI inop. Verify RCIC OPERABLE by administrative means)

Determines unit in 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO (TS 3.5.1.D - HPCI and C RHR Inop)

Tech. Specs. 3.6.1.3.B.1, on FCV 73-2 or 73-3 when tagged (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to close and de-activate)

EXAMINER NOTE: When the valves are closed they are now considered OPERABLE because they are in the required position following an isolation signal, however the isolation logic is still INOPERATIV HLTS-3-2 REV 0 PAGE 23 OF 63 X Simulator Event Guide (Continued)

Event 4: SRV-1-22 Fails Open TIME POSITION EXPECTED ACTION(S)

CREW Recognizes SRV open Main Steam Relief Valve Open alarm lowering generator output SRO Directs response per 3-AOI-1-1 BOP Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT-1-4, on Panel 3-9-3, OR MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1 on Panel 3-9-4 Determines SRV-1-22 from acoustic monitor

[2] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch several times as required:

CLOSE to OPEN to CLOSE positions

Cycles relief valve and reports SRV closed

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A)

HLTS-3-2 REV 0 PAGE 24 OF 63 X Simulator Event Guide (Continued)

Event 4: SRV-1-22 Fails Open (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 4.2.3 Other Actions and Documentation

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

[2] REFER TO Technical Specifications Sections 3.5.1 and 3.4.3 for Automatic Depressurization System and relief valve operability requirement [3] INITIATE suppression pool cooling as necessary to maintain suppression pool temperature less than 95° [4] IF the relief valve can NOT be closed AND suppression pool temperature Can NOT be maintained less than or equal to 95°F, THEN PLACE the reactor Mode 4 in accordance with 3-GOI-100-12 [5] DOCUMENT actions taken and INITIATE Work Order for the valv SRO Evaluates Tech Spec operability of ADS valve IAW TS 3.5.1(H) and 3.4.3(A). Determines valve operable and 3.5.1.H is not applicable, but requests Eng. evaluation. (Functional evaluation)

HLTS-3-2 REV 0 PAGE 25 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS ATC Announces Recirc 3A high vibration alarm 3-ARP-9-4A window 20 Consults ARP for Panel 9-4 A. CHECK temperatures for RECIRC PMP MTR 3A WINDING AND BRG TEMP recorder, 3-TR-68-58 on Panel 3-9-21 are below those listed for 3-XA-55-4A, Window 1 B. CHECK for a rise in Drywell equip sump pumpout rate due to seal leakag C. DISPATCH personnel to 3-LPNL-925-0412 (Vibration Mon. System) on EL 565' (S-R17) and REPORT the Vibration Data for Pump A to the Unit Operator and any other alarm indications. The person shall advise the Unit Operator of any changes in the vibration value D. IF alarm seals in, THEN ADJUST pump speed slightly to try reset the alar E. IF unable to reset alarm, THEN CONSULT with Shift Manager, and with his concurrence, SHUTDOWN the Recirc pump and REFER TO 3-AOI-68-1A or 3-AOI-68-1 F. IF pump operation continues, THEN RECORD pump 3A seal parameters hourly on Attachment 1, Page 22 of this AR HLTS-3-2 REV 0 PAGE 26 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS SRO Contacts Reactor Engineer ATC Announces Recirc A Seal Leakage Alarm 3-ARP-9-4A window 25 A. DETERMINE initiating cause by comparing No. 1 and 2 seal cavity pressure indicators on Panel 3-9-4 or IC Plugging of No. 1 RO - No. 2 seal cavity pressure indicator drops toward zero, and control leakage lowers to 0.5 gp Plugging of No. 2 RO - No. 2 seal pressure approaches no. 1 seal pressure and control leakage lowers to 0.5 gp Failure of No. 1 seal - No. 2 seal pressure is greater than 50% of the pressure of No. 1. The controlled leakage will be 0.9 gp Failure of No. 2 seal - no. 2 seal pressure is less than 50% of the No. 1 sea HLTS-3-2 REV 0 PAGE 27 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS ATC Identifies Seal Failure via Instrumentation Recognizes lowering pressure on Recirc Pump A #1 seal B. RECORD pump seal parameters hourly on Attachment 1, Page 28 of this procedure, unless other acceptable compensatory methods for recording these parameters is evaluated and approved by Engineerin C. IF single seal failure is indicated, THEN INITIATE seal replacement as soon as possible. Continued operation is permissible if Drywell leakrate is within T.S. limit SRO Directs crew to watch for signs of increased leakage ATC Acknowledges Recirc Pump A seal leakoff high alarm; 3-ARP-9-4A window 18, informs SR Recognizes lowering pressure on Recirc Pump A outboard seal; informs SRO Monitors drywell parameters; notes pressure and temperature increasing; informs SRO

HLTS-3-2 REV 0 PAGE 28 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS SRO When vibration report received or dual seal failure is reported, directs A Recirc Pump tripped ATC C. IF dual seal failure is indicated, THEN

1. SHUTDOWN Recirc Pump 3A by depressing RECIRC DRIVE 3A SHUTDOWN, 3-HS-96-1 . VERIFY TRIPPED, RECIRC DRIVE 3A NORMAL FEEDER, 3-HS-57-1 . VERIFY TRIPPED, RECIRC DRIVE 3A ALTERNATE FEEDER, 3-HS-57-1 . CLOSE Recirculation Pump 3A suction valv REPORT to SRO of failure of suction valve to clos Directs AUO to close Recirc Pump suction valve locally at Boar . CLOSE Recirculation Pump 3A discharge valv . REFER TO 3-AOI-68-1A or 3-AOI-68-1B AND 3-OI-6 . DISPATCH personnel to secure Recirculation Pump 3A seal wate HLTS-3-2 REV 0 PAGE 29 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS ATC [2] Checks Power to flow map to verify in region 1 or 2 Informs SRO of being in region 1 Checks APRMs and LPRMs for indication of power oscillations Informs SRO of Power Oscillations SRO Directs inserting emergency shove sheet control rods BOP Keeps SRO informed as drywell pressure approaches 2.45 psig

HLTS-3-2 REV 0 PAGE 30 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS SRO Directs venting per 3-AOI-64-1 EXAMINER NOTE: Venting may not be performed based on Drywell pressur BOP Vents per 3-AOI-64-1

[3] VENT Drywell as follows:

[3.1] CLOSE SUPPR CHBR INBD ISOLATION VLV 3-FCV-64-34 (Panel 3-9-3).

[3.2] VERIFY OPEN, DRYWELL INBD ISOLATION VLV, 3-FCV-64-31 (Panel 3-9-3).

[3.3] VERIFY 3-FIC-84-20 is in AUTO and SET at 100 scfm (Panel 3-9-55).

[3.4] VERIFY Running, required Standby Gas Treatment Fan(s) SGTS Train(s)

A, B, C (Panel 3-9-25).

[3.5] IF required, THEN REQUEST Unit 1 Operator to START Standby Gas Treatment Fan(s) SGTS Train(s) A, B. (Otherwise N/A)

HLTS-3-2 REV 0 PAGE 31 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS

[3.6] IF required, THEN RECORD venting data in 3-SI-4.7.A.2.a (Otherwise N/A)

[3.7] PLACE 3-FCV-84-20 CONTROL DW/SUPPR CHBR VENT, 3-HS-64-35, in OPEN (Panel 3-9-3).

[3.8] MONITOR stack release rates to prevent exceeding ODCM limit Directs Logs person to monitor release rates SRO Directs manual reactor scram prior to reaching 2.45psig DW pressure ATC Scrams the reactor

HLTS-3-2 REV 0 PAGE 32 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS SRO Directs 3-AOI-100-1 ATC Carry out actions of 3-AOI-100-1 SRO Enters EOI- 1 & 2 at 2.45 psig drywell pressure SRO Directs venting per Appendix 12 BOP 1. VERIFY at least one SGTS train in servic . VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV, 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV, 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALV HLTS-3-2 REV 0 PAGE 33 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS 3. IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN .

PERFORM step 13 to secure the vent path and reenter this procedure if further venting is require . IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN . PERFORM step 13 to secure the vent path and reenter this procedure if further venting is require BOP 5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN . BEFORE CAD is initiated, PERFORM Step 13 to secure the vent pat NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR 3-FIC-84-20, PATH A VENT FLOW CON NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vente HLTS-3-2 REV 0 PAGE 34 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS 6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR Suppression Chamber can NOT be vented, OR SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

Step 10 to vent the Drywell through 3-FCV-84-19, OR Step 11 to vent the Drywell through 3-FCV-84-2 . CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR Step 9 to vent the Suppression Chamber through 3-FCV-84-2 HLTS-3-2 REV 0 PAGE 35 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scf f. CONTINUE in this procedure at step 1 HLTS-3-2 REV 0 PAGE 36 OF 63 X Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND 3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND Release rates as determined below:

i. IF. . .PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress THEN. .MAINTAIN release rates below those specified in Attachment ii. IF. . .Severe Accident Management Guidelines are being executed, THE .MAINTAIN release rates below those specified by the TSC SAM Tea iii. IF. . .Venting for ANY other reason than items i or ii above, THE .MAINTAIN release rates below Stack release rate of 1.4 x 107 Ci/s AND 0-SI-4.8.B.1.a.1 release fraction of BOP Contacts LOG AUO to monitor release rates

HLTS-3-2 REV 0 PAGE 37 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA TIME POSITION EXPECTED ACTION(S)

SRO - Directs RPV pressure controlled 800 to 1000 psig with one or more of the following:

- MSRV's (App 11A)

- RCIC (App 11B) (will not work)

- Directs RPV level be maintained between +2" to +51" with one or more of the following:

-RCIC (App 5C) (will not work)

-CRD (App 5B)

BOP Controls pressure 800 to 1000 psig with one or more of the following:

- MSRV's (App 11A)

1. IF ..... Drywell Control Air is NOT available, THEN ... EXECUTE EOI Appendix 8G, CROSSTIE CAD TO DRYWELL CONTROL AIR, CONCURRENTLY with this procedur . IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other option HLTS-3-2 REV 0 PAGE 38 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA TIME POSITION EXPECTED ACTIONS BOP 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 VALV b. 2 3-PCV-1-180 MN STM LINE D RELIEF VALV c. 3 3-PCV-1-4 MN STM LINE A RELIEF VALV d. 4 3-PCV-1-31 MN STM LINE C RELIEF VALV e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALV f. 6 3-PCV-1-42 MN STM LINE D RELIEF VALV g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALV h. 8 3-PCV-1-19 MN STM LINE B RELIEF VALV i. 9 3-PCV-1-5 MN STM LINE A RELIEF VALV j. 10 3-PCV-1-41 MN STM LINE D RELIEF VALV k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALV l. 12 3-PCV-1-18 MN STM LINE B RELIEF VALV m. 13 3-PCV-1-34 MN STM LINE C RELIEF VALV HLTS-3-2 REV 0 PAGE 39 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA TIME POSITION EXPECTED ACTIONS BOP Recognizes MSIV closures and reports to SR BOP Controls RPV level +2 to +51 with one or more of the following:

-RCIC (App 5C) (will not work)

-CRD (App 5B)

BOP -CRD (App 5B)

1. IF ..... Maximum injection flow is NOT required, THEN ... VERIFY CRD aligned as follows:

a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD syste b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to obtain flow rate of 65 to 85 gp c. THROTTLE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV, to maintain 250 to 350 psid drive water header pressure differentia d. EXIT this procedur HLTS-3-2 REV 0 PAGE 40 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA TIME POSITION EXPECTED ACTIONS 2. IF .. BOTH of the following exist:

CRD is NOT required for rod insertion, AND Maximum injection flow is required, THEN LINE UP ALL available CRD pumps to the RPV as follows:

a. IF .. CRD Pump 3A is available, THEN VERIFY RUNNING CRD Pump 3A or 3 b. IF .. CRD Pump 3B is available, THEN VERIFY RUNNING CRD Pump 3A or 3 c. OPEN the following valves to increase CRD flow to the RPV:

3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV 3-PCV-85-27, CRD CLG WATER PRESS CONTROL VLV 3-FCV-85-50, CRD EXH RTN LINE SHUTOFF VALV BOP Reports 3B CRD pump tripped

HLTS-3-2 REV 0 PAGE 41 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTIONS BOP d. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, on Panel 9-5 to control injection WHILE maintaining 3-PI-85-13A, CRD ACCUM CHG WTR HDR PRESS, above 1450 psig, if possibl e. IF ....Additional flow is necessary to prevent or mitigate core damage, THEN ..DISPATCH personnel to fully open the following valves as required:

3-THV-085-0527, CRD PUMP DISCH THROTTLING (RB NE, el 565)

3-BYV-085-0551, CRD PUMP TEST BYPASS (RB NE, el 565).

SRO Directs determining the cause of the isolation Directs H 2 O 2 Analyzers placed in service BOP Places H 2 O 2 Analyzers in service 1. Place Analyzer isolation bypass keylock switches to bypas . Select DW or Supp Chmbr and momentarily pull out select switch handle to start sample pump HLTS-3-2 REV 0 PAGE 42 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

SRO Directs SP cooling be placed in service per App 17A BOP Places SP cooling in service per App 17A 1. IF ..... Adequate core cooling is assured, THEN ... BYPASS LPCI Injection Valve Timers as necessary using EOI Appendices 16F and 16 . PLACE RHR SYSTEM I(II) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW heade 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 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 VL HLTS-3-2 REV 0 PAGE 43 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

d. IF ..... Directed by SRO, THEN ... PLACE the following keylock switches in MANUAL OVERRIDE:

3-XS-74-122, RHR SYS I LPCI 2/3 CORE HEIGHT OVR XS-74-130, RHR SYS II LPCI 2/3 CORE HEIGHT OVR e. IF ..... LPCI INITIATION Signal exists, THEN ... MOMENTARILY PLACE the following in select:

3-XS-74-121, RHR SYS I CTMT SPRAY/CLG VLV SELEC XS-74-129, RHR SYS II CTMT SPRAY/CLG VLV SELEC HLTS-3-2 REV 0 PAGE 44 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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

LPCI OUTBD INJECT VALV g. OPEN 3-FCV-74-57(71), RHR SYS I(II) SUPPR CHBR/POOL ISOL VL h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operatin i. THROTTLE 3-FCV-74-59(73), RHR SYS I(II) SUPPR POOL CLG/TEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64),

RHR SYS I(II) FLOW:

Between 7,000 and 10,000 gpm for one-pump Operation. OR At or below 13,000 gpm for two-pump operatio j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM I(II) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

HLTS-3-2 REV 0 PAGE 45 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

k. MONITOR RHR Pump NPSH using Attachment l. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchanger m. IF .. Additional Suppression Pool Cooling flow is necessary, THEN PLACE additional RHR and RHRSW pumps in service using Steps 2.b through ATC/BOP Monitors containment parameters SRO Enters EOI-2 on DW pressure and re-enters EOI-1 and directs the following:

- Verify all available DW coolers in service SRO Directs cooldown ATC/BOP Verify all available DW coolers in service ATC/BOP Commences a cooldown as directed SRO Determines cannot maintain suppression chamber pressure less than 12 psig and directs suppression chamber sprayed

HLTS-3-2 REV 0 PAGE 46 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP Sprays suppression chamber per App 17C 1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step . IF .. Adequate core cooling is assured, OR Directed by EOI-2 to spray the Suppression Chamber irrespective of adequate core cooling, THEN BYPASS LPCI Injection Valve Timers as necessary using EOI Appendices 16F and 16 . IF .. Directed by SRO to spray the Suppression Chamber using Standby Coolant Supply, THEN CONTINUE in this procedure at Step . IF .. Directed by SRO to spray the Suppression Chamber using Fire Protection, THEN CONTINUE in this procedure at Step HLTS-3-2 REV 0 PAGE 47 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW heade 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 I(II) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRID c. MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS I(II) CTMT SPRAY/CLG VLV SELECT, switch in SELEC d. IF..... 3-FCV-74-53(67), RHR SYS I(II) INBD INJECT VALVE, is OPEN, THEN... VERIFY CLOSED 3-FCV-74-52(66), RHR SYS I(II) OUTBD INJECT VALV e. VERIFY OPERATING the desired RHR System I(II) pump(s) for Suppression Chamber Spra f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS I(II) SUPPR CHBR/POOL ISOL VL g. OPEN 3-FCV-74-58(72), RHR SYS I(II) SUPPR CHBR SPRAY VALV HLTS-3-2 REV 0 PAGE 48 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP h. IF..... RHR System I(II) is operating ONLY in Suppression Chamber Spray mode, THEN... CONTINUE in this procedure at Step i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM I(II) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

j. RAISE system flow by placing the second RHR System I(II) pump in service as necessar k. MONITOR RHR Pump NPSH using Attachment l. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1,350 and 4,500 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 VL n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchanger HLTS-3-2 REV 0 PAGE 49 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 6. WHEN ... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR Directed by SRO to stop Suppression Chamber Sprays, THEN ... STOP Suppression Chamber Sprays as follows:

a. CLOSE 3-FCV-74-58(72), RHR SYS I(II) SUPPR CHBR SPRAY VALV b. VERIFY CLOSED 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE c. IF..... RHR operation is desired in ANY other mode, THEN... EXIT this EOI Appendi d. STOP RHR Pumps 3A and 3C (3B and 3D).

e. CLOSE 3-FCV-74-57(71), RHR SYS I(II) SUPPR CHBR/POOL ISOL VL HLTS-3-2 REV 0 PAGE 50 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

SRO When SC pressure exceeds 12 psig or if SRO determines cannot maintain DW temp. <280 then directs the following:

- Ensures Recirc. pumps shutdown

- DW blowers secured

- DW sprayed per App 17B ATC Trips Recirc. pumps BOP Secures DW blowers Requests 16F & 16G be performed Sprays the DW using RHR per App 17B 1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure at Step . IF ..... Adequate core cooling is assured, OR Directed to spray the Drywell irrespective of adequate core cooling, THEN ... BYPASS LPCI Injection Valve Timers as necessary using EOI Appendices 16F and 16 HLTS-3-2 REV 0 PAGE 51 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 3. VERIFY Recirc Pumps and Drywell Blowers shutdow . IF ..... Directed by SRO to spray the Drywell using Standby Coolant supply, THEN ... CONTINUE in this procedure at Step . IF ..... Directed by SRO to spray the Drywell using Fire Protection, THEN ...

CONTINUE in this procedure at Step . INITIATE Drywell Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW heade 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 I(II) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRID c. MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS I(II) CTMT SPRAY/CLG VLV SELECT, switch in SELEC HLTS-3-2 REV 0 PAGE 52 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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

LPCI OUTBD INJECT VALV e. VERIFY OPERATING the desired System I(II) RHR pump(s) for Drywell Spra f. OPEN the following valves:

3-FCV-74-60(74), RHR SYS I(II) DW SPRAY OUTBD VLV 3-FCV-74-61(75), RHR SYS I(II) DW SPRAY INBD VL g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM I(II) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

HLTS-3-2 REV 0 PAGE 53 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP h. IF..... Additional Drywell Spray flow is necessary, THEN... PLACE the second System I(II) RHR Pump in servic i. MONITOR RHR Pump NPSH using Attachment j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

k. THROTTLE the following in-service RHRSW outlet valves to obtain between 1,350 and 4,500 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 HX 3C RHRSW OUTLET VLV 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VL l. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchanger HLTS-3-2 REV 0 PAGE 54 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

SRO Directs DW sprays/SC sprays be stopped when that area reaches 0 psig BOP Stops DW/SC sprays when that area reaches 0 psig Monitors containment parameters SRO Monitors RPV water level, determines level is lowering. Re-enters EOI-1 at

+2 RPV level

- Directs performance of App 7B (SLC)

ATC Calls Rx Bldg AUO to perform App 7B Crew Monitors Drywell / PSC / and RPV water level SRO Enters C1 at -100 to - 122 Directs ADS inhibited ATC Closes RFP discharge valves Reports 3A CRDP tripped

HLTS-3-2 REV 0 PAGE 55 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP Inhibits ADS SRO After entering C1 align all available injection systems for injectio Containment sprays terminated When water level reaches TAF (-162) and before - 200 directs the following:

Enters C2 (Critical step)

- Six ADS valves opened (Critical step)

- RPV level returned +2 to +51 BOP When directed by US terminates Containment Sprays and lines up RHR for LPCI BOP Opens and verifies open 6 ADS valves (Critical step)

SRO Directs restoring Rx level with Condensate, Core Spray, or RHR (Critical step)

SRO Classifies event as Site Area Emergency (1.1-S1)

ATC/BOP Restores RPV water level +2 to +51 using: (Critical step)

-RHR-Core Spray-Condensate

HLTS-3-2 REV 0 PAGE 56 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

App 6A Condensate 1. VERIFY CLOSED the following Feedwater heater return valves:

3-FCV-3-71, HP HTR 3A1 LONG CYCLE TO CNDR 3-FCV-3-72, HP HTR 3B1 LONG CYCLE TO CNDR 3-FCV-3-73, HP HTR 3C1 LONG CYCLE TO CND . VERIFY CLOSED the following RFP discharge valves:

3-FCV-3-19, RFP 3A DISCHARGE VALVE 3-FCV-3-12, RFP 3B DISCHARGE VALVE 3-FCV-3-5, RFP 3C DISCHARGE VALV . VERIFY OPEN the following drain cooler inlet valves:

3-FCV-2-72, DRAIN COOLER 3A5 CNDS INLET ISOL VLV 3-FCV-2-84, DRAIN COOLER 3B5 CNDS INLET ISOL VLV 3-FCV-2-96, DRAIN COOLER 3C5 CNDS INLET ISOL VLV

HLTS-3-2 REV 0 PAGE 57 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

4. VERIFY OPEN the following heater outlet valves:

3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VLV 3-FCV-2-125, LP HEATER 3B3 CNDS OUTL ISOL VLV 3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VL . VERIFY OPEN the following heater isolation valves:

3-FCV-3-38, HP HTR 3A2 FW INLET ISOL VLV 3-FCV-3-31, HP HTR 3B2 FW INLET ISOL VLV 3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV 3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV 3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VLV 3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV

HLTS-3-2 REV 0 PAGE 58 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-83, RFP 3A SUCTION VALVE 3-FCV-2-95, RFP 3B SUCTION VALVE 3-FCV-2-108, RFP 3C SUCTION VALV . VERIFY at least one condensate pump runnin . VERIFY at least one condensate booster pump runnin . ADJUST 3-LIC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5).

10. VERIFY RFW flow to RP HLTS-3-2 REV 0 PAGE 59 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

App 6D or 6E Core Spray Sys I (Loop II similar)

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV 3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VLV 3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALV . VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALV . VERIFY CS Pump 3A and/or 3C RUNNIN . WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS I INBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pum . MONITOR Core Spray Pump NPSH using Attachment HLTS-3-2 REV 0 PAGE 60 OF 63 X Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

App 6B or 6C RHR Sys I (Loop II similar)

1. IF ..... Adequate core cooling is assured AND It becomes necessary to bypass LPCI Injection Valve Timers to control injection, THEN ... EXECUTE EOI Appendix 16F concurrently with this procedure 2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL . VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VL . 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 CHBR/POOL ISOL VLV 3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE 3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VL . VERIFY RHR Pump 3A and/or 3C runnin . WHEN ... RPV pressure is below 450 psig, THEN ... VERIFY OPEN 3-FCV-74-53, RHR SYS I LPCI INBD INJECT VALV . IF ..... RPV pressure is below 230 psig, THEN ... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALV HLTS-3-2 REV 0 PAGE 61 OF 63 XII. Crew Critical Tasks Task 1) Manually isolate HPCI before 2 areas exceed Maximum Safe Radiation or Temperature levels.

2) Emergency depressurizes RPV based upon not being able to maintain reactor water level above -162, but before reaching - 200 3) Restores / maintains water level above - 162 after ED

HLTS-3-2 REV 0 PAGE 62 OF 63 XIII. SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-3-2 9 Total Malfunctions Inserted; List: (4-8)

1) HPCI steam line break 2) RBCCW 3A pump trips 3) 3A Recirc. high vibration 4) 3A Recirc pump suction valve fails open and will not close 5) Failure of ADS/SRV 1-22 6) Drywell Leak 7) CRD pump 3B fails to start 8) CRD pump 3A trips 9) RCIC 71-8 fails to open 3 Malfunctions That Occur After EOI Entry; List: (1-4)

1) CRD pump 3B fails to start 2) CRD pump 3A trips 3) RCIC 71-8 fails to open 2 Abnormal Events; List: (1-3)

1) SRV fails open 2) HPCI steam line break 2 Major Transients; List: (1-2)

1) Loss of all high pressure makeup 2) Drywell Leak 3 EOIs used; List: (1-3)

1) EOI-1 2) EOI-2 3) EOI-3 2 EOI Contingencies Used; List: (0-3)

1) C1 2) C2 90 Run Time (minutes)

45 EOI Run Time (minutes); 50 % of Scenario EOI Run Time 3 Crew Critical Tasks (2-5)

Yes Technical Specifications Exercised (yes/no) - Technical Requirements Manual

XI Shift Turnover Information Equipment out of service/LCOs: 3C RHR Pump is out of service. T.S 3.5.1.A.1, 3.6.2.3, 3.6.2.4, 3.6.2.5 have been entered. Unit 2 is 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months into a seven day LCO.

Appendix R LCO addressed and in LCO tracking.

Operation/Maintenance for the Shift: Unit 3 is at 79% power, Alternate EHC Pumps per section of OI 47A. Increase reactor power to 85% using Recirc flow (GOI-100-12,step 5.132) with no pre-conditioning limitations. Reactor Engineering will evaluate any further power changes.

Continue with 3-SR-3.5.1.7 which is in progress and is complete up to Step 7.11 (HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure).

Loop II RHR has been placed in Torus cooling and 3-SR-3.6.2.1.1 needs to be started 5 minutes before starting HPCI. Units 1 & 2 are at 100% power,.

Unusual Conditions/Problem Areas: 3-FCV-73-36 seal-in circuit has been disabled per step 7.6 of 3-SR-3.5. Appendix D Scenario Outline Form ES-D-1 Facility: BFN Scenario Number: HLTS-3-2 Op-Test Number: HLT0610 Examiners:__________________ Operators: _________________

__________________ _________________

Initial Conditions:

Unit 3 is at 79% power. 3C RHR Pump is out of service. T.S 3.5.1.A.1, 3.6.2.3, 3.6.2.4, 3.6. have been entered. Unit 3 is 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months into a seven day LCO. Appendix R LCO addressed and in LCO tracking. Loop II of RHR has been vented within the hour in preparation for placing Torus cooling in service. Valve 3-FCV-73-36 seal-in circuit has been disabled per step 7.6 of 3-SR-3.5.1.7 Turnover:

Continue with 3-SR-3.5.1.7 which is in progress and is complete up to Step 7.11 (HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure).

Alternate EHC Pumps per section 6.3 of 3-OI-47A. Increase reactor power to 90% using Recirc flow (3-GOI-100-12, step 5.132) at 8 Mwe per minut Event Malfunction Event Event Number Number Type* Description 1 N/A N-BOP The crew will alternate EHC pumps using 3-OI-47 N/A R-ATC The crew will continue with power ascension using 3-GOI-12 R-SRO and 3-OI-6 imf hp08 C-BOP The crew will recognize and respond to a HPCI steam line C-SRO break. HPCI will fail to auto isolate and must be manually TS-SRO isolate The SRO will enter and execute EOI- imf rd01a C-ATC Recognize and respond to a 3A CRD pump trip using 3-AOI-85- imf ad01g 40 C-BOP The crew will recognize and respond to a stuck open SRV C-SRO using 3-AOI-1- . bat RRPAVIB M The crew will recognize and respond to a recirc pump high imf cr02a 75 All vibration, dual seal failure, trip, core power oscillations and 3:00 scra The crew will carry out actions using EOI-1 & 2 and 3-AOI-100- imf th22 100 M The crew will recognize and respond to a MSIV Closure and 1:30 All LOCA using EOI-1 & The crew will monitor and control primary containment until reactor water level approaches TA The crew will transition to EOI C-1 and perform Emergency Depressurization to enable level restoration using low pressure systems.

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

HLTS-3-3 Revision 0 Page 1 of 49 SIMULATOR EXERCISE GUIDE TITLE : POWER REDUCTION, CORE SPRAY 3D PUMP INADVERTANT START, RECIRCULATION PUMP TRIP, REACTOR POWER OSCILLATIONS, ATWS WITH MSIVS OPEN REVISION : 0 DATE : January 20, 2008 PROGRAM : BFN Operator Training - HLT PREPARED BY: \

(Operations Instructor) Date REVIEWED BY: \

(Operations Training Manager or Designee) Date

\

(Operations Superintendent or Designee) Date (Required for Exam Scenarios only)

VALIDATION \

BY: (Operations SRO) (Required for Exam Scenarios only) Date

HLTS-3-3 Revision 0 Page 2 of 49 NUCLEAR TRAINING REVISION/SROAGE LOG REVISION DESCRIPTION OF DATE PAGES REVIEWED BY NUMBER REVISION AFFECTED 0 INITIAL 01/20/08 All csf

HLTS-3-3 Revision 0 Page 3 of 49 PROGRAM: BFN Operator Training I COURSE: Examination Guide II TITLE: POWER REDUCTION,CORE SPRAY SR FAILURE, RECIRCULATION PUMP TRIP, REACTOR POWER OSCILLATIONS, ATWS WITH MSIVS OPEN IV. LENGTH OF LESSON: 1 to 1 1/2 hours Training Objectives Terminal Objective Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedure . Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment/unit from operation. (SOER 94-1 and SOER 96-01) Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, abnormal, annunciator, and emergency procedure Enabling Objectives The operating crew will recognize and respond to an inadvertent start of a Core Spray pump and determine required actions per Technical Specification . The operating crew will recognize and respond to a recirculation pump trip with reactor power oscillations in accordance with 3-AOI-68- . The operating crew will recognize and respond to CRD pump 3A trip per 3-AOI-85- . The operating crew will recognize and respond to an ATWS in accordance with EOI-1 and C- . The operating crew will recognize and respond to high radiation in accordance with EOI- HLTS-3-3 Revision 0 Page 4 of 49 V References: The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard) Calculator Control Rod Insertion Sheet Stopwatch Hold Order / Caution tags Annunciator window covers Steam tables

HLTS-3-3 Revision 0 Page 5 of 49 IX. Console Operation Instructions Scenario File Summary File: bat HLTS3-3 MF/RF/IOR DESCRIPTION 1) imf fw26b 0 B FW flow failure 2) bat tohpci Tags out HPCI 3) imf th23 (e3 0) 2.5 15:00 Fuel failure 4) imf rp08a RPS A1 scram failure 5) imf rp08b RPS A2 scram failure 6) trg e1 CSD Set trigger e1 to file CSD 7) trg e2 CSDHS Set trigger e2 to file CSDHS 8) trg e3 MODESW Set trigger e3 to file MODESW 9) trg e1= dor zdihs7542a Trigger e1 initiates command 10) trg e2= ior zloil7542 on Trigger e2 initiates command 11) imf tc02 0 Fails Bypass valves closed File: bat HLTS3-3-1 MF/RF/IOR DESCRIPTION 1) imf th03a (none 10:00) Trips 3A Recirc. pump 2) imf th03b Trips 3B Recirc. pump 3) imf cr02a 65 10:00 Power Oscillations 4) bat atws90 90% Hydraulic ATWS 5) Imf tc01 (e3 5:00) Fail bypass valves closed 5 min after mode sw File bat tohpci MF/RF/IOR DESCRIPTION 1) ior ypomtrglesh fail__cn__po Tag gland seal exhauster ior ypovfcv733a close 73-3 close 2) ior ypovfcv733 fail__now Tag FCV 73-3 ior ypovfcv7316 fail_now Tag FCV 73-16 3) ior ypovfcv7381 fail__now Tag FCV 73-81 4) ior zdihs7347a ptl Tag HPCI Aux oil pump 5) ior zohs7347a[1] off 6) imf hp05 HPCI trip File bat HLTS3-3-4 MF/RF/IOR DESCRIPTION 1) trg e4 RODDRIFT Stops drifting rod motion at notch 4 trg e4 = dmf rd07r2627

HLTS-3-3 Revision 0 Page 6 of 49 IX. Console Operation Instructions Scenario File Summary File bat app01f MF/RF/IOR DESCRIPTION 1) mrf rp13a byp Bypasses automatic scrams 2) mrf rp13b byp (Appendix 1F) File bat app02 MF/RF/IOR DESCRIPTION 1) mrf rp12a test Bypasses ARI 2) mrf rp12b test (Appendix 2) File bat app08ae MF/RF/IOR DESCRIPTION 1) mrf rp06a byp Bypasses MSIV isolation on low 2) mrf rp06b byp RPV water level (Appendix 8A)

3) mrf rp06c byp 4) mrf rp06d byp 5) mrf rp14a byp Bypasses Rx Bldg ventilation 6) mrf rp14b byp isolation on low RPV level File bat atws90east MF/RF/IOR DESCRIPTION 1) imf rd17a SDV level switch failure 2) imf rd09a 90 90% hydraulic ATWS East SDV File bat sdvtd MF/RF/IOR DESCRIPTION a) dmf rd17a Deletes SDV level switch failure b) dmf rd17b c) imf rd17a (none 7:00) Inserts level switch failure after 7 minutes d) imf rd17a (none 7:00)

HLTS-3-3 Revision 0 Page 7 of 49 I Console Operation Instructions Console Operator Manipulations ELAP TIME PFK DESCRIPTION/ACTION Sim.Setup reset 28 100% MOC Sim. Setup restorepref HLTS3-3 Establishes Function Keys Sim. Setup setup Verify Function Keys Sim. Setup esc Clears Function Key Popup Sim.Setup F3 See scenario file summary (bat HLTS3-3)

Sim.Setup manual Tag out HPCI. Hang out of service cover on B FW Flow Indicator Sim.Setup manual HPCI AOP and SPE pumps in PTL. Place Main Generator Voltage Regulator in Manual ELAP TIME PFK DESCRIPTION/ACTION 2 minutes after Unit at 95% power F4 Core Spray pump 3D start ior zdihs7542a start When CS D Starts: bat CSD bat CSD If lockout light does not illuminate when CS F5 Illuminates lockout light pump stopped, then Ior zloil7542 on 2 minutes after Tech Specs addressed for F6 Control Rod 26-27 drifting i CS pump imf rd072627 in bat HLTS3-3-4 Assigns trg e4 to stop rod motion at notch 42.

ROLE PLAY: As AUO at HCU 18-35, REPORT - The scram inlet riser is hot to the touch.

ROLE PLAY: As AUO at HCU 18-35, REPORT - 3-SHV-85-588 valve is closed.

ROLE PLAY: Respond as needed as AUO at HCU and as Operator at pnl 9-16 in AUX INST ROOM.

ROLE PLAY: As AUO at HCU 18-35, REPORT - solenoids operating normally (no chattering) and the valve stems indicate closed. Also, when directed, REPORT - 3-SHV-85-588 is ope MORE FOLLOWS

HLTS-3-3 Revision 0 Page 8 of 49 I Console Operation Instructions Console Operator Manipulations ELAP TIME PFK DESCRIPTION/ACTION When directed by Chief Examiner: <shift>F2 Initiates Recirc pump trips and power bat HLTS3-3-1 oscillations. ATWS After scram inserted <shift>F3 SDV switches enabled bat sdv When appendix 2 requested, wait 3 minutes <shift>F4 Bypass ATWS/ARI circuit bat app02 When requested to perform appendix 1F, wait <shift>F5 Jumper out scram logic 5 minutes bat app01f When requested to perform Appendix 8A and <shift> F6 Allows restart of Reactor/Refuel zone 8E, wait 5 minutes bat app08ae ventilation When scram is reset <shift> F7 SDV switches enabled bat sdvtd If requested to close 3-FCV-85-586, wait 5 <shift> F8 Provides drive water pressure for rod minutes mrf rd06 close insertion If requested to open 3-FCV-85-586, wait 1 <shift> F9 Pressurizes charging water header minute mrf rd06 open When Reactor is manually scrammed (2nd <shift>F3 SDV switches enabled time) bat sdv When Reactor is scram reset (2nd time) <shift> F7 SDV switches enabled bat sdvtd

<shift> F10 Removes power oscillations dmf cr02a

<shift> F11 Deletes ATWS bat atws-1 Terminate the scenario when the following conditions are satisfied or upon request of the Chief Examiner:

1. All rods fully inserte . RPV water level +2 to +5 . Reporting requirements mad HLTS-3-3 Revision 0 Page 9 of 49 IX. SCENARIO SUMMARY:

The unit is operating at 100% power with a 5% power reduction scheduled. HPCI is tagged out for maintenance on the Auxiliary Oil Pump and is expected to be returned to service within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . It has been out of service for 14 hour1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months The Main Generator voltage regulator was placed in Manual to allow PMs on the Automatic regulator. PMs are complete and the voltage regulator can be returned to Automati Core Spray 3D pump inadvertent start is received and the Crew must consult Tech Specs to determine required action Control Rod 26-27 drifts inadvertently into the core and stops at Notch 4 B Recirc pump trips, resulting in power oscillations with some fuel failure. While responding to the power oscillations per AOI-68-1, 3A Recirc pump trips and a manual scram must be inserte The crew will experience a hydraulic ATWS and respond per 3-EOI-1. The SDV will fail to drain totally, thus requiring two additional reactor scrams to insert control rod HLTS-3-3 Revision 0 Page 10 of 49 X. Information to Evaluators: Ensure recorders are inking and recording and ICS is active and updatin Assign Crew Positions based on the required rotatio . SRO: Unit Supervisor ATC: Board Unit Operator BOP: Desk Unit Operator Conduct a shift turnover with the Shift Manager and provide the Shift Manager with a copy of the Shift Turnove Direct the shift crew to review the control board and take note of present conditions, alarms, et Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluato . All rods inserted Water level +2 to +51 Reporting requirements have been made

HLTS-3-3 Revision 0 Page 11 of 49 X Simulator Event Guide Event 1a: POWER REDUCTION TIME POSITION EXPECTED ACTIONS ATC Reduces reactor power in accordance with 3-GOI-100-12 and 3-OI-

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM) 3-HS-96-17A(17B), push-buttons, to achieve balanced jet pump flows. AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-6A(16B) /LOWER SLOW(MEDIUM) 3-HS-96-18A(18B), pushbuttons, to achieve balanced jet pump flow [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-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 BOP Peer checks during power reduction

HLTS-3-3 Revision 0 Page 12 of 49 XI. Simulator Event Guide Event 1b: VOLTAGE REGULATOR TO AUTOMATIC TIME POSITION EXPECTED ACTIONS SRO Directs BOP to return voltage regulator to automatic per 3-OI-47 section 8.1 BOP VERIFY VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, is in MA PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-57-26, to RAISE UNTIL the upper limit is reached (red light illuminated).

PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 32-HS-57-26, to LOWER UNTIL the lower limit is reached (green light illuminated).

ADJUST GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-57-26, UNTIL GEN TRANSFER VOLTS, 2-EI-57-41, indicates zer PLACE VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, in AUT VERIFY GEN VOLT REGULATOR TRIP TO MAN, 3-EA-57-132 (3-XA-55-8A, window 3) alarm RESET GEN VOLT REGULATOR TRIP TO MAN, 3-EA-57-132 (3-XA-55-8A, window 3).

HLTS-3-3 Revision 0 Page 13 of 49 XI. Simulator Event Guide Event 2: SPURIOUS START OF 3D CORE SPRAY PUMP TIME POSITION EXPECTED ACTIONS BOP Reports start of 3D Core Spray pump and verifies no valid automatic start signa SRO Directs trip of 3D Core Spray pump BOP Trips 3D Core Spray pump. Informs SRO that Lockout indicator for 3D Core Spray Pump is illuminated indicating the pump will not start automatically if neede SRO Consults Tech Spec 3.5.1 determines that 3.5.1.A is a 7 day Action Statement for 3D Core Spray pump and 3.5.1.D is a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Action Statement in effect with HPCI and one (1) Low Pressure ECCS system inoperabl HLTS-3-3 Revision 0 Page 14 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS ATC Announces Rod Drift alarm 3-ARP-9-5A window 28 A. DETERMINE which rod is drifting from Full Core Displa Identifies rod 26-27 as drifting i B. IF rod drifting in, THEN REFER TO 3-AOI-85- C. IF rod drifting out, THEN REFER TO 3-AOI-85- D. REFER TO Tech Spec Section 3.1.3, 3.1 ATC Recognizes that Rod 26-27 stops moving at Notch 4 SRO Directs actions per 3-AOI-85-5 SRO Directs rod be continuously inserted to 00

HLTS-3-3 Revision 0 Page 15 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS ATC 3-AOI-85-5 Immediate Actions

[1] IF multiple rods are drifting into core, THEN

_NA MANUALLY SCRAM Reactor. REFER TO 3-AOI-100- Subsequent Actions

[1] IF the Control Rod travels greater than two notches from its intended position, THEN INSERT Control Rod to position 00 using CONTINUOUS IN. (otherwise N/A)

ATC [2] NOTIFY Reactor Enginee ATC [3] CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).

[4] ADJUST control rod pattern as directed by Reactor Engineer and CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).

HLTS-3-3 Revision 0 Page 16 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS

[5] IF CRD Cooling Water Header DP is excessive and causing the control rod drift, THEN ALTERNATELY ADJUST tape setpoint of CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and position of CRD DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A, to establish the following conditions (otherwise N/A):

CRD CLG WTR HDR DP, 3-PDI-85-18A, of about 20 psid, and CRD DRIVE WTR HDR DP, 3-PDI-85-17A, between 250 and 270 psid, and CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, between 40 and 65 gp ATC Directs AUO to check the following per 3-AOI-85-5:

[6] VERIFY scram pilot air header aligned to scram inlet and outlet valve [7] CHECK CRD SCRAM OUTLET VALVE, 3-FCV-085-39B, for leakage as indicated by the following:

Scram riser for affected HCU has higher than normal Temperature

CRD SCRAM OUTLET VALVE, 3-FCV-085-39B, producing flow noise

HLTS-3-3 Revision 0 Page 17 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS ATC [8] CHECK CRD SCRAM INLET VALVE, 3-FCV-085-39A, for leakage as follows:

[8.1] CHECK insert riser for affected HCU for higher than normal temperatur ATC Directs AUO to perform the following;

[8.2] CLOSE CHARGING WATER SOV, 3-SHV-085-588 and OBSERVE CRD ACCUMULATOR NITROGEN SIDE PRESS, 3-PI-085-034, for lowering tren SRO Declares accumulator inoperable per Tech Spec 3.1.5.A and addresses actions (when charging water is isolated)

EXAMINER NOTE: With charging water isolated to the HCU, the control rod no longer satisfies the OPERABILITY requirement that the control rod is capable of being scrammed even if the rod is fully inserte ATC After report from AUO thart scram inlet valve is leaking, Directs scramming of affected rod from panel 9-16 in Aux. Inst. Room

HLTS-3-3 Revision 0 Page 18 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS ATC [9] IF either Scram Inlet or Outlet Valve is found to be leaking, THEN PERFORM the following to scram the control rod (otherwise N/A):

[9.1] ESTABLISH communications between Control Room and the following locations:

Hydraulic control unit affected, elevation 565, Reactor Building

Panel 3-9-16 in Auxiliary Instrument Room, elevation 593, Control Bay

[9.2] VERIFY CLOSED CHARGING WATER SOV, 3-SHV-085-58 ATC [9.3] INITIATE individual rod scram by actuating selected rod scram switch on Panel 3-9-16 to its scram (DOWN) positio [9.4] VERIFY control rod has reached FULL IN on Panel 3-9- [9.5] IF attempting to reseat scram valves, THEN RETURN rod scram switch for associated control rod to its normal (UP) position at Panel 3-9-16,.

ATC Have AUO check locally;

[9.6] CHECK solenoid operation of CRD SCRAM INLET and OUTLET VALVEs 3-FCV-85-39A and 3-FCV-85-39B, (they should function normally without chatter or abnormal buzzing.)

[9.7] CHECK stem travel indicators on CRD SCRAM INLET and OUTLET VALVEs 3-FCV-85-39A and 3-FCV-85-39B. IF either scram valve indicates OPEN, THEN NOTIFY control roo HLTS-3-3 Revision 0 Page 19 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS ATC [9.8] CHECK blue Scram indicator light on Full Core Display extinguishe [9.9] RESET Rod Drift Alarm and CHECK DRIFT indicator light on Full Core Display extinguished. (N/A if rod is still drifting in)

[9.10] CHECK annunciator CONTROL ROD DRIFT (3-XA-55-5A, Window 28) reset. (N/A if rod is still drifting in)

ATC Have AUO perform the following;

[9.11] SLOWLY OPEN CHARGING WATER SOV, 3-SHV-085-58 ATC [9.12] CHECK amber ACCUM indicator light on Full Core Display extinguishe [9.13] CHECK red indicating light for associated HCU extinguished on local Panel 3-28-4(3-25-22).

[9.14] NOTIFY Site Engineerin [9.15] INITIATE a work orde HLTS-3-3 Revision 0 Page 20 of 49 XI. Simulator Event Guide Event 3: CONTROL ROD DRIFT IN TIME POSITION EXPECTED ACTIONS N/A [10] IF insert directional control valve is suspected of leaking, THEN ATTEMPT to reseat valve as follows (otherwise N/A):

[10.1] INSERT control rod one notc [10.2] NOTIFY Site Engineerin [10.3] INITIATE a work order.

N/A [11] IF attempts to stop control rod drifting are unsuccessful, THEN PERFORM the following (otherwise N/A):

[11.1] VERIFY control rod drive is at position 00 or FULL I [11.2] REMOVE associated HCU from servic REFER TO 3-OI-85 and Tech Spec 3. ATC Reports to SRO rod settles to 00 position SRO Initiates actions to determine CR operability and suggests actions including maintenance and inspectio ATC De-selects and re-selects Rod 26-27 to clear RBM DOWNSCALE 3-ARP-9-5A (W 31).

HLTS-3-3 Revision 0 Page 21 of 49 X Simulator Event Guide Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS TIME POSITION EXPECTED ACTIONS ATC Recognizes B Recirculation pump trip SRO Directs 3-AOI-68-1 entry Contacts Rx Engr to place APRMs in SLO mode (If time permits)

ATC/BOP [1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN (Otherwise N/A),

A. SCRAM the Reacto [2] IF Region I or II of the Power to Flow Map (Illustration 1) is entered, THEN (Otherwise N/A)

IMMEDIATELY take actions to INSERT control rods to less than 95.2% loadline. Refer to 0-TI-464, Reactivity Control Plan Development and Implementatio [3] RAISE core flow to greater than 45%. Refer to 3-OI-6 HLTS-3-3 Revision 0 Page 22 of 49 X Simulator Event Guide Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS TIME POSITION EXPECTED ACTIONS

[4] INSERT control rods to exit regions if not already exited. Refer to 0-TI-464, Reactivity Control Plan Development and Implementatio Inserts rods on emergency shove sheet (Critical Task)

[5] CLOSE tripped Recirc Pump discharge valve 3-FCV-68-7 [6] MAINTAIN operating Recirc pump flow less than 46,600 gp Refer to 3-OI-6 Verifies flow on A Recirc pump < 46,600 gpm

[7] [NER/C] WHEN plant conditions allow, THEN, (Otherwise N/A)

MAINTAIN operating jet pump loop flow greater than 41 x 106 lbm/hr (3-FI-68-46 or 3-FI-68-48). [GE SIL 517]

Verifies jet pump flow > 41,100 lbm/hr

HLTS-3-3 Revision 0 Page 23 of 49 X Simulator Event Guide Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS TIME POSITION EXPECTED ACTIONS

[10] [NER/C] WHEN the Recirc Pump discharge valve has been closed for at least five minutes (to prevent reverse rotation of the pump) [GE SIL-517], THEN (N/A if Recirc Pump was isolated in Step 4.2[8]) OPEN Recirc Pump discharge valve as necessary to maintain Recirc Loop in thermal equilibriu ATC Recognizes power oscillations ATC/BOP Notices failure to Scram on OPRM Trip or anticipates trip and inserts a manual scram (Critical Task)

SRO Directs manual reactor scram (Critical Task)

ATC Inserts manual scram Places Mode switch in shutdown Recognizes hydraulic ATWS Provides scram report

HLTS-3-3 Revision 0 Page 24 of 49 X Simulator Event Guide Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS TIME POSITION EXPECTED ACTIONS SRO Enters EOI-1/C-5 and verifies Verifies Mode switch to shutdown ARI initiated Directs ADS inhibited (Critical Task)

BOP Inhibits ADS (Critical Task)

SRO Directs Appendix 1F and Appendix 2 BOP Contacts AUO to perform outside portions of App 1F & 2

HLTS-3-3 Revision 0 Page 25 of 49 X Simulator Event Guide Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS TIME POSITION EXPECTED ACTIONS SRO Directs Appendix 1D ATC 1. VERIFY at least one CRD pump in servic . IF ..... Reactor Scram or ARI CANNOT be reset, THEN ... DISPATCH personnel to CLOSE 3-SHV-085-0586, CHARGING WATER SOV (RB NE, El 565 ft).

Dispatches AUO to close 3-SHV-85-58 . VERIFY REACTOR MODE SWITCH in SHUTDOW . BYPASS Rod Worth Minimize . REFER to Attachment 2 and INSERT control rods in the area of highest power (Critical Task)

HLTS-3-3 Revision 0 Page 26 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP Recognizes 3A Recirc pump trip, if not tripped by ATC Operator due to ATWS Crew Recognize and reports OG Pretreatment Radiation High OG Annual Release Limit Exceeded Turbine Building High Radiation Notifies RadCon, and Chemistry Evacuates appropriate area of Turb. Bld SRO Directs RPV pressure be maintained 800-1000 psig BOP Controls RPV pressure between 800-1000 psig with SRVs

HLTS-3-3 Revision 0 Page 27 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS SRO Directs water level be lowered to control power per Appendix 4 (Critical Task)

Directs Appendix 8A and 8E be performed Reports SAE 1.2-S ATC 1. PREVENT injection to RPV from the following systems in any order as required: (Critical Task)

a. HPCI 1) IF ......HPCI Turbine is NOT at zero speed, THEN ....PRESS and HOLD 3-HS-73-18A, HPCI TURBINE TRIP push-butto ) WHEN ....HPCI Turbine is at zero speed, THEN ....PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 3-HS-73-18A, HPCI TURBINE TRIP push-butto BOP b. RCIC 1) IF ......DIRECTED by SRO to allow RCIC injection, THEN ....EXIT step ) PRESS 3-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC Turbin HLTS-3-3 Revision 0 Page 28 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP c. CORE SPRAY NOTE: Following receipt of an automatic initiation signal, it is NOT necessary to wait until the pump actually starts before performing the next ste Following an initiation signal, PLACE ALL Core Spray pump control switches in STO BOP d. LPCI SYSTEM I PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STO OR BEFORE RPV pressure drops below 450 psig, 1) VERIFY Appendix 16F has been performed, AND 2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALV HLTS-3-3 Revision 0 Page 29 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP e. LPCI SYSTEM II PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STO OR BEFORE RPV pressure drops below 450 psig, 1) VERIFY Appendix 16G has been performed, AND 2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALV HLTS-3-3 Revision 0 Page 30 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS ATC f. CONDENSATE and FEEDWATER 1) LOWER RFPT 3A(3B)(3C) speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:

Using 3-LIC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL AND individual 3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL PDS in AUTO, OR Using individual 3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL PDS in MANUAL, OR Using individual 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNO ) 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 CONTRO ) TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:

3-HS-3-125A, RFPT 3A TRIP 3-HS-3-151A, RFPT 3B TRIP 3-HS-3-176A, RFPT 3C TRI HLTS-3-3 Revision 0 Page 31 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS Crew Monitors suppression pool temperature Calls AUO to perform App 8A & 8E ATC After Appendix 1F and 2 complete resets scram and drains SDV ATC App 1F 2. WHEN ... RPS Logic has been defeated, THEN ... RESET Reactor Scra . VERIFY OPEN Scram Discharge Volume vent and drain valve . DRAIN SDV UNTIL the following annunciators clear on Panel 3-9-4:

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

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

HLTS-3-3 Revision 0 Page 32 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS ATC Continues to insert control rods per Appendix1D BOP Maintains water level as directed with RFP / RCIC BOP Maintains Pressure control using the following appendices:

11D Main Steam line Drains 11F RFPT 11A SRVs BOP App 11D 2. VERIFY hotwell pressure below -7 in. H . CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS rese b. OPEN the following valves (Panel 3-9-3):

3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV 3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VLV 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER 4. THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rat HLTS-3-3 Revision 0 Page 33 of 49 X Simulator Event Guide Event 6: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP App 11F 2. VERIFY MSIVs ope . VERIFY Hotwell Pressure at or below -7 in. H . PLACE RFPTs in service as follows:

a. VERIFY the following:

1) At least one condensate pump runnin ) At least one condensate booster pump runnin ) Condensate System aligned to supply suction to RFP b. VERIFY Main Oil Pump running for EACH RFPT to be starte c. VERIFY CLOSED 3-FCV-3-19(12)(5), RFP 3A(3B)(3C)

DISCHARGE VALV d. DEPRESS 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT RAISE/LOWER, and VERIFY amber light is illuminate HLTS-3-3 Revision 0 Page 34 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP e. DEPRESS 3-HS-3-124A(150A)(175A), RFPT 3A(3B)(3C)

TRIP RESE f. PLACE 3-HS-46-112A(138A)(163A), RFPT 3A(3B)(3C)

START/LOCAL ENABLE, in STAR g. CHECK RFPT 3A(3B)(3C) speed increases to approximately 600 rp h. VERIFY OPEN 3-FCV-3-20(13)(6), RFP 3A(3B)(3C) MIN FLOW VALV i. PLACE 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT RAISE/LOWER in RAISE to raise RFPT speed, maintaining discharge pressure less than 1250 psi HLTS-3-3 Revision 0 Page 35 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP App 11A 2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other option . OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO: PCV-1-179 MN STM LINE A RELIEF VALV PCV-1-180 MN STM LINE D RELIEF VALV PCV-1-4 MN STM LINE A RELIEF VALV PCV-1-31 MN STM LINE C RELIEF VALV PCV-1-23 MN STM LINE B RELIEF VALV PCV-1-42 MN STM LINE D RELIEF VALV PCV-1-30 MN STM LINE C RELIEF VALV PCV-1-19 MN STM LINE B RELIEF VALV PCV-1-5 MN STM LINE A RELIEF VALV PCV-1-41 MN STM LINE D RELIEF VALV PCV-1-22 MN STM LINE B RELIEF VALV PCV-1-18 MN STM LINE B RELIEF VALV PCV-1-34 MN STM LINE C RELIEF VALV HLTS-3-3 Revision 0 Page 36 of 49 XI. Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS ATC When alarms WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (3-XA-55-4A, Window 1)

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

Are clear, directs 3-85-586 re-opened and after accumulator alarms are clear, Inserts manual scram (Critical Task)

Crew Recognizes some control rod movement, but all control rods not in SRO Directs reactor reset, drain SDV, and re-scram (Critical Task)

Directs SLC injection if Torus temperature approaches 110 de Enters EOI-2 on Torus water level Directs Venting per Appendix 12 Directs placing H 2 O 2 monitors in service

HLTS-3-3 Revision 0 Page 37 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP Performs Appendix 12 to vent Torus 1. VERIFY at least one SGTS train in servic . VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV, 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV, 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALV . IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN . PERFORM step 13 to secure the vent path and reenter this procedure if further venting is require . IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN . PERFORM step 13 to secure the vent path and reenter this procedure if further venting is require HLTS-3-3 Revision 0 Page 38 of 49 XI. Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP 5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN . BEFORE CAD is initiated, PERFORM Step 13 to secure the vent pat NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR 3-FIC-84-20, PATH A VENT FLOW CON NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vente . IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR Suppression Chamber can NOT be vented, OR SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

Step 10 to vent the Drywell through 3-FCV-84-19, OR Step 11 to vent the Drywell through 3-FCV-84-2 . CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR Step 9 to vent the Suppression Chamber through 3-FCV-84-2 HLTS-3-3 Revision 0 Page 39 of 49 XI. Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scf f. CONTINUE in this procedure at step 1 HLTS-3-3 Revision 0 Page 40 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND 3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND Release rates as determined below:

i. IF. . .PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress THEN. .MAINTAIN release rates below those specified in Attachment ii. IF. . .Severe Accident Management Guidelines are being executed, THEN. .MAINTAIN release rates below those specified by the TSC SAM Tea iii. IF. . .Venting for ANY other reason than items i or ii above, THE .MAINTAIN release rates below Stack release rate of 1.4 x 107 Ci/s AND 0-SI-4.8.B.1.a.1 release fraction of BOP Contacts LOG AUO to monitor release rates

HLTS-3-3 Revision 0 Page 41 of 49 XI. Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS ATC Maintains water level as directed to control power ATC After SDV drained and after accumulators recharged, scrams reactor again and verifies all rods in (Critical Task)

SRO Directs level be restored +2 to +51 (Critical Task)

SRO Directs SLC stopped (if injected)

Crew Recognize RM-90-29A Rx Bldg High Radiation (conditional)

BOP Evacuates Reactor Building SRO Enters EOI-3 on high Rx Bldg radiation and directs ventilation restored per Appx 8 HLTS-3-3 Revision 0 Page 42 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS BOP App 8F 1. VERIFY PCIS Rese . PLACE Refuel Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch is in OF b. PLACE 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch to SLOW A (SLOW B).

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminat d. VERIFY OPEN the following dampers:

3-FCO-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR 3-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR 3-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR 3-FCO-64-10, REFUEL ZONE EXH INBD ISOL DMP HLTS-3-3 Revision 0 Page 43 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS 3. PLACE Reactor Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS, control switch is in OF b. PLACE 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS, control switch in SLOW A ( SLOW B).

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminat d. VERIFY OPEN the following dampers:

3-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR 3-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR 3-FCO-64-42, REACTOR ZONE EXH INBD ISOL DMPR 3-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMP HLTS-3-3 Revision 0 Page 44 of 49 X Simulator Event Guide Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN TIME POSITION EXPECTED ACTIONS ATC/BOP Announces MAIN STEAM LINE RADIATION HIGH-HIGH Annunciator 3-ARP-9-3A window 27 (if received)

A. VERIFY alarm on 3-RM-90-136 thru 137 on Panel 3-9-1 B. CONFIRM main steam line radiation level on recorder 3-RR-90-135, Panel 3-9- C. IF alarm is VALID and scram has NOT occurred, THEN PERFORM the following:

IF core flow is above 60%, THEN 1. LOWER core flow to between 50-60%.

2. MANUALLY SCRAM the Reacto . REFER TO 3-AOI-100- D. IF plant conditions DO NOT require the execution of 3-C-5, Power/Level Control, THEN VERIFY the MSIVs CLOSE E. NOTIFY RADCO HLTS-3-3 Revision 0 Page 45 of 49 XI Crew Critical Tasks (CCT)

TASK SAT/UNSAT Manual scram due to Scram failure of OPRM Trip within one minut . Prevent ADS actuatio . Controls power by :

Inserting control rods per RC/Q-2 Lowering reactor water level per EOI-C- . Maintains RPV water level above -180 with rods out

HLTS-3-3 Revision 0 Page 46 of 49 XII Scenario Verification Data EVENT K/A Number RO SRO 1. Control Rod Drift 201002A2.02 .3 2. APRM Failure 215005A2.03 .7 2.1.12 .0 3. Recirculation Pump Trip/Power Oscillations/ATWS 295001 .4 295025 .9 295037 .0

HLTS-3-3 Revision 0 Page 47 of 49 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-3-3 7 Total malfunctions Inserted; List: (4-8) Recirc Trip Power Oscillations ATWS Fuel Failure Core Spray pump 3D trip Control Rod Drift 2 Malfunctions That Occur After EOI Entry; List: (1-4)

1) ATWS 2) Fuel Failure 2 Abnormal Events; List: (1-3)

1) Control Rod Drift 2) Recirc Trip 2 Major Transients; List: (1-2)

1) ATWS 2) Fuel Failure 3 EOIs used; List: (1-3)

1) EOI-1 2) EOI-2 3) EOI-3 1 EOI Contingencies Used; List: (0-3)

1) C5 75 Run Time (minutes)

35 EOI Run Time (minutes); __50___ % of Scenario EOI Run Time 4 Crew Critical Tasks (2-5)

Yes Technical Specifications Exercised (yes/no)

X SHIFT TURNOVER INFORMATION Equipment out of service/LCOs: HPCI tagged out for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months to repair Auxiliary Oil Pump. Expected back in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Flow indicator 3-78B out of service, IMs are looking for a new transmitter. Main Generator voltage regulator in manual for PMs on Automatic voltage regulator. Spare RBCCW pump in service to Unit 2.

Operation/Maintenance for the Shift: Reduce power to 95% with recirculation flow due to high river water temperature. PMs on voltage regulator complete, return voltage regulator to automatic.

Unusual Conditions/Problem Areas: None

Appendix D Scenario Outline Form ES-D-1 Facility: BFN Scenario Number: HLTS-3-3 Op-Test Number: HLT0610 Examiners:__________________ Operators: _________________

__________________ _________________

Initial Conditions:

The HPCI system is tagged out for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months to repair the Auxiliary Oil Pump. It is expected back in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Flow indicator 3-78B is out of service. Instrument Mechanics are looking for a new transmitte The Main Generator voltage regulator has been placed in Manual for PMs on the Automatic voltage regulator. The spare RBCCW pump in service to Unit 2.

Turnover:

Reduce power to 95% using recirculation flow due to low system load requirements. PMs on the voltage regulator are complete. Return the Main Generator voltage regulator to Automatic operatio Event Malfunction Event Event Number Number Type* Description 1 N/A R-ATC The ATC operator will reduce reactor power to 95% using R-SRO recirc flow using 3-OI-6 N/A N-BOP The BOP operator will return the Main Generator voltage N-SRO regulator to Automatic using 3-OI-4 ior zdihs7542a C-BOP The crew will recognize and respond to an inadvertent start of start C-SRO the 3D Core Spray pum TS-SRO The SRO will address Tech Spec imf rd07 xx-xx R-ATC The crew will recognize and respond to a control rod drifting C-SRO into the core using 3-AOI-85- imf ed12a C The crew will recognize and respond to a loss of 3A 480V All RMOV boar bat NRC/ M The crew will recognize and respond to a recirc pump trip, HLTS10-1 All power oscillations, scram and ATW Timed out from M The crew will recognize and respond to a fuel failure during batch file All the ATWS recovery actions.

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

HLTS-3-4 Revision 0 Page 1 of 43 SIMULATOR EVALUATION GUIDE TITLE : RWM FAILURE, CRD PUMP TRIP, RBCCW PUMP TRIP, FEED PUMP CONTROL FAILURE, FUEL FAILURE, RWCU LINE BREAK WITH FAILURE TO ISOLATE, RAPIDLY DEPRESSURIZE WITH 2 AREAS APPROACHING MAXIMUM SAFE RADIATION LEVELS REVISION : 0 DATE : January 20, 2008 PROGRAM : BFN Operator Training - HLT PROVIDE COPY OF 3-GOI-100-1A TO EXAMINEES PREPARED BY: _______________________________________/_____________

(Operations Instructor) Date REVIEWED BY: ________________________________________/_____________

(Operations Training Manager or Designee) Date CONCURRED : _______________________________________/_____________

(Operations Superintendent or Designee) Date VALIDATION : ________________________________________/_____________

BY (Operations SRO: Required for Exam Scenarios Only) Date

HLTS-3-4 Revision 0 Page 2 of 43 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION DATE PAGES REVIEWED BY NUMBER OF AFFECTED REVISION 0 INITIAL 2/5/2008 All R.M. Spadoni

HLTS-3-4 Revision 0 Page 3 of 43 Program: BFN Operator Training I Course: Examination Guide III. Title: RWM FAILURE, CRD PUMP TRIP, RBCCW PUMP TRIP, FEEDPUMP CONTROL FAILURE, FUEL FAILURE, RWCU LINE BREAK WITH FAILURE TO ISOLATE, RAPIDLY DEPRESSURIZE WITH 2 AREAS APPROACHING MAXIMUM SAFE RADIATION LEVELS AND EMERGENCY DEPRESSURIZE AFTER 2 AREAS REACH MAXIMUM SAFE RADIATION LEVELS I Length of Scenario: 1 to 1 1/2 hours Examination Objectives: Terminal Objective Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedure . Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment/unit from operatio (SOER 94-1 and SOER 96-01) Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedure Enabling Objectives: The operating crew will start and warm-up B RFP In accordance with OI-6 section . The operating crew will recognize and respond to a failure of RWM in accordance with 3-OI-85-5 and Tech. Spec . The operating crew will recognize and respond to a CRD pump trip in accordance with 3-AOI-85- HLTS-3-4 Revision 0 Page 4 of 43 4. The operating crew will recognize and respond to a RBCCW pump trip in accordance with 3-AOI-70-1.

5. The operating crew will recognize and respond to Feedpump control failure in accordance with 3-AOI-3-1.

6. The operating crew will recognize and respond to a fuel failure in accordance with ARPs and EOI-3.

7. The operating crew will recognize and respond to a break in the RWCU system and rapidly depressurize the RP HLTS-3-4 Revision 0 Page 5 of 43 V References: The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenario Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard) Calculator Control Rod Insertion Sheet Stopwatch Hold Order / Caution tags Annunciator window covers Steam tables

HLTS-3-4 Revision 0 Page 6 of 43 VIII. Console Operator Instructions Scenario File Summary File: bat HLTS3-4 MF/RF/IOR# Description a.) ior zdihs691 null Fails 69-1 to close b.) imf cu04 25 RWCU suction line break c.) imf cu06 d.) bat 7048FTC fail 70-48 to not auto close File: bat HLTS3-4-1 MF/RF/IOR# Description a.) imf rm10g 1000 5:00 Fails rm14 upscale b.) imf rm10e 1000 10:00 Fails rm09 upscale File: bat 7048ftc MF/RF/IOR# Description a.) ior zlohs7048a[2] on Override red light on b.) ior ypovfcv7048 fail_power_now Fails power to valve c.) trg e1=bat 7048-1 Set trigger to 70-48 HS d.) Imf fw10c Fail 3C RFP auto trips File: bat 7048-1 MF/RF/IOR# Description a.) dor zlohs7048a[2] Delete Override on red light b.) dor ypovfcv7048 Restore power to valve File: bat HLTS3-4-4 MF/RF/IOR# Description a.) imf fw30c (none 0) 60 30 50 Run up and stop 3C RFP controller in manual

HLTS-3-4 Revision 0 Page 7 of 43 VII Console Operator Instructions Console Operator Manipulations ELAP TIME PFK DESCRIPTION/ACTION Sim. Setup Reset IC 9 ~9% power, MOC Sim. Setup Manual Place Hold Order Tags on A RFP suction and discharge valves Sim. Setup Manual Ensure RWM is latched with no Insert or Withdrawal blocks and comp/prog lights reset, rod group 39 - 06-47 selected Sim. Setup Manual Verify 3A RFP suct & disch valve lights extinguished. If not, bat 3arfptag Sim Setup <Shift F1> Set 70-48 to not close on low pressure bat 7048ftc and fail 3C RFP auto trips After RFP warmed and F3 Fails RWM ( imf rd14a )

When requested by Examiner ROLE PLAY: If asked, have not performed a startup with RWM bypassed within last calendar quarter ROLE PLAY: If requested to verify open 3-1-155 and 3-1-156, report that they are open After Tech Specs imf rd01a Trips 3A CRD Pump.

addressed for RWM ROLE PLAY: When sent to investigate the trip of 3A CRD Pump, report that the breaker is tripped on over-current.

After the crew starts 3B CRD pump and with Lead F8 Trips A RBCCW pump Examiners concurrence: (imf sw02a)

HLTS-3-4 Revision 0 Page 8 of 43 VIII. Console Operator Instructions (continued) Console Operator Manipulations If requested to align spare Aligns spare RBCCW pump to Unit 3 RBCCW pump to Unit 3 F9 (mrf sw02 align)

Wait 3 minutes If requested to reset local F12 mrf an01e reset RWCU panel alarms After spare RBCCW pump <Shift F3> Fails RFP governor in raise direction in aligned and RWCU Bat HLTS3-4-4 manual for 30 sec returned to service Two (2) Minutes after F6 fuel failure Feedpump governor (imf th23 5 15:00)

problem When directed by examiner F7 RWCU line break with failure to isolate (bat HLTS3-4)

ROLE PLAY: If requested to attempt to close 69-1 locally at the breaker, wait 5 minutes and report it will not close ROLE PLAY: If requested to check Aux Inst rm, report 835 A&C and 835 B&D reading 90 deg F and fairly steady After attempts to close 69-1 F10 Causes Rad monitors to reach max are made (bat HLTS3-4-1)

Terminate the scenario when the following conditions are satisfied or when requested by Chief Examiner:

1. Reactor Water level restored between +2 to +51" 2. RPV rapidly depressurized 3. RPV emergency depressurized

HLTS-3-4 Revision 0 Page 9 of 43 IX. Scenario Summary The plant is at approximately 9% power withdrawing control rods to open sufficient bypass valves to roll the main turbine . B RFP needs to be started and warmed in preparation for water level contro During the control rod withdrawal, the RWM will experience a program fault which will block rod movement. Tech. Specs will be addressed and control rod withdrawal will continue when a second licensed operator is present to ensure withdrawal is in accordance with the BPW A CRD pump will trip causing the crew to start the standby CRD pum An RBCCW pump will trip causing RWCU to be secured and the spare RBCCW pump aligned to Unit 3 and the RWCU system returned to servic The In-service RFP will experience a governor fault causing it to inject cold water into the RPV causing a power spike and some fuel failure. Later the RWCU system develops and leak and fails to isolate requiring entry into EOI-3 and subsequent rapid depressurization due to 2 areas approaching max safe radiation level HLTS-3-4 Revision 0 Page 10 of 43 X. Information to Evaluators: Ensure recorders are inking and recording and ICS is active and updatin Assign Crew Positions based on the required rotatio . SRO _________________ ATC _________________ BOP _________________ Conduct a shift turnover with the Shift Manager and provide the Shift Manager with a copy of the Shift Turnove Direct the shift crew to review the control board and take note of present conditions, alarms, et Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluato . Reactor water level restored at +2" to +51" RPV rapidly depressurized RPV emergency depressurized when 2 areas are above max safe value HLTS-3-4 Revision 0 Page 11 of 43 X Simulator Event Guide EVENT 1: Warming up second RFP TIME POSITION EXPECTED ACTIONS SRO Directs warming up B RFP in accordance with 3-OI-3 BOP Warms up B RFP utilizing section 5.6 of 3-OI- ARP-9-6C window 32 A. VERIFY reactor Feedpump flow on Panel 3-9- N/A B. REFER TO 3-OI-3, Section N/A C. IF annunciation is caused by RFW Control System malfunction, THEN REQUEST assistance from Site Engineering and IM HLTS-3-4 Revision 0 Page 12 of 43 X Simulator Event Guide EVENT 1: Warming up second RFP TIME POSITION EXPECTED ACTIONS BOP Place in auto and verify open RFP min flow valve 3-FCV-3-13 Place 3B start/local enable 3-HS-46-138A in start and observe RFP accelerates to 600 rpm Verify no abnormal rubbing or vibration is observed Raise speed to ~1000 rpm using 3-HS-46-9A Place TG motor 3-HS-3-127A in Auto Depress 3B trip 3-HS-3-127A and verify HP and LP stop valves close Verify TG auto engages or RFP rolling on min flow Depress 3B trip reset 3-HS-3-150A and verify blue light extinguishes and HP and LP stop valves open Place 3B start/local enable 3-HS-46-138A in start and observe RFPT speed increases to ~ 600 rpm

HLTS-3-4 Revision 0 Page 13 of 43 XI : Simulator Event Guide EVENT 2: RWM FAILURE TIME POSITION EXPECTED ACTIONS ATC Announces RWM ROD BLOCK 3-XA-55-5B window 35 alarm and refers to AR A. CHECK RWM panel for erro B. CHECK rod position and COMPARE it with Control Rod Movement Data Sheet (3-SI-4.3.B.1.a) (3-SR-3.1.3.5(A)).

C. IF RWM becomes inop, THEN REFER TO 3-OI-85 and Tech Spec 3.1, 3.3, Table 3.3.2.1- SRO Directs ATC to bypass RWM per OI-85 Refers to T.S. 3.1, 3.3, table 3.3.2.1-1 Contacts Rx Engineer

HLTS-3-4 Revision 0 Page 14 of 43 XI : Simulator Event Guide EVENT 2: RWM FAILURE TIME POSITION EXPECTED ACTIONS ATC 3-OI-85 section 8.17

[1] VERIFY the following initial conditions are satisfied:

The Shift Manager/Reactor Engineer has directed the Rod Worth Minimizer to be bypasse * A second licensed operator is available to verify control rod positio [2] REVIEW all Precautions and Limitations in Section [3] PLACE RWM SWITCH PANEL, 3-XS-85-9025, in BYPAS [4] CHECK the Manual Bypass light is illuminate [5] CHECK all other indications on the Rod Worth Minimizer Operator's Panel are extinguishe HLTS-3-4 Revision 0 Page 15 of 43 XI : Simulator Event Guide EVENT 2: RWM FAILURE TIME POSITION EXPECTED ACTIONS ATC [6] CHECK the Blue Rod Out Permit light above 3-HS-85-48 is illuminate [7] RESET CONTROL ROD WITHDRAWAL BLOCK annunciator (3-XA-55-5A, Window 7).

SRO Determines T.S. 3.3.2.1 condition C.2.1-1 & 2.2 applie Greater than 12 rods withdrawn and 2nd person to verify compliance with BPW HLTS-3-4 Revision 0 Page 16 of 43 X Simulator Event Guide EVENT 3: CRD PUMP 3A TRIP TIME POSITION EXPECTED ACTIONS ATC Recognize annunciator MOTOR TRIPOUT 3-ARP-9-8c (W 33) is in alar Acknowledges and resets MOTOR TRIPOUT annunciato Recognize 3A CRD pump has tripped and performs Immediate Operator Actions in accordance with 3-AOI-85-3, CRD System Failur .1 Immediate Actions

[1] IF operating CRD PUMP has TRIPPED AND STANDBY CRD PUMP is AVAILABLE, THEN (Otherwise N/A)

PERFORM the following at Panel 3-9-5:

[1.1] PLACE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, in MAN at minimum settin HLTS-3-4 Revision 0 Page 17 of 43 X Simulator Event Guide EVENT 3: CRD PUMP 3A TRIP TIME POSITION EXPECTED ACTIONS ATC [1.2] START associated standby CRD Pump using one of the following:

CRD PUMP 3B, using 3-HS-85-2A

CRD Pump 3A, using 3-HS-85-1A

[1.3] ADJUST CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, to establish the following conditions:

CRD CLG WTR HDR DP, 3-PDI-85-18A, approximately 20 psi CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, between 40 and 65 gp [1.4] BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and PLACE in AUTO or BALANC HLTS-3-4 Revision 0 Page 18 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS BOP Responds to loss of RBCCW pump 3A trip and attempts to restart 3A RBCCW pump and reports it failed to star ARP-9-4C window 12 A. VERIFY 3-FCV-70-48 CLOSING/CLOSE Reports that the 3-FCV-70-48 sectionalizing valve failed to clos B. VERIFY RBCCW pumps A and B in servic C. VERIFY RBCCW surge tank low level alarm is rese D. DISPATCH personnel to check the following:

RBCCW surge tank level locall RBCCW pumps for proper operatio E. REFER TO 3-AOI-70-1 for RBCCW System failure and 3-OI-70 for starting spare pum HLTS-3-4 Revision 0 Page 19 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS SRO Directs securing RWCU pumps per 3-AOI-70-1 BOP Immediate Actions

[1] IF RBCCW Pump(s) has tripped, THEN: ATTEMPT to restart tripped pump(s).

[2] IF RBCCW Pump(s) cannot be restarted, THEN:

(Otherwise N/A) SHUT DOWN RWCU System Pump (Reference TRM 3.4.1)

Secures RWCU pumps and reports that the 3-FCV-70-48 sectionalizing valve failed to clos N/A IF Reactor is at power AND Drywell Cooling cannot be immediately restored, AND core flow is above 60%,THEN:

(Otherwise N/A):

N/A REDUCE core flow to between 50-60%.

N/A MANUALLY SCRAM the Reactor and PLACE Mode Switch to SHUTDOWN. REFER TO 3-AOI-100- N/A SHUT DOWN both Recirc Pump N/A DEPRESS RECIRC DRIVE 3A SHUTDOWN, 3-HS-96-1 N/A DEPRESS RECIRC DRIVE 3B SHUTDOWN, 3-HS-96-2 N/A INITIATE a 90F/HR cooldown rate. REFER TO 3-AOI-100- N/A IF any EOI entry condition is met, THEN: (Otherwise N/A)

HLTS-3-4 Revision 0 Page 20 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS

[3] IF unable to restart a tripped pump, THEN:

(Otherwise N/A) PLACE Spare RBCCW Pump in servic REFER TO 3-OI-7 REQUEST Unit 1 to place the spare RBCCW pump in service to support Unit 3 operation. (REFER TO 1-OI-70).

Contacted U1 Operator to place the spare pump in service to Unit Back to 3-AOI-70-1

[4] IF RBCCW flow was restored to two pump operation THEN: (Otherwise N/A)

[4.1] REOPEN RBCCW SECTIONALIZING VLV, 3--HS--70-48A. After Spare RBCCW pump placed in service, (conditional, SRO may not direct valve to be opened after failure to auto close and if so, will NOT place RWCU in service.)

[4.2] RESTORE the RWCU system to operation. (REFER TO 3-OI-69)

HLTS-3-4 Revision 0 Page 21 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS BOP 3-OI-69 section 5.1 [8]

RWCU Pump Startup

[1] REVIEW precautions and limitations in Section [2] VERIFY RWCU prestartup requirements in Section have been complete [3] VERIFY RESET the RWCU Group 3 isolation using PCIS DIV I RESET, 3-HS-64-16A-S32 and PCIS DIV II RESET, 3-HS-64-16A-S33 at Panel 3-9- [4] IF a condition exists which could have caused 3-FCV-069-0094 to isolate, THEN VERIFY OPEN 3-FCV-069-0094, RWCU SYSTEM APP R FLOW CONTROL VLV, locally. (Unit 3 Rx Bldg, El 593' R-17 S-Line).

[5] VERIFY RWCU HEAT EXCHANGERS RBCCW FLOW CONTROL, 3-TIC-069-0010A is in MANUAL, and FULL OPEN demand is on 3-TCV-70-49. (REFER TO Illustration 5)[BFPER 03-000348-000]

[6] VERIFY CLOSED the following:

RWCU BLOWDOWN PRESS CONTROL VLV, using 3-HC-69-15

RWCU BLOWDOWN TO MAIN CNDR, using 3-HS-69-16A

RWCU BLOWDOWN TO RADWASTE, using 3-HS-69-17A

HLTS-3-4 Revision 0 Page 22 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS

[7] IF a Caution Order is present on the control room hand switch for RWCU PUMP 3A(3B) informing operator that 3-SHV-070-0573A(0573B) is closed, THEN PERFORM the following:

[7.1] OPEN 3-SHV-070-0573A(0573B), RWCU PUMP A(B)

CLG WTR INLE [7.2] REMOVE Caution Order from the control room hand switch for RWCU PUMP 3A(3B) informing operator that 3-SHV-070-0573A(0573B) is CLOSE [8] NOTIFY chemistry RWCU is being placed in service and to check the durability monito [9] VERIFY OPEN the following valves:

RWCU INBD SUCT ISOLATION VALVE, 3-FCV-69-1

RWCU OUTBD SUCT ISOLATION VALVE, 3-FCV-69-2

RWCU DEMIN BYPASS VALVE, 3-FCV-69-8

[10] OPEN 3-FCV-069-0012 by one of the two methods described belo HLTS-3-4 Revision 0 Page 23 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS BOP * PLACE 3-HS-69-12A in the OPEN position, THEN RETURN 3-HS-69-12A to the NORM position when intermediate position (red and green light) is indicate * PLACE 3-HS-69-12A in the OPEN position, THEN RETURN 3-HS-69-12A to the NORM position when FULL OPEN position (red light only) is indicate N/A [11] PLACE seal purge in operation to pump(s) to be placed in service. REFER TO Section [12] START RWCU RECIRC PUMP 3A(3B) using control switch 3-HS-69-4A(4B)-A, and A RISE flow, using RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent low flow tri [13] IF two pump operation is desired, THEN START the second RWCU RECIRC PUMP 3B(3A) using control switch 3-HS-69-4B(4A)-A, and A RISE flow using RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent low flow tri [14] IF the RWCU filter-demineralizers is to be placed in service, THEN REFER TO Section (all local actions except Operator closing 3-FCV-69-8 valve as AUO rolls demins in service)

HLTS-3-4 Revision 0 Page 24 of 43 X Simulator Event Guide EVENT 4: LOSS OF 3A RBCCW pump TIME POSITION EXPECTED ACTIONS 3-ARP-9-4B window 24 A. DISPATCH personnel to local Panel 25-3, to determine cause of alar B. IF alarm is valid, THEN REFER TO 3-ARP-25-3 for appropriate operator actio C. IF this alarm meets the requirements AND the Shift Manager desires the annunciator to be disabled, THEN REFER TO OPDP- BOP Coordinates with AUO to roll demins in service SRO Dispatches personnel to investigate pump loss May contact Rx Engineer about heat balance Contacts Chemistry Reviews TRM LCO 3.4.1 and verify it does not apply whether RWCU is placed in service or no HLTS-3-4 Revision 0 Page 25 of 43 X Simulator Event Guide EVENT 5: FEEDWATER CONTROLLER FAILURE TIME POSITION EXPECTED ACTIONS ATC Observes period rise by meter or annunciator and checks for cause of reactivity addition ATC Ranges IRMs as necessary to prevent a reactor scram BOP Attempts to take control of A RFP by adjusting 3-HS-46-8C and reports that C RFP cannot be controlled IF Feedwater Control System has failed, THEN PERFORM the following:

PLACE individual RFPT Speed Control Raise/Lower switches in MANUAL GOVERNOR (depressed position with amber light illuminated).

ADJUST RFP Discharge flows with RFPT Speed Control Raise/Lower switches as necessary to maintain leve IF level continues to rise, THEN TRIP a RFP, as necessar HLTS-3-4 Revision 0 Page 26 of 43 X Simulator Event Guide EVENT 5: FEEDWATER CONTROLLER FAILURE TIME POSITION EXPECTED ACTIONS SRO Directs tripping C RFP and using B RFP for RPV level control (Critical Task)

BOP Trips C RFP by depressing 3-HS3-125C and raises B RFP speed by using 3-HS-46-9B (Critical Task)

BOP Opens B RFP discharge valve 3-HS-3-12B when B RFP discharge pressure is within 250 lbs of reactor pressur HLTS-3-4 Revision 0 Page 27 of 43 X Simulator Event Guide EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION TIME POSITION EXPECTED ACTIONS BOP Announces TURBINE BUILDING HIGH RADIATION 3-ARP-9-3A window 27 DETERMINE area with high radiation level on Panel 3-9-1 (Alarm on Panel 3-9-11 will automatically reset if radiation level lowers below setpoint.)

IF the TSC is NOT manned, THEN USE public address system to evacuate area where high airborne conditions exis N/A IF the TSC is manned, THEN REQUEST the TSC to evacuate non-essential personnel from affected area NOTIFY RADCO MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed i HLTS-3-4 Revision 0 Page 28 of 43 X Simulator Event Guide EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION TIME POSITION EXPECTED ACTIONS BOP Announces RX BLDG HIGH RADIATION and determines which area and evacuates that area. North and South RWCU are DETERMINE area with high radiation level on Panel 3-9-1 (Alarm on Panel 3-9-11 will automatically reset if radiation N/A level lowers below setpoint.)

IF the alarm is from the HPCI Room while Flow testing is being performed, THEN REQUEST personnel at the HPCI Quad to validate conditions NOTIFY RADCO IF the TSC is NOT manned and a VALID radiological condition exists., THEN USE public address system to evacuate area where high airborne conditions exist MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed i HLTS-3-4 Revision 0 Page 29 of 43 X Simulator Event Guide EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION TIME POSITION EXPECTED ACTIONS BOP Announces OFF-GAS ANNUAL RELEASE LIMIT EXCEEDED 3-ARP-9-4C window 27 To determine if the Off Gas Annual Release Rate Limit is exceeded, PERFORM the following:

VERIFY alarm condition on the following:

OFFGAS PRETREATMENT RADIATION recorder, 3-RR-90-157 on Panel 3-9-2

OG PRETREATMENT RAD MON RTMR radiation monitor, 3-RM-90-157 on Panel 3-9-10 CHECK off-gas flow and monitor sample flow norma NOTIFY RADCO BOP/SRO Notifies Chemistry to perform analysis and Radcon SRO Declares a NOUE on a valid OG pretreatment rad alar HLTS-3-4 Revision 0 Page 30 of 43 X Simulator Event Guide EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION TIME POSITION EXPECTED ACTIONS BOP REQUEST Chemistry perform radiochemical analysis to determine sourc N/A WITH OPS MGT and Shift Managers permission, PLACE charcoal beds in parallel with another unit. REFER TO 3-OI-6 IF fuel damage is suspected, THEN REFER TO 3-SI-4.6.B.5 (3-SR-3.4.6.1) for dose equivalent iodine - 131 determinatio REFER TO 0-SI-4.8.B.1.a.1 and 3-SI-4.6.B.6 (3-SR-3.4.6.1-a)

for ODCM compliance and to determine if power level reduction is require IF directed by Shift Manager or Unit Supervisor, THEN REDUCE reactor power to maintain off-gas radiation within ODCM limit REFER TO EPIP- HLTS-3-4 Revision 0 Page 31 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS BOP Reports on RWCU leak detection alarms 3-ARP-9-3D window

N/A IF this alarm is received in conjunction with RWCU ISOL LOGIC CHANNEL A TEMP HIGH [3-XA-55-5B, window 32]

and RWCU ISOL LOGIC CHANNEL B TEMP HIGH [3-XA-55-5B, window 33], THEN EXIT this procedure and GO TO 3-ARP-9-5B. Otherwise, CHECK RWCU Leak Detection System temperatures on Panel 3-9-21 and Panels 9-83, 9-84, 9-85 and 9-86 in the auxiliary instrument room. . The 834 and 835 Temp Loops are also displayed on ICS under 'HPTURB' for Main Steam Tunnel and 'RWCU' for the Pipe Trenc IF high temperature is indicated on TS69-29D, E, F, G or H or TIS 69-835A, B, C, or D, THEN ENTER 3-EOI-3 Flowchar CHECK Rx Bldg. RWCU system ARMs, 3-RI-90-13A and 14A on Panel 3-9-11, and Rx Zone Exhaust Rad Monitor, 3-RR-90-142 on Panel 3-9- DISPATCH personnel to investigate the affected are SRO Enters EOI-3 on either high temp or high radiation

HLTS-3-4 Revision 0 Page 32 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS ATC Recognizes that 69-1 failed to isolate and attempts to manually close Crew Directs outside personnel to attempt to close 69-1 locally at the breake SRO Directs Rx Scram before any area temp is above the maximum safe operating temperatur ATC Scrams reactor and provides scram report SRO Directs ATC to perform actions of 3-AOI-100-1

HLTS-3-4 Revision 0 Page 33 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS SRO/BOP Continue to monitor and trend secondary area temps and radiation levels BOP Reports that 2 areas are approaching maximum safe radiation levels SRO Directs rapid depressurization ot the RPV using BPVs BOP Opens all BPVs using the Jack BOP/ATC Coordinate level control during depressurization to prevent flooding the RPV BOP Determines that 2 areas are above max safe radiation values SRO Determines that Emergency Depressurization is Required and enters C2 (Critical Task)

Directs BOP to open all ADS valves (Critical Task)

BOP Opens all ADS valves (Critical Task)

HLTS-3-4 Revision 0 Page 34 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS Reports Main Steam Line Radiation High - High 3-ARP-9-3A window 27 A. VERIFY the alarm on 2-RM-90-136and 2-RM-90-137 on Panel 2-9-1 B. CONFIRM main steam line radiation level on recorder 2-RR-90-135, Panel 2-9- C. IF alarm is valid and Reactor Scram has not occurred, THEN PERFORM the following:

1. IF core flow is above 60% THEN LOWER core flow to between 50-60%..

2. MANUALLY SCRAM the Reacto . REFER to 2-AOI-100-1 .

D. IF plant conditions DO NOT require execution of 2-C-5, THEN VERIFY the MSIVs close E. NOTIFY RADCO F. VERIFY actions of 2-ARP-9-3A Window 7 have been complete G. IF Technical Specification limits are exceeded, THEN REFER TO EPIP- HLTS-3-4 Revision 0 Page 35 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS 3-ARP-9-3A window 7 A. CHECK following radiation recorders:

1. MAIN STEAM LINE RADIATION monitor, 2-RR-90-135 on Panel 2-9- . OFFGAS PRETREATMENT RADIATION, 2-RR-90-157 on Panel 2-9- . OFFGAS RADIATION, 2-RR-90-160 on Panel 2-9- . OFFGAS POST-TREATMENT RADIATION, 2-RR-90-265 on Panel 2-9- . STACK GAS RADIATION, 0-RR-90-147 on Panel 1-9- B. NOTIFY RADCO C. [NRC/C] NOTIFY Chemistry to perform radiochemical analysis of primary coolant. [NCO 940247001]

HLTS-3-4 Revision 0 Page 36 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS SRO Directs Rx water level be maintained +2 - +51 using Condensate, Core Spray, or RHR App 6A Condensate 1. VERIFY CLOSED the following Feedwater heater return valves:

3-FCV-3-71, HP HTR 3A1 LONG CYCLE TO CNDR 3-FCV-3-72, HP HTR 3B1 LONG CYCLE TO CNDR 3-FCV-3-73, HP HTR 3C1 LONG CYCLE TO CND . VERIFY CLOSED the following RFP discharge valves:

3-FCV-3-19, RFP 3A DISCHARGE VALVE 3-FCV-3-12, RFP 3B DISCHARGE VALVE 3-FCV-3-5, RFP 3C DISCHARGE VALV . VERIFY OPEN the following drain cooler inlet valves:

3-FCV-2-72, DRAIN COOLER 3A5 CNDS INLET ISOL VLV 3-FCV-2-84, DRAIN COOLER 3B5 CNDS INLET ISOL VLV 3-FCV-2-96, DRAIN COOLER 3C5 CNDS INLET ISOL VLV

HLTS-3-4 Revision 0 Page 37 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS 4. VERIFY OPEN the following heater outlet valves:

3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VLV 3-FCV-2-125, LP HEATER 3B3 CNDS OUTL ISOL VLV 3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VL . VERIFY OPEN the following heater isolation valves:

3-FCV-3-38, HP HTR 3A2 FW INLET ISOL VLV 3-FCV-3-31, HP HTR 3B2 FW INLET ISOL VLV 3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV 3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV 3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VLV 3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV

HLTS-3-4 Revision 0 Page 38 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS 6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-83, RFP 3A SUCTION VALVE 3-FCV-2-95, RFP 3B SUCTION VALVE 3-FCV-2-108, RFP 3C SUCTION VALV . VERIFY at least one condensate pump runnin . VERIFY at least one condensate booster pump runnin . ADJUST 3-LIC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5).

10. VERIFY RFW flow to RP HLTS-3-4 Revision 0 Page 39 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS App 6D (6E) Core Spray Sys I (Loop II similar)

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV 3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VLV 3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALV . VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALV . VERIFY CS Pump 3A and/or 3C RUNNIN . WHEN ... RPV pressure is below 450 psig, THEN ...

THROTTLE 3-FCV-75-25, CORE SPRAY SYS I INBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pum . MONITOR Core Spray Pump NPSH using Attachment HLTS-3-4 Revision 0 Page 40 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS App 6B (6C) RHR Sys I (Loop II similar)

1. IF ..... Adequate core cooling is assured AND It becomes necessary to bypass LPCI Injection Valve Timers to control injection, THEN ... EXECUTE EOI Appendix 16F concurrently with this procedur . VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL . VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VL . 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 CHBR/POOL ISOL VLV 3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE 3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VL HLTS-3-4 Revision 0 Page 41 of 43 X Simulator Event Guide EVENT 7: RWCU LINE SUCTION BREAK TIME POSITION EXPECTED ACTIONS 5. VERIFY RHR Pump 3A and/or 3C runnin . WHEN ... RPV pressure is below 450 psig, THEN ... VERIFY OPEN 3-FCV-74-53, RHR SYS I LPCI INBD INJECT VALV . IF ..... RPV pressure is below 230 psig, THEN ... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALV HLTS-3-4 Revision 0 Page 42 of 43 XII. Crew Critical Tasks TASKS SAT/UNSAT Trips C RFP prior to reaching Main _______

Steam Lines (120 on 3-55 level instrument) Emergency Depressurize when 2 areas _______

reach maximum safe values. (Within 5 minutes)

HLTS-3-4 Revision 0 Page 43 of 43 XIII. Scenario Verification Data EVENT TASK NUMBER K/A RO SR CONTROL O MANIPULATION Warm up RFP 259001 3.9 A4.02 RWM Failure 201006 3.2 A4.01 CRD Pump Trip 201001 3.2 A2.01 RBCCW Pump 295018 Trip AK3.03 3.1 AA1.01 3.3 AK3.04 3.3 3.3 RFP Governor 259001 A2.07 3.7 failure 295008 AA1.08 3.5 3.5 Fuel Failure 295014 AA1.05 3.9 AA1.07 4.0 4.1 RWCU Line Break 295033 EA1.05 3.9 EK3.01 3.3 HLTS-3-4 Revision 0 Page 44 of 43 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-3-4 7 Total Malfunctions Inserted; List: (5-8)

1) RWM Failure 2) CRD Pump trip 3) RFP controller failure 4) Fuel Damage 5) RWCU line break 6) A RBCCW pump trip 7) Failure of 69-1 to close 8) Failure of RFPs to trip on Hi level 1 Malfunctions That Occur After EOI Entry; List: (1-2)

1) RWCU line Break 3 Abnormal Events; List: (2-4)

1) RFP control failure 2) CRD Pump trip 3) RBCCW pump trip 1 Major Transients; List: (1-2)

1) RWCU line break (small LOCA)

_2 EOIs used; List: (1-2)

1) EOI-1 2) EOI-3 1 EOI Contingencies Used; List: (0-2)

1) C2 63 Run Time (minutes)

52 EOI Run Time (minutes); 83 % of Scenario EOI Run Time 2 Crew Critical Tasks (2-3)

Yes Technical Specifications Exercised (yes/no)

SHIFT TURNOVER SHEET Equipment Out of Service/LCOs 3A RFP is uncoupled and awaiting overspeed testing.

Suction, Discharge and Minimum Flow valves are tagged.

Operations/Maintenance For the Shift: Continue with reactor startup at step 5.69.8 of 3-GOI-100-1A. Continue with warm-up of B RFP per OI-3 at step 5.6.[18]. Thrust bearing/ Overspeed/ Stop Valve and Control Valve tests are complete for B RFP.

Place 3B RFP 100 psig below reactor pressure.

Unusual Conditions/Problem Areas: Power System Alert in effect for the next 36 Hour Appendix D Scenario Outline Form ES-D-1 Facility: BFN Scenario Number: HLTS-3-4 Op-Test Number: HLT0610 Examiners:__________________ Operators: _________________

__________________ _________________

Initial Conditions:

The unit is starting up following a refuel outage. Reactor power is at ~ 1%. C RFP is uncoupled for performance of turbine overspeed testing. Currently at step 5.76.8 of 2-GOI-100-1A.

Turnover:

The 3C RFP is uncoupled and the suction and discharge valves are tagged for performance of turbine overspeed. Currently at step 5.76.8 of 3-GOI-100-1A and at step 5.6.13 of 3-OI-3 for warming 3B RF Event Malfunction Event Event Number Number Type* Description 1 none R-ATC Crew will continue to pull rods to increase power and start N-BOP warming up 2B RFP R-SRO 2 imf rd14a I-ATC Crew will respond to a RWM failure. SRO references ITS I-SRO TS-SRO 3 imf sw02a trip C-BOP Crew will respond to a RBCCW pump trip 7048FTC C-SRO Crew manually closes 70-48 after fails to auto close 4 ior zdihs468a C-BOP Crew will respond to feedwater controller malfunction which imf th23 5 C-SRO results in cold water injection 5 imf th23 5 M Crew responds to fuel failure after cold water injection All 6 imf cu04 25 M Crew responds to a RWCU line break and scrams reactor ior zdihs691 All before any area reaches max safe valu null

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

IR 05000259/2008301

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v t e Inspection Report - Browns Ferry - 2008301 (Operator Exams)
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2008 Quarterly Integrated 1Q (0) 2Q (3) 3Q (1) 4Q (2) Assessments Mid Cycle End of Cycle 7(2) 8(0) 9(0) 10(0) Security 401(0) Operator Exams 301(0) 302(0) Emergency Planning 501(0) Other

IR 05000259/2008301

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