Text

Initial Exam 2011-302 Draft Simulator Scenarios 4 of 4
	ML12074A045
Person / Time
Site:	Watts Bar
Issue date:	04/29/2011
From:	; Operator Licensing and Human Performance Branch
To:	; Tennessee Valley Authority
References
	50-390/11-302
	Download: ML12074A045 (158)
	v • d • e

ppendix D Scenario Outline Form ES-D-1 Facility: Watts Bar October 2011 Scenario No. 7 Op Test No.: 2 Examiners: Operators: SRO RO BOP Initial Conditions: 92% Reactor Power, MOL, RCS boron concentration 765 ppm. Control Bank D at 199 steps.

Turnover: Train A/Channel I Work Week. Power is at 92%, after completion of Turbine Valve testing.

The TDAFW pump is out of service due to broken trip-and-throttle valve linkage. LCO 3.7.5.b was entered 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago. The repairs are expected to be completed in the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Protected equipment signs have been posted for lA-A MDAFW pump, the lB-B MDAFWP pump, the 1A DG and the lB DG. IC Condensate Booster pump A is out of service due for bearing replacement, with repairs in progress. A return to 95% power following Turbine Valve testing is in progress, using GO-4, Normal Power Operations. A Reactivity Plan has been provided by Reactor Engineering. Chemistry has requested that letdown flow be maintained at 75 gpm during the power escalation.

Event MaIf. No. Event Type* Event Description No.

1 n/a R-RO Continue power escalation to 95% using GO-4, Normal Power N-BOP/SRO Operations.

2 rxl 5d TS-SRO 1 -LT-3-1 06 fails high. Requires a Tech Spec evaluation.

3 fw56b C-BOP 1 B #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

4 pic 1-RO 1 -PIC-68-340A, PZR PRESS MASTER CONTROL fails.

340a_ai rcrO5 remote 5 cc07a C-BOP lA-A CCS pump shaft shears and I B-B CCS pump fails to start cc03b TS-SRO automatically.

6 th03c C-RO An RCS leak (approximately 30 gpm) develops.

7 th02c M-ALL Large break LOCA develops at the reactor trip. A AIR RETURN ch29a fan trips on overcurrent.

8 rhO2 C-RO Auto swap-over to containment sump fails. 1-FCV-63-72 fails rhl2 0 closed, and cannot be reopened.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Watts Bar Examination October 2011 NUREG 1021 Revision 9

ppendix D Scenario Outline Form ES-D-1 Scenario 7 - Summary Initial Condition 92% Reactor Power, MOL, RCS boron concentration 765 ppm. Control Bank D at 199 steps.

Turnover Train A/Channel I Work Week. Power is at 92%, after completion of Turbine Valve testing. The TDAFW pump is out of service due to broken trip-and-throttle valve linkage. LCO 3.7.5.b was entered 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago. The repairs are expected to be completed in the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Protected equipment signs have been posted for lA-A MDAFW pump, the lB-B MDAFWP pump, the 1A DG and the lB DG. 1C Condensate Booster pump A is out of service due for bearing replacement, with repairs in progress. A return to 95% power following Turbine Valve testing is in progress, using GO-4, Normal Power Operations. A Reactivity Plan has been provided by Reactor Engineering. Chemistry has requested that letdown flow be maintained at 75 gpm during the power escalation.

Event 1 Continue power escalation to 95% using GO-4, Normal Power Operations.

Event 2 1-LT-3-106, SG 4 LEVEL fails high. Requires a Tech Spec evaluation and entry into LCO 3.3.1, 3.3.2, and 3.3.3 for multiple functions.

Event 3 lB #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOI-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a load reduction.

Event 4 1-PIC-68-340A, PZR PRESS MASTER CONTROL fails. Requires the RO to take IMMEDIATE OPERATOR ACTION to place 1 -PIC-68-340A, PZR PRESS MASTER CONTROL in MANUAL and restore pressure to normal. Requires entry into AOl-i 8, Malfunction of Pressurizer Pressure Control System, Sub section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

Event 5 lA-A CCS pump shaft shears and 1 B-B CCS pump fails to start automatically.

Requires entry into AOl-i 5, Loss of Component Cooling Water (CCS). Requires the BOP to manually start the 1 B-B CCS pump. Requires a Tech Spec evaluation and entry into LCO 3.7.7.

Event 6 An RCS leak (approximately 30 gpm) develops. Requires entry into AOI-6, Small Reactor Coolant System Leak. Leak worsens when the crew realigns charging and letdown per AOI-6, Small Reactor Coolant System Leak.

Event 7 Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on start.

Event 8 Auto swap-over to containment sump fails. i-FCV-63-72 fails closed, and cannot be reopened. When ES-i .3, Transfer to Containment Sump is performed, one train of RHR will be aligned.

Appendix D Watts Bar Examination October 2011 NUREG 1021 Revision 9

ppendix D Scenario Outline Form ES-D-1 Scenario 7 Critical Task Summary Critical Task 1 Manually start the I B-B Component Cooling Water (CCS) pump within 10 minutes of the trip of the lA-A Component Cooling Water (CCS) pump to establish Reactor Coolant pump oil cooling.

Critical Task 2 Transfer to cold leg recirculation and establish one train of ECCS recirculation flow prior to exiting ES-i .3, Transfer to Containment Sum p.

Appendix D Watts Bar Examination October2011 NUREG 1021 Revision 9

Watts Bar Nuclear Plant 10-2011 NRC Examination Scenario 7 Simulator Console Operators Instructions SIMULATOR SETUP INFORMATION ENSURE Examination Security has been established.

RESET to Initial Condition 306 by performing the following actions:

a. Select lCManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 306.

c. Right click on lC# 306.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC 306.

Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. SELECT Director on the THUNDERBAR menu (right hand side of Instructor Console Screen).

4. ENSURE the following information appears on the Director Screen:

Key Description Type Event Delay Inserted Ramp Initial Final Value r hs-46-56a-l 05010 afwt a-s U position(green) 0 00:00:00 00:00:00 00:00:00 0ff Off hs-l -l 7a-l 13060 stm flow to afpt isolation(green) 0 00:00:00 00:00:00 00:00:00 Off Off hs-l-18a-l 13060 stm flow to afpt isolation(green) 0 00:00:00 00:00:00 00:00:00 Off Off rhl2 fail cnt sump to rhr pmp a fcv 63-72 to any position M 00:00:00 00:00:00 00:00:00 0 0 cc03b ccs pump lb-b auto start inhibit M 00:00:00 00:00:00 00:00:00 Active Active rhO2 failure of auto transfer to containment sump M 00:00:00 00:00:00 00:00:00 Active Active ch29a oc trip of air return fan a-a M 00:00:00 00:00:00 00:00:00 Active Active Page 1 of 4

Watts Bar Nuclear Plant 10-2011 NRC Examination Scenario 7 Simulator Console Operators Instructions SIMULATOR SETUP INFORMATION Key Description Type Event Delay Inserted Ramp Initial Final Value

] hs-2-84a-1 05010 condensate booster pump c control switch 0 00:00:00 00:00:00 00:00:00 stop stop siO7 rwst leak M 19 00:00:00 00:00:00 8 0 thOic -

loca hot leg loop 3 M 19 00:00:00 00:02:00 100 0 rxl5d stm gen level transmitter fail, cntlr chnls sg #4 lt-3-106 M 2 00:00:00 00:00:00 100 57.9746 fw56b hdp 3b bearing wear M 3 00:00:00 00:01:45 11 0 rcr05 pzr plc 68-340 local/control room control 0 4 00:00:00 00:00:00 remote local pic-68-340a_ai 03250 rcs przr press control R 4 00:00:00 00:00:00 0 32.8125 cc07a ccs pump I a-a shaft break M 5 00:00:00 00:00:00 Active InActive th03c -

loca small leak loop 3 M 6 00:00:00 00:01:00 1.75 0

5. Place simulator in RUN and acknowledge any alarms.

PLACE Hold Order RED tags on 1-HS-1-17A, STM HDR TO T-D AFW PMP and 1-HS-1-18A, STM HDR TO T-D AFW PMP.

Place PINK Protected Equipment tags on 1-HS-3-118A, AFW PMP A-A, 1-HS-3-128A, AFW PMP B- B, 1-HS-82-4, START STOP and 1-HS START STOP. -

7. -

ENSURE the Train A Week Channel 1 sign is placed on 1-M-30.

8. Place simulator in FREEZE.

9. ENSURE Watts Bar Nuclear Plant Unit I Reactivity Briefing Book MOL (MiddleOf Life) is provided to the crew as part of the Turnover Package, and that the MOL placards are on 1-M-6, below the Boric Acid and Primary Water lntegrators.

10. WHEN prompted by the Chief Examiner, place the Simulator in RUN.

Page 2 of 4

Watts Bar Nuclear Plant 10-2011 NRC Examination Scenario 7 Simulator Console Operators Instructions Exam Simulator Event Event DescriptionlRole Play No. No.

I n/a Continue power escalation to 95% using GO-4.

ROLE PLAY: None 2 2 1-LT-3-106 fails high. Requires a Tech Spec evaluation.

ROLE PLAY: When contacted as Work Control, repeat back the request to remove the 1-LT-3-106, SG 4 LEVEL from service.

3 3 1 B #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

ROLE PLAY: When contacted as an AUO to assess #3 HDT, repeat back the request. Open THUNDER VIEW screen fw6 and report #3 HDT levels.

ROLE PLAY: When contacted as an AUO, repeat back request and then report that the lB #3 HDT pump bearings are very hot.

ROLE PLAY: When the BOP dispatches an AUO to the lB 6.9 KV Unit Board to check the breaker for the lB #3 HDT pump, the Console Operator will report either:

If the pump tripped that the breaker tripped on instantaneous overcurrent OR If the BOP stopped the lB #3 HDT pump manually, the Console Operator will report that no relays have been actuated.

ROLE PLAY: If the BOP dispatches additional personnel to monitor #2 feedwater heater levels, repeat back the request. Open INSIGHT file heaters and provide data as requested.

ROLE PLAY: When contacted as Work Control, repeat back request to have a troubleshooting and repair package for the lB #3 HD pump.

4 4 1-PIC-68-340A, PZR PRESS MASTER CONTROL fails, causing a false high pressure signal to be

processed.

ROLE PLAY: When contacted as Work ControI, repeat back request to have a troubleshooting and repair package made up for l-PIC-68-340, PZR PRESS MASTER CONTROL.

Page 3 of 4

Watts Bar Nuclear Plant 10-2011 NRC Examination Scenario 7 Simulator Console Operators Instructions Exam Simulator Event Event Description/Role Play

No. NO.

5 5 1 A-A CCS pump shaft shears and 1 B-B CCS pump fails to start automatically.

ROLE PLAY: When contacted as Work Control, repeat back the request to have a troubleshooting and repair package made up for the failure of the IA-A CCS pump shaft, and for the failure of the low pressure signal to start the lB-B CCS pump.

ROLE PLAY: When contacted 6 6 Small RCS leak develops.

ROLE PLAY: None Leak progresses to a Large Break LOCA.

ROLE PLAY: When contacted as the Control Building AUO, back request to check low analyzer temp lights, and reports that the lights are NOT LIT.

ROLE PLAY: When contacted as the Control Building AUO, repeat back the request, and then report that Appendix A, B and C have been performed. Enter remote functions sirOl, sirl4 and sirO6 to perform actions.

ROLE PLAY: RO may contact Control Building AUO to check on status of E-1, Appendix B performance. Reports that power to l-FCV-63-l has been restored.

1 B-B 6.9 KV Shutdown Board trip.

ROLE PLAY: When dispatched to the lB-B 6.9 KVShutdown Board, report that differential relay operation caused the board to be lost. The lB-B 6.9 KV Shutdown Board is severely damaged, but there is NO fire.

Page 4 of 4

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # I Page 1 of 50 Event

Description:

Continue power escalation to 95% using GO-4, Normal Power Operations.

Time Position Applicants Actions or Behavior EXAMINER: The following actions are taken from GO-4, Normal Power Operation Section 5.2, Unit Startup from 30% to 100% Reactor Power, beginning at Step 42. The SRO may direct that a dilution be started prior to the beginning of GO-4 actions.

EXAMINER: The SRO may elect to perform the power escalation using MANUAL rod control. SOI-85.01, Control Rod Drive and Indication System, Section 5.6, Manual Rod Control With Reactor At Power, is includes as Attachment 1.

The following actions are taken from SOl-62.02, Boron SOI-62.02 Concentration Control, Section 6.6, Minor Dilution.

NOTES

1) Section 6.6, Minor Dilution, may be reproduced, laminated, displayed, reused, etc. as desired.

2) Minor Dilution is defined as the addition of Primary Water done several times each shift to compensate for fuel burn-up, and maintain Tavg on program.

[1] ENSURE 1-HS-68-341H, BACKUP HEATER C, is ON, to equalize Pzr-RCS CB.

RD RO determines that that the GREEN indicating light is DARK and the RED indicating light is LIT on 1-HS-68-341H, BACKUP HEATER C.

[2] ADJUST 1-FQ-62-142, PW BATCH COUNTER, for required quantity.

RO adjusts 1-FQ-62-142 PWBATCH COUNTER as follows:

1. Depresses and holds the black pushbutton.

RD 2. While holding the pushbutton, the applicant raises the red translucent cover.

3. While still holding the pushbutton, the applicant enters the appropriate number of gallons of PWin the display.

4. While still holding the pushbutton, the applicant lowers the red translucent cover and then releases the pushbutton.

[3] PLACE 1-HS-62-140B, VCT MAKEUP MODE in DIL.

RD RO rotates 1-HS-62-140B, VCT MAKEUP MODE from the AUTO position three positions to the right to the DIL position.

[4] (p) TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.

[4.1] CHECK Red light is LIT.

RD RO rotates 1-HS-62-140A VCT MAKEUP CONTROL to the right to the START position, and allows the switch to return to the mid position. RO observes the RED indicating light LIT in 1-HS-62-140A.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: 2 Scenario # 7 Event# 1 Page 2 of 50 Event

Description:

Continue power escalation to 95% using GO-4, Normal Power Operations.

Time Position Applicants Actions or Behavior

[5] MONITOR the following parameters:

Instrument Location Parameters 1-PI-62-122 1-M-6 VCT PRESS 1 LI 62 129A 1-M-6 VCT LEVEL RO 1-FI-62-142 1-M-6 PWTO BLENDER FLOW 1-FQ-62-142 1-M-6 PW BATCH COUNTER 1-FQ-62-139 1-M-6 BA BATCH COUNTER

[6] WHEN dilution is COMPLETE, AND 1-FCV-62-128 is closed, THEN PLACE 1-HS-62140B, VCT MAKEUP MODE, in AUTO.

RO RO rotates 1-HS-62-140B, VCT MAKEUP MODE from the DIL position three positions to the left to the AUTO position.

[7] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.

[7.1] CHECK Red light is LIT.

RO When the dilution stopped automatically, 1-HS-62-140A VCT MAKEUP CONTROL received a STOP signal. To enable AUTO makeup, 1-HS-62-140A VCT MAKEUP must be rotated the right to the START position.

[8] IF desired to reduce VCT level, THEN GO TO Section 8.5, VCT RO Level Reduction.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 1 Page 3 of 50 Event

Description:

Continue power escalation to 95% using GO-4, Normal Power Operations.

Time Position Applicants Actions or Behavior The following actions are taken from GO-4, Normal Power Operation Section 5.2, Unit Startup from 30% to 100% Reactor Power, beginning at Step 46.

NOTES

1) Tl-45, Determination of Preconditioned Reactor Power, identifies ramp rates, specific power levels where HOLD times are required, and control rod withdrawal limits.

2) Power escalation ramp rates and hold times should be per the most conservative of either the fuel pre-conditioning guidelines of Tl-45 or the Turbine loading recommendations of SQl-47.0 2

3) Turbine load change may be stopped by depressing the HOLD push button, using VPL, or by depressing the MANUAL push button

[46] CONTINUE ascension to 100% power by performing the following:

[46.1] IF during any of the following steps the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise OR PUSH TURBINE MANUAL to place the turbine control mode in manual mode and PROCEED to section 5.6

[46.2] CHECK VALVE POS LIMIT light is NOT LIT.

[46.3] SET VALVE POSITION LIMIT at 100% or to 5% above RO the Gov Control Indication.

[46.4) SET LOAD RATE at predetermined value.

For a load escalation of 10% in an hour, the LOAD RATE will be set at 1%, the lowest value that can be selected.

[46.5] PUSH REFERENCE CONTROL (raise) button to set desired load in SETTER display.

The BOP will depress the REFERENCE CONTROL A (raise) button and raise the SETTER display by 1%.

NOTE The Conditioned Power Level (CPL) needs to be tracked for ramp rate considerations.

[47] DETERMINE the CPL and ramp rate restrictions from TI-45, Determination of Preconditioned Reactor Power, AND RECORD RO section reviewed I restrictions in narrative log:

RECORD section reviewed I restrictions in table below:

SRO enters data from the REACTIWTY PLAN provided.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: 2 Scenario# 7 Event# 1 Page 4 of 50 Event

Description:

Continue power escalation to 95% using GO-4, Normal Power Operations.

Time Position Applicants Actions or Behavior NOTES

1) RCS should be diluted to raise TAVG, then Turbine load raised along with TAVG. Control rods will be used along with dilution to maintain I and if needed for temperature.

2) During power ascension, #1 bearing has experienced higher than normal metal temperature but never exceeded the alarm set point. The cause of the elevated temperature is due to the partial arc admission design of the HP turbine and the less than optimal alignment between the HP turbine and the A LP turbine. Although this condition is expected, operators should closely monitor #1 bearing metal temperature during power ascensions and take appropriate corrective actions as required. Contact the Predictive Maintenance Group for additional guidance.

[47.1] IF returning to this step from AOl-I 1, Loss of Condenser Vacuum, ENSURE Operations manager approval is obtained prior to increasing load.

SRO determines that this step is not applicable.

[47.2] (p) PUSH GO button.

[47.3] MONITOR Generator Megawatts RISING.

[47.4] CHECK that load rise has STOPPED when reference display equals setter OR IF desired to stop the load RO change, THEN STOP the load change by depressing the HOLD pushbutton BOP monitors load rise and checks that the load change stops when the REFERENCE and SETTER displays are matched.

[47.5] WHEN desired to resume the load change, THEN (p)

PRESS the GO push button and CONTINUE to monitor load.

Given a LOAD ESCALATION rate of 10% in one hour, the steps will be repeated approximately once every 6 minutes.

NOTE Guidance given in 1-PI-OPS-1-MCR, Plant Instruction - Main Control Room, should be used for Reactor power indication.

[47.6] MONITOR NIS, AT and ICS calorimetric computer points RO as applicable.

NOTE Operation with the VALVE POS LIMIT light LIT is NOT desired. However, operation with VALVE POS LIMIT light LIT is acceptable if unsatisfactory load swings are experienced.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario# 7 Event# 1 Page 5 of 50 Event

Description:

Continue power escalation to 95% using GO-4, Normal Power Operations.

Time .

Position Applicants Actions or Behavior

[48] IF desired to place Turbine on the Valve Position Limiter, as the unit approaches full power, and Turbine load set for 100%

power, THEN

[48.1] SLOWLY and CAUTIOUSLY PULSE the VALVE BOP POSITION LIMIT in the LOWER direction while monitoring Megawatts for a drop and the VALVE POS LIMIT light to ILLUMINATE

[48.2j WHEN VALVE POS LIMIT light ILLUMINATES, THEN STOP limiter adjustment.

Cue Console Operator to insert Event 2.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: 2 Scenario # 7 Event # 2 Page 6 of 50 Event

Description:

l-LT-3-106, SG 4 LEVEL fails high. Requires a Tech Spec evaluation.

Time 1 Position Applicants Actions or Behavior Indications:

ARI-119B SG 4 LEVEL HI-HI.

l-LI-3-106, SG 4 LEVEL indicator off-scale high.

Redundant SG 4 level channels (1 -LI-3-1 07 and 1 -LI-3-1 10) indicate normal level (approximately 60%).

Diagnoses and announces the failure of 1-LI-3-106, SG 4 LEVEL BOP high.

SRO Enters and directs actions of ARI 119-B SC 4 LEVEL HI-HI.

ARI 119-B The following actions are taken from ARI-119B SG 4 LEVEL HI-HI.

NOTE Hi-Hi SG level sensed by 2/3 LS will initiate a Turbine Trip and Feedwater Isolation.

[1] CHECK SG level on 1-LI-3-106, 1-LI-3-107 and 1-LI-3-110

[1-M-4].

BOP BOP observes 1-LI-3-106, 1-LI-3-107 and 1-LI-3-11O and determines that 1-Ll-3-106, SG 4 LEVEL has failed high.

[2] IF level is high, THEN:

[2.1] IF power is less than 50%, THEN ENSURE Turbine Trip and Feedwater Isolation AND GO TO AOl-I 7, TURBINE TRIP. [0.1]

BOP [2.2] IF power is greater than or equal to 50%, THEN ENSURE Reactor Trip AND GO TO E-0, REACTOR TRIP OR SAFETY INJECTION. [C.1]

Based on redundant indicators, the BOP determines that actual SG 4 level is NOT high and that actions to remove the unit from service are NOT warranted.

[3] IF instrument failure, THEN:

[3.1] REFER TO Tech Specs.

3.3.1, Reactor Trip System (RTS) Instrumentation Function 13, SG Water Level Low-Low, Condition U, With one SRO Steam Generator Water Level Low-Low channel inoperable, place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND for the effected protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR be in Mode 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: 2 Scenario # 7 Event # 2 Page 7 of 50 Event

Description:

1-LT-3-106, SG 4 LEVEL fails high. Requires a Tech Spec evaluation.

Time Position Applicants Actions or Behavior

[3.1] REFER TO Tech Specs.(continued from previous page.)

3.3.2, ESFAS Instrumentation.

Function 5. b SG Water Level High-High (P-14), Condition I With one Steam Generator Water Level-High High channel inoperable, place the channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR be in Mode 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND be in Mode 4 within 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months .

Function 6. b SG Water Level Low-Low, Condition M, With one Steam Generator Water Level--Low--Low channel inoperable, Place the channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND for the effected protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR be in Mode 3 within 78 SRO hours AND be in Mode 4 within 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months .

3.3.3, PAM Instrumentation Function 15, Steam Generator Water Level (Narrow Range)

Condition A One or more Functions with one required channel inoperable, restore required channel to OPERABLE STATUS within 30 days.

[3.2] NOTIFY Work Control to initiate action to remove affected RPS Channel from service.

When the SRO contacts Work Contro4 the Console Operator repeats back the request to remove the 1-LT-3-106, SG 4 LEVEL from service.

EXAMINER: The crew briefing is optional. The next event may be entered prior to the brief.

Crew Brief would typically be conducted for this event as time allows SRO prior to the next event.

Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.

SRO Operations Management Typically Shift Manager.

Maintenance Personnel Typically Work Control Center (WCC).

(Note: Maintenance notification may be delegated to the Shift Manager).

Cue Console Operator to insert Event 3, if not already entered.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 3 Page 8 of 50 Event

Description:

1 B #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOl-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a rapid load reduction.

Time Position Applicants Actions or Behavior Indications:

14-D M-1 THRU M-6 MOTOR OVERLOAD 14-E M-1 THRU M-6 MOTOR TRIPOUT 29-E #3 HD TANK LEVEL HI/LO 30-E #3 HD TANK BYP TO CONDENSER OPEN BOP Diagnoses and responds to the trip of I B #3 Heater Drain pump.

May place 1-HS-6-122A, #3 HEATER DRAIN PMP C in STOP, BOP PULL-TO-LOCK when the WHITE overload light is LIT.

BOP May dispatch an AUO to monitor #3 Heater Drain tank level.

May dispatch an AUO to the I B #3 Heater Drain Tank pump to BOP determine status of the pump.

Enters and directs actions of AOl-37, Turbine Runback Response, SRO Section 3.2, #3 HDT High Level or Low Pump Flow.

The following actions are taken from AOI-37, Turbine Runback AOI-37 Response, Section 3.2, #3 HDT High Level or Low Pump Flow.

1. MONITOR turbine runback annunciator:

[28-El TURBINE RUNBACK BOP is DARK.

BOP BOP confirms that wIndow 28-E TURBINE RUNBACK BOP is DARK.

2. CHECK #3 HDT flow less than 10,000 GPM.

BOP BOP reports 1-FR-6-107, HTR DR PMPS FLOW RED pen indicates less than 10,000 gpm flow.

3. CHECK turbine load above 1000 MW (85%) turbine load.

BOP BOP reports turbine load is greater than 1000 MW as indicated by 1-EI-57-16A, MEGAWATTS.

4. MAINTAIN SG levels on program or trending toward program BOP levels.

BOP reports SG levels are on program.

5. MONITOR Feedwater pump suction pressure greater than 250 psig.

BOP BOP reports 1-Pl-2-129, MFW PMPS SUCT PRESS stable above 250 psig.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 3 Page 9 of 50 Event

Description:

1 B #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOl-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a rapid load reduction.

L Time Position Applicants Actions or Behavior j

6. DISPATCH operator(s) to assess #3 HDT and pump status.

When the BOP dispatches AUOs to assess #3 HDT the Console Operator will call up THUNDER VIEW screen fw6 and reports #3 HDT levels.

When the BOP dispatches an AUO to the lB #3 HDT pump, the Console Operator will report that the pump bearings are very hot.

BOP When the BOP dispatches an AUO to the lB 6.9 KV Unit Board to check the breaker for the lB #3 HDT pump, the Console Operator will report either:

If the pump tripped that the breaker tripped on instantaneous overcurrent OR If the BOP stopped the lB #3 HDT pump manually, the Console Operator will report that no relays have been actuated.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 3 Page 10 of 50 Event

Description:

1 B #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOI-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a rapid load reduction.

[ Time Position Applicants Actions or Behavior

7. INITIATE a manual boration:

a. DETERMINE recommended boration flow rate and volume from Reactivity Briefing Sheet:

RO determines the recommended boration flow rate to be 40 gpm and the volume to add to be 341 gallons of boron.

b. INITIATE normal boration:

1) ADJUST BA flow controller, 1 -FC-62-1 39, to desired flow rate.

RO adjusts 1-FC-62-139 to the value corresponding to the flow rate for the selected load reduction rate.

2) ADJUST BA batch counter 1-FQ-62-139 to required quantity.

RO adjusts 1-FQ-62-139 BA BATCH COUNTER as follows:

1. Depresses and holds the black pushbutton.

RO 2. While holding the pushbutton, the applicant raises the red translucent cover.

3. While still holding the pushbutton, the applicant enters 000341 in the display.

4. While still holding the pushbutton, the applicant lowers the red translucent cover, and then releases the pushbutton.

3) PLACE mode selector 1-HS-62-140B to BOR.

RO rotates 1-HS-62-140B VCT MAKEUP MODE from AUTO to the right to BOR position.

4) (p) PLACE VCT makeup control 1 -HS-62-1 40A, to START.

RO rotates 1-HS-62-140A, VCT MAKEUP CONTROL to the right to the START position.

5) VERIFY desired boric acid flow indicated on 1-FI-62-139.

RO observes the appropriate flow rate on 1-Fl-62-139, BA TO BLENDER FLOW NOTE Condenser Backpressure limits may be displayed on CS, turn-on code AOl1 1.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 3 Page 11 of 50 Event

Description:

1 B #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOl-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a rapid load reduction.

Time Position Applicants Actions or Behavior

8. ESTABLISH a turbine load reduction, to less than or equal to 76% power, at a rate greater than or equal to 2%/rn in, and less than 5%/mm:

a. PLACE turbine in IMP IN.

b. SET a desired load in the SETTER with the REFERENCE CONTROL.

BOP depresses the reference control V (down) button to reduce the setter display to less than 80% load as directed by BOP the SRO.

c. SET the LOAD RATE at greater than or equal to 2%/rn in, and less than 5%/mm.

BOP selects the load reduction rate directed by the SRO using the LOAD RATE % PER MIN thumbwheel selector. It is expected that a load reduction rate of 2-4%/minute will be used..

d. DEPRESS GO pushbutton.

BOP depresses the REFERENCE CONTROL GO button.

9. MONITOR T-avg and T-ref:

RO T-avg trending to T-ref.

Mismatch less than 5°F.

NOTE Runback circuitry being armed may be verified on 1-L-262 on 1-PIS-47-13, HP TURBINE IMPULSE STEAM PRESSURE [7291T3J]. Pressure equivalent load is indicated on ICS point PO300A.

10. CONTINUE load reduction, if in progress, until one of the following is satisfied:

BOP

Turbine load is less than 1000 MW (85%). OR

Condensate and Feedwater parameters are acceptable to support unit operation at current power level.

BOP 11. STOP load reduction AND GO TO Step 13.

RO 13. ENSURE T-avg and T-ref within 3°F.

14. ENSURE at least two #3 HDT pumps RUNNING with adequate BOP flow to maintain S/G levels.

BOP reports that the IA and IC #3 HDT pumps are running.

15. MONITOR the following to determine if main turbine free of water induction:

FWHT level alarms.

BOP

Turbine vibration.

. Turbine Metal Temperature ICS points T2609A-T261 IA and T2060A-T2062A (turn-on code TURBM ET).

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 3 Page 12 of 50 Event

Description:

lB #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOl-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a rapid load reduction.

Time Position Applicants Actions or Behavior SRO 16. MONITOR AFD within the limits of LCO 3.2.3.

BOP 17. ENSURE SIG levels return to program.

18. DISPATCH personnel as necessary to check the following to determine cause of #3 HDT high level or low pump flow:

3 HDT level, flow & controls.

#2 FW heater level.

1-LCV-6-106A, #3 HDT level control [T2D1708 in valve pit].

1. 3 HDT pump cavitation control 1-HS-6-106A, NOT reset BOP [TI D/708 on west wall].

Personnel may have already been dispatched to monitor parameters related to the #3 HDT.

If the BOP dispatches additional personnel to monitor #2 feedwater heater levels, the Console Operator will repeat back the request The Console Operator will open INSIGHT file heaters and provide data as requested.

19. ENSURE condensate system pumps in service as unit load SRO requires:

REFER TO GO-4, Normal Power Operation

20. IF reactor power dropped by greater than or equal to 15% in one hour, THEN NOTIFY Chemistry to initiate power change SRO sampling requirements.

SRO determines that the power change was not sufficient to require power change sampling.

21. REFER TO SOI-5 & 6.01, Extraction Steam, Heater Drains, and BOP Vent System, to adjust #3 HDT LEVEL and reset pump cavitation control 1-HS-6-106A as necessary.

BOP 22. CHECK VALVE POS LIMIT light LIT.

23. RETURN valve position limiter to normal

a. ENSURE turbine in IMP OUT.

BOP b. (p) REDUCE turbine load using REFERENCE CONTROL V (lower) and GO button until VALVE POS LIMIT light not LIT.

c. RAISE valve position limiter to 95%.

24. ENSURE reset of C-7 BOP a. CHECK C-7 LOSS OF LOAD STM DUMP INTERLOCK annunciator LIT [66-El 24.a. RESPONSE NOT OBTAINED:

SRO GO TO Step 25

25. INITIATE repairs to failed equipment.

SRO When SRO contacts Work Control, the Console Operator will repeat back request to have a troubleshooting and repair package for the lB #3 HD pump.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event# 3 Page 13 of 50 Event

Description:

lB #3 HDT pump bearing seizes, causing a motor overload then a motor trip-out.

Requires entry into AOl-37, Turbine Runback Response, Section 3.2, #3 HDT High Level or Low Pump Flow. Requires a rapid load reduction.

Time Position Applicants Actions or Behavior SRO 26. RETURN TO instruction in effect.

EXAMINER: The crew briefing is optional. The next event may be entered prior to the brief.

Crew Brief would typically be conducted for this event as time allows SRO prior to the next event.

Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.

Operations Management Typically Shift Manager.

SRO Maintenance Personnel Typically Work Control Center (WCC).

(Note: Maintenance notification may be delegated to the Shift Manager).

Cue Console Operator to insert Event 4, if not already entered.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 4 Page 14 of 50 Event

Description:

1-PIC-68-340A, PZR PRESS MASTER CONTROL fails. Requires the RD to take IMMEDIATE OPERATOR ACTION to place i-PIC-68-340A, PZR PRESS MASTER CONTROL in MANUAL and restore pressure to normal. Requires entry into AOI-18,Malfunction of Pressurizer Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

Time Position Applicants Actions or Behavior Indications:

90-A PZR PRESS HI Diagnoses and announces the failure of i-PIC-68-340 PZR PRESS RD MASTER CONTROL Performs IMMEDIATE OPERATOR ACTIONS of AOl-I 8, RD Malfunction of Pressurizer Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

RD May enter and take actions of ARI 90-A, PZR PRESS Hi, Enters and directs actions of AOl-i 8, Malfunction of Pressurizer SRO Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

ARI 90-A The following actions are taken from ARI 90-A PZR PRESS HI.

CAUTION Reactor trip will occur at 2385 psig on 2/4 PZR pressure switches. Status of these switches is on 1-)(X-55-6A, Reactor Trip Si Status Panel.

NOTE Variable heaters turn off when PZR pressure is greater than 2250 psig. Spray valves start to open at 2260 psig and are full open at 2310 psig.

[1] CHECK PZR pressure on 1-Pl-68-334 and 1-Pl-68-340 RO

[1 -M-5].

[2] IF a PZR pressure channel has failed, THEN:

[2.1] PLACE PZR master controller 1-PIC-68-340A in manual RD control and stabilize pressure.

[2.2] GO TO AOl-i 8.

The following actions are taken from AOl-I 8, Malfunction of AOI-18 Pressurizer Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

EXAMINER: With the output of the 1-PIC-68-340A, PZR PRESS MASTER CONTROL failed, actual pressure will be dropping. The applicants will enter LCO 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits when pressure drops below 2214 psig, and exit when pressure returns above 2214 psig.

NOTE Step I is an IMMEDIATE ACTION step.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 4 Page 15 of 50 Event

Description:

1-PIC-68-340A, PZR PRESS MASTER CONTROL fails. Requires the RO to take IMMEDIATE OPERATOR ACTION to place 1.-PIC-68-340A, PZR PRESS MASTER CONTROL in MANUAL and restore pressure to normal. Requires entry into AOI-18,Malfunction of Pressurizer Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

Time Position Applicants Actions or Behavior

1. CHECK PZR pressure STABLE or TRENDING to desired RO pressure:

RO reports that PZR pressure was dropping initially.

1. RESPONSE NOT OBTAINED:

PLACE PZR master controller 1-PIC-68-340A in MANUAL and RO RESTORE press to normal.

RO reports that 1-PIC-68-340A has been placed in MANUAL as part of the IMMEDIATE ACTION.

2. ENSURE 1..XS-68-340D selected to OPERABLE channels for control and backup:

PT-68-340 & 334 OR RO

PT-68-334 & 323 OR

PT-68-340 & 322 RO reports that all PZR PRESS channels are OPERABLE.

3. CHECK PZR press STABLE or RISING.

RO RO reports current condition of PZR pressure, either as STABLE or RISING.

4. DETERMINE if PZR heaters and sprays are operating properly:

a. CHECK master control controlling sprays and heaters.

RO RO may report that 1-PIC-68-340A, PZR PRESS MASTER CONTROL is controlling in MANUAL.

b. CHECK PZR press greater than 2250 psig.

4.b RESPONSE NOT OBTAINED:

RO WHEN PZR press is greater than 2250 psig, THEN PERFORM Step 4.c.

c. ENSURE all PZR heaters OFF RO

d. ENSURE PZR sprays maintain RCS press on program.

5. ENSURE operable channel selected for recording with 1-XS RO 340B.

RO reports that all PZR PRESS channels are OPERABLE.

6. ENSURE TR-68-2A placed to operable channel using 1-XS RO 28, T RCDR TR-68-2A LOOP SELECT [1-M-5}.

RO reports that all PZR PRESS channels are OPERABLE.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: 2 Scenario# 7 Event# 4 Page 16 of 50 Event

Description:

1-PIC-68-340A, PZR PRESS MASTER CONTROL fails. Requires the RO to take IMMEDIATE OPERATOR ACTION to place 1-PIC-68-340A, PZR PRESS MASTER CONTROL in MANUAL and restore pressure to normal. Requires entry into AOl-i 8,Malfunction of Pressurizer Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

Time Position Applicants Actions or Behavior

7. CHECK PZR level at or trending to PROGRAM.

RO RO reports that PZR level is on program.

8. NOTIFY Work Control to remove any failed channel from service and repair any failed controllers.

SRO SRO determines that there is no failed channel to remove from service, but may contact Work Control to repair the failed controller.

9. WHEN pressurizer pressure stable and equipment status supports returned to normal, THEN ENSURE the following in AUTO:

SRO

PZR Master controller

PZR spray controllers

All heater groups EXAMINER: Since 1-PIC-68-340, PZR PRESS MASTER CONTROL has failed LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits will be entered during the initial response of the system to the failure, and then exited when PZR pressure is returned above 2214 psig.

10. REFER TO the following Tech Specs:

3.3.1, RTS Instrumentation Not applicable

3.3.2, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Not applicable

3.3.4, Remote Shutdown System Not applicable

3.4.1, RCS Pressure, Temperature, and Flow Departure from SRO Nucleate Boiling (DNB) Limits See NOTE above.

3.4.3, RCS Pressure and Temperature (PIT) Limits Not -

applicable

3.4.9, Pressurizer Not applicable

3.4.10, Pressurizer Safety Valves Not applicable 3.4.11, Pressurizer Power -Operated Relief Valves Not -

applicable

11. INITIATE repairs to failed equipment.

When SRO contacts Work Control, the Console Operator will SRO repeat back request to have a troubleshooting and repair package made up for 1-PIC-68-340, PZR PRESS MASTER CONTROL.

SRO 12. RETURN TO Instruction in effect.

EXAMINER: The crew briefing is optional. The next event may be entered prior to the brief.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ESD-2 OpTestNo.: 2 Scenario# 7 Event# 4 Page 17 of 50 Event

Description:

1-PIC-68-340A, PZR PRESS MASTER CONTROL fails. Requires the RO to take IMMEDIATE OPERATOR ACTION to place 1-PIC-68-340A, PZR PRESS MASTER CONTROL in MANUAL and restore pressure to normal. Requires entry into AOl-i 8,Malfunction of Pressurizer Pressure Control System, Section 3.1, Pressure Transient Due to Instrument or Controller Malfunction.

Time Position N Applicants Actions or Behavior Crew Brief would typically be conducted for this event as time allows SRO prior to the next event.

Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.

Operations Management Typically Shift Manager.

SRO Maintenance Personnel Typically Work Control Center (WCC).

(Note: Maintenance notification may be delegated to the Shift Manager).

Cue Console Operator to insert Event 5, if not already entered.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: 2 Scenario # 7 Event # 5 Page 18 of 50 Event

Description:

lA-A CCS pump shaft shears and 1 B-B CCS pump fails to start automatically.

Requires entry into AOl-i 5, Loss of Component Cooling Water (CCS). Requires the BOP to manually start the 1 B-B CCS pump. Requires a Tech Spec evaluation.

Time It Position IL Applicants Actions or Behavior Indications:

Multiple alarms on panel i-M-27B related to Component Cooling Water flow on Train A.

Diagnoses and announces the failure of the lA-A CCS pump to BOP pump forward.

May place 1-HS-70-46A, CCS PMP lA-A in the STOP, PULL-TO-BOP LOCK position.

May place i-HS-70-38A, CCS PMP lB-B in the START position, BOP since the automatic start on low header pressure failed.

Enters and directs actions of AOl-i 5, Loss of Component Cooling SRO Water (CCS), Section 3.2, Loss of CCS flow.

The following actions are taken from AOl-I 5, Loss of Component Cooling Water (CCS), Section 3.2, Loss of CCS flow.

1. CHECK CCS pumps status:

a. CHECK any CCS pump TRIPPED or running pump NOT pumping forward:

ERCW/CCS Motor tripout alarm, BOP

Low header pressure (Train A or B),

Multiple low flow alarms.

BOP determines that the IA-A CCS pump is no longer pumping forward.

b. CHECK at least one U-i Train A header supply pump RUNNING AND pumping forward:

BOP BOP determines that there is NO U-I Train A pump running and the SRO enters stepl.b RNO.

Critical Task I Manually start the lB-B Component Cooling Water (CCS) pump within 10 minutes of the trip of the IA-A Component Cooling Water (CCS) pump to establish Reactor Coolant pump oil cooling.

Critical 1 .b. RESPONSE NOT OBTAINED:

Task I START available U-i Train A CCS pump.

BOP BOP rotates handswitch I-HS-70-38A, CCS PMP lB-B to the S TART position and verifies that IA CCS header pressures and flows return to normal.

2011-10 Watts Bar NRC Examination

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 5 Page 19 of 50 Event

Description:

lA-A CCS pump shaft shears and lB-B CCS pump fails to start automatically.

Requires entry into AOl-I 5, Loss of Component Cooling Water (CCS). Requires the BOP to manually start the I B-B CCS pump. Requires a Tech Spec evaluation.

Time I Position Applicants Actions or Behavior

c. CHECK any Train B header supply pump RUNNING AND pumping forward:

. C-s

2B-B BOP reports the C-S CCS pump is running and pumping forward.

d. PLACE any non-operable or tripped CCS pump in STOP/PULL TO-LOCK.

BOP If not already performed the BOP places 1-HS-70-46A, CCS PMP IA in the STOP, PULL-TO-LOCK position.

e. CHECK TWO U-i Train A header supply pumps RUNNING:

BOP BOP reports that only one Train A pump is running.

e. RESPONSE NOT OBTAINED:

ENSURE at least one of the following CLOSED to avoid excessive flow:

RHR HX A, 1-FCV-70-156, BOP OR

SEP HX A, O-ECV-70-197.

BOP reports that I-HS-70-156A, RHR HX IA OUTLET is CLOSED.

f. CHECK flows returned to NORMAL.

BOP BOP reports that low flow alarms are clear on the CCS annunciator panel.

g. CHECK A and B side Surge Tank levels between 57% and 85%.

BOP BOP reports A and B side Surge Tank levels approximately 70%.

BOP h.GOTOStepi5.

EXAMINER: AOI-15, Loss of Component Cooling Water (CCS), Appendix A, Header Cross-Reference, is contained as Attachment 1.

15. EVALUATE affected equipment operation USING Appendix A.

SRO SRO may direct BOP to perform Appendix A, Header Cross-Reference.

2011-10 Watts Bar NRC Examination

rAppendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 5 Page 20 of 50 Event

Description:

iA-A CCS pump shaft shears and lB-B CCS pump fails to start automatically.

Requires entry into Aol-i 5, Loss of Component Cooling Water (CCS). Requires the BOP to manually start the 1 B-B CCS pump. Requires a Tech Spec evaluation.

Time I Position Applicants Actions or Behavior

16. WHEN CCS returned to normal, THEN:

CHECK only one CCS pump per Train.

CHECK one TBBP running.

BOP places either 1-HS-60-131A, THRM BAR BSTR PMP IA SRO (TBBP) or 1-HS-70-130A, THRM BAR BSTR PMP lB (TBBP) in STOP and then PULL A-P AUTO.

BOP ensures that the running pump (1-HS-60-131A, THRM BAR BSTR PMP IA (TBBP) or 1-HS-70-130A, THRM BAR BSTR PMP lB (TBBP)) is in the PULL A-P AUTO position.

17. REFER TO Tech Spec 3.7.7, Component Cooling Water System (CCS).

SRO LCO 3.77, Component Cooling Water System (CCS), Condition A, With one CCS train inoperable, restore CCS train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

18. NOTIFY Work Control to initiate repairs.

When SRO contacts Work Control, the Console Operator will SRO repeat back the request to have a troubleshooting and repair package made up for the failure of the IA-A CCS pump shaft, and for the failure of the low pressure signal to start the lB-B CCS pump.

19. WHEN repairs are complete, THEN:

a. ENSURE 1-HS-70-63A, Ui SURGE TANK MAKEUP LCV in P-AUTO.

b. ENSURE CCS, CVCS, CS, RHR and SI pumps are returned to normal alignment USING the following Instructions:

SRO

S0l-70.01, Component Cooling Water (CCS).

. SOI-62.01, CVCS - Charging and Letdown.

SOl-72.01, Containment Spray System.

SO 1-74.01, Residual Heat Removal System.

. SOI-63.01, Safety Injection System.

SRO 20. RETURN TO Instruction in effect.

EXAMINER: The crew briefing is optional. The next event may be entered prior to the brief.

Crew Brief would typically be conducted for this event as time allows SRO prior to the next event.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 5 Page 21 of 50 Event

Description:

lA-A CCS pump shaft shears and 1 B-B CCS pump fails to start automatically.

Requires entry into AOl-15, Loss of Component Cooling Water (CCS). Requires the BOP to manually start the I B-B CCS pump. Requires a Tech Spec evaluation.

Time L Position Applicants Actions or Behavior Notificafions should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.

Operations Management Typically Shift Manager.

SRO Maintenance Personnel Typically Work Control Center (WCC).

(Note: Maintenance notification may be delegated to the Shift Manager).

Cue Console Operator to insert Event 6, if not already entered.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 6 Page 22 of 50 Event

Description:

An RCS leak (approximately 30 gpm) develops. Requires entry into AOl-6, Small Reactor Coolant System Leak. Leak worsens when the crew realigns charging and letdown per AOl-6.

Time Position Applicants Actions or Behavior Indications:

144-A, ICE COND INLET DOOR OPEN 103-B, CNTMT MOISTURE HI VCT level trend indicates a reduction in level PZR level trend indicates a reduction in level Charging-Letdown mismatch indicates that charging flow is rising Containment Radiation monitors indicate a rising trend.

Containment pressure is slowly rising.

RO Diagnoses and announces the RCS leak into containment.

May place 1-HIC-62-93A, CHARGING FLOW PZR LEVEL RD CONTROL in MANUAL and raise charging flow.

May adjust 1-HIC-62-89 to adjust RCP seal injection flow after RD adjusting 1 -HIC-62-93.

Enters and directs actions of AOl-6, Small Reactor Coolant System SRO Leak.

The following actions are taken from AOl-6, Small Reactor AOI-6 Coolant System Leak.

NOTE During performance of this instruction the need for rapid load reduction or Unit trip should be continuously evaluated.

RD 1. CHECK CCP in service.

2. ADJUST 1 -FCV-62-89 AND 1 -FCV-62-93 as necessary to RD maintain pzr level on program.

RO may have taken actions to maintain PZR level on program.

RD 3. CHECK letdown flow in service for 75 gpm.

4. INCREASE VCT Auto makeup:

a. DOUBLE setting on Boric Acid and PW water flow controllers

1-FC-62-142 RO doubles the PW setting from 35% to 70% on 1-FC-62-142.

RO

1-FC-62-139 RO doubles the current BA setting from on 1-FC-62-139.

b. ENSURE RED light lit on 1-HS-62-140A.

RO observes 1-HS-62-140A, MAKEUP CONTROL RED indicating light is LIT and GREEN indicating light is DARK.

SRO 5. CHECK in Modes 1 through 3 2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 6 Page 23 of 50 Event

Description:

An RCS leak (approximately 30 gpm) develops. Requires entry into AOI-6, Small Reactor Coolant System Leak. Leak worsens when the crew realigns charging and letdown per AOl-6.

Time Position Applicants Actions or Behavior NOTE Pzr level must be allowed time to change following changes in charging flow.

6. MONITOR the following parameters:

Pzr level STABLE or RISING.

RO

Containment pressure STABLE or DROPPING.

RCS pressure STABLE or RISING.

6. RESPONSE NOT OBTAINED:

IF any of the following occur:

Loss of pzr level is IMMINENT,

Containment pressure is approaching 1 .5 psig.

BOP

RCS pressure is approaching 1970 psig (dropping),

THEN 1)(p)TRIP Rx.

2) INITIATE SI.

3) ** GO TO E-0, Rx Trip or Safety Injection.

7. CHECK secondary plant radiation NORMAL:

Condenser exhaust monitors.

SRO

S/G blowdown monitors.

Main steam line monitors.

8. MAKE plant announcement via PA:

SRO Attention plant personnel. A primary system leak has developed.

Any personnel located either inside containment or in the Auxiliary Building should exit the area immediately. (Repeat)

CAUTION Attempts to quantify leak rate should not delay performance of the remaining steps.

NOTE Appendix B may be used to estimate RCS leak rate.

9. INITIATE leak rate estimate:

a. STOP any heatup/cooldown in progress.

SRO

b. ADJUST charging flow to STABALIZE pzr level.

c. CHECK Net Charging on ICS (UF1 016)

10. CHECK safety valves CLOSED:

EVALUATE tailpipe temp and acoustic monitors.

RO RO observes stable temperature for safety valves on 1-Tl 330, 1-TI-68-329 andl-Tl-68-328.

2011-10 Watts Bar NRC Examination

I Appendix D Required Operator Actions Form ESD-2 OpTestNo.: 2 Scenario # 7 Event # 6 Page 24 of 50 Event

Description:

An RCS leak (approximately 30 gpm) develops. Requires entry into AOl-6, Small Reactor Coolant System Leak. Leak worsens when the crew realigns charging and letdown per AOl-6.

Time I Position I Applicants Actions or Behavior 11 CHECK PORVs CLOSED:

EVALUATE tailpipe temp and acoustic monitors.

RO RO observes stable temperature on 1-TI-68-331, PORV334A &

334 TAILPIPE TEMP.

NOTE Relief valves (pzr PORVs, pzr safeties, CVCS letdown, RHR suction, and SI lines), and Rx head vent isolation valves could be leaking to the PRT. Further investigation will have to be made if PRT conditions become abnormal and leakage path is not readily identifiable.

12. MONITOR PRT conditions NORMAL:

Level.

SRO

Temperature.

Press.

NOTE If leak is on CVCS, pzr level should begin rising with charging and letdown isolated. Appendix B can be used to verify small leaks are isolated.

13. ISOLATE letdown:

CLOSE 1..FCV-62-72, (45 gpm).

CLOSE 1-FCV-62..73, (75 gpm).

CLOSE 1-FCV-62-74, (75 gpm).

RO rotates 1-HS-62-74A, LETDOWN ORIFICE C 75 GPM CIV-bA to the left to the CLOSE position.

RD

CLOSE 1-FCV-62-76, (5 gpm).

CLOSE 1-FCV-62-69.

RO rotates 1-HS-62-69A, RCS LETDOWN FRM LOOP 3 IN CNTMT to the left to the CLOSE position.

CLOSE 1-FCV-62-70.

RO rotates 1-HS-62-70A, RCS LETDOWN FRM LOOP 3 IN CNTMT to the left to the CLOSE position.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: 2 Scenario # 7 Event # 6 Page 25 of 50 Event

Description:

An RCS leak (approximately 30 gpm) develops. Requires entry into AOl-6, Small Reactor Coolant System Leak. Leak worsens when the crew realigns charging and letdown per AOl-6.

Time Position Applicants Actions or Behavior

14. ISOLATE charging:

CLOSE 1-FCV-62-85.

CLOSE l-FCV-62-86.

RO rotates 1-HS-62-86, ALT CHARGING LINE TO LOOP 4 to the left to the CLOSE position.

RO

CLOSE 1-FCV-62-90.

RO rotates 1-HS-62-90, CHARGING LINE ISOL to the left to the CLOSE position.

CLOSE I -FCV-62-91.

RO rotates 1-HS-62-91, CHARGING LINE ISOL to the left to the CLOSE position.

NOTE Normal range of seal injection flow is between 8 and 13 gpm per RCP with a minimum allowed flow of 6 gpm.

15. MINIMIZE RCP seal injection flow (greater than 6 gpm per SRO pump), and EVALUATE pzr level trend.

NOTE Pzr level must be allowed time to change following changes in charging flow.

EXAMINER: When Step 15 has been accomplished, the Console Operator will increase the severity of the leak from 1.75% to 17.5%. The applicants are expected to perform Step 6 RNO actions to trip the reactor and initiate a safety injection signal based on IMMINENT LOSS of PZR level.

6. RESPONSE NOT OBTAINED:

IF any of the following occur:

Loss of pzr level is IMMINENT,

. Containment pressure is approaching 1 .5 psig.

BOP

RCS pressure is approaching 1970 psig (dropping),

THEN

1) (p)TRIP Rx.

2) INITIATE SI.

3) ** GO TO E-0, Rx Trip or Safety Injection.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event# 7 and 8 Page 26 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-O, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for l-FCV-62-73.

Time Position Applicants Actions or Behavior The following actions are taken from E-O, Reactor Trip or Safety Injection.

NOTE Steps 1 thru 4 are IMMEDIATE ACTION STEPS.

Status Trees I SPDS should be monitored when transitioned to another instruction.

1. ENSURE reactor trip:

Reactor trip and bypass breakers OPEN.

RO checks 1-52RTB, RX TRIP BKR A GREEN indicating light LIT on panel 1-M-4.

RO checks l-52RTB, RC TRIP BKR B GREEN indicating light LIT on panel 1-M-4 RO checks 1-52BYA, BYPASS BKR A lights DARK RO checks 1-52BYB, BYPASS BKR B lights dark RO

RPls at bottom of scale.

RO observes 1-MON 85 5000/1 CERPI Monitor I and 1-MON-85 5000/2 CERPI MONITOR 2 for indication that all SHUTDOWN and CONTROL bank rods are inserted.

Neutron flux DROPPING.

RO observes neutron flux trending down on 1-NR-92-145, NEUTRON FLUX LEVEL RECORDER. May also observe levels decreasing on 1-Nl-92-135A, CH I NEUTRON MON % PWR, and 1-Nl-92-136A, CH II NEUTRON MON % PWR.

2. ENSURE Turbine Trip:

All turbine stop valves CLOSED.

RO RO observes that indicating lights on 1-XX-47-1000 EHC CONTROL for individual throttle and governor valves are GREEN.

3. CHECK 6.9 kV shutdown boards:

a. At least one board energized from:

RO CSST (offsite),

OR DIG (blackout).

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 27 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1 Loss of Reactor or Secondary Coolant. 1 A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior

4. CHECK SI actuated:

a. Any SI annunciator LIT.

RO will announce that the window 70-A, SI ACTUATED is LIT. May RO also announce that FIRST OUT 76-G SI MANUAL is LIT.

b. Both trains SI ACTUATED.

1 -XX-55-6C

1 -XX-55-6D EXAMINER: E-O, Reactor Trip or Safety Injection, Appendixes A arid B are included as Attachment 2.

5. PERFORM Appendixes A and B, E-O, pages 16-30.

BOP BOP is assigned to perform actions contained in the Appendices.

A separate copy of the Appendices is contained in this package for Examiner use.

SRO 6. ANNOUNCE reactor trip and safety injection over PA system.

7. ENSURE secondary heat sink available with either:

Total AFW flow greater than 410 gpm, OR RO It is expected that Adverse Containment (>2.81 psig) conditions will exist soon after the entry into E-0. When announced, the crew will use the bracketed parameter values.

At least one SIG NR level greater than 29% [39% ADV].

8. MONITOR RCS temperature stable at or trending to 557°F using:

RCS Loop T-avg with any RCP running, RO OR

RCS Loop T-cold with RCPs out-of-service.

8. RESPONSE NOT OBTAINED:

IF temp less than 557°F, THEN ENSURE steam dumps and SIG PORVs CLOSED.

IF cooldown continues, THEN CONTROL total AFW flow to maintain greater than 410 gpm UNTIL NR level in at least one SIG greater than 29% [39% ADV].

IF cooldown continues after AFW flow is controlled, THEN

PLACE steam dump controls OFF.

CLOSE MSIVs.

ENSURE MSIV bypasses CLOSED.

IF RCS temp greater than 564°F, THEN ENSURE either steam dumps or SIG PORVs OPEN.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 28 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety lnjecton, and a transition to E-1 Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior

9. ENSURE excess letdown valves CLOSED:

1 -FCV-62-54 RO

1 -FCV-62-55 RO observes GREEN indicating lights LIT on handswitches 1-HS-62-54A, EXCESS LTDN ISOL, and 1-HS-62-55A, EXCESS LTDN.

10. CHECK pzr PORVs and block valves:

a. Pzr PORVs CLOSED.

b. At least one block valve OPEN.

RO observes 1-HS-68-340AA, PZR PORV34OA, CLOSED, GREEN indicating light is LIT;, RED indicating light is DARK.

RO RO observes 1-HS-68-334A, PZR PORV 334, CLOSED, GREEN indicating light is LIT;, RED indicating light is DARK.

RO observes 1-HS-68-333A, BLOCK VLVFOR PORV34OA, OPEN, GREEN indicating light is DARK, RED indicating light is LIT.

RO observes 1-HS-68-332A, BLOCK VLVFOR PORV 334, OPEN, GREEN indicating light is DARK, RED indicating light is LIT.

11. CHECK pzr safety valves CLOSED:

EVALUATE tailpipe temperatures and acoustic monitors.

RO observes response of 1-TI-68-330, SAFETY 68-563 TAILPIPE RO TEMP. 1-TI-68-329, SAFETY 68-564 TAILPIPE TEMP, and 1-TI 328, SAFETY 68-565, stable at approximately 110 F.

BOP may observe 1-XI-68-363, PZR VALVES ACOUSTIC MONITOR indicating lights are DARK for 1-XI-68-363 (68-563), 1-Xl-68-364 (68-564) and 1-XI-68-365 (68-565

12. CHECK pzr sprays CLOSED.

RO RO observes the pzr spray valves closed by GREEN indicating lights LIT for 1-Xl-68-340B, PZR SPRAYLOOP 2 and 1-Xl 340D, PZR SPRAY LOOP 1.

NOTE Seal injection flow should be maintained to all RCPs.

13. CHECK if RCPs should remain in service:

The RCPs may have been tripped prior to reaching this step in RO E-0, due to the actuation of the Containment Phase B signal.

a. Phase B signals DARK [MISSP].

b. RCS pressure greater than 1 500 psig.

2011-10 Watts Bar NRC Examination

I Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 29 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1 -FCV-62-73.

Time Position Applicants Actions or Behavior

14. CHECK SIG pressures:

All SIG pressures controlled or rising.

RO observes PAM pressure instruments on SG I through 4 (black labels) and determines that pressures are controlled. May also RD observe trends on 1-PR-1-2, SG I & 2 PRESS PSIG, and 1-PR-I-23, SG 3 & 4 PRESS PSIG to assess this step.

All SIG pressures greater than 120 psig.

RO observes PAM pressure instruments on SG I through 4 (black labels) and determines that pressures are greater than 120 psig.

15. CHECK for RUPTURED SIG

All SIGs narrow range levels CONTROLLED or DROPPING.

RO informs the SRO that SIG narrow range levels are controlled after observing PAM narrow range level instruments (black RD labels).

Secondary side radiation NORMAL from Appendix A.

BOP informs the SRO that secondary radiation levels are normal after performing Appendix A, Step 8.

16. CHECK cntmt conditions:

Cntmt pressure NORMAL.

RO reports containment pressure is abnormally high.

Radiation NORMAL from Appendix A.

BOP BOP in forms the SRO that containment radiation recorders were not normal prior to isolation.

Cntmt sump level NORMAL.

Cntmt temp ann window DARK [104-B].

SRO enters RESPONSE NOT OBTAINED column.

16. RESPONSE NOT OBTAINED:

SRO **

GO TO E-1, Loss of Reactor or Secondary Coolant.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 30 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation ofswapoverfor l-FCV-62-73.

Time Position Applicants Actions or Behavior EXAMINER: During the performance of E-1, Loss of Reactor or Secondary Coolant, entry conditions for FR-P.1, Pressurized Thermal Shock, and FR-C.2, Degraded Core Cooling, will be met. FR-C.2, Degraded Core Cooling, actions are contained on Pages 35 through 39 of 44. FR-P.1, Pressurized Thermal Shock, actions are contained on Page 40 of 44.

The following actions are taken.from E-1, Loss of Reactor or Secondary Coolant.

EXAMINER: As the RCS leak becomes larger, containment temperature and pressure will rise sharply. 265-A UPPER CNTMT RE-2711272 RAD HI and 265-B LOWER CNTMT RE-2731274 are expected to alarm, since testing has shown rad monitor to give unreliable indication for up to 2 minutes following a rapid increase or decrease in containment temperature. The alarms will clear after the initial temperature transient.

NOTE Seal injection flow should be maintained to all RCPs.

EXAMINER: The RCPs may have been stopped previously.

1. CHECK if RCPs should remain in service:

RD

a. Phase B DARK [MISSPJ.

1. a. RESPONSE NOT OBTAINED RD

a. STOP all RCPs. ** GO TO Step 2.

SRO 2. REFER TO EPIP-1, Emergency Plan Classification Flowchart.

NOTE Time since initiation of event is defined by performance of Step 3.

3. RECORD current time to mark initiation of LOCA and determination SRO of time for hot leg recirc.

4. CHECK SIG pressures:

All SIG pressures controlled or rising.

RO obseries PAM pressure instruments on SG I through 4 (black labels) and determines that pressures are controlled. May also RD observe trends on 1-PR-I-2, SG I & 2 PRESS PSIG, and 1-PR-1-23, SG 3 & 4 PRESS PSIG to assess this step.

All S/G pressures greater than 120 psig.

RO observes PAM pressure instruments on SG I through 4 (black labels) and determines that pressures are greater than 120 psig.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario# 7 Event# 7and8 Page 31 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation ofswapoverfor 1-FCV-62-73.

Time Position Applicants Actions or Behavior

5. MAINTAIN Intact SIG NR levels:

a. MONITOR levels greater than 29% [39% ADVJ.

RO in forms the SRO that SIG narrow range levels are controlled after observing PAM narrow range level instruments (black BOP labels).

b. CONTROL intact SIG levels between 29% and 50% [39% and 50% ADVI.

RO acknowledges the need to control SG levels between 39 and 50%.

EXAMINER: The status of secondary radiation may have already been reported as normal by the BOP during performance of E-O Appendix A.

6. CHECK secondary radiation:

SIG discharge monitors NORMAL.

BOP

Condenser vacuum exhaust rad monitors NORMAL.

SIG blowdown rad monitor recorders NORMAL trend prior to isolation.

7. ENSURE cntmt hydrogen analyzers in service:

PLACE 1-HS-43-200A in ANALYZE [M-1Oj.

BOP places 1-HS-43-200A, H2ANALYZERA FAN to the ANALYZE position on panel 1-M-10.

PLACE 1-HS-43-210A in ANALYZE [M-10].

BOP places 1-HS-43-210A, H2 ANALYZER A FAN to the ANALYZE position on panel 1-M-10.

CHECK low flow lights NOT lit [M-1 01.

BOP BOP checks 1-Xl-43-200, LO FLOW- ANAL A, WHITE indicating light is DARK.

BOP checks 1-Xl-43-210, LO FLOW ANAL B, WHITE indicating light is DARK.

LOCALLY CHECK low analyzer temp lights NOT lit AND RESET local alarm panel. [North wall of Train A 480V SD Bd rm].

When contacted as the Control Building AUO the Console Operator repeat back request to check low analyzer temp lights, and reports that the lights are NOT LIT.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 32 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for I-FCV-62-73.

Time Position Applicants Actions or Behavior

8. MONITOR pzr PORVs and block valves:

a. Pzr PORVs CLOSED.

RO observes 1-HS-68-340AA, PZR PORV34OA, CLOSED, GREEN indicating light is LIT, RED indicating light is DARK.

RO observes 1-HS-68-334A, PZR PORV 334, CLOSED, GREEN RO indicating light is LIT, RED indicating light is DARK.

b. At least one block valve OPEN.

RO observes 1-HS-68-333A, BLOCK VLVFOR PORV34OA, OPEN, GREEN indicating light is DARK, RED indicating light is LIT.

RO observes 1-HS-68-332A, BLOCK VLVFOR PORV 334, OPEN, GREEN indicating light is DARK, RED indicating light is LIT.

EXAMINER: Containment pressure may not be below 2.0 psig when the operators evaluate this step initially. Since it is a continuous action step, when containment pressure does drop below 2.0 psig, the actions will be performed.

9. DETERMINE if cntmt spray should be stopped:

a. MONITOR cntmt pressure less than 2.0 psig.

b. CHECK at least one cntmt spray pump RUNNING.

SRO c. RESET cntmt spray signal.

d. STOP cntmt spray pumps, and PLACE in A-AUTO.

e. CLOSE cntmt spray discharge valves I-FCV-72-2 and 1-FCV 39.

9. a. RESPONSE NOT OBTAINED:

RO WHEN cntmt pressure is less than 2.0 psig, THEN PERFORM Sub steps 9b thru e.

10. ENSURE both pocket sump pumps STOPPED [M-15]:

1-HS-77-410.

BOP

1-HS-77-411.

BOP observes handswitch 1-HS-77-410, POCKET SUMP PMP A GREEN indicating light is LIT, and 1-HS-77-411, POCKET SUMP PMP B GREEN indicating light is LIT.

1 1. CHECK SI termination criteria:

a. CHECK RCS subcooling greater than 65°F [85°F ADV].

RO RO determines that subcooling is less than 85°F by observing 1-Tl-68-105, RCS SUBCOOLING and 1-XI-68-115 RCS SUB COOLING indicators.

a. RESPONSE NOT OBTAINED:

SRO **

GO TO Caution prior to Step 12.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 33 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1 -FCV-62-73.

Time Position Applicants Actions or Behavior CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.

12. RESET SI and CHECK the following:

RO resets SI signal by depressing 1-HS-63-134A, SI RESET TR A and 1-HS-63-134B one at a time.

SI ACTUATED permissive DARK.

RD RO observes and reports that Window 70-A, SI ACTUATED is DARK.

AUTO SI BLOCKED permissive LIT.

RO observes and reports that Window 70-B, AUTO SI BLOCKED is DARK.

13. DETERMINE if RHR pumps should be stopped:

a. CHECK RCS pressure greater than 150 psig.

RD

b. CHECK RHR suction aligned from RWST.

c. CHECK RCS pressure stable or rising.

c. RESPONSE NOT OBTAINED:

ENSURE CCS from RHR heat exchanger 1-FCV-70-153 and 1-FCV-70-156 OPEN.

BOP rotates 1-FCV-70-156 RHR HX IA OUTLET to the right to the OPEN position. Ensures RED indicating light is LIT and GREEN indicating light is DARK.

CLOSE SEP heat exchanger A CCS supply 0-FCV-70-1 97.

BOP rotates 0-FCV-70-197, SFP HXA SUPPLY to the left to the CLOSE position. Ensures RED indicating light is DARK and GREEN indicating light is LIT.

GO TO Step 14.

14. CHECK pressure in all S/Gs controlled or rising.

RO observes PAM pressure instruments on SG I through 4 (black RO labels) and determines that pressures are controlled. May also observe trends on 1-PR-1-2, SG I & 2 PRESS PSIG, and 1-PR-I-23, SG 3 & 4 PRESS PSIG to assess this step.

15. CHECK RCS pressure stable or dropping.

RD RO observes RCS pressure on 1-XI-68-100, RVLIS ICCM PLASMA -

DISPLAY and/or 1-Xl-68-1 10, RVLIS ICCM PLASMA DISPLAY and determines that pressure is dropping.

2011-10 Watts Bar NRC Examination

[Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 34 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1 -FCV-62-73.

Time Position Applicants Actions or Behavior

16. MONITOR electrical board status:

a. CHECK offsite power available.

BOP b. CHECK all shutdown boards ENERGIZED by offsite power.

c. PLACE any unloaded D/G in standby USING SOl-82 Diesel Generators.

EXAMINER: AOI-17, Turbine Trip, Section 3.3, BOP Realignment is contained as Attachment 3.

17. INITIATE BOP realignment:

REFER TO AOl-i 7, Turbine Trip.

SRO assigns AOI-17, Turbine Trip to the BOP for performance on a not to interfere basis.

EXAMINER: E-1, Loss of Reactor or Secondary Coolant, Appendixes are contained as Attachment 4.

18. INITIATE 480V board room breaker alignments USING the following:

Appendix A (E-1), CLA Breaker Operation.

Appendix B (E-1), I -FCV-63-1 Breaker Operation.

BOP

Appendix C (E-1), 1-FCV-63-22 Breaker Operation.

When contacted as the Control Building AUO, the Console Operator will repeat back the request, and then report that Appendix A through C have been performed. Console Operator enters remote functions sirOl, sirl4 and sirO6 to perform actions.

EXAMINER: When the swapover setpoints are reached, the automatic swapover will NOT OCCUR.

19. ENSURE RHR available for cntmt sump recirculation:

Power to at least one operable RHR pump AVAILABLE.

RO

Cntmt sump valve 1-FCV-63-72 or 1-FCV-63-73 to operable RHR

pump AVAILABLE.

20. EVALUATE plant equipment status:

BOP

REFER TO Appendix D (E-1), Equipment Evaluation.

21. CHECK Aux Bldg radiation for loss of RCS inventory outside cntmt:

a. Area monitor recorders 1-RR-90-1 and 0-RR-90-12A Aux Bldg points NORMAL.

BOP BOP reports that Aux Bldg area radiation levels are normal.

b. Vent monitor recorder 0-RR-90-1 01 NORMAL trend prior to isolation.

BOP reports that Aux Bldg vent radiation levels are normal.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 35 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1 A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for i-FCV-62-73.

Time Position Applicants Actions or Behavior

22. NOTIFY Chemistry of event status and plant conditions.

SRO When SRO contacts Chemistry, the Console Operator will repeat back information supplied.

23. DETERMINE if RCS cooldown and depressurization is required:

SRO a. CHECK RCS pressure greater than 150 psig.

b. ** GO TO ES-i .2, Post LOCA Cooldown and Depressurization.

24. PREPARE for switchover to RHR cntmt sump:

a. ENSURE power restored to 1-FCV-63-1 USING Appendix B (E 1), 1-FCV-63-1 Breaker Operation.

When RO dispatches the Control Building AUO to perform Appendix B, the Console Operator will repeat back the request.

RO The Console Operator will enter remote function rhrl4 to restore power to 1-FCV-63-1.

b. CHECK RWST level less than 34%.

RO observes RWST level and reports that level is dropping.

c. ** GO TO ES-i .3, Transfer to Containment Sump.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: 2 Scenario# 7 Event# 7and8 Page 36 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1 A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior The following actions are taken from FR-C.2, Degraded Core FR-C.2 Cooling.

CAUTION RHR pumps should NOT be run longer than 100 minutes without CCS to the RHR heat exchangers.

1. MONITOR RWST greater than 34%.

RO observes RWST level dropping, but greater than 34%. AS RO soon as RWST level drops to below 34%, the SRO will immediately transition to ES-1.3, Transfer to Containment Sump.

2. ESTABLISH RHR valve alignment:

a. CHECK RWST level greater than 34%.

RO observes RWST level dropping, but greater than 34%.

b. ENSURE RHR suction valves from RWST OPEN:

1 -FCV-63-1.

RO observes 1-HS-63-IA, RWST TO RHR ECCS SUCTlON is OPEN by RED indicating light LIT, GREEN indicating light DARK.

1-FCV-74-3 and 1-FCV-74-21.

RO observes 1-HS-74-3A, RHR PMP A SUCTlON and 1-HS 21A, RHR PMP A SUCTION, are OPEN by RED indicating lights RO LIT, GREEN indicating lights DARK.

c. ENSURE RHR discharge valves OPEN:

1-FCV-74-16 and 1-FCV-74-28.

RO observes RED indicating light LIT on 1-XI-74-16, RHR HXA OUTLET FLOW CNTL FCV-74-16. RO observes RED indicating light LIT on 1-Xl-74-28, RHR HXB OUTLET FLOW CNTL FCV 16.

a 1-FCV-63-93 and 1-FCV-63-94.

RO observes 1-HS-63-93A, RHR TO CL 2&3, and 1-HS-63-94A, RHR TO CL 1&4, are OPEN by RED indicating lights LIT, GREEN indicating lights DARK.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 37 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1 Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time I Position Applicants Actions or Behavior

3. ESTABLISH SI pump valve alignment:

a. CHECK RWST level greater than 34%.

RO observes RWST level dropping, but greater than 34%.

b. ENSURE SI pump suction valves from RWST OPEN:

1-FCV-63-5.

RO observes 1-HS-63-5A, RWST TO SI PMPS SUCTION is OPEN by RED indicating light LIT, GREEN indicating light DARK.

1-FCV-63-47 and 1-FCV-63-48.

RO observes 1-HS-63-47A, SI PMP A SUCTlON and 1-HS-63-48A, SI PMP A SUCTION, are OPEN by RED indicating lights LIT, RO GREEN indicating lights DARK.

c. ENSURE SI pump discharge valves OPEN:

1-FCV-63-152.

RO observes 1-HS-63-152A, SI PMP A TO CL 1-2-3-4, is OPEN by RED indicating light LIT GREEN indicating light DARK.

1-FCV-63-153.

RO observes 1-HS-63-153A, SI PMP B TO CL 1-2-3-4, is OPEN by RED indicating light LIT, GREEN indicating light DARK.

1 -FCV-63-22.

RO observes 1-HS-63-22A, SI PMPS TO CL 1-2-3-4, is OPEN by RED indicating light Lfl, GREEN indicating light DARK.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 38 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1 -FCV-62-73.

Time N Position Applicants Actions or Behavior

4. ESTABLISH charging pump valve alignment:

a. CHECK RWST level greater than 34%.

RO observes RWST level dropping, but greater than 34%.

b. ENSURE charging pump suction valves from RWST OPEN:

1-LCV-62-135.

RO observes 1-HS-62-135A, RWST TO CHARGING PMPS SUCTION, is OPEN by RED indicating light LIT;, GREEN indicating light DARK.

1-LCV-62-136.

RO observes 1-HS-62-136A, RWST TO CHARGING PMPS SUCTION, is OPEN by RED indicating light LIT;, GREEN indicating light DARK.

c. ENSURE charging pump suction valves from VCT CLOSED:

1-LCV-62-132.

RO RO observes 1-HS-62-132A, VCT TO CHARGING PMPS SUCTION, is CLOSED by RED indicating light DARK, GREEN indicating light LIT.

1-LCV-62-133.

RO observes 1-HS-62-133A, VCT TO CHARGING PMPS SUCTION, is CLOSED by RED indicating light DARK, GREEN indicating light LIT.

d. ENSURE BIT outlet valves OPEN:

1-FCV-63-25.

RO observes 1-HS-62-25A, BIT OUTLET;, is OPEN by RED indicating light LIT, GREEN indicating light DARK.

1 -FCV-63-26.

RO observes 1-HS-62-26A, BIT OUTLET, is OPEN by RED indicating light LIT, GREEN indicating light DARK.

5. ENSURE ECCS flow from charging pumps:

a. ENSURE charging pumps RUNNING.

RO observes 1-HS-62-108A, CCP A-A ECCS, and 1-HS-63-104A, RO CCP B-B ECCS, are RUNNING by RED indicating lights LIT, GREEN indicating lights DARK.

b. ENSURE flow thru BIT.

RO observes flow on 1-FI-63-170, BIT FLOW.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 39 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time ,, Position Applicants Actions or Behavior

6. ENSURE ECCS flow from SI pumps:

a. CHECK RCS pressure less than 1350 psig.

RO observes RCS pressure on 1-XI-68-110 RVLIS ICCM PLASMA -

DISPLAY and determines that pressure is less than 1350 psig.

b. ENSURE SI pumps RUNNING.

RO RO observes 1-HS-63-IOA, SI PMP A (ECCS), and 1-HS-63-15A, SI PMP A (ECCS), are RUNNING by RED indicating lights LIT, GREEN indicating lights DARK.

c. ENSURE SI pump flow.

RO observes flow on 1-FI-63-151, SI PMP A FLOW and 1-Fl-63-20, SIPMPB FLOW 2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: 2 Scenario # 7 Event # 7 and B Page 40 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time N Position Applicants Actions or Behavior EXAMINER: The actions of Step 7 may have already been accomplished during the performance of E-1, Step 13.

7. ENSURE ECCSflowfrom RHR pumps:

a. CHECK RCS pressure less than 150 psig OR RHR aligned to cntmt sump recirc.

b. ENSURE RHR pumps RUNNING.

c. ENSURE RHR pump flow.

RO

d. ENSURE CCS from RHR heat exchangers OPEN:

1-FCV-70-153.

1-FCV-70-156.

e. ENSURE SFP heat exchanger A CCS supply CLOSED:

0-FCV-70-197.

EXAMINER: The following actions were accomplished when E-1, Appendices A and B were completed.

8. INflATE 480V board room breaker alignments USING:

SRO

Appendix A (FR-C.2), Ice Condenser AHU Breaker Operation.

Appendix B (FR-C.2), CLA Breaker Operation.

9. ENSURE pzr depressurization paths ISOLATED:

a. CHECK pzr PORVs CLOSED.

RO observes 1-HS-68-340AA, PZR PORV 340A, CLOSED, GREEN indicating light is LIT, RED indicating light is DARK.

RO observes 1-HS-68-334A, PZR PORV 334, CLOSED GREEN indicating light is LIT, RED indicating light is DARK.

b. CHECK at least one pzr PORV block valve OPEN.

RO observes 1-HS-68-333A, BLOCK VLV FOR PORV34OA, OPEN, GREEN indicating light is DARK, RED indicating light is LIT.

RO observes 1-HS-68-332A, BLOCK VLV FOR PORV 334, OPEN GREEN indicating light is DARK, RED indicating light is LIT.

CAUTION

The reactor head vent throttle valve position indication may NOT be accurate.

Monitoring of the PRT level, press, and temp is required to confirm throttle valve position.

Isolation of a failed throttle valve requires both reactor vessel head vent block valves to be closed.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 41 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior

10. ENSURE RCS depressurization paths ISOLATED:

a. ENSURE letdown orifice valves CLOSED.

RO observes 1-HS-62-76A, 1-HS-62-72A, 1-HS-62-73A and 1-HS-62-74A ORIFICE ISOLATION VALVES are CLOSED by RED indicating lights DARK, GREEN indicating lights LIT.

b. ENSURE letdown isolation valves CLOSED:

1 -FCV-62-69.

1 -FCV-62-70.

RO observes 1-HS-62-69A and 1-HS-62-70A, RCS LETDOWN FRM LOOP # IN CNTMT are CLOSED by RED indicating lights DARK, GREEN indicating lights LIT.

c. ENSURE excess letdown isolation valves CLOSED:

I -FCV-62-54.

1 -FCV-62-55.

RO observes GREEN indicating lights LIT on handswitches 1-HS-62-54A, EXCESS LTDN ISOL, and 1-HS-62-55A, EXCESS LTDN.

RO d. ENSURE power removed from post accident sample valves:

1-HS-43-250A in BLOCK [M-10].

1-HS-43-309A in BLOCK [M-10].

BOP observes 1-HS-43-250A and 1-HS-43-309A are in the BLOCK position, and RED indicating lights DARK, GREEN indicating lights LIT.

e. ENSURE reactor vessel head vent valves CLOSED:

I -FSV-68-394.

1 -FSV-68-395.

RO observes that the 1-HS-68-394, RX HEAD VENT ISOL, and 1-HS-68-395, RX HEAD VENT ISOL, are labeled PDI C (Power Disconnected CLOSED).

1 -FSV-68-396.

1 -FSV-68-397.

RO observes that the 1-HIC-68-396, RX HEAD VENT FLOW CONTROL, and 1-HIC-68-397, RYHEAD VENTFLOW CONTROL, are labeled PDIC (Power Disconnected CLOSED). -

11. EVALUATE RCP status:

RO

a. CHECK at least one RCP RUNNING.

11 .a. RESPONSE NOT OBTAINED:

SRO IF all four RCPs stopped, THEN **

GO TO Step 14.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 42 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior

14. DETERMINE if core cooling restored:

SRO

a. RVLIS greater than 33%.

14.a. RESPONSE NOT OBTAINED:

IF RVLIS rising, THEN RETURN TO Step 1.

IF RVLIS stable or dropping, THEN ** GO TO Step 15.

15. CHECK cold leg accumulator isolation valve status:

a. Power to CLA isolation valves AVAILABLE.

Power was restored by performance of E-1, Appendix A.

b. CLA Isolation valves OPEN:

RO

1-FCV-63-1 18.

1-FCV-63-98.

1 -FCV-63-80.

1-FCV-63-67.

GOP 16. MONITOR CST volume greater than 200,000 gal.

CAUTION If Intact SIGs are NOT available for use in subsequent steps, then a Faulted or Ruptured SIG should be used to cooldown the RCS.

17. MONITOR Intact SIG NR levels:

GOP a. At least one intact SIG NR level greater than 29% [39% ADVI.

b. CONTROL levels between 29% and 50% [39% and 50% ADVJ.

CAUTION The following step will cause accumulator injection which may cause a RED path condition in FR-P, Pressurized Thermal Shock Status Tree. FR-C.2 should be completed before transition to FR-P.1, Pressurized Thermal Shock.

NOTE After the low steamline pressure SI signal is blocked, main steamline isolation will occur if the high steam pressure rate setpoint is exceeded.

2011-10 Wafts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 43 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior

18. DEPRESSURIZE all intact S!Gs to inject accumulators:

a. WHEN RCS pressure is less than 1962 psig (P-Il), THEN

BLOCK low pzr pressure SI.

BLOCK low steam pressure SI.

b. MAINTAIN cooldown rate in RCS cold legs less than 100°F/HR.

BOP

c. DUMP steam to condenser.

d. ALLOW cold leg accumulators to inject during RCS cooldown.

e. CHECK SIG pressures less than 200 psig.

f. CHECK RCS pressure less than 250 psig.

g. STOP SIG depressurization.

RO 19. ENSURE RHR pumps RUNNING.

20. DETERMINE if cold leg accumulators should be isolated:

a. CHECK RCS pressure less than 250 psig.

b. ENSURE SI RESET:

R

SI ACTUATED permissive DARK

AUTO SI BLOCKED permissive LIT

c. CLOSE cold leg accumulator isolation valves.

CAUTION Subsequent steps may cause transition to FR-C.1, INADEQUATE CORE COOLING.

RO 21. ENSURE all four RCPs STOPPED.

22. DEPRESSURIZE all intact SIGs to atmospheric pressure:

SOP a. MAINTAIN T-cold cooldown rate less than 100°F/HR.

b. DUMP steam to condenser.

23. ENSURE ECCS flow:

Flow thru BIT, OR RD

SI pump flow OR

RHR pump flow.

24. CHECK if core cooling restored:

SRO . RVLIS greater than 60%.

At least two T-hots less than 350°F.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario# 7 Event# 7and8 Page 44 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation ofswapoverfor l-FCV-62-73.

Time Position Applicants Actions or Behavior

24. RESPONSE NOT OBTAINED:

IF RVLIS less than or equal to 60%,

SRO OR Three T-hots greater than or equal to 350°F, THEN GO TO Step 22.

25. ** GO TO E-1, LOSS OF REACTOR OR SECONDARY SRO COOLANT, Step 17.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 45 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1 A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for I -FCV-62-73.

Time Position Applicants Actions or Behavior FR-P.1 The following actions are taken from FR-P.1, Pressurized Thermal Shock.

NOTE Steps I thru 4 are IMMEDIATE ACTION STEPS.

Status Trees I SPDS should be monitored when transitioned to another instruction.

RO 1. CHECK RCS pressure greater than 150 psig.

1. RESPONSE NOT OBTAINED:

RO IF RHR pump injecting greater than 1350 gpm to RCS, THEN RETURN TO Instruction in effect.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 46 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swapover to containment sump fails. Requires manual initiation of swapover for I -FCV-62-73.

Time Position Applicants Actions or Behavior The following actions are taken from ECA-1.1, Transfer to ES-1.3 Containment Sum p.

CAUTION

ECCS flow to RCS must be maintained at all times to ensure adequate core cooling.

Transfer to recirculation mode may cause high radiation in the Auxiliary Building.

NOTES

Performance of this Instruction is a higher priority than performance of the FRs because it maintains ECCS pump suction.

The transfer sequence should be performed without delay. Implementation of FRs is delayed UNTIL transfer sequence is completed or transitioned from.

1. ENSURE both RRR pumps RUNNING.

SRO RO observes that IA-A and lB-B RHR pumps are running.

2. ESTABLISH CCS to RHR heat exchangers [M-27B]:

a. ENSURE RHR heat exchanger outlet valves 1 -FCV-70-1 53 and 1-FCV-70-1 56 OPEN.

b. CLOSE SFP heat exchanger A CCS supply 0-FCV-70-197.

BOP c. ENSURE CCS flow to ESF supply header and greater than 5000 gpm.

Train A: 1-Fl-70-159

Train B: 1-Fl-70-165

d. MONITOR level in CCS surge tanks.

3. CHECK RWST level less than 34%.

RO RO observes RWST level is less than 34%.

4. CHECK cntmt sump level greater than or equal to 16.1 %.

RO RO observes cntmt sump level greater than 16.1%.

5. ENSURE automatic switchover complete:

RO a. ENSURE cntmt sump valvesl-FCV-63-72 and 1-FCV-63-73 OPEN.

EXAMINER: When the swapover setpoints are reached, the automatic swapover will NOT OCCUR.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 47 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. 1A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior 5.a. RESPONSE NOT OBTAINED:

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

RO places 1-HS-74-IOA, RHR PMP A (ECCS) in the STOP, PULL RO TO-LOCK position.

IF flow from cntmt sump can NOT be established, THEN GO TO ECA-i .1, Loss of RHR Sump Recirculation.

SRO determines that flow can be established from RHR Train B, and remains in ES-1.3, Transfer to Containment Sump.

b. ENSURE RWST to RHR suction valves i-FCV-74-3 and 1-FCV-74-21 CLOSED.

RO

c. INITIATE power restoration to i-FCV-63-1 USING Appendix A (ES-i .3), 1-FCV-63-i Breaker Operation.

CAUTION If RWST level drops to 8%, then any charging, SI or cntmt spray pump taking suction from the RWST must be stopped.

RO 6. MONITOR RWST level greater than 8%.

DETERMINE if cntmt spray should be stopped:

RO

a. MONITOR cntmt press less than 2.0 psig.

7.a. RESPONSE NOT OBTAINED:

RO WHEN cntmt press less than 2.0 psig, THEN PERFORM Substeps 7b thru e. **GO TO Step 8.

8. DETERMINE if ONE train cntmt spray should be stopped:

a. CHECK BOTH trains cntmt spray delivering flow.

RO b. RESET cntmt spray signal.

c. STOP ONE cntmt spray pump AND PLACE in A-AUTO.

d. CLOSE spray discharge valve for stopped pump.

9. MONITOR RCS press less than 1350 psig.

RO RO observes RCS pressure on 1-Xl-68-110 RVLIS ICCM -

PLASMA DISPLAY and determines that pressure is less than 1350 psig.

CAUTION If a valve fails during the transfer sequence, any corrective action should be postponed UNTIL transfer is complete, EXCEPT as required to satisfy each step.

NOTE Each transfer sequence action is identified by a number on the control board (e.g. #1).

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 48 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time Position Applicants Actions or Behavior Critical Task 2 Transfer to cold leg recirculation and establish one train of ECCS recirculation flow prior to exiting ES-1.3, Transfer to Containment Sump.

Start of 10. (#1) ISOLATE SI pump miniflow:

Critical

CLOSE 1 -FCV-63-3.

Task 2 RO rotates 1-HS-63-3 to the left to the CLOSE position.

RO

CLOSE 1-FCV-63-175.

RO rotates 1-HS-63-175 to the left to the CLOSE position.

CLOSE I-FCV-63-4.

RO rotates 1-HS-63-4 to the left to the CLOSE position.

Critical 11. (#2) ISOLATE RHR crossties:

CLOSE 1-FCV-74-33.

RO rotates handswitch 1-HS-74-33 to the left to the CLOSE RO position

CLOSE 1-FCV-74-35.

RO rotates handswitch 1-HS-74-35 to the left to the CLOSE position Critical 12. (#3) ALIGN charging pump and SI pump supply from RHR:

OPEN 1-FCV-63-6.

RO rotates handswitch 1-HS-63-6 right to the OPEN position

OPEN 1-FCV-63-7.

RO RO rotates handswitch 1-HS-63-7 right to the OPEN position

ENSURE 1-FCV-63-177 OPEN.

RO determines 1-HS-63-177 is OPEN observing the RED light is LIT and GREEN light is DARK.

NOTE 1-FCV-63-8 and 1-FCV-63-1 1 are interlocked with the SI pump miniflows being full closed.

Critical 13. (#4) ALIGN RHR discharge to charging pump and SI pump suction:

a. OPEN 1-FCV-63-8.

RO RO determines that 1-HS-63-8 will NOT open due to failure of 1-FCV-63-72 to open, required by interlock circuit to open 1-HS-63-8.

2011-10 Watts Bar NRC Examination

rAppendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 49 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary coolant. 1 A Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1 -FCV-62-73.

Time Position Applicants Actions or Behavior 13.a. RESPONSE NOT OBTAINED:

ENSURE Train B RHR operation:

Train B RHR pump RUNNING.

1-FCV-63-11 DPEN.

RO rotates handswitch 1-HS-63-11 right to the OPEN position

Either 1-FCV-63-6 or 1-FCV-63-7 DPEN.

b. OPEN 1-FCV-63-11.

RO addressed opening 1-FCV-63-11 in the previous step.

Critical 14. DO NOT CONTINUE this Instruction UNTIL Steps 10 thru 13 RD complete.

CAUTION If RCS press is greater than 1350 psig, the SI pumps should NOT be restarted because the recirc path is isolated.

15. RESTART any charging pumps and SI pumps as necessary.

RD RO determines that NO pumps were stopped, so SRO continues to next step.

CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.

Critical 16. (#5) RESET SI, and CHECK the following:

RO depresses 1-HS-63-134A SI RESET TR A and 1-HS-63-134B, RD SI RESET TR B and observes the following:

SI ACTUATED permissive DARK.

AUTD SI BLDCKED permissive LIT.

17. IF offsite power is lost, THEN

a. PLACE charging pumps in PULL TO LOCK.

b. RESTART RHR pumps.

c. RESTART charging pumps.

SRO d. IF RCS press less than 1350 psig, THEN RESTART SI pumps.

RO observes RCS pressure on 1-Xl-68-110 RVLIS ICCM -

PLASMA DISPLAY and determines that pressure is less than 1350 psig.

CAUTION ECCS pump discharge flow and motor amps should be monitored WHILE closing the RWST suction valves.

2011-10 Watts Bar NRC Examination

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2 Scenario # 7 Event # 7 and 8 Page 50 of 50 Event

Description:

7) Large break LOCA develops at the reactor trip. Requires entry into E-0, Reactor Trip or Safety Injection, and a transition to E-1, Loss of Reactor or Secondary Coolant. IA Air Return fan trips on overcurrent. 8) Auto swap-over to containment sump fails. Requires manual initiation of swapover for 1-FCV-62-73.

Time I Position 1 Applicants Actions or Behavior Critical 18. (#6) ISOLATE charging pump suction from RWST:

a. CLOSE 1-LCV-62-135.

RO pushes 1-HS-62-135 handswitch in, and then rotates the handswitch to the left to the CLOSED position

b. CLOSE 1 -LCV-62-1 36.

RO pushes 1-HS-62-136 handswitch in, and then rotates the RD handswitch to the left to the CLOSED position

c. ENSURE 1-HS-62-135A in A-AUTO (pushed in).

RO determines that the handswitch for 1-HS-62-135 has remained in the pushed-in position

d. ENSURE i-HS-62-136A in A-AUTO (pushed in).

RO determines that the handswitch for 1-HS-62-136 has remained in the pushed-in position Critical 19. (#7) ISOLATE SI pump suction from RWST:

CLOSE i-FCV-63-5.

RD RO rotates handswitch 1-HS-63-5A to the left to the CLOSED position.

End of 20. (#8) ISOLATE RHR suction from RWST:

Critical a. ENSURE power restored to i-FCV-63-1 USING Appendix A Task 2 (ES-i .3), 1-FCV-63-i Breaker Operation.

RD b. CLOSE 1-FCV-63-i.

RO may contact Control Building AUO to check on status of E 1, Appendix B performance. The Console Operator reports that power to 1-FCV-63-1 has been restored.

I I EXAMINER: When 1 -FCV-63-i, RWST TO RHR ECCS SUCTION is CLOSED, inform applicants that another crew will continue from this point, and terminate the scenario.

END OF SCENARIO 2011-10 Watts Bar NRC Examination

Scenario I SHIFT TURNOVER CIIECK[JST Page 1 of2 SHIFT TURNOVER CHECKLIST Page 1 of I Q SM US/MCR Unit 1 1 UO Unit Off-going Name Q AUO Station Q STA (STA Function) On-coming Name Part 1 Completed by off-going shift / Reviewed by on-coming shift:

RCS Cb = 765 ppm Abnormal equipment lineup I conditions:

The TDAFW pump is out of service due to broken trip-and-throttle valve linkage. LCO 3.7.5.b was entered 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago. The repairs are expected to be completed in the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Protected equipment signs have been posted for lA-A MD AEW pump, the lB-B MD AFWP, the IA DG and the lB DG. 1C Condensate Booster pump A is out of service for bearing replacement, with repairs in progress.

SI/Test in progress/planned: (including need for conduct of evolution briefings)

Major Activities/Procedures in progress/planned:

Train AlChannel I Work Week. 92% Reactor Power, MOL, RCS boron concentration 765 ppm. Control Bank D at 199 steps. Turbine Valve testing and minor EHC repairs are complete and a power ascension to 95% is to be conducted using GO-4, Normal Power Operations.

Radiological changes in plant during shift:

Part 2 Completed by on-coming shift prior to assuming duties Q Review station rounds / Abnormal reading (AUOs only)

Q Review Narrative Logs (previous day and cany-over items)

D Current qualification status Review the current controlling Reactivity Management Plans (N/A for AUOs)

Review current TS/TRM/ODCMIFPR Required Actions (N/A for AUOs)

Wallcdown MCR Control Boards with off-going Operator (N/A for AUOs, as applicable for SM/STA5)

SRIPER reviews complete for previous shift (SM/US/STA)

Relief Time: Relief Date:

Part 3 Completed by on-coming shift. These items may be reviewed after assuming duties:

Review Operator Workarounds, Burdens and Challenges (applicable Unit/Station)

Review applicable ODMI actions (first shift of shift week)

Q Review changes in Standing / Shift Orders (since last shift worked)

Q Review changes to TACFs issued (since last shift worked) (N/A for AUOs)

Review Control Room Deficiencies (first shift of shift week) (N/A for AUOs)

Q Review Component Deviation Log (N/A for AUOs)

TVA 40741 Page 1 nfl OPDP-l-l [01-14-2011]

Scenano 7 SHIFT TURNOVER CHECKLIST Page 1 of2 SHIFT TURNOVER CHECKLIST Page 1 of 1 0 SM Q US/MCR Unit 1 UO Unit Off-going Name 0 AUO Station Q STA (STA Function) On-coming Name Part 1 Completed by off-going shift / Reviewed by on-coming shift RCS Cb = 765 ppm Abnormal equipment lineup / conditions:

The TDAFW pump is out of service due to broken trip-and-throttle valve linkage. LCO 3.7.5.b was entered 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago. The repairs are expected to be completed in the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Protected equipment signs have been posted for lA-A MD AEW pump, the lB-B MD AFWP, the 1A DG and the lB DG. IC Condensate Booster pump A is out of service for bearing replacement, with repairs in progress.

SI/Test in progress/planned: (including need for conduct of evolution briefings)

Major Activities/Procedures in progress/planned:

Train A/Channel I Work Week. 92% Reactor Power, MOL, RCS boron concentration 765 ppm. Control Bank D at 199 steps. Turbine Valve testing and minor EHC repairs are complete and a power ascension to 95% is to be conducted using GO-4, Normal Power Operations.

Radiological changes in plant during shift:

Part 2 Completed by on-coming shift prior to assuming duties 0 Review station rounds / Abnormal reading (AUOs only) 0 Review Narrative Logs (previous day and carry-over items)

D Current qualification status D Review the current controlling Reactivity Management Plans (N/A for AUOs)

D Review current TS/TRMIODCM/FPR Required Actions (N/A for AUOs)

Q Walkdown MCR Control Boards with off-going Operator (N/A for AUOs, as applicable for SM/STAs)

Q SRIPER reviews complete for previous shift (SM/US/STA)

Relief Time: Relief Date:

Part 3 Completed by on-coming shift. These items may be reviewed after assuming duties 0 Review Operator Workarounds, Burdens and Challenges (applicable Unit/Station)

D Review applicable ODMI actions (first shift of shift week)

C Review changes in Standing / Shift Orders (since last shift worked)

C Review changes to TACFs issued (since last shift worked) (N/A for AUO5)

C Review Control Room Deficiencies (first shift of shift week ) (N/A for AUOs)

O Review Component Deviation Log (N/A for AUOs)

TVA 40741 Page 1 of I OPDP-l-1 [01-14-20111

Scenario 7 Attachment I AOl1 5 Loss of Component Cooling Water (CCS).

Appendix A

WBN Loss of Component Cooling Water AOI-15

Unit I (CCS) Rev. 0032 AppendixA (Page 1 of 2)

Header Cross-Reference ESF EQUIPMENT IA COMPONENT NORMAL FLOW FLOW INDICATOR CCP 1A Gear & Oil Cooler 28 gpm 1-FI-70-146 SIP IA Oil Cooler 15 gpm 1-Fl-70-147 CS Pump IA Oil Cooler 2 gpm 1-Fl-70-150 RHR Pump 1A Seal HX 10 gpm 1-Fl-70-151 RHR HX 1A 5000 gpm 1-FI-70-158 ESF EQUIPMENT lB COMPONENT NORMAL FLOW FLOW INDICATOR CCP lB Gear & Oil Cooler 28 gpm l-Fl-70-145 SIP lB Oil Cooler 15 gpm 1-Fl-70-148 CS Pump lB Oil Cooler 2 gpm 1-FI-70-149 RHR Pump lB Seal HX 10 gpm 1-FI-70-152 RHR HX lB 5000 gpm 1-FI-70-155 Page 31 of 33

WBN Loss of Component Cooling Water AOl-15 Unit I (CCS) Rev. 0032 Appendix A (Page 2of2)

Header Cross-Reference NOTE All listed equipment affected by ioslation Misc Equip and Rx Bldg Hdrs.

COMPONENT ACTION

. RX BLDG HDR EQUIPMENT Excess Letdown HX REMOVE from service USING SOl-62.01.

RCP Motor Bearings STOP RCP(s) if motor bearing rises to 195°F (alarm at 185°F).

RCPs must be tripped within 10 minutes of loss of CCS to oil coolers.

Thermal Barrier Booster Pump STOP TBBPs.

supply CHECK RCP seal temp & flow.

Post Accident Sampling NOTIFY Chemistry.

MISC HDR EQUIPMENT Seal Water HX CHECK VCT temp. Should be slight rise in seal supply temp (max 130°F).

Letdown HX ISOLATE charging and letdown.

(Excess Letdown NOT available)

Sample HXs NOTIFY Chemistry.

Waste Gas Compressor REMOVE from service USING SOl-.77.02.

Page 32 of 33

Scenario 7 Attachment 2 EO, Reactor Trip or Safety Injection Append ix A and B Attachments I through 5

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Appendix A (Page I of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained ENSURE PCB5 OPEN: OPEN manually.

PCB 5084.

PCB 5088.

2. ENSURE AFW pump operation: ESTABLISH at least one train AFW operation.

o Both MD AFW pumps RUNNING.

TDAFWpump RUNNING.

LCVsinAUTO,OR controlled in MANUAL.

3. ENSURE MEW isolation: Manually CLOSE valves AND

MEW isolation and bypass STOP pumps, as necessary.

isolation valves CLOSED.

MEW reg and bypass reg valves CLOSED. IF any valves can NOT be closed, THEN

MEP A and B TRIPPED.

Standby MEP STOPPED. CLOSE #1 heater outlet valves.

Cond demin pumps TRIPPED.

Cond booster pumps TRIPPED.

Page 16 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Appendix A (Page 2 of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained

4. MONITOR ECCS operation:

a. Charging pumps RUNNING. a. Manually START charging pumps.

b. Charging pump alignment: b. ENSURE at least one valve in each set aligned.

RWST outlets 1-LCV-62-135 and 1-LCV-62-136 OPEN.

o VCT outlets 1 -LCV-62-1 32 and 1-LCV-62-133 CLOSED.

Charging 1-FCV-62-90 and 1-FCV-62-91 CLOSED.

c. RHR pumps RUNNING. c. Manually START RHR pumps.

d. SI pumps RUNNING. d. Manually START SI pumps.

e. BIT alignment: e. ENSURE at least one valve

Outlets 1-FCV-63-25 aligned, and flow thru BIT.

and 1-FCV-63-26 OPEN.

Flowthru BIT.

f. RCS pressure greater f. ENSURE SI pump flow.

than 1650 psig.

IF RCS press drops to less than 150 psig, THEN ENSURE RHR pump flow.

Page 17 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Appendix A (Page 3 of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained I

5. CHECK cntmt isolation: ACTUATE Phase A and

a. Phase A isolation: Cntmt Vent Isolation signal,

Train A GREEN. OR

Train B GREEN.

Manually CLOSE valves and

b. Cntmt vent isolation: dampers as necessary.

Train A GREEN.

Train B GREEN.

Page 18of31

WBN Reactor Trip or Safety Injection E-0

Uniti Rev. 0029 Appendix A (Page 4 of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained

6. CHECK cntmt pressure: PERFORM the following:

Phase B DARK [MISSP]. 1) ENSURE Phase B actuated.

Cntmt Spray DARK [MISSP]. 2) ENSURE Cntmt Spray actuated.

Cntmt press less than 2.8 psig. 3) ENSURE cntmt spray pumps running.

4) ENSURE cntmt spray flow.

5) ENSURE Phase B isolation:

Train A GREEN.

Train B GREEN

Manually CLOSE valves and dampers as necessary.

6) STOP all RCP5.

7) ENSURE MSIVs and bypasses CLOSED.

8) PLACE steam dump controls OFF.

9) WHEN 10 minutes has elapsed since Phase B actuated, THEN ENSURE air return fans start.

10) USE adverse cntmt [ADV] setpoints where provided.

7. DISPATCH AUO to perform Attachment I (E-0), Ice Condenser AHU Breaker Operation.

Page 19 of 31

WBN Reactor Trip or Safety Injection E-0

Uniti Rev 0029 Appendix A (Page 5 of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained

8. CHECK plant radiation NORMAL: NOTIFY Unit Supervisor IMMEDIATELY.

SIG blowdown rad recorder I -RR-90-1 20 NORMAL prior to isolation [M-12].

Condenser vacuum exhaust rad recorder 1-RR-90-1 19 NORMAL prior to trip [M-12].

1-RR-90-106 and 1-RR-90-112 radiation recorders NORMAL prior to isolation [M-12].

S/G main steamline discharge monitors NORMAL [M-30].

Upper and Lower containment high range monitors NORMAL

[M-30].

NOTIFY Unit Supervisor conditions NORMAL.

9. ENSURE all D/Gs RUNNING. EMERGENCY START D/Gs

10. ENSURE ABGTS operation:

a. ABGTS fans RUNNING. a. Manually START fans.

b. ABGTS dampers OPEN: b. Locally OPEN dampers.

o FCO-30-146A.

FCO-30-146B.

FCO-30-157A.

FCO-30-157B.

Page2Oof3l

WBN Reactor Trip or Safety Injection E-0

, Unit I Rev. 0029 Appendix A (Page 6 of 9)

Equipment Verification Step

[ Action/Expected Response Response Not Obtained II. ENSURE at least four ERCW pumps Manually START pumps as necessary.

RUNNING, one on each shutdown board preferred.

12. ENSURE ERCW supply valves IF ERCW can NOT be OPEN to running DIGs. aligned to running DIG, THEN EMERGENCY STOP affected D/G.

13. ENSURE O-FCV-67-152, CCS HX C Manually OPEN O-FCV-67-152 ALT DISCH TO HDR B, is open to to position A.

position A.

14. CLOSE O-FCV-67-144, CCS HX C DISCH TO HDR A.

15. MONITOR EGTS operation: Manually START fans

EGTS fans RUNNING.

AND

ENSURE dampers OPEN -

OPEN dampers.

VERIFY filter bank dp between 5 and 9 inches of water.

16. ENSURE CCS pumps RUNNING: Manually START pumps as necessary.

IA-ACCS pump.

lB-B CCS pump.

C-S or 2B-B CCS pump.

17. DISPATCH AUO to shutdown Upper and Lower CNTMT rad monitors USING SOI-90.02.Gaseous Process Radiation Monitors Page 21 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Appendix A (Page 7 of 9)

Equipment Verification Step ction/Expected Response Response Not Obtained

18. WHEN Attachment 1 is complete (Ice Condenser AHU Breakers OPEN),

THEN ENERGIZE hydrogen igniters

[1-M-1 0]:

1-HS-268-73 ON.

1-HS-268-74 ON.

NOTE The following equipment is located on 1-M-9.

19. CHECK CNTMT PURGE fans STOP fans AND STOPPED.

PLACE handswitch in PULL-TO-LOCK.

20. CHECK FUEL HANDLING EXH fans STOP fans AND STOPPED, Fuel and Cask loading dampers CLOSED: PLACE handswitch in PULL-TO-LOCK, THEN Manually CLOSE dampers.

21. ENSURE AB GEN SUPPLY and STOP fans AND EXH fans STOPPED.

PLACE handswitch in PULL-TO-LOCK.

NOTE Dampers 1-HS-30-158 and 2-HS-30-270 remain open during ABI.

22. ENSURE AB GEN SUP & EXH Manually CLOSE dampers.

dampers CLOSED.

Page 22 of 31

WBN Reactor Trip or Safety Injection E-0 Unit *1 Rev. 0029 Appendix A (Page 8 of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained

23. ENSURE MCR & SPREAD RM Manually CLOSE dampers.

FRESH AIR dampers CLOSED:

FCV-31-3.

FCV-31-4.

24. ENSURE at least one CB EMER CLEANUP fan RUNNING and associated damper OPEN:

CB EMERG CLEANUP FAN A-A, Manually START fan.

OR

Fan B-B RUNNING..

FCO-31-8, OPEN. NOTIFY TSC if at least one damper NOT OPEN.

OR

FCO-31-7, OPEN

25. ENSURE at least one CB EMER PRESS fan RUNNING and associated damper OPEN:

CB EMERG PRESS FAN A-A, Manually START fan.

OR FAN B-B RUNNING.

FCO-31-6, OPEN. NOTIFY TSC if at least one damper NOT OPEN.

OR

FCO-31-5, OPEN.

Page23of3l

WBN Reactor Trip or Safety Injection E-0

Unit I Rev. 0029 Appendix A (Page 9 of 9)

Equipment Verification Step Action/Expected Response Response Not Obtained

26. ENSURE Control Building fans STOPPED and dampers CLOSED:

SPREADING ROOM SUPPLY Manually STOP fans AND and EXH FANS AND dampers.

if any damper NOT

TOILET & LKR RM EXHAUST FAN AND dampers.

27. INITIATE Appendix B (E-O), Phase B Pipe Break Contingencies.

Page24of3l

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Appendix B (Page I of I)

Phase B Pipe Break Contingencies Step Action/Expected Response Response Not Obtained

1. CHECK PHASE B actuated. WHEN PHASE B actuation occurs,

[MISSP 1-XX-55-6C, -6D1

- THEN GO TO step 2.

2. ENSURE 1-FCV-32-1 10 CLOSED. DISPATCH AUO to perform

[CISP 1-)(X-55-6E]

- Attachment 2 (E-0).

(A-train, window 13)

3. ENSURE 1-FCV-67-107 CLOSED. DISPATCH AUO to perform

[CISP 1-XX-55-6E]

- Attachment 3 (E-0).

(A -train, window 43)

4. ENSURE 1-FCV-70-92 CLOSED. DISPATCH AUO to perform

[CISP 1-XX-55-6E]

- Attachment 4 (E-0).

(A -train, window 73)

5. ENSURE 1-FCV-70-140 CLOSED. DISPATCH AUO to perform

[CISP 1-XX-55-6F1

- Attachment 5 (E-0).

(B -train, window 74)

Page25of3l

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Attachment I (Page I ofi)

Ice Condenser AHU Breaker Operation OPEN the following to remove power from ice condenser air handling units AND REPORT completion to UO:

BOARD COMPT NOMENCLATURE 480 V Reactor Vent 13D 1-BKR-232-A000/13D ICE COND Board IA-A 1-AHU-61-114/8112116/20124128 480 V Reactor Vent 14D 1-BKR-232-A000/14D ICE COND Board lA-A 1-AHU-61-3/7/1 1/1 5/1 9/23/27 480 V Reactor Vent 13D 1-BKR-232-B000/13D ICE COND Board 1 B-B I -AH U-6 1-2/6/10/14/18/22/26/30 480 V Reactor Vent 14D 1-BKR-232-B000/14D ICE COND Board 1 B-B 1 -AHU-61 -5/9/13/17/21/25/29 Page 26 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Attachment 2 (Page 1 ofl)

Control Air Isolation A. CLOSE O-ISV-32-1013 CONTROL AIR EL 713 AB HDR ISOL

[A6IS EL. 713] (chain operated behind Fuel and Waste Handling Bd. A).

B. IF O-ISV-32-1013 CANNOT BE CLOSED, THEN OPEN and DISCONNECT C&SS air compressor breakers:

1. O-BKR-32-25 [480V SD BD 1A2-A, C/3D]

2. O-BKR-32-26 [48OVSD BD IBI-B, C/3D]

3. O-BKR-32-27 [48OVAUX BLDG COM BD, CI6C]

4. O-BKR-32-4900A [480V TURB BLDG COM BD, C/6C]

Page 27 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Attachment 3 (Page 1 ofl)

ERCW Isolation UNLOCK AND CLOSE I -ISV-67-523B, LOWER CNTMT VENT CLR I B &1 D ERCW SUP ISOL [A2U/692] (U-i penetration room North of AB Pipe Chase Cooler lB-B in overhead)

Page 28 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Attachment 4 (Page 1 ofl)

CCS Return Isolation CLOSE I-ISV-70-700, RCP OIL COOLER CCS RETURN ISOLATION

[A4N EL. 710 U-I Penetration Room] (approximately 10 ft. North of Penetration Room Cooler lB-B on mezzanine above RHR Sump Valve Room)

Page 29 of 31

WBN Reactor Trip or Safety Injection E-0 Unit I Rev. 0029 Attachment 5 (Page 1 ofl)

CCS Supply Isolation CLOSE 1-ISV-70-516, REACTOR BUILDING CCS SUPPLY ISOLATION

[A6IT EL. 737] (Behind Elevator approximately 2 ft. west on mezzanine above A CCS Heat Exchanger)

Page3Oof3l

Scenario 7 Attachment 3 AOl-I 7, Turbine Trip.

Section 3.3 BOP Realignment.

WBN Turbine Trip AOI-17 Uniti Rev. 0047 Step Action/Expected Response Response Not Obtained 3.3 BOP Realignment CAUTION Performance of this instruction should not be allowed to delay or interfere with actions required by applicable emergency procedures or abnormal operating procedures.

NOTES

Control room operators may initiate shutdown of pumps and equipment from the bench board immediately after a trip.

Performance of this instruction will subsequently verify proper secondary equipment alignment.

o Steps in this section and items in Attachment I may be performed out of sequence.

Attachment I may be initiated as soon as Turbine has tripped while MCR completes Section 3.2. Initiation of Attachment I may be part of briefing for preplanned Turbine trip with performance to begin when NAUO is notified of Turbine trip by UO.

DISPATCH turbine building NAUO to perform Attachment I.

2. NOTIFY condensate demineralizer NAUO prior to Operator initiated press changes in condensate.

3. REMOVE generator excitation from service:

a. PLACE voltage regulator to TEST.

b. OPEN exciter field breaker.

c. PLACE exciter regulator control to OFF.

Page II of 26

WBN Turbine Trip AOI-17 Uniti Rev. 0047 Step Action/Expected Response Response Not Obtained 3.3 BOP Realignment (continued)

4. MONITOR main turbine:

a. VERIFY seal oil backup pump a. ENSURE seal oil backup pump running. 1-HS-47-61D in NORMAL

b. ENSURE turning gear oil pump (T7J/729 behind MTOT)

RUNNING.

c. WHEN less than 600 rpm, THEN ENSURE bearing lift oil pump RUNNING.

d. WHEN turbine is at ZERO RPM, THEN ENSURE turbine on turning gear.

e. MAINTAIN MTOT lube oil temp between 95°F° and 100°F (may require RCW isolation if TCV has excessive leakage).

f. MAINTAIN GENERATOR H2 (Cold Gas) temp 95°F (may require RCW isolation if TCV has excessive leakage).

g. ENSURE Gland Steam Spillover Bypass valve is CLOSED using 1-HS-47-1 91A.

5. ALIGN MSR5:

a. PUSH RESET on MSR control panel.

b. CLOSE MSR HP steam and bypass isol.

c. ENSURE MSR warming valves CLOSED.

d. OPEN MSR startup vents.

e. CLOSE MSR operating vents.

Page 12 of 26

WBN Turbine Trip AOI-17

Unit I Rev. 0047 Step Action/Expected Response Response Not Obtained 3.3 BOP Realignment (continued)

6. CHECK MSIVs OPEN. IF vacuum is to be maintained, THEN ENSURE auxiliary boiler is aligned for steam seals.

7. ENSURE adequate FW press:

a. ENSURE two hotwell pumps RUNNING.

b. IF FW isolation reset, THEN ENSURE one condensate booster pump RUNNING if needed for unit conditions.

c. ENSURE CNDS demin pumps OFF.

d. STOP #3 HDT pumps, and CLOSE the discharge valves to condensate heater strings. Notify NAUO performing Attachment 1 that #3 HDT pumps are stopped.

e. STOP #7 HDT pumps, and CLOSE the discharge valves to condensate heater strings.

8. SHUTDOWN any MEW pump NOT required.

9. SHUTDOWN any RCW pumps NOT required.

10. SHUTDOWN any CCW pumps NOT required.

Page 13 of 26

WBN Turbine Trip AOl-17 Unit I Rev. 0047 Step Action/Expected Response Response Not Obtained 3.3 BOP Realignment (continued)

11. ALIGN extraction steam valves and drain valves:

a. CLOSE #1 and #2 Heater extraction steam valves.

b. ENSURE turbine drain valves OPEN.

c. OPEN MEW pump turbine drain valves.

12. PERFORM as required:

a. OBTAIN switching instructions from NEAD, and OPEN main generator PCB(s)

MODs.

b. PULL-TO-LOCK bus duct cooling fans.

c. VERIFY MTOT and seal oil temps STABLE and trending to 95°E.

13. IF MEW isolated to steam generators, THEN REQUEST Chem Lab sample condensate and feedwater prior to re-admitting water to S/Gs from condensate-feedwater system.

14. IF EGTS started, THEN SHUTDOWN one train after I to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and place in P-AUTO:

REFER TO SOI-65.02, Emergency Gas Treatment System, section on Auto EGTS Actuation.

Page 14 of 26

WBN Turbine Trip AOI-17 Unit I Rev. 0047 Step Action/Expected Response Response Not Obtained 3.3 BOP Realignment (continued)

15. IF ABGTS started, THEN SHUTDOWN one train after I to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and place in P-AUTO:

REFER TO SOl-30.06, Auxiliary Building Gas Treatment System, section on Auto Start of ABGTS CAUTION Rx trip bkrs must be cycled to allow reset of MEW when isolated by SI, HI-HI S/C level, or flood level in MS valve vault room. If any SI signal is present with Auto SI blocked, cycling Rx trip bkrs will initiate SI actuation.

16. IF MFW NOT in service, THEN ESTABLISH MFW:

REFER TO Attachment 2, Establishing MEW Eollowing Reactor Trip.

17. CHECK S/C NR levels between 38% IF S/G level can NOT be maintained, and 50%. THEN START M-D AEW pumps.

18. RETURN TO applicable Instruction.

End of Subsection Page.15 of 26

Scenario 7 Attachment 4 E1, Loss of Reactor or Secondary Coolant.

Appendix A through D

WBN Loss of Reactor or Secondary Coolant E-1 Uniti Rev. 0016 j Appendix A (Page 1 ofl)

CLA Breaker Operation CLOSE the following to restore power to cold leg accumulator isolation valves:

BOARD COMPT NOMENCLATURE 480 V Reactor MOV 3F2 1-BKR-63-1 18A Board 1A1-A SIS CLACCUM 1 OUT ISOL (1-FCV-63-1 18) 480 V Reactor MOV I 7F2 I -BKR-63-80A Board IAI-A SIS CLACCUM 3 OUT ISOL (1 -FCV-63-80) 480 V Reactor MOV 3F2 1 -BKR-63-98A Board 1B1-B SISCLACCUM2OUTISOL (1 -FCV-63-98) 480 V Reactor MOV 16F2 1-BKR-63-67A Board IB1-B SIS CLACCUM 4 OUT SQL (1 -FCV-63-67)

Page 20 of 24

WBN Loss of Reactor or Secondary Coolant E-1 Uniti Rev. 0016 Appendix B (Page 1 ofl)

I -FCV-63-I Breaker Operation CLOSE the following to restore power to I -FCV-63-I BOARD COMPT NOMENCLATURE 480 V Reactor MDV 2E1 1-BKR-63-IA Board 1AI-A RWSTTDRHR SUCT (1 -FCV-63-1)

Page 21 of 24

WBN Loss of Reactor or Secondary Coolant E-1 Unit I Rev. 0016 Appendix C (Page 1 ofl) 1-FCV-63-22 Breaker Operation CLOSE the following to restore power to 1-FCV-63-22:

BOARD COMPT NOMENCLATURE 480 V Reactor MOV 2F2 I -BKR-63-22A Board IB1-B SIP COLD LEG INJECTION (I -FCV-63-22)

SHUNT TRIP BREAKER Page 22 of 24

WBN Loss of Reactor or Secondary Coolant E-1 Unit I Rev. 0016 Appendix 0 (Page 1 ofl)

Equipment Evaluation A. EVALUATE plant equipment and systems needed to support long term cooling and recovery actions, as time and personnel availability permits:

1. Cntmt Isolation Status.

2. Emergency Gas Treatment System: One train in operation, REFER TO SOl-65.02.

3. Auxiliary Building Gas Treatment: One train in operation, REFER TO SOl-30.06.

4. Auxiliary Building Isolation alignment: REFER TO SOl-30.06.

5. Main Control Room Isolation alignment: REFER TO SOl-31 .01.

6. ERCW System: Both trains in operation.

7. Component Cooling Water System: Both trains in operation.

8. Ice Condenser System: AHUs energized after cntmt hydrogen concentration verified (if applicable). REFER TO SOI-61 .01.

9. Permanent Hydrogen Mitigation System: lgniters de-energized when no longer needed. REFER TO SOl-268.01.

Page 23 of 24

WBN Administration Of The TI-7.012 I Reactivity Briefing Sheets And Rev. 0005 Reactivity Control Plans Page 21 of 24 Appendix A (Page 1 of 1)

Reactivity Control Plan (Example Form)

Station: WBN Unit: 1 Cycle: 10 Burnup: 10,000 MWD/MTU Revision: 0 Preparer: Reviewer:

I Date RXE I Date Approver: Authorizer RXES or designee I Date Ops I Date RXE support required Onsite? l1Yes DNo Describe:

Titleof ReactivityControl Plan: Power Ascension from 92% to 100% MOL Assumptions: 1. Calculated volumes below assume Tave maintained on Tref.

2. Reactor is stable at 92% RTP.

3. Conditioned power level is assumed to be -96.2% Fuel will continue to decondition at a rate of 2%RTP/day. See TI-45 for further guidance.

MajorSteps: 1. Ramp up to CPL (-96% RTP) at 10*/hr.

2. Ramp up to 100% RTP at 3%/hr per TI-45.

3. Maintain reactor at 100% RTP.

Detailed

Description:

NOTE: See attached plots.

NOTE: Allowing Tave drift will typically reduce the total amount of necessary boration and dilution.

NOTE: Use BEACONDE ICS Screen so long as DOGHOUSE ICS Screen shows AFD is within the ÷/- 3% band.

Ramp Up to CPL (-96%RTP, per the schedule):

1. DILUTE -750 gal of PW.

2. WITHDRAW CBD to -206 steps to control AFD on target.

Ramp Up to 100%:

1. DILUTE -235 gal of PW.

2. WITHDRAW CBD at -215 steps to control AFD on target.

Maintain Power at 100%:

1. BORATE -45 gal of BA for Xenon decay.

2. DILUTE -100 gal/hr for Xenon build-in.

3. WITHDRAW CBD to 220 steps as conditions allow.

WBN Administration Of The Tl-7.012 I Reactivity Briefing Sheets And Rev. 0005 Reactivity Control Plans Page 21 of 24 Critical Parameter Limit Required Action Control Rod Height > RIL Lo If rods < RIL Lo, then ENSURE RCS borated amount specified in Step 1 and WITHDRaW rods.

Activated: I Terminated: I SM or US Date SM or US or RXE Date

Power Ascension from 92% to 100% (MOL) 220

,10 00 -- - -- - - - - - - - - - --

190 . * * . . . . . . . . .

1 p

L) CBD(RampDown)

CBD (Ideal) 170 .. . .. .. . .. . .. . .. ... . .. . .. .

-ri RILL0

= = : I RILLoLo Power (%)

II

Power Ascension from 92% to 100% (MOL) 90 210 85 205 80 200 Power oo CBD 75 195 Q) ----RIL Lo o

70 190 Q RIL LoLo

. .a*::

65 185 60 180 55 . 175 50 I I 170 0:00 2:00 4:00 6:00 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 0:00 Time

Power Ascension from 92% to 100% (MOL) 100 775 1

95 1 770 90 765 p4 85 760 ç 0

r4 755 o\o ii

- - - Powe

750 W 75 Q) RCSCb o 0 70 745 0

65 740 0 XI El) 60 735 I

-730 50 725 0:00 2:00 4:00 6:00 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 0:00 Time

Power Ascension from 92% to 100% (MOL) s ::° 90 80 85 70 H

(t 80 60 I I I o Power 75 I I I 50 Total BA o

70 40 i-1 65- - 30 0

60 -

20 I -10 55-50- 0 0:00 2:00 4:00 6:00 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 0:00 Time

Power Ascension from 92% to 100% (MOL) 100 250 95 225 90 200

85 175 80 150r1

- (1 o\0 Power

75. l2S

__BARatJ o -

70* 100 0

.75 j 4

65 0

60 50 V 25 55 50 0 0:00 2:00 4:00 6:00 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 0:00 Time

Power Ascension from 92% to 100% (MOL) 90 2000 85 1750

-4 (IS 80 1500 o Power 75 1250

- Total PW r1 70 1000 H

65 750 0

60 500 55- I 250 50 I 0 0:00 2:00 4:00 6:00 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 0:00 Time

Power Ascension from 92% to 100% (MOL) 100 220

]

95 215 90 210 85 205 0) 3)

80 200j. Power I CBD I

S-i 75 195.

0) 4J RILL0 0

70 190 0 RIL Lo-Lo Ii 65 l05 60 100 55 175 I

50 I 170 0:00 2:00 4:00 6:00 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 0:00 Time

I hiI Watts Bar Nuclear Plant Uniti General Operating Instructions GO-4 Normal Power Operation Revision 0061 Quality Related Level of Use: Continuous Use Effective Date: 04-01-2011 Responsible Organization: OPS, Operations Prepared By: Brent G. Henderson Approved By: Brian Mcllnay

WBN Normal Power Operation GO-4 Unitl Rev. 0061 Page2of6o Revision Log Rev or Change Effective Affected Page Number Date Numbers Description of RevisionlChange 55 03/09/10 2, 7, 8, 13 Added additional precautions from SERC Mitigation Plan.

56 05/06/10 2, 25 Non-intent change.

Added chemistry hold at 50% lAW CM-I .02 Rev 9, Secondary Chemistry Strategic Plan.

57 08/25/10 2, 6-8, 10, 15, Changed power level where IMP-OUT is 16, 18, 19, 21, considered based on operator comments and 24-25, 27, 28, reordered steps accordingly [PER 232422-0011.

30-33, 35, 36, Added symbol (p) prior to actions that directly 39-40, 43-46, affect reactivity. Updated Source Note 48, 49, 52, identification, updated SELD notification, added 54-56, 58 end of section steps, and made minor editorial changes lAW with Writers Guide, procedure

. upgrades lAW ODM-23.

58 09/24/10 2, 5, 19, 22, Added startup of #3 HD Tank to the 40-45%

46, 49, 50 power level. Moved shutdown of #3 HD Tank pumps and bypass of tank to 40% power level.

Consolidated notes as a result of changes. This is interim action for PER244876. Added verification of runback light prior to stopping first #3 HDT pump based on existing note. Updated SPP titles.

59 11/17/10 2, 22 Revised start of #3 HDT pumping forward to place two pumps in service.

60 02/16/11 2, 11, 13, 18, Minor/editorial change: Added note to P&Land 20, 28, 31, 33, prior to each power acension step concerning #1 34, 36, 41, 51, bearing higher than normal temperature.

54, 56, 58 [PER 293256] Added end of section notices and updated shop names.

61 04/01/11 2, 7, 8, 14, 45, Minor/editorial change: Corrected step numbers, 50 changed name of Load Dispatcher, corrected reference to SOl-5&6.01. (PCR 4798, 4813, 5184, 5240)

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 3 of 60 Table of Contents

1.0 INTRODUCTION

4 1.1 Purpose 4 1.2 Scope 4

2.0 REFERENCES

4 2.1 Performance References 4 2.2 Developmental References 5 3.0 PRECAUTIONS AND LIMITATIONS 6 3.1 PRECAUTIONS 6 3.2 LIMITATIONS 9 4.0 PREREQUISITES 12 5.0 INSTRUCTIONS 13 5.1 General 13 5.2 Unit Startup from 30% to 100% Reactor Power 14 5.3 Unit Shutdown from 100% to 30% Reactor Power 42 5.4 Power Coastdown at End of Life 52 5.5 Frequency Variation Response 55 5.6 Operating with Turbine Controls in Manual Mode 57 6.0 RECORDS 59 6.1 QA Records 59 6.2 Non-QA Records 59 Source Notes 60

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page4of60

1.0 INTRODUCTION

1.1 Purpose This instruction provides actions to perform power ascension from 30% to 100%

Reactor power, power reduction from 100% to 30% Reactor power, and power coast down operations.

1.2 Scope This GO contains the following operations:

5.1 General 5.2 Unit Startup from 30% to 100% Reactor Power 5.3 Unit Shutdown from 100% to 30% Reactor Power 5.4 Power Coastdown at End of Life (EOL) 5.5 Frequency Variation Response

2.0 REFERENCES

2.1 Performance References A. CM-3.01, System Chemistry Specifications B. CM-5.02, Hideout Return Sampling and Analysis C. GO-5, Unit Shutdown from 30% Reactor Power to Hot Standby D. 0-SI-0-3, Weekly Log E. 1-Pl-OPS-1-MCR, Plant Instruction Main Control Room F. 1-Sl-0-20, Hot Channel Factor Determination G. 1-SI-0-21, Excore QPTR H. 1-61-68-28, Primary Radiochemistry Requirements I. 1-SI-68-30, Reactor Coolant System Total Flow Measurement Using Elbow Tap Differential Pressures J. 1-51-92-1, NIS Daily Comparison

WBN Normal Power Operation GO-4 Uniti Rev. 0061

, Page5of6o 2.1 Performance References (continued)

K. 1-Sl-92-5, Hourly Axial Flux Difference Inspection L. SOl-2 & 3.01, Condensate And Feedwater System M. SOl-5 & 6.01, Extraction Steam, Heater Drains, and Vent System N. SOI-27.01, Condenser Circulating Water System

0. SOl-44.01, HTHW Building Heating System P. SO 1-47.02, Turbo-Generator Startup Operation Q. S0l-58.01, Bus Duct Cooling System R. NPG-SPP-01 .2, Administration of Site Technical Procedures S. Nuclear Operating Book T. Tl-45, Determination of Preconditioned Reactor Power U. AOI-17.0, Turbine Trip V. E-0, Reactor Trip or Safety Injection 2.2 Developmental References A. WBN Technical Specifications B. GOI-7, Generic Equipment Operating Guidelines C. SPP-10.4, Reactivity Management Program D. Westinghouse Nuclear Fuel Division, MFRD-01-222, Limitations and Conditions for Westinghouse Fuel Operations, Revision 6, Dated January 2002 (RIMS L360201 11801).

E. NERC Reliability Standard, VAR-002-1.lb

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 6 of 60 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS

1) If a precaution cannot be complieditb,jcv shall initial, date, and write a brief explanation of why the precaution could NOT be corn plied with. Precautions that contain must, shall, or will, must be adhered to.

changes in Reactor power, all rod position indicators (RPI5),

Step Counters, and NIS should be periodically monitored for the following During conditions: [c.61 Correct Power Distribution Quadrant Power Tilts Rod Insertion I

Rod misalignment Inoperable RPls

6. Inoperable rods.

B. Plant Instruction 1-Pl-OPS-1-MCR is applicable at all times and, during changes in reactor power, additional emphasis should be given to indication of reactor thermal power level using the guidance given in 1-PI-OPS-1-MCR. [C.8]

. Maximum Pzr-RCS CB difference is 50 ppm and is maintained by use of Pzr heaters and spray.

If a Turbine load rise is blocked by the Load Limiter, load must be reduced by sing the load reference setter until the VALVE POS LIMIT light is out, then the load limiter setpoint raised using caution to observe that load does not change, then load rise may be resumed.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 7 of 60 3.1 PRECAUTIONS (continued)

Turbine is normally operated in IMP OUT control below 30% turbine load. IMP IN operation above 30% turbine load is permissible as long as the unit remains stable (e.g. no instabilities due to IMP IN operation.)

Full flow Cond Dl polishing is maintained during power ascension if system parameters allow.

During operation above 50% power, every effort must be made to maintain condenser air in-leakage less than 5 cfm.

After refueling, NIS indications may be inaccurate until calibrated at higher power levels. NIS calibration procedures will adjust PRM trip setpoints lower than normal to ensure excore detectors protect against an overpower condition.

Reactor Engineering should be contacted for guidance on core operating recommendations during unusual power maneuvers at End of Life (EOL).

To ensure that NIS reactor power level indications remain within 0 to 2% of true power during power level changes, a check should be performed about every 20% power level change (when greater than 15% power), by comparing calorimetric power to each NIS power range drawer (i.e., the performance of 1-Sl-92-1.) This power level check does not preclude the operating crews from making prompt changes in response to changing plant conditions or needs.

Applicable ICS computer point(s) should be used as an indication of true reactor power when greater than 30% power. [Cl]

When reducing power for compliance to LCO 3.7.1, Reactor Engineering shall be notified to revise neutron flux high reactor trip set points to a value less than or equal to the applicable value specified in Tech Spec Table 3.7.1-1.

Drift of governor valve position has been experienced while the valve position limiter (VPL) was on the governor controller. VPL light (on 1-XX-47-2000) has een LIT and has extinguished without operator action. [c.ioi 1 Inhours Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up to 4 when placing the second Turbine Driven Main Feedwater Pump DMFWP) in service or removing one of two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.

Operation of main generator without automatic voltage control could impact grid voltage requirements. The Load Dispatcher and Operations Duty Specialist DS) should be notified within 30 minutes if the generator is in service without automatic voltage regulator.

Main Generator operation without Automatic Voltage control requires that Narrative Log entries be made (time, .da+/-e, reason & duration)..

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page8of6o 3.1 PRECAUTIONS (continued)

Main Generator operation outside of the Voltage Schedule requires that Narrative Log entries be made (time, date, reason & duration) and that notification be made to Load Dispatcher within 30 minutes.

1)

\%_\

Plant Operations shall notify the Transmission Balancing Authority (BA) or Transmission Operator (TO) of protective relay or equipment failures that create a creditable risk to plant generation. A creditable risk to generation represents a potential reduction in transmission system reliability.

Reliability Directives to the Generator Operator are via the Balancing Authority

\..)( or Transmission Operator. Required action time may range from immediate to no longer than 30 minutes. Actions shall be taken without delay. The directives may be associated with preventing or clearing Local System issues, or neighboring system issues:

Plant operations shall take timely actions as directed by the BA or TO to

\J\ mitigate critical conditions to return the bulk electrical system to a reliable state.

Plant operations shall comply with BA or TO directives unless such actions would violate safety, equipment, regulatory or statutory requirements.

. Plant operations shall immediately inform the BA or TO of the inability to perform directives so that the WA Reliability Entities may implement alternate remedial actions.

14O Failure to comply with the NERC VAR-002 r em nt could result in a Utility Violation and/or monetary penalties.

While the Main Generator is tied to the grid, perform the following:

The Load Dispatcher shall be notified of any Voltage Regulator automatic trips to Manual or urgent Manual Transfers between AUTO and Manual as soon as practical but notification shall be within 30 minutes.

The Load Dispatcher shall be notified prior to a planned Voltage Regulator transfer between Manual and AUTO.

All position changes (to and from AUTO or manual) of the Voltage Regulator shall be entered into the Narrative Log along with the date, time of position change, reasons, anticipated duration and notifications made.

The Greek symbol (p) denotes those steps with actions that directly affect reactivity.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 9 of 60 3.2 LIMITATIONS Turbine loading rates are obtained per SOl-47.02.

Pre-conditioned power levels and maximum allowable rates of power changes are specified by Tl-45, Determination of Preconditioned Reactor Power.

If power is reduced, Tl-45, Determination of Preconditioned Reactor Power, should be consulted for applicable restrictions.

Declared fuel defects as determined by the Fuel Reliability Assessment Team or Shift Manager, have more limiting ramp rates as specified by TI-45.

(i Mode 1, greater than or equal to 50% Reactor power, the indicated Axial Flux

\ Difference (AFD) shall be maintained within the acceptable operating region of Nuclear Operating Book (NOB), Sheet A-I, Target Band vs. Power Level (TS 3.2.3).

Mode I, greater than or equal to 50% Reactor power and AFD monitor Alarm inoperable, AFD must be logged every hour by initiating 1-SI-92-5 (SR 3.2.3.1).

Mode 1, greater than 50% Reactor power and the Quadrant Power Tilt Ratio (QPTR) Alarm inoperable, QPTR must be calculated every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by initiating 1-Sl-0-21 (SR 3.2.4.1).

For a change in the rated thermal power greater than or equal to 15% in

\J. one hour, Chemistry shall check Reactor coolant DE 1-131 specific activity by initiating I-Sl-68-28 (SR 3.4.16.2).

During power changes, letdown shall be maximized to minimize the risk of Crud Induced Power Shift (CIPS).

WBN Normal Power Operation GO-4 Unit I Rev 0061 Page 10 of 60 32 LIMITATIONS (continued)

To prevent high vibratory stresses and fatigue damage to the last stage LP Turbine blades, do not operate Turbine, even for brief periods, outside the following limits:

A & B and C CONDENSER VACUUM LO-LO AND LO ALARMS 6.50 658, 6.2(

6.00 I C ZONE

/1 Regio;Accepiblefor n 0 eCNLY

/ 1096, 5.5

< 5.50 0) z OP RATE ELOW I 0-LO V CUUM 095, 5.3 D 4

.-.-. A BZONES C A RMS(S LID LII ES) 658

, \

w 5.00 __

D

, 508 109 rN C) 0 I 4.50 -1_____

w OJERATEN 7/

/(__ ___

4.00 ..- Tf.SREGI IN _

w 377, 3.40 .

\

z 3.50 r

..- LO-LOVACUUMCZONE LO VACUUM IN C ZONE 3.00 LO-LO-VACUUM A & B ZONE 377, 3.15 LO-VACUUMA & B ZONE OO% U AD 147 MWe 2.50 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 LOAD (MWe)

Generator may be operated without a bus duct cooler up to 60% Turbine load.

L. Reactor thermal power limits:

Reactor thermal power SHALL NOT exceed 100% RTP as defined in I -Pl-OPS-1-MCR Instruction 1-PI-OPS-1-MCR provides guidance on Plant monitoring/t rending NIS and reactor thermal power. [c.8].

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 11 of 60 3.2 LIMITATIONS (continued)

To support shutdown for refueling achieving adequate inventory in the BATs is

\_I\a long lead item that should be considered prior to initiating shutdown.

During power ascension, #1 bearing has experienced higher than normal metal temperature but never exceeded the alarm set point. The cause of the elevated emperature is due to the partial arc admission design of the HP turbine and the less than optimal alignment between the HP turbine and the A LP turbine.

Although this condition is expected, operators should closely monitor #1 bearing metal temperature during power ascensions and take appropriate corrective actions as required. Contact the Predictive Maintenance Group for additional guidance.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Pagel2of6O Date t 1

Th4( Initials 4.0 PREREQUISITES Ic STARTUP No.

?14OTES\

) Throughout this Instruction where h4EI statement occurs, the step should be marked N/A if the stated condition does not exist.

1 ) Prerequisites may be complied in any order. If a prerequisite cannot be complied with, the SM shall initial, date, and write a brief explanation. Prerequisites that contain ust, shall, or will, cannot be N/Ad.

3) This instruction may be entered from a partial shutdown or startup, N/A sections NOT applicable and annotate reason.

[1 REVIEW of Precautions and Limitations Section 3.0 COMPLETE Turbine-Generator load between 25% and 28%.

TAVG being maintained in the operational band.

4] SG level controls being maintained in AUTO.

Holdup Tank AVAILABLE to accommodate RCS letdown.

Steam Dump in the TAVG mode.

6.9kV Unit and RCP boards have been transferred to the I

USSTs.

EHC System should be in OPER AUTO (pushbutton LIT).

Generator pressurized with H2 per Capability Curve in SOI-47.02.

System Load Coordinator has been NOTIFIED.

1] Radiation Protection has been NOTIFIED.

Chemistry has been NOTIFIED.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 13 of 60 Date_________ Initials 5.0 INSTRUCTIONS 5.1 General OTES Section 5 steps must be performe ntally, unless specifically stated otherwise.

nor SM approval must be obtained to deviate.

During normal operation, Radiation Protection should be notified of power changes.

1] IF at End of Life (EOL), and required to initiate power coast down, THEN GO TO Section 5.4, Power Coastdown at End of Life. ,tJ >4 IF performing Startup, THEN NSURE Section 4.0 Prerequisites COMPLETE.

End of Section

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 14 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power NOTE After any significant lube oil perturbation such as a reactor trip or plant startup), it is expected that contaminants in the lube oil system will rise and cause material to be collected in the MTOT strainer and increase the zP across the Turbo TOC filters.

c.

( The following step may be performed anytime after the generator is synchronized to the grid and should be performed as soon as manpower allows. At the Shift Managers discretion, this step may be N/Ad if the lube oil system was NOT shutdown during this outage.

3) Failure to comply with the following NERC VAR-002 requirements could result in a Utility Violation and/or monetary penalties.

) The Load Dispatcher shall be notified of any Voltage Regulator automatic trips to Manual or urgent Manual Transfers between Auto and Manual as soon as practical, Ut within 30 minutes.

The Load Dispatcher shall be notified prior to a planned Voltage Regulator transfer S.between Auto and Manual.

S

) All position changes (Auto or Manual) of the Voltage Regulator shall be entered into the Narrative Log along with the date, time of position change, reasons, anticipated uration, and notifications made.

\Operation of main generator without automatic voltage control could impact grid voltage requirements. Refer to SOl-47.02 for MVAR limits.

Main Generator operation outside of the Voltage Schedule requires that notification be

-IN,,.made to the Load Dispatcher within 30 minutes. Narrative Log entries shall be made that include time, date, reason & duration, and notifications made.

DMain Generator operation without Automatic Voltage control requires that Narrative entries be made (time, date, reason & duration) and that notification be made to Operations Duty Specialist (ODS) within twenty four (24) hours.

11 ENSURE NAUO performs the following:

[1. INSPECT the MTOT strainer AND CHANGE basket if essary.

[1.2] CHECK the o TOC filters AP AND IF any filter(s) need to be change required by SOl-20-01, THEN ENSURE WO is initiated to cha filter(s) AND ENSURE maintenance is notified.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 15 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[2] CHECK SG and Feedwater secondary chemistry

\ specifications are WITHIN LIMITS.

\ CAUTION After refueling, N.Jndications may be inaccurate until calibrated at higher power. DO NOT raise power grter than 75% until Reactor Engineering ensures power range setpoints have been s&to the full power values.

[3] IF this is sta p following refueling, THEN, ENSURE applile portions of the PETs are COMPLETE for operation greater thn 30% power.

\ RxEngr.

[4] ENSURE the remainingmps are ALIGNED and READY for service:

A. Condensate Booster Pumper SOI2& 3.01. D B. Hotwell Pump per SO 1-2 & 3 C. #3 HD Pumps per SOl-5 & 6.01 0 D. #7 HD Pumps per SOl-5 & 6.01 0 NOTE All MSR TCVs must be closed prior to opening any MSR preheat vhs, i.e. no TCV dogged open.

[5] IF Moisture Separator Reheaters are not in service, THEN PLACE (MSRs) in service per SO I-i .04.

WBN Normal Power Operation GO-4 Unit I Rev. 0061

. PageI6of6O Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

\

NOTES

1) I5, Determination of Preconditioned Reactor Power, identifies ramp rates, specific po levels where HOLD times are required, and limits on control rod withdrawal.

2) Powercalation ramp rates and hold times should be per the most conservative of either the4ieI pre-conditioning guidelines of TI-45 or the Turbine loading recommendns of SO 1-47.02.

[6] PERFO 1-SI-92-1 between approximately 30%

and 35% Rctor Power to ensure all Power Range Monitors are equal to o\reater than calorimetric power. [c.7]

[7] LOG the folIowin\

A. Turbine Load Ramit. D B. Control rod withdrawa rate linqit.

NO The Conditioned Power Level (CPL) needs to be çed for ramp rate considerations.

[8] DETERMINE the CPL and ramp rate restS tions from TI-45, Determination of Preconditioned Reactor P&er, AND RECORD section reviewed / restrictions in na?ive log:

RECORD section reviewed / restrictions in table DATA FROM Tl-45 \pERF VERIF liTAL INITIAL Applicable Tl-45 Section Reviewed: IV Ramp rate restrictions: IV

[9] ENSURE letdown flow is maximized.

WBN Normal Power Operation GO-4 Uniti Rev 0061 Page 17 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

CAUTION Raisingfdwater flow to >40% will cause the non-reset MFP turbine condenser inlet and outlet vaIve.tpclose.

NOTES

1) Turbine maybe opete4in IMP IN above 30% turbine load as long as IMP IN does NOT cause unit instabiIit%,[MP IN will control turbine load as a percentage of impulse pressure that correlates to °Md vs. % of vake opening in IMP OUT. This will allow for a more linear load ascensionN Jf

2) Turbine load change may be stopped eprssing the HOLD push button, using VPL, or by depressing the MANUAL push bTh$tQ

[10] IF desired to operate in IMP IN, THEN

[10.1] OBTAIN Unit SRO concurrence to operatel?N4P IN.

Unit SRO

[10.2] PLACE Turbine in IMP IN.

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 18 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued) ftl] INITIATE power rise to between 45 and 49% by performing

\ the following:

I\1] IF during any of the following steps the REFERENCE

\ changes in an undesired manner, THEN

\ ADJUST VPL to stop turbine load rise qR Pi)H TURBINE MANUAL to place the turbine control modeq manual mode and PROCEED to section5.6

[11.2] ENSURpower escala on limits of TI-45 or SOI-47.02 are NOT exceeded.\

[11.3] SET VALVE çSITlON LIMIT to 60% or as desired 5% above Gov Control Indicatio\

[11.4] SET LOAD RATE P\redetermined value.

[11.5] PUSH REFERENCE CNTROL A (raise) button to set desired load in SETTER play.

NOTE\

1) RCS should be diluted to raise TAVG, then Turb load raised along with TAVG. Control rods will be used along with dilution to maintain AI\nd if needed for temperature.

2) During power ascension, #1 bearing has experiencehigher than normal metal temperature but never exceeded the alarm set point. te cause of the elevated temperature is due to the partial arc admission design ohe HP turbine and the less than optimal alignment between the HP turbine and the A\LP turbine. Although this condition is expected, operators should closely monitor #1 bring metal temperature during power ascensions and take appropriate corrective actio as required. Contact the Predictive Maintenance Group for additional guidance.

[11.6] (p) PUSH GO button.

[11.7] MONITOR Generator Megawas RISING.

WBN Normal Power Operation GO-4 Unitl Rev. 0061 Page 19 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[8J CHECK that load rise has STOPPED when reference display equals setter IF id to stop the Io4d change, THEN STOP tFoad change fty depressing the HOLD PushbuttoriNN

[11.9] WHEN desired esurIe the load change, THEN (p) PRESS the GO pt\utton and continue to monitor load.

[11.10] REPEAT Steps 5.2[11.2] throui.2[11.9] to bring load to between 45 and 49%, WHILE CONTNUlNG this instruction during load rise.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 20 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTES TAVO is programmed from 557°F at no load, to 586.2°F at 100% at a rate of 0.29 °FI%

\ower.

2) PcJ\evel is programmed at 25% to 60% as a function of TAvG.

3) Instru ent Maintenance (IM) support is required if controller adjustments are needed.

[12] ONITOR the following as load is raised:

cOMPARE TAVG, AT, and NIS to check indications are cbqistent with expected values. c.ii D

RCPal flow between 8 and 13 gpm per pump. D

Pzr Ievepprogram.

All RPIs, Ste.çounters, Loop AT, and NIS for correct power distributik, quadrant p wer tilts, rod insertion, rod misalignment, ino\rable RPI and inoperable rods. c.ej

, 0

MFW Regs operatinropeI iruto (within 5% from 0 deviation is accePtable)\\ 0

IF MFW Regs not maintaini SG level in the 5% band, THEN ENSURE Instrument Maintenanc(ji1) is notified. C

Feedwater Heater, MSR Drain Tank, Heater Drain Tank level controllers are adjusted to malqtain levels normal.

NOTE MFP suction pressure should be maintained greater than 175 psig.

[13] WHEN required to support MFP suction pressure, THEN PERFORM the following per SO 1-2 & 3.01:

[13.1] START the third HWPump.

[13.2] START I CBP.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 21 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

\ CAUTION Excçding 40% Turbine Load before properly addressing the status of the MFPT Condçser Valves may cause feedwater/condensate oscillations and result in a plant transien\

[14] PERFORM the following PRIOR to attaining 40% Turbine ISQad, to ASSESS and CONTROL the desired status of the M Turbine Condenser valves:

[14.1] ECORD the position of the following valves:

NOMENCLATURE\

\ POSITION LOCATION OPEN CLOSE UNID PERF

____________________________ INITIAL MFPTA CONDENSER CNDS INNç 1-M-2 1-FCv-2-210 MFPTACONDENSERCNDS 1-FCV-2-205 OUTLET 1 MFPT B CONDENSER CNDS INLET 1-FCV-2-211 MFPT B CONDENSER CNDS 1-M.>\ 1-FCV-2-216 OUTLET NOT\

In Mode 1, entry into Tech Spec 3.3.2 condition J mçbe suspended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when placing the second Turbine Driven Main Feedwar Pumps (TDMFWP) in service.

Refer to Tech Spec 3.3.2 table 3.3.2-1.

[14.2] IF all the valves in Step 5.2[14.1j are THEN PERFORM one of the following actions (NIkQption NOT used):

ENSURE BOTH MFP Turbine Trip Circuits FST.

OR

SLOWLY CLOSE THE MFPT INLET and OUTLET CONDENSER CNDS valves LOCALLY for the MFP which is NOT pumping forward.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page22of6O Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTE Due the difference in established range for the pressure transmitters which control AMSACquto arm/block functions (i.e., 1-PT-1-314 and 315) and other turbine impulse pressure tqnsmiffers (e.g., 1-PT-I -72 or 73), AMSAC may remain blocked above an indicated tune load corresponding to a reactor power of 40%. Turbine load may need to be adjusted toqommodate this difference and allow AMSAC arming.

[15] WH reactor power is approximately 40%, THEN PERFOMhe following:

[15.1] CHECIMSAC ARMED by 1-HS-3-264A, AMSAC TEST/BLOK pushbutton 1 RMED 40% light LIT.

\ NOT With verbal approval from Operations SupNQtendent, placing #7 Heater Drain System pumping forward may be deferred until poweri approximately 60%, if system conditions warrant.

[15.2] OBTAIN Chemistry concurrencat#7 HD Tank chemistry is in LIMITS, THEN START #7 HD Pump to pump forward çSOl-5 & 6.01.

[15.3] CLOSE operating MFP Turbine drains (N!ANmp NOT operating):

Description Handswitch Position \In itials MFPTA DRAIN VLVS 1-HS-46-14 CLOSED MFPT B DRAIN VLVS 1-HS-46-41 CLOSED

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 23 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTE St,5.2[16] applicable following Refueling Outage or as requested by System Engineering, otherse NIA.

[1 ENSURE CUNO filters have been cleaned by maintenance by

\ contacting System Engineering after long cycle cleanup or

\rior to startup of MFPs.

[17] WN between 40 and 45% power, THEN

[17.1] ETURN # 3 HD Tank to normal per SOI-5 & 6.01, Stion 8.6.

[17.2] STAkf the first and scond #3 HD Pumps to pump forwar\P\er SOI-5 &

[17.3] ENSURE)W Regrspond, and stabilize in the acceptable

[17.4] CHECK 1-LCV- 106A controlling properly.

N OS

1) With verbal approval from Operations Supeendent, placing the second MFP in service may be deferred until approximately 60%\Power.

2) In Mode 1, entry into Tech Spec 3.3.2 condition J qy be suspended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when placing the second Turbine Driven Main Feedwer Pumps (TDMFWP) in service. Refer to Tech Spec 3.3.2 table 3.3.2-1. \\

[17.5] PLACE the second MFP in seMce per SO01.

[17.6] CLOSE the second MFP Turbine drains (N/A othe>\

MFP):

N Description MFPT A DRAIN VLVS Handswitch 1-HS-46-14 Position CLOSED Initial\ 1 MFPT B DRPJNVLVS 1-HS-46-41 CLOSED

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 24 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTES

1) Step 5.2[18] mib performed at anytime when both MFPTs are in service and in AUTO.

2) With both MFPTs in AUTihy be nec to adjust the MFPT speed control bias on one of the MFPTs to prevenfThfrom ighting each other (oscillating).

[181 IF MFPTs begin oscillating, THE SLOWLY ADJUST one MFPT speed cjbias in the direction (greater than 50), UNTIL M,rssto

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 25 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[\9] WHEN Reactor power is 45%, THEN PERFORM the following:

[.1] ENSURE Turbine Throttle Valve leakoffs LOCKED OPEN:

\

NOMELATURE PERF VERIF LOCATION POSITION UNID INITIAL INITIAL HP TURBINSTEAM T3H1755 LOCKED 1 -LOV.-47-0727 SEAL LEAKOP Under Skirt OPEN CV HP TURBINE STM T3J/755 LOCKED 1-LOV-47-0728 SEAL LEAKOFF \ OPEN CV HP TURBINE STEA\ T3H1755 LOCKED 1-LOV-47-0729 SEAL LEAKOFF \ Under Skirt OPEN CV HP TURBINE STEAM b T3J/755 LOCKED 1-LOV-47-0730 SEAL LEAKOFF OPEN CV

[19.2] IF excessive flis noted m any of leakoff valves, THEN

\ tiflz\

[19.2.11 ENSURE #7 HDnkjpressure is less than #6 heater shell pressu1 and initiate a WO for the applicable Throttle va1

[19.2.2] ENSURE 1-PCV-47-193LAND SEAL STEAM CNDS SPlLLOVERRESS CNTL, operating in conjunction with 1\CV-47-189, HP STEAM SEAL SUPPLY, to MAt F1(AlN Steam Seals at between 16 to 20 psia.

[19.3] ENSURE the following as system paramete.\permit:

[19.3.1] 3HWPumpsRUNNING. D

[19.3.2] CBP(s) RUNNING (when required). \\ D

[19.3.3] 2 MFPs RUNNING (only I required if approved by Operations Superintendent). D

[19.3.4] 2#3HDPumpsRUNNING. D

[19.4] START the 2nd #7 HD Pump per SOl-5 & 6.01.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 26 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

\ NOTE Seaso.çemperatures dictate whether all CCW Pumps are required (N/A if NOT required).

N.5] PLACE remaining CCW Pumps in service to maintain

\\ maximum condenser vacuum per SOl-27.0I.

[19.6]\CHECK Generator H2 pressure sufficient for anticipated

\\ per SOl-47.02, Appendix E, Capability Curve.

[20] MAINTAIWJess than 50% power UNTIL notified by Chemistry that SG andçondensate/feedwater limits for exceeding 50%

are satisfied. \

\

NoTE During steady state operation and pIarçd load changes, indicated Axial Flux Difference (AFD) should be maintained within the Taet Band of Nuclear Operating Book (NOB),

Sheet A-I, Target Band vs. Power Level.

[21] BEFORE exceeding 50% React?Rower, PERFORM 1-Sl-0-21 to: c.gj

[21.1] CHECK AFD within limits.

[21.2] CHECK QPTR within limits.

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 27 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTES

1) \l-45, Determination of Preconditioned Reactor Power, identifies ramp rates, specific per levels where HOLD times are required, and control rod withdrawal limits.

2) Por escalation ramp rates and hold times should be per the most conservative of eitherQie fuel pre-conditioning guidelines of TI-45 or the Turbine loading recomthendations of SO 1-47.02.

3) Turbine lo change may be stopped by depressing the HOLD push button, using VPL, or by dressing the MANUAL push button

4) The Condition4 Power Level (CPL) and needs to be tracked for ramp rate considerations.

[22] DETERMIN the CPL and ramp rate restrictions from Tl-45, Determination Preconditioned Reactor Power, AND RECORD sectioviewed I restrictions in narrative log:

RECORD section reI,ed / res tions in table below:

7

\ N/mA FROM TI-45 PERF VERIF

/ t INITIAL INITIAL Applicable TI-45 Section Reviewed: IV Ramp rate restrictions: IV

[23] CONTINUE ascension to 90% power b4o 74% if following refueling) by performing the following: \

[23.1] IF during any of the following steps the FERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise OR PUSH TURBINE MANUAL to place the turbine control ode in manual mode and PROCEED to section 5.6.

[23.2] ADJUST VALVE POSITION LIMIT to 90% or to 5%

above the Gov Control Indication.

123.3) SET LOAD RATE at predetermined value.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 28 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

\ [23.4] PUSH REFERENCE CONTROL A (raise) button to set

\ desired load in SETTER display.

\ NOTES

1) RCS suld be diluted to raise TAVG, then Turbine load raised along with TAVO. Control rods will used along with dilution to maintain Al and if needed for temperature.

2) During pow ascension, #1 bearing has experienced higher than normal metal temperature it never exceeded the alarm set point. The cause of the elevated temperature isue to the partial arc admission design of the HP turbine and the less than optimal aligment between the HP turbine and the A LP turbine. Although this condition is expec1d, operators should closely monitor #1 bearing metal temperature during power ascenjons and take appropriate corrective actions as required. Contact the Predictive Maintence Group for additional guidance.

[23.5] (p) PUS GO button.

[23.6] MONITOR erator Megawatts RISING.

[23.7] CHECK that lorise has S OPPED when reference equals setrtJJ IF desired to stop the loaange THEN STOP the load change by DRESSlNG the HOLD pushbutton.

[23.8] (p) WHEN desired to resume the l change, THEN PRESS the GO push button and conftue to monitor load.

[24] WHEN power is 48%, THEN CHECK Permissive 70-C, P-8 LO PWR-FLOW TRIP BLOCKED, NOT LIT.

[25] WHEN power reaches 50%, THEN

[25.1] RECORD the time.

TIME

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 29 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[25.2] CHECK AFD monitor alarm NOT in alarm state by the

\\ plant process computer. [83D Alarms]

[261\WHEN power is greater than 50%, THEN H.CK the following:

[26.1] Nermissive 69-E, P-9 RX TRIP FROM TURB TRIP B1s.CKED, NOT LIT.

[26.2] AIarr3-B, POWER RANGE UPR DETECTOR FLUX DEVN,TLIT.

[26.3] Alarm 83-C>OWEA/FGE LWR DETECTOR FLUX DEVNNOTLt\ /

[26.4] Alarm 83-D, PLANçCOMPUTER GENERATED ALARM (SEE ICS), NOT LIT\

[27] IF condenser air in-leakage exds 10 cfm, THEN

[27.1] INITIATE immediate correcti<neasures and

[27.2] ENSURE Operations Superintennt or Plant Manager is notified.

[28] PERFORM 1-SI-92-1 at approximately 55% ctor Power to ensure all Power Range Monitors are equal to oreater than calorimetric power. [Cl]

[29] EVALUATE Placing Building Heat in service from #3 Extraction Steam using SOI-44.01.

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 30 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

CAUTION

3d #7 Heater drains must be pumping forward before exceeding 60% Turbine load.

[ PERFORM the following:

BEFORE Turbine load is above 60%,

[30\J ENSURE all steps that were deferred for heater drains are COMPLETE:

[30.N #3 HD Pump, Section 5.2[17.2], COMPLETE.

[30.1.2]\#7 HD Pump, Section 5.2[15.2] COMPLETE.

[30.2] ENSI*E at least 1 Bus Duct Cooler in service per SOI-581.

NTES

1) Cond Demin Pumps may need to ,tarted at lower power if #7 HD Pumps amps are swinging, or if MFP suction pressure npds to be raised by approximately 40 psig.

2) Operating Cond Demin Pumps at eIevateystem header pressure may cause 1-LCV-6-106A to control outside its optimumçnge and create system swings.

3) Two Cond Demin pumps must be started at the me time.

[31] WHEN system header pressure dictates (, NPSH to MFP),

THEN START two Cond Demin Pumps per SOl-2&3.01.

NOTE In Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when placing the second Turbine Driven Main Feedwater Pumps (TDMFWP) inSrvice.

Refer to Tech Spec 3.3.2 table 3.3.2-1. \j

[32] ENSURE 2 TDMFPs in service (or I TDMFP and one SMFP in service), BEFORE raising power above 60%.

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 31 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

\ CAUTION Operatinbove 85% turbine load with less than three #3 pumps running will limit the #3 HDT level thqtrol valve, 1-LCV-6-106A, to its preset throttled position of approximately 30%

and iIluminatee blue light on the panel above the 1-LCV-6-106A Reset switch. This condition may ai result in a turbine runback.

[33] WHE 0% Turbine load is reached, THEN PERFORI,e following:

[33.1] PLACENrd #3 HD Pump in service per SQl-S & 6.01.

[33.2] ENSURE M\W Regs respor)d, and stabilize in the acceptable ba

[33.3] CHECK 1-LCV 6A con/rlling properly.

[33.4] IF required, THEN PLACE third CBP in servic

[33.5] IF necessary, START the third ond Demin Pump.

[34] ENSURE applicable portions of the PETs e COMPLETE for power operation above 75% power.

RXE

[35] IF Power Range high-flux trip setpoints were reduc following refueling OR activities occurred which could cause e ected NIS response to be non-conservative, THEN ENSURE Power Range high-flux trip setpoints are adjusted i accordance with the applicable system 92 Sls.

IM Date Ti

[36] PERFORM 1-SI-92-1 at approximately 75% Reactor Power to ensure all Power Range Monitors are equal to or greater than calorimetric power. [c.7j

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 32 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[37] ENSURE both Stator Water Heat Exchangers are in service prior to exceeding 75% power [C.7]

\ NOTE The numrs below the pressure indication for 1-PIS-47-13 correspond to four relays (LED5) thaenable the runback logic. The numbers 1, 2, 3, 4 should be illuminated indicating alf{ur relays are enabled.

[38] )cECK HP Turbine Impulse Pressure I Turbine Runback LE (1, 2, 3, 4) lit on panel L-262A, 1-PIS-47-13 TB 729 coluthç T3/J.

[39] IF starts following refueling, THEN CONTINUqscension to 90% RTP by performing the following:

1) Power escalation should bhe monservative of either the fuel pre-conditioning guidelines of Tl- or the Turbine loading recommendations of SOl-47.02.

2) Turbine load change may be stoppedy.depressing the HOLD push button, using VPL, or by depressing the MANUAL pusPkutton

[39.1] IF during any of the following st s the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise.

OR PUSH TURBINE MANUAL to place the turbine ontrol mode in manual mode and PROCEED to section .6

[39.2] SET VALVE POSITION LIMIT at 95% or as desired above the Gov Control Indication.

[39.3] SET LOAD RATE at predetermined value.

[39.4] PUSH REFERENCE CONTROL i\ (raise) button to set desired load in SL I I hR display.

WBN Normal Power Operation GO-4 Unitl Rev. 0061 Page 33 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

\

\ NOTES

1) RCS\hould be diluted to raise TAVG, then Turbine load raised along with TAVG. Control rods w1be used along with dilution to maintain Al and if needed for temperature.

2) During per ascension, #1 bearing has experienced higher than normal metal temperaturbut never exceeded the alarm set point. The cause of the elevated temperature isdue to the partial arc admission design of the HP turbine and the less than optimal alInment between the HP turbine and the A LP turbine. Although this condition is expehed, operators should closely monitor #1 bearing metal temperature during power ascehions and take appropriate corrective actions as required. Contact the Predictive Maintqnce Group for additional guidance.

[39.5] (p) PUS GO button.

[39.6] MONlTORçnerator egawatts RISING.

[39.7] CHECK that lo risJij STOPPED when reference display equals seItr I OR IF desired to stop the lochange THEN STOP the load change by Npressing the HOLD pushbutton.

[39.8] WHEN desired to resume the lo\change, THEN PRESS the GO push button and citnue to monitor load.

[40] BEFORE raising above 80% power, THEN ENSURE the following:

[40.1] 1-LCV-6-106A controlling properly.

[40.2] 1-LCV-6-105A and 105B are NOT open.

WBN Normal Power Operation GO-4 Unit I Rev 0061 Page 34 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

OTE After operations less than 85% Reactor p more than 2 weeks, Reactor Engineering evaluation of Hot Channel Factors per 1-Sl-0-20 is required, before exceeding 90% power.

I IF evaluation of Hot Channel Factors is required, THEN NSURE 1-SI-0-20, COMPLETE.

IkXE Turbine is normally operated in IMP OUT crw 30% turbine load. IMP IN operation above 30% turbine load is permissible as long as the unit remains stable (e.g. no instabilities due to IMP IN operation).

42] IF desired to limit instabilities due to IMP IN operation at loads greater than 90%, THEN 2.1 OBTAIN Unit SRO concurrence to operate in IMP OUT.

Unit SRO

.2] PLACE Turbine in IMP OUT.

NOTE Performing NIS check and adjustment relatively close to 100% power may eliminate the need to RE-PERFORM these actions upon reaching 100% power.

[43] WHEN power is at or above 95%, THEN PERFORM the following

[43.1] ADJUST PR NIS per 1-SI-92-1, NIS Daily Comparison.

[43.2] ENSURE Instrument Maintenance (IM) performs 1-S 1-68-30 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after power stabilizes at 90% or above (N/A if NOT applicable).

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 35 of 60 Date 77M1 Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued) 43.3] ENSURE the following level controllers maintaining levels within normal ranges:

. Feedwater heaters.

MSR drain tanks 44] IF this a startup following a refueling, THEN HOLD power between 94 and 98% to complete post-refueling /

AVA sting.

5] IF startup is following refueling, THEN ENSURE applicable portions of the PETs are COMPLETE for /

full power operation.

FXE 7N)

Tl-45, Determination of PreconditiSrted-R ctorlower, identifies ramp rates, specific

_power levels where HOLD times are required, and control rod withdrawal limits.

Power escalation ramp rates and hold times should be per the most conservative of either the fuel pre-conditioning guidelines of TI-45 or the Turbine loading recommendations of SOl-47.02 Turbine load change may be stopped by depressing the HOLD push button, using

._)ç VPL, or by depressing the MANUAL push button CONTINUE ascension to 100% power by performing the following:

[46.1] IF during any of the following steps the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise OR PUSH TURBINE MANUAL to place the turbine control mode in manual mode and PROCEED to section5.6

[46.2] CHECK VALVE POS LIMIT light is NOT LIT.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 36 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[46.3] SET VALVE POSITION LIMIT at 100% or to 5% above the Gov Control Indication.

[46.4] SET LOAD RATE at predetermined value.

[46.5] PUSH REFERENCE CONTROL A (raise) button to set desired load in SETTER display.

NOTE The Conditioned Power Level (CPL) needs to be tracked for ramp rate considerations.

[47] DETERMINE the CPL and ramp rate restrictions from TI-45, Determination of Preconditioned Reactor Power, AND RECORD section reviewed I restrictions in narrative log:

RECORD section reviewed / restrictions in table below:

DATA FROM TI-45 PERF VERIF INITIAL INITIAL fplicable TI-45 Section Reviewed: IV Ramp rate restrictions: IV NOTES

1) RCS should be diluted to raise TAVO, then Turbine load raised along with TAvG. Control rods will be used along with dilution to maintain Al and if needed for temperature.

2) During power ascension, #1 bearing has experienced higher than normal metal temperature but never exceeded the alarm set point. The cause of the elevated temperature is due to the partial arc admission design of the HP turbine and the less than optimal alignment between the HP turbine and the A LP turbine. Although this condition is expected, operators should closely monitor #1 bearing metal temperature during power ascensions and take appropriate corrective actions as required. Contact the Predictive Maintenance Group for additional guidance.

[47.1] IF returning to this step from AOl-Il, Loss of Condenser Vacuum, ENSURE Operations manager approval is obtained prior to increasing load.

[47.2] (p) PUSH GO button.

[47.3] MONITOR Generator Megawatts RISING.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 37 of 60 Date_________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[47.4] CHECK that load rise has STOPPED when reference display equals setter OR IF desired to stop the load change, THEN STOP the load change by depressing the HOLD pushbutton

[47.5] WHEN desired to resume the load change, THEN (p) PRESS the GO push button and CONTINUE to monitor load.

NOTE Guidance given in 1-PI-OPS-1-MCR, Plant Instruction - Main Control Room, should be used for Reactor power indication.

[47.6] MONITOR NIS, zT and ICS calorimetric computer points as applicable.

NOTE Operation with the VALVE POS LIMIT light LIT is NOT desired. However, operation with VALVE POS LIMIT light LIT is acceptable if unsatisfactory load swings are experienced.

[48] IF desired to place Turbine on the Valve Position Limiter, as the unit approaches full power, and Turbine load set for 100%

power, THEN

[48.1] SLOWLY and CAUTIOUSLY PULSE the VALVE POSITION LIMIT in the LOWER direction while monitoring Megawatts for a drop and the VALVE POS LIMIT light to ILLUMINATE

[48.2] WHEN VALVE POS LIMIT light ILLUMINATES, THEN STOP limiter adjustment.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 38 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

[49] WHEN unit stabilizes at desired Reactor power, THEN

[49.1] ENSURE Load Coordinator is notified that power escalation is complete.

[49.2] ENSURE RADIATION PROTECTION is notified that the power escalation is complete.

[49.3] ENSURE Chemistry is notified that power escalation is complete.

CAUTION Do not raise limiter position, except as noted below in step 5.2[49.4], UNLESS Turbine control is positively controlling Turbine.

[49.4] PERFORM the following if the limiter limits Reactor power to less than 100%:

[49.4.1] ADJUST the SETTER/REFERENCE controls to reduce Turbine load UNTIL VALVE POS LIMIT light is NOT LIT.

[49.4.2] RAISE the VALVE POSITION LIMIT to allow load rise using the SETTER/REFERENCE controls, not to exceed 100% RTP as defined in I -PI-OPS.1 -MCR.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 39 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

CAUTION Power SHALL NOT exceed an 8-hour average of 100% RTP (as defined in 1 -PI-OPS-i-MCR)

NOTES

1) Plant Instruction 1-Pl-OPS-1-MCR is applicable at all times for determination of reactor thermal power, and for limitations regarding the trending of reactor thermal power [c.8].

2) Maintaining reactor thermal power within limits is a continuous action by a Licensed Reactor Operator. Step 5.2[50.1] is exempt from the Continuous Use requirements as described in SPP-2.2, Administration Of Site Technical Procedure

[50] OBSERVE the following restrictions and guidelines:

WHILE operating at full power,

[50.1] MAINTAIN reactor thermal power within the limits provided in 1-Pl-OPS-1-MCR.

NOTE Rod control should be maintained in auto to allow proper response to load reductions and runbacks.

[50.2] MAINTAIN Control Bank D greater than 200 steps during steady state operation, and AFD within the target band of NOB, Sheet A-i to optimize core power distribution.

WBN Normal Power Operation GO4 Unitl Rev 0061 Page 40 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTE IF the turbine control is transferred from IMP OUT to IMP IN, when the turbine is at or near 100% load, THEN the potential exists for the turbine controller to raise load greater than 100%. (this can cause difficulty in controlling the Reactor at power levels near the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months limit of 3459 MWT) IF the controller sets load above 100%, it will not allow load to be dropped below 100% (Hi load Limit) while in IMP IN. The operator must GO TO IMP OUT and lower unit load before attempting to return to IMP IN.

[50.3] IF desired to operate in IMP IN AND conditions permit (e.g. unit stable & governor valve tracking meter at null zero mid position), THEN

[50.3.1] OBTAIN Unit SRO concurrence to operate in IMP IN.

Unit SRO

[50.3.2] PLACE Turbine in IMP IN.

NOTE Operation with the VALVE POS LIMIT light LIT is NOT desired. However, operation with VALVE POS LIMIT light LIT is acceptable if unsatisfactory load swings are experienced.

CAUTION The potential for rapid load adjustments should be thoroughly considered prior to VPL adjustment when the VPL light (on 1-XX-47-2000) is LIT.

[50.4] IF desired to use the VPL for load control, THEN PERFORM one of the following (NIA option NOT used):

[50.4.1] ADJUST Turbine load to desired setting, and LOWER VPL setting as required, OR

[50.4.2] ADJUST VPL to desired setting, and RAISE Turbine load.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 41 of 60 Date________ Initials 5.2 Unit Startup from 30% to 100% Reactor Power (continued)

NOTE Adjustment of VPL and/or Turbine load to maintain signal overlap is expected to minimize load variation.

[50.5] WHEN the VPL light (on 1-XX-47-2000) is LIT, THEN Turbine load may be adjusted by performing either of the following (N/A option NOT used):

[50.5.1] ADJUST VPL to desired setting to change Turbine load, OR

[50.5.2] ADJUST Turbine load to desired setting.

End of Section

WBN Normal Power Operation GO-4 Unit I Rev. 0061

. Page 42 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power SHUTDOWN No.

[1] Operations Superintendent has authorized load reduction.

[2] REVIEW of Precautions and Limitations Section 3.0 COMPLETE.

[3] IF reducing power for compliance to LCO 3.7.1, THEN:

[3.1] ENSURE Reactor Engineering revises neutron flux high reactor trip setpoints per Tech Spec 3.7.1.

[3.2] MAINTAIN power less than revised trip setpoint as allowed by Tech Spec 3.7.1.

[4] ENSURE RADIATION PROTECTION is notified of impending load reduction.

[5] ENSURE Chemistry evaluates status and flowrate of the following for the impending load reduction:

Steam Generator Blowdown.

Condensate Polishers.

[6] ENSURE COND DI Operator is notified of load reduction and to remove beds as needed.

[7] ENSURE Load Coordinator is notified of impending load reduction.

[8] ENSURE letdown flow is maximized.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 43 of 60 Date_________ Initials 53 Unit Shutdown from 100% to 30% Reactor Power (continued)

NOTES

1) For a change in the rated thermal power greater than or equal to 15% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Chemistry shall check Reactor Coolant DE 1-131 specific activity by initiating 1-SI-68-28 (SR 3.4.16.2).

2) QPTR alarms should be expected during significant load reductions, and the required LCO entries should NOT be considered as unplanned.

3) For core operating recommendations for situations such as End of Life or unusual power maneuvers, contact Reactor Engineering.

4) Turbine load change may be stopped by depressing the HOLD push button, using VPL, or by depressing the MANUAL push button.

5) Tl-45, Determination of Preconditioned Reactor Power, identifies rate of power decreases when plant conditions and/or operating limitations do not require a faster reduction in power.

6) The Conditioned Power Level (CPL) needs to be tracked for ramp rate considerations.

[9] DETERMINE the CPL and ramp rate restrictions from TI-45, Determination of Preconditioned Reactor Power, AND RECORD section reviewed I restrictions in narrative log:

RECORD section reviewed I restrictions in table below:

DATA FROM TI-45 PERF VERIF INITIAL INITIAL LApplicable TI-45 Section Reviewed:

Ramp rate restrictions:

IV IV

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 44 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

NOTE Controlling load reductions, Rod position and boron concentration will ensure Axial Flux remains within allowed limits. (For example, Boric acid addition can be set up to control rate of Rod insertion during a downpower to control iXI within the required limits)

[10] REVIEW the following to ensure Axial Flux requirements are understood:

. Axial Flux Target Band from Nuclear Operating Book D e Guidance for controlling Axial Flux in Reactivity Briefing Sheet. I:

. Reactor Engineering operating recommendations (if available) D

[11] MAINTAINAxiaI Fluxwithin 3% oftheAFDtargetfrom 100%

to 40% by ADJUSTING:

. Boron Concentration per SOI-62.02. D

Load rate. D

Control Rod Position. D NOTES

1) Turbine may be operated in IMP IN above 30% turbine load as long as IMP IN does NOT cause unit instability. IMP IN will control turbine load as a percentage of impulse pressure that correlates to % load vs. % of valve opening in IMP OUT. This will allow for a more linear load change.

2) Turbine load change may be stopped by depressing the HOLD push button, using VPL, or by depressing the MANUAL push button

[12] IF desired to operate in IMP IN, THEN

[12.1] OBTAIN Unit SRO concurrence to operate in IMP IN.

Unit SRO

[12.2] PLACE Turbine in IMP IN.

WBN Normal Power Operation 00-4 Unit I Rev. 0061 Page 45 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

[13] INITIATE load reduction by PERFORMING the following on the Turbine EHC panel:

[13.1] IF during any of the following steps the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise OR PUSH TURBINE MANUAL to place the turbine control mode in manual mode and PROCEED to section 5.6

[13.2] ADJUST REFERENCE CONTROL V (lower) button to set desired load in SETTER display.

[13.3] SET LOAD RATE as required.

[13.4] (p) PUSH GO button.

[13.5] MONITOR Generator Megawatts DROPPING.

[13.6] CHECK that load change has STOPPED when reference display equals setter OR IF desired to stop the load change, THEN STOP the load change by DEPRESSING the HOLD pushbutton

[13.7] WHEN desired to resume the load change, THEN (p) PRESS the GO push button and continue to monitor load.

[13.8] ADJUST VALVE POSITION LIMIT to 5% above the Gov Control Indication or as needed.

[13.9] REPEAT Steps 5.3[13.1] to 5.3[13.5] to achieve desired load.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 46 of 60 Date_________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

CAUTION Do NOT exceed load rate of 5%/minute, or 10% step change

[14] MONITOR the following during the load reduction:

[14.1] TAVG following TREF program.

[14.2] All RPIs, Step Counters, Loop AT, and NIS for correct power distribution, quadrant power tilts, rod insertion, rod misalignment, inoperable RPIs, and inoperable rods[c.6J NOTE If the Unit Shutdown was initiated to enter a Refueling Outage, the following step may be N/Ad.

[15] PERFORM 1 -Sl-92-1 at approximately 80% Reactor Power to ensure all Power Range Monitors are equal to or greater than calorimetric power.[c.7]

NOTES

1) Shutdown of Cond Demin Pumps and #3 HD Pumps is based on header pressure, and the ability of the HD Pumps to pump forward.

2) Operating Cond Demin Pumps at elevated system header pressure may cause 1-LCV-6-106A to control outside its optimum range and create system swings.

[16] WHEN system header pressure dictates (e.g., NPSH to MFP),

THEN REMOVE the following from service:

[16.1] One of the three CBPs per SOl-2 & 3.01.

[16.2] One of the three Cond Demin Pumps at below 80%

feedwater flow per SO 1-2 & 3.01.

[16.3] CHECK I -LCV-6-1 06A controlling properly.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 47 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

NOTES

1) In Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when removing one of the two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.

2) One MFP may be removed from service below 60%.

3) Operation between 45% and 60% power, with only on MFP in service, must be approved by Operations Superintendent.

4) Runback circuitry being armed is verified on 1-L-262 on 1-PIS-47-13, HP TURBINE IMPULSE STEAM PRESSURE [729/T3J].

5) HDT Runback is armed when Relay No. 2 is lit and MFP Trip Runback is armed when Relay No. 3 is lit. There is a 3-second time delay after the #3 HDT Runback logic is made before the Runback is initiated.

6) If holding less than 60% power, Cond Demin Pumps may be left running.

[17] WHEN system header pressure dictates (e.g., NPSH to MFP),

THEN REMOVE the following equipment from service:

[17.1] SIMULTANEOUSLY STOP both operating Cond Demin Pumps per SOl-2 & 3.01.

[17.2] VERIFY 1-PIS-47-13, Relay No.2 is NOT LIT [1-L-262],

THEN STOP one #3 HD Pump.

[18] WHEN 65% power is reached, THEN STOP one of the two #7 HD Pumps.

NOTE If the Unit Shutdown was initiated to enter a Refueling Outage, the following step may be NIAd.

[19] PERFORM 1-Sl-92-1 at approximately 60% Reactor Power to ensure all Power Range Monitors are equal to or greater than calorimetric power. [Cl]

WBN Normal Power Operation GO-4 Unit I Rev. 0061

. Page 48 of 60 Date_________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

[20] IF #3 Extraction Steam in service to Auxiliary Steam Header, THEN

PLACE Auxiliary Boiler in service per SOI-12.01 OR

REMOVE Building Heat System from service using SOl-44.01.

[21] WHEN 50% power is reached, THEN CHECK Permissive 69-E, P-9 RX TRIP FROM TURB TRIP BLOCKED, LIT.

[22] WHEN 48% Reactor power is reached, THEN CHECK Permissive 70-C, P-8 LO PWR-FLOW TRIP BLOCKED, LIT.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 49 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

[23] WHEN 45% power is reached, THEN REMOVE the following equipment from service:

[23.1] IF condenser vacuum will permit, THEN REDUCE the number of CCW Pumps per SOl-27.0l.

NOTE In Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when removing one of two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.

[23.2] IF 2 MFPs are in service, THEN SHUTDOWN one MFP per SOl-2 & 3.01.

[23.3] STOP the 2nd #7 HD Pump, AND PLACE both #7 HD Pumps handswitches in P-T-L.

[23.4] CLOSE the #7 HD Pumps discharge valves [1-M-2]:

Description Handswitch Initials

7 HD PMPS TO HTR STRINGA 1-HS-6-143A

7 HD PMPS TO HTR STRINGB 1-HS-6-163A

7 HD PMPS TO HTR STRINGC 1-HS-6-184A

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 50 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

CAUTION

3 HDT should be placed on full bypass before planned tripping of main turbine to prevent back filling of #2 heaters. Backfilling could result in auto isolation of all three #2 heaters on Hi HI level.

[24] WHEN 40% power is reached, THEN REMOVE the following equipment from service:

[24.1] STOP the remaining #3 HD Pumps, and place handswitch in PULL-TO-LOCK:

Description Handswitch Position Initials

3 HEATER DRAIN PMPA 1-HS-6-112A R-T-L

3 HEATER DRAIN PMP B 1-HS-6-117A P-T-L

3 HEATER DRAIN PMP C 1-HS-6-122A P-T-L

[24.2] CLOSE the #3 HD Pumps discharge valves. [1-M-2]

Description Handswitch Initials

3 HD PMPS TO HTR STRJNGA 1-HS-6-108A

3 HD PMPS TO HTR STRINGB 1-HS-6-109A

3 HD PMPSTO HTR STRINGC 1-HS-6-I1OA

[24.3] PLACE #3 HDT in Full Bypass Operation in accordance with SOI-5 & 6.01, Section 8.5 NOTE If the Unit Shutdown was initiated to enter a Refueling Outage, the following step may be N/Ad.

[25] PERFORM 1-Sl-92-1 at approximately 40% Reactor Power to ensure all Power Range Monitors are equal to or greater than calorimetric power. [Cl]

WBN Normal Power Operation GO-4 Unit I Rev 0061 Page 51 of 60 Date________ Initials 5.3 Unit Shutdown from 100% to 30% Reactor Power (continued)

NOTE AMSAC is blocked if below 40% power for greater than 360 sec.

[26] WHEN less than 40% power, THEN CHECK 1-HS-3-264A, AMSAC TEST/BLOCK pushbutton, AMSAC BLOCK <40%, light LIT.

[27] COORDINATE with Chemistry to establish SG monitoring per CM-5.02, Hideout Return Sampling and Analysis.

[28] WHEN 30% power is reached, THEN PERFORM the following:

[28.1] ENSURE Turbine is operating in IMP OUT.

[28.2] STOP I of the two operating CBPs per SOl-2 & 3.01.

[28.3] STOP I of the three operating HW Pumps.

[29] IF Reactor and Turbine shutdown or low power operation is required, THEN GO TO GO-5, Unit Shutdown from 30% Reactor Power to Hot Standby.

End of Section

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 52 of 60 Date________ Initials 5.4 Power Coastdown at End of Life NOTE[c.2]

This section provides instructions for core burnup cycle length extension using power coastd own.

Reactor power and turbine power slowly coasts down from full power at a predicted rate with TAVG and TREF being maintained on program. Core cycle may be extended for 30 days or more.

Coastdown enables the plant to reach the refueling date with a core burnup within the prescribed burnup window if the normal cycle length is insufficient for the calendar refueling date.

[1] REVIEW of Precautions and Limitations Section 3.0 COMPLETE.

[2] ENSURE Reactor Engineering is contacted for predicted reactor power reduction vs. Time (EFPD) during coastdown.

[3] ENSURE RCS CB is less than or equal to 50 ppm.

[4] ENSURE Holdup Tanks and Waste Gas Decay Tanks have sufficient capacity to hold excess water from dilution.

[5] ENSURE RADIATION PROTECTION is notified of power coastdown.

[6] ENSURE Chemistry is notified of power coastdown.

[7] ENSURE COND DI Operator is notified of power coastdown and to remove beds as needed.

[8] ENSURE Load Coordinator is notified of power coastd own.

[9] ENSURE letdown flow is maximized.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 53 of 60 Date________ Initials 5.4 Power Coastdown at End of Life (continued)

CAUTIONS

1) Reactor power changes should be limited to 1%/hour to avoid Xenon peaking which could force plant shutdown.

2) Do NOT perform unnecessary power maneuvers or testing, e.g., turbine valve test, which could result in uncontrollable Xenon oscillation.

3) Nonessential work on systems which could cause plant upset should be deferred

4) Secondary plant runbacks such as MFP trip or #3 HD Tank runback require Unit shutdown if Reactor power is not promptly returned to pre-transient level due to the resulting severe Xenon transient.

5) Management should be consulted to evaluate the feasibility of a Unit restart if a Reactor trip occurs with RCS CB less than 50 ppm.

6) Do not exceed the positive AFD limit of NOB, Sheet A-I during power coastdown.

NOTES

1) TAVG is programmed from 557°F at no load to 586.2°F at 100%, at a rate of 0.29 °FI%

power.

2) To maintain TAVG and TREF on program, the operator will be required to reduce reactor power daily during coastdown. Predicted daily power reduction varies during coastdown, and is a function of Effective Full Power Days (EFPD.)

3) For core operating recommendations during coastdown or unusual power maneuvers, Reactor Engineering should be contacted.

[10] MONITOR TAVG on program with TREF within 1.5°F

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 54 of 60 Date_________ Initials 5.4 Power Coastdown at End of Life (continued)

NOTE Placing an unborated mixed bed in service should be performed only after consultation and concurrence with plant management.

[11] WHEN RCS CB is less than or equal to 50 ppm, THEN DEBORATE RCS as necessary to maintain TAVG on program with TREF per SOl-62.04.

NOTE Alarm 64-F, C-Il BANK D AUTO WITHDRAWL BLOCKED, will be LIT when Bank D rods are withdrawn to 220 steps.

[12] IF deboration using Mixed Bed Demin is ineffective for maintaining TAvG-TREF on program, THEN WITHDRAW Rods to maintain TAVG program.

[13] WHEN Rods are fully withdrawn, THEN LOWER Turbine load slowly to maintain TAVG program.

[14] REFER TO Section 5.3 to remove secondary equipment as load drops.

End of Section

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 55 of 60 Date_________ Initials 5.5 Frequency Variation Response NOTE The actions of this Section assume all data and voice communications are lost between WBN and System Load Coordinator.

[1] MONITOR system frequency.

[2] ATTEMPT to establish communications with System Load Coordinator.

[3] WHEN communications with System Load Coordinator established, THEN FOLLOW Load Coordinators instructions for restoration, and RETURN to Instruction in effect.

[4] IF communications with System Load Coordinator CAN NOT be established, THEN CONTINUE this Instruction.

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 56 of 60 Date________ Initials 5.5 Frequency Variation Response (continued)

CAUTION The following guidance does not authorize exceeding any established parameter limitation for equipment or Unit operation. Normal trip and safety setpoints continue to apply.

[5] CONTROL Unit load per the following table:

IF frequency is THEN PERFORM the following:

INITIATE reactor or turbine trip, and Greater than 60.50 Hz GO TO E-O, Reactor Trip or Safety Injection or AOl-17, Turbine Trip (if below 50% load)

Greater than 60.15 Hz DROP Unit load at 1% per minute UNTIL frequency less than 60.03 Hz Between 60.15 Hz GO TO Step 5.5[1]

and 59.85 Hz Less than 59.85 Hz RAISE Unit load at 1% per minute to maximum of 100%

UNTIL frequency greater than 59.98 Hz Less than 57.50 Hz INITIATE reactor or turbine trip, and GO TO E-0, Reactor Trip or Safety Injection or AOl-I 7, Turbine Trip (if below 50% load)

End of Section

WBN Normal Power Operation GO-4 Uniti Rev. 0061 Page 57 of 60 Date________ Initials 5.6 Operating with Turbine Controls in Manual Mode NOTES

1) This section should only be used when the OPERATOR AUTO mode is malfunctioning and the turbine is online.

2) When the turbine controls are in MANUAL mode the active Turbine Manual buttons will be illuminated.

3) Turbine load changes immediately when a raise or lower button is pressed.

4) Brief momentary button presses are best for making small load changes.

5) Raising and Lowering load contained in steps 5.6[2j and 5.6[3j below may be used alternatively to achieve desired load.

[1] IF turbine controls are NOT in TURBINE MANUAL mode and TURBINE MANUAL mode is desired, THEN PRESS TURBINE MANUAL button in TURBINE MODES group

[2] INITIATE load reduction by PERFORMING the following on the Turbine EHC panel

[2.1] (p) MOMENTARILY PRESS the lower button (GV) in the TURBINE MANUAL group.

[2.21 MONITOR REFERENCE DROP.

[2.3] REPEAT Steps 5.6[2.1] to 5.6[2.2] achieve desired load.

WBN Normal Power Operation GO-4 Unit I Rev.. 0061 Page 58 of 60 Date________ Initials 5.6 Operating with Turbine Controls in Manual Mode (continued)

CAUTION Raise and Lower buttons operate Governor Valves at a rate of 33%! minute. If Fast push button is also depressed at the same time the valve movement rate is 133.3%! minute

[3] INITIATE load increase by PERFORMING the following on the Turbine EHC panel

[3.1] (p) MOMENTARILY PRESS the raise button (GV) in the TURBINE MANUAL group.

[3.2] MONITOR REFERENCE INCREASE.

[3.3) REPEAT Steps 5.6[3.1] to 5.6[3.2] achieve desired load.

[4] IF OPERATOR AUTO turbine control mode is desired, THEN PRESS OPER AUTO button in TURBINE MODES group.

End of Section

WBN Normal Power Operation GO-4 Unit I Rev. 0061 Page 59 of 60 6.0 RECORDS 6.1 QA Records The following documents are QA records and handled in accordance with the Document Control and Records Management (DCRM) program:

Completed Data Package 62 Non-QA Records None

WBN Normal Power Operation 00-4 Unit I Rev. 0061 Page 60 of 60 Source Notes (Page 1 ofl)

Implementing Requirements Statement Source Document Statement Nuclear Instrumentation Miscalibration SOER 90-003 C.1 Coastdown of a Unit INPO OER 89-3497 C.2 Nuclear Fuel Defects recommendation SOER 90-002 C.3 2.C Turbine operation in IMP IN/IMP OUT Westinghouse Ltr C.4 modes. DELETED on June 11,1996 GP-89-155 per Westinghouse IetterTG 96-031.

Turbine low load/high back pressure Westinghouse Advisory Ltr 86-02 C.5 operations Control rod mispositioning SOER 84-02, Rec. 8 C.6 Decalibration Effects of Calorimetric Westinghouse Bulletin C.7 Power Measurements on the NIS ESBU-TB-92-14-R1 Revise GOs to provide guidance to WBPER96O26O C.8 prevent exceeding (power) limits.

Specify instruments to be monitored Corrective action to prevent missing WBPER97OIO1 C.9 surveillance requirements.

Both WBN and SQN have experienced WBPER 02-017251 C.10 drift while on VPL.

ML12074A045

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1.0 INTRODUCTION

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

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