ML090720036

2009 Initial Examination 05000327-09-301 and 05000328-09-301, Draft Simulator Scenarios

ML090720036
Person / Time
Site:	Sequoyah
Issue date:	02/04/2009
From:	- No Known Affiliation
To:	NRC/RGN-II
References
50-327/09-301, 50-328/09-301 50-327/09-301, 50-328/09-301
Download: ML090720036 (281)

Text

BORON.txt 0[REACTF-VERS SQ2.1]BORATION/DILUTION CALCULATION SEQUOYAH UNIT 1 CYCLE 16 RCS AVG TEMP 560.0 DEG F RCS PRESSURE 2235.0 PSIG PZR LEVEL 39.4%MAKEUP WTR CONC.0 PPM BORIC ACID CONC 6820.0 PPM INITIAL CONC FINAL BORIC ACID MAKEUP WTR BORON CONC CHANGE BORON CONC ADDITION ADDITION (PPM)(PPM)(PPM)(GAL)(GAL)----------

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1475.0-9.7 1465.3.0 421.4 0 page 1 Page 1 of 2 NRC09A Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION Sim. Setup Reset IC- 188 Perform switch check. Allow the simulator to run for at least 3 minutes before loading SCEN file or starting the exercise. This will initialize ICS.

Load SCENS: NRC09A Place simulator in RUN.

Place OOS equipment in required position with tags. Clear alarms. Initialize simulator at 24 % RTP. Place Mode 1 placard on panels.

Place A Train Week sign on the simulator Active when SCENS loaded imf RH01A f:1 ior ZLOHS7410A_GREEN f:0 1A-A RHR PUMP INOPERABLE.

PLACE 1A-A RHR PUMP HS IN PTL AND TAG WITH HOLD ORDER.

Place Protected equipment tags on B Train RHR Pump, SI Pump, and CCP.

Event 1 INCREASE POWER Event 2 When Power change complete as Directed by Lead Examiner Insert: Key-1 imf RX06B f:1 k:1 PZR LEVEL TRANSMITTER FAILS LOW CHNL 2 68-335 If MSS or MIG contacted to trip Bistables, inform the crew that IMs will report to the MCR in ~45 minutes.

Event 3 When LT AOP and Tech Spec Eval complete as Directed by Lead

Examiner Insert: Key-2 imf RD07D4 f:1 k:2 DROPPED ROD D-4 (Rx Trip Not required)

If dispatched to investigate at Rod control panels report no obvious problem. Need maintenance to investigate. Report in ~5 min.

If MSS contacted to initiate maintenance respond maintenance personnel will report to the MCR in ~30 min.

Event 4 When Rod AOP and Tech Spec Eval complete as Directed by Lead Examiner Insert: Key-3 irf TCR02 f:2 k:3 Inadvertent turbine trip.

IF DISPATCHED to investigate wait ~2 min THEN report maintenance personnel inadvertently bumped local trip device.

Page 2 of 2 NRC09A Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

Event 5 Active when SCENS loaded Imf EG07 f:1 MAIN GENERATOR TRIP FAILURE (Gen PCBs can be manuallay opened)

Event 6 When crew Announces Turbine Trip Using PA system (AOP-S.06, Step 8) as Directed by Lead Examiner Insert: Key-4 imf RD07M4 f:1 k:4 imf RD07M12 f:1 k:4 imf RD07D12 f:1 k:4 DROPPED ROD M-4

DROPPED ROD M-12 DROPPED ROD D-12

Note: Simulates dropping remainder of rods in the group to require Rx Trip.

Event 7 Active when SCENS loaded imf RP01C f:1 BOTH RX TRIP BKRS FAIL TO OPEN (ATWS)

When dispatched to open Reactor Trip Breakers locally, wait ~3 min (Note: Delay as necessary until Emergency Boration is initiated) and insert: Key-6 irf RPR05A f:1 k:5 irf RPR05B f:1 k:5 RX TRIP BREAKER A MANUAL TRIP RX TRIP BREAKER B MANUAL TRIP Note: Simulates personnel opening reactor trip breakers locally.

Event 8 When FR-S.1 Complete as Directed by Lead

Examiner Insert: Key-7 imf FW23C f:25 r:120 k:6 LOOP 3 FEEDWATER LINE BREAK INSIDE CNTMT. Event 9 Active when SCENS loaded imf RP07 f:1 FAILURE OF HI-HI CNTMT PRESS LOGIC TO INITIATE PHASE B CNTMT ISOLATION.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 1 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior Console Operator:

No action required for Event 1 Indications available:

None: Crew will continue power increase from 24% IAW 0-GO-4, Section 5.5 at Step [21]

CREW BOP Increase Turbine Load as directed RO Withdraw Control Rods as directed RO Perform dilutions as directed Evaluator Note:

The following Steps are from 0-SO-62-7 Boron Concentration Control , Section 6.2, Dilute CAUTION 1: When making an RCS dilution of

>3000 gallons, it should be done in batches with an RCS boron concentration verification at the halfway point (e.g., 1500 gallons). Allow at least 15 minutes between batches.

CAUTION 2; Returning the Boric Acid Blender to service after unplugging, cleaning, or maintenance on the Boric Acid System could introduce debris, sludge, air or chunks of solidified boron into the CCP suction resulting in pump damage. Extreme care must be exercised to properly flush the Boric Acid Blender system following an outage.

NOTE 1: If an excessive amount of dilution is required (plant startup), the pressurizer heaters should be energized to cause pressurizer spray operation for equalizing boron concentration in RCS and pressurizer.

NOTE 2: Dilute mode will be used anytime a long-term positive reactivity addition is desired. The operator should use the normal dilute mode whenever conditions permit.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 2 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior RO ENSURE unit is NOT in a Tech Spec or TRM action that prohibits positive reactivity additions.

NOTE: HUT level increase of 1% is equal to 1380 gallons (TI-28 fig. C.21)

RO RO ENSURE makeup system is aligned for AUTO operation in accordance with Section 5.1.

RO RECORD the quantity of dilution water required to achieve desired boron concentration using Appendix D. (N/A for minor power changes)

NOTE Due to eyeball interpolation the verified calculation may slightly differ from the initial calculation. The following signoff indicates that any differences in the two results have been discussed and are close enough to be considered validated.

SRO PERFORM Appendix I Independent Verification of Calculation for Amount of Boric Acid or Primary Water. (N/A if App. D was performed by SRO to verify data from Rx Engineering) (Step not required provided in shift turnover package)

RO PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the STOP position.

RO PLACE [HS-62-140B], CVCS Makeup Selector Switch to the DILUTE position.

RO ENSURE [HS-62-140D], Boric Acid Valve to the Blender is CLOSED (Green light is LIT). RO SET [FQ-62-142], Batch Integrator for the desired quantity.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 3 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior NOTE: Primary Water Flow Controller

[FC-62-142] receives its reference signal (70 gpm) from setpoint potentiometer (dial indicator) located on panel M-6. A setpoint of 35% corresponds to a 70 gpm primary water flow rate.

RO ADJUST [FC-62-142], Primary Makeup Water Flow Controller for the desired flow rate.

RO PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the START position.

NOTE: Flow oscillations and/or erratic controller response may require manual operation of Primary Water Flow Controller

[FC-62-142] until stable conditions exist.

RO NOTE: Alternate dilution in small amounts is acceptable on a regular basis, provided no significant changes in seal water temperature or seal leakoff are indicated. Batches of 5 to 10 gallons may be added through FCV-62-144 on a frequency not to exceed once per 30 minutes. ICS points for No. 1 seal leakoffs and seal water temperatures on the RCPs should be monitored during and after dilution.

RO NOTE: It may take approximately 15 minutes before any changes to reactivity are indicated on nuclear instrumentation or RCS temperature indication.

RO MONITOR nuclear instrumentation and reactor coolant temperature to ensure the proper response from dilution.

RO IF [LI-62-129], Volume Control Tank Level, increases to 63

percent, THEN ENSURE [LCV-62-118], Volume Control Tank Divert Valve OPENS to divert excess water to the Holdup Tanks.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 4 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior RO Lead Examiner may direct initiation of the next event at his discretion. Steps on the next two pages are associated with performance of repetitive dilutions or may not be performed until all dilutions are complete.

RO [17] IF power increase in progress and additional dilutions will be required, THEN use this table to re-perform steps

[4] through [18].

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 5 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 6 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior RO REALIGN the blender controls for AUTO makeup to the CVCS in accordance with Section 5.1.

RO ENSURE dilution(s) is logged in Unit Narrative Log.

NOTE 6 Sample may be obtained at normal RCS sample intervals provided the unit is at power and the unit response following the dilution is as expected.

IF RCS boron sample is required, THEN NOTIFY Chem Lab to obtain RCS boron sample.

Evaluator Note: The following Steps continue the 0-GO-4 Section 5.5 power increase at step [22].

BOP RO RO SRO (Step is N/A based on turnover information)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 7 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior CREW (Concentration will be within acceptable range)

SRO (Step will be N/A)

BOP BOP SRO (Step will be previously completed)

(Pumps will be aligned and ready for service)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 8 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior BOP CREW BOP SRO (Step should be N/A)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 9 of 38 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior SRO (Chemistry will be within limits per turnover information)

SRO (Step will be N/A)

SRO (SI has been completed)

SRO CREW SRO When power has been raised sufficiently lead examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 10 of 38 Event

Description:

Pressurizer Level Channel Fails Low Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 2 Indications available: Annunciator XA-55-5A Window E-3 "LS-68-335E/D PRZR LVL LOW HEATER OFF & LETDOWN SECURED" Indicator LT-68-335 indicates Zero Letdown is Isolated Pressurizer Heaters turn off RO Diagnose and announce failure.

SRO Enter and direct actions of AOP-I.04 Section 2.4 RO RO (RNO Required)

RO (RNO Required)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 11 of 38 Event

Description:

Pressurizer Level Channel Fails Low Time Position Applicant's Actions or Behavior SRO Action 6 (From Table 3.3-1 Item 11) Applies N/A Action 2a (From Table 3.3-10 Item 7) Applies Action b applies until selector switch is used to remove the failed channel from heater control.

RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 12 of 38 Event

Description:

Pressurizer Level Channel Fails Low Time Position Applicant's Actions or Behavior CREW (Appendix J will apply)

SRO Lead Examiner may cue next event when AOP I.04 and Tech Spec Evaluation are complete.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 13 of 38 Event

Description:

Control Bank D Group 1 Dropped Rod (D-4)

Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 3 Indications available: Control Bank D Rod D-4 Rod Bottom Light Lit and RPI indicates Zero. Annunciator XA-55-4B Window D-7 "FULL LENGTH RODS RODS AT BOTTOM Additional Annunciators - Various Automatic Rod Withdrawal RO Diagnose failure and place rods in manual to stop withdrawal Refer to Annunciator Response Procedure SRO Enter and direct action of AOP-C.01 Section 2.2 RO RO RO BOP/RO CREW OR (If applicable RNO action N/A <50% power)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 14 of 38 Event

Description:

Control Bank D Group 1 Dropped Rod (D-4)

Time Position Applicant's Actions or Behavior RO S N/A Action c App lies N/A N/A N/A DNB Parameters LCO 3.2.5 Action may apply momentarily while RCS pressure is <2220 psia (2 205 psig)

S R O OR (N/A Power already less than 7 5%) (STA may be requested to perform SDM Calcula tion)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 15 of 38 Event

Description:

Control Bank D Group 1 Dropped Rod (D-4)

Time Position Applicant's Actions or Behavior CREW OR (If applicable RNO action N/A <50% power)

CREW CREW CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 16 of 38 Event

Description:

Control Bank D Group 1 Dropped Rod (D-4)

Time Position Applicant's Actions or Behavior (RNO Required)

Lead Examiner may cue the next event when Tech Spec Evaluation Complete and SRO has determined that AOP-C.01 cannot continue until repairs complete.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 & 5 Page 17 of 38 Event

Description:

Inadvertent Main Turbine Trip, Main Generator Fails to Trip Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 4 Indications available:

Main Turbine Trip: Alarm XA-55-4C (Turb 1st out) Window E-4 "ZS-47-24 AUTO STOP TURBINE TRIP" Steam Dump Valves Open Turbine Stop Valves Closed

Main Generator Fails to Trip: Alarm XA-55-1A Window B-1 "GENERATOR REVERSE POWER TRIP and Generator PCBs not Open Evaluator Note: When turbine Trips the crew may attempt to manually trip the reactor even though it is not required. If Rx trip is attempted, an ATWS will occur and the crew will not enter AOP-S.06 for Turbine Trip. Therefore, most of the following event guide will not apply. Proceed to the next event guide for ATWS.

Crew Diagnose Turbine Trip with Rx Trip not Required RO Monitor for Generator Breaker trip ~ 30 seconds after the Turbine trip. Open PCB when they fail to open. (Should open as prudent action or AOP-S.06 will direct opening them at step 4)

SRO Enter and direct actions of AOP-S.06 BOP RO (RNO required)

(Manual insertion required)

RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 & 5 Page 18 of 38 Event

Description:

Inadvertent Main Turbine Trip, Main Generator Fails to Trip Time Position Applicant's Actions or Behavior BOP (if not previously performed RNO Required)

BOP RO BOP/RO CREW Lead Examiner may cue the next event when desired.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 & 7 Page 19 of 38 Event

Description:

Remaining Control Bank D Group 1 Rods (M-4, M-12, D-12) Drop, ATWS Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 6 Note: If Crew attempts Rx Trip when turbine trips (Event 4), Event 6 will not be required to initiate ATWS.

Indications Available:

Dropped Rods/ATWS: Rod Bottom lights lit for Rods M-4, M-12, D-12. RPIs indicate Zero for Rods M-4, M-12, and D-12. Alarm (Reactor 1 st Out) XA-55-4D Window C-4 "NC-41U POWER RANGE HI NEUTRON FLUX RATE REACTOR TRIP Alarm XA-55-6A Window B-1 "NC-41U/NC-41K NIS POWER RANGE HIGH NEUTRON FLUX RATE" Both Reactor Trip Breakers Closed RO Identify ATWS after attempting both Rx trip Switches.

CREW Dispatch Personnel to locally Trip reactor as prudent action or later as directed by procedure.

SRO Enter and Direct actions of FR-S.1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 & 7 Page 20 of 38 Event

Description:

Remaining Control Bank D Group 1 Rods (M-4, M-12, D-12) Drop, ATWS Time Position Applicant's Actions or Behavior CRITICAL TASK 1 - Option 1 RO (RNO Required)

(Manual Rod Insertion will be required) Critical Task "Prior to completion of FR-S.1 step 4" BOP Evaluator Note:

If FR-S.1 entered directly without performance of AOP-S.06 BOP should Monitor and Open Generator Breakers >30 seconds after the Main Turbine Trip.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 & 7 Page 21 of 38 Event

Description:

Remaining Control Bank D Group 1 Rods (M-4, M-12, D-12) Drop, ATWS Time Position Applicant's Actions or Behavior BOP (RNO) (RNO) (RNO) (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 & 7 Page 22 of 38 Event

Description:

Remaining Control Bank D Group 1 Rods (M-4, M-12, D-12) Drop, ATWS Time Position Applicant's Actions or Behavior

CRITICAL TASK 1 - Option 2 RO/BOP PLACE boric acid transfer pumps in fast speed. ADJUST emergency borate valve [FCV-62-138]

to obtain boric acid flow between 35 gpm and 150 gpm on

[FI-62-137A]. MONITOR emergency boration flow:

a. CHECK emergency boration flow established on

[FI-62-137A]. b. IF boric acid flow less than 35 gpm, THEN (N/A) Critical Task "Prior to completion of FR-S.1 step 4" RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 & 7 Page 23 of 38 Event

Description:

Remaining Control Bank D Group 1 Rods (M-4, M-12, D-12) Drop, ATWS Time Position Applicant's Actions or Behavior CREW RO/BOP (RNO May be required if not previously performed and Reactor still not tripped)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 & 7 Page 24 of 38 Event

Description:

Remaining Control Bank D Group 1 Rods (M-4, M-12, D-12) Drop, ATWS Time Position Applicant's Actions or Behavior SRO BOP SRO/RO (SRO should return to E-0)

When Crew Returns to E-0 Lead Examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 25 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 8 Indications available: Loop 3 Main Feedwater line Break Inside Containment: Alarm XA-55-5C Window B-3 "MS-30-241 LOWER COMPT MOISTURE HI Alarm XA-55-6E Window C-6 "ZS-61-186 ICE CONDENSER LOWER INLET DOOR OPEN Containment Pressure Increasing Containment Radiation Not Increasing Hi-Hi Containment Pressure Phase B Auto failure: Containment Spray Pumps Auto Start from containment pressure

>2.81 psi. MSIV Closure if not manually closed Phase B status lights not green on panels 6K and 6L (M-6)

CREW Diagnose Secondary Side Break inside containment and ensure Safety Injection actuated.

SRO Direct actions of E-0 Evaluator Note: Crew may manually close MSIVs based on foldout page of E-0 if Hi-Hi containment pressure signal does not close them first. AFW to Faulted S/G may also be isolated per the Foldout Page.

Evaluator Note: At some point during performance of E-0, FR-Z.1 may be entered due to High containment pressure since status tree monitoring is already in effect due to transition to FR-S.1 for ATWS. FR-Z.1 steps are included in this event guide at the transition to E-2. Entry into FR-Z.1 should be brief for a Secondary side break.

NOTE 1: Steps 1 through 4 are immediate action steps.

NOTE 2: This procedure has a foldout page.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 26 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior RO BOP BOP RO BOP (ES-0.5 At end of Scenario) (Note: If Phase B Failure not already identified and corrected it will be addressed during performance of ES-0.5)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 27 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior BOP (If not previously performed AFW to faulted S/G may be isolated at this step)

BOP/RO (MSIVs will be closed if not previously performed)

(Applicable Foldout Page actions include Tripping the RCPs and Isolating AFW to Faulted S/G #3 if not previously performed)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 28 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior RO (RCPs will likely already be stopped)

RO/BOP (If No Perform RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 29 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior RO B OP (R NO) (Transition to E-2)

Evaluator Note: Applicable FR-Z.1 Steps are included next prior to E-2 Steps. If FR-Z.1 previously performed, continue to E-2 Steps that follow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 30 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior RO RO (Note: If Phase B Failure not already identified and corrected it should be manually actuated at this step)

RO (SRO return to E-0 or E-2 as applicable)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 31 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior SRO Enter and Direct actions of E-2 CRITICAL Task 2 Part 1 BOP (RNO if not previously performed)

(Critical Task "Prior to completion of E-2")

BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 32 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior CRITICAL TASK 2 - PART 2 BOP (Critical Task: "Prior to completion of E-2")

BOP CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 & 9 Page 33 of 38 Event

Description:

Loop 3 Feedwater Line Break In Containment, Phase B Cntmnt Isol Auto Failure Time Position Applicant's Actions or Behavior CREW OR Lead Examiner may terminate Scenar io when Crew transitions to ES-1.1.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # ES-0.5 Page 34 of 38 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior ES-0.5 Actions VERIFY D/G ERCW supply valves OPEN.

BOP VERIFY at least four ERCW pumps RUNNING.

BOP VERIFY CCS pumps RUNNING:

Pump 1A-A (2A-A) Pump 1B-B (2B-B) Pump C-S.

BOP VERIFY EGTS fans RUNNING.

BOP VERIFY generator breakers OPEN.

BOP VERIFY AFW pumps RUNNING:

MD AFW pumps TD AFW pump.

NOTE AFW level control valves should NOT be repositioned if manual action has been taken to control S/G levels, to establish flow due to failure, or to isolate a faulted S/G.

BOP CHECK AFW valve alignment:

a. VERIFY MD AFW LCVs in AUTO.

b. VERIFY TD AFW LCVs OPEN.

c. VERIFY MD AFW pump recirculation valves FCV-3-400 and FCV-3-401 CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # ES-0.5 Page 35 of 38 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP VERIFY MFW Isolation:

MFW pumps TRIPPED MFW regulating valves CLOSED MFW regulating bypass valve controller outputs ZERO MFW isolation valves CLOSED BOP MONITOR ECCS operation:

VERIFY ECCS pumps RUNNING: CCPs RHR pumps SI pumps VERIFY CCP flow through CCPIT.

CHECK RCS pressure less than 1500 psig.

VERIFY SI pump flow. CHECK RCS pressure less than 300 psig.

VERIFY RHR pump flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # ES-0.5 Page 36 of 38 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP VERIFY ESF systems ALIGNED:

Phase A ACTUATED:

o PHASE A TRAIN A alarm LIT [M-6C, B5].

o PHASE A TRAIN B alarm LIT [M-6C, B6].

Containment Ventilation Isolation ACTUATED:

o CONTAINMENT VENTILATION ISOLATION TRAIN A alarm LIT [M-6C, C5].

o CONTAINMENT VENTILATION ISOLATION TRAIN B alarm LIT [M-6C, C6].

Status monitor panels:

o 6C DARK o 6D DARK o 6E LIT OUTSIDE outlined area o 6H DARK o 6J LIT. Train A status panel 6K:

o CNTMT VENT GREEN o PHASE A GREEN Train B status panel 6L:

o CNTMT VENT GREEN o PHASE A GREEN Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # ES-0.5 Page 37 of 38 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP (If not previously performed, Manual Phase B Containment Isolation should be actuated at this point)

(Step continued in next Table Cell)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # ES-0.5 Page 38 of 38 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP VERIFY pocket sump pumps STOPPED: [M-15, upper left corner] HS-77-410, Rx Bldg Aux Floor and Equipment Drain Sump pump A HS-77-411, Rx Bldg Aux Floor and Equipment Drain Sump pump B.

BOP DISPATCH personnel to perform EA-0-1, Equipment Checks Following ESF Actuation.

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

Sequoyah Scenario No.:

1 Op Test No.:

NRC Examiners:

Operators:

Initial Conditions: ~24% power equilibrium. 1A-A RHR Pump Out of Service.

Turnover: Plant startup was held at ~24% for approximately 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> for MFW Regulating valve repair. Repairs are complete continue Power increase to 100%. Target CTs: Insert Negative Reactivity using rods or boration prior to completion of FR-S.1 Step 4. Isolate Faulted S/G #3 prior to transition out of E-2 by closing the faulted S/G MSIV or MSIVs for all non-faulted S/Gs and isolating all feedwater flow, including AFW flow, to the faulted S/G. Event # Malf. No. Event Type*

Event Description 1 N/A R-ATC N-SRO/BOP Increase power from ~24%.

2 RX06B TS-SRO I-SRO/ATC Pressurizer level Channel failure. Requires AOP-I.04 performance including selection of operable channel and restoration of letdown. SRO Tech Spec Evaluation.

3 RD07D4 TS-SRO C-SRO/ATC Dropped Rod (D-4) with reactor trip not required results in Auto rod withdrawal and Immediate action to place rods in manual. AOP-C.01 is performed. SRO Tech Spec Evaluation.

4 TCR02 C-SRO Inadvertent Turbine Trip does not result in or require reactor trip since power is less than 50%. Crew will stabilize plant and perform AOP-S.06.

5 EG07 C-SRO/BOP Main generator fails to trip when main turbine trips requiring main generator PCBs to be manually opened.

6 RD07M4 RD07M12 RD07D12 M-All Remaining rods in same group with rod D-4 are dropped resulting in reactor trip signal however, reacto r trip does not occur due to ATWS.

7 RP01C C-All ATWS - Both RTBs fail to open. Rods are manually inserted and Emergency Boration is initiated.

8 FW23C C-SRO/BOP Loop 3 Feedwater Line break inside containment.

9 RP07 C-SRO/ATC Failure of Hi-Hi containment pressure logic to initiate Phase B containment isolation.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9 Appendix D Scenario Outline Form ES-D-1 Scenario 1 Summary Crew will assume shift at ~24% power with 1A-A RHR pump out of service. Crew directions will be to increase power to 100%.

When adequate power change has been completed, Pressurizer level Channel LT 68-335 fails low resulting in letdown isolation. SRO will direct performance of AOP-I.04 to select operable channel and restore letdown. SRO will also evaluate Tech Specs.

When AOP-I.04 is complete and letdown has been restored, Control rod D-4 drops into the core. Due to power level and core location, an automatic reactor trip signal is not generated and manual reactor trip is not required for a single dropped rod. However, automatic rod withdrawal results requiring ATC to take immediate action to place rods in manual. SRO w ill direct performance of AOP-C.01 and evaluate Tech Specs. When applicable actions of AOP-C.01 are complete, an inadvertent Main Turbine trip will occur. An automatic Reactor trip signal is not generated with power level less than 50%. Crew should be able to stabilize plant and implement AOP-S-06 including power reduction to 20%. Rods should still be in manual. Normally 30 seconds after a turbine trip, the Generator trips and the PCBs open, however, in this scenario the generator trip fails to occur which requires manually opening the Main Generator PCBs. It is possible that if power level has been increased substantially above the initial 24% level, a heater string isolation could occur requiring manual Reactor Trip while performing AOP-S.06.

Assuming heater string isolation does not occur, the remaining 3 rods in the group with rod D-4 drop into the core producing an automatic negative rate reactor trip signal. The reactor does not trip due to an ATWS condition and the crew will enter FR-S.1. ATC will manually insert control rods and most likely BOP will initiate emergency boration to complete the first critical task. One of the ROs will dispatch operators to trip the reactor locally.

When the crew has completed FR-S.1, a feedwater line break occurs on loop #3 inside containment which will require a safety injection. When containment pressure reaches the Hi-Hi pressure setpoint of 2.81 psi, automatic Phase B containment isolation does not occur requiring manual actuation. Crew will continue in E-0 and transition to E-2 to isolate or verify isolated the faulted S/G to complete the second critical task. Upon completion of E-2, crew should transition to SI Termination procedure ES-1.1. FR-Z.1 may require brief entry for high containment pressure but is exited at step 4 for faulted S/G entry.

The scenario may be terminated when crew transitions to SI Termination procedure ES-1.1.

Appendix D NUREG 1021 Revision 9 Time: Now Date:

Today Unit 1 MCR Checklist (751-2428 ID 7636)

Part 1 - Completed by Off-going Shift / Reviewed by On-coming Shift Mode 1, 24% Power 175 MWe PSA Risk: Green Grid Risk: Green

RCS Leakage ID .02 gpm, UNID .01 gpm Cumulative Purge Time _50.5 Hours_

NRC phone Authentication Code Until 0800 H3H8 After 0800 42DF Common Tech Spec Actions U-1 Tech Spec Actions LCO 3.5.2 & 3.6.2.1 - 1A-A RHR pump has been tagged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance to perform motor winding test. Expected Return to service is ~2 hours.

Protected Equipment 1B-B RHR Pump 1B-B Safety Injection Pump 1B-B Charging Pump

Shift Priorities Plant Startup was suspended at ~24% for repairs to Loop #2 MFW Reg valve which are now complete. Continue power increase to 100% per Reactor Engineer SpreadShee

t. Spreadsheet has been verified by the SRO/STA and 0-SO-62-7 Appendix D and E have been performed. Currently in 0-GO-4, Section 5.5, step [21]. Pre-Conditioned power level is 100%.

Part 2 - Performed by on-coming shift Verify your current qualifications Review Operating Log since last held shift or 3 days, whichever is less Standing Orders / Shift Orders TACF Immediate required reading LCO Actions Part 3 - Performed by both off-going and on-coming shift Walk down of MCR Control Boards

Time: Now Date:

Today MAIN CONTROL ROOM (7690) Train_A_Week OUTSIDE (7666) [593-5214] AUXILIARY BUILDING (7775) 1A-A RHR pump has been tagged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance to perform motor winding test.

Expected Return to service is ~2 hours.

TURBINE BUILDING (7771) (593-8455)

Time: Now Date:

Today Equipment Off-Normal (Pink Tags) UNID And Noun Name Panel Problem Description WO / PER Number Date Scheduled MCR WO List ID And Noun Name Panel Problem Description WO/PER Number Date Scheduled

UNIT ONE REACTIVITY BRIEF Date: Today Time: Now

General Information RCS Boron:

1475 ppm Today BA Controller Setpoint:

38%

• RCS B-10 Depletion:

2 ppm Operable BAT:

A BAT A Boron:

6850 ppm BAT C Boron:

6850 ppm RWST Boron:

2601 ppm Nominal Gallons per rod step from 219:

7 gallons of acid, 36 gallons of water

• Verify boric acid flow contro ller is set at Adjusted BA Controller Setting iaw 0-SO-62-7 section 5.1 Estimated values for a 1° Change in Tave **

Gallons of acid:

26 Gallons of water:

138 Rod Steps: 4 Estimated rods/boron for emergency step power reduction ** (Assuming Xenon equilibrium and no reactivity effects due to Xenon. 2/3 total reactivity from rods, 1/3 from boron)

Power reduction amount Estimated Final Rod Position Estimated boron addition 10% 198 Steps on bank D 101 gallons 30% 174 Steps on bank D 295 gallons 50% 152 Steps on bank D 485 gallons

• • These values are approximations and not int ended nor expected to be exact. The values may be superseded by Rx Engineering or SO-62-7 calculated values. These values are calculated assuming 100%

steady state power operation onl

y. Engineering data last updated one week ago. Data Valid until one week from now. Previous Shift Reactivity Manipulations Number of dilutions: 0 Number of borations: 0 Rod steps in: 0 Gallons per dilution: 0 Gallons per boration: 0 Rod steps out: 0 Total amount diluted: 0 Total amount borated: 0 Net change: 0 IN/Out Current Shift Estimated Reactivity Manipulations Number of dilutions: ***

Number of borations: ***

Rod steps in: ***

Gallons per dilution: ***

Gallons per boration: ***

Rod steps out: ***

Total expected dilution: ***

Total expected boration: ***

Net change: *** In/Out Remarks: Rx Power - 100% MWD/MTU - 1000 Xenon & Samarium at Equilibrium

• • • Per Reactor Engineering Spreadsheet.

Next Unit 1 Flux Map is scheduled -

three weeks from now Unit 1 M-P is 0 PPM Unit Supervisor: _______________________________

Name/Date Operations Chemistry Information Boron Results Sample Point Units Boron Date / Time Goal Limit U1 RCS ppm 1475 Today / Now Variable Variable U2 RCS ppm 816 Today / Now Variable Variable U1 RWST ppm 2601 Today / Now 2550 - 2650 2500 - 2700 U2 RWST ppm 2569 Today / Now 2550 - 2650 2500 - 2700 BAT A ppm 6850 Today / Now Variable Variable BAT B ppm 6850 Today / Now Variable Variable BAT C ppm 6850 Today / Now Variable Variable U1 CLA #1 ppm 2556 Today / Now 2470-2630 2400-2700 U1 CLA #2 ppm 2575 Today / Now 2470-2630 2400-2700 U1 CLA #3 ppm 2591 Today / Now 2470-2630 2400-2700 U1 CLA #4 ppm 2589 Today / Now 2470-2630 2400-2700 U2 CLA #1 ppm 2531 Today / Now 2470-2630 2400-2700 U2 CLA #2 ppm 2650 Today / Now 2470-2630 2400-2700 U2 CLA #3 ppm 2522 Today / Now 2470-2630 2400-2700 U2 CLA #4 ppm 2526 Today / Now 2470-2630 2400-2700 Spent Fuel Pool ppm 2547 Today / Now

> 2050 > 2000 Lithium Results Goal Midpoint U1 RCS Lithium ppm 1.1 Today / Now

>1 >1 U2 RCS Lithium ppm 2.43 Today / Now 2.18-2.48 2.33 Primary to Secondary Leakrate In formation (Total CPM RM-90-99/119)

Indicator Units U1 Date / Time U2 Date/Time SI 50 S/G Leakage?

Yes/No No Today / Now No Today / Now SI 137.5 CVE Leakrate gpd < 0.1 Today / Now

< 0.1 Today / Now 5 gpd leak equivalent cpm 380 Today / Now 68 Today / Now 30 gpd leak equivalent cpm 1980 Today / Now 83 Today / Now 50 gpd leak equivalent cpm 3250 Today / Now 206 Today / Now 75 gpd leak equivalent cpm 4850 Today / Now 455 Today / Now CVE Air Inleakage cfm 10 Today / Now 12.5 Today / Now Bkgd on 99/119 cpm 50 Today / Now 40 Today / Now Correction Factor 99/119 cpm/gpd 10.69 Today / Now 14.13 Today / Now Steady state conditions are necessary for an accurate det ermination of leak rate using the CVE Rad Monitor

Unit 1 DELTA REACTO R POWER ASSUMED INSERTED EXPECTED DELTA RHO BORON DELTA RECOMMEND RECOMMEND IODINE DATE/TIME TIME POWER DEFECT ROD HT WORTH XENON BORON CONC PPM DILUTION BORATION CONC (hrs)(%)(pcm)(steps)(pcm)(pcm)(pcm)(ppm)(ppm)(gal)(gal)(% eq)0 24.0 376.0 175.0-350.8-1537.0---1475.0---------24.2 Today 1 34.0 553.0 191.0-230.4-1514.3 37.0 1473.2-5.9 252 0 24.7 Today 2 44.0 714.9 201.0-129.0-1478.9 23.0 1471.5-4.1 183 0 26.1 Today 3 54.0 859.9 216.0-30.7-1439.1 6.9 1470.3-1.1 49 0 28.4 Today 4 64.0 1003.0 216.0-29.1-1401.7 104.0 1453.6-16.7 741 0 31.4 Today 5 74.0 1151.8 216.0-27.5-1371.7 117.2 1434.8-18.8 846 0 35.1 Today 6 84.0 1304.9 216.0-25.8-1352.6 132.4 1413.5-21.3 968 0 39.4 Today 7 94.0 1463.3 216.0-24.0-1346.4 150.4 1389.4-24.1 1119 0 44.3 Today 8 100.0 1566.2 216.0-23.0-1356.7 112.2 1371.4-18.0 845 0 49.5 Today 9 100.0 1574.3 216.0-23.0-1388.9 40.3 1364.9-6.5 305 0 54.5 Today 10 100.0 1577.2 216.0-23.0-1440.7 54.7 1356.2-8.8 417 0 58.9 Today 11 100.0 1581.1 216.0-23.0-1505.0 68.2 1345.2-10.9 524 0 63.0 Today 12 100.0 1586.0 216.0-23.0-1576.4 76.4 1333.0-12.2 592 0 66.6 Today 13 100.0 1591.5 216.0-23.0-1651.3 80.4 1320.1-12.9 628 0 69.9 Today 14 100.0 1597.2 216.0-23.0-1726.9 81.3 1307.1-13.0 642 0 72.9 Today 15 100.0 1603.1 216.0-23.0-1801.2 80.2 1294.3-12.8 639 0 75.5 Today 16 100.0 1608.9 216.0-23.0-1873.0 77.6 1281.8-12.4 625 0 77.9 Today 17 100.0 1614.6 216.0-23.0-1941.4 74.1 1270.0-11.9 602 0 80.1 Today 18 100.0 1620.1 216.0-23.0-2005.9 70.0 1258.8-11.2 574 0 82.1 Today 19 100.0 1625.2 216.0-23.0-2066.3 65.5 1248.3-10.5 542 0 83.8 Today 20 100.0 1630.0 216.0-23.0-2122.4 61.0 1238.5-9.7 508 0 85.4 Today 21 100.0 1634.5 216.0-23.0-2174.4 56.4 1229.5-9.0 473 0 86.8 Today 22 100.0 1638.7 216.0-23.0-2222.2 52.0 1221.2-8.3 438 0 88.1 Today 23 100.0 1642.5 216.0-23.0-2266.1 47.7 1213.6-7.6 405 0 89.3 Today 24 100.0 1646.0 216.0-23.0-2306.2 43.7 1206.6-7.0 373 0 90.4 Today 25 100.0 1649.2 216.0-23.0-2342.9 39.9 1200.2-6.4 342 0 91.3 Today 26 100.0 1652.1 216.0-23.0-2376.3 36.4 1194.4-5.8 313 0 92.2 Today 27 100.0 1654.9 216.0-23.0-2406.7 33.1 1189.1-5.3 287 0 92.9 Today 28 100.0 1657.3 216.0-23.0-2434.4 30.1 1184.3-4.8 262 0 93.6 Today 29 100.0 1659.6 216.0-23.0-2459.5 27.3 1180.0-4.4 238 0 94.3 Today 30 100.0 1661.6 216.0-23.0-2482.2 24.8 1176.0-4.0 217 0 94.8 Today 31 100.0 1663.5 216.0-23.0-2502.8 22.5 1172.4-3.6 197 0 95.3 Today 32 100.0 1665.1 216.0-23.0-2521.4 20.3 1169.2-3.2 179 0 95.8 Today 33 100.0 1666.7 216.0-23.0-2538.3 18.4 1166.2-2.9 162 0 96.2 Today 34 100.0 1668.0 216.0-23.0-2553.6 16.6 1163.6-2.7 147 0 96.6 Today 35 100.0 1669.3 216.0-23.0-2567.4 15.0 1161.2-2.4 133 0 96.9 Today 36 100.0 1670.4 216.0-23.0-2579.8 13.6 1159.0-2.2 121 0 97.2 Today Unit 1 37 100.0 1671.4 216.0-23.0-2591.1 12.3 1157.1-2.0 109 0 97.5 Today 38 100.0 1672.3 216.0-23.0-2601.3 11.1 1155.3-1.8 99 0 97.7 Today 39 100.0 1673.2 216.0-23.0-2610.4 10.0 1153.7-1.6 89 0 98.0 Today 40 100.0 1673.9 216.0-23.0-2618.7 9.0 1152.3-1.4 81 0 98.2 Today 41 100.0 1674.6 216.0-23.0-2626.2 8.2 1151.0-1.3 73 0 98.3 Today 42 100.0 1675.2 216.0-23.0-2632.9 7.4 1149.8-1.2 66 0 98.5 Today 43 100.0 1675.7 216.0-23.0-2639.0 6.6 1148.7-1.1 59 0 98.7 Today 44 100.0 1676.2 216.0-23.0-2644.5 6.0 1147.8-1.0 54 0 98.8 Today 45 100.0 1676.7 216.0-23.0-2649.5 5.4 1146.9-0.9 48 0 98.9 Today 46 100.0 1677.1 216.0-23.0-2653.9 4.9 1146.1-0.8 44 0 99.0 Today 47 100.0 1677.4 216.0-23.0-2658.0 4.4 1145.4-0.7 39 0 99.1 Today 48 100.0 1677.8 216.0-23.0-2661.6 4.0 1144.8-0.6 36 0 99.2 Today 49 100.0 1678.1 216.0-23.0-2664.9 3.6 1144.2-0.6 32 0 99.3 Today 50 100.0 1678.3 216.0-23.0-2667.9 3.2 1143.7-0.5 29 0 99.3 Today 51 100.0 1678.6 216.0-23.0-2670.5 2.9 1143.2-0.5 26 0 99.4 Today 52 100.0 1678.8 216.0-23.0-2672.9 2.6 1142.8-0.4 24 0 99.5 Today 53 100.0 1679.0 216.0-23.0-2675.1 2.4 1142.4-0.4 21 0 99.5 Today 54 100.0 1679.2 216.0-23.0-2677.1 2.1 1142.1-0.3 19 0 99.6 Today 55 100.0 1679.3 216.0-23.0-2678.8 1.9 1141.8-0.3 17 0 99.6 Today 56 100.0 1679.5 216.0-23.0-2680.4 1.7 1141.5-0.3 16 0 99.6 Today 57 100.0 1679.6 216.0-23.0-2681.8 1.6 1141.3-0.2 14 0 99.7 Today 58 100.0 1679.7 216.0-23.0-2683.1 1.4 1141.1-0.2 13 0 99.7 Today 1000 MWD/MTU Hold Tavg = Tref +/- 1.5F Total 16893 0 6850 BAT ppm Small hourly boration/dilution volumes may be accumulated for larger single additions Reason for Maneuver Plant Startup Date Today RxEng Name Comments Page 1 of 2 NRC09B Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION Sim. Setup Reset IC- 189 Perform switch check. Allow the simulator to run for at least 3 minutes before loading SCEN file or starting the exercise. This will initialize ICS.

Load SCENS: NRC09B Place simulator in RUN.

Place OOS equipment in required position with tags. Clear alarms. Initialize simulator at 10-3 % RTP. Place Mode 2 placard on panels.

Place A Train Week sign on the simulator Ensure Intermediate Range Channel N36 any Source Range Channel and on selected N45 Recorder.

Event 1 Increase power to 1-2%

Event 2 When Power Increase complete as Directed by Lead Examiner insert: Key-1 imf NI04B f:0 k:1 IR CHANNEL FAILURE IR CHNL 2 (N-36) FAILS LOW If IMs or MSS contacted, inform the crew that the IMs will report to the MCR in ~45 minutes.

Event 3 When IR AOP and Tech Spec complete as Directed by Lead Examiner insert: Key-2 imf CV25A f:1 k:2 PT-62-81 FAILS LOW If MSS contacted, inform the crew that IMs will report to the MCR in ~45 miutes.

Event 4 When manual letdown pressure control has been established as Directed by Lead Examiner insert: Key-3 imf ED08C f:1 k:3 LOSS OF 480V SHUTDOWN BOARD 1B1-B If personnel are dispatched to check the board locally report the normal supply breaker tripped apparently, due to 51 overcurrent rela

y. Report in ~3 min.

If dispatched to check D/G oil temperature, report temperature of ~99 degrees. Report in ~

10 min. Event 5 When 480v Bd AOP and Tech Spec complete as Directed by Lead Examiner insert: Key-4 imf TH05A f:4.2 k:4 STEAM GENERATOR TUBE FAILURE SG #1 (~200 gpm)

If RADCON/Chem Lab are requested to survey/sample S/Gs, wait ~20 min then report as RADCON that S/G #1 is slightly higher than background and other S/Gs.

Wait 45 minutes and report as Chem Lab that ruptured S/G is #1 S/G.

Page 2 of 2 NRC09B Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

Event 6 Active when SCENS loaded imf RP16K608A f:1 Failure of Train "A" ESF Equipment to start.

No auto Train "A" CR Isolation

No auto start of CCP 1A-A (Note: CCP1A-A may have been previously started manually No auto start of SI pump 1A-A

No auto start of RHR pump 1A-A No auto start of CCS pump 1A-A (Note: 1A-A CCS pmp already running)

Event 7 Active when SCENS loaded imf MSCOHS115A f:1 ior ZLOHS115A_RED f:1 LOOP 1 TDAFW PUMP STEAM SUPPLY VALVE

1-FCV-1-15 FAILS OPEN.

If dispatched to check valve locally report no obvious problem locally. Report in ~8 min.

Event 8 Immediately when E-3 cooldown to target temperature complete as Directed by Lead Examiner insert: Key-5 imf MS06A f:25 k:5 MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT - LP1 If personnel dispatched to look for steam leak, report steam coming from West Valve Vault room. If requested to bypass Con-DI wait

~10 min and insert: Key-6 irf CNR02 f:3 k:3 k:6 HS-14-3, COND DEMIN BYPASS VLV (OPEN)

Report when complete.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 1 of 35 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior Console Operator:

No action required for Event 1 Indications available:

None. Crew will perform startup IAW 0-GO-3, Section 5.2 NOTE Average loop T (UO485) is considered to be the most accurate power indication below 15% power. NIS power range and steam dump demand should also be monitored.

(REFER TO 0-SO-1-2 for steam dump demand program.)

RO WITHDRAW RODS OR DILUTE to bring reactor power to between 1 and 2% RTP, while continuing with this instruction.

NOTE After refueling operations the "Initial Startup System Parameter Log" is performed during power escalations to provide the operator with alternate indications of power level (indications independent of calorimetric calculations). If significant differences occur (approx. 5%) between the alternate power indications then Engineering should be

notified.

US IF startup is after a refueling or maintenance on NIS, THEN INITIATE performance of 0-PI-OPS-000-001.0, Initial Startup System Parameter Log.

This Step N/A

RO COMPARE NIS power range instrumentation with loop T indicators and steam dump demand to evaluate accuracy of PRMs.

RO SELECT the highest reading IRM or I and PRM channels to be recorded on NR 45.

Crew REVIEW plant parameters and indications to determine plant stability prior to startup of Main Feed Pump.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 2 of 35 Event

Description:

Raise Power Time Position Applicant's Actions or Behavior RO MAINTAIN reactor power approximately 1%.

NOTE Steps 5.2[7] and 5.2[8] may be performed in any order. (The following 2 steps)

BOP WHEN total Aux FW flow to SGs 1 and 2 is constant and greater than or equal to 300 gpm, THEN CLOSE [FCV-3-400],

AFW PUMP A RECIRC ISOL VLV, and PLACE handswitch

[HS-3-400A] in the PULL TO LOCK position.

BOP WHEN total Aux FW flow to SGs 3 and 4 is constant and greater than or equal to 300 gpm, THEN CLOSE [FCV-3-401], AFW PUMP B RECIRC ISOL VLV, and PLACE handswitch

[HS-3-401A] in the PULL TO LOCK position.

NOTE Control rod bank D should be

>165 steps at steady state power levels below 85% RTP. This guidance is to preclude long-term operation at <165 steps to avoid potential impact on safety analysis assumptions. Short-term operation at <165 steps is NOT a concern.

RO ENSURE the plant is stabilized between 1 and 2% reactor power.

RO COMPARE NIS intermediate range instrumentation with loop T indications to evaluate accuracy of IRMs.

RO RECORD IRM readings: N35 % RTP N36 % RTP When power has been raised sufficiently to record a reactivity manipulation, and demonstrate AFW control, lead examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 3 of 35 Event

Description:

NIS Intermediate Channel N-36 Fails Low Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 2 Indications available:

N-36 indicator on Panel M-4 Fails low. NR-45 Recorder channel (M-6) fails low (if selected). Note: No audible Alarms received.

RO Diagnose and announce failure.

SRO Enter and direct actions of AOP-I.01 Section 2.2 RO (RO may adjust rods to stabilize power)

RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 4 of 35 Event

Description:

NIS Intermediate Channel N-36 Fails Low Time Position Applicant's Actions or Behavior SRO Action 3b (From Table 3.3-1 Item 5) Applies Action 8a (From Table 3.3-1 Item 22.A) Applies but no actions required for SR Rx Trip.

N/A Action 1a (From Table 3.3-10 Item 17b)

N/A RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 5 of 35 Event

Description:

NIS Intermediate Channel N-36 Fails Low Time Position Applicant's Actions or Behavior Evaluator Note: Some steps may be performed by RO or BOP depending on SRO direction for back panel operations.

RO/BOP RO/BOP RO/BOP RO RO SRO Lead Examiner may cue next event when AOP I.01 and Tech Spec Evaluation are complete.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 6 of 35 Event

Description:

Letdown Pressure Transmitter PT-62-81 Fails low.

Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 3 Indications available:

Alarm XA-55 6C Window C-4: "TS-62-75 Low Pressure Letdown Relief Temp High"Letdown Flow drops to zero.

RO Refer to Annunciator Response Procedure.

RO (Indicates zero Pressure)

RO (Should restore ~75 gpm letdown flow)

RO RO Evaluator Note: Remaining steps of ARP are N/A. Lead Examiner may cue the next event when manual letdown flow control has been established.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 7 of 35 Event

Description:

480 volt Shutdown board 1B1-B Failure Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 4 Indications available:

Alarm XA-55 1B Window D-6: "480V SD BD 1B1-B Failure/Undervoltage Panel M-1 Indicator 1-EI-57-83A indicates Zero Volts. Green Lights on both 480V SD BD 1B1-B supply Bkr mimic lights on (M-1)

RO Refer to ARP for XA-55-1B window D-6 RO RO RO SRO Enter and direct actions of AOP-P.05 section 2.5 BOP RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 8 of 35 Event

Description:

480 volt Shutdown board 1B1-B Failure Time Position Applicant's Actions or Behavior RO SRO Evaluator Note: SRO should identify Tech for the inoperable board and other more limiting Tech Specs from the list in Appendix AA. LCO 3.8.2.1, Action a (8 hr action for 480V BD 1B1-B Inop) LCO 3.4.3.2 Action d (1 hr action to close and remove power from PORV with De-Energized Block Valve. Action d also requires implementation of Action b which potentially leads to 3.0.3 since the block valve cannot be closed to comply with Action b.) Several other Tech Specs less limiting than the PORV Spec may also be identified.

BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 9 of 35 Event

Description:

480 volt Shutdown board 1B1-B Failure Time Position Applicant's Actions or Behavior BOP (Note: Vital Charger II is normally in service therefore crew

may not dispatch personnel)

BOP BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 10 of 35 Event

Description:

480 volt Shutdown board 1B1-B Failure Time Position Applicant's Actions or Behavior Crew BOP SRO When Tech Spec Evaluation complete, Lead Examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 11 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 5 Insert S/G #1 SGTR at 4.2 severity (~200 gpm).

Indications Available:

Loop 1 Steam Generator tube Rupture: 0-AR-M12-A, C1, CNDS VAC PMP LO RNG AIR EXH MON HIGH RAD Pressurizer pressure decreasing Pressurizer level decreasing and charging flow increasing Loop 1 Main Steam Line Rad Monitor Increasing Train A SSPS Slave Relay Failure: Train A CRI annunciator not lit with SI 1A-A RHR Pump not running with SI 1A-A SI Pump not running with SI TDAFW Pump Steam supply form Loop 1 Fails open; Red light on and Valve will not close for man transfer to loop 4.

Evaluator Note: Crew may momentarily enter AOP-R.01 for S/G Tube leak prior to Rx Trip and Safety Injection RO Manually Trip Reactor and initiate SI.

SRO Enter and Direct performance of E-0, Reactor Trip Or Safety Injection.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 12 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior NOTE 1: Steps 1 through 4 are immediate action steps.

NOTE 2: This procedure has a foldout page.

Evaluator Note: Slave Relay failure should be identified and manual actions taken during performance of prudent operator actions immediately following performance of Immediate Operator Actions. Manually Start 1A-A RHR Pump (M-6) Manually start 1A-A SI Pump (M-6) Manually Actuate A Train Control Room Isolation (M-6)

Evaluator Note: Crew may also attempt to transfer the TDAFW steam supply from the ruptured S/G early as prudent action. If steam supply transfer is attempted the failed open steam supply valve from S/G #1 should be identified and steam supply to the TDAFW pump isolated. If not isolated early the failure will be addressed later in E-3.

RO BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 13 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP RO Evaluator Note: If not previously Identified, Slave relay failures should be identified during performance ES-0.5. When Identified, equipment should be

manually actuated promptly.

BOP (ES-0.5 At end of Scenario)

BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 14 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP/RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 15 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior RO/BOP (If No Perform Following RNO)

(AFW Flow to Ruptured S/G #1 may be isolated during control step. Level should be >10%)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 16 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior RO BOP BOP (Crew will Transition to E-3 at this Step)

SRO Enter and direct performance of E-3 Steam Generator Tube rupture. RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 17 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior RO BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 18 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP (FCV-1-15 will not close RNO Required)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 19 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior Critical Task 1 - Part 1 BOP Critical Task: Prior to Initiation of RCS Cooldown to Target Temperature.

Evaluator Note: Isolating TDAFW pump from Ruptured S/G should also be considered part of this critical task.

Critical Task 1 -

Part 2 BOP (Crew will isolate or verify isolated AFW to Loop 1 S/G)

Critical Task: Prior to Initiation of RCS Cooldown to Target Temperature.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 20 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP Critical Task 1 -

Part 1 (Cont'd) BOP (FCV-1-15 will not close, if not previously performed RNO will be required)

BOP SRO Determine Target Temperature using table on next page.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 21 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 22 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 23 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP BOP RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 24 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP RO RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 25 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior Critical Task 2 BOP (Critical Task: Prior to RCS Depressurization)

IMPORTANT Evaluator Note: When cooldown complete, initiate Event 8 (S/G #1 Steamline break outside containment to ensure prompt transition to ECA-3.1 in the next step.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5,6, & 7 Page 26 of 35 Event

Description:

1. 1 S/G Tube Rupt, ESF Slave Relay Failure, TDAFW Stm Supply Vlv Fails Open Time Position Applicant's Actions or Behavior BOP (Pressure in S/G #1 will be rapidly decreasing due to steamline break, RNO required)

(SRO should transition to ECA-3.1)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 27 of 35 Event

Description:

S/G #1 SteamLine Break outside containment Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 8 Indications available: S/G #1 Pressure decreasing Auto Closure of intact S/G MSIVs SRO Enter and direct actions of ECA-3.1, SGTR AND LOCA SUBCOOLED RECOVERY RO RO RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 28 of 35 Event

Description:

S/G #1 SteamLine Break outside containment Time Position Applicant's Actions or Behavior RO RO RO BOP (If Not RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 29 of 35 Event

Description:

S/G #1 SteamLine Break outside containment Time Position Applicant's Actions or Behavior RO CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 30 of 35 Event

Description:

S/G #1 SteamLine Break outside containment Time Position Applicant's Actions or Behavior CREW BOP (If not RNO Next Step)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 31 of 35 Event

Description:

S/G #1 SteamLine Break outside containment Time Position Applicant's Actions or Behavior BOP (SRO Should continue in ECA-3.1)

BOP CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 32 of 35 Event

Description:

S/G #1 SteamLine Break outside containment Time Position Applicant's Actions or Behavior Evaluator Note: Since a cooldown has already been performed in E-3, it is likely that only a small amount of additional cooldown, if any, will be required during the first hour since the trip. Tcold at the time of the trip should have been ~547 degrees. Cooldown should be limited such that Tcold is not decreased below ~447 degrees until an hour has

elapsed since the trip.

Critical Task 3 (Critical Task: Prior to RCS Depressurization

) Scenario may be terminated when cooldown evaluation is complete and cooldown is initiated as required.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: Audit Scenario # 2 Event # ES-0.5 Page 33 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior ES-0.5 Actions VERIFY D/G ERCW supply valves OPEN.

BOP VERIFY at least four ERCW pumps RUNNING.

BOP VERIFY CCS pumps RUNNING:

Pump 1A-A (2A-A) Pump 1B-B (2B-B) Pump C-S.

BOP VERIFY EGTS fans RUNNING.

BOP VERIFY generator breakers OPEN.

BOP VERIFY AFW pumps RUNNING:

MD AFW pumps TD AFW pump.

NOTE AFW level control valves should NOT be repositioned if manual action has been taken to control S/G levels, to establish flow due to failure, or to isolate a faulted S/G.

BOP CHECK AFW valve alignment:

a. VERIFY MD AFW LCVs in AUTO.

b. VERIFY TD AFW LCVs OPEN.

c. VERIFY MD AFW pump recirculation valves FCV-3-400 and FCV-3-401 CLOSED.

BOP VERIFY MFW Isolation:

MFW pumps TRIPPED MFW regulating valves CLOSED MFW regulating bypass valve controller outputs ZERO MFW isolation valves CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: Audit Scenario # 2 Event # ES-0.5 Page 34 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP MONITOR ECCS operation:

VERIFY ECCS pumps RUNNING: CCPs RHR pumps SI pumps

VERIFY CCP flow through CCPIT.

CHECK RCS pressure less than 1500 psig.

VERIFY SI pump flow. CHECK RCS pressure less than 300 psig.

VERIFY RHR pump flow. (If Not previously performed A Train RHR and SI pumps should be started in this step)

BOP VERIFY ESF systems ALIGNED:

Phase A ACTUATED:

o PHASE A TRAIN A alarm LIT [M-6C, B5].

o PHASE A TRAIN B alarm LIT [M-6C, B6].

Containment Ventilation Isolation ACTUATED:

o CONTAINMENT VENTILATION ISOLATION TRAIN A alarm LIT [M-6C, C5].

o CONTAINMENT VENTILATION ISOLATION TRAIN B alarm LIT [M-6C, C6].

Status monitor panels:

o 6C DARK o 6D DARK o 6E LIT OUTSIDE outlined area o 6H DARK o 6J LIT. Train A status panel 6K:

o CNTMT VENT GREEN o PHASE A GREEN Train B status panel 6L:

o CNTMT VENT GREEN o PHASE A GREEN (Even thought not specifically checked in this step A Train CRI failure may also be addressed at this step)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: Audit Scenario # 2 Event # ES-0.5 Page 35 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP VERIFY pocket sump pumps STOPPED: [M-15, upper left corner] HS-77-410, Rx Bldg Aux Floor and Equipment Drain Sump pump A HS-77-411, Rx Bldg Aux Floor and Equipment Drain Sump pump B.

BOP DISPATCH personnel to perform EA-0-1, Equipment Checks Following ESF Actuation.

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

Sequoyah Scenario No.:

2 Op Test No.:

NRC Examiners:

Operators:

Initial Conditions:

~10-3 % power in Intermediate Range Turnover: Raise Power to 1-2% Power Target CTs: Isolate Steam flow and Feedwater flow to ruptured S/G prior to initiation of RCS Cooldown to target temperature.

Cooldown RCS to less than or equal to target temperature prior to RCS depressurization.

Evaluate RCS T-cold 100 o F/hr cooldown requirements, and initiate cooldown as required by ECA-3.1 prior to RCS depressurization. Event # Malf. No. Event Type*

Event Description 1 R-ATC N-SRO/BOP Raise Power to 1-2%

2 NI04B TS-SRO I-SRO/ATC Intermediate Range Channel N-36 Fails low. ATC/SRO Identify and bypass failed channel per AOP. SRO Tech Spec Evaluation.

3 CV25A C-SRO/ATC Letdown back pressure transmitter fails low manual control required to restore normal letdown flow.

4 ED08C TS-SRO C-SRO/BOP Failure of 480 V Shutdown Board 1B1-B & related Safety Related Pumps are locked out. SRO Tech Spec Evaluation.

5 TH05A M-All S/G #1 Tube Rupture ~200 gpm requires Reactor Trip and Safety Injection.

6 RP16K608 A C-SRO/ATC Train "A" SSPS Slave Relay failure requires manual isolations and ESF equipment starts.

7 MSCOHS1 15A C-SRO/BOP Steam supply to Turbine Driven AFW pump from S/G #1 fails open and cannot be transferred to S/G #4. Requires isolation to reduce releases.

8 MS06A C-SRO/BOP S/G #1 Steam Line Brk Outside Containment. Requires crew implementation of actions in Faulted/Rupture S/G Procedure ECA-3.1.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9 Appendix D Scenario Outline Form ES-D-1 Scenario 2 Summary The Crew will assume shift with the unit in a startup and power in the intermediate range with instructions to continuing raising power to the Point of Adding Heat. ATC will manipulate control rods as directed by SRO, BOP will primarily control S/G le vels as power is increased.

When the power increase is complete, Intermediate range channel N-36 will fail low. SRO will enter AOP-I.01 and direct RO actions to bypass the failed channel. If power increase is still in progress when the failure occurs, ATC will stabilize reactor power. SRO will evaluate Tech Specs and determine power cannot be increased above 5% until N-36 is operable.

After the NIS channel failure has been addressed, letdown backpressure transmitter PT-62-81 will fail low. Automatic control action will reduce letdown flow to attempt to increase pressure. ATC manual control of the controller in accordance with the annunciator re sponse procedure will be re quired to restore normal letdown flow.

When normal letdown flow has been restored, 480 Vac Shutdown board 1B1-B will be lost due to a board fault and will not be restored during the scenario. SRO will implement AOP-P.05 and direct various ESF pumps to be locked out due to loss of power to the pump or supporting equipment. SRO will evaluate Tech Specs to identify, as a minimum, the Tech Spec directly related to the board and any other more limiting Tech Specs including 3.0.3 due to power loss to PORV block valve.

When 480 Vac board AOP actions and SRO Tech Spec evaluation is complete, Steam Generator #1 will develop a ~200 gpm tube rupture requiring Reactor Trip, Safety Injection, and implementation of emergency procedures. During performance of E-3, crew will isolate ruptured S/G to complete the first critical task and cooldown to target RCS Temperature to complete the second critical task.

When Safety Injection is actuated, a Slave Relay failure in the SSPS results in failure of several automatic actions to occur including Train "A" Control Room isolation and several ESF Pump Starts. Manual action is required by ATC to initiate isolation and start ESF Pumps.

During performance of E-3 actions, or possibly earlier as prudent action, operators will attempt to transfer steam supply for the Turbine Driven Auxiliary Feedwater pump from ruptured S/G #1 to S/G #4. The normal transfer will not work due to a failure of the #1 S/G steam supply valve. Isolation of an upstream steam supply will be required to reduce offsite releases from the ruptured S/G.

After the cooldown to target temperature in E-3 is complete, ruptured S/G #1 will develop a steam line break outside containment upstream of the MSIV resulting in depressurization of the Ruptured S/G and transition to Emergency Contingency Procedure ECA-3.1. In ECA-3.1 the Crew will evaluate current RCS cooldown and initiate continued cooldown to cold shutdown as required at this time consistent with specified T-cold cooldown limit of 100 oF/hr to complete the third critical task.

The scenario may be terminated after RCS Cooldown evaluation is complete and cooldown is initiated if required.

Appendix D NUREG 1021 Revision 9 Time: Now Date:

Today Unit 1 MCR Checklist (751-2428 ID 7636)

Part 1 - Completed by Off-going Shift / Reviewed by On-coming Shift Mode 2, 10

-3% Power 0 MWe PSA Risk: Green Grid Risk: Green

RCS Leakage ID .02 gpm, UNID .01 gpm Cumulative Purge Time _50.5 Hours_

NRC phone Authentication Code Until 0800 H3H8 After 0800 42DF Common Tech Spec Actions U-1 Tech Spec Actions Protected Equipment Shift Priorities Plant Startup in progress following 1 week shutdown. O-GO-2 Section 5.3 is complete and Plant is stable at ~10-3 % power. Continue reactor startup in accordance with 0-GO-3 Section 5.2, step 1 and stabilize between 1and 2% power. Rx Engineering spreadsheet for power increase above 1 to 2% is being developed and verified and will be provided prior to power increase above that point. The Preconditioned

power level is 100%.

Part 2 - Performed by on-coming shift Verify your current qualifications Review Operating Log since last held shift or 3 days, whichever is less Standing Orders / Shift Orders TACF Immediate required reading LCO Actions Part 3 - Performed by both off-going and on-coming shift Walk down of MCR Control Boards

Time: Now Date:

Today MAIN CONTROL ROOM (7690) Train_A_Week OUTSIDE (7666) [593-5214] AUXILIARY BUILDING (7775) TURBINE BUILDING (7771) (593-8455)

Time: Now Date:

Today Equipment Off-Normal (Pink Tags) UNID And Noun Name Panel Problem Description WO / PER Number Date Scheduled MCR WO List ID And Noun Name Panel Problem Description WO/PER Number Date Scheduled

UNIT ONE REACTIVITY BRIEF Date: Today Time: Now

General Information RCS Boron:

1729 ppm Today BA Controller Setpoint:

47%

• RCS B-10 Depletion:

2 ppm Operable BAT:

A BAT A Boron:

6850 ppm BAT C Boron:

6850 ppm RWST Boron:

2601 ppm Nominal Gallons per rod step from N/A: N/A gallons of acid, N/A gallons of water

• Verify boric acid flow contro ller is set at Adjusted BA Controller Setting iaw 0-SO-62-7 section 5.1 Estimated values for a 1° Change in Tave **

Gallons of acid:

N/A Gallons of water:

N/A Rod Steps: N/A Estimated rods/boron for emergency step power reduction ** (Assuming Xenon equilibrium and no reactivity effects due to Xenon. 2/3 total reactivity from rods, 1/3 from boron)

Power reduction amount Estimated Final Rod Position Estimated boron addition 10% N/A Steps on bank D N/A gallons 30% N/A Steps on bank D N/A gallons 50% N/A Steps on bank D N/A gallons

• • These values are approximations and not int ended nor expected to be exact. The values may be superseded by Rx Engineering or SO-62-7 calculated values. These values are calculated assuming 100%

steady state power operation onl

y. Engineering data last updated one week ago. Data Valid until one week from now. Previous Shift Reactivity Manipulations Number of dilutions: 0 Number of borations: 0 Rod steps in: 0 Gallons per dilution: 0 Gallons per boration: 0 Rod steps out: 0 Total amount diluted: 0 Total amount borated: 0 Net change: 0 IN/Out Current Shift Estimated Reactivity Manipulations Number of dilutions: ***

Number of borations: ***

Rod steps in: ***

Gallons per dilution: ***

Gallons per boration: ***

Rod steps out: ***

Total expected dilution: ***

Total expected boration: ***

Net change: *** In/Out Remarks: Rx Power - 0% MWD/MTU - 1000

• • • Reactor Engineering Spreadsheet to be provided.

Next Unit 1 Flux Map is scheduled -

three weeks from now Unit 1 M-P is 0 PPM Unit Supervisor: _______________________________

Name/Date Operations Chemistry Information Boron Results Sample Point Units Boron Date / Time Goal Limit U1 RCS ppm 1729 Today / Now Variable Variable U2 RCS ppm 816 Today / Now Variable Variable U1 RWST ppm 2601 Today / Now 2550 - 2650 2500 - 2700 U2 RWST ppm 2569 Today / Now 2550 - 2650 2500 - 2700 BAT A ppm 6850 Today / Now Variable Variable BAT B ppm 6850 Today / Now Variable Variable BAT C ppm 6850 Today / Now Variable Variable U1 CLA #1 ppm 2556 Today / Now 2470-2630 2400-2700 U1 CLA #2 ppm 2575 Today / Now 2470-2630 2400-2700 U1 CLA #3 ppm 2591 Today / Now 2470-2630 2400-2700 U1 CLA #4 ppm 2589 Today / Now 2470-2630 2400-2700 U2 CLA #1 ppm 2531 Today / Now 2470-2630 2400-2700 U2 CLA #2 ppm 2650 Today / Now 2470-2630 2400-2700 U2 CLA #3 ppm 2522 Today / Now 2470-2630 2400-2700 U2 CLA #4 ppm 2526 Today / Now 2470-2630 2400-2700 Spent Fuel Pool ppm 2547 Today / Now

> 2050 > 2000 Lithium Results Goal Midpoint U1 RCS Lithium ppm 1.1 Today / Now

>1 >1 U2 RCS Lithium ppm 2.43 Today / Now 2.18-2.48 2.33 Primary to Secondary Leakrate In formation (Total CPM RM-90-99/119)

Indicator Units U1 Date / Time U2 Date/Time SI 50 S/G Leakage?

Yes/No No Today / Now No Today / Now SI 137.5 CVE Leakrate gpd < 0.1 Today / Now

< 0.1 Today / Now 5 gpd leak equivalent cpm 380 Today / Now 68 Today / Now 30 gpd leak equivalent cpm 1980 Today / Now 83 Today / Now 50 gpd leak equivalent cpm 3250 Today / Now 206 Today / Now 75 gpd leak equivalent cpm 4850 Today / Now 455 Today / Now CVE Air Inleakage cfm 10 Today / Now 12.5 Today / Now Bkgd on 99/119 cpm 50 Today / Now 40 Today / Now Correction Factor 99/119 cpm/gpd 10.69 Today / Now 14.13 Today / Now Steady state conditions are necessary for an accurate det ermination of leak rate using the CVE Rad Monitor

Page 1 of 4 NRC09C Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION Sim. Setup Reset IC- 16 Perform switch check. Allow the simulator to run for at least 3 minutes before loading SCEN file or starting the exercise. This will initialize ICS.

Load SCENS: NRC09C Place simulator in RUN.

Place OOS equipment in required position with tags. Clear alarms. Initialize simulator at 100 % RTP BOL Place Mode 1 placard on panels.

Place A Train Week sign on the simulator Active when SCENS loaded imf RH01A f:1 ior ZLOHS7410A_GREEN f:0 1A-A RHR PUMP INOPERABLE.

PLACE 1A-A RHR PUMP HS IN PTL AND TAG WITH HOLD ORDER.

Place Protected equipment tags on B Train RHR Pump, SI Pump, and CCP.

Event 1 When Directed by Lead Examiner insert: Key-1 irf ED120B1B007 f:0 k:1 120VAC BD 1-I BREAKER 7, CONTAINMENT RAD MAN 1-RE-9O-106 (Open Brkr)

If Dispatched to 120 v vital power board I, report Bkr 7 to 1-RE-90-106 tripped. Report in ~ 3 min.

If Dispatched to RM-90-106 report pump not running. Report in ~ 5 min.

Event 2 After ARP and Tech Spec Eval complete as Directed by Lead Examiner insert: Key-2 imf CH01C f:100 k:2 CONTAINMENT PRESSURE TRANSMITTER FAILURE PDT-30-44 (100%)

If MSS contacted report IM will report to MCR in ~45 min.

Page 2 of 4 NRC09C Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

Event 3 when AOP and Tech Spec Eval complete as Directed by Lead Examiner insert: Key-3 imf HD03A f:1 k:3 imf HD06A f:60 k:3 #3 HEATER DRAIN PUMP A TRIP LCV-6-105A FAILS TO VARIABLE POSITION (60%) Results in BOP Runback in 3-5 min.

If requested, provide tank level and valve position information from simulator diagram. Report in ~ 5 min.

If dispatched to check pump, report motor is hot and smells like burnt insulation. Report in

~ 5 min If dispatched to check motor breaker report instantaneous overcurrent relay operation. Report in ~ 5 min.

Event 4 Active when SCENS loaded imf RD09 f:1 RODS FAIL TO MOVE IN AUTO If Operations personnel dispatched to check rod control system locally, respond the problem is not obvious locally. Maintenance will need to investigate. Report in ~ 5 min.

Event 5 When AOP for HDT RB complete including reset of Turb and Steam Dump controls as Directed by Lead Examiner insert: Key-4 imf RX20 f:1 k:4 MAIN STEAM HEADER PRESSURE TRANSMITTER FAILS HI, PT-1-33 (Main Feedwater Pump Speed Increases)

If Maintenance requested to investigate inform crew that IMs will report to the MCR in ~45 min to discuss the failure.

Event 6 When MFP Speed and S/G levels are controlled and AOP is complete as Directed by Lead Examiner insert: Key-5 imf TH04A f:12 k:5 PZR SAFETY FAILURE SV-68-563 (Fails partially open ~13 gpm leak)

Page 3 of 4 NRC09C Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

Event 7 N/A Initiate Rapid Plant shutdown using AOP-C.03 per AOP-R.05.

If crew elects to shutdown using O-GO-5, provide the following input from Operations Management as required with Lead Examiner concurrence:

Operations Management directs rapid shutdown using AOP-C.03 to minimize chance of SV leak worsening.

Event 8 Modify SV Failure after load decrease complete as Directed by Lead

Examiner.

mmf TH04A f:100 PZR SAFETY FAILURE SV-68-563 (Fails Full Open requiring Rx Trip and SI)

Event 8 (Cont'd)

Event trigger 6 min after PRT rupture {th_rupt}imf TH01B f:0.075 d:360 LOCA - HOT LEG LOOP 2 (~400 gpm) (Note: Provides additional RCS leakage to simulate more severe SV Failure)

Event 9 Active when SCENS loaded imf RH01B f:1 RHR PUMP B TRIP ON START (Instantaneous Overcurrent)

If dispatched to check pump locally report smell of burnt insulation. Report in ~5 min.

If dispatched to check breaker locally, report instantaneous overcurrent relay operation.

Report in ~5 min.

Event 10 Active when SCENS loaded imf RP17A f:1 imf RP17B f:1 FAILURE OF AUTO PHASE A ISOL - TRN-A FAILURE OF AUTO PHASE A ISOL - TRN-B (Can be manually actuated)

Event 11 Active when SCENS loaded imf CSCOHS7210A f:2

ior ZLOHS7210A_GREEN f:1 CONTAINMENT SPRAY PUMP 1B AUTO/MAN START FAILURE

OVERRIDE CONTAINMENT SPRAY BUMP 1B SWITCH GREEN LIGHT ON If dispatched to check pump or breaker report no obvious problem locally. Report in ~5 min.

Page 4 of 4 NRC09C Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

If crew requrest transfer of 1A Spray pump to Aux and closing locally wait ~ 3 min and insert: Key-6 ior AN_OV_609 f:2 k:6 ior ZLOHS7210A_RED f:0 k:6 ior ZLOHS7210A_GREEN f:0 k:6 ior ZLOHS7210A_WHITE f:0 k:6 6900V SD BD 1B-B XFER SW IN AUX MODE CNTMT SPRAY PMP B MTR SW - RED OFF CNTMT SPRAY PMP B MTR SW - GRN OFF CNTMT SPRAY PMP B MTR SW - WHT OFF After inserting key-6, wait ~2 min and report the pump would not start after transfer to Aux Control.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 1 of 49 Event

Description:

120 Volt Vital A/C Breaker to Lower Cntmnt Rad Monitor RM-90-106 Trips Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 1 Indications available: Alarm XA-55-1C, A-7 "120V AC VITAL PWR BD 1-I UV OR BKR TRIP" Alarm XA-55-12A, A-4 "1-RA-90-106A CNTMT BLDG LWR COMPT AIR MON HIGH RAD" Alarm XA-55-12A, A-5 "1-RA-90-106B CNTMT BLDG LWR COMPT AIR MON GAS INSTR MALF" Alarm XA-55-12A, A-6 "1-RA-90-106C CNTMT BLDG LWR COMPT AIR MON PART INSTR MALF" Flow light Dark on RI-90-106A (M-12)

Evaluator Note: Primary response is contained in two Annunciator Response Procedures. One is for the Breaker trip the other is for the radiation monitor instrument malfunction. Applicable steps from each are listed below.

Crew Refer to Annunciator Response Procedures for Vital Board I

Breaker Trip.

BOP CREW Refer to Annunciator Response Procedures for Rad Monitor Gas or Particulate Instrument Malfunction.

BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 2 of 49 Event

Description:

120 Volt Vital A/C Breaker to Lower Cntmnt Rad Monitor RM-90-106 Trips Time Position Applicant's Actions or Behavior SRO 3.3.3.1 Radiation Monitoring Instrumentation:

Action b. requires Action 27 of Table 3.3-6 item 2.b.i & ii. 3.4.6.1 RCS Leakage Detection Instrumentation.

Action b. Applies. 3.4.6.2 RCS Leakage Operational Leakage:

N/A CREW When Tech Spec Evaluation complete lead examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 3 of 49 Event

Description:

Cntmnt Press Transmitter PT-30-44 Fails to 100%

Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 2 Indications available: Alarm XA-55-6B, A-6 "PDS-30-42-B/A CONTAINMENT HIGH PRESSURE S.I. ACTUATE Alarm XA-55-6B A-7 "PDS-30-42A CONTAINMENT HI-HI PRESSURE STEAMLINE ISOL Indicator PDI-30-44 on M-6 Failed upscale Blue Light for S/G Level Adverse SP Prot Set II Lit on M-4 (XI-3-204) Alarm XA-55-3C, E-2 "STM GEN LEVEL ADVERSE SETPOINT SR-I.05 O Implement actions of AOP SRO ns are complete) (Tech Spec Evaluation will probably not be done until AOP actio Action 11 from Table 3.3-1 item 14.D. Ap plies Action 17 Applies from Table 3.3-3 ite m 4.c & 4.c c.d.ii. Action 18 Applies from Table 3.3-3 items 2.c, 3.b.3, Action 38 Applies from Table 3.3-3 Items 6.c.i.d & 6.

Action 1 from Table 3.3-10 item 4 Ap plies SRO (Go To Sectio n 2.1)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 4 of 49 Event

Description:

Cntmnt Press Transmitter PT-30-44 Fails to 100%

Time Position Applicant's Actions or Behavior CREW (Appendix C is applicable)

When Tech Spec Evaluation is complete lead examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 & 4 Page 5 of 49 Event

Description:

Plant Runback #3 HDTP A Trip, HDT Bypass vlv fail 60%, Control Rod Auto fail Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 3 Indications available:

1. 3 Heater Drain Tank Pump A Trip: White light on associated handswitch HS-6-112A (M-2) and Buzzer Alarm XA-55-1B, E-4 "MOTOR OVERLOAD PANEL 1-M-1 THRU 1-M-6 Alarm XA-55-2C, B-7 "ZS-6-105A & B NO 3 HTR DR TK BYPASS TO COND Runback: Alarm XA-55-2A, B-1 "TURBINE RUNBACK BOP Generator Megawatts decreasing Auto Rod Failure: Megawatts decreasing with no rod insertion Evaluator Note: Runback does not occur immediately when #3 HDT pump trips. Bypass valve failure will eventually result in reducing #3 HDT discharge flow to less than 5500 gpm as #3 HDT level decreases due to excessive bypass flow. The Runback will be delayed 2-3 minutes from the time of the pump trip.

BOP Refer to AOP for motor trip out alarm SRO Enter and Direct actions of AOP-S.04 Section 2.1 BOP BOP (RNO until Runback actually occurs))

(Skip c. until Runback occurs. Continue where noted below)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 & 4 Page 6 of 49 Event

Description:

Plant Runback #3 HDTP A Trip, HDT Bypass vlv fail 60%, Control Rod Auto fail Time Position Applicant's Actions or Behavior Evaluator Note: Following 3 steps will not be performed until runback actually occurs.

BOP RO (Manual insertion required when runback occurs)

RO Evaluator Note: Continue at this step until runback occurs.

BOP BOP CREW BOP BOP CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 & 4 Page 7 of 49 Event

Description:

Plant Runback #3 HDTP A Trip, HDT Bypass vlv fail 60%, Control Rod Auto fail Time Position Applicant's Actions or Behavior W CRE (RNO) BO P R O SR O (SRO may address AOP-C.01 for the Auto Rod Failure at this time. AOP-C.01 performance not assumed for this scenario)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 & 4 Page 8 of 49 Event

Description:

Plant Runback #3 HDTP A Trip, HDT Bypass vlv fail 60%, Control Rod Auto fail Time Position Applicant's Actions or Behavior When Turbine controls have been restored and Steam Sump C-7 Interlock has been reset, lead examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 9 of 49 Event

Description:

Steam Hdr Pressure Transmitter PT-1-33 Fails High Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 5 Indications available: Alarm XA-55-3C, C-1 "PS-3-4 NO 1 FW HTR PRESSURE HI" Indicator PI-1-33 on M-4 Failed upscale. Main Feedwater Pump speed increasing SRO Enter and direct performance of AOP-S.01, Section 2.2.

BOP (Main Feed Pump Speed will need to remain in manual for the rest of the scenario)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 10 of 49 Event

Description:

Steam Hdr Pressure Transmitter PT-1-33 Fails High Time Position Applicant's Actions or Behavior BOP (MFP Trip not required)

BOP RO CREW SRO Lead Examiner may cue the next event when desired.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 11 of 49 Event

Description:

Pressurize Safety Valve Leak ~13 gpm Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 6 Indications Available: Alarm XA-55-5A, D-2 "TS-68-328 PRESSURIZER SAFETY VALVE LINES TEMP HIGH Safety Valve Acoustic Monitor indication increasing (~50%) XX-68-363A on M-4 Tailpipe temperature indicator TI-68-563 increasing on M-4 RCS Press decrease SRO Enter and direct actions of AOP-R.05.

SRO (Not Evaluated for this event)

SRO CREW SRO (Should Go To Section 2.1)

RO RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 12 of 49 Event

Description:

Pressurize Safety Valve Leak ~13 gpm Time Position Applicant's Actions or Behavior RO RO RO BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 13 of 49 Event

Description:

Pressurize Safety Valve Leak ~13 gpm Time Position Applicant's Actions or Behavior CREW (RNO) (RNO) (Step continued next Table Cell)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 14 of 49 Event

Description:

Pressurize Safety Valve Leak ~13 gpm Time Position Applicant's Actions or Behavior CREW (RNO) (Crew may elect to vent PRT during scenario to keep pressure within normal range)

BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 15 of 49 Event

Description:

Pressurize Safety Valve Leak ~13 gpm Time Position Applicant's Actions or Behavior CREW (RNO) (Step RNO Continued next Table Cell)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 16 of 49 Event

Description:

Pressurize Safety Valve Leak ~13 gpm Time Position Applicant's Actions or Behavior CREW CREW Evaluator Note: Leak exceeds 10 gpm Tech Spec Limit therefore, Shutdown should be initiated. AOP-R.05 may be discontinued at this point and shutdown initiated. See Next Event Guide.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 17 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior Console Operator: No action required for this event.

Indications Available:

N/A Directed by procedure.

Evaluator Note: Crew may decide to shutdown using 0-GO-5 rather than AOP-C.03. If this is the case, a prompt from Operations Management should be provided that rapid shutdown should be performed using AOP-C.03.

S RO 3. Enter and direct performance of AOP-C.0 S RO CR EW BOP/RO B OP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 18 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior SRO/RO (Due to previous runback, power is not at 100%, Boration volume may be around 500-600 gal for reduction from ~80% to 20% at 10 gal/%)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 19 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 20 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior RO (Automatic Rod control not available due to earlier failure RNO Required)

OR OR Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 21 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior BOP (Automatic MFP Speed Not available due to earlier failure.

RNO Required)

BOP RO SRO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 22 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior SRO RO CREW SRO (RNO) SRO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 23 of 49 Event

Description:

Rapid Plant Shutdown Due to Small RCS Leak Using AOP-C.03 Time Position Applicant's Actions or Behavior CREW When sufficient load reduction has been completed, lead examiner may cue the next event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 24 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 8 Indications available: Safety Valve Acoustic Monitor indication Maximum (XX-68-363A on M-4) Pressurizer Pressure decreasing SRO Direct Manual Rx Trip and Safety Injection.

SRO Enter and Direct Actions of E-0 Evaluator Note: Crew may Trip RCPs based on E-0 foldout page at any time during performance of E-0 when RCP Trip Criteria are met. If not addressed based on foldout page, RCPs should be stopped at step 8 of E-0. (CRITICAL TASK 1)

Crew may manually initiate Phase A Containment Isolation during performance of E-0 as prudent action. If not initiated as prudent action, it will be initiated during performance of ES-0.5. (CRIITICAL TASK 2). NOTE 1: Steps 1 through 4 are immediate action steps.

NOTE 2: This procedure has a foldout page.

RO BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 25 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior BOP RO BOP (ES-0.5 at end of Scenario)

BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 26 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior BOP/RO Critical Task 1 RO (Critical Task - Trip RCPs based 1250 psi RCP Trip criteria

Prior to Exiting E-0)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 27 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO/BOP OR (If No Perform RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 28 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO (RNO Required)

(Transition to E-1)

Evaluator Note: The primary procedure flowpath at this point should be E-1 to ECA-1.1 at step 15 of E-1. The Event Guide for this path follows. Upon transition to E-1, Status Tree monitoring is in effect therefore, during the performance of E-1, crew may transition to FR-Z.1 based on containment pressure >2.8 psi. An event guide for the applicable portions of FR-Z.1 follows this event

guide for E-1 and ECA-1.1.

Also, During performance of E-1, ECA-1.1, or FR-Z.1, sump swapover conditions may occur (RWST <27%). The crew should transition to ES-1.3. An event guide for the applicable portions of ES-1.3 follow the event guide for FR-Z.1. If ES-1.3 is implemented, the crew should transition to ECA-1.1 at step 5. Whenever ECA-1.1 is entered, it allows for concurrent performance of FR-Z.1 with ECA-1.1 if required.

Evaluator Note: When Phase B occurs during E-0 or E-1, 1B-B Containment spray pump will fail to Auto start and will not manually start.

When the pump fails to start, crew should attempt to manually start it. This failure requires no other specific action other than dispatching personnel to determine the problem as time allows. This failure may be addressed during performance of ES-0.5.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 29 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior SRO Enter and Direct Actions of E-1.

SRO (RCPs should already be stopped)

RO/BOP OR (RNO) (Step continued next table cell)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 30 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 31 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior BOP RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 32 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO/BOP (Based on crew specific timing criteria may or may not be met) (RNO if required)

OR (Pressure should still be decreasing slowly RNO required)

(Sub steps d. and e. included for information only)

RO (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 33 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO (RNO) BOP RO/BOP (RNO) RO/BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 34 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO (RNO) BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 35 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO OR (RNO) SRO Enter and direct actions of ECA-1.1 RO (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 36 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior RO RO (RNO) BOP RO RO RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8, 9, & 10 Page 37 of 49 Event

Description:

Przr SV Fails 100%, 1B-B RHR Pmp Trips, Both Trn Phase A Isol Auto Fail Time Position Applicant's Actions or Behavior CRITICAL TASK 3 RO RO (RNO - Required # of Spray pumps should be 0. Running spray pump 1A-A should be stopped)

(Critical Task: Stop Containment Spray Pumps prior to initiating RCS cooldown in ECA-1.1)

Lead Examiner may Terminate Scenario When Running Containment Spray Pump is shutdown in the preceding ECA-1.1 step.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # FR-Z.1 Page 38 of 49 Event

Description:

High Containment Pressure Time Position Applicant's Actions or Behavior FR-Z.1 Actions RO RO RO BOP (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # FR-Z.1 Page 39 of 49 Event

Description:

High Containment Pressure Time Position Applicant's Actions or Behavior RO (RNO) RO RO RO (Phase A Failures should be previously addressed at this point)

RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # FR-Z.1 Page 40 of 49 Event

Description:

High Containment Pressure Time Position Applicant's Actions or Behavior RO BOP BOP BOP OR (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # FR-Z.1 Page 41 of 49 Event

Description:

High Containment Pressure Time Position Applicant's Actions or Behavior BOP (RNO as required)

(Steps c. thru e. as required)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # FR-Z.1 Page 42 of 49 Event

Description:

High Containment Pressure Time Position Applicant's Actions or Behavior RO RO (RNO) SRO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-1.3 Page 43 of 49 Event

Description:

Transfer To RHR Containment Sump Time Position Applicant's Actions or Behavior ES-1.3 Actions RO RO (RNO) RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-1.3 Page 44 of 49 Event

Description:

Transfer To RHR Containment Sump Time Position Applicant's Actions or Behavior RO/SRO (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-0.5 Page 45 of 49 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior ES-0.5 Actions VERIFY D/G ERCW supply valves OPEN.

BOP VERIFY at least four ERCW pumps RUNNING.

BOP VERIFY CCS pumps RUNNING:

Pump 1A-A (2A-A) Pump 1B-B (2B-B) Pump C-S.

BOP VERIFY EGTS fans RUNNING.

BOP VERIFY generator breakers OPEN.

BOP VERIFY AFW pumps RUNNING:

MD AFW pumps TD AFW pump.

NOTE AFW level control valves should NOT be repositioned if manual action has been taken to control S/G levels, to establish flow due to failure, or to isolate a faulted S/G.

BOP CHECK AFW valve alignment:

a. VERIFY MD AFW LCVs in AUTO.

b. VERIFY TD AFW LCVs OPEN.

c. VERIFY MD AFW pump recirculation valves FCV-3-400 and FCV-3-401 CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-0.5 Page 46 of 49 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP VERIFY MFW Isolation:

MFW pumps TRIPPED MFW regulating valves CLOSED MFW regulating bypass valve controller outputs ZERO MFW isolation valves CLOSED BOP MONITOR ECCS operation:

VERIFY ECCS pumps RUNNING: CCPs RHR pumps SI pumps VERIFY CCP flow through CCPIT.

CHECK RCS pressure less than 1500 psig.

VERIFY SI pump flow. CHECK RCS pressure less than 300 psig.

VERIFY RHR pump flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-0.5 Page 47 of 49 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior CRITICAL TASK 2 BOP VERIFY ESF systems ALIGNED:

Phase A ACTUATED:

o PHASE A TRAIN A alarm LIT [M-6C, B5].

o PHASE A TRAIN B alarm LIT [M-6C, B6]. (RNO) Critical Task: Initiate at least one train of Phase A Containment Isolation prior to completion of ES-0.1 Containment Ventilation Isolation ACTUATED:

o CONTAINMENT VENTILATION ISOLATION TRAIN A alarm LIT [M-6C, C5].

o CONTAINMENT VENTILATION ISOLATION TRAIN B alarm LIT [M-6C, C6].

Status monitor panels:

o 6C DARK o 6D DARK o 6E LIT OUTSIDE outlined area o 6H DARK o 6J LIT. Train A status panel 6K:

o CNTMT VENT GREEN o PHASE A GREEN Train B status panel 6L:

o CNTMT VENT GREEN o PHASE A GREEN Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-0.5 Page 48 of 49 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP (RNO - 1B-B Cntmnt Spray Pmp will not start Auto or Manual)

(Step continued in next Table Cell)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # ES-0.5 Page 49 of 49 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP VERIFY pocket sump pumps STOPPED: [M-15, upper left corner] HS-77-410, Rx Bldg Aux Floor and Equipment Drain Sump pump A HS-77-411, Rx Bldg Aux Floor and Equipment Drain Sump pump B.

BOP DISPATCH personnel to perform EA-0-1, Equipment Checks Following ESF Actuation.

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

Sequoyah Scenario No.:

3 Op Test No.:

NRC Examiners:

Operators:

Initial Conditions: 100% Power BOL 1A-A RHR Pump Out of Service. Turnover: Maintain Current Plant conditions. Target CTs: Trip Reactor Coolant Pumps based on 1250 psi RCP Trip Criteria prior to exiting E-0. Initiate at least one train of Phase A Containment isolation prior to completion of ES-0.5. Operate/Stop containment Spray pumps in accordance with ECA-1.1 to minimize RWST outflow prior to initiating RCS cooldown to cold shutdown in ECA-1.1. Event # Malf. No. Event Type*

Event Description 1 ED120B1B 007 TS-SRO C-SRO 120 Vac Vital power breaker to lower Containment radiation monitor 1-RM-90-106 trips. SRO Tech Spec Evaluation.

2 CH01C TS-SRO I-SRO Containment pressure instrument fails high requiring implementation of AOP-I.05. SRO Tech Spec Evaluation.

3 HD03A HD06A C-SRO/BOP Number 3 Heater Drain Tank (HDT) pump A trips resulting in #3 HDT bypass to condenser valve opening and sticking partially open resulting in plant runback. AOP-S.04 performance required including BOP reset of main turbine and steam dump controls.

4 RD09 C-SRO/ATC Control Rods fail to move in Auto during plant runback. ATC manually controls rods to control RCS temperature. If time allows, SRO refers to AOP-C.01.

5 RX20 C-SRO/BOP Steam header pressure transmitter PT-1-33 fails high increasing MFP speed and requiring manual control of MFP.

6 TH04A C-SRO/ATC Pressurizer safety valve develops small leak (~13 gpm). Requires performance of AOP-R.05 and manual control of charging. Leak also requires rapid plant shutdown.

7 N/A R-ATC N-SRO/BOP Perform rapid plant shutdown using AOP-C.03. Manual Rod control will be required.

8 TH04A M-All Leaking Pressurizer safety valve fails full open requiring Reactor Trip and Safety Injection.

9 RH01B C-SRO/ATC 1B-B RHR pump trips on start from SI. With 1B-B RHR pump out of service containment sump recirculation capability is lost which eventually requires implementation of ECA-1.1.

10 RP17A RP17B C-SRO/ATC Both trains of Phase A Containment Isolation fail to automatically actuate. Manual actuation of at least one train of isolation is required. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9 Appendix D Scenario Outline Form ES-D-1 Scenario 3 Summary Crew will assume shift at 100% power BOL with the Train A RHR pump out of service for repairs. Crew directions will be to maintain current plant conditions.

Shortly after assuming shift, 120 Vac vital power supply breaker to lower containment radiation monitor 1-RM-90-106 will trip. BOP should refer to annunciator response procedures and dispatch personnel to check the power board and radiation monitor. SRO will evaluate Radiation monitoring and RCS leakage detection instrumentation Tech Specs.

After Tech Spec evaluation is complete, containment pressure instrument will fail high requiring implementation of AOP-I.05. SRO will evaluate and apply Reactor Trip, ESF and Post Accident Monitoring instrumentation Tech Specs.

After AOP and Tech Spec Evaluation are complete, Number 3 Heater Drain Tank Pump A will trip. Increasing #3 Heater Tank level will result in bypass to condenser valve 1-LCV-6-105A opening which sticks partially open eventually resulting in low #3 HDT level and reduced HDT return flow to the condensate system below the runback criteria. A BOP automatic plant runback will occu

r. During the runback, automatic rod insertion will not work requiring manual rod control for RCS Temperature control. Following the runback, AOP-S.04 will require resetting turbine controls and steam dump controls. If time allows prior to the next event SRO may begin implementation of AOP-C.01 which contains minimal actions that can be taken for this event.

When turbine and steam dump controls have been reset from the runback, Main Steam Header pressure transmitter PT-1-33 fails high. Speed of both Main Feedwater pumps will increase to attempt to increase D/P between Main Steam Header and Feedwater pressure. Manual control of MFW pump is required SRO will implement AOP-S.01.

When Main Feedwater pump speed and S/G levels are controlled, Pressurizer safety valve SV-68-563 develops a leak of ~13 gpm. Crew will diagnose t he leak and enter AOP-R.05 fo r RCS leakage. Charging flow adjustments will be required and a leak rate estimate will be re quired to determine that the leak exceeds Tech Spec limits and Rapid plant shutdown is required. Rapid plant shutdown will be initiated using AOP-C.03.

After the rapid shutdown has resulted in sufficient power reduction, the leaking Przr safety valve will fail full open requiring reactor trip and safety injection. RCS pressure will reach the 1250 psi Reactor Coolant pump trip criteria setpoint. At this point, timely RCP trip is required to complete the first critical task.

When SI is actuated, both trains of Phase A Containment Isolation fail to automatically actuate. Since the Pressurizer Relief Tank ruptures shortly after the SV fails open, at least one train of containment isolation is required to ensure leakage from the containment is minimized. Timely manual actuation of Phase A containment isolation (at least one train) is required to complete the second critical task.

Also, when Safety Injection is actuated the only operable RHR pump (1B-B) trips on overcurrent. With both RHR pumps unavailable transition to ECA-1.1 due to loss of containment sump recirculation capability will eventually be required. Depending on crew specific timing, they may progress through E-0, E-1, ES-1.1, FR-Z.1, ES-1.2, and ES-1.3 prior to transitioning to ECA-1.1. In ECA-1.1, crew will ensure both containment spray pumps are stopped to conserve RWST inventory to complete the last critical task.

The scenario may be terminated after Containment Spray pumps are shutdown as required in ECA-1.1.

Appendix D NUREG 1021 Revision 9 Time: Now Date:

Today Unit 1 MCR Checklist (751-2428 ID 7636)

Part 1 - Completed by Off-going Shift / Reviewed by On-coming Shift Mode 1, 100% Power 1204 MWe PSA Risk: Green Grid Risk: Green

RCS Leakage ID .02 gpm, UNID .01 gpm Cumulative Purge Time _50.5 Hours_

NRC phone Authentication Code Until 0800 H3H8 After 0800 42DF Common Tech Spec Actions U-1 Tech Spec Actions LCO 3.5.2 & 3.6.2.1 - 1A-A RHR pump has been tagged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance to perform motor winding test. Expected Return to service is ~2 hours.

Protected Equipment 1B-B RHR Pump 1B-B Safety Injection Pump 1B-B Charging Pump

Shift Priorities

Part 2 - Performed by on-coming shift Verify your current qualifications Review Operating Log since last held shift or 3 days, whichever is less Standing Orders / Shift Orders TACF Immediate required reading LCO Actions Part 3 - Performed by both off-going and on-coming shift Walk down of MCR Control Boards

Time: Now Date:

Today MAIN CONTROL ROOM (7690) Train_A_Week OUTSIDE (7666) [593-5214] AUXILIARY BUILDING (7775) 1A-A RHR pump has been tagged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance to perform motor winding test.

Expected Return to service is ~2 hours.

TURBINE BUILDING (7771) (593-8455)

Time: Now Date:

Today Equipment Off-Normal (Pink Tags) UNID And Noun Name Panel Problem Description WO / PER Number Date Scheduled MCR WO List ID And Noun Name Panel Problem Description WO/PER Number Date Scheduled

UNIT ONE REACTIVITY BRIEF Date: Today Time: Now

General Information RCS Boron:

1093 ppm Today BA Controller Setpoint:

27%

• RCS B-10 Depletion:

2 ppm Operable BAT:

A BAT A Boron:

6850 ppm BAT C Boron:

6850 ppm RWST Boron:

2601 ppm Nominal Gallons per rod step from 219:

7 gallons of acid, 36 gallons of water

• Verify boric acid flow contro ller is set at Adjusted BA Controller Setting iaw 0-SO-62-7 section 5.1 Estimated values for a 1° Change in Tave **

Gallons of acid:

26 Gallons of water:

138 Rod Steps: 4 Estimated rods/boron for emergency step power reduction ** (Assuming Xenon equilibrium and no reactivity effects due to Xenon. 2/3 total reactivity from rods, 1/3 from boron)

Power reduction amount Estimated Final Rod Position Estimated boron addition 10% 198 Steps on bank D 101 gallons 30% 174 Steps on bank D 295 gallons 50% 152 Steps on bank D 485 gallons

• • These values are approximations and not int ended nor expected to be exact. The values may be superseded by Rx Engineering or SO-62-7 calculated values. These values are calculated assuming 100%

steady state power operation onl

y. Engineering data last updated one week ago. Data Valid until one week from now. Previous Shift Reactivity Manipulations Number of dilutions: 0***

Number of borations: 0 Rod steps in: 0 Gallons per dilution: 0 Gallons per boration: 0 Rod steps out: 0 Total amount diluted: 0 Total amount borated: 0 Net change: 0 IN/Out Current Shift Estimated Reactivity Manipulations Number of dilutions: 0 Number of borations: 0 Rod steps in: 0 Gallons per dilution: 0 Gallons per boration: 0 Rod steps out: 0 Total expected dilution: 0 Total expected boration: 0 Net change: 0 In/Out Remarks: Rx Power - 100% MWD/MTU - 1000 Xenon & Samarium at Equilibrium

• • • The boron letdown curve is flat for the next 25 EFPD.

Next Unit 1 Flux Map is scheduled -

three weeks from now Unit 1 M-P is 0 PPM Unit Supervisor: _______________________________

Name/Date Operations Chemistry Information Boron Results Sample Point Units Boron Date / Time Goal Limit U1 RCS ppm 1093 Today / Now Variable Variable U2 RCS ppm 816 Today / Now Variable Variable U1 RWST ppm 2601 Today / Now 2550 - 2650 2500 - 2700 U2 RWST ppm 2569 Today / Now 2550 - 2650 2500 - 2700 BAT A ppm 6850 Today / Now Variable Variable BAT B ppm 6850 Today / Now Variable Variable BAT C ppm 6850 Today / Now Variable Variable U1 CLA #1 ppm 2556 Today / Now 2470-2630 2400-2700 U1 CLA #2 ppm 2575 Today / Now 2470-2630 2400-2700 U1 CLA #3 ppm 2591 Today / Now 2470-2630 2400-2700 U1 CLA #4 ppm 2589 Today / Now 2470-2630 2400-2700 U2 CLA #1 ppm 2531 Today / Now 2470-2630 2400-2700 U2 CLA #2 ppm 2650 Today / Now 2470-2630 2400-2700 U2 CLA #3 ppm 2522 Today / Now 2470-2630 2400-2700 U2 CLA #4 ppm 2526 Today / Now 2470-2630 2400-2700 Spent Fuel Pool ppm 2547 Today / Now

> 2050 > 2000 Lithium Results Goal Midpoint U1 RCS Lithium ppm 1.1 Today / Now

>1 >1 U2 RCS Lithium ppm 2.43 Today / Now 2.18-2.48 2.33 Primary to Secondary Leakrate In formation (Total CPM RM-90-99/119)

Indicator Units U1 Date / Time U2 Date/Time SI 50 S/G Leakage?

Yes/No No Today / Now No Today / Now SI 137.5 CVE Leakrate gpd < 0.1 Today / Now

< 0.1 Today / Now 5 gpd leak equivalent cpm 380 Today / Now 68 Today / Now 30 gpd leak equivalent cpm 1980 Today / Now 83 Today / Now 50 gpd leak equivalent cpm 3250 Today / Now 206 Today / Now 75 gpd leak equivalent cpm 4850 Today / Now 455 Today / Now CVE Air Inleakage cfm 10 Today / Now 12.5 Today / Now Bkgd on 99/119 cpm 50 Today / Now 40 Today / Now Correction Factor 99/119 cpm/gpd 10.69 Today / Now 14.13 Today / Now Steady state conditions are necessary for an accurate det ermination of leak rate using the CVE Rad Monitor

BORON.txt 0[REACTF-VERS SQ2.1]BORATION/DILUTION CALCULATION SEQUOYAH UNIT 1 CYCLE 16 RCS AVG TEMP 578.2 DEG F RCS PRESSURE 2235.0 PSIG PZR LEVEL 60.0%MAKEUP WTR CONC.0 PPM BORIC ACID CONC 6820.0 PPM INITIAL CONC FINAL BORIC ACID MAKEUP WTR BORON CONC CHANGE BORON CONC ADDITION ADDITION (PPM)(PPM)(PPM)(GAL)(GAL)----------

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1093.0 17.3 1110.3 191.8.0 0 page 1 Page 1 of 3 NRC09D Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION Sim. Setup Reset IC- 16 Perform switch check. Allow the simulator to run for at least 3 minutes before loading SCEN file or starting the exercise. This will initialize ICS.

Load SCENS: NRC09D Place simulator in RUN.

Place OOS equipment in required position with tags. Clear alarms. Initialize simulator at 100 % RTP BOL Place Mode 1 placard on panels.

Place A Train Week sign on the simulator Active when SCENS loaded imf RH01A f:1 ior ZLOHS7410A_GREEN f:0 1A-A RHR PUMP INOPERABLE.

PLACE 1A-A RHR PUMP HS IN PTL AND TAG WITH HOLD ORDER.

Place Protected equipment tags on B Train RHR Pump, SI Pump, and CCP.

Event 1 Initiate Unit Shutdown for Main Gen H2 Leak Repair.

Event 2 When sufficient Load decrease complete as Directed by Lead Examiner insert: Key-1 imf CC10A f:1 k:1 CCS PUMP A OVERCURRENT TRIP If personnel dispatched to motor report motor hot to the touch and burned electrical insulation odor. Report in ~ 5 min.

If dispatched to Breaker, report Overcurrent Trip. Report in ~ 5 min.

Event 3 when CCS AOP and Tech Spec Eval complete complete as Directed by Lead Examiner insert:

Key-2 imf RC05 f:50 k:2

1-FCV-68-334 PRZR PORV FAILS 50% OPEN

Page 2 of 3 NRC09D Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

If Dispatched to remove power from 1-FCV-68-333 use Key-3 irf RCR04 f:0 k:3 PRZ PORV BLOCK VLV FCV-68-333 PWR REMOVAL When Dispatched to remove power from PORV Block Valve 1-FCV-68-333, wait ~ 5 min, insert remote function, and report to crew.

Event 4 When PORV AOP and TS Eval complete complete as Directed by Lead Examiner insert: Key-4 imf CV09 f:1 k:4 VCT LEVEL TRANSMITTER FAILS HIGH; 130-A (Letdown is diverted to HUT can be manually re-aligned to VCT)

If dispatched to check LI-62-129C in ACR report normal. If value requested report same as indicator on M-6 (Use camera to determine value). Report in ~ 5 min.

If dispatched to check LI-62-130 Locally (Panel L-268) report 100%. Report in ~ 5 min.

Event 5 When Letdown re-aligned to VCT complete as Directed by Lead Examiner insert: Key-5 imf FW05A f:1 k:5 TURBINE DRIVEN FEED PUMP A TRIP (lo Oil Pressure)

If dispatched to check the pump report significant oil line leak locally. If oil pumps (normal and DC emergency) are stopped the leak will decrease to trickle. Modify report accordingly. Report in ~ 3 min.

Role play as Fire OPS personnel and contain the spill as required.

Role play as Envoirnmental if contacted to evaluate the spill.

Event 6 Active when SCENS loaded imf FW10 f:1 TURBINE AFW PUMP AUTO-START FAILURE (Will manually start)

Page 3 of 3 NRC09D Rev 0 CONSOLE OPERATOR INSTRUCTIONS ELAP. TIME IC/MF/RF/OR # DESCRIPTION

Event 7 When Turb control Restoration I/P (AOP-S.01) as Directed by Lead Examiner insert: Key-6 imf MS02A F:100 k:6 imf MS02B F:100 k:6 imf MS02C F:100 k:6 imf MS02D F:100 k:6 MAIN STEAM LINE BREAK Outside Cntmt on

S/G # 1, 2, 3, & 4 (Note: Simulator Models limit Max individual S/G Break size. These 4 breaks are comparable to a 20% Design Basis S/L Break and therefore will be reported to the crew as a single break on S/G #1).

If dispatched to look for steam leak report large volume of steam coming from west valve vault room. MSIV closure will isolate the leak therefore, modify report as required based on MSIV status. Report in ~ 5 min.

Event 7 (Cont'd)

Active when SCENS loaded IMF RP16K616A F:1 IMF RP16K616B F:1 IMF RP16K623A F:1 IMF RP16K623B F:1 Tr A Main Stm Isol signal to FCV-1-4/11 Fails Tr B Main Stm Isol signal to FCV-1-4/11 Fails Tr A Main Stm Isol signal to FCV-1-22/29 Fails Tr B Main Stm Isol signal to FCV-1-22/29 Fails (All four MSIV do not receive an Auto main steam isolation signal requiring manual closure.)

Event 8 Event Trigger 10 sec after SI imf EG02A f:1 e:2 d:10 DIESEL GENERATOR TRIP DG 1A-A - (D/G Differential Trip 10 Sec after SI)

If dispatched to check D/G report Gen Differential Relay actuation. Report in ~ 10 min. Event 9 When crew starts checking SI termination criteria in E-0 as Directed by Lead Examiner insert: Key-7 imf ED01 f:1 k:7 TOTAL LOSS OF OFFSITE POWER

Report Grid disturbance from load dispatcher time to recover not yet known. Call and report in ~ 5 min.

If Unit 2 Status Requested, Unit 2 is tripped and stable, both 6.9 Kv Shutdown Boards are energized from D/Gs, no other problems at this time. Event 10 Active when SCENS loaded imf EG12B f:1

DG 1B-B BREAKER 1914 AUTO CLOSE

FAILURE (Bkr can be manually closed with Bkr switch after placing D/G 1B-B Synchronize switch in "SYNC" position at panel M-26)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 1 of 35 Event

Description:

Decrease Power Time Position Applicant's Actions or Behavior Console Operator:

No action required for Event 1 Indications available: None: Crew will initiate power reduction IAW 0-GO-5 Section 5.3.

SRO Direct a load reduction in accordance with 0-GO-5 Normal Power Operations, Section 5.3, and 0-SO-62-7 Boron Concentration Control, Section 6.4.

Evaluator Note:

Following Steps are from 0-SO-62-7 Boron Concentration Control, Section 6.4 CAUTION: Returning the Boric Acid Blender to service after unplugging, cleaning, or maintenance on Boric Acid System could introduce debris, sludge, air or solidified boron into CCP suction resulting in pump damage. Extreme care must be exercised to properly flush the Boric Acid piping following an outage.

NOTE: If a large amount of boration is required (plant shutdown), pzr heaters should be energized to cause spray operation for equalizing boron concentration in RCS and pressurizer.

RO ENSURE makeup system aligned for AUTO operation in accordance with Section 5.1.

NOTE Steps 2 and 3 are N/A for minor power changes OR if immediate boration is required to maintain shutdown margin, to maintain rods above the insertion limit, during an emergency shutdown (AOP-C.03), during recovery of a dropped/misaligned rod (AOP-C.01), or at Chemistry recommendation in mode 3, 4, 5 or 6.

RO RECORD the quantity of boric acid required to achieve desired boron concentration using Appendix D.

___________ gals Crew PERFORM Appendix I Independent Verification of Calculation for Amount of Boric Acid or Primary Water. (N/A if App. D was performed by SRO to verify data from Rx Engineering)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 2 of 35 Event

Description:

Decrease Power Time Position Applicant's Actions or Behavior RO DETERMINE available boric acid volume in in-service BAT.

___________ gals RO PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the STOP position.

RO PLACE [HS-62-140B], CVCS Makeup Selector Switch to the BORATE position.

RO ADJUST [FC-62-139], Boric Acid Flow Controller to the desired flow rate.

RO SET [FQ-62-139], Batch Integrator to the desired quantity.

RO PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the START position.

RO ENSURE Boric Acid Pump aligned to blender in FAST speed by right red light LIT on [HS-62-230A] OR [HS-62-232A]. NOTE Flow oscillations and/or erratic controller response may require manual operation of Boric Acid Flow Controller

[FC-62-139] until stable conditions exist.

RO VERIFY Boric Acid Flow established.

NOTE It may take approximately 15 minutes before any changes to reactivity are indicated on nuclear instrumentation or RCS temperature indication.

RO IF reactor is critical, THEN MONITOR nuclear instrumentation and reactor coolant temperature to ensure proper response

from boration.

NOTE BAT operability limits are prescribed by TRM 3.1.2.6 (Modes 1-3) or 3.1.2.5 (Modes 4-6).

RO MONITOR Boric Acid Storage Tank level.

RO IF Volume Control Tank level increases to 63 percent, THEN ENSURE [LCV-62-118], Volume Control Tank Divert Valve OPENS to divert excess water to the Holdup Tank.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 3 of 35 Event

Description:

Decrease Power Time Position Applicant's Actions or Behavior NOTE Sample may be obtained at normal RCS sample intervals provided the unit is at power and the unit response following the boration is as expected.

RO WHEN boration is complete, THEN PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the STOP position. CHECK no primary water flow on either

[FI-62-142A] OR [FQ-62-142]. ENSURE [FC-62-142], Primary Water to Blender Flow Controller is in AUTO position and the potentiometer (dial indicator) is set at 35%. ADJUST [FC-62-139], Boric Acid Flow Controller to the desired blend solution in accordance with TI-44 Boron Tables. ENSURE [FCV-62-128]

is CLOSED. PLACE [HS-62-140B], CVCS Makeup Selector Switch to the AUTO position. PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the START position.

IF RCS boron sample required, THEN NOTIFY Chem Lab to obtain RCS boron sample.

NOTE Boration is done in batches until the total boron and/or power change is completed.

RO REPEAT this section as required to complete total boron change. RO WHEN total boration is complete, THEN: REALIGN the blender controls for AUTO makeup to the CVCS in accordance with Section 5.1.

NOTIFY Chem Lab to obtain RCS boron sample.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 4 of 35 Event

Description:

Decrease Power Time Position Applicant's Actions or Behavior US IF in modes 1, 2, or 3, THEN ENSURE requirements of TRM 3.1.2.6 are met.

Evaluator Note:

Following Steps are from 0-GO-5, Normal Power Operation, Section 5.3 Beginning at Notes prior to step 7. NOTES 1) Guidance on restoration of EHC Controls after a BOP runback is contained in Appendix B, Turbine Runback Restoration. 2) For core operating recommendations for situations such as end of core life coast down or unusual power maneuvers, contact Reactor Engineering for guidance.

3) It is recommended that AFD be controlled within the target band.

4) The following general approach should be used during power reduction: (a) borate RCS to reduce RCS TAVG within limits of TREF, (b) reduce turbine load to match TREF with TAVG (c) periodically take rod control to MANUAL from AUTO and insert the bank to move AFD near the target value, (d) return rod control to AUTO when not using the bank to control AFD, and (e) repeat the above as necessary to accomplish the load change.

5) Actions effecting reactivity are directed in the following step. 0-SO-62-7 requirements shall be adhered to for reactivity changes (i.e. reactivity balance, amounts of boric acid or water). All appropriate verifications and peer checks shall be utilized during performance.

BOP INITIATE a load reduction.

BOP MONITOR turbine load decreasing.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 5 of 35 Event

Description:

Decrease Power Time Position Applicant's Actions or Behavior MONITOR MFP discharge pressure:

DETERMINE MFP D/P Program setpoint using Appendix A.

IF auto control of any MFWP controller is NOT functional, THEN ADJUST MFWP speed as necessary to maintain MFWP A and B flow/speed approximately matched USING one of the following:

MFWP speed controller in MANUAL OR Gov Vlv Positioner USING 1, 2-SO-2/3-1, Sect 8.6.

CAUTION Do NOT exceed a load change rate of plus or minus 5%/minute or a step change of 10% NOTE TAVG is programmed from 578.2°F at 100% power to 547°F at zero power at a rate of

0.312°F per % power.

Crew MONITOR the following during the load reduction:

TAVG following TREF program.

All RPIs, group step counters for rod insertion limits and inoperable rods or rod misalignment, Loop T, and NIS for correct power distribution and quadrant power tilts.

Core AFD within ~5% control band around the power level dependent target value.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 6 of 35 Event

Description:

Decrease Power Time Position Applicant's Actions or Behavior NOTE Valve position limit and governor control meter are displayed on EHC Display panel 1, 2-XX-047-2000 (M-2).

BOP Valve position limit approximately 10% above the current governor control indication as turbine load is changed.

When power has been decreased sufficiently lead examiner may cue the next event at his discretion.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 7 of 35 Event

Description:

1A-A Component Cooling Water Pump Trip Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 2 Indications available: 0-AR-M27-B-A, A1, CCS REAC BLDG SUPPLY HEADER FLOW LOW 0-AR-M27-B-A, E4, ERCW/CCS PUMP MOTOR TRIP Crew Responds to alarm response procedure(s)

SRO Enter AOP-M.03, Loss of Component Cooling Water SRO (Tech Spec Evaluation will most likely not be performed until AOP actions are complete)

N/A N/A N/A Action already in effect at turnover due to 1A-A RHR pump out of service.

N/A Tech Spec Evaluation continued in next table Cell)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 8 of 35 Event

Description:

1A-A Component Cooling Water Pump Trip Time Position Applicant's Actions or Behavior (Tech Spec Evaluation - Continued)

N/A Action already in effect at turnover due to 1A-A RHR pump out of service.

72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Action Applies SRO Determine section 2.1 applies (CCS Pump Trip or Failure) from

table, CAUTION: The Containment Spray Pumps may experience bearing failure after 10 minutes of loss

of CCS cooling.

NOTE 1: When the associated TRAIN of CCS is out of service the CCPs, SI Pumps, and RHR Pumps are INOPERABLE for ECCS purposes due to not being able to fulfill its design function for sump recirculation. LCOs 3.5.2, 3.5.3, 3.6.2.1, 3.7.3 should be evaluated and appropriately entered by the SRO.

NOTE 2: When CCS is out of service to mechanical seal HXs ONLY, the affected CCPs, SI Pumps, and RHR Pumps have been evaluated to be OPERABLE and AVAILABLE. These pumps can run indefinitely without CCS cooling water to mechanical seal HXs Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 9 of 35 Event

Description:

1A-A Component Cooling Water Pump Trip Time Position Applicant's Actions or Behavior BOP ENSURE the following pump that is currently aligned to B Train RUNNING: C-S CCS Pump OR 1B-B CCS Pump OR 2B-B CCS Pump (Determines that the C-S Pump is aligned to the B train header)

SRO Go to Step 10 BOP IDENTIFY and LOCK OUT failed CCS Pump.

CAUTIONS: Loss of component cooling water flow to the RCP motor, requires RCP be stopped within two (2) minutes. Containment Spray Pumps may experience bearing failure during operation after 10 minutes of loss of CCS cooling.

NOTE 1: When the associated TRAIN of CCS is out of service the CCPs, SI Pumps, and RHR Pumps are INOPERABLE for ECCS purposes due to not being able to fulfill its design function for sump recirculation. LCOs 3.5.2, 3.5.3, 3.6.2.1, 3.7.3 should be evaluated and appropriately entered by the SRO.

NOTE 2: When CCS is out of service to mechanical seal HXs ONLY, the affected CCPs, SI Pumps, and RHR Pumps have been evaluated to be OPERABLE and AVAILABLE. These pumps can run indefinitely without CCS cooling water to mechanical seal HXs BOP ENSURE affected Unit's standby CCS Pump (aligned to Train A) RUNNING.

BOP CHECK Train A CCS Heat Exchanger inlet pressure NORMAL for present plant conditions.

[1-PI-70-24A, 1A1/1A2 CCS HX] [2-PI-70-17A, 2A1/2A2 CCS HX] Between 87 psig and 110 psig (Determines pressure approximately 105 psig)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 10 of 35 Event

Description:

1A-A Component Cooling Water Pump Trip Time Position Applicant's Actions or Behavior SRO Go to Procedure and step in effect (Tech Spec Evaluation will likely occur at this point)

When directed to go to appropriate plant procedure and Tech Spec Evaluation complete, Lead Examiner may cue the next event

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 11 of 35 Event

Description:

Pressurizer PORV Fails ~50% Open Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 3 Indications available: Alarm XA-55-5C, B-6, "XS-68-363 PRESSURIZER RELIEF VALVE OPEN" Alarm XA-55-5A, E2, "PRESSURIZER POWER RELIEF LINE TEMP HIGH" PORV 334 position indication extinguished Acoustic monitors on M4 indicate flow RO Take immediate/prudent action to close PORV Block Valve. May also attempt to close the open PORV as well.

RO Refer to actions in Annunciator Response Procedure for XA-55-5C, B-6 Evaluator Note: SRO may only refer to the AOP-R.05 since the RCS leak is isolated when PORV Block Valve is closed. AOP-R.05 is not included in this Event Guide.

SRO Direct performance of AOP-I.04 Section 2.1. "Uncontrolled RCS pressure drop due to open PORV in Modes 1-3"

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 12 of 35 Event

Description:

Pressurizer PORV Fails ~50% Open Time Position Applicant's Actions or Behavior RO (RNO if not previously performed)

RO RO RO SRO SRO Action may be applicable for a short time if RCS pressure drop to

less than 2205 psig before the PORV is isolated.

Action b applies and requires PORV restored or Block valve closed and Power removed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 13 of 35 Event

Description:

Pressurizer PORV Fails ~50% Open Time Position Applicant's Actions or Behavior CREW (Section 8.3 contains instructions for removing power from Block Valve))

RO CREW SRO When Tech Evaluation Complete, Lead Examiner may cue the next event at their discretion.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 4 Page 14 of 35 Event

Description:

Volume Control Tank Level Transmitter LT-62-130 Fails High Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 4 Indications available: Alarm XA-55-6C, A-3, "LS-62-129A/B VOLUME CONTROL TANK LEVEL HI-LOW" 1-LT-62-130 Indication failing high (ICS or M-6 Trend Recorder)

RO Refer to and perform applicable portions of Annunciator Response Procedure.

Evaluator Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this

event guide.

RO RO Lead Examiner may cue the next event when desired.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 & 6 Page 15 of 35 Event

Description:

Main Feedwater Pump 1A Trips, Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 5 Indications Available: Alarm XA-55-3B, A-2 "TRIPPED" Alarm XA-55-3B, A-2 "MFPT A OIL PRESSURE LOW Green Light on MFPT A Reset/Trip Switch HS-46-9A (M-3) Main Turbine Runback Initiated (Megawatts Decreasing)

SRO Enter and direct actions of AOP-S.01, Section 2.3 BOP RO BOP BOP (If TDAFW Pump not started previously as prudent action it should be started at this step)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 & 6 Page 16 of 35 Event

Description:

Main Feedwater Pump 1A Trips, Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior BOP CREW RO RO (RNO if required)

CREW CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 & 6 Page 17 of 35 Event

Description:

Main Feedwater Pump 1A Trips, Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior B OP B OP When Lead Examiner may cue the next event at their discretion.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 & 8 Page 18 of 35 Event

Description:

SteamLine Brk Outside Cntmnt & Auto Close Fail of All MSIVs, D/G 1A-A Trip Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 7 Indications Available: Automatic Reactor Trip and Safety Injection (Within a few seconds) 1 st Out Alarm XA-55-4D, F-1 "STEAM LINE LO PRESS SI REACTOR TRIP" All S/G Pressures Dropping uncontrolled All MSIVs Open (Red Light on Handswitch) with "STEAM LINE LO PRESS SI REACTOR TRIP" Alarm actuated.

Evaluator Note: Crew may close MSIVs based on E-0 foldout page at any time during performance of E-0.

Evaluator Note: D/G failure occurs ~10 seconds after Safety Injection occurs. Crew will likely address this failure when the Immediate Actions are complete.

SRO Enter and Direct Actions of E-0, "Reactor Trip Or Safety Injection" NOTE 1: Steps 1 through 4 are immediate action steps.

NOTE 2: This procedure has a foldout page.

RO BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 & 8 Page 19 of 35 Event

Description:

SteamLine Brk Outside Cntmnt & Auto Close Fail of All MSIVs, D/G 1A-A Trip Time Position Applicant's Actions or Behavior BOP RO BOP (ES-0.5 at end of Scenario)

BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 & 8 Page 20 of 35 Event

Description:

SteamLine Brk Outside Cntmnt & Auto Close Fail of All MSIVs, D/G 1A-A Trip Time Position Applicant's Actions or Behavior CRITICAL TASK 1 BOP/RO (MSIVs will be closed if not previously performed) (Critical Task - Manually close all 4 MSIVs prior to transition to ECA-2.1) RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 & 8 Page 21 of 35 Event

Description:

SteamLine Brk Outside Cntmnt & Auto Close Fail of All MSIVs, D/G 1A-A Trip Time Position Applicant's Actions or Behavior RO/BOP (If No Perform RNO)

RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 & 8 Page 22 of 35 Event

Description:

SteamLine Brk Outside Cntmnt & Auto Close Fail of All MSIVs, D/G 1A-A Trip Time Position Applicant's Actions or Behavior BOP (Transition to E-2 should not be required if MSIVs have been closed) BOP RO/BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 & 8 Page 23 of 35 Event

Description:

SteamLine Brk Outside Cntmnt & Auto Close Fail of All MSIVs, D/G 1A-A Trip Time Position Applicant's Actions or Behavior Evaluator Note:

The next Event should be initiated during performance of the next step.

CREW OR Lead Examiner should Cue the next event prior to Entry into ES-1.1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 & 10 Page 24 of 35 Event

Description:

Loss of Offsite Power, 1B-B D/G Supply Bkr to Shutdown BD Auto Close Fail Time Position Applicant's Actions or Behavior Console Operator: When directed, initiate Event 9 Indications available: Loss of Offsite Power: Numerous alarms, buzzers, and white disagreement lights on component switches and switchyard breakers. Numerous Electrical board Voltages indicate 0 volts including the Shutdown Boards and Unit boards. (Battery supplied AC & DC boards will be energized) D/G 1B-B SD Board Supply Breaker Auto Close Failure: O Volts on 1B-B Shutdown Board Voltage Indicator EI-57-66 on M-1 D/G 1B-B Breaker 1914 Mimic on M-1 and Handswitch on M-26 green light. 1B-B Shutdown board load breaker mimic on M-1 red lights indicating no board differential operation.

Evaluator Note: Event guide assumes crew will enter ECA-0.0 to close D/G 1B-B supply breaker to SD BD 1B-B. Crew may perform this as Prudent action in which case ECA-0.0 is not required.

Evaluator Note: Scenario should be terminated when D/G Supply breaker to 1B-B SD Board is closed and board is energized.

Evaluator Note: Crew may designate and operator to perform AOP-P.01 for Loss of Offsite Power Reader Doer method. A partial Event Guide for AOP-P.01 is included at the end of the scenario event guide if needed.

CREW Diagnose Loss of Offsite power and both SD BDs De-Energized.

SRO Enter and direct action of ECA-0.0

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 & 10 Page 25 of 35 Event

Description:

Loss of Offsite Power, 1B-B D/G Supply Bkr to Shutdown BD Auto Close Fail Time Position Applicant's Actions or Behavior RO BOP RO CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 & 10 Page 26 of 35 Event

Description:

Loss of Offsite Power, 1B-B D/G Supply Bkr to Shutdown BD Auto Close Fail Time Position Applicant's Actions or Behavior RO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 & 10 Page 27 of 35 Event

Description:

Loss of Offsite Power, 1B-B D/G Supply Bkr to Shutdown BD Auto Close Fail Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 & 10 Page 28 of 35 Event

Description:

Loss of Offsite Power, 1B-B D/G Supply Bkr to Shutdown BD Auto Close Fail Time Position Applicant's Actions or Behavior CRITICAL STEP 2 BOP (Steps a. & b. may not be performed since 1A-A D/G has differential fault and 1B-B D/G is already running)

(RNO Required)

(Critical Task: Energize SD BD 1B-B from D/G 1B-B prior to placing equipment in PTL in ECA-0.0)

TERMINATE SCENARIO WHEN D/G 1B-B SUPPLY BREAKER TO SD BD 1B-B IS CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # ES-0.5 Page 29 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior ES-0.5 Actions VERIFY D/G ERCW supply valves OPEN.

BOP VERIFY at least four ERCW pumps RUNNING.

BOP VERIFY CCS pumps RUNNING:

Pump 1A-A (2A-A) Pump 1B-B (2B-B) Pump C-S. (1A-A CCS Pump will not be running due to earlier failure in the scenario)

BOP VERIFY EGTS fans RUNNING.

BOP VERIFY generator breakers OPEN.

BOP VERIFY AFW pumps RUNNING:

MD AFW pumps TD AFW pump.

NOTE AFW level control valves should NOT be repositioned if manual action has been taken to control S/G levels, to establish flow due to failure, or to isolate a faulted S/G.

BOP CHECK AFW valve alignment:

a. VERIFY MD AFW LCVs in AUTO.

b. VERIFY TD AFW LCVs OPEN.

c. VERIFY MD AFW pump recirculation valves FCV-3-400 and FCV-3-401 CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # ES-0.5 Page 30 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP VERIFY MFW Isolation:

MFW pumps TRIPPED MFW regulating valves CLOSED MFW regulating bypass valve controller outputs ZERO MFW isolation valves CLOSED BOP MONITOR ECCS operation:

VERIFY ECCS pumps RUNNING: CCPs RHR pumps SI pumps VERIFY CCP flow through CCPIT.

CHECK RCS pressure less than 1500 psig.

VERIFY SI pump flow. CHECK RCS pressure less than 300 psig.

VERIFY RHR pump flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # ES-0.5 Page 31 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP VERIFY ESF systems ALIGNED:

Phase A ACTUATED:

o PHASE A TRAIN A alarm LIT [M-6C, B5].

o PHASE A TRAIN B alarm LIT [M-6C, B6].

Containment Ventilation Isolation ACTUATED:

o CONTAINMENT VENTILATION ISOLATION TRAIN A alarm LIT [M-6C, C5].

o CONTAINMENT VENTILATION ISOLATION TRAIN B alarm LIT [M-6C, C6].

Status monitor panels:

o 6C DARK o 6D DARK o 6E LIT OUTSIDE outlined area o 6H DARK o 6J LIT. Train A status panel 6K:

o CNTMT VENT GREEN o PHASE A GREEN Train B status panel 6L:

o CNTMT VENT GREEN o PHASE A GREEN

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # ES-0.5 Page 32 of 35 Event

Description:

Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP VERIFY pocket sump pumps STOPPED: [M-15, upper left corner] HS-77-410, Rx Bldg Aux Floor and Equipment Drain Sump pump A HS-77-411, Rx Bldg Aux Floor and Equipment Drain Sump pump B.

BOP DISPATCH personnel to perform EA-0-1, Equipment Checks Following ESF Actuation.

BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # AOP-P.01 Page 33 of 35 Event

Description:

Loss Of Offsite Power Time Position Applicant's Actions or Behavior AOP-P.01 Actions BOP (RNO) (May attempt to close 1B-B D/G BKR to SD BD 1B-1 at this step) BOP BOP BOP (RNO)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # AOP-P.01 Page 34 of 35 Event

Description:

Loss Of Offsite Power Time Position Applicant's Actions or Behavior BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # AOP-P.01 Page 35 of 35 Event

Description:

Loss Of Offsite Power Time Position Applicant's Actions or Behavior RO Appendix D Scenario Outline Form ES-D-1 Facility:

Sequoyah Scenario No.:

4 Op Test No.:

NRC Examiners:

Operators:

Initial Conditions: 100% Power BOL Equilibrium 1A-A RHR Pump Out of Service Turnover: Unit 1 main Generator has developed a small H2 leak which cannot be repaired on line. Management has decided to shutdown the Unit to make repairs. Shutdown the Unit using 0-GO-5 over the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Target CTs: Manually Close all 4 Main Steam Isolation Valves prior to transition to ECA-2.1.

Energize Shutdown board 1B-B from D/G 1B-B from prior to placing equipment in PTL in ECA-0.0. Event # Malf. No. Event Type*

Event Description 1 N/A R-ATC N-SRO/BOP Decrease power.

2 CC10A TS-SRO C-SRO 1A-A CCS Pump trips. AOP-M.03 implemented. SRO Tech spec Evaluation.

3 RC05 TS-SRO C-SRO/ATC Pressurizer PORV fails ~50% open requiring Block valve closure. AOP-I.04 implemented. SRO Tech Spec Evaluation.

4 CV09 C-SRO/ATC Volume control Tank level transmitter fails High. Letdown is diverted to HUT. Manually re-align to VCT.

5 FW05A C-SRO Main Feedwater Pump 1A trips on low oil pressure. Auto plant runback is initiated. AOP-S.01 is implemented.

6 FW10 C-SRO/BOP Turbine Driven Auxiliary Feedwater pump fails to Auto Start during runback. Requires manual start.

7 MS02A MS02B MS02C MS02D RP16K616A

RP16K616B RP16K623A RP16K623B M-All Steam Line break outside containment downstream of MSIVs requiring Reactor Trip and Safety Injection. Manual isolation required due to auto failure of all 4 MSIVs.

8 EG02A N/A D/G 1A-A Generator Differential Trip 10 Sec after SI.

9 ED01 C-SRO/BOP Loss off Offsite Power.

10 EG12B C-SRO/BOP 1B-B D/G Breaker to Shutdown board 1B-B fails to auto close (Can be manually closed) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9 Appendix D Scenario Outline Form ES-D-1 Scenario 4 Summary Crew will assume shift at 100% power BOL with the 1A-A RHR pump out of se rvice for repairs. Crew directions will be to shutdown the Unit using 0-GO-5 over the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Unit 1 main Generator has developed a small H2 leak which cannot be repaired on line. Management has decided to shutdown the Unit.

When adequate power decrease is complete, Component Cooling water pump 1A-A will trip and the standby pump will auto start. SRO will implement AOP-M.03 and evaluate Tech Specs.

When AOP-M.03 and Tech Spec Evaluation complete, Pressurizer PORV FCV-68-334 fails ~50% open. PORV block valve should be closed as an immediate action and AOP-I.04 implemented. SRO will evaluate Tech Specs and should identify that power is to be removed from the block valve in accordance with Tech Specs. When AOP I.04 and Tech Spec Evaluation complete, Volume Control Tank level instrument LT-62-130A fails High which causes letdown to divert to the Holdup tank. ATC should refer to the Annunciator response procedure and manually realign letdown to the VCT. This instrument does not have an indicator in the main control room, however, indication is available on the plant computer system (ICS) and locally.

Following realignment of letdown to VCT, Main Feedwater Pump turbine 1A will trip due to low oil pressure from a leaking oil pressure senseline. MFW Pump trip will initiate an auto plant runback to ~72% and require performance of AOP-S.01. During the runback, the Turbine Driven AFW Pump will fail to Auto start and should be started as prudent action or during performance of the AOP.

When Crew begins reset of turbine controls following the runback, a steamline break occurs downstream of MSIVs requiring Reactor trip and Safety Injection. The steam Line break will be isolated when the MSIVs are closed, however, due to a failure of the auto MSIV steamline isolation signals to all MSIVs the crew will manually close the MSIVs to complete the first critical task. Also, ten seconds after the 1A-A D/G starts from the SI signal it will trip due to a generator differential. The crew will continue in E-0 to check SI termination criteria.

When the crew begins checking the SI termination criteria in E-0, a loss of offsite power will occur. 1B-B D/G breaker to the shutdown board will not automatically close and will require manual closure to energize the 1B-B shutdown board. Crew may close the D/G Breaker to the shutdown board as prudent action or transition to ECA-0.0 which contains procedural direction for closing the breaker. Energizing the 1B-B Shutdown Board from the 1B-B D/G will complete the second critical task.

The scenario may be terminated when the 1B-B Shutdown board is energized from a D/G 1B-B and the crew transitions to SI Termination procedure ES-1.1.

Appendix D NUREG 1021 Revision 9 Time: Now Date:

Today Unit 1 MCR Checklist (751-2428 ID 7636)

Part 1 - Completed by Off-going Shift / Reviewed by On-coming Shift Mode 1, 100% Power 1204 MWe PSA Risk: Green Grid Risk: Green

RCS Leakage ID .02 gpm, UNID .01 gpm Cumulative Purge Time _50.5 Hours_

NRC phone Authentication Code Until 0800 H3H8 After 0800 42DF Common Tech Spec Actions U-1 Tech Spec Actions LCO 3.5.2 & 3.6.2.1 - 1A-A RHR pump has been tagged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance to perform motor winding test. Expected Return to service is ~2 hours.

Protected Equipment 1B-B RHR Pump 1B-B Safety Injection Pump 1B-B Charging Pump

Shift Priorities Unit 1 main Generator has developed a small H2 leak which cannot be repaired on line. Management has decided to shutdown the Unit to make repairs. Shutdown the Unit using 0-GO-5 over the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Initiate boration and rod insertion per Reactor Engineer SpreadSheet. Spreadsheet has been verified by the SRO/STA. 0-SO-62-7 Appendix E and D have been performed.

Part 2 - Performed by on-coming shift Verify your current qualifications Review Operating Log since last held shift or 3 days, whichever is less Standing Orders / Shift Orders TACF Immediate required reading LCO Actions Part 3 - Performed by both off-going and on-coming shift Walk down of MCR Control Boards

Time: Now Date:

Today MAIN CONTROL ROOM (7690) Train_A_Week OUTSIDE (7666) [593-5214] AUXILIARY BUILDING (7775) 1A-A RHR pump has been tagged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance to perform motor winding test.

Expected Return to service is ~2 hours.

TURBINE BUILDING (7771) (593-8455)

Time: Now Date:

Today Equipment Off-Normal (Pink Tags) UNID And Noun Name Panel Problem Description WO / PER Number Date Scheduled MCR WO List ID And Noun Name Panel Problem Description WO/PER Number Date Scheduled

UNIT ONE REACTIVITY BRIEF Date: Today Time: Now

General Information RCS Boron:

1093 ppm Today BA Controller Setpoint:

27%

• RCS B-10 Depletion:

2 ppm Operable BAT:

A BAT A Boron:

6850 ppm BAT C Boron:

6850 ppm RWST Boron:

2601 ppm Nominal Gallons per rod step from 219:

7 gallons of acid, 36 gallons of water

• Verify boric acid flow contro ller is set at Adjusted BA Controller Setting iaw 0-SO-62-7 section 5.1 Estimated values for a 1° Change in Tave **

Gallons of acid:

26 Gallons of water:

138 Rod Steps: 4 Estimated rods/boron for emergency step power reduction ** (Assuming Xenon equilibrium and no reactivity effects due to Xenon. 2/3 total reactivity from rods, 1/3 from boron)

Power reduction amount Estimated Final Rod Position Estimated boron addition 10% 198 Steps on bank D 101 gallons 30% 174 Steps on bank D 295 gallons 50% 152 Steps on bank D 485 gallons

• • These values are approximations and not int ended nor expected to be exact. The values may be superseded by Rx Engineering or SO-62-7 calculated values. These values are calculated assuming 100%

steady state power operation onl

y. Engineering data last updated one week ago. Data Valid until one week from now. Previous Shift Reactivity Manipulations Number of dilutions: 0***

Number of borations: 0 Rod steps in: 0 Gallons per dilution: 0 Gallons per boration: 0 Rod steps out: 0 Total amount diluted: 0 Total amount borated: 0 Net change: 0 IN/Out Current Shift Estimated Reactivity Manipulations Number of dilutions: 0 Number of borations: 0 Rod steps in: 0 Gallons per dilution: 0 Gallons per boration: 0 Rod steps out: 0 Total expected dilution: 0 Total expected boration: 0 Net change: 0 In/Out Remarks: Rx Power - 100% MWD/MTU - 1000 Xenon & Samarium at Equilibrium

• • • The boron letdown curve is flat for the next 25 EFPD.

Next Unit 1 Flux Map is scheduled -

three weeks from now Unit 1 M-P is 0 PPM Unit Supervisor: _______________________________

Name/Date Operations Chemistry Information Boron Results Sample Point Units Boron Date / Time Goal Limit U1 RCS ppm 1093 Today / Now Variable Variable U2 RCS ppm 816 Today / Now Variable Variable U1 RWST ppm 2601 Today / Now 2550 - 2650 2500 - 2700 U2 RWST ppm 2569 Today / Now 2550 - 2650 2500 - 2700 BAT A ppm 6850 Today / Now Variable Variable BAT B ppm 6850 Today / Now Variable Variable BAT C ppm 6850 Today / Now Variable Variable U1 CLA #1 ppm 2556 Today / Now 2470-2630 2400-2700 U1 CLA #2 ppm 2575 Today / Now 2470-2630 2400-2700 U1 CLA #3 ppm 2591 Today / Now 2470-2630 2400-2700 U1 CLA #4 ppm 2589 Today / Now 2470-2630 2400-2700 U2 CLA #1 ppm 2531 Today / Now 2470-2630 2400-2700 U2 CLA #2 ppm 2650 Today / Now 2470-2630 2400-2700 U2 CLA #3 ppm 2522 Today / Now 2470-2630 2400-2700 U2 CLA #4 ppm 2526 Today / Now 2470-2630 2400-2700 Spent Fuel Pool ppm 2547 Today / Now

> 2050 > 2000 Lithium Results Goal Midpoint U1 RCS Lithium ppm 1.1 Today / Now

>1 >1 U2 RCS Lithium ppm 2.43 Today / Now 2.18-2.48 2.33 Primary to Secondary Leakrate In formation (Total CPM RM-90-99/119)

Indicator Units U1 Date / Time U2 Date/Time SI 50 S/G Leakage?

Yes/No No Today / Now No Today / Now SI 137.5 CVE Leakrate gpd < 0.1 Today / Now

< 0.1 Today / Now 5 gpd leak equivalent cpm 380 Today / Now 68 Today / Now 30 gpd leak equivalent cpm 1980 Today / Now 83 Today / Now 50 gpd leak equivalent cpm 3250 Today / Now 206 Today / Now 75 gpd leak equivalent cpm 4850 Today / Now 455 Today / Now CVE Air Inleakage cfm 10 Today / Now 12.5 Today / Now Bkgd on 99/119 cpm 50 Today / Now 40 Today / Now Correction Factor 99/119 cpm/gpd 10.69 Today / Now 14.13 Today / Now Steady state conditions are necessary for an accurate det ermination of leak rate using the CVE Rad Monitor

Unit 1 DELT A R EACTO R POWER A SSUME D INSERTED E XPECTE D D ELTA RH OBORONDELT A E COMME N RECOMM EIODINEDATE/TIMETIMEPOWERDEFECTROD HTWORTHXENONBORONCONCPPMDILUTIONBORATIONCONC (hrs)(%)(pcm)(steps)(pcm)(pcm)(pcm)(ppm)(ppm)(g al)(g al)(% eq)0100.0 1702.4 216.0-23.0-2728.0---1093.0---------99.9 Toda y190.0 1530.3 200.0-102.5-2739.8-80.71105.912.9014299.4Toda y280.0 1358.4 185.0-199.2-2784.3-30.71110.84.905498.0Toda y370.0 1193.8 175.0-271.2-2851.0-26.01114.94.104695.7Toda y460.0 1032.9 165.0-344.1-2933.1-5.91115.80.901092.7Toda y550.0 874.0 160.0-385.3-3026.3-24.51119.73.904389.0Toda y640.0 712.4 155.0-425.8-3128.3-19.21122.83.103484.6Toda y730.0 548.2 150.0-465.7-3237.5-15.01125.22.402679.8Toda y820.0 376.6 150.0-472.9-3353.8-48.21132.97.708574.4Toda y 1000MWD/MTUHold Tavg = Tref +/- 1.5FTotal0442 6850 BAT ppm Small hourly boration/dilution volumes ma y be accumulated for lar g er sin g le additions Reason for Maneuve r Unit Shutdown for Main Gen H2 Leak Repai r Date Toda y RxEn g Name Comments Unit 1 0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0 180.0 200.0 220.0 240.0024681012141618202224262830323436384042444648505254565860626466 Time% Power or Steps

-2800.0-2600.0-2400.0-2200.0-2000.0-1800.0

-1600.0-1400.0-1200.0-1000.0-800.0Xenon (pcm)

RodWorths U1C16 Table 6-34 HFP Integral Rod Worth (Table Inverted)Bank DCycle Burnup (MWD/MTU)

Steps04000100001600021438 Withdrawn52-1164-1123-1135-1359-151360-1078-1039-1050-1265-1416 68-999-962-973-1174-1318 76-927-892-902-1085-1219 84-856-824-836-1001-1122 92-782-754-769-923-1033100-700-675-698-851-954 108-656-632-659-816-917 116-609-587-618-780-879 124-560-540-575-740-836 132-510-491-529-695-788 140-459-442-481-647-735 148-408-392-431-594-678 156-358-343-381-539-617 164-309-296-330-482-555 172-261-249-279-421-488 180-214-203-228-356-417 188-167-157-177-286-341 196-121-113-127-213-260 204-78-72-80-140-177 212-39-35-39-72-94 220-8-8-7-17-23 22800000 23100000 23200000 U1C16 Table 6-33 HZP Integral Rod Worth, Peak Xenon (Table Inverted)Bank DCycle Burnup (MWD/MTU)

Steps04000100001600021438 Withdrawn52-1298-1311-1404-1601-171560-1216-1230-1310-1496-1611 68-1140-1152-1215-1377-1485 76-1071-1082-1122-1249-1341 84-1006-1014-1039-1129-1202 92-943-952-974-1037-1094100-876-892-933-992-1042 108-840-861-919-985-1035 116-803-828-903-980-1032 124-762-791-881-972-1027 132-719-750-849-955-1014 140-673-704-807-928-992 148-625-653-755-891-959 RodWorths156-574-599-695-842-915164-520-540-626-782-859 172-460-476-548-708-787 180-393-404-460-615-696 188-317-322-363-503-583 196-234-236-262-377-451 204-152-151-165-247-309 212-76-75-79-125-164 220-17-17-17-29-39 22800000 23100000 23200000 U1C16 Table 6-32 HZP Integral Rod Worth, No Xenon (Table Inverted)Bank DCycle Burnup (MWD/MTU)

Steps04000100001600021438 Withdrawn52-1214-1172-1210-1574-169460-1136-1097-1131-1464-1585 68-1063-1028-1058-1344-1457 76-998-966-993-1220-1317 84-933-904-934-1106-1184 92-863-838-878-1020-1082100-781-761-821-978-1033 108-735-718-791-970-1025 116-687-672-758-964-1022 124-636-624-719-955-1015 132-585-574-675-936-999 140-533-523-625-907-974 148-481-471-571-867-937 156-430-419-512-816-889 164-379-368-450-752-828 172-326-315-384-674-752 180-272-260-315-579-658 188-214-203-243-467-543 196-155-145-170-343-413 204-98-91-104-219-277 212-48-44-49-108-143 220-11-10-11-24-34 22800000 23100000 23200000 RodWorths RodWorths 2-D Interpolation of Table 6-X(L)XX(H)Y(L)YY(H)(Steps)(Burnup)212216220010004000196200204010004000 180185188010004000 172175180010004000 164165172010004000 156160164010004000 148155156010004000 148150156010004000 148150156010004000#REF!#REF!#REF!010004000

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1. N/A0#N/A010004000 RodWorths-3 4 InsertedA(LL)A(L,H)A(H,L)A(H,H)Rod Worth (pcm)-39.0-35.0-8.0-8.0-23.0-121.0-113.0-78.0-72.0-97.8

-214.0-203.0-167.0-157.0-182.0

-261.0-249.0-214.0-203.0-240.5

-309.0-296.0-261.0-249.0-299.8

-358.0-343.0-309.0-296.0-330.0

-408.0-392.0-358.0-343.0-360.5

-408.0-392.0-358.0-343.0-391.6

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1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

RodWorths#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A RodWorths#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A RodWorths 2-D Interpolation of Table 6-X(L)XX(H)Y(L)YY(H)(Steps)(Burnup)212216220010004000196200204010004000 180185188010004000 172175180010004000 164165172010004000 156160164010004000 148155156010004000 148150156010004000 148150156010004000#REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000 RodWorths#REF!#REF!#REF!010004000#REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000

1. REF!#REF!#REF!010004000#N/A0#N/A010004000

1. N/A g = Tref #N/A010004000#N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/Ar Main G e#N/A010004000#N/AToday#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000 RodWorths#N/A0#N/A010004000#N/A0#N/A010004000

1. N/A0#N/A010004000

1. N/A0#N/A010004000 RodWorths-3 3 InsertedA(LL)A(L,H)A(H,L)A(H,H)Rod Worth (pcm)-76.0-75.0-17.0-17.0-46.4-234.0-236.0-152.0-151.0-193.1

-393.0-404.0-317.0-322.0-347.3

-460.0-476.0-393.0-404.0-438.4

-520.0-540.0-460.0-476.0-517.4

-574.0-599.0-520.0-540.0-552.6

-625.0-653.0-574.0-599.0-586.7

-625.0-653.0-574.0-599.0-619.1

-625.0-653.0-574.0-599.0-619.1#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

RodWorths#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A RodWorths#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A RodWorths 2-D Interpolation of Table 6-32X(L)XX(H)Y(L)YY(H)A(LL)(Steps)(Burnup)212216220010004000-48.0196200204010004000-155.0 180185188010004000-272.0 172175180010004000-326.0 164165172010004000-379.0 156160164010004000-430.0 148155156010004000-481.0 148150156010004000-481.0 148150156010004000-481.0#REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

RodWorths#REF!#REF!#REF!010004000#REF!#REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!

1. REF!#REF!#REF!010004000#REF!#N/A0#N/A010004000#N/A

1. N/A g = Tref #N/A010004000#N/A#N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/Ar Main G e#N/A010004000#N/A#N/AToday#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A RodWorths#N/A0#N/A010004000#N/A#N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A

1. N/A0#N/A010004000#N/A RodWorths 1-D Xenon I InsertedA(L,H)A(H,L)A(H,H)Rod WorthHZ P (pcm)0-44.0-11.0-10.0-28.9-46.4-145.0-98.0-91.0-124.4-193.1

-260.0-214.0-203.0-232.9-347.3

-315.0-272.0-260.0-302.9-438.4

-368.0-326.0-315.0-369.6-517.4

-419.0-379.0-368.0-401.8-552.6

-471.0-430.0-419.0-433.7-586.7

-471.0-430.0-419.0-465.7-619.1

-471.0-430.0-419.0-465.7-619.1#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

RodWorths#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

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1. N/A#N/A#N/A#N/A#N/A RodWorths#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A

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1. N/A#N/A#N/A#N/A#N/A RodWorths I nterpolatio n 1-D Rod Worth Table Interpolatio n P Power DefectPower (%)

InterpolatedHZPHFP Interpolate d-3947By Xenon0100By Power-28.9-34.3-34.3-23.0-23.0-124.4-145.6-145.6-97.8-102.5

-232.9-267.9-267.9-182.0-199.2

-302.9-342.8-342.8-240.5-271.2

-369.6-410.7-410.7-299.8-344.1

-401.8-440.5-440.5-330.0-385.3

-433.7-469.4-469.4-360.5-425.8

-465.7-497.5-497.5-391.6-465.7

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1. N/A#N/A#N/A#N/A#N/A RodWorths on d PowerDefects U1C16 Table 6-23 Power Defect at 150 MWD/MTU Boron Concentration (ppm)

Power100011001200130014001500

(%)0 000000 5104102100989694 10204200196192188184 15301294288282276270 20394385377369361354 25484474464454444434 30573560548536524512 35659644630616602589 40744727711695679663 45828809791772755737 50912891870849829810 55995971948926904882 601078105210271002978954 65116111331105107810511025 70124512141184115511261097 75133012961264123112001169 80141513791344130912751242 85150214631424138713511315 90158915471506146614271388 95167816331589154615041463 100176817201673162715821538 U1C16 Table 6-24 Power Defect at 4000 MWD/MTU Boron Concentration (ppm)

Power90010001100120013001400

(%)0 000000 5989694929088 10192189185181177173 15284278272266260254 20372364356348341333 25458448438429419409 30542530519507495484 35625611597584570557 40707691675659644628 45789770752734717699 50870849829809789770 55951928905883861840 6010321007982958934910 6511151087105910321006980 70119711671137110810791051 PowerDefects 75128112481216118411521122 80136613301295126112271193 85145314141376133913021266 90154114991458141713781339 95163015851541149714551414 100172116721625157915331489 U1C16 Table 6-25 Power Defect at 10000 MWD/MTU Boron Concentration (ppm)

Power400500600700800900

(%)0 000000 5116114112111109107 10227224220217213210 15335330325319314309 20441434426419412406 25544535526517508499 30646635624613602591 35748734721707694682 40849832817801786771 45950931913895878861 50105110301009989969950 55115411301107108410611039 60125812311205117911541130 65136413341305127612491221 70147214391407137513441314 75158215461510147614421409 80169516551616157815411505 85181117671725168316431603 90193018821836179117471704 95205220001950190118531807 100217721212067201419621912 U1C16 Table 6-26 Power Defect at 16000 MWD/MTU Boron Concentration (ppm)

Power0100200300400500

(%)0 000000 5158156154152150147 10312307303299295290 15461454448442435429 20607598589581572564 25749738727717706696 30889876863850838825 PowerDefects 3510281012996981966952 40116511461128111110931077 45130112801259123912191200 50143614121389136613441323 55157215451519149314691445 60170916791649162115931566 65184718131781174917181689 70198719491913187818441812 75212920872048200919721936 80227422282184214221022062 85242223722324227822332190 90257425202467241723682321 95273126712614255925062455 100289328282766270626482593 U1C16 Table 6-27 Power Defect at 21438 MWD/MTU Boron Concentration (ppm)

Power0100200300400500

(%)0 000000 5165163161158156154 10327322318313309304 15486479472465458451 20641632623614605596 25794783771760749738 30945931917904891878 35109410781062104610301015 40124212231204118611691151 45138913671346132613061286 50153615111487146414421420 55168216551628160215771553 60182917991769174017131686 65197719431910187918481819 70212720892053201819851953 75227822362197215921222087 80243223862343230122612223 85258825382491244624022361 90274826942642259325462500 95291228532797274326922643 100308130172956289728422789 PowerDefects16001700180019002000 000009290888684180177173169165 265259253248242 346338331323316 425415406396387 501489478467456 575562549536523 648633618603588 720703686669652 790771752734715 860839819798778 9309078848628391000974950925901 106910421015988962 11391109108010511023 12091177114611151084 12801245121111781145 13511314127712421207 14221383134413061268 14951452141113701330150016001700180019002000 000000868583817977169166162158155151 249243238232227221 326318311304296289 400391382373364355 473461450440429418 544531518505493480 613598584569555541 682665649633616601 751732713695677660 819798777757737718 886864841819797776 9559299058818578341023996969943917892 PowerDefects1092106210331005977950116111291098106710371008 123111961163113010971066 130212651228119311581124 137313331294125612191183 1445140313611320128112421000110012001300140015001600 00000001061041031011009897 207204201198195192188 304300295290285281276 399392386379373367360 491482474466458450442 581570560550541531521 669657645633622610599 757743729715701688675 844827811796780765750 9319128948768598428251018997977957937918899 11061083106010381016994973 1195116911441119109510711048 1285125612291201117511491123 1377134513151285125612271200 1470143614021370133813071277 1565152814911456142213881355 1662162215821544150614701434 1762171816751633159315541515 1863181617691725168116391597600700800900100011001400 0000000145143141139136134128 286282278273269265253 423417410404398392374 556548540532524516492 686676666656646636607 813801789777765754719 PowerDefects9379239098968828698291060104410281012997982937 1181116311451127111010931043 1302128112611241122212031147 1421139813761354133213111250 1540151514901466144314201353 1660163216051578155215271455 1780174917201691166216351556 1901186818351804177317431658 2024198819521918188418521760 2149210920702033199719621862 2276223321912150211120731966 2406235923132269222721862070 25392488243923912345230121776007008009001100 00000151149147144140 299295290286277 445438431425412 587578570561544 727716706695674 8658528398278021000986971957928 11341118110110851052 12671248123012111175 13991378135713371297 15291506148414621418 16601635161015861539 17911763173617101659 19211891186218341778 20532020198919581898 21862151211620832019 23212282224522092140 24572415237523372262 25962551250824662386 27382689264225972512 PowerDefects 2-D Interpolation o f X(L)XX(H)Y(L)YY(H)(% Power)(ppm)95100100100010931100909095100010931100 808085110011061200 707075110011111200 606065110011151200 505055110011161200 404045110011201200 303035110011231200 202025110011251200#REF!#REF!#REF!110011331200

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0#REF!#REF!#REF!#REF!#REF!#REF!

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185#REF!#REF!#REF!#REF!#REF!#REF!

271005#REF!#REF!#REF!

354#N/AMWD/MTU#N/A#N/A0#N/A 434#N/ABAT ppm#N/A#N/A0#N/A 512005#N/A0#N/A 587005#N/A0#N/A 662005#N/A0#N/A 735005#N/A0#N/A 808005#N/A0#N/A 880005#N/A0#N/A 952#N/AMWD/MTU#N/A#N/A0#N/A 1025#N/A#N/A#N/A#N/A0#N/A 1098005#N/A0#N/A 1172005#N/A0#N/A 1247005#N/A0#N/A 1323005#N/A0#N/A 1399005#N/A0#N/A 1477005#N/A0#N/A 1557005#N/A0#N/A005#N/A0#N/A 005#N/A0#N/A 005#N/A0#N/A 005#N/A0#N/A 005#N/A0#N/A1600005#N/A0#N/A005#N/A0#N/A 0005#N/A0#N/A 124005#N/A0#N/A 245005#N/A0#N/A 362005#N/A0#N/A 476005#N/A0#N/A 587005#N/A0#N/A 696005#N/A0#N/A PowerDefects 802005#N/A0#N/A 907005#N/A0#N/A 1010005#N/A0#N/A 1111005#N/A0#N/A 1211 1310 1408 1506 1604 1702 1801 1899 1999 2100 PowerDefects f Table 6-2 3 PowerA(L,L)A(L,H)A(H,L)A(H,H)Defect (pcm)1678.01633.01768.01720.01723.41589.01547.01678.01633.01549.9 1379.01344.01463.01424.01376.9 1214.01184.01296.01264.01210.8 1052.01027.01133.01105.01048.3891.0870.0971.0948.0887.7 727.0711.0809.0791.0723.8 560.0548.0644.0630.0557.3 385.0377.0474.0464.0383.0

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1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A PowerDefects#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A PowerDefects 2-D Interpolation of Table 6-X(L)XX(H)Y(L)YY(H)A(L,L)(% Power)(ppm)951001001000109311001585.09090951000109311001499.0 8080851100110612001295.0 7070751100111112001137.0 606065110011151200982.0 505055110011161200829.0 404045110011201200675.0 303035110011231200519.0 202025110011251200356.0#REF!#REF!#REF!110011331200#REF!

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1. N/ABAT ppm#N/A#N/A0#N/A#N/A005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A#N/AMWD/MTU#N/A#N/A0#N/A#N/A

1. N/ABAT ppm#N/A#N/A0#N/A#N/A005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A PowerDefects005#N/A0#N/A#N/A005#N/A0#N/A#N/A 005#N/A0#N/A#N/A 005#N/A0#N/A#N/A PowerDefects

-2 4 PowerA(L,H)A(H,L)A(H,H)DefectX(L)(pcm)1541.01672.01625.01628.3951458.01585.01541.01460.990 1261.01376.01339.01293.080 1108.01216.01184.01133.970958.01059.01032.0978.460 809.0905.0883.0825.850 659.0752.0734.0671.840 507.0597.0584.0516.330 348.0438.0429.0354.020

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1. N/A#N/A#N/A#N/A0 PowerDefects#N/A#N/A#N/A#N/A0#N/A#N/A#N/A#N/A0

1. N/A#N/A#N/A#N/A0

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1. REF!#REF!#REF!#REF!#REF!#REF!#REF!05#REF!#REF!#REF!#REF!#REF!MWD/MTU#N/A#N/A0#N/A#N/A#N/A BAT ppm#N/A#N/A0#N/A#N/A#N/A05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/AMWD/MTU#N/A#N/A0#N/A#N/A#N/A BAT ppm#N/A#N/A0#N/A#N/A#N/A05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A PowerDefects05#N/A0#N/A#N/A#N/A05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A 05#N/A0#N/A#N/A#N/A PowerDefects PowerA(H,L)A(H,H)DefectX(L)XX(H)(pcm)(% Power)1863.01816.01819.3951001001762.01718.01624.8909095 1528.01491.01434.0808085 1345.01315.01253.1707075 1169.01144.01079.6606065997.0977.0909.1505055 827.0811.0740.2404045 657.0645.0567.7303035 482.0474.0390.5202025

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1. N/A#N/A#N/A005 PowerDefects#N/A#N/A#N/A005#N/A#N/A#N/A005

1. N/A#N/A#N/A005

1. N/A#N/A#N/A005 PowerDefects 2-D Interpolation of Table 6-26Y(L)YY(H)A(L,L)A(L,H)A(H,L)A(H,H)(ppm)1000109311002227.02186.02345.02301.01000109311002111.02073.02227.02186.0 1100110614001852.01760.01962.01862.0 1100111114001635.01556.01743.01658.0 1100111514001420.01353.01527.01455.0 1100111614001203.01147.01311.01250.0 110011201400982.0937.01093.01043.0 110011231400754.0719.0869.0829.0 110011251400516.0492.0636.0607.0 110011331400#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

PowerDefects#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!#REF!00100#N/A#N/A#N/A#N/A 00100#N/A#N/A#N/A#N/A 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 00100#N/A#N/A#N/A#N/A 00100#N/A#N/A#N/A#N/A 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 PowerDefects001000.00.0158.0156.0001000.00.0158.0156.0 001000.00.0158.0156.0 001000.00.0158.0156.0 PowerDefects 2-D Interpo l PowerDefectX(L)XX(H)Y(L)Y(pcm)(% Power)(ppm)2304.19510010090010932075.79090959001093 1850.280808511001106 1632.270707511001111 1416.760606511001115 1200.050505511001116979.040404511001120 751.330303511001123 514.020202511001125

1. REF!#REF!#REF!#REF!11001133

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

PowerDefects#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!005#REF!#REF!#N/A#N/AMWD/MTU#N/A00

1. N/A#N/ABAT ppm#N/A000.000500 0.000500 0.000500 0.000500 0.000500 0.000500#N/A#N/AMWD/MTU#N/A00

1. N/A#N/ABAT ppm#N/A000.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 0.000500 PowerDefects0.0005000.000500 0.000500 0.000500 PowerDefects o lation of Table 6-2 7 PowerY(H)A(L,L)A(L,H)A(H,L)A(H,H)Defect (pcm)11002466.02386.02597.02512.02515.011002337.02262.02466.02386.02264.6#REF!2019.0#REF!2140.0#REF!#REF!

1. REF!1778.0#REF!1898.0#REF!#REF!

1. REF!1539.0#REF!1659.0#REF!#REF!

1. REF!1297.0#REF!1418.0#REF!#REF!

1. REF!1052.0#REF!1175.0#REF!#REF!

1. REF!802.0#REF!928.0#REF!#REF!

1. REF!544.0#REF!674.0#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

PowerDefects#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#REF!100#N/A#N/A#N/A#N/A#N/A 100#N/A#N/A#N/A#N/A#N/A 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 100#N/A#N/A#N/A#N/A#N/A 100#N/A#N/A#N/A#N/A#N/A 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 PowerDefects1000.00.0165.0163.00.01000.00.0165.0163.00.0 1000.00.0165.0163.00.0 1000.00.0165.0163.00.0 PowerDefects 1-D Power Defect Table Interpola Burnup (MWD/MTU)15040001000016000209581723.41628.31819.32304.12515.0 1549.91460.91624.82075.72264.6 1376.91293.01434.01850.2#REF!

1210.81133.91253.11632.2#REF!

1048.3978.41079.61416.7#REF!887.7825.8909.11200.0#REF!

723.8671.8740.2979.0#REF!

557.3516.3567.7751.3#REF!

383.0354.0390.5514.0#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

PowerDefects#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!

1. REF!#REF!#REF!#REF!#REF!#N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A#N/A#N/A

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0 PowerDefects#N/A#N/A#N/A0.00.0#N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0

1. N/A#N/A#N/A0.00.0 PowerDefects a tio n Interpolated By Burnup 1702.4 1530.3 1358.4 1193.8 1032.9 874.0 712.4 548.2 376.6

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1. REF!

1. REF!

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1. REF!

1. REF!

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1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

PowerDefects

1. REF!#REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!

1. REF!#N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A

1. N/A PowerDefects

1. N/A#N/A

1. N/A

1. N/A BoronWorth U1C16 Table 6-7 Differential Boron Worth BoronCycle Burnup (MWD/MTU)

Conc1505001000200040006000 (ppm)0-6.445-6.436-6.427-6.419-6.442-6.508 200-6.419-6.41-6.4-6.392-6.415-6.481 400-6.392-6.383-6.373-6.365-6.387-6.453 600-6.365-6.356-6.346-6.338-6.36-6.425 800-6.337-6.328-6.318-6.31-6.332-6.397 1000-6.309-6.299-6.29-6.281-6.304-6.37 1200-6.279-6.27-6.26-6.252-6.275-6.342 1400-6.249-6.24-6.231-6.223-6.247-6.314 1600-6.219-6.21-6.201-6.193-6.218-6.286 1800-6.187-6.179-6.17-6.163-6.189-6.258 BoronWorth BoronWorth BoronWorth8000100001200014000160001800021438-6.608-6.734-6.882-7.047-7.228-7.423-7.798-6.58-6.707-6.855-7.02-7.2-7.395-7.768-6.553-6.679-6.827-6.992-7.172-7.366-7.736

-6.525-6.652-6.799-6.964-7.143-7.335-7.701

-6.497-6.624-6.772-6.935-7.113-7.304-7.665-6.47-6.596-6.743-6.907-7.083-7.271-7.627-6.442-6.569-6.715-6.877-7.052-7.238-7.587

-6.414-6.541-6.687-6.847-7.02-7.203-7.544

-6.387-6.513-6.658-6.817-6.988-7.167-7.5

-6.359-6.485-6.629-6.787-6.954-7.13-7.454 BoronWorth BoronWorth BoronWorth 2-D Interpolation of Table 6

-X(L)XX(H)Y(L)YY(H)(ppm)(Burnup)100010931200100010002000100011061200100010002000 100011111200100010002000 100011151200100010002000 100011161200100010002000 100011201200100010002000 100011231200100010002000 100011251200100010002000 100011331200100010002000#REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000 BoronWorth#REF!#REF!#REF!100010002000#REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!100010002000

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1. REF!#REF!#REF!10001000200000200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 00200100010002000 BoronWorth0020010001000200000200100010002000 00200100010002000 00200100010002000 BoronWorth

-7 BoronA(L,L)A(L,H)A(H,L)A(H,H)Worth (pcm)-6.290-6.281-6.260-6.252-6.276-6.290-6.281-6.260-6.252-6.274

-6.290-6.281-6.260-6.252-6.273

-6.290-6.281-6.260-6.252-6.273

-6.290-6.281-6.260-6.252-6.273

-6.290-6.281-6.260-6.252-6.272

-6.290-6.281-6.260-6.252-6.272

-6.290-6.281-6.260-6.252-6.271

-6.290-6.281-6.260-6.252-6.270#REF!#REF!#REF!#REF!#REF!

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1. REF!#REF!#REF!#REF!#REF!-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427 BoronWorth-6.427-6.419-6.400-6.392-6.427-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427

-6.427-6.419-6.400-6.392-6.427 DiluteBorate TI-44 Data 1-D (10 ppm change/10)Interpolation RCS CbDiluteBorateDILUTEBORATE514308.79.3158.311.1501430.879.3858.011.1100675.619.4557.811.1 150442.409.5257.811.1 200328.919.5957.611.1 250261.769.6657.411.1 300217.399.7457.311.2 350185.889.8156.911.2 400162.359.89#REF!#REF!

450144.129.96#REF!#REF!

500129.5510.04#REF!#REF!

550117.6610.12#REF!#REF!

600107.7710.21#REF!#REF!

65099.4210.29#REF!#REF!

70092.2710.37#REF!#REF!

75086.0710.46#REF!#REF!

80080.6010.54#REF!#REF!

85075.8910.63#REF!#REF!

90071.6510.72#REF!#REF!

95067.8610.81#REF!#REF!100064.4510.91#REF!#REF!

105061.3711.00#REF!#REF!

110058.5611.10#REF!#REF!

115056.0111.20#REF!#REF!

120053.6611.30#REF!#REF!

130049.5211.50#REF!#REF!

140045.9711.71#REF!#REF!

150042.8911.93#REF!#REF!

250025.7014.70#REF!#REF! #REF!#REF!#REF!#REF! #REF!#REF!#REF!#REF!

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