ML090720036: Difference between revisions

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"

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.

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 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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)

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 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 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.

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 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)

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 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 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 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 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 18 of 35

Event Description: #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 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 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 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 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 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 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 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 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.

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.

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:

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)

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

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.

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)

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)

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.

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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)----------

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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.

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)

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)

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

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

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.

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