ML020250180

Final - Operating Section C (RO & SRO)

ML020250180
Person / Time
Site:	Millstone
Issue date:	01/04/2002
From:	Wilson M Dominion Nuclear Connecticut
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
050-423/2001-302 2K1NRC-001, Rev 0, IR-01-302
Download: ML020250180 (198)

Text

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1 STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 I.

Summary:

Facility: Millstone 3 PWR:

Scenario No: 2K1NRC-001 Op-Test No:2K1LOIT Examiners:

Operators:_

Initial Conditions: IC-18; 100% power, middle of life, MP2 in a refueling outage Event Malf. No.

Event Event Description No:

Type

• 1 None N(RO)

Shift Letdown 75 gpm Orifices using OP 3304A, Charging and Letdown, Section 4.7.3 2

None R(ALL)

CONVEX ordered load reduction 1*0 3CHS*MV8104 C(RO) 3CHS*MV8104 will not open 3

RX05B I(RO)

RCS Loop 2 Hot Leg Temperature Instrument fails high 4

RX1 5 l(BOP)

Main Steam Header Pressure Channel fails low 5

ED01 M(ALL)

Loss of Offsite Power TC03 C(BOP Main Turbine Trip Failure EG06B

) C(US/

"B" EDG will not start (can be started locally)

EG08A BOP)

"A" EDG will initially start then later trip 6

RC07A C(RO)

PZR PORV is partially open 7

SW08B/D C(RO)

Service Water Fails to Auto Start

• ( N ) ormal (R) eactivity (I ) nstrument (C) omponent ( M ) ajor Section 7 Page4of 4

Title:

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Assessor:

Steve Jackson QUALITATIVE ATTRIBUTES Y_1.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y_2.

The scenario consists mostly of related events.

Y_3.

Each event description consists of:

the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

Y_4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

_Y_5.

The events are valid with regard to physics and thermodynamics.

_Y_6.

Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

_N/A_7.

If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

_Y_8.

The simulator modeling is not altered.

_y__9.

The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario.

____Y_10.

Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section D.4 of ES301

_Y_11.

All individual operator competencies can be evaluated, as verified using form ES-301-6.

_Y_12.

Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios).

_Y_13.

Level of difficulty is appropriate to support licensing decisions for each crew position.

Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Lesson

Title:

Station Blackout ID Number:

2K1NRC-001 Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01.

Total Malfunctions (TM) - Include EM's-5 to 8 required Station Blackout, RCS Hot Leg Temperature Instrument fails high, PORV Fails Open on Trip, PT-507 Fails Low, Loss of Offsite Power, Auto Start Failure on EDG, Immediate Boration normal flowpath not available (MV8104 stuck shut), SW pump fails to auto start

02.

Malf's after EOP entry (EM's)- 1 to 2 required Auto Start Failure on EDG, PORV Fails Open on Trip

03.

Abnormal Events (AE)-2 to 4 required Rapid Downpower, Instrument Failure Response (Tc), Instrument Failure (PT-507),

Immediate Boration normal flowpath not available (MV8104 stuck shut)

04.

Major Transients (MT)-1 to 2 required Loss of Offsite AC, Station Blackout

05.

EOP's (EU) entered/requiring substantive actions 1 to 2 required E-0, Reactor Trip or Safety Injection, ECA-0.0, Loss of All AC Power

06.

EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to 2 required ECA-0.0, Loss of All AC Power,

07.

Critical Task (CT) - 2 to 3 required E Q Manually trip the main turbine before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF.

ECA-0.0 -- A:

Manually close the open PZR PORV before completing step 4 of ECA-0.0 or when power is restored to the block valve.

ECA-0.0 -- F:

Manually start the SW pump and verify SW flowpath before completing step 25 of ECA-0.0.

08.

Approximate Scenario Run Time: 45 to 60 min. (One scenario may approach 90 minutes)

09.

EOP run time:

10.

Technical Specifications are exercised during the scenario.

Total: 8 Total: 2 Total: 4 Total: 2 Total: 2 Total: 1 Total: 3 Total: 60 min Total: 30min (Y/N)_Y NOTES:

Reactivity Manipulation:

Rapid Downpower ordered by CONVEX Section 8 Page 2 of 2

MILLSTONE NUCLEAR POWER STATION LOIT NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

Revision ID Number:

STATION BLACKOUT 0

2K1 NRC-001 A

This document is the property of Millstone Nuclear Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Nuclear Power Station.

SIM EXAM 001

SUMMARY

OF CHANGES RE: NRC VALIDATION Changed leaking PORV to the B PORV (456). Deleted actions to close PORV.

Changed PT-507 failure ramp from 180 seconds to 240 seconds.

Added statement to "Check 3CHS*AV8149C Letdown Orifice in service" during Simulator set-up.

Corrected editorial error (changed 3204A to 3304A throughout).

Added statement "Total leakage flowrates listed in step 4.7.1.a have been determined to be 15.8 gpm" to the Turnover Sheet to avoid crew delay calculating these values.

Added Tech Spec detail.

Amended critical task to read.

[Critical Task] [Manually close the open PZR PORV (or block valve) before completing step 3 of ECA-0.0 or when power is restored to the block valvel Added Remotes for Instrument Rack Room doors.

SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1.

Cover Page

2.

Table of Contents

3.

Exam Overview

4.

Evaluation Guide

5.

Scenario Initial Conditions Sheet

6.

Scenario Validation Checklists

7.

Reference and Task Tracking

8.

Scenario Attributes Checklist Attachments NUTIMS Module Report STOP A.T REITHN ACT REVIEW

SECTION 3 EXAM OVERVIEW

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Exam Brief:

The plant is at 100% power, MOL steady state operations with all control systems in automatic. The crew will initially respond to an Engineering department request and shift Letdown 75 gpm Orifices using OP 3304A, Charging and Letdown, Section 4.7.3. When that normal evolution is complete, the crew will perform a rapid downpower required by CONVEX. The unit will be ordered to reduce load by 200 MwE to 1000 MwE (-83 %). The Immediate Boration step will require an alternate path as 3CHS*MV8104 will not open.

Once the Load Reduction is commenced, the RCS Loop 2 Hot Leg Temperature Instrument will fail high. Abnormal Tave, Delta T and Rod motion will evidence this failure.

The crew should respond using AOP 3571, Instrument Failure Response, to defeat the failed channel input, trip bistables and address Tech Specs. The US may or may not choose to halt the downpower while dealing with this malfunction When the downpower is complete, MSS-PT507, Main Steam Header Pressure Channel, will fail low slowly. The crew should take manual control of the Master Feedpump Speed Controller to stop the feed system transient. This transient may cause an automatic reactor trip signal or the crew may gain control of the transient.

If the crew is able to control the feed transient, a Loss of Offsite power will initiate a reactor trip and plant shutdown. The Main Turbine will not automatically trip [Critical Task].

The "B" EDG will not start due to it's inability to respond to signals from the Sequencer or MB8. Though the "A" EDG will initially start it will not load and will exhibit degraded frequency due to a damaged governor linkage. The crew may conservatively decide to shutdown the EDG; if not the "A" EDG will trip at step 4 of E-0 and will not be able to be re started.

The crew should carry out the actions of E-0. When the "A" EDG trips the crew should transition to ECA-0.0, Loss of all AC Power. At step 3 of ECA-0.0 the crew should diagnose that a PZR PORV is partially open and close the associate PORV Block Valve after attempting to close the PORV [Critical Task]. Plant assistance (a PEO/NLO, Maintenance, Engineering, etc.) should be dispatched to both EDGs to ascertain the reason for the start failures. The "B" EDG will be able to be started locally using ECA-0.0, Attachment E. The "B" EDG local start attempts will succeed when the crew has completed step 5 of ECA-0.0. Service Water will need to be restored to the running EDG [Critical Task]. The crew should then Go To step 24 as per the note prior to step 6.

The scenario will end when the crew has selected a recovery procedure, at step 27, based on plant conditions (ECA-0.1, Loss of All AC Power Recovery Without SI Required or ECA-0.2, Loss of All AC Power Recovery With SI Required).

The SM should classify this event as a Site Area Emergency - Charlie Two due to Loss of Voltage on Buses 34C and 34D > 15 minutes (EAL PSl).

3.

Plant/Simulator differences that may affect the scenario are:

NONE

4.

Duration of Exam:

60 minutes

SECTION 4 EVALUATION GUIDE STATION BLACKOUT

Title:

ID Number:

2K1 NRC-001 Revision: 0 All Control Room Conduct, Operations and Communications shall be in accordance with MP-14-MMM.

"Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 43

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide.

Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.

As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1.

Place the simulator in FREEZE if possible.

2.

Announce to the Crew that there is a simulator problem.

3.

Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4.

Deal with the problem (reboot, call STSB, etc.)

5.

After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6.

Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7.

Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 43

SECTIUN 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Simulator Setup Instructions:

1.

HANG Exam Placards on the simulator doors.

2.

START the Sun Workstation.

a.

IF the Sun Workstation is running THEN go to SIM ACTIVE.

3.

PLACE Recorder Power to ON.

4.

VERIFY that the current approved training load is loaded.

5.

REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

6.

RESET to IC-18, TEMP IC 2K1NRC-001

7.

ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

8.

PLACE Simulator to RUN.

9.

ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.

10.

RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.

11.

ENSURE Simulator fidelity items cleared.

a.

CHECK the STEP COUNTERS at correct position for plant conditions.

b.

PLACE 7

tiles under the DEMINS IN SERVICE lamacord label on MB6.

c.

PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d.

PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e.

CLEAR DCS alarms on MB7 and BOP console.

Section 4 Page 3 of 43

SECTiuN 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

f.

VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.

g.

ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

1)

See laminated directions on clipboard in Sim booth.

12.

RESET Computer Terminals to At Power displays if 100% power IC.

a.

MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L112 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)

b.

MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL T412", (585-588)

c.

MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d.

BOP Console (AY5A), BOP Picture 26, Circ Water

e.

STA Console, (AY3), NSSS Picture 15, RCP Seals

13.

RESET Rad Monitor Screen to Status Grid.

14.

OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

15.

IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS."

16.

LOCK the Simulator Room front door.

Section 4 Page 4 of 43

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 AsinExpected Action 5-Qfnnr4rr4 PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K1NRC EXAM EQUIPMENT Initial Malfunctions (CV) 3CHS*MV8104 EG06B EG08A TC03 RC07B (RC) 3RCS*PV456 (RC) 3RCS*PV456 SW02B SW02D Emergency Boration Valve Open - False EDG "B" Fail to Start EDG "A" Load Limiter Failure ramp-30 seconds Turbine Fails to Trip PORV 456 Leakage PORV 456 Green - True PORV 456 Red - True Service Water Pump B Failure to Auto Start Service Water Pump D Failure to Auto Start 0%

15%

BT1 (Rx Trip)

BT1 (Rx Trip)

BT1 (Rx Trip)

BT1 (Rx Trip)

BT1 (Rx Trip)

BT1 (Rx Trip)

Event Malfunctions RCS Narrow Range Hot Leg Temperature TE421A Failure Main Steam Header Pressure Transmitter PT507 Failure Loss of Offsite Power 100%

0%

ramp=120 seconds ramp=240 seconds EDG "A" Trip Lead Examiner:

Refer to the "Briefing Script for the Operational Exam" and brief the crew.

Section 4 Page 5 of 43 I/O MALF MALF MALF MALF I/O I/O MALF MALF MALF MALF MALF MALF RX05B RX15 ED01 EG07A

• • • • • Check 3CHS*AV8149C Letdown Orifice in service*****

t i=x n*.P.t*_d AP.tinn

.*f*nrJ*rrl

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assiqn Revision: 0 Expected Action Standard Event 1:

US OP 3304A, Charging and Letdown, Rev.28-01

[Normal Evolution]

RO US US RO RO T=O OP 3304A, Step 4.7.3 OP 3304A, Step 4.7.3.a OP 3304A, Step 4.7.1 CAUTION OP 3304A, Step 4.7.1 NOTE OP 3304A, Step 4.7.1 OP 3304A, Step 4.7.1.a Section 4 Page 6 of 43 IF shifting the 75 gpm letdown orifices PERFORM the following:

Refer To Step 4.7.1 and PLACE the 45 gpm orifice in service.

Changes in letdown flowrate will result in a change in VCT temperature, pressure and level due to the slow response of the controllers.

When performing this section as directed by an emergency or annunciator response procedure, the 17 gpm limitation of Step 4.7.1.a does not apply.

IF desired to increase letdown flow by placing the 45 gpm orifice in service, PERFORM the following:

VERIFY that the total of the flowrates listed below does not exceed 17 gpm:

"* Total RCP seal return flow

"* Total RCS leakage TOTAL Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDAIMalf Instructor Information/Activity Task Assian AsinExpected Action tn M

Revision: 0 NOTE: Call back after 2 minutes as PEO if asked to do CHS pump pre start checks.

RO RO RO RO RO RO RO RO Refer To Section 4.4 and START second charging pump (MB3):

"* 3CHS*P3A, "CHG PP A"

"* 3CHS*P3B, "CHG PP B" PLACE 3CHS-FK121, "CHG LINE FLOW," to "MANUAL" (MB3).

INCREASE charging flow to approximately 110 gpm.

OPEN 3CHS*AV8149A, "L/D ORIFICE ISOL" (MB3).

VERIFY letdown flow increased to approximately 131 gpm, as indicated on 3CHS-FI 132, "LETDOWN FLOW".

ADJUST charging flow to maintain pressurizer level.

PLACE 3CHS-FK121, "CHG LINE FLOW," to "AUTO" (MB3).

CLOSE letdown flow orifice isolation (MB3) for the appropriate orifice:

3CHS*AV8149B, "L/D ORIFICE ISOL" OP 3304A, Step 4.7.1.b OP 3304A, Step 4.7.1.c OP 3304A, Step 4.7.1.d OP 3304A, Step 4.7.1.e OP 3304A, Step 4.7.1.f OP 3304A, Step 4.7.1.g OP 3304A, Step 4.7.1.h OP 3304A, Step 4.7.3.b Section 4 Page 7 of 43 Expected Actinn Rfnntlnrtl

SEC'i ON4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assiqn Revision: 0 Expected Action Standard 3CHS*AV8149C, "LID ORIFICE ISOL" OPEN letdown flow orifice isolation (MB3).

"* 3CHS*AV8149C, "L/D ORIFICE ISOL"

"* 3CHS*AV8149B, "L/D ORIFICE ISOL" VERIFY letdown flow (approximately 131 gpm) is reestablished as indicated on 3CHS-FI 132, "LETDOWN FLOW" (MB3).

VERIFY charging flow is approximately 110 gpm as indicated on 3CHS-FI 121A, "CHG LINE FLOW" (MB3).

IF desired, Refer To Step 4.7.2 and REMOVE the 45 gpm orifice from service.

IF desired to decrease letdown flow by removing the 45 gpm orifice from service, PERFORM the following:

OP 3304A, Step 4.7.3.c OP 3304A, Step 4.7.3.d OP 3304A, Step 4.7.3.e OP 3304A, Step 4.7.3.f OP 3304A, Step 4.7.2 Section 4 Page 8 of 43 RO RO RO RO RO Standard

SECTIUN 4 Lesson

Title:

STATION BLACKOUT ID Number:

Time 2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assian Revision: 0 Expected Action Standnrd When letdown flow orifice A isolation is closed, anticipated charging flow to modulate to approximately 55 gpm, as indicated by 3CHS-FI 121A, "CHG LINE FLOW' (MB3).

CLOSE 3CHS*AV8149A, "LID ORIFICE ISOL" (MB3)

VERIFY normal letdown flow of approximately 75 gpm is established as indicated by 3CHS-FI 132, "LETDOWN FLOW' (MB3).

STOP the second charging pump (MB3):

OP 3304A, Step 4.7.2.a NOTE OP 3304A, Step 4.7.2.a OP 3304A, Step 4.7.2.b OP 3304A, Step 4.7.2.c

• 3CHS*P3A, "C HG PP A"

• 3CHS*P3B3, "CHG PP B" T= After L/D Orifice shift EVENT 2: CONVEX Rapid Downpower CALL as CONVEX: Grid instabilities required that we shed load. Millstone:

Perform an emergency generation reduction of 200 MwE to 1000 MwE in the next 15 minutes. Maintain VARS loading at it's current value. Call CONVEX when target power is reached.

Section 4 Page 9 of 43 RO RO RO RO CALL FROM SIM BOOTH Expected Action RtnnHnrrl

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Exnected Action Standard AOP 3575, Rapid Downpower, Rev.7 A CONVEX requested emergency generation reduction should be completed within 15 minutes of notification.

If a unit shutdown is required, the target power level should be between 20% and 25% reactor power.

If at any time ROD CONTROL BANKS LIMIT LO - LO (MB4C 4 - 9) annunciator is received, DO NOT go to AOP 3566, Immediate Boration.

Immediately perform step 9.

CREW Determine Power Reduction Rate

(%/min).

US Check desired power reduction rate LESS THAN OR EQUAL TO 5%/min.

US Check power reduction CONVEX REQUESTED CREW Perform load reduction at 5% min and Proceed to step 2.

US Check Rod Control In AUTO.

AOP 3575 Step 1 NOTE AOP 3575 Step 1 AOP 3575 Step 1.a AOP 3575 Step 1.b AOP 3575 Step 1.c AOP 3575 Step 2 Section 4 Page 10 of 43 Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Revision: 0 Task Assign Expected Action Standard CREW US US BOP BOP BOP AOP 3575 Step 3 AOP 3575 Step 3.a AOP 3575 Step 3.b AOP 3575 Step 3.c AOP 3575 Step 3.d AOP 3575 Step 3.e AOP 3575 Step 3.f Align EHC Panel Check turbine OPERATING MODE MANUAL Check LOAD LIMIT LIMITING light LIT Intermittently Press DECREASE LOAD pushbutton until LOAD LIMIT LIMITING light - NOT LIT Rotate LOAD LIMIT SET adjust knob at least one full turn in raise direction Select DECREASE LOADING RATE to ON Select LOAD RATE LIMIT % MIN to required power reduction rate (%

min)

If at any time the power reduction rate or target power level must be changed, Return to step 1.

Verify Power Reduction Rate Check power reduction rate 5% MIN AOP 3575 Step 4 NOTE AOP 3575 Step 4 AOP 3575 Step 4.a Section 4 Page 11 of 43 US/RO RO

SECI iUN 4 Lesson

Title:

STATION BLACKOUT ID Number:

Time 2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assiqn Revision: 0 Expected Action Standard Check power reduction - REQUIRED TO STABILIZE PLANT Proceed to step 5.

Initiate Rapid Boration Verify RCS makeup system in AUTO START one boric acid transfer pump.

I/O, 3CHS*MV8104, Emergency Boration Valve, Close - True OPEN emergency boration valve (3CHS*MV8104).

RO NOTE: 1/O forces RNO for Gravity Boration.

Verify direct boric acid flow (3CHS-FI 183A) - INDICATED.

Perform the following to initiate gravity boration:

1. Place the charging line flow control valve in MAN.

2. OPEN at least one gravity feed boration valve.

AOP 3575 Step 5.d AOP 3575 Step 5.d RNO Section 4 Page 12 of 43 RO RO INITIAL I/O, 3CHS*

MV8104 AOP 3575 Step 4.b AOP 3575 Step 4.b RNO AOP 3575 Step 5 AOP 3575 Step 5.a AOP 3575 Step 5.b AOP 3575 Step 5.c Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Ext~ected Action Standard Record time boration started Time Energize all PZR heaters.

Determine required boric acid addition by multiplying total power change (A%) by 15 (gal/%) = __

gal.

Determine required time to borate by dividing required gallons of boric acid by the direct boric acid flowrate (net charging flow rate if using gravity boration) _

min.

Check turbine load decrease - IN PROGRESS OR COMPLETED.

AOP 3575 Step 5.f AOP 3575 Step 5.g AOP 3575 Step 5.h AOP 3575 Step 5.i AOP 3575 Step 5.j Section 4 Page 13 of 43

3. CLOSE at least one VCT outlet isolation valve.

4. Limit net charging flow to the RCS to LESS THAN 75 gpm (charging +

seal injection - RCP seal return).

5. Adjust charging line flow control valve as required.

6. Proceed to step 5.f.

RO US Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assiqn Revision: 0 Expected Action Standard Us RO Proceed to NOTE prior to step 7 If a unit shutdown is being performed, the final MWe load should be approximately 230 MWe.

Initiate Load Reduction.

Check turbine OPERATING MODE MANUAL Check rapid or gravity boration - IN PROGRESS Check LOAD RATE LIMIT % MIN set at - 3% OR 5%.LIMITING light - LIT.

Select LOAD RATE LIMIT % MIN to 3% or 5%.

Utilizing DECREASE LOAD pushbutton, Adjust LOAD SET to desired final MWe (target power level)

Check power reduction - CONVEX REQUESTED.

AOP 3575 Step 5.j RNO AOP 3575 Step 7 NOTE AOP 3575 Step 7 AOP 3575 Step 7.a AOP 3575 Step 7.b AOP 3575 Step 7.c AOP 3575 Step 7.c RNO AOP 3575 Step 7.d AOP 3575 Step 7.e Section 4 Page 14 of 43 US/BOP BOP BOP BOP BOP BOP BOP Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assiqn Revision:

0 Exoected Action Standard Maintain initial MVAR loading during power reduction, unless directed otherwise.

US/RO Check boration - IN PROGRESS BOP The following step places one TD FW pump in manual while allowing the other TD FW pump to automatically unload during the downpower.

US/BOP Align One Feedwater Pump For Automatic Unloading BOP Verify removing a feedwater pump from service during the downpower DESIRED Proceed to step 9.

US/RO Verify Rod Position RO Check ROD CONTROL BANKS LIMIT LO - LO (MB4C 4 - 9) annunciator - LIT.

AOP 3575 Step 7.g AOP 3575 Step 8 NOTE AOP 3575 Step 8 AOP 3575 Step 8.a AOP 3575 Step 8.a RNO AOP 3575 Step 9 AOP 3575 Step 9.a Section 4 Page 15 of 43 BOP AOP 3575 Step 7.f Standard

SECi iN 4

Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard US/RO RO RO Section 4 Page 16 of 43 Proceed to step 9.e and, IF at any time, the annunciator is received, THEN Perform steps 9.b, 9.c and 9.d.

Verify boration from a BAT tank is in progress at GREATER THAN OR EQUAL TO 33 gpm.

Perform the applicable action:

IF rapid OR gravity boration is in

progress, THEN Increase boration flow.

IF normal OR no boration is in

progress, THEN Perform steps 5.a through 5.e.

IF the required boration flow can NOT be established, THEN TRIP the reactor and Go to E - 0, Reactor Trip or Safety Injection.

AOP 3575 Step 9.a RNO AOP 3575 Step 9.b AOP 3575 Step 9.b RNO

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision:

0 ExDected Action Standard Continue boration at GREATER THAN OR EQUAL TO 33 gpm until the rods are restored above the insertion limit.

Refer to the following Technical Specifications and Determine additional actions:

AOP 3575 Step 9.c AOP 3575 Step 9.d T/S 3.1.1.1.1 T/S 3.1.3.6 RO Check ROD CONTROL BANKS LIMIT LO (MB4C 3 - 9) annunciator LIT US Proceed to NOTE prior to step 10

and, IF the annunciator is received, THEN Perform step 9.f and 9.g.

US Check power reduction - CONVEX REQUESTED.

US/BOP If desired, Slow or Stop the power reduction.

Increase the boration flow rate as required.

AOP 3575 Step 9.e AOP 3575 Step 9.e RNO AOP 3575 Step 9.f AOP 3575 Step 9.f RNO AOP 3575 Step 9.g Section 4 Page 17 of 43 RO US US/RO Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 Exnected Action Standard RO AOP 3575 Step 10 NOTE Boric acid total volume addition and flow rates are based on approximations. Adjustments should be made to these values as necessary to ensure the reactor reaches the desired end state of:

"* Tavg on program

"* Rods above the Rod Insertion Limit

"* AFD on or above the target value Restore From Rapid Boration.

Check rapid boration - IN PROGRESS.

Proceed to Step 11.

Restore From Gravity Boration Check gravity boration - IN PROGRESS AOP 3575 Step 10 AOP 3575 Step 10.a AOP 3575 Step 10.a RNO AOP 3575 Step 11 AOP 3575 Step 11.a Section 4 Page 18 of 43 US RO US US RO Expected Action Rt*nd*rd

SECTiON 4 Lesson

Title:

STATION BLACKOUT ID Number:

Time 2K1 NRC-001 IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard Check gravity boration performed for the required time determined in step 5.i.

OPEN both VCT outlet isolation valves.

CLOSE both gravity feed boration valves.

Restore PZR level to program value and Place charging line flow control valve in AUTO.

EVENT 3: RCS Th Instrument Fails" AOP 3571, Instrument Failure, US Rev. 7 US RO Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback.

If a reactor trip occurs, immediately go to E-0, Reactor Trip or Safety Injection.

Determine The Initiating Parameter And Place The Affected Controller In MANUAL.

AOP 3571 Step 1 CAUTION AOP 3571 Step 1 NOTE AOP 3571 Step 1 Section 4 Page 19 of 43 RO RO RO RO T= When discovered by crew

("as-is" failure)

MALF

RX05B, 100%,180 seconds AOP 3575 Step 11.b AOP 3575 Step 11.c AOP 3575 Step 11.d AOP 3575 Step 11.e

SECT-ION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard Stabilize The Plant Parameters.

It is desired that I&C personnel trip the bistables specified in this procedure. If, during off-hours, IC&E personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.

Perform Corrective Actions Using Appropriate Attachment Instrument Failure RCS Narrow Range Temperature Channel Failure AOP 3571 Step 2 AOP 3571 Step 3 NOTE AOP 3571 Step 3 Attachment A

ATTACHMENT A: RCS Narrow Range Temperature Channel Failure US The following annunciators are symptoms of an RTD failure:

TAVE/AUCT TAVE DEVIATION TREF/AUCT TAVE DEVIATION AT/AUCT AT DEVIATION MB4C 5-5 MB4C 6-5 MB4C 4-5 Section 4 Page 20 of 43 US US US

SECTIUN 4 Lesson

Title:

STATION BLACKC ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign RO Expected Action OVERPOWER AT TAVE HI OVERTEMP AT LOOP 1,2,3,4, OVR TEMP AT LOOP 1,2,3,4 OVR PWR AT LOOP 1,2,3,4 OVR TEMP AT LOOP 1,2,3,4 OVR PWR AT LOOP 1,2,3,4 TAVE LO LOOP 1,2,3,4 TAVE LO-LO Defeat the failed channel input.

"* Loop Temp Cutout - AT 3RCS-TS41 1 F

"* Loop Temp Cutout - TAVG - 3RCS TS412T

"* OT/OPAT Record Select - 3RCS-Section 4 Page 21 of 43 Revision: 0 Standard MB4C 3-6 MB4C 5-6 MB4C 4-6 MB4F 1,2,3,4 5

MB4F 1,2,3,4 6

MB4F 1,2,3,4 7

MB4F 1,2,3,4 8

MB2D 1,2,3,4 7

MB2D 1,2,3,4 8

AOP 3571 Attachment A Step 1

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Expected Action Standard TS411E RO Check the following annunciators NOT LIT:

TREF/AUCT TAVE DEVIAITON MB4C 6-5 TAVE HI - MB4C 5-6 RO Restore TAVE - TREF error to within 1 OF and return rod control to automatic.

RO Monitor PZR level until stable. If PZR level controller is in manual, Restore pressurizer level to program level and Place PZR level controller in automatic.

CREW When conditions have stabilized, Observe MB annunciators and parameters. Immediately report any unexpected or unexplained conditions to the Shift Manager.

US Determine which Reactor Protection System bistable(s) requires tripping:

Place a check mark in the box above the appropriate channel that requires tripping on page 4 of this Attachment.

AOP 3571 Attachment A Step 2 AOP 3571 Attachment A Step 3 AOP 3571 Attachment A Step 4 AOP 3571 Attachment A Step 5 AOP 3571 Attachment A Step 6 AOP 3571 Attachment A Step 6a Section 4 Page 22 of 43

SECT-ION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard

[Tech Specs]

3.3.1 Functional Unit 7 & 8, Action 6 3.3.2 Functional Unit 5.d, Action 20 3.3.2 Functional Unit 9.b, Action 21 Refer to Technical Specification 3.3.1 and 3.3.2.

AOP 3571 Attachment A Step 6b Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped.

Request the I&C Department trip the appropriate bistables using the last page of Attachment A and Attachment S.

Verify the appropriate bistable status lights are lit.

Following corrective action by the I&C Department, the channel may be AOP 3571 Attachment A Step 6c AOP 3571 Attachment A Step 6d AOP 3571 Attachment A Step 6e AOP 3571 Attachment A Section 4 Page 23 of 43 REMOTES RXR 107 RXR 31 RXR 35 RXR 2 RXR 6 RXR 111 RXR 115 RXR 107 US Standard

SECI iUN 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard declared OPERABLE if it complies with Step 7 NOTE the guidelines provided in the Table found on page 3 of this Attachment.

US Request I&C Department perform AOP 3571 corrective maintenance on failed Attachment A instrument.

Step 7 EVENT 4: Main Steam Header Pressure Channel Failure ATTACHMENT J : Main Steam Header Pressure Channel Failure US US BOP MALF RX15, 0%

ramp=120 seconds Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback.

If a reactor trip occurs, immediately go to E-0, Reactor Trip or Safety Injection.

Determine the initiating parameter and place the affected controller in MANUAL.

AOP 3571 Step 1 CAUTION AOP 3571 Step 1 NOTE AOP 3571 Step 1 Stabilize the plant parameters.

AOP 3571 Step 2 Section 4 Page 24 of 43 Downpower complete or Examiner's Cue BOP

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Expected Action Standard US US NOTE: Move on when correct Attachment has been identified. It is not necessary to accomplish the steps in the attachment.

US It is desired that I&C personnel trip the bistables specified in this procedure. If, during off-hours, I&C personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.

Perform corrective actions using appropriate attachment.

Instrument Failure Main Steam Header Pressure Channel Failure The following annunciators are symptoms of a MS header pressure instrument failure (PT-507): None BOP Verify feedwater pump A and B master speed control (3FWS-SK509A) in MANUAL and restore feed pump differential pressure to normal operating band (Program: 40-140 psid)

AOP 3571 Step 3 NOTE AOP 3571 Step 3 Attachment J

AOP 3571 Attachment J NOTE AOP 3571 Attachment J Step 1 Section 4 Page 25 of 43

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

Time 2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard BOP Place steam generator pressure controller (3MSS-PK507) in MANUAL and reduce the output to minimum. (Automatic STEAM PRESSURE steam dump mode is inoperable until the channel is restored.)

CREW When conditions have stabilized, Observe MB annunciators and parameters and immediately report any unexpected or unexplained conditions to the Shift Manager.

US There are no Technical Specifications or bistables associated with 3MSS-PT507.

US Request I&C Department perform corrective maintenance on failed instrument.

T= Feedwater Transient or AOP 3571, Att. J identified AOP 3571 Attachment J Step 2 AOP 3571 Attachment J Step 3 AOP 3571 Attachment J Step 4 NOTE AOP 3571 Attachment J Step 4 EVENT 5: Loss of Offsite Power Crew Go to E-0, Reactor Trip or Safety Injection.

Section 4 Page 26 of 43 MALF ED01 E-0, Reactor Trip or Safety Injection, Rev. 20 i

Standard

SEC-r ION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Expected Action Standard

"* Foldout page must be open ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 105 R/hr in containment.

The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

E-0, Step 1, NOTE Verify Reactor Trip Check reactor trip and bypass breakers - OPEN

"* Check rod bottom lights - LIT

"° Check neutron flux DECREASING RO

[Critical Task] [ Manually trip the main turbine before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF]

BOP TRIP the reactor.

Verify Turbine Trip E-0, Step 1, RNO E-0, Step 2 Section 4 Page 27 of 43 RO E-O, Step 1

SEC1 ioN 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard BOP BOP BOP NOTE: After A EDG Trip expect transition to step 3 of ECA-0.0 US Check all turbine stop valves CLOSED TRIP the turbine IF the turbine will not trip THEN Runback the turbine to close the control valves IF the turbine cannot be runback THEN CLOSE the MSIVs and MSIV bypass valves Verify Power to AC Emergency Busses Check busses 34C and 34D - AT LEAST ONE ENERGIZED Check busses 34C and 34D - BOTH ENERGIZED Try to Restore power to de-energized AC emergency busses.

Check If SI Is Actuated E-0, Step 2.a E-0, Step 2.a RNO E-0, Step 3 E-0, Step 3.a E-0, Step 3.b E-0, Step 3.b, RNO E-0, Step 4 Section 4 Page 28 of 43 T= Step 4 of E-0 MALF EG07A

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Ext~eted AtionStandard NOTE: Crew may have tripped EDG due to abnormal operations ECA-0.0, Loss of All AC Power, Rev. 15 RO US US Verify Safety Injection Actuation annunciator - LIT Check if SI is required CSF Status Trees should be monitored for information only. Other Functional Response procedures shall NOT be implemented until at least one AC emergency bus is energized and direction is given in ECA-0.1 or ECA-0.2.

EOP 35 E-0, Step 4.a E-0, Step 4, RNO ECA-0.0 Step 1 NOTE Check reactor trip and bypass breakers - OPEN ECA-0.0 Step 1 Check neutron flux DECREASING TRIP the reactor.

IF reactor trip can NOT be verified, THEN Dispatch an operator to locally TRIP the reactor trip and bypass breakers.

ECA-0.0 Step 1, RNO ECA-0.0 Step 2 Section 4 Page 29 of 43 RO Verify Reactor Trip BOP Verify Turbine Trip Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Expected Action Check all turbine stop valves CLOSED TRIP the turbine.

IF the turbine will NOT trip, THEN Runback the turbine to close the control valves.

IF the turbine can NOT be runback, THEN CLOSE MSIVs and MSIV bypass valves.

EVENT 6: Leaking PORV RO NOTE: A PORV is partially open MALF RC07B @

BT1

[Critical Task]

[Manually close the open PZR PORV (or block valve) before completing step 3 of ECA-0.0 or when power is restored to the block valve]

RO Check If RCS Is Isolated Verify PZR PORVs - CLOSED IF PZR pressure is LESS THAN 2350 psia, THEN CLOSE THE PORVs.

CLOSE letdown orifice isolation valves.

Verify excess letdown and reactor head vent isolation valves - CLOSED ECA-0.0 Step 3.b ECA-0.0 Step 3.c Section 4 Page 30 of 43 Time Standard ECA-0.0 Step 2.a ECA-0.0 Step 2.a.a RNO ECA-0.0 Step 3 ECA-0.0 Step 3.a ECA-00 Step 3.a RNO RO RO

SECTiON 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Expected Action Standard BOP US Us BOP ECA-0.0 Step 4 ECA-0.0 Step 5 CAUTION ECA-0.0 Step 5 NOTE ECA-0.0 Step 5 ECA-0.0 Step 5.a ECA-0.0 Step 5.a.1 ECA-0.0 Step 5.a.1 RNO Verify AFW Flow To All Intact SGs GREATER THAN 530 gpm If power is NOT restored to Bus 34C within 30 minutes, Inverter 6 de energizes and the process computer will be unavailable.

The SBO diesel may be aligned to either bus pair 34A and 34C or 34B and 34D. The preferred bus pair is 34A and 34C.

Try To Restore Power To Any AC Emergency Bus Energize AC emergency bus from its emergency diesel generator START one emergency diesel generator Locally Start one EDG using Attachment E Verify AC emergency bus automatically energized Energize an AC emergency bus from its EDG.

ECA-0.0 Step 5.a.2 ECA-0.0 Step 5.a.2 RNO Section 4 Page 31 of 43 Standard

SECI ioN 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf Revision: 0 Instructor Information/Activity Task Assign Expected Action NOTE: Respond as PEO if directed.

IF an AC emergency bus can NOT be energized from its EDG, THEN Perform the applicable action:

"* IF offsite power is available, THEN Perform the following:

1) STOP the EDG

2) Using OP 3343, "Station Electrical Service 4.16 Kv," Try to energize bus through the RSST or the NSST as follows:

1)

Restore Bus 34C (34D) to service

2)

Restore Bus 34A (34B) to service IF offsite power is unavailable, THEN locally Energize an emergency bus with a running EDG using Attachment F.

BOP Check AC emergency busses - AT LEAST ONE ENERGIZED US/BOP Perform the following:

ECA-0.0 Step 5.b ECA-0.0 Step 5.b RNO Section 4 Page 32 of 43 Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assiqn Revision: 0 ExDected Action Standard NOTE: Respond as PEO if directed.

NOTE: Respond as PEO if directed.

REMOTES:

RXR 106,107,108,109 ANN I/O:

MB4C, A-4T, A-4B US

1) OPEN all SBO bus tie breakers:

For Bus 34A: 34A1 - 1 For Bus 34B: 34B1 - 2 For Bus 24E: A505 (Unit 2)

2) Locally Start SBO diesel using Attachment G.

3) Locally Align the selected AC bus pair using one of the following attachments:

For Busses 34A and 34C:

Attachment H For Busses 34B and 34D Attachment I

4) Open Instrument Rack Room cabinet doors using Attachment B and Proceed to CAUTION prior to step 6.

Maintain one service water pump available to automatically load on its AC emergency bus to provide emergency diesel generator cooling.

Section 4 Page 33 of 43 Time ECA-0.0 Step 6 CAUTION Standard

SECTION 4 Lesson

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US If a SI signal is actuated during this procedure, it must be reset to permit manual loading of equipment on an AC emergency bus.

US Spurious fire alarms may occur in areas where the temperatures exceed 120°F due to a loss of ventilation. The locking out of CO 2 protected areas which have spurious fire alarms is recommended.

US When power is restored to any AC ECA-0.0 emergency bus from offsite or an Step 6 emergency diesel generator, NOTE recovery actions should continue starting with Step 24.

ADVERSE CTMT is defined as Ctmt temperature GREATER THAN 180OF or Ctmt radiation level GREATER THAN 1 05R/hr.

US Block Automatic Loading Of AC ECA-0.0 Emergency Busses Step 6 CREW RESET the following if necessary ECA-0.0 Step 6.a Section 4 Page 34 of 43

EVALUA-I ION GUIDE

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard SI Aux FW for Lo-Lo SG Level CREW Place Following Control Switches In ECA-0.0 PULL-TO-LOCK Step 6.b Charging pumps One service water pump per train RPCCW pumps Quench spray pumps Recirculation spray pumps Sl pumps RHR pumps SMD AFW pumps CAR fans Section 4 Page 35 of 43

STATION BLACKOUT EVALUAI ION GUIDE ID Number:

2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assiqn ExDected Actions Standard T=MDAFW pumps in PTL US BOP 0

Control Building HVAC chillers NOTE: Respond as PEO if directed.

T+2 min. Acknowledge EDG trouble.

REMOTE:

EGR05: A EGR07: B T+5 min. EDG Local Control REMOTE:

EGR09: A EGR11: B T+6 min. EDG Output Breaker Local Control REMOTE:

EGR13: A EGR15: B THEN: DELETE EG06B BUT complete all before Crew completion of Step 6.

NOTE: Crew should Go To step 24 ECA-0.0 Step 7 ECA-0.0 Step 7.a Section 4 Page 36 of 43

Title:

Time

"* CRDM cooling fans

"* Auxiliary Building filter exhaust fans Energize Any AC Emergency Bus From The SBO Diesel.

Verify both AC emergency busses DEENERGIZED.

Revision: 0 Standard

STATION BLACKOUT EVALUAI ION GUIDE ID Number:

2K1NRC-001 Instructor I nformation/Activitv Task Assinn I~n~t, t

" 1.7 Cl" CA1-U Instructor~~~~~~'~La Inomain/clvt Uva-alA-i

.1 US US BOP BOP EVENT 7: Restore Service Water

[Critical Task]

[Manually start the SW pump and verify SW flowpath before completing step 25 of ECA-0.0]

RO Consult with the ADTS and determine if the SBO diesel should be used to power a deenergized AC emergency bus.

IF the SBO diesel is NOT to be used to power deenergized emergency bus, THEN Proceed to Step 24.

Stabilize SG Pressures.

Adjust SG atmospheric dump valves or atmospheric dump bypass valves.

Verify Service Water System Operation For Each Energized Emergency Bus.

Check diesel generator heat exchanger SW outlet isolation valves (3SWP*AOV39A and 3SWP*AOV39B)

- OPEN.

OPEN valves.

ECA-0.0 Step 25.a ECA-0.0 Step 25.a RNO Section 4 Page 37 of 43

Title:

Time IDA/Malf Revision: 0 ECA-0.0 Step 7.a RNO ECA-0.0 Step 24 ECA-0.0 Step 24.a ECA-0.0 Step 25 ICyn,*t"f* Ar'fi*ne

STATION BLACKOUT I

EVALUATION GUIDE ID Number:

2K1NRC-001 Instructor Information/Activitv Task

~4.

.'l~l1/4ll11~)O Undi U Check service water pumps - ONE PER TRAIN RUNNING.

START one pump per train.

Place service water pumps in PULL TO-LOCK to AUTO.

Check service water pump discharge valves - OPEN FOR RUNNING PUMPS For pump A (3SWP*MOV102A)

For pump B (3SWP*MOV1 02B)

For pump C (3SWP*MOV102C)

For pump D (3SWP*MOV102D)

OPEN valves.

NOTE: As PEO, may be asked to locally close MOV*71A. Wait 5 minutes and, if simulator still in dynamic mode, report valve closed.

Check TPCCW heat exchanger SW supply isolation valves (3SWP*MOV71A and 3SWP*MOV71B)

- CLOSED.

Section 4 Page 38 of 43

Title:

Time IDA/Malf Revision: 0 ECA-0.0 Step 25.b ECA-0.0 Step 25.b RNO ECA-0.0 Step 25.c ECA-0.0 Step 25.d ECA-0.0 Step 25.d RNO ECA-0.0 Step 25.e Fvnar-t*H A rtiane

Title:

STATION BLACKOUT ID Number:

2K1NRC-001 Time IDA/Malf EVALUA1 ION GUIDE Instructor Information/Activity Task Assian AsinExpected Actions qnnrnf Revision: 0 US BOP BOP US NOTE: Use REMOTES EDR18 @ T+2 and EDR44 @ T+4 and report.

BOP When placing loads on an energized emergency bus, DO NOT exceed the capacity of the power source.

Perform the Following For Each Energized AC Emergency Bus:

Verify the following equipment is energized:

0 480 volt emergency busses

"* Battery chargers Load equipment as necessary.

Energize previously de-energized DC loads.

Energize Inverter 6 from MCC 32-3T:

Verify Bus 34C - ENERGIZED RESET LOP ECA-0.0 Step 26.c.1 ECA-0.0 Step 26.c.2 Section 4 Page 39 of 43 ECA-0.0 Step 26 CAUTION ECA-0.0 Step 26 ECA-0.0 Step 26.a ECA-0.0 Step 26.a RNO ECA-0.0 Step 26.b ECA-0.0 Step 26.c Expected Antinn.*

,£f* nrt* rrl

STATION BLACKOUT EVALUAi ION GUIDE ID Number:

2K1NRC-001 IDA/Malf Instructor Information/Activity Task Assign Exoected Actions Sta ndrd~n NOTE: Respond if asked that communications console is energized US US US Locally CLOSE the feeder breaker on 32T (32T1 3-2) to MCC 32-3T Locally Verify Inverter 6 DC input ammeter indicating zero amps.

Verify communications console ENERGIZED.

Select Recovery Procedure.

Check RCS subcooling based on core exit TCs - GREATER THAN 320F (1 15°F ADVERSE CTMT)

Go to ECA - 0.2, Loss of All AC Power Recovery With SI Required.

Check PZR level - GREATER THAN 16% (50% ADVERSE CTMT).

Go to ECA - 0.2, Loss of All AC Power Recovery With SI Required.

ECA-0.0 Step 26.c.3 ECA-0.0 Step 26.c.4 ECA-0.0 Step 26.d ECA-0.0 Step 27 ECA-0.0 Step 27.a ECA-0.0 Step 27.a RNO ECA-0.0 Step 27.b ECA-0.0 Step 27.b RNO Section 4 Page 40 of 43

Title:

Time Revision: 0 Expected Actions

£f*nd*rd

Title:

STATION BLACKOUT ID Number:

Time EVALUATION GUIDE 2K1NRC-001 IDA/Malf Instructor Information/Activity Us US Check SI equipment NOT actuated Verify SI pumps - STOPPED Verify RHR pumps - NOT RUNNING IN SI MODE Verify charging pump cold leg injection valves - CLOSED Go to ECA-0.2, Loss of All AC Power Recovery With SI Required.

Go to ECA-0.1, Loss of All AC Power Recovery Without SI Required.

ECA-0.0 Step 27.c ECA-0.0 Step 27.c RNO ECA-0.0 Step 27.d TERMINATE UPON TRANSITION TO ECA-0.1 or ECA-0.2 Section 4 Page 41 of 43 Task t,

"0 C51H C11U Instructor Infor ation/Activitv Assinn PY antarl A.-+in C +

A Revision: 0

(

• v nc*t',f,*,rt Ar, finne

SECTION 4 ID Number:

2K1 NRC-001 EVALUATION GUIDE

1.

SUMMARY

The following Critical Tasks are covered in this exam:

TASK DESCRIPTION Manually trip the main turbine before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF.

Manually close the open PZR PORV before completing step 3 of ECA-0.0 or when power is restored to the block valve Manually start the SW pump and verify SW flowpath before completing step 25 of ECA-0.0 such that the EDG does not fail because of damage caused by engine overheating.

TASK #

E-0 -- Q K/A >/= 3.0 045-K1.18 3.6/3.7 ECA-0 01 0-A2.03

-A 4.1/4.2 010-A4.03 4.0/3.8 ECA-0.0 076-A2.01

-- F 3.5/3.7 BASIS FOR SELECTION Failure to trip the main turbine under the postulated plant conditions causes challenges to CSFs beyond those irreparably introduced by the postulated conditions and constitutes a demonstrated inability by the crew to "take an action...that would prevent a challenge to plant safety."

Failure to close the PORV under the postulated plant conditions constitutes "mis operation or incorrect crew performance that leads to degradation of any barrier to fission product release."

Failure to restore SW flow means that the EDG is running without SW cooling which leads engine overheating. Failure to perform the critical task constitutes "mis-operation or incorrect crew performance that leads to degraded emergency power capacity."

Note: [*] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide.

Section 4 Page 42 of 43 Revision: 0

SECTION 4 STATION BLACKOUT ID Number:

2K1NRC-001 EVALUATION GUIDE Revision: 0 Section 4 Page 43 of 43

Title:

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number:

2K1NRC-001 Reactor Power:

Operating History:

RCS Boron:

Core Burnup:

100%

250 days on line 1150 ppm 8,000 MWD/MTU Condensate Demins:

Evolutions in Progress:

Major Equipment OOS:

7 demins in service Millstone Unit 2 is offline for scheduled refueling outage.

NONE Crew Instructions:

Engineering department has requested that you shift Letdown 75 gpm Orifices from 3CHS*AV8149C to 3CHS*AV8149B using OP 3304A, Charging and Letdown, Section 4.7.3.

Total leakage flowrates listed in step 4.7.1.a have been determined to be 15.8 gpm.

Plant/Simulator Differences:

Real Time and Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.

0 If not using the speed dial option on the phone system, the operator must dial either

1. 3333 or #3334 to reach the person/department they desire.

0 The following PPC programs do not function on the simulator:

Samarium Follow Xenon Follow Sequence of Events Section 7 Page1of 4 Revision: 0

SECTION 6 VALIDATION CHECKLIST STATION BLACKOUT ID Number:

2K1NRC-001 Revision: 0 Remote functions:

All remote functions contained in the guide are certified.

Malfunctions:

All malfunctions contained in the guide are certified.

Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02.

Simulator Operating Limits:

The simulator guide has been evaluated for operating limits and/or anomalous response.

Test Run:

The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected.

Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.)

11/20/01 Technical Reviewer Date Section 7 Page2of 4

Title:

SECTION 7 REFERENCE AND TASK TRACKING STATION BLACKOUT ID Number:

2K1NRC-001

1.

References:

AOP*3571 AOP*3575 EOP*E-0 EOP*ECA-0.0 EOP*ERGEXE EOP* Step -DOC EOP*ERGHP EPI*FAP06*003 NUREG*1021 rev 8 Instrument Failure Response Rapid Downpower Reactor Trip or Safety Injection Loss of Offsite Power Westinghouse Owners Group Executive Document MP3 step deviation Document Westinghouse Owners Group Background Document Event Assessment, Classification and Reportability Examiners Standards Section 7 Page3of 4

Title:

Revision: 0

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1 SGTR AT LOW POWER ID Number:

2KINRC-002 I.

Summary:

( R ) eactivity (I) nstrument ( C ) omponent ( M ) ajor Section 7 Page 1 of 1

Title:

Revision: 0 Facility: Millstone 3 PWR:

Scenario No: 2K1NRC-002 Op-Test No:2K1LOIT Examiners:

Operators:

Initial Conditions: IC-22; 50% power, middle of life, MP2 in a refueling outage, Unit performing power ascension.

Event Malf.

Event Event Description No:

No.

Type

• 1 None R(RO)

Power Increase per OP 3204, At Power Operations N(ALL) 2 ED08D I(ALL)

Loss of 125 V DC Bus 4 3

CV1OB I(RO)

VCT Level Transmitter Fails High 4

IA03 C(ALL)

Loss of Instrument Air 5

SG01A M(ALL)

SGTR "A" S/G 6

RP09A M(ALL)

Reactor Fails to Trip from MB4 & MB7 RP09B 7

RP11L C(BOP)

Feed Water Isolation Fails to Actuate 8

MS09A C(BOP)

S/G A Atmospheric Steam Dump Valve Fails Open

• ( N ) ormal

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

SGTR AT LOW POWER ID Number:

2KINRC-002 Revision: 0 Assessor:

Steve Jackson QUALITATIVE ATTRIBUTES Y_1.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y__2.

The scenario consists mostly of related events.

Y_3.

Each event description consists of:

the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

Y_4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y__5.

The events are valid with regard to physics and thermodynamics.

Y_6.

Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

_N/A_7.

If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

Y_8.

The simulator modeling is not altered.

Y_9.

The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario.

.Y__10.

Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section D.4 of ES301 Y_11.

All individual operator competencies can be evaluated, as verified using form ES-301-6.

Y__12.

Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios).

Y__13.

Level of difficulty is appropriate to support licensing decisions for each crew position.

Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Lesson

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01.

Total Malfunctions (TM) - Include EM's-5 to 8 required Total: 8 Loss of 125 V DC Bus 4, Loss of Instrument Air, VCT Level Transmitter Failure, Service Air Compressor Trip, SGTR, Rx Fails to Trip from MB 4 & 7, ESF System (FWI)

Fails to Auto Actuate,S/G A Atmospheric Dump Valve Fails Open

02.

Malfs after EOP entry (EM's)- 1 to 2 required Total: 2 ESF System (FWI) Fails to Auto Actuate,S/G A Atmospheric Dump Valve Fails Open

03. Abnormal Events (AE)-2 to 4 required Total: 4 Loss of 125 V DC Bus 4, Loss of Instrument Air, Rx Fails to Trip from MB 4 & 7, ESF System (FWI) Fails to Auto Actuate

04.

Major Transients (MT)-1 to 2 required Total: 2 Rx Fails to Trip from MB 4 & 7, SGTR

05.

EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 2 E-0, Reactor Trip or Safety Injection, E-3, Steam Generator Tube Rupture "06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 0 2 required None

07.

Critical Task (CT) - 2 to 3 required Total: 3 E-0-A:

Manually trip the reactor from the control room with either Main Board trip switch or by opening 32B and 32N supply breakers before completing step 1 of E-0.

E-O--OA Close feedwater isolation valves such that at least one valve is closed on each Steam Generator before the completion of step 9 of E-0 E-3-A:

Isolate feedwater flow into and steam flow from the ruptured SG prior to step 4 of E-3.

08. Approximate Scenario Run Time: 45 to 60 min. (One scenario may Total: 70 min approach 90 minutes)

09.

EOP run time:

Total: 30 min

10.

Technical Specifications are exercised during the scenario.

(Y/N)

Y._

NOTES: Reactivity Manipulation:Increase power per OP 3204, At Power Operations Section 8 Page 2 of 2

MILLSTONE NUCLEAR POWER STATION LOIT NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

Revision:

ID Number:

SGTR AT LOW POWER 0

2K1 NRC-002 This document is the property of Millstone Nuclear Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Nuclear Power Station.

A I

SIM EXAM 002

SUMMARY

OF CHANGES RE: NRC VALIDATION Added description of VCT level failure to the Exam Summary page..

Changed power increase from 3%/hr to 5%/hr throughout and added note from OP 3204, step 4.1, NOTE, to the Scenario Initial Conditions sheet, giving approval for the higher rate.

Added nomenclature for MP3 Battery Buses.

Added Tech Spec details.

Corrected editorial error (wrong REMOTE number).

Deleted critical task from step 14.a; not listed on ES-301-4; already had 3.

SIM EXAM 002 NOTE ON SGTR "TIMING" CRITICAL TASK The DBA SGTR "timing" critical task was not added to this simulator scenario because there are several delaying malfunctions prior to entering E-3 which tend to invalidate any time critical criteria.

In addition, the scenario already contains three critical tasks:

Manually trip the reactor Task # E A Close Feedwater Isolation valves (faulted FWI)

Task # E OA Isolate steam flow from ruptured S/G Task # E-3 -- A

SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1.

Cover Page

2.

Table of Contents

3.

Exam Overview

4.

Evaluation Guide

5.

Scenario Initial Conditions Sheet

6.

Scenario Validation Checklists

7.

Reference and Task Tracking

8.

Scenario Attributes Checklist Attachments NUTIMS Module Report AC",

REV'W

SECTION 3 EXAM OVERVIEW

Title:

SGTR AT LOW POWER ID Number:

2KlNRC-002 Revision: 0 Exam Brief:

1.

Plant is in mode 1, 50 % power, preparing to increase power per OP 3204, At Power Operations. The crew is directed to increase power to 75% at 5%/hr.

After the power ascension is clearly underway, the crew will experience a Loss of 125 Volt DC Bus 4 and will respond using AOP 3563, Loss of DC Bus Power. There are no Main Board actions other than verifying system response. The US should evaluate Tech Specs list in the AOP. If attempted, power cannot be restored to the Battery Bus.

After Tech Specs are addressed, VCT Level Transmitter LT-185 Fails High. The crew will respond using the ARP MB3A, 4-10, and may use AOP 3571.

Then a slow Loss of Instrument Air will occur. The loss will not be rapid nor will feedwater control immediately be lost. The crew should respond using AOP 3562, Loss of Instrument Air. Once dispatched, the PEO will discover an isolable filter leaking air and the SAS compressor tripped on hi-hi temperature. Upon receiving permission from the US to isolate the leak, the leak will significantly increase and a reactor trip will be required. When the reactor trip occurs, the PEO will successfully isolate the leak, and lAS pressure will return to normal.

The reactor will not manually trip from MB 4 or MB 7. Tripping Bus 32B and 32N will succeed in tripping the reactor[Critical Task]. The US should direct a PEO/NLO to locally trip the reactor trip breakers.

The plant trip will cause a steam generator tube rupture to occur on the "A" S/G.

Safety Injection should be manually actuated, if it has not already occurred, when directed at step 4 in E-0.. At step 9 of E-0 the crew will discover that Feed Water Isolation has Failed to Auto Actuate and must be manually aligned [Critical Task]. At step 25 a transition to E-3, Steam Generator Tube Rupture will be made. At the time of the transition the rupture S/G Atmospheric Dump Valve will fail open when the pressure transmitter, 3MSS-PT20A, fails high. Step 3.b of E-3 will direct that the isolation valve be closed (3MSS*MOV18A) [Critical Task].

2.

The SM should classify this event as a Alert - Charlie One due to Entry into E-3, "Steam Generator Tube Rupture" AND Reactor Coolant Leak > the Capacity of One Charging Pump (EAL RCB4 [LQ)

3.

Plant/Simulator differences that may affect the scenario are:

NONE

4.

Duration of Exam:

60 minutes

SECTION 4 EVALUATION GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 All Control Room Conduct, Operations and Communications shall be in accordance with MP-14-MMM.

"Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 62

Title:

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide.

Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.

As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1.

Place the simulator in FREEZE if possible.

2.

Announce to the Crew that there is a simulator problem.

3.

Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4.

Deal with the problem (reboot, call STSB, etc.)

5.

After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6.

Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7.

Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 62

SECTION 4

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Simulator Setup Instructions:

1.

HANG Exam Placards on the simulator doors.

2.

START the Sun Workstation.

a.

IF the Sun Workstation is running THEN go to SIM ACTIVE.

3.

PLACE Recorder Power to ON.

4.

VERIFY that the current approved training load is loaded.

5.

REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

6.

RESET to IC-22: TEMP IC 2K1 NRC-002

7.

ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

8.

PLACE Simulator to RUN.

9.

ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.

10.

RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.

11.

ENSURE Simulator fidelity items cleared.

a.

CHECK the STEP COUNTERS at correct position for plant conditions.

b.

PLACE 5

tiles under the DEMINS IN SERVICE lamacord label on MB6.

c.

PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d.

PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e.

CLEAR DCS alarms on MB7 and BOP console.

Section 4 Page 3 of 62

SECTiON 4

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

f.

VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.

g.

ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

1)

See laminated directions on clipboard in Sim booth.

12.

RESET Computer Terminals to At Power displays if 100% power IC.

a.

MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F1 32 (40-120), CHS-L112 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)

b.

MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL T412", (585-588)

c.

MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d.

BOP Console (AY5A), BOP Picture 26, Circ Water

e.

STA Console, (AY3), NSSS Picture 15, RCP Seals

13.

RESET Rad Monitor Screen to Status Grid.

14.

OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

15.

IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS."

16.

LOCK the Simulator Room front door.

Section 4 Page 4 of 62

SECTION 4

Title:

ID Number:

Time SGTR AT LOW POWER 2K1 NRC-002 IDA/Malf Initial Malfunctions MALF RP09A MALF RP09B MALF RP10A MALF RP10B MALF RP11L MALF SG01A Event Malfunctions MALF ED09D MALF CV10B MALF IA03 MALF IA01 MALF MS09A Lead Examiner:

Task Instructor Information/Activity Assign Expected Action PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K1NRC EXAM EQUIPMENT Reactor Trip Breaker Failure (MB4)

Reactor Trip Breaker Failure (MB7)

Train A Automatic Reactor Trip Failure Train B Automatic Reactor Trip Failure Feed Water Isolation (FWI) Fails to Actuate Steam Generator A Tube Rupture 50%

Revision: 0 Standard BT1 Loss of 125 Volt DC Bus (Battery 4)

VCT Level Instrument LT 185 Failure 100%

60 second ramp Instrument Air Header Leak 25%

60 second ramp Service Air Compressor Trip S/G A Atmospheric Steam Dump Valve Fails Open 100%

No ramp Refer to the "Briefing Script for the Operational Exam" and brief the crew.

Section 4 Page 5 of 62

(

(

SECTION 4

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T=0 EVENT 1: Increase Power OP 3204, AT POWER INSTRUCTIONS OP 3204 OPERATIONS, REV. 15 Step 4

[Reactivity Manipulation]

Load Increase OP 3204 Step 4.1 US

1. This section provides instructions to OP 3204 increase load from 25% to 100%

Step 4.1.

power following a plant startup or for NOTE partial load increases at power. If used for a partial load increase, the SM/US should determine, on a case by case basis, which steps apply for the planned increase.

2. The load increase rate should not OP 3204 exceed 3%/hour unless approved by Step 4.1 Reactor Engineering and the Unit Director/Duty Officer.

3. The optimum control rod withdrawal OP 3204 rate is 3 steps per hour.

Step 4.1 To ensure leak rate calculation OP 3204 compliance, PERFORM the following:

Step 4.1.1 Section 4 Page 6 of 62 j"

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activitv Task Assian Revision: 0 Assian

~Exnected ActionnSadr

a.

IF the duration of the planned power increase will preclude obtaining a valid RCS leakrate calculation within the required 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> T/S surveillance interval, Refer to SP3601 F.6, "Reactor Coolant System Water Inventory Measurement" and PERFORM a leak rate calculation.

b. IF the plant will not be in a stable condition when the RCS leakrate calculation becomes due, STOP the power increase while sufficient time remains to stabilize the plant for the calculation.

INITIATE load increase as follows:

a. INITIATE RCS boron dilution using one of the following:

"* Refer to OP 3304C, "Primary Makeup and Chemical Addition,"

and ALIGN for dilution.

Refer to OP 3304B, "Boron Thermal Regeneration System,"

and DILUTE the RCS using BTRS (ACB < 100 ppm).

OP 3204 Step 4.1.1. a OP 3204 Step 4.1.1.b OP 3204 Step 4.1.2 OP 3204 Step 4.1.2.a Section 4 Page 7 of 62

Title:

Us Expected Actinn Rt*nrh*rd

SEC1iUON 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activity Task Assian ExDected Action Standa rd

b. COORDINATE power increase with CONVEX.

c. WHEN Tavg begins to increase due to dilution, Refer to OP 3323A, "Main Turbine," and LOAD turbine at desired rate to desired power level while continuing with this procedure.

WHEN RCS boron concentration is being changed, PERFORM the following:

a. IF Tavg or rod control responds in an unexpected manner, STOP makeup in progress and DETERMINE cause.

b. ENERGIZE pressurizer heaters as necessary to equalize boron concentration between the pressurizer and RCS.

c. IF RCS boron concentration change exceeds 50 ppm, Refer to OP 3301 G, "Pressurizer Pressure Control," and INITIATE actions to equalize boron concentration while continuing with this procedure.

1. Maintaining AFD within target band is not required below 50% RTP or during RAOC operation but is recommended OP 3204 Step 4.1.2.c OP 3204 Step 4.1.2.c OP 3204 Step 4.1.3 OP 3204 Step 4.1.3.a OP.3204 Step 4.1.3.b OP 3204 Step 4.1.3.c OP 3204 Step 4.1.4 NOTE Section 4 Page 8 of 62

Title:

Revision: 0 us US Standard

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activity Task Assiqn Expected Action to maintain optimum reactor control.

2. It may be necessary to insert control rods to maintain AFD in the target band.

3. During load increases, AFD change is a function of control rod withdrawal (positive effect) and increased Th (negative effect).

Refer to the "Reactor Engineering Curve

& Data Book", "Axial Flux Difference Versus Thermal Power" and MAINTAIN AFD as follows:

a. IF power is greater than 50%, perform the following:

1) MAINTAIN AFD within specified RAOC limits.

2) IF AFD exceeds RAOC limits, Refer to TIS 3.2.1.1, "Power Distribution Limits, Axial Flux Difference," and DETERMINE action requirement.

b. IF AFD approaches the positive edge of the target band, PERFORM the following:

OP 3204 Step 4.1.4 OP 3204 Step 4.1.4.a OP 3204 Step 4.1.4.b

1) PLACE control rod bank SEL Section 4 Page 9 of 62

Title:

(.

Revision: 0 Standard US

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activity Task Assian Expected Ac~tion

-Qfnnl'4nrr switch in "MAN."

2) ADJUST dilution rate to maintain Tavg-Tref matched.

3) WHEN AFD decreases to the target value, PLACE control rod bank SEL switch in "AUTO," if desired.

c. IF AFD exceeds the positive edge of the target band, PERFORM the following:

OP 3204 Step 4.1.4.c

1) STOP the load increase.

2) INCREASE dilution rate.

3) WHEN AFD begins to decrease, CONTINUE load increase at a rate less than original rate.

d.

IF AFD can not be maintained within OP 4.1.4.d the target band OR exceeds the target band by more than 5%, NOTIFY Reactor Engineering.

Section 4 Page 10 of 62

Title:

(

Revision: 0

(

I=x n*_r.t*.d At.finn

• f*nH*rH

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Instructor Information/Activitv Task Assion Expec~ted Ar~tinn r

e. IF a partial load increase at power is being accomplished, PERFORM the following:

1) DILUTE as necessary during load increase to compensate for power defect.

2) BORATE to compensate for Xenon burnout and DILUTE as Xenon builds in to equilibrium concentration.

3) IF continuous power operation below 85% for longer than 14 days has occurred, REQUEST Reactor Engineering provide guidance for any power holds required for flux mapping during power ascension.

IF a power change exceeding 15% of RTP within a 1-hour period occurs, REQUEST Chemistry Department perform an isotopic analysis for Iodine between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the power change.

Changes in condensate demineralizer valve alignment may cause a condensate flow transient resulting in an unanticipated power increase.

OP 3204 Step 4.1.4e OP 3204 Step 4.1.5 OP3204 Step 4.1.6 CAUTION Section 4 Page 11 of 62

Title:

Time IDA/Malf US US Exn*cted A ctinn

_*f* nrl= rrl

S SECTIU)N 4 SGTR AT LOW POWER ID Number:

2KINRC-002 Time IDA/Malf Instructor Information/Activitv Task Assian Expected Action US OP 3204 Step 4.1.6 OP 3204 Step 4.1.7 Refer to OP 3319C, "Condensate Demineralizer Mixed Bed System," and PLACE condensate demineralizers in service as necessary to maintain the following:

"* Flow through in-service demineralizers between 1200 gpm and 3200 gpm.

"* Differential pressure less than 60 psi.

IF "AMSAC TROUBLE/BYPASS" (MB4C 6-8) is lit, REQUEST IC&E Department perform SP3446C1 1, "AMSAC Operability Test", if required while continuing with this procedure.

IF performing a startup following a turbine shutdown, PERFORM the following:

a. Refer To OP3323A, "Main Turbine,", "SJAE Backpressure Data," and ADJUST the in service stream jet air ejector intercondenser suction valve as necessary to maintain condenser backpressure as low as achievable in the 2.0 to 4.0 inches HgA operating band while continuing with this procedure.

b. Prior to exceeding 30% reactor power, OP 3204 Section 4 Page 12 of 62

(

Title:

Revision: 0 Exneced AtionStandard OP 3204 Step 4.1.8.c OP 3204 Step 4.1.8.a US Standard

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Instructor Information/Activitv Task InsrucorInfrmtio/Ativtv Assirm1 7ad

-J -

• ~~UV~4 I**%vflJBI

.Lc1AI4-I REQUEST Chemistry verify secondary chemistry, except dissolved oxygen, is in specification.

c. WHEN turbine load is at 295 MWe (approximately 33% reactor power),

STOP power increase and MAINTAIN turbine load between 290 and 300 MWe.

d. Refer ToOP3329, "Condenser Air Removal," and PLACE a second SJAE in service.

e. REQUEST Chemistry verify dissolved oxygen in specification.

f.

WHEN dissolved oxygen is in specification, INITIATE load increase as follows:

1) INITIATE RCS boron dilution using one of the following:

Refer To OP 3304C, "Primary Makeup and Chemical; Addition, " and ALIGN for dilution.

"* Refer To OP 3304B, "Boron Thermal Regeneration System," and DILUTE RCS Step 4.1.8.b OP 3204 Step 4.1.8.c OP 3204 Step 4.1.8.d OP 3204 Step 4.1.8.e OP 3204 Step 4.1.8.f Section 4 Page 13 of 62

(

Title:

Time IDA/Malf

(

l*v n*-r,4"*,rl A r,(.;,,*n 0 4.* *,.,I- _.J

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Instructor InformationlActivitv Task Assiain Fnrtd a"

01 IntutrIfr aio/ciivE

.e

-f~

Q--Cf

'.F~IA A,

using BTRS (ACB < 100 ppm)

2) COORDINATE power increase with CONVEX.

3) WHEN Tavg begins to increase due to dilution, Refer To OP 3323A, "Main Turbine," and LOAD turbine at desired rate to desired power level while continuing with this procedure.

WHEN generator load increases greater than 300 MWe, PLACE the "FW PUMPS P4 TRIP BYPASS" selector switch (MB5) in "NORMAL."

WHEN generator load is greater than 360 MWe AND sustained loads greater than 780MWe are anticipated, Refer To OP 3317, "Reheat and Moisture Separator,"

and SUPPLY steam to the reheaters by performing one of the following:

"* PLACE the MSR reheaters in service for automatic operation

"* Manually PLACE the MSR reheaters in service during power ascension (30%- 65%)

OP 3204 Step 4.1.9 OP 3204 Step 4.1.10 Section 4 Page 14 of 62

Title:

Time IDA/Malf US US I

ya FxnJanf*,tl Affirm

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Instructor Information/Activity Task Assian Fnr~t~

GilliGI Intuco

-nomtonAtvt Ex...

acted4..tfan EVENT 2: Loss of 125 V DC Bus 4 AOP 3563, Loss of DC Bus Power, Rev. 5 NOTE: Nomenclature for MP3 Battery Buses:

Bus 301A-1 Bus 301 B-1 Bus 301A-2 Bus 301 B-2 Bus 301C-1 Bus 301D-1 US US Battery I Battery 2 Battery 3 Battery 4 Battery 5 Battery 6 If DC Bus 301A-1, 301B-, 301 C-I, or 301 D-1 is the affected bus, the Rx must be manually tripped and the actions in E-0 performed. Att, A, B, E, or F respectively, of this procedure, provide additional guidance which may be used concurrently with E-0.

Perform the applicable actions based on abnormal MB Annunciators and Indications

"* Check Bus 301A-1 -ENERGIZED

"* Check Bus 301B-1-ENERGIZED

"* Check Bus 301A-2-ENERGIZED

"* Check Bus 301 B-2-ENERGIZED

"* Check Bus 301C-l-ENERGIZED

"* Check Bus 301 D-1-ENERGIZED Section 4 Page 15 of 62

Title:

Time IDA/Malf MALF ED09D T= Reactivity manipulation complete and Examiner's Cue.

AOP 3563 Step 1 NOTE AOP 3563 Step 1 I= xnl=P*t*tl Ar'tirtrt Qf A

Ar

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activitv Task Assian Asio xpected Arcti-n

-Qt!nrInrI Use Att D Proceed to Step 2 US Verify VIAC-4 is energized from inverter 4 or the alternate power supply.

US/BOP Restore normal DC power alignment

/PEO using OP 3345C, 125 Volt DC.

[Tech Specs]

3.8.2.1 Action b 3.8.3.1 Action c.

US Refer to the following technical specifications for required actions:

AOP 3563 Step 1 RNO AOP 3563 Step la RNO AOP 3563 Att.D step I AOP 3563 Att.D step 2 AOP 3563 Att. D step 3

NOTE: If called, Electrical Maintenance reports a bus fault on Battery 4.

3.8.2.1 D.C. Sources Modes 1-4 3.8.2.2 D.C. Sources modes 5 and 6

3.8.3.1 Onsite Power Distribution Modes 1-4 3.8.3.2 Onsite Power Distribution Modes 5 and 6 Continue with normal plant evolutions using applicable plant procedures US AOP 3563 step 2 Section 4 Page 16 of 62 (i

Title:

Revision: 0

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I*xnn*t*rl A*tinn

SECTION 4 SGTR AT LOW POWER ID Number:

Time 2K1NRC-002 IDA/Malf Instructor Information/Activitv Task Assinn 1h.~~~f %J I-I

,%ruil Revision: 0 T= Tech Specs addressed in AOP 3564 and Examiner's Cue MALF

CV1OB, 100%,60 sec ramp EVENT 3: VCT Level Transmitter Fails High AUTOMATIC FUNCTIONS Us US Us US IF VCT level is high, 3CHS*LCV1 12A, VCT letdown divert, fully diverts to boron recovery tanks, (GWS).

IF VCT level is low, 3CHS*AOV71, "VCT/DEGASIFIER," diverts to VCT.

If either VCT level indicator fails to respond to decreasing VCT level, automatic shift to RWST is disabled.

[Commitment 1.1.1]

IF 3CHS-LT185 and 3CHS-LT1 12, indicate less than 4.4%, the following occur:

3CHS*LCV112D and 3CHS*LCV112E, charging pump suction valves from RWST, open.

3CHS*LCV112B and 3CHS*LCV1 12C, VCT outlet 3353.MB3A 4-10 Step 1 3353. M B3A 4-10 Step 2 3353. M B3A 4-10 Step 3 CAUTION 3353.MB3A 4-10 Step 3 3353.MB3A 4-10 Step 3.1 3353.MB3A 4-10 Step 3.2 Section 4 Page 17 of 62

Title:

(

• Y nlarf,",* A ¢*';^n

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Instructor Information/Activitv Task ss~ian ry~~gr Ap" aln

~~~~

~

~

0 5.-

JAII~

CORRECTIVE ACTIONS RO isolation valves, close.

CHECK the following to confirm alarm:

3353.MB3A 4-10 Step 1 3CHS-LI 185, VCT level (MB3)

CHS-L112, VCT level computer point IF 3CHS-LT185 is failed high, PERFORM the following:

PLACE 3CHS-LCV1 12A, VCT letdown divert (MB3), in "VCT".

1. Removing "NAL card" allows automatic shift to RWST when 3CHS-LT1 12 indicates VCT LO-LO level.

2. "VCT LEVEL HI/LO" (MB3A 4-10) locks in on low level.

REQUEST Instrument and Control Department remove "NAL card" 3CHS-LB-185A - B (RPS-RAKGP4) to simulate VCT LO-LO level.

IF VCT level is high, PLACE 3CHS*LCV1 12A, VCT letdown divert, in "GWS" to restore VCT 3353.MB3A 4-10 Step 5 3353.MB3A 4-10 Step 5.1 3353.MB3A 4-10 Step 5.2 NOTE 3353.MB3A 4-10 Step 5.2 3353.MB3A 4-10 Step 5.3 Section 4 Page 18 of 62

Title:

Time IDA/Malf C

Revision: 0 US RO US US RO = as necessary F::yr ekr-farl d -f"i~n

SECTION 4

Title:

ID Number:

Time SGTR AT LOW POWER 2K1 NRC-002 IDA/Malf Instru4ctor Information/Activity Task Assion Expected Action level 41 to 54%.

Revision: 0 Standard Section 4 Page 19 of 62 C

(

SEC~iUN 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activity Task Assign Expected Action RO RO VERIFY 3CHS*LCV1 12A, VCT letdown divert, in "AUTO".

IF VCT level is high, PERFORM the following:

IF VCT makeup is in progress, STOP VCT makeup.

CHECK 3CHS-LK1 85, VCT level control, controlling 3CHS*1 12A, VCT letdown divert, in full divert (0 output), (MB3).

IF 3CHS*1 12A, VCT letdown divert, not in full divert, PLACE 3CHS*LCV1 12A, VCT letdown divert, in "GWS" to restore VCT level 41 to 54%.

WHEN VCT level is 41 to 54%,

PLACE 3CHS*LCV1 12A, VCT letdown divert, in "AUTO," and MAINTAIN VCT level 41 to 54%

with 3CHS-LK185, VCT level control, in "MANUAL".

IF 3CHS-LK185, VCT level control, does not control 3CHS-LCV1 12A, VCT letdown divert, in "AUTO" or "MANUAL," CYCLE (1

Title:

Revision: 0 3353.MB3A 4-10 Step 6 3353.MB3A 4-10 Step 7 3353.MB3A 4-10 Step 7.1 3353.MB3A 4-10 Step 7.2 3353.MB3A 4-10 Step 7.3 3353.MB3A 4-10 Step 7.4 3353.MB3A 4-10 Step 7.5 Section 4 Page 20 of 62 Standard

SECTIUN 4 SGTR AT LOW POWER ID Number:

2KINRC-002 Time IDA/Malf Instructor Information/Activity Task Assian AsinExnected Action 5St~nnrbrd 3CHS*LCV1 12A, VCT letdown divert (MB3), to maintain VCT level 41 to 54%.

IF VCT level is greater than 4.4.% AND less than 15.7%, PERFORM the following:

VERIFY makeup control mode selector in "AUTO".

VERIFY makeup control switch in "START".

IF auto makeup not in progress, Refer To OP 3304C, "Primary makeup and Chemical Addition,"

and PERFORM manual makeup to restore VCT level 41 to 54%.

SEND Operator to check 3CHS*AOV71, "VCT/DEGASIFIER," in "OPEN TO VCT" (GWS).

If VCT level cannot be maintained, the Operator shall manually maintain VCT level or shift charging pump suction to RWST. [Commitment 1.1.1]

IF VCT level is less than 4.4% OR can not be maintained manually, PERFORM 3353.MB3A 4-10 Step 8 3353.MB3A 4-10 Step 8.1 3353.MB3A 4-10 Step 8.2 3353.MB3A 4-10 Step 8.3 3353.MB3A 4-10 Step 8.4 3353.MB3A 4-10 Step 9 CAUTION 3353.MB3A 4-10 Step 9 Section 4 Page 21 of 62

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Title:

Revision: 0 RO US US Exnected Action

• t* nd* rrl

SECTION 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activitv Task Assian Expected Ac~tion the following to shift charging pump suction to RWST:

OPEN 3CHS*LCV112D and 3CHS*LCV112E, charging pump suction from RWST, (MB3).

CLOSE 3CHS*LCV112B and 3CHS*LCV1 12C, VCT outlet isolation valves, (MB3).

IF VCT level is off - scale low, REQUEST engineering evaluate the potential for gas binding the charging pumps (SOER 97-01).

MONITOR charging pump discharge pressure, flow and amps for indication of gas binding.

Go To OP 3204, "At Power Operation," and COMMENCE plant shutdown.

WHEN VCT level control repair is complete, REQUEST Instrument and Control Department verify "NAL card" 3CHS*LB - 11 2A - B and "NAL card" 3CHS*LB - 185A - B installed.

3353.MB3A 4-10 Step 9.1 3353.MB3A 4-10 Step 9.2 3353.MB3A 4-10 Step 9.3 3353.MB3A 4-10 Step 9.4 3353.MB3A 4-10 Step 9.5 3353.MB3A 4-10 Step 10 Section 4 Page 22 of 62

!K

Title:

Revision: 0 Exneced Acion tandard US Rtnnd*rd

SECI ION 4 SGTR AT LOW POWER ID Number:

Time 2K1 NRC-002 IDA/Malf Instructor Information/Activitv Task Assian Exnected Action

.qtfanrl2nri T= VCT Level Failure addressed and Examiner's Cue MALF

IA03, 25%, 60 sec ramp IA01 EVENT 4: Loss of Instrument Air NOTE: Manipulate MALF severity to maintain IAS pressure above 70 psig with 2 lAS compressors running.

AOP 3562, Loss of Instrument Air, Rev 4 CREW RO NOTE: The crew should implement this step when air pressure decreases sufficiently.

Succeed T+5 minutes after being dispatched and after informing Control Room. REMOVE MALF IA03.

US RO/

CREW US The actions specified in this procedure may be performed concurrently with E 0, Reactor Trip or Safety Injection.

Verify Plant Status.

Check instrument air pressure rapidly decreasing OR loss of feedwater control.

Proceed to Step 2 and, IF instrument air pressure decreases rapidly OR feedwater control is lost, THEN TRIP the reactor and Go to E-0, Reactor Trip or Safety Injection.

TRIP the reactor and Go to E-0, Reactor Trip or Safety Injection.

Check Instrument Air System Alignment.

Section 4 Page 23 of 62

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Title:

Revision: 0 AOP 3562 Step 1 NOTE AOP 3562 Step 1 AOP 3562 Step l.a AOP 3562 Step 1.a RNO AOP 3562 Step 1.b AOP 3562 Step 2 Exnected Actinn

.qfnnH*rH

SECI ioN 4 SGTR AT LOW POWER ID Number:

2K1NRC-002 Task Assiann A

Od I-v

-rfr At,#,U d

RO PEO RO NOTE: As PEO, perform local checks.

See next page.

US US US RO RO RO Verify both instrument air compressors

- RUNNING.

Locally Place both instrument air compressor control switches to CS (continuous service).

Check instrument air pressure STABLE OR INCREASING.

Perform the following:

1)

Using Attachment A, locally Start air compressors and Perform filter and dryer checks.

2)

Proceed to Step 2.d.

Proceed to Step 12.

Check for air leakage in Ctmt:

1)

CLOSE instrument air Ctmt isolation valve (31AS*MOV72)

2)

Check instrument air pressure STABLE OR INCREASING.

OPEN instrument air Ctmt isolation valve (31AS*MOV72) and Proceed to Step 2e.

AOP 3562 Step 2.a.

AOP 3562 Step 2.a RNO AOP 3562 Step 2.b AOP 3562 Step 2.b RNO AOP 3562 Step 2.c AOP 3562 Step 2.d AOP 3562 Step 2.d. 1 AOP 3562 Step 2.d.d AOP 3562 Step 2.d.2 RNO Section 4 Page 24 of 62

Title:

Time IDA/Malf Instructor Information/Activitv Revision: 0 I::: v n*r t,',rl A rti,,,,n

(

EVALUATION GUIDE SGTR AT LOW POWER ID Number:

Time 2K1 NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions US US T= +2min of order MODIFY MALF IA03 to 60%

NOTE: When reporting, PEO discovers the body of the in-service filter housing cracked and leaking air.

Filter can be isolated and the standby filter placed in service.

Service Air compressor has tripped on hi-hi temperature.

WHEN given the order to isolate filter MODIFY malfunction. After reactor has tripped, remove malfunction and report that leak has been isolated.

US BOP

3)

Proceed to Step 3.

Using OP 3332A, "Instrument Air System," Start the shutdown instrument air compressor(s), if desired Dispatch personnel to search for air leaks by performing walk-downs of the following locations:

US AOP 3562 Step 2.d.3 AOP 3562 Step 2.e AOP 3562 Step 2.f Turbine Building Auxiliary Building Intake Structure ESF Building Control and Service Building Waste Disposal Building Fuel Building Verify TD AFW Pump Steam Supply Isolation Valves - CLOSED.

Throttle auxiliary feed flow as necessary.

AOP 3562 Step 3 AOP 3562 Step 3 RNO Section 4 Page 25 of 62

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Title:

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Revision: 0 Standard

EVALUATION GUIDE

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US/ RO Verify Letdown In Service AOP 3562 Check letdown isolation valves -

Step 4 OPEN

"* Check letdown orifice isolation valves - AT LEAST ONE OPEN RO Perform the following:

AOP 3562

a.

CLOSE charging header isolation Step 4 RNO valve (3CHS*MV8106).

b.

CLOSE letdown orifice isolation valves.

c.

If desired, using OP 3304A, "Charging and Letdown," establish reactor vessel head vent letdown to the PRT.

The High Radiation Area key is AOP 3562 required for local access to charging Step 5 pump A cubicle.

NOTE US/ RO Verify Seal Injection Flow -

AOP 3562 BETWEEN 8 and 13 gpm.

Step 5 Section 4 Page 26 of 62

I EVALUAl ION GUIDE SGTR AT LOW POWER 2K1 NRC-002 Instructor Information/Activity Task Assign Expected Actions Perform the following:

a.

Locally throttle Open the appropriate charging pump bypass valve.

For charging pump A 3CHS*V272 For charging pump B 3CHS*V270 For charging pump C 3CHS*V271

b.

Locally Close charging RCP seal isolation valve (3CHS*V273)

US/ RO Verify Train A and B Chilled Water CTMT Header Isolation Valves OPEN AOP 3562 Step 5 RNO AOP 3562 Step 6 Check inlet valves 3CDS*CTV38A 3CDS*CT91A 3CDS*CT38B 3CDS*CTV91 B Check outlet valves 3CDS*CTV39A 3CDS*CTV40A 3CDS*CTV39B 3CDS*CTV40B Section 4 Page 27 of 62

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Title:

ID Number:

Time IDA/Malf RO Revision: 0 Standard

(

Title:

SGTR AT LOW POWER ID Number:

2KINRC-002 Time IDA/Malf EVALUA I ON GUIDE Instructor Information/Activity Task AssiQn EXoected Actions Standaird RO OPEN the Train A and Train B RPCCW supply and return isolation valves to chilled water.

All condenser temperature and level instruments/indicators are pneumatic and do not provide accurate indication on a loss of instrument air.

US/ BOP Monitor Condenser Hotwell Level NORMAL PEO Locally Close normal makeup isolation valve (3CNS-V2).

US/ RO Monitor VCT Level - NORMAL.

RO Perform the following:

a.

OPEN RWST to charging isolation valves.

b.

CLOSE VCT to charging isolation valves.

Control RCS Pressure.

Energize PZR heaters or use normal spray valves as necessary.

AOP 3562 Step 6 RNO AOP 3562 Step 7 CAUTION AOP 3562 Step 7 AOP 3562 Step 7 RNO AOP 3562 Step 8 AOP 3562 Step 8 RNO AOP 3562 Step 9 AOP 3562 Step 9.a Section 4 Page 28 of 62 Revision: 0 US RO Standard

EVALUATION GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 Instructor Information/Activity Task Assign Expected Actions Use one PZR PORV to depressurize if necessary.

Traveling screen differential pressure instruments/indicators are pneumatic and do not provide accurate indication on a loss of instrument air.

Traveling screen differential pressure circulating water pump trip relays are pneumatic and will not operate to trip the pump is if the situation requires.

US/ PEO Increase Surveillance of Intake Structures Locally Place control switches for traveling screens to SLOW.

AOP 3562 Step 9.a RNO AOP 3562 Step 10 CAUTION AOP 3562 Step 10 Verify RHR Alignment Check RHR Train A or B - IN COOLDOWN Mode Proceed to Step 12.

AOP 3562 Step 11 AOP 3562 Step 11.a AOP 3562 Step 11.a RNO Section 4 Page 29 of 62

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Title:

Time IDA/Malf

(

RO Revision: 0 Standard RO/

BOP

SGTR AT LOW POWER f

ID Number:

2K1NRC-002 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Revision: 0 Standard Standard NOTE: The crew should implement this step when air pressure decreases sufficiently.

PEO: Succeed in isolating leak when the crew trips the reactor and inform Control Room.

REMOVE MALF IA03.

US RO/

CREW Proceed to Step 2 and, IF instrument air pressure decreases rapidly OR feedwater control is lost, THEN TRIP the reactor and Go to E-0, Reactor Trip or Safety Injection.

TRIP the reactor and Go to E-0, Reactor Trip or Safety Injection.

T= Reactor Trip MALF (initial)

SG01A on BT1 EVENT 5: SGTR NOTE:

US should go to "Master Silence" before ordering reactor trip.

E-0 (Rev. 20) STEPS RO Crew TRIP the reactor Go to E-0, Reactor Trip or Safety Injection.

"* Foldout page must be open ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 105 R/hr in containment.

Section 4 Page 30 of 62 EVALUATION GUIDE

Title:

k AOP 3562 Step 1.a RNO (REPEAT)

AOP 3562 Step 1.b (REPEAT)

E-O, Step 1, NOTE Expected Actions

EVALUAI ION GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assigcn Expected Actions

• The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

EVENT 6: Reactor Fails to Trip from MB4 or MB7 RO TRIP the reactor.

E-0, Step 1, RNO

[Critical Task]

NOTE: Necessary to implement this RNO to trip the reactor NOTE: Necessary to implement this RNO to complete tripping the reactor.

When dispatched as PEO wait 2 minutes (ensure the crew has completed step 9 to avoid complicating the FWI restoration)

THEN BOP US IF reactor will NOT trip, THEN TRIP Bus 32B and 32N.

Dispatch an operator to locally TRIP the reactor trip and bypass breakers.

E-0, Step 1.a, RNO E-0, Step 1.b, RNO MALF RP02A and RP02B RO Verify Reactor Trip E-0, Step 1

"* Check reactor trip and bypass breakers - OPEN Check rod bottom lights - LIT Section 4 Page 31 of 62

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Title:

Time

(

MALF (initial)

RP09A RP09B Revision: 0 Standard

SGTR AT LOW POWER EVALUAi iON GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activitv Task Assian E~efir ntne-(fnnrf4r Check neutron flux DECREASING Verify Turbine Trip Check all turbine stop valves CLOSED Verify Power to AC Emergency Busses Check busses 34C and 34D - AT LEAST ONE ENERGIZED Check busses 34C and 34D - BOTH ENERGIZED Check If SI Is Actuated Verify Safety Injection Actuation annunciator - LIT Check if SI is required CTMT pressure GREATER THAN 18 psia OR RCS pressure LESS THAN 1890 psia OR E-0, Step 2 E-0, Step 2.a E-0, Step 3 E-0, Step 3.a E-0, Step 3.b E-0, Step 4 EOP 35 E-0, Step 4.a E-0, Step 4, RNO Section 4 Page 32 of 62

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Title:

Time Revision: 0 BOP BOP BOP BOP US RO US FYn*_r.f*=rl Anfinnc

.*f* nrla rrl

SGTR AT LOW POWER EVALUAI ION GUIDE ID Number:

2K1NRC-002 IDA/Malf Intuco Ipce ActionsioStandardx Instructor InfoLmation/Atanaar A ~ ~ u~C Task A00inn Revision: 0 NOTE: SI will ultimately be required, most likely on PZR Level RO RO RO BOP PZR level LESS THAN 16%

OR RCS subcooling LESS THAN 320F OR SG pressure LESS THAN 660 psig IF SI is required, THEN initiate SI.

Verify Service Water Pumps - AT LEAST ONE PER TRAIN RUNNING Verify Two RPCCW Pumps - ONE PER TRAIN RUNNING Verify ECCS Pumps Running

"* Check SI pumps - RUNNING

"* Check RHR pumps - RUNNING

"* Check two charging pumps RUNNING Verify AFW Pumps Running Check MD pumps - RUNNING E-0, Step 5 E-0, Step 6 E-0, Step 7 E-0, Step 8 E-0, Step 8.a Section 4 Page 33 of 62

(

Title:

Time

(

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 t(

( [

EVALUAlI ION GUIDE Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard START pump(s)

E-0, Step 8.a, RNO Check turbine - driven pump -

E-0, RUNNING, IF NECESSARY Step 8.b OPEN steam supply valves.

E-0, Step 8.b, RNO EVENT 7: FWI does not actuate

[Critical Task] Close feedwater isolation valves such that at least one valve is closed on each Steam Generator before the completion of step 9 of E-0.

NOTE: FWI Pumps has failed to actuate.

BOP Verify FW Isolation Check SG feed regulating valves CLOSED Check SG feed regulating bypass valves - CLOSED Check FW isolation trip valves CLOSED Check MD FW pump - STOPPED Check TD FW pumps - TRIPPED Section 4 Page 34 of 62 E-0, Step 9

(

EVALUATION GUIDE SGTR AT LOW POWER ID Number:

Time 2K1 NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions

"* Check SG blowdown isolation valves - CLOSED

"* Check SG blowdown sample isolation valves - CLOSED

"* Check SG chemical feed isolation valves - CLOSED Check If Main Steam Lines Should Be Isolated Check Ctmt pressure GREATER THAN 18 psia OR Any SG pressure LESS THAN 660 psig Proceed to Step 11 Check if CDA Required Check Ctmt pressure is GREATER THAN 23 psia OR Ctmt spray is initiated E-0, Step 10 E-0, Step 10.a E-0, Step 10.a, RNO E-0, Step 11 E-0, Step 11.a Section 4 Page 35 of 62

(

Title:

(

Revision: 0 Standard BOP RO

SGTR AT LOW POWER EVALUATION GUIDE ID Number:

Time 2K1 NRC-002 IDA/Malf Instructor Information/Activitv Revision: 0 Task Assian "C

US RO RO RO RO Proceed to Step 12.

Verify CIA Check ESF Group 2 status columns 2 through 10 - LIT Verify Proper ESF Status Panel Indication

"* Verify ESF Group I lights - OFF

"* Verify ESF Group 2 lights - LIT

"* IF Main Steam Line Isolation has occurred, THEN verify ESF Group 3 lights - LIT

"* IF CDA has occurred, THEN verify ESF Group 4 lights - LIT Determine If ADVERSE CTMT Conditions Exist

"* Ctmt temperature GREATER THAN 180°F OR

"* Ctmt radiation GREATER THAN 105 R/h,

(

Title:

(

E-0, Step1 1,a, RNO E-0, Step 13 E-0, Step 13.a E-0, Step 14 E-0, Step 15 Section 4 Page 36 of 62 I::,x'nAnfA¢l Anfinnc

_(*f"u n H,"* rH

(

(

EVALUAT ION GUIDE

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard CREW DO NOT use ADVERSE CTMT E-0, parameters.

Step 15, RNO CREW To provide adequate ECCS flow, RCS E-0, subcooling and PZR level should be Step 16, monitored to ensure that the charging CAUTION pump is manually restarted if RCS subcooling based on core exit TCs decreases to LESS THAN 320F (115°F ADVERSE CTMT) or PZR level decreases to LESS THAN 16% (50%

ADVERSE CTMT).

CREW If offsite power is lost after SI reset, E-0, manual action to restart safeguards Step 16, equipment may be required.

CAUTION CREW DO NOT reset CDA if recirculation E-0, spray pumps are required and have not Step 16, automatically started.

CAUTION RO Verify ECCS Flow E-0, Step 16 Check charging pump flow indicator -

E-0, FLOW INDICATED Step 16.a RO Check RCS pressure - GREATER E-0, THAN 1650 psia (1950 psia ADVERSE Step 16.b CTMT)

Section 4 Page 37 of 62

.. _jvvtR iu Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Proceed to Step 16.i E-0, Step 16.b, RNO RO Check PORV block valves - OPEN E-0, Step 16.c RO OPEN energized block valves.

E-0, Step 16.c RNO RO VERIFY the following:

E-0, Step 16.d

1) Charging pumps - TWO RUNNING

2) RCS subcooling based on core exit TC's GREATER THAN 320F (1 15°F ADVERSE CTMT).

3) Secondary heat sink:

"* Total feed flow to SGs GREATER THAN 530 gpm OR NR level in at least one SG GREATER THAN 8% (42%

ADVERSE CTMT)

4) RCS pressure - STABLE OR INCREASING Section 4 Page 38 of 62 EVALUAM tON GUIDE

SGTR AT LOW POWER EVALUATION GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activitv CREW should perform a short brief and come out of "Master Silence" at the completion of Step 16.

US

5) PZR level - GREATER THAN 16%

(50% ADVERSE CTMT)

Proceed to Step 17.

E-0, Step 16.d RNO Verify Adequate Heat Sink Check NR level in at least one SG GREATER THAN 8% (42% ADVERSE CTMT)

Proceed to Step 17.d.

Control feed flow to maintain NR level BETWEEN 8% and 50% (42% and 50% ADVERSE CTMT)

Proceed to Step 18.

Verify Total AFW Flow - GREATER THAN 530 gpm Verify AFW Valve Alignment PROPER EMERGENCY ALIGNMENT Verify ECCS Valve Alignment PROPER EMERGENCY ALIGNMENT Check Plant Status E-0, Step 17 E-0, Step 17.a E-0, Step 17.a, RNO E-0, Step 17.b E-0, Step 17.c E-0, Step 17.d E-0, Step 18 E-0, Step 19 E-0, Step 20 Section 4 Page 39 of 62

(

Title:

Time (i

Task Assinn VCHC1 Revision: 0 BOP US BOP US BOP BOP RO US PV arn~-farl Anfinno

SGTR AT LOW POWER EVALUATION GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activitv Task Asinn vnrFr~-

%rip, V0 tnd Revision: 0 NOTE: When asked, REPORT that "all SLCRS doors indicate closed."

RO RO RO RO Verify SLCRS doors - CLOSED Check CBI annunciator - LIT Check if CBI is required

"* Ctmt pressure GREATER THAN 18 psia OR

"* Control Building radiation monitor in alarm OR SI manually actuated IF CBI required, THEN initiate CBI.

IF CBI is NOT required, THEN proceed to Step 21.

Check RCS Temperature E-0, Step 21 Verify RCS cold leg WR temperature BETWEEN 5501F and 560°F E-0, Step 21.a Section 4 Page 40 of 62

Title:

Time

(

E-0, Step 20.a E-0, Step 20.b E-0, Step 20.b, RNO RO US RO I:: v r*,"*t-,f,-, PI A,,-,H*,

(

(

EVALUAI ION GUIDE

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Perform the applicable action:

E-0, Step 21.a, RNO IF temperature is GREATER THAN 550°F AND 560-F, THEN

1) Dump steam to the condenser, if available OR Dump steam to atmosphere.

US

2) Proceed to Step 22.

"* IF the temperature is LESS THAN 5500, THEN proceed to Step 21c.

US Proceed to Step 22 E-0, Step 21.b BOP Maintain total feed flow BETWEEN 530 E-0, and 600 gpm until NR level is Step 21.c GREATER THAN 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric dump and E-0, dump bypass valves Step 21.d BOP Check the following valves - CLOSED E-0, Step 21.e

"* MSIVs

"* MSIV bypass valves Section 4 Page 41 of 62

\\

EVALU,-

iON GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions Perform the following:

Place both condenser steam dump interlock selector switches to OFF.

IF unexpected cooldown continues, THEN CLOSE the MSIVs and MSIV bypass valves.

Check PZR Valves Verify PORVs - CLOSED RO Verify normal PZR spray valves CLOSED RO Verify PZR safety valves - CLOSED CREW To prevent damage to the RCP seal(s),

seal injection flow should be maintained to all RCPs.

Check If RCPs Should Be Stopped Verify RCS pressure - LESS THAN 1500 psia (1800 psia ADVERSE CTMT)

E-0, Step 21.e, RNO E-0, Step 21.e.1, RNO E-0, Step 21.e.2, RNO E-0, Step 22 E-0, Step 22.a E-0, Step 22.b E-0, Step 22.c E-0, Step 23, CAUTION E-0, Step 23 E-0, Step 23.a Section 4 Page 42 of 62

Title:

Time

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Revision: 0 Standard US BOP BOP RO RO RO

EVALUX,.jN GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions Proceed to Step 24 RO Verify charging or SI pumps - AT LEAST ONE RUNNING US Proceed to Step 24 RO STOP all RCPs BOP/RO Check If SG Secondary Boundaries Are Intact Check pressure in all SGs

"* NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER

"* NO SG COMPLETELY DEPRESSURIZED Check If SG Tubes Are Intact Verify trend history and alarm status of radiation monitors Main steam line - NORMAL E-0, Step 23.a, RNO.

EOP 35 E-0, Step 23.b E-0, Step 23.b, RNO E-0, Step 23.c E-0, Step 24 E-0, Step 24.a E-0, Step 25 Section 4 Page 43 of 62

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Us Revision: 0 Standard BOP RO Standard

EVALUAI,.N GUIDE SGTR AT LOW POWER ID Number:

Time 2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions

"* Condenser air ejector - NORMAL

"* SG blowdown - NORMAL us Initiate monitoring of CSF Status Trees E-0, and Go to E-3, Steam Generator Tube Step 25.b, Rupture.

RNO EVENT 8: S/G Atmospheric Dump Valve Fails Open E-3, Steam Generator Tube Rupture, Rev. 16 US US RO BOP To prevent damage to the RCP seal(s), seal injection flow should be maintained to all RCPs.

Foldout page must be open Check If RCPs Should Be Stopped Verify RCS pressure - LESS THAN 1500 psia (1800 psia ADVERSE CTMT)

Proceed to step 2.

Identify Ruptured SGs E-3 Step 1 CAUTION E-3, Step 1, NOTE E-3, Step 1 E-3, Step 1.a E-3, Step 1.a, RNO E-3, Step 2 High radiation from any SG steam line as indicated by the trend history or alarm status Section 4 Page 44 of 62

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T= Entry into E-3 Revision: 0 MALF MS09A Standard

EVALUA*I.JN GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions OR US US

[Critical Task][ Isolate feedwater flow into and steam flow from the ruptured SG prior to step 4 of E-3.]

BOP

"* High radiation from any SG sample OR

"* Unexpected increase in any SG level Proceed to steps 5 through 12 and, WHEN the ruptured SGs identified, THEN Return to the CAUTION prior to step 3 and Perform steps 3 and 4.

If the TD AFW pump is the only available source for feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.

At least one SG must be maintained available for RCS cooldown.

Isolate Flow From Each Ruptured SG E-3, Step 2, RNO E-3, Step 3, CAUTION E-3, Step 3, CAUTION E-3, Step 3 Section 4 Page 45 of 62

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EVALUAI.JN GUIDE

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Verify each ruptured SG atmospheric E-3, Step dump valve controller - IN AUTO AT 3.a 1125 psig Perform the following:

E-3, Step Place the SG atmospheric dump valve 3.a, RNO controller in MANUAL.

Adjust the setpoint controller to 1125 psig.

Place the controller in AUTO.

Check each ruptured SG atmospheric E-3, dump valve - CLOSED Step 3.b WHEN E-3, Step 3.b, ruptured SG pressure is LESS RNO THAN 1125 psig.

THEN Verify the SG atmospheric dump valve is closed IF the atmospheric dump valve is NOT

closed, THEN Place the controller in MANUAL and Close.

Section 4 Page 46 of 62

EVALUA). 1jN GUIDE(

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard IF the atmospheric dump valve can NOT be closed, THEN CLOSE the atmospheric dump isolation valve.

3MSS*MOV18A 3MSS*MOVl 8B 3MSS*MOV1 8C 3MSS*MOV18D IF the ruptured SG atmospheric dump isolation valve can NOT be closed, THEN locally Close the atmospheric dump isolation valve.

Check each ruptured SG atmospheric E-3, dump bypass valve - CLOSED.

Step 3.c CLOSE each ruptured SG steam E-3, Step supply isolation valve to TD AFW 3.d pump.

Verify each ruptured SG blowdown E-3, sample isolation valve - CLOSED Step 3.e Section 4 Page 47 of 62

EVALUAM 1,N GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions Verify each ruptured SG blowdown sample isolation valve - CLOSED CLOSE each ruptured SG MSIV and MSIV bypass valve.

CLOSE the main steam line drains upstream of the MSIVs and TD AFW pump for each ruptured SG as follows:

SGA 3DTM*AOV29A 3DTM*AOV61A 3DTM*AOB63A 3DTM*AOB64A If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless the SG is needed for RCS cooldown.

Check Ruptured SG Level E-3, Step 3.f E-3, Step 3.g E-3, Step 4, CAUTION E-3, step 4 Section 4 Page 48 of 62

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Time

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EVALUAi.JN GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assion EXDected Actions Standard Verify one of the following is satisfied:

"* Ruptured SG WR level - GREATER THAN 67% (95% ADVERSE CTMT)

OR

"* Ruptured SG NR level - GREATER THAN 8% (42% ADVERSE CTMT)

Perform the following:

1. Maintain feed flow to the ruptured SGs.

2. Proceed to CAUTION prior to Step 5 and WHEN WR level is GREATER THAN 67% (95% ADVERSE CTMT)

OR NR level is GREATER THAN 8%

(42% ADVERSE CTMT) THEN Stop feed flow to ruptured SG.

Stop feed flow to ruptured SGs.

If any PZR PORV opens because of high PZR pressure, Step 5.a should be repeated when pressure decreases to LESS THAN 2350 psia.

E-3, Step 4.a E-3, Step 4.a, RNO E-3, Step 4.b E-3, Step 5, CAUTION Section 4 Page 49 of 62

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SGTR AT LOW POWER VALUA'i,,N GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions RO E-3, step 5 E-3, Step 5.a E-3, Step 5.b E-3, Step 6 E-3, Step 6.a Check PZR PORVs And Block Valves Verify PORVs - CLOSED Verify PORV block valves - AT LEAST ONE OPEN Check If SG Secondary Boundaries Are Intact Check pressure in all SGs

"* NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER

"* NO SG COMPLETELY DEPRESSURIZED To aid in identifying previously undetected steam generator tube failures, the wide range SG level indication should be used if the narrow range level is off scale.

Check Intact SG Levels Verify NR level - GREATER THAN 8%

(42% ADVERSE CTMT)

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Revision: 0 Standard E-3, Step 7, NOTE E-3, step 7 E-3, Step 7.a Section 4 Page 50 of 62 BOP US Standard

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EVALUA'I.jN GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assian AsinExnected Actions Stnndrdnr Maintain total feed flow GREATER THAN 530 gpm until NR level is GREATER THAN 8% (42% ADVERSE CTMT) in at least one SG.

Control feed flow to maintain NR level between 8% and 50% (42% and 50%

ADVERSE CTMT)

IF NR level in any intact SG continues to increase in an uncontrolled manner, THEN Return to CAUTION prior to step 1.

If offsite power is lost after SI reset, manual action to restart safeguards equipment may be required.

DO NOT reset CDA if recirculation spray pumps are required and have not automatically started.

RESET SI And CDA RESET CIA And CIB Establish Instrument Air to Ctmt Check instrument air compressors - AT LEAST ONE RUNNING E-3, Step 7.a, RNO E-3, Step 7.b E-3, Step 7.b, RNO E-3, Step 8, CAUTION E-3, Step 8 E-3, Step 9 E-3, Step 10 E-3, Step 10.a Section 4 Page 51 of 62

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Time Revision: 0 US RO RO RO Rf*nd*rd

EVALUA',jN GUIDE SGTR AT LOW POWER ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions BOP NOTE: When requested:

EDR18: T+2 minutes EDR44: T+4 minutes and call in report OPEN instrument air Ctmt isolation valves Check Electrical Alignment Verify AC emergency busses ENERGIZED BY OFFSITE POWER Proceed to Step 11.g.

Locally perform the following to energize MCC 32-3T:

1. CLOSE the feeder breaker on 32T for MCC 32-3T (32T1 3-2) 2 Verify inverter 6 DC input ammeter indicating zero amps.

Verify busses 34A and 34B - BOTH ENERGIZED BY OFFSITE POWER.

Proceed to Step 11.1.

Check RCPs - ANY RUNNING.

E-3, Step 10.b E-3, Step 11 E-3, Step 11.a E-3, Step 11.b E-3, Step 11.g E-3, Step 11.h E-3, Step 11.i E-3, Step 11.1 Section 4 Page 52 of 62

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Revision: 0 Standard REMOTE EDR18 EDR44

SGTR AT LOW POWER E /

EVALUA'I,,uN GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assian AsinExpected Ac~tionsn.f~n~n Revision: 0 NOTE: Use the following remotes RCR 23, RCR 24, RCR 25, RCR 26 US RO Locally (SM Key Locker #34-38) on each RCP circuit breaker and potential transformer cubicle, use the setpoint switches' (43PP and 43PB) to select COLD for the over current trip setpoint (eight switches)

To provide adequate ECCS flow, RCS pressure should be monitored to ensure that the RHR pumps are manually restarted if pressure decreases to LESS THAN 300 psia (500 psia ADVERSE CTMT).

Check If RHR Pumps Should Be Stopped Verify RCS pressure - GREATER THAN 300 psia (500 psia ADVERSE CTMT)

STOP RHR pumps and Place in AUTO E-3, Step 11.m E-3, Step 12, CAUTION E-3, Step 12 E-3, Step 12.a E-3, Step 12.b Section 4 Page 53 of 62 (I

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Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US DO NOT proceed to step 13 if E-3, isolation of the ruptured SGs from Step 13, the intact SGs is NOT complete CAUTION unless a ruptured SG is needed for cooldown. Closing the MSIV and MSIV bypass valve for the ruptured SGs or for the intact SGs to be used for cooldown will satisfy the isolation requirement.

BOP Check Ruptured SGs Pressure -

E-3, Step 13 GREATER THAN 420 psig US To allow steam dump operation to E-3, continue during a controlled Step 14, cooldown, ensure the Low-Low NOTE Tavg interlock is bypassed at 553°F.

US Ensure Low Steam Line Pressure SI E-3, is blocked when pressurizer Step 14, pressure is LESS THAN 2000 psia.

NOTE US After the Low Steam Line Pressure E-3, SI signal is blocked, MSI will occur if Step 14, the high steam pressure rate NOTE setpoint is exceeded.

US The RCP trip criteria does not apply E-3, once a controlled cooldown is Step 14, initiated.

NOTE US/BOP Initiate RCS Cooldown E-3, Step 14 Section 4 Page 54 of 62

SGTR AT LOW POWER G

EVALUAI,,ON GUIDE ID Number:

2K1NRC-002 Instructor Information/Act ivitv Task Assinn 11+

0" 0

Insruto Ino

,-,nAcivt JQI AUQ A

US/BOP Determine required core exit temperature without interpolating (use lower pressure)

Lowest Ruptured SG Pressure (psig) 1285 538 498 1185 528 485 1085 516 470 985 504 453 Core Exit Temps (OF)

ADVERSE Dump steam to condenser from intact SGs at maximum rate.

Verify annunciator CONDENSER AVAIL FOR STM DUMP C-9 (MB4D 5

6) - LIT Establish no demand signal on steam pressure controller output Transfer condenser steam dumps to Steam Pressure Mode Place both condenser interlock selector switches - ON E-3, Step 14.b E-3, Step 14.b.1 E-3, Step 14.b.2 E-3, Step 14.b.3 E-3, Step 14.b.4 Section 4 Page 55 of 62

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Time IDA/Malf Revision: 0 E-3, Step 14.a PY Ae-fint-4 Apfirnt-Core ExitTemps (OF)

NNI*h/IAI

SGTR AT LOW POWER EVALUA'i.N GUIDE ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activitv Task Assian Expected Actions C~fnnr1nrrd Adjust steam pressure controller to dump steam to condenser at maximum rate.

Verify cores exit TCs - LESS THAN REQUIRED TEMPERATURE Stop RCS cooldown Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE DO NOT proceed to step 15 unless RCS cooldown is complete.

Check Ruptured SGs Pressure STABLE OR INCREASING Check RCS Subcooling Based on Core Exist TCs - GREATER THAN 52°F (135°F ADVERSE CTMT)

Depressurize RCS To Minimize Break Flow and Refill PZR Verify normal PZR spray - AVAILABLE E-3, Step 14.b.5 E-3, Step 14.c E-3, Step 14.d E-3, Step 14.e E-3, Step 15, CAUTION E-3, Step 15 E-3, Step 16 E-3, Step 17 E-3, Step 17.a Section 4 Page 56 of 62

Title:

Time Revision: 0 US BOP RO RO Exne.cf*.d Antinn.*

.*f* ntln rrl

EVALUAI.uN GUIDE

Title:

ID Number:

2K1NRC-002 IDA/Malf Instructor Information/Activity Task Assign Expected Actions Spray PZR with maximum available spray until one of the following occur:

" RCS pressure - LESS THAN ruptured SGs pressure AND PZR level is GREATER THAN 16% (50%

ADVERSE CTMT)

OR

" PZR level - GREATER THAN 73%

(63% ADVERSE CTMT)

OR

"* RCS subcooling based on core exit TCs - LESS THAN 32°F (1 15'F ADVERSE CTMT)

CLOSE spray valves Normal spray valves Auxiliary spray valve Proceed to CAUTION prior to step 20.

E-3, Step 17.b E-3, Step 17.c E-3, Step 17.c.1 E-3, Step 17.c.2 E-3, Step 17.d Section 4 Page 57 of 62 SGTR AT LOW POWER Time

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EVALUA,,jN GUIDE

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Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Voiding in the upper head region E-3, shall NOT preclude SI termination.

Step 20, S1 MUST be terminated when CAUTION termination criteria are satisfied to prevent overfilling of the ruptured SGs.

RO Check If ECCS Flow Should Be E-3, Step 20 Terminated Verify RCS subcooling based on core E-3, exit TCs - GREATER THAN 320F Step 20.a (1 15-F ADVERSE CTMT)

Verify secondary heat sink:

E-3,

"* Total feed flow to SGs - GREATER Step 20.b THAN 530 gpm AVAILABLE OR

". NR level in at least one intact SG GREATER THAN 8% (42%

ADVERSE CTMT)

RCS pressure - STABLE OR E-3, INCREASING Step 20.c PZR level - GREATER THAN 16%

E-3, (50% ADVERSE CTMT)

Step 20.d Section 4 Page 58 of 62

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Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 Time IDA/Malf Instructor Information/Activity Task Assign Expected Actions RO E-3, Step 21 STOP ECCS Pumps

"* STOP SI pumps and Place in AUTO

"* STOP" all but one charging pump and Place in AUTO Establish Normal Charging Flow Path Fully Open charging line flow control valve Verify charging header loop isolation valves (3CHS*AV8146 or 3CHS*AV8147) - ONE OPEN Re-position valves to establish only one open.

OPEN charging header isolation valves (3CHS*MV8106 and 3CHS*MV8105)

CLOSE the charging pump miniflow isolations to the RWST (3CHS*MV851 1A and 3CHS*MV851 1 B)

CLOSE both charging pump cold leg injection valves Align Charging Pump Recirculation

(

Revision: 0 Standard E-3, Step 22 E-3, Step 22.a E-3, Step 22.b E-3, Step 22.b, RNO E-3, Step 22.c E-3, Step 22.d E-3, Step 22.e E-3, Step 23 Section 4 Page 59 of 62 RO RO

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ID Number:

Time 2K1 NRC-002 IDA/Malf Instructor Information/Activity Task Assign Revision: 0 Standard Expected Actions RO RO OPEN the charging pump recirculation isolation valves 3CHS*MV81 11 A 3CHS*MV81 11 B 3CHS*MV8I 11 C 3CHS*MV81 10 Control Charging Flow to Maintain PZR Level Verify ECCS Flow Not Required Check RCS subcooling based on core exit TCs - GREATER THAN 32 0F (1 15-F ADVERSE CTMT)

Check PZR level - GREATER THAN 16% (50% ADVERSE CTMT)

E-3, Step 23.a E-3, Step 24 E-3, Step 25 E-3, Step 25.a E-3, Step 25.b TERMINATE UPON Verification That ECCS Flow is NOT Required (E-3, Step 25).

Section 4 Page 60 of 62 SGTR AT LOW POWER

SECTION 4 ID Number:

2K1NRC-002 Revision: 0 EVALUATION GUIDE I.

SUMMARY

The following Critical Tasks are covered in this exam:

TASK DESCRIPTION TASI4 Manually trip the reactor from E-0 the control room with either Main Board trip switch or by opening 32B and 32N supply breakers before completing step 1 of E-0.

Close feedwater isolation E-0--C valves such that at least one valve is closed on each Steam Generator before the completion of step 9 of E-0.

Isolate feedwater flow into and E-3--A steam flow from the ruptured SG prior to step 4 of E-3.

-A K/A >/= 3.0 001.A2.13 4.4/4.6

)A 059-K4.19 3.2/3.4 000-038 EA1.16 4.4/4.3 BASIS FOR SELECTION Failure to manually trip the reactor cause a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated condition. Additionally it constitutes an ".incorrect performance which necessitates the crew taking compensating action which complicates the event mitigation strategy...

Failure to close at least one feedwater isolation valve on each steam generator, under the postulated plant conditions and when it is possible to do so, constitutes a "demonstrated inability by the crew to recognize a failure/ incorrect auto actuation of an ESF system or component."

Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. Upon a loss of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that

"...necessitates the crew taking compensating action which complicates the event mitigation strategy......

Note: [*] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide.

Section 4 Page 61 of 62

SECTION 4

Title:

SGTR AT LOW POWER ID Number:

2K1NRC-002 EVALUATION GUIDE Revision: 0 Section 4 Page 62 of 62

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number:

2K1NRC-002 Reactor Power:

Operating History:

RCS Boron:

Core Burnup:

50%

1 day on line 970 ppm 8,000 MWD/MTU Condensate Demins:

Evolutions in Progress:

Major Equipment OOS:

5 demins in service Power Ascension Millstone Unit 2 is Offline for scheduled refueling outage NONE Crew Instructions:

The previous crew completed a CONVEX ordered downpower to 50% reactor power.

You are directed to increase power to 75% at 5%/hr lAW OP 3204, At Power Operations, beginning at step 4.1.15. Heater Drain pumps and MSR Drain Tank Pumps are still in service and the Reheater Drain Tank level control is on the normal level control valves. This load increase rate has been approved by Reactor Engineering and the Unit Director.

Plant/Simulator Differences:

Real Time and Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.

Auto-log terminals need to be refreshed after entry is made.

0 If not using the speed dial option on the phone system, the operator must dial either

1. 3333 or #3334 to reach the person/department they desire.

0 The following PPC programs do not function on the simulator:

Samarium Follow Xenon Follow Sequence of Events Section 7 Page 1 of 1 Revision: 0

SECTION 6 VALIDATION CHECKLIST SGTR AT LOW POWER

Title:

ID Number:

2KINRC-002 Revision: 0 Remote functions:

All remote functions contained in the guide are certified.

Malfunctions:

All malfunctions contained in the guide are certified.

Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02.

Simulator Operating Limits:

The simulator guide has been evaluated for operating limits and/or anomalous response.

Test Run:

The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected.

Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.)

Technical Reviewer Date Section 7 Page 1 of 1

SECTION 7 REFERENCE AND TASK TRACKING SGTR AT LOW POWER ID Number:

2K1NRC-002 Revision: 0 I.

References:

OP*3204 ARP*MB4A,4-10 AOP*3563 AOP*3562 EOP*E-0 EOP*E-1 EOP*E-3 EOP*ERGEXE EOP* Step -DOC EOP*ERG HP EPIP*FAP 001 NUREG*1021 rev 8 At Power Operations VCT Level Instrument Fails High Loss of 125 VDC Bus Loss of Instrument Air Reactor Trip or Safety Injection Loss of Reactor or Secondary Coolant SGTR Westinghouse Owners Group Executive Document MP3 step deviation Document Westinghouse Owners Group Background Document Event Assessment, Classification and Reportability Examiners Standards Section 7 Page 1 of 1

Title:

Initial Dynamic Simulator Scenario NUREG-1 021, Appendix D, Attachment 1 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Operators:

Revision: 0 I. Summary:

Scenario No: 2KINRC-004 Op-Test No:2K1LOIT Examiners:

Initial Conditions: IC-18; 100% power, middle of life, MP2 in a refueling outage Event Malf.

Event Event Description No:

No.

Type

• 1 None N(RO)

Shift Train B Service Water Pumps per OP 3326, Section 4.6 2

RX10A I(RO)

PZR Level Channel 459 Fails Low 3

FW01 C(BOP)

Loss of Condenser Vacuum NONE R(ALL)

Rapid Downpower; AOP 3575 4

MS03 C(ALL)

Small Steam Break in the Turbine Building ED06C C(BOP)

Loss of MCC 32-3T PCO1 C(ALL)

Loss of Plant Process Computer 5

ED05A M(ALL)

Loss of Voltage to Load Center 32A (Trip Initiator)

MS07B Uncontrolled Depressurization of All Steam Generators MS07D MS12A MS12C 5(rods RD16 C(RO)

Multiple Rods Stick Out on Reactor Trip 6

RP08A C(ALL)

MSLI Fails to Auto Actuate RP08B

• ( N) ormal (R) eactivity

( I ) nstrument (C) omponent (M) ajor Section 7 Pagel of2

Title:

Facility: Millstone 3 PWR:

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision: 0 Assessor:

Steve Jackson QUALITATIVE ATTRIBUTES Y_1.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y_2.

The scenario consists mostly of related events.

Y__3.

Each event description consists of:

the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

Y_4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y_5.

The events are valid with regard to physics and thermodynamics.

Y_6.

Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectiveS.

_N/A_7.

If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

_Y_8.

The simulator modeling is not altered.

Y_9.

The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario.

Y_10.

Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section D.4 of ES301 Y__11.

All individual operator competencies can be evaluated, as verified using form ES-301-6.

Y__12.

Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios).

Y_13.

Level of difficulty is appropriate to support licensing decisions for each crew position.

Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

Uncontrolled Depressurization of All S/G's ID Number:

2K1NRC-004 Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01.

Total Malfunctions (TM) - Include EM's-5 to 8 required Total: 8 PZR Level Channel Fails Low, Loss of Condenser Vacuum, Multiple Stuck Rods on the Trip, Steam Break in the Turbine Building, Loss of Bus 32A, Loss of Plant Process Computer (MCC 32-3T), Uncontrolled Depressurization of All S/G's, ESF System (MSLI) Fails to Auto Actuate

02.

Malf's after EOP entry (EM's)- 1 to 2 required Total: 2 ESF System (MSLI) Fails to Auto Actuate, Uncontrolled Depressurization of All S/G's

03. Abnormal Events (AE)-2 to 4 required Total: 3 AOP 3559, Loss of Condenser Vacuum, AOP 3566, Immediate Boration, AOP 3571, Instrument Failure Response

04.

Major Transients (MT)-1 to 2 required Total: 1 Uncontrolled Depressurization of All S/G's

05.

EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 2 E-0, Reactor Trip or Safety Injectiion, ECA-2.1, Uncontrolled Depressurization of All S/G's

06.

EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 1 2 required ECA-2.1, Uncontrolled Depressurization of All S/G's

07.

Critical Task (CT) - 2 to 3 required Total: 2 E-0-P:

Manually actuate Main Steamline Isolation or close MSIVs.

ECA-2.1 - A Control the AFW flow rate to at least 100 gpm per SG in order to minimize the RCS cooldown rate

08.

Approximate Scenario Run Time: 45 to 60 min. (One scenario may Total: 60 min approach 90 minutes)

09.

EOP run time:

Total: 30 min

10.

Technical Specifications are exercised during the scenario.

(Y/N)

Y NOTES:

Reactivity Manipulation:

Downpower required by Loss of Vacuum procedure Section 8 Page 2 of 2

MILLSTONE NUCLEAR POWER STATION JA LOIT NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

Revision:

ID Number:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 0

2K1 NRC-004 II This document is the property of Millstone Nuclear Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Nuclear Power Station.

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SIM EXAM 004

SUMMARY

OF CHANGES RE: NRC VALIDATION Deleted critical task on exercise brief page. This was left over from previous revision.

Clarified that US can delegate manual status trees on exercise brief page.

Deleted the Boolean trigger from malfunctions MS12A & MS12C; unnecessary.

Defined which Tech Specs apply in body of Sim Guide Added note that "US or designee must do manual status trees because the computer is NOT available" Added Simulator REMOTES to specify energizing accumulator isolation valves.

SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1.

Cover Page

2.

Table of Contents

3.

Exam Overview

4.

Evaluation Guide

5.

Scenario Initial Conditions Sheet

6.

Scenario Validation Checklists

7.

Reference and Task Tracking

8.

Scenario Attributes Checklist Attachments NUTIMS Module Report STOP TH I HK

11cý PFVIEW

SECTION 3 EXAM OVERVIEW

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision: 0

1.

Exercise brief:

The plant is at 100% power, MOL steady state operations with all control systems in automatic. The crew will initially shift Train B Service Water Pumps using OP 3326, Service Water Service, Section 4.6.

When that normal evolution is complete, the controlling channel of PZR Level, LT459, will fail low causing 3RCS*LCV459 to close (isolating letdown), de-energizing PZR heaters and increasing Charging flow to maximum. The crew will respond using AOP 3571, Instrument Failure Response, to stabilize the plant, trip bistables, address Tech Specs and restore normal plant conditions.

Once the crew has recovered from the PZR level instrument failure Main Condenser vacuum will begin to degrade from an unknown cause. Condenser backpressure will increase to greater than 5 inches Hg Absolute necessitating a plant shutdown using AOP 3575, Rapid Downpower, at 5%/min. At -70%

reactor power a small steam break will occur in the Turbine Bldg. which will ultimately lead to a Reactor Trip. On the Reactor Trip multiple rods will stick out of full insertion.

Corollary damage from this steam leak will include the loss of MCC 32-3T, the normal source of power to the Plant Process Computer. During the automatic shift of power supplies to Load Center 32P, the Plant Process Computer will be lost and will not return for this scenario.

Once the Loss of Load Center 32A causes the unit to trip, the "A" & "C" MSIVs will fail to close and the "B" and "D" SG low set safety valves will stick open. Main Steamline Isolation will fail to automatically actuate but can be manually actuated [Critical Task]. The crew should proceed through E-0 to E-2 to ECA-2.1. At the transition from E-0 to E-2 (E-0 step 23) the first opportunity to check status trees will occur. With the Plant Process Computer unavailable, the US should perform or designate manual status trees using input from the board operators.

While carrying out the SI termination steps in ECA-2.1, the "A" MSIV will close. The crew should complete the SI Termination steps, steps 12 through 28. The scenario will end when the crew elects to transition to E-2.

2.

The SM should classify this event as a Alert - Charlie One based on an Unisolable Steam Line Break Outside CTMT.(EAL BA2)

3.

Plant/Simulator differences that may affect the scenario are: NONE

4.

Duration of Exam:

60 minutes Section 3 Page 1 of 1

SECTION 4 EVALUATION GUIDE UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision: 0 All Control Room Conduct, Operations and Communications shall be in accordance COP 200.1,Conduct of Operations, and OP 3260, Unit 3 Conduct of Operations.

"Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 62

Title:

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide.

Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.

As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1.

Place the simulator in FREEZE if possible.

2.

Announce to the Crew that there is a simulator problem.

3.

Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4.

Deal with the problem (reboot, call STSB, etc.)

5.

After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6.

Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7.

Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 62

(

SECTION 4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

1.

START the Sun Workstation. IF the Sun Workstation is running THEN go to SIM ACTIVE.

2.

PLACE Recorder Power to ON.

3.

VERIFY that the current approved training load is loaded.

4.

REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

5.

RESET to IC18: Temp IC 2K1 NRC-004

6.

ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

7.

PLACE Simulator to RUN.

8.

ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.

9.

RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.

10.

ENSURE Simulator fidelity items cleared.

a.

CHECK the STEP COUNTERS at correct position for plant conditions.

b.

PLACE 4 tiles under the DEMINS IN SERVICE lamacord label on MB6.

c.

PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d.

PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e.

CLEAR DCS alarms on MB7 and BOP console.

f.

VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.

g.

ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

Section 4 Page 3 of 62 t"

(

C "SECTIUN 4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1 NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

1)

See laminated directions on clipboard in Sim booth.

11.

RESET Computer Terminals to At Power displays if 100% power IC.

a.

MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F1 32 (40-120), CHS-L112 (40-80), CHS-F121 (40-80), RCS L461 (40-80)

b.

MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-T412*, (585-588)

c.

MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d.

BOP Console (AY5A), BOP Picture 26, Circ Water

e.

STA Console, (AY3), NSSS Picture 15, RCP Seals

12.

RESET Rad Monitor Screen to Status Grid.

13.

OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

14.

IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS."

15.

LOCK the Simulator Room front door.

Section 4 Page 4 of 62

(

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assian

(.

Revision:

0 Expected Action PLACE THE FOLLOWING EQUIPMENT OOS:

Malfunctions RP08A RP08B MS07B MS07D MS12A MS12C RD16 Standard 2K1NRC Exam Equipment MSI Fails to Auto Actuate (Train A)

MSI Fails to Auto Actuate (Train B)

B S/G Low Setpoint Safety Stuck Open D S/G Low Setpoint Safety Stuck Open A S/G MSIV Stuck Open C S/G MSIV Stuck Open Multiple Rods Stick Out on Reactor Trip Event Malfunctions MALF RX1 OA PZR Level LT*459 Fails Low 0%

20 second ramp Lowering Condenser Vacuum

-100% (@ 5"HgAbs or begin downpower MODIFY to 50%)

Steam Leak Downstream of the MSIVs

-10%

30 second ramp MB08C, 1-10 MB08C, 1-11 VP1B, 1-8 ED06C PCO1 ED05A BATT 6 TROUBLE INV 6 TROUBLE TB VENT PANEL TROUBLE Loss of Voltage to MCC 32-3T Loss of Plant Process Computer Loss of Voltage to Load Center 32A Section 4 Page 5 of 62 Initial MALF MALF MALF MALF MALF MALF MALF Standard 100%

100%

MALF MALF BT1 BT1 FW01

MS03, ANN I/O ANN I/O ANN I/O MALF MALF MALF ON ON ON Exnected Action Standard

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity I

(

Task

,ssign Expected Action Revision:

0 Standard Lead Examiner:

Refer to the "Briefing Script for the Operational Exam" and brief the crew.

Section 4 Page 6 of 62

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assion

(

Revision:

0 Expected Action Standard EVENT 1: Shift SW Pumps US Shifting Train B Service Water Pumps OP 3326,Section 4.6, Shifting B Train Service Water Pumps, Rev 21 chg 2

[Normal Evolution]

RO NOTE: Both trains of Service Water are in service. As PEO, wait 2 to 3 minutes after direction and then report hypochlorite shifted.

VERIFY 3SWP*P3B, "SW BSTR PP",

stopped US After pump swap 3SWP*P3, MCC/RCA booster pump, may be inoperable until vented. Venting should be accomplished in a timely manner. Specific two hour time limits may apply as specified in T/S 3.8.1.1.d, "Electrical power Systems, A.C.

Sources."

US/PEO IF hypochlorite is being injected at the service water pump suction bell, Refer To OP 3328, "Hypochlorite," and PERFORM the appropriate actions:

IF both trains of service water are in service, SHIFT injection from two trains service water to one train service water.

IF only one train of service water is in service, SHUTDOWN the Hypochlorite System.

Section 4 Page 7 of 62 OP 3326 Step 4.6 OP 3326 Step 4.6.1 OP 3326 Step 4.6.2 CAUTION OP 3326 Step 4.6.2 Exoected ction Standard

Exam

Title:

ID Number:

Time SECTiON 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assian Revision:

0 Exoected Action Exoeced AtionStandard NOTE: All pre-start checks have been completed US US US RO IF shifting to 3SWP*P1 D, service water pump D, PERFORM the following; VERIFY 3SWP*P1 D, service water pump D, upper and lower motor bearing lube oil level approximately at 'STANDSTILL" mark.

To limit time Service Water System flow exceeds limits through the RPCCW heat exchanger, if the RPCCW heat exchanger is the major load on the Service Water System, there should be no delay in performing steps 4.6.3.b through 4.6.3.d.

START 3SWP*P1 D, service water pump D, and VERIFY the following valves open (MB1):

OP 3326 Step 4.6.3 OP 3326 Step 4.6.3.a OP 3326 Step 4.6.3.b CAUTION OP 3326 Step 4.6.3.b 3SWP*MOV102D, "DISD" 3SWP*MOV24D, "SWP MOV24D" IF hypochlorite is being injected into the service water pump discharge header, PERFORM the following:

1. Refer To OP 3328, "Hypochlorite," and ALTERNATE hypochlorite injection to 3SWP*P1 D, service water pump D.

OP 3326 Step 4.6.3.c Section 4 Page 8 of 62 US Standard

(f Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assian Revision:

0 Exoected Action Exneced AtionStandard

2. WHEN the hypochlorite injection isolation valve for the off-going pump is closed, PLACE hand switch for 3SWP*P1B, service water pump B, in "STOP" and HOLD (MB1).

3. Go To step 4.6.3.e.

WHEN service water header pressure stabilizes, PLACE 3SWP*P1B, service water pump B, in "AUTO" and RELEASE hand switch (MB1).

VERIFY 3SWP*MOV102B, "DIS B,"

closed (MB1).

VERIFY the following annunciators not lit:

"* MB1C 4-3, "SERVICE WTR PUMP DIS PRES LO"

"* MB1E 6-2, "SERVICE WATER SYSTEM" CHECK for positive indication of service water pump shaft gland seal leakoff.

WHEN approximately three minutes of pump operation have elapsed, VERIFY OP 3326 Step 4.6.3.e OP 3326 Step 4.6.3.f OP 3326 Step 4.6.3.g OP 3326 Step 4.6.3.h OP 3326 Step 4.6.3.i Section 4 Page 9 of 62 RO RO RO PEO RO Standard

(

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activitv Task Assian

(

Revision:

0 AsinExpected Actionntincrl REMOTE Lead/Follow switches US/PEO SWR02 3SWP*MOV24D, "SWP-MOV24D," closed (MB1).

At bus 34D, PLACE service water pump "LEAD/FOLLOW' switch to "B FOLLOW/D-LEAD" (34D 16-2).

Go To step 4.6.5.

NOTE: Planned end of normal evolution IF hypochlorite is to be injected at the service water pump suction bell, PERFORM the following:

Event 2: PZR Level Channel Fails Low T+ Shifting of Service Water Pumps complete RX10A 0%

20sec ramp NOTE: This will close 3CHS*LCV459, isolating letdown, de-energize PZR Heaters, and increase Charging flow to maximum.

Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback.

If a reactor trip occurs, immediately go to E-0, Reactor Trip or Safety Injection AOP 3571 Step 1, CAUTION AOP 3571 Step 1, NOTE Section 4 Page 10 of 62 OP 3326 Step 4.6.3.j OP 3326 Step 4.6.5 US US Exnected AP.tinn Rtnnd*rd

{

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor InformationlActivitv Task Assian Revision:

0 sinExnected Ac~tion Stsand-1r RO US/

CREW AOP 3571 Step 1 AOP 3571 Step 2 Determine the initiating parameter and place the affected controller in MANUAL.

Stabilize the plant parameters.

It is desired that IC&E personnel trip the bistables specified in this procedure. If, during off-hours, IC&E personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.

Perform Corrective Actions Using Appropriate Attachment Instrument Failure PZR Level Channel Failure Defeat the failed channel input.

Pressurizer Level Select - Control 3RCS-LS459D C

AOP 3571 Attachment C Step 1 Section 4 Page 11 of 62 AOP 3571 Step 3, NOTE AOP 3571 Step 3 Attachment US US Exoected Actinn Rf*nrl*rrl

(

Exam

Title:

ID Number:

Time SECIiON 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 Exnected Action Sta ndaird

• Pressurizer Level Select - Record 3RCS-LS459E Restore PZR level to normal.

US/ RO If necessary, using OP 3304A, "Charging and Letdown," Restore letdown.

RO Place PZR level controller in automatic.

RO Reset pressurizer heaters as necessary.

CREW When conditions have stabilized, Observe MB annunciators and parameters. Immediately report any unexpected or unexplained conditions to the SM.

US Determine which Reactor Protection System bistable(s) requires tripping:

Place a check mark in the box above the appropriate channel that requires tripping on the last page of this attachment.

AOP 3571 Attachment C Step 2 AOP 3571 Attachment C Step 3 AOP 3571 Attachment C Step 4 AOP 3571 Attachment C Step 5 AOP 3571 Attachment C Step 6 AOP 3571 Attachment C Step 7 AOP 3571 Attachment C Step 7a Section 4 Page 12 of 62 Expected Action

• t*nd*rrl

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 Asia xpected Ac~tion S~tanrfnrri

[Tech Specs]

3.3.1, Functional Unit 11, Action 6 IF PZR level increases to > 67.5%

then also Refer to Technical Specification 3.3.1, 3.3.3.5, and 3.3.3.6.

AOP 3571 Attachment C Step 7b 3.4.3.1, Action b.

REMOTE Bistables: RXR 106 (door open/close)

RXR 25 (459A)

Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped.

Request the I&C Department trip the appropriate bistables using Attachment C and Attachment S.

Verify the appropriate bistable status lights are lit.

Request I&C Department perform corrective maintenance on failed instrument.

T= Complete AOP 3571, Att.C or Examiner's Cue Event 2: Loss of Condenser Vacuum NOTE: Put in early if possible. Takes

-5 minutes to develop.

AOP 3571 Attachment C Step 7c AOP 3571 Attachment C Step 7d AOP 3571 Attachment C Step 7e AOP 3571 Attachment C Step 8 Section 4 Page 13 of 62

(

Expected Action

• tnndnrd

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assian Expec~ted Artion

!-tzmn rIrrI Revision:

0 NOTE: Main Condenser vacuum will begin to degrade from an unknown cause, possibly boot rupture.

Backpressure will stabilize at about 5.8 in. Hg Abs.

Sim. Driver: Modify MALF FW01 to 50% to maintain Cond Vacuum at about 5.8 in. Hg Abs. At 5" Hg Abs or when crew begins rapid downpower.

Should be above 5 in. Hg Abs. but not approach 7.5 in. Hg Abs.(Rx Trip Criteria)

US BOP Note: First pass through the procedure Condenser Backpressure probably will not be >5 inches Hg Absolute BOP Check If Turbine Load Should Be Reduced Verify condenser backpressure LESS THAN OR EQUAL TO 7.5 inches Hg Absolute Verify condenser backpressure GREATER THAN 5 inches Hg Absolute AOP 3559 Step 1 AOP 3559 Step 1.a AOP 3559 Step 1.b Section 4 Page 14 of 62 FW01 @

100%,

THEN 50%

I::xnect*d Ae.tinn Rf*ndnrd

(

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Expected Arfti-n 4nnr

(

Revision:

0 NOTE: Continuous Action; expect to return to step 1.c Proceed to step 2 and, IF condenser backpressure increases to GREATER THAN 5 inches Hg Absolute THEN AOP 3559 Step 1.b RNO Return to step 1.c.

Verify turbine load - GREATER THAN 360 Mwe Using AOP 3575, "Rapid Downpower,"

Lower turbine load at 5%/min until one of the following occur:

Backpressure LESS THAN EQUAL TO 5 inches Hg Absolute OR Turbine load at 360 Mwe AOP 3559 Step 1.c AOP 3559 Step 1.d Check Circulating Water System Operation Verify circulating water pumps - ONE PER CONDENSER RUNNING Verify water box outlet isolation valves

- OPEN Verify all circulating water pumps RUNNING AOP 3559 Step 2 AOP 3559 Step 2.a AOP 3559 Step 2.b AOP 3559 Step 2.c Section 4 Page 15 of 62 BOP l*xn*_r.t*_d A r.finn

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assign

(.

Revision:

0 Expected Action NOTE: All local equipment indications, in this step, will appear normal.

Verify the traveling screen differential pressure - LESS THAN 12 inches H20 US/ PEO Check Condenser Air Removal Alignment Verify steam jet air ejector auxiliary steam supply valve (3ASS-AOV22)

OPEN Using OP 3329, "Condenser Air Removal," locally Perform the following:

Verify both sets of steam jet air ejectors in service Verify all first stage jets in service on each air ejector Check for indications of air ejector backfiring Verify isolation dampers for gaseous waste to Unit 1 stack (3GWS*AOD78A and 3GWS*AOD78B) - OPEN At Gas Waste Panel (3GWS-PNL-P6),

Verify process vent fans (3GWS FN1A or 3GWS-FN1B) - ONE RUNNING AOP 3559 Step 3.a AOP 3559 Step 3.b AOP 3559 Step 3.b.1 AOP 3559 Step 3.b.2 AOP 3559 Step 3.b.3 AOP 3559 Step 3.c AOP 3559 Step 3.d Section 4 Page 16 of 62 Standard AOP 3559 Step 2.d AOP 3559 Step 3

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Expec~ted Ac~tion Q2flt1nrr4 Revision:

0 Locally (Turbine Bldg 38' southwest)

Verify steam jet air ejector exhaust valves (3ARC-AOV36A and 3ARC AOV36B) - OPEN Check Gland Seal Pressure BETWEEN 2 and 6 psig Locked valve key is required for some local operations.

Check Condensate Surge Tank Level

"* GREATER THAN 18,000 gal

"* NOT DECREASING IN AN UNEXPECTED MANNER A turbine trip occurs if the exhaust hood temperature exceeds 225 0F.

BOP Check Exhaust Hood Temperature Annunciators EXH HOOD A, B, and C TEMP HI (175°F) (MB6A 5-4, 5-5, and 5-6) - NOT LIT US/ PEO Check For Condenser In-Leakage AOP 3559 Step 3.e AOP 3559 Step 4 AOP 3559 Step 5 Note AOP 3559 Step 5 AOP 3559 Step 6 Note AOP 3559 Step 6 AOP 3559 Step 7 Section 4 Page 17 of 62 BOP US BOP Exn*.r.t*_d A Ptinn

• f*nd=rd

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assion

(

Revision:

0 Exnected Action Standard NOTE: If dispatched, the PEO will hear air inleakage around the "B" Main Condenser rubber boot.

Verify condenser vacuum breakers (MB7) (3ARC-MOV20A-B-C)

CLOSED Locally Check vacuum breaker loop seals (Turbine Bldg 60' west)

FILLED Locally Check for unusual noises indicative of air in-leakage Check seal water supply pressure annunciator EXT STM NRV SEAL PRES LO (MB6A 3-6B) - NOT LIT Using OP 3353.MB6A, "Main Board 6A Annunciator Response," Perform corrective actions for MB6A 3-6B.

Contact Engineering to assist in locally checking condenser penetrations for air in-leakage US Review Current Maintenance and Testing Activities.

US/ PEO Verify Condenser Backpressure STABLE OR DECREASING AOP 3559 Step 8 AOP 3559 Step 9 Section 4 Page 18 of 62 AOP 3559 Step 7.a AOP 3559 Step 7.b AOP 3559 Step 7.c AOP 3559 Step 7.d AOP 3559 Step 7.d RNO AOP 3559 Step 7.e Standard

(

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 Assian

~Expec~ted Ac~tion nfnjr NOTE: At second pass through procedure the backpressure should be at the correct value for requiring a Rapid Downpower AOP 3575, Rapid Downpower, Rev. 7 Return to step 1.

US

[Reactivity Manipulation]

CREW US US AOP 3559 Step 9 RNO A CONVEX requested emergency generation reduction should be completed within 15 minutes of notification.

If a unit shutdown is required, the target power level should be between 20% and 25% reactor power.

If at any time ROD CONTROL BANKS LIMIT LO - LO (MB4C 4

- 9 ) annunciator is received, DO NOT go to AOP 3566, Immediate Boration. Immediately perform step 9.

Determine Power Reduction Rate

(%/rmin).

Check desired power reduction rate LESS THAN OR EQUAL TO 5%/min.

Check power reduction CONVEX REQUESTED AOP 3575 Step 1 NOTE AOP 3575 Step I AOP 3575 Step 1.a AOP 3575 Step 1.b Section 4 Page 19 of 62 Condenser Back pressure

>5"HgAbs Exn*.c.tod Acfinn

.*f* nrl= rrl

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assian Revision:

0 Exoected Action Exoeced AtionStandard US NOTE: AOP 3559 requires 5%/minute downpower CREW US CREW US US BOP BOP BOP Proceed to Step 1.d.

Determine power reduction rate using Table.

Check Rod Control In AUTO.

Align EHC Panel Check turbine OPERATING MODE MANUAL Check LOAD LIMIT LIMITING light LIT Intermittently Press DECREASE LOAD pushbutton until LOAD LIMIT LIMITING light - NOT LIT Rotate LOAD LIMIT SET adjust knob at least one full turn in raise direction Select DECREASE LOADING RATE to ON Select LOAD RATE LIMIT % MIN to required power reduction rate (%

min)

AOP 3575 Step 1.b RNO AOP 3575 Step 1.d AOP 3575 Step 2 AOP 3575 Step 3 AOP 3575 Step 3.a AOP 3575 Step 3.b AOP 3575 Step 3.c AOP 3575 Step 3.d AOP 3575 Step 3.e AOP 3575 Step 3.f Section 4 Page 20 of 62 Standard

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assian

(

Revision:

0 Expected Action US/RO RO Note: Either the Action/Expected Response or RNO flowpath is acceptable. (judgement call if time available to perform boration at this step).

RO If at any time the power reduction rate or target power level must be changed, Return to step 1.

Verify Power Reduction Rate Check power reduction rate 5% MIN Check power reduction - REQUIRED TO STABILIZE PLANT Proceed to step 5.

AOP 3575 Step 4.b RNO Proceed to NOTE prior step 7.

Initiate Rapid Boration Verify RCS makeup system in AUTO START one boric acid transfer pump.

AOP 3575 Step 4.c AOP 3575 Step 5 AOP 3575 Step 5.a AOP 3575 Step 5.b Section 4 Page 21 of 62 Standard AOP 3575 Step 4 NOTE AOP 3575 Step 4 AOP 3575 Step 4.a AOP 3575 Step 4.b RO RO Exoected Action Standard

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 AsinExnected Action 5Standzmrri OPEN emergency boration valve (3CHS*MV8104).

Verify direct boric acid flow (3CHS-FI 183A) - INDICATED.

OPEN charging line flow control valve, to match boric acid flow (3CHS-FI 183A)

Record time boration started Time Energize all PZR heaters.

Determine required boric acid addition by multiplying total power change (A%) by 15 (gal/%) = __

gal.

Determine required time to borate by dividing required gallons of boric acid by the direct boric acid flowrate (net charging flow rate if using gravity boration) min.

Check turbine load decrease - IN PROGRESS OR COMPLETED.

Section 4 Page 22 of 62 RO RO Us AOP 3575 Step 5.c AOP 3575 Step 5.d AOP 3575 Step 5.e AOP 3575 Step 5.f AOP 3575 Step 5.g AOP 3575 Step 5.h AOP 3575 Step 5.i AOP 3575 Step 5.j Expected Actinn Rtnnd*rd

K Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Intrctr nfrmtin/ctvivAssion Expectetd Arti-n nfnrn C

Revision:

0 US US CREW AOP 3575 Step 5.j RNO AOP 3575 Step 5.k AOP 3575 Step 6 NOTE Proceed to NOTE prior to Step 7.

Proceed to NOTE prior to Step 8.

Boric acid total volume addition and flow rates are based on approximations. Adjustments should be made to these values as necessary to ensure the reactor reaches the desired end state of:

"* Tavg on program

"* Rods above the Rod Insertion Limit

"* AFD on or above the target value Align RCS Makeup System For Boration.

Determine required boric acid addition by multiplying total power change (A%) by 15(gal/%) =

gal.

Set the boric acid batch counter to total gallons of boric acid required.

AOP 3575 Step 6 AOP 3575 Step 6.a AOP 3575 Step 6.b Section 4 Page 23 of 62 US US/RO RO I::* n*_r.f*rl Antinn

_*f* nrl-, rrl

Exam

Title:

ID Number:

Time SECTIuN 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assign

(

Revision:

0 Expected Action Staie Us RO RO RO RO RO US RO RO Check power reduction rate-AT 0.5%/min.

Adjust boric acid blend flow controller pot setting to 3.75 (15 gpm) and Proceed to Step 6.e.

Adjust boric acid blend flow controller pot setting to 1.9 (7.5 gpm).

Select BORATE on the reactor coolant makeup select switch.

Select START on the reactor coolant makeup start switch.

Verify boric acid flow - INDICATED Return to step 5.

Energize all PZR heaters.

If a unit shutdown is being performed, the final MWe load should be approximately 230 MWe.

ndard AOP 3575 Step 6.c AOP 3575 Step 6.c RNO AOP 3575 Step 6.d AOP 3575 Step 6.e AOP 3575 Step 6.f AOP 3575 Step 6.g AOP 3575 Step 6.g RNO AOP 3575 Step 6.h AOP 3575 Step 7 NOTE Section 4 Page 24 of 62 ExDected Action Sta

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor I nformationlActivitv Revision:

0 Task Insrucor nfomaton/ctiitv AssiaintI"I FXnprfard Ar-finn Q*a nf-A Af NOTE: Proceed to next event when examiner is satisfied with the performance of the power change reactivity manipulation.

US/BOP Initiate Load Reduction.

BOP BOP BOP BOP BOP BOP BOP Check turbine OPERATING MODE MANUAL Unload turbine at required rate using the STANDBY LOAD SET pot and Proceed to step 7.e.

Check rapid or gravity boration - IN PROGRESS Proceed to step 7.d.

Check LOAD RATE LIMIT % MIN set at - 3% OR 5%.LIMITING light - LIT.

Select LOAD RATE LIMIT % MIN to 3% or 5%.

Utilizing DECREASE LOAD pushbutton, Adjust LOAD SET to desired final MWe (target power level)

AOP 3575 Step 7 AOP 3575 Step 7.a AOP 3575 Step 7.a RNO AOP 3575 Step 7.b AOP 3575 Step 7.b RNO AOP 3575 Step 7.c AOP 3575 Step 7.c RNO AOP 3575 Step 7.d Section 4 Page 25 of 62 k

FYn*r.f*l Arfi*n

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Expected Action 4tnnn

(

Revision:

0 Check power reduction - CONVEX REQUESTED.

Inform CONVEX of load reduction rate (MWe/min) and final MWe level.

Maintain initial MVAR loading during power reduction, unless directed otherwise.

Check boration - IN PROGRESS Return to step 5.

The following step places one TD FW pump in manual while allowing the other TD FW pump to automatically unload during the downpower.

US/BOP Align One Feedwater Pump For Automatic Unloading Verify removing a feedwater pump from service during the downpower DESIRED Section 4 Page 26 of 62 BOP US BOP US/RO US BOP AOP 3575 Step 7.e AOP 3575 Step 7.e RNO AOP 3575 Step 7.f AOP 3575 Step 7.g AOP 3575 Step 7.g RNO AOP 3575 Step 8 NOTE AOP 3575 Step 8 AOP 3575 Step 8.a BOP I=x n*.e.t*_d Acfinn

• f*nd*rd

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor I nformation/Activitv Task Isrco nom to/ciivAssinn r,~

C111 01 Revision:

0 T=.

Examiner Cue; Reactivity Manipulation Complete T= Steam Leak Evident to Crew MALF

MS03,

-10%, 30 second ramp ANN I/O

MB08C, 1-10

MB08C, 1-11 VP1B, 1 18 MALF ED06C PCO1 EVENT 4: Small steam break in the Turbine Building Small steam leakage will cause shorting and loss of load center 32A.

Plant Process Computer will shutdown on transfer from it's normal power supply.

NOTE: Annunciator signs of steam leakage.

BATT 6 TROUBLE INV 6 TROUBLE ON ON TB VENT PANEL TROUBLE ON Loss of Voltage to MCC 32-3T Loss of Plant Process Computer EVENT 5: Uncontrolled Depressurization of All SIGs Loss of Voltage to Load Center 32A.

Initiates Reactor Trip Section 4 Page 27 of 62 T= Ready for Rx Trip MALF ED05A i

FYnarta At-fif, n Q*

A A

(,

Exam

Title:

ID Number:

Time SECTIUN 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Expected Action Standard NOTE:

US should go to "Master Silence" before ordering reactor trip.

E-0, Reactor Trip or Safety Injection (Rev. 20) STEPS T= Manual Trip by crew decision or Auto Trip RO Crew TRIP the reactor Go to E-0, Reactor Trip or Safety Injection.

On the trip, the B & D S/G low setpoint safeties will open and fail to close.

Additionally, when manual or automatic MSI occurs, the A & C MSIVs will fail to close.

Foldout page must be open E-0, Step 1, NOTE ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 105 R/hr in containment.

The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

E-0, Step 1 Section 4 Page 28 of 62 MALF MS07B MS07D MALF MS12A MS12C on BT1 RO Verify Reactor Trip Exi)ected Action Standard

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 Expected Action EVENT 5 (rods): Multiple Rods Stick Out on the Reactor Trip NOTE: RO should identify condition and verify reactivity concerns are being met by SI flow.

BOP BOP BOP BOP US RO Check reactor trip and bypass breakers - OPEN Check rod bottom lights - LIT Check neutron flux DECREASING Verify Turbine Trip Check all turbine stop valves CLOSED Verify Power to AC Emergency Busses Check busses 34C and 34D - AT LEAST ONE ENERGIZED Check busses 34C and 34D - BOTH ENERGIZED Check If SI Is Actuated Verify Safety Injection Actuation annunciator - LIT E-0, Step 2 E-0, Step 2.a E-0, Step 3 E-0, Step 3.a E-0, Step 3.b E-0, Step 4 EOP 35 E-0, Step 4.a Section 4 Page 29 of 62

(

Exneced AtionStandard Standard

(

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDAIMalf Instructor Information/Activitv Task Assian 11~~tr Av1tn Intuco Infrmtin/Atiit Ex e-frlAt-i Qf~ndnirA

(

Revision:

0 RO RO RO BOP BOP Verify Service Water Pumps - AT LEAST ONE PER TRAIN RUNNING Verify Two RPCCW Pumps - ONE PER TRAIN RUNNING Verify ECCS Pumps Running

"* Check SI pumps - RUNNING

"* Check RHR pumps - RUNNING

"* Check two charging pumps RUNNING Verify AFW Pumps Running Check MD pumps - RUNNING Check turbine - driven pump RUNNING, IF NECESSARY Verify FW Isolation

"* Check SG feed regulating valves CLOSED

"* Check SG feed regulating bypass valves - CLOSED

"* Check FW isolation trip valves CLOSED E-0, Step 5 E-0, Step 6 E-0, Step 7 E-0, Step 8 E-0, Step 8.a E-0, Step 8.b E-0, Step 9 Section 4 Page 30 of 62 F:xn*rf*rl &rfi*n

(

ID Number:

Time 2K1 NRC-004 IDA/Malf Instructor Information/Activity Task Assign Expected Action Revision:

0 Standard EVENT 6: MSI fails to Auto Actuate

[CRITICAL TASK]

E-0-P: Manually actuate MSI or close MSIVs NOTE: MSI fails to auto actuate BOP

"* Check MD FW pump - STOPPED

"* Check TD FW pumps - TRIPPED

"* Check SG blowdown isolation valves - CLOSED

"* Check SG blowdown sample isolation valves - CLOSED

"* Check SG chemical feed isolation valves - CLOSED Check If Main Steam Lines Should Be Isolated Check Ctmt pressure GREATER THAN 18 psia OR Any SG pressure LESS THAN 660 psig Proceed to Step 11 E-0, Step 10 E-0, Step 10.a E-0, Step 10.a, RNO Section 4 Page 31 of 62 SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs Exam

Title:

INITIAL MALF RP08A RP08B

(

Exam

Title:

ID Number:

Time K

SECTiON 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor I nformation/Activitv Task Assinn F rn,~t Gillrh 01.I' Intuco Information*Activ1 Revision:

0 Verify MSIVs and MSIV bypass valves

- CLOSED Initiate MSI.

IF MSI will NOT actuate, THEN CLOSE the MSIVs and MSIV bypass valves.

Check if CDA Required Check Ctmt pressure is GREATER THAN 23 psia OR Ctmt spray is initiated Proceed to Step 12.

Verify CAR Fans Operating In Emergency Mode Check CAR fan status:

"* CAR fans A and B - RUNNING

"* CAR fan C-STOPPED E-0, Step 11 E-0, Step 11.a E-0, Step11,a, RNO E-0, Step 12 E-0, Step 12.a Section 4 Page 32 of 62 BOP E-0, Step 10.b E-0, Step 10.b, RNO RO US BOP BOP FYnar-fad Ae-fifn Qf A

A

Exam

Title:

ID Number:

Time

(

(

2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Revision:

0 AsinExpected Ac~tion S~tandazrd START/STOP CAR fans as necessary.

Verify RPCCW Ctmt supply and return header isolations - OPEN Verify Train A and B RPCCW supply and return to chill water valves - OPEN Verify CIA Check ESF Group 2 status columns 2 through 10 - LIT Initiate CIA AND Verify minimum safety function is met.

IF CIA will NOT actuate, THEN reposition valves as necessary for minimum safety function using Attachment A Verify Proper ESF Status Panel Indication

"* Verify ESF Group 1 lights - OFF

"* Verify ESF Group 2 lights - LIT E-0, Step 12.a, RNO E-0, Step 12.b E-0, Step 12.c E-0, Step 13 E-0, Step 13.a E-0, Step 13.a, RNO E-0, Step 14 Section 4 Page 33 of 62 BOP RO RO RO RO RO RO RO SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs Exnected Actinn Rt*nd*rd

SECTION 4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard IF Main Steam Line Isolation has occurred, THEN verify ESF Group 3 lights - LIT RO/BOP Align component(s) as necessary for E-0, minimum safety function.

Step 14, RNO RO Determine If ADVERSE CTMT E-0, Step 15 Conditions Exist

"* Ctmt temperature GREATER THAN 180°F OR

"* Ctmt radiation GREATER THAN 10o R/hr CREW DO NOT use ADVERSE CTMT E-0, parameters.

Step 15, RNO CREW To provide adequate ECCS flow, RCS E-0, subcooling and PZR level should be Step 16, monitored to ensure that the charging CAUTION pump is manually restarted if RCS subcooling based on core exit TCs decreases to LESS THAN 32 0F (1 150F ADVERSE CTMT) or PZR level decreases to LESS THAN 16% (50%

ADVERSE CTMT).

Section 4 Page 34 of 62

SECTION 4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1 NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard CREW If offsite power is lost after SI reset, E-0, manual action to restart safeguards Step 16, equipment may be required.

CAUTION CREW DO NOT reset CDA if recirculation E-0, spray pumps are required and have not Step 16, automatically started.

CAUTION RO Verify ECCS Flow E-0, Step 16 Check charging pump flow indicator -

E-0, FLOW INDICATED Step 16.a RO Check RCS pressure - GREATER E-0, THAN 1650 psia (1950 psia ADVERSE Step 16.b CTMT)

US Proceed to Step 16.i E-0, Step 16.b, RNO RO Check PORV block valves - OPEN E-0, Step 16.c RO VERIFY the following:

E-0, Step 16.d

1) Charging pumps - TWO RUNNING

2) RCS subcooling based on core exit TC's GREATER THAN 320F (1 15°F ADVERSE CTMT).

Section 4 Page 35 of 62 z'

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assigin

(

Revision:

0 Expected Action Staindard

3) Secondary heat sink:

"* Total feed flow to SGs GREATER THAN 530 gpm OR

"* NR level in at least one SG GREATER THAN 8% (42%

ADVERSE CTMT)

4) RCS pressure - STABLE OR INCREASING

5) PZR level - GREATER THAN 16%

(50% ADVERSE CTMT)

CREW should perform a short brief and come out of "Master Silence" at the completion of Step 16.

US Proceed to Step 17.

E-0, Step 16.d RNO Verify Adequate Heat Sink Check NR level in at least one SG GREATER THAN 8% (42% ADVERSE CTMT)

Proceed to Step 17.d.

Verify Total AFW Flow - GREATER THAN 530 gpm E-0, Step 17 E-0, Step 17.a E-0, Step 17.a, RNO E-0, Step 17.d Section 4 Page 36 of 62 BOP US BOP Exoected Action Sta

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv

(

Task BOP RO US NOTE: When asked, REPORT that "all SLCRS doors indicate closed."

RO RO RO RO BOP BOP Exam

Title:

ID Number:

Time Stop purge supply fan.

Section 4 Page 37 of 62 IDA/Malf Instructor Information/Activitv A

Re Expected Action Verify AFW Valve Alignment PROPER EMERGENCY ALIGNMENT Verify ECCS Valve Alignment PROPER EMERGENCY ALIGNMENT Check Plant Status Verify SLCRS doors - CLOSED Check CBI annunciator - LIT Verify CBI status Verify ESF Group 2 CBI lights - LIT Align HVAC components as necessary for minimum safety function.

Control Building purge supply fan and purge exhaust fan - NOT RUNNING Perform the following:

vision:

0 Standard E-0, Step 18 E-0, Step 19 E-0, Step 20 E-0, Step 20.a E-0, Step 20.b E-0, Step 20.c E-0, Step 20.c.1 E-0, Step 20.c.1, RNO E-0, Step 20.c.2 E-0, Step 20.c.2, RNO

(

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Instructor Information/Activitv Task Assian

(

Revision:

0 Assion

~~Expected Ac~tionn.fn~r

"* Stop purge exhaust fan.

"* Locally Close instrument air isolations

"* 31AS-V725

"* 31AS-V726

"* 31AS-V644

"* Locally Close instrument air isolation valve for 3HVC-AOD134 Control building air bank isolation valves - OPEN (after 60 seconds)

OPEN valves E-0, Step 20.c.3 E-0, Step 20.c.3, RNO IF at least one air bank isolation valve can NOT be opened, THEN locally throttle Open at least one pair of air bank isolation bypass valves to maintain 0.125 inches water at Control Building AP indicator on VP1.

"* 3HVC*V750 and 3HVC*V751

"* 3HVC*V758 and 3HVC*V759 Section 4 Page 38 of 62 BOP BOP BOP I=xn*.e.t*_d At.finn R'l'n n t'l* rrl

Exam

Title:

ID Number:

Time

(

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Expected Action Standard When called, WAIT 3 - 5 min, Then REPORT "All Control Building pressure boundary doors are Closed and Dogged."

BOP PEO RO RO RO RO US RO STOP kitchen exhaust fan Close and Dog (as applicable) Control Building pressure boundary doors.

Check if CBI is required

"* Ctmt pressure GREATER THAN 18 psia OR

"* Control Building radiation monitor in alarm OR

"* SI manually actuated IF CBI required, THEN initiate CBI.

IF CBI is NOT required, THEN proceed to Step 21.

Check RCS Temperature E-0, Step 20.d E-0, Step 20.e E-0, Step 20.b, RNO E-0, Step 21 Section 4 Page 39 of 62 BOOTH INST NOTE Exoected ction Standard

(

(

(1 SECTION 4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1 NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Verify RCS cold leg WR temperature -

E-0, BETWEEN 550°F and 560°F Step 21.a US Perform the applicable action:

E-0, Step 21.a, RNO IF temperature is GREATER THAN 550°F AND 560°F, THEN

1) Dump steam to the condenser, if available OR Dump steam to atmosphere.

US

2) Proceed to Step 22.

"* IF the temperature is LESS THAN 5500, THEN proceed to Step 21c.

US Proceed to Step 22 E-0, Step 21.b BOP Maintain total feed flow BETWEEN 530 E-0, and 600 gpm until NR level is Step 21.c GREATER THAN 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric dump and E-0, dump bypass valves Step 21.d BOP Check the following valves - CLOSED E-0, Step 21.e Section 4 Page 40 of 62

SECTION 4 Exam

Title:

ID Number:

Time T= When Directed UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf 1/O Instructor Information/Activitv Task Assian Revision:

0 Instrutor Iformaton/Acivitv sinn Xne~frlt~ Arfinn

!2iA 0

MSIVs MSIV bypass valves Perform the following:

Place both condenser steam dump interlock selector switches to OFF.

IF unexpected cooldown continues, THEN CLOSE the MSIVs and MSIV bypass valves.

Check PZR Valves Verify PORVs - CLOSED Verify normal PZR spray valves CLOSED E-0, Step 21.e, RNO E-0, Step 21.e.1, RNO E-0, Step 21.e.2, RNO E-0, Step 22 E-0, Step 22.a E-0, Step 22.b Section 4 Page 41 of 62 NOTE: 2 are not closed. US may direct PEO to pull fuses on MSIV using guidance in E-2.

I/O (MS) 3MSS*CTV27A*LR Red-Off I/O (MS) 3MSS*CTV27A*LR Grn-Off I/O (MS) 3MSS*CTV27C*LR Red-Off I/O (MS) 3MSS*CTV27C*LR Grn-Off US BOP BOP RO RO I::yn*rf*rl A*tinn

.*f"* nrla rrl

(

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activitv Task Assian Expected Ac~tion Sannt

(

Revision:

0 RO Verify PZR safety valves - CLOSED CREW To prevent damage to the RCP seal(s),

seal injection flow should be maintained to all RCPs.

Check If RCPs Should Be Stopped Verify RCS pressure - LESS THAN 1500 psia (1800 psia ADVERSE CTMT)

Proceed to Step 24 Verify charging or SI pumps - AT LEAST ONE RUNNING Proceed to Step 24 STOP all RCPs BOP/RO Check If SG Secondary Boundaries Are Intact Check pressure in all SGs E-0, Step 23 E-0, Step 23.a E-0, Step 23.a, RNO.

EOP 35 E-0, Step 23.b E-0, Step 23.b, RNO E-0, Step 23.c E-0, Step 24 E-0, Step 24.a Section 4 Page 42 of 62 E-0, Step 22.c E-0, Step 23, CAUTION RO RO US RO US RO Exoect*.tl A c.tinn Rf*nH*rH

Exam

Title:

ID Number:

Time SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDAIMalf Instructor InformationlActivitv Task Assian Expec~ted Ac~tinn fndr

(

Revision:

0 NOTE: US or designee must do manual status trees because the computer is NOT available US NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER NO SG COMPLETELY DEPRESSURIZED Initiate monitoring of CSF Status Trees and Go to E-2, Faulted Steam Generator Isolation.

E-2, FAULTED STEAM GENERATOR ISOLATION, Rev. 8 BOP Us NOTE: 2 are not closed. US may direct BOP PEO to pull fuses on MSIV using guidance in E-2.

At least one SG must be maintained available for RCS cooldown.

Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown or sampling is required.

If RWST level decreases to LESS THAN 520,000 gal, Go to ES-1.3, Transfer to Cold Leg Recirculation, to align the ECCS system.

Check Main Steam Isolation And Bypass Valves - CLOSED CLOSE valves.

IF flow path(s) can NOT be isolated, E-2 CAUTION E-2, Step 1 E-2, Step 1 RNO Section 4 Page 43 of 62 E-0, Step 24.a RNO RNO T= When requested I/Os I*x n*_r.t*.d Artinn

Exam

Title:

ID Number:

Time

(

SECI ION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDAIMalf Instructor Information/Activitv Task Intrctr nfrmtin/ctvAvssian EXnertard Ar~tinn Qannr Revision:

0 THEN Dispatch an operator to locally Close valve(s) using Attachment A for guidance.

US Check at least one SG boundary intact.

RO/ BOP Check pressures in all SGs - AT LEAST ONE STABLE OR INCREASING US IF all SG pressures decreasing in an uncontrolled manner, THEN Go to ECA 2.1, Uncontrolled Depressurization of All Steam Generators.

E-2, step 2 E-2, step 2.a E-2, Step 2.a RNO ECA-2.1, Uncontrolled Depressurization of All Steam Generators, Rev 13 US If any SG pressure increases at any time, except while performing SI termination in Steps 12 through 28, Go to E-2, Faulted Steam Generator Isolation.

If, during the performance of the procedure, the capability to feed SGs at GREATER THAN 530 gpm is NOT available, Go to FR-H.1, Response to Loss of Secondary Heat Sink.

ECA 2.1 Step 1 CAUTION Section 4 Page 44 of 62 I/O (MS) 3MSS*CTV27A*LR Red-Off I/O (MS) 3MSS*CTV27A*LR Gm-Off I/O (MS) 3MSS*CTV27C*LR Red-Off I/O (MS) 3MSS*CTV27C*LR Gm-Off FYn*.rt#d & r.tinn

• f=nd=rd

SECTION 4 Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard If the TD AFW pump is the only available source of feed flow, steam supply to the pump must be maintained from one SG.

US Foldout page must be open.

ECA 2.1 Step 1 NOTE CREW Check Secondary Pressure ECA 2.1 Boundary Step 1 Verify MSIVs and MSIV bypass valves - CLOSED Verify SG feed regulating valves CLOSED Verify SG feed regulating bypass valves - CLOSED Verify FW isolation trip valves CLOSED Verify steam supply valves to TD AFW pump - CLOSED IF MD AFW PUMP RUNNING Verify the SG atmospheric dump valves - CLOSED Section 4 Page 45 of 62

(

(

SECTION 4 Lesson

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2KINRC-004 Time IDA/Malf Instructor Information/Activitv Task Assian Expec ted Ac~tion I5qt2 nrIfre Revision: 0 Verify SG blowdown isolation valves - CLOSED Verify SG blowdown sample isolation valves - CLOSED Verify main steam line drains upstream of MSIVs and TD AFW pump - CLOSED Close valves or isolation valves.

IF a flow path can NOT be isolated, THEN Dispatch an operator to locally Close valves, one loop at a time, using Attachment B.

ECA 2.1 Step 1 RNO Section 4 Page 46 of 62 (l

SG A SG B SGC SGD 3DTM*AOV29A 3DTM*AOV29B 3DTM*AOV29C 3DTM*AOV29D 3DTM*AOV61A 3DTM*AOV61 B 3DTM*AOV61C 3DTM*AOV61 D 3DTM*AOV63A 3DTM*AOV63B 3DTM*AOV63D 3DTM*AOV64A 3DTM*AOV64B 3DTM*AOV64D I:xaected Ae.finn

• f*nd*rH

(

(

EVALUAiION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time I DA/Malf Instructor Information/Activity Assign Expected Actions Standard A minimum feed flow of 100 gpm must ECA 2.1 be maintained to each SG with a NR Step 2 level LESS THAN 8% (42% ADVERSE CAUTION CTMT).

[Critical Task]

BOP Control Feed Flow To Minimize RCS ECA 2.1 Control the AFW flow rate to at least Cooldown.

Step 2 100 gpm per SG in order to minimize the RCS cooldown rate before a severe (orange-path) challenge develops to the integrity CSF Check cooldown rate in RCS cold legs ECA 2.1

- LESS THAN 80°F/hr.

Step 2.a Decrease AFW flow to 100 gpm to ECA 2.1 each SG and Proceed to Step 2c.

Step 2.a RNO Check NR level in all SGs - LESS ECA 2.1 THAN 50%.

Step 2.b Control feed flow to maintain NR level ECA 2.1 LESS THAN 50% in all SGs.

Step 2.b RNO Check RCS hot leg WR temperatures -

ECA 2.1 STABLE OR DECREASING.

Step 2.c Control feed flow or Dump steam to ECA 2.1 stabilize RCS hot leg WR Step 2.c temperatures.

RNO Section 4 Page 47 of 62

!(

(.

(

EVALUA1 ION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Seal injection flow should be ECA 2.1 maintained to all RCPs.

Step 3 NOTE RO Check If RCPs Should Be Stopped.

ECA 2.1 Step 3 Verify RCS pressure - LESS THAN ECA 2.1 1500 psia (1800 psia ADVERSE Step 3.a CTMT).

Proceed to step 4.

ECA 2.1 Step 3.a RNO Verify charging or SI pumps - AT ECA 2.1 LEAST ON RUNNING.

Step 3.b Proceed to Step 4.

ECA 2.1 Step 3.b RNO Stop all RCPs.

ECA 2.1 Step 3.c BOP Check DWST Level - GREATER ECA 2.1 THAN 80,000 gal.

Step 4 US If any PZR PORV opens because of ECA 2.1 high PZR pressure, Step 5a must be Step 5 repeated after pressure decreases to CAUTION LESS THAN 2350 psia.

Section 4 Page 48 of 62

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EVALUATION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Check PZR PORVs And Block ECA 2.1 Valves Step 5 Verify PORVs - CLOSED.

ECA 2.1 Step 5.a Verify block valves - AT LEAST ONE ECA 2.1 OPEN.

Step 5.b RO Check Secondary Radiation.

ECA 2.1 Step 6 Verify trend history and alarm status of ECA 2.1 radiation monitors Step 6.a

"* Main steam line - NORMAL

"* Condenser air ejector - NORMAL

"* SG blowdown - NORMAL Align for SG activity samples ECA 2.1

1. RESET SG blowdown sample Step 6.b isolation

2) OPEN SG blowdown sample isolation valves US Request Chemistry obtain activity ECA 2.1 samples using HP coverage.

Step 6.c Section 4 Page 49 of 62

EVALUATION GUIDE UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Exam

Title:

ID Number:

Time Task Assian Revision:

0 Exo~ected Actions Standa~rd US ECA 2.1 Step 7 CAUTION If offsite power is lost after SI reset, manual actions to restart safeguards equipment may be required.

"* DO NOT reset CDA if recirculation spray pumps are required and have not automatically started.

To provide adequate ECCS flow, RCS pressure should be monitored to ensure that the RHR pumps are manually restarted if pressure decreases to less than 300 psia (500 psia ADVERSE CTMT).

Check If RHR Pumps Should Be Stopped.

Check RHR pumps - RUNNING.

Check RCS pressure.

Pressure - GREATER THAN 300 psia (500 psia ADVERSE CTMT)

Pressure - STABLE OR INCREASING.

(

Instructor Information/Activity ECA 2.1 Step 7 ECA 2.1 Step 7.a ECA 2.1 Step 7.b ECA 2.1 Step 7.b.1 ECA 2.1 Step 7.b.2 Section 4 Page 50 of 62 RO

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EVALUAI ION GUIDE UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 IDA/Malf Exam

Title:

ID Number:

Time Task Assian Expec~ted-Artinnc qnrne

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Revision:

0 RESET ESF actuation signals 0 SI CDA

"* LOP eCIA CIB STOP RHR pumps and Place in AUTO.

The recirculation spray pumps are sequenced to automatically start 11 minutes after CDA actuation.

Check If Containment Spray Should Be Stopped.

Verify quench spray pumps RUNNING.

Proceed to Step 9.

IF the ADTS determines to operate both pumps, THEN Proceed to Step 8f.

Section 4 Page 51 of 62

/

Instructor Information/Activitv ECA 2.1 Step 7.c RO ECA 2.1 Step 7.d ECA 2.1 Step 8 NOTE ECA 2.1 Step 8 ECA 2.1 Step 8.a ECA 2.1 Step 8.a RNO I:yn*.c.tm.d AP.finn*

.*1 n rl'* r*l

(

EVALUA'i ION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2KINRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Check RWST Level - GREATER ECA 2.1 THAN 520,000 gal.

Step 9 RO Check If Accumulators Should Be ECA 2.1 Isolated.

Step 10 Verify at least two RCS hot leg WR ECA 2.1 temperatures - LESS THAN 3800F.

Step 10.a REMOTE Accumulator Isolation Valves:

Unlock and CLOSE the SI accumulator ECA 2.1 SIR 15 isolation valve breakers:

Step 10.b S 32-2R-F4M SIR 16 S

32-2R-R5F SIR 17 32-2W-F4M SIR 18 0

32-2W-R3J CLOSE all SI accumulator isolation ECA 2.1 valves Step 10.c REMOTE Accumulator Isolation Valves:

PLACE the SI accumulator isolation ECA 2.1 SIR 15 valve breakers to OFF and LOCK:

Step 1 0.d S

32-2R-F4M SIR 16 S

32-2R-R5F SIR 17 S

32-2W-F4M SIR 18 32-2W-R3J Section 4 Page 52 of 62

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(

2K1NRC-004 IDA/Malf Exam

Title:

ID Number:

Time Task Assion Expected Ac~tions

~

Zqt2nriorri

(

Revision:

0 US NOTE: If asked as I&C to monitor ICC Cabinet, use steam tables and report subcooling and RVLMS head and plenum levels: FULL US Proceed to Step 11.

Check If ECCS Flow Should Be Reduced.

Verify RCS subcooling based on core exit TCs - GREATER THAN 320F (1 15°F ADVERSE CTMT).

Verify RCS pressure - STABLE OR INCREASING.

Verify PZR level - GREATER THAN 16% (50% ADVERSE CTMT).

Perform the following:

1. DO NOT stop ECCS pumps.

2. Try to stabilize PZR pressure using normal spray.

3) Return to Step 11a.

If offsite power is lost after SI reset, manual actions to restart safeguards equipment may be required.

Section 4 Page 53 of 62 EVALUATION GUIDE UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs Instructor Information/Activity ECA 2.1 Step 10.a RNO ECA 2.1 Step 11 ECA 2.1 Step 11.a ECA 2.1 Step 11.b ECA 2.1 Step 11.c ECA 2.1 Step 11.c RNO ECA 2.1 Step 12 CAUTION Exne.c.t*.d Ar.finn.*

.*f* nrl,* rrJ

UNCONTROLLED EVALUATION GUIDE DEPRESSURIZATION OF ALL S/Gs

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Revision:

0 2K1NRC-004 IDA/Malf Exam

Title:

ID Number:

Time Task Assian Exnected Actions Staind-Hr RO DO NOT reset CDA if the recirculation spray pumps are required and have not automatically started.

If any SG pressure increases, Complete Steps 12 through 28, then Go to E-2, Faulted Steam Generator Isolation.

RESET ESF Actuation Signals

"* SI

"* CDA

"* LOP

°CIA CIB NOTE: Not possible. This MCC was damaged/de-energized by the steam leak and cannot be re-energized. If the crew does not realize this, as the PEO, report that the feeder breaker trips free during attempts to close.

BOP/

RO Restore Power To MCC 32-3T.

Locally Close the feeder breaker on 32T (32T1 3-2) to MCC 32-3T.

ECA 2.1 Step 13.a Section 4 Page 54 of 62 Instructor Information/Activity ECA 2.1 Step 12 ECA 2.1 Step 13 Exoected Actions

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("

EVALUAI ION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Locally Verify inverter 6 DC input ECA 2.1 ammeter indicating zero amps.

Step 13.b T= Step 14 REMOVE NOTE: Simulates one of the MSIVs RO Establish Instrument Air To Ctmt.

ECA 2.1 of ECA-2.1 MALF going shut. Allows transition back to Step 14 MS12A E-2 after ECA-2.1 step 28 Check instrument air compressors - AT ECA 2.1 LEAST ONE RUNNING.

Step 14.a START one instrument air compressor.

ECA 2.1 Step 14.a RNO OPEN instrument air Ctmt isolation ECA 2.1 valves.

Step 14.b RO STOP All But One Charging Pump ECA 2.1 And Place In AUTO.

Step 15 RO Check RCS Pressure - STABLE OR ECA 2.1 INCREASING.

Step 16 RO Establish Normal Charging Flow ECA 2.1 Path.

Step 17 Fully Open charging line flow control ECA 2.1 valve.

Step 17.a Verify charging header loop isolation ECA 2.1 valves (3CHS*AV8146 or Step 17.b 3CHS*AV8147) - ONE OPEN.

Section 4 Page 55 of 62

EVALUAI ION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Re-position valves to establish only ECA 2.1 one open.

Step 17.b RNO OPEN charging header isolation valves ECA 2.1 (3CHS*MV8106 and 3CHS*MV8105).

Step 17.c CLOSE the charging pump miniflow ECA 2.1 isolations to the RWST Step 17.d (3CHS*MV851 1A and 3CHS*MV851 11B).

CLOSE the remaining charging pump ECA 2.1 cold leg injection valve.

Step 17.e RO Align Charging Pump Recirculation.

ECA 2.1 Step 18 OPEN the charging pump recirculation ECA 2.1 isolation vales Step 18.a 3CHS*MV81 1 1A 3CHS*MV8I 118B 3CHS*MV811 1 C 3CHS*MV81 10 RO Control Charging Flow To Maintain ECA 2.1 PZR Level.

Step 19 RO Check If SI Pumps Should Be ECA 2.1 Stopped.

Step 20 Section 4 Page 56 of 62

EVALUATION GUIDE UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1NRC-004 IDA/Malf Instructor Information/Activity Task Assign Revision:

0 Standard Expected Actions Check SI pumps - RUNNING.

Check RCS pressure

"* Pressure - GREATER THAN 1650 psia (1950 psia ADVERSE CTMT).

"* Pressure - STABLE OR INCREASING.

DO NOT stop additional SI pumps.

Return to CAUTION prior to Step 2.

STOP SI pumps and Place in AUTO.

STOP RHR Pumps and Place In AUTO.

Verify ECCS Flow Not Required.

Check RCS subcooling based on core exit TCs - GREATER THAN 320F (1 15°F ADVERSE CTMT).

Check PZR level - GREATER THAN 16% (50% ADVERSE CTMT).

Section 4 Page 57 of 62

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Exam

Title:

ID Number:

Time RO RO ECA 2.1 Step 20.a ECA 2.1 Step 20.b ECA 2.1 Step 20.b RNO ECA 2.1 Step 20.c ECA 2.1 Step 21 ECA 2.1 Step 22 ECA 2.1 Step 22.a ECA 2.1 Step 22.b

EVALUATION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Control charging flow to maintain PZR ECA 2.1 level.

Step 22.b RNO IF PZR level can NOT be maintained, THEN

1. Operate ECCS pumps as necessary.

2) Return to CAUTION prior to Step 2.

RO Check RCS Hot Leg WR ECA 2.1 Temperatures - STABLE OR Step 23 DECREASING.

Control AFW flow OR Dump steam to ECA 2.1 stabilize RCS hot leg WR Step 23 temperatures.

RNO BOP Check NR Level In All SGs - LESS ECA 2.1 THAN 50%.

Step 24 Control AFW flow to maintain NR level ECA 2.1 LESS THAN 50% in all SGs.

Step 24 RNO RO Check If Letdown Can Be ECA 2.1 Established.

Step 25 Verify PZR level - GREATER THAN ECA 2.1 30% (50% ADVERSE CTMT).

Step 25.a Section 4 Page 58 of 62

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EVALUATION GUIDE Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision:

0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Proceed to CAUTION prior to Step 28, ECA 2.1 and WHEN PZR level increases to Step 25.a GREATER THAN 30% (50%

RNO ADVERSE CTMT), THEN Return to Step 25.

Verify RPCCW pumps - AT LEAST ECA 2.1 ONE RUNNING.

Step 25.b Perform the following to establish ECA 2.1 normal letdown:

Step 25.c

1. Verify Train A RPCCW pump RUNNING

2) Using OP 3304A, "Charging and Letdown," Establish normal letdown (with continuous charging) at normal operating pressure

2) Proceed to CAUTION prior to step 28.

RO Check RCS Makeup System.

ECA 2.1 Step 26 Adjust boric acid flow controller to pot ECA 2.1 setting 8.3.

Step 26.a Using OP 3304C, "Primary Makeup ECA 2.1 and Chemical Addition," Align for auto Step 26.b makeup Section 4 Page 59 of 62 Ii

UNCONTROLLED 2K1 NRC-004 IDA/Malf EVALUAM iON GUIDE DEPRESSURIZATION OF ALL S/Gs Revision:

0 Instructor Information/Activitv Task Assign RO RO Previous Note: If any SG pressure increases, Complete Steps 12 through 28, then Go to E-2, Faulted Steam Generator Isolation.

NOTE: Terminate scenario on the transition to E-2 Verify BTRS - OFF.

Align Charging Pump Suction to VCT.

OPEN VCT to charging isolation valves.

2) Using OP 3304A, "Charging and Letdown," Place excess letdown in service.

3) Proceed to CAUTION prior to Step 28.

CLOSE RWST to charging isolation valves.

Control PZR Pressure.

Maintain pressure stable using PZR heaters and normal spray as necessary.

ECA 2.1 Step 26.c ECA 2.1 Step 27 ECA 2.1 Step 27.a ECA 2.1 Step 27.b ECA 2.1 Step 28 ECA 2.1 Step 28.a TERMINATE SCENARIO Section 4 Page 60 of 62

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Exam

Title:

ID Number:

Time

(

Expected Actions Standard T= E-2 transition Tm Inor atonAciv

SECTION 4 ID Number:

2KINRC-004 Revision: 0 EVALUATION GUIDE

1.

SUMMARY

1. The following Critical Tasks are covered in this exercise:

TASK DESCRIPTION Manually actuate Main Steamline isolation or close MSIVs before a severe (orange path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA-2.1, whichever happens first Control the AFW flow rate to at least 100 gpm per SG in order to minimize the RCS cooldown rate before a severe (orange-path) challenge develops to the integrity CSF TASK #

E-0-P K/A >/= 3.0 E12-EAl-1 3.8/3.8 039-K4.05 3.7/3.7 ECA-2.1

-- A E12.EA1.3 3.4/3.9 BASIS FOR SELECTION Failure to close the MSIVs under the postulated plant conditions causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Such an omission constitutes a "demonstrated inability by the crew to recognize a failure of the auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety."

Failure to control the AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF and to the subcriticality and the containment CSFs beyond those irreparably introduced by the postulated plant conditions. Thus, failure constitutes "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety."

Note: [CRITICAL TASK]

Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide.

Section 4 Page 61 of 62

Exam

Title:

ID Number:

SECTION 4 UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs 2K1 NRC-004 Revision: 0 EVALUATION GUIDE Section 4 Page 62 of 62

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number:

2K1NRC-004 Reactor Power:

Operating History:

RCS Boron:

Core Burnup:

Condensate Demins:

Evolutions in Progress:

Major Equipment OOS:

Revision: 0 100%

250 days on line 1100 ppm 8000 MWD/MTU 7 IN SERVICE Millstone Unit 2 is in a Refueling Outage None Crew Instructions:

Shift Train B Service Water Pumps to "B" pump running, "D" pump in standby, using OP 3326, Service Water Service, Section 4.6 Plant/Simulator Differences:

"* Rad Monitor Historical Data-Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.

"* If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire.

"* The following PPC programs do not function on the simulator:

"* Samarium Follow

"* Xenon Follow

"* Sequence of Events Section 5 Page 1 of 1

SECTION 6 VALIDATION CHECKLIST Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision: 0 Remote functions:

All remote functions contained in the guide are certified.

Malfunctions:

All malfunctions contained in the guide are certified.

Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02.

Simulator Operating Limits:

The simulator guide has been evaluated for operating limits and/or anomalous response.

Test Run:

The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected.

Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.)

11/20/2001 Technical Reviewer Date Section 6 Page 1 of I Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs

SECTION 7 REFERENCE AND TASK TRACKING Exam

Title:

UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs ID Number:

2K1NRC-004 Revision: 0 I.

References:

AOP 3571 AOP 3559 EOP E-0 EOP E-2 EOP ECA-2.1 EPIP 4400 ERGEXE EOP* Step _DOC EOP*ERGHP NUREG*1021 rev 8 Instrument Failure Response Loss of Condenser Vacuum Rx Trip or Safety Injection Faulted Steam Generator Isolation Uncontrolled Depressurization of All Steam Generators Event Assessment, Classification and Reportability Westinghouse Owners Group Executive Document MP3 Step Deviation Document Westinghouse Owners Group Background Document Examiners Standards Section 7 Pagel of2 Exam