Text

February Retake Exam 50-327/2003-301 & 50-328/2003-301, Draft Simulator Scenarios
	ML032450477
Person / Time
Site:	Sequoyah
Issue date:	03/07/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Scalice J; Tennessee Valley Authority
Shared Package
ML032461208	List: IR 05000327/2003301; ML032450469; ML032450477; ML032450480; ML032450486; ML032450488;
References
	50-327/03-301, 50-328/03-301
	Download: ML032450477 (16)
	v • d • e

Draft Submittal

I - .

, ..

SEQUOYAH RETAKE EXAM

50-327 & 50-32812003-301

FEBRUARY 27,2003

1.

Operating Test Simulator Scenarios

~

Appendix D

Scenario Outline

Form ES-D-I

Facility: Sequoyah

Scenario No.:

1

Op-Test No.:

1

Examiners:

Operators:

Initial Conditions: Piant is at 94% Dower followinq a triD after a refuelina outaue. 1Cmd leakaue in

3 SIG.

Turnover: Maintain current plant Power level and dace excess letdown in service. A Severe

Thunderstorm Warninq is in effect for Hamilton and Rhea counties for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. There is

general increased securitv due to validated threats in the US.

Event

No.

Preinsert

Malf.

No.

1

2

3

4

(N)ormal,

(R

RHOIA

RPI 6K

605A

RXI 8

100%

FWO5B

THO1 A

C

xtivity,

Event

Description

Set up simulator to IC- 9.

B Containment Spray Pump 00s

B MDAFW Pump 00s

A RHR Pump Fails

Phase A fails to actuate

Place Excess Letdown in Service

Tavg Channel fails High

B MFP trips

Large Break LOCA Loop 1

Nstrument, (C)omponent, (M)ajor, (P)RA, (Lbw Power

Appendix D

Operator Actions

Form ES-DP

Time

Position

Applicant's Actions or Behavior

so-62-1 SteDs

I OATC

1 OBTAIN permission from Unit 1 SRO to remove letdown from service

~~

OATC

I OATC I IF excess letdown is to be put in service, THEN PERFORM 1-SO-62-6, AND RETURN.

CLOSE following letdown isolation valves: 1-FCV-62-69, 1-FCV-62-70

SO-62-6 Steps

ENSURE [I-FCV-62-93] is in MANUAL AND OPERATE as needed to regulate charging flow to keep pressurizer

level on program

I OATC I ENSURE following letdown orifice valves CLOSED [l-FCV-62-721,lI-FCV-62-731,ll-FCV-62-74]

I us

NOTIFY RADCON that Excess Letdown is being PLACED in SERVICE

CRO

OATC

us

ENSURE [I-FCV-70-143] CCS water to the excess letdown heat exchanger is OPEN

ENSURE [I-FCV-70-85] Excess Letdown Heat Exchanger CCS flow control valve is OPEN

ENSURE [l-Fl-70-84] is indicating greater than 230 gpm

ENSURE Excess Letdown 3-way divert valve 11-FCV-62-59] is in NORMAL

OPEN [l-FCV-62-54] Cold Leg Loop #3 Excess Letdown isolation valve

OPEN [l-FCV-62-55] Excess Letdown containment isolation valve

OPEN [l-FCV-62-56] slowly to increase excess letdown flow to desired amount, not to exceed 240°F heat

exchanger outlet temperature, as indicated on 1-TI-62-58

NOTIFY RADCON that Excess Letdown has been placed in service

NUREG-1021, Revision 8, Supplement 1

1

Aooendix D

Operator Actions

Form ES-D-2

Op-Test No.:_

Scenario No.:

1

Event No.:

2

Page -1-

of -1-

Event Description: -Tavg

Channel Fails High

I

I us

I OATC

1 CRO

I OATC

I OATC/CRO

I OATC

I us

Applicant's Actions or Behavior

AOP-C.01 Steps

EVALUATE the following Tech SDecs for applicabilitv

EVALUATE EPIP-I, Emeraencv Plan Classification Matrix

DIAGNOSE the failure: Continuous conbol bank movement. Section 2.2

~~

CHECK rod control: ENSURE rod control in MAN, CHECK rod motion STOPPED (YES) br,4;Q j&&

CHECK for instrumentation malfunction

CHECK nuclear instrumentation OPERABLE

CHECK RCS RTDs OPERABLE

CHECK turbine impulse pressure channels OPERABLE

CHECKT-ref OPERABLE, USING TR-68-2B

CHECK Auct T-avg OPERABLE, USING TR-68-26

PLACE Steam Dumps in Steam Pressure Mode

IF pressurizer level does not control in automatic, THEN CONTROL pressurizer level manually

DETERMINE Program T-avg for current reactor power USING TI-28 Figure A.9

NOTIFY MIG of T-avg failure

RESTORE T-avg. to T-Ref: POSITION control rods, ADJUST turbine load, ADJUST RCS boron concentration

CHECK for steam line or feedwater line breaklleak CHECK for rising reactor Dower with dropping T-avg (NO)

CHECK for inadvertent boration flow: CHECK evidence of boration flow INDICATED (NO)

CHECK for inadvertent dilution flow: CHECK evidence of dilution flow INDICATED (NO)

CHECK for rod control system integrity, VERIFY T-avg. and T-Ref matched, PLACE control rods in AUTO

(NO)

NOTIFY Duty Operations Manager of the situation

NOTIFY IM to determine and correct cause of rod control circuit failure

NUREG-1021, Revision 8, Supplement 1

2

Appendix D

Operator Actions

Form ES-D-2

Op-Test No.:-

Scenario No.:

1

Event No.:

3

Page -1-

of -2-

Event Description:

~

"8"

MFP Trips

Applicant's Actions or Behavior

AR-M3B (A2) Steps

I CRO

IF unit > 80% load, THEN , VERlW all auxiliarv feedwater pumps start

II

I us

IF unit > 80% load and one MFP trips, THEN, GO TO AOP-S.01, Loss of Normal Feedwater

II

AOP-S.01 Steps

II

VERIFY turbine runback to less than 73% load (-880 Mwe).

VERIFY control rods inserting automatically to match T-avg and T-ref

ENSURE running main feedwater pump FULLY LOADED, speed controller output at maximum

[M-3, SIC-46-20A or SIC-46-20BI.

ENSURE the following for Auxilialy Feedwater Pumps

I CRO

MDAFW Pumps RUNNING (M-41:

II

I CRO

TDAFW Pump RUNNING [M-3].

II

I CRO

TDAFW Pump LCVs OPEN [M-3].

II

I CRO

MDAFW Pump recirculation valves CLOSED [M-41: FCV-3-400, FCV-3-401

II

I CRO

ENSURE affected Main Feedwater Pump Turbine Condenser isolation valves CLOSED, Condenser B

II

ENSURE ihe seam generator o owoown valves C-OSED [M-41:

RESTORE steam generator levels 10 program level

EVALUATE placing aadifonal condensate pJmps IN SERVICE as necessary (N/A)

ENSURE Ln:1 STAB.-IZED

I CRO

DISPATCH an operator to investigate cause of main feedwater pump trip

II

I CRO

CLOSE Turbine Driven Auxiliaw Feedwater PumD LCVs as rewired IM-31:

II

I CRO

RESET Steam Dump Load Rejection Signal:

PLACE HS-1-103A and 1038, Steam Dump Control, in OFF.

I

I CRO

PLACE HS-I-l03D, Steam Dump Control, in RESET and VERIFY spring return to TAVG.

II

I CRO

VERIFY C-7, LOSS OF LOAD INTERLOCK alarm, DARK [M-4A, 5E]

I

NUREG-1021, Revision 8, Supplement 1

3

Appendix D

Operator Actions

Form ES-DP

CRO

cR0

CRO

cR0

CRO

cR0

Op-Test No.:-

Scenario No.:

1

Event No.:

3

Page -2-

of -2-

Event Description :

" B MFP Trips

SO-3-2 Steps

ENSURE all automatic AFW start signals clear

IF shutdown of A-A AFW pump is required, THEN

PLACE [1-HS-3-118A] to STOP

ENSURE [l-FCV-3-400] recirc isolation valve is CLOSED

IF shutdown of E-B AFW pump is required, THEN

PLACE [l.HS-3-128A] to STOP

ENSURE [l-FCV-3-401] recirc isolation valve is CLOSED

IF the AFW system is to be put in standby, THEN

PLACE the system in standby readiness per Section 5.1 and Appendix A of this Instruction

Time

-

Position

CRO

Applicant's Actions or Behavior

AOPS.01 Steps Continued

ENSURE Steam Dump demand is zero (Will have to place in Steam Press Mode due to previous failure)&K

PLACE HS-I-103A and 1036, Steam Dump Control, in ON.

RESTORE following systems to NORMAL

Auxiliary Feedwater USING 1,260-3-2

Steam Generator Blowdown USING 1,2-S0-15-1

&

I

NUREG-1021, Revision 8, Supplement 1

4

Appendix D

Operator Actions

Form ES-DP

Op-Test No.:-

Scenario No.:

1

Event No.:

4

Page -1-

of -5-

Event Description :-Large

Break LOCA Loop 1

Applicant's Actions or Behavior

E-0 Actions

~~

VERIFY reactor TRIPPED

VERIFY turbine TRIPPED

VERIFY shutdown boards ENERGIZED

DETERMINE if SI actuated (Yes)

VERIFY CCS oumps RUNNING

CHECK ERCW system operation, VERIFY at least four ERCW pumps RUNNING, VERIFY DIG ERCW supply

valves OPEN

VERIFY ECCS pumps RUNNING

VERIFY CCP flow through CCPIT

CHECK RCS pressure less than 1500 psig (YES)

VERIFY ESF systems ALIGNED, Phase A ACTUATED, Containment Ventilation Isolation ACTUATED, Status

monitor panels, Train A status panel 6K, Train B status panel 6L

MONITOR containment spray NOT required (NO)

cr;fi;g fa $/L

ENSURE containment wrav INITIATED

Containment surav uumus RUNNING

Containment spray header isolation valves FCV-72-39

and FCV-72-2 OPEN

Containment spray recirculation valves to RWST FCV-72-34

and FCV-72-13 CLOSED

Containment spray header flow greater than 4750 gpm per train

Panel 6E LIT

ENSURE Phase B valves CLOSED, Panel 6K PHASE B GREEN, Panel 6L PHASE B GREEN

STOP RCPs

MONITOR containment air return fans

WHEN 10 minutes have elapsed, THEN ENSURE containment air return fans are running

NUREG-1021, Revision 8, Supplement 1

5

~

Appendix D

Operator Actions

Form ES-D-2

Op-Test No.:-

Scenario No.:

1

Event No.:

4

Page -2-

of -5-

Event Description :-Large

Break LOCA Loop 1

Time -

Position

OATC

CRO

OATC

OATC/CRO

CRO

USlCRO

CRO

OATC

EXAMINER NOTE

OATC

CRO

OATC

us

EXAMINERNOTE

Applicant's Actions or Behavior

CHECK if main steam lines should be isolated (YES), VERIFY MSlVs and MSlV bypass valves CLOSED

VERIFY MFW Isolation

II

VERIFY AFW Dumas RUNNING. MDAFW . TDAFW

I1

CHECK AFW valve alignment

I

DETERMINE if secondary heat sink available (Yes)

I

MONITOR RCS temperatures

I

ll

IF any RCP running, THEN CHECK T-avg stable at or trending to between 547°F and 552OF (NO)

IF temperature less than 547OF and dropping, THEN PERFORM the following; ENSURE steam dumps and

atmospheric reliefs CLOSED (NO)

IF cooldown continues, THEN, PERFORM the following; CONTROL total feed flow USING EA-3-6, Manual

Control of AFW Flow, MAINTAIN total feed flow greater than 440 gpm UNTIL narrow range level greater

than 10% 125% ADVl in at least one SIG

IF cooldown continues, THEN, CLOSE MSlVs and MSlV bypass valves

II

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

CHECK pressurizer PORVs, safeties, and spray valves

Depending on crew speed, the crew may go back to step 7c when RCS pressure goes

below 1500 psig

MONITOR RCP trip criteria; At least one CCP OR SI pump RUNNING AND RCS pressure less than 1250

psig (NO')

II

A phase B signal should be generated during this portion of the procedure

STOP RCPs

II

CHECK if SIG secondary pressure boundaries are INTACT: All SIG pressures controlled or rising, All SIG

pressures greater than 140 psig (YES)

CHECK if SIG tubes are INTACT (YES)

CHECK if RCS is INTACT: Containment pressure NORMAL (NO)

PERFORM the following: MONITOR status trees, GO TO E-1, Loss of Reactor or Secondary Coolant

11

STA Should ldentify a Transition to FR-P. 1 is required

II

NUREG-1021, Revision 8, Supplement 1

6

Appendix D

Operator Actions

Form ES-DP

rime

Position

OATC

CRO

Scenario No.:

1

Event No.:

4

Page -3-

of 5 -

lp-Test No.:-

vent Description :-Large

Break LOCA Loop 1

Applicant's Actions or Behavior

FR-P.l Steps

MONITOR RWST level greater than 27%.

MONITOR CST level areater than 10%.

OATC

uDLM,NERNoTE

OATC

CHECK RCS pressure greater than 180 psig (NO)

IF at least one RHR pump flow greater than 1500 gpm, THEN RETURN TO procedure and step in effect

S JA Should Identify a Transition to FR-Z. 1 is required

FR-2.1 Steps

MONITOR RWST level greater than 27%.

VERIFY containment ventilation dampers CLOSED, Panel 6K CNTMT VENT GREEN, Panel 6L CNTMT VENT

GREEN

VERIFY Phase A valves CLOSED, Panel 6K PHASE A GREEN, Panel 6L PHASE A GREEN (Action should be

taken to close valves that failed to actuate)

VERIFY Phase B valves CLOSED, Panel 6K PHASE B GREEN, Panel 6L PHASE B GREEN

VERIFY containment spray operation

STOP RCPs

CHECK procedure applicability for containment spray operation, RHR sump recirculation capability AVAILABLE

VERIFY containment spray pumps RUNNING

MONITOR RWST level greater than 8%.

VERIFY containment sDrav suction ALIGNED to RWST

1 OATC

I VERIFY containment smav discharae alianment

OATC

I O A Z

I VERIFY EGTS ooeration. VERIFY EGTS fans RUNNING, VERIFY EGTS oDeration NORMAL

MONITOR containment air return fans, WHEN 10 minutes have elapsed, THEN VERIFY containment air return fan:

RUNNING

~

I OATC

I VERIFY MSlVs and MSlV bvDaSS Valves CLOSED

~ -

CRO

DETERMINE if any S/G Faulted (NO)

I OATC

I DETERMINE if anv S/G Intact. CHECK at least one S/G Dressure, Controlled or rising, and Greater than 140 psig

NUREG-1021, Revision 8, Supplement 1

7

Appendix D

Operator Actions

Form ES-D-2

Position

Op-Test No.:-

Scenario No.:

1

Event No.:

4

Page -4-

of -5-

Event Description :-Large

Break LOCA Loop 1

Applicant's Actions or Behavior

~~

FR-2.1 steos continued

-

Time

~~

OATC

~

~~

~

MONITOR if containment spray should be stopped

CHECK any containment spray pump RUNNING

CHECK containment pressure less than 2.0 psid

OATC I MONITOR if RHR spray should be placed in service (NO)

~

OATC

~~

~

VERIFY containment vacuum relief isolation valves OPEN, FCV-30-46 OPEN, FCV-30-47 OPEN, FCV-30-48

OPEN

E-1 Steps

OATC I RESET Containment Spray

CRO

OATC

1 STOP containment spray pumps and PLACE in A-AUTO

CHECK if S/G secondary pressure boundaries are INTACT: All S/G pressures controlled or rising, All S/G

pressures greater than 140 psig (YES)

MAINTAIN Intact SIG narrow range levels: > 25%, Between 25.50%

VERIFY secondary radiation NORMAL: CHECK the following radiation monitors, including available trends prior to

isolation: Main steamline NORMAL, Condenser exhaust NORMAL, SIG blowdown recorder RR-90-120, pen #I

and pen #2 NORMAL, Post-Accident Area Radiation Monitor recorder RR-90.2686, points 3 (blue), 4 (violet).

5 (black), and 6 (brown) NORMAL. IM-31 (backof M-30)1

CLOSE containment spray discharge valves FCV-72-2 and FCV-72-39.

OATC

fin-,.

I MONITOR if containment vacuum control should be returned to normal. CHECKcontainment Diessure less than

OATC I MONITOR RCP trip criteria; At least one CCP OR SI pump RUNNING AND RCS pressure less than 1250 psig

US

I NOTIFY chem lab to take SIG activity samples every 60 minutes

us

I NOTIFY RADCON to survey main steamlines and SIG blowdown

nATC

I MONITOR pressurizer PORVS and block valves: Power to block valves AVAILABLE, Pressurizer PORVS

.,. . , " I CLOSED, At least one blockvalve OPEN

CRO

I ENSURE Reactor Building auxiliary floor and equipment drain sump pumps (pocket sump pumps) STOPPED

NUREG-1021, Revision 8, Supplement 1

8

Appendix D

Operator Actions

Form ES-D-2

Op-Test No.:-

Scenario No.:

1

Event No.:

1

Page -5-

of -5-

Event Description :-Large

Break LOCA Loop 1

Time

Position

Applicant's Actions or Behavior

-~

E-1 Steps

CRO

II

1 OATC

1 MONITOR SI termination criteria

Secondary heat sink: Narrow range level in at least one Intact S/G greater than 10% 125% ADV]. Or Total feed

flow to Intact SlGs greater than 440 gpm

I1

1 OATC

I RCS subcooling based on core exit TlCs greater than 40°F

OATC

CHECK any containment spray pump running

CHECK containment pressure less than 2.0 psid.

RESET containment spray.

STOP containment spray pumps and PLACE in A-AUTO.

CLOSE containment spray discharge valves FCV-72-2 and FCV-72-39.

MONITOR if containment vacuum control should be returned to normal

II

1 OATC I RCS pressure stable or rising (NO)

I1

I OATC I MONITOR if containment spray should be stopped

II

I OATC

1 CHECKcontainment pressure less than 1.5 psid.

I1

I OATC I VERIFY containment vacuum relief isolation valves OPEN: FCV-30-46, FCV-30-47, FCV-30-48

TERMINATE THE EXERCISE AT TRANSITION TO ES-1.3

NUREG-1021, Revision 8, Supplement 1

9

Page 5 of 36

OPL271 SNRCS

Rev 0

ELAP. TIME

Sim. Setup

This remote function

is insetted when the

CAE file is loaded.

This remote function

is active when the

CAE file is loaded.

CONSOLE OPERATOR'S INSTRUCTIONS

ICIMFIRFIOR #

Reset IC-9

Perform switch check. Allow

the simulator to run for

atleast 3 minutes before

loading CAE or starting the

exercise. This will initialize

ICs.

Load cae ! nrcexamsb

Place simulator momentarily

in RUN, Place 00s

equipment in required

position with tags, Clear

alarms and Return to

FREEZE.

Disable override "RCR".

RCR Off

Important Note -->

MRF csr04 off

IOR zlohs7220a[l] off

IOR zlohs7220a[2] off

IOR zdihs7220a close

IOR zlohs7213a[l] off

IOR zlohs7213a[2] off

IOR zdihs7213a close

IOR zlohs7221a[l] off

IOR zlohs7221 a[2] off

IOR zdihs7221a close

MRF fwr35 out

IOR zlohs3126aa[l] off

IOR zlohs3126aa[2] off

IOR zlohs3126aa[3] off

IOR zlohs3126aa[4] off

IOR zdihs3126aa close

IESCRIPTION

nitialize simulator at 95% RTP.

'lace Mode 1 placards on panel. Update M-5

3lacard with RCS Ce from Chemistry Report.

Steps control banks to proper position. Shutdown

banks should be fully withdrawn.

Ensure operator aid placard is marked NO to core

burnup greater than 12000 MWD/MTU.

Place B Train Week sign on the simulator.

1 B-B Cntmt Spray breaker racked out and pump

tagged for maintenance.

Place a hold order on the 1s-B CS handswitch

and valves US-72-20/21 & 13.

1 B-B MDAFW pump breaker racked out and pump

tagged for maintenance.

Place a hold order on the 16-6 MDAFW pump &

US-3-126 handswitches.

Page 6 of 36

OPL271 SNRCS

Rev 0

This malfunction is

active when the

CAE file is loaded

This malfunction is

active when the

CAE file is loaded

At examiner

discretion, after TS

reviewed, insert this

malfunction

At examiner

discretion, after TS

reviewed, insert this

malfunction

CONSOLE OPERATOR'S INSTRUCTIONS

imf rpl6k605a (none 0)

imf rp16k605b (none 0)

imf rxl8 (none 20000) 100 1

asis

imf fw05b (none 20000)

active when the

CAE file is loaded

At examiner

discretion, before

S/G blowdown

restored, insert this

malfunction

imf th0la (none 20000) 100

1 0

RHR PUMP IA-A TRIPS or Fails to Start

When the Support ASOS/AUO are dispatched to

investigate, wait - 5 min. and report that the

relay target is instantaneous overcurrent and

the pump smells hot.

Tr A Phase A Relay Failure.(SYS

77/blowdown/sample)

Tr B Phase A Relay Failure.(SYS

77/blowdown/sample)

T-AVE CONTROL SIGNAL FAILURE

MAIN FEED PUMP 1 B TRIP

When personnel dispatched to investigate, wait

- 3 minutes and report that appears to be a

problem with oil pressure switch.

Steam dumps should be put in steam pressure

mode not Tavg due to previous failure.

LOCA Hot Leg Break Loop 1

1. Ensure recorders are inking and recording and ICs is active and updating.

2. Assign Crew Positions: (Assign positions based on evaluation requirements for personnel) Log

positions in Attachment A.

PR - Procedure Reader

OATC - Reactor Operator

CRO - Balance of Plant Operator

3. Provide the PR with a copy of the Shift Turnover.

4. Direct the shift crew to review the control board and take note of present conditions, alarms, etc.

5. Critical Tasks (CTs) are noted with (CT#) under the event header for each page. The crew position

which should perform specific actions to ensure a CT is satisfied will be noted with the symbol 0.

Page 32 of 36

OPL271 SNRCS

Rev 0

SIMULATOR EXERCISE GUIDE

Rx Power L

MWD/MTU Sass

Unit 1

I

Train B Week

1

Place excess letdown in service in preparation for maintenance on NRHX then maintain current

I

I Power Level.

I

3.6.2.1 for 1 B-B CS pump.; Tagged for maintenance to replace motor.

I

3.7.1.2.a for 1 B-B MD AFW pump.; Tagged for maintenance to replace pump.

There is general increased security due to validated threats in the US.

The National Weather Service has announced a severe storm warning for Hamilton and Rhea

I cniinties. It is to remain in effect for 2 more hours.

I

~

There is a small 140 aPd) S/G tube leak in #3 S/G. Chem lab is sampling and monitoring.

I

. -.

I

~.

I

Page 34 of 36

OPL271SNRCS

Rev 0

U1 RCS

U2 RCS

SIMULATOR EXERCISE GUIDE

PPm

1 3 4

Today I Now

1.71 -2.01

1.86

PPm

3.1 9

Today I Now

3.02-3.34

3.18

Operations Chemistry Information

Primary to Secondary Leakrate Information (Total CPM RM-90-99/119)

Indicator

I Units I

u1

I DateITime I

u2

I

Date/Time

I

Background onRM-99-

40

Today I Now

40

Today I Now

119

Key Parameters are RCS Lithium & Hydrogen, SGBD Sodium, Sulfate & Molar Ratio, and FW

Iron

ES-501

Post-Examination Check Sheet

Form ES-501-1 (R8, SI)

2.

Facility written exam comments reviewed and incorporated and

NRC grading completed, if necessary

Operating tests graded by NRC examiners

3.

Task Description

N/A

1

Date

ComDlete

4.

NRC Chief examiner review of written exam and operating test

grading completed

5.

Responsible supervisor review completed

I

1.

Facility written exam comments or graded exams received and

verified complete

3/3/03

3/4/03

N/A

6.

Management (licensing official) review completed

1

3 / 7 1 a s

7.

8.

Facility notified of results

License and denial letters mailed

9.

I O .

Reference material returned after final resolution of any

N/A

Examination report issued (refer to NRC MC 0610)

ML032450477

Text

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