Text

February Retake Exam 50-327/2003-301 & 50-328/2003-301, Final Simulator Scenarios
	ML032450486
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: ML032450486 (11)
	v • d • e

Final Submittal

SEQUOYAH RETAKE EXAM

50-327 & 50-328/2003-301

FEBRUARY 27,2003

Appendix D

Scenario Outline

Form ES-D-1

(AN

Facility: Sequovah

Scenario No.:

1

Op-Test No.:

1

Examiners:

Operators:

Initial Conditions:

3 SIG.

Plant is at 94% power following a trip after a refuelina outaue. 10 gpd leakage in

Turnover: Maintain current plant power level and place 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

aeneral increased securitv due to validated threats in the US.

Event

Malf.

Event

No.

Type*

Description

Set up simulator to IC- 9.

Preinsert

I B Containment spray Pump oos

I

Preinsert

B MDAFW Pump 00s

Preinsert

C

A

RHR Pump Fails

Preinsert

RP16K

C

Phase A

fails to actuate

RHOlA

605A

1

-

N

Place Excess Letdown in Service

(RO)

100%

(RO)

2

RX18

I

Tavg Channel fails High

I

(N)ormal, (R)eactivity, (I)nstrument,

(C)omponent, (M)ajor, (P)RA, (L)ow Power

Appendix D

Operator Actions

Form ES-D-2

Op-Test No.:-

Scenario No.:

1

Event No.:

1

Page -1-

of -1-

Event Description: -

Removing Letdown from ServicelPlace Excess Letdown in Service

Time

-

Position

Applicant's Actions or Behavior

-

SO-62.1 Steps

OATC

OBTAIN permission from Unit 1 SRO to remove letdown from service

OATC

1 IF excess letdown is to be Dut in service, THEN PERFORM 1-SO-62-6, AND RETURN

~

OATC

us

OATC I ENSURE following letdown orifice valves CLOSED: v-FCV-62-721,ll-FCV-62-73], 11-FCV-62-741

SO-62-6 Steps

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

level on program

NOTIFY RADCON that Excess Letdown is being PLACED in SERVICE

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

CRO

ENSURE 11-FCV-70-851 Excess Letdown Heat Exchanger CCS flow control valve is OPEN

CRO

1 ENSURE H.FCV-70-143] CCS water to the excess letdown heat exchanger is OPEN

ENSURE [I.Fl-70-841 is indicating greater than 230 gpm

us

NOTIFY RADCON that Excess Letdown has been placed in service

OATC

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

OATC

1 OPEN [I-FCV-62-551 Excess Letdown containment isolation valve

~~

OATC

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

NUREG-1021, Revision 8, Supplement 1

1

Appendix D

. _ _

Operator Actions

Form ES-D-2

us

CREW

1) Op-Test No.:-

Scenario No.:

1

Event No.:

2

Page -1-

of -1-

EVALUATE the following Tech Specs for applicability

EVALUATE EPIP-1, Emergency Plan Classification Matrix

DIAGNOSE the failure: Continuous control bank movement, Section 2.2

I Event Description: -Tavg

Channel Fails High

OATC

Time

Position

Applicant's Actions or Behavior

AOP-C.01 Steps

CHECK for instrumentation malfunction

CHECK nuclear instrumentation OPERABLE

CHECK RCS RTDs OPERABLE

~

OATC

CRO

OATC

I1

I OATC

I CHECK rod control: ENSURE rod control in MAN, CHECK rod motion STOPPED (YES)

CHECK T-ref OPERABLE, USING TR-68-26

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

~

us

OATC/CRO

OATC

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 breakneak: CHECK for rising reactor power with dropping T-avg (NO)

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

II

I CRO

1 CHECK turbine impulse pressure channels OPERABLE

OATC

us

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

11

'

1 OATC

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

II

I OATC

I CHECKfor inadvertent dilution flow: CHECK evidence of dilution flow INDICATED (NO)

NUREG-1021, Revision 8, Supplement 1

2

Appendix D

Operator Actions

Form ES-D-2

Position

CRO

us

Op-Test No.:-

Scenario No.:

1

Event No.:

3

Page -1-

of 2 -

Event Description: -

" E MFP Trips

Applicant's Actions or Behavior

AR-M3B (N)

Steps

IF unit > 80% load, THEN, VERIFY all auxiliaty feedwater pumps start

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

OATC

CRO

I AOP-S.OI Steps

~

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-46-206].

ENSURE the following for Auxiliary Feedwater Pumps

CRO

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

~

CRO

PRO

TDAFW Pump RUNNiNG [M-3].

TDAFW Pump LCVs OPEN lM-31.

MDAFW Pumo recirculation valves CLOSED lM-41: FCV-3-400, FCV-3-401

CRO

I MDAFW Pumps RUNNING [M-4]:

_____

CRO

us

CRO

us

RESTORE steam generator levels to program level

EVALUATE placing additional condensate pumps IN SERVICE as necessary (NIA)

ENSURE unit STABILIZED

DISPATCH an operator to investigate cause of main feedwater pump trip, places 1-HS46-27A & 30A in PTL

CRO

I ENSURE affected Main Feedwater Pump Turbine Condenser isolation valves CLOSED, Condenser 8

CRO

I ENSURE the steam generator blowdown valves CLOSED [M-41:

CLOSE Turbine Driven Auxiliary Feedwater Pump LCVs as required [M-3]:

RESET Steam Dump Load Rejection Signal: (May decide not to do this step, since in Stm. Press. Mode)

PLACE HS-1-103A and 1036, Steam Dump Control, in OFF.

PLACE HS-1-103D, Steam Dump Control, in RESET and VERIFY spring return to TAVG.

CRO

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

NUREG-1021, Revision 8, Supplement 1

3

Appendix D

Operator Actions

Form ES-D-2

Op-Test No.:-

Scenario No.:

1

EventNo.:

3

Page -2-

of -2-

Event Description :

" B MFP Trips

I

I w

I

NUREG-1021, Revision 8, Supplement 1

4

Appendix D

Operator Actions

Form ES-D-2

Op-Test No.:-

Scenario No.:

1

Event No.:

4

Page -1-

of -5-

Event Description :-Large

Break LOCA Loop 1

Position

OATC

CRO

CROlOATC

CRO

CROlOATC

OATC

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 pumps 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 Dane1 6K. Train B status Dane1 6L

MONITOR containment spray NOT required (NO)

ENSURE containment spray INITIATED

Containment spray pumps 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

~

CRO

~~

~

Operator Actions

VERIFY MFW Isolation

VERIFY AFW pumps RUNNING, MDAFW, TDAFW

~~

~

Form ES-D-2

OATC

Op-Test No.:-

Scenario No.:

1

Event No.:

4

Page -2-

of 5 -

Time -

__

-

.__

MONITOR RCS temperatures

Position

Applicant's Actions or Behavior

OATC

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

~

OATC

EXAMINER NOTE

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 Dsia

CRO

I CHECK AFW valve alignment

OATC

CRO

1 DETERMINE if secondary heat sink available (Yes)

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

psig (NO*)

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

STOP RCPs

OATC

OATC/CRO

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

1 atmosDheric reliefs CLOSED (NO)

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

IF cooldown continues, THEN, PERFORM the following; CONTROL total feed flow USING EA-3-8, Manual

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

CRo

I than 10% 125% AD4 in at least one SIG

US/CRO

I IF cooldown continues, THEN, CLOSE MSlVs and MSIV bypass valves

CRO

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

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

Dressures greater than 140 wig (YES)

CRO

I

CRO

1 CHECK if S/G tubes are INTACT (YES)

1 SJA Should Identify a Transition to FR-P. 1 is required

UlMINER NOTE

NUREG-1021, Revision 8, Supplement 1

6

Appendix D

Operator Actions

Form ES-D-2

escription :.

Scenario No.:

1

Event No.:

4

Page -3- of -5-

- Large Break LOCA Loop 1

Position

OATC

CRO

OATC

EXAMNERNOTE

OATC

CRO

Applicant's Actions or Behavior

FR-P.l Steps

MONITOR RWST level greater than 27%

MONITOR CST level greater than 10%.

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 (E-I)

STA Should /dentify a Transition to FR-Z. 1 is required (May transition to ES-1.3)

FR-Z.l 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 spray suction ALIGNED to RWST

VERIFY containment sDrav discharge alionment

VERIFY EGTS operation, VERIFY EGTS fans RUNNING, VERIFY EGTS operation NORMAL

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

RUNNING

VERIFY MSlVs and MSlV bypass valves CLOSED

DETERMINE if any SIG Intact, CHECK at least one SIG pressure, Controlled or rising, and Greater than 140 psig

DETERMINE if any SIG Faulted (NO)

NUREG-1021, Revision 8, Supplement 1

7

~

Appendix D

Operator Actions

Farm ES-D-2

Op-Test NO.:-

Scenario No.:

1

EventNo.:

4

Page -4-

of -5-

Event Description :-Large

Break LOCA Loop 1

Time I Position

I

1 OATC

I OATC .+

OATC

I OATC

1 OATC +

I OATC

1 CRO

I CRO

-1 CRO

Applicant's Actions or Behavior

FR-Z.l steps continued

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

~

MONITOR if containment spray should be stopped

CHECK anv containment sorav 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, CHECK containment pressure less than

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

OPEN

E-I Steps

MONITOR RCP triD criteria: At least one CCP OR SI pump RUNNING AND RCS pressure less than 1250 psig

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

pressures areater than 140 Dsia (YES)

MAINTAIN Intact SIG narrow range levels: > 25%, Between 25 - 50%

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

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-90-2W points 3 (blue), 4 (violet),

5 (black). and 6 (brown) NORMAL. IM-31 (back of M-30)I

NOTIFY chem lab to take SIG activity samples every 60 minutes

~~

~~~~~

~~

NOTIFY RADCON to survey main steamlines and SIG blowdown

MONITOR pressurizer PORVs and block valves: Power to block valves AVAILABLE, Pressurizer PORVs

CLOSED, At least one block valve OPEN

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

Time

Op-Test No.:-

Scenario No.:

1

Event No.:

1

Page -5-

of -5-

Event Description :-Large

Break LOCA Loop 1

Position

Applicant's Actions or Behavior

E 4 Steps

OATC

CRO

OATC

II

I OATC I MONITOR SI termination criteria

II

RCS subcooling based on core exit T/Cs greater than 40°F

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

flow to Intact S/Gs greater than 440 gpm

RCS pressure stable or rising (NO)

MONITOR if containment spray should be stopped

CHECK any containment spray pump running.

~

OATC

II

I OATC I CHECK containment pressure less than 2.0 psid.

II

RESET containment spray.

STOP containment spray pumps and PLACE in A-AUTO.

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

OATC

N

1 OATC

1 MONITOR If containment vacuum control should be returned to normal

n

CHECK containment pressure less than 1.5 psid.

VERIFY containment vacuum relief isolation valves OPEN: FCV-30-46, FCV-3047, FCV-3048

II

I TERMINATE THE EXERCISE AT TRANSITION TO ES-1.3

II

I

NUREG-1021. Revision 8, Supplement 1

9

ML032450486

Text

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