ML032340709

Administrative Topics Outline

Form ES-301-1

Facility: McGuire

Examination Level (circle one): RO / SRO

Operating Test Number:

Date ofExamination: Weeks of June 16 and 23,2003

Administrative Topic

Desw@w+ (see Note)

w

. .

&La

Conduct of Operations

Conduct of ODerations

A,1,B

EauiPment Control

A73

Radiation Control

Emerqency Plan

Describe activitv to be performed-

Evaluate Overtime Eligibility

(Modified)

Calculate ECP with an additional ECB calculation

Evaluate a Work Order for Clearance to do Work.

(New)

Evaluate Liquid Waste Release with Fault

(New)

Evaluate Condition for PARS

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless

ihev are retakinq only the administrative topics, when 5 are required.

22 of 27

NUREG 1021, Draft Revision 9

Administrative Topics Outline

Form ES-301-1

~~

~

Facility: McGuire

Examination Level (circle one): RO I SRO

Operating Test Number:

Date ofExamination: Weeks of June 16 and 23, 2003

Administrative Topic

-(see

Note)

A.1.a

Conduct of Operations

v

. .

A.1.b

Conduct of Operations

A2

Eauiprnent Control

A73

Radiation Control

A 4

Emeraencv Plan

Describe activitv to be performed-

~

~~

~

Calculate QPTR with an Inoperable Power Range Instrument

and Make Technical Specification Evaluation

Calculate ECP

Identify Boundaries for Tagout

(New)

Utilizing a Survey Map, Calculate the maximum permissible Stay

Time with the Alert limit ofthe Duke Power Basic Administrative

limits.

NOTE All Items (5 total) are reqdred for SROs KO applica<!s require onlv 4 items unles.?

they are retakinq only the adrn!nlstrativetoplcs when 5 are requireo

-

22 of 27

NUREG 1021, Draft Revision 9

ES-301 control Room/In Plant Systems Outline

Form ES-301-2

system / JPM Title

L,'

'v

Safety

Type Codes*

Function

a. Respond to a Leak on RHR While in Mid-loop

(SROU)

b. Calculate Boric Acid Pot and Perform Manual

D,S,L

4P

D,A,S

1

Makeup

c. Synchronize Main Generator (New Voltage

d. Align for Cold Leg Recirculation

e. Isolate Stuck Open PORV (Immediate Action JPM)

Regulator)

(SROU)

N,S,A,L

4s

D,A

2

D,A

3

7

I

D,A

I

f. Respond to a Failure of Power Range N-42

g. RN Alignment after a Loss of AC Power on Unit

Start Up Unit 2 Lower Containment Ventilation

2

(SROU)

h.

D, C

8

D,C

5

systems

In-Plant Systems (3 for RO, 3 for SRO-I; 3 or 2 for SRO-U

~~

~

a. Establish Reactor Coolant Pump Seal Injection

b. Start 1A Hydrogen Analyzer

from SSF

(SROU)

c. Manually Start 'H' Instrument Air Compressor

for 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months run. (SROU)

D

2

N, A, R

5

D

8

NUREG-1021, Draft Revision 9

Operating Test Quality Checklist

Form ES-301-3

\\u

'ZDOJ

Facility: M t &i~ci*@

Date of Examination: % k C

Operatin

1. GENERAL CRITERIA

b.

There is no day-tc-day repetition between this and other operating t&o

be add

during this examination.

The operating test shall not duplicate items from the applicanl

Overlap with the written examination and between different PE

is within acceptable limits.

It appears that the operating test will differentiate between MI

C.

d.

2. W

A

L

K

.

T

H

R

O

U

G

H

~

a

Each JPM includes the foliowing. as applicable:

. system response and othq

- statements describing ii

~ criteria for successful o

- identification of CnWI 1

d. NRC Supervisor

M m e L

~

NOTE

The facility signature is not applicable for NRCdeveloped tests.

Independent NRC reviewer initial items in Column "c:" chief examiner concurrence required.

__

NUREG-1021, Draft Revision 9

24 of 27

u

I

ii

I

Simulator Scenario Quality Checklist

Form ES-301-4

QUALITATIVE ATTRIBUTES

Initials

a

b'

1.

Tne niua wno;rions are realist c. 'n that some eqL'pment and/or instrumentation may De OJt of

SeN:ce. bJ1 it OOeS not cJe tne operalors nto expected evenu.

2.

The scenarios wnsist mostly of related events.

EP- @L

3.

Each event description wnsists of

the point in the scenario when it is to be initiated

the maifunction(s) that are entered to initiate the event

the symptomstcues that will be visible to the aew

the expected operator actions (byshift position)

the event termination point (if applicable)

4

ho more than one non-mecnanisuc fa Jre (e 9.. pipe brea4 is inwrporaleo nlo me Scenar 0

w mod1 a credib e precea ng ncioent SLCn as a seism c event

5.

The events are valid with regard to physics and thermodynamics.

I chldc

Lb CN

6.

Seqdencng and tim ng of events s reasonaole. ana allows the exam.nat on team to obta n

wmpiete eva Jat on resLlls WmmensJrale wdh the scenar o ob:ectives.

If lime wmpression techniqJes are Jseo. tne scenario sLmmary c early so inoicates. Operators

nave sLffc'ent lme to carry out expected acuviues without JnoJe t me wnstrainrs. CJes are

7

The simulator modeling is not altered.

L4. coc

6.

9.

The scenarios have been validated. ~ ~ ~ ! r s ! ~ a ~ ~ ~ t ~ . l O . . ~ F . ~ . . ~ . ~ ~ 4 6 ~ ~ ) ~ . ~ . ~ y

open simulator

performance deficiencies have been evaluated to ensure that functional fidelity is maintained

while running the planned scenarios.

d

10

Every operator w.II be evaluate0 Jsmg at least one new or significantly mootfed scenar 0 AI

other scenar os have been altere0 n accordance w.th Section 0 45 of ES-301

I

11.

All individual operator competencies can be evaluated, asverified using Form ES-301-6 (submit

the form along with the simulator scenarios).

12

Eacn applicant will be sign.ficanily involveo .n the min mLm nmber of trans ents and evenls

spec fiea on Form ES-301-5 (sJbrn.1 rhe form w tn Ihe simL a m Scenar os)

I

.I.,

13.

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

118 Idr-

I

TARGET QUANTITATIVE AlTRlBUTES (PER SCENARIO, SEE SECTION

Actual Attributes

--

D.W52d)

1.

Total malfunctions (5-8)

7 / 7 /

2.

Malfunctions afler EOP entry (1-2)

2/21> a&

3.

Abnormal events (2-4)

41% 4

I%

d'

4.

Major transients (1-2)

2 / L / I /A OJC

..,

5.

EOPs enteredtrequiring substantive actions (1-2)

2/2./2 ck. (b(

6.

EOP contingencies requiring substantive actions (0-2)

0 t D l 0

w l

7.

Critical tasks (2-3)

2 1212

25 of 27

NUREG-1021, Draft Revision 9

Transient and Event Checklist

Form ES-301-5

I

..-,,

OPERATING TEST NO.:

Reactivitv

1"

Normal

0

21

I strument

omponen

Maior

1

c

AsRO

e

I

u

I

Reactivity

0

Normal

1 '*

1, sf

1

21

1

7

I strument

omponen

Major

2-6

c

s,piu

e

Instructions:

(1)

(2)

Enter the operating test number and Form ES-D-1 e\\ent numbers for

each evolution type.

Reactivity manipulations may be conducted under normal or controlled

abnormal conditions (refer to Section D.45.d) but must be significant per

Section C.2.a ofAppendix D. * Reactivity and normal evolutions may be

replaced with additional instrument or component malfunctions on a one-

for-one basis.

Whenever practical, both instrument and component malfunctions should

be included; only those that require verifiable actions that provide insight

to the applicant's competence count toward the minimum requirement.

(3)

Author:

Charles Sawyer

NRC Reviewer:

Richard S. Baldwin

26 of 27

NUREG-1021, Draff Revision 9

Transient and Event Checklist

Form ES-301-5

Reactivity

0

Normal

I *

1

2:

1

7

I strument

omponen

Major

2-6

I

SRO-U

8

3-4

28,

7

Author:

Charles Sawyer

NRC Reviewer:

Richard S. Baldwin

26 of 27

NUREG-1021, Draft Revision 9

-\\

Competencies Checklist

Form ES-301-6

SRU 1

-

1

R m t

Competencies

v

Interpret I Diagnose Events

and Conditions - -

Comply With and

Use Procedures (1)

Operate Control

Boards (2)

Communicate and

Interact-

Demonstrate Suoervisow

A

NRC Reviewer:

_

27 of 27

NUREG-1021, Draft Revision 9

Competencies Checklist

F

o

~

ES-301-6

b'

nse type and enter one or more event numbers that will allow the

/

NRC Reviewer:

27 of 27

NUREG-1021, Draft Revision 9

Competencies Checklist

F

o

~

ES-301-6

--1

.. ,.

u

.

..,,

.&.,

ctions:

one or more event numbers that will allow the

for every applicant.

I

NRC Reviewer:

27 of 27

NUREG-1021, Draft Revision 9

I

Competencies Checklist

F

o

~

ES-301-6

nse type and enter one or more event numbers that will allow the

petency for every applicant.

NRC Reviewer:

27 of 27

NUREG-1021, Draft Revision 9

I ES-401

Written Examination

Form ES-40136

i/

I

ii

L .-'

Quality Checklist

-acility: McGuire

Exam: Weeks of June 16 & 23,2003

Exam Level:

I

7.

Between 50 and 60 percent of the questions on

randomlv selected KiAs suwort the hisher

c.ognit.!vc.!s!vc!.s;

enter the actual .R.O./.S.R.O

)

8.

Referenceslhandouts provided do not give away answers

cp. &C

9.

Question content conforms with specific KIA statements in the previously

approved examination outline and is appropriate for the Tier to which they

are assigned: deviations are justified

Question psychometric quality and format meet ES, Appendix B,

guidelines

items; the total is correct and agrees with value on cover sheet

& ($1

10.

11.

The exam contains ~ t t I . e . r e ~ . u ~ ~ ~ e d . . n u r r ~ b . ~ . . ~ f

one-point. multiple choice

,&?

Date

4-/7.0.

lhaj-aa

d / /& ,OJ

q - I l - b S

a. Author

b. Facility Reviewer r)

CIWcbli

d. NRC Regional Supervisor A I C & EL

c o r d

c. NRC Chief Examiner (#) &&&o

5. % L04J,n) ? A A-

f. ER i S . I C J ) U C , a

Note:

The facility reviewer's initialskignature are not applicable for NRC-developed examinations.

3004 34

NUREG-1021, Drafi Revision 9

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ES-403

Written Examination Grading

Form ES-403-1

Quality Checklist

Facility:

McGuire

Date of Exam: June 30,2003

Exam Level: W/SRO

Initials

ling examinations checked to ensure that grades

Printed Name / Signature

Date

a. Grader

Richard S.

yd=J

b. Facility Reviewer(*)

N/A

c. NRC Chief Examiner (*) @hL,,

0 Lch

1 1

"d-

0-

d. NRC Supervisor (*)

/*)ICWOEL

E a u w / m . & /

f G j l f ;

712 Y/s,

(*)

The facility reviewer's signature is not applicable for examinations graded by the

NRC; two independent NRC reviews are required.

5of5

NUREG-1021, Draft Revision 9

ES-403

Written Examination Grading

Form ES-403-1

Quality Checklist

Item Description

1.

Clean answer sheets copied before grading

Date of Exam: June 30,2003

Exam Level: R O 1 m

Facility:

McGuire

Initials

I

a

&

documented

Applicants' scores checked for addition errors

(reviewers spot check > 25% of examinations)

Grading for all borderline cases (80 +/- 2% overall and 70 +/-

4% on the SRO-only) reviewed in detail

All other failing examinations checked to ensure that grades

are justified

Performance on missed questions checked for training

questions missed by half or more of tho applicants

3.

4.

5.

6.

deficiencies and wording problems; evaluate validity of

Date

m

w

M

P%

7 / Z B j 3 3

Uh\\w+, O;;h&>)

~ / /c &@&A&--

/z </O>

a. Grader

Richard S. Baldwin

b. Facility Reviewer(*)

N/A

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

P7lCUc)EL E . E A P ) S I P S / 4 E : i z . . 2 k -

712 6

/Q>

(*)

The facility reviewer's signature is not applicable for examinations graded by the

NRC; two independent NRC reviews are required.

NUREG-1021, Draft Revision 9

ES-501

Post-Examination Check Sheet

Form ES-501-1

Task Description

1.

Facility written exam comments or graded exams received and

verified complete

Date

Complete

7/08/03

~

2.

Facility written exam comments reviewed and incorporated and

NRC grading completed, if necessary

Operating tests graded by NRC examiners

3.

4.

NRC Chief examiner review of written exam and operating test

grading completed

5.

Responsible supervisor review completed

711 6/03

7/28/03

7/29/03

5.

7.

Management (licensing official) review completed

License and denial letters mailed

7/30/03

210f 23

3.

Facility notified of results

3.

Examination report issued (refer to NRC MC 0612)

NUREG-I 021, Draft Revision 9

7/30/03

8/7/03

IO.

Reference material returned after final resolution of any

a p p e a I s

NA

NRC EXAM

2003

SCENARIOS

Appendix D

Scenario Outline

Form ES-D-1

Event

Malf.

No.

1

2

3

4

5

6

7

Facility: McGuire

Scenario No.: 1

Op-&t NO.:

Examiners:

Operators:

Event

Type*

Description

N

C

I

C

N

(BOP) Establish Normal Letdovm

C

M

ATWWLoss of Heat Sink

(RO) Main turbine Bearing Oil Pump Test

(BOP) 1 NV-137 Fails to Hold UP Tank (ARP)

(RO) S/G 'B' Steam Pressure Channel 1 Fails

(BOP) ET6 Blackout due to Ground Fault

(RO) '1 B' FWPT Trips and Runback to 50%

Initial Conditions: 100% Power, 'B' Train Components in Service, 'IA' Auxiliary Feedwater

Pump is tagged, 'IA" Diesel Generator is tagged, thunderstorms are in the area

Second FWPT trips afier crew settles out in AOP.

No Auto SI, Failure of Auto Turbine Trip

TD CA pumps trips on overspeed

Failure of turbine to runback automatically

(N)ormal,

(R)eactidty,

(I)nstrument,

(C)omponent,

(Major

4004 41

NUREG-1021, Drat? Revision 9

PROGRAM: McGuire Operations Training

MODULE:

TOPIC:

Initial License Operator Training Class 21

Nuclear Regulatory Commission Simulator Exam

Scenario 1

REFERENCES:

1.

2.

3.

4.

5.

i

d

6.

7.

8.

9.

10.

McGuire Technical Specifications

PTIl /B/4250/028

APIA /A/5500/03

Load Rejection

APII lA/5500/06

APll /A/5500/07

AP/1/A/5500/12

EP/l/A/500O/E-O

EP/llA/5000/FR-S.1

EPll/A/5000/FR-H.I

RP/O/A/5700/00

Classification of Emergency

Main Turbine Bearing Oil Pump Test

Loss of SIG Feedwater

Loss of Electrical Power

Loss of Letdown, Charging or Seal Injection

Reactor Trip or Safety Injection

Response to Nuclear Power Generation/An/VS

Response to Loss of Secondary Heat Sink

n

Author:

Facility Review:

April 3,2003

Rev.1

1

i/

1.

2.

3.

4.

5.

6.

7.

a.

EVENT SUMMARY

Main Turbine Bearing Oil Pump Test.

INV-137 fails to HUT.

SIG B Channel 1 Steam Pressure fails High. Enter AP-6

IETB BIO. Ground fault on bus. Enter AP-7

Place Normal Letdown in service, per AP-12

Load Rejection due.to trip of 1B FWPT with a failure of the Turbine to runback. Enter AP-03

ATWS. Failure of Auto & Manual Rx trips, failure of Auto turbine trip on loss of 2nd FWPT. Enter E-0

and transition to FR-S.1.

Loss of Heat Sink. A MDCA tagged in Initial Conditions, B MDCA unavailable due to BO on IETB

and TDCA trips on over speed when started. Enter FR-H.l

2

'u'

L'

Bench Mark,

Sim. setup

_

I

SIMULATOR OPERATOR INSTRUCTIONS

IC - 130

RUN

Update Status Board,

Setup OAC

Setup ICCM, Turbine

Displays, &Trend

Recorders.

Check Rod Step

Counters agree with rod

positions

(M) EPQOOIA

Set = 1

(LOA) CA009

Set = F

(M) IPEOOIA

(M) IPEOOIB

(M) IPE002A

(M) IPE002B

(M) DEH002B6

(M) DEH003A

.

DESCRIPTIOI~~.

,.

.

See Shift Turnover Information

LOSS of DIG "1A Control Power

Rackout breaker for "1A Auxiliary Feedwater Pump

Defeats automatic and manual reactor trips

Blocks all turbine runbacks

Failure of Auto Turbine tripped blocked

3

I

Bench Mark

ACTIVITY

'

(M) CA005

(M) ISE002B

--+---

Freeze.

, Fill out the NLO's

Available section of

Shift Turnover Info.

Prior to Crew

RUN

Briefing

DESCRIPTION

Turbine Drlven AFW pump trips on over speed

Failure of automatic Safety Injection - both trains

~~

-

rew Briefing

1. Assign Crew Positions based on evaluation requirements

?, Review the Shift Turnover information with the crew.

3. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

T-0

At direction of

examiner

At direction of

examiner

At direction of

examiner

Begin Familiarization

Period

(OVR) NV070D

Select: ON

(XMT) SM016

Ramp = 10

Set = 1300, insert

(M)EP008B

Insert

(M) KC008C

Set = 0. insert

(M) KC007D

Set = 0, insert

INV-137 to HUT

'ails SIG " 6

Steam Pressure Channel 1 HIGH

.oss of 1 ETB due to ground Fault

illow manual closing of 1 KC18B and 1 KC-228B

Bench Mark

At direct.on of

examiner

Af direction of

examiner

Set = 100, insert

(M) LFOO3B

(M) IWE002A

Set - 125

(M) LF003A

(MAL) IPEOOIA

(MAL) IPEOOIB

(MAL) ISE007A

Block Both

(MAL) ISE007B

Block Both

Terminate the sceni

.

..

'

' DESCRIPTION

'

.

,

..

..

.

~. .

1

I

j .

. .

..

,

I .

Initiates a oil leak on 1B FWPT

Trips the "16 FWPT if necessary - Initiates an turbine

runback - RO must manually runback the turbine

Speeds up '"A

FWPT

Trips the '"A

FWPT and initiates an ATWS

Delete -Opens reactor trip breaker 30 seconds after

request by operator

Allows feedwater to be reset in H-I

upon direction of Chief Examiner

5

I

EVENT 1: . Normal Operations - PT/I/B/4250/028 Main Turbine Bearing Oil Pump Test

Ro

Pump

Start Emerg Brg Oil Pump

Stop and ensure in Auto Emerg Brg Oil Pump

Verify Acceptance Criteria met.

6

I

Event 2:

INV-137 Fails to HUT position

I

Event 3:

Steam Generator1B Steam Pressure Channel 1 Failure HIGH

Pos.

Expected Actions/ Behavior

Comments

Per annunciator response and API06

the operator will swap failed channel tc

Refer to annunciator responses

A-2

operable channel

c-2

Enters API06 Loss of S/G Feedwater

Places Feed Regulator to Manual

Restores SIG level to program level

Checks the following channel indicating the

same:

Feedflow

Selects operable channel

Steam Flow

SIG Level

Checks the reactor trip breakers closed

lmmediafe Action

Immediate Action

Yes

Monitor SIG NR Level

If at any time SIG NR Level approache

17% or 83%, then trip Reactor

~~

SRO \\Contacts WCC to have WR written, have I&E

IFailure will not be repaired

investigate and repair failed channel and

evaluate T.S..

Exit procedure

Tech Spec 3.3.2.4.d.1 I3.3.2.d.2 I

3.3.4.3.b 13.3.3.19 116.10.1

Check CMICF feeding SIG

At this time 1 ETB blacks out

8

SIG level stable or trending to program

Checks NC temperature with NC pumps on

stable or trending to programmed temperature

When the following are met then return affected

SIG CF control to automatic

1, Selected control channels indicated correctly

Feed flow

Steam flow

SIG level

2. Affected SIG level restored to program level

3. Automatic control is desired

Checks proper CF alignment

Event 4:

B/O 1 ETB Ground Fault

Pos.

Expected Actions/ Behavior

~~

Crew

Recognizes loss of operating train "ET6

Enters AP/07 Case 2

Checks bus energized and sequencer applying

loads

If both NV pumps off, Then isolate NORMAL

letdown.

Start opposite train:

NVpump

KCpump

RN'pump

Go to step 3

Verifies NO Safety Injection has occurred

If both NV pumps off then isolate:

Excess letdown

ND letdown

If any pump was manually started per step 1 go

I

lign KC as follows:

Places 1KC-51A to AUTO

to step 5

Check D/Gs - OFF

1

1KC3A

Ensures the following are open

. 1KC-345A

thermal barrier valves open

raise KC flow to KF Hx by opening 1KC-14:

Ensures KC flow is less than 4000 gpm per

Check ND system in RHR mode at time of B/O

Check 1A RN pump - Running -YES

Ensure 1 RN-86A is open

operating KC pump

Chec6s any charging pump - Running - YES

I

i

Notifies Unit 2 RO to start 2A RN pump

Throttle IRN-89A to desired cooling

Comments

,.

imediate Acfions

he DIG will not start due to a ground

ult on 1 ETB.

imediate Actions

train NV pump will be on

S

o Go to steD 7

XAMINER CUE:

4 RN pump is running

9

Pos.

. Expected Actions/ Behavior, (' :, '

.:.. " '

,, Comments - . :

.

2'

?

. .

. . , .

' I

.

3

".

L

. "

Checks B/O on 1 ETA

No, go to step 22

Dispatches operator to close:

IKC-2288

IKC-18B

Checks 1B NO train - was in RHR mode

No. Go to step 29

10

Checks normal letdown - IN SERVICE

No, have BOP place letdown back in

service per AP12.

Will hand off to BOP AP-12 and direct him to

BOP will place letdown back in service

place normal Letdown in service. And continue per AP-'l2.

on in AP-7

Check VCT make up Control system

~~

~

Announce occurrence on page

Check if an SI has occurred during the event.

An SI has not occurred; the SRO will ga

to the RNO. He may ask the Unit 2 BOF

to perform EP/1/N5000/G-1 Encl. 13 or

he may direct the Unit 1 RO to perform

it. It is time critical to have the enclosure

initiated within 30 minutes of the BO

Have available licensed operator initiate Encl. 7 He may ask the Unit 2 BOP to perform

Encl. 7 or he may direct the Unit 1 RO

to perform it. It is time critical to have

the enclosure initiated within 30 minute:

of the BO

Checks DIG on bus that BO is on. If it is not

known that bus is locked out the RO will be

directed to attempt to start DIG.

Will go to step 42 per RNO step 40. Determine

an SA has not occurred and go to step 44

Control CA flow

All CA will be off.

Place recirc valve for KC pumps to auto for A

Train and to Close for B Train

SRO Will continue through AP-7

I

Event 5: Placing Letdown in Service

Time

.

,

.

Pos.

'

' . Expected Actions/ Behavior

Comrne'nts

INV-2A

If a loss of charging through the Regenerative

HX has occurred, Then ensure closed

lNV-458A

lNV457A

INV-35A

Check PZR Level < 96%

If at any time "REGEN HX LETDN HI TEMP"

alarms, close:

0 INV-1A

No

BOP will take action if appropriate

Ro

SRo

Bop

Stop any power or temperature changes in

progress

Announces occurrence on page

IF this AP entered due to loss of letdown only,

then go to step 36.

Ensure Closed

SRO will go to step 36 in this AP

1 NV-457A

lNV-458A

1 NV-35A

Ensures "NC Sys MIU Controller" in AUTO

Ensures charging flow going down to maintain

Pzr at Droaram level

1 Bop IChecks normal PZR Spray available

Bop

Checks "Letdn Relief Hi Temp" alarm has

remained dark

Checks INV-21A-closed

Checks Pzr heater qroup supply breakers -

Place A, B, and D PZR heater groups in manual

and on

Checks the following OPEN

11

Maximizes spray flow

SRo

1 NV-2A

Go to step 48

-

, . . > , , , V ! ?:,;

.

. ..

,,.:,..

.:'

"

'. Expekteh Actions/ Behavior

.

..

"

stablish normal Letdown

Ensure 1 NV-459 closed

Place INV-124 in manual and 10 to 20%

Check INV-1Aand INV-2Aopen

Establish Regenerative Hx cooling by

open

throttling 1 NV-28 to establish 65 gpm

charging flow and throttling INV-241 to

establish 8 gpm seal flow

35A

Open 1 NV-78,I NV-IA, 1 NV-2A & 1 NV-

Letdown isolated < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Throttle open 1 NV-459 to establish

letdown flow

Adjust 1 NV-124 to maintain Letdown

pressure between 250 & 350 psig

Adjust charging flow while maintaining sea

flow 5 6 gpm, Regenerative Hx temp.

380 degrees and PZR level at program.

Place 1 NV-124 in auto

hen PZR level matches program level

Place 1 NV-238 to auto

Adjust seal flow to 8 gpm

Notify Chemistry normal letdown is in

service

Check INV-127 aligned to Demin

ODerate PZR heaters as reauired

When time allows notify Engineering to

document transients

Return to procedure and step in effect

At this time an oil leak develops on 1B

FWPT

I NV-7B will not have power. Position

vi11 be determined using OAC

elect Demin if required

rP-7 Step 29

12

~-

-~

~-

-~

I

Event 6:

Trip of 18 FWPT due to oil leak - Failure of Turbine to Runback

SRO May decide to reduce load per AP-4 in an

attempt to get power low enough to secure the

FWPT. or he may decide to trip the FWPT and

CREW

go to AP-3

Recognizes trip of 1 B FWPT and Load Rejectior

SRO Enters AP-03 Load Rejection

Ensures Control Rods in Auto

1.

lCM-420 - OPEN

I RO IEnsures impulse pressure decreasing to < 410

Check Turbine Generator Tied to Grid and

output going down.

I

t this time 1A FWPT will trip and initiate an

TWS

Checks Control rods moving in as required &

aligned with associated bank.

C o m m e n ti

.

. .

UE: NLO at FWPT reports oil is

xaying everywhere

crew does not trip the 1 B FWPT ther

will be tripped to get them in a runbac

Checks proper CM system operation:

Standby Hotwell and Condensate Booster

pumps RUNNING

his is an immediate action Step.

0 will take Turbine to manual and

duce impulse pressure to 400-410

jig in fast action

Psig

Check PIR meters less than 20%

Designates an operator to continuously monitor

reactor power and go to step 9.

Checks condenser dump valves modulating

open

OP Should start pumps and check

ianual loader OPEN

0

Checks load rejection -due to loss of CF pump

-

Event 7:

ATWS with a loss of Heat Sink

Pos.

Expected Actions! Behavior

Crew Recognizes ATWS

SRO Recognizes reactor did not trip and implements

F-0 and goes to FR-S.1

Checks Reactor trip:

All rod bottom lights LIT

Reactor trip and bypass breakers OPEN

IIR amDs - Goina Down

Crew IMonitors fold out page

Checks Reactor trip:

All rod bottom lights LIT

Reactor trip and bypass breakers OPEN

IIR amps -Going Down

RO Checks turbine trip:

All throttle valves closed

All governor valves closed

' Comments,

. ;; . .

' .'

.

..

.

,

..

RO should attempt to trip reactor using

switches and will realize the turbine ha

lot tripped and should trip the turbine.

Checks proper CA pump status:

MD CA pumps - ON

Check NIR level in at least 3 SIGs greater

than 17%

Manually inserts rods

Manually trips turbine if not already

ione.

Initiates emergency boration of NC system:

Ensures one NV pumps ON

Opens 1 NV-265B

Starts both boric acid transfer pumps

Checks emergency boration flow > 30 gpm

Checks INV-244A and INV-245B OPEN

Checks Pzr pressure < 2335 psig

Close

1VQ-lA,IVQ-6A,lVQ-2B & 1VQ5B

IA Tagged out

I B no power 1 ETB deenergized

TD CA tripped on over speed

INV-265B no power

Mill have to align NV pump suction to

he FWST

I NV-245B position will be verified usin(

IAC

14

SRO If an SI1 signal exists or occurs perform Encl. 3

SRO Checks the following trips have occurred:

Reactor trip

Reactor trip breakers

Turbine trip

Reactor trip bypass breakers

MIG Set Generator Breakers

MIG set Motor Breakers

Dispatches operator to open:

RO Controls SIG levels:

If CA flow is less than 700 gpm, then

start pumps and align valves as

required,

Checks NR level in at least one SIG > 11%

1.

Checks VI header pressure > 60 psig

(Maintain total CA flow areater than 70(

gpm until at least on S/G NR level

greater than 11%

Throttles feed flow to maintain SIG NR level

between 11 % and 50%

BOP Checks'all dilution paths ISOLATED

Places NC System MIU controller to OFF

I

Places Reactor Makeup water pumps to

1

STOP

RO Checks steam lines intact:

If any SIG depressurized or pressure

going down in an uncontrolled manner

AI1 S/G pressures - Stable or Going UP

the following

closed:

All SIG pressurized

All MSlVs

All MSlV bypass valves

BOP Checks NC T-colds - Stable or Goina UP

RO Checks Core Exit TICS 1200 degrees

SRO Checks the reactor subcritical:

Yes

PIR channels < 5%

I/R SUR - NEGATIVE

WIR Neutron Flux c 5%

SRO Calls chemistry to obtain current boron

concentration

SRO Refers to RPIOOO Classification of Emergency

SRO Return to procedure and step in effect.

SRO Goes to FR-H.l

Crew Determines feed flow is less than 450 gpm but

not due to operator action

Due to RED Path on Heat Sink goes tc

H-I.

15

NC Pressure > greater than any non-faulted

Anv NC T-hot - areater than 350 dearees

SIG pressure

Crew Monitor foldout page

SRO IF Feed and Bleed Criteria met go to step 20

SRO Perform steps 21-25 quickly to establish Feed

At this point in the scenario Feed and

Bleed criteria may be met.

land Bleed

BOP IEnsure NC pumps off

BOP Initiate SI1

BOP Check NV pumps to cold legs indicating flow

ISA-3 Is closed, linkage is

16

SRo IWCC informsthat'lA CA pump is available

SRo \\Returns to steo 7 in FR-H.l

SRo !Attempt to establish CA flow to at least one SIG I

Ro Check Power to both motor driven CA pumps

Check that CA valves have been aligned per

Encl. 4

1A CA has power

Ro

Start 1A CA DUmD

Ro Check TD CA running

NO

Ro Check total CA flow >450 gpm

SRo A CA pump running and step 35 has been

implemented .Go to Step 7h

Ro Check any SIG less than 12% WR

Ro

Check core exit TIC stable or going down

SRo Will direct RO to open CA control Valve to either

A or B SIG (which ever had the highest level) to

establish flow rate required to lower core exit

TIC

At this point in scenario thefe should be

a SIG with less than 12% WR

At this point in scenario core exit TIC

may be going up.

17

Note to Examiner: Be sure SRO classifies event at end of scenario.

Classification of Event: General Emergency due to:

L.

1) Valid reactor trip signal received or required and automatic trip

was not successful.

AND

2) Manual reactor trip from the control room was not successful in

reducing reactor power to less than 5% and decreasing.

AND

3) Heat Sink CSF-RED

18

SHIFT TURNOVER INFORMATION

UNIT 1 STATUS:

I

r

Pzr[B]: 953ppm

Xe: 2895pcm

Power Level: 100%

NCS [B] 953 ppm

Power History:

At this power since startup

Core Burnup: 350 EFPDS

L.

CONTROLLING PROCEDURE: OP/l/N6100/03 Controlling Procedure for Unit Operation

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT

"1A Diesel Generator tagged for PM.

" 1 A Motor Driven Auxiliary Feedwater Pump tagged for oil sample.

Unit 2 is available for Auxiliary Steam

PT/l/B/4250/028' Main Turbine Bearing Oil Pump Test is scheduled to be performed

Vibration readings are not required for PT/I/B/4250/028

Work Control SROlOffsite Communicator

Tim

u

Plant SRO

Gary

NLO's AVAILABLE

Aux Bldg. Missy

TurbBldg. AI

51h Rounds. Tom

Extra(s) Richard, Andy

Unit 2

AUX Bldg. Warren

Turb Bldg. Greg

-

19

Appendix D

Scenario Outline

Form ES-D-1

1

2

3

A

Facility: McGuire

Scenario No.: 2

Op-Zst NO.:

Examiners:

Operators:

~

~~~

~~~~~~~~~~~~~~~~~~~~~~~~~~

N

C

I

C

(RO) Remove FWPT from Service

(RO) ICF-20 Feed Regulating Valve Fails OPEN

(BOP) Pressurizer Pressure Channel 1 Fails HIGH uith

Spray Valve Failure

(BOP) 1 RN-1878 Fails Closed -Loss of RN to KC

Initial Conditions: 35% Powr, 'B' Train Components in Service, ' I A Auxiliary Feedwater

Pump is tagged, '1A Diesel Generator is tagged, thunderstorms are in the area

Turnover: Remove FWPT from Service

5

6

7

Event

Malf.

Event

11

No.

1

No.

1 Type'

1

C

M

SGTR with LOOP

(RO) ISB-12 Condenser Dump Fails OPEN

(BOP) 1KC-132 Erratic -Letdown Heat Exchanger Valve

1

_

-

~

No Auto SI

Event

Description

4

(N)ormal, (R)eactiuty, (I)nstrument, (C)omponent, (Major

4004 41

NUREG-1021, Drafl Revision 9

PROGRAM: McGuire Operations Training

MODULE:

TOPIC:

Initial License Operator Training Class 21

Nuclear Regulatory Commission Simulator Exam

Scenario 2

REFERENCES:

1.

2.

3.

4.

5.

6.

7.

8.

9.

,4

McGuire Technical Specifications

OPlllN61001003

APll /A/5500/01

Steam Leak

APJI /A/5500/06

SIG Feedwater Malfunction

APlllA/5500/11

Pressuizer Pressure Anomalies

APlllN5500120

Loss of RN

EPll /N5000/E-0

Reactor Trip or Safety Injection

EPII /N5000/E-3

Steam Generator Tube rupture

RPIOIA/5700/000

Classification of Emergency

Controlling Procedure for Unit Operation

n

Author:

Facility Review:

April 3,2003

Rev.1

1

EVENT SUMMARY

b' 1. Remove from service one FWPT per OP/1/A/6100/003.

2. ICF-20 (C SIG FRV) fails open. Enter AP-6

3. Pressurizer Pressure Channel 1 fails High. 1 NC-27 fails open. Enter AP-11

4. IRN-1878 closes, Loss of RN to operating KC Hx. Enter AP-20

5. ISB-3 (Condenser Dump Valve) fails open. Enter AP-1

6. 1 KC-132 fails closed in Auto.

7. SGTR. Enter AP-10

8. Manual Rx Trip and SI. Enter E-0

9. Implement F-0 and Go to E-3 from E-0 step 21

10. LOOP

2

i/

W

Bench Mark

Sim Setup

I

SIMULATOR OPERATOR INSTRUCTIONS

. ACTIVITY

Rod Step On

IC - 131

RUN

Update Status Board,

Setup OAC

Setup ICCM, Turbine

Displays, & Trend

Recorders.

Check Rod Step

Counters agree with rod

positions

(M) EPQOOIA

Set = 1

(LOA) CA009

Set = F

(M) IPEOOIA

(M) IPEOOIB

(M) ISE003A

(M) ISE007A

(M) ISE007B

(M) IRE01088

(M) IREOIOFZ

. . .

, . .

'

C

.

. . .

a .I '

DESCRIPTION

. .

See Shift Turnover Information

Loss of DIG " 1 A Control Power

Rack out breaker for " 1 A Auxiliary Feedwater Pump

Defeats automatic reactor trips

Phase A Train A isolation fails to actuate automatically

FWI train A fails to actuate automatically

FWI Train B fails to actuate automatically

Control Rod B8 stuck

Control Rod F2 stuck

3

Bench,Mark.

.

. .- ,. '..'DESCRIPTION

. . . .,:.

. !,;;!:,:'.:

' .'.. :'C:ACTIVIW. .:&'

.: . 1, ,. .:

,

.

...,

(M) EMF171

EMF-71 fails as is

, i .

a

' .

. . ,

. .

I . .

.

. ../. .

.

.'

' .

.,.

.

I

(M) EMF174

Set as is

(M) ISE002A

(M) ISEOOZB

EMF-74 fails as is

Failure of automatic Safety Injection - both trains

2. Review the Shift Turnover Information with the crew.

3. Direct the crew to Review the Control Boards taking note of present conditions, alarms

Prior to Crew

Briefing

T-0

Freeze.

Update Fresh Tech.

, Spec. Log.

Fill out the NLO's

Available section of

Shift Turnover Info.

RUN

At direction of

examiner

At direction of

examiner

At direction of

examiner

Begin Familiarization

Period

(M) IFE006C

Set 100,Ramp 20

(XMT) NC038

Set 2500, Ramp 5

Trigger 1

(M) ILE003A

Set 100

Trigger 1

Fails ICF-20 ( C S/g FRV ) open

Fails PZR Pressure Channel 1 HIGH

Fails 1 NC-27 oDen

4

examiner

Set 100, Ramp 10

Set100 Ram

Set 450, Ramp 300

examiner

5

W

\\ c

Pos.'.

I

EVENT 1:

'

Remove from service one FWPT per OPll/N6100//003

.

~, .,

. . r &.. ,

.I

',. ' ' I ' . '

>. .'

. ' ..' "Comments

' : .

.

...

,

e

.

..

. . ~

~

' ,

, . I . i

. .

' 1 ,

Expected'Actions/B'eha\\;:ior.',

Conduct a prejob br;ef

Prejob brief will be conducted prior to

-

Time -

Ro

taking turnover.

Ensure AMSAC actuation is blocked

Place FWPT's to Manual

Raise speed on FWPT to remain in service until

an increase is seen in

CF suction flow

CF header pressure

Turbine RPM

CF Hdr Press/ SM Hdr Press DIP

Ro

Lower speed on FWPT to be removed from

service and raise speed on FWPT to remain in

service while maintaining constant

CF header pressure

CF header flow

CF Hdr PressISM Hdr Press DID

Calculate program DIP

Adjust FWPT to obtain program DIP

Place FWPT in auto

SID FWPT removed from service using

0 PI1 /N6250/00 1

Reduce speed of FWPT to be SID to minimum

Verify CF pump Recirc is open

6

Event 2:

ICF-20 fails open

Pds.

' ' . 'Expected Actions/ Behavior

SRO IEnters API06 SIG Feedwater Malfunction

Refer to annunciator responses

A-3

. c-3

Monitor SIG NR Level

Places Feed Regulator to Manual

Restores S/G level to program level

Checks the following channel indicating the

same:

Feedflow

Steam Flow

SIG Level

Checks the reactor trip breakers closed

> P-11

BOP Checks NC temperature with NC pumps on

stable or trending to programmed temperature

Check CMICF feeding SIG

failed valve and evaluate T.S.

Exit procedure

When the following are met then return affected

SIG CF control to automatic

1. Selected control channels indicated correctl)

Feedflow

Steam flow

S/G level

2. Affected SIG level restored to program level

3. Automatic control is desired

Checks proper CF alignment

Checks procedure enter due to automatic

control of ICF-20 failing

Comments

.

er annunciator response and API06

le operator will swap failed channel tc

perable channel

mediate Action

es

at any time SIG NR Level approache

7% or 83%, then trip Reactor

utomatic will not operate

ailure will not be repaired

I

Event 3: Pressurizer Pressure Channel 1 Failure HIGH with INC-27 failed open

. .

,

.

I

.

,

. .,

, .

.:

, .

'POS. I

Expected Actions/ Behavior.

Comments.

. ,

i

BOP Recognizeslreports PZR pressure decreasing

SRO llmolements AP/I I

Pzr Pressure Anomalies,

BOP Checks Pzr Pressure decreasing

lmmediate action Yes

BOP Checks all channels the same

BOP Checks Pzr PORV's Closed

Immediate action Yes

BOP Checks Spray Valves Closed

lmmediate Action No Places PZR

Press Cntrl Select to back up channel

lmmediate action 1 NC-27 open takes

controller to manual and closes valve

BOP Checks Pzr PORV's -closed

I

~~~

~~

BOP /Checks Sorav Valves Closed

SRO Go to Step 9

BOP Checks NV-21A , CLOSED

BOP Checks Pzr A,B & D heaters ON

Place Pzr heaters mode select switc

in manual

control oressure.

Turn on heaters as necessary to

~~

~

~~

BOP Checks I C PZR heater - ON

If pressure below desired pressure,

then:

Place "Pzr PRESS MASTER in

Control Pressure

When Pzr pressure return to normal

and automatic control is desired the

dace Pzr master in auto.

manual

BOP Checks Pzr pressure going UP

SRO Go to step 22

SRO Ensures "Pzr PRESS REC SELECT" is on an

operable channel

SRO Will notify WCC to write WR, have I&E

investigate and repair and evaluate T.S.

Failure will not be fixed

T.S.: 3.3.1.61 3.3.1.8.aI3.3.1.8.bl

3.3.2.1.d I3.3.2.3.a.3 / 3.3.2.5.c /

3.3.2.6.~/3.3.2.8.b/3.3.4.2/3.3.6.3/

3.4.1 13.4.11

8

I

Event 4

IRN-1876 (RN to KC Heat Exchanger) Fails CLOSED

Pos. .

Expected Actions/ Beha&

I

Comments

SRO Go to AP-20 Loss of Operating RN Train -

Lase 1

Recognizes loss of RN flow to KC HX

BOP IChecks for potential loss of LLI

~XAMINER CUE:

Check suction flow path -available

Checks idle train available to start

Check Unit 2 RN pumps that are aligned to

Unit 2 RN pumps are Operating

LLI- operating properly

properly

Starts 1A RN Pump

Ensures IRN-86A OPEN

Go to step 4

Enclosures for local venting of RN

pumps and NV Pump cooling via gravit)

drain have not been performed.

IT0 start 1A RN pump performs the following

I

Places manual loader for IRN-89A to 10%

1

OPEN

Check 18 KC pumps on

Ensure 1 KC-228B and IKC-188 open

Ensure 1 KC-230A and 1 KC3A closed

Checks 1B RN pump running properly

Yes

If BOP answers no, he will place IRN-

187 in manual and open (the

malfunction will prevent from opening).

He will then be directed to secure the

1 B RN pump. The SRO will then go to

step 5

If the BOP answers yes, the SRO Will g(

to step 5

Throttles IRN-89A to establish desired flow

while maintainina less than 16.000 aDm

BOP bheck 1A KC pumw on

IN0

Ensure CR Area Chiller in Service per Encl.3.

Swap operating equipment cooled by affected

train of RN to opposite train

Request Unit 2 RO to perform

GO lhnltioate reason for loss of RN train

I

9

Pos.

.

. .

. I ..,;

: . ,

Expected Actions/.Behav;or

. .

.

. . . , ;

.

,_ . . .

.

% .

.

< . .

Coniments , .:.,

. . . I

. , .

Swaps trains of KC per Enclosure 2

Limits KC flow to 4000 gpm per operating KC

Checks the following open:

1, 1 RN-40A

2. IRN-41B

3. 1RN43A

4. Any KC pump running

Checks both ND pumps OFF

GotoStep19

Ensukes IRN-1878 select switch is in manual

Throttle open 1 RN-89A to establish desired

flow to 1A KC HX maintain less than 16,000

gPm

pump

Places 1 KCdlA in the AUTO position

Ensure IKC-51A openslcycles

Starts 1Al and 1A2 KC pumps

Aligns Reactor Bldg header to 1A train as

follows:

1. Open 1KC9A

2. Open IKC-230A

3. Close 1 KKC-228B

4. Close 1 KC-1 88

Checks both ND pumps OFF

Places IRN-1878 Mode Select switch to

Auto

Check close 1 RN-187B

Places control switch for 1 KC-54B to close

position Stops 1 B1 and 1 B2 KC pumps

Stops 1B1 and 182 KC pumps

~

love to next event during swap of NV

ains

1OP

10

Swaps trains of NV per OP/l/A16200/001 B

Enclosure 4.2

Event 5:

1%-3 (Condenser Dump Valve) Fails OPEN

Pos.

Expected Actions1 Behavior

Comments

REWIRecognizes symptoms of a steam leak

IT-ave-Tref annunicator may come in

Crew

.~

T-ave decreasing

Enters AP-01 Steam Leak

Monitors fold out page

Reduces turbine load to maintain:

Excore NI -less than 100%

NC loop D/Ts -less than 60 degrees

T-ave, atT-ref

Checks Pzr level - at or going to programmed

level

Will return to step 3 if Pzr level can not be

maintained.

Announces occurrence on Daae

alarm

I.

Power increasina

I

Checks Unit 2 -steam header pressure

Exits procedure when leak is isolated.

-RO lldentifies and isolates leak:

.

Checks condenser dump valves - 1 OPEN

Checks containment conditions - NORMAL

Checks steam line drain valves - CLOSED

Checks turbine driven CA pump - OFF

condenser dump valve Will be OPEN

dump interlock Bypass channel

call WCC to have valve

RO must select "OFF RESET" on

and B. Due to failure valve will not

Checks SIG PORVs -CLOSED

11

I

Event 6:

1 KC-132 fails Closed

Takes manual control of 1KC132. Opens valve,

lowers UD Hx outlet temperature.

Calls WCC to have WR written and Have I&E

investigate and repair.

12

Event 7:

SGTR on "A" SIG

I

Time

Pos.

1 BOP

ecognizes symptoms of SGTR

nters AP-10 Case 1

hecks PZR level Stable or going up

erforms the following

Charging flow 4 7 5 gpm

Ensures 1 NV-238 opening

Open 1 NV-241 maintain 6 gpm seal flow

Isolate letdown

Start 1A NV pump

PZR level going down with max Charging flow

)ired Tripping of Reactor and ensure SI1

itiated.

c'

13

Event 7:

SGTR on "A" S/G

E-0 Evaluation

rew

Monitors Foldout page

jRO/

,

.. ..

.

Comments ," . . .

.

Check Reactor Trip:

rod bottom lights

reactor trip breakers open

I/R amps decreasing

Check Turbine Generator tripped

TV'sclosed

Check CTA and ETB energized

Check SI status light - LIT

Check LOCA sequencers (A & B) actuated

Announce "Unit 1 Safety Injection" on page

Checks ESF Monitor Light Panel

Groups 1,2 and 5 DARK

Group3 LIT

Checks OAC in service

Checks Group 4, Rows A thru F LIT as

Required

Check the following on Monitor Light Panel

Group 4 LIT

. c-3

C-6

F-4

F-5

Checks CA is running and at least 3 SIG's NR

level > 17%

mediate action

I I rod bottom lights will not be lit due tc

rods being stuck out. Per RNO RO W I

ip Reactor and SRO and RO should

etermine the Reactor is tripped.

_ _ _ ~

mediate action

nmediate action

mediate action

.ut0 actuation of Phase A is blocked

,OP will

ensure both trains Phase A

Isolation are initiated

Align or start S/l and Phase A

components with individual

windows in Group 4 as

required.

,ut0 Action of FWI is blocked

OP will

Check OAC Monitor Light

Program for associated light

Align valves as required while

SRO continues on with the

procedure.

14

BOP Checks RN pumps running

SRO Directs Unit 2 Operator to throttle RN to

minimum & start 2A RN pump

2A RN pump is running

RO Checks.all S/G pressures > 775 psig

BOP Checks Containment pressure has remained

less than 3 psig

BOP Checks NV Pump to Cold Leg Flow gauge -

indicating flow - YES

checks NC pressure < 1600 psig

EXAMINER CUE:

BOP will ensure ND pump mini-flow

valves are open

SRO When available notifies OSM or other SRO to

implement Generic Enclosure 21

EXAMINER CUE:

OSM will ensure Generic Enclosure

21 implemented.

Checks CA flow > 450 gpm and takes

control of CA to maintain no load levels

checks VI header pressure > 60 psig

Maintains NIR level between 11% and 50%

BOP Checks NC pumps ON and Tave stable or

trending to 557 degrees

If not stable and decreasing crew will g

to Enclosure 3

BOP Checks Pzr PORV & Spray Valves closed

RO Checks subcooling > 0 deg.

RO Checks all main steam lines INTACT

ROI Report S/G tube rupture parameters indicate

BOP that SIG tubes NOT intact

SRO Implement CSF Status Trees and go to E-3

PER RNO Implement F-0 and Go to E.

15

~

Event: STGR on "A" SIG

E-3 Evaluation

Pos.

,.

..

i_/

c.

i ,

_/'

. .,' . ' Expected Actions/;Behavior ",',

'* .,

, .;:?

. . .

.. . .

.,. : * ;.* \\

8: ',.%'

.. ,

z . ..I. ;;, . .

!

.

,~ ..

REW Monitor foldout page

ROI

Identify "A" as the ruptured SIG

1.

close ISM-83

RO IClose the following on ruptured SIGs:

~~

Check at least one SIG -AVAILABLE FOR NC

SYSTEM COOLDOWN

Isolate steam flow from ruptured SIGs as

follows:

checks ruptured SIG PORV closed

check SIG 1 B and I C INTACT

check IBB-IB and 1BBdA Closed

I

16

-

MSlV

MSlV bypass valve

Checks ruptured SIG NR levels greater than

11%

Isolates feed flow to " A SIG

Close 1 CA-66A

Close 1 CA-62A

Checks Pzr PORV and isolation valves:

All Pzr PORVs CLOSED

Checks main stream lines intact:

All SIG pressurized

Reset the following:

SI1

Sequencers

Phase A isolation

Phase B isolation

Established VI to containment

IVI-1296 open

1VI-160B open

IVI-1506 open

Controls intact SIG levels:

Throttles feed flow to maintain intact SIGs

Power to all Pzr PORVs available

At least one Pzr PORV isolation valve OPE1

All SIG pressures stable or going up

Checks VI header pressure > 85 psig.

NIR level in all intact SIGs > 11%

NIR levels between 22% and 50%

Checks 1 ETA and IETB energized by offsite

power

Checks ruptured SIG identified

'b'

ii

Ro

Checks the following closed on ruptured SIG:

1.

MSlV

1.

MSlV bypass valve

RO /Checks ruptured SIG pressure greater than 280 I

psig.

BOP Checks,any NC pump running

BOP When P-11 status light lit then block steamline

isolation and maintains NC pressure less than

1955 psig.

RO Initiate a NC system cooldown as follows:

Determine required core exit temperature base

on lowest ruptured SIG pressure.

Check Condenser available

COND AVAILABLE FOR STEAM D U M P

status light - LIT

MSlV on intact SIGs OPEN

Place Steam Dumps in steam pressure mode.

When P-12 stat light lit place steam dumps in

bypass interlock.

Dump steam to condenser at max rate.

REW Recognizes the LOOP B DIG starts and

energizes ETB. ETA is deenergized due to ?A

DIG tagged. Restarts SI1 equipment previously

3nce the RO has initiated a cooldown a

-0OP will occur.

on.

SRO Recognizes NCPs are off and loss of condenser

Vacuum. Returns to Step 15 in E-3

BOP Checks any NC pump running

BOP When P-I 1 status light lit then block steamline

isolation and maintains NC pressure less than

1955 psig.

17

I

Select "MANUAL" on "SM PORV

MODE SELECT"

Determine required core exit temperature base

on lowest ruptured S/G pressure.

Check:

COND AVAILABLE FOR STEAM DUMP

status light - LIT

MSlV on intact S/Gs OPEN

Adjust manual loader on intact S/G

PORVs as required to control intacl

S/G depressurization rate at

approximately 2 psig per second.

30P

Check low pressure steamline isolation -

BLOCKED

Check core exit T/Cs - less than required

temperature.

Stop NC system coodown

Maintain core exit TICS less than required

temperature.

Checks ruptured SIG pressure - stable or going

up

Checks NC subcooling based on core exit TICS

> than 20 degrees

Depressurizes the NC system

1. Checks ruptured S/G NR level less than

73%

2. Checks normal Pzr spray available

Depressurize NC system using one PZR PORV

Observe caution prior to step 21 and go

to step 21

18

Crew

satisfied

.

NC Subcooling c 0

PZR level >76%

NC pressure < ruptured SIG pressure &

PZR level > 11 %

Check NC System Pressure going up

Checks for SI1 termination criteria

1. NC subcooling greater than 0 degrees

2. Secondary heat sink

3. NC pressure - stable or going up

Must meet all criteria to terminate.

-

.

14. Pzr ievel greater than 11%

19

II

I BOP Istop NI pumps and one NV pump

I

BOP Check NV pump suction aligned to FWST

Open INV-1508 & INV-151A

Close INI-9A &INI-lOB

SHIFT TURNOVER INFORMATION

UNIT 1 STATUS:

L

Power Level: 40%

NCS[E.?] 13ppm

Pzr [B]: 13 ppm

Xe: 2895pcrn

Power History: At this power for 400 days

Core Burnup: 440 EFPDs

CONTROLLING PROCEDURE: OP/l/N6100/03 Controlling Procedure for Unit Operation

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

"1A Diesel Generator tagged for PM.

"1A Motor Driven Auxiliaw Feedwater Pump tagged for PM

. _.

Unit 2 is available for Auxiiiary Steam

Remove 1 B FWPT from service and Shutdown per 0P/l/N6100/003 Encl. 4.2 Step 3.6.13 to

repair oil leak.

Work Control SROlOffsite Communicator

Tim

Plant SRO

Gary

NLO's AVAILABLE

Unit 1

Aux Bldg.

Missy

TurbBldg. AI

gTH Rounds. Tom

Extra(s) Richard, Andy

-

Unit 2

Aux Bldg. Warren

Turb Bldg. Greg

-

20

Appendix D

Scenario Outline

Form ES-D-1

Facility: McGuire

Scenario No.: Spare

Op-Sst No.:

Examiners:

Operators:

Initial Conditions: 100% Power, 'B Train Components in Service, '1A Auxiliary Feedwater

Pump is tagged, '1A Diesel Generator is tagged, thunderstorms are in the area

Turnover: Reduce Turbine Load to 90% to Perform Turbine Valve Movement Test

(N)ormal, (R)eactiwty, (I)nstrument, (C)omponent, (Major

40041 41

NUREG-1021, Draft Revision 9

PROGRAM: McGuire Operations Training

MODULE:

TOPIC:

Initial License Operator Training Class 21

Nuclear Regulatory Commission Simulator Exam

Scenario Spare

REFERENCES:

1.

McGuire Technical Specifications

2.

OP/l /A/6 1 00/003

Controlling Procedure For Unit Operation

3.

AP/I/A/5500/06

S/G Feedwater Malfunction

4.

AP/l/A/5500/10

NC System Leakage within Capacity of Both NV

Pumps

5.

AP/l/A/5500/14

Rod Control Malfunction

6.

AP/l/A/5500/16

Malfunction of Nuclear Instrumentation

7.

EPll/Al5000/EO

Reactor Trip or Safety Injection

8.

RPIO/A/5700/00

Classification of Emergency

u

April 3, 2003

Rev.1

1

EVENT SUMMARY

ii 1. Reduce power in preparation for Turbine Valve Movement Test

2. B NC loop T Cold fails High. Enter AP-14

3. D SIG NR Level Channel 1 fails Low. Enter AP-6

4. PR-42sfails. Enter AP-16

5. PZR Level Master fails

6. NC System Leak. Enter AP-10

7. Rods Ejection 2000 gpm NC system leak. Enter E-0

2

Bench Mark

Sim Setup

I

SIMULATOR OPERATOR INSTRUCTIONS

Rod Step On

IC - 127

~

RUN

Update Status Board,

Setup OAC

Setup ICCM, Turbine

Displays, &Trend

Recorders.

Check Rod Step

Counters agree with rod

positions

(M) EPQOOIA

Set = 1

(LOA) CA009

Set F

(M) IPEOOIA

(M) IPEOOIB

(M) DEH003A

~~

~

(M) ISE003B

Sel + BLK Auto

See Shift Turnover Information

Loss of DIG "1A Control Power

Rack out breaker for "1A Auxiliary Feedwater Pump

Defeats automatic reactor trips

Failure of Auto Turbine tripped blocked

Failure of Phase '"A

train " B

to actuate automatically

3

Bench Mark

...'

.. .. . .'i ACTIVITY ;,;

1 " i : ..

(M) ISE002A

Prior to Crew

Briefing

'

I

_

.

'

..

.

,

. .

.

..

.. ..

' .

':

.: ;DESCRIPTION'

,

.

,:

, .

. .

Failure of automatic Safety 1n;ection - both trains

(M) ISE002B

Freeze.

Update Fresh Tech.

Spec. Log.

Fill out the NLO's

Available section of

Shift Turnover Info.

RUN

Crew Briefina "

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3 Direct the crew to Review the Control Boards taking note of present conditions, alarms

T-0

At direction of

examiner

At direction of

examiner

At direction of

examiner

At direction of

examiner

At direction of

examiner

At direction of

examiner

Begin Familiarization

Period

(XMT) NC102

Set = 630, Ramp = 10

(XMT) CF008

Set = 0, Ramp 10

(M) ENB013D

Set =200, Ramp = 10

(OVR) N C l l l

Set 400, Ramp = 60

(M) NC007A

Set = .25, Ramp = 300

(M) NC005

Set = 2000

Terminate the scenai

B NC Loop T-Cold fails High

'"A

SIG NIR Level Channel 1 fails Low

Power Range N-42 fails High

PZR Level Master fails High

NC System leak 50 gpm

Ejected rod M8. Leak rate increases to 2000 gpm

upon direction of Chief Examiner

4

Event 1:

Reduce Load per OP/l/N6100/003 Step 3.2

Ro

Check quality Thermal power best OAC points

Operate PZR Heaters per OP/l/A6100/003

Enc1.4.3

I

Reduce Turbine load per OP/1/A/6300/001 A

(Turbine Generator Load Change)

CREW

I

- .

I

I CREW IMaintain Control Rods within insertion and

withdrawal limits per COLR

Maintain' AFD within Target Band

At 98% power Place MW Loop in service

5

I

Event 2:

B NC Loop T Cold fails High

POS.

Expected .Actions/.Betiavior

Comments

'

RO IRecoonizes Unwarranted Control Rod Insertion knnunciator AD-6 B -10

IT-refr-auct Abnormal

Enters AP-14. Stops load decrease

If more. than one rod dropped - trip Rx

Places CRD Bank Selector Switch to manual

and verifies movement stopped

Check all control banks aligned with associated

lmmediate action

bank

Checks Rod Control Urgent Failure alarm DARb

Checks to following reactor control instruments

NORMAL

T-ref indication

"1A NC loop T-ave

Turb Imp Press Ch 1

"1 B NC IOOD T-ave

.oop " B T-ave identified

o

to Enclosure 4

"IC" NC loop T-ave

"1 D" NC loop T-ave

Goes to Enclosure 4

BOP /Announce occurrence on page

withdrawal:

Ensures no inadvertent mode change will

occur.

Ensures rods are withdrawn in a deliberate

manner.

I

RO IChecks the following normal:

T-ref indication

Checks the following normal:

"1A NC loop T-ave

"IB" NC IOOD

T-ave

. Places DTT Defeat switch to failed

Loop "B" Tave identified

BOP will perform the following:

1.

Turb Imo PressCh 1

I

"1 C NC loop T-ave

"1 D" NC loop T-ave

I

failed

loop IOOD

Places T-ave Defeat switch to

. - - I ~

RO will perform the following as

necessary to maintain T-ave at T-ref:

BoratelDilute NC system

Adjust turbine load

When T-ave at T-ref +I- 1 degree and

auto rod control is desired, then return

rod control to auto.

Position control rods in manual

Ensure P-12 is in required state for

existing plant conditions

6

Tech Spec 3.3.1 and 3.3.2

ithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of failure.

OPDT

OTDT

LowT-ave

Checks if failed channel has been identified

Call WCC SRO and have WR written, IAE to

investigate and repair and evaluate T.S.

YES

t

Event 3:

"A"

SIG NR Level channel 1 fails Low

Pos.

Expected Actions/ Behavior

Comments

Refer to annunciator responses

Annunciators on 1AD-4

Per annunciator response and API06

the operator will swap failed controller

lmmediate Action

A-I

B-1

from normal to alternate

Places Feed Regulator to Manual

Restores SIG level to program level

Checks the following channel indicating the

same:

Feedflow

Steam Flow

SIGaLevel

lmmediate Action

8

Announce Occurrence on page

Check Reactor Trip Breakers closed and > P-I 1

Monitor SIG NR Level

Check CMICF feedina SIG

If at any time SIG NR Level approache:

17% or 83%, then trip Reactor

SIG level stable or trending to program

Checks NC temperature with NC pumps on

stable or trending to programmed temperature

When the following are met then return affected

SIG CF control to automatic

1. Selected control channels indicated correctly

Feed flow

Steam flow

SIG level

2. Affected SIG level restored to program level

3. Automatic control is desired

Checks proper CF alignment

Contacts WCC to have WR written, have I&

investigate and repair failed channel and

evaluate T.S.

Exit procedure

Failure will not be repaired

I

Event 4:

PR-42 fails High

I

II

BOP pnounce occurrence on page

Checks N-42 as only failed channel

RO Position "PR to S/G Program Level Channel

Defeat" switch to defeat inoperable channel.

Reports'power stable

Complete steps to take channel out of service

and verifies proper lights - lit

Ensure operable PR channel selected to record

channel

OPDT

on NR45'chart recorder

Adjusts control rods to maintain T-Ave = T-Ref

When T-Ave = T-Ref to within + or - 1 deg-F.

then return Rods to "Auto" if desired

Instruct IAE to fail associated BIS's for failed

investigate and repair and have T.S. evaluated

T.S. 3.3.1.2/3.3.1.3/3.3.1.6/3.3.1.7/

3.3.1.16.b/3.3.1.16.~/3.3.1.16.d

9

OTDT

When IAE trips B/S's, verifies proper status

lights -lit

Call WCC to have WR written, have I&E

Instrument will not be repaired

Event 5:

Pressurizer Level Master fails High

CREW

dREW

SRo

.

,.

. . . .

.

. . .

. ,

.

. .

,

.

. . .

1 Pos. 1

'.

Expected ActionslBehah'.:

.: '1

, i

comments

I

-

Recognize charging flow increasing.

Determine from plant conditions (NC System

temperature and pressure stable and PZR level

going up) that there is an instrument failure.

Direct BOP to place 1 NV-238 in manual and

control charging flow.

Contact WCC to write WR, have I&E investigate

and repair.

10

Event 6:

NC System Leak 50 gpm

REW

Pos.

Expected Actions/ Behavior

REW Recognize symptoms of a system leak

Estimate leak rate

Refer to RP/O/A/5700/000

If at any time NC leakage exceeds T.S. place in

service Outside Air Pressure Filter Train

Have another SRO evaluate if leakage exceeds

SLC 16.9.7 condition C limits

If VCT level less than 16% swap NV pump

suction to FWST

Check seal leakoff on NC pumps greater than 6

gpm

Check Thermal Barriers intact

Check if leak suspected on Letdown line near

Demineralizers

Check leak on Letdown line

Check VCT intact

Check the following normal, PZR Safeties, PZR

PORVs and PRT conditions

Ensure INV-238 opening

Check CLA levels normal

Check NCDT parameters normal

BOP Check Containment floor and equipment sumps

normal

Check leak location identified

11

SRO Contact Station Management to evaluate need

I/

I

I to Shutdown

u

Check unit shutdown required

Shutdown per AP-4

EnterAP-4

Initiate a 2000 gpm leak by ejecting control

rod M8

12

~

Event 7

NC System leak 2000 gpm due to ejected rod

I

I SRO IReviews Foldout page with crew

INCP trip criteria based on loss of

subcooling

RO Report Reactor Trip:

Immediate Action

rod bottom lights

Reactor will be tripped manually

reactor trip breakers open

IIR amps decreasing

Wsclosed

Turbine will be tripped manually

Reports Turbine Generator tripped

Immediate Action

BOP Reports ETA and ETB energized

lmmediate Action

RO Reports SI status light - not LIT

Immediate Action

BOP Report LOCA sequencers (A & B) actuated

Immediate Action

RO Announce "Unit 1 Safety Injection" on page

BOP Checks ESF Monitor Light Panel

Groups 1,2 and 5 DARK

Group 3 LIT

Checks OAC in service

BOP Reports all Ss and St components in Group 4

LIT

RO Reports that CA is running and at least 3 SIGs

NR level > 17%

SA will be manually initiated

BOP Reports KC pumps running

BOP Reports RN pumps running

SRO Directs Unit 2 Ooerator to throttle RN to

EXAMINER CUE:

.~~

lminimum & stari ZA RN pump

1.

2A RN pump is running

I RO ICheckslreports all S/G pressures > 775 psig

I

BOP Reports Containment pressure has not

remained less than 3 psig

SRO Record time of reactor trip

BOP Reports Monitor Light Group 4, Row G, lit

BOP Stop all NC pumps while maintaining seal

injection

BOP Secure RV pumps

BOP Energize H2 Igniters

. , '..

.... ,,*.:':,&. : .,.,

.:.

?,, .: .

Pos.; I '

.Expected Actions/,Bihavior

.

.. > .,,

,. ,_..

+.;:.*,,

,. .. 2'

i

,.:,

. ....

..

.';."Comments .

.

.::

, . ; ;.

checks NI pumps indicating flow

checks NC pressure < 286 psig

checks ND pumps indicating flow

Dispatch operator to secure all NF AHUs

Perform Encl. 2

BOP Report NV Pump to Cold Leg Flow gauge -

indicating flow - YES

checks NC pressure < 1600 psig

SRO When available notifies OSM or other SRO to

imolement Generic Enclosure 21

Containment EMFS - normal

Ice Condenser Lower Inlet Doors Open

alarm - DARK

I

EXAMINER CUE:

OSM will ensure Generic Enclosure

121 is implemented.

RO 1.

Checks CA flow > 450 gom and takes

14

I

ROI

control of CA to maintain no load levels

che6ks VI header pressure > 60 psig

Maintains NIR level between 32% and 50%

If any NC pump ON, then check Tave stable If not stable and decreasing crew will go

or trending to 557 degrees

If all NC pumps off, then check NC T-colds

stable or trending to 557 degrees.

Reports Pzr PORV & Spray Valves closed

Reports subcooling < 0 deg.

Reports all main steam lines INTACT

Report SIG tube rupture parameters indicate

that SIG tubes intact

Checks if NC system is intact:

to Enclosure 3

One PORV will be open but isolated

Containment sump level normal

Implement F-0

Containment pressure < 1 psig

REW

Evaluate CSF trees

Enter FR-P.l

I

SRo

Event 7

FR-P.l Evaluation

Reports ND pump flow is > 500 gpm

Return to procedure and step in effect and

enters FR-2.1

1 5

FR-2.1 Evaluation

-,.- lhas not occurred and continue in procedure

Crew IMonitors foldout page

I

Bop [Ensure NC pumps and RV pumps are off.

2

Bop

Dispatches operator to close breakers for

INI-173Aand INI-1788

Reports containment pressure less than 15 psis

Reports both NS pumps on

Continues in FR-2.1

Checks OAC in service

Checks the following light lit on group 4

c-3

. c-6

G-4

G-5

Checks NS system in operation as follows

Checks the following valves aligned

INS-18A - closed

1 NSQOA - open

1 NS-1 B closed

1 NS3B - open

Reports containment pressure greater than 3

Checks the following valves open

INS-32Aand INS-29A

INS-128 and INS-158

checks NS pumps on

Check phase "6" HVAC equipment per Encl.3

Checks MSlVs and MSlV bypass valves closed

Checks steam lines intact

ECA 1.1 in effect - NO

Bop

Psig

SRO Checks if any ND train is operating in the cold

eg rec:rc mode - NO. When transfer to Cold

\\Leg Recirc is complete perform step 14.

Go to step 15

Ensures operator sent to stop NF AHUs

Checks H2 analyzers in service NO.

Send operators to put H2 Analyzers in service

Goes to E-I

o to step 10.d

16

I

Event 7

E-1 Evaluation

Y

I . . ~

.

. * . ,

~

.

,

Time I Pos; .I .

j' ' EXpected'Actioni! Behavior %.

, . jl e.;

. , .

'comment'$

'. ..., :i ,

, . . c . I.

. . .

.

. o

.

. .

,.

.. . ',..

Enters E-I

Reviews fold out page with crew and reminds

crew to monitor FWST level for 180 inches (Lo

level)

NOTE: When FWST decreases to

180 inches, the crew should enter

EPIES-1.3 and manually swap to sum1