ML020910678

Feb. 2002 Exam 50-369, 370/2002-301 Draft Simulator Scenarios & Written Exam Samole Outlines

ML020910678
Person / Time
Site:	McGuire, Mcguire
Issue date:	02/15/2002
From:	NRC/RGN-II
To:	Duke Energy Corp
References
50-369/02-301, 50-370-02-301 50-369/02-301, 50-370/02-301
Download: ML020910678 (77)

See also: IR 05000369/2002301

Text

Draft Submittal

(Pink Paper)

1.

Written Exam Sample outlines

MCGUIRE EXAM

50-369, 370/2002-301

FEBRUARY 11 - 15, 2002

McGuire Sample Plan

Facility: McGuire

Date of Exam: 2/22/02

Exam Level: RO

K/A Category Points

Point

Tier

Group

I

K

A A A

Total

1

2

3

4

5

6

1

2

3

4

Emergency &

2

4

2

5

2

2

17

Abnormal

3

0

1

0

W,

__ 3

Plant

Tier

Evolutions

Totals

6

4

9

'4

8

5

36

1

4

2

4

3

1

2

0

4

1

1

1

23

2r2-

---

--

-2 0 r3

3

1

2

3

20

Plant

3

0

1

0

1

0

1

0

3

1

1

0

8

Systems

Tier

Totals

5

3

7

6

3

3

3

10

3

4

4

51

3

Generic Knowledge and

Cat I

Cat 2

Cat 3

I Cat 4

Abilities

4

3

3

3

13

Note: 1. Ensure that at least two topics from every K/A category are sampled

within each tier (I.e., the "Tier Totals" in each K/A category shall not be less than

two).

2. The point total for each group and tier In the proposed outline must match that

specified in the table. The final point total for each group and tier may deviate by

+/-1 from that specified in the table based on NRC revisions. The final exam must

total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A

topics from a system unless they relate to plant-specific priorities.

4. Systems /evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.

The generic K/As in Tiers I and 2 shall be selected from Section 2 of the K/A

Catalogue, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic,

the topic's importance ratings for the RO license level, and the point totals for

each system and category. K/As below 2.5 should be justified on the basis of

plant specific priorities. Enter the Tier totals for each category in the Table

above.

For Official Use Only Until After 2/22/02

Form ES

arget

16

17

3

36

23

20

8

51

13

Totals:

12/10/01

Summary

Copy 1 of 3

-Md .1d.ing

J.D.W

ok

ok

1Mj jUpd dnWD

CRE t

zviz

ioz

I I MNPV

lw-MA 401H 9LOON

Lm

9VAC

mi,. d.np

5.1ý3 ..

3 P.-I (LD3"owm) PLOON

opqýe,,MMWqwpM

ýIrMIMPr

IMMIMMV

f I AWSKM ý3

$0 0-01 (V&WAR)

M00i

SIX

a VL

'ý3

ýU

ýWOD 990000

Emel

.. iiaNoa puuawiw,.,w%

C

61 -H-UO

IA IUMA LOOOO

d

A

wenO pue ý

W P

qn,,ý

C, wu.ý

d .PW

in hllW

LIAV

--TT toc

V

I

J"M% -31"" A"I*nN P "Ol Z9000

"n"

VLO t

9ME

-- l-AIOAPU-iSMN

91 .. 9 IMM -- la -V I . .............

M

MM_

MM

9 1 InoqtMig uall"S 6900"

vv,z

IL*gc

LMC

f4pw. .

M. Mlonmoip AM,

p;p%13

",

ft

O'C

C9v 1,

din,

nMM NNnMuopjý iMdMi.1 N- -lWnqW M NIIMV

Fo z

V I wnn*wA is.U*Puoo 10 0*01 19

M"

a CIL

S"

wwm

ýuý

o p. lý

. Np.p Min.

ftqý

ul"i, M Min.

NI-Iýpo

,p u

qaq=pýjndjum.

me

ýO Us3dV3

zzza ýMjv inun Atý -n miý -j

1.1-1----3-.nid.U..11.-%S(Zý31AA)OMODO

dwjw;WNWmnýlu"Iý lwdmulmv

m 11

CBS L

,,

, Ad.0

McOulre Sample Plan

113.4101

Ptt Sam £xa.olnafon

Bankersi

4O

.jens 8yptrS .

2

merou

ifif

.. tr

SyK1em12NKme

KK

K

3

1K

1K

A 1

A

A1A

G

K-iAToplo(i)

Imp.

points

Ouestion

Abc~dy to monitor automatic operation of tpe...Mtdpstld of odladlity at any

001 Coatrol Rod Did.e

3.081

Ime when adding positve reactivity

-3/49140

86U

K1oospledge

or the affect Mat a lose Or malfurnotioa wit have on ,,.Str/og

003 IReactodr Coolant Pump

6.14

eulntet

2,6/2S

1

867

004 Chemical Volume Control

2.0

Knowedasdg

of bus pownt supplies to.. .o*dtw inatrunmontaloat

2"/2? 1

885

m ility to pr edct t h im pac al ot I he followdng n

r

lfuc

ar

o perat ed,. i d

bided cn those padictlons.

use procedures to correct, c*nloo or onalgate the

013 Eng~n*ered Sefety Features A*ctaton

2I01

2,01

coleuences of. LOCA

46W48

1

540

Knowledge of pyslcal connecut/oe and/or cause and effect

014 Rod Position Indication

l10A

I

relatio ripe..

IS

30/33

893 1

KrnoýtMac, of des/on feature(s) and/or nledcck(a) which provIde for, Sorc

01)1

0

1

.rl n r[, Gu4,1)1tttlon

410

range detector hut ff al high powers

878

Ktorwladge of The effect anal a lose or ma/function

w. ill have on

Natural

017 In-core Temperature Monitor

301

ciculatlon Indications

3.5"/37

911

022 Containment Cooling

1422 Kn(ow/edoa .1 the bases for prIorItizIn Safety functions duri*n abnormal / nme 30/40

I

658

AbIlity to prod/cl the impacts 0f the toilowicg nalniton cc operation

and

based on those predictions. use procedures 1O correct, control Or mitigate

Mte

025 Ice Condenser

1202

consequences of .High/low fior cooling temperature

27-12,5

1

681

Knowledge of ae effoct Ial loss or malftncton - wl have on

026 Containment Spray

3 02

1

ReWlreulatori

sprla sy-M

ase4 ,

e

knowledge of physical connections and/or cause and effect

856 C ondensate

1 03

relaionships

MFW

26 826

1

4151

Know/edge of physicai convectiora and/or ca*se and effect

059 Mea/ Feedweatr

0

.

.

relationships ./G,

3S1/33

1

14

oat Au/ltlarv/Emerganlcy Feadwatar

3.02

Krowledge of the affect that a ions or malfunction

.wilt have or

.6/0

4 2/44

r

16 I

Ability to manually operate and/or monitor in the control room

S

Battety

0613 DC Eecrtrial

4 03

disoharga rate

30"31

1

8819

Ability to manbaliy operate and/or monitor in the conrtol room

BattStoppage

of

088 Liquid Red Waste

403

relese ifliri tare eceeded

3 9/3 8

1

407

KnOWledge of physical cornections and/or cats, and effect

071 Waste Gas Disposal

106

-relationshps.

ARM and PRM syste..

3 113 1

771 1

Ai/lily to predict The impacts or the folow/mg malfunotrt or operation.. and

based on those priedfifchors use procedures to correct, control or mitigate the

072 Area Radiation Monitoring

2 02

-case/qUcfh

of.. Detector tors

2 N2o9

1

No

022 Contain* .t.

Cot*/* g

201

Kowledge of bus power supplies to containment cooling fans

3 0'`3 1

1

898

Antry to manually operate andlor

nortior In the control room.. LOss of

423N

1

0.. 4.

1

2J1

=2OreouS/ont

Total

10

10

1

For Off0il LUse Only Untii After 2122102

12111101

SYSTEMS T2 31

Copy 3 at 3

I -f-I

1W

!EW

C,

'I ii

i

-U I

if i

I I

I

I

I I

I

I

II=1=

cli

4'

iii

iii 'Ii

• 1

Ii

U

[a

r

If

2. I

I I

I

I a

S

I-

Iii

2. I

I

g a

S

a

0,

U

I I I

I

I I

I

I

I

I a

a

I

C

I

C I

IC

2 a I

C S

2.

BE

C

>

ii

a a

V

I

I

0

3

2

3

B

'V

II

I

I

I

I

C I

I

jig

if'

C

0,

2.

it ill

II

IF

I

I

I I

I

Ni

I

2.

I

I

S

2 a

S

a

a

C

I 3

S

-. I I' I

C

FJT 'i IN

 t

it

II 1I di

I I

_ 14



i!i

H

I





-

a

a 



I ' U

a



I



Ii

I I 5 k j!

z

I



i

S.

V

I

McGulre Sample Plan

Cate

I K/A #

Topic

Im .

Points

1 Question

Conduct of

Operations

,.A tarift, rnnfrniiad nrnr.srliirs cony

13.1/3.2

1

143.1

21.2

t~bl'iIty to. oJI

an

e

u

Ability to perform specific system and integrated plant procedures during all modes

2.1,23

of operation

3.9/4.0

1

331.1

Ability to locate switches, controls and indications and to determine it they are

2.1.31

correctly reflecting the desired plant lineup

4.2/3.9

1

164.1

i~~~ ~ ~ d4icnrle

oeuacp

.1.

I

Ifr

-

Equipment

Control

Radiation

Control

(multi unit) Ability to explain the variation in control board layouts, systems,

2.2.4

instrumentation, and procdra.Ullac onusl aL~l an

• =

• ,,-

...

2..3

Koweg

f o

otrlporamn

2.5/2.9

16.

33

2.3.2

Knowledge of facility ALARA program

2.5/2.9

1

124

Knowledge of radiation exposure limits and contamination control including

2.3.4

permissible levels in excess of those authorized

2.5/3.1

703.1

____________

I3

Emergency

Procedures

and Plan

I

I........

.

2.4.25

Knowledge or lire proneciion proceuuua...

Knowledge o acili

pro*,rcon requireaents including tire bnigae* and po*tble lire

2.4.26

fighting equipment usage

12.9/3.3

1

889

3

3

Tier 3 Point Total

13

131

13

For Official Use Only Until After 2/22/02

12/10/01

Generics

Copy I of 3

4

2.8/3.0"

260.1

3

2 9/3.4

910

McGuire Sample Plan

Facility: McGuire

Date of Exam: 2/22/02

Exam Level: SRO

K/A Catego

Points

Point

Tier

Group

K

K K K

5

6

A

A

A

A

G

1

2

3

6I 1

2

3 14

Total

3

1

6

2 0M J2

24

Emergency &

2

3

2

3

2

4

2

16

Abnormal

3

0

1

0

0

1

X

1

3

Plant

Tier

J

Evolutions

Totals

6

4

9

,

4

15*i;

Nn

5

43

2

2

0

0

2

2

2

1

3

4

0

1

2

17

Plant

3

0

0

0

1---

0 0---

--

1

1

0

4

Systems

Tier

Totals

4

2

5

4

2

2

3

9

2

4

3

40

3

Generic Knowledge and

Cat 1

Cat 2

Cat 3

Cat 4

Abilities1

5

4

4

4

17

Note: 1. Ensure that at least two topics from every K/A category are sampled

within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than

2. The point total for each group and tier in the proposed outline must match that

3. Select topics from many systems; avoid selecting more than two or three K/A

topics from a system unless they relate to plant-specific priorities.

4. Systems /evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.

The generic K/As in Tiers I and 2 shall be selected from Section 2 of the K/A

Catalogue, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic,

the topic's importance ratings for the SRO license level, and the point totals for

each system and category. K/As below 2.5 should be justified on the basis of

plant specific priorities. Enter the Tier totals for each category in the Table

above.

For Official Use Only Until After 2/22/02

12/10/01

Iatgnt

24

16

3

43

19

17

4

40

17

Totals

Summary

_2

Copy 1 of 3

S

'aII

I I

I

I

I

I

I

S

I

B

Ii

Ii

h H

ii

S I

I

a I

I

a

i-ar-

2

IF

ii ii ii

II

-a

Mi

2

S

'4

w

C

'Ii

3

2

ft

• U

r

 I

m

2

i

2

7

=

-

t

to

o

0 a

r

K

I

o

a

K

2

0

a

(S

2

__

2



F 31





I



I

I ill

2

r-

aII;

 I

-4

a

4"

I  :

 I dl

 I





a

S

(a

IwIcaI(aI&

r

cC

I I

ii

I

I a

I

I

S

I

0

-u

t

I!

I I

I

m

S

N

2

9.

0

-

I

I

F

a

I

2

-

I

I

-.

1.

I

I

M

0 a

5*

>

o

m

2

z



r

'4

I

t

0

0

K

0

'4

I

I

ii

17

Ii I

I

9.

t

I a I

I

3

I

S

-4

LEE

4

1 1ý I;t

MMAIddol

I

I

I

I

1 &0 L I

I I IN

.........

VL

]AM

ýWjn at, p uo,"jd" vuOi.odc, " p WOý

COO

L

L V97

ýý

vd .

Buow .5ý

J. "ma

OW Co Ala0el

I

I

I

1

11011

L I IN ý.m -.

8 w -I

umol

4

Asý

jeodýý

BUIOOOIA

OW P VýMld-l OUNOW- " 0 -Ovsý

IOU L

VIOLE

O'dAsof

lj.-lAASVHVA-ý9MHKI

No W.4K

OW-M .

POOOO

Z 1 dnsývn iuOlooo JýOOVO OoOl MOM

ý

lsssp

-OPUW lo P-POINISIP

c I Owl

4.8

RMliI GOOM

m

k

I'M 91

mos".

1p

I, i ý.ý

H - uOpominng -dPljW"H LOOM

u

I

ft

im

ZO U -3dV3

LOMLIZL

ww,"v

ioun A1.0 -n i-ý

ýA

ulml

-.

1

1-

l-..

-

-

wimpul MMSAS Asloo we ý

p

uoipunA Amog) MON 10 SdVM

I

dux

(.).Id.1 VM

...

n,

'Us,

ýL

C;- I M-3

UOId.IdwvSwInGoW

S M CIAM so %dMOx, ývOqm otp A -um""Id.,

ONWO

UNWO

I'MOTA

...

pnsismdOýý wbMlMM-..q4llWl

I

I

I

t----------------------------------------------In

m

o

0

S

o

3I

-4

I

I

C 'Si

C

a

o------------------------

o

I 

a

dii I

 I

 a

a

III

I"

o

.4

1-

I

a

---

I

t a

I T

I j

1

-U

ni

z I

'C

0

0

K

0

r

ft

iM

Sr

B U

-u2>

ii

'I

I

I

I

P

-4

0

B

-U

-w

0

0

Mgobule Sample Plan

Copy 3 of 3

System

K

I

A

WA Toplccs)

Imp.

Points

QuestNoa

System~~~~~~~~~~

~~

N e1

2

3

4

--

,*

=

,

ilt toMa ila automatic

Po stalo

of th

e

Anti

ci pation

of crt a

yityat

any

001 Controal Rod Des308

1

i

.ewhen adding positive nar civityi3

bc

9/4 0

186

Knwldg

Reato Cooan

efettht8lsso

afucinAd

aeopSas

0CmP

W3 1 ..

3

00 Chemical V

Conure

2

l lofu

owe

supplies

tConri2 insnm

tion

26-/27

1 885

4648

1540"

based an to

afe

aedictionso

use Pocedures to correct conh ol av ltigo t outhe

14-

= A

3 ' 64 :,

401

range detector shutoff at high powers

3 1/33

1 878

M

W4

1

3

0

0-0irt~__97

Knowledgnaes nofM

yofuMa

a lsseor rat

sodrt wil hav eon

iar

011 In-eon. Temperature Monitor

301

cIrculation Indications

3

7"

7

1

Knowledge of the bases for prionitining

safety functions during abnormal/

022 Coentainment Cooling

-

4.22 emergency openations

30140

I 858

022 Containment Cooling

201-

-

-

-

-

-

-

-

-

Knowledge of bus power supnes to. containment cooling fans

3 0"/3 1

t 898

Ability to predict teaimpacts of the following malfunction operation.

nd

based on those predo*ions, use procedures to coaTed. control oa mittgate the

t25Ic Condenser

-

-

-

-

-

-

2 02

coom mnoseuct

S of. Higintlaw toot coolng ternperature 27-12S

1 581e

Knowledge of physical connections andulor cause and effact

04 C.onlldensate.

1

netationsahips MFW

2612S

1 4151

3Ablity

to manually

oparate and/or monitor tn e caotr

.

Losso

,56 Condeneat.

2 04

condensate puumps

36y2o 8

649 1

Knouolity of.

r

y ....

a

I

a

deraan man

r inthc

o na

e

a

.. roo

So p

of

159

M i

n

e~

l

at

r

.

,.

, 01

a a ti na ip* .S /G $

3..

. **

,. . .

1113 3

1914

1

059~~I1

Main.

.....

',

pffnifT

tN

Liqsi

t

Cad

dW

eost

40

3

reate

i

n

isae

cexc

os

393

8

407

0

21

Waso

. Os .

Olsposal

306

C

ora

aioshi

p

ARM

and

PRMsystems

3 /3

1

191

1

A b i lit y t o p e d

h em

a y

s opr

t

he

a

wfogoin

M a

l n

a

o o p e S a io n

a e d

SArea Radeiaton MonitorDng

202

o

u

of

ee

steo

o

efa

due

28/2d9

affe

WA

ACathersaanTl.

4.

2

413

1

2

0

1

Ore uPan

TOtl

23

23

2

-a

e on

wh

os p3d cto1

us11c d r s t

o r c , o t o * m tg t

h

For Official Use Only Until Aft., V22102

12/11/91

SYSTEMS T2G1

E

Ct

0

I

I

S

I

I I I

I

i

I

I II

I

I I

U

a

C

&

P

I I

I

I

I

f II

S I

I

I I!

-i I

ii II ii

SI iii

ii'

Sb lii

I

5

)

S

C

CI

ii

iii

II  Hi

I I I I

Ii

I

j

I

I

Ii I I

I

Ii

I.

I

1

I

131 liii

115

-

I a

S

ri

• i

Ij

0; A

Ii

0

I

I

8

I

I

!ii

Im

I!

17

05

4

I

A*

E

McGulre Sample Plan

I

I Ah~ih, t, a*ht~in anti,,rlf

V

r,n*ntrnllnd nrocedure CODV

Conduct of

Operations

(muti

nitAbiityto xplin he vanation In control; board layouts, systeTms=,

-A

..

-.

..

,

.^.,I

r..in.*

hw*Jmaon iinik a t R facility

.21 ly

0U nH

--

" w

--

, ..........

pFFF93u-m-s-cr

all mo

re

A.bility to perform specific system and ,..e.*r=*dpa

nprocdrsdnn=l

o

21.3 of operation

1.1.

3.

Ablt o1Ct wths otosadidcations and to determine-i tey are

2..1 correctly reflecting the desired plant lineup

1./.

6.

I

nnlI

II

,

1224

instrumentation, and prUoce

• Ijd'Iure

a

g 'ons

gt

'tv

....

2..3 Knowledge of rod control programming

2.563.9

Total

Knowledge of facility ALARA program

1

Knowledge of radiation eJ(xposure 10111s and co-nta-min-atio-n-c=4

Including

permissible levels in excess of those authordzed

1251.

Radiation

Control

IT o t a l

1 ./ .

2425

Knowledge of fire protection procedures

1

Knowledge of facility protemtion requirements including tire brigade and portable i re

2.4.26

fighting equipment usage

Emergency

Procedures

and Plan

4

4

Toter 3 on

oa

7

17

1

For Official Use Only Until After 2/22/02

12/10/01

'Tota

Equipment

Control

I

I

~II

Copy 1 of 3

111 143.11

5

5

I ....

260.11

I

12.8/3.0" I

1

4

4

Generics

3.1/3.2

I

NRC Written Exam Sample Plan Development Method

The sample plan was developed in accordance with the methodology recommended by

the NRC in Attachment 1 of ES-401. The following statements amplify this process.

Differences of Method: The sample plan was developed using the random number

generation function of Excel instead of using tokens. The random number generation

function is programmed to produce an evenly distributed random number between 0 and

the number entered into the argument of the function. For example, if the number 20 is

entered as the argument, the function produces a resultant between 0 and 20 on an evenly

distributed random basis. The result is mathematically equivalent to using the method of

selection by tokens.

Initially, all K/A E/APE, System and Generic topics listed in ES-401 are screened and

those topics that apply only to B&W or CE are eliminated. All NRC K/A topics and all

Westinghouse (WE) E/APEs are retained for sampling. Using the selection methodology

described in Attachment I to ES-401, an Excel spreadsheet is used to generate the RO

examination. When the K/A is randomly selected, the author manually enters the

corresponding K/A stem statement, the K/A description and importance rating from

NUREG 1122.

SRO Exam Samoline: The SRO examination spreadsheet automatically imports all

applicable RO K/As into the corresponding Tiers and Groups in the SRO sample plan.

The final outcome results in 89 K/As that are common to both the RO and the SRO

sample plans. There are 7 E/APEs and 4 Generic SRO-only K/As that must then be

randomly selected to increase the number of questions to 100. These K/As are restricted

to those K/As that are identified as having ties to 1OCFR55.43(b) in NUREG 1122 for

those K/As in Tiers 1 and 2. For Tier 3 (generic K/As), one additional SRO-only K/A is

randomly added to each of the four K/A generic categories. It should be noted that there

are very few generic K/As that were explicitly correlated to 10CFR55.43 in NUREG

1122 (and no generic K/As in category 2.3 (Radiation Control) although

1 OCFR55.43(b)(4) states: "Radiation hazards that may arise during normal and

abnormal situations, including maintenance activities, and emergency situations. ') This

seems inappropriate, as one of the primary differences between the jobs of RO and SRO

is the SRO responsibility for plant administrative tasks. Therefore, all generic K/As are

randomly sampled when adding the fourth K/A to each generic category. These are then

reviewed to ensure that an SRO-only question can be drafted to the K/A.

This produces an exam outline with 100 K/As of which 89 are common to both exams

and 1 are unique to the SRO exam. Similarly, there will be 11 system K/As that are

used on the RO exam but not used on the SRO exam due to the larger number of RO

system K/As in the sample plan.

During the exam development process, 25 questions will be written that are unique to the

SRO exam. The sampling process only identifies 11 of these questions. The exam

authors will identify 14 additional SRO-only questions as they become more familiar

Record of Rejected K/As

Tier and

Randomly

Reasons for Rejection

Group

Selected K/A

1 - 1

APE 026 Loss

There is no significant difference between Units 1 and 2 in

of Component

regards to the Component Cooling Water system.

Cooling Water

G 2.2.4

1-1

APE 026 Loss

"Knowledge of procedures and limitations involved in

of Component

initial core loading" does not apply to the CCW system

Cooling Water

because there are no procedures and limitations on this

G2.2.31

system that are unique to initial core loading..

1-2

APE 008

This K/A states: "Ability to operate and/or monitor the

Pressurizer

... LPI system for a pressurizer vapor space accident

Vapor Space

(Relief Valve Stuck Open)". There is no plant requirement

Accident

to operate the low-pressure injection system under these

AAl.05

conditions because plant pressure would stabilize above the

low pressure system injection point.

2-1

System 004

Resampled from K6.12 top K6.04 because there is no BIT

CVCS K6.12

installed at McGuire. K6.12 only applies to systems with a

Boron Injection Tank. Approved per telcon with Lee

Miller on 10/10/01.

2-1

System 068

System 068 (Liquid Radiological Release) was randomly

Liquid

selected to be tested twice. This system is already being

Radiological

tested once and the number of valid test items that could be

Release

developed is relatively small. The CVCS (NV) system was

randomly selected to fill out the sample plan for a total of

23 RO systems.

2-1

System 071

System 071 (Waste Gas Disposal) was randomly selected

Waste Gas

to be a tested twice. This system is already being tested

Disposal

once and the number of valid test items that could be

developed is relatively small. The ESFAS system was

randomly selected to replaced the WGD system and fill out

the sample plan for a total of 23 RO systems.

2-1

System 072

System 072 (Area Radiation Monitoring) was randomly

Area Radiation

selected to be a second system for testing. This system is

Monitoring

already being tested once and the number of valid test

items that could be developed is relatively small. The

Condensate system was randomly selected to replaced the

ARM system and fill out the sample plan for 23 RO

systems.

2-1

System 022

This generic K/A "Knowledge of low power and shutdown

Containment

implications in accident (e.g. LOCA, loss of RHR)

Cooling G2.4.9

mitigation strategies" does not apply to the containment

cooling system. The containment cooling system is not

used to mitigate low power or shutdown accidents.

Form ES-401 -10

ES-401

Draft Submittal

(Pink Paper)

Operating Test Simulator Scenarios

MCGUIRE EXAM

50-369, 370/2002-301

FEBRUARY 11 - 15, 2002

Appendix D

Scenario Outline

Form ES-D-I

Facility:

McGuire

Examiners:

Scenario No.:

1

Op-test No.:

Operators:

Objectives: 1) The crew will deal with minor malfunctions that will be

compounded by the rods not working in automatic.

2)

The crew will have to cut

load due to condenser dump valve being open and power going above 100%.

3)The

crew will deal with a loss of essential bus as a result the crew will have to

swap to the other train of components.

4)

The crew must deal with a small NC

leak that becomes a LOCA and a loss of ECR.

Initial

Conditions: 100% Power/

"B"

Train Components in Service/

Turnover: "IA"

D/G Tagged/

"IA" AFW pump tagged/ Unit 2 is available for

auxiliary steam/ Maintain present plant conditions

Event

Malf.

Event

Event

No.

No.

Type t

Description

1

RO

Tref failure -

fails

to 557 degrees

2

BOP

Pressurizer Level Channel 2 fails

low

2

N

Place excess letdown in service

3

RO

Atmospheric dump valve fails

open

3

R

Reduce turbine load due to dump valve failure

4

BOP

Loss of ETB with failure of D/G to start

5

M(ALL)

LOCA with a failure of ECR

Post major event failures

Main Steam isolation fails

in automatic

2 rods fails

to insert on trip

Automatic Phase "A"

on "A"

train

does not work

No automatic Safety Injection

Sump suction valve fails

to open automatically

The loss of ETB is

a DAS at MCGuire.

It

comprises

i

of the important core melt events.

(N)ormal, R)eactivity,

(I)nstrument,

(C)omponent,

(M)ajor

NUREG 1021, Revision 8

PROGRAM: McGuire Operations Training

MODULE:

TOPIC:

Initial License Operator Training Class 20

Nuclear Regulatory Commission Simulator Exam

Scenario 1

REFERENCES:

McGuire Technical Specifications

AP/1/A/5500/01

Steam Leak

AP/1/A/5500/12

Loss of Letdown, Charging or seal Injection

AP/1/A/5500/14

Rod Control Malfunction

AP/1/A/5500/07

Loss of Electrical Power

EP/1/A/5000/E-0

Reactor Trip or Safety Injection

EP/1/A/5000/E-1

Loss of Reactor or Secondary Coolant

EP/1A/5000/FR-P.1

Response to Imminent Pressurized Shock

EP/1/A/5000/FR.Z.1

Response to High Containment Pressure

EP/1/A/5000/ES-1.3

Transfer to Cold Leg Recirculation

RP/O/A/5700/00

Classification of Emergency

Author:

Facility Review:

NRC Review:

February 1, 2002

Rev. 1

1

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

SIMULATOR OPERATOR INSTRUCTIONS

Bench Mark

ACTIVITY

DESCRIPTION

S

Sim. Setup

Rod Step On

[]

IC-142

o]

RUN

O

Update Status Board,

See Shift Turnover Information

Setup OAC

Setup ICCM, Turbine

Displays, & Trend

Recorders.

Check Rod Step

Counters agree with rod

positions

El

(M) EPQ001A

Loss of D/G "IA" Control Power

Set = 1

El

(LOA) CA009

Rack out breaker for "1 A" Auxiliary Feedwater Pump

Set = Rack Out

o

(MAL) IRE010D14

2 Rods fail to insert when tripped

(MAL) IRE010H2

o

(M)

ISE002A

No automatic S/I both trains

(M) ISE002B

(M) ISE006A

Failure of automatic Main Steam Isolation

(M) ISE006B

El

(M) ISE003A

Failure of Phase "A" Train "A" to automatically actuate

El

(OVR) SVO05D

Fails 1SV-47 OPEN

Off - Insert

El

(M) NI002F

"A" train containment sump valve fails to automatically

open

Set = 0

o

(M)

NV020E

Fails 1 NV-35 open

Set = 100

2

Bench Mark

ACTIVITY

DESCRIPTION

o]

Freeze.

E]

Update Fresh Tech.

Spec. Log.

o]

Fill out the NLO's

Available section of

Shift Turnover Info.

E]

Prior to Crew

RUN

Briefing

o3

Crew Briefing

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.

E

T

T-0

Begin Familiarization

Period

O

At direction of

(MAL) IRE001

Tref fails to 557 degrees

examiner

Set = 557

At direction of

(XMT) ILE002

Pressurizer level channel 2 fails to "0"

examiner

Set = 0

INV-1A will not reopen

(M) NV020A

Set = 0

Set both to trigger 1

At Direction of

(MAL) IDE004A

Fails atmospheric dump valve open

Examiner

Set = 100

Ramp = 2

O]

At direction of

(MAL) EP008B

Trips Operating Train ETB

examiner

At step 39 of

(M) NCO07A

Initiates a small NC system leak

AP/07

Set = 1

Ramp 300

At direction of

(M) NC008A

Initiates LOCA

examiner

0

Delete malfunction when BOP opens 1NI-185A

Terminate the scenario upon direction of Chief Examiner

3

Event 1:

Tref failure

Time

Pos.

Expected Actions/ Behavior

Comments

RO

Recognizes Unwarranted Control Rod Insertion

and informs Crew.

"

No turbine or reactor power excursion

"

Tref circuit failed to 557 degrees

RO

Places CRD Bank Selector Switch to manual

RO places Rods in Manual

and verifies movement stopped

Checks rod movement stopped

SRO Enters AP/14, Rod Control Malfunctions and

directs activities.

RO

Performs the following as necessary to maintain

Tcolds 555 degrees to 557 degrees

"* Lower turbine load or

"* Borate NC system

RO

Announce occurrence on page

RO

RO

RO

SRO

Check all rods - ALIGNED WITH ASSOCIATED

BANK

Checks "Rod Control Urgent Failure" alarm dark

Checks the following normal:

Turb Imp Pressure Channel 1

T-ref

1 A NC loop T-ave

1B NC loop T-ave

1 C NC loop T-ave

1D NC loop T-ave

Go to Enclosure 4

Go to Enclosure 4 (Response to

Continuous Rod Movement)

SRO e

Evaluate rod movement

Tref circuit is the failure SRO

Check the following normal

should notify IAE to investigate and

1. Turb Imp Pressure Channel 1

maintain Tcolds 555 degrees to 557

2. T-ref

degrees by adjusting control rods in

3. 1A NC loop T-ave

manual or adjusting turbine load or

4. 1 B NC loop T-ave

boration/dilution of NC system.

5.

1C NC loop T-ave

6.

1D NC loop T-ave

Checks to see if failed channel has been

identified

1

Exit procedure

4

Event 2:

Pressurizer Level Channel 2 Failure

Poe.

Expected Actions/Behavior

Comments

BOP On a loss of letdown ensure the following

INV-35A will not close - BOP must

closed:

attempt to close. Immediate action

• 1 NV-458A

of AOP.

• 1 NV-457A

• 1NV-35A

SRO Enters AP/12 Loss of Letdown, Charging or Seal

Injection

BOP If at any time "REGEN HX LETDN HI TEMP"

BOP will take action if appropriate

alarms, close:

• 1NV-1A

1NV-1A closed due to failure

• 1NV-2A

RO

Stop any power or temperature changes in

progress

RO

Announces occurrence on page

SRO IF this AP entered due to loss of letdown only,

SRO will go to step 35 in this AOP

then go to step 35.

BOP Ensures "NC Sys M/U Controller" in AUTO

BOP Ensures charging flow going down to maintain

Pzr at program level

BOP Checks "Letdn Relief Hi Temp" alarm has

remained dark

BOP Checks 1NV-21A - closed

5

Event 2:

Pressurizer Level Channel 2 Failure

I Pos. F

Expected Actlons/ Behavior

Comments

BOP

0 D

NO, due to level instrument failure

BOP will perform the following:

1. Ensures the following are selected to

an operable channel

"Pzr level control select" 1-3 position

" Pzr level rec select"

2. Ensure Pzr level greater than 17%

3. Place the following switches in "MAN"

A

B

Checks Pzr heater group supply breakers

closed

b. Check normal spray available

c. Place the following Pzr heater groups in

Manual and ON to maximize spray.

• A

D

Close the following breakers:

A

B

"D

• Close C Pzr heater group supply

breaker

BOP Checks the following OPEN

NO, go to step 42

"* 1NV-1A

"* 1NV-2A

SRO Checks to see if immediate restoration of normal Orifice isolation valve NV-35 has not

letdown is possible

closed. So will go to step 47 to place

excess letdown in service.

"* Both NV 1 & 2 open in the past 30 minutes

May have to provide management

"* Orifice isolation valves closed before or at the guidance that excess letdown is

same time as NV 1 & 2.

desired.

6

4

5

Event 2:

Pressurizer Level Channel 2 Failure LO

Pos.

Expected Actlons/ Behavior

J

Comments

BOP Establish excess letdown

Adjust charging to minimum while maintaining

the following:

"* NC pump seal injection flow greater than 6

gpm

"* Pzr level at program level

1. Opens the following:

• 1KC-315B and 1KC-305B

• Places 1 NV-27B to VCT position

2. Opens and closes 1NV-26

3. Checks the following OPEN:

• 1 NV-94AC

• 1NV-95B

4. Opens 1 NV-24B and 1 NV-25B

5. Slowly opens 1 NV-26 while maintaining

excess letdown heat exchanger temp. less

than 200 degrees.

SRO Go TO step 47.n

BOP Notified chemistry that excess letdown is in

service.

Adjust charging flow as desired while

maintaining:

"* NC pump seal injection flow greater than 6

gpm

"* Pzr level at program level

"* Operate Pzr heaters as desired

SRO

SRO should notify Work Control Center or IAE

Tech Spec. 3.3.1 function 9

to investigate and repair failed instrument

7

Atmospheric Dump Valve Fails OPEN

Time

Poo.

Expected Actior

Behavior

Comments

CREW Recognizes symptoms of a steam leak

T-ave-Tref annunicator may come in

alarm

"* T-ave decreasing

"* Power increasing

SRO Enters AP/01 Steam Leak

Crew Monitors fold out page

RO

Reduces turbine load to maintain:

"* Excore NI - less than 100%

"* NC loop DITs - less than 60 degrees

"* T-ave at T-ref

BOP Checks Pzr level -stable or going up

SRO Will return to step 3 if Pzr level can not be

maintained.

RO

Announces occurrence on page

RO

Identifies and isolates leak:

"* Checks S/G PORVs - CLOSED

"* Checks condenser dump valves -CLOSED

An atmospheric dump valve will be

OPEN - RO must select "OFF RESET'

"* Checks atmospheric dump valves - 1 OPEN on Steam dump interlock Bypass

"channel A and B. Isolation valve will nol

• Checks containment conditions - NORMAL

close. Must dispatch an operator to fail

"* Checks turbine driven CA pump - OFF

air to atmospheric dump valve.

"* Checks steam line drain valves - CLOSED

"* Checks Unit 2 - steam header pressure

SRO Exits procedure when leak is isolated.

8

Event 3:

Event 4:

Loss of Operating Train ETB

Time I Poe.

Expected Actions/ Behavior

Comments

Crew Recognizes loss of operating train "ETB"

SRO Checks bus energized and sequencer applying

The diesel will NOT start due to failure

loads.

SRO entered AP/07

BOP If both NV pumps off, Then isolate NORMAL

Critical

letdown.

Start opposite train:

"* NV pump

"* KC pump

"* RN pump

Go to step 3

SRO Verifies NO Safety Injection has occurred

"A" train NV pump will be on

If both NV pumps off then isolate:

"* Excess letdown

"* ND letdown

If any pump was manually started per step 1 go

to step 5

SRO Check D/Gs - OFF

BOP Align KC as follows:

Critical

Places 1 KC-51 A to AUTO

Ensures the following are open

1. 1 KC-3A

2.

1KC-230A

3.

1KC-394A

4.

1 KC-345A

5.

If needed keep thermal barrier valves open

raise KC flow to KF hx by opening 1 KC-1 49

Ensures KC flow is less than 4000 gpm per

operating KC pump

SRO Checks any charging pump - Running - YES

BOP Align RN as follows:

"* Check 1A RN pump- Running -YES

"* Close 1 RN-43A

"* Throttle 1 RN-89A to desired cooling

SRO Notifies Unit 2 RO to start 2A RN pump

EXAMINER CUE:

2A RN pump is running

SRO Checks B/O on 1 ETA

NO, go to step 22

BOP Checks 1RN-86A-OPEN

SRO Dispatches operator to close:

1KC-228B

1KC-18B

9

Event 4:

Loss of Operating Train ETB

Time

Poe.

Expted Actlons/ Behavior

T

Comments

SRO Checks 1B ND train -was not in RHR mode

Go to step 30

SRO

Checks normal letdown - IN SERVICE

No, may have operator place excess

letdown back in service.

SRO Go to step 36

RO

Announces occurrence on page.

SRO Checks D/G on bus that was blacked out - NO

Place affected D/G Mode Select to

"C/R"

"* Depress then release the "RESET"

pushbutton for the affected train's

sequencer.

"

Start D/G.

BOP Check bus energized and sequencer applying

Place affected D/G Mode Select to

loads

"C/R"

"* Ensure normal and standby breaker

open to allow auto loading of bus.

"* If bus not energized or sequencer

not loading bus then go to

Enclosure 1.

SRO Go to Enclosure 1 - Manual Loading of

Emergency Bus

BOP e

Ensure S/I Reset

Check 1 ETA - Energized from Offsite

Power

Go to Step 15

BOP Check 1ETB - Energized from Offsite Power -

Go to step 20

NO

BOP Hold "RESET" on "1B D/G LOAD Seq" while

completing steps 21 through 23.

10

Event 4:

Loss of Operating Train ETB

11

Time

Poe.

Expected Actions/ Behavior

I

Comments

BOP Unload 1 ETB bus as follows:

1. Open 1B CA pump breaker

2.

Open the remaining pump breakers on

1ETB

"* NV

"* ND

"* NI

"* KC

"* RN

"* KF

"* Ensure Train B NS is reset and open NS

pump breaker

3. Open 600v essential transformer feeder

breakers:

S1 ELXB

1ELXD

1 ELXF

BOP *

Place "IB D/G Mode Select switch to "C/R" Breaker will not close.

Close "1 ETB Emerg Breaker"

Release "RESET" on "1B" D/G Load

SEQ"

Stop D/G

Return to procedure and step in

effect.

Go back to step 38 in body of

procedure.

NC LEAK WILL BEGIN AT THIS POINT

Event 5:

NC System Leakage

Time I Pos. I

Expected Actions/ Behavior

Comments

BOP Report either of the following:

"

Pzr level decreasing

"

Pzr press decreasing

"

Containment Vent Isol (EMF39)

"*

"Ice Cond Doors Open" Annunciator

SRO Go to AP/10 (Case II) NC System Leakage

and directs activities

BOP

Report Pzr Level decreasing:

"

Report NV-238 opening

"

Open NV-241 while

maintaining 6 gpm

Seal Injection Flow

Starts additional NV Pump

Isolate excess letdown

• If Pzr level less than 4% then:

"

Manually Trip Reactor

"

Manually SI

Crew Returns to step 1 if Pzr level can not be

maintained.

Crew Isolated leak if location is known

BOP Reports Pzr Pressure stable or trending to 2235

psig

RO

Reports Main Steam line is INTACT

" Reactor power at turbine power

" NC loop T-Ave is stable

SRO When leak is determined greater than makeup

capability, directs crew to trip reactor and initiate

Safety Injection

RO

Manually trips Reactor (Train A & B)

Two rods fail to insert

Critical BOP Manually initiates Safety Injection both trains

12

AP-10 Evaluation

Event 5:

LOCA

Time I Poe.

Expected Actions/ Behavior

Comments

SRO Go to EP/E-0 and directs activities

SRO Reviews Foldout page with crew

NCP trip criteria based on loss of

subcooling

RO

Report Reactor Trip:

"* rod bottom lights

TWO rods will be stuck

"* reactor trip breakers open

"* I/R amps decreasing

RO

Reports Turbine Generator tripped

1

TV's or GV's closed

BOP Reports ETA and ETB energized

"B" will be de-energized

RO

Reports SI status light - LIT

After Immediate Actions are

completed by operator they can

close MSIV's if they recognize they

are open and should be closed.

BOP Report LOCA sequencers (A & B) actuated

RO

Announce "Unit 1 Safety Injection" on page

BOP Checks ESF Monitor Light Panel

"* Groups 1,2 and 5 DARK

The "B" side of all panels will be dark

"* Group 3 LIT

"* Checks OAC in service

BOP Reports all Ss and St components in Group 4

If not already done BOP should

NOT -LIT

manually initiate Phase "A" Train "A"

RO

Reports that CA is running and at least 3 S/G's

Motor driven pumps are not available.

NR level > 17%

BOP Reports KC pumps running

"A" train only

BOP Reports RN pumps running

"A" train only

13

E-0 Evaluation

Event 5:

LOCA

Time

Pos.

Expmct* d Actlonsd Behavior

Comments

SRO Directs Unit 2 Operator to throttle RN to

EXAMINER CUE:

minimum & start 2A RN pump

2A RN pump is running

RO

Checks/reports all S/G pressures > 775 psig

BOP Reports Containment pressure has remained

NO

less than 3 psig

a

record approximate time of reactor

trip

"* Check row G on Monitor Light

Group 4

"* If any row G is dark on energized

train

Stop all NC pumps

Stop all RV pumps

Energize H2 igniters by depressing

"ON" and Override

When time allows check Phase B

HVAC equipment per Enclosure 2

BOP Report NV Pump to Cold Leg Flow gauge

indicating flow - YES

"* checks NC pressure < 1600 psig

"* checks NI pumps indicating flow

"* checks NC pressure - less than 286 psig

"* checks ND pumps - indicating flow to cold

legs

SRO When available notifies OSM or other SRO to

EXAMINER CUE:

implement Generic Enclosure 22

OSM will ensure Generic Enclosure

22 is implemented.

RO

Checks CA flow > 450 gpm and takes

RO will take control of auxiliary

control of CA to maintain no load levels

feedwater.

checks VI header pressure > 60 psig

Maintains N/R level between 32% and 50%

BOP

If any NC pump ON, then check Tave stable

or trending to 557 degrees

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

stable or trending to 557 degrees.

BOP Reports Pzr PORV & Spray Valves closed

BOP Reports subcooling > 0 degrees based on Core

Exit Thermocouples

BOP Reports all main steamlines INTACT

RO/ Report S/G tube rupture parameters indicate

BOP that S/G tubes intact

14

Event 5:

LOCA

Time

Pos.I

Expected Actions/ Behavior

Comments

SRO Checks if NC system is NOT intact:

Perform the following:

"* Containment EMFs - normal

If H2 igniters are off then perform

"* Ice Condenser Lower Inlet Doors Open

the following:

alarm - DARK

Energize H2 igniters by depressing On

Containment pressure < 1 psig

and Overrride

Containment sump level normal

Dispatch operator to stop all NF AHU's

Implement F-0 CSFST

Go to E-1

CSFST will necessitate going to P-1 then Z-1

The crew will only do the first step on

P-1 and based on pressure will exit

P-1.

BOP P-1 - Response to Imminent PTS

ND pump flow is greater than 500 gpm

Check NC pressure - Greater than 286 psig

-Then return to procedure and step in

NO

effect. Go to Z-1

SRO Will go to Z-1, Response to High Containment

Pressure

CREW If loss of emergency coolant recirc has occurred,

THEN this procedure may be completed as time

allows.

Crew Monitors foldout page

BOP Stop all NC pumps.

BOP Ensure all RV pumps are in manual and off.

SRO Dispatch operator to remove tags and close

breakers for the following valves:

"* 1EMXA-R2A

"* 1EMXAB1-6B

BOP Check containment pressure - LESS THAN 15

PSIG.

BOP Check any NS pump - ON

SRO The remainder of this EP may be performed as

time allows.

15

Event 5:

LOCA

Time

Pos.

Expected Actions/ Behavior

Comments

SRO

ES 1.3 Transfer to cold leg recirc.

BOP Checks containment sump level - greater than 3

feet

Checks KC flow to each ND heat exchanger

No, on "B" train crew will do RNO

BOP greater than 5000 gpm

BOP Resets Safety Injection and Sequencer

MAKE SURE SIMULATOR RUNNER

READY TO DELETE MALFUNCTION

FOR 1NI-185A IN NEXT STEP.

BOP Align ND system for recirc:

Place the control permissive in

Critical

Check 1 NI-185A OPEN - NO

"BYPASS" and open 1 NI-185A

Checks 1A ND pump on - YES

Go to step 6b

Check 1 NI-1 84B OPEN - NO

Go to step 6e

Close 1 FW-27A

Check any ND pump on

Align NV and NI systems for recirc:

BOP Check NC pressure less than 1600 psig

Close the following:

"*1NI-115A

"

1NI-144B

Close 1NI-147A

Close

1ND-30A

Align ND train discharge to NI and NV pump

suctions:

"

Open 1NI-332A

"

Open 1ND-58A

Close 1NI-100B-

can not close

Close 1NV-221A

SRO !Check if NS should be aligned for recirc - NO go

to step 9

SRO Check is ND aux spray is required - NO go to

step 10

16

Event 5:

LOCA

EXAMINER NOTE: Be sure SRO classifies event at end of scenario.

Classification of event: ALERT

17

Time( Poe. I

Expected Actions/ Behavior

j

Comments

CREW If at any time a B/O signal occurs, then restart

S/I equipment previously on.

SRO Checks for proper recirc flow and valve

alignment

Checks the following closed

1ND-19A

1NV-151A

1NV-221A

Checks flow indicated from:

"* NV pump

"* NI pump

"* ND pump

Checks the following closed:

I 1KC-50A

1KC-1A

Check KC flow to ND heat exchanger

established

SRO Implement F-0 CSFST

SRO Return to procedure and step in effect.

TERMINATE SCENARIO AT DIRECTION OF CHIEF EXAMINER

SHIFT TURNOVER INFORMATION

UNIT 1 STATUS:

{PRIVATE

}Power Level:

{PRIVATE

}Power History

100%

NCS [B] 7,

At 100% for 100 days

59ppm

Pzr [B]: 759 ppm

Xe: OAC

Core Burnup: 200 EFPDs

CONTROLLING PROCEDURE:

OP/1/A/6100/03 Controlling Procedure for Unit Operation

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

"lA" Diesel Generator tagged for maintenance.

"1 A" Auxiliary Feedwater pump tagged for oil change - PM

Unit 2 is available for auxiliary steam.

Reduce power to 90% to do turbine valve movement test.

Work Control SRO/Offsite Communicator

Unit 2 SRO

Thad

Jim

NLO's AVAILABLE

Unit 1

Aux Bldg.

Robb

Turb Bldg.

Fred

Extra(s) Bill, Craig, Russ, Ron

Unit 2

Aux Bldg. Joe

Turb/Service Bldg. Mike

18

Appendix D

Scenario Outline

Form ES-D-l

Facility:

McGuire

Scenario No.-

2

Op-test No.:

Examiners:

Operators:

Objectives: 1) Determine if

the crew can deal with a variety of malfunctions

using immediate actions and AOP's.

2) Determine if

the crew can perform an

orderly shutdown of the plant then handle a large STGR without filling

the

steam generator.

Initial

Conditions: 55% Power/

"B" Train Components in Service/

Turnover:

"lA" DIG Tagged/

"lA" AFW pump tagged/ Unit 2 is

available for

auxiliary steam/ Begin load increase

Event

Malf.

Event

Event

No.

No.

Type*

Description

1

RO

Power Range 43 fails

high

2

BOP

Pressurizer Pressure channel 2 fails

high

3

BOP

NC PORV 36 fails

to 25% open - must close block

valve to isolate

4

RO

S/G Control Valve failure - normal controller

fails

5

M (ALL)

Steam generator Tube Leak -

40 gallons per minute

6

N

Removing Feedwater Pump from service

6

R

Load reduction due to shut down of plant

7

M (ALL)

SGTR -

430 gpm

Post Major Event Failures

Failure of automatic feedwater isolation

MSIV on ruptured S/G will not close

No automatic Safety Injection

One reactor trip

breaker will not open

EMF for ruptured S/G failed as is

(N)ormal, R)eactivity,

(I)nstrument,

(C)omponent,

(M)ajor

NUREG 1021, Revision 8

PROGRAM: McGuire Operations Training

MODULE:

TOPIC:

Initial License Operator Training Class 20

Nuclear Regulatory Commission Simulator Exam

Scenario 2

REFERENCES:

McGuire Technical

AP/1/A/5500/06

AP/1/A/5500/11

AP/1/A/5500/10

AP/1/A/5500/16

EP/1/A/5000/E-0

EP/1/A/5000/E-3

RP/O/A/5700/00

Specifications

Loss of S/G Feedwater

Pressurizer Pressure Anomalies

NC System Leakage Within the Capacity of both NV Pumps

Malfunction of Nuclear Instrumentation

Reactor Trip or Safety Injection

Steam Generator Tube Rupture

Classification of Emergency

Author:

Facility Review:

NRC Review"

February 1, 2002

Rev.1

1

1.

2.

3.

4.

5.

5.

6.

7.

SIMULATOR OPERATOR INSTRUCTIONS

Bench Mark

ACTIVITY

DESCRIPTION

Q

Sim. Setup

Rod Step On

o

IC-143

o]

RUN

O

Update Status Board,

See Shift Turnover Information

Setup OAC

Setup ICCM, Turbine

Displays, & Trend

Recorders.

Check Rod Step

Counters agree with rod

positions

o

(MAL) EPQ001A

Loss of D/G "iA" Control Power

Set = 1

o

(LOA) CA009

Rackout breaker for "lA" Auxiliary Feedwater Pump

Set = F

o

(M)

SM006A

MSIV on ruptured generator fails open

O

(M) ISE002A

No automatic S/I both trains

(M) ISE002B

O

(M)

ISE007A

Failure of Feedwater Isolation - both trains

(M) ISE007B

o

(M)

EMF133

Set EMF 33 at 10

Set = 10

O

(M)

EMF173

Fails EMF 24 to "0"

Set = 1

O

(M)

IPE001A

Failure of "A" train reactor trip breaker to open

(M) IPE002A

[]

2

SIMULATOR OPERATOR INSTRUCTIONS

Bench Mark

ACTIVITY

DESCRIPTION

O]

Freeze.

o]

Update Fresh Tech.

Spec. Log.

o]

Fill out the NLO's

Available section of

Shift Turnover Info.

o

Prior to Crew

RUN

Briefing

o]

Crew Briefing

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.

o

T-0

Begin Familiarization

Period

O

At direction of

(MAL) ENBO13E

Power Range NI 43 fails high

examiner

Set = 200

Ramp = 5

O

At direction of

(MAL) NCO03F

Pressurizer Pressure Channel 2 fails HIGH and NC

PORV NC-36 sticks at 25% open

examiner

Set = 25

Set both to trigger 1

(XMT) NC039

Set = 2500

O

At direction of

(MAL) IFE009B1

S/G "B" Control Valve Failure

examiner

Set = 0

Ramp = 5

At direction of

(M) S/G001A

Initiates 50 gpm tube leak on "A" steam generator

examiner

Sel = 50

Ramp = 120

C

(M)

S/G001A

Initiate once FWPT has been shutdown

Sal =435

Design basis tube rupture

Ramp = 120

o]

Terminate the scenario upon direction of Chief Examiner

3

Event 1:

Power Range 43 Fails High

Time

Pos.f

Expected Actions/Behavior

Comments

RO

Determines NI-43 has failed high and places

Immediate action

rods to manual

SRO Entered AP/16 Malfunction of Nuclear

Instrumentation

RO

Checks S/G levels at programmed level

Should place reg. Valve for "A" and "D"

S/G to manual and return to program

level

RO

Announce occurrence over page

RO

Checks P/R channels - only one failed

RO

Positions "PR to S/G Program level defeat"

switch to 41/43 position

RO

Secures any power increase.

BOP Performs the following actions at the

"Miscellaneous Control and Indication Panel"

"* Rod Stop Bypass to N43

"* Power Mismatch Bypass to N43

BOP Performs the following actions at the "Detector

Current Comparator" drawer

"* Upper Section to N43

"* Check upper section light lit

"* Lower Section to N43

"* Check lower section light lit

BOP Performs the following at the "Comparator and

Rate" drawer

"* Comparator Channel to N43

"* Check comparator light for N43 lit

BOP Trips bistables for failed channel

e Remove control power fuses from N43

RO

Checks the following status lights for the failed

channel lit:

"* NUC Overpower Rod Stop Bypass

"* P/R Hi Flux Lo Stpt

"* P/r Hi Flux Hi Stpt

"* P/R Hi Flux rate

4

Event 1:

Power Range 43 Fails High

Time

Poe.

Expected Actions/ Behavior

j

Comments

RO

Checks the following annunciators lit:

"* P/R Hi Voltage Failure

"* P/R Hi Flux Hi Stpt Alert

"* P/R Hi Flux Rate Alert

RO

Checks the following status light lit:

"* P/R Lo Setpoint Train A Trip Blocked

"* P/R Lo Setpoint Train B Trip Blocked

SRO If desired to control S/G levels in auto then

return affected s/G CF control valves to auto

RO

Ensures operable P/R channel selected to

record on NIS recorder

RO

Adjust control rods to maintain T-ave at T-ref

RO

When T-ave within 1 degree of T-red and auto

rod control desired then return control rods t

auto

SRO Instructs IAE to fail OTDT and OPDT bistables

Tech Spec evaluation

within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of failure

Table 3.3.1-1

3.3.1.2

3.3.1.3

3.3.1.6

3.3.1.16 b,c,d

3.3.1.7

CREW Ensures proper bistables failed for P/R 43

"* NC loop C OPDT Trip

"* NC loop C OTDT Trip

______

I _______

I __________________________________________

5

Event 2 and 3: Pressurizer Pressure Channel 2 Fails High with NC 36 failed to 25%

Time

Poe.

Expected Actions/ Dehei..r

Comments

BOP Recognizes/reports PZR pressure decreasing

SRO Implements AP/1 1 Pzr Pressure Anomalies,

Case 2 and directs activities

BOP Reports Pzr Pressure decreasing

Critical BOP Determines all channels not the same

Places "Pzr Pressure Control Select" to

backup channel - 1-4 position

Critical BOP Checks/reports Pzr PORV's Closed

Will try to close - will not close - must

close block valve

BOP Checks/reports Spray Valves Closed

BOP Reports Pzr PORVs - closed

No for NC-36 will close 1 NC-269

BOP Reports Spray Valves Closed

SRO Go to Step 9

RO

Announce occurrence on page

BOP Checks/reports NV-21A , CLOSED

BOP Checks/reports Pzr A,B & D heaters ON

BOP Checks 1 C PZR heater - ON

BOP Checks Pzr pressure going UP

SRO Go to step 21

SRO Ensures "Pzr PRESS REC SELECT" is on an

operable channel

SRO Will notify Work control center and/or IAE to

Failure will not be fixed

investigate and repair

Tech spec issue with two channels of

OTdT inoperable.

Tech Spec 3.0.3 for two channels

Plus Tech Specs

"* 3.3.1.6

" 3.3.1.8

" 3.3.2.1 .d

" 3.3.2.8.b

6

Event 4:

Normal Controller for "B" S/G Fails Low

Time_ Pos.

Expected Actlons/ Behavior

Comments

BOP Refer to annunciator responses

Annunciators on 1AD-4

C-2

SRO Goes to AP/06 Loss of Feedwater

Critical

RO

Places Feed Regulator to Manual

If S/G CF control valve fails to

Restores S/G level to program level

respond in manual then:

o Select ALT on control circuit

.

Restore to program level

RO

Checks the following channel indicating the

Immediate Action step

same:

"* Feed flow

"* Steam Flow

"* S/G Level

RO

Checks S/G CF control valve in manual control

YES

RO

When the following are met then return affected

S/G CF control to automatic

1. Selected control channels indicated correctly

"* Feed flow

"* Steam flow

"* S/G level

2.

Affected S/G level restored to program level

3. Automatic control is desired

SRO Checks the reactor tripped

NO

RO

Maintains S/G level

Go to step 7

RO

Controls feed flow to maintain S/G NR level - at

programmed level

SRO Checks NC temperature with NC pumps on

stable or trending to programmed temperature

SRO Checks procedure enter due to failed controller

SRO Contacts I&E to repair failed controller

Failure will not be repaired

Exit procedure

7

Event 5:

S/G Tube Leakage on "A" S/G

Time

Po.

Expected Action) Behavior

Comments

BOP Report either of the following:

"* Pzr level decreasing

"* Pzr press decreasing

"* EMF 24 - Blocked - crew will not see

SRO/ Refer to Ann. Response and/or AP 10

BOP/ e

Notify RP shift

RO

-

RDW shift

CT lab

Refer to AP/1 0

1

Have operator secure drains to TB sump

SRO Go to AP/10 (Case I) S/G Tube Leakage and

directs activities

BOP

Report Pzr Level decreasing:

"* Report NV-238 opening

"* Open NV-241 while

maintaining 8 gpm

Seal Injection Flow

"* Starts additional NV Pump

Reduce letdown to

45 gpm or isolate letdown

• If level less than 11% then:

Manually Trip Reactor

Manually SI

SRO If primary to secondary leak is greater than 100 Leak is < 100 gpm

gpm, then trip reactor and go to E-0

RO

Announce occurrence on page

SRO If at anytime while in this procedure Pzr level

can not be maintained stable then perform step

1.

BOP Checks Pzr pressure - stable or trending to

2235 psig.

SRO If NC leakage exceeds Tech Spec limits then

Tech Spec 3.4.13

ensure outside air pressure filter train in service.

SRO Check if unit shutdown is required:

1. Leakage in one S/G - greater than 125 gpd

2. Reduce load in step 8

"

Ensure reactor power is less than 50%

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of exceeding 125 gpd

• Be

in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of exceeding

125 gpd.

SRO Reduce load PER one of the following:

"

AP/1/A/5500/04 Rapid Downpower OR

"

OP/1A/6100/03 Controlling procedure for

Unit Operation

8

Event 5:

S/G Tube Leakage on "A" S/G AP/04 Evaluation - Rapid Downpower

Time f Poe.

Expected Actlons/ Behavior

Comments

RO

Identify "C" S/G as having excessive leakage

AP/04 evaluation Rapid Downpower

Monitor foldout page

determine power reduction rate

check control rods in AUTO - YES

notify SOC of load reduction

initiate turbine load reduction

borate the NC system

check control rods moving in as

required

check turbine impulse pressure >

290#

May refer to RP/00 Classification of

Emergency and RP/10 Immediate

NRC Notification Requirements

check turbine control in AUTO

check Unit 2 aux steam available to

supply header

check P/R instruments indicate

power < 40%

Check < P-8

all CF flows < 40%

Impulse pressure < 290#

Once FWPT is removed from

service the leak size will increase

SRO When leak is greater than makeup capability,

Crew will go back to step 1 of AP/1 0

directs crew to trip reactor and initiate

when Pzr level begins decreasing

Safety Injection

RO

Manually trips Reactor (Train A & B)

Critical BOP Manually initiates Safety Injection

9

Event 6:

SGTR on "A" S/G

E-0 Evaluation

Time

Pos.

Expected Actions/Behavior

Comments

SRO Go to EP/E-0 and directs activities

SRO Reviews Foldout page with crew

RO

Report Reactor Trip:

rod bottom lights

reactor trip breakers open

SI/R amps decreasing

RO

Reports Turbine Generator tripped

TV's or GV's closed

BOP Reports ETA and ETB energized

RO

Reports SI status light - LIT

BOP Report LOCA sequencers (A & B) actuated

SRO/ Announce "Unit 1 Safety Injection" on page

RO

BOP Checks ESF Monitor Light Panel

If not already recognized the crew

"* Groups 1,2 and 5 DARK

should initiate feedwater isolation.

"* Group 3 LIT

Checks OAC in service

BOP Reports all Ss and St components in Group 4

NOT -LIT

RO

Reports that CA is running and at least 3 S/G's

NR level > 17%

BOP Reports KC pumps running

BOP Reports RN pumps running

10

Event:

SGTR "A" S/G

11

[Time j Poe.

Expected Abilons/ Behavior

Comments

SRO Directs Unit 2 Operator to throttle RN to

EXAMINER CUE:

"minimum & start 2A RN pump

2A RN pump is running

RO

Checks/reports all S/G pressures > 775 psig

BOP Reports Containment pressure has remained

less than 3 psig

BOP Report NV Pump to Cold Leg Flow gauge

indicating flow - YES

Crew will ensure ND pump mini-flow

"

checks NC pressure < 1600 psig

valves are open

"

checks NI pumps indicating flow - NO

SRO When available notifies OSM or other SRO to

EXAMINER CUE:

implement Generic Enclosure 22

OSM will ensure Generic Enclosure

22 implemented.

RO

e

Checks CA flow > 450 gpm and takes

control of CA to maintain no load levels

checks VI header pressure > 60 psig

I

Maintains N/R level between 11% and 50%

BOP Checks NC pumps ON and Tave stable or

If not stable and decreasing crew will go

trending to 557 degrees

to Enclosure 3

BOP Reports Pzr PORV & Spray Valves closed

BOP Reports subcooling > 0 deg.

BOP Reports all main steamlines INTACT

RO/ Report S/G tube rupture parameters indicate

Implements F-0 and E-3

BOP that S/G tubes NOT intact

Event: STGR on "A" S/G

Time

Pos.

Expected Actions/ Behavior

Comments

SRO Implement CSF Status Trees and go to EP/E-3

SRO Go to EP/E-3 and directs activities

SRO Monitor foldout page

RO/

Identify "A" as the ruptured S/G

BOP

RO

Check at least one S/G - AVAILABLE FOR NC

SYSTEM COOLDOWN

RO

Isolate steam flow from ruptured S/Gs as

follows:

a

checks ruptured S/G PORV closed

RO

Check S/G 1B and 1C INTACT

RO

Check blowdown isolation valves - CLOSED:

1BB- 1B

1BB- 5A

BOP Close steam drain and check "CLSD" light lit for

ruptured S/Gs:

1SM-83A (A SM Line Drain)

RO

Close the following on ruptured S/Gs:

MSIV on ruptured S/G will not close.

Critical

MSIV

RO will close other S/G

MSIV bypass valve

a

MSIVs

MSIV bypass valves

steam dumps

Close SM-14,SM-15,AS-12,TL-3

SPI and SP2

Dispatch an operator to isolate

steam line drains per enclosure 4

When cooldown is initiated in

subsequent steps then use intact

S/G PORVs for steam dump.

12

E-3 Evaluation

Event 6:

SGTR on "A" Steam Generator

Event: Pos.

Expected Actions/ Behavior

Comments

RO

Checks ruptured S/G NR levels greater than

11%

Isolates feed flow to "A" S/G

Close 1CA-66AC

Close 1CA-62A

BOP Checks Pzr PORV and isolation valves:

"* Power to all Pzr PORvs available

"* All Pzr PORVs CLOSED

"* At least one Pzr PORV isolation valve OPEN

RO

Checks main stream lines intact:

"* All S/G pressures stable or going up

"* All S/G pressurized

BOP Reset the following:

S/I

Sequencers

Phase A isolation

Phase B isolation

BOP Established VI to containment

"* 1VI-129B open

"* 1VI-160B open

I 1VI-150B open

Checks VI header pressure > 85 psig.

RO

Controls intact S/G levels:

"* N/R level in all intact S/Gs > 11%

"* Throttles feed flow to maintain intact S/Gs

N/R levels between 22% and 50%

BOP Checks 1 ETA and 1 ETB energized by offsite

power

SRO Checks ruptured S/G identified

SRO Checks the following closed on ruptured S/G:

NO, MSIV open

"

MSIV

"

MSIV bypass valve

SRO Checks ruptured S/G pressure greater than 280

psig.

13

Event:

STGR on "A" S/G

Time

Pos.

Expected Actions/ Behavior

Comments

SRO Checks any NC pump running

SRO When P-11 status light lit then block steamline

isolation and maintain NC pressure less than

1955 psig.

RO

Initiate a NC system cooldown as follows:

Critical

Determine required core exit temperature based

on lowest ruptured S/G pressure.

"* COND AVAILABLE FOR STEAM DUMP"

status light - LIT

"* MSIV on intact S/Gs OPEN

NO

"

If Pzr pressure is greater than 1955

psig, then depressurize to 1900 psi9

using Pzr PORV.

"* Depress "BLOCK" on low pressure

steamline isolation block switches.

"* Maintain NC pressure less than

1955 psig.

Ensure Main Steam Isolation reset.

Ensure S/G PORVs reset.

Dump steam using all intact S/Gs

PORVs at maximum rate as follows:

Close S/G PORV manual loader on

ruptured S/G

2. Place intact S/G PORV manual

loaders at 50%

3.

Select "MANUAL" on "SM PORV

MODE SELECT"

4.

Adjust manual loader on intact S/G

PORVs as required to control intact

S/G depressurization rate at

approximately 2 psig per second.

"

Check low pressure steamline isolation

BLOCKED

"

Check core exit T/Cs - less than required

temperature.

"

Stop NC system coodown

"

Maintain core exit T/Cs less than required

temperature.

SRO Checks ruptured S/G pressure - stable or going

up

SRO Checks NC subcooling based on core exit T/Cs

> than 20 degrees

14

Event: STGR on "A" S/G

Time

Pos.

Expected Actions/ Behavior

Comments

BOP Depressurizes the NC system

1. Checks ruptured S/G NR level less than

73%

2. Checks normal Pzr spray available

If crew uses PORV go to step 21.

3.

Initiates NC depressurization using

maximum spray

4.

Do not continue in procedure until one of the

following satisfied:

"

NC subcooling less than 0 degrees

"

Pzr level greater than 76%

Or

Both of the following

NC pressure less than ruptured S/G pressure

Pzr level greater than 11%

Go to step 23

Crew Checks for S/I termination criteria

1. NC subcooling greater than 0 degrees

Must meet all criteria to terminate.

2. Secondary heat sink

3.

NC pressure- stable or going up

4.

Pzr level greater than 11%

BOP Stop S/I pumps as follows:

a

NI pumps

1

All but one NV pump

BOP Isolate NV S/I flowpath

"* Check NV pump - SUCTION ALIGNED TO

FWST

"* Check the following valves OPEN:

1NV-150B

1NV-1 51A

"* Close the following valves:

1 NI-9A

1NI-10A

STOP SCENARIO HERE

TERMINATE SCENARIO AT DIRECTION OF CHIEF EXAMINER

EXAMINER NOTE: Be sure SRO classifies event at end of scenario.

Classification of event: Site Area Emergency

15

SHIFT TURNOVER INFORMATION

UNIT 1 STATUS:

(PRIVATE

}Power Level:

55%

NCS [B] 866 ppm

Pzr [B]: 865 ppm

Xe: Per OAC

(PRIVATE

}Power History:

Reduced power to 20% to add Oil to Core Burnup: 200 EFPDs

"D" reactor coolant pump.

CONTROLLING PROCEDURE:

OP/1/A/6100/03 Controlling Procedure for Unit Operation enclosure 4.1

step 3.21.

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

"lA" Diesel Generator tagged for maintenance.

"lA" Auxiliary Feedwater pump tagged - PM

Unit 2 is available for auxiliary steam.

Continue load increase at 2 MW/Min.

Conditioned power level 100%.

Work Control SRO/Offsite Communicator

Unit 2 SRO

Thad

Jim

NLO's AVAILABLE

Unit 1

Unit 2

Aux Bldg.

Robb

Turb Bldg. Fred

Aux Bldg. Joe

Turb/Service Bldg. Mike

Extra(s) Bill, Craig, Russ, Ron

16

Appendix D

Scenario Outline

Form ES-D-1

Facility: McGuire

scenario NO.: pare

Jp-LeL

+/-NtJ

Scenario No.:

Opare

operators:

Objectives: 1) Diagnose failures that are not readily understood such as

letdown back pressure instrument and charging line leak. 2)Deal with a small

steam generator tube leak after a large steam line break. This exercise will

give the candidates opportunity to exercise a variety of AOPs and EOPs.

Initial Conditions: 70% Power! Increasing Load! "B" Train Component in

service

Turnover:

"A"

D/G inoperable/ "A" CA pump tagged/Unit 2 is available for

auxiliary steam/ Begin load increase to 100%.

Event

Malf.

Event

Event

No.

No.

Type*

Description

iN

Load Increase

1R

Rod Withdrawal/Dilution

2

SOP

Letdown Back pressure Instrument Failure

3

RO

Steam Generator Narrow Level Instrument fails low

4

BOP

Charging Line Leak

5

RO

power Mismatch Circuit Failure

6

M(ALL)

Steam Leak becomes Steamline Break Inside

Containment with a SGTR

Post Major Event Malfunctions

No automatic spray actuation

No Auto Main Steam Isolation -

done manually

Tube Leak on Faulted Steam Generator

No automatic safety injection

(N)ormal, R)eactivity,

(I)nstrument,

(C)omponent,

(M)ajor

NUREG 1021, Revision 8

Op-test No.:

PROGRAM: McGuire Operations Training

MODULE:

Initial License Operator Training Class 20

TOPIC:

Nuclear Regulatory Commission Simulator Exam

Spare Scenario

REFERENCES:

1.

2.

3.

4.

5.

5.

6.

7.

8.

9.

McGuire Technical Specifications

AP/1/A/5500/06

AP/1/A/5500/12

AP/1/A/5500/14

AP/1/A/5500/10

EPIl/AI5000IE-O

EP/I/A/5000/E-2

EPI1IlA5000IE-3

EP/I/N5000/FR-Z.1

RPIOIA/57001000

Loss of S/G Feedwater

Loss of Letdown, Charging or Seal Injection

Rod Control Malfunction

NC System Leakage Within Capacity of Both Charging

Pumps

Reactor Trip or Safety Injection

Faulted Steam Generator Isolation

Steam Generator Tube Rupture

Response to High Containment Pressure

Classification of Emergency

Author:

Facility Review:

NRC Review"

December 0, 2001

Rev. 1

1

SIMULATOR OPERATOR INSTRUCTIONS

[] Sim. Setup

Rod Stop On

.

IC-144

[]

RUN

o3

Update Status Board,

See Shift Turnover Information

Setup OAC

Setup ICCM, Turbine

Displays, & Trend

Recorders.

Check Rod Step

Counters agree with rod

positions

o

(M)

EPQ001A

Loss of D/G "IA" Control Power

Set = Rack Out

o

(LOA) CA009

Rackout breaker for "IA" Auxiliary Feedwater Pump

Set = Racked Out

o

(MAL) ISE006A

Blocks auto main steam isolation

(MAL) ISE006B

Block auto

O

(MAL) ISE004B

Failure of Phase "B" train "B" to actuate

Block auto

O]

(M) ISE002A

Failure of automatic Safety Injection - both trains

(M) ISE002B

2

V~ E~

T

OESOWIPTION, ~~A<

<

-Freeze.

o]

Update Fresh Tech.

Spec. Log.

o

Fill out the NLO'e

Available section of

Shift Turnover Info.

o

Prior to Crew

RUN

Briefing

o]

Crew Briefing

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.

o

T-0

Begin Familiarization

Period

o

At direction of

(XMT) NV030

Fails NV letdown back pressure regulator - causes a loss

examiner

of letdown

Set = 0

o

At direction of

(XMT) CF020

Steam Generator "B" Narrow Range Instrument Fails

examiner

Set= 0

Ramp = 5

Q

At direction of

(MAL) NV0O8C

Initiates leak on charging line

examiner

Ramp = 10

Set = 25

3

Bench Mark

ACTIVITY

DESCRIPTION

-l At direction of

(MAL) IRE001

Power Mismatch Circuit Failure

examiner

Set = 557

Q

At direction of

examiner

(MAL) SM007A

Set = 3e4

Ramp 200

(MAL) SM007A

Set = 4e6

Set to trigger 1

(MAL) SM001A

Set = 200

Set to trigger I

Initiates a Steam Leak

Initiates Steam Break

Initiates a SGTR

Terminate the scenario upon direction of Chief Examiner

4

0]

At direction

examiner

of

-5-

Normal Operations - Turbine Load Decrease

SRO Notifies SOC of load increase

RO

SRO Increases load per OPIIIN63001001A and

RO

OPI1IAG6100103

Determines load changing rate

RO

Depress the "LOAD RATE" pushbutton

RO

Set the selected rate of load change in the

"Variable Display" window

RO

Depress the "ENTER" pushbutton

RO

Depress the "REFERENCE" pushbutton

RO

Set in the desired load

RO

Depress the "ENTER" pushbutton

RO

Depress the "GO" pushbutton

RO

erify that the load starts to change at the

selected rate

Event: Normal Operations

Rod Insertion

SRO Provide guidance to RO on expectations for rod SRO should provide some general

wthdrawal on load increase.

guidance as to using rods to maintain

maintains control rods within insertion limits Iave within a pre-determined range of

AFD within target band

Tref.

RO

Will withdraw rods as necessary based on

nstructions from SRO

BOP

Will dilute NC system per guidance provided

I

I

5

I

I

EVENT:

Event:

Letdown Back Pressure Instrument Failure

SRO EZnters AP/12 Loss of Letdown, Charging or Seal

Injection

BOP On a loss of letdown ensure the following

Immediate action step

closed:

• 1NV-458A

• 1 NV-457A

• 1

NV-35A

BOP If at any time "REGEN HX LETDN HI TEMP'

BOP will take action if appropriate

larms, close:

• 1NV-1A

• 1NV-2A

RO

Stop and power or temperature changes in

progress

RO

Announces occurrence on page

BOP Checks "1B" NV pump- ON

BOP Checks to following NV pump parameters

stable:

• Motor AMPs

• Charging header pressure

• Charging flow

BOP Checks seal injection flow parameters:

- Seal flow to each NC pump > 6 gpm

a Seal Water Inj Filter Hi D/P alarm - DARK

SRO IF this AP entered due to loss of letdown only,

SRO will go to step 35 in this AOP

then go to step 35.

BOP Ensures "NC Sys M/U Controller" in AUTO

SOP Ensures charging flow going down to maintain

Pzr at program level

SRO NOTE: A failure of the letdown pressure

instrument may cause loss of letdown.

BOP Checks "Letdn Relief Hi Temp" alarm has

No, crew should evaluate note prior

remained dark

to step 37.

BOP Checks 1NV-21A -closed

6

Event:

Letdown Backpressure Instrument Failure

N'

4A~lI.

XŽ> i

r- 7-

BOP

BOP

SRO

BOP

SRO

S........

..

r,

5.

1NV-1A

1NV-2A

Open letdown line isolation valves:

1NV-7B

• 1NV-1A

• INV-2A

• 1NV-35A

1. Establish desired letdown rate by completing

the following concurrently:

" Slowly throttle open 1 NV-459

" Adjust 1 NV-124 to maintain letdown pressure

between 250 and 350 psig.

2. Do not continue until desired flow rate is

established.

3. Adjust charging flow as desired

4. Crew may stay on variable orifice or swap to

75 gpm orifice.

End of Procedure

Checks Pzr heater group supply breakers

closed

YES

Checks the following OPEN

" INV-2A

" 1NV-2A

Checks to see if immediate restoration of normal

letdown is possible

" Both NV 1 & 2 open in the past 30 minutes

" Orifice isolation valves closed before or at the

same time as NV I & 2.

Establish normal letdown

1. Ensures 1 NV-459 is closed

2. Place 1 NV-124 in manual between 10-20%

open

3. Establish cooling to Regenerative Hx by

performing the following concurrently:

"L Throttle open 1NV-238

"* Throttle INV-241 to establish approximately 8

gpm seal injection

Check the following OPEN

7

NO, go to step 42

Yes, go to step 46.

Crew should determine normal letdown

control is not available and establish

excess letdown.

1. Opens the following

• 1KC-315

• 1 KC-305

2. Places 1 NV-27B to VCT position

3. Opens and closes 1 NV-26

4. Checks to following OPEN

• INV-94

• 1NV-95

5. Opens INV-24 and 1NV-25

& Slowly opens INV-26

7. Notifies chemistry that excess

letdown is in service.

Event 2:

Steam Generator "B' Narrow Range Level Failure

ifl

7*

,,

BOP Refer to annunciator responses

Per annunciator response and AP/06

the operator will swap failed channel to

"

A-3

operable channel

"* B-3

RO

Places Feed Regulator to Manual

Immediate Action step

Restores S/G level to program level

RO

Checks the following channel indicating the

Immediate Action step

same:

"* Feed flow

"* Steam Flow

"* S/G Level

RO

Checks S/G CF control valve in manual control

YES

RO

When the following are met then return affected

SIG CF control to automatic

1. Selected control channels indicated correctly

"

Feed flow

"

Steam flow

"

S/G level

2

Affected S/G level restored to program level

3.

Automatic control is desired

SRO Checks the reactor tripped

NO

RO

Maintains S/G level

Go to step 7

RO

Controls feed flow to maintain S/G NR level - at

programmed level

SRO Checks NC temperature with NC pumps on

stable or trending to programmed temperature

SRO Checks procedure enter due to failed controller

SRO Contacts I&E to repair failed controller

Failure will not be repaired

Exit procedure

8

Event 3:

NC System Leakage- Charging Line Leak AP-10 Evaluation

Pdt4*1f~k4m777ht8a77 i..7

ý

'tl

7,

Q

ZP

I

1,

-

3 .

BOP Report either of the following:

"*

Pzr level decreasing

"*

Pzr press decreasing

"* Containment Vent Isol (EMF39)

"Ice Cond Doors Open" Annunciator

SRO Go to AP/10 (Case II) NC System Leakage

and directs activities

BOP

Report Pzr Level decreasing:

"* Report NV-238 opening

"* Open NV-241 while

maintaining 6 gpm

Seal Injection Flow

"

Starts alternate NV Pump

"

Reduce letdown to 45 gpm or isolate

letdown

• If Pzr level less than 11% then:

Manually Trip Reactor

Manually SI

RO lnnounce Occurrence on page

SRO If Pzr level can not be maintained go to step 1

SRO If location of leak is known, than initiate actions Crew may go to step 18

to isolate leak.

BOP Reports Pzr Pressure at or increasing to

2235 psig

RO

Reports Main Steam line is INTACT

" Reactor power at turbine power

" NC loop T-Ave is stable

SRO IRefer to RPI000

SRO Ensures OPIOIA/6450111 done if NC leakage

exceeds Tech Spec leakage

SRO Ensures VCT aligned to FWST if VCT level goes

below 16%

9

qt

BOP Checks the following EMFs normal:

"*1EMF-38L

" 1EMF-39L

" 1EMF-40

a 1EMF-41

"1 EMF-46A

" 1EMF-46B

BOP Checks NC pump thermal barrier KC outlet flow GO to step 17

_computer alarms NORMAL

SRO If leak is suspected on letdown line near

It should not be suspected there.

dlemineralizers

SRO If leak on letdown line, then isolate leak as

Leak is not on letdown line.

follows:

If leak is on normal charging line then isolate as

follows:

1. close letdown isolation valves

• 1NV-458A

• 1 NV-457A

• 1NV-35A

• 1NV-1A

• 1NV-2A

Isolate charging:

• Close 1 NV-244A

• Close 1 NV-245B

• Manually throttle 1 NV-238 to maintain 6-10

Crew should have already established

gpm seal injection flow per NC pump.

excess letdown

SRO Checks the following NORMAL:

• Pzr Safeties

e Pzr PORvs

• PRT Conditions

SRO Checks CLAs level NORMAL

SRO Checks the NCDT NORMAL

SRO Checks the containment floor and equipment

sumps NORMAL

10

11

Event 4: Power Mismatch Circuit Failure

RO

Recognizes Unwarranted Control Rod Insertion

and informs Crew.

"

No turbine or reactor power excursion

"

Tref normal

RO

If more than one rod dropped - trip Rx

RO

Places CRD Bank Selector Switch to manual

RO places Rods in Manual

and verifies movement stopped

SRO

Enters AP/14, Rod Control Malfunctions and

directs activities.

RO

Perform the following to maintain T-colds 555

to 557 degrees.

Lower turbine load or raise T-cold

Or

Borate the NC system to lower T-cold

RO

,nnounce occurrence on paging system

RO

Check all control banks aligned with associated

bank

RO

Checks Rod Control Urgent Failure alarm

DARK

RO

Checks to following reactor control instruments

NORMAL

"i Turb Imp Press Ch 1

"* T-ref indication

"* "IA" NC loopT-ave

"* "lB" NC loop T-ave

"* "lC" No loopT-ave

"

'110" NC loop T-ave

RO

Check Nuclear power P/R Channels

NORMAL

SRO rill go to enclosure 4 based on unwarranted

rod movement.

CREW Evaluates the following prior to any control rod

withdrawal:

"

Ensures no inadvertent mode change will

occur.

"* Ensures rods are withdrawn in a deliberate

manner.

12

Event 4: Power Mismatch Failure

13

CO.hecks the following normal:

"Turb Imp Press Ch 1

" T-ref indication

BOP

Checks the following channels - NORMAL

SRO Checks if failed channel - HAS BEEN

IDENTIFIED.

RO

When the problem is repaired then

Ensure T-ave at T-ref +/- 1 degree and auto

rod control is desired, then return rod control to

auto.

ýR-O

Exits procedure

I

I

...-

I

E-O Evaluation

Event:

Steam Line Break Inside Containment with SGTR

SRO

SRO

<F

A IO

4

ý

I

Go t EP/-U

ad aiectsactiitie

Ro to EPiE-O and parects acthvices

Reviews Foldout page with crew

-RO

lReport Reactor Trip:

RO

rod bottom lights

reactor trip breakers open

I/R amps decreasing

Reports Turbine Generator tripped

"lTV's or GV's closed

BOP IReports ETA and ETB energized

RO

Reports SI status light - LIT

BOP Report LOCA sequencers (A & B) actuated

SROP

RO

SOP

Announce "Unit 1 Safety Injection' on page

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

NOT -LIT

R*eports that CA is running and at least 3 S/G's

NR level > 17%

Reports KC pumps running

BOP lReports RN pumps running

Crew should take actions to correct

Phase "B" alignment.

14

RO

-I

BOrP

Event:

Steam Line Break Inside Containment

15

SRO Directs Unit 2 Operator to throttle RN to

EXAMINER CUE:

minimum & start 2A RN pump

2A RN pump Is running

RO

Checks/reports all S/G pressures > 775 psig

BOP Reports Containment pressure has remained

NO

less than 3 psig

BOP Report NV Pump to Cold Leg Flow gauge

indicating flow - YES

"

checks NC pressure < 1600 psig

"checks NI pumps indicating flow - NO

SRO When available notifies OSM or other SRO to

implement Generic Enclosure 22

RO

@ Checks CA flow > 450 gpm and takes

control of CA to maintain no load levels

"

checks VI header pressure > 60 psig

"

Maintains N/R level between 11% and 50%

BOP Checks NC pumps ON and Tave stable or

If not stable and decreasing crew will go

trending to 557 degrees

to Enclosure 3

BOP Reports Pzr PORV & Spray Valves closed

BOP Reports subcooling > 0 deg.

BOP Reports all main steamlines INTACT

NO, crew will go to F-2 and implement

F-0 - Crew should go to Z-1

Steamllne Break Inside Containment with SGTR

_i-I

16

_____________

I

Z -1 Evaluation

Event:

CREW If loss of emergency coolant recirc has occurred,

THEN this procedure may be completed as time

allows.

CREW Monitors foldout page

BOP Stop all NC pumps

BOP Ensure all RV pumps are in manual and off.

SRO Dispatch an operator to remove tags and close

breakers for the following valves:

" 1NI-173A

" INI-178B

BOP Checks containment pressure - LESS THAN 15

PSIG.

BOP Check any NS pump - ON

SRO The remainder of this EP may be performed as

time allows.

Event: Steam Line Break Inside Containment E-2

Crew

Alonitors foldout page

Crew

Vlaintamns one SAG available for NC system

cooldown

SRO

hecks the following closed,

o All MSIVs

• All MSIV Bypasses

SRO Check at least one SIG pressure - stable or

going up

RO

Identifies faulted SIG;

" Any SIG pressure - going down in an

uncontrolled manner

" Any SIG depressurized

RO

Checks faulted S/G PORV closed

RO

Isolates faulted S/G as follows for "A" S/G:

" Check S/G A FDW Isolated status light LIT

" Close 1CA-66A

Close 1CA-62A

Check closed 1B8-1A & 1BB-5A

Close 1SM-83

SRO Checks if SIG tubes INTACT

NO, 1EMF-24 will indicated a tube leak

Checks EMFs normal

"* IEMF-24

"* 1EMF-25

"* 1EMF-26

"* 1EMF-27

SRO Go to EP-E-3 Steam Generator Tube Rutpure

17

Even: STR on

1"A"

SIG

E-= vluto

SRO

Implement CSF Status Trees and go to Erit--

I SRO Go to EP/E-3 and directs activities

SRO INonitor foldout page

RO/

BOP

RO

Identify "A" as the ruptured S/G

Check at least one S/G - AVAILABLE FOR NC

SYSTEM COOLDOWN

RO

Isolate steam flow from ruptured S/Gs as

Follows:

checks ruptured S/G PORV closed

RO

ICheck SIG 1B and 1C INTACT

RO

BOP

RO

RO

Check blowYdown isolation valves - CLOSED:

"* 1BB-1

"* 1BB- 5

Close steam drain and check "CLSDL" light lin for

ruptured S/Gs:

1SM-83 (ASM Line Drain)

Close the following on ruptured S/Gs:

"* MSIV

"* MSIV bypass valve

Checks ruptured S/G NR levels greater than

11% (32% ACC)

Isolates feed flow to "D' S/G

"* Closed 1CA-66A

"* Closed 1CA-62A

I

I

-I-

Event: SGTR on"D" Steam Generator

18

I

I

I

E-3 Evaluation

Event: STGR on "A" S/G

BOP

hecks Pzr PORV and isolation valves:

Power to all Pzr PORvs available

All Pzr PORVs CLOSED

At least one Pzr PORV isolation calve OPEN

RO

Checks main stream lines intact

NO, "A" depressurizing or depressurized

"All S/G pressures stable or going up

"All S/G pressurized

BOP Reset the following:

"

S/I

"* Sequencers

"* Phase A isolation

"* Phase B isolation

BOP Established VI to containment

" 1VI-129B open

" 1VI-160B open

"

1VI-150B open

"

Checks VI header pressure > 85 psig.

RO

Controls intact S/G levels:

"* N/R level in all intact S/Gs > 11% (32%

ACC)

"

Throttles feed flow to maintain intact SIGs

NIR levels between 22% and 50%

BOP Checks 1 ETA and 1 ETB energized by offsite

power

SRO Checks ruptured S/G identified

SRO Checks the following closed on ruptured S/G:

a

MSIV

MSIV bypass valve

SRO Checks ruptured S/G pressure greater than 280 NO, crew should go to ECA 3.1

psig.

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

Classification of Event: Site Area Emergency

19

SHIFT TURNOVER INFORMATION

UNIT I STATUS:

Power Level:

100%

NCS [B] 66 ppm

Pzr [B]: 66 ppm

Xe: 2895pcm

Power History:

At this power for 400 days

Core Bumup: 440 EFPDs

CONTROLLING PROCEDURE:

OPI1IN6100103 Controlling Procedure for Unit Operation

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

"IA' Diesel Generator tagged for maintenance.

"IA" Auxiliary Feedwater Pump Tagged for PM

Unit 2 is available for auxiliary steam

Begin load reduction to take the plant to mode 6 to begin refueling outage.

Reactor group has determined it will take 300 gallons of boric acid for the shutdown.

Insert 50 gallons of acid to begin shutdown and use rods for AFD control.

Begin load reduction at 2 MW/min.

Work Control SROiOffsite Communicator

Unit 2 SRO

Thad

Jim

NLO's AVAILABLE

Unit I

Unit 2

Aux Bldg.

Eric

Turb Bldg. Fred

Extra(s) Mark, Bruce

20

Aux Bldg Bill

TurblService Bldg Buster