Text

Forwards Comments on Written Exams Administered on 880323, Providing Assistance to NRC Examiners in Establishing Appropriateness of Exam Questions
	ML20154B463
Person / Time
Site:	Browns Ferry
Issue date:	03/30/1988
From:	Pomrehn H; TENNESSEE VALLEY AUTHORITY
To:	Brockman K; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18033A344	List: ML18033A343; ML18033A345; ML20154B463;
References
	NUDOCS 8809140021
	Download: ML20154B463 (52)
	v • d • e

- --

~'

ENCLOSURE 3 o

Tl.NNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000

.;jVEO

- - '""' ^****** " '

OM 3!Oi2!

it!i : 3 5 Mr. Ken Brockman, Chief Operator Licensing Section

,, g,i g U.S. Nuclear Regulatory Comission, Region II

" ' ~ ' " 'g ' g *

,,i 101 Marietta Street, NW Atlanta, Georgia 30323

Dear Mr. Brockman:

In accordance with the provisions of NUREG-1021. "Operator Licensinr, Examiner Standards," Standard ES-201, enclosed are coments by the Browns Fo;ry Operator Training Group staff concerning the written examinations administered at Browns Ferry Nuclear Plant, March 23, 1988.

The enclosed coments are vf fered with the intent of providing assistance to the NRC examiners in establishing the appropriateness of the examination questions. Also, the coments serve to clarify and expand the answers on the NRC answer ke'/ as supported by TVA reference material.

With respect to any questions deleted, NRC is requested to consider allowing the examinee full credit for these questions in light of the time, effort and concentration required of the examinee.

These coments are respectfully submitted, and it is hoped the enclosed coments and proposed resolutions af ford the examinees every opportunity to successfully pass the examination based upon the knowledges and skills required to safely operate the facility.

Vary ttvly yours, TFNN SEE VALLE HORITY

/

D H. P.

mrehn SiteDjrector,BFN Enclosure 0009140021 000023 PDR ADOCK 05000259 O

PDR An Egal Opportumty Employer

t

-. _. = _.

(

4 4

4 9

8 0

4 4

4 8

8 0

8 9

9 9

8 8

),

1 Cqm s TiB t Au a e ri ROhMVWTMI.DtJi: W..t3 f

f 1

l

=@MMNOdCN N N C P9 = N es e O

@ N ew' 4 M 1

e m 51 N r= q = = ei O O. cc c d = =..N. N = C OoMQ=cdOO.CO 9

I e e e e e e e e e e e e o e e e

> e o e e e ee ie J

N l eno N O C O - C O O M O N -cO 9 m a.* @ e =P*<reiO O C'O j O - ew M N. m O. l 0. 0 e

( e P

at

n Ck i O

N

)

m

=

ei a:

O mC O

4 Q. 0. 2 4

3(

Wd

.J i

e-su u J o. La, O e W O >

i ce s 20 w

Oi z a a M a w, < as < rt d' er 1

.J$l e,

s. a LL

ct u O := 4 O V O

E 5 4 E s i =.e. h D.

l Z W t4 L.J W

.O HHUHH w

E ta i

to O 'J u u t. ' U O L U v t. 0. Q 4 3 Q 4

-=

1 M!

l.

1 I

)

4 D

"r h

44 M f 3

i I

I 57 h$

h a

o m.:n.:n.I.:

aso sse nsssas f

9 i

.m e

i e e i e e e e e e e a

O.O. Q,N N. N N.

N o.

a-I'

N.iNNC

.J. e, 1

a-

\\

O i

't A

1 t

N s

N Se-o6

= v.m. N N 21 % O g

i i

N h

H 3, s' P. o.d t O Q N N. N N.

S

- S e P* P. P= o c 4

l MO m e = c h. g > N N

1, w e.

er e n e e e e

< a.

l m

C ed Q.eO. =O4=

r cl < a t E E P* N N f"' E 2 g m s

e e e o e g

a ei r1 l

3 l

4 l

l l

l

\\

e a

ty 4

fg e

ej mi

-cJi e c 1$ 2 5 m.o. c 0 0 Q

2

-v a

=

a N29 9

O C

9 Q

l 4 60 t

I lJ 1

=

i

==N99

A M V

W CQ S 01 4 9 N. N i ci es IN N

I

%T-mo.

. o.

t.i 9 O J

,w ri 23 }v <

,y r h a h h s m ~i,s i

,s e

e l

e e e

.x ONC-O-

O-

a l m N N ei ei e i v r.

.o e

ci e

Q

=0

, =.

Ne

'Y 9

W I

i2 i

.o.

t M

<he l ' %

mS e,

=

,o o tt 3 % C 4lss ae

' O O *t "n "o e 85 mOC l

h9.TT T

a v e,

e S y 4 4 ANe w 1x t

, % %. oo oo o

e. N N v >

T c el e.

aO91 0 ') Q O O CiOOQO m

srS as: e i e e e e e i e e e

r w e e e

&,A

=-Q p = 9 0 ei e) e e e e o e ae w.

g O v C = O 3 = 0 e.t l

a., W a'O T

> 3 eJ ad o

.a O Cl O O *10 O d S O *) O P3 o e f1 a

a N

e e e l

w

.J 9 9 9 e.3 *

t vv4e 7i.'

-O-3 ed Q e i e o e e e

> e e o eO Q O l

a"L.M. PP M..M. el.M. e'.l el m M. '9.P1 l

4' ' ti i

N

.I.

s'4 1

oNp

@ 94 ay v%yo N m N e.e a em. s m

g I

E l 8

dlNI= mom 40043

% 1 o

'O e o ee eoe e o I e e r e Q.,32.

33C S. N. N' h. *S 3 34 - = O "

l O.

= =.g 3 090=O/

-c4.=

L P. l o o

.i 3

n m e e o e

.. e e Qa>a>>a>>>>>a>-

=

9 I

r$A

.i =

N>

.o.

a

. :e w iw

=o

%e ue e

e e P

q Ali A o.<$.c..o..<,l.o.O. 4 o *= 7. 9

,O 1.

P 9 6 "t

4 e.9 e l s <o -s 8 4a f N. p.* a. N.

.e ei i e e, e e i sie i q ~ e. e ow e

~

. m

.=

e

6 e e h e

<C E. U. Q S. U.

. U231.g 9 4 2 2 9'N- $N232 9

89 % QP

,o0-4 3

1 = O = -O9 N t" e

t dv5..-

e1 N N iai

1 m W to'J

)6 i i e i eeiet a eHbw m 9 ~} 9

e e o e

=

= 9.% *= <.t y

}

i

= =.e O 61i ft o 4-9 o as o O o D v,.4 "t %

= *,

NPI m N.* *e = 1 9

W.4! -

OO "'OON*

l l

il 3 j f

,g

~.e.a

{

Qo,

,N

,~~4o t

o. r., 03

- i O,

u to s 9 avrIw qwvwf ie.4N. c o c o e P'4 0.x

~ e = m o.< e.i m.g so.. a.

n.

-en1

,. f~

gNe i

1 a-a o. o n

.e ne,r e tl

't e e it W

< s. u at.

31 L.

i e e i-e e

O O Cl o.u e

7 ei e e e W{'

OmQ-01

OM

m e o 1E O C COC OOCl

.J N O.e >

a' r4

.d 5.=r o m m 'n % P*

1. ' L d'

1E.

eo e

S as r O cl

.o..ll.

aJ M 41$

eq Q -== 3 I

r1 N m e19 v Ji M

-O 4

Tn g4

.J

.= 0 t ' O O "'I O O f'. O O d O J* '$ "!"

ceS oa4")wHw W l l

r l

1

'i

.J o <

44(

-T M

4 M

2 3 c4 f' I N. N. rilNN e j u =e.ie. N N..I.

~ o. ofe ~.

N N..c,, o. n. e. n. m B

u t N. a4 N N. m

=

i e s ~ w ; eq

. o v s N

N 3.

ee fe -

)e o e C 3, r

==-

a.--.e=

4 P,

=

e o e eooe e I e e t O. 4 O. <. SJ O. O t, i

i 6

M I 'M t.a i

OO O OmQ=Or

-O/

O

' Q o o' *. ]LJ L 4 o

om-

-49 25 99 am S 1' @ e u' Q.

I e'

N et, P'

j

%tMdi mmf o c el s 4 % '*3 17 N 'i ww1 W u '% A J

'J, N ad N *' C 9 T r'i i S A *, A o ti o p A p i t 4

I t

.d>

Pi n P4 9 ( NOW

.J u. e.

e e

*

e e*

'3 A,

. i e,

=

oe

.,-o i

==1

=

s M

i I

3.,..

a

- ~. n. m 3. 7 ~e

-e.

i x. s

o..,n ~..n. na, nN, e y

N.e.

m

.,m,- 7. Lel,,4 e O v

o-o

.e ym e

O. n.. m. o. :.,

O.m Js ONC-O--O-2 e=

e e e

e 3

2.

6 w:

ed.

==,

i.c 2 4

i i,.

e

, mu m

O rs o eg % m % A 8.J a ei e'

%f amm 49-

.mel N m e, N m e

m ma a i t

8 i N,- M = w L1' '2' i

N, m n., 4 On

-ma ax 4<

> r n,I.> 3 4,=

N,o,N3m

- xxa

,2 i

s Q

,~ :

N m

4 4

N

=

l J=

J<

d

< - a

.n. d y n, i.3 a

> > c,4 m e ins 212 x -..i=-

6 a

w s bi.

p-u Ne w

w

.a e, eegme1 ~ ~. ~ w tr u w

-a~x q.J 4 w :

n.

Jcxx<

,3 s

1 w

1 i

sego 4,0,,eOOnw4w 1

4 ; s_.[ [ ' ;et h m tJtH H M tWr:1tMYiiT O HJTR N U M D1T10 4 : N'P f

C

\\

C 4

8 f

C 0

0 0

0 S

9 3

3

)

i 3

i

....e.

..n.,.,e

.4

i J ft 3-82-#2 TI sE s444 bdua0 FtidWf - I SEO. NO.

7 e** PERIODIC 455 coke PEdFOROA%CE LCGe**

m..

e i

r r 92{unf sel:1 J g Ita*M ati CAI IddAIED LPAJL aF ADINTI y-i

)

n.'

\\

e

.. 44

+;

34 43 45 43

-],' A {

V 0 30 do

++ Ju ++

++ 39 ++

++ 30 ++

C

[

9**,

B 2d 43 43 48

=h.S i 55 A

++ 20 ++

39 ++

++ 48 ++

++ 34 ++

I,.

~

s

. 4,

58 32 ++

++ 43 *

++ 49 ++

++ 50 ++

++ 45 46

++ 48 ++

',8 p.

37 si n4 to sn

' f, 9

33 50 70 67 00 52

8

(* e '

1 4r

.. 21 ++

.2.*

7e 4

.. 7: 46 46

.6..

.a..

7,.

p!

43

++

++ 48 ++

e 4o ++

++ 48 4o

49 *

++ 47 ++

++ 45 ++

++ 37 ++

9I 52 -

54 S3 55 s7 st 42 a

esl tJ, 20 5o 5#

57 58 39

'=

t Fe '

3,

.+

.+ 3 +.

.* o24:,

++ 55 ++

++ 59 ++

++ 66 ++

++ 33 ++

9 35

++ 4o o

++ 58 ++

++ SO ++

++ $3 ++

++ 47 ++

++ 58 ++

++ 38 *

'O' sn Ai su an EA As AA I

- l 58

$3 00 60 42 65 43 f*' 8 i JI

++

++ 05 ++

$$ ++

++ of ++-

++ 49 ++

++ $7 ++

++ 68 ++

++ 44 ++

t l

s N

s,.I 2..

.o..

4,

,4 4,

5_,..

4,..

3...

.)

AA

{ @C)j de do el 53 59 61 44 f

23

++

++ 67 ++

++ 66 ++

++ 58 ++

++ 60 ++

++ 55 ++

69 ++

++ 40 ++

(*.9 y

n j.,'

W/;

19

++

++ 3d ++

45 **

++ 53 ++

48 ++

++ 44

45 ++

++ 31 ++

G l

++

']

[

_ 47 s)

A>

^)

sv u

u 47 So 05 05 59 58 27 i

W *[,;

45

"4; ++

++ oo ++

+ 72 ++

++ 07 ++

++ oo ++

++ 60 ++

++ 2I 6,-

,9 g ---

,j j

W k.

O l

18 U

++

++ 40 ++

++ 46 ++

47 ++

++ 45 *

++- 31 ++

s c

m o

u o

x x.l i"

3 20

.sd 60 57 32 N

I wJ.;.;

.l v7 A

++ 4a ++

++ 64 ++

++ og.+

++ 59 ++

++ 27

l l*!

I 03

++

w::

el

q j.

a) in u

na n

>s u

u u

o u

sn u

sa i

m W f W

OPLAATOd SUJJ VAL Cd LUG

__. L.1-Sid add _1E_t1ESLf. JA.L_1113_id11_ 2215_.2015_2.IV., ld23 I

b l d. __

i s

w e

l i

(

i B. F. L i

1 t

r i

\\

Mt i

x

\\

8

\\

f'~~y

=-

L

\\

ur

\\

n__g u_

uu=

utw_s ua ig

\\

\\.

i

{

T.V.A.

4 l

BROWKG FERRY TRA(N(NG i

AND V(8(TOR CENTER i

I i

i l

r l

l

)l l1\\i re e

57320592 4

00 H. 2 2 's 3 2 217630350.)'.0. O. 0 0

2207823%0 65.I.1 4 3. tr.7 1 9 1 13 55I 7420OoO 700Ol 00O3O21 1 4114 8

3%7 7

4 4

01 21 21 30 - 00 9

9 0

1 11 2

8 R

O A

D RC G

N P PPR a

4C 3

TA L

l r FCLPFO4FD Y

UN NLRCtF m T t. F R*

F0VPD, CCLsm SI TFfFOY

CuWWs E A A A A R "R 2 P P N t FnTTT(

TIO F r i

O a

E CPGJCCCCCCCCCPDORDmnnMWPi*

! iI S

5 5

4 435 3 -

4 -

4224 l >2d4 Q

8

> 1 - 1 3 0 4 1 6 4 *>

IG I 000063084 0000

.1 04080V1 098 L 0 0 0 0 0. f. 8 80 0,0 0 W

9 3

3 222200002222 I

26 L1 1 11 1 1 3 1 8 3 1 3 8

0 5

1 R

949

) -

1 -

U r5 41 ?231 01 1 241636411p 2

8

>74 9147 TL444400002.y22 0

9 H. 2 5

I Av I

2 2

Wit 77HnfeH U2UIC51 0 *, I l A h H H H 7 7' t

8 e

3 E

8 5 '> '> ') 4. teHl g 8 I ooo G

01 5

5 i e t

s 1

6 u V t

l t

i 794 4 -

0-c 4 O

L 1

CH4 4422O02o02 9

142448533V U

l e53j33 T G I 448 E

71 - 1 3 6 4 /. 0 4 *>

8 8 1 I

L-C 3>

1 2 J 3 2 2 3')3's ' '

nt p J1 5 '> 5 '3 >

01 O201 06 1 8

H N

V8 s

2 2

C I.

2I s4 4 A

I 4

1 U F

d E

h D

o S

Afl :22 s/6 - > 94 i

- s J04,JW>4 9, $d l

r 3a2 2

I l

A J

R

)'

=.

f 4

. I I' !1 h.

, s >

1 2 1

t

(

4 o1 l 9 423 4d 1

st

.,,r.

8 A....

s W E v. 4. o. 2 f m. 21 MJvJ0UU00J9U0 J

o7

- 2 R

P 1 1 5

E F E 04UI04l J1 I t

W 9v2 4

4 5

a 00G03000); 3 00 S O 7093 2

l r

C L444441444444.0o0 s

d**

01 o

V D

R S

$24 5-i I

2 6

8 O S 7

PJ3333333J1 33 RI 1 14 1 1 1 1 1 1 i1

- 1363T' 3 35

=.

412o 232>4 0>30#

B 41 00029 57.5

=

vouvV)

C D4 l

3. d. 0 0 43 3 f. *., t. l. I I '. 0 9l

)

0 03U8J3I l.

s4 v1t l

1 1 4 d

2 2

d..

' vve5 evvV9Vvvs O

DP 4 1 I

5384 P

o 0

L l d I

R

> 08 2. v.

T s i AAA 2

E I

1

> 's 5 3 6 3 ;, 2 ',

e.

, ! l

2. 's 1 > J. 8 l

- - - - - - - - l 8 82 1 f T'.

l.

8 1 I 0 442 4 -

I P

i d324e4>t 21 I.

4 8 8 1

14. o. 3 '. u. 31 l

A. C. $ C. o. d. C. U.

uCS844468421W2RWl 41 -

s l

t.

f! 4418 322331 33EEit C

J/o3 1

r 4 0. )'. l >

J'1310l

) 3l I

/ - - - - - - - - - - - - T T f.

I

'4 F > 3Ju9Vl 1

3 s 3 34 48 # 61

. /

1 i s A*

s 4 4

-s 0

4 1 8 8 s

2 l' 328 41 44 4! 4t Ia A <,. 1 4 f e.

e.s o, 4 v

4 9

1 s

i s.

4 1 st 4 4 -

9-I e 144

)492i8 41 1t a) 4 3 3. t I

4 1 244 4 -> 1 4#

, s '. I.

, >I.

L'.l211dJ1#

f t l l t 4 es A

u. u. 0 u. <,. o.,. u. e A i 1

l7/0 v8 U 31 1 101 7 08 0

4 8

J. i A. i. c. A. J. a.

AU0000O000t

. e.. -. -

s.

U0LI v J3080/I 0v1 I

i

/ el ct 3>Jn44 2a4v J

3 L

1

'. 23

> S

%s4 20.l 1 v.

l E

4 i4^9 s6 ei u t

1 d

4244 rJ i ) ) 3 3 1 3 1: I I.

J. 0, )r. )r )>

J 9

5 sl L

l l

1 l 3 '

4 v)

U L 2 2 2 2. :. 2. i. '.,,. s1i s

. s s,

t.3 a

f

' J. 21 1

J -

o-L 4

3

>>/i 21l 2J4l J 41 2

? ) *>, I ! s

)

P s.

C1 4 44 l 1l 8 l 8 4 1

, J *,

1 J

> 3 0. v.

2 6. h OI'2 ! 1 v. / 4 I

J. A. J. A. a. C. ) C.

E i EA i

U51 L

uu5 O O

0bl 8

'. : 3 n, 48 e J t

I.

t4 9J >>> a, s

) s5

>tLLi J

I 1

u'e

r. s r. r A,/ s r d i 1 11 JJ 4 s A

8 24:

8 4 t

I

>8 4 I n 2 > 3

>s ->,, -..

.081 9

'e r

(

wJ0 1L C '.

t r14 t 1 8 4 4 8 4 4 8 8 2 f 9

d 1

5 9

284 1

t.

1 bs 1

d4 5u44 3 -

I 4

L rrF

- 24d W

2 2. '). I.

a, 8 f444 M

4 4 9 A 2 ). 024445 Ooe

- t 68 1

-. to.1

7. l 1

dr 's e

4 l

448

s. *> 1 1 1 34 t

1 4,

e

d. d. J.. u. ;l.. 0, f.

d1 8

s.

OW L a J ~

. e. 4 4 4 s

U>3 -, - - *- - - - - -

2 c

e2 n.

,8 J e

s. Na t.

n d,

d J

l "e d '. o 4 01 4

I Lt 2 '

8 l

>1 3I 3 /5 i

85. 4 E c c$

s 3 22>32J2-.1 N L *< L r u2' >

I u a ',

a '.

k J#

J.

J0 s*

. 2 uJ d

8 4.

l W v M. d 8

e d.

l.

'4 s, s / / s t..J d

a

'e s 25 t n a.

lL3 r ut rvJr 4 ; c,.

r. 4 l'

i GI G4 W G L <* L ;s L O (. 's a s.

la.

t l

4 s w4 -

a GG r

i c

AAiJt

+

r vt

s. 1iA 4

t /tiL i

l

. 8 9) b

.. )

1 e 3 t e ii 's J

L:.4 A 4 4 4

a e

w I

1 ll1lll lllll1

e 6

4 4

4

+

4 4

4 5

P= N $ F tr w m==

T4WC

- w P= =

l W e 9* W W W w we

@* 't W M F ** t, O s e

+

4 e

4 4

+

6 e

+

4 g

9 3L

'.i e

+

4

+

C 9

9

+

9 4

4

+

9

+

1 P* O A9TC

== # N P*

-ONT O

T

- O P "d"

@C4 4CCC

't @ # C MFMN 9##4 9w#v

+

4

+

6

+

c

+

4 4

+

4 4

+

T

+

C

+

4

+

e e

4

+

e 4

+

4 ed

+

4

+

g

'i

,., O g N, P= P= S.

% C N,N

-%Sp e% or3

,o ei P. >

j m.e,= m 3

b m.

pA res o

sre es o r e r.,

n

.~

O

+

0

+

2:

WJ

+

4 9

9 9

+

4 4

9 d

4 4

N

.J J:

3

+

,C b

O r n er

% fm g e s.==

3 6%%

rQ^s

%9*a

.- es e %

% 3 *3 s a

=

?f

+9 T T T a O

'l P*

'P O O O 5QDT

F d A D

- O O.1

- O C O fr "1

l C

"3 te u.

T3

+

4 e

4 4

+

6 O

.t i

1 b

' eg me

+

4 6

e

+

e 4

q T

LU

.J T

"l.

4 M

U S

' 4.

O n

4 s

+

a a

+

s

+

s

+

. a N

u 4

+

e r

+

.+

+

N o69 3sS

-N-?

ca av nN O,Og

.3 2

'i

? 993 s*3 ?

'c 9.9 0

mnOo

.3. ) 3.*

9 ao%

-, 3 o 3 1:

'7

9 g er -9

)%%

+

C U

~7 0

==

N U

M

+

rd

==

+

6

+

e e

+

6 e

6 4

N Q )

B w

w 4

k h

3"S N

Lu O 1,

o e

a

+

6

==

Y v

+

v

+

e 6

= 9O

$ $ 7 ^*

3. *m

- )

9=

$ *4 OT CN g 3 $

O ** 7

9

.J

= > a"t ? $

- =.1 o 3 n

e9 6 a.

gt o+

m ca N 4 331

=* 6 no N

+

k

+

O

+

Y N

0 h.

Y,

+

we 2

+

3

)

7

+

e e

+

-) o,

.as N % 9 *.

aj m %

omya 3,

s%

J f*1 "i * *f T n.9.1 9S$Q

P 4

!% O 9 "* *F W

a=o

') 2

+

=

4 4

4 9

e 9

+

4 e

7. J J.

4 e*s

'i )

?

9 0

v

+

N

.77

?

e

+

)

3?

I e

== ",

s 4

O ~1 e

9 7 *J D <

QU34 4 '1 7 t P1 J ' *.

p m

A N

9 A

I

)

S 9

.i T

f 4

7

1 N

PJ

=

d

' Ou stion 5.14 (3.00)

Question 1.02 (3.00)

O i

LIST the three (3) "thermal limits" observed during reactor operation and STATE the limiting condition for each. (i.e., what the thermal limit is there to protect assinst.)

Ans..r, 1.

LHCR - Linsar Heat Generation Rate

(.5) designed to limit the pin power at any node in the reactor to a value i

that limits the fuel clad strain to less than one percent plastic strain.

(.5) l 4

2.

APLHCR - Average Planer Linear Heat Generation Rate

(.5)

(designed to limit average pin power at any node to a value such that following a design basis accident the) maximum fuel clad temperature

[

will not exceed 2200*F.

(.5) j 3.

MCPR - Minimum Critical Power Rt,tio

(.5) l (designed to limit the power of any fuel element to below the value i

that will) prevent any point in the bundic from experiencing the onset j

of transition boiling.

(.5)

I i

Reference:

l BFNPt Heat Transfer and Fluid Flow, pp. 9-16 through 9-26.

Chapter 9. Objectives 2.3, 3.3, and 4.3.

l TVA Connent:

j i

The question does not elicit the detailed response of the answer key,

}

specifically LHCR. The P-1 edit at BFN uses acronyms for these parameters and thses should be acceptable.

l LHCR = MFLPD and CMFLPD

}

APLHCR = MAPRAT and CMAPR j

l MCPR - CMFCP and MFLCPR j

(Reference chapter 9 and attached P-1 edit) l TVA Resolutiont l

I Answer key should be changed to accept prevent >1% plastic strain vice.

}

"pin power at any node".

Also key should reflect credit for acronym's if

}

used for thermal limit desigr.ator.

i a

\\

1 l.

1755Q i

LO i

t I

l i

t 1

l 1.04 (1.00)

Pcts 1 of 2 i

l j

.5.02 (1.00) i

.O Reactor power is 60 on IRM range 2 with the MINIMUM permissible stable f

positive period allowed by procedure COI-100-1.

Heating power is determined to be 40 on IRM range 7.

CALCULATE how long it will take for power to reach the point of adding heat if the period remains constant.

i I

Answers l

r

)

60 on range 2 is equal to 0.06 on range 7

(.25)

P(t) = P(0)e**-t/T

(.25) i P(o) = 0.06, P(t) = 40, period = 60 seconds

(.25) i i

l l

t = 60 In 40.0.06

(.25) i

= 390 seconds or 6.5 minutes

(.25) i Reference k

BFNP: Reactor Theory, pp. 3-17 and 3-19 Chapter 3, Objective 3.2 i

i COI-100-1, p. 13 f

I TVA Comment:

l i

I Answer key assumes that the reading on IRM range 7 is 40 on the 0-40 scale, i

j and thus 40 on the range 8 (0-125 scale),

but, heating range is normally l

reached mid range 7. so some may assume the question was giving POAH as 40/125 t

on range 7.

This means that P(o) =.19/125 on range 7, instead of P(o) =

.06/40 on range 7.

Then, t = T in (40/125) = 321 see

.19/125 Instead of t = T in (4Q/3 ) = 390 see.

.s

'O "40/125" is a reasonaba,: assumption also sinco 40/40 would result in full j

scale readings and scram trips.

At BFNP, we commonly use the 0-125 scale on j

l any range.

j i

[

TVA Resolution.

l Allow use of either 40/40 or 40/125

(

l

- Use 40/40 on Range 7 as POAH t

l t = 390 sec l

l 9E t

l

- Use 40/125 on range 7 as POAH I

t = 321 sec.

I L

l i

l 1749Q I

1.04 (1.00)

Pcss 2 of 2 5.02 (1.00) v TVA Comenti Plant procedure COI 100-1 does allow for reactor periodJ of < 60 seconds, but t 30 seconds, although it is desirable to have a period of > 60 seconds. This question tests the application and understanding of Reactor Theory, therefore a candidate who elects to choose 60 seconds or 30 seconds as the minimum permissible period should receive credit. (REF GOI 100-1, p. 13)

TVA Resolution:

Expand the answer key to accept a response using 30 seconds as minimum period in addition to current answer key.

f 1749Q O

1 lO l

Page 13 BF GOI-100 1

(~,}

AUG 21 1315 w_-

Section III. Startup (Continued {

INITIALS / TIME /DATE A,

Criticality (Continued)

TWttttttttttttttttttttttttttttttttttttttttttttttttttttttttTTttttttttttttttttstyt CAUTION DURING A HOT STARTUP FOLLOWING A REACTOR SCRAM AT HIGH POWER, THE CONDITIONS OF PEAK XENON VITH NO MODERATOR VOIDS COULD EXIST AT THE TIME OF STARTUP.

UNDER THESE CONDITIONS, EITREMELY HIGH ROD NOICH WORTHS CAN BE ENCOUNTERED.

f ttttt t ttttttttttttttttT% tttttttttttttt tttTTit ttttt ttttWittttttttttttttt tttttttt e

4.

Upon approval of the shift engineer, start control rod withdrawal in accordance with OI-85.

(R)

/ /

2 NQTE: Shif t all' SRM and IRM recorders to f ast ', speed prior to,

criticality and return to slow spted after initial period measurements are calculated.

l NOTE: Within the approved control rod withdrawal' seq'uence, it is possible to have a period less than 60 seconds.

If a period less than,JQ, seconds is observed, insert rods until suberiticality is observed and contact the nuclear engineer and shift engineer befora pulling any

( )*..

more rods. Periods less than 5 seconds are reportable o

to the NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

Observe the period meter when pulling rods and govern withdrawal rate'to avoid having a period shorter than 60 seconds.

(R)

/ /

NOTE:

Reactor is critical when neutron flus rises on a constant (stable) period without further. control rod movement.

l 6.

When critical, recor1Lt.ime, rodgion, rod-nutth, petiod, and reactor way r_ temperature from recirculation loop A in daily journal.

(R)

/ /

NOTE: Measure period as follows:

j For 10% power rise, multiply time of rise by 10.5.

For doubling time, multiply time of rise by 1.445.

For decade rise, divide time of rise by 2.3.

1 e

For direct period measurement when on IRMs:

a.

Time 25 to 68 on black scale ranges b.

Time 8 to 22 on red scale ranges 1

l

()* Revision 0005M

s

' 5.16 (2.00) 1.16 (2.00)

()

Question:

The attached FIGURE (GTH-747 represents parameter changes for a plant transient on UNIT TWO.

Use this figure and the following inforr.ation to answer EACH of the questions below:

(1)

Initial Power Level = 100%

(2)

Bypass Valves go to Full Open position (3)

No operator action is taken a.

The DECREASE in turbine st!-

tiow.

(point 4) b.

The INCREASE in power.

(point 7) c.

THe IK4REASE in turbine steam flow.

(point 5 and AREA 6) d.

The DECREASE in pressure.

(point 2)

Answer:

a.

BPV's open causing EHC to close Turbine CV's.

(.5) b.

Power increased due to lower feedwater temperature.

(Less steam to the Turbine)

(.5) c.

All BPV's are open at point 5.

(.25) EHC follows increasing pressure by opening CV's. (.25) d.

Pressure decreases due to BPV's opening.

(.5)

Reference:

BFNP OPL171.055 LO a 4.1/4.2 3.6/3.7 4.1/4.1 TVA Comment:

Part C; Since the question stated that the BPV's were full open due to operation of the BPV jack, requiring this in the answer should not be required.

TVA Resolution:

Accept for full credit (.5), EHC follows increasing pressure by opening CV's.

1755Q O

' Ouestion 2.02 (2.00)

Question 6.01 (2.00) f STATE whether the following statements concerning the Primary Containment Isolation System are TRUE or FALSE:

a.

Most of the PCIS motor operated valves fail closed on loss of power to the valve.

b.

The containment isolation reset switches on panel 9-5 must be operated to manually reset a RCIC turbine steam supply isolation.

c.

Loss of RPS Bus A will NOT cause any PCIS isolation valves to close, d.

The TIP guide tube ball valve will isolate on a high radiation signal.

An s'.'e r :

a.

False (MOV's fail as-is) b.

False (separate reset switch for RCIC) c.

True (both logic channels must desner,;lzo) d.

False (only high D/W pressure or low RPV level)

(0.5 each)

Reference:

BFNP: OPLl71.017 PCIS, pp. 6, 17 and 18 Objectives V.D and V.E.

TVA Comentt Part C Answer key states True (both logic channels must de-coergize).

This is a true statement if RPS power is supplied to the respective logic channel. When the RPS bus power is lost, the relay loses potential even though the opposite PCIS channel relays have closed contacts.

01-99 attachment 2 indicates valves that will isolate on RPS

'A' (inboard) or RPS

'B' (outboard) power loss.

TVA Resolution:

Answer key should be changed to reflect E31se as the correct response.

1752Q O

t g

i I

TITLE: REACTOR PROTECTION SYSTEM OPERATING INSTRUCTIONS UNIT 2 1

]

2-o!-99 AnACanm 5 l,

I CLASS: SAFEn RELATEo RET 0003 (Page 1 of 5) i RPS BUS A or & POWER TRANSTER

1. Transfer of power supply to either RPS Sua A or 1 may result in the following events:

. V_A_4V_[

FUNCTION /8YSTEM ACTION FCV-32-62 Drywell Control Air Compressor suction CLOSES

[

r; e

FCV-32-63 _

Drywell Control Air Compressor suction CLOSES

(

FCV-64-17 Drywell/ Suppression Chamber purge inlet CLOSES FCV-64-18 Drywell purge inlet inboard CLOSES i

FCV-64-19 Suppression Chamber purge inlet inboard CLOSES l

~

I FCV-64-29 Drywell purge exhaust inboard CLOSES

\\'

FCV-64-30 Drywell purge exhaust outboard CLOSES o

FCV-64-31

.Drywell purge exhaust bypass to SCTS CLOSES g

6 FCV-64-32 Suppression Chamber purge exhaust inhoard CLOSEF FCV-64-33 Suppression Chamber purge exhaust outboard CLOSES FCV-64-34 Suppression Chamber purge exhaust bypass to SGTS CLOSES j

i FCV-64-36 Drywell/Suppe Chbr purge exhaust to SGTS CLOSES

(

FCV-64-139 Drywell to Suppr Chbr DP compressor suction CLOSES j

FCV-64-140 Dryv.ill to iuppr C! c DP compressor disch".rge CLOSES I

FCV-76-17 Drywell/ Suppression Chamber nitrogen purge inlet CLOSES j

FCV-76-24 Drywell/ Suppression Chamber nitrogen purge inlet JLOSES CLOSES TCV-76-18 Drywell nitrogen purge inlet f

FCV-76-19 Suppression Chamber nitrogen purge inlet CLOSES f

FCV-76-49

Containment Inerting System A sample CLCSES l

l FCV-76-50 Containeent Inerting System A sample CLOSES i

i e

2382p Page 25 of 29 2-0I-99 L-

J N.

TITLE: REACTOR PROTECTION SYSTEM OPERATING INSTRUCTIONS UNIT 2

(

)

2-0!-99 AnAcaxM 5 l

CLASS: SAFETY RELATED REV 0003 (Page 2 of 5)

RPS BUS A or B POVER TRANSFER

1. Transfer of power supply to either RPS Bus A or B (Continued):

VALVE FUNCTION / SYSTEM ACTION FCV-76-51 Containment Inerting System A sample CLOSES FCV-76-52 Containment Inerting System A sample CLOSES FCV-76-53 Containment Inerting System A sample CLOSES I

FCV-76-54 Containment Inerting System A sample CLOSES Inert ng System A sample CLOSES f

i FCV-76-55 Containment FCV-76-36 Containment Inerting System A sample CLOSES FCV-76-57 Containment Inerting System A sample CLOSES p.

FCV-76-58 Containment Inerting System A sample CLOSES

.b Containment Inerting System B sample CLOSES FCV-76-59 TCV-76-60 Containment Inerting System B sample CLOSES FCV-76-61 Containment Inerting System B rample CLOSES FCV-76-62 Containment Inerting System B sample CLOSES j

FCV-76-63 Containment Inerting System B sample CLOSES FCV-76-64 Containment Inerting System B sample CLOSES FCV-76-65 Containment Inerting System B sample CLOSES FCV-76-66 Containment Inerting System B sample CLOSES TCV-76-67 Containment Inerting System B sample CLOSES FCV-76-68 Containment Inerting System B sarcple CLOSES FCV-84-20 Drywell or Suppr Chbr exhaust to SGTS CLOSES 2382p Fage

~$ of 29 2-0I-99 5

i l

TITLEt REACTOR PROTECTION SYSTEM OPERATING INSTRUCTIONS UNIT 2 2-0I-99 CLASSt SAFETY RELATED ATTACNMENT 5 l

r O

RET 0003 (Pase 3 of 5)

{

i i

RPS SUS A or 5 POWER TRANSTER l'

/

1. Transfer of power supply to either RPS Bus A or 8 (Continued):

B&df.1 FUNC7 TON /8V8 TEM AGT19!!

TCV-90-254A Drywell radiation monitoring sample Closes TCV-90-2545 Drywell radiation monitoring sample CLOSES TCV-90-255 Drywell radiation monitoring sample CLOSES

[

t

['

TCV-90-257A Drywell radiation monitoring sample CLOSES 9

TCV-90-2578 Drywell radiation monitoring aseple CLOSES 1

I f

i TCO-64-13 Reactor lone ventilation CLOSES r

!l TCO-44-14 Reactor Zone ventilation CLOSES f

)'

TCO-64-40 Reactor Zone ventilation CLOSES l

f l

FCo-64-41 Reactor Zone ventilation CLOSES t

TCO-64-42 Reactor Zone ventilation CLOSES

(

d TCO-64-43 Reactor Zone ventilation CLOSES f

TCO-64-5 Refuel Zone ventilation CLOSES I

l TCO-64-6 Refuel Zone ventilation CLOSES j

[

1 FCo-64-9 Refuel Zone ventilation CLOSES l

l" CLOSES t

TCO-64-10 Refuel Zone ventilation i

1'

[

TCO-64-44 Refuel Zone ventilation OPENS j

)

TCO-64-45 Refuel Zone ventilation OPENS

[

Reactor Zone supply and exhaust fans TRIP l

l i

1 Refuel Zone supply and exhaust fans TRIP Standby Cas Treatment System S, TARTS l

Cont 1 Bay Emergency pressurization

^*

Traversing Incore Probe System Af.'TO RE*RACT l

i 2382p Page 27 of 29 2-0I-99 l L

(

l

TITLE REACTOR PROTECTION SYSTEM OPERATING INSTRUCT!0fts UNIT 2 2-01-99 CIASS SAFETY RELATED ATTACEMENT 5 l

RET 0003 (r..

5 of 5)

RPS SUS A or B POWER TRANSTER

2. Transfer of power to RFS Bus A only may result in the following events in addition to those listed for RPS Bus 4 or 3 power

transfer:

V.GV.,[

f11NCT10N/8Y$ TEM LM FCV-74-44 RER shutdown cooling inboard suction CLOSES TCV-74-53 RNA System I inboard injection CLOSES TCV-74-102 RHR System HP flush / vent CLOSES TCV-74-103 RMK System LP flush / vent CLOSES TCV-75-57 Drain pump A inboard isolation CLCSES I

TCV-77-15A prywell equipment drain discharge CLOSES l

TCV-77-2A Drywell floor drain discharge CLOSES TCV-69-1 RWCU inlet CLOSES TCV-69 RWCU inlet CLOSES TCV-69-12 RWCU outlet CLOSES TCV-1-14 MSIV.AC control power DE-ENERGIZES TCV-1-26 MSIV ?.C :ontrol power DE-ENERGI2ES TCV-1-37 MSIV AC c.

ol power DE-ENERGIZES TCV-1-51 MSIV AC contru 'ower DE-ENERCI2ES TCV-1-55 Main Steam Line drain inboard CLOSES TCV-43-13 Recire loop inboard sample CLOSIS O

2332p Page 23 of 29 2-01-99

)

L

TITu REACT 0k PROTECTION SYSTEM OPERATINO INSTRUCTIONS UNIT 2 2-0I-99 AnACnMENT 5 l

U class: sArzn REuTcn BEV 0003 (Page 5 of 5)

RFC SUS A or 8 POWER TRANSFER

3. Transfer of power to RPS Bus 5 only ma; result in the following events in addition to those listed for RPS Bus A or R power transfer:

VALVE TUNCTION/ SYSTEM ACTION TCV-74-47 RER shutdown cooling outboard suction CLOSES 1

FCV-74-67 RER Systes II inboard injection CLOSES TCV-74-119 RER System HP flush / vent CLOSES 1

FCV-74-120 RER System LP flush / vent CLOSES TCV-75-58 Drain pump A outb'oard isolation CLOSES i

i i

FCV-77-158

. Drywell equipment drain discharre CLOSES TCV-77-25 Drywell floor drain discharge CLOSES FCV-69-2 RWCU inlet CLOSES FCV-69-12 RWCU outlet CLOSES a

FCV-1-15 MSIV AC control power DE-ENERGIZES TCV-1-27 MSIV AC control power' DE-ENERGIZES l

l FCV-1-38 MSIV AC contro.1 power DE-ENERGIZES FCV-1-52 MSIV AC control power DE-ENERGIZES TCV-1-56 Main Steam Line drain outboard CLOSES TCV-43-14 Recire loop outboard' sample CLOSES j

{

[

u 2382p Page 29 of 29 2-0!-99 LAST PAGE e me m

-w-w+---w-

-y,,-

y,

k I

Page 24 BF OI-64 DEC!'t "U

(

JV. Abnormal Oovrations (Continued) f; P.

PRIMARf C0hIAINMENT ICULATIONS (1-8) 4.

(Continued) d.

HPCI exhaust diaphraga pressure high (10 psis between rupture dises).

l Refer to 0I-73, Abnormal Section, for operator actions.

m Group 5 - RCIC isolation is initiated by one or more of the L.

5.

j following:

o

[E RCIC steamline space high temperature (200 ).

j a.

h' RCIC steamline high. flow (450" water AP or > 1501, af ter b.

second time dels/).

i('

RCIC steamline low pressure (50 psig).

I c.

j j

'~

d.

RCIC exhaust diaphragm pressure high (10 psig between i

rupture dises).

Refer to 01-71, Abnormal Section, for operator actions, j

p Group 6 - Ventilation systems isolation is initiated by one or j1 6.

j more of the followinst.

Reactor icw level (+11 inches above instemment zero).

j

),

a.

b.

High drywell pressure (2.45 psis).

Reactor building high radiation (100 mr/hr).

I c.

Refer to 01-30, Abnormal Section, for operater actions.

)

A 1.

Rx zone ventilation hl radiation 100me/hr.

j f

2.

Refuel done area hi radiation 200mr/hr.

Group 7 - Process line isolation is initiated by the following 7.

i condition only.

[

The respective turbine steam supply valve not fully closed.

(

a.

Refer to 01-64, Abnormal Section, for operator actions.

Group 8 - TIP ! solation is initiated by the followins:

8.

I High drywell pressure at 2.45 psig.

I a.

b.

Reactor vessel low water level at < 11 inches above l

Refer to GOI-100-9. Abnormal Sectich, for instrument zero.

operator actions.

L E

a 0087N l

Question 2.05 (1.00)

Question 6.02 (1,00)

('

During your shift the Drywell Air System (DWAS) isolates. You verify a Group VI isolation has not occurred.

a.

Name one other signal that could have caused the DWAS isolation.

i b.

WHAT air system valves close when the DWAG isolates? (i.e., valves within DWAS that will closes when the system gets an isolation signal).

Answers a.

reactor zone ventialtion radiation sig'al

(.5) b.

D/W air compressor suction valves (63,62)

(.5)

Reference:

BFNP OPL171.054, Control and Station Air Systems, p. 11.

Objectives V.C.

i TVA Comment:

Part A:

The control air Jesson plan does make it appeari due to outline format, that Reactor zone high radiation is not a group VI 1

isolation signal. The PCIS lesson plan 171.017 page 12 and OI j

64, page 24 indicates it is a group 6 PCIS isolation. The candidates know the isolation signals and this question confused i

them. The format of OPL171.054 is being corrected.

The loss of control air on U1 6 U2 will result in closure of the salves 62 &

[

63. (REF 01 32A, Section 3.0) l 4

i TVA Resolution:

l l

}

Part At This question caused a great deal of confusion. The question should be deleted with credit for the time spent addressing the l

response since this was a timed examination.

i l

I i

1752Q 1

?

I i

\\

?

([2)

[

i 1

Pcg2 12 of 22 OPL17TJf7 i

03/11/86 Rev. O g

V Table 1 i

(continued) i I

Location Initfation Ref. to Power to Power to l

Signals Group 5

-- Valve Type-Drywell Open (3)

Close (4) 1 i

RCIC spar:e hi RCIC turbine.

M0 Gate.

Inside AC AC temp. '.'00'T steam supply isolation valve

' ~ '

(FCV 71-2)

RCIC steamline RCIC turbine NO Gate Outside DC DC hi flow 150%

steam supply L

(after a 3 i

second delay) isolat. ion valve RCIC steamline (FCV 71-3) low press.

50 psig RCIC high pressure t

between I

rupture 4

l disc 10 psig

[

l Location

'l Initiation Ref, to Power to Power to 1

Signals Group 6 Valve Type Drywell Open (3)

Close (4) l Rx low level Dryvell nitrogen A0 butter-Outside Air /AC Spring

+11" purge inlet fly isolation valves 111 dryvell (FCV-76-18) press +2.45 i

Suppression A0 Butter-Outaide Af r/AC Spring psig chamber nitrogen fly 111 Rad Rx bldg purge inlet ventilation isolation valves (FCV-76-19)

I P%ggs}9 %8 mr/hr.

1A 111 Rad refuel Drywell main A0 Butter-Outside Air /AC Spring l

zone exhaust iso-fly

[

A) tee ar/hr lation valves l

(s1 (FCV-64-29 and l

p 30)

AJ NOTE: 0 & MR 294 l

i i

Pas? 13 of 1 l OPL171.017 g_.

03/11/86 Rev. O i

i

~

Table 1 (continued) m i

I.ocation j

~ Initiation

~

Ref. to Power to Power to

~

'Sinnals - ~ Croup 6 Valve Type Drywell Open (3)

Close (4) l r

~

." SuppNesion A0 Butter-Outside Air /AC Spring ^

~

. & r hamber mais.

fly l

e enhamat isol.

f

~

valves ~(FCV-

~~

i a 64-32 and 33) i Drywell/

A0 Butter-Outside Air /AC Spring

[

suppression fly

~ hamber purse i

c inlet (FCV-64-17)

Drywell _

A0 Butter-Outside Air /AC Spring L.

atmosphere fly

~

purge inlet (TCV-64-18)

Drywell hydrogen 50 Gate Inside AC Spring j

sample line valves analyzer A (TSV-76-49) l Drywell hydrogen SO Gate Outside AC Spring sample line valves analyzer A j

(FSV-76-50)

~

Drywell oxygen SO Gate Inside AC ~

Spring sample line i

valves analyzer A l

(TSV-76-51) t Dryvell oxygen SO Gate Outside AC Spring i

sample line l

valves analyzer A (FSV-76-52) j Torus oxygen SO Gate Inside AC Spring i.

sample line j

valves analyzer A (FSV 76-53) i i

l l

c Paga J of 22 g.

OPL171.017 03/11/86 Rev. O

._s k (v)

Table 1 (continued)

Location Initi~ation Ref, to Power to Power to

~

Signals Group 6 Valve Type Drywell Open (3}

Close (4)

S Torus oxygen SO Gate Outside AC Spring sample line valves analyzer A (FSV-76-54)

Torus hydrogen SO Gate Inside AC Spring sample line valves analyzer A (TSV-76-55)

Torus hydrogen SO Gate Outside AC Spring sample line valves analyzer A l

(TSV-76-56)

Sample return SO Gate Inside AC Spring f

valves

.+nalyzer A (FSV-76-57)

Sample return 00 Gate Outside AC Spring valves -

Analyzer A (rSV-76-58)

Dryvell hydrogen SO Gate Inside AC Sprins sample line j

valves -

Analyzer B (TSV-76-59) l Dr)vell hydrogen 50 Gate Outside AC Spring sample line valves -

Analyzer B (FSV-76-60)

Dr>vell oxygcn SO Gate Inside AC Spring sample line

[

valves -

f.

Analyzer B t

(FSV-76-61)

Page 15 of 22

~

OPLl71.017 03/11/86 Rev. O nU Table 1 (continued)

Location Initintion Ref. to Power to Power to

Signals Group b Valve Type Dryvell Open (3)

Close (4)

Drywell oxygen SO Gate Outside

/C Spring sample line valves -

~

Analyzer B (FSV-76-62)

Torus oxygen SO Gate Inside AC Spring sample line valves -

Analyzer B (FSV-76-63)

Torus oxygen SO Gate Outside AC Spring sample line O.

valves -

Analyzer B (FSV-76-64)

Torus hydrogen SO Gate Inside AC Spring sample line valves -

Analyzer B (FSV-76-65)

Torus hydrogen 50 Gate Outside AC Sprin's sample line valves -

Analyzer B

(

(FSV-76-66) l

[

Sample return SO Gate Inside AC Spring valves -

4 Analyzer B (FSV-76-67)

Sample return SO Gite outside AC Spring valves -

Analyzer B (FSV-76-68)

O

Paga 16 cf 22 OPL17T.Tf7 03/11/86 Rev. 0 Table 1 (continued)

Location initintion Ref, to Power to Power to iSignals_

Group 6 Valve Type Dryvell Open (3)

Close(4J Suppression A0 Butter-Outside Air /AC Spring chamber purge fly inlet (FCV-64-19)

Dryvell/

A0 Butter-Outside Air /AC Spring suppression fly chamber nitrogen purge inlet (FCV-76-17)

Dryvell exhaust A0 Butter-Outside Air /AC Spring valve bypass fly to standby gas O'

treatment system (FCV-64-31)

Suppression A0 Butter-Outside Air /AC Spring chamber exhaust fly valve bypass to standby gas treatment system (FCV-64-34)

Dryvell/

A0 Butter 'ntside Air /AC Spring

(

suppression fly L

chamber nitrogen purge inlet (FCV-76-24)

System suction A0 Valve Outside Air /AC Spring isolation valves toaircompressors "A" and "B '

(FCV-32-62,63)

I i

O

I,.

l' TIT 128 DETWELL COIrrtCL AIR STSTEM OPERATINS INSTRUCT!0IIS 13t!T 1 1-41-32A Class sar:TT as!Asso 857 0001 Fr.

p 1.4 flest querians (Castieued) b 1.4.4 ASIf1431-14, Wiring Magram 1109 AC/1309 BC Talves and Nies.

Coenseties Diagram

[,i 3.4.5 47A1 M4 series Talve Tabulaties of Psrher Tage

{

,1.4.4 4TM01 series, lestrusset Tebalaties 1.4.7 1 4 75410-31-1, Neshemical Centeel Diagram Centrol Air System 1.4.4 1 4 73610-76-1, Mechanical Centeel Diagram Contatammet Zeerting L(

Systee

[

1.4.9 1-4751447-4.10 Flow Diagram Centre 1 Air System 1.4.10 47W611-31-1 Nethemical Logie Diagres Drywell Air,Compresser I"

1.5 Tender Itansala

(,

1.5.1

!agereell - Reed testructions and Parte List nedet 1 Air Dryer O

- (Fess 11348) Centreet.75411 CTIt $51 L'

1.5.1. Ingereell - Reed testructions Firger Talve 1 through 3 heroepower j

Type 30 Compressere (Itedel 13 AIE, and 135 BEL) (Form AP-4145)

Centreet 15411 C998 $51 i

i i

3.0 PRE &l/TI M M LDt!Taf1 M i-l 3.1 DRTWELL COIF!BOL AIR C01W180808 SOCTIGI valvoe, 1-FCT-32-4* end

'r. PCT-31-43, will eleoe se rey of the followieg aroup ?!.eeleties signale:

3

'l

]I

, 3.1.1 taw teoster Water Invol (+ 11 Leebee).

I 3.1.1 Brywell Bish Pressure (1.45 pois).

j Ill' 3.1.3 teacter Building ventileties Radiettee Eigh (71 er/hr).

3.1 nafvtLL C0erTt0L A!n Colemasset SUCTICII volves,1-FCT-32-41 and 1-FCT-31-43 will close en less of Plant Centrol Air supply.

3.3 The Drywell Centrol Air Compressors will trip es low sil level in the I

creekcase.

l~

4 5iO Oeneral Revision 2301p Page 3 of 3$

l ')!-3:A ir

b L

j

ggfation 2.07 (3.00)

Concerning the CRD system!

O a.

WHAT are the norual values for CRD hydraulic system FLOW and DRIVE I

WATER DIFFERINTIAL PRESSURE?

(.5) b.

WHAT percentage of CRD hydraulic system FLCW is supplied to the CAD cooling water headert (1.0) a t

c.

Inunediately following a reactor scram the control rod full-in (green) l lights on panel 9-5 are lit but there is no position readout j

dispisyed.

IIPLAIN WHY this occurs and WHAT eventually happens that I

allows the control rod to settle into the 00 position.

(1.5) j r

Answert r

a l

a.

45 to 65 spm (accept 0.25 to 0.33 gpm per CRD)

[

260 psid (accept 250 to 210 puid) f f

b.

100% (accept "all")

(

c.

Following a scram, but before the SDV is full, the control rod will be f

)

in the over travel-in position since there is still a large D/P across the piston, i

After the SDV is full, there is no D/P across the piston and the i

control rod will settle into the 00 position.

I I

i O

8FNPt OPL171.005, CRDH, pp. 9, 10, 24 through 29, and 40.

j L.O. M, 0, and S l

I 1752Q i

O i

r j

Question 2.07 (3.00)_

(continu:d)

TVA Coment:

a.

The normal valve for CRD hydraulic system flow given in the answer key (45 to 65 gpm) is the flow to the drive and cooling water headers and is the Indicated system flow on panel 9-5.

The total system flow however includes 4 to 6 spm (REF BF 12.24. pg. 81 attached) to each of the Reactor Recirculation pumps and 20 gpm (REF OPL171.005. pg. 18) pump minimum flow which are not seen by the flow indication. The total CRDH system flow can thus be as high as 97 gpm. An answer of 45 to 100 gpm should be accepted for full credit.

b.

The percentage of flow which is directed to the cooling wat.r header will vary based on the point used to calculate CRD hydraulle system j

flow in part a.

However, even if the 45 to 65 spm throught the flow element is used as the system flow, at least part of the finw thrcugh the stabilizing valves (~ 2 spm) does not so through the cooling water header but goes through the exhaust header orificed check valve j

and lifts the 40D valve on some rods to relieve to the reactor. The flow through the cooling water header is something less than 100% and each answer should be evaluated individaally based on the students assumptions.

Resolutiont l

a.

Full credit should be given fort 45-65 gpm as stated in answer key or expand the answer key to accept 45 i

j to 100 gpm.

1 b,

change to reflect full credit for <100% flow l

l l

17!2Q j

)

i 1

I e

i l

l i

1

dnnessee Valley Authority pap 31 Browns Terry Nuclear Plant

!! E V 0004 Sr-12.2s i

Standard Practice

('

).mC:ct? :~ s (Continued) l Elevation 565 (Continued)

Unit 2 l

2300-0700 0700-1500 1500-2300 i

l

--.,-a-..

mnnnnenm Core Spray Sparger Break ($!-2) memnw,***

vawnwwnnu, l

--_..__u wr==*mm I

Pd!$ 75-28

- - - - ***m m mm PdIS 75-54 a

j a

- mm****

-.w, Ventflation (An 81d4 440-V Vent 84 2B) u--

wwwmm***

Ra 2one Supply Tan A

~~

i (0FF. SLOW, /AS*)

Ra :one Supply Tan 8 (0FF, Stou, TAST)

(

)

Refuel Zone Supply Tan A l

(OFF, 314N, TAST)

(

)

Refuel Zone Supply Tan B j

(OFF, SLOW, TAST)

- - - - wwmanene manmmsm t

Reaetor Rec 1re Pump,

- - - - wwww **mm****

msnmemm l

A Seal Water Flow (4-6 spe) 6r,

N.. ;

B Seal _ Water Flow (4-6 gpal l

Drywell A/C Suction filter 2 min

- - - - *mwnnwnm 4

f I

Blowdown (32-204)

(!) ****mwm ammmane

)

mananma mansannm \\

p j

Rx 'Jater Level ($I-2) scenannemj

[

vanawanam !

t LIS-3-52 munenwnmi menneeem i

- mmumm ennennem i.

i L:3-3-62 u.-.. -

manneaam l

[

i vnnnenewww

maannaan, 5econdary Cortairmnt Doors (closed)

- - wwa*we manananm r

4 g

l No. 236 Unit 2 to Air Lock (PN)

( !_)

(f)

(:j

[

j

!b. 234 Unit 2 Inside Eqpt Lock (?N)

(!)

(:)

4 tb. 237 Unit 2 Outside Eqpt Lock (!N)

<!)

(:)

( )'

i

?b. 240 Unit 2 to Elev Shaft ( $'J )

(!)

(:)

!b. 244 Unit 2 to Air Lock (NE)

(!)

(:)

{

tb. 242 Unit 2 to Elev Shaft (SE)

(!)

(:)

()

CRD NCU sanual valve check (visual) mawawnnm maannaam (Monday)

(I) enwnnewm mennenam j 1492p i

I

l Page 46 of 49' OPL17 G 5 l

03/06/86 Rev. 1

, pJ l

N N

a l

j.

g l

[0!a,.l

g 3

{.,

i

~'

L I

I

i si l

l I

I l

l is a

l tl I

I:,

l rh i

S

[

l 1+

3,.

U. i... ~..

f, w

i

__.;. jigJ i

vi gi e

_e D -@.

I l

c>*

g I(jy @I T*'"

b u l w i li _.

y ;

ol e

g

,7 v

V m

w

c -to: j g i = 8 L l ^ ^ t ? ? g Ll_io;7# = i 0 I l 5 i g y% :,, y i l I. O (_._ - @c

Nq ww l<,

t o f

F2

2$p'

li y,Q%;I p

l i r3 I ] Q s FIGL1E 3 CONTROL RCD DRIVE NYDR.R'LIC SYSTUI (TP-3) Paga _26 ef 49 OPL171.005 03/06/86 c3 Rev. 1 ) 1,esson Outline Instructor Notes (b) The flow control valve maintains a constant flow of 55-65 GPM through the system. (That is, the flow control valve will hava to open further as reactor pressure increases in order to maintain the required system flow.) ~ (c) If flow stays constant in the system, the pressure drop across the drive and cooling water pressure control valves will stay constant regardless of-reactor pressure. (d) As a result," the drive and cooling water pressure control valves will require adjusting only once (upon system startup) and will not require constant gt adjustment during a startup or shutdown. (6) System return line (Figure 6) TP-6 (a) Flow path Returns water from the CRD hydra,ulic system to reactor. NOTE: GE SIL No. Supplement 2

1. Via cooling water pressure control valves and cooling water supply lines up through drives and into the vessel.

Additionally 1-2 gpm is distributed tFrough the exhaust header orificed check valve. This flow unseats the 40D valve at - 3 psid and llows to P-over area into vessel. During control rod movement when the selected HCU 40D or 40B talve opens the drive water flows to the exhaust, water header. This c flow is distributed through '] the other HCU's 40D valves. ( This occurs because the 40D valves require only 3 psid to unseat as opposed to 20 psid for the cooling water header flow path. s. l

Question 2.08 (1.50)

Question 6.04 (1.50) () A Core Spray line breaks inside the shroud, s. WILL the break cause an alarm in the control room (YES or NO)? (.5) b. HOW will the break affect core spary performance for that loop? (1.0) 6nswer: l a. No (.5) (If a core spray line breaks inside the shroud, the dif terential pressure indicating switch will det.ct reactor pressure I inside the shroud as usual; therefore, no abnormal differential pressure will be indicated.) t b. The core spray loop can perform a flooding function (.5) but its apray will not provide full core spray coverage (.5) Feference: BFNP OPL171.045, Core Spray, pp. 15 and 16, Objective V.K. TVA Comment: The answer key requires "flooding function" for full credit; however, an answer which addresses lost of spray function should receive full credit since break was inside shroud as given is question. TVA Resolution: Accept lost of spray cooling function for full credit. [ f r I 1752Q i l i I l t l h f t f ~ - - _ _ - - - _ _ Questien 6.07 (2.50) Question 3.1 (2,501 gU The plant is operating at 100% power and 100% core flow when the "A" flow converter output falls to zero. MATCH from Column B the action that will exist for each trip function in Column A given the above conditions. NOTE REPSONSES MAY BE USED HORE THAN ONCE COLUMN A tot,UMW 3

a. "A" APRM Hi-H1 thermal

1. Rod Block

b. "B" APRM Hi-H1 thermal

2. Half Scram

c. "C" APRM Hi

3. Full Scrsm

d. "D" APRM HL

4. None 1

e. "E" APKN Hi-H1 neutron f Answert a. 2 b. 4 ) e. 1 ] d. 4 e. 4 j Re f ererige t BFWPt LP 22. L.O.D TVA Com ent 7 Clarification received by several candidates resulted in no credit. The clarification givent conditions in Column 'A' existed in addLM )n to the flow converter ' A' f ailure. An additional answer should be developed that addresses the question in this context. Therefore a candidate who successfully answers based upon this clarification will not be jeopardized. TVA Resoluttent Expand the answer key to accept for full credit a correct response to the question taken from the concept of Colum.n 'A' existing in addition to the flow converter failure. 1753Q

guggilon 3.05 (2.00)

You are in the process of propsring the Main Turbine for startup in accordance with OI-47.III.c. The following conditions exist: O. Main Turbine is reset VALVES CLOSED is selected Waming rate indicator is at sero position Load 11: sit is set at 100% FAST accele.*ation rate is selected a. STATE the position for E4CH of the following valves with the turbine in this condition. (1) Main stop Valves (2) Control Valves (3) CIVS Stop (4) Intercept b. You now select SHELL WARMINC to prewatta the turbine by pressurisation of the Hp turbine. STATE the new position of the valves, specified in part "a" above, given this changed ccadittor.. Answers a. (1) Closed (2) Closed (3) Open (4) Closed b. (1) No. 2 bypass open Nos. 1,3,4 closed (2) open (3) Closed (4) Closed Fe f ere'111t BFWP LP 10, L.O.D 01-47 TVA Coeunentt part 5: With the initial conditions stated, i.e "warning rate at aero." the number 2 stop valve internal pilot (bypass) will remain closed untti the warning rate potentiometer is increased. The watleing rate potentiometer must be at low speed stop (sero position) procedurally and mechanically to select shell or chest warning. IVA Resolution part B Change answer key to accept number 2 stop valve internal pilot (bypass) valve closed and stop valves closed should be accepted for full credit. 'Page 20 BF OI-4* tt? 01 G85 Ill}h III. Operatint Instruction 1 (Continued) (Continued) C. Preparation for Startup I 1. To reset main turbine (Continued) Depress the master reset pushbuttta switch (HS-47-678) until b. f* the emergency trip system TRIPPED 11the goes out l (appvosinately 3 to 5 seconds)., The mechanical trip valve and the vacuum trip w!!! also light c. ..t their RESET lanps. 6 d. Observe the followingt-. Tha No. 2 stop valve is held closed. 1) The No. 1, 3, and 4 main stop valves are held closed by their respective test solenoid valves untti the No. 2 2) 't anta stop valve reaches its full open position. The control valves are held closed. 3) intercept valves are Leld closed. 4,

5) The intermediate stop valves will open.

To prewars, by pressurization HP turbine. 2. f When the first stage bowl temperature is < 250'P. This is to be E9II prewarming by 9tessurization is 'necessary.done a f L Power range, Check the following permissives met! s.

1) Turbine reset.

.1) VALVES CLOSED selected. Varning rste indicator,must_be_at sero _ posit. ion. -t 3) b. Set load limit to 100%. Select FAST acceleration rate. c. Prior to performing the next step, close theFCV-1 E211t 4 following valves: 3UPPLY To RFFTs). ' Revision for pagination L 00051

Page 21 BF OI-47 III. Operatint Instructions (Concinued)

SEP 0 ?,1995 C. Preparation for Startup (Continued) 2. To prewarm, by pressurization HP turbine. (Continued) t d. Open/ check open steam leads drain FCV-6-109. Select SHELL WARMING and observe: e.

1) Shell warming light comes ON.

2) Intercept valves remain CLOSED.

i~ 3) Intermediate stop valves go' CLOSED. ~ r

4) Coatrol valves fully OPEN.

.s

5) Main stop valve No._2 servo current 16 at tero.

f. Press INCREASE button until pressure starts to build up in the high pressure turbine. NOTE: In the event the turbine should roll off turning gear, the governor will limit turbine speed to 100 rpm by closing the enntrol valves. NOTE: If turbine rolls off turning gear, decrease flow to 'zero, wait until zero speed on the turbine then place h turbine back on turning gear and repeat the above step as necessary. i Monitor high pressure turbine exhaust pressure to maintain 60. g. l l 100 psig. L. NOTE: Monitor computer point A345(U-1&3) D345 (U-2) continuously to maintain turbine 1st stage pressure ~60-100 psig. Reactor scram may result when in shell warming with.stop valves closed and turbine 1st stage pressure > 142 psis. l. NOTE: The first stage bowl metal temperature differential is limited to 750F. f (I. metal should not exceed 150 F/hr. NOTE: The temperature rise on the inner first stage bowl 0 h. Keep differential expansion within limits. i. Xeep HP shell temperature 250-2800F and steam chest temperature 2800F. i ' Revision for pagination O L r 0005R C l l. 0Page 22 BF OI-47 i - Stp 0 3 1985 L III. Operating Instructions _ (Continued) C. Preparation for Startup (Continued) (Cont ' aut.d ) To prewarm, by pressurization HP turbine. 2. Continue to warm for length of time indicated by Figura 47-2,. I f j. .Upon completion of warming, zero flow and select OFF. -> 1. l J, The control' valves will now'close and the intermediate ~ 1 r h NOTE: valves will open. s 1. Open all drain valves. 3. Valve chest warming. Check the following permissives met: a. li Turbine reset. t-

2) VALVES CLOSED selected.

-> 3) Warming rate indicator must be set at_zeto. b. Select CHEST WARMING mode. The control, intercept, and main stop valves should-be NOTE: l~ closed. Slowly increase flow through the No. 2 MSV to establish the I c. required warming rate. L The warming rate should be regulated in such a way as NOTE: to remain within the control valve chest metal temperature differential limits given on Figure 47-1, After steam chest pressure and temperature are at rated and d. the differential expansion is normal, terminate cheet warming by pushing 0FF button. The turbine should be rolled within 2-3 hours after NOTE: completion of the prewarming operations so that unnecessary cooling is avoided.

Revision for pagination 0005R e

J Questien 3.08 (3.00) Answer EACH of the following with respect to the Rod Sequencer Control System: /^^ 1 ( )\\ a. The RSiS was developed for three different regions of rod withdrawal: (1) 100% cod density to 50% rod density (2) 50% cod density to preset power level I (3) Beyond preset power level For EACH region above STATE BOTH the design function of the RSCS AND the type of rod control in effect to accomplish this fuention. (1.5) b. During a reactor startup under rod sequencer "A" all A12 and A34 rods are fully withdrawn then the Sequencer Mode Selector (SMS) and Rod Sequencer Seclector (RSS) switches are placed in "Normal". LIST four (4) interlocks this action enables. (1.0) c. State the effect on RSCS if its turbine generator let stage shall pressure input fails HIGH. (.5) Answer: a. (1) Prevents selection or movement of rods out of sequence (.25) Sequence Control (.25) (2) Prevents withdrawal errors within the sequence (.25) Group Notch Control (.25) O' (3) None (RSCS bypassed) (.25) Nono (.25) b. (1) Allows selection of any "B" sequence rod (.25) (2) Enables group notch control (GNC) logic (.25) (3) Bypasses the continuous withdraw mode of RMC (.25) (4) Prevents selection of any "A" sequence rod (.25) c. Bypasses all rod sequence cor. trol logic (.25)

Reference:

BFNP:

LP 25, L.O. A & I.1

' Ou*stion 3.08 (3.00) continutd TVA Comment:

O Part a.

The purpose (Design Function) of the RSCS system is to restrict control rod movement in the startup and low power ranges. This limits peak full enthalpy to <280 calories /gm upon the postulated rod drop accident.

(REF:

OPLl71.025, p. 3).

In any region in which RSCS is enforcing, selection of rods not in the required sequence is prevented.

In region from 100% Rod density to 50%

Rod density, only one RSCS group A, or A,, (B, or 3

3 if starting up using B sequence rods) can be selected.

B4 In region from 50% rod density to preset power level only the rods in opposite sequence (B, and B,4) can be selected.

3 This region also enforces Group Notch Logic on the individual RSCS groups. Group Notch Logic will keep all rods within a RSCS group within one notch of the other rods in the group (i.e. RSCS does not enforce group insert or withdraw limits)

TVA Resolution:

Part a (100% RD to 50% RD):

Restrict control rod movement of rods not in selected sequence.

Sequence control Part a (50% and Preset power level):

Restrict control rod movement of rods not in solected sequence and enforces group notch control.

Group Notch Control 1753Q O

Question 3.13 (2.50)

Question 6.14 (2.50) r Answer EACH of the following with regard to the 250V Unit and Plant DC power system:

a.

LIST three (3) major types of loads supplied by this system.

(.75) b.

EXPLAIN how a reliable source of DC power is maintained to these loads.

INCLUDE ALL NORMAL, ALTERNATE & BACKUP POWER SUPPLIES AND ASSOCIATED COMPONENTS.

(1.0) c.

EXPLAIN why DC power is preferred for these types of load (other thatn for imporived reliability).

BE SPECIFIC. THREE RESPONSES REQUIRED FOR FULL CREDIT.

(.75)

Answer:

a.

(1)

DC motor operated valves (2)

DC motor operted pumps (3)

Control power for ECCS (4)

Logic power for ECCS (any 3 @.25 ea) b.

The DC bus normally is supplied by a battery charger (.25) powered from the 430V AC shutdown board (.25)

Alternate power to the charger is from the 480V common board 1 (manual transfer only) (.25)

Backup power is supplied by a (120 cell lead-acid) battery on a float charge (.25) c.

(1)

Provides more constant pull on coils (2)

Absence of hysterisis effects (3)

Absence of oddy current losses

( 25 each)

Reference:

BFNP:

LP 37, L.O. A, B & C I

a 3.13 rnd 6.14 continutd TVA Comment:

,s Part a 3 major types of loads: The objective does state motive power for

-s D.C. p3wered pumps and motor operated valves. The control and logic power for ECCS. The candidates responses could be more specific. The logic and control provided by the D.C. system is supplied to more than ECCS.

Part b Reliability of DC is subjective and all Normal, Alternate and Backup power and associated components. This is objective based and relative straight fortfard. But consider the bold print DC power INCLUDE ALL NORMAL. ALTERNTE AND BACKUP POWER SUPPLIES AND ASSOCIATED COMPONENTS.

Considering D.C. only:

(1) normal battery charger (2) alternate battery charger (3) the battery itself Considering A.C.:

Both the normal and alternate battery chargers (manual transfer between two) have normal AC from 480V shutdown board with manual transfer to alternate AC from 480V common board.

Part c Not objective based, more a plant design consideration than a concern of an oprator.

TVA Resolution:

)

Part a Anser key should be expaned to reflect credit given for responses stating control power and logic power. Control power may be specified by boards ex: 480V shutdown boards, cooling tower switch gear 4Kv shutdown boards.

Logic power may specify systems.

The candidates response should be analyzed and credit givan for valid response.

Part b Candidates should receive credit for a response that addresses the question from the D.C. application. The answer key should be (expanded to reflect a correct response for:

Normal - normal battery cahrger Alternate - alternate battery charger Backup (lead acid) battery l

(

Part c Delete the question or conversely analyze the responses for validity and credit respectively, i

l l

1753Q lO l

I

Question 7.03 Question 4.04 O,

The following parameter changes / annunciators are observed by the reactor eperator:

RBCCW temperature Lower than normal RBCCW Surge Tank HI Level alarm (No other alarms present) a.

WHICH one (1) of the following malfunctions would most likely cause (1.0) these indications:

1.

Raw Cooling Water leah in the RBCCW Heat Exchanger (s).

2.

Reactor Coolant leak into RBCCW via NRHX.

3.

Fuel Pool Cooling System leak from RBCCW.

4.

RBCCW Makeup Valve (fiol valve) leak, 5.

DWEDS Heat Exchanger leak into RBCCW.

b.

LIST three (3) of the conditions /circumstartes that will cause the (1.5) isolation valve to non-essential equipment (HOV-48) to automatically close.

NOTE:

BE SPECIFIC AND INCLUDE SETPOINT VALUES Answer:

a.

1 (1.0)

O\\

b.

1) Low Reactor Water Level <= -114.5 (0.2) and 90.1) DC voltage applied to SD board (s)

(0.2)

2) Drywell Pressure > 2.45 psig (0.2) and (0.1) DU voltage applied to SD board (s)

(0.2)

3) Low discharge header pressure < 57 psig.

(0.5)

Reference:

BFNP: OI 70 LO A, A01-70, LP 171.047 3.8/4.1 3.3/3.4 2.9/3.2 TVA Comment:

(B) OI-70 list the signals as loss of normal AC power in conjunction with an accident signal or 57 psig header pressure. This should be the correct answer.

LP 171-047 List Signals as (1)

Initiation of Unit 1 and 2 480 volt load shed logic.

(2) Low RBCCW supply header pressure (57 psis)

TVA Resolutions (B) Accept answer in "B" above as correct for full credit if only two responses are given.)

1757Q

Question 4.13 (1.00)

Question 7.12 (1.00)

-s LIST two (2) systems that require tagging prior'to entry into the Primary Containment.

INCLUDE in your answer the required status or position of the system.

Answer:

TIP (.25) withdrawn (.25)

Nitrogen Isolation Valves to Primary Containment (.25) closed (.25)

Reference:

BFNP:

BF 14.9 LO A 3.2/3.7 3.2/3.4 comment:

Per BF 14.9 the Tips are to be withdrawn and tagged also the Nitrogen Isolation Valves to Primat-y Containment are to be closed and tagged (76-539,76-541, 76-24, 84-37 and 84-38) as can be seen the Nitre 3en systems tagged are Sy. 76 and Sy. 84.

Sy. 76 valves are the purge and mal ip nitrogen valves.

Sy. 84 is the CAD valves.

O

\\~ /

TVA Resolution:

Accept for full credit any two of the following:

1.

Tips withdrawn and tagged 2.

CAD system isolated and tagged (system 84) 3.

Nitrogen isolated and tagged (system 76) 1754Q i

l i

O

Question 7.16 Question 4.14 O

A single Recircalation Pump trips while operating at 100% poer in automatic

control, s.

STATE the immediate action (s) that should be performed on the RUNNING PUMPL.

b.

EXPLAIN WHY the Running Pump speed must be reduced to <50% of rated speed prior to starting the idle pump.

Answer:

a.

Place Recirculation Subpanel in Manual (.5) and reduce speed to establish 100% loop flow (45,200 gpm) (.5) b.

Prevents excessive Jet Pump vibration.

Reference TVA Comment a.

OI 68 does say place recirculation subpanel in manual and reduce speed to establish 100% loop flow; however, the same thing could be done with O

pump in auto using the master controller.

The purpose is to reduce flow to within required limits.

The method is not fixed as long as actions taken result in 100% loop flow.

TVA Resolution Revise answer key to only require reduction to 100% loop flow for full credit.

Re-assign point value 75% pump flow 25% sub-panel manual.

1757Q O

I

Question 8.03 (2.50) 3 O

STATE whether a Radiation Work Permit (RWP) is "REQUIRED" or NOT REQUIRED" for RACH of the s!tnation given below:

a.

An employee will need to work in an area having airborne radioactivity of 15% MPC.

b.

Work will be done in a designated "RADIATION AREA".

c.

Work is to be done in an area with 1500 DPM/100 cm2 loose surface contamination.

d.

A radiological survey inside a Contamination Zone will be performed while standing outside the Zone.

e.

Trash and procetive clothing will be removed from o Contamination Zone while standing outside the Contamination Zone on the stepoff pad.

Answer:

a.

not required b.

not required c.

required d.

not required e,

not required

(.5 each)

O TVA Comment:

Operations does not do surveys to determine how an area will be zoned and operations does not have equipment to determine airborne or contamination areas. This is done by RADCON. The people had to assume that numbers given in Part

'A' and 'C' would require the area be so zoned in order to got correct answer.

TVA Resolution:

Don't ecquire people to know from memory limits for zones that they don't have equipment to check and are not responsible for doing.

1758Q O

Question 8.09 (2.50)

()

Unit 1 Technical Specifications specify for REACTIVITY CONTROL.

"A sufficient number of control rods shall be operable so that the core could be made suberitical in the most reactive condition during the operating cycte i

LIST the three (3) conditions / assumptions which are used to verify thic "Reactivity Margin" (Adequate Shutdown Margin).

Anower:

(L)

Highest worth rod (.25) fully withdrawn (.25)

(2)

Xenon free core (3)

Cold core (68'F)

Reference:

EIH:

U2 TS, 1.0 "SDM" BFNP: U1 TS, 3.3/4.3A, OPL174.728 LO 9 TVA Comment:

The wording of the question can be misleading as to what response is required.

Since question stated "most reactive", it is possible to assume this to mean "cold and xenon free."

TVA Resolution:

Accept as another response for full credit:

Strongest control rod fully withdrawn 2.

All other operable control rod fully inserted 3.

.38% AK/K margin 1758Q O

i Question 8.10 (1.50) f)

STATE the six (6) ITEMS to be recorded in the daily journal when the Reactr-d is declared "critical" during a Reactor startup in accordance with GP 100-1.

Answer:

Time Rod Group Rod Number Rod Notch Period Recirc Loop Temperature

Reference:

BFNP: OPL171.174.724, LO 6 TyA Comment:

Rod group is not listed in GOI 100-1 as one of the items to be recorded wher declare Reactor critical.

TVA Resolution:

Change key to delete ' Rod Group' from answer key and accept (5) five responses for full credit.

O 1758Q o

r'------------

p....

{

e' age 13 BF GOI-100-1

()x AU3 21 1335 Section III. Startup (Continued)

INITIALS / TIME /DATE A.

Criticality (Continued) 199999999999999999999999999999999999999999999999999999999999339ttttttttttttttttt CAUTION DURING A HOT STARTUP FOLLOWING A REACTOR SCRAM AT HIGH POWER THE CONDITIONS OF PEAK XENON WITH NO MODERATOR VOIDS COULD EXIST AT THE TIME OF STARTUP.

UNDER

'fHESS CONDITIONS, EXTREMELY HIGH ROD NOTC11 WORTHS CAN BE ENCOUNTERED.

I tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt 4.

Upon approval of the shift engineer, start control rod withdrawal in

~

accordance with OI-85.

(R)

/ /

NOTE:

Shif t all SRX and IRM recorders to f ast speed prior to criticality and return to slow speed after initial period measurements are calculated.

NOTE: Within the approved control cer: withdrawal sequence, it is possible to have a p9riod less than 60 seconds.

If a period less than 30 seconds is observed, insert rods until suberiticality is observed and contact the

(%

nuclear engineer and shif t er.gineer before pulling any

\\_)

more rods. Periods less than 5 seconds are reportable to the NRC within 24 hoars.

5.

Observe the period meter when pulling rods and govern withdrawal rate'to avoid having a period shorter than 60 seconds.

(R) _

/,_ __

/

NOIg:

Reactor is critical when neutron flux rises on a constant (stable) period without further control rod movement.

6.

When critical, record time, rod position, rod notch, period, and reactor water temperature from recirculation loop A in daily journal.

(R)

_/ /

NOTE: Measure period as follows:

For 101 power rise, multiply time :/ rise by 10.5.

For doubling time, multiply time of rise by 1.445.

For decade rise, divide time of rise by 2.3.

s For direct period measurement whtn on IRMs:

a.

Time 25 to 68 on black scale ranges b.

Time 8 to 22 on red scale ranges

Revision 0005M 1

.s Question 8.12 (2.00)

()

DESCRIBE t he four (4) standards (i.e. symbols / colors) used in marking TEMPORARY ALTERATIONS on plant drawings and WHAT they mean.

Answer:

1.

Green - information deleted (by the TEMPALT) 2.

Red - information added (by the TEMPALT) 3.

Red circle - surrounds area affected (by the TEMPLAT) 4.

TACF # - number assigned to track the TEMPLAT and is placed beside the red circle.

Reference:

BFNP:

PMI-8.1, L.O. F TVA Comment:

PMI 8.1 have teen revised (revision attached) and changed the color requirements or were intended to be changed. The new revision has you circle affected area in yellow in one part, but says place TACF # beside Red circle in another part. The new revision was placed in Required Reading so some people may respond using new colors..

TVA Resolution:

7 Accept for full credit:

Yellow or red for color on area to be circled.

i 1758Q l

l O

3 PMI-8.1 g

TITI.E: TEMPORMtY ALTERATIONS REV 0002 3

C1. ASS : SAFETY REIATED 5.2 (Continued) 1.

(Continued)

Green - information to be deleted by temporary alteration.

Red

- information to be added by temporary alteration.

Yellow-circle the area affected by temporary alteration.

TACTO - to be written beside red circle (the originator is responsible for placing this number on the drawings after the SE has assigned a TACT number).

J.

DNE Draf ting Services is responsible for updatie.g the as-constructed plant drawings affected by Tfr/s. The drawings should be revised and distribu md in accordance with g

Standard Practice BF-2.5.

g k.

In the evant the SE deems it necessary for the temporary alteration to be placed more quickly than the above procedure E

will allow (but the condition is not an emergency), the SE 3

can direct the originator to mark up the SE's office copy and the affected control room (s) copies of the as-constructed drawings.

(The standar6 for marking drawings listed in Paragraph 5.2.3.1 above will be used). When this is done, the STA will verify the accuracy of the drawing changes made by the criginator.

It should be stressed that this is not g

the normal procedure to follow, but when and if it is g

followed, the originator is still responsible for taking a copy of the marked up drawings to DNE Drafting Services for update and distribution in accordance with Standard Practice BT-2.5 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

After installation, the SE's clerk will make two copier,of E

the TACT. One copy will be mailed to the Technical Services g

System Engineering section. 'Ihe other copy will be mailed to Planning and Scheduling.

E I

I I

O I

1.,

ea,e e e, 3.

m1...,

I

3....

TITLE: TEMPORARY ALTERATIONS PMI-. 1 CUSS: SAFETY REMTED REV 0002 i

5.2 (Continued) d g.

On the TACF, under the rection, "Effects, Limitation (s),

I and/or Actions," the originator should briefly describe the effect(s) of the temporary alteration. A detailed explanation is required where the temporary alteration has an I

effect en the system or other systems that may jeopardi:e the safe and continued operation of the plant. Note any limitation and/or action required during the period that the temporary alteration may exist. Explicit information shall I

be noted for situations that may require isnmtdiate operator action.

List any requirements which must be completed prior to removal of temporary alterations such as approval of DCR, i

clearance of nonconforming item, etc.

If a system or component cannot be made operable with the temporary alteration in place, it shall be so stated in this section of the TACT.

h.

On the TACF on the lines Tests That Will Be Performed To Prove Operability After TACT Installation and Tests That Will Be Performed To Prove Operability After TACF Removal, the I

orginator shall list all tests which will be done after installation and after removal of the temporary alteration.

'Ihese tests should be written and performed (a) to assure m

system integrity and (b) to provide for evaluating the Ls' performance of the alteration before system operation.

If the originator believes that testing is not required, he should provide a brief justification of why testing is not I

required.

1.

The originator is responsible for supplying two sets of I

marked up drawings with the TACT. These drawings will be stamped "For Information Only".

These drawings will show the configuration of the affected equipment after installation of the temporary alteration. One set of drawings will be used I

by DNE Drafting Services as a reference for marking up the original drawings. One will remain with the original TACF in the TACT file as a reference copy.

If time permits, the TACT originator should work with the DNE Drafting Services to determine which drawings need to be marked up and included with the TACT file. The Shift Engineer's controlled copy of the as-constructed drawings and the affected unit control room's as-constructed drawings, shall be marked before the system is decla-ed operable. The following standards will be used in marking drawings:

I l'

1.e,,

, age, o, s

-.1 I

ENCLOSURE 4 SIMULATION FACILITY FIDELITY REPORT Facility Licensee:

Tennessee Valley Authority Facility Licensee Docket No.:

50-259, 50-260, and 50-296 Facility Licensee No.:

DPR-33, DPR-52, and DPR-68 Operating Tests administered at:

Browns Ferry Nuclear Plant Operating Tests Given On:

May 2-12, 1988 During the conduct of the simulator portion of the operating tests identified above, the following apparent performance and/or human factors discrepancies were observed:

1.

The CRD system modeling is inaccurate in that cooling water header d/p does not go below 30 psid during normal system operation, while it should indicate approximately 20 psid.

2.

Feedwater system modeling interacts with recirculation pump operation such that a recirculation pump runback proceeds down to approximately 52% flow while the plants' procedural runback specification is approximately 75%

flow.

3.

Plant procedure allows 3 element level control at 10% power and the simulator does not respond adequately at such a low power. This may be the result of a procedural or modeling problem. Candidates appeared unfamiliar with the simulator's response and devoted significant time to investigative efforts during the examination.

4.

The RBCCW system displayed a modeling problem in that when a slow degradation in flow to approximately 90% by the partial closure of the return from the drywell valve was simulated, an inappropriately rapid response (2 to 3 seconds) in the temperature increase was indicated.

5.

The simulator's copy of 01-68, did not have attachment C to which the candidate had been procedurally referenced. This may be a result of the many recent procedural changes. Checks should be made on all recent O!

changes, and more care should be given to ensure proper referencing is maintained when such changes are made.

6.

While at 75% power one MSIV was simulated to close.

The simulator modeling gave 3 seriuus EHC problem which resulted in severe pressure transients of such duration and magnitude as to lead the operator to manually scram the reactor.

L m

F 2

7.

The remote closure of the suction from the suppression pool to the RHR pumps was poorly modeled such as to allow continued pump operation.

8.

The simulator self-initiated three events that were programed for use later in the scenario.

..

ML20154B463

Contents

Text

Dear Mr. Brockman:

( e P

O-

OM

==

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

ML20154B463

Text

Dear Mr. Brockman:

( e P

O-

OM

==

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

Search