ML20044A820

Exam Rept 50-331/OL-90-01 on 900605-06.Exam Results:Senior Reactor Operator Passed Operating & Written Portions of Exam

ML20044A820
Person / Time
Site:	Duane Arnold
Issue date:	07/03/1990
From:	Jordan M, Hironori Peterson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20044A819	List: ML20044A818 ML20044A820
References
50-331-OL-90-01, 50-331-OL-90-1, NUDOCS 9007130199
Download: ML20044A820 (9)

Text

,.

4 U.S. NUCLEAR REGULATORY COINISSION REGION 111 Report No. 50-331/0L-90-01 Docket No. 50-331 License No. DPR-49 Licensee:

lowa Electric Light and Power Company lE Towers P. O. Box 351 Cedar Rapids, IA 52406 Facility Name:

Duane Arnold Energy Center Examination Administered At: Duane Arnold Energy Center Palo, Iowa Examination Conducted: June 5 and 6, 1990 R111 Examiner:

Bob Orton Chief Examiner. lifroriori PeC on '. /hq

_ ud]gS patt Approved '3y:

wN V

] d J,/974 Tiidhael JordaY, Chief

(/Dalfe BWR Section Operations Branch Division of' Reactor Safety Examination Summary Examination administered on June 5 and 6,1990 (Report No. 50-331-OL-90-01)).

Written and Operating Examinations were administered to one Senior Reactor Operator-(SRO) candidate.

Results: The candidate successfully passed the operating and written portions of the examination.

The following is the summary of major strengths and weaknesses noted during the administration of the licensing examination.

'g g $ 7 1 $ $ $ $

S O 1

V

i

8. *. b ? f., tMJ'.

• f d ' " } v ; ' { '

h.

., '..$ Q i }'?

1 I t. ;; ' " ' ' ' ' ~ cif

^*

• i ?

i

'4 d5 4i; m

. ik, h" k..' h t

5

1. w e p. s; ;-u -

o

,.. i i

q q.,,1. y ( /, c p., m....- y; p,

_ s{

~.

pr.%Dm/Me I y j. v'

?

y [.

J....

e',

"EP 4.

i r '^

e.j j da p -c y

4 -

4;. :

q i

A..,o.ew yre yg ; e %,.

.e j

- s v,

<y

.L w

o

.. e u

- m s'

s,

- p.

,d[

yi

.j j

.y g

}

7-o ?,

t 4

.jt, 3

li Ef' q

h, 4*-

.,.gi g s, g,U-g.,,,

y, s

4 p-de 3

_+gy1 a lk t,, o.

,u. 6 s.ete -

a p..

)

m g,: e, 3

m

.c;i

?

i p

~

"O ', K STRENGTHS 1

't

.i Q(@h k, vh[.( x F~"

4

_q y

l id

}.

jiVY i

sw s.

pggy g' tew1P.14t? specific'simulatorc

,o.:

2

-w i u

zee n

v W_..,E 4

,m

- +

2 g r., ':-

,t p.QQ : ' p}d:

.y :...

.\\

q+

f,>

s i

i a

3

.. : ;., n i

y y

n

.OWEA M SSES' '",

-z '. mo l-

1. c

,p W y (t t

5 5

A

a>y L

1,-:

y h y 6 } seiof Anormal Opera _tihgiProcedur Q,-sAOP)j j Ki 11 1h M t

~d5 U Mig U

Q< &y 3, yi j=49 g 9 6. G S 4y

. - iN:

t i

u

=

g,'

hs, v,<

- 4 e r, g,

q4 s

i s

- = i -

<4

<< y 2 4 s,,

c.

i

' ; [t'9 h'

b

.., $ '.y

'-'4i

-it.-

_n gg n - [

t

.q,g an gp

~.

p.19 Ij.w

-o,-

4 4

,r,.

6 su cy

-t

.gt 4

r p.- -.x,.,, -

,q c ep"W>

j f; p r.

i s,

qnwp' r,o t

,;y,.

27-

'r-qsc W

J' 5

3 a, ( n, s'

2 3

I rh

) rA.M.. ;,

f g

L i

g_

7

,4, 6

1],

t

n r.2,L t, i.

' ' +

I*

'i

_ u.

%j.W L

,\\,

3

' ; b

.W.

,y2 y

.q r

h..

m.

':y

,b y

s p;y; m:h p <.

wm w u&

t

+

r o

m a

-M LI.

, ~ 4-2;;

.cLa.

o-1 y;

t c

i

')

A[

i' t

h -w g u.,;d $l t u,L. A * ) _'

gw t

-~N I

.^i '

lh,

itkd - Q

'!!i ci y

e V M,} ao 1,

,.OH "Al

, q N

i P

n ra 4;.

[-

'g r a t-4 r

,3,, :;f.1 s

s i o, Y. -

n c-2 g ep1 q

~f,..

i

,, w w, 3

yh[ip,v

N

,'g.

i r

(

pr

_ JNY

!U 4

E-t 1-MW[f M

!3M n i

o'lp

-01 4

e, 1

q[

't

,j '

t (

3.

Y5 l

] [ '. 4, i,

t'

,4,: ;,

,e

i,, p.

6 i

7 i

s-i.,

.b-1 t

4

. my 4.

e )ec

_.. +

n 1

a m.w

p g r

,"t.

s t.

ii i '

3 i

r d :.

.,?m, W-

, st

,: k t

t 7

I pa i

q--

i t.

6 d; 1.h.. M d,.

J y h.

. :i,,

% :j f h ( t..'p. i j' -

f f,i 1

4 ;3 %a v c tr',

n;-

t 'r s

.p-M f V Mqu-1 1

y 4

i 2,

5 s

a.

u ; 9 M.gg..-

-13 y [. ' ' %p s

3 '

n @

m-2 g

m q ;g p i <

m.3,

~q,

s

,.p.' W

'M?! L i_ b s f?

1 t

z O #( )dh;1lie h i q.

Wp

.:I.t3 o6 -

eh

.=tl

,d y,

2.!

, pt.

g< > ?

a

' g g-s p@y i

+ 1 $U ' { t

' i 'i hS 5

2

(!

-gl:

i n<

4,, t a v I.i s x. i d _.;

m..),h;f b9, t D n c., E. yf U. j -.

G ~i i aw lJ..

s:

i

~

,,u n.

vk ad

-l>

t

@h y.i..l {,9 7..'

S.J.

-h S

a.

.yi, 3r-1,-

- ---j [

• y N gih 7 di Nil

,/

• '. p.

s < - -

Of

^

t i

, + ii -

.C iph f; -

't

.3. e

-tv i

..:kN. N.,

fb i rti dif j M. S

. %gi.;. y,7, e.

r e

3...

i r

,t a e

s c

o

,m l _'

'p; :,n ' - ' 5 - -

r

.li

- ' t i.

i'

/!i

.__u n

t,G,

..,t4

~5:n

,[gh. <

jEtL-.

l<

(ii r

J c M;i - <

d. c.e.

, ti.AW c,

-v i

W n:'W g]'

g i.e y

s t

o, 3'1

a.

a'

,.D.

M 1 '.,,,

<[.

r 4

I 3

,L -,

4p +

p { j n,g k.

5O'.d i i

~{'

fL k

' pQ.~p::

C {'..c,3 r

j i

,w.

,u hhijfii ss

' Q

. 4t

q. c.

y

,[S <

y.,e eq@p. <

M p

iV n.3 4 9 ' ?g..

' i J.

^

7' i

h p, i,d D-'a hi s

' ; q,i

'. N -

i K e? m J g Kr, si '

Q4 g

3 Ks'

-y M

3 4

My

'n iP

's<.pc s

3.

+

s;w n s..

y-u 't

-.1

- je;:.

so j 1

y 3 0 j w x.f ! #

t. gf f ' ' ',

L.,

L T. l f iL g -

4 f y

6 M4 hv a4X, ': w p

. t ;

,a',

t wa

'x ; =iq.A y 3,. <

s 9_ v hcpi,4?lr s

pr g

i i

$4' rg g

• 4 Q T.: M f ; 'tu,

,4; gry %p' 1 c.

4 S m

.:, 7 a

rm[>>

y N r.

. 3--- m t;; -

6, 1

J_ ;I;

. :i II y > -

L-. ;J' _

i y

1 N M,c w{ &

E M.3 ps n y tw '

m fh.h} cy,p(;m' f

- I

..1 3p e d+b,e,, E. t P,,,,

.: t mo

s k )f l

-- y W_J W ^

(-

1 a

% ';i-ic. r a

R f '.y,:. :

?-m

-m-n

-h w,,

,y-i i ?l m,

5

_e-4 1.c y, -

4 y

a, s ~

T. ) gl;;.

?f l t

9,

> D.' ['," -$ d '_

8 1 g

4

,0--

m.

i i Tp p

=

G k~ a 6

E d.N I. O' s s ie n..:.Lt.

i

? t; '

%_m.

..iM

.l. b]j i siiQMQw_,.. waisM?$&

b..

' -(

y

lc: ?

.i l

REPORT DETAILS-c

-1.

Examiners.

~

I

'+*H; Peterson, Chief Examiner, NRC.Rlli f

B; Orton, Battelle Pacific Northwest Laboratories (PNL)

.2.-

Persons Contucted

.i f

Facility Representatives (1

F

• R. Hannen, PlantiSuperintendent - Nuclear a

b*

4*S. Swails, Training Superintendent 1

• D' Fowler, Operations shif t Supervisor.

i e

{,

+*F. Van Etten,: Training Operations Supervisor.-

NRC Representatives-F h

• M.1 E.' Parker, Senior Resident Inssector p

+*H.' E. Bielby Sr., Examiner, NRC, legion 111 nt

+*D.10ueno, Summer. Intern, NRC Region Ill

)t F

+ Denotes those present at the training Staff l pre-exit meeting on June 8

'l

~

p 1990.

j q

e o

• Denotes those present at'the Management. exit' meeting on June 8, 1990.'

L ummary of Results",

j i

l 3.

S Y

WRITTEN'.

OPERATING OVERALL PASS / FAIL PASS / Fall PASS / FAIL:

y y

ii

".SROJ 1/0 1/0 1/0 4.

General Observations

[

g-

<The following observations were made by the examiners while administering; i; 5 g

the licensing. examination::

t s'

7!

Plant Housekeeping was very good, d

- The new ' plant specific simulator was initially: utilized for the j

[f first NRC. examination and. it performed adequately.

1 1

Security, Radiation Protection and Operations personnel were cooperative in assuring that there were no unnecessary delays f

associated with badging, dosimetry and accessing the station.

F-l Throughout the operating test, +he Candidate, Training and Operation Personnel' all acted courteously and professionally.

[

t v

-t t

3 1,

fR s+

4 Ji.

'e i

U ii

~

e S'

-Examination Review l

q d

.The written examination was reviewed with personnel from the training b

department prior to-its administration.: The simulator scenarios were i

< reviewed and verified with personnel f rom-the Duane Arnold Sinclator n

Training Organization. All licensee individuals involved with the review-of the examination materials signed security agreements to ensure that there was no compromise of the examination.

The pre-exam review'of the written examination'with the licensee was r.,

performed during the week of May 21. 1990. All facility _ comments were:

i resolved prior to the administration of the' written examination..

L following the e:tamination, the licensee submitted four (4)=commentsLon p

the as administered written exam. These post-exam comments identified-i minor answer key errors. The NRC resolution of these comments are

[

enclosed in this. report.

5 6.

Exit Meeting n

\\

A pre-exit meeting was conducted with the Licensee's Training Department, s"

on June 8,1990.

A' formal management exit meeting was also held at the; c

Duane Arnold Energy Center on June 8, 1990. The Licensee representatives ~

j that attended the meetings are listed in section 2 of this report.

L The.following items were discussed during the exit meetings;

' i L

e a.

The observations made by the examination.during the administration-3 i

oftheexam.-(SeeSection4)

')

L 1

-b..

Licensee's post-examination comments and subsequent NRC resolution' of these comments.

(SeeEnclosure2) u.

The results of the examination were not presented at the exit meeting.,

w

4 l

i i

FACILITY' COMMENTS AND NRC I

~RI50LUTION OF COPrlENTS l

L

- NRC response to facility post examination comments on the SRO written examination administered on June 5 1990.

j QUESTION: 016(1.00) o WHICHONE(1)LoftheifollowingisNOT'oneoftheassumptionsusedinihe x

design of the negative reactivity added by the Standby Liquid Contro1LSystem?,

7 l

.(1.0 F

i a.

Overcome the' reactivity added by void collapsing j

e 1

b.-

Overcome the reactivity added by the moderator going from hot to

. cold conditions i

h 1

R c.

Overcome the reactivity added by Samarium decay d.

Over:ome the reactivity added by the reduced neutron leakage at cold.

~

L, shutdown conditions t

S LANSWER:

016 (1.00)-

j o

.a.

[+1.00)-

1

REFERENCE:

F 1.

.DAEC Lesson Plan C-4,-SBLC, pg 4 and 17 Learning Objecti've 4 2.

21100K503(3.2/3.5)

.j 211000K503

..(KA's) r

-1:

a FACILITY' COMMENTS:

j r

-Answer.C is correct.

Void collapsing is a design consideration,'while l

Samarium is not, l

FACILITY JUSTIFICATION:-

DAEC System Description, C-4. SBLC, page 3.

!NRC RESOLUTION: Coment accepted and incorporated into the answer key.

"I

.. QUESTION: 067(1.00)'

h F

GIVEN that:-

3 k

Load selector a 600MWe Load limit = 10 t

a t

i t.I y

i

+

.p L:

t, n

c

o Max. Conb.. limit = 110%

Throttle Pres. = 947 psig

'A' Pressure Reg. = 920 psig The ' A' EHC Pressure Regulator setpoint f ails downscale. Use Attachments to-answer the following question. WHICH ONE (1) of the following is the Bypass Valve demand signal of the EHC logic system to the following scenario:

(SeeAttachmentsNo.2,3EHCLOGICCONTROL)

(1.0)

~

a.

0%

b.

5%

c.

,10%

d.

15%

ANSWER: 067 (1.00) b.

[+1.00]

REFERENCE:

1.

DAEC SYS DESC D-11 FIG 8.

2.

295005a105(3.6/3.6).

FACILITY COMMENTS:

It would be impossible to ascertain the position of the bypass valves in this dynamic situation. The steady state to steady state conditions would lead to 0%makingLanswer(a) correct.

FACILITY' JUSTIFICATION:

DAEC System Description D-11, Fig 8, Fig 9.

NRC RESOLUTION:

Comment accepted and incorporated into the answer key.

2 4

er~j.,

4 t wc;j s 1

.se

+.

y;.

p > & y-.

v.4e t -

f e s"i ?

L ATTACHMENT 3 l

.Y QUESTION: 069(1.00)'

l 4

The following are four separate Radiological Environmental Monitorir.g reports

.i average over a calendar quarter. Using attachment No. 8 (Tech Specs 3.16),

$, J < WHICH ONE (1) of the following require a special Report to the NRC within:

i 7

,. y 30 days?-

q t. T in 250 t

A a.

Iron (59)inwater=10.PCiper. liter,' Cobalt ~(58)inwatera.

j pCi per liter, tanthanum (140) in Milk = 15. pCi per liter

m..,

fe b.

Cesium.(137)inFish1000pCiperliter, Manganese (54)'inwater=

,.. w

100 PCI per liter, lodine 131Lin Food' products 50 pCi per kilogram.-

i AM l

,; ?

c.

-Barium (140) in Milk 150'pCi per liter, lodine-(131) in Air =.3 pCi-per cubic meter

~

j F(.

4 d.

~ Cesium (134)inair3pCipercubicmeter,' Cobalt.(60)-in. Fish'=150 t

4 pCi per kilogram, manganese (54) in water 25 pCi per. liter a

1 II ANSWER:- 069'.(1.00)

[

L

3.,

X-a.

[+ 1. 00].-

{

REFERENCE:

~,

j

~

1;;

DAEC TECH SPECS 3.16 y

2.

' 295017G002(3.1/4.7)

J A>

2950170002

..(KA's)

N F^blLITYCOMMENTS: Answer b is correct.- - Performing the calculation of=

Table 3.16-3, la) results in a value less than 1.0, whereas (b) results'in a value of'1.1..

U 1

%J FACILITY' JUSTIFICATION:

e<

.PAEC TECH SPECS 3.16 j

4 NRC RESOLUTION:

4 1

W Comment' accepted and incorporated into the answer key, a

w

).'

t 4.

E j

s I

U 3

1 q

iJh-

+

+

j ATTACHMENT 4 QUESTION: 072(1.00)

During a loss of Coolant Accident with high containment pressure the reactor operator reconnends that he open the Containment Spray valves MO 1902, INBOARD DRYWELL SPRAY and MO 1903, OUTBOARD DRYWELL SPRAY. WHICHONE(1)ofthe following condition must be met prior to opening these valves? (1.0) a.

DW pressure greater than 2 psig.

b.

Reactor vessel level is 30 inches, c.

Containment Spray Valve switch in automatic.

d.

LPCI initiation signal is reset.

Answer: 072 (1.00) c.

[+1.00]

REFERENCE:

1.

DAEC System Description C-1, pg. 21 and fig 17 2,

295024K215(3.8/3.9)

FACILITY-COMMENTS:

(c) is not correct. The switc5 is called ENABLE CONTAINMEf4T SPRAY VALVE.

It does not have a AUTO position.

(Positionsare Manual, RESET,or" NORMAL").

(a) is most correct answe, since 2 psig signal is a requirement for Containment Spray.

QC_lLITYJUSTIFICATION:

DAEC System Description C-1, pg. 21 NRC RESOLUTION:

Connent accepted and incorporated into the answer key.

1 I

4 pp,Q4

• P '

?-

J a

m p,,s mv;c y;^

e ti,:

^ '.;

$[e x > Gu 1

SIMULATION FACILITY REPORT e~ q ;;L y gy i

3 '; a.

r Facility Licensee: DuaneArnoldEnergyCenter(DAEC) o i,

-J Facility Licensee Docket No. 50-331 i

yf K i

ff

Operating' Tests Administered At: DAEC J

6; go?

~

Palo, Iowa-

.pW r

xl During the conduct of the. simulator portion of the operating tests..the.-

@ M following items were observed (ifinone, so state):

w F ',

1 TEM DESCRIPTION 4

n' p'

i

'LPRM.

During the simulator scenarioL y

malfunction of an LPRM to fail Y

'downscale, the downscale P3 annunciator, failed to work.-

uy P*

JTorus Pressure Indication During.the simulator' scenario t.

casualty of a steam Leak into the' Torus, the initiation of the Torus!

l k,

Spray-was ordered with the Torus-l 1

pressure indicating ( 2 psig on-J;

'i one meter. This pressure p::

indicator was not calibrated and j

W, was-indicating =approximately O!,

5 ps.ig-lower than the 'other Torus 1

pressure meter.

1

E

[-j b

.. m 3;

(4 '

i

}!,,,

l

dit, f

):'

f4 y

O...

lP.E I

4 W&, ',

un r

m3 o

4 i

[f i

'y

+

i s

n,,

?

J i

<i i

.r 5

4

'