Text

Forwards Summary of Enforcement Conference on 900712 Re Unit 1 Inadvertent Diversion of Higher Pressure Reactor Coolant Water to Refueling Water Storage Tank on 900611,per Insp Repts 50-413/90-17 & 50-414/90-17.Handouts Also Encl
	ML20055H410
Person / Time
Site:	Catawba
Issue date:	07/18/1990
From:	Reyes L; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H; DUKE POWER CO.
References
	NUDOCS 9007260169
	Download: ML20055H410 (23)
	v • d • e

. . . . . . . . . . . . . . . _ . . . . .

. . . . . . . . . . . . . . .

. . . . . .

... . . . . . . . . . _ . . . . . .

. . . . . . . . . ~ . . . . . . . . . .

.. :

..

, jl

...

.

. , .

.

Al.18-1990

. - .

1

lj

Docket Nos.- 50-413, 50-414--

l

License-Nos.'NPF-35, NPF-52

!l

!

'

Duke Power Company

1

-

ATTN: Mr. H. B. Tucker, Vice President

-l

Nuclear Production Department .

P. O. Box 1007

'

i

Charlotte, NC- 28201-1007_.

1

Gentlemen:

E

SUBJECT:

ENFORCEMENT CONFERENCE SUMMARY-

!

(NRC INSPECTION REPORT NOS. 50-413/90-17AND50-414/90-17)1

j

(

This letter refers to the Enforcement- Conference held at our request on-

3

July.12, 1990.

This meeting concerned. activities authorized for your Catawba :

1

facility.

The issues discussed at this conference related to the Unit 1 event

!.

on June-11, 1990, involving inadvertent diversion of higher: pressure reactor -

coolant water to the Refueling Water Storage Tank.- A list of attendees ~.-'a-

,

suninary, and a - copy of your handouts are enclosed. . We are continuing- our-

i

review of these issues to determine the appropriate enforcementLaction..

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,

Title 10. Code of Federal Regulations, a copy of this letter and its enclosures

_

will be placed in the NRC Public Document Room.

Should you have any questions concerning this matter, please' contact us.

]

.

'

Sincerely,

j

JS]

l

Luis A. Reyes . Director

-

,

Division of' Reactor Projects

Enclosures:

1 '. List of Attendees

J

2.

Enforcement Conference' Summary

3.

Enforcement. Conference Handouts

-cc w/encls:

l

.T. B. Owen, Station Manager

Catawba Nuclear Station

P. O. Box 256

4

Clover,.SC 29710

(cc w/encls cont'd - see page 2)

1

9007260169 90071g

G

{DR

ADOCK 05000413

PDC

.-

.

-

_ ..

..

.

.- - _ _ _

- _ 'W

S

_

. . ,

,.

.,m

- '

A la tw-

'

Duke Power Company

2

. cc w/encls:' .(Cont' inued)

A. V. Carr, Esq.

Duke Power Company

P..O. Box 1007

Charlotte, NC 28201-1007

J. Michael McGarry, III,:Esq.

Bishop, Cook, Purcell and Reynolds

1400 L Street, NW .

Washington, D.

C._

20005

L)Q

North Carolina MPA-1

3100'Smoketree Ct., Suite 600

P. O. Box 29513-

'

Raleigh 'NC 27626-0513

I

Heyward G. Shealy, Chief

Bureau of Radiological Health

a

South Carolina' Department of Health

'

and Environmental Control

!

2600 Bull Street.

Columbia, SC 29201

l

Richard P. Wilson Esq.

Assistant-Attorney General-

S. C. Attorney Ge'neral's Office-

'

P. O. Box 11549

y

):

Columbia, SC: 29211

.

Michael.Hirsch

Federal Emergency Management Agency

i

500 C Street, SW, Room 840-

Washington. D. C.

20472-

North Carolina Electric-

Membership Corporation

i

3400 Sumner Boulevard

1

P. O. Box 27306

Raleigh, NC27611

-

Karen E. Long

Assistant Attorney General

i

N. C. Department of-Justice

'

P. 0. Box 629

Raleigh, NC 27602

Saluda River. Electric-

Cooperative, Inc.

P. O. Box 929

.Laurens, SC 29360

(cc w/encls cont'd - see page 3)

l

,

.

.7

-

<

.-

,

'

-

, , . .

Duke _Fower Company

3

-M 18 W

cc w/encis:

(Continued)

S. S..Kilborn, Area Manager

j

Mid-South Area ESSD Projects-

-Westinghouse Electric Corporation

MNC West Tower

. Bay 239'

P. O. Box 335

.

Pittsburg, PA .15230

County Manager of York County-

'

York County Courthouse

->

York,'SC 29745

~ Piedmont Municipal 1 Power Agency

i

121 Village-Drive

{

'Greer, SC -29651

'

State of' South Carolina

.

I

bec w/encls.

K. N. Jabbour, NRR

'

B. R. Bonser, RII

M. B. Shymlock, RII

.A.-R. Herdt, RII

Document Control Desk

NRC Resident Inspector

U.S. Nuclear Regulatory Commission-

.t

Route 2, Box 179-N

'

York..SC 29745

-

J. Lieberman

i

l

i

L

-!

!

,

.

RII

GKelly

.

4I

&

(AHerdt

J nki s

7//7/90

7/p /90

7/g /90

.

_ _ _ _ _ _ - _ _ _

_

..

.

.-

'

,-

..-

...

?

-

ENCLOSURE 1

,

t

LIST OF ATTENDEES

t

!

U.S. Nuclear Regulatory Commission

B. Breslau, Reactor Engineer

. .

L. A. Reyes, Director, Division of Reactor Projects

,

E. W. Merschoff,~ Deputy Director, Division of Reactor Safety

.

_

'

-

G. R. Jenkins, Director, Enforcement and Investigation Coordination ~ Staff

A.'R. Herdt,' Branch Chief, Division of. Reactor Projects

P. J. .Kellogg, Section Chief, DivisionLof Reactorf Safety

K. N. Jabbour, Project Manager 0ffice of Nuclear Reactor Regulation

W..T. Orders, Senior. Resident Inspector, Catawba

E. M. Kelly, Acting Section " Chief, Division uof Reactor Projects

D. B. Matthews, Assistant Director Projects .NRR

Duke Power Company

T. B. Owen, Station Manager, Catawba

a

R. N. Casler,- Operations Superintendent,- Catawba

1

A. S. Bhatnager,-Performance Engineer,. Catawba

r

,

G. B. Swindlehurst, Design Engineer, Duke Power Company

'

,

'

M. S. Tuckman, General Manager,. Duke Power Company

~

A. Crisp, Reactor Operator, Duke Power Company '

14. Ravan, Shift Supervisor, Duke Potter Company

i

,

P. R. Pappas, North Carolina Electric Membership Corporation'

.

'-

1

r

,

.

V

i

'l

.

,.

_

. . _ ,

.

__

-*

.-

.

~

. . .

-)

J

-ENCLOSlfRE 2

l

ENFORCEMENT CONFERENCE SUMMARY

j

On-July 12, 1990, representatives from Duke Power Company (DPC) met with the

,

NRC in the Region II office in Atlanta, Georgia to discuss issues concerning

i

the' June 11,'1990, residual; heat removal system design ands test ~ evolution,.

1

operator response to the' event, root -cause, corrective action and safety

R

-

significance of the event.

,

Following opening remarks by Luis Reyes, Director, Division of Reactor Projects

(DRP)

DPC gave a presentation,(Enclosure 3) on the. issues.- T.; B. Owen, the

Catawba Station Manager. . introduced DPC'sL presentations.- . The presentation

-

covered the sequence of events, system description, operator response, root

j

-

cause and contributing causes, corrective actions, and the safety significance.-

1

~

A. summary and concluding remarks were made by T

B.: 0 wen and M. S.:Tuckman.

The NRC closed the meeting by stating that. DPC's presentations had: served to

enhance Region II's understanding of the issues and DPC's corrective actions,

i

+

1

l

1

l.

4

-

'

.

p

-

,

,.

&

-

- , , . - ,

e-.

m

- 6 -; d , - .

.,

ENCLOSURE-3-

, .; , __; _

.-

DUKE POWER COMPANY

,

CATAWBA NUCLEAR STATION.

1

i

ENFORCEMENTICONFERENCE

]

.

!

JULY 12,1990

,

.

,

I

1

-

.

I

$

s.

.

e

~*

e

,a

AGENDA

!

INTRODUCTION

TONY OWEN

SEQUENCE OF EVENTS

IRICH CASLER

4

ROOT CAUSE

TONY OWEN

1

CORRECTIVE ACTIONS

TONY OWEN

\\

SAFETY EVALUATION

opggg;SWINDLEMURST

SUMMARY

TONY OWEN

'

1

l\\

s

i

,

I

_

-

--

--. - _. -

._.-

. .

.

.

..

,

~

-

.. . .

.

,

PLANT STATUS PRIOR TO EVENT

,

'

MODE:5

-

<

0.

NC PRESSURE l335 PSIG

~

,

1

t

O

NC TEMPERATURE 195' DEGREES F

t

'

a

TWO NC PUMPS RUNNING

.

%

RHR . ALIGNMENT

e,'

O

'A' TRAIN IN SERVICE

iO

'B' TRAIN RECIRC:TO FWST

.

NO:OTHER ACTIVITIES IN PROGRESS

1

h

l

'

L

. .

- . . . . - ,

. -

. . -

.-.._._.-_.,.-..........,J,-,_.-.-...:-.,_,_.-

'

!

.,34,

-? ,.;. . ,

...

-I

.

'

-

.-

'

i

'

e

.

,

[8BEftfELHIGN

__-_

,

l

HDFREG

E" 3IN

'

3r

IAfsK '

I

M.m&

.

O

'

FW27A

I

AQ

-l

' '

l

."

~

,

1

}$""'"

1

,

. NI

l

'

l.

-fh2A

i

'

sele 73A

O

L OOP C ,y

. .

,,

CoeI) EG

O-

peo

800e9

.seps;

g

)

H.

.,x -4x:-

%

____

L

cl)t ,$ u * N -

'*

M

-

'^

1 m

'

i

.d 6U

V

>

8eD32A

'

..

1

eeD24A

90033'

-,

i

-

FWSI M

L

,

NV135

NWlt.D.HeFOR'

CLEAfe te DugesesG

.

HEFL8ELageG

fw

-

m

..

4

.

j

.

,

i

COLD LEG

ND

.

g

~

Y

1x -cac

W;

toora

T

en

seass

- senes

,

K

- '

CotD tEGq se7en .

-l

se

!

i

~

-<: w ,,A

.

l

eeD-

a

i

l

t (Mr C

-s

-

eusr i tu

.jg

,

--

.

-

,

.

. ,

. _.

-. . , -

-.

. . . - , .

<

.

,

.

. . . .

.

',

J

SEQUENCE OF EVENTSi

1

'

'B' TRAIN:RHR CHECK VALVE TEST COMPLETION:

.

O

RNRIPUMP OFF

L

0

FWST ISOLATED FROM;'B' TRAIN RHRi

,

TWO OPERf TORS INSTRUCTED TO CLOSE ND-33

,

CONTROL ROOMIOPERATOR BECAME CONFUSED

.

O

DID NOT WAIT FOR THE ND-33 PROCEDURE:

STEP TO BE; COMPLETED:

.

'

O

OPENED 'B' TRAIN RHR:ISOLATIONS TO

NC SYSTEM

O

bPENED ND-32A

.

. ..-,.-

- ,. ,.-,,--,

...

,__L-

. - -

.,__.._-._..-_m.,._

. . . , ._i,,--- .. . . , . . .- ., . . . ~ .

-~.m..,-.v.,..-.,~,,%,.-.

.

1

-

.

'

.

'

.

. -

.

.-

N e.

.

Gw

u

na

tou e

e

Uss o

vo

e

a

eat

a.s a

ee

s

i

mv

a

r

a

[w

W

.

A

2

nh

,o

,.

.

e

,,

>.

e

g ,, r

'

p

,.

ias

,,3

-

g

,

w

<

o

='

a

ra

We

x

-

r

b

b

'

fru

m

-

b

-

.

1 J

AA

M

.

s

.

V

i

.

%e

-

i-

sG

s

eO

o

m

c

r

G

n0

QF

6

O0'

s

8

0

F0 G

l

9

0

aU0

1

HDL

.FE

D. U U

CF

L

s

(Be

.

ec

Am

o

VE

a

sO

8L

cs

'

e

8

'

_

C

n

-

A

o. s

'

e

_

4

5

2

.

_

O n e. 'ox"

D

'

3

v

" .m v

.

'

_

s

N -

f

-

_.

a

_

4

""

-

?

_

9e

A

sl

2

~

x6

_

'

3

-

D

_

,

8

-

.

-

0

_

.

.-

3@

m

_

a

3

-

0

I1

.

-

09

.

I 1

'g

l

i i ' .-

1

l

-

^

3

n

,

7

o

_

8

T

i

_

N

S

.

s

W

e

W

q

s

F

o ' u.

ca

a

c

aE

wa $>

'r:

t

x o 5

en

t

a oo

t o

f>

t ot

a to

c

_ _

.

_ _

,

.

,

i.

'

.

. . .

.

l

s

I

\\

TRANSFERRED 5,000 GALS FROM NC TO FWST

i

!

l

O

MAJORITY WAS TRANSFERRED IN LESS

THAN 30 SECONDS

i

O

NC' PRESS 80 PSIG

i

3

-

i

O

NC TEMP 204 DEGREES F

c

b

. .

O

PRESSURIZER LEVEL 45% TO 0%

'

~

O

MANUALLY TRIPPED NC PUMPS AT

200 # NO.1 SEAL DIP

.

4

L

'

i

!

)

>

.

-

. . - . . . . - _ _ _ . _ _ _ , . _ _ _ _ _ . _ . . _ _ _ _ . . . . _ _ . _ _ . .

. .

.

. .

.

. .

.

. . .

-_ . . _ ___

l-

..

.

,

..

*

.

l

I

r

!

,

,

l

!

OPERATOR IMMEDIATELY CLOSED VALVES AND

1

STABILIZED PLANT

l

'

i

1

l

O

OPERATOR STATIONED AT RVLIS

>

i

,

4

l

O

MONITORED FWST I OFFSITE RELEASE

i

'

<

,

?

l

O

MONITORED RHR PUMP 1A PERFORMANCE

'l

l

t

O

RESTORED PRESSURIZER LEVEL WITHIN

l

15 MINUTES

1

i

O

RETURNED THE UNIT TU MODE 5 WITHIN

'

15 MINUTES

'

,

8

e

.

,

I

!

$

- - . . . , _ , _ , , , , . . , . . . . _ _ _ , . . , , - , . . - - . . _ _ . _ - . . - . . . , . _ . _ . . - , . . . . , _ . . . - _ . . _ - - , . _ . . . _ _ _ _ . . . _ . . . . _ . _ . - . _ . . _ . , - . _ , . _ _ _ . .

- _ _ . . _ _ - , _ _ _ _ _ _

- .

- - _ _ _ _ _ _ _ - - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ -

!

-

.

?,

g

.

. .

.

'

i

l

.

i

ROOT CAUSE

HUMAN ERROR

1

i

!

'

Cr

OPERATOR BECAME CONFUSED.

.

!

r

s

O

PROCEEDED WITH PROCEDURE

!

,

.

h

e

l

'

\\

.

!

'

.

$

i

!

i

I

l

\\

.

wga3-w-p----e-mees-

w---,sr.

,y-.,,,.-gg-a

eye.%

,.e-iy

,

,...meeg.-g-+.,%9.,g-9.yg

,,s.,.

yy,p-e--.w..c,,-engwy9

ppm 9,9 9 py =.wy--

---ww.--w+=w9.y4-+3.-*

I

~'

'

.

. .

,

CORRECTIVE ACTIONS

ON-GOING CORRECTIVE ACTIONS -

HUMAN PERFORMANCE

(WASHINGTON PRESENTATION)

<

ADDITIONAL CORRECTIVE ACTIONS -

HUMAN PERFORMANCE

flNITIATED BY THIS EVENT)

EQUIPMENT EVALUATION

- _ _ - _ _ _ _ - _ - _ - _ - _ _ ,

i

'

.

'

-

,.

.

,

ON-GOING CORRECTIVE ACTIONS -

HUMAN PERFORMANCE

(WASHINGTON PRESENTATION)

l

1

l

i

l

!

l-

O

MANAGEMENT ACTIONS

'

.

O

PROCEDURES

\\

.

1

,

O

COMMUNICATIONS

O

CONFIGURATION CONTROL

i

?

,

1

e

'

t

.

J

l

>

--. .-

.

--.._--,.....,,%--.

_,..,,_.,...,..,,,,,,._,,,,,,_.,._,,.-,.,,,,m,,,,,,,,_.,..yyu,ww-,,,-,-.

. , , + - ,

---.r...,~.,,...-,.,

-

.

. . .

-

EFFECTS OF ON-GOING CORRECTIVE ACTIONS

TAILGATE MEETING

ACTIVITY CONTROLLED BY PROCEDURE -

NOT COMPLEX

.

NO OTHER ACTIVITIES IN PROGRESS

SUCCESSFUL COMPLETION OF TEST ON

'A' TRAIN

OPERATOR TESTIMONIAL

1

i

_ _ _ _ _

,

.

<

.

. . .

ADDITIONAL CORRECTIVE ACTIONS

i

1

i

ADDITIONAL TRAINING FOR SHIFT

J

SUPERVISORS

i

4

i

,

'

l

EXERCISE BREAK

i

'

t

i

V

l

PROCEDURES

-

OPERATOR TESTIMONIAL

<

1

'

,

l

i

e

l

. .

. . .

.

_ _ _ _ _ _ . . _ _ _ . . . . . _ _ . . _ _ _ . . . _ . . _ _ . . . . . _ . . _ _ _ _ ,

l

.

(

. . .

.

t

I

'

I

'

l

SUBSEQUENT ACTIONS

j

NRC INVOLVEMENT - JUNE 11TH TO 14TH

l

.

1

EXTENSIVE REVIEWS I ANALYSES COMPLETED

i

4

l

'

O

PUMPS

i

'!

l

!

O

SYSTEMS

f

(

.

1

O

SUPPORTS

O

INSTRUMENTS

'

O

PROCEDURES

-

.

'

O

GAS RELEASE

I

a

REGION il I NRR BRIEFED -

JUNE 14TH

l

!

)

!

,....

- - . .

....- ,,..-,. _ -. ... - ,. _ ,...... _ .- ,_. --, ,_ .. .

_ , . . - , . ~ . . . . . . . - - . , , . . . . ,

u

.

,

.,

, ,.

.

SAFETY SIGNIFICANCE EVALUATION

REACTOR COOLANT DIVERSION TO FWST

SCENARIO

INITIAL CONDITIONS:

0

- 195 F

- 355 PSIG

- DECAY HEAT 7 MW

- NORMAL PRESSURIZER LEVEL

- TWO REACTOR COOLANT PUMPS ON

- STEAM GENER ATORS OPERABLE

l

- RHR TRAIN A IN SERVICE

- RHR TRAIN B EXITING TEST

(PUMP OFF, SUCTION ISOLATED, DISCHARGE ALIGNED TO

FWST THROUGH VALVE ND-33)

- LOCAL CLOSURE OF VALVE ND-33 IN PROGRESS

INITIATING EVENTS:

- RHR TRAIN B SUCTION VALVES FROM RCS OPENED (ND36B k

4

ND37A): DIVERSION TO FWST FROM TRAIN. B

- RHR TRAIN A X-CONNECT VALVE (ND32A) TO TRAIN B

DISCHARGE OPENED: PUMPED DIVERSION TO FWST FROM

!

TRAIN A

-

,

t

.

,

-

t

i

,

'

.

,.

OPERATOR ACTIONS REQUIRED FOR MITIGATION AND RECOVERY

I

.

1)

ISOLATE RCS LEAK PATHS

,

TRAIN A:

j

e STOP RHR PUMP AND ISOLATE SUCTION FROM RCS

QR

!

o -lSOLATE DISCHARGE TO FWST OR LEAK

,

" - CLOSE ND 32A REMOTELY

- ND33 CLOSURE ALREADY. UNDERWAY

,

- ISOLATION VIA OTHER REMOTE VALVES

i

>

,

TRAIN B:

" e ISOLATE SUCTION- FROM RCS

,

O.,R

o ISOLATE DISCHARGE TO FWST OR LEAK

- CLOSE ND65 REMOTELY

- ND33 CLOSURE ALREADY UNDERWAY

- REMOTE ISOLATION VIA OTHER VALVES

2)

RESTORE RCS INVENTORY

e NV (CHARGINGISI PUMP) FROM FWST-

"

e ND (RHR PUMP) FROM FWST -

e COLD LEG' ACCUMULATORS - LOCAL RESTORATION TO

SERVICE

e NI (SI PUMP) - LOCAL RESTORATION TO SERVICE

3)

ESTABLISH A HEAT SINK

-

e RESTORE AN ND' TRAIN IN RHR MODE

"

^

e STEAM STEAM GENERATORS

4)

STABILIZE UNIT

.-

. . .

.-.

.

_ _ _ _ . _ . _ . . . _ . _ . .

. . . _ . . _ _ . _ _ _ _

_ _ _ _

._ ._ ._ __

.

_ . . . _ _ _

'

<

j

i

-

. , . -

..

!

l

i

ACTIONS TAKEN (**'>

)

1) CLOSE ND32A - 30 SECONDS

ISOLATE RHR TRAIN B SUCTION - 5 MINUTES -

2) ALIGNED NV PUMP TO FWST - 6 MINUTES

3) RESTORE ND TRAIN A RHR MODE - 30 SECONDS

I

4) UNIT . ABILIZED - 15 MINUTES

_

1

'

ALSO: RCPs TRIPPED ON LOW #1 SEAL

DELTA-P AND HIGH VIBRATION

h

!

?

v

9

!

o

--

-

.

--

..

.

-

. .

- . . - .-

'

~,

3

.

,. .*

.

CONCLUSIONS

e

OPERATOR ACTION WAS REQUIRED TO CORRECT A SITUATION

INITIATED BY OPERATOR ERROR

,

o

OPERATOR RESPONSE WAS EXCELLENT

- OPTIMUM ACTIONS TAKEN

- RAPID RESPONSE

- UNIT WAS QUICKLY STABILIZED.

i

,

e

CONSEQUENCES LIMITED TO A LOSS OF APPROXIMATED 5,000 GAL OF

PRIMARY COOLANT. THE PRESSURIZER DID NOT EMPTY.

e

REVIEW OF POSFIBLE DAMAGE TO EQUIPMENT CONFIRMED THAT NONE ,

OCCURRED.

I

.

- PRESSUR12ER HEATUP AND COOLDOWN LIMITS WERE EXCEEDED.

.

VENDOR EVALUATION CONCLUDED NO OPERABILITY CONCERN

'

EXISTED.

- RCPs WERE NOT DAMAGED

- ND PUMP 'A' NOT DAMAGED DUE TO BRIEF HIGH FLOW SITUATION

- ND HEAT EXCHANGER 'A' NOT DAMAGED

- NO DA?,iAGE TO PIPING AND SUPPORTS

r

'

'L RESULTING DOSE RATE (0.406 MREMlYR) IS 0.08% OF THE TECH

j

e

,.

SPEC LIMITS

'

e

BASED ON:

- MODE 5 INITIAL CONDITIONS

,

!

- LIMITED LOSS OF RCS INVENTORY

- NO EQUIPMENT DA'MGE

I

- VERY LOW DOSE CONSEQUENCE

,

- AVAILABILITY OF REDUNDANT MEANS OF MITIGATING AND

RECOVERING FROM THE EVENT

THE EVENT IS CONSIDERED TO BE LOW IN SAFETY SIGNIFICANCE

I

L

...

.

-

.

--

ML20055H410

Text

Navigation menu

Search