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

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Al.18-1990

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

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

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Duke Power Company 1

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

Nuclear Production Department . ;

P. O. Box 1007

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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-

July.12, 1990. This meeting concerned. activities authorized for your Catawba :

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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:

.T. B. Owen, Station Manager

l

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 .-

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Duke Power Company 2 A la tw-

. 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

North Carolina MPA-1

3100'Smoketree Ct., Suite 600

P. O. Box 29513-

L)Q

'

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- '

y

P. O. Box 11549

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

3400 Sumner Boulevard i

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

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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 l

MNC West Tower . Bay 239'

P. O. Box 335 .

Pittsburg, PA .15230 i

' '1

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 .

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bec w/encls.

K. N. Jabbour, NRR ;

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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

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York..SC 29745

-

J. Lieberman

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RII RII RII

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7//7/90 7/p /90 7/g /90 .

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ENCLOSURE 1 ,

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LIST OF ATTENDEES

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U.S. Nuclear Regulatory Commission

B. Breslau, Reactor Engineer . .

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

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

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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,.

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Catawba ,

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

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

A. Crisp, Reactor Operator, Duke Power Company '

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14. Ravan, Shift Supervisor, Duke Potter Company i

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

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-ENCLOSlfRE 2 l

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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

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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

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cause and contributing causes, corrective actions, and the safety significance.- 1

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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,

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.- ENCLOSURE-3-

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DUKE POWER COMPANY

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CATAWBA NUCLEAR STATION.

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ENFORCEMENTICONFERENCE ]

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JULY 12,1990

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AGENDA

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INTRODUCTION TONY OWEN

SEQUENCE OF EVENTS IRICH CASLER

4

ROOT CAUSE TONY OWEN ;

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CORRECTIVE ACTIONS TONY OWEN \

SAFETY EVALUATION opggg;SWINDLEMURST

SUMMARY TONY OWEN

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PLANT STATUS PRIOR TO EVENT ,

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0. NC PRESSURE l335 PSIG 1

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O NC TEMPERATURE 195' DEGREES F t

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TWO NC PUMPS RUNNING .

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RHR . ALIGNMENT

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O 'A' TRAIN IN SERVICE

iO 'B' TRAIN RECIRC:TO FWST .

NO:OTHER ACTIVITIES IN PROGRESS

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J SEQUENCE OF EVENTSi

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'B' TRAIN:RHR CHECK VALVE TEST COMPLETION: .

O RNRIPUMP OFF

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0 FWST ISOLATED FROM;'B' TRAIN RHRi ;

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TWO OPERf TORS INSTRUCTED TO CLOSE ND-33

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CONTROL ROOMIOPERATOR BECAME CONFUSED

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O DID NOT WAIT FOR THE ND-33 PROCEDURE:

STEP TO BE; COMPLETED:

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O OPENED 'B' TRAIN RHR:ISOLATIONS TO

NC SYSTEM

O bPENED ND-32A

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\ TRANSFERRED 5,000 GALS FROM NC TO FWST

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l O MAJORITY WAS TRANSFERRED IN LESS

THAN 30 SECONDS ;

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O NC' PRESS 80 PSIG

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c O NC TEMP 204 DEGREES F

b . .

O PRESSURIZER LEVEL 45% TO 0% ;

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O MANUALLY TRIPPED NC PUMPS AT

200 # NO.1 SEAL DIP

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OPERATOR IMMEDIATELY CLOSED VALVES AND ;

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STABILIZED PLANT l

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O MONITORED FWST I OFFSITE RELEASE

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l O MONITORED RHR PUMP 1A PERFORMANCE

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O RESTORED PRESSURIZER LEVEL WITHIN

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O RETURNED THE UNIT TU MODE 5 WITHIN

15 MINUTES

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i ROOT CAUSE ;

HUMAN ERROR 1

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Cr OPERATOR BECAME CONFUSED. .

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CORRECTIVE ACTIONS

ON-GOING CORRECTIVE ACTIONS -

HUMAN PERFORMANCE

(WASHINGTON PRESENTATION)

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ADDITIONAL CORRECTIVE ACTIONS -

HUMAN PERFORMANCE

flNITIATED BY THIS EVENT)

EQUIPMENT EVALUATION

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ON-GOING CORRECTIVE ACTIONS -

HUMAN PERFORMANCE

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(WASHINGTON PRESENTATION)

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O MANAGEMENT ACTIONS

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O PROCEDURES 1

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O COMMUNICATIONS

O CONFIGURATION CONTROL ;

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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

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ADDITIONAL CORRECTIVE ACTIONS

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ADDITIONAL TRAINING FOR SHIFT J

SUPERVISORS i

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EXERCISE BREAK i

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< OPERATOR TESTIMONIAL :

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SUBSEQUENT ACTIONS

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j NRC INVOLVEMENT - JUNE 11TH TO 14TH

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EXTENSIVE REVIEWS I ANALYSES COMPLETED 4

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O PUMPS ;

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O SYSTEMS :

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1 O SUPPORTS

O INSTRUMENTS :

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O PROCEDURES -

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O GAS RELEASE I

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REGION il I NRR BRIEFED - JUNE 14TH

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SAFETY SIGNIFICANCE EVALUATION

REACTOR COOLANT DIVERSION TO FWST

SCENARIO

INITIAL CONDITIONS:

- 1950F

- 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

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OPERATOR ACTIONS REQUIRED FOR MITIGATION AND RECOVERY I

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1) ISOLATE RCS LEAK PATHS

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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

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TRAIN B: *

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" 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

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_ _ _ _ . _ . _ . . . _ . _ . . . . . _ . . _ _ . _ _ _ _ _ _ _ _ ._ ._ ._ __ . . . _ . . . _ _ _

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ACTIONS TAKEN (**'> ;

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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

4) UNIT . ABILIZED - 15 MINUTES I

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ALSO: RCPs TRIPPED ON LOW #1 SEAL

DELTA-P AND HIGH VIBRATION

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CONCLUSIONS

e OPERATOR ACTION WAS REQUIRED TO CORRECT A SITUATION l

INITIATED BY OPERATOR ERROR

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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

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- 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

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

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SPEC LIMITS

'

e BASED ON:

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- 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

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ML20055H410

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