IR 05000219/1993042

From kanterella
Jump to navigation Jump to search
Meeting Rept 50-219/93-42 on 930505.Major Areas Discussed: Status of Plant Emergency Operating Procedure Program
ML20036B090
Person / Time
Site: Oyster Creek
Issue date: 05/07/1993
From: Conte R, Walker T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20036B062 List:
References
50-219-93-42-MM, NUDOCS 9305180150
Download: ML20036B090 (21)


Text

.-

.

..L

.

U. S. NUCLEAR REGULATORY COMMISSION

,

'

REGION I

REPORT NO.

50-219/93-42 DOCKET NO.

50-219

'

LICENSE NO.

DPR-16 LICENSEE:

General Public Utilities Nuclear Corporation

,

P.O. Box 388 Forked River, New Jersey 08731 FACILITY:

Oyster Creek Nuclear Generating Station

,

MEETING AT:

Region I Office, King of Prussia, Pennsylvania l

MEETING CONDUCTED: May 5,1993 7/Y3 SUBMITTED BY:

e/ -

T. Waffer, Senior Operations Engineer Date

BWR Section, Operations Branch

.

Division of Reactor Safety

.

APPROVED BY:

/

2//P/I(/

67O

,

I ich'ard J. Conte, Chief,"BWR Section Date rations Branch, DRS Summary: A meeting was held at the licensee's request on May 5,1993, to discuss the

,

status of the Oyster Creek Emergency Operating Procedure (EOP) program. Previous NRC

[

inspections had identified that the licensee's programmatic approach taken to develop, l

'

implement, and maintain high quality EOPs was weak. The licensee discussed the corrective actions taken to improve the EOP program.

l

!

!

!

!

9305180150 930510

>

PDR ADOCK 05000219 G

PDR

.

,

.

.

7

,

l

.L

.

.

DETAILS j

i 1.0 INTRODUCTION

!

On May 5,1993, at the NRC Region I Office, the below listed personnel participated in a

!

meeting to discuss the status of the Oyster Creek Emergency Operating Procedure (EOP)

[

j program.

l 2.0 MEETING ATTENDEES

}

i 2.1 General Public Utilities Nuclear Corporation J. Barton Director, Oyster Creek

{'

P. Scallon Manager, Plant Operations W. Behrle Director, Plant Engineering, Oyster Creek

M. Godknecht Plant Engineering, Oyster Creek

,

"

H. Tritt Lead Instructor, Operations Training B. DeMerchant Licensing Engineer, Oyster Creek P. Hansen Engineer, Senior I, Parsippany

,

S. Dietz Senior Public Affairs Representative 2.2 U. S. Nuclear Regulatory Commission

M. W. Hodges Director, Division of Reactor Safety

'

L. Bettenhausen Chief, Operations Branch, DRS A. R. Blough Chief, Projects Branch No. 4 J. Rogge Chief, Projects Section No. 4B D. Florek Senior Operations Engineer

<

T. Walker Senior Operations Engineer i

C. Sisco Operations Engineer

,

i 3.0 LICENSEE PRESENTATION l

The Oyster Creek Manager of Plant Operations introduced the presentation and discussed the

.

concerns identified during previous NRC inspections. A licensee representative from Plant

Engineering discussed the improvements that have been made to the EOP program. A j

representative from Operations Training discussed the status of training on the revised EOPs

[

and support procedures and use of the plant specific simulator for EOP training. The l

'

Director of Oyster Creek provided closing remarks and emphasized the management

!

involvement in the EOP program. The licensee's presentation is included as Attachment 1.

i Attachment: Licensee Presentation n

i I

!

'

.

B hh tvv4- \\

-

-

..

-

,

\\

/

OYSTER CREEK NUCLEAR GENERATING STATION

.

/

>

'

x//

/

-

/

/

-

1IIi lII ITl l I I Iit

-

Ili 'll

!H

_

v GPU N U C LE A R EOP STATUS M E ETI N G MAY 5,

1993

..

.-

.

.-

..

.

__

,

i

'

.

0YSTER CREEK NUCLEAR GENERATING STATION f

EMERGENCY OPERATING PROCEDURES STATUS

!

MAY 5, 1993

!

AGENDA

-;

INTRODUCTION AND PHIL SCALLON

!

BACKGROUND i

!

!

e IMPROVEMENTS TO MIKE GODKNECHT

!

E0P PROGRAM i

i l

l e

E0P TRAINING STATUS HERB TRITT i

i

-

i

!

e CLOSING REMARKS JOHN BARTON l

'

!

,

e QUESTIONS.AND ANSWERS tlRC/GPUN

!

!

!

~

.

!

)

.

-

-

.

.

E

&

L g'

,

e

+

9O

!

[

.

t

.

!

k

>

e o

!

a P

,

s

.

E e

INTRODUCTION AND PREVIOUS CONCERNS

,

i i

s

[

.

Y t

e i

.

i

I t

J

.

t b

.

I a

!

,

I

.

-

h l

,

t

i l

9 i

.

.

-

-

_

.

,

,

,

-:

.

!

i

.;

.,

EMERGENCY OPERATING PROCEDURE INSPECTIONS

.

,

1988 TEAM INSPECTION

STEVE VARGA, NRR, LEAD INSPECTOR

,

i i

1991 SPECIAL SAFETY INSPECTION l

NICK CONICELLA, TEAM LEADER

!

!

I f

'I

1992 SPECIAL SAFETY INSPECTION CARL SISCO, TEAM LEADER i

!

-

- - - - -


-

- - - -

- -

- - - - - -

-

-

-

-

-

-

,

.

. *

,

'

.

.

NRC PAST CONCERNS

,

"

E0P PROGRAM DOES NOT APPEAR TO HAVE THE l

.

STRONG MANAGEMENT INVOLVEMENT TO ENSURE

'

THE QUALITY OF THE E0Ps IS MAINTAINED l

^

,

PROGRAMMATIC APPROACH TAKEN TO DEVELOP, e

IMPLEMENT AND MAINTAIN HIGH-QUALITY E0Ps

IS WEAK A NUMBER OF CONTROL PROCEDURES ARE STILL j

e IN THE APPROVAL PROCESS

INCOMPLETE VALIDATION AND VERIFICATION j

.

.

i

-

LACK OF PLANT SPECIFIC SIMULATOR e

-

LACK.0F JOB TASK ANALYSIS AND 0JT PROGRAM L

e i

.

I

.

..

_ _. -

=.

-

. -,

. -.

. -._

-

-

-.

.

.

.

l

-

_.

,

,

c

..

f

.. *

r

!

!

.

k i

i

!

i

.

I

'

r

>

I P

r k

k r

.

I

$

.

-

,

.

ti

!

,

,

.

t IMPROVEMENTS TO EOP PROGRAM

,

I s

t

$

f I

J t

e t

I l

t

\\

$

f I

I

,

u I

I I

,

.

!

I h

M ~

f

/

I e

!

!

i

>

t b

,

i f

I i

l

?

r

f r

I

!

!

!

?

>

e

-

,-

.

.

.

.:

!

-

OYSTER CREEK EOP COMMITTEE _

!

e E0P COMMITTEE FORMED 3/92 l

t e

REGULAR MEMBERS

PLANT OPERATIONS

-

PLANT ENGINEERING

-

PLANT TRAINING

!

-

i TECHNICAL FUNCTIONS ENGINEERING i

-

i

'

j HUMAN FACTORS

-

l e

ESTABLISHED INTERFACE WITH OTHER GROUPS

.

-

QUALITY ASSURANCE

-

EMERGENCY PREPAREDNESS

-

CHEMISTRY / RADIOLOGICAL CONTROLS

-

!

!

,

E

,

-

-

-

-

-

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

..

.

.-

.

.

.

ACCOMPLISHED OVER THE LAST YEAR

-

.

REWRITE'0F E0P FLOWCHARTS r

REWRITE OF E0P SUPPORT PROCEDURES

.

DEVELOPMENT 0F E0P ADMINISTRATION PROGRAM e

VERIFICATION 0F E0P FLOWCHARTS AND SUPPORT PROCEDURES e

!

INITIAL VALIDATION OF E0P FLOWCHARTS e

INITIAL VALIDATION OF SUPPORT PROCEDURES OUTSIDE CONTROL e

ROOM

e MODIFICATIONS TO SUPPORT E0PS

--,..--.~.-c

. - -

.-.--~.,,.,,4---*.-,,-m---.,-

,...

r,

-, -,. - - -


~.-,,...-....a-w.

.

++--,#

s.... - -

-.-+<vo-we,-.--.-....l-.-..-w.,-,

- - -

r-,-..-. ' - -, - - - -

.<#.----..,.,--


, -,,,

..,-.,.m-,- - - - - -, - -,.- - - - - -+

.

-:.

-

.

CONTROL PROCEDURE STATUS

!

CONTROL PROCEDURES DEVELOPED AND IN PLACE e

E0P PROGRAM CONTROL

-

DEFINES E0P COMMITTEE'S ROLE

~

DEFINES CONTROL OF PSTG AND E0PS LISTS INFO SOURCES THAT NEED REVIEW

i DEFINES WHEN V & V MUST BE PERFORMED DEFINES TRAINING REQUIREMENTS

_

VERIFICATION OF E0P PROGRAM DOCUMENTS

-

!

PROCESS FOR VERIFYING E0P DOCUMENTS i

VALIDATION OF E0PS j

-

PROCESS FOR VALIDATING E0PS

_ _. _ _ _ _ _ _ _ _ _ __ _ j

.

.'

.:

-:

!

CONTROL PROCEDURE STATUS

!

!

i

'

e

!

l E0P WRITER'S GUIDE DEVELOPED AND IN PLACE e

.

COVERS BOTH FLOWCHARTS AND f

-

SUPPORT PROCEDURES

,

,

'

!

.

e QA INVOLVEMENT AT EACH STEP i

,

P

.

i t

!

!

,

e

I

.

.

,

,

i

'

..

ONGOING TASKS l

!

.,

i TECHNICAL DOCUMENTATION UPGRADE e

TECH BASIS FOR PSTGS

-

-

(SIMILAR TO APPENDIX B 0F EPGs)

.

PSTG TO E0P IMPLEMENTATION DOCUMENT l

-

,

.

a EXPAND APPENDIX C TO INCLUDE ALL VALUES

-

-

c IN PSTG l

I

.

,

!

-.

.

..

. -

-

_

.

-

__

_.

l

-

,

.

...

.

.

i

'

ONGOING TASKS l

I i

'

e DEVELOPING A USER'S GUIDE FOR E0P i

FLOWCHARTS i

.

i CONTROLLED REFERENCE DOCUMENT FOR USE BY

-

-

'

THE OPERATORS

1 l

b

,

.

CONTINU0US EVALUATION OF FLOWCHARTS AND

e

!

SUPPORT PROCEDURES DURING TRAINING

,

i i

!

f f

i

.i

.

!

i

'

i

..

!

!

I

!

.

L

.

-

t

9 e

..

F t

t i

!

EOP TRAINING STATUS

.

?

i i

!

i

..

-

.

.

.

s:

!

t CLASSROOM TRAINING

,

!

!

!

TWO TO FIVE HOURS PER CYCLE

!

.

!

i e

REVIEW MAJOR FLOWPATHS j

.

f e

EMPHASIZE CHANGES

'

!

.

WALK THROUGH SUPPORT PROCEDURES l

i

!

>

e COMPLETED JOB TASK ANALYSIS

!

'

!

>

f i

!

l

I

..

.

-

.

.

.

.:

3 --

ON-THE-JOB-TRAINING ESTABLISHED FORMAL EQUIPMENT OPERATOR e

PROGRAM i

!

IN-PLANT SUPPORT PROCEDURES e

!

l NEW/ REVISED PROCEDURES EMPHASIZED l

e-

!

CONDUCTED BY SUPERVISORS AND INSTRUCTORS e

!

i i

l l

.

..

--

.

.

'

'

>:

,7 SIMULATOR TRAINING 16 TO 18 HOURS PER TRAINING CYCLE e

ADDITIONAL 16 HOURS DURING RELIEF WEEK e

PROGRESSIVELY WORK THROUGH FLOW CHARTS e

SCENARIOS IN THIRD AND FOURTH CYCLE e

G0 FURTHER THAN REQUIREMENTS OF NUREG 1021 (EXAMINER STANDARD)

EVALUATED BY ALL LEVELS OF MANAGEMENT e

INCLUDING VICE PRESIDENT

-

.

.

,

'

,

CONTINUOUS IMPROVEMENTS i

i

FLOWCHART REVIEWS DURING SIMULATOR e

TRAINING i

t

,

I SUPPORT PROCEDURE REVIEWS DURING OJT AND e

SIMULATOR TRAINING

.

>

.

REVIEWS DURING TRAINING MATERIALS

.

t DEVELOPMENT

.

!

l

'

,

i

.

.

-

- -

- - -

-

-

- -

- -- -

e

h e

B

i I

f I

_

.

,

CLOSING REMARKS

,

i I

>

f

-

>

k (

,

h I

>

f r

F l

.

k k

,

.:

?

.

>

.

CONTROL ROOM CHANGES i

i

i I

i

.

E0P TABLES INSTALLED IN CONTROL ROOM l

!

!

!

e REASSIGNMENTS OF CONTROL ROOM l

RESPONSIBILITIES DURING EMERGENCY

!

SITUATIONS i

l

i

.

!

I i

i

!

!

I

,

!

~

..-

.

..

.

..

,

.