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Forwards Insp Repts 50-313/96-27 & 50-368/96-27 on 961022-29 & 1121 & 25 & Notice of Violation.Problems Identified in Implementation of Fire Protection Requirements of App R
	ML20138J365
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/03/1997
From:	Gwynn T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Hutchinson C; ENTERGY OPERATIONS, INC.
Shared Package
ML20138J368	List: IR 05000313/1996027; ML20138J365; ML20138J377;
References
	EA-96-512, NUDOCS 9702070133
	Download: ML20138J365 (6)
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i UNITED STATES

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FEB - 31997

EA 96-512

C. Randy Hutchinson, Vice President

Operations

Arkansas Nuclear One

Entergy Operations, Inc.

1448 S.R. 333

Russellville, Arkansas 72801-0967

SUBJECT: NRC INSPECTION REPORT 50-313;368/96-27 AND NOTICE OF VIOLATION

Dear Mr. Hutchinson:

An NRC specialinspection was conducted on October 22-29 and November 21-25,1996,

at your Arkansas Nuclear One, Units 1 and 2 reactor facilities, following a fire in the Unit 1

reactor building on October 17,1996. The enclosed report presents the scope and results

of that inspection. The overall conclusions of the inspection were discussed with Mr. R.

Edington and others of your staff on November 5,1996. A final telephonic exit meeting

was held with your staff on December 11,1996. In addition, the overall results of this

inspection were discussed with Mr. Dwight Mims, on February 3,1997.

The inspection identified several problems in your implementation of the fire protection

requirements of Appendix R. Most significantly, a recent Unit 1 modification to replace

Reactor Coolant Pump B failed to install an adequate lube oilleakage collecti)n system,

which resulted in an oil fire inside the reactor building. Our concern regarding this failure is

heightened due to several missed opportunities to identify and correct the problem prior to

the fire occurring. Specifically, the design change which replaced the reactor coolant

pump motor did not receive an adequate fire protection review. The oilleakage observed

during maintenance was not thoroughly investigated. Repeated observations of oilleakage

by radiation protection personnel were not investigated. Most importantly, the reports of

oil-soaked insulation and excessive smoking during the plant heatup were not adequately

communicated and reviewed. These instances indicated that your corrective action

programs may not have adequately addressed fire hazards and fire protection deficiencies

as significant conditions adverse to the quality and safe operation of the plant.

As a result of concerns raised during the inspection, your staff subsequently submitted a

10 CFR 50 Appendix R exemption request for Unit 2, dated December 23,1996, for the

remote lube oil fill lines which had been installed on the reactor coolant pump motors. This

exemption request will be reviewed by the Office of Nuclear Reactor Regulation.

The inspection identified a violation involving your f ailure to notify the NRC of your j

declaration of an unusual event during the fire. The violation is cited in the enclosed

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9702070133 970203

PDR ADOCK 05000313

G PDR

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Entergy Operations., Inc. -2-

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Notice of Violation (Notice) and the circumstances surrounding the violation are described I

in detail in the enclosed report. Please note that you are required to respond to this letter

and should follow the instructions specified in the enclosed Notice when preparing your

response. The NRC will use your response, in part, to determine whether further

, enforcement action is necessary to ensure compliance with regulatory requirements. !

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In addition, two apparent violations were identified and are being considered for escalated

enforcement action in accordance with the " General Statement of Policy and Procedure for

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NRC Enforcement Actions" (Enforcement Policy), NUREG-1600. The first apparent

. violation involves inadequate fire protection design features for the oil collection system for

the Unit 1 and 2 reactor coolant pump motors. Our concern regarding this apparent

violation is heightened by the occurrence of the fire in the reactor building and by the

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second apparent violation involving the failure to identify and take prompt corrective action

for three prior instances of observed oilleakage. Accordingly, no Notice of Violation is

presently being issued for these inspection findings. In addition, please be advised that the

number and characterization of apparent violations described in the enclosed inspection

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report may change as a result of further NRC review.

A predecisional enforcement conference to discuss these apparent violations will be

scheduled with your staff. The decision to hold a predecisional enforcement conference

does not mean that the NRC has determined that a violation has occurred or that

enforcement action will be taken. This conference is being held to obtain information to

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enable the NRC to make an enforcement decision, such as a common understanding of the

facts, root causes, missed opportunities to identify the apparent violation sooner,

corrective actions, significance of the issues and the need for lasting and effective

corrective action. In addition, this is an opportunity for you to point out any errors in our

inspection report and for you to provide any information concerning your perspectives on

1) the severity of the violations,2) the application of the factors that the NRC considers

when it determines the amount of a civil penalty that may be assessed in accordance with

Section VI.B.2 of the Enforcement Policy, and 3) any other application of the Enforcement

Policy to this case, including the exercise of discretion in accordance with Section Vll.

1 This conference will be open to public observation in accordance with the recent revisions

to the Enforcement Policy.

You will be advised by separate correspondence of the results of our deliberations on this

matter. No response regarding these apparent violations is required at this time,

in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,

its enclosure and your response will be placed in the NRC Public Document Room (PDR).

To the extent possible, your response should not include any personal privacy, proprietary,

or safeguards information so that it can be placed in the PDR without redaction.

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Should you have any questions concerning this inspection, we will be pleased to discuss

them with you.

j Sincerely,

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s n b.. Ae*Y

T omas P.

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/ yn

ivision of Reactor Safety

irector

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i Docket Nos.: 50-313;50-368

j License Nos.: DPR-51 ; NPF-6

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! Enclosures:

1. Notice of Violation 1

2. NRC Inspection Report .

1 50-313;368/96 27 l

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l cc w/ enclosures:

j- Executive Vice President

& Chief Operating Officer

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Entergy Operations, Inc.

1 P.O. Box 31995

l Jackson, Mississippi 39286-1995

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! Vice President

l Operations Support

Entergy Operations, Inc.

! P.O. Box 31995

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Jackson, Mississippi 39286

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Manager, Washington Nuclear Operations

j ABB Combustion Engineering Nuclear

Power

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12300Twinbrook Parkway, Suite 330

l- Rockville, Maryland 20852

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! County Judge of Pope County

l; Pope County Courthouse

Russellville, Arkansas 72801

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Entergy Operations, Inc. -4-

Winston & Strawn

1400 L Street, N.W.

Washington, D.C. 20005-3502

Bernard 8evill, Acting Director

Division of Radiation Control and

Emergency Management

Arkansas Department of Health

4815 West Markham Street, Slot 30

Little Rock, Arkansas 72205-3867 ,

Manager

Rockville Nuclear Licensing

Framatone Technologies

1700 Rockville Pike,' Suite 525

Rockville, Maryland 20852

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Entergy Operations, Inc. -5-

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E-Mail report to T. Boyce

E-Mail report to NRR Event Tracking System (IPAS)

bec to DMB (IE01)

bec distrib. by RIV:

L. J. Callan Resident inspector

DRP Director MIS System

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Branch Chief (DRP/C) RIV File

l~ Project Engineer (DRP/C) DRS-PSB

J Branch Chief (DRP\TSS) Leah Tremper (OC/LFDCB, MS: TWFN 9E10)

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SRI ANO J. Leiberman (MS O-7H5)

OE: EA (MS O-7H5)

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G. F. Sanborn

DRS AI 97-G-0020

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E-Mail report to T. Boyce

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E-Mail report to NRR Event Tracking System (IPAS)

j bec to DMB (IE01)

bec d!strib, by RIV:

L. J. Callan Resident inspector

DRP Director MIS System

Branch Chief (DRP/C) RIV File

Project Engineer (DRP/C) DRS-PSB

Branch Chief (DRP\TSS) Leah Tremper (OC/LFDCB, MS: TWFN 9E10)

SRIANO J. Leiberman (MS O-7H5)

OE:EA (MS O-7H5)

G. F. Sanborn

DRS AI 97-G-0020

DOCUMENT NAME: R:\_ANO\AN627RP.PMQ

To receive copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N = No copy

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ML20138J365

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