ML20236W692

Forwards Insp Repts 50-313/87-29 & 50-368/87-29 on 870818- 20.Weaknesses Noted Re Former Design Program,Including Failure to Recognize Abnormal Temp Conditions.Enforcement Conference Scheduled for 871218

ML20236W692
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/03/1987
From:	Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Campbell G ARKANSAS POWER & LIGHT CO.
Shared Package
ML20236W693	List: IR 05000313/1987029 ML20236W692
References
NUDOCS 8712080171
Download: ML20236W692 (3)

See also: IR 05000313/1987029

Text

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zIn Reply Refer Tb:

. DEC 319EIT

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~ Dockets: 50-313/87-29

E :50-368/87-29

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Arkan ns Power & Light Company

ATTN: 'Mr. Gene Campbell'

Vice President, Nuclear

Operations

~P. 0. Box 551

Little Rock, Arkansas 72203

Gentlemen:

'This're erslto.the special inspection conducted by an NRC inspection

. team.during.the period August 18-20, 1987, relating to the effects of

high containment temperatures on components and structures of Arkansas Nuclear

One, Unit 1 and.to the containment; temperature profiles of Unit 2. This also

crefers to discussions'~of our findings'with members of your staff during the

course of_the inspection.

The enclosed inspection report identifies the specific areas examined during the

inspection. Within these areas, the inspection consisted of selective

examination of procedures and representative records, interviews with

personnel, and observations by the..NRC inspectors,

During this inspection, it vas found that weaknesses in your former Design.

Program continue to generate potential' safety significant problems that have

not been identified, analyzed, or properly reported.

. We are particularly concerned about the ' apparent failure of AP&L to recognize,

prior to August-1987, that the abnormal-containment temperature conditions in

. Unit 1-represented'a departure from the stated design bases that should have

been subjected to a thorough and comprehensive evaluation. The. failure to do

so, has perpetuated an improper characterization of containment temperature '

information in the " updated" Final Safety Analysis Report. It is also

' apparent'that this failure to recognize the abnormal temperature distributions

has' led y ur own engineering staff to use erroneous information in determining

the. effects 'of temperature-on aging of many items of electrical equipment

which must remain environmentally qualified.

As discussed in our telephone conversation of December 1,1987, with your

staff, we have scheduled an enforcement conference in our office at 10:00 a.m.

on December 18,'1987, to discuss your understanding of these violations, the

reasons for occurrence, and your corrective actions. We will also discuss the

NRC enforcement policy, if appropriate.

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Arkansas Power & Light Company -2-

l In accordance with 10 CFR Part-2.790(a), a copy of this letter and the

l ' enclosure will be placed in the NRC Public Document Room.

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

discuss them with you.

Sincerely,

'Orlglnni Sicned By

A. B. Beach

L. J. Callan, Director

Division of Reactor Projects

Enclosure:

Appendix - NRC Inspection Report

50-313/87-29

50-368/87-29

cc w/ enclosure:

Arkansas Nuclear One

ATTN: J. M. Levine, Director

Site Nuclear Operations

P. O. Box 608

Russellville, Arkansas 72801

Arkansas Radiation Control Program Director

bectoDMB(IE01)

bec distrib. by RIV:

• PS/A_ *RRI

RPSB-DRSS *Section Chief (PS/A)

• RIV File DRP

• RSTS Operator * Project Engineer, PS/A ,

• R. Hall DRS

• D. Norman D. Powers

R. D. Martin, RA *D Weiss, RM/ALF

• MIS System *G. Dick, NRR Project Manager j

• R. E. Ireland

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R. W. Starostecki, NRR l

F. J. Miraglia, Jr., NRR W. D. Lanning- {

J. Calvo, NRR i

E. L. Jordan AEOD- l

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Arkansas f'ower & Light Company -2-

In accordance with 10 CFR Part 2.790(a), a copy of this letter and the

enclosure will be placed in the NRC Public Document Room.

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

discuss them with you.

Sincerely,

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L. J. Callan, Director

q Division of Reactor Projects  !

Enclosure: I

Appendix - NRC Inspection Report ,

50-313/87-29

50-368/87-29

cc w/ enclosure:

Arkansas Nuclear One

l ATTN: J. M. Levine, Director

Site Nuclear Operations

P. O. Box 608

Russellville, Arkansas 72801

l

Arkansas Radiation Control Program Director '

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