ML20236W692
| 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: |
| References | |
| NUDOCS 8712080171 | |
| Download: ML20236W692 (3) | |
See also: IR 05000313/1987029
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50-313/87-29
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- 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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8712080171 871203
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Arkansas Power & Light Company
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In accordance with 10 CFR Part-2.790(a), a copy of this letter and the
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' 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
- RSTS Operator
- Project Engineer, PS/A
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- R. Hall
- D.
Norman
D. Powers
R. D. Martin, RA
- D
Weiss, RM/ALF
- MIS System
- G. Dick, NRR Project Manager
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- R. E. Ireland
R. W. Starostecki, NRR
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F. J. Miraglia, Jr., NRR
W. D. Lanning-
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Arkansas f'ower & Light Company
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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
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Enclosure:
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Appendix - NRC Inspection Report
,
50-313/87-29
50-368/87-29
cc w/ enclosure:
Arkansas Nuclear One
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ATTN:
J. M. Levine, Director
Site Nuclear Operations
P. O. Box 608
Russellville, Arkansas
72801
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Arkansas Radiation Control Program Director
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