ML20046B066
| ML20046B066 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 07/23/1993 |
| From: | Hopkins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Leslie Liu IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| Shared Package | |
| ML20046B067 | List: |
| References | |
| EA-93-187, NUDOCS 9308030059 | |
| Download: ML20046B066 (4) | |
See also: IR 05000331/1993009
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JUL 2 31993
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Docket No. 50-331
EA 93-187
Iowa Electric Light and Power
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Company
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ATTN: Mr. Lee Liu
Chairman of the Board
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and Chief Executive
Officer
IE Towers
P. O. Box 351
Cedar Rapids, IA 52406
Dear Mr. Liu:
,
SUBJECT: NRC INSPECTION REPORT NO. 50-331/93009
This refers to the inspection conducted by Messrs. M. Parker and C. Miller of
this office on May 22 through July 7,1993. The inspection included a review
of activities authorized for your Duane Arnold Energy Center (DAEC) facility.
At the conclusion of the inspection, the findings were discussed with those
members of your staff identified in the enclosed report (Enclosure 1).
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Areas examined during the inspection are identified in the report.
Within
these areas, the inspection consisted of a selective examination of procedures
and representative records, interviews with personnel, and observation of
activities in progress.
Based on the results of this inspection, (50-331/93009(DRP), two apparent
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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),_10 CFR Part 2, Appendix C.
The
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first apparent violation (TS 3.5.G.1), is of concern to us because the
"A"
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standby diesel generator was inoperable for a time significantly in excess of
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that allowed by your technical specifications, and would not have been able to
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perform its safety function had it been called upon.
In the second apparent-
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violation (TS 6.8.1), the control room operators were unaware of the status of
an important emergency core cooling system component for approximately 14
hours even though the condition was indicated on the "B" core spray mimic
panel in the control room. This failing, combined with other problems
identified with shift briefings and inappropriate annunciators, gives us
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concern that your control room operations have not been conducted with the
appropriate attention to detail and sensitivity for safety required of this
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Iowa Electric Light and Power
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important operating function.
I am of the view that your recent crew
performance significantly departs from the high standard of professionalism
and quality normally present and expected in the control room of a nuclear
power plant.
Inasmuch as these inspection findings are being considered for
escalated enforcement action, no Notice of Violation is presently being
issued.
Please be advised that the number and characterization of apparent
violations described in the enclosed inspection report may change as a result
of further NRC review.
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An enforcement conference to discuss these apparent violations has been
scheduled for July 29, 1993, at 9 a.m. (CDT) in the Region III office in
Glen Ellyn, Illinois. This enforcement conference will be open to public
observation in accordance with the Commission's trial program as discussed in
the enclosed Federal Reaister (Enclosure 2). The purposes of this conference
are to discuss the apparent violations, their causes and safety significance;
to provide you the opportunity to point out any errors in our inspection
report; and to provide an opportunity for you to present your proposed
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corrective actions.
In particular, we expect you to address the root cause of
the SBDG failure and your corrective actions, and actions you are taking to
ensure that operator duties including routine equipment monitoring,
surveillances, and briefings are conducted in a professional and rigorous
manner.
In addition, this an opportunity for you to provide any information.
concerning your perspectives on 1) the severity of the violations, 2) 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) the possible basis for exercising discretion in
accordance with Section VII of 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 addition, the results of a Safety Assessment / Quality Verification
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inspection at the Duane Arnold Energy Center conducted on April 5-9 and
May 3-7, 1993, by Mr. R. Pulsifer and Ms. B. Korona of NRR is included as a
separate enclosure (Enclosure 3). During this inspection, no violations of
NRC requirements wete identified.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter and the enclosed inspection reports will be placed in the NRC
Public Document Room.
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Iowa Electric Light and Power
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
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Edward G. Greenman, Director
Division of Reactor Projects
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Enclosures:
I.
Inspection Report
No. 50-331/93009(DRP)
2.
Federal Reaister Notice
3.
NRR Safety Assessment /
Quality Verification Report
cc w/ enclosure:
D. Wilson, Plant
Superintendent - Nuclear
K. Young, Manager, Nuclear
Licensing
OC/LFDCB
Resident Inspector, RIII
Stephen Brown, Iowa Dept.
of Commerce
Licensing Project Mgr., NRR
J. Luehman, OE
J. Lieberman, OE
J. Goldberg, OGC
J. Partlow, NRR
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
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Edward G. Greenman, Director
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Division of Reactor Projects
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Enclosures:
1.
Inspection Report
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No. 50-331/93009(DRP)
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2.
Federal Register Notice
3.
NRR Safety Assessment /
Quality Verification Report
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cc w/ enclosure:
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D. Wilson, Plant
Superintendent - Nuclear
K. Young, Manager, Nuclear
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Licensing
OC/LFDCB
Resident Inspector, RIII
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Stephen Brown, Iowa Dept.
of Commerce
Licensing Project Mgr., NRR
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J. Luehman, OE
J. Liebermann, OE
J. Goldberg,.OGC
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J. Partlow, NRR
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