ML20216B070
| ML20216B070 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/02/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Franz J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| Shared Package | |
| ML20216B075 | List: |
| References | |
| 50-331-97-06, 50-331-97-6, NUDOCS 9709050221 | |
| Download: ML20216B070 (2) | |
See also: IR 05000331/1997006
Text
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9
September 2,
1997
'
r
Mr. John F. Franz, Jr.
Vice President, Nuclear
IES Utilities, Incorporated
i
200 First Street SE
'
P.O. Box 351
Cedar Rapids, lA 52406-0351
4
SUBJECT:
NRC SYSTEM OPERATIONAL PERFORMANCE INSPECTION REPORT
50 331/97006(DRS) AND NOTICE OF VIOLATION
Dear Mr. Franz:
This refers to the System Operational Performance inspection completed on site April 25 at
the Duane Amold Enargy Center facility and to the review in Region lli of additional
Information from June 9 to July 1,1997. The inspection team assessed the residual heat
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removal (RHR) system's operational performance by a detailed review of RHR design,
maintenance, operation, and surveillance and testing. Additionally, the inspection team
assessed the effectiveness of licensee controls in identifying, resolving and preventing
problerns. The enclosed report presents the results of this inspection.
.
Based on the inspection results, certain of your activities appeared to be in violation of NRC
requirements, as specified in the enclosed Notice of Violation (Notice). The violations are
of concern since they involved untimely r,orrective actions, the use of American Society of
Mechanical Engineers Code stroking times versus the Updated Safety Analysis Report
design values for surveillance testing, failure to adhere to station procedures, and
inadequate design cor. trol. We are also concerned about problems identified regarding
attention to detailin the performance of calculations.
The team noted a well established motor-operated valve technical program and a good
trending program. Additionally, the team determined the action request program was well
utilized by plant personnel and a low threshold for problem identification was
demonstrated. Material condition of the RHR system was considered good.
.
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 complianco with
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regulator e requirements,
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J. Franz
2
September 2,
1997
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,
its enclosure (s), and your response will be placed in the NRC Public Document Room.
Sincerely,
John A. Grobe, Acting Director
Division of Reactor Safety
Docket No. 50 331
Enclosures:
2. Inspection Report 50 331/97006(DRS)
,
cc w/encls:
L. Root, President and Chief
Operating Officer
G. Van Middlesworth, Plant Manager
K. E. Paveler, Manager, Licensing
and Ernergency Planning
Chairperson, Iowa Utilities Board
Distribution:
Docket File w/ encl
Rill PRR w/enci
Rlli Enf. Coordinator w/enct
PUBLIC IE 01 w/enct
TSS w/enci
OC/LFDCB w/enci
LPM, NRR w/ encl
CAA1 w/encI
DRP w/enct
A. B. Deach, Rlil w/enci
DOCDESK w/enct
DRS w/enci
J. L. Caldwell, Rlll w/ encl
DOCUMENT NAME: G:\\DRS\\DUA97006.DRS -
To receive a copy of thle document. Indicate in the box 'C" = Copy w/o evach/cri
'E' = Copy w/ attach /enct
'N' = No gopy
OFFICE
Rill:DRG
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Rlll:DRS ,lE
Rill:DRP
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Rill:DRS m)
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NAME
Westber's/kic/P
Ring 4/6
Jordan 9h}l]
Jacobson/GE:n
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DATE
08/ly /97
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08/q /97
08/Lf/97 /
Oq
/97
OFFICIAL RECORD COPY
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