ML20148K258
| ML20148K258 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/11/1997 |
| From: | Howell A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| Shared Package | |
| ML20148K264 | List: |
| References | |
| 50-445-97-12, 50-446-97-12, NUDOCS 9706170403 | |
| Download: ML20148K258 (4) | |
See also: IR 05000445/1997012
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-UNITEo STATES
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NUCLEAR REGULATORY COMMISSION
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REGloN IV
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611 RYAN PL AZA DRIVE, SUITE 400
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Mr. C. L. Terry
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TU Electric
Group Vice President, Nuclear
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ATTN: Regulatory Affairs Department
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P.O. Box 1002
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Glen Rose, Texas 76043
SUBJECT: NRC INSPECTION REPORT 50-445/97-12: 50-446/9712 AND NOTICE OF
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VIOLATION
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Dear Mr. Terry:
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An NRC inspection was conducted April 21 through May 2,1997, at your Comanche Peak
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Steam Electric Station, Units 1 and 2 reactor facilities. The enclosed report presents the -
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scope and results of that inspection. The final results of this inspection were discussed
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with Mr. T. Hope and members of your staff on June 11,1997.
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The inspection evaluated the status of your corrective action and self-assessment
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programs. These programs were functioning well and were adequately supporting the safe
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operation of the plant. However, four violations were identified as discussed below.
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The first violation involved the failure to report required information in a licensee event
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report, as required by 10 CFR 50.73. The report did not contain information relevant to
past occurrences of the slow closure of a main feedwater isolation valve. The violation is
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of concern because the failure to provide this information resulted in an incomplete
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portrayal of the safety implications of the event. During the inspection, you stated an
objection to this violation based on your interpretation of the reporting requirements of
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NUREG 1022, " Licensee Event Report System." As discussed in Section O3.1 of the
inspection report, we have concluded that the omitted information was clearly within the
scope of the intent of the existing regulations.
The second violation involved four examples of the failure to identify conditions adverse to
quality in your corrective action system; and one example of the f ailure to correct the root
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cause of a signification condition. This violation was of concern because the omissions
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were indicative of an inattention to ' detail on the part of several plant groups and the failure
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to implement generally-expected corrective action practices. Specifically, your staff did not
initiate operations, notifications, and evaluation forms for identified discrepancies and your
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corrective actions f ailed to consider the missed opportunities to identify the inoperability of
a feedwater isolation valve.
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9706170403 970611
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ADOCK 05000445
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The third violation involved the failure to perform safety evaluations for configuration
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changes that involved changes to drawings in the Final Safety Analysis Report. During the
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inspection, you stated an objection to this violation, in that, you believed that previous
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NRC inspections had accepted this practice. As discussed in Section E2.4 of the attached
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inspection report, we have concluded that our previous inspection activities did not remove
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the regulatory requirement to evaluate changes which affect the Final Safety Analysis
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Report.
The fourth violation involved the failure to adequately control the installation of temporary
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leaded shielding to plant structures. This resulted from an inadequate procedure used to
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install the leaded shielding.
These violations are cited in the enclosed Notice of Violation (Notice) and the
circumstances surrounding the violations are described in detailin the enclosed reoort,
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Please note that you are required to respond to this letter and should follow ths
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
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to ensure compliance with regulatory requirements.
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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,
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its enclosure (s), arid your response will be placed in the NRC Public Document Room
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(PDR). To the extent possible, your response should not include any personal privacy,
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proprietary, or safeguards information so that it can be placed in the PDR without
redaction.
Should you have any questions concerning this inspection, we will be pleased to discuss
them with you.
Sincerely,
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Arthur T. Howell ill, Director-
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Divisior of Reactor Safety
Docket Nos.: 50-445; 50-446
Enclosures:
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2. NRC Inspection Report
50-445/97 12;50-446/97-12
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TU Electric
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cc w/ enclosures:
Mr. Roger D. Walker
TU Electric
Regulatory Affairs Manager
P.O. Box 1002
Glen Rose, Texas 76043
Juanita Ellis
President - CASE
1426 South Polk Street
Dallas, Texas 75224
TU Electric
Bethesda Licensing
3 Metro Center, Suite 610
,
Bethesda, Maryland 20814
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George L. Edgar, Esq.
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1800 M. Street, NW
Washington, D.C. 20036
G. R. Bynog, Program Manager /
Chief Inspector
Texas Department of Licensing & Regulation
Boiler Division
P.O. Box 12157, Capitol Station
Honorable Dale McPherson
County Judge
P.O. Box 851
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Glen Rose, Texas 76043
Texas Radiation Control Program Director
1100 West 49th Street
John Howard, Director
Environmental and Natural Resources Policy
Office of the Governor
P.O. Box 12428
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TU Electric
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E-Mail report to T. Boyce (THB)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
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E-Mail report to T. Boyce (THB)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
bec to DCD (IE01)
bec distrib. by RIV:
Regional Administrator
Resident inspector (2)
DRP Director
DRS-PSB
Branch Chief (DRP/A)
MIS System
Project Engineer (DRP/A)
RIV File
Branch Chief (DRP/TSS)
DRS AI 97-G-
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DOCUMENT NAME:
To receive copy of document, indicate in box: "C" = Copy without enclosures
"E" = Copy with enclosures "N" = No copy
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