ML20214K488
| ML20214K488 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/15/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| Shared Package | |
| ML20214K490 | List: |
| References | |
| EA-87-057, EA-87-57, NUDOCS 8705280458 | |
| Download: ML20214K488 (3) | |
See also: IR 05000413/1987006
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MAY 151987
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Docket Nos. 50-413, 50-414
EA 87-57
uke Power Company
ATTN: Mr. H. B. Tucker, Vice President
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Nuclear Production Department
422 South Church Street
Charlotte, NC 28242
Gentlemen:
SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NOS. 50-413/87-06,
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50-414/87-06, AND 50-413/87-08, 50-414/87-08)
This refers to the Nuclear Regulatory Connission (NRC) inspections conducted -
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at the Catawba facility on January 30 to February 19 1987 and February 26 to
March 25, 1987. -The reports documenting these inspections were sent to you
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with-letters dated March 12, 1987 and April 10, 1987, respectively. . Associated
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with these inspections, failures to comply with NRC regulatory requirements were
identified by your plant staff. NRC concerns relative to these findings were
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discussed by M. Ernst, Deputy Regional Administrator, NRC, Region II, with you
and members of your staff in an Enforcement Confe.ence held on April 16, 1987_.
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Violation A described in the enclosed Notice of Violation involved failures
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in the design control process. These failures resulted in systems being placed
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in service which, under certain conditions, were in a degraded condition.
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the first example, because curbs had not been specified on the design drawings,
the units have operated since initial startup with Containment Air Return Fans
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that would be susceptible to flooding and degraded operation under postulated
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loss of coolant accident (LOCA) conditions.
In the second example, due to
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unclear design drawings, one of two required Pressurizer Power. Operated Relief
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Valves was connected incorrectly to the backup nitrogen supply and would not
have operated under certain postulated conditions. ~These examples emphasize
the need to assure that design control is adequate such that proper equipment
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is installed to fulfill regulatory requirements and the design basis.
In accordance with the " General Statement of Policy and Procedure for NRC
Enforcement Actions," 10 CFR Part 2, Appendix C (1987), Violation A described
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in the enclosed Notice has been classified at a Severity Level III. A civil
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penalty is considered for a Severity Level III violation. However, after
consultation with the Director, Office of Enforcement, and the Deputy Executive
Director for Regional Operations, I have decided that a civil penalty.will not
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be proposed in this case because both examples of the violations were identified
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by your staff and promptly reported to the NRC and prompt actions were taken-to
comply with appropriate Technical Specifications. Mitigation is also appropriate
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because the licensee had initiated an extensive ongoing program to remedy the
type of desig:. engineering deficiencies as identified herein. These deficiencies
in design control, which occurred before this program was initiated, have been
thoroughly discussed in conjunction with other recent enforcement actions
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8705280458 870515
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DR
ADOCK 05000413-
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Duke Power Company
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related to the McGuire, Oconee and Catawba Stations, as well as during the
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management meeting on this subject held at the Region II Office on March 6,1987.
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Because Violations B and C involve issues of lesser safety significance, each
has been categorized as a Severity Level IV violation.
In Violation B, involving
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a failure to promptly evaluate the operability of components in the Containment
Spray System, poor design / operations interface was a contributing factor to the
untimely evaluation. - There was not'a violation of technical specification
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requirements in that your staff's final evaluation determined that the heat
exchanger was never below its required heat exchange capability. Violation C
involved the failure to properly follow a station ' surveillance testing procedure
and additionally procedural deficiencies were identified.
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You are required to respond to this letter and should follow the instructions
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specified in the enclosed Notice when preparing your response.
In-your
response, you should document the specific actions taken and any additional
actions you plan to prevent recurrence. After reviewing your response to this
Notice, including your proposed corrective actions and the results of future
inspections, the NRC will determine whether further NRC enforcement- action is
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necessary to ensure compliance with NRC regulatory requirements.
Based on the design control program deficiencies identified at your Oconee _and
McGuire Stations the NRC recognizes that corrective actions are currently being
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implemented which should also significantly reduce the likelihood of occurrence
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of violations such as in the enclosed Notice. Therefore, please address what
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additional measures, if any, your staff has identified to improve your management
system which controls and encourages.the quality of your engineering support and
the communications interface between the site and design engineering._ Also,
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please describe any additional measures you may have or are planning to take
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to improve the timeliness of engineering support for your nuclear sites.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,
Title 10, Code of Federal Regulations, a copy of this letter and its enclosure
will be placed in the NRC Public Document Room.-
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The responses directed by this letter and its enclosure are not subject to the
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clearance procedures of the Office of Management and Budget as required by the
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Paperwork Reduction Act of 1980, Pub. L. No.96-511.
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Sincerely
ORIGINAL SIGNED BY
M.l.ERNST
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J. Nelson Grace
Regional Administrator
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Enclosure:
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pc w/ encl:
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g/J. W. Hampton, Station Manager
Senior Resident Inspector - McGuire
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MAY 151987
Duke Power Company
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