ML20211K409
| ML20211K409 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/12/1986 |
| From: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Campbell G ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML20211K417 | List: |
| References | |
| EA-86-151, NUDOCS 8611170164 | |
| Download: ML20211K409 (4) | |
Text
..
Docket No. 50-313 NOV 12196 License No. DPR-51 EA 86-151 Arkansas Power & Light Company ATTN: Mr. Gene Campbell Vice President, Nuclear Operations First National Bank Bldg.
Capitol & Broadway Little Rock, Arkansas 72201 Gentlemen:
SUBJECT:
NOTICE OF VIOLATION AND PROPOSED IllPOSITION OF CIVIL PENALTY (NRC INSPECTION REPORT NO. 50-313/86-01)
This refers to the Safety System Functional Inspection (SSFI) conducted on January 6-31, 1986, at the Arkansas Nuclear One-Unit I facility. Violations of HRC requirements were identified as a result of this inspection in the referenced inspection report sent to you by letter dated March 31, 1986. An enforcement conference was conducted in the Region IV office on July 11, 1986, with Messrs. M. Pendergrass, T. Cogburn, J. Levine and others of your staff and Messrs J. Partlow, R. Hall, J. Gagliardo, and others of the NRC staff to discuss the apparent violations and other concerns identified during the SSFI.
The most significant violation identified during the SSFI involved a modifi-cation to the steam supply lines to the turbine driven Emergency Feedwater (EFW) pump and is described in Violation I of the enclosed Notice of Violation and Proposed Imposition of Civil Penalty (Notice). The final design of the EFW upgrade (a post-THI modification) had been submitted to the NRC for approval by letter dated December 1, 1981. The change was implemented by design change package DCP 82-D-1050 and installation was completed during the 1984 refueling outage. However, the modification deleted two check valves which had been included in the EFW upgrade presented in the December 1, 1981 submittal. The steam supply check valves are required to prevent blowdown of both steam generators during a nonisolable stean line break, essuming a single failure of one AC power supply; specifically, the " red" AC power supply which drives the motor-driven EFW pump and provides motive power to close the normally open isolation valve from the "A" steam generator. Although these check valves were deleted by the design change package because operating experience had 8611170164 861112 PDR ADOCK 05000313 C
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l Arkansas Power & Light Company l l
shown that these check valves did not perform reliably in service, the deletion l
of these check valves was made without an adequate review for all possible l
design basis accident scenarios.
l This violation is of significant concern because it reveals weaknesses in your program for the review of plant changes and of the administrative controls established to assure that design reviews are properly performed, including plant change reviews and licensee safety evaluations performed in accordance with 10 CFR 50.59. These plant change reviews are important to assure that regulatory requirements continue to be satisfied and that changes to the plant do not constitute a change to the technical specifications or an unreviewed safety issue.
To emphasize the importance of assuring that plent changes and modifications are properly reviewed for possible impacts on existing safety analyses and design bases I have been authorized, after consultation with the Director, Office of Inspection and Enforcement, to issue the enclosed Notice of Violation and Proposed Imposition of Civil Penalty in the amount of Fifty Thousand Dollars
($50,000) for Violation I described in the enclosed Notice.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actior.s,"
10 CFR Part 2, Appendix C (1986) (Enforcement Policy) Violation I described in the enclosed Notice has been categorized at a Severity Level III. The escalation and mitigation factors in the Enforcement Policy were censidered and no adjustment has been deemed appropriate.
Violation II in the enclosed Notice involves deficiencies identified in the areas of design control, equipment testing, maintenance procedure accuracy, and document control. These violations involve deficiencies of a less serious nature than that in Violation I but are of more than minor concern and demonstrate the need for additional licensee management attention in the preparation and implementation of plant modifications to safety systems.
Therefore, these violation have been categorized as Severity Level IV violations.
You are required to respond to this letter and should follow the instructions 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, the NRC will determine whether further NRC enforcement action is necessary tc ensure compliance with NRC regulatory requirements.
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.
Arkansas Power & Light Company <
l The responses directed by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
l Sincerely, CRIGINAL SIGNED BY i
ROBERT D. l.iMI!:!
4 1
Robert D. Martin Regional Administrator 1
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Enclosure:
Notice of Violation and Proposed Imposition of Civil Penalty 4
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