ML18033A990
| ML18033A990 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/02/1989 |
| From: | Wilson B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18033A989 | List: |
| References | |
| 50-259-89-38, 50-260-89-38, 50-296-89-38, NUDOCS 8910200119 | |
| Download: ML18033A990 (4) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Tennessee Valley Authority Browns Ferry 1, 2, and 3
Docket Nos. 50-259, 50-260, and 50-296 License Nos.
DPR-33, DPR-52, and DPR-68 During the Nuclear Regulatory Commission (NRC) inspection conducted on August 16 - September 15, 1989, a violation of NRC requirements was identified.
The violation involved failure to comply with procedures for the performance of post maintenance testing.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1989),
the violation is listed below:
Technical Specification section 6.8.1.1.c requires that written procedures be established, implemented, and maintained covering test activities for safety related equipment.
Site Director Standard Practice 2.1, Site Procedures and Instructions, requires that the site be operated and maintained in accordance with
- written, approved procedures and instructions which have been formally issued and distributed for use.
Plant Manager Instruction 6.2, Conduct of Maintenance, requires that post maintenance testing (PMT) be performed on all plant process equipment following all corrective maintenance activities.
Contrary to the above, following the performance of scheduled maintenance, established procedures were not properly implemented in the following examples:
a.
The required PMT designated on the maintenance request (MR) was not performed following scheduled maintenance on the "3C" Diesel Generator (DG) auto-start lockout relay on August 4, 1989.
The "3C" DG was subsequently declared operable without performance of the PMT.
b.
The required PMT was not performed following scheduled maintenance on the "D2" Residual Heat Removal Service Water (RHRSW) pump on August 16,
- 1989, and on the "D3" RHRSW pump on September 1, 1989.
In both cases the PMT designated in the MR was not accomplished prior to returning the applicable components to service.
The above examples constitute a Severity Level IV Violation (Supplement I) applicable to all three units.
l Tennessee Valley Authority Browns Ferry 1, 2, and 3
2
'ocket Nos. 50-259, 50-260, and 50-296 License Nos.
DPR-33, DPR-52, and DPR-68 Pursuant to the provisions of 10 CFR 2.201, Tennessee Valley Authority is, hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control
- Desk, Washington, DC
- 20555, with a copy to the Associate Director for Special
- Projects, Office of Nuclear Reactcor Regulation, and a copy to the NRC Resident Inspector, Browns Ferry, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION 0
Dated at Atlanta, Georgia this Q~h "day of October, 1989 ruce A. Wilson, Assistant Director for Inspection Programs TVA Projects Division Office of Nuclear Reactor Regulation