ML18033B269
| ML18033B269 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/17/1990 |
| From: | Wilson B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18033B268 | List: |
| References | |
| 50-259-90-05, 50-259-90-5, 50-260-90-05, 50-260-90-5, 50-296-90-05, 50-296-90-5, NUDOCS 9004250255 | |
| Download: ML18033B269 (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 February 16 - March 16, 1990, violations of NRC requirements were identified.
The violations involved failure to follow procedures and to establish compensatory fire protection measures.
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:
A.
Technical Specification (TS)
Section 6.8.1.1a requires that written procedures be established, implemented and maintained cover ing applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Appendix A of Regulatory Guide 1.33 includes operating procedures for onsite AC power sources and the reactor protection system as recommended procedures.
Site Directors 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.
Contrary to the above, on March 1, 1990, during the performance of Procedure O-OI-57B, 480V/240V AC Electrical System Operating Instructions, procedures were not properly implemented in that the operator failed to check the normal feeder breaker AC volts greater than 450 volts as required by 0-0I-57B step 8.6.3 prior to transfer ring 480 volt power sources.
This is a Severity Level IV Violation (Supplement I) applicable to all three units.
B.
TS 3.11.E requires that the fire hose stations shown in Table 3. ll.c shall be operable whenever equipment in the areas protected by the fire hose stations is required to be operable.
When a fire hose station is inoperable, a gated wye shall be connected to the nearest operable hose station.
One outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station.
Contrary to the above, this requirement was not met for the following two examples:
9004250255 900417 F DE AXiOCI 0 0002~9 PDC
t 0
Tennessee Valley Authority Browns Ferry 1, 2, and 3
2 Docket Nos. 50-259, 50-260, and 50-296 License Nos.
On March 1,
- 1990, a
NRC inspector identified that inoperable hose stations for both Units 1 and 2, on reactor building elevations
- 639, 621,
- 593, and
- 565, were protected by a single gated wye connection connected to a single 50 foot roll of hose from operable hose stations at each elevation in Unit 3.
The length of connected hose was insufficient to provide coverage for Units 1 and 2.
The combined length of the reactor buildings is 425 feet.
2.
After reviewing the inspector's concerns in example
- one, the licensee determined that the hold order (0-90-60) which was issued to isolate the Unit 1 and 2 fire protection systems for a system outage had been expanded on March 1, 1990, to include Unit 3.
This resulted in the removal from service of all hose stations within all three reactor buildings.
This condition remained until the Unit 3 hose stations were returned to service on March 5, 1990.
This is a Severity Level IV Violation (Supplement I) applicable to all three units.
Pursuant to the provisions of 10 CFR 2.201, you are 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 Reactor 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.
FOR THE NUCLEAR REGULATORY COMMISSION B uce A. Wilson, Assistant Director for Inspection Programs TVA Projects Division Office of Nuclear Reactor Regulation Dated at Atlanta, Georgia this 10~
day of April 1990
l