ML18036B056
| ML18036B056 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/02/1992 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18036B055 | List: |
| References | |
| 50-260-92-33, NUDOCS 9211100142 | |
| Download: ML18036B056 (3) | |
Text
ENCLOSURE 1
Tennessee Valley Authority Browns Ferry 2
'ocket No. 50-260 Licensee No.
DPR-52 During the Nuclear Regulatory Commission (NRC) inspection conducted on September 17 - October 16, 1992, violations of NRC requirements were iden-tified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, the violations are listed below:
A.
B.
Technical Specification Table 3.2.E, Instrumentation That Monitors Leakage Into Drywell, requires for drywell air sampling under action note three that upon receipt of alarm, immediate action will be taken to confirm the alarm and assess the possibility of increased leakage.
Alarm response procedure, l-ARP-0-3, requires for annunciator XA-55 12, RA-90-256A Drywell Leak Detection Radiation HI, that the operator request chemistry laboratory take and analyze a drywell atmosphere sample.
Contrary to the above, on September 25,
- 1992, immediate action was not taken to confirm an alarm at 2:55 a.m.,
on drywell detection radiation monitor detector, 2-RH-90-256.
The sample was requested but not performed.
At 7: 10 a.m.,
the monitor was declared inoperable and logged as inoperable because the particulate channel was erroneously in alarm.
Work order 92-61547-00 was initiated to troubleshoot and correct the problem with the particulate channel in alarm.
Later the 4 to 8 a.m.
unidentified floor leakage provided indication of increased drywell leakage and Unit 2 was shutdown.
This is a Severity Level IV Violation (Supplement I) applicable to Unit 2 only.
Technical Specification 3. 11.G. l.a, requires that with a required fire-rated sealing device inoperable, within one hour establish
- a. continuous fire watch on at least one side of the sealing device.
Implementing procedure for fire watches, FPP-2, Fire Protection
- Program, Attachment L, requires that the fire watch shall be on continuous alert for fire, signs of fire, and/or any act that, might result in a fire.
Contrary to the above, on October 2,
- 1992, a
NRC inspector identified that the fire watch established by Limiting Condition for Operation, 2-92-184.3. 11.G, for an inoperable fire wrap, was not on continuous alert and was inattentive in his duties.
This is a Severity Level IV Violation (Supplement I) applicable to Unit 2 only.
9211100142 921102 PDR ADOCK 05000259 8
Tennessee Valley Authority Browns Ferry 2
2 Docket No. 50-260 Licensee No.
DPR-52 Pursuant to the provisions of 10 CFR 2.201, the Tennessee Valley Authority is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, a copy to the NRC..
Resident Inspector, within 30 days of the date of. the letter transmitting this Notice of Violation.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(I) the reason for the violation, or if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the
~
date with full compliance will be achieved.
If an adequate reply is not received in the time specified in this'otice, an order or demand for informa-tion may be issued as to why the license should not be modified, suspended, or
- revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this p~J day ofMosa. ~1992