ML18033B711
| ML18033B711 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/10/1991 |
| From: | Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18033B710 | List: |
| References | |
| 50-259-91-10, 50-260-91-10, 50-296-91-10, NUDOCS 9105210230 | |
| Download: ML18033B711 (5) | |
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 March 16, 1991 - April 19,
- 1991, two violations of NRC requirements were identified.
The first violation involved examples of failure to implement testing program requirements.
The second violation was for failure to maintain Technical Specification (TS) requirements for compensatory sampling.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
( 1991),
the violations are listed below:
A.
10 CFR 50 Appendix B, Criterion XI, Test Control, requires that a test program shall be established to assure that all testing required to demonstrate that structures,
- systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.
Test results shall be documented and evaluated to assure that test requirements have been satisfied.
Contrary to the
- above, activities involving test control were not correctly implemented in accordance with requirements for the following two examples:
l.
Adequate post modification testing (PMT) requirements were not stipulated following completion of design change P3051.
The reactor building to torus vacuum breakers opened unexpectedly when torus pressure was greater than reactor building pressure during the integrated leak rate test on March 18, 1991.
The vacuum breakers are designed to vent air from the reactor building to the torus when reactor building pressure exceeds torus pressure by 0.5 psig.
2.
During the return to service activities for the A3 residual heat removal service water
- pump, PMT was not completed.
The pump was not caution tagged as required by procedure SDSP 14.9, for components awaiting PMT.
The pump failed to start on October 4,
- 1990, when aligned to start for testing the 3D diesel generator.
The cause was later determined to be a wiring error during implementation of DCN W4515A.
The same pump failed to autostart on September 27,
- 1990, during diesel generator testing and the cause had not been determined as of October 4, 1990.
This is a Severity Level IV Violation (Supplement I) applicable to all three units.
9105210230 910510 PDR ADOCK 05000259 G
Tennessee Val ley Authority t
Browns Ferry I, 2, and 3
Docket Nos. 50-259, 50-260, and 50-296 License Nos.
TS Section 3.2.D requires the radioactive liquid effluent monitoring instrumentation listed in Table 3.2.D to be operable when effluent releases are in progress via the instrument pathway.
Table 3.2.D includes Raw Cooling Water (RCW) monitor 2-RM-90-132.
TS 3.2.D also requires that grab samples be collected and analyzed at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the RCW monitor is inoperable and effluent releases are continued.
TS Section 3.2.K requires the radioactive gaseous effluent monitoring instruments listed in Table 3.2.K to be operable.
Table 3.2.K includes Reactor/Turbine Building Ventilation monitors 1=RM-90-250, 2-RM-90-250, and 3-RM-90-250 and Radwaste Building Ventilation monitor 0-RM-90-252.
TS 3.2.K also requires that actions be taken whenever the instruments are declared inoperable and effluent releases are being conducted through an affected pathway.
The required actions include a flow rate estimate at least once every four hours.
Contrary to the
- above, on March I, 1991, the licensee determined that surveillance instruction data was not valid for the following two examples:
1.
Flow rate estimates taken on December 5,
1990, at 4:00 a.m., for inoperable monitors 1-RM-90.-250, 2-RM-90-250, 3-RM-90-250, and O-RM-90-252.
2.
A compensatory grab sample taken on December 11, 1990, at 10:03 a.m.,
for inoperable RCW monitor 2-RM-90-132.
This is a Severity Level IV Violation (Supplement I) applicable to all three Units.
Pursuant to the provisions of 10 CFR 2.201, 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, and 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 Notice, an order may be issued to show
Tennessee Val ley Authority t
Browns Ferry 1, 2, and 3
Docket Nos. 50-259, 50-260, and 50-296 License Nos.
DPR-33, DPR-52, and DPR-68 cause 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.
FOR THE NUCLEAR REGULATORY COMMISSION Dated at Atlanta, Georgia this l04 day of May 1991 TVA Projects