ML20205P593
| ML20205P593 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/22/1986 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205P587 | List: |
| References | |
| 50-327-86-11, 50-328-86-11, NUDOCS 8605210474 | |
| Download: ML20205P593 (2) | |
Text
r ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah License Nos. DPR-77 and DPR-79 The following violations were identified during an inspection conducted on February 3-7, 1986.
The Severity Level was assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).
1.
10 CFR 50, Appendix B, Criterion V requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accom-plished in accordance with these instructions, procedures, or drawings.
Contrary to the above, a.
On February 4 and 5,1986, deficiencies were identified during perfor-mance of Electrical Maintenance Instruction MI-10.9 which demonstrated that the procedure was inadequately prescribed and was not being properly implemented. These deficiencies included:
(1) The procedure calls for five undervoltage (UV) trips prior to returning the reactor trip circuit breaker to service after maintenance, but Westinghouse recommends ten UV trips in NSD-TB-83-02, Revision 1, page 5.
(2) The technical review of the procedure was inadequate due to such significant discrepancies as:
poor quality drawings, which were difficult to read, typographical errors which caused the technician to stop work, the voltage specified to energize the undervoltage coil during maintenance was greater than the actual voltage inside the reactor trip breaker cabinet; the procedure calls for replace-ment of the undervoltage trip attachment (UVTA) after 1250 opera-tions, but provides no formal tracking of the trip attachments actuations and Step 6.3.11.3 requires that the breaker trip force be recorded, but provides no place for recording the trip force.
(3) The licensee did not have unique identification numbers for the reactor trip breakers prior to October 1985.
Thus, the mainte-nance history on each breaker was not readily traceable.
b.
On February 5 and 6,1986, deficiencies were identified during perfor-mance of Surveillance Instruction SI-227.1 which demonstrated t..at the 8605210474 860422 PDR ADOCK 05000327 O
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Tennessee Valley Authority 2
Docket Nos. 50-327 and 50-328 Sequoyah License Nos. DPR-77 and DPR-79 procedure was inadequately prescribed and was not being properly implemented by instrument mechanics during post maintenance testing of reactor trip breakers. These deficiencies included:
(1) The procedure did not provide verification that appropriate initial conditions were established prior to performing the procedure.
Consequently, the test could not be successfully performed on February 5, 1986.
(2) Step 9.0 of the procedure was vague in explaining use of activat-ing test pushbuttons.
As a result, the mechanic involved initially was unable to properly initiate the test.
(3) Test personnel were not familiar with the procedure and methods used to identify components inside reactor trip breaker cabinets.
This resulted in miswiring of test leads and misinterpretations of the procedure.
This is a Severity Level IV violation (Supplement I).
Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including:
(1) admission or denial of the alleged violations; (2) the reasons fcr the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid.
further violations; and (5) the date when full compliance will be achieved.
Security or safeguards information should be submitted as an enclosure to facili-tate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.
Date: