ML20053A843
| ML20053A843 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/05/1982 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053A829 | List: |
| References | |
| 50-327-82-04, 50-327-82-4, 50-328-82-04, 50-328-82-4, NUDOCS 8205270345 | |
| Download: ML20053A843 (2) | |
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APPENDIX A NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 & 50-328 Sequoyah 1 and 2 License Nos. DPR-77 & DPR-79 As a result of the inspection conducted on February 6 - flarch 5,1982, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980),
the following violations were identified.
A.
10 CFR 50.59 requires that the licensee not make changes in the facility as described in the Final Safety Analysis Report (FSAR) if the change involves an unreviewed safety question.
Prior to making a change in the facility as described in the FSAR the licensee shall perfonn a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
Contrary to the above, the licensee changed a system as described in the FSAR without performing a written safety evaluation to determined that the change did not involve an unreviewed safety question. On February 10, 1982 the licansee blanked the floor drains in the Unit 2 west main steam valve room and installed portable pumps to redirect the secondary steam leakage condensate to the yard drainage system.
The floor drains in the west main steam valve room normally drain to the Floor Drain Collecting Tank in the Auxiliary Building per FSAR figures 9.3-9 and 9.3-10.
This is a Severity Level IV Violation (Supplement I.D.1.).
Applicable to Unit 2.
l B.
Technical Specification 3.1.3.3 requires that one rod position indicator (excluding demand position indication) shall be operable and capable of l
determining the control rod position within 12 steps for each shutdown or I
control rod not fully inserted in modes 3, 4 and 5 when the reactor trip breakers are closed.
Contrary to the above, the licensee did not maintain one rod position indicator operable for each shutdown rod not fully inserted capable of indicating rod position within 12 steps in flodes 3, 4 and 5.
At various times on both units since initial operation the licensee has maintained shutdown control rods withdrawn with the reactor coolant system below normal operating temperature (NOT). With rod position indication calibrated at NOT, it will not indicate actual rod position within 12 steps at less than NOT.
This is a Severity Level V Violation (Supplement I.E.).
Applicable to Units 1 and 2.
82052747 f
Tennesse Valley Authority 2
Docket Hos. 50-327 & 50-328 Notice of Violation License Nos. DPR-77 & DPR-79 Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) admission or denial of the alleged viola-tions; (2) the reasons for 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.
Corisideration may be given to extending your response time for good cause shown.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Date: APR 0 51992 p
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