ML20045C132
| ML20045C132 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 06/15/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20045C129 | List: |
| References | |
| 50-327-93-300, 50-328-93-300, NUDOCS 9306220114 | |
| Download: ML20045C132 (2) | |
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ENCLOSURE 1 NOTICE OF VIOLATION i
Tennessee Valley Authority Docket Nos.: 50-327 and 50-328 Sequoyah License Nos.: DPR-77 and DPR-79 l
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During an NRC inspection conducted on May 17-20, 1993, a violation of NRC l
requirements was identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," the violation is listed i
below:
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 accomplished in accordance with these instructions, procedures, or drawings.Section IV of the Sequoyah Procedures Generation Package (Verification and Validation Program) article D.1 requires that the Emergency Operating Procedures be technically correct and that the step deviation document be accurate and complete.
Contrary to the above, 1.
The Step Deviation Document (EPM-3) was not accurate and complete in that section 3.2.3 did not agree with step 10.b of ES-3.2 (Post-Steam Generator Tube Rupture Cooldown by Ruptured S/G Depressurization).
EPM-3 stated that the Blowdowr. method was chosen as the preferred means to depressurize the ruptured steam generator in ES-3.2; however, the actual procedure used the condenser steam dump valves as the preferred method.
2.
The Step Deviation Document was not technically correct in that it stated that the intent of Westinghouse Owners Group guideline ES-l 0.0 was fully met by the Sequoyah Emergency Operating Procedures due to the transition steps within the instructions and inclusion of additional transitions on the foldout pages of applicable instructions; however, the transition from E-3 to E-1 could not be made within the framework of the Sequoyah Emergency Operating Procedures.
This is a Severity Level IV violation (Supplement I).
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, D.C.
20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:
(1) 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 9306220114 93061S PDR ADOCK 05000327 Y
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3 corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or Demand for Information 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 /8 day of 1993 i
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