ML20099K271
| ML20099K271 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/21/1985 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20099K248 | List: |
| References | |
| NUDOCS 8503200223 | |
| Download: ML20099K271 (2) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 B5 JM123 AW400 Chestnut StrY Tower January 21, 198 5 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administcator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Mr. O'Reilly:
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - NRC.-0IE REGION II INSPECTION REPORT 50-327/84-35 AND 50-328/84 RESPONSE TO VIOLATION The subject OIE inspection report dated December 28,1984 from s
D. M. Vercelli to H. G. Parris cited TVA with one Severity Level V Violation. Enclosed is the response to the item of violation in the subject inspection report.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY R. H. Shell Nuclear Engineer Enclosure oc (Enclosure):
A' r. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8503200223 850226 PDR ADOCK 05000327 G
PDR An Equal Opportunity Employer
ENCLOSURE RESPONSE - NRC-0IE INSPECTION REPORT NOS. 50-327/84-35 AND 50-328/84-35 D. M. VERRELLI'S LETTER TO H. G. PARRIS DATED DECEMBER 28, 1984 Items 50-327/84-35 and 50-328/84-35 Technical Specification 6.8.1 requires that written procedures be established, covering activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Paragraph 3 of Appendix A requires specific procedures for the Emergency Core Cooling System (ECCS). System Operating Instruction (SOI)-63.1 was established to satisfy this requirement.
Contrary to the above, adequate procedures were not established in that Valve Checklists 63.1A-3 and 63.1A-4, Revision 26, of S0I-63.1, Emergency Core Cooling System, Revision 30, each failed to list a level transmitter root valve for the cold leg accumulators.
This is a Severity Level V violation (Supplement I).
1.
Admission or Denial of the Alleged Violation TVA admits the violation occurred as stated.
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2.
Reason for the Violation if Admitted During original compilation or subsequent revision of the valve checklist, root valve 63.362A for level transmitter LT-63-81 and root valve 63-366A for level transmitter LT-63-60 were inadvertently lef t out.
3.
Corrective Steps Which Have Been Taken and Results Achieved A temporary change was made to the procedures involved on November 29, 1984, to include the missing root valves. On December 12, 1984, the temporary procedure change became a permanent revision.
4.
Corrective Steps Which Will Be Taken To Avoid Further Violations Personnel periodically review procedures which involve the operation of the plant. Procedures will continue to be verified for accuracy, and to reflect the current status of the plant on a continuing basis. We believe this inadvertent deletion of the two root valves to be an isolated occurrence, and no other corrective actions are required.
5.
Date When Full Compliance Will Be Achieved Full compliance was achieved on December 12, 1984.
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