ML20004D792
| ML20004D792 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/03/1981 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20004D793 | List: |
| References | |
| NUDOCS 8106100044 | |
| Download: ML20004D792 (1) | |
See also: IR 05000327/1981012
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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Tennessee Valley Authority
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ATTN:
H. G. Parris
Manager of Power
500A Chestnut Street Tower II
Chattanooga, TN 37401
Gentlemen:
Subject: Report Nos.
Q:-32218
2)an
Thank you for your letter of May 11, 1981, informing us of steps you have
taken to correct the violation concerning activities under NRC Operating
License No. DPR-77 and NRC Construction Permit No. CPPR-73 brought to your
attention in our letter of March 27, 1981. We will examine your corrective
actions and plans during subsequent inspections.
We appreciate your cooperation with us.
Sincerely,
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R. C.
ewis, Acting Director
Division of Resident and
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Reactor Project Inspection
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cc:
H. J. Green, Division Director
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G. G. Stack, Project Manager
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J. M. Ballentine, Plant
Superintendent
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J. F. Cox, Supervisor, Nuclear
Licensing Section
M. J. Burzynski, Project Engineer
H. N. Culver, Chief, Nuclear
Safety Review Staff
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710 6100 0f'/
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1400 Chestnut Stt eet Tower II
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Mr James P. O'Reilly, Director
Office of Inspection and Enforcement
U.S. Nuclear Regulatory Commission
Region II - Suite 3100
101 Marietta Street
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - NRC-0IE REGION II INSPECTION REPORT
50-327/81-12, 50-328/81-09 - REVISED RESPONSE TO VIOLATION
The subject inspection report dated Ma:'ch 27, 1981, cited TVA with one
Severity Level IV Violation in accordance with 10 CFR 2.201.
A response to
the violation was submitted on April 17, 1981. Enclosed is our revised
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response as requested by D. Quick.
If you have any questions, please get in touch with D. L. Lambert at
FIS 857-2581.
To the best of my knowledge, I declare the statements contained herein are
complete and true.
Very truly yours,
TENNESSEE VALLEY AUTHORITY
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L2-M. Mills, Manager
Nuclear Regu. " w and Safety
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Enclosure
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Mr. Victor Stello, Director (Enclosure)
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Office of Inspection and Enforcement
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U.S. Nuclear Regulatory Commission
Washington, DC 20555
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ENCLOS0URE
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2
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REVISED RESPONSE TO VIOLATION 50-327/81-12-01
Violation 50-327/81-12-01
Technical Specification 3.6.1.1 requires that containment integrity shall
be maintained in modes 1, 2, 3, and 4 and that containment penetration
isolation be verified periodically.
Containment -integrity is based in part
on 10 CFR 50, Appendix A, Criterion 56, which requires that lines that
penetrate containment and are open to the containment atmosphere be
isolated by one locked closed valve inside and one locked closed valve
outside containment.
Contrary to the above, containment integrity has not been adeauately
maintained or verified in that, position requirements for the inside
containment isolation valve for the service air system, valve 1-33-704, was
not included in system operating instruction S0I-88.1, Containment
Isolation Integrity. Valve 1-33-704 was normally maintained in the open
position; however, the outside containment isolation valve, 1-33-740, was
maintained closed and periodically verified to be in the proper position
during unit operation.
This is a Severity Level IV Violation (Supplement I.D.3.).
Admission or Denial of the Alleged Violation
TVA admits the violation occurred as stated.
Reason for the Violation if Admitted
The original design and construction was that valve 1-33-704 was a check
valve. The valve was subsequently replaced with a manually operated valve
which should have been normally closed. When this modification was made,
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drawing 47W846-2 was marked up indicating this change and submitted to
drawing control. This was the correct procedure for having the drawing
revised to include the modification; however, drawing control incorrectly
revised the drawing to show a normally open valve. When the valve lists in
SOI-88.1 and SI-14 were made, this valve was therefore omitted.
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Corrective Steps Which Have Been Taken and 'Results Achieved
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Upon the discovery that valve 1-33-704 had been incorrectly identified as a
normally open manually nperated valve, a temporary . alteration control form
was issued to ensure that this valve was closed and containment integrity
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maintained.
Corrective Steps Which Will Be Taken to Avoid Further Violations
Drawing 47W846-2 is being changed to show valve 1-33-704 as a normally
closed manually operated valve.
Operating instruction SOI-88.1 and
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surveillance instruction SI-14 are being revised to include valve 1-33-
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704. Additionally, a drawing review was performed, and comparisons to the
valves listed in S0I-88.1 and SI-14 were made. This was done to confirm
that there were no other valves incorrectly identified on the drawings and
that there were no additional valves incorrectly positioned.
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Date When Full Compliance Will Be Achieved
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We are now in full compliance.