ML20083P756
| ML20083P756 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/13/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8404200148 | |
| Download: ML20083P756 (2) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II S
April 13, 1984 Director of Nuclear Reactor Regulation l
Attention:
Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Ms. Adensas:
f In the Matter of
)
Docket No. 50 -327 l
3 Tennessee Valley Authority
)
Please refer to act letters to you dated November 14, 1983, and March 23 and April 3,1984 which requested an exemption for the Sequoyah unit 1 schedular requirements of 10 CFR 50.49(g). Your subsequent approval of the exemption was granted on April 11, 1984 via your letter to H. G. Parris.
l TVA has identified an additional 12 components which we have been unable to complete during the unit 1, cycle 2 refueling outage. Enclosed is a listing of these components. These components have been previously identified in TVA's May 20, 1983 final rule submittal (D. S. Kammer to you) and justification for continued operation (JCOs) have been provided to you by previous Electrical Equipment Environmental Qualification Report (EEEQR) submittals. The JCOs provided are still applicable.
We are therefore requesting an extension for the remaining 12 components to the unit 1, cycle 3 outage which is now scheduled for June through September of 1985.
If you have any questions concerning this matter, please get in touch with K. P. Parr at FTS 858-2685.
Very truly yours, TENNESSEE VALLEY AUTHORITY
\\,
L. M. Mills, Manager Nuclear Licensing Sworn,
nd subsc bed fore me this
' day of A,t 1984 Notary Publio y
My Commission Expires I -
Enclosure oct U.S. Nuclear Regulatory Commission (Enclosure)
Region II Attnt Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 g g Atlanta, Georgia ~
TVA SOTH ANNIVERSARY q
M An Equal Opportunity Employer
ENCLOSURE NCR 2B 8152 The six components listed below are used as containment isolation valves.
It was determined that certain environmental conditions could exist that might cause a failure of the limit switches associated with the valves listed below. The failure of the limit switches might permit the valves to reopen when a containment isolation signal is reset; therefore, a design change to install a seal-in circuit independent of the limit switch position was required to prevent an inadvertent opening of these containment isolation valves. The necessary drawings to perform this modification were not completed and issued until March 1984. Tais did not allow sufficient time for proper planning and scheduling of thi.s modifica-tion during the cycle 2 refueling outage. This modification will require extensive wiring changes (i.e., cable pulling, terminations, etc. ), but can be completed during the non-outage period following this refueling outage; therefore, this modification will be scheduled to be completed tefore March 31, 1985, but no later than the next refueling outage. The following components are affected.
FCV-62-72, 73, 74 FCV-77-16 FCV-87-7, 8 NCR EEB 8037 The six pressure switches listed below are located on the motor-driven auxiliary feedwater pump's suction header and are designed to initiate a automatic switchover from the normal condensate storage tank water supply to the essential raw cooling water system in the event of a low supply header pressure from the condensate storage tank. To meet the postulated environmental conditions at the pressure switches, it was determined that the p 'sently installed pressure switches could not be qualified and new pressure switches would be required. The new switches were procured and delivered to the site. Subsequently, these items were non-conforned at the site because of inadequate vendor documentation. Attempts to correct this inadequacy within a timeframe to support the cycle 2 outage were unsuccess ful. This modification will be scheduled for completion before March 31, 1985, but no later than the next refueling outage. The following components are affected.
PS-3-139 A, B, D PS-3-144 A, B, D
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