ML20057D669
| ML20057D669 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/01/1993 |
| From: | Fenech R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20057D670 | List: |
| References | |
| TVA-SQN-TS-93, TVA-SQN-TS-93-0, NUDOCS 9310050160 | |
| Download: ML20057D669 (3) | |
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~ Tennesseo Vaney Authority Post Othce Box 2000, Soddy Daisy Tennessee 37379-2000
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Robert A. Fenech i
Vice Presdent, Sequoyah Nuclear Plant October 1, 1993 TVA-SQN-TS-93-09 10 CFR 50.90 I
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-U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 f
Gentlemen:
In the Matter.of
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Docket Nos. 50-327 Tennessee Valley-Authority
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50-328 i
SEQUOYAH NUCLEAR FIANT (SQN) - TECHNICAL SPECIFICATION -(TS) CHANGE 93-09,
" REVISED SETPOINTS AND TIME DELAYS FOR THE LOSS-OF-POWER INSTRUMENTATION" '
In accordance with 10 CFR 50.90, we are enclosing a requested amendment i
to Licenses DPR-77 and DPR-79 to change the TSs of SQN Units 1 and 2.
I The' proposed change revises the setpoints and. time delays for the auxiliary feedweter (AFW) loss-of-power and 6.9-kilovolt (kV) shutdown board loss-of-voltage and degraded-voltage instrumentation in Items 6 and 7 of TS Table 3.3-4, respectively. These changes are required to support proposed modifications to the SQN loss-of-power instrumentation.
The proposed values for this' instrumentation are the result.of recent
=l calculations for minimum-voltage requirements to maintain adequate voltage for safety-related loads. These values, when implemented, will t
enhance the ability to ensure that the operating voltage levels will not impact electrical loads-such that safety functions cannot be maintained.
In addition, changes.to Tables 3.3-3, 3.3-5, 4.3-2, and the AFW bases have been incorporated to reflect the new design'and logic for the loss-of-voltage and degraded-voltage instrumentation and to incorporate enhancements to the affected TS sections.
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The proposed TS change is identified in Enclosure 1.
The justification for the proposed TS change is provided in Enclosure 2.
A proposed determination of no significant hazards consideration pe,rformed pursuant to'10 CFR 50.92 is provided in Enclosure 3.
I Implementation.of the proposed changes to the TS will require that the associated physical plant modifications be performed at the same time.
The present TSs include specific setpoint ranges that do not agree with 04006)
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- s U.S. Nuclear Regulatory Commission Page 2 October 1, 1993 the proposed values and implementation of these changes cannot be executed without a TS amendmat. Therefore, TVA requests that implementation of this revision be dependent upon the associated modification activities such that TS implementation will not be required until completion of plant changes. The current schedule for implementation of these modifications to the loas-of-power instrumentation for both units is during the Unit 2 Cycle 6 refueling outage.
Please direct questions concerning this issue to Keith C. Weller at (615) 843-7527.
Sincerely, hbY
~L<A Robert A. Fenech Sworn to and subscr bed before me this./_41_dayof 1993 Notary Publi fly Conunission Expires
, 'l 7 Enclosures cc: See page 3 i
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.s U.S. Nuclear Regulatory Commission Page 3 October 1, 1993 Enclosures cc-(Enclosures):
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director (w/o Enclosures)
Division of Radiological Health 3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711
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