ML20095D543
| ML20095D543 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/08/1995 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20095D547 | List: |
| References | |
| NUDOCS 9512130150 | |
| Download: ML20095D543 (4) | |
Text
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IUA Tennessee Vaney Authonty, Post OMee Box 2000 SoddrDa+sy Tennessee 37379 December 8,1995 TVA-SON-TS-93-09, Revision 1 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)
CHANGE 93-09, REVISION 1, " REVISED SETPOINTS AND TIME DELAYS FOR THE LOSS-OF-POWER INSTRUMENTATION"
References:
- 1. TVA letter to NRC dated October 1,1993,"Sequoyah Nuclear Plant (SQN) - Technical Specification (TS) Change 93-09, ' Revised Setpoints and Time Delays for the Loss-Of-Power instrumentation'"
- 2. NRC letter to TVA dated May 24,1994, " Issuance of Amendments (TAC Nos. M87872 and M87873)(TS 93-09)"
- 3. NRC letter to TVA dated August 22,1995, " Issuance of Technical Specification Amendments for the Sequoyah Nuclear Plant, Units 1 and 2 (TAC Nos. M92212 and M92213)(TS 93-09)"
In accordance with 10 CFR 50.90, we are enclosing an amendment to Licenses DPR-77 and DPR-79 to change the TSs of SON Units 1 and 2. The proposed change revises the setpoints and time delays for the auxiliary feedwater (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 rnodifications to the SON loss-of-power instrumentation. The proposed values for this instrumentation are the result of calculations for minimum-voltage requirements to maintain adequate voltage for safety-related loads. These values, when implemented, will 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 j
for the loss-of-voltage and degraded-voltage instrumentation and to incorporate enhancements to the affected TS sections.
10005G 9512130150 951208
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DR ADDCK 050 327 De
i U.S. Nuclear Regulatory Commission i
Page 2 December 8,1995 By Reference 1, TVA su'omitteo a TS change request to NRC that supported a i
modification to implement the changes described above. NRC approved these i
proposed changes by Reference 2. Subsequent detailed evaluations for the implementation of the modification indicated a significant impact existed to the allowed outage times and would require the removal of safety functions from service.
Therefore, TVA redesigned the modification to provide the proposed voltage i
protection enhancement without incurring the safety impact involved in the implementation of the original design. This revised change request supplements the
' original request provided by the reference.
The proposed TS change is identified in Enclosure 1. Enclosure 1 is a mark-up of the affected NRC approved TS pages issued by Reference 2 for Amendments 182 and 174 for Units 1 and 2 respectively. The justification for the proposed revision to this TS change is provided in Enclosure 2. The original no significant hazards -
consideration performed pursuant to 10 CFR 50.92 is not affected by the changes proposed in this submittal and is included in Enclosure 3.
NRC approved implementation of the original request, by Reference 3i upon~
installation of the proposed modification and TVA requests that this provision remain unchanged. TVA is currently staging the revised modification for implementation in March of 1996. Approval of this modification by March 1996 would support completion of the enhanced voltage protection scheme prior to the Unit 2 Cycle 7 refueling outage and would allow for outage work reductions provided by the qualification of the alternate 6.9-kV feeder breakers.
i Please direct questions concerning this issue to Keith Weller at (423) 843-7527.
Sincerely, kl R. H. Shell Manager SON Site Licensing d befo me Sworn gand subscr
's 2 day of 4 PM W /It) 1995 1
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Notary P'ublic
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Y i-Enclosures cc: See page 3 l
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a U.S. Nuclear Regulatory Commission i
Page 3-
. December 8,1995 i
' (Enclosures):
Mr. D. E. LaBarge, Project Manager 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 lgou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711
ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328
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(TVA-SON-TS-93-09, REVISION 1)
LIST OF AFFECTED PAGES l
l Unit 1 j
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3/4 3-27a 3/4 3-27b t) nit 2 3/4 3-27a 3/4 3-27b i
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