ML20080H014
| ML20080H014 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/10/1995 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20080H023 | List: |
| References | |
| NUDOCS 9502140353 | |
| Download: ML20080H014 (2) | |
Text
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'e IUA T essee Vaney Authonty. Post Office Box 2000. SoddeDamy Tennessee 37379 February 10, 1995 TVA-SQN-TS-93-04, Revision 2 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SQN) - TECHNICAL SPECIFICATION (TS) CHANGE 93-04, REVISION 2, CONTAINMENT VACUUM RELIEF LINES
References:
1.
SQN Licensee Event Report 50-327/92015 dated August 27, 1992 2.
TVA letter to NRC dated March 19, 1993, "Sequoyah Nuclear Plant (SQN) - Technical Specification (TS)
Change 93-04, Action Statement Clarification for Containment Vacuum Relief Penetrations" 3.
TVA letter to NRC dated May 16, 1994, "Sequoyah Nuclear Plant (SQN) - Technical Specification (TS) Change 93-04, Revision 1, Containment Vacuum Relief System" In accordance with 10 CFR 50.90, we are enclosing a requested amendment to Licenses DPR-77 and DPR-79 to change the TSs of SQN Units 1 and 2.
The proposed change revises the containment isolation valve Specification 3/4.6.3 and the vacuum relief valve Specification 3/4.6.6 to address the dual functions of SQN's containment vacuum relief system.
Revision 2 of TS 93-04 is based on recent discussions with the NRC staff.
The information in this revision supersedes the information previously provided in References 2 and 3.
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 performed pursuant to 10 CFR 50.92 is provided in Enclosure 3.
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- a U.S. Nuclear Regulatory Commission Page 2 February 10, 1995 The immediate corrective action in Reference 1 involves a compensatory action that requires expedient actions by Operations to remain within the TS allowed outage time. NRC staff review and approval are requested as soon as possible to eliminate this potential plant shutdown concern. TVA requests a 45-day implementation period for this TS change following issuance.
.Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734.
Sincerely, A,l1.2/dl R. H. Shell Manager SQN Site Licensing Sworn to apa subscribef pefore me
/OL day of < -trItM/2OJ 1995 GMA iJ iWD LJ Nota /y'P'ublic
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My Commission Expires M O[
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Enclosures cc (Enclosures):
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Conunission One White Flint, North 11555 Rockville Pike i
Rockville, Maryland 20852-2739 i
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 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-0199
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