ML20044B988

Application for Amends to Licenses DPR-77 & DPR-79, Consisting of Proposed TS Change 93-002, Removal of 10CFR50,App J Containment Test Requirements from Ts.

ML20044B988
Person / Time
Site:	Sequoyah
Issue date:	03/10/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20044B989	List: ML20044B988 ML20044B990
References
TVA-SQN-TS-93, TVA-SQN-TS-93-0, NUDOCS 9303160073
Download: ML20044B988 (2)

Text

{{#Wiki_filter:7......_. 3,, 6- ' Tennessee Valley Authonty, Post Othce Box 2000. Saady-Daisy Tennessee 37379-2000 l Robert A, Fenech Vice President, Sequcriah f4uclear Plant i March 10, 1993 , TVA-SQN-TS-93-02 10 CFR 50.90 , U.S. Nuclear Regulatory Commission ATTN: Document Control Desk  ; Washington, D.C. 20555 Gentlemen: , l In the Matter of ) Docket Nos. 50-327. l Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - TECHNICAL SPECIFICATION (TS) CHANGE 93-02, ,

                " REMOVAL OF 10 CFR 50, APPENDIX J CONTAINMENT TEST REQUIREMENTS FROM TS"                                           l

Reference:

TVA letter to NRC dated January 7, 1993, "Sequoyah Nuclear' . Plant (SQN) - Unit 2 - 10 CFR 50, Appendix J, Exemption Request" In accordance with 10 CFR.50.90, we are enclosing a requested' amendment-to License DPR-77 and DPR-79 to change the TSs..of SQN Units 1 and 2. .The e proposed change incorporates a reference to the test requirements of-10 CFR 50, Appendix J, " Primary Reactor Containment Leakage Tes. ting for  ! Water-Cooled Power Reactors,".and removes'the-current detailed test requirements from TSs. Other related containment system specifications have been appropriately revised to remove references that a're no longer .[ applicable. An unrelated change to a footnote in TS Table:3.6-2 provides a needed clarification to SQN's TS. The proposed changes have been-modeled.after the recently approved standard TSs for Westinghouse Electric Corporation plants (NUREG-1431), and are intended to reduce the. i..j need for future duplicative TS changes associated with Appendix J-  ; exemptiens. .i L The proposed TSl change is identified in Enclosure'1. The justification j for the proposed TS change.is provided in Enclosure 2. A proposed' I determination of no significant hazards consideration performed pursuant  ! to 10 CFR 50.92 is provided in Enclosure 3. It should be noted that TVA's proposed.TS amendment contains changes for

               . SQN Unit 2. that are needed tre support the 10 CFR 50, Appendix J,                                                 i 9303160073 930310                         .

PDR ADOCK 050003273 -Mn/4- '! P -PDR y y L/i / =

                                                                                                                         .l[l

w 3

               %,                                                                               ~
        'A U.S. Nuclear Regulatory Commission Page 2                                                                          ;

March 10, 1993 I exemption request provided in the above referenced letter. Accordingly, NRC approval of this change is needed before the Unit 2 Cycle 6 refueling i outage currently scheduled to start September 17, 1993. 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) S43-7734. Sincerely,  ;

                              $        -A Robert A. Fenech Sworn to and subscribed before me                                             ,

this /d day of 22/21cl_. 1993 L211C.A YW!arvN No/ary/Public My Commission Expires M 9 /~ Nd P Enclosures cc (Enclosures): Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission i One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2/39 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 i Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II I 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-0199  ; ~}}