ML20211J065

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Forwards Revised Commitment to Amend FSAR Section 6.2.4 & Table 6.2.4-1 Re Containment Isolation Sys Design,By 880415. Sys Description Revised in Response to Unresolved Items Noted in Insp Repts 50-327/86-20 & 50-328/86-20
ML20211J065
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/13/1987
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To: Youngblood B
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
0608C, 608C, NUDOCS 8702260364
Download: ML20211J065 (3)


Text

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e TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSCE 374o1 SN 157B Lookout Place FEB 131987 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Office of Nuclear Reactor Regulation

' Washington, D.C. 20555 Attention: Mr. B. J. Youngblood In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328

$EQUOYAH NUCLEAR PLANT (SQN) - CONTAINMENT ISOLATION SYSTEM DESIGN REVIEW -

  1. ENAL SAFETY ANALYSIS REPORT (FSAR) UPDATE COMMITMENT 11 iimpection Report Numbers 50-327/86-23 and 50-328/86-20, transmitted from J. A 31shinski to S. A. White by letter dated April 23, 1986, identified unresuved items (URIs) 50-327/36-20-09 and 50-328/86-20-09, Containment Isolation Design Pertaining to the Chemical and Volume Control System. The subject URIs were the basis upon which NRC initiated a review of the containment isolation system design for SQN. To support both the closeout of the URIs and NRC review, we made an initial submittal to NRC on May 30, 1986, that provided a revised detailed description of the SQk containment isolation system decign. A supplemental submittal that addressed NRC concerns raised during the review of our initial submittal was made on September 24, 1986. A tnied submittal which addressed additional NRC concerns and superseded our previous two submittals detailing SQN containment isolation system design was made on January 2, 1987. It is our understanding that NRC is currently reviewing this third submittal.

Each of the three submittals also committed us to amend section 6.2.4 and table 6.2.4-1 of the SQN FSAR to reflect the revised containment isolation system design description as accepted by NRC. To date, that approval has not been received. Thus, section 6.2.4 and table 6.2.4-1 will not be modified to reflect the revised containment isolation system design as described in our January 2, 1987 submittal during the FSAR amendment effort currently underway at SQN. Rather, we have tentatively scheduled the amendment for the next annual FSAR amendment which is scheduled for April 15, 1987, pending notification of NRC acceptance of the text provided in our January 2, 1987 submittal.

This interpretation of this commitment was discussed with and agreed to by J. J. Holonich, of your staff, on January 30, 1987. Our commitment to amend the SQN FSAR is given in the enclosure to this submittal.

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Ao I An Equal Opportunity Employer

6 U.S. Nuclear Regulatory Commission FEB 131987 Please direct any additional questions that you may have regarding this or other SQN containment isolation issues to Timothy S. Andreychek at (615) 870-7470.

Very truly yours, TENNES2EE VALLEY AUTHORITY A

e . 1tQ R. Gridley, Director Nuclear Safety and Licensing Enclosure cc (Enclosure):

U.S. Nuclear Regulatory Commission Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia. 30323 Mr. J. J. Holonich Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. G. G. Zech, Director TVA Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennesseo 37319 1

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. ENCLOSURE SEQUOYAH NUCLEAR PLANTS UNITS 1 AND 2 CONTAINMENT ISOLATION SYSTEM DESIGN FSAR AMENDMENT COMMITMENTS ACTIVITY COMMITMENT DATE Amend FSAR to reflect revised April 15, 1988

  • containment isolation cystem design as accepted by NRC.
  • This commitment date is contingent upon receipt of NRC acceptance of the SQN containment isolation desi5 n description by September 15, 1987. If acceptance is not received by that d. ate, the commitment date slips one year.

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