ML20207Q505
| ML20207Q505 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/20/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Youngblood B NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20207Q506 | List: |
| References | |
| NUDOCS 8701270440 | |
| Download: ML20207Q505 (3) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place SAN 20 B8I U.S.NuclearRegislatoryCommission Attn: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention: Mr. B. J. Youngblood In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT - REACTOR VESSEL SURVEILLANCE CAPSULE U ANALYSIS
SUMMARY
REPORT Technical specification 4.4.9.1.2 for unit 1 of the Sequoyah Nuclear Plant requires the reactor vessel material irradiation surveillance specimen to be.
removed and examined at intervals required by 10 CFR 50 Appendix H in accordance with the schedule specified by Table 4.4-5 of the unit 1 technical specifications. Enclosure 1 provides the summary report for the reactor vessel surveillance capsule U as required by Appendix H to 10 CFR 50.
The enclosed report is titled, " Reactor Vessel Material Surveillance Program for Sequoyah Unit No. 1: Analysis of Capsule U."
The enclosed report was originally required to be submitted to NRC within one year from withdrawal from the reactor. As documented in the October 28, 1986 letter from T. M. Novak to S. A. White, NRC approved a 3-month extension request to allow the report to be submitted on or before January 28, 1987.
Based on the results and recommendations in the enclosed report, we plan to submit a technical specifications change for unit 1 to revise the lead factors and withdrawal times as shown in enclosure 2 (Revision of Table 4.4-5 to be proposed) before startup of unit 1.
The next set of specimens, capsule X, is scheduled by the revised table to be withdrawn at approximately 5.6 effective full power years (EFPY) instead of 5.0 EFPY as presently required in the current unit 1 technical specifications.
Based on the results of the analysis of the surveillance capsule U, no changes in the technical specification pressure temperature limit curves, figures 3.4-2 and 3.4-3 of the unit 1 technical specifications are required at this time.
These pressure temperature limit curves are valid for a RTnor (1/4T) up to 146*F and a Rinor (3/4T) up to 125*F. Our projections, which are based on fluence data from the report, indicate that RTnor (1/4T) will reach 146 F in approximately 14.0 EFPY and RTuor (3/4T) will reach 125 F in approximately 8.9 EFPY.
By utilizing the methods used to develop the pressure temperature curves in the summary technical report, the pressure temperature limit curves 8701270440 87012C SrSk PDR ADOCK 05000327" P
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.j-U.S. Nuclear Regulatory Commission 6AN 20 987 will be acceptable for approximately 8.9 EFPY.
However, we will reassess the need for technical specification revisions after the results from the analysis of capsule X are available.
If you have any questions regarding this subject, please call M. J. Burzynski at (615) 870-6172.
Very truly yours, TENNESSEE VALLEY AUTHORITY R.
ridley, D rector Nuclear Safety and Licensing Enclosures cc (Enclosures):
U.S. Nuclear Regulatory Commission Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NH, 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, Tennessee 37319
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1 ENCLOSURE 1 FINAL
SUMMARY
REPORT OF
" REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM FOR SEQUOYAH UNIT NO. 1:
ANALYSIS OF CAPSULE U" 4
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