ML20066B095
| ML20066B095 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/21/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066B080 | List: |
| References | |
| NUDOCS 8211060384 | |
| Download: ML20066B095 (3) | |
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SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.16 TO FACILITY OPERATING LICENSE DPR-77 AND AMENDMENT NO. 7 TO FACILITY OPERATING LICENSE OPR-79 TENNESSEE VALLEY AUTHORITY INTRODUCTION On July 15, 1982, TVA informed the NRC of a proposed anendment to change the steam generator low-low level reactor trip and auxiliary feedwater pump start setpoints.
The proposed change would decrease the setpoints by 3 percent.
An October 7,1982, letter to Harold R. Denton provided the justification for this change; the lower setpoint would allow greater flexibility during low power operations and reduce unnecessary reactor trips.
EVALUATION The steam generator low-low level reactor trip and auxiliary feedwater pump start setpoints are identi fied in Tables 2.2-1 and 3.3-4 of Sequoyah Units 1 and 2 Tech-nical Specifications.
The staff agrees that ' e setpoints of items 13 and 6c. of Tables 2.2-1 and 3.3-4, respectively, can be enanged to 18 percent.
In conjunction, the corresponding allowable values in the tables can be changed to 17 percent.
.n the October 7 transmittal, TVA reported that 39 percent of the trips at Sequoyah Units 1 and 2 resulted from low-low steam generator levels.
The lower setpoint will increase operational flexibility at the low-low steam generator levels reducing the likelihood of reactor trips which unnecessarily challenge the integrity of the reactor protection system.
The setpoint calculation is based upon the proprietary "Setpoint Methodology Report" by the Westinghouse Electric Corporation which the staff has found acceptable. The Setpoint Methodology Report concludes that the channel statistical allowance for the steam generator low-low level reactor trip is 16.2 percent which allows a 1.8 percent l
margin of safety (18 percent - 16.2 percent). At the time the 21% setpoint was estab-lished, the NRC was concerned that the setpoint just equaled the total error accumu-l lation. The report concludes that while the margin of safety is reduced from 4.8 percent to 1.8 percent of level measurement spanned, it remains sufficient and alleviates the NRC concern. Also, the Setpoint Methodology Report has been used in other Westinghouse reports in addition to having been submitted on other dockets for the purpose of evaluating setpoints.
l ENVIRONMENTAL CONSIDERATION We have determined that the amendment does not authorize a change in effluent types i
or total anounts nor an increase in power level and will not result in any signif-icant environmental impact. Having made this determination, we have further con-cluded that the amendment involves an action which is insignificant from the stand-point of environmental impact and, pursuant to 10 CFR 951.5(d)(4), that an environ-l mental impact statement or negative declaration and environmental impact appraisal r eed not be prepared in connection with the issuance of this amendment.
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CONCLUSION We have concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the probability or con-sequences of accidents previously considered, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant decrease in ' safety margin, the amendment does not involve a significant hazards consideration,
,1 there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Connission's regu-lations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: October 21, 1982 Principal Contributors: Helanie Hiller, Licensing Branch No. 4,DL Carl Stahle, licensing Branch No. 4. DL OFFICF),..................
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7590-01 UNITED STATES fluCLEAR REGULAIORY COMMISSION DOCKET N05. 50-327 AND 50-328
, TENNESSEE VALLEY AUTHORITY NOTICE OF ISSUANCE OF AMENDMENTS FACILITY OPERATING LICENSE N05. OPR-77 AND DPR-79 The U. S. Nuclear Regulatory Commission (the Convaission) has issued Amendment No. 16to Facility Operating License No. OPR-77 and Amendment No. 7 to Facility Operating License No. DPR-79, issued to Tennessee Valley Authority (licensee) for the Sequoyah Nuclear Plant, Units 1 and 2 (the facilities) located in Hamilton County, Tennessee. These amendments change the steam generator low-low level reactor trip and auxiliary feedwater pump start setpoints.
The amendments are effective as of their dates of issuance.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regu-lations.
The Commission has made appropriate findings as required by the Act and the Commission's regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not required since 1
the amendments do not involve a significant hazards consideration.
l The Commission has detennined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR s51.5(d)(4) environmental impact stateaents, or negative declarations and environmental impact appraisals need not be prepared in connection with issuance of these amendments.
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. For further details with respect to this action, see (1) Tennessee Valley Authority letter dated July 15,1982,(2) Amendment No.16 to Facility Operating License No. DPR-77 with Appendix A Technical Specification page changes; (3) Amend-i ment No. 7 to Facility Operating License No. DPR-79 with Appendix A Technical Specification page changes; and (4) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D. C., and the Chattanooga Hamilton County Bicentennial Library,1001 Broad Street, Chattanooga, Tennessee 37402. A copy of Amendment No.16and Amendment No. 7 may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
- 20555, Attention: Director, Division of Licensing.
8E Dated at Bethesda, Maryland, this 21 day of October 1982.
FOR E NOCLEAR REGULATORY COMMISSION
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i Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
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h October 21, 1982 AMEN 0 MENT fl0. 16TO FACILITY OPERATING LICENSE DPR SEQUOYAH UNIT 1 AMEN 0HENT NO. 7 TO FACILITY OPERATING LICENSE DPR SEQUOYAH UNIT 2 DISTRIBUTION w/ enclosures:
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PDocket No. 50-327/328 NRC POR LB #4 r/f Local PDR C. Stable NSIC M. Duncan TERA I&E A. Rosenthal, ASLAB OELD ASLBP E. Adensam ACRS(16)
R. Hartfield, itPA W. Jones (10)
R. Diggs, ADM D. Eisenhut/R. Purple J. Souder T. Barnhart (8) l l
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