ML20151B976
| ML20151B976 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/12/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151B974 | List: |
| References | |
| NUDOCS 8807210182 | |
| Download: ML20151B976 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE Of SPECIAL PROJECTS SUPPORTING WENDMENT NO. 76 TO FACILITY OPERATING LZCENSE NO. OPR-77 AND ANENOMENT NO. ~[7 TO FACIllTY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 Ak0 50-328 1:0 INTRODUCTION By letter dated February 3,1987 the Tennessee Valley Authority (TVA) requested amendments to the sequoyah Nuclear Plant, Units 1 and 2 Appendix A Technical Specifications (TS). The proposed amendments would clarify TS Table 3.3-9 Shutdown Monitoring Instrumentation. The proposed changes to Table 3.3-9 are as follows:
1)
The measurement range shown for pressurizer level (item 5) is to be changed from 0-525 inch to 0-100 percent.
2)
The measurenent range shown for auxiliary feedwater flow rate (item 11) is to be changed from 0-880 gpm to 0-440 cpm.
3)
The minimum number of channels operable for reactor coolant temperature-hot leg (item 3) is to be changed from 1 to 1/ loop.
4)
The minimum reqaired channels operable for auxiliary feedwater flow rate (item 11) is to,be changed from 1 to 1/ steam generator.
2.0 EVALUATION The proposed change associated with pNssurizer level measurement range indication from 0-525 inches to 0-100 percent, will enhance the clarity of Table 3.3-9.
The change eliminates inconsistency between parameters identified in the table and actual measured parameters depicted by control room indicating devices. The control room indicators read out in 0-100% of level.
The proposed change to the measurement range for feedwater flow rate will likewise eliminate inconsistency between table entries and actual indication.
The appropriate quantity to be measured and indicated is the inlet flow to the steam generators. The 0-880 gpm range currently indicated on Table 3.3-9 is the discharge capacity of the steam driven auxiliary feedwater pump. Since the amount of auxiliary feedwater flow to each steam generator is the p. eneter measured on Table 3.3-9 and not the discharge capacity of the steam driven pump, the given measurement should reflect the 0-440 gpm range of the feedwater indicators for each steam generator.
8807210182 880712 DR ADOCK 050 7
s d The two remaining changes wh'ch are in the "Minimum Channels Operable" column of Table 3.3-9 are editorial (nd are intended only to clarify the number of channels required on a per loop or per steam generator basis. The "1/" in the present Table 3.3-9 for the reactor trip breaker indication and auxiliary feed-water flow rate is not correct. The correct numbers are "l/ loop" and "l/ steam generator," respectively. This change eliminates the potential for misinterpre-tation of the TS requirements.
The staff has eviewed the licensee's proposed changes to the Sequoyah Units 1 and 2 TS and finds them acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the *estricted area as defined in 10 CFR Part 20. The staff has determined that the amendnent involves no significant in:rease in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission his previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operatlos in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's ra.gulations, and the issuance of the amendmer.t will not be inimical to the common defense and security nor to the health anc, safety of the public.
Principal Contributor:
E. N. Fields Dated: July 12, 1988 1
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