ML20245H746
| ML20245H746 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/07/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245H744 | List: |
| References | |
| NUDOCS 8908170263 | |
| Download: ML20245H746 (3) | |
Text
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.k UNITED STATES r
'7A})W. g NUCLEAR REGULATORY COMMISSION i
l o n WASHINGTON, D. C. 20555 Y e!
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION.
SUPPORTING AMENDMENT NO. 80 TO FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUlHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1-DOCKET NO. 50-395
1.0 INTRODUCTION
In a letter dated August 24, 1988, South Carolina Electric & Gas Company (the licensee) submitted a proposed change to Technical Specifications (TS) Section 3/4.2, D. C. Sources, of the V. C. Summer Nuclear Station.
The purpose of the TS amendment request was to modify the value for the average electrolyte temperature referenced in TS 4.8.2.1.b.3 and the value for the battery capacity in-TS 4.8.2.I.e.
The proposed amendment request would change the average electrolyte temperature from 60 to 65 degrees Farenheit and the battery capacity from 80% to 90%.
2.0 EVALUATION The licensee identified during an emergency power review that the calcula-tion for sizing ESF batteries IA and IB used a derating factor for aging and temperature more conservative than those identified in the TS. The calculations used an aging derating factor of 90% and a temperature derating factor of 94% (65 degrees Farenheit) as opposed to an 80% aging derating factor and 90% (60 degrees Farenheit) temperature derating factor, as presently stated in the TS.
It was identified, based upon a letter from the battery manufacturer, that the original calculations of December 26, 1980 l
showed the capacity of the battery at. the end of its useful life to be 90%.
With respect to the temperature derating factor, the licensee indicated i
that a factor of 94% had been utilized to account for the effect of minimum j
temperature. Table 3.11-3 of the Summer Final Safety Analysis Report (FSAR) identified the minjmum design temperature for the battery room to be 65 J
degrees Farenheit.
In actual plant operation, the battery room temperature is controlled by a thermostat which is set to maintain room temperature at 75 degrees Farenheit.
If the control system malfunctions, a bistable controller connected to a temperature element in the room will close the j
supply damper if the temperature falls below 70 degrees Farenheit. The l
damper will reopen if the temperature increases.
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2-The-licensee indicated that the standard temperature for stating' cell capacity is 77 degrees Farenheit and that temperature correction factors are used to determine the additional battery capacity required at lower temperatures to achieve the same battery performarece as if it were 77 degrees Farenheit. The licensee stated in their submittal that the electrolyte temperature is assured to be at a temperature equal to or greater thhn anbient because of the heating effects of the float charge.
Thus, the minimum room design temperature of 65 degrees Farenheit was used in conjunction with the vendor supplied curves for.the specific battery in use to establish the derating factor of 94%.
The staff has reviewea the licensee's submittal.
The bases for this TS indicate that' by verifying that the average electrolyte temperature is above the minimum for which the battery was sized is.one of a number of surveillance which all together ensure the effectiveness of the charging system, the ability to handle high discharge rates and the battery capacity at a given time with the rated capacity.
The staff has reviewed the proposed changes. The changes proposed reflect the actual design basis for the facility and are actually more conservative than the values identified in the TS. Therefore, the staff has determined that the licensee's request is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
. This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in the 10 CFR Part 20 and changes to the surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types of any effluents that may be released off-site and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards con-sideration and there has been no public comment on such finding. Accord ingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),noenvironmentalimpactstatementorenvironmentalassessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The Comission has issued a " Notice of Consideration of Issuance of Amend-ment to Facility Operating License and Propose No Significant Hazards Consideration Determination and Opportunity 1cr Hearing" which was published in the FEDERAL REGISTER on May 3, 1989 (54 FR 18959) and consulted with the State of South Carolina.
No public cocrents or request for hearing were received, and the State of South Carolina did not have comments.
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q The staff has concluded, based upon the. considerations discussed above,-
R-a that: (1) tiiere is reasonable assurance that the health and safety of the.
ubite will not be" endangered by. operation in the proposed inanner, and p(2).such. activities' wf11 be. conducted in compliance with the Comission's 1
l regulations and the issuance of this. amendenent will not be inimical to 1
. the comon defense and security or to the health and safety of the public.
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' Principal Contributor: J. Hayes.
i Dated: August 7. 1989
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