ML20058B418
| ML20058B418 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/14/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058B416 | List: |
| References | |
| TAC-11945, NUDOCS 8207260008 | |
| Download: ML20058B418 (3) | |
Text
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8 UNITED. STATES 8
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NbCLEAR REGULATOPY COMM'ISSION n
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%*'..... o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDf1ENT NO. 54 TO' FACILITY OPERATIflG LICENSE NO. DPR-72,e FLORIDA POWEP, CORPORATldN, ET AL
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,o CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT i.
,1 DOCKET ti0. 50-302
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Intro 8uction By letter dated March 21, 1979, as supplemented November 27,= 19'79, and February 15, 1980, Florida Power Corporation (FPC) requested amendment. of >
Appendix A to the Crystal River Unit No. 3 (CR-3) operating license to revise the Technical Specification (TS) requirements, for nuclear overpower trip setpoints.
n Evaluation FPC proposes raising the maximum allowable nuclear overpower tri[setpoints when one, two, or three, r* steam line safety valves (MSLSVs) are inoperable.
The reason for the above 'p'roposed changes is.to take credit for the fact that the actual relieving capacity of the MSLSVs b more 19 arc 6% in excess of the, v required relieving capacity presented in the Final Safgty Analysis Report
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(FSAR).
Raising the trip setpoints for the cases of one, two, or three_
inoperable MSLSVs will enhance the maneuverability of the plant. '
CR-3 has a total of 16 MSLSVs, eight on each main stern line;'seven valv'es relieve 845,759 lbs/hr. e.ach and one valve relieves 5fh;574 l>s/hr.
The total relieving capacity of the; 16 valves eq'uals 13,00'7,774 lbs /hr.
This.value is 118.3% of the total secondiry steam flow which is ll.0x106 lbs/hr et 100%
rated thermal power.
At the present time, with all 16 MSLSVs operable, the nuclear overpeser Arip setpoint is 105.5%.
At this setpoint, considering the measurir7 Mrtbr.; the raaximum actual thermal power could be as high as.112% of the rated valde,2 i.e., a relieving capacity of 112% of the total rated s, team flow is therefore requi red.
The TSs require:
"With one or more main steam line crw safety valves inoperable, operation in MODES 1, 2 and 3 may proceW :provided, thi.t within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPLRABLE status or the nuclear overpower trip retpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and ir. COLD SHUTDOWN within the following 30. hours"., fresently the reactor trip setnoint reductions are derived based on the following equation:
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S = A - NB X 105.5
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c where: S= Reduced nuclear overpower trip setpoint in percent of rated thermal power.
8207260008 820714 PDR ADOCK 05000302 P
PDR A
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CR-3 A = Required relieving capacity of all safety valves per steam generator to relieve 112% of rated steam generation rate, lbs/hr.
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N = Maximum number of inoperable safety valves per steam generator.
B = Maximum actual relieving capacity of any one safety valve, lbs/hr.
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C = Total actual relieving capacity of all safety valves per steam generator (118% of rated steam generation rate), lbs/hr.
105.6%
= Nuclear overpower trip setpoint specified for an all-operable safety valves condition.
Equation (1) above results in the trip setpoints currently listed in the TSs.
This equation uses a conservatively low remaining safety valves relief capacity and a conservatively high required relief capacity. FPC's proposed
, change modifies equation (1) as follows:
/
I=
{NB X 105.5%
(2)
S p
' 'where the variables on the righthand side have the same values as those for
'/
. equation (1) above.
Equation (2) uses the actual remaining safety valves
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The modification reli,ef capacity and the maximum required relief capacity.
a in. equation (2) increases the numerator value and decreases the denominator value, consequently resulting in higher nuclear overpower trip setpoints as indicated in the proposed change to Table 3.7-1 of the TSs. We find the modified trip setpoints acceptable because they are consistent with valve
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relief capacities.
' En'vironmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant enviromental impact. Having
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made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an ewironmental impact statement, or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
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 consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the amendment does not involve a j
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significant hazards consideration, (2) 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 Commission's regulations 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.
Dated: July 14,1982 The following fjRC personnel have contributed to this Safety Evaluation:
S. Diab, P. Erickson.
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