ML20043B117
| ML20043B117 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/21/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043B116 | List: |
| References | |
| NUDOCS 9005240208 | |
| Download: ML20043B117 (3) | |
Text
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o UNITED STATES
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NUCLEAR REGULATORY COMMISSION l
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WAsMNOTON, D. C. 20b55
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.129 TO FACILITY OPERATING LICENSE NO. OPR-72 FLORIDA POWER CORPORATION, ET AL.
CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 BACKGROUND By letter dated March 15, 1990, Florida Power Corporation (FPC or the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No. DPR-72 for the Crystal River Unit No. 3 Nuclear Generating
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Plant (CR-3).
The proposed amendment would increase the fuel manufacturing i
tolerances as used in the calculation of nuclear heat flux hot channel factor i
frem 1.4% to 2.0%.
EVALUATION Nuclear heat flux hot channel factor (Fn) is a design limit nuclear power i
peaking factor.
Analyses of the possibTe power shapes have determined that the design limits on nuclear power peaking at full power are met provided that i
F < 3.13.
TS 3.2.2 requires that F <3.13 at full power.
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F is most restrictive when calculated at full power. This is true for all n
pDssible control rod bank positions.
Therefore, if Fn is within limits at full power, then for operation at a fraction of rated therNa1 power the design limits must also be met. When using the incore detectors to make the power distribution maps to determine F, the measured peaking factor is increased by 0
a certain percentage in order to account for manufacturing tolerances, and further increased in order to account for measurement error.
Currently, TS surveillance section 4.2.2.2 requires that F be increased by 1.4% to account o
for manufacturing tolerances and further increased by 7.5% to account for measurement uncertainty.
For fuel cycle 8, approximately one third of the fuel in the reactor will be replaced with new fuel purchased from Babcock & Wilcox.
During fuel pellet fabrication for the cycle 8 fuel, two fuel pellet lots were found to have combinations of high average enrichment and variability that resulted in one of the U-235 gms/ inch measurements being beyond the manufacturing specification limit. A statistical evaluation performed by Babcock & Wilcox indicated that for the worst case fuel lot, the actual manufacturing tolerance should be increased to 1.84%. Therefore, the licensee requested to increase the 9005240208 900521 PDR ADOCK 05000302 P
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~2-l tolerance as listed in the TS to 2.0% in order to be conservative and to provide i
a reasonable bounding value that is not likely to require a change in the future.
L The proposed change will not increase the F limit, and F shall remain below or
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equal to 3.13.
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The staff has evaluated the licensee's proposed changes and finds that they are acceptable.
Furthermore, as the requested increase in the error factor due to manufacturing tolerances would have the effect of reducing the allowable l
measured nuclear heat flux hot channel factor, the change is conservative.
SUMMARY
Based on our review, the changes proposed in this request are adequate and acceptable.
t ENVIRONMENTAL CONSIDERATION P
This amendment involv+s a change to a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
We have 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 offsite, 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 consideration and there has been no public comment on such finding.
Accordingly, this 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 or environmental assessment need be prepared in connection with the issuance of this amendment.
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 operation in the proposed manner, and (2) 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: May 21, 1990 Principal Contributor:
G. Wunder i
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' DATED:
May 21. 1990 L
AMENDMENT NO.129 TO FACILITY OPERATING LICENSE NO. DPR-72-CRYSTAL RIVER UNIT 3 (Sacket(file #
NRC & Local"PDRs PDII-2 Reading t
S. Varga, 14/E/4
.G. Lainas, 14/H/3 i
H. Berkow D.-Miller H. Silver LG. Wunder OGC-WF
- 0. Hagan, 3302 MNBB.
E. Jordan, 3302 MNBB L
B. Grimes, 9/A/2
.G. Hill (4), P1-137 Wanda Jones, P-130A J. Calvo, 11/F/23 J. Miller, 11/F/23 ACRS (10)
GPA/PA OC/LFMB t
M. Sinkule. R-II I
cc:
Plant Service list f
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