L-2002-199, Reactor Vessel Surveillance Capsule Report of Test Results

Reactor Vessel Surveillance Capsule Report of Test Results

ML022940116
Person / Time
Site:	Turkey Point
Issue date:	10/08/2002
From:	Mcelwain J Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2002-199
Download: ML022940116 (2)

Text

SOCT 0 8 2002 FPL L-2002-199 10 CFR 50.4 10 FR 50.60(a)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reactor Vessel Surveillance Capsule Report of Test Results Pursuant to the requirements of 10 CFR 50.60(a) and 10 CFR Part 50 Appendix H, Reactor Vessel MaterialSurveillance ProgramRequirements, paragraph IV.A., enclosed is the summary technical report for the capsule removed during the Fall 2001 Turkey Point Unit 3 refueling outage. The report is titled Analysis of Capsule Xfrom The FloridaPowerAnd Light Company Turkey Point Unit 3 Reactor Vessel Radiation Surveillance Program,WCAP-15916, dated September 2002. Capsule X contained material specimens representative of a Turkey Point Unit 3 reactor vessel forging, 123S266-VAI, and the limiting, intermediate to lower shell girth weld, SA-101 1, for both Turkey Point Units 3 and 4. Since the limiting weld is common to both units, and the forging bounds both units, the test results are applicable to both Turkey Point Units 3 and

4. In addition, by letter dated April 22, 1985, the NRC approved an integrated surveillance program for Turkey Point Units 3 and 4.

The report includes the data required by ASTM E-185, as specified in paragraph IfI.B. 1 of 10 CFR 50 Part Appendix H, and the results of all applicable fracture toughness tests conducted on the beltline materials in the irradiated and unirradiated conditions.

Comparisons of the measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at Turkey Point Unit 3 meet the acceptance criteria specified by Regulatory Guide 1.190, and therefore validate the model used to calculate the neutron exposures.

The fluence projections presented in the enclosed report were calculated assuming no part length burnable Hafnium absorber assemblies present. Turkey Point Units 3 and 4 have used part length burnable Hafnium absorbers since 1985 for flux reduction purposes.

FPL's current fuel management plans include the use of part length Hafnium absorbers.

Therefore, the fluence projections presented in this report are higher than the actual expected fluence and the fluence used to generate the Turkey Point Units 3 and 4 Reactor Coolant System Heatup and Cooldown Limitations, Technical Specification Figures 3.4 rvo an FPL Group company

L-2002-199 Page 2 2 and 3.4-3. However, FPL has determined that with the current fuel management philosophy, which includes the use of part length Hafnium absorbers, no Technical Specification or operating procedure changes are required.

If there are any questions about this submittal, please contact R. D. Gil at (561) 694 3370.

Very truly yours, MElIwain Vice President Turkey Point Plant Enclosure JPM/OIH cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant