ML17346A359
| ML17346A359 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/26/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Williams J FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML17346A360 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8405170151 | |
| Download: ML17346A359 (10) | |
Text
Docket Nos.
50-250 and 50-251 April 26,1984 Mr. J.
W. Williams, Jr., Vice President Nuclear Energy Department Florida Power and Light Company Post Office Box 14000 Juno Beach, Florida 33408
Dear Mr. Williams:
DIS UTI o
et N
L PDR Gray File ORBgl Rdg DEisenhut CPar rish EJordan JNGrace OELD ACRS (10)
GVissing RWoods
SUBJECT:
EVALUATION OF REACTOR VESSEL MATERIALS DATA FOR TURKEY POINT PLANT UNITS 3 AND 4 REACTOR VESSELS By letter dated February 10, 1984, you provided a report which included a
larger data base of information on the chemical composition of the reactor vessel welds for the Turkey Point, Units 3 and 4, reactor vessels than was previously available to the NRC staff.
As a result of your evaluation of the data, you concluded that the RT d should be +10'F without any standard deviation, Copper content equal to II.36% and Nickel content equal to 0.605.
The Component Integrity Section, Materials Engineering Branch, Division of Engineering has reviewed the report provided in the submittal referenced above.
The staff has concluded, based on the enclosed Safety Evaluation, that the data base supports the above values and they are acceptable for screening criteria calculations for.Pressurized Thermal Shock considerations for the Turkey Point Units 3 and 4, reactor vessels.
Sincerely, Mx SI~g.
Enclosure:
As stated cc w/enclosure:
See next pa Steven A. Var ga, Chief Operating Reactors Branch 81 Division of Licensing ORBgl:
DMcDonal ;ps
/gQ/84 B
L a
84 8405170i5i 840426 PDR ADOCK 05000250 P
Il If 4~
C:g I
~
i.
i/Hev), the current fluence level for these plants.
19 Therefore by reducing the best estimate value of copper content from 0.32 to 0.26 we have reduced the calculated value of RT NDT by about
'24'F.
For comparison, the margin added to the mean, per the provision of proposed Revision 2 is 56'F.
III. Conclusion To be consistent with the practice of using the mean of the measured values for the weld wire heat
- number, as written in Revision 2 of Reg.
Guide 1.99, the staff accepts the mean value of 0.26K Cu.
The corresponding nickel content is 0.605.
FPL also provides some measured values of initial reference temperature for weld SA 1101, obtained from an EPRI report.
Following ASHE Code rules, the initial RT HDT was found to 'be +10'F.
The staff accepts this value.
Date:
April 26, 1984 Princi al Contributor:
P.
Randall
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