ML17229A262
| ML17229A262 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/13/1997 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| TAC-M95484, TAC-M95485, NUDOCS 9703170136 | |
| Download: ML17229A262 (5) | |
Text
March 13, 1997 Hr. Thomas F. Plunkett President, Nuclear Division Florida Power and Light Company Post Office Box 14000 Juno
- Beach, Florida 33408-0420
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION PRESSURIZED THERMAL SHOCK EVALUATION ST.
LUCIE, UNITS 1
AND 2 (TAC NOS.
H95484 AND H95485)
Dear Hr. Plunkett:
By letter dated May 14, 1996, Florida Power and Light Company (FPL) submitted a pressurized thermal shock evaluation for St. Lucie Units 1 and 2.
A request for additional information (RAI) was issued by the staff on October 15, 1996.
FPL responded to the RAI by letter dated January 14, 1997.
As a result of our continuing review, the Nuclear Regulatory Commission staff has identified additional information which is needed to complete its assessment of this evaluation.
The specific questions are listed on the enclosed Supplemental RAI.
A response to this RAI is requested within 60 days of receipt.
If you have questions concerning this issue, please contact me at (301) 415-1495.
Sincerely, ll
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'Docket 'Nos I
Enclosur'e!
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.0-335,and,50-389 Supplemental-RAI sure,:
See next page
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Original signed by Leonard A. Wiens, Senior Project Manager Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation DISTRIBUTION:
Docket File
'Varga PUBLIC JZwolinski St.
Lucie r/f OGC ACRS JJohnson DOCUMENT NAME:
G:iSTLUCIEi2NDSTLUC.RAI To receive e copy of this domaent, indicate in the box:
eC" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure eNa
~ ko co y PD I I-3/LA OFFICE PDII-3/PM HAME Llliens BClayton PD I I -3/D FIIebdon DATE 03/ 9/ /
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Mr. T. F. Plunkett Florida Power and Light Company
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I ST.
LUCIE PLANT cc:
Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.
Hwy A1A Jensen Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S.
Ross, Attorney Florida Power 5 Light 11770 US Highway 1
North Palm Beach, FL 33408 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. Thomas R.L. Kindred County Administrator St.
Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Regional Administrator
~
Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 H. N. Paduano, Manager Licensing 8, Special Programs Florida Power and Light Company P.O.
Box 14000 Juno
- Beach, Florida 33408-0420 J.
A. Stall, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, Florida 34957 Mr. J. Scarola Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, Florida 34957 Mr. Kerry Landis U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323-0199 E. J.
Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, Florida 34957
1 4
SUPP E
N A VEST FOR D
0 INFO MAT 0 ESSU I ED ERMAL S OCK EV LUATION S
LUCIE UNITS 1
AND 2 The Nuclear Regulatory Commission staff requests additional information for
'he Florida Power and Light Company (the licensee) pressurized thermal shock evaluation, as, stated below:
1)
The licensee's response to guestion 2 of the staff's Request for Additional Information (RAI) provided the basis for determining initial RT~, (RT~,+>) values for several weld wire heats.
The licensee's responses w>th respect to three of the five heats were acceptable.
However, the following information is necessary to complete our evaluation of the remaining two heats:
a)
The limiting weld in the St. Lucie 1 reactor vessel beltline is fabricated from weld wire heat 305424.
This heat of weld wir e was also used to fabricate the Beaver Valley 1 surveillance weld and welds in the LaSalle 1 reactor vessel beltline.
The licensee's response 2 to the RAI indicated that the LaSalle and St. Lucie 1
Charpy data were not used to assess the RT,
for the St. Lucie 1
vessel.
Explain the effect on the value oF @gpss(u) that would result from including the Charpy data from St. Lucie 1 and LaSalle 1.
Verify whether the RTQ 7(Q) value for heat 305424 remains drop weight controlled (i.e., toes the lower bound Charpy curve become controlling).
b)
With regard to heat 83642, St. Lucie 2 reported an RTQQ7
) value of
-80'F; and Beaver Valley 2 reported a value of -30'F.
fNe response stated that an RT>>,<>> of -80 F would be used for the St. Lucie 2 weld.
Provide the basis for selecting the non-conservative value of
-80'F.
If justification cannot be provided, use a generic value in which plus or minus 2 sigma would bound the St. Lucie 2 and the Beaver Valley 2 data points.
2)
The licensee's response to guestion 3 of the RAI stated that "the fluence at the St. Lucie 1 limiting weld...has been updated."
The fluence value was 1.20 E19n/cm in the original submi)tal.
Table 3 of the response to the RAI shows a value of 1.06 E19n/cm Provide supporting documentation that justifies the decrease in the fluence value for St.
Lucie 1.
This includes an explanation of the analysis that was used to determine the revised fluence.
3)
Where applicable, update the RT,7$ Tables as described in the response to the RAI.
Specifically, Tables 1 and 2 from Attachment B pages B-4 and B-51, respectively and Table 3 of Attachment A, page A-13.
ENCLOSURE