ML17241A396
| ML17241A396 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/25/1999 |
| From: | Gleaves W NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0574, TAC-MA0575, TAC-MA574, TAC-MA575, NUDOCS 9907070366 | |
| Download: ML17241A396 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055.'I-0001 3une 25, 1999 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
CLOSURE OF TAC NOS. MA0574 AND MA0575-RESPONSE TO THE REQUEST FOR INFORMATIONIN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY,"FOR ST. LUCIE PLANT, UNITS 1 AND2
Dear Mr. Plunkett:
On May 19, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev. 1, Supp. 1), "Reactor Vessel Structural Integrity," to holders of nuclear operating licenses.
In issuing the Generic Letter (GL), the staff required addressees of the GL to:
(1) identify, collect, and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code ofFederal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code ofFederal Regulations (Appendices G and H to 10 CFR Part 50).
On August 16, 1995, you submitted your initial response to GL 92-01, Rev. 1, Supp. 1, and provided the requested information relative to the structural integrity assessments for St. Lucie, Units "1 and 2. The staff evaluated your response to GL 92-01, Rev. 1, Supp.
1, and provided its conclusion relative to your response on August 6, 1996.
However, since the time of the staffs closure letter, the Combustion Engineering (CE) Owners Group has submitted additional data regarding the alloying chemistries of beltline welds in CE fabricated vessels.
The additional alloying data were submitted in Topical Reports CE NPSD-1039 Rev. 2 and CE NPSD-1119, Rev. 1, for CE fabricated RPV welds.
RF On August 28, 1997, you provided your final response to the staff regarding your assessment of the information in the topical reports noted above.
The staff has reviewed the information that you submitted and determined that it adequately reflects the information contained in CE Topical Reports CE NPSD-1039, Rev. 2, and CE NPSD-1119, Rev. 1, for CE fabricated RPV welds.
~~0 As a result of the staffs review of your responses to GL 92-01, Rev.
1 and GL 92-01, Rev. 1, Supp. 1, the staff has revised the information in the Reactor Vessel Integrity Database 99070703bb 990b25 PDR ADQCK 05000335' PDR
T.F. Plunkett (RVID) and is releasing it as RVID Version 2. The new database is posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/
index. html). We recommend that you review this information. Ifthe staff does not receive comments by September 1, 1999, we willassume that the data entered into the RVID are acceptable for your plant.
No additional information is necessary with regard to the structural integrity assessments.
Future submittals on pressure and temperature limits, pressurized thermal shock, or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC numbers MA0574 and MA0575. If you have any questions regarding this matter, please contact me at (301) 415-1479.
Sincerely, original signed by:
.William C. Gleaves, Project Manager, Section 2 Project Directorate II
'ivision of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.
50-335 and 50-389 cc: See next page DISTRIBUTION:
Docket File PUBLIC St. Lucie Reading BClayton WGleaves OGC ACRS LWert, Rll A.D. Lee, EMCB DOCUMENT NAME: G ~PDII-21St. Lucie>MA057485.co.WPD To recehre a co of this document. indicate in the born C
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06 99 PDII-ALA BCla ton 06/ /99 P DII-2ts SPeterso 06 99 OFFICIALRECORD COPY 06/ /99 06/ /99
~$v T.F. Plunkett (RVID) and is releasing it as RVIDVersion 2. The new database is posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/
index. html). We recommend that you review this information, Ifthe staff does not receive comments by September.1, 1999, we willassume that the data entered into the RVIDare acceptable for your plant. No additional information is necessary with regard to the structural integrity assessments.
Future submittals on pressure and temperature limits, pressurized thermal shock, or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC numbers MA0574 and MA0575. Ifyou have any questions regarding this matter, please contact me at (301) 415-1479.
Sincerely, original signed by:
William C. Gleaves, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.
50-335 and 50-389 cc: See next page DISTRIBUTION:
Docket File PUBLIC St. Lucie Reading BClayton WGleaves OGC ACRS LWert, Rll A.D. Lee, EMCB DOCUMENT NAME: G:>PDII-21St. Lucie>MA057485.co.WPD To receive a co of this document, indicate ln the born C
~ Co without attachment/enclosure E
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~ No co OFFICE PDII-2)PM NAME DATE 06 99 PDII-2tLA C
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06/2/99 P DII-2'ILS SPeterso 06)$99 06/ /99 06/ /99 OFFICIALRECORD COPY
T.F. Plunkett and is releasing it as RVIDVersion 2. The new database is posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/index.html ). We recommend that you review this information. Ifthe staff does not receive comments by September 1, 1999, we willassume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structural integrity assessments.
Future submittals on pressure and temperature limits, pressurized thermal shock, or upper shelf energy should reference the most current information.
This closes the staffs efforts in regard to TAC numbers MA0574 and MA0575. The staff appreciates your efforts in regard to this matter.
Ifyou have any questions regarding this matter, please contact me at (301) 415-1479.
Sincerely, NZ William C. Gle ves, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.
50-335 and 50-389 cc: See next page
Mr. T. F. Plunkett Florida Power and Light Company ST. LUCIE PLANT Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 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 & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. WilliamA. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin ¹C21 Tallahassee, Florida 32399-1741 J. A. Stall, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. R. G. West Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. John Gianfrancesco Manager, Administrative Support and Special Projects P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997