ML17241A475
| ML17241A475 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/04/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML17241A476 | List: |
| References | |
| TAC-MA5311, NUDOCS 9910080054 | |
| Download: ML17241A475 (3) | |
Text
Mr. T. F. Plunkett President - Nuclear Divisi~
Florida Power and Light Company P.f3. Box 14000 Juno Beach, Florida 33408-0420 October 4, 1999
SUBJECT:
RELIEF FROM ASME CODE REQUIREMENTS RELATEDTO THE INSERVICE INSPECTION PROGRAM SECOND 10-YEAR INTERVALFOR ST. LUCIE PLANT, UNIT2 (TAC NO. MA5311)
Dear Mr. Plunkett:
By letter dated April 5, 1999, as supplemented July 22, 1999, the Florida Power and Light Company submitted to the U.S. Nuclear Regulatory Commission (NRC), a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code,Section XI, requirements for certain inservice inspections of reactor pressure vessel-to-nozzle welds at St. Lucie Plant, Unit 2, contained in your second 10-year interval Inservice Inspection (ISI) Program for Unit 2. The staff has reviewed and evaluated the information provided in the proposed revision to the second 10-Year ISI program, Relief Request (RR) No. 25, for St. Lucie Plant, Unit 2.
The NRC hereby authorizes the proposed alternative to the Code requirements for ISI RR-25, pursuant to Title 10, Code of Federal Re ulations, Section 50.55a(a)(3)(i), in that the staff finds that the proposed alternativ, with the conditions stated in the enclosed safety evaluation, willprovide an acceptable level of quality and safety and an equivalent or better examination than the requirements in the 1989 Edition of the ASME Code.
Sincerely, Origiaa1 signed 'by:
Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosures:
Safety Evaluation
"" ~ Ft'>~K ~t'.Pi')Ptl, lPglm cc w/encl: See next page DISTRIBUTION:
RScholl (email SE)
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- see previous concurrence enclosure "N"=No co The ISI program RR, which is authorized herein, is acceptable for implementation.
The granting of relief is based upon the fulfillmentof any commitments made by you in the basis for the RR and the proposed alternativ.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555<001 October 4, 1999 Mr. T. F. Plunkett President -'uclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
RELIEF FROM ASME CODE REQUIREMENTS RELATED TO THE INSERVICE INSPECTION PROGRAM SECOND 10-YEAR INTERVALFOR ST. LUCIE PLANT, UNIT2 (TAC NO. MA5311)
Dear Mr. Plunkett:
By letter dated April 5, 1999, as supplemented July 22, 1999, the Florida Power and Light Company submitted to the U.S. Nuclear Regulatory Commission (NRC), a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code,Section XI, requirements for certain inservice inspections of reactor pressure vessel-to-nozzle welds at St. Lucie Plant, Unit 2, contained in your second 10-year interval Inservice Inspection (ISI) Program for Unit 2. The staff has reviewed and evaluated the information provided, in the proposed revision to the second 10-Year ISI program, Relief Request (RR) No. 25, for St. Lucie Plant, Unit 2.
The ISI program RR, which is authorized herein, is acceptable for implementation.
The granting of relief is based upon the fulfillmentof any commitments made by you in the basis for the RR and the proposed alternative.
The NRC hereby authorizes the proposed alternative to the Code requirements for ISI RR-25, pursuant to Title 10, Code of Federal Re ulations, Section 50.55a(a)(3)(i), in that the staff finds that the proposed alternative, with the conditions stated in the enclosed safety evaluation, will provide an acceptable level of quality and safety and an equivalent or better examination than the requirements in the 1989 Edition of the ASME Code.
Sincerely, Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosures:
Safety Evaluation cc w/encl: See next page