ML020590313
| ML020590313 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/28/2002 |
| From: | Goshen J NRC/NRR/DLPM/LPD2 |
| To: | Young D Florida Power Corp |
| Goshen, JM, NRR/DLPM, 415-1437 | |
| References | |
| IEB-01-001, TAC MB2623 | |
| Download: ML020590313 (4) | |
Text
February 28, 2002 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
BULLETIN 2001-01, CIRCUMFERENTIAL CRACKING OF REACTOR PRESSURE VESSEL HEAD PENETRATION NOZZLES, RESPONSES FOR CRYSTAL RIVER UNIT 3 (TAC NO. MB2623)
Dear Mr. Young:
On August 3, 2001, the U.S. Nuclear Regulatory Commission (NRC) staff issued Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, to the industry requesting that addressees provide information related to the structural integrity of the reactor pressure vessel head penetration (VHP) nozzles for their respective facilities, including the extent of VHP nozzle leakage and cracking that has been found to date, the inspections and repairs that have been undertaken to satisfy applicable regulatory requirements, and the basis for concluding that their plans for future inspections will ensure compliance with applicable regulatory requirements at their respective pressurized water reactor plants. You were requested to respond to Items 1 and 3 of the Bulletin within 30 days of its issuance.
You provided your Bulletin response by letter dated August 30, 2001, indicating that your plant is classified as having moderate susceptibility to primary water stress corrosion cracking in the VHP nozzles, based on a relative susceptibility ranking of 5 to 30 effective full-power years from the Oconee Nuclear Station, Unit 3, condition. The staff finds that you have provided the requested information. In your response, you committed to perform an effective visual examination of 100 percent of the VHP nozzles during the September 2001 refueling outage.
This is consistent with the description for such an examination provided in Bulletin 2001-01.
The NRC staff has concluded that the inspection schedule and scope described in your Bulletin response provide reasonable assurance that the public health and safety will be maintained at your plant.
You also provided a response to Item 5 of the Bulletin on November 19, 2001, within 30 days after plant restart as requested in Bulletin 2001-01. This response described the extent of VHP nozzle leakage and cracking detected at your plant, including the number, location, size, and nature of each crack detected, and a description of the inspections (type, scope, qualification requirements, and acceptance criteria), repairs, and other corrective actions you have taken to satisfy applicable regulatory requirements. This response noted that an engineering evaluation
D. Young subsequent to your Bulletin 2001-01 response determined that the visual examination completed during the September 29, 2001, refueling outage meets the intent of the qualified visual examination described in Bulletin 2001-01.
If you have any questions, please feel free to give me a call at (301) 415-1437.
Sincerely,
/RA/
John M. Goshen, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page
D. Young February 28, 2002 engineering evaluation subsequent to your Bulletin 2001-01 response determined that the visual examination completed during the September 29, 2001, refueling outage meets the intent of the qualified visual examination described in Bulletin 2001-01.
If you have any questions, please feel free to give me a call at (301) 415-1437.
Sincerely,
/RA/
John M. Goshen, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page DISTRIBUTION:
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PDII-2/SC NAME JGoshen BClayton WBateman RCorreia DATE 02/21/02 02/21/02 02/13/02 02/21/02 OFFICIAL RECORD COPY
Florida Power Corporation CRYSTAL RIVER UNIT NO. 3 GENERATING PLANT cc:
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, Florida 33733-4042 Mr. Daniel L. Roderick Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Michael A. Schoppman Framatome ANP 1911 North Ft. Myer Drive, Suite 705 Rosslyn, Virginia 22209 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, Florida 34450-4245 Ms. Sherry L. Bernhoft Manager Regulatory Affairs Crystal River Nuclear Plant (NA2H) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Senior Resident Inspector Crystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, Florida 34428 Mr. Richard L. Warden Manager Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708