ML053070386
| ML053070386 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/23/2005 |
| From: | Mozafari B Plant Licensing Branch III-2 |
| To: | Young D Florida Power Corp |
| Mozafari B,NRR/DLPM, 415-2020 | |
| Shared Package | |
| ML053070396 | List: |
| References | |
| TAC MC5813 | |
| Download: ML053070386 (4) | |
Text
November 23, 2005 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:
CRYSTAL RIVER UNIT 3 - CORRECTED PAGE FOR SAFETY EVALUATION OF AMENDMENT NO. 222 REGARDING PROBABILISTIC METHODOLOGY FOR TUBE END CRACK ALTERNATE REPAIR CRITERIA (TAC NO. MC5813)
Dear Mr. Young:
On October 31, 2005, the Nuclear Regulatory Commission issued Amendment No. 222 to Facility Operating License No. DPR-72 for Crystal River Unit 3. Due to an administrative error, the first page of the safety evaluation (SE) contained an incorrect date for Addendum C to Topical Report BAW-2346P, Revision 0. Instead of August 12, 2005, it should be August 30, 2005.
Enclosed is the corrected page 1 of the SE. Please replace the first page of the SE with the enclosed page to correct the erroneous date. We are sorry for any inconvenience this may have caused.
Sincerely,
/RA/
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
Corrected Page 1 of SE cc w/encl: See next page
November 23, 2005 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:
CRYSTAL RIVER UNIT 3 - CORRECTED PAGE FOR SAFETY EVALUATION OF AMENDMENT NO. 222 REGARDING PROBABILISTIC METHODOLOGY FOR TUBE END CRACK ALTERNATE REPAIR CRITERIA (TAC NO. MC5813)
Dear Mr. Young:
On October 31, 2005, the Nuclear Regulatory Commission issued Amendment No. 222 to Facility Operating License No. DPR-72 for Crystal River Unit 3. Due to an administrative error, the first page of the safety evaluation (SE) contained an incorrect date for Addendum C to Topical Report BAW-2346P, Revision 0. Instead of August 12, 2005, it should be August 30, 2005.
Enclosed is the corrected page 1 of the SE. Please replace the first page of the SE with the enclosed page to correct the erroneous date. We are sorry for any inconvenience this may have caused.
Sincerely,
/RA/
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
Corrected Page 1 of SE cc w/encl: See next page Distribution:
PUBLIC RidsAcrsAcnwMailCenter RidsRgn2MailCenter (JMunday)
PDII-2 Reading RidsOgcRp RidsNrrPMBMozafari RidsNrrDlpmLpdii RidsNrrLABClayton RidsNrrDlpmDpr RidsNrrDlpmLpdii2 GHill (2 Hard Copies)
TBoyce EMurphy KKarowski LLund Package No.: ML053070396 Amendment No. 222: ML052940179 Accession Number: ML053070386 NRR-106 OFFICE NRR/LPLD/PM NRR/LPLD/LA NRR/LPLD/BC NAME BMozafari BClayton MMarshall DATE 11/08/05 11/07/05 11/23/05 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 222 TO FACILITY OPERATING LICENSE NO. DPR-72 FLORIDA POWER CORPORATION, ET AL.
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated January 25, 2005, as supplemented by letters dated August 12, September 9, and October 21, 2005, Florida Power Corporation submitted a license amendment request for Crystal River Unit 3 (CR-3) regarding the implementation of the alternate tube criteria (ARC) for the tube end crack (TEC) degradation mechanism affecting the steam generator (SG) tubes. This amendment request involves changes to the method for evaluating the primary to secondary leakage which potentially may occur during a main steam line break (MSLB). Specifically, the amendment request would add the following text to the CR-3 Improved Technical Specifications (ITS) 5.6.2.10.2.f:
The contribution to MSLB leakage rates from TEC indications shall be determined utilizing the methodology in Addendum B dated August 10, 2005 to Topical Report BAW-2346P, Revision 0.
The projection of TEC leakage that may develop during the next operating cycle shall be determined using the methodology in Addendum C dated August 30, 2005 to Topical Report BAW-2346P, Revision 0.
The supplement dated August 12, 2005, revised the original proposed initial no significant hazards consideration determination that was published on March 15, 2005 (70 FR 12746) and the NRC published a revised notice in the Federal Register. The supplemental letters dated September 9, and October 21, 2005, provided clarifying information that did not expand the scope of the original application or change the proposed no significant hazards consideration determination published August 26, 2005.
2.0 BACKGROUND
CR-3 is a two loop pressurized-water reactor (PWR) with once-through SGs (OTSGs) manufactured by Babcock & Wilcox. OTSGs differ from recirculating SGs of the type manufactured by Westinghouse and other manufacturers, in that the tubes are straight (no u-bends) extending from the tube inlets at the upper tubesheet to the tube outlets at the lower tubesheet. Both ends of each tube are roll expanded against the respective tubesheet over a 1-inch length and are seal welded to the respective tubesheet at the tube end. The tubes are Mill Annealed Alloy 600.
Mr. Dale E. Young Crystal River Nuclear Plant, Unit 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, Florida 33733-4042 Mr. Jon A. Franke Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Jim Mallay 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. Craig Fugate, 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 Mr. Michael J. Annacone Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Daniel L. Roderick Director Site Operations Crystal River Nuclear Plant (NA2C) 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. Terry D. Hobbs Manager Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 David T. Conley Associate General Counsel II - Legal Dept.
Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551