ML093230559

Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application

ML093230559
Person / Time
Site:	Crystal River
Issue date:	11/30/2009
From:	Robert Kuntz License Renewal Projects Branch 2
To:	Franke J Progress Energy Florida
KUNTZ R, NRR/DLR, 415-2989
References
TAC ME0274
Download: ML093230559 (5)

Text

November 30, 2009 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

Dear Mr. Franke:

By letter dated December 16, 2008, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me at by telephone at 301-415-3733 or by e-mail at Robert.Kuntz@nrc.gov.

Sincerely,

/RA/

Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

As stated cc w/encl: See next page

ML093230559 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:DCI:CSGB BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz SFigueroa RTaylor DWrona RKuntz (Signature)

DATE 11/23/09 11/20/09 11/24/09 11/24/09 11/30/09

Letter to Jon Franke from Robert F. Kuntz dated November 30, 2009

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO: 50-302 RAI B.2.37-2

1. In July 2008, BADGER testing of Carborundum plates at Palisades Nuclear Plant (Palisades) revealed degradation of neutron absorber materials exceeding technical specification requirements. In response to the Palisades operating experience, the U.S.

Nuclear Regulatory Commission issued Information Notice 2009-26: Degradation Of Neutron-Absorbing Materials in the Spent Fuel Pool. Crystal River Unit 3 Nuclear Generating Plant (CR-3) has not provided sufficient information to justify the current surveillance of Carborundum using only a weight loss correlation of a 15% boron loss for a 20% weight loss. Given recent operating experience with Carborundum, discuss how the material condition of Carborundum will be monitored during the period of extended operation aside from the coupon testing and whether neutron attenuation testing will be used during the period of extended operation. If neutron attenuation or a comparable test will be performed, please provide the following:

Provide the scope of the testing. Include the structures and components that will be under surveillance.

Describe how the neutron-absorbing capacity and degradation of material will be monitored and trended. Include a description of the parameters, calculations, and acceptance criteria pertaining to the additional testing.

Discuss how the structures and components will be maintained for the extended licensing period. Please include the methods, techniques (e.g. BADGER testing, blackness testing), frequency, sample size, data collection and timing.

Describe the acceptance criteria of the testing and how it ensures that Carborundums structure and function are maintained over the extended period.

Describe the corrective actions that would be implemented if test results are not acceptable (e.g. expansion criteria).

2. The inspection interval for Carborundum was recently extended from every five years to every 10 years. Based on current operating experience, i.e., Palisades, and a 2004 failed sample with weight loss of 21% at CR-3, please provide additional justification for extending the surveillance inspections of the sample coupons to 10 years.

RAI 3.3.2.2.6-2 Discuss the surveillance program that will be implemented for Boral used in the spent fuel storage racks during the extended license period by providing the following:

Provide the scope of the program. Please include the structures and components that will be under surveillance.

Describe how the neutron-absorbing capacity and degradation of material will be monitored and trended. Please include a description of the parameters, calculations, and acceptance criteria.

Discuss how the structures and components will be maintained for the extended licensing period. Include the methods, techniques (e.g., visual, weight, volumetric, surface inspection), frequency, sample size, data collection and timing.

Describe the acceptance criteria of the program and how it ensures that Borals structure and function are maintained over the extended period.

Describe the corrective actions that would be implemented if test results are not acceptable.

RAI B.2.7-2.1 The response to RAI B.2.7-2 (in letter dated October 13, 2009) included a sample list of Condensate System components for which wall thinning is predicted and measured by ultrasonic testing (UT). The list includes the initial wall thickness (nominal), current (measured) wall thickness and the thickness predicted by the CHECWORKS FAC model.

Clarify the information in the Wear Rate Analysis: Combined Summary Report table. In particular, describe the initial, predicted, and measured wall thicknesses. For example, line Item 108-001P has an initial wall thickness of 0.375, a CHECWORKS predicted value of 0.444, and a current measured value of 0.455 mils. Clarify how the current measured thickness is greater than the initial thickness. In addition, provide the initial (measured) wall thickness for each system found in the table.

RAI B.2.16-1.1 The response to RAI B.2.16-1 (in letter dated October 13, 2009) stated that Performance of UT of the two tanks [FST-2A and FST-2B] is no longer contingent upon whether visual inspection proves inadequate or indeterminate. New preventive maintenance periodic activities using UT and internal tank inspections have recently been generated for FST-2A and FST-2B.

Provide the frequency of UT and internal inspections of the FST-2A and -2B tanks. Discuss whether periodic cleaning of the tanks will be conducted.

Crystal River Unit 3 Nuclear Generating Plant cc:

Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)

Florida Power Corporation P.O. Box 14042 St. Petersburg, FL 33733-4042 Mr. James W. Holt Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, FL 32399-1741 Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304 Mr. Ruben D. Almaguer, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, FL 34450-4245 Mr. Stephen J. Cahill Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. Daniel R. Westcott Supervisor, Licensing & Regulatory Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428-6708 Senior Resident Inspector Crystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL 34428 Mr. Jack E. Huegel Manager, Nuclear Oversight Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. David T. Conley Associate General Counsel II - Legal Dept.

Progress Energy Service Company, LLC P.O. Box 1551 Raleigh, NC 27602-1551 Mr. Michael P. Heath Supervisor, License Renewal Progress Energy 8470 River Road, 2E Southport, NC 28461 Mr. Mark Rigsby Manager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. Robert J. Duncan II Vice President, Nuclear Operations Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551

Crystal River Unit 3 Nuclear Generating Plant cc:

Mr. Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551