ML072120604

Request for Additional Information Regarding 1.6-Percent Measurement Uncertainty Recapture Power Uprate

ML072120604
Person / Time
Site:	Crystal River
Issue date:	08/07/2007
From:	Stewart Bailey NRC/NRR/ADRO/DORL/LPLII-2
To:	Young D Florida Progress Corp
Bailey S , NRR/ADRO/DORL, 415-1321
References
TAC MD5500
Download: ML072120604 (5)

Text

August 7, 2007Mr. Dale E. Young, Vice PresidentCrystal River Nuclear Plant (NA1B)

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

SUBJECT:

CRYSTAL RIVER, UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATIONREGARDING 1.6-PERCENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC NO. MD5500)

Dear Mr. Young:

By letter dated April 25, 2007, the Florida Power Corporation submitted an application to amendthe Crystal River, Unit 3 facility operating license and technical specifications. The proposedamendment consists of a 1.6-percent measurement uncertainty recapture power uprate that will increase the rated thermal power from 2568 megawatts thermal (MWt) to 2609 MWt.The Nuclear Regulatory Commission staff has determined that it needs additional information inorder to complete its review. Please respond to the enclosed request for additional information (RAI) within 30 days of the date of this letter.Please contact me at 301-415-1321 if you have any questions on this issue.Sincerely,/RA/Stewart N. Bailey, Senior Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-302

Enclosure:

RAI cc w/encl: See next page

ML072120604 NRR-088OFFICELPL2-2LPL2-2/PMLPL2-2/LACSGB/BCLPL2-2/BCNAMEMVaalerSBaileyBClaytonAHiserTBoyceDATE08/06/0708/07/0708/02/077/9/2007*08/07/07* by memo Mr. Dale E. YoungCrystal 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 33733-4042Mr. Michael J. AnnaconePlant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Mr. Jim MallayFramatome ANP 1911 North Ft. Myer Drive, Suite 705 Rosslyn, Virginia 22209Mr. William A. Passetti, ChiefDepartment of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Attorney GeneralDepartment of Legal Affairs The Capitol Tallahassee, Florida 32304Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, Florida 34450-4245 Mr. Stephen J. Cahill (Acting)Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Mr. Jon A. FrankeDirector Site Operations Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Senior Resident InspectorCrystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, Florida 34428Ms. Phyllis DixonManager, Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708David T. ConleyAssociate General Counsel II - Legal Dept.

Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551Mr. Daniel L. RoderickVice President, Nuclear Projects & ConstructionCrystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Mr. David VarnerManager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 EnclosureREQUEST FOR ADDITIONAL INFORMATIONCRYSTAL RIVER UNIT NO. 31.6-PERCENT MEASUREMENT UNCERTAINTY RECAPTUREPOWER UPRATE LICENSE AMENDMENTDOCKET NO. 50-302By letter dated April 25, 2007, the Florida Power Corporation (the licensee) submitted LicenseAmendment Request No. 296 for the Crystal River Unit No. 3 (CR-3) facility operating license and technical specifications. The proposed amendment consists of a 1.6-percent measurement uncertainty recapture (MUR) power uprate that will increase the rated thermal power from 2568 megawatts thermal (MWt) to 2609 MWt. The Nuclear Regulatory Commission staff has determined that it needs responses to the following items in order to continue the review:1.On page 34 of Attachment D, you indicated that "a review of calculations performedwhich assessed the integrity of tubes containing flaws of various types when subjected to operating and accident loads was conducted." In addition, you indicated "this review ensured that existing structural margins are maintained for the MUR Power Uprate Program design conditions." This wording is unclear; therefore, confirm that this review did ensure that all existing structural margins are maintained for the power uprate.

In addition, please discuss how the various flaw types for SG tubes (existing and potential) were affected by the MUR power uprate.2.In Section 4.2.5.2, Inservice Testing (IST) Program, you indicate ". . . that the MURuprate is bounded by current analysis and any changes are insignificant." Please discuss the possible "insignificant changes" that may be made to the IST Program and what makes these changes "insignificant." 3.Confirm that the steam generators (SGs) will continue to satisfy all original designcriteria under the power uprate conditions. In addition, confirm that your analysis addresses the current condition of your SGs (e.g., plugs, tube repairs, loose parts, etc.)

and addresses flow induced vibration. Also, provide confirmation that your SG tube plugging limit is still appropriate for power uprate conditions, given the guidance in Regulatory Guide 1.121, "Bases for Plugging Degraded PWR (Pressurized-Water Reactor) Steam Generator Tubes."4.Confirm that the coating qualification temperature and pressure profile used by CR-3 tooriginally qualify Service Level I coatings remains bounding in light of the power uprate pressures and temperatures. If the original coating qualification pressure and temperature profile is no longer bounding, discuss the conditions to be used and corrective actions that will be taken to assure that Service Level I containment coatings will be qualified. 5.Please confirm the following regarding the SG blowdown system:a.That you considered whether the additional operating time due to the poweruprate will result in system components being more susceptible to flow

accelerated corrosion (FAC).b.That your current evaluation of the SG blowdown system under power uprateconditions considered the effect of a potential increase of impurities in the SG water.c.That any change to the inlet pressure of the SG blowdown system is still withinthe range of original design operating parameters.6.You indicated that "the predicted increases in maximum component wear rates andreductions in service lives will be managed by the CR-3 FAC program." Discuss how significant the increases in wear rates and reductions in service lives are for the power uprate conditions. In addition, discuss any changes made to CR-3's FAC program (i.e., criteria used for selecting components for inspection following the power uprate, criteria for repair and replacement, increased inspection scope, etc.) due to the power uprate conditions. Also, identify the systems that are expected to experience the greatest increase in wear as a result of the power uprate. Discuss whether inspections will be performed to assess wear prior to entering power uprate conditions. 7.Provide confirmation that your evaluation for the chemical and volume control systemdemonstrates that the conditions for the power uprate are bounded by the original design conditions (thermal performance, letdown and makeup requirements, etc.).