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, 2007 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 NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 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 amend the Crystal River, Unit 3 facility operating license and technical specifications. The proposed amendment 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 in order 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 Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

RAI cc w/encl: See next page

ML072120604 NRR-088 OFFICE LPL2-2 LPL2-2/PM LPL2-2/LA CSGB/BC LPL2-2/BC NAME MVaaler SBailey BClayton AHiser TBoyce DATE 08/06/07 08/07/07 08/02/07 7/9/2007* 08/07/07

• by memo Mr. Dale E. Young Crystal River Nuclear Plant, Unit 3 Florida Power Corporation cc:

Mr. R. Alexander Glenn Mr. Stephen J. Cahill (Acting)

Associate General Counsel (MAC-BT15A) Engineering Manager Florida Power Corporation Crystal River Nuclear Plant (NA2C)

P.O. Box 14042 15760 W. Power Line Street St. Petersburg, Florida 33733-4042 Crystal River, Florida 34428-6708 Mr. Michael J. Annacone Mr. Jon A. Franke Plant General Manager Director Site Operations Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Mr. Jim Mallay Senior Resident Inspector Framatome ANP Crystal River Unit 3 1911 North Ft. Myer Drive, Suite 705 U.S. Nuclear Regulatory Commission Rosslyn, Virginia 22209 6745 N. Tallahassee Road Crystal River, Florida 34428 Mr. William A. Passetti, Chief Department of Health Ms. Phyllis Dixon Bureau of Radiation Control Manager, Nuclear Assessment 2020 Capital Circle, SE, Bin #C21 Crystal River Nuclear Plant (NA2C)

Tallahassee, Florida 32399-1741 15760 W. Power Line Street Crystal River, Florida 34428-6708 Attorney General Department of Legal Affairs David T. Conley The Capitol Associate General Counsel II - Legal Dept.

Tallahassee, Florida 32304 Progress Energy Service Company, LLC Post Office Box 1551 Mr. Craig Fugate, Director Raleigh, North Carolina 27602-1551 Division of Emergency Preparedness Department of Community Affairs Mr. Daniel L. Roderick 2740 Centerview Drive Vice President, Nuclear Projects &

Tallahassee, Florida 32399-2100 Construction Crystal River Nuclear Plant (SA2C)

Chairman 15760 W. Power Line Street Board of County Commissioners Crystal River, Florida 34428-6708 Citrus County 110 North Apopka Avenue Mr. David Varner Inverness, Florida 34450-4245 Manager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708

REQUEST FOR ADDITIONAL INFORMATION CRYSTAL RIVER UNIT NO. 3 1.6-PERCENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT DOCKET NO. 50-302 By letter dated April 25, 2007, the Florida Power Corporation (the licensee) submitted License Amendment 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 performed which 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 MUR uprate 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 design criteria 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 to originally 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.

Enclosure

5. Please confirm the following regarding the SG blowdown system:

a. That you considered whether the additional operating time due to the power uprate 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 uprate conditions 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 within the range of original design operating parameters.

6. You indicated that the predicted increases in maximum component wear rates and reductions 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 system demonstrates that the conditions for the power uprate are bounded by the original design conditions (thermal performance, letdown and makeup requirements, etc.).