ML030300194

Request for Additional Information Regarding Reduction in Minimum Reactor Coolant System Flow

ML030300194
Person / Time
Site:	Saint Lucie
Issue date:	01/30/2003
From:	Moroney B NRC/NRR/DLPM/LPD2
To:	Stall J Florida Power & Light Co
Moroney B, NRR/DLPM, 415-3974
References
TAC MB6526
Download: ML030300194 (5)

Text

January 30, 2003 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING REDUCTION IN MINIMUM REACTOR COOLANT SYSTEM FLOW (TAC NO. MB6526)

Dear Mr. Stall:

By letter dated October 15, 2002, Florida Power and Light Company submitted an amendment to reduce the design reactor coolant system flow rate to accommodate an increase in the steam generator plugging level.

The U.S. Nuclear Regulatory Commission staff has reviewed your submittal and finds that a response to the enclosed request for additional information is needed before we can complete the review. This request was discussed with your staff on January 10, 2003, and Mr. George Madden of your staff agreed that a response would be provided within 30 days.

If you have any questions, please feel free to contact Eva Brown at (301) 415-2315.

Sincerely,

/RA by Eva Brown for/

Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-389

Enclosure:

Request for Additional Information cc w/encl: See next page

ML030300194 OFFICE PDII-2/PM PDII-2/PM PDII-2/LA SRXB/SC PDII-2/SC NAME EBrown for EBrown BClayton FAkstulewicz KJabbour for BMoroney AHowe DATE 1/29/03 1/29/03 1/29/03 1/29/03 1/29/03 Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:

Senior Resident Inspector Mr. R. E. Rose St. Lucie Plant Plant General Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6351 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mr. J. T. Voorhees Division of Emergency Preparedness Acting Licensing Manager Department of Community Affairs St. Lucie Nuclear Plant 2740 Centerview Drive 6351 South Ocean Drive Tallahassee, Florida 32399-2100 Jensen Beach, Florida 34957 M. S. Ross, Attorney Mr. Don Mothena Florida Power & Light Company Manager, Nuclear Plant Support Services P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator Mr. Rajiv S. Kundalkar St. Lucie County Vice President - Nuclear Engineering 2300 Virginia Avenue Florida Power & Light Company Fort Pierce, Florida 34982 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. William A. Passetti, Chief Department of Health Mr. J. Kammel Bureau of Radiation Control Radiological Emergency 2020 Capital Circle, SE, Bin #C21 Planning Administrator Tallahassee, Florida 32399-1741 Department of Public Safety 6000 SE. Tower Drive Mr. Donald E. Jernigan, Site Vice President Stuart, Florida 34997 St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957

REQUEST FOR ADDITIONAL INFORMATION REDUCTION IN MINIMUM REACTOR COOLANT SYSTEM FLOW AMENDMENT FLORIDA POWER AND LIGHT SAINT LUCIE UNIT 2 DOCKET NO. 50-389

1) In Attachment 4, on pages 2, 4 and 5 specify replacement of DNB-SAFDL of 1.28 with appropriate correlation limit for DNB-SAFDL. Given that there are two departure from Nucleate Boiling correlations that can be used, how do you choose which limit to use and where is that detailed?

a) Is it true that there is now only GUARDIAN fuel in the core (Section 3.1, Attachment 6, Page 3)?

b) Section 2 of Attachment 6 on page 2 states that the conclusions of this evaluation remain applicable to all fuel designs currently used in the St. Lucie Unit 2 core. Do you need to use two different correlations?

c) Are you using CE-1 and ABB-NV or McBeth? Are these approved for GUARDIAN fuel?

2) Section 2.0 of Attachment 6 on page 2 states that the flow reduction results in

. . . small coolant and fuel rod temperature increases . . . Table 3.1-1 of Attachment 6 on page 4 includes the maximum clad surface temperature. Please explain why this did not increase with reduced flow.

3) Please clarify the meaning of the plot in Attachment 4 on page 3. Is this the axial and radial peak distribution or only the axial power distribution?

4) Demonstrate that the appropriate criteria will be met for all non-loss-of-coolant accident events. Please quantify results in your demonstration. Include a statement of the methodology used and whether there were any deviations from the methodology and treatment of uncertainties as previously approved by the staff. Please confirm that any changes in the use of the methodology continues to comply with any staff requirements for its use.

Enclosure