ML062910274

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Supplemental RAI, Spent Fuel Pool Boraflex Remedy
ML062910274
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 10/24/2006
From: Moroney B
NRC/NRR/ADRO/DORL/LPLII-2
To: Stall J
Florida Power & Light Co
Moroney B, NRR/DORL, 415-3974
References
TAC MC9740, TAC MC9741
Download: ML062910274 (5)


Text

October 24, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

TURKEY POINT PLANT, UNIT NOS. 3 AND 4 - SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT FOR A SPENT FUEL POOL BORAFLEX REMEDY (TAC NOS. MC9740 AND MC9741)

Dear Mr. Stall:

By letter dated January 27, 2006, Florida Power & Light Company submitted requests to amend the Operating Licenses for Turkey Point Nuclear Plant, Units 3 and 4. The proposed amendments would revise the Technical Specifications to include new spent fuel pool storage patterns and the use of Metamic rack inserts, in order to remove reliance on Boraflex as a neutron absorber.

On August 8, 2006, the U.S. Nuclear Regulatory Commission (NRC) staff issued a Request for Additional Information (RAI) with a requested response within 60 days. Subsequently, the NRC staff has identified a need for additional details and clarification of the proposed surveillance program for the Metamic rack inserts. These are contained in the enclosed supplemental RAI.

This was discussed with members of your staff on October 3, 2006, and on October 16, 2006, Mr. Paul Czaya agreed that a combined response to both RAIs would be provided by November 30, 2006.

If you have any questions, please contact me at (301) 415-3974.

Sincerely,

/RA/

Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251

Enclosure:

Supplemental RAI cc w/encl: See next page

Mr. J. A. Stall TURKEY POINT PLANT Florida Power and Light Company cc:

Mr. William E. Webster Vice President, Nuclear Operations Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW.

Suite 220 Washington, DC 20004 T. O. Jones, Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035 County Manager Miami-Dade County 111 Northwest 1 Street, 29th Floor Miami, Florida 33128 Senior Resident Inspector Turkey Point Nuclear Plant U.S. Nuclear Regulatory Commission 9762 SW. 344th Street Florida City, Florida 33035 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Michael O. Pearce Plant General Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035 James Connolly Licensing Manager Turkey Point Nuclear Plant 9760 SW 344th Street Florida City, FL 33035 Mark Warner, Vice President Nuclear Operations Support Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Becky Ferrare Licensing Department Administrator Turkey Point Nuclear Plant 9760 SW 344th Street Florida City, FL 33035

ML062910274 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA CSGB/BC-A LPL2-2/BC NAME BMoroney BClayton AHiser by memo dated LRaghavan DATE 10/18/06 10/18/06 10/20/06 10/24/06

Enclosure SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL BORAFLEX REMEDY FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR PLANT, UNITS 3 AND 4 DOCKET NOS. 50-250 AND 50-251 By letter dated January 27, 2006 (ML060900250), Florida Power and Light Company (the licensee) submitted a request for review and approval of an amendment to the Turkey Point Unit 3 Operating License (DPR-31) and Turkey Point Unit 4 Operating License (DPR-41). The proposed amendments would revise Technical Specifications Sections 3/4.9.1-Boron Concentration, 3/4.9.14 - Spent Fuel Storage, and 5.5.1 - Criticality, to include new spent fuel storage patterns and the use of Metamic' rack inserts. A request for additional information (RAI) dated August 8, 2006 (ML062180074), was forwarded to the licensee. The NRC staff has subsequently identified a need for the following additional information that was not included in the August 8, 2006, RAI.

1.

The license amendment request proposes use of formed, welded, or a combination of formed and welded inserts. Is it correct for the staff to assume that a combination of formed and welded inserts means that a number of welded inserts and a number of formed inserts may be used? However, if this means that an insert design may consist of welding and forming, please provide a schematic of this insert design.

In addition, you indicated that the surveillance program will not vary with insert design, however, areas of interest in different designs should be documented in the surveillance program (i.e., base material, welds, heat affected zones, bend areas).

2.

Given that spent fuel pool (SFP) conditions may vary between Unit 3 and Unit 4, please confirm that the Metamic' insert surveillance program applies to both Unit 3 and Unit 4.

3.

Please provide the following details regarding the surveillance program:

a.

Baseline examinations that will be performed on the Metamic' inserts prior to being placed in the SFP (i.e., areal density, dimensional measurements, weight, visual inspections, photographs). In addition, discuss whether the baseline inspections will be performed at the fabrication facility or at the site.

b.

The frequency of Metamic' insert surveillances and its justification for each unit. This discussion should include the length of each interval, rationale and criteria by which decreasing/increasing intervals are determined, and the maximum length of time for the interval.

c.

The number of inserts to be examined during each surveillance and the rationale and criteria for making changes in the number of inserts to be examined during that surveillance and future surveillances.

d.

The details of the visual examinations that will be performed during each surveillance to ensure the acceptability of the Metamic' absorber material. This discussion should also include the criteria that will used to determine if additional testing and/or re-evaluation of the examination results is necessary.

e.

Plans to perform examinations to validate your visual examinations (i.e., weight measurements, dimensional measurements (length, width, and thickness),

Boron content measurement, neutron attenuation testing) and at what frequency these validation examinations will be performed.

f.

Reporting requirements for adverse insert test results.