ML071080265: Difference between revisions

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As stated cc w/encl: See next page
As stated cc w/encl: See next page


ML071080265                                      NRR-088 OFFICE        LPL2-2/PM      LPL2-2/LA        CSGB/BC-A          LPL2-2/BC NAME          BMozafari      BClayton        AHiser            TBoyce by memo dated DATE          4/19/07        4/18/07          02/20/07          4/19/07
ML071080265                                      NRR-088 OFFICE        LPL2-2/PM      LPL2-2/LA        CSGB/BC-A          LPL2-2/BC NAME          BMozafari      BClayton        AHiser            TBoyce by memo dated DATE          4/19/07        4/18/07          02/20/07          4/19/07 REQUEST FOR ADDITIONAL INFORMATION FLORIDA POWER AND LIGHT COMPANY ST. LUCIE NUCLEAR POWER PLANT, UNIT 2 DOCKET NUMBER 50-389
 
REQUEST FOR ADDITIONAL INFORMATION FLORIDA POWER AND LIGHT COMPANY ST. LUCIE NUCLEAR POWER PLANT, UNIT 2 DOCKET NUMBER 50-389
: 1. Discuss your plans to modify TS Section 6.8.4.l.2.c.3 to be consistent with your current TS. All tubes with sleeves that have a nickel band shall be plugged after one cycle in operation. The staff is aware that the staffs previous suggestion for this TS section had a typographical error.
: 1. Discuss your plans to modify TS Section 6.8.4.l.2.c.3 to be consistent with your current TS. All tubes with sleeves that have a nickel band shall be plugged after one cycle in operation. The staff is aware that the staffs previous suggestion for this TS section had a typographical error.
: 2. Proposed TS Section 6.8.4.l.2.c.4.ii does not appear to be complete, since it assumes the repair criteria is independent of the location of the lower sleeve joint within the tubesheet. For example, if there is a lower sleeve joint at 10 inches from the top of tubesheet, the currently proposed TS would allow flaws below this region to remain in service. It is not clear that this is technically acceptable. As a result, discuss your plans to modify this TS section to address the repair criteria for the various locations where the sleeve joint could exist.
: 2. Proposed TS Section 6.8.4.l.2.c.4.ii does not appear to be complete, since it assumes the repair criteria is independent of the location of the lower sleeve joint within the tubesheet. For example, if there is a lower sleeve joint at 10 inches from the top of tubesheet, the currently proposed TS would allow flaws below this region to remain in service. It is not clear that this is technically acceptable. As a result, discuss your plans to modify this TS section to address the repair criteria for the various locations where the sleeve joint could exist.

Latest revision as of 16:24, 13 March 2020

Request for Additional Information Regarding the Steam Generator Tube Integrity Technical Specification Amendment
ML071080265
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/19/2007
From: Mozafari B
NRC/NRR/ADRO/DORL/LPLII-2
To: Stall J
Florida Power & Light Co
Mozafari B, NRR/ADRO/DORL, 415-2020
References
TAC MD2322
Download: ML071080265 (4)


Text

April 19, 2007 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 THE STEAM GENERATOR TUBE INTEGRITY TECHNICAL SPECIFICATION AMENDMENT (TAC NO. MD2322)

Dear Mr. Stall:

On May 25, 2006, Florida Power & Light Company (the licensee) submitted a license amendment request (LAR) regarding St. Lucie Unit 2 steam generator (SG) tube integrity technical specifications (TS). The proposed amendment would revise the SG tube integrity TS to be consistent with the U.S. Nuclear Regulatory Commissions (NRCs) approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. The licensee submitted additional information regarding this LAR in letter dated January 22, 2007.

The NRC staff has determined that more information is needed to complete our review.

Enclosed is the Request for Additional Information.

This request was discussed with Mr. Ken Frehaufer of your staff on March 19, 2007, and it was agreed that a response would be provided by April 20, 2007. If you have any questions, please feel free to contact me at 301-415-2020.

Sincerely,

/RA/

Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389

Enclosure:

As stated cc w/encl: See next page

ML071080265 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA CSGB/BC-A LPL2-2/BC NAME BMozafari BClayton AHiser TBoyce by memo dated DATE 4/19/07 4/18/07 02/20/07 4/19/07 REQUEST FOR ADDITIONAL INFORMATION FLORIDA POWER AND LIGHT COMPANY ST. LUCIE NUCLEAR POWER PLANT, UNIT 2 DOCKET NUMBER 50-389

1. Discuss your plans to modify TS Section 6.8.4.l.2.c.3 to be consistent with your current TS. All tubes with sleeves that have a nickel band shall be plugged after one cycle in operation. The staff is aware that the staffs previous suggestion for this TS section had a typographical error.
2. Proposed TS Section 6.8.4.l.2.c.4.ii does not appear to be complete, since it assumes the repair criteria is independent of the location of the lower sleeve joint within the tubesheet. For example, if there is a lower sleeve joint at 10 inches from the top of tubesheet, the currently proposed TS would allow flaws below this region to remain in service. It is not clear that this is technically acceptable. As a result, discuss your plans to modify this TS section to address the repair criteria for the various locations where the sleeve joint could exist.
3. Discuss your plans to modify proposed TS Section 6.8.4.l.2.d to clearly define when the inspection exclusion is applied. For example, For tubes with no portion of a lower sleeve joint in the hot-leg tubesheet region, the portion of the tube below 10.3 inches from the top of the hot leg tubesheet or expansion transition, whichever is lower, is excluded when the alternate repair criteria in TS Section 6.8.4.l.2.c.4 are applied.

In addition, the second sentence in the fifth paragraph on page 8 of Attachment 4 should be modified to read, For the original SGs, when the alternate repair criteria in TS Section 6.8.4.l.2.c.4 are applied, a SG tube is defined. . . .

4. Given that the original SGs have an approved SG tube repair method (i.e., sleeving),

discuss your plans to modify TS Section 6.9.1.13.e to read as follows, Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism.

5. On page 13 of Attachment 4 it is stated, To ensure that the margin is consistent with the Staffs discussion in the Reference 3, St. Lucie Unit 2 procedures further administratively limit operational leakage. This sentence appears to imply that meeting the margins defined in Reference 3 will ensure you always meet your accident induced leakage limit. That was not the intent of the discussion in Reference 3. Discuss your plans to modify this sentence to read as follows, St. Lucie Unit 2 procedures further administratively limit operational leakage with the intent that the accident induced leakage limits are not exceeded.
6. On page 19 of Attachment 4, you indicate, in part that site boundary doses for an SG tube rupture (SGTR) will not exceed an appropriately small fraction of Title 10 of the Code of Federal Regulations (10 CFR), Part 100. The staff was under the impression that your SGTR source term is based on 10 CFR, Part 50.67. Confirm whether Part 100 is the appropriate reference on page 19 and correct if necessary.

Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:

Mr. William E. Webster Mr. Christopher R. Costanzo Vice President, Nuclear Operations Plant General Manager Florida Power & Light Company St. Lucie Nuclear Plant P.O. Box 14000 6351 South Ocean Drive Juno Beach, FL 33408-0420 Jensen Beach, Florida 34957 Senior Resident Inspector Mr. Terry Patterson St. Lucie Plant Licensing 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 Mark Warner, Vice President Division of Emergency Preparedness Nuclear Operations Support Department of Community Affairs Florida Power & Light Company 2740 Centerview Drive P.O. Box 14000 Tallahassee, Florida 32399-2100 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Mr. Rajiv S. Kundalkar Florida Power & Light Company Vice President - Nuclear Engineering P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company Mr. J. Kammel 801 Pennsylvania Avenue, NW. Radiological Emergency Suite 220 Planning Administrator Washington, DC 20004 Department of Public Safety 6000 Southeast Tower Drive Mr. Douglas Anderson Stuart, Florida 34997 County Administrator St. Lucie County Mr. Bill Parks 2300 Virginia Avenue Operations Manager Fort Pierce, Florida 34982 St. Lucie Nuclear Plant 6351 South Ocean Drive Mr. William A. Passetti, Chief Jensen Beach, Florida 34957-2000 Department of Health Bureau of Radiation Control Mr. Seth B. Duston 2020 Capital Circle, SE, Bin #C21 Training Manager Tallahassee, Florida 32399-1741 St. Lucie Nuclear Plant 6351 South Ocean Drive Mr. Gordon L. Johnston Jensen Beach, Florida 34957-2000 Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000