ML110460287

Turkey Point, Units 3 & 4, EPU - Steam Generator Tube Integrity and Chemical Engineering (Csgb) Request for Additional Information - Round 1

ML110460287
Person / Time
Site:	Turkey Point
Issue date:	02/15/2011
From:	Paige J C Plant Licensing Branch II
To:	Abbatiello T Florida Power & Light Co
Paige, Jason C, NRR/DORL,301-415-5888
References
Download: ML110460287 (2)

Text

From: Paige, Jason Sent: Tuesday, February 15, 2011 10:30 AM To: tom.abbatiello@fpl.com Cc: Abbott, Liz; Tiemann, Philip; Tomonto, Bob

Subject:

Turkey Point EPU - Steam Generator Tube Integrity and Chemical Engineering (CSGB) Request for Additional Information - Round 1 Tom, Below are requests for additional information (RAIs) regarding the Turkey Point extended power uprate license amendment request. On February 15, 2011, you stated that a call is not needed to discuss the draft RAIs sent to you via email. The below RAIs reflect the questions that were sent to you and agreed upon by Florida Power & Light Company (FPL). FPL agreed upon providing its responses within 30 days of the date of this email. If you have any questions, feel free to contact me.

CSGB-1.1 By letter dated October 21, 2010, Attachment 4, the licensee provides table 2.1.7-1, which summarizes the current and post extended power uprate (EPU) loss of coolant accident parameters applicable to Service Level 1 coatings. However, the table does not provide the results of the design basis accident (DBA) testing qualifying the Service Level 1 coatings. Provide the DBA testing results for the maximum temperature, pressure, pH and irradiation for the coatings used in containment in order for the NRC staff to ensure that the DBA tests bound the proposed EPU conditions.

CSGB-1.2 Florida Power & Light Company's Service Level 1 coating specifications failed to provide corrosion control to Turkey Point Nuclear Plant Units 3 and 4 containment liners. a. Per Licensee Event Report 2010-005-00, corrective actions to prevent coating failure reoccurrence include application of a coating system suitable for immersion service on the liner plate in the lower region of the reactor pit area for both plants. Explain how the coating system used will be qualified for normal and maximum hypothetical accidental conditions, including immersion. Provide the results of the qualification testing performed for the coating system used in this repair. b. As a result of this new operating experience, explain the changes to plant specifications and programs for Service Level 1 protective coatings; specifically with respect to procurement, storage, removal of existing coatings, surface preparations, application, inspection, applicator's certification, quality assurance documentation, and condition assessments. CSGB-1.3 The flow accelerated corrosion (FAC) monitoring program includes the use of a predictive method to calculate the wall thinning of components susceptible to FAC. In order for the staff to evaluate the accuracy of these predictions, the staff requests a sample list of components for which wall thinning is predicted and measured by ultrasonic testing or other methods. Include the initial wall thickness (nominal), current (measured) wall thickness, and a comparison of the measured wall thickness to the thickness predicted by the model.

Jason Paige, Turkey Point Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: (301) 415-5888