ML110190623

Turkey Point Nuclear Generating Plant, Units 3 & 4, E-mail, Extended Power Uprate Instrumentation and Controls Request for Additional Information - Round 1

ML110190623
Person / Time
Site:	Turkey Point
Issue date:	01/19/2011
From:	Paige J C Plant Licensing Branch II
To:	Abbatiello T, Abbott L, Tiemann P Florida Power & Light Co
Paige, Jason C, NRR/DORL,301-415-5888
References
Download: ML110190623 (2)

Text

From: Paige, Jason Sent: Wednesday, January 19, 2011 2:18 PM To: tom.abbatiello@fpl.com; Abbott, Liz; Tiemann, Philip Cc: Tomonto, Bob

Subject:

Turkey Point Extended Power Uprate (EPU) - Instrumentation and Controls (EICBs) 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 January 18, 2011, the Nuclear Regulatory Commission staff and Florida Power & Light Company discussed draft RAIs to gain a common understanding of the questions. During the call, it was concluded that an additional RAI would need to be generated. Question #2 below is the new RAI generated from the call. The below RAIs reflect the questions discussed and agreed upon during the January 18, 2011, call. 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.

EICB-1.1 TSTF-493, Option A "with changes to setpoint values" requires the licensee to provide summary calculations for each type of setpoint being revised, including Limiting Trip Setpoint (LTSP), Nominal Trip Setpoint (NTSP), Allowable Value (AV), As-Found Tolerance (AFT), and As-Left Tolerance (ALT). Provide the values of AFT and ALT for all revised setpoints listed in Table 3-11 of WCAP-17070-P, Rev. 0, and describe how you determine these AFT and ALT values with examples and/or diagrams. Also, it is not clear to U.S. Nuclear Regulatory Commission (NRC) staff why RCA is considered as acceptance magnitude for AFT on page 51 of WCAP-17070-P, nor what criterion is used to establish the ALT. EICB-1.2 The first section in Table 3-2 "Overtemperature T" of WCAP-17070-P, Rev. 0 (page 21), lists the allowance values for Rack Calibration Accuracy (RCA).

Provide the detail conversion calculation for the first four values (+/-0.5, +/-0.1, +/-0.4 and +/-0.2).

EICB-1.3 Section 3.1.4 of Attachment 1 (pages 1-5 and 1-6) of the submitted CD includes the following setpoint change:

15.a Turbine Trip-Emergency Trip Header Pressure However, the licensee did not provide the technical evaluation in Attachment 4, Section 2.4.1.2 nor in WCAP-17070-P, Rev. 0. Provide the technical evaluation and summary calculations (including LTSP, NTSP, AV, AFT, ALT, and margin) as listed in Table 3-11 of WCAP-17070-P, Rev. 0. Also, provide the bases to establish LTSP, NTSP, AV, AFT, ALT, and margin.

EICB-1.4 In Attachment 4, Table 2.4.4-1, row 7, "Steam enthalpy (moisture uncertainty) of submitted CD, the licensee listed the uncertainty values of steam enthalpy as 0.00%, and stated that the calorimetric calculation provides sufficient margin and is conservative with respect to the actual steam quality. What do you assume the value of steam quality in the calculation?

Explain and justify the uncertainty value of steam enthalpy is conservative in the calorimetric uncertainty calculation with your steam quality assumption.

EICB-1.5 In Attachment 4,Section I.5 "Out of Service [OOS] Requirements" (pages 2.4.4-6 to 2.4.4-8) of submitted CD, the licensee stated "The allowed outage time [AOT] for - the Cameron LEFM CheckPlus system will be 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided steady-state conditions persist." in page 2.4.4-6. The licensee then briefly described the LEFM CheckPlus system uncertainty in other maintenance modes (with 0.42%,

0.44% and 0.47% uncertainties in page 2.4.4-14) and stated "If the 48-hour allowed outage time is expected to be exceeded, then the plant will be operated at a power level consistent with the accuracy of the available plant instrumentation" in page 2.4.4-8.

a. Provide a list of all OOS conditions in detail.

b. Clarify that you have the same AOT (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) with all OOS conditions, and will restrict plant power to less than or equal to 2599 MWt (98.30% of the proposed licensed power) if the plant experiences a power change of greater than 2% during the 48-hour AOT period.

c. Provide detailed information (preferably with a table) with the proposed licensed power percentage and maximum MWt under each OOS conditions when the 48-hour outage period is exceeded.

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