L-2012-177, Supplemental Response to NRC Mechanical and Civil Engineering Branch (Emcb) Regarding Extended Power Uprate License Amendment Request

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Supplemental Response to NRC Mechanical and Civil Engineering Branch (Emcb) Regarding Extended Power Uprate License Amendment Request
ML12114A225
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/19/2012
From: Richard Anderson
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2012-177
Download: ML12114A225 (7)
v • d • e


Text

Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 FPL.

April 19, 2012 L-2012-177 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit 2 Docket No. 50-389 Renewed Facility Operating License No. NPF-16 Supplemental Response to NRC Mechanical and Civil Engineering Branch (EMCB) Regarding Extended Power Uprate License Amendment Request

References:

(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-021),

"License Amendment Request for Extended Power Uprate," February 25, 2011, Accession No. ML110730116.

(2) Email from T. Orf (NRC) to C. Wasik (FPL), "St. Lucie 2 EPU draft RAIs -

Mechanical & Civil Engineering Branch (EMCB)," January 13, 2012.

(3) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2012-059),

"Response to NRC Mechanical and Civil Engineering Branch (EMCB) Request for Additional Information Regarding Extended Power Uprate License Amendment Request," February 29, 2012, Accession No. ML12065A148.

By letter L-2011-021 dated February 25, 2011 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. NPF-16 and revise the St. Lucie Unit 2 Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an Extended Power Uprate (EPU).

By email from the NRC Project Manager dated January 13, 2012 [Reference 2],

additional information was requested by the NRC staff in the Mechanical and Civil Engineering Branch (EMCB) to support their review of the EPU License Amendment Request (LAR). The request for additional information (RAI) identified 47 questions. By letter L-2012-059 dated February 29, 2012 [Reference 3], FPL provided the requested information. In that letter, FPL also committed to provide a supplemental response to RAI EMCB-1 in a separate submittal. The attachment to this letter provides FPL's first supplemental response to RAI EMCB-1.

Aoo0La 4 .

an FPL Group company

L-2012-177 Page 2 of 2 This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2011-021 [Reference 1].

This submittal contains no new commitments and no revisions to existing commitments.

In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.

Should you have any questions regarding this submittal, please contact Mr. Christopher Wasik, St. Lucie Extended Power Uprate LAR Project Manager, at 772-467-7138.

I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.

Executed on 1"7- 4pr; i-AC,/.2 Very truly yours, hard L.nde Site Vice President St. Lucie Plant Attachment (1) cc: Mr. William Passetti, Florida Department of Health

L-2012-177 Attachment Page 1 of 5 Supplemental Response to NRC Mechanical and Civil Engineering Branch (EMCB) Request for Additional Information The following information is provided by Florida Power & Light (FPL) in response to the U. S.

Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support Extended Power Uprate (EPU) License Amendment Request (LAR) for St. Lucie Nuclear Plant Unit 2 that was submitted to the NRC by FPL via letter (L-2011-021) dated February 25, 2011, Accession Number ML110730116.

In an email dated January 13, 2012 from NRC (Tracy Oft) to FPL (Chris Wasik),

Subject:

St.

Lucie 2 EPU draft RAIs - Mechanical & Civil Engineering Branch (EMCB), the NRC requested additional information regarding FPL's request to implement the EPU. The RAI consisted of forty-seven (47) questions from the NRC's Mechanical and Civil Engineering Branch (EMCB).

By letter L-2012-059 dated February 29, 2012, Accession No. ML12065A148, FPL provided the requested information. In that letter, FPL also committed to provide a supplemental response to RAI EMCB-1 in a separate submittal. This attachment provides FPL's first supplemental response to RAI EMCB-1.

EMCB-1 The staff requests that the licensee provide assurance that all structural modifications and/or additions have been identified and designed and that all structural evaluations and required design calculations to demonstrate that all systems, structures and components (SSCs) credited to and/or affected by the proposed extended power uprate (EPU) have been completed and controlled documentation exists which finds said SSCs structurally adequate to perform their intended design functions under EPU conditions.

Supplemental Response:

As described in letter L-2012-059, FPL advised the NRC that with the exception of the EPU modifications listed below, applicable safety related and/or seismic piping and associated structural evaluations and design calculations for affected systems, structures and components (SSCs) credited to and/or affected by the proposed EPU have been completed. The following EPU modifications were identified as not being complete at that time:

" Main Steam, Feedwater, and Condensate Pipe Support Modification,

" Chemical and Volume Control System (CVCS) Vent Modification,

  • Control Room Air Conditioning Margin Improvement.

This supplemental response provides the completed design details for the first two EPU modifications.

Piping stress summary data for the safety-related and/or seismic main steam and feedwater piping systems impacted by EPU is provided in Table 1. A list of the safety-related and/or seismic main steam and feedwater pipe support modifications that are required for the EPU is provided in Table 2. Note that the attachment steel calculations for the main steam and feedwater piping support modifications located in the Turbine Building are not complete at this time. A supplemental response will be submitted to NRC providing confirmation that these structural steel calculations are complete.

L-2012-177 Attachment Page 2 of 5 There are no safety-related and/or seismic piping or pipe support modifications for the St. Lucie Unit 2 condensate piping system.

Piping stress summary data for the chemical and volume control system (CVCS) vent modification is provided in Table 3 and a list of the associated pipe support modifications is provided in Table 4.

Design information regarding the control room air conditioning margin improvement modification is not complete. Design details regarding this EPU modification will be provided to NRC in a supplemental response.

L-2012-177 Attachment Page 3 of 5 Table 1 Main Steam and Feedwater Piping Stress Summary at EPU Conditions Piping Analysis Loading Existing EPU Design Psiptiong ANai 3 Condition Stress Stress Allowable s Margin Description (Note 3) (Note 2) (psi) (psi) Stress (psi) (Note 1)

Main Steam Piping from Equation 8 6,624 9,062 15,000 0.60 SG-2A to Containment Equation 9U 4,169 10,975 18,000 0.61 Penetration P-1 Equation 9F 4,582 10,600 36,000 0.29 Equation 10 8,208 7,986 22,500 0.35 Equation 8 6,613 8,711 15,000 0.58 Main Steam Piping from Equation 9U 4,755 11,025 18,000 0.61 SG-2B to Containment Penetration P-2 Equation 9F 5,033 11,037 36,000 0.31 Equation 10 8,427 7,943 22,500 0.35 Equation 8 7,828 7,926 15,000 0.53 Main Steam Piping from Equation 9U 9,567 13,170 18,000 0.73 Containment Penetrations P-1 and P-2 to HP Turbine Equation 9F 5,693 13,186 36,000 0.37 Equation 10 19,149 20,535 22,500 0.91 Equation 8 5,222 6,061 15,000 0.40 Feedwater Piping from Containment Penetration Equation 9U 8,840 10,013 18,000 0.56 P-3 to SG-2A Equation 9F 8,276 9,477 36,000 0.26 Equation 10 14,089 12,096 22,500 0.54 Feedwater Piping from Equation 8 5,664 6,325 15,000 0.42 Containment Penetration Equation 9U 7,567 9,010 18,000 0.50 P-4 to SG-2nn Equation 9F 9,144 9,339 36,000 0.26 Equation 10 9,330 11,304 22,500 0.50 Feedwater Piping from Equation 8 8,321 8,730 15,000 0.58 Feedwater Pumps to Equation 9U 7,371 13,911 18,000 0.77 Containment Penetrations Equation 9F 7,371 13,924 36,000 0.39 P-3 and P-4 Equation 10 16,119 17,950 22,500 0.80 Notes:

1. Stress Interaction Ratio (also called "Design Margin") is based on the ratio of EPU stress divided by the Allowable stress.
2. The pipe stress analysis equation numbers listed in this table correspond to ASME Section III, NB-3650, NC-3650, and ND-3650 equation numbers.
3. Description is based on pipe stress analysis segment of a given system included in the analysis.

L-2012-177 Attachment Page 4 of 5 Table 2 Main Steam and Feedwater Pipe Support Modifications for EPU Conditions Support Mark Pipe Size Building Modification Description Item Number (in.) Location 1 MS-4100-6080 MS 34 Reactor Containment New support 2 MS-4100-6080 MVS 34 Reactor New support 2 MS-4101-315A MVS 34 Containment New support 3 MS-4102-274 MS 38 Turbine Bldg Add weld 4 MS-4102-32B MS 38 Turbine Bldg Add cover plate 5 MS-4102-48 MS 38 Turbine Bldg Add tube steel brace 6 MS-4102-3910 MS 38 Turbine Bldg Add weld 7 BF-4004-258 FW 20 Turbine Bldg Add weld 8 BF-4004-38 FW 20 Turbine Bldg Replace snubbers Notes:

FW = Feedwater MS = Main Steam Table 3 Maximum Piping Stress for Chemical and Volume Control (CVCS) Vent Modification Code Existing EPU Allowable Equation Maximum Maximum Stress1 (psi) Stress Ratio Stress (psi) Stress (psi)

Equation 8 4835 4979 17200 .0.289 Equation 9B 6386 12037 20640 0.583 Equation 9D. 6974 17186 41280 0.416 Equation 10 13222 9950 27800 0.358 Note:

1. The allowable stress values are based on a design temperature of 250 0F.

L-2012-177 Attachment Page 5 of 5 Table 4 Pipe Supports Affected by Chemical and Volume Control (CVCS) Vent Modification Pipe Support Mark Piping System Number Support Attribute Of Concern Resolution CH-136-Ri Added pipe line CH-1 011 New Support CH-136-R2 Added pipe line CH-1 011 New Support CH-1 36-R3 Added pipe line CH-1 011 New Support CH-136-R4 Added pipe line CH-1012 New Support CH-136-R5 Added pipe line CH-1 004 New Support CH-136-R6 Added pipe line CH-1 004 New Support CH-136-R7 Added pipe line CH-1 019 New Support CH-136-R8 Added pipe line CH-1 017 New Support CH-136-R9 Added pipe line CH-1019 New Support CH-136-RlO Added pipe line CH-1007 New Support CH-136-R11 Added pipe line CH-1013 New Support CH-136-R12 Added pipe line CH-1 013 New Support CH-136-R13 Added pipe line CH-1 013 New Support CH-136-R14 Added pipe line CH-1 013 New Support CH-136-R15 Added pipe line CH-1014 New Support CH-136-R16 Added pipe line CH-1005 New Support Chemical and Volume Control CH-136-R17 Added pipe line CH-1020 New Support System (CVCS) CH-136-R18 Added pipe line CH-1 015 New Support Vent Modification CH-136-R19 Added pipe line CH-1015 New Support CH-136-R20 Added pipe line CH-1 015 New Support CH-136-R21 Added pipe line CH-1 015 New Support CH-136-R22 Added pipe line CH-1 016 New Support CH-136-R23 Added pipe line CH-1 006 New Support CH-136-R24 Added pipe line CH-1 006 New Support CH-136-R25 Added pipe line CH-1 006 New Support CH-136-R26 Added pipe line CH-1 021 New Support CH-136-R27 Added pipe line CH-1 018 New Support CH-136-R28 Added pipe line CH-1 008 New Support CH-136-R29 Added pipe line CH-1 008 New Support CH-2082-39 Existing Support Acceptable CH-2082-1 01 Existing Support Acceptable CH-2082-106 Existing Support Acceptable CH-2082-115 Existing Support Acceptable CH-2082-126 Existing Support Acceptable

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