L-2009-101, Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 2008

Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 2008

ML091210106
Person / Time
Site:	Saint Lucie
Issue date:	04/22/2009
From:	Katzman E Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2009-101
Download: ML091210106 (9)

Text

0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 April 22, 2009 FPL L-2009-101 10 CFR 50.59(d)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Report of 10 CFR 50.59 Plant Changes Pursuant to 10 CFR 50.59(d)(2), the attached report contains a brief description of any changes, tests, and experiments, including a summary of the 50.59 evaluation of each which were made on Unit I during the period of May 28, 2007 through November 21, 2008. This submittal correlates with the information included in Amendment 23 of the Updated Final Safety Analysis Report to be submitted under separate cover.

Please contact us should there by any questions regarding this information.

Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/tlt Attachment an FPL Group company

-I St. Lucie Unit I Docket No. 50-335 L-2009-101 Attachment ST. LUCIE UNIT 1 DOCKET NUMBER 50-335 CHANGES, TESTS AND EXPERIMENTS MADE AS ALLOWED BY 10 CFR 50.59 FOR THE PERIOD OF MAY 28, 2007 THROUGH NOVEMBER 21, 2008

St. Lucie Unit 1 Docket No. 50-335 L-2009-101 Attachment INTRODUCTION This report is submitted in accordance with 10 CFR 50.59 (d) (2),

which requires that:

i) changes in the facility as described in the SAR; ii) changes in procedures as described in the SAR; and iii) tests and experiments not described in the SAR that are conducted without prior Commission approval be reported to the Commission in accordance with 10 CFR 50.90 and 50.4. This report is intended to meet these requirements for the period of May 28, 2007 through November 21, 2008.

This report is typically divided into three (3) sections. First, changes to the facility as described in the Updated Final Safety Analysis Report (UFSAR) performed by a Plant Change/Modification (PC/M). Second, changes to the facility/procedures as described in the UFSAR, or tests/experiments not described in the UFSAR, which are not performed by a PC/M. And third, a summary of any fuel reload 50.59 evaluation.

However, there were no changes to the facility/procedures as described in the UFSAR, or tests/experiments not described in the UFSAR, performed by a PC/M. In addition, the fuel reload PC/M did not require a 50.59 evaluation. Therefore, only the evaluations that fall into Section 2 are provided.

Each of the documents summarized in Section 2 includes a 10 CFR 50.59 evaluation that evaluated the specific change(s). Each of these 50.59 evaluations concluded that the change does not require a change to the plant technical specifications, and prior NRCapproval is not required.

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F St. Lucie Unit 1 Docket No. 50-335 L-2009-101 Attachment TABLE OF CONTENTS SECTION 1 PLANT CHANGE/MODIFICATIONS PAGE None 4 SECTION 2 50.59 EVALUATIONS PAGE SEFJ-08-012 R.0 Operation with Reduced LPSI Flow Rate Due 6 to Observed Flow Anomaly at Valve HCV-3654 SENS-08-043 R.0 Removing the Automatic Control Function 7 For TCV-14-4A & Blocking the Valve Fully Open SECTION 3 RELOAD EVALUATION PAGE None 8 3

St. Lucie Unit 1 Docket No. 50-335 L-2009-101 Attachment SECTION 1 PLANT CHANGE / MODIFICATIONS For the time period of this report, the were no changes to the facility as described in the Updated Final Safety Analysis Report (UFSAR) performed by a Plant Change/Modification (PC/M).

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St. Lucie Unit I Docket No. 50-33 5 L-2009-1101 Attachment SECTION 2 50.59 EVALUATIONS 5

.4 St. Lucie Unit 1 Docket No. 50-335 L-2009-101 Attachment EVALUATION SEFJ-08-012 REVISION 0 Operation with Reduced LPSI Flow Rate Due to Observed Flow Anomaly at Valve HCV-3654 Summary:

This evaluation provides for operation during the next fuel cycle with the potential for a decrease in LPSI flow rates of up to 300 gpm.

While operating the shutdown cooling system during the SLI-22 refueling outage, a flow distortion in the 1B2 LPSI injection line was observed, where the LPSI flow through HCV-3645 decreased by approximately 250 gpm. A review of computer data indicated that the flow reduction was short-lived and that full flow was restored within 10 minutes without any operator intervention. In addition, a corresponding flow increase (of <50 gpm) was observed through the other three in-service LPSI injection header(s). The reduction of flow through HCV-3645 is an important issue because this valve is the motor-operated valve for LPSI injection into RCS Loop 1B2, which is a safety related function. This flow path is credited for automatically injecting water into the reactor coolant system during the injection phase of a LOCA, to support short term emergency core cooling. In addition, the flow path through HCV-3645 is used for quality-related functions associated with shutdown cooling operations.

As a result of the above anomalies, a calculation was performed by the PSL-I fuel vendor AREVA to assess the effects of a reduction of LPSI flow of 300 gpm during the injection phase of a large break LOCA, when the LPSI pumps are credited during post-accident conditions. The net effect of the 300 gpm flow reduction was an increase in LBLOCA peak clad temperature (PCT) of 12°F to 2059 0 F. The new PCT value is within the regulatory limit of 2200OF provided in 10 CFR 50.46, and therefore is acceptable.

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St. Lucie Unit 1 Docket No. 50-335 L-2009-101 Attachment EVALUATION SENS-08-043 REVISION 0 Removing the Automatic Control Function for TCV-14-4A

& Blocking the Valve Fully Open Summary:

The purpose of this evaluation is to demonstrate that the 1A ICW system is capable of performing its intended safety function while TCV-14-4A is clamped in the fully open position.

Valve TCV-14-4A is normally automatically controlled to maintain component cooling water temperatures during power operation. Valve TCV-14-4A will be clamped in the fully open position, its failed safe position, such that maximum flow is available through the 1A CCW heat exchanger during accident conditions.

This condition is also acceptable for normal at power service conditions. Valve TCV-14-4A is required to be open (throttled) during all operational modes. During accident conditions, TCV-14-4A can open further to permit increased ICW flow through the 1A CCW heat exchanger if required.

By clamping the valve fully open, accident heat load removal is assured. This configuration has been evaluated and it has been determined to be acceptable for normal operating conditions.

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A.-

St. Lucie Unit 1 Docket No. 50-335 L-2009-101 Attachment SECTION 3 RELOAD EVALUATION The fuel reload PC/M 08032 did not require a 10 CFR 50.59 evaluation.

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