L-2016-221, License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Inter-Val, Supplement

License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Inter-Val, Supplement

ML16347A658
Person / Time
Site:	Turkey Point
Issue date:	12/02/2016
From:	Summers T Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2016-221
Download: ML16347A658 (4)

Text

10 CFR 50.90 L-2016-221 December 2, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Inter-Val, Supplement

References:

Florida Power & Light Company letter L-2016-055, "License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval," April 4, 2016(ML16110A266)

In Reference 1, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 242 for Turkey Point Units 3 and 4. The proposed amendment would revise Technical Specification (TS) 3/4.7.6, Snubbers, to conform with the Snubber Testing Program. The Snubber Testing Program implements Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," of the ASME OM Code, 2004 Edition with 2005 and 2006 Addenda.

The attachment to this letter supplements Reference 1 by providing a mark-up of TS Index page x reflecting the proposed deletion of Table 4.7.2, Snubber Visual Inspection Interval, and the page renumbering of Sections 3/4.7.7, 3/4.7,8 and 3/4.7.9. The revision to the index reflects the changes requested in Reference 1 and is a purely administrative addition.

This supplement does not alter the conclusion in Reference 1 that the changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the changes.

No new or revised commitments are included in this letter.

Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035

Florida Power & Light Company L-2016-221 Page 2 of 2 Should you have any questions regarding this submission, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on the Zi\ldday of December 2016.

Sincerely, Thomas Summers Site Vice President Turkey Point Nuclear Plant Attachment cc: NRC Regional Administrator, Region II NRC Senior Resident Inspector NRC Project Manager Ms. Cindy Becker, Florida Department of Health

ATTACHMENT Markup of Technical Specifications Index Page x (1 page follows)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves ......... ... .. ............ .. ..... ... .......... ..... .... ........... ... ... ... ... ... .... ....... ... .. . 3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER LEVELWITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION ... ... ....... ...... . 3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP .. ..... ......... .......... ..... .. ...... ........ . . 3/4 7-2 Auxiliary Feedwater System .... ........ ........ ............ ... ........... ............. .... ... ... .. ... . 3/4 7-3 TABLE 3.7-3 AUXILIARY FEEDWATER SYSTEM OPERABILITY ................ ..*..... .... .. .... ... . 3/4 7-5 Condensate Storage Tank .... ... .... .... ........... ... ....... ..... ......... ...... ..... ..... .. .... .. ... . 3/4 7-6 Specific Activity ........ ....... ........ ... .. ..... ...... ..... ........... ...... ..... ........ .. ... .. ............. . 3/4 7-8 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS ..... ......... ... ... ...... ........ ..... .. .......... .... ...... ...... ..... .. ....... .. ... ...... . 3/4 7-9 {

Main Steam Line Isolation Valves ........ .. ............ ...... ..... ....... ......... ...... .. .. ...... . 3/4 7-10 Standby Feedwater System ........ ............ ......... .. ............. ... ... .. ... .. .... .. ... ... ..... . 3/4 7-11 Feedwater Isolation ... ..... .... ..... .. ....... .. .... ...... .... ....... ...... .... ... ... ... .. .. ....... .. ... .. . 3/4 7-13 3/4.7.2 COMPONENT COOLING WATER SYSTEM ...... ......... .... .. ... ... ....... .... .. ........ . 3/4 7-14 3/4.7.3 INTAKE COOLING WATER SYSTEM .. ... .. .... ..... .... ...... ....... ... ............ ... ....... . 3/4 7-16 3/4.7.4 ULTIMATE HEAT SINK ... ........ .... .... ...... ......... ... ............. ............ .... ... ...... ...... .

3/4.7 .5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM .... ... ....... ... ..... .. .

3/4.7.6 SNUBBERS ....... ..... ............ ......... .... .. ... ...... ...... .. ... ........ .... .... ... ... ...... ..... ...... .

TABLE 4.7 2 3/4.7.7 3/4.7.8 w

3/4.7.9 GAS DECAY TANKS... .... ......... ..... ... .... ... ... .... .. .. ... .. ......... ... ......... ....... .... ... ... . 314 7--&:l TURKEY POINT - UNITS 3 & 4 x AMENDMENT NOS. ~ AND -2.§8