ML033630559

Additional Information Regarding Technical Specification (TS) Change 00-14, Pressure Temperature Limits Report (PTLR) and Request for Exemption from the Requirements of 10 CFR 50, Appendix G

ML033630559
Person / Time
Site:	Sequoyah
Issue date:	12/18/2003
From:	Salas P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MB6436, TAC MB6437
Download: ML033630559 (4)

Text

-p Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy. Tennessee 37384-2000 December 18, 2003 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos. 50-327 Tennessee Valley Authority 50-328 SEQUOYAH NUCLEAR PLANT SQN) - ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION (TS) CHANGE 00-14, "PRESSURE TEMPERATURE LIMITS REPORT (PTLR) AND REQUEST FOR EXEMPTION FROM THE REQUIREMENTS OF 10 CFR 50, APPENDIX G" (TAC NOS. MB6436 AND MB6437)-

Reference:

TVA letter to TVA dated March 28, 2003,

."Sequoyah Nuclear Plant (SQN) -- Response to Request for Additional Information (RAI)

Regarding Technical Specification (TS) Change 00-14, 'Pressure Temperature Limits Report (PTLR) and Request for Exemption From the Requirements of 10 CFR 50, Appendix G,' (TAC Nos. MB6436 and MB6437)"

Enclosed is additional-information to support NRC review of SQN TS Change 00-14. The additional information supplements the information provided in the reference letter and responds to two NRC follow-up questions from a September 16, 2003 telephone conferece call with your staff.

• 1. ~~ ~ ~ ~ +

Prhted ar recyded per

U.S. Nuclear Regulatory Commission Page 2 December 18, 2003 There are no commitments contained in this submittal.

Please direct questions concerning this issue to me at (423) 843-7 70 or J. D. Smith at (423) 843-6672.

as Lic ng and Industry Affairs Manager I declare under penalty of perjury that t regoing.s tru and correct. Executed on this V day of Enclosure cc (Enclosure):

Framatome ANP, Inc.

P. 0. Box 10935 Lynchburg, Virginia 24506-0935 ATTN: Mr. Frank Masseth Mr. Michael J. Marshall, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop O-8G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Lawrence E. Nanney, Director Division of Radiological Health Third Floor L&C Annex 401 Church Street Nashville, Tennessee 37243-1532

- s ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN)

ADDITIONAL INFORMATION FOR TECHNICAL SPECIFICATION (TS) CHANGE NO. 00-14, DOCKET NOS. 50-327 AND 50-328 The following additional information is provided in response to NRC staff questions from review of Westinghouse Topical Report WCAP-15984-P, Revision 1, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Sequoyah Units 1 and 2."

NRC Question 1 Provide a more precise estimate of when (in minutes into the heatup transient) the stress intensity factor (SIF) for the 0.1T outside diameter flaw at the location to which Figure 4-2 applies will exceed 33.2 ksi-inA0.5.

TVA Response Figure 4-2 of WCAP-15984-P, Revision 1, provides a summary of all the time steps in the heatup/cooldown transient for the governing location in the head. For a postulated flaw of depth equal to 0.1T, the stress intensity factor exceeds the value of 33.2 ksi-in^0.5 at a time of 344 minutes into the transient, which is at the end of the heatup. Other time steps where the stress intensity factor exceeds 33.2 ksi-in^0.5 include 355, 375, and 405 minutes. For these times, the reactor vessel is at least 500 degrees Fahrenheit, so the toughness is on the upper shelf, at least 200 ksi-in^0.5. This value is far above the minimum lower-shelf toughness, thus, fracture could not occur in this region.

This provides a simple and conclusive demonstration that there is no need for a flange requirement.

NRC Question 2 Identify whether or not a 0.1T outside diameter flaw at any location other than that to which Figure 4-2 applies will exceed a SIF of 33.2 ksi-inA0.5 at a time step earlier in the heatup transient. If so, provide the time (in minutes into the heatup transient) when the other location exceeds 33.2 ksi-inA0.5.

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4 TVA Response As stated in the report, the location covered by Figure 4-2 of WCAP-15984, Revision 1, is the governing location for the heatup/cooldown transient. Therefore, there are no other locations in the head where the stresses could be higher at a given temperature.

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