ML090540252

Proposed Technical Specifications Amendment TS 5.5.9, Steam Generator Program, TS 5.6-8, Steam Generator Tube Inspection Report.

ML090540252
Person / Time
Site:	Catawba
Issue date:	02/19/2009
From:	Morris J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TS 5.5.9, TS 5.6.8
Download: ML090540252 (6)

Text

Duke JAMES R. MORRIS, VICE PRESIDENT EEnergy Duke Energy Carolinas,LLC Carolinas Catawba Nuclear Station 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax February 19, 2009 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC (Duke)

Catawba Nuclear Station, Unit 2 Docket Number 50-414 Proposed Technical Specifications (TS) Amendment TS 5.5.9, "Steam Generator (SG) Program" TS 5.6.8, "Steam Generator (SG) Tube Inspection Report"

Reference:

Letters from Duke to NRC, same subject, dated November 13, 2008 and February 5, 2009 The'reference letters collectively comprise Duke's request for an amendment to Catawba Facility Operating License NPF-52-and-the subject TS. The amendment request proposed a one-cycle revision to the subject TS to incorporate an Interim Alternate Repair Criterion (IARC) in the provisions for SG tube repair criteria during the End of Cycle 16 Refueling Outage and subsequent Cycle 17 operation.

On February 12, 2009, a telephone conference call was held among members of Duke and the NRC staff. Based on the results of this call, Duke is revising the Facility Operating License condition proposed in the November 13, 2008 reference letter. The revised condition is included in the attachment to this letter.

The original regulatory and environmental analyses supporting the amendment request are not impacted by this amendment request supplement.

There are no new NRC commitments contained in this letter or its attachment.

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www. duke-energy.corn

U.S. Nuclear Regulatory Commission Page 2 February 19, 2009 Pursuant to 10 CFR 50.91, a copy of this letter and its attachment is being sent to the designated official of the State of South Carolina.

Inquiries on this matter should be directed to L.J. Rudy at (803) 701-3084.

Very truly yours, James R. Morris LJR/s Attachment

U.S. Nuclear Regulatory Commission Page 3 February 19, 2009 James R. Morris affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.

JamesvR. Morris, Vice President Subscribed and sworn to me:

Date Notary 0 ii My commission expires:  ?/'Z za5 /1-Date

,kjP. JAC/C 4rWcOASiO

U.S. Nuclear Regulatory Commission Page 4 February 19, 2009 xc (with attachment):

L.A. Reyes U.S.' Nuclear Regulatory Commission NRegional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA. 30303 A.T. Sabisch Senior Resident Inspector (CNS)

U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.H. Thompson (addressee only)

NRC Project Manager (CNS)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 S.E. Jenkins Section Manager Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201

ATTACHMENT REVISED FACILITY OPERATING LICENSE CONDITION

Amendment Implementation Number Additional Condition Date 165 The schedule for the performance of new and By January 31, 1999 revised surveillance requirements shall be as follows:

For surveillance requirements (SRs) that are new in Amendment No. 165 the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment No. 165. For SRs that existing prior to Amendment No. 165, including SRs with modified acceptance criteria and SRs who intervals of performance are being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of amendment No. 165. For SRs that existed prior to Amendment No. 165, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No. 165 172 The maximum rod average burnup for any rod Within 30 days of shall be limited to 60 GWd/mtU until the date of amendment.

completion of an NRC environmental assessment supporting an increased limit.

For steam generator (SG) integrity Prior to any entry assessments, the ratio of 2.5 will be used in into Mode 4 during completion of both the Condition Monitoring Cycle 17 operation (CM) and the Operational Assessment (OA) upon implementation of the Interim Alternate Repair Criterion (IARC). For example, for the CM assessment, the component of leakage from the lower 4 inches of the most limiting SG during the prior cycle of operation will be multiplied by a factor of 2.5 and added to the total leakage from any other source and compared to the allowable accident analysis leakage assumption. For the OA, the difference in leakage from the allowable limit during the limiting design basis accident minus the leakage from the other sources will be divided by 2.5 and compared to the observed leakage. An administrative limit will be established to not exceed the calculated value.

Renewed License No. NPF-52 Amendment No.