ML061380647

E-mail: Commitment (PD)

ML061380647
Person / Time
Site:	Oyster Creek
Issue date:	05/03/2006
From:	Roy Mathew Office of Nuclear Reactor Regulation
To:	Lofaro R Brookhaven National Lab (BNL)
References
%dam200606, TAC MC7624
Download: ML061380647 (7)

Text

Mathew - commitment Page I From: Roy Mathew To: Lofaroebnl.gov Date: 5/3/06 9:06AM

Subject:

commitment see attached.

Please note that previous drywell commitments are in letter dated April 4, 2006 (ML060970288).

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Subject:

commitment Creation Date: Wed, May 3, 2006 9:06 AM From: Roy Mathew Created By: RKM(anrc.gov Recipients Action Date & Time bnl.gov Transferred 05/03 9:08 AM Lofaro (Lofaroaftbn.gov)

Post Office Delivered Route bnl.gov Files Size Date & Time MESSAGE 514 Wednesday, May 3, 2006 9:06 AM 2130-06-20328 Supplemental commitments 5-01-06.pdf 170547 Wednesday, May 3, 2006 8:38 AM Options Auto Delete: No Expiration Date: None Notify Recipients: No Priority: Standard Reply Requested: No Return Notification: None Concealed

Subject:

No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened

I RyMte -2100202Supeetlcm itmns:=10.d Paged11 Page 1 I Roy Mathew 2130-06-20328 Supplemental commitments 5-01-06.pdf AmerGen Energy Company, LIC www.exeloncorp.com Amer~n.g An Exelon Company 2oo Exeion Way KennettSquare, PA19348 10 CFR 50 10 CFR 51 10 CFR 54 2130-06-20328 May 1, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

Supplemental Commitments Associated with AmerGen Application for Renewed Operating Ucense - Oyster Creek Generating Station (TAC No. MC7624)

In recent months, the NRC Staff has been performing Audit activities associated with the AmerGen Energy Company LLC (AmerGen) application for a renewed operating license for Oyster Creek Generating Station (Oyster Creek). The Enclosure attached to this letter formalizes several commitments made verbally to the NRC during the course of these Aging Management Program (AMP) and Aging Management Review (AMR) Audit activities during the week of April 17, 2006.

In addition, note that Aging Management Program descriptions submitted as part of Appendix A of the LIcense Renewal Application (I.e., the UFSAR supplement information) affected during the NRC review process will be updated and submitted on a schedule supporting the NRC Staff's completion of Safety Evaluation Report activities.

Similarly, an update to the License Renewal Commitment LUst, Appendix A.5 of the LRA, will be provided, which will reflect the post-Audit integrated set of Aging Management Program related license renewal commitments.

If you have any questions regarding this information, please contact Fred Polaski, Manager, License Renewal, at 610-765-5935.

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

Respectfully, Executed on 05-/- @

Date Michael P. Galiagher Vice President, Ucense Renewal Projects AmerGen Energy Company, LLC

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Enclosure:

Regulatory Commitments cc: Regional Administrator, USNRC Region I NRC Project Manager, NRR - Ucense Renewal, Safety NRC Project Manager, NRR - License Renewal, Environmental, w/o Enclosure NRC Project Manager, OCGS, Part 50 NRC Senior Resident Inspector, OCGS Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection Oyster Creek File No. 05040

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ENCLOSURE REGULATORY COMMITMENTS

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Roy Mainew - 213U0-06-2bu3Z supplemental commitments b-01-05-ndt Pnae A I i rov iviatnew - L1.3U-U-U3Lb uoiementai commitments -U1-O6ndt Ptri A1 May 1, 2006 Page I of 2 ENCLOSURE - REGULATORY COMMITMENTS CommItted One-lime Commitment Date or Action Programmatic Outage (yes/No) (YeslNo)

1. As noted in ArnerGen's 4/4/06 letter to Every other No Yes NRC, AmerGen will perform torus coating refueling Inspections in accordance with ASME outage prior Section Xl Subsection IWE every other to and during refueling outage prior to and during the the period of period of extended operation. This new extended commitment clarifies that the scope of each operation of these Inspections will Include the wetted area of all 20 torus bays. Should the current towus coating system be replaced, the Inspection frequency and scope will be re-evaluated. Inspection scope will, as a minimum, meet the requirements of ASME Section XI, Subsection IWE.

2. AmerGen will develop refined acceptance Prior to the No Yes criteria and thresholds for entering torus next torus coating defects and unacceptable pit depths coating into the Corrective Action Process for further inspection, evaluation. These improvements will be which is also incorporated into the Inspection prior to the implementing documents prior to the next extended performance of these Inspections, which Is period of also prior to the period of extended operation operation.

3. AmerGen will replace the previously un- Prior to the Yes No replaced, buried safety-related ESW piping period of prior to the period of extended operation. extended operation

4. The One-Time Inspection program will Prior to the Yes No also include destructive or nondestructive period of examination of one (1) socket welded extended connection using techniques proven by past operation.

Industry experience to be effective for the Identification of cracking In small bore socket welds. Should an Inspection opportunity not occur (e.g., socket weld failure or socket weld replacement), a susceptible small-bore socket weld will be examined either destructively or non-destructively prior to entering the period of extended operation.

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5. In addition to AmerGen's previous Prior to the Yes No commitment to perform one-time visual period of examinations of the drywell shell in the areas extended exposed by the trenches In the bottom of the operation drywell (reference AmerGen 4/4/06 letter to NRC), one-time Ultrasonic Testing (UT) measurements will be taken to confirm the adequacy of the shell thickness in these areas, providing further confidence that the drywell remains capable of performing its intended function.

6. During the next UT inspections to be Prior to the Yes No performed on the drywell sand bed region period of (reference AmerGen 4/4106 letter to NRC), extended an attempt will be made to locate and operation evaluate some of the locally thinned areas Identified in the 1992 Inspection from the exterior of the drywell. This testing will be performed using the latest UT methodology with existing shell paint in place. The UT thickness measurements for these locally thinned areas may be taken from either inside the drywell or outside the drywell (sand bed region) to limit radiation dose to as low as reasonably achievable (ALARA).

7. Certification by a Professional Engineer of July 31, 2006 Yes No the reactor vessel design specification and design reports prepared for the fatigue activities associated with the Oyster Creek License Renewal Application will be performed by July 31, 2006. 1 1 1