ML060970288

Oyster Creek, Commitments Associated with Containment (Drywell and Torus) Condition Monitoring Related to Amergen Application for Renewed Operating License

ML060970288
Person / Time
Site:	Oyster Creek
Issue date:	04/04/2006
From:	Gallagher M AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
%dam200606, 2130-06-20284, FOIA/PA-2009-0070, TAC MC7624
Download: ML060970288 (6)

Text

Michael P.GallagheT, PE Telephone 610.765.5958 AmerGen An Exelon Company SM Vice President www.exeloncorp.com License Renewal Projects michaelp.gallagher@exeloncorp.com 10 CFR 50 ArnerGen 10 CFR 51 200 Exelon Way 10 CFR 54 KSA/2-E Kennett Square, PA 19348 2130-06-20284 April 4, 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:

Commitments Associated with Containment (Drywell and Torus) Condition Monitoring Related to AmerGen Application for Renewed Operating License -

Oyster Creek Generating Station (TAC No. MC7624)

References:

1. Letter from C.N. Swenson (AmerGen Energy Company, LLC) to USNRC "Application for Renewed Operating License, Oyster Creek Generating Station," dated July 22, 2005

2. Letter 2130-05-20238 from C. N. Swenson to USNRC "Additional Commitments Associated with Application for Renewed Operating License -

Oyster Creek Generating Station," dated December 9, 2005 In Reference 1, AmerGen Energy Company, LLC (AmerGen) committed to manage the aging of the Oyster Creek Generating Station (OCGS) containment in accordance with its ASME Section Xl, Subsection IWE Program. In Reference 2, AmerGen made a commitment to perform certain inspections of the Drywell shell in the sand bed region to confirm that actions previously taken have eliminated corrosion that had been occurring in that area of the Oyster Creek Generating Station (OCGS) primary containment.

AmerGen is now committing to perform additional actions to provide further assurance that the Drywell shell will remain capable of performing its design functions throughout the license renewal period. These prior and new commitments are collectively detailed in the attached Enclosure.

A new commitment is also made with regard to inspecting the coating material applied to the inside of the OCGS containment torus. This commitment is included in the listing provided in the Enclosure.

A04

April 4, 2006 Page 2 of 2 The above-described commitments will be specifically included as part of Commitment 27 from Table A.5 of Reference 1. Table A.5 contained the complete listing of Regulatory Commitments associated with the OCGS License Renewal Application. For completeness, Table A.5 will be re-submitted to the NRC under separate cover at a later date, capturing these and other commitments (unrelated to the Oyster Creek primary containment) made during the NRC's review of the OCGS License Renewal Application.

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 __-0 ___ -__6_

Date Michael P. Gallagher Vice President, License Renewal Projects AmerGen Energy Company, LLC

Enclosure:

Regulatory Commitments cc: Regional Administrator, USNRC Region I NRC Project Manager, NRR - License 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

ENCLOSURE REGULATORY COMMITMENTS

April 4, 2006 Page 1 of 3 ENCLOSURE - REGULATORY COMMITMENTS The following table identifies commitments made in this document. Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for information and are not regulatory commitments.

Committed One-Time Commitment Date or Action Programmatic Outage (Yes/No) (Yes/No)

1. Prior to the period of extended operation, Prior to period No Yes AmerGen will perform additional visual of extended inspections of the epoxy coating that was operation and applied to the exterior surface of the Drywell every ten shell in the sand bed region, such that the years during coated surfaces in all 10 Drywell bays will the period of have been inspected at least once. In extended addition, the Inservice Inspection (ISI) operation Program will be enhanced to require inspection of 100% of the epoxy coating every 10 years during the period of extended operation. These inspections will be performed in accordance with ASME Section Xl, Subsection IWE. Performance of the inspections will be staggered such that at least three bays will be examined every other refueling outage.

2. Ultrasonic Testing (UT) thickness Prior to period No Yes measurements of the drywell shell in the of extended sand bed region will be performed on a operation and frequency of every 10 years. The initial at 10-year inspection will occur prior to the period of intervals extended operation. The UT measurements thereafter will be taken from the inside of the drywell at the same locations where UT measurements were performed in 1996. The inspection results will be compared to previous results.

Statistically significant deviations from the 1992, 1994, and 1996 UT results will result in corrective actions that include the following:

• Perform additional UT measurements to confirm the readings.

• Notify NRC within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of confirmation of the identified condition.

• Conduct visual inspection of the

April 4, 2006 Page 2 of 3 Committed One-Time Commitment Date or Action Programmatic Outage (Yes/No) (Yes/No) external surface in the sand bed region in areas where any unexpected corrosion may be detected.

• Perform engineering evaluation to assess the extent of condition and to determine if additional inspections are required to assure drywell integrity.

• Perform operability determination and justification for operation until next inspection.

These actions will be completed prior to restart from the associated outage.

3. Consistent with current practice, a Refueling No Yes strippable coating will be applied to the outages prior reactor cavity liner to prevent water intrusion to and during into the gap between the drywell shield wall the period of and the drywell shell during periods when extended the reactor cavity is flooded. operation

4. The reactor cavity seal leakage trough Periodically No Yes drains and the drywell sand bed region drains will be monitored for water leakage.

5. A visual examination of the drywell shell in Prior to the Yes, if Yes, if the drywell floor inspection access trenches period of equipment maintained will be performed to assure that the drywell extended restored to within IWE steel remains intact. If degradation is operation original Inspection identified, the drywell shell condition will be configuration. Program evaluated and corrective actions taken as necessary. These surfaces will either be inspected as part of the scope of the ASME Section Xl, Subsection IWE inspection program or they will be restored to the original design configuration using concrete or other suitable material to prevent moisture collection in these areas.

6. The coating inside the torus will be Every other No Yes visually inspected in accordance with ASME refueling Section Xi, Subsection IWE, per the outage prior Protective Coatings Program. to and during the period of extended operation

April 4, 2006 Page 3 of 3 Committed One-Time Commitment Date or Action Programmatic Outage (Yes/No) (Yes/No)

7. AmerGen will conduct UT thickness Every other No Yes measurements in the upper regions of the refueling drywell shell every other refueling outage at outage prior the same locations as are currently to and during measured. the period of extended operation