L-09-243, Supplemental Information for Review of License Renewal Application and License Renewal Application Amendment No. 41

Supplemental Information for Review of License Renewal Application and License Renewal Application Amendment No. 41

ML092530241
Person / Time
Site:	Beaver Valley
Issue date:	09/04/2009
From:	Sena P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-09-243, TAC MD6593, TAC MD6594
Download: ML092530241 (6)

Text

FENOC Beaver Valley Power Station P.O. Box 4 Shippingport,PA 15077 FirstEnergyNuclear Operating Company PeterP. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 September 4, 2009 L-09-243 10 CFR 54 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC Nos. MD6593 and MD6594), and License Renewal Application Amendment No. 41 Reference 1 provided the FirstEnergy Nuclear Operating Company (FENOC) License Renewal Application (LRA) for the Beaver Valley Power Station (BVPS). Reference 2 provided Amendment No. 40 to Reference 1. This letter clarifies and expands information provided in Reference 2 as discussed in a September 3, 2009 telephone conference call between FENOC and the U. S. Nuclear Regulatory Commission (NRC).

The Attachment provides the clarification and expanded information. The Enclosure provides Amendment 41 to the BVPS LRA.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.

I declare under penalty of perjury that the foregoing is true and correct. Executed on September 41 2009.

Sinceel, Peter P. Sena III 4ic

Beaver Valley Power Station, Unit Nos. 1 and 2 L-09-243 Page 2

References:

1. FENOC Letter L-07-113, "License Renewal Application," August 27, 2007.

2. FENOC Letter L-09-242, "Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC Nos.

MD6593 and MD6594), and License Renewal Application Amendment No. 40,"

September 2, 2009.

Attachment:

Supplemental Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Section B.2.3

Enclosure:

Amendment No. 41 to the BVPS License Renewal'Application cc: Mr. K. L. Howard, NRC DLR Project Manager Mr. S. J. Collins, NRC Region I Administrator cc: w/o Attachment or Enclosure Mr. B. E. Holian, NRC DLR Director Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRC DORL Project Manager Mr. D. J. Allard, PA BRP/DEP Director Mr. L. E. Ryan, PA BRP/DEP

ATTACHMENT L-09-243 Supplemental Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Section B.2.3 Page 1 of 2 Responses to Questions No. 1 and No. 2 (in FENOC Letter L-09-242) are replaced, in their entirety, with the following:

1. Describe the failure criteria for volumetric (UT) examination which will trigger the UT scanning at additional locations. In establishing the criteria, distinguish between the criteria used; (1) if the metal thinning is attributed to degradation on the inside surface of the liner, and (2) if the metal thinning is attributable to the exterior surface (in contact with the containment concrete) of the liner.

Metal thinning attributed to degradation on the inside surface of the liner will be managed in accordance with the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code Section XI, Subsection IWE Program. The statistical sampling program is not applicable to degradation of the inside surface of the liner.

Industry and site specific operating experience (OE) has demonstrated that pitting corrosion degradation due to foreign material manifests itself with pits that have measurable breadth and shape. FENOC characterizes a statistical failure at the concrete to liner interface as a random location with greater than 10% loss of material, displaying measurable breadth and shape; unless through engineering evaluation it is determined that indications are attributed to fabrication/erection practices or locations not indicative of corrosion. If a statistical failure is identified, it will be placed into the corrective action program and evaluated in accordance with 10 CFR 50, Appendix B, Criterion XVI. The random sample plan will assure a confidence level of 95% that 95%

of the accessible ultrasonically untested containment liner is not experiencing localized pitting corrosion degradation of concern. Statistical failures will be re-examined during subsequent outages until dispositioned. Locations with identified loss of material less than 10% but with a breadth and shape will be entered into the corrective action program and tracked as a point of interest for monitoring during subsequent outages until dispositioned.

Unit 1 inspections for the initial samplelot of a minimum of 75 random samples will be completed in the next three refueling outages, beginning with the next Unit 1 refueling outage in 2010. The entire sample plan will be completed by January 29, 2016. Results will be available for on-site review and included in the summary report letter as described in Question 3.

Attachment L-09-243 Page 2 of 2

2. Describe how you intend to statistically analyze the results of the UT examinations of the random and non-random samples (e.g., Kriging analysis or similar method) to determine the general state of the liner. Provide justification that your approach will adequately characterize the general state of the liner.

The purpose of the random sampling plan is to make valid characterizations about the general state of the containment liner. The random sampling plan includes 100% UT of a minimum of 75 1-ft x 1-ft square areas randomly selected on the accessible ultrasonically untested portion of the containment liner per unit. The completion of the random sample plan, with a minimum of 75 samples, will provide a confidence level of 95% that 95% of the accessible ultrasonically untested liner is not experiencing localized pitting corrosion of concern with greater than 10% loss of material.

FENOC will evaluate if an appropriate/applicable statistical method exists to gain additional insight into potential liner degradation. Data gathered will be evaluated and used to determine the general state of the liner.

During the course of data collection, FENOC will evaluate the data for wall thinning or corrosion that may potentially challenge the capability of the liner to perform its intended function. These conditions will be entered into the corrective action program for evaluation and disposition.

ENCLOSURE Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2 Letter L-09-243 Amendment No. 41 to the BVPS License Renewal Application Page 1 of 2 License Renewal Application Sections Affected Table A.4-1 The Enclosure identifies the correction by Affected License Renewal Application (LRA)

Section, LRA Page No., and Affected Paragraph and Sentence. The count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate. Below each section the reason for the change is identified, and the sentence affected is printed in italicswith deleted text lined eu and added text underlined.

Enclosure L-09-243 Page 2 of 2 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Table A.4-1 Page A.4-9 Item No. 32 Commitment No. 32 in LRA Table A.4-1, "Unit I License Renewal Commitments," is revised as follows:

Sectio Related LRA No.

Item. Implementation Number Commitment Schedule Source Section No/

Comments 32 Supplemental volumetric Unit I FENOC None examinations will be performed on the inspections for Letter Unit 1 containmentliner priorto the the initialsample L-09-205, period of extended operation. SA lot of a minimum and minimum of seventy-five (one foot of 75 random square)_fandomly selected (as ultrasonic FENOC described in FENOC Letter L-09-205) examinations will Letter sample locations will be examined (as be completed in L-09-242 described in FENOC Letter the next three and L-09-242243). If degradationis refueling identified, it will be addressed through outages, FENOC the corrective action programLas beginning with Letter described in FENOC Letter L-09-243). the Unit I L-09-243 refueling outage in 2010.

The random sample plan will be completed by January29, 2016