ML083250640

Summary of Telephone Conference Call Held 11/14/08, Between the NRC and FENOC, Concerning RAIs Pertaining to the Beaver Valley Power Station, Units 1 and 2, License Renewal Application

ML083250640
Person / Time
Site:	Beaver Valley
Issue date:	12/15/2008
From:	Kent Howard Division of License Renewal
To:	FirstEnergy Nuclear Operating Co
References
TAC MD6593, TAC MD6594
Download: ML083250640 (8)

Text

December 15, 2008 LICENSEE: FirstEnergy Nuclear Operating Company FACILITY: Beaver Valley Power Station, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 14, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company held a telephone conference call on November 14, 2008, to discuss and clarify the staffs requests for additional information (RAIs) concerning the Beaver Valley Power Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs RAIs.

provides a listing of the participants and Enclosure 2 contains a listing of the RAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

Kent L. Howard, Sr., Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosures:

As stated cc w/encls.: See next page

ML083250640 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME IKing KHoward DWrona DATE 11/20/08 11/21/08 12/15/08

TELEPHONE CONFERENCE CALL BEAVER VALLEY POWER STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS NOVEMBER 14, 2008 PARTICIPANTS AFFILIATIONS Kent Howard U.S. Nuclear Regulatory Commission (NRC)

Bryce Lehman NRC Hansraj Ashar NRC Zuhan XI NRC Farhad Farzam NRC Clifford Custer FirstEnergy Nuclear Operating Company (FENOC)

John Thomas FENOC Glenn Ritz FENOC Levi Stahl FENOC Tony Dometrovich FENOC Larry Freeland FENOC

REQUESTS FOR ADDITIONAL INFORMATION BEAVER VALLEY POWER STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION NOVEMBER 14, 2008 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company (FENOC) held a telephone conference call on November 14, 2008, to discuss and clarify the following requests for additional information (RAIs) concerning the Beaver Valley Power Station (BVPS), Units 1 and 2, license renewal application (LRA).

RAI 3.5.2.2-1 In LRA Subsection 3.5.2.2, the applicant stated that the concrete specifications for BVPS concrete were designed in accordance with American Concrete Institute (ACI) 318 and constructed in accordance with ACI 301 using materials conforming to ACI and American Society for Testing and Materials (ASTM) standards. The Generic Aging Lessons Learned (GALL) Report suggests that concrete is constructed in accordance with the recommendations in ACI 201.2R for a quality concrete with low water-to-cement mix ratio (0.35-0.45), smaller aggregate, long curing period, adequate air entrainment (3-6%), and through consolidation.

Please compare BVPS concrete with ACI 201.2R including water-to-cement ratio and air content.

RAI 3.5.2.2-2 In LRA Section 3.5.2.2.1.1 and Item 3.5.1-01 of LRA Table 3.5.1, the applicant concluded that aging of concrete areas due to corrosion of embedded steel is not applicable to containment structures. However, in LRA Appendix B.2.5, ASME Section XI, Subsection IWL, the following statement is made: Previous BVPS Containment Building inspections have identified minor issues such as mildew and rust stains, spalling, surface cracks, and loose foreign materials.

Please clarify if corrosion of embedded steel is the cause for rust stains and spalling and surface cracks. If yes, justify your conclusion in the LRA that the aging effect is not applicable, and related items in LRA Table 3.5.1 and Table 3.5.2.

Discussion: The applicant indicated that the questions are clear. The staff wanted the applicant to explain their response to RAIs 3.5.2.2-1 and 3.5.2.2-2 dated June 16, 2008. The staff questioned why FENOC called aging effects for some concrete not applicable. The applicant explained that the use of Electric Power Research Institute (EPRI) structural tools and the BVPS site operating experience led to the conclusion that the aging effects were not applicable. The EPRI structural tools do not identify degradation of below grade concrete or loss of material of embedded steel (in concrete) as applicable aging effects. The applicant also stated that BVPS operating experience has not shown degradation of concrete. The applicant explained that despite the fact that FENOC did not expect aging effects to occur, an aging management program (AMP) was assigned to periodically inspect the subject concrete. The staff reiterated their concern that the aging effects were not applicable because of the potential for chemical conditions in groundwater to change in the future. FENOC stated that in every

case, the subject concrete was managed by an AMP, so degradation would be detected should it occur in the future. The staff again asked why FENOC had called the aging effect not applicable. FENOC then clarified that N/A in the LRA tables meant that a GALL row was not assigned. The staff then asked for the FENOC position in writing. FENOC pointed out that the docketed response to RAI B.2.39-2, dated June 6, 2008, contained the written position. The response to RAI B.2.39-2 was then reviewed by the staff. The staff then concurred that FENOCs proposed position was acceptable.

RAI 2.4.22-5 (Item 14)

From Table 2.4-22, Reactor Containment Building Components Subject to Aging Management Review, of the LRA, it is not clear if the following components of the Containment Structure have been screened-in and subject to an aging management review (AMR). Please confirm and explicitly clarify their inclusion in Table 2.4-22, and ensure that the appropriate AMR results are identified or justify their exclusion.

14. Emergency seepage removal system, including concrete shafts extending from grade to the instrument pits located in the top of the containment.

Discussion: Based on the discussion with the applicant, the staff indicated that this question requires further clarification. This is a continued discussion from October 22, 2008. FENOC again stated its position on the Statements of Consideration (SOC), stating that verification of surveillances for active components is not specified and reiterated that actions taken are being taken to address the issue in Part 50 space. The staff stated that they were looking for an additional submittal under license renewal, but would consult with the Office of General Council on the interpretation of the SOC.

Memorandum from K. Howard, dated December 15, 2008 DISTRIBUTION:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 14, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY:

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Beaver Valley Power Station, Units 1 and 2 cc:

Joseph J. Hagan President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308 James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Paul A. Harden Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 David W. Jenkins, Attorney FirstEnergy Corporation Mail Stop A-GO-15 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-A P.O. Box 4, Route 168 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077 Cliff Custer FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077 Steve Dort FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077 Mike Banko FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077