ML11196A127

Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station

ML11196A127
Person / Time
Site:	Davis Besse
Issue date:	07/21/2011
From:	Cuadradodejesus S License Renewal Projects Branch 1
To:	Allen B FirstEnergy Nuclear Operating Co
CuadradoDeJesus S
References
TAC ME4640
Download: ML11196A127 (7)

Text

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Barry S. Allen, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)

Dear Mr. Allen:

By letter dated August 27, 2010, FirstEnergy Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's request for additional information is included in the enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel. CuadradoDeJesus@nrc.gov.

Sincerely, d~a~eZus,2:Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosure:

As stated cc w/encl: Listserv

DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI8.2.41-1

Background:

The SRP-LR, Revision 2, Section A.1.2.3.4, describes the recommendations for an acceptable detection of aging effects program element for a plant-specific program and states that "the discussion [of the inspection method or technique] should provide justification, including codes and standards referenced, that the technique and frequency are adequate to detect the aging effects before a loss of SC-intended function."

FirstEnergy Operating Company's (the applicant) Inspection of Internal Surfaces in Misce"aneous Piping and Ducting Program, as provided in License Renewal Application (LRA)

Section B.2.41 by letters dated May 24, 2011, and June 3, 2011, states that "enhanced visual exams" will be conducted to manage cracking for susceptible stainless steel components.

However, the LRA does not state to what predetermined criteria (standard) enhanced visual examinations will be conducted.

Issue:

The LRA does not state the standard that enhanced visual examinations wi" be conducted against.

Request:

Revise LRA Section B.2.41, Inspection of Internal Surfaces in Misce"aneous Piping and Ducting Program, to indicate the standard to which enhanced visual examinations wi" be conducted in order to manage cracking.

RAI8.2.41-2

Background:

The SRP-LR, Revision 2, Section A.1.2.3.10, describes the recommendations for an acceptable operating experience program element for new aging management programs (AMPs) and states that "an applicant should commit to a review of future plant-specific and industry operating experience for new programs to confirm their effectiveness."

LRA Table A-1, Davis-Besse License Renewal Commitments, does not include a commitment to perform a review of future operating experience to confirm the effectiveness of the new Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program.

ENCLOSURE

-2 Issue:

This program's LRA commitment list is not consistent with the current staff position as stated within the SRP-LR, Revision 2, concerning reviews of future operating experience for new aging management programs.

Request:

Revise LRA Table A-1, Davis-Besse License Renewal Commitments, for the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to include a commitment to perform a future review of operating experience to confirm the effectiveness of this program or justify why such a review is not necessary.

RAJ 8.2.41-3

Background:

SRP-LR, Revision 2, Table 3.0-1 states that the recommended description for the final safety analysis report (FSAR) supplement for a plant-specific AMP should include the bases for determining that aging effects will be managed during the period of extended operation.

The applicant's Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Program's updated safety analysis report (USAR) supplement provided in LRA Section A.1.41 by letters dated May 24, 2011, and June 3, 2011, does not state what type of inspections will be used to manage the program's aging effects.

Issue:

The USAR supplement for the applicant's Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Program does not state the type of inspections that will be used to manage the program's aging effects, and therefore does not adequately describe the basis for how the program will manage aging effects during the period of extended operation.

Request:

Revise the USAR supplement associated with the Internal Surfaces in Miscellaneous Piping and Ducting Program to include the type of inspections that will be used to manage the program's aging effects, consistent with SRP-LR, Revision 2, or justify why the revision is not necessary.

- 3 RAI4.6-1

Background:

In LRA Section 4.S.1, "Containment Vessel," the applicant states that:

Analysis of 400 pressure cycles (from -25 to 120 psi) and 400 temperature cycles (from 30°F to 120°F) were performed against the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III, Paragraph N-415.1.

The applicant also states that the values of 400 pressure and temperature cycles used to exclude fatigue analyses will not be exceeded for SO years of operation and thus the TLAAs associated with the exclusion of the containment vessel from fatigue analysis per ASME Section III, Paragraph N-415.1 will remain valid through the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(1)

In LRA Section 4.S.2, "Permanent Canal Seal Plate", the applicant states that:

The fatigue analysis of the permanent canal seal plate seal membrane shows that the maximum fatigue usage factor is based on 50 full heatup/cooldown cycles.

Issue:

The staff reviewed LRA Section 4.S, 4.3.1, and the applicant's USAR Section 3.8 and did not find the design basis information regarding:

1. The total number of transients used to determine that requirements of a fatigue waiver per Subparagraph N-415.1 were met for the containment vessel

2. The basis for the number of transients used in the original fatigue analysis of the permanent canal seal plate The staff needs more information to confirm that fatigue evaluations for the containment vessel will remain valid for the period of extended operation in accordance with 10 CFR 54.21 (c)(1).

The staff also needs more information to verify the number of cycles used in the design of the permanent canal seal plate.

- 4 Request:

Provide the following information:

1. A description of the original design basis used to determine that requirements of a fatigue waiver per Subparagraph N-415.1 were met for the containment vessel.

2. The basis for the LRA statement that the maximum fatigue usage factor for the permanent canal seal plate is based on 50 cycles.

July 21, 2011 Barry S. Allen, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)

Dear Mr. Allen:

By letter dated August 27, 2010, FirstEnergy Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's request for additional information is included in the enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel.CuadradoDeJesus@nrc.gov.

Sincerely, IRA!

Samuel Cuadrado-De Jesus, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosure:

As stated cc w/encl: Listserv DISTRIBUTION:

See next page ADAMS Accession No.: ML11196A127

• concurrence via e-mail IOFFICE LA:DLR/RPB1*

PM:DLR/RPB1 BC:DLR/RPB1 LA:DLR/RPB1 PM:DLR/RPB1 NAME SFigueroa SCuadrado DMorey SFigueroa SCuadrado

. DATE 07/18/2011 07/19/2011 07/20/2011 07/21/2011 07/21/2011

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I OFFICIAL RECORD COpy

Letter to Barry S. Allen from Samuel Cuadrado-De Jesus dated July 21, 2011

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)

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