ML11234A386

Lr - Today'S Conference Call with Davis Besse

ML11234A386
Person / Time
Site:	Davis Besse
Issue date:	06/16/2011
From:	Office of Nuclear Reactor Regulation
To:
References
Download: ML11234A386 (3)

Text

Davis-BesseNPEm Resource From: CuadradoDeJesus, Samuel Sent: Thursday, June 16, 2011 10:23 AM To: dorts@firstenergycorp.com

Subject:

RE: Today's Conference Call with Davis Besse Youre welcome Steve. Our Technical staff will be referring to the Standard Review Plan for License Renewal rev2 and GALL v2 during the meeting it would be a good idea for your team to have them for the teleconference.

From: dorts@firstenergycorp.com [1]

Sent: Thursday, June 16, 2011 9:21 AM To: CuadradoDeJesus, Samuel

Subject:

RE: Today's Conference Call with Davis Besse Thank you... we will be ready to discuss these items at 1:00 PM.

_____

Steve Dort DBNPS License Renewal 419.321.7662 work 412.974.3369 cell From: "CuadradoDeJesus, Samuel" <Samuel.CuadradoDeJesus@nrc.gov>

To: "'dorts@firstenergycorp.com'" <dorts@firstenergycorp.com>

Cc: "'custerc@firstenergycorp.com'" <custerc@firstenergycorp.com>, "Medoff, James" <James.Medoff@nrc.gov>

Date: 06/16/2011 09:03 AM

Subject:

RE: Today's Conference Call with Davis Besse Steve Below are the topics our staff will be discussing during the conference call today. Please forward it to your team.

1) Discuss absence of a TLAA on their bases for non-Class 1, non-piping components.

2) Discuss extension of the scope of RAI 4.1-2 to both the time-dependent J-integral analysis in and the time-dependent fatigue flaw growth analysis in Structural Integrity Associates (SIA) Topical Report No. SIR-99-040, Revision 1, "ASME Code Case N-481 of Davis Besse Reactor Coolant Pumps." (ADAMS Accession No. ML011200090). The scope of the RAI, as issued, only talked about the fatigue flaw growth analysis in the Report, which forms the basis for applying VT-1 or EVT-1 visual examinations of the outside surfaces of the reactor coolant pump (RCP) casing welds in lieu of the UT examinations that would be required by the ASME Section XI Code of Record. There is a possibility, that 10 CFR 50.55a made them update to a more recent edition of the ASME Section XI Code that has incorporated the visual examinations requirements for the pump casings. If this is the case we need to know whether their CLB is still relying on the SIA report in support using the visual methods cited in the updated ASME Section XI Code of Record.

3) Discuss their UFSAR Appendix 5A design basis for RCP flywheel integrity - we agree that the RTndt analysis for the flywheels in that appendix does not need to include a time-dependent neutron fluence-based RTndt adjustment in the manner that they are included in the RTndt analyses for the reactor vessel beltline components (i.e. beltline base metals and weld components). However, USFAR Appendix 5A states that the SRP 5.4.1.1 acceptance basis is an 80ºF difference basis between the RTndt value and the operating temperature (which according to the UFSAR Appendix, puts the minimum 120ºF operating temperature for them). Contrary to this statement, we determined that the SRP 5.4.1.1 states (recommends) that the difference between the RTndt value and the operating temperature should be at least 1

100ºF, which for full conformance with the SRP basis would dictate a minimum operating temperature of 140 ºF for the RCP flywheels at Davis Besse. The UFSAR Section 5A also states that Section 3.1 of the UFSAR gives the 120 ºF operating temperature basis for the flywheels, but we could not find any such basis in UFSAR Section 3.1. The other thing we need to inform them is that SRP 5.4.1.1 on flywheel integrity (which they use as the UFSAR Appendix 5A basis) states that the RTndt values for the RCP flywheel plate will be based on actual drop-weight testing results; however, they establish the RTndt value for the SA-533 flywheel plates materials using generic application of the RTndt values for their SA-533 plate materials for the RV beltline materials (pick 40ºF as the highest value. We are aware that this is a current licensing basis issue - thus no RAI will be issued.

4) DCI/CVIB will discuss aging management of reactor vessel internal (RVI) components with them, with Seung Mins (DLR) participation on CASS AMRs for RVI components. Chris Sydnor is DCI/CVIBs lead review. Ganesh Cheruvenki may attend. The discrepancy between the Technical Specification 5.5.4 inspection requirements for their RVI vent valve discs and their plant-specific PWR Vessel Internals Program criteria are among one matter that needs to be discussed with them. The other is on the adequacy of the AMRs for the RVI components.

The call will be held at 1:00 PM EDT, 12 noon CDT and 10:00 PDT.

The phone number and pass code for the conference call are:

Phone Number: 877-917-9488 Participant passcode: 60937

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Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 139 Mail Envelope Properties (Samuel.CuadradoDeJesus@nrc.gov20110616102300)

Subject:

RE: Today's Conference Call with Davis Besse Sent Date: 6/16/2011 10:23:21 AM Received Date: 6/16/2011 10:23:00 AM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients:

"dorts@firstenergycorp.com" <dorts@firstenergycorp.com>

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