ML071990528

Summary of the June 28, 2007, Meeting with PSEG Nuclear, LLC, Regarding an Application for an Extended Power Uprate for the Hope Creek Generating Station Regarding Dryer Analysis Acceptance Criteria

ML071990528
Person / Time
Site:	Hope Creek
Issue date:	08/13/2007
From:	Lamb J G NRC/NRR/ADRO/DORL/LPLI-2
To:	Public Service Enterprise Group
SHea J J, NRR/DORL, 415-1388
References
TAC MD3002
Download: ML071990528 (5)

Text

August 13, 2007LICENSEE:PSEG NUCLEAR, LLC FACILITY:HOPE CREEK GENERATING STATION

SUMMARY

OF THE JUNE 28, 2007, MEETING WITH PSEG NUCLEAR, LLC, REGARDING AN APPLICATION FOR AN EXTENDED POWER UPRATE FOR THE HOPE CREEK GENERATING STATION REGARDING DRYER ANALYSIS ACCEPTANCE CRITERIA (TAC NO. MD3002)On June 28, 2007, a Category 1 public meeting was held between the Nuclear RegulatoryCommission (NRC) and representatives of PSEG Nuclear, LLC (PSEG, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the acceptance criteria for boiling-water reactor (BWR) Steam Dryer predictive load under Extended Power Uprate (EPU) conditions. A list of attendees is provided as Enclosure 1 and Enclosure 2 lists the meeting agenda.By letter dated September 18, 2006 (Agencywide Documents Access and Management SystemAccession Number ML062680451) PSEG submitted an amendment request for an EPU at Hope Creek. A technical issue related to an EPU for BWRs is the acoustic loading on the plant steam dryers and steam lines under increased steam flow conditions. Licensees are required to submit analysis that predict under EPU operating conditions that increased pressure loading on the installed, modified or newly constructed dryers will not exceed the American Society of Mechanical Engineers (ASME) fatigue stress allowable limits. The NRC staff has not generically approved a specific methodology for predicting EPU dryer loading. However, the NRC staff requires that a licensee provide justification of analysis model predictions based on projected plant data at EPU conditions as power ascension progresses from current license thermal power following an EPU approval. During the meeting, the NRC staff restated the audit results. The results included: (1) PSEGsagreement to forego its reliance on the Scale Model Test (SMT) as a quantitative predictive tool to project the dryer performance during power uprate, (2) address the staff's concern with the acoustic circuit model's (ACM) ability to predict pressure loads at particular frequency ranges, (3) to revise its evaluation, if necessary, using the latest ACM model (Version 4) rather than an older version, (4) the staff noted that the limit curves at EPU, proposed by the PSEG, needed to rely on plant data rather than the SMT, and finally (5) PSEGs agreement to address other findings regarding their steam dryer finite element model parameters, used to calculate weld stesses, and bias error and random uncertainty assumptions. A specific question was raised regarding the acceptable "margin" for the analytical work relatedto the steam dryer evaluation, when compared to the recent Vermont Yankee Safety Evaluation on the same subject. The NRC staff clarified that a specific quantitative value for acceptable margin for the steam dryer analysis has not been established; however, a justification should be provided for the uncertainty assumption in each aspect of the analysis to insure a qualitative assessment could be made regarding its acceptability.

PSEG Public Meeting-2-By extrapolating the analysis at EPU conditions, the licensee will demonstrate that theassociated ASME Code fatigue stress limits will be met. Then, the licensee will establish a startup plan to analyze data collected during EPU power ascension to confirm that the stress limits is not exceeded.Members of the public were in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to me at 301-415-N/A or jgl1@nrc.gov. /ra/John G. Lamb, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-354

Enclosures:

1. List of Attendees

2. Meeting Agendacc w/ encls: See next page PSEG Public Meeting-2-By extrapolating the analysis at EPU conditions, the licensee will demonstrate that theassociated ASME Code fatigue stress limits will be met. Then, the licensee will establish a startup plan to analyze data collected during EPU power ascension to confirm that the stress limits is not exceeded.Members of the public were in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to me at 301-415-N/A or jgl1@nrc.gov. /ra/John G. Lamb, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-354

Enclosures:

1. List of Attendees

2. Meeting Agendacc w/ encls: See next pageDistributionPublicD. Screnci, OPA R-IRidsRgn1MailCenterRidsNrrDorlM. Grey, R-IRidsOgcMailCenter RidsNrrDorlLpl1-2J. Lamb, OEDO R-IRdsAcrsAcnwMailCenter LPL1-2 R/FC. PetrovitchE. Brown RidsNrrPMJSheaP. HilandT. Scarbrough H. ChernoffK. ManolyADAMS ACCESSION NO.: Meeting Summary - ML071990528OFFICEDORL/LPL1-2:SHDORL/LPL1-1:LADORL/LPL1-2:PMEMCB:BCDORL/LPL1-2:BCNAMECPetrovitchSLittleJSheaKManolyHChernoffDATE7/19/077/19/077/23/07 8/10/078/13/07 OFFICIAL RECORD COPY Hope Creek Generating Station cc:

Mr. Dennis WinchesterVice President - Nuclear Assessments PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George P. BarnesSite Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George H. GellrichPlant Support Manager PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Michael J. MassaroPlant Manager - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. James MallonManager - Licensing 200 Exelon Way - KSA 3-E Kennett Square, PA 19348Jeffrie J. Keenan, EsquirePSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Michael JesseManager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038Township ClerkLower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038Mr. Paul Bauldauf, P.E., Asst. DirectorRadiation Protection Programs NJ Department of Environmental Protection and Energy

CN 415 Trenton, NJ 08625-0415Mr. Brian BeamBoard of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102Regional Administrator, Region IU.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406Senior Resident InspectorHope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 ATTENDANCE FOR PUBLIC MEETING WITH PSEG ON JUNE 28, 2007NAMEORGANIZATIONPatrick HilandNRR\DEKamal ManolyNRR\DE Thomas ScarbroughNRO\DE Harold ChernoffNRR\DORL Eva BrownNRR\DORL Paul DavisonPSEG Shelly KuglerPSEG Pam CowanPSEG Paul DukePSEG George BarnesPSEG Morie GillmanTVA Tony LangleyTVA J. D. WolcottTVA John G. LambNRC OEDO Jerry Humphreys*State of New Jersey

• Conference CallEnclosure 1 MEETING AGENDAEXTENDED POWER UPRATEHOPE CREEK GENERATING STATIONPSEG NUCLEAR, LLCDOCKET NO. 50-354 ScheduleDiscussion TopicsJune 28, 200711:00 a.m. - 11:15 a.m.Introductory Remarks/Introductions11:15 a.m. - 11:45 a.m.- Licensee view of acceptance criteria.- Review of docketed analysis to date.

- Ongoing Dryer re-analysis based on staff audit input.

- Power Ascension Plan.

- Schedule plan for submittal.

11:45 a.m. - 12:00 p.m.NRC staff questions and comments. Enclosure 2