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:	John Lamb NRC/NRR/ADRO/DORL/LPLI-2
To:	Public Service Enterprise Group
SHea J, NRR/DORL, 415-1388
References
TAC MD3002
Download: ML071990528 (5)

Text

August 13, 2007 LICENSEE: 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 Regulatory Commission (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 System Accession 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) PSEGs agreement 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 staffs concern with the acoustic circuit models (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 related to 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 By extrapolating the analysis at EPU conditions, the licensee will demonstrate that the associated 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 Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosures:

1. List of Attendees

2. Meeting Agenda cc w/ encls: See next page

PSEG Public Meeting By extrapolating the analysis at EPU conditions, the licensee will demonstrate that the associated 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 Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosures:

1. List of Attendees

2. Meeting Agenda cc w/ encls: See next page Distribution Public D. Screnci, OPA R-I RidsRgn1MailCenter RidsNrrDorl M. Grey, R-I RidsOgcMailCenter RidsNrrDorlLpl1-2 J. Lamb, OEDO R-I RdsAcrsAcnwMailCenter LPL1-2 R/F C. Petrovitch E. Brown RidsNrrPMJShea P. Hiland T. Scarbrough H. Chernoff K. Manoly ADAMS ACCESSION NO.: Meeting Summary - ML071990528 OFFICE DORL/LPL1-2:SH DORL/LPL1-1:LA DORL/LPL1-2:PM EMCB:BC DORL/LPL1-2:BC NAME CPetrovitch SLittle JShea KManoly HChernoff DATE 7/19/07 7/19/07 7/23/07 8/10/07 8/13/07 OFFICIAL RECORD COPY

Hope Creek Generating Station cc:

Mr. Dennis Winchester Mr. Michael Jesse Vice President - Nuclear Assessments Manager - Regulatory Assurance PSEG Nuclear P.O. Box 236 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Township Clerk Mr. George P. Barnes Lower Alloways Creek Township Site Vice President - Hope Creek Municipal Building, P.O. Box 157 PSEG Nuclear Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs Mr. George H. Gellrich NJ Department of Environmental Plant Support Manager Protection and Energy PSEG Nuclear CN 415 P.O. Box 236 Trenton, NJ 08625-0415 Hancocks Bridge, NJ 08038 Mr. Brian Beam Mr. Michael J. Massaro Board of Public Utilities Plant Manager - Hope Creek 2 Gateway Center, Tenth Floor PSEG Nuclear Newark, NJ 07102 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. James Mallon 475 Allendale Road Manager - Licensing King of Prussia, PA 19406 200 Exelon Way - KSA 3-E Kennett Square, PA 19348 Senior Resident Inspector Hope Creek Generating Station Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission PSEG Nuclear - N21 Drawer 0509 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038

ATTENDANCE FOR PUBLIC MEETING WITH PSEG ON JUNE 28, 2007 NAME ORGANIZATION Patrick Hiland NRR\DE Kamal Manoly NRR\DE Thomas Scarbrough NRO\DE Harold Chernoff NRR\DORL Eva Brown NRR\DORL Paul Davison PSEG Shelly Kugler PSEG Pam Cowan PSEG Paul Duke PSEG George Barnes PSEG Morie Gillman TVA Tony Langley TVA J. D. Wolcott TVA John G. Lamb NRC OEDO Jerry Humphreys* State of New Jersey

• Conference Call Enclosure 1

MEETING AGENDA EXTENDED POWER UPRATE HOPE CREEK GENERATING STATION PSEG NUCLEAR, LLC DOCKET NO. 50-354 Schedule Discussion Topics June 28, 2007 11:00 a.m. - 11:15 a.m. Introductory Remarks/Introductions 11:15 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