ML050950439

Summary of Category Meeting with Hope Creek Generating Station, PSEG Nuclear LLC, Regarding Future Application for Extended Power Uprate

ML050950439
Person / Time
Site:	Hope Creek
Issue date:	05/13/2005
From:	Dan Collins NRC/NRR/DLPM/LPD1
To:
Collins D S, NRR/DLPM, 415-1427
References
Download: ML050950439 (9)

Text

May 13, 2005 LICENSEE: PSEG NUCLEAR, LLC.

FACILITY: HOPE CREEK GENERATING STATION

SUMMARY

OF MARCH 15, 2005, CATEGORY 1 MEETING WITH PSEG NUCLEAR LLC, REGARDING FUTURE APPLICATION FOR EXTENDED POWER UPRATE OF HOPE CREEK GENERATING STATION On March 15, 2005, the Nuclear Regulatory Commission (NRC) staff met with representatives of PSEG Nuclear, LLC (PSEG or the licensee), the licensee for the Hope Creek Nuclear Generating Station (Hope Creek), and General Electric (GE), the licensees contractor. The purpose of the meeting was to discuss NRC staff expectations regarding content quality of applications for an extended power uprate (EPU). PSEG has announced its intention to seek NRC approval for an EPU for the Hope Creek facility. The March 15, 2005, discussion between the NRC staff and PSEG was intended to ensure that any future EPU application for Hope Creek provides a sufficient level of depth and breadth for the NRC staff to complete its review with only limited need for additional information from the licensee.

Topics discussed are listed in Enclosure 1. A copy of the licensees presentation is provided in . Following the licensees presentation, open discussion was held regarding some of the agenda topics. Items discussed that are not covered by material in Enclosure 2 are summarized below, grouped by topic area:

Use of Review Standard, RS-001 The NRC staff noted that, per RS-001, applications should:

• follow the RS-001 template to the extent possible,

• identify all modifications or changes that require NRC approval in order to implement EPU, including those associated with operator actions and the plant licensing basis,

• provide a mark-up of the template regulatory evaluation section,

• list balance-of-plant areas that are not affected by the EPU and provide a sufficiently detailed explanation of why they are not affected, Reactor Systems Topics Large Transient Testing The NRC staff indicated that PSEG should provide justification in their application if they chose not to perform large transient testing. The NRC staff stated all of the transients in Standard Review Plan 14.2.1 must be addressed if the topical report NEDC-33066P is not going to be used. The NRC staff asked if a quantitative risk versus benefit evaluation had been performed.

The licensee responded that their risk versus benefit evaluation is qualitative.

Codes and Methods In response to a question from the licensee regarding the acceptability of the GE Interim Process, the NRC staff noted that the staffs evaluation of the interim process is still in its initial stages. Hence, an application that merely states that the applicant will follow that process will have more uncertainty associated with its review schedule and ultimate approval. The staff expressed a preference that applications provide specific responses to the questions that were posed to the Vermont Yankee Nuclear Power Station in requests for additional information rather than merely commit to follow the still-to-be-reviewed GE process.

Mechanical and Materials Engineering Topics Flow Induced Vibration (e.g., steam dryers and recirculation piping)

Some of the issues raised by the NRC staff concerning flow induced vibration were:

• Potential failures and effects modes should be analyzed based on Quad Cities experience and Exelons extent of condition review.

• If PSEG decided not to use risk-informed inservice inspection, then vibration is another degradation mechanism that should be addressed.

The NRC staff indicated that they are specifically interested in reviewing the forcing function used in the flow-induced vibration analysis.

Structural Evaluation of Reactor Coolant Pressure Boundary (RCPB)

The NRC staff stated that the application should identify existing flaws with respect to RCPB, and provide an evaluation of how an EPU will affect the flaws, and provide a sufficient justification of the licensees conclusion that the plant can be operated safely at EPU conditions.

Probabilistic Risk Assessment (PRA) Topics PRA Scope and Quality The NRC staff pointed out that RS-001 included Attachment 1 to Matrix 13, which covered the expected scope of the risk assessment. The staff suggested that PSEG examine the recent docketed Beaver Valley material on EPU. In addition, the staff stated that Attachment 1 includes risk from internal and external events, at power and shutdown, and PRA quality considerations.

Environmental Topics Environmental Assessment Scope and Quality The NRC staff stated that the application should address how an EPU will affect the electric shock potential with respect to transmission facility. In addition, the environmental impacts associated with the fuel cycle and transportation impacts and postulated accident doses should be evaluated. Additionally, the NRC staff indicated that a biological assessment should be provided if the last environmental report was written before the National Environmental Policy Act was implemented.

A list of meeting attendees is provided as Enclosure 3.

Please direct any inquiries to me at 301-415-1427 or dxc1@nrc.gov.

/RA/

Daniel S. Collins, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosures:

1. Agenda

2. PSEG Presentation Slides

3. Attendees cc w/encls: See next page

AGENDA MEETING BETWEEN THE NUCLEAR REGULATORY COMMISSION AND PSEG NUCLEAR, LLC, REGARDING PENDING APPLICATION FOR EXTENDED POWER UPRATE FOR HOPE CREEK GENERATING STATION Opening Remarks and Introductions 1:00 - 1:05 General Topics 1:05 - 1:25 Use of RS-001 Reactor Systems Topics 1:25 - 1:45 MELLLA/MELLLA Plus Mixed Core Analyses Large Transient Testing Containment Topics 1:45 - 2:05 Containment Overpressure Considerations Break 5 minutes Mechanical and Materials Engineering Topics 2:10 - 2:30 Flow Induced Vibration (e.g., steam dryers and recirculation piping)

Structural Evaluation of Reactor Coolant Pressure Boundary Probabilistic Risk Assessment Topics 2:30 - 2:50 PRA Scope and Quality Environmental Topics 2:50 - 3:10 Environmental Assessment Scope and Quality Break 10 minutes Open Discussion 3:20 - 3:40 Questions and Answers 3:40 - 3:55 Summary 3:55 - 4:00 Enclosure 1

MARCH 15, 2005, HOPE CREEK EPU PRE-APPLICATION MEETING ATTENDEES NRC F. Akstulewicz NRR/DSSA/SRXB R. Caruso ACRS D. Collins NRR/DLPM/PDI-2 L. Fields NRR/DRIP/RLEP C. Holden NRR/DLPM/PDI S. Laur NRR/DSSA/SPSB R. Lobel* NRR/DSSA/SPSB L. Marsh NRR/DLPM G. Miller NRR/DLPM/PDI-2 T. Owusu NRR/DLPM/PDI-2 P. Patnaik NRR/DE/EMCB W. Poertner* NRR/DE/EMEB D. Roberts* NRR/DLPM/PDI-2 W. Ruland NRR/DLPM/PDIII T. Scarbrough* NRR/DE/EMEB J. Stang* NRR/DLPM/PDIII J. Tatum NRR/DSSA/SPLB S. Unikewicz* NRR/DE/EMEB C. Wu* NRR/DEEMEB S. Wu NRR/DSSA/SRXB

• part-time attendance PSEG T. DelGaizo S. Mannon P. Duke D. McHugh J. Ferrante R. Moore, Sr.

W. He D. Notigan K. Hutko F. Safin GE P. Tran E. Schrull NJ (BNE)

D. Zannoni PPL Susquehanna J. Bartos J. Geosits M. Gorski J. Oddo Enclosure 3

Hope Creek Generating Station cc:

Mr. Michael P. Gallagher Ms. R. A. Kankus Vice President - Eng/Tech Support Joint Owner Affairs PSEG Nuclear Exelon Generation Company, LLC P.O. Box 236 Nuclear Group Headquarters KSA1-E Hancocks Bridge, NJ 08038 200 Exelon Way Kennett Square, PA 19348 Mr. Michael Brothers Vice President - Nuclear Assessments Lower Alloways Creek Township PSEG Nuclear c/o Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. George P. Barnes Dr. Jill Lipoti, Asst. Director Site Vice President - Hope Creek Radiation Protection Programs PSEG Nuclear NJ Department of Environmental P.O. Box 236 Protection and Energy Hancocks Bridge, NJ 08038 CN 415 Trenton, NJ 08625-0415 Mr. George H. Gellrich Plant Support Manager Brian Beam PSEG Nuclear Board of Public Utilities P.O. Box 236 2 Gateway Center, Tenth Floor Hancocks Bridge, NJ 08038 Newark, NJ 07102 Mr. Michael J. Massaro Regional Administrator, Region I Plant Manager - Hope Creek U.S. Nuclear Regulatory Commission PSEG Nuclear 475 Allendale Road P.O. Box 236 King of Prussia, PA 19406 Hancocks Bridge, NJ 08038 Senior Resident Inspector Ms. Christina L. Perino Hope Creek Generating Station Director - Regulatory Assurance U.S. Nuclear Regulatory Commission PSEG Nuclear - N21 Drawer 0509 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038

A list of meeting attendees is provided as Enclosure 3.

Please direct any inquiries to me at 301-415-1427 or dxc1@nrc.gov.

/RA/

Daniel S. Collins, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosures:

1. Agenda

2. PSEG Presentation Slides

3. Attendees cc w/encls: See next page DISTRIBUTION PUBLIC PD1-2 Reading BSheron LMarsh/JLyons CHolden DRoberts GMiller EThrom JTatum PPatnaik MStutzke FAkstulewicz RDennig KGrimes CRaynor OPA GMatakas, RI JJolicoeur, EDO RI DScrenci, RI ORA TOwusu TMensah OGC ACRS DCollins Meeting Summary: ML050950439 Package: ML050960141 Slides: ML050960117 OFFICE PDI-2/GE PDI-2/PM PDI-2/LA SPLB/ SRXB/SC NAME TOwusu DCollins CRaynor JTatum FAkstulewicz DATE 4/15/05 4/18/05 4/15/05 4/19/05 4/22/05 OFFICE EMEB EMCB SPSB RLEP PDI-2/SC NAME TScarbrough PPatnaik SLaur LFields DRoberts DATE 4/20/05 4/20/05 4/20/05 4/27/05 5/12/05 OFFICIAL RECORD COPY