Letter Sequence Meeting |
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MONTHYEARML0825401402008-09-16016 September 2008
Meeting Slides Point Beach Nuclear Plant Meeting with NRC on Epu.
Project stage: Request
ML0826801102008-10-0606 October 2008
9/8/08 - Point Beach Nuclear Plant, Units 1 and 2, Summary of the September 8, 2008, Meeting with FPL Energy Point Beach, LLC, on Their Proposed Extended Power Uprate Application (Tac No. MD9526 and MD9527)
Project stage: Meeting
ML0832505122008-11-26026 November 2008
FPL Energy Point Beach, LLC - Request for Withholding of Proprietary Information from Public Disclosure for Point Beach Nuclear Plant, Units 1 and 2
Project stage: Withholding Request Acceptance
2008-11-26
[Table View] |
9/8/08 - Point Beach Nuclear Plant, Units 1 and 2, Summary of the September 8, 2008, Meeting with FPL Energy Point Beach, LLC, on Their Proposed Extended Power Uprate Application (Tac No. MD9526 and MD9527)| ML082680110 |
| Person / Time |
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| Site: |
Point Beach  |
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| Issue date: |
10/06/2008 |
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| From: |
Jack Cushing
Plant Licensing Branch III |
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| To: |
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| Cushing, J S, NRR/DORL/LPLIII-1,415-1424 |
| References |
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| TAC MD9526, TAC MD9527 |
| Download: ML082680110 (8) |
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[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 6, 2008 LICENSEE: FPL Energy Point Beach, LLC FACILITY: Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2,
SUMMARY
OF THE SEPTEMBER 8, 2008, CATEGORY 1 MEETING WITH FPL ENERGY POINT BEACH, LLC, ON THEIR PROPOSED EXTENDED POWER UPRATE APPLICATION (TAC NO. MD9526 AND MD9527)
On September 8, 2008, a Category 1 pUblic meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of FPL Energy Point Beach, LLC (FPL, the licensee) at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland. A list of attendees is provided as Enclosure 1.
The purpose of the meeting was to discuss the licensee's proposed extended power uprate (EPU). The licensee requested the meeting to communicate their plans for the EPU with the NRC staff and to seek feedback from the NRC staff.
The licensee's presentation (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082540140) focused on the following matrices from Review Standard (RS)-001, "Review Standard for Extended Power Uprates".
EPU Overview
- Matrix 1 - Materials and Chemical Engineering
- Matrix 2 - Mechanical and Civil Engineering
- Matrix 3 - Electrical Engineering
- Matrix 4 - Instrumentation and Controls
- Matrix 6 - Containment Review Considerations
- Matrix 7 - Habitability, Filtration, and Ventilation
- Matrix 8 - Reactor Systems
- Matrix 9 - Source Terms and Radiological Consequences Analyses
- Matrix 10 - Health Physics
- Matrix 11 - Human Performance
- Matrix 12 - Power Ascension and Testing Plan
- Matrix 13 - Risk Evaluation The licensee plans to submit an application for a 17% increase in core power level on November 1, 2008, with a requested approval date of January 1, 2010. The implementation for Unit 1 is scheduled during the Spring 2010 and for Unit 2 during the Spring of 2011. The licensee plans to submit an alternate source term (AST) amendment that will be referenced in the EPU, by the end of September 2008. NRC management previously expressed concern about the licensee's plans to submit the AST amendment so close to the EPU amendment given the fact that the AST amendment had been submitted and withdrawn, twice. The NRC staff recommended the
-2 licensee wait to submit the EPU until after the NRC staff issues its requests for additional information (RAls) on the AST amendment.
The NRC staff asked about the licensees plans to upgrade its auxiliary feedwater (AFW) systems. The licensee responded that they were still evaluating the proposed modifications to the AFW system. The NRC staff informed the licensee that the design for the modifications needs to be complete before submittal of the amendment. The point the NRC staff focused on was, the completeness of activities relating to identified mechanical modifications that are needed for the EPU. The NRC staff has seen some applications from pressurized water reactor (PWR) licensees seeking EPU where the licensees do not seem to think the NRC staff need to know of the "extent and nature" of plant hardware modifications that will be performed (e.g.,
description of configuration changes). Quite often, licensees submit the applications before completing the necessary design work that must be in place before commencing with the EPU.
Licensees need to include baseline data from current licensed thermal power in the application, for the feed and steam line piping vibration because the American Society of Mechanical Engineers Operation and Maintenance Code 3 (O&M-3) limits may be exceeded if the extent and nature of the specific plant modifications are not described and evaluated in the application.
The NRC staff recommended the licensee review safety evaluations and the RAls that were asked for Millstone 3 and Comanche Peak stretch power uprates. The NRC staff stated, and the licensee agreed, that for modifications performed under Title 10 of the Code of Federal Regulations (10 CFR) 50.59, the evaluation required by the regulation would be complete before submitting the application.
The NRC staff asked about the licensee's plans to address the non-conservative technical specifications (TS) that the licensee's calculation reconstitution project identified. The licensee stated they planned to address any TS that need to be changed in the EPU. The NRC staff informed the licensee that, the NRC staff expectations on how licensees are supposed to address non-conservative TS are contained in NRC Administrative Letter 98-10: "Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety".
The NRC staff asked if the licensee still planned to send the input files for the small break loss-of-coolant accident and the required submittal under 10 CFR 50.46. The licensee responded they would submit the required documentation.
In the electrical area, the licensee stated, they will evaluate the environmental qualifications of plant equipment in the EPU and not in the AST. The licensee also stated that the grid stability evaluation has already been evaluated by the grid operator.
The licensee stated, they planned to make modifications that will reduce the core damage frequency by an order of magnitude, and address fire protection issues associated with the AFW system.
In the environmental area the licensee stated that there were no significant environmental impacts, and they had been working with the State of Wisconsin. The NRC staff recommended that the Iicens-ee review RS-001 to make sure all the environmental impacts are analyzed. In particular, Tables S-3 and S-4 of 10 CFR 51 contain requirements on analyzing the environmental impacts of the fuel cycle.
-3 The meeting concluded with the licensee thanking the NRC staff for the feedback on the upcoming EPU submittal.
Members of the public were not in attendance therefore, Public Meeting Feedback forms were not received.
Please direct any inquiries to Jack Cushing at 301-415-1424, or Jack.Cushing@nrc.gov.
0<< .
\fA::.;r~*V. ~~AN\ ~~.
Ja~)(cushing, Se or projec(Wanager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
List of Attendees cc w/encls: Distribution via ListServ
LIST OF ATTENDEES FOR MEETING WITH FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REGARDING A PROPOSED EXTENDED POWER UPRATE Name Title Orqanization Liz Abbott Director Nuclear Projects Eng FPL Ivy Netzel PBNP Licensinq FPL Norman Hanley Project Manager Shaw Stone & Webson Robert Taylor Chief, Accidental Dose Branch NRC DyLanne Dungneaud Reactor Eng/Accident Dose NRC Branch Robert Krsek SRI/Point Beach NRC Jay Collins NRRIDCI/CPI\I B NRC Emma Wong NRR/DCI/CSGB NRC Naeem Iqbal NRRIDRAlAFPB NRC Uriel Bachrach Enqineer Westinqhouse Andrew Bowman Engineer Westinghouse David Dominicis Project Manager Westinqhouse Patricia Vaugh Project Manager Westinghouse Mark Hartzman Sr. Mech Eng. US NRC Kamal Manoly Branch Chief, EMCB, DE NRR Tom Alexion SR Project Manaqer NRC Hukam Garg Sr. Electrical Engineer NRR/DE/EICB Benjamin Parks Rx Systems Engineer NRC Shawn O. Marshall Rx Systems Engineer NRC/Res Lois M. James Branch Chief NRR/DORL/LpI3-1 Jack Cushing Project Manager/Point Beach NRR/DORL/LpI3-1 Steve Hale FPL Engineering Dir. Power Uprate Jim Peschel Licensing Director FPL Pat Vaugh Westinghouse Andrew Bowman Westinghouse ENCLOSURE
October 6, 2008
-3 The meeting concluded with the licensee thanking the NRC staff for the feedback on the upcoming EPU submittal.
Members of the public were not in attendance therefore, Public Meeting Feedback forms were not received.
Please direct any inquiries to Jack Cushing at 301-415-1424, or Jack.Cushing@nrc.gov.
lRAI P. Tam for Jack Cushing, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
List of Attendees cc w/encls: See next page DISTRIBUTION:
PUBUC LPL3-1 R/F RidsNrrDorlLpl3-1 RidsNRRPMJCushing RidsN rrLATHarris RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrDraAadb RidsNrrDeEmcb RidsNrrDciCpnb RidsNrrDciCsgb RidsNrrDssSpbp S Marshall, RES RidsNrrDraAfpb
- email MDB/BC RTaylor 9/18/08(*)