ML090980352
| ML090980352 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/13/2009 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Florida Power Corp |
| Saba F, NRR/DORL/LPL2-2, 301-415-1447 | |
| Shared Package | |
| ML090980360 | List: |
| References | |
| TAC MD8530 | |
| Download: ML090980352 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 13, 2009 LICENSEE:
Florida Power Corporation FACILITY:
Crystal River, Unit 3
SUBJECT:
SUMMARY
OF APRIL 1, 2009, MEETING WITH PROGRESS ENERGY TO DISCUSS PLANNED EXTENDED POWER UPRATE AT CRYSTAL RIVER, UNIT 3 (TAC NO. MD8530)
On April 1, 2009, the Nuclear Regulatory Commission (NRC) staff conducted a Category 1 public meeting with Florida Power Corporation (the licensee), now doing business as Progress Energy and its contractor, AREVA, at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the submittal of an extended power uprate (EPU) application for Crystal River, Unit 3 (CR-3) that is currently planned to be submitted in 2009. The licensee is planning to implement the EPU during the plant 2011 refueling outage (17R), which would raise its rated thermal power from 2609 Mwt to 3014 Mwt (-15.5 percent). This project will position CR-3 as the first Babcock &
Wilcox plant to operate at over 3000 Mwt. A list of attendees is enclosed. The licensee's slide presentation may be accessed from the NRC's Agencywide Documents Access and Management System Accession No. ML090910729.
DISCUSSION During the meeting, the licensee provided an overview of the CR-3 and its EPU background, such as, implemented power uprates over the years of CR-3 operation including measurement uncertainly recapture during the 2007 refueling outage, planned balance of plant efficiency modification that will increase electrical power by 0.9 percent is planned for installation during the 2009 refueling outage, and scope of modifications that will be performed in support of the EPU during 17R.
During the meeting, the Progress Energy/AREVA staff and the NRC staff discussed the upcoming EPU amendment's format, environmental report, technical details, linked/related amendments, and the EPU and its linked licensing actions schedule. The licensee explained that the format and content of the EPU submittal will be consistent with the RS-001, Revision 0, "Review Standard for Extended Power Uprates," using R.E. Ginna Nuclear Power Plant as model. The CR-3 EPU application will be also consistent with Nuclear Energy Institute (NEI) guidance NEI-08-10. The EPU environmental report format will be consistent with Browns Ferry's and Susquehanna's submittals, and it will use, to the extent possible, the CR-3's license renewal environmental report.
The licensee is planning to commence plant modifications for power uprate during the 2009 refueling outage and finishing EPU-related modifications in the 2011 refueling outage. In addition, steam generator replacement will take place during the 2009 refueling outage. During the meeting the licensee explained that the EPU technical details were developed from following up on aspects discussed in prior meetings and from addressing the emergent issues. Further, the licensee discussed the basis for inclusion of the following issues: low pressure injection system cross-tie modification, enhanced secondary depressurization, margin management,
- 2 operational and post modification testing, large transient testihg, dose related aspects, environmental qualification evaluation, grid stability, loss of coolant accident (LOCA) status, and emergency feedwater wetting issue. During the discussions, the NRC staff advised the licensee to provide submittals that contained all necessary information to perform the required reviews.
The NRC staff asked the licensee about the technical details and justifications that will be provided in the EPU application. Specifically, the NRC staff advised the licensee to provide:
justification for the manual action related to the enhanced secondary depressurization, detailed information on the large transient testing, updates to the meteorological data and accident dose calculations, and supporting documents related to LOCA. The NRC staff also asked the licensee to include information in the EPU application for validating anticipated transient without scram setpoints. Regarding the environmental qualification (EO) evaluation, the NRC staff emphasized providing supporting technical details for the equipment that will be added or removed from the plant EO list because of the EPU conditions at CR-3.
On February 26, 2009, the licensee submitted two EPU-related amendments; the methodology of rod ejection accident analysis under EPU and an application to adopt Technical Specification Task Force (TSTF) Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS [Reactor Coolant System] Specific Activity Technical Specification." The NRC staff is performing a detailed review of the first application. However, regarding the adoption of TSTF-490, the NRC staff identified that the application did not provide sufficient technical information to enable the NRC to complete its review. During the meeting, the licensee informed the NRC of its intention to withdraw this application, and resubmit it, either in parallel with the EPU application or after the EPU amendment approval. Regarding the EPU licensing amendment request, the licensee is planning to submit its application by September 25, 2009.
Presently, the NRC staff and the licensee are not planning any additional pre-application meetings regarding the upcoming EPU application. Therefore, this concludes activities related to TAC No. MD8530. A new TAC will be opened, if the need for further discussions of some of the EPU-related licensing activities (e.g., large transient testing) is identified.
Members of the public were invited and in attendance. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1447 or farideh.saba@nrc.gov.
Farideh Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
List of Attendees U. S. Nuclear Regulatory Commission Public Meeting with Progress Energy/AREVA Regarding Crystal River, Unit 3 Extended Power Uprate April 1,2009 U. S. NUCLEAR REGULATORY COMMISSION T. Alexion T. Attard G. Armstrong M. Blumberg T. Boyce L. Brown G. Cranston H. Garg V. Goel W. Jessup S. Jones R. Kuntz PROGRESS ENERGY E. Avella J. Franke B. McCabe D. Porter L. Wells D. Westcott K. Wilson AREVA NP, INC.
J. Seals G. Lapinsky A. Mendiola A. Obodoako J. Paige Jay Patel Jigar Patel N. Patel R. Pederson R. Pettis F.Saba C. Schulten R. Taylor Enclosure
- 2 operational and post modification testing, large transient testing, dose related aspects, environmental qualification evaluation, grid stability, loss of coolant accident (LOCA) status, and emergency feedwater wetting issue. During the discussions, the NRC staff advised the licensee to provide submittals that contained all necessary information to perform the required reviews.
The NRC staff asked the licensee about the technical details and justifications that will be provided in the EPU application. Specifically, the NRC staff advised the licensee to provide:
justification for the manual action related to the enhanced secondary depressurization, detailed information on the large transient testing, updates to the meteorological data and accident dose calculations, and supporting documents related to LOCA. The NRC staff also asked the licensee to include information in the EPU application for validating anticipated transient without scram setpoints. Regarding the environmental qualification (EO) evaluation, the NRC staff emphasized providing supporting technical details for the equipment that will be added or removed from the plant EO list because of the EPU conditions at CR-3.
On February 26, 2009, the licensee submitted two EPU-related amendments; the methodology of rod ejection accident analysis under EPU and an application to adopt Technical Specification Task Force (TSTF) Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS [Reactor Coolant System] Specific Activity Technical Specification." The NRC staff is performing a detailed review of the first application. However, regarding the adoption of TSTF-490, the NRC staff identified that the application did not provide sufficient technical information to enable the NRC to complete its review. During the meeting, the licensee informed the NRC of its intention to withdraw this application, and resubmit it, either in parallel with the EPU application or after the EPU amendment approval. Regarding the EPU licensing amendment request, the licensee is planning to submit its application by September 25, 2009.
Presently, the NRC staff and the licensee are not planning any additional pre-application meetings regarding the upcoming EPU application. Therefore, this concludes activities related to TAC No. MD8530. A new TAC will be opened, if the need for further discussions of some of the EPU-related licensing activities (e.g., large transient testing) is identified.
Members of the public were invited and in attendance. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1447 or farideh.saba@nrc.gov.
IRA!
Farideh Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC Lp12-2 RtF RidsNrrLACSola (hard copy)
RidsNrrDorlLpl2-2 RidsNRRPmCrystalRiver RidsRgn2MailCenter RidsAcrsAcnw MailCTR ADAMS Accession No. Meeting Notice: Ml090850173 Summary: Ml090980352 ISlides: Mlo90910729 Pac age:
k Ml090980360 NRC-001 OFFICE LPLlI-2/PM LPLlI-2/LA LPLlI-2/BC NAME FSaba CSoia TBoyce DATE 4/9/09 4/9/09 4/13/09 OFFICIAL RECORD COpy