ML092120002
| ML092120002 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/31/2009 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Franke J Florida Power & Light Co |
| Saba F, NRR/DORL/LPL2-2, 301-415-1447 | |
| Shared Package | |
| ML092120149 | List: |
| References | |
| TAC ME1799 | |
| Download: ML092120002 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 31, 2009 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
Attn: Supervisor, Licensing &
Regulatory Programs (NA1B) 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - INDIVIDUAL PLANT ACTIONS REGARDING THE PRESSURIZED-WATER REACTOR OWNERS GROUP TOPICAL REPORT, BAW-2374, REVISION 2, "RISK-INFORMED ASSESSMENT OF ONCE-THROUGH STEAM GENERATOR TUBE THERMAL LOADS DUE TO BREAKS IN REACTOR COOLANT SYSTEM UPPER HOT LEG LARGE-BORE PIPING" (TAC NO. ME1799)
Dear Mr. Franke:
On June 25, 2009, a meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the Pressurized-Water Reactor Owners Group (PWROG) to discuss the proposed resolution of items related to the PWROG topical report, BAW-2374, Revision 2, "Risk-informed Assessment of Once-Through Steam Generator Tube Thermal Loads due to Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping." A summary of the meeting can be found at the NRC's Agencywide Documents Access and Management System through Accession No. ML091820001. During this meeting, representatives of Florida Power Corporation participated in a presentation regarding the status of this matter as it relates to Crystal River Unit 3 Nuclear Generating Plant.
The NRC staff requests that you provide a written response to the enclosed list of actions taken from the meeting summary of the June 25, 2009 meeting. This response should describe your plans to address these items and will enable the staff to evaluate the need for any further regulatory action. A response is requested within 30 days from the date of this letter.
Sincerely, r~*aL/ £- ~(~
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
As stated cc w/encl: Distribution via Listserv
ACTIONS RESULTING FROM JUNE 25, 2009 MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND THE PRESSURIZED-WATER REACTOR OWNERS GROUP The U.S. Nuclear Regulatory Commission (NRC) requests that within 30 days from the date of this letter, each Babcock and Wilcox (B&W) licensee submit a letter providing plans to address the following items resulting from the June 25, 2009, public meeting regarding once-through steam generator (SG) tube loads under conditions resulting from postulated breaks in reactor coolant system upper hot leg large-bore piping:
- 1) Confirmation that its justification for continued operation for addressing tube integrity following a large break loss-of-coolant accident (LBLOCA) remains valid.
(All B&W licensees)
- 2) Confirmation that compensatory measures, such as changes to emergency operating procedures, have been incorporated into plant procedures and operator training has been performed. (All B&W licensees)
- 3) Confirmation that 10 CFR 50.46(a)(3) reporting requirements have been satisfied. (All B&W licensees)
- 4) Confirmation that all LBLOCAs (including those in the candy-cane region of the reactor coolant system (RCS)) are considered as design basis accidents in the assessments of SG tube integrity following each SG tube inspection. (All B&W licensees)
- 5) Provide confirmation that the design of the replacement SGs is sufficient to withstand the loads associated with a LBLOCA including the thermal loads associated with a LBLOCA in the candy-cane region of the RCS. (Oconee and Crystal River, only)
- 6) Commitment to provide the structural limit associated with the most limiting LBLOCA for the replacement SGs as part of the next SG tube inspection report (required by the technical specifications) following completion of the next inspection of the tubes in the replacement SGs, unless previously submitted.
(All B&W licensees)
Enclosure
Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
Attn: Supervisor, Licensing &
Regulatory Programs (NA1B) 15760 W. Power Line Street Crystal River, Florida 34428-6708 SUB~IECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - INDIVIDUAL PLANT ACTIONS REGARDING THE PRESSURIZED-WATER REACTOR OWNERS GROUP TOPICAL REPORT, BAW-2374, REVISION 2, "RISK-INFORMED ASSESSMENT OF ONCE-THROUGH STEAM GENERATOR TUBE THERMAL LOADS DUE TO BREAKS IN REACTOR COOLANT SYSTEM UPPER HOT LEG LARGE-BORE PIPING" (TAC NO. ME1799)
Dear Mr. Franke:
On June 25,2009, a meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the Pressurized-Water Reactor Owners Group (PWROG) to discuss the proposed resolution of items related to the PWROG topical report, BAW-2374, Revision 2, "Risk-informed Assessment of Once-Through Steam Generator Tube Thermal Loads due to Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping." A summary of the meeting call be found at the NRC's Agencywide Documents Access and Management System through Accession No. ML091820001. During this meeting, representatives of Florida Power Corporation participated in a presentation regarding the status of this matter as it relates to Crystal River Unit 3 Nuclear Generating Plant.
The NRC staff requests that you provide a written response to the enclosed list of actions taken from the meeting summary of the June 25, 2009 meeting. This response should describe your plans to address these items and will enable the staff to evaluate the need for any further regulatory action. A response is requested within 30 days from the date of this letter.
Sincerely, IRA!
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMCrystalRiver LPL2-2 r/f RidsNrrLACSola Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDorlLpl2-2 Resource RidsRgn2MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDprPspb Resource RidsNrrDciCsgb Resource RidsNrrDraAadb Resource Accession N PKG ML092120149 e
ML092120002 Summary: ML091820001 ADAMs os.:
L tt er:
OFFICE DORULPL2-2/PM DORULPL2-2/LA DRAlAADB/BC DPRIPSPB/BC DCI/CSGB/BC DORULPL2-2/BC NAME FSaba CSoia RTaylor SRosenberg (EBowman for)
MGavrilasl No comments TBoyce (MMarkley for)
DATE 07/31/09 07/31/09 07/31/09 07/31/09 7/31109 07/31/09 OFFICIAL RECORD COPY