ML060330656
| ML060330656 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/06/2006 |
| From: | Banerjee M Plant Licensing Branch III-2 |
| To: | Crane C Exelon Generation Co |
| Banerjee M, NRR/ADPT, 415-2277 | |
| References | |
| TAC MC9243 | |
| Download: ML060330656 (5) | |
Text
February 6, 2006 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SAFETY LIMIT MINIMUM CRITICAL POWER RATIO AMENDMENT REQUEST(TAC NO. MC9243)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated December 15, 2005, Exelon Generation Company, LLC, submitted a request to revise the values of the safety limit minimum critical power ratio in Technical Specification Section 2.1.1, Reactor Core SLs, for Quad Cities Nuclear Power Station, Unit 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This request for additional information was e-mailed to your staff, and we held a telephone conference with your staff to discuss the questions on February 1, 2006. It was agreed that you would provide a response by February 10, 2006.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2277.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. Christopher M. Crane, President February 6, 2006 and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SAFETY LIMIT MINIMUM CRITICAL POWER RATIO AMENDMENT REQUEST(TAC NO. MC9243)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated December 15, 2005, Exelon Generation Company, LLC, submitted a request to revise the values of the safety limit minimum critical power ratio in Technical Specification Section 2.1.1, Reactor Core SLs, for Quad Cities Nuclear Power Station, Unit 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This request for additional information was e-mailed to your staff, and we held a telephone conference with your staff to discuss the questions on February 1, 2006. It was agreed that you would provide a response by February 10, 2006.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2277.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLF R/F RidsNrrDorlLplf RidsNRRPMMBanerjee RidsNrrLADClarke RidsAcrsAcnwMailCenter RidsOGCRp RidsRgn3MailCenter RidsNrrDorlDpr JHoncharik GCranston THuang ADAMS Accession Number: ML060330656 OFFICE LPL3-2/PM LPL3-2/PM LPL3-2/LA SBWB/BC LPL3-2/BC (A)
NAME JHoncharik MBanerjee DClarke GCranston MLandau DATE 2/1/06 2/2/06 2/1/06 2/2/06 2/6/06 OFFICIAL RECORD COPY
Quad Cities Nuclear Power Station Units 1 and 2 cc:
Site Vice President - Quad Cities Nuclear Power Station Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Nuclear Power Station Plant Manager Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Regulatory Assurance Manager - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Resident Inspectors Office U.S. Nuclear Regulatory Commission 22712 206th Avenue N.
Cordova, IL 61242 David C. Tubbs MidAmerican Energy Company One River Center Place 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, IL 61201 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President of Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Manager Licensing - Dresden, Quad Cities and Clinton Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED SAFETY LIMIT MINIMUM CRITICAL POWER RATIO AMENDMENT FOR QUAD CITIES NUCLEAR POWER STATION, UNIT 2 DOCKET NO. 50-265 In reviewing the Exelon Generation Companys (EGCs) submittal dated December 15, 2005, related to a request to revise the values of the safety limit minimum critical power ratio (SLMCPR) in Technical Specification Section 2.1.1, Reactor Core SLs, for the Quad Cities Nuclear Power Station, Unit 2, the NRC staff has determined that the following information is needed in order to complete its review:
1.
Describe how the Unit 2 Cycle 19 (U2C19) core loading pattern is established for the mixed core configuration as shown in Figure 1 of Attachment 5 with respect to:
a) meeting the cycle energy requirements; b) satisfying all licensing requirements; c) providing adequate thermal margins and operational flexibility; and d) meeting other design and manufacturing criteria established by EGC and Westinghouse.
2.
On Page 5 of 24 in Attachment 5, clarify that the USAG14 correlation does sufficiently address the Global Nuclear Fuel (GNF) 10 CFR Part 21 issue with respect to Critical Power Determination since the USAG14 correlation was generated based on GEXL14 critical power ratio (CPR) data. If the correlation does not sufficiently address the GNF 10 CFR Part 21 issue, provide the corrective actions including any penalty factor. Also, identify whether the USAG14 correlation was reviewed and approved by the staff, and if not reviewed, provide a copy of the USAG14 for staff review.
3.
Justify that the adjustment (multiplication) factor in Section 4 of Attachment 5 of the submittal that is applied when using the USAG14 correlation is conservative.
4.
Provide clarification that the calculated SLMCPR in Table 1 of Attachment 5 for GE14 fuel for Cycle 19 is the same as that in Cycle 18 for dual-loop operation and single-loop operation since the Cycle 19 is an aggressive mixed core operation and the once burned fuel may still dominate.
5.
It appears that there is no effect on the SLMCPR calculation due to the fuel channel bow. Provide information for mean and standard deviation for both Westinghouse SVEA 96 Optima 2 and GNF GE14 fuel channel bow as shown in Table 2 of and describe their impact on the Cycle 19 SLMCPR values.
6.
Describe the process to determine the total core flow uncertainty for dual-loop operation and single-loop operation for Cycle 19 operation and justify that the core flow uncertainty in Section 3 of Attachment 5 of the submittal is conservative for the Cycle 19 SLMCPR calculation, or justify an increase in core flow uncertainty.
7.
The proposed TS changes involve two sets of SLMCPR for two fuel types from two different vendors. Describe the procedures to apply these two sets of safety limits to the real Cycle 19 operation with respect to display, alarm, monitoring systems and actions taken if the CPR margin is challenged.