References 2 and 3 provided additional information as requested. April 25, 2011

Transcription

1 April 25, 2011 U.S. Nuclear Regulatory Commission AnN: ATTN: Document Control Desk Washington, DC Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos and Subject: Spent Fuel Pool Criticality Documents Reference: 1) Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Spent Spent Fuel Pool Criticality Documents," Documents, dated February 9, ) Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Spent Spent Fuel Pool Criticality Documents," Documents, dated February 23, ) Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Spent Spent Fuel Pool Criticality Documents," Documents, dated April 18,2011 In the Reference 1 letter, as requested by the U.S. Nuclear Regulatory Commission Senior Resident Inspector at Peach Bottom Atomic Power Station, Exelon Generation Company, LLC (Exelon) submitted several documents for NRC review. We note that there is no outstanding license amendment request associated with this issue. References 2 and 3 provided additional information as requested.

2 U.S. US. Nuclear Regulatory Commission Spent Fuel Pool Criticality Documents April 25, 2011 Page 2 In this submittal, attached is a copy of the requested note from procedure RT-R /3, Revision 8 (Boraflex Surveillance Using the Racklife Program). If any additional information is needed, please contact Tom Loomis at (610) Respectfully, David P. Helker Manager, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) RT-R , Revision 8 (Boraflex Surveillance Using the Racklife Program) - Page 12 of 14 2) RT-R , Revision 8 (Boraflex Surveillance Using the Racklife Program) - Page 13 of 14 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS P8APS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland

3 Attachment 1 j. iuawtpejw RT..R , Revision 8 (Boraflex Surveillance Using the Racklife Program) (wel6ojd 04,ppeU atg 6u!sfl a3uemaiuns xejpog) 8 Uo!s!AOH -o66-voo-u-iu Page 12 of 14 jij. O J. a6ed

4 ( /0.0256)) 1 2 f jel2 o4 NOTE Operability Evaluation (IR ) ) and the associated Technical Evaluation (IR , 1, or currentrent revision) are both based on a Boron Carbide loss of 45% relative to the minimum certified B-1Oo areal density of g/cm2, which equals g/cm2. Therefore,, the minimum B-1O B-10 areal density i y of any in-service Boraflex panel must be greaterr than g/cm2. RACKLIFE utilizes the nominal as-built B-10 areal density ( g/cm2) when calculating percent Boron Carbide (B4C) 1loss. s. Therefore,, the RACKLIFE Boron Carbide loss acceptance criterion that iis equivalent to the Op Eval 1/ Tech Eval criteria is calculatedculated as: RACKLIFE I B4C Loss = (11 - ( /0.0256) ) = 54.88% For conservatism, an acceptance criterion of 54.8% peak panel B4C loss will be used VERIFY that the peak panel B4C loss is less than 54.8%. R EXIT the RACKLIFE program by clicking "File", File, THEN "Exit". Exit.

5 Attachment 2 juawpejw RT..R , Revision 8 (Boraflex Surveillance Using the Racklife Program) (wti6ojd a3ppej aqj 6U!Sfl a3ubfliaajns xaj4wo9) 9 UO!S!AOU C H-LU Page 13 of 14 tl i 40. e5ij

6 RT-R-004 RT R Rev. 8 Page 13 of 14 3 Rev. NOTE li Evaluation (IR ) and the associated Technical Evaluation (IR , or current revis ) are both based on loss of 45% relative to the minimum fi B-10 areal densi of g/cm2, which equals g/cm2. Therefore, minimum B-10 areal density of any in- ce Boraflex panel must be r than g/cm2. Operability Evaluation (IR ) and the associated Technical Evaluation (IR , or current revision) are both based on a Boron Carbide loss of relative to the minimum certified B-lO areal density of g/cm2, which equals g/cm2. Therefore, the minimum B-10 areal density of any in-service Boraflex panel must be greater than g/cm2. Page 13 of 14 RACKLIFE utilizes the nominal as-built B-10 areal density ( g/ ) when calculating percent Boron Carbide (B4C) loss. Therefore, the RACKLIFE Boron Carbide loss acceptance cri that is to the Op Eval / Tech Eval criteria is calculated as: RACKLIFE utilizes the nominal as-built B-10 areal density ( g/cm2) when calculating percent Boron Carbide (B4C) loss. Therefore, the RACKLIFE Boron Carbide loss acceptance criterion that is equivalent to the criteria is calculated as: Eval / Tech Eval RACKLIFE % B4C Loss = (1 - ( /0.0256)) = 54.88% RACKLIFE B4C Loss (1 ( /0.0256)) 54.88% For conservatism, an acceptance criterion of 54.8% peak panel B4C loss will be used. For conservatism, an acceptance criterion of 54.8% peak panel B4C loss will be used VERIFY that the peak panel B4C is less than 54.8% VERIFY that the peak panel is less than 54.8%. loss loss R CJI EXIT the RACKLIFE program by clicking "File", THEN "Exit" EXIT the RACKLIFE program by clicking File, Exit. 7.0 PROCEDURE COMPLETION 7.0 COMPLETION Initial Initial 7.1 Records Completion 7.1 Records Completion COMPLETE Section 2 of Cover Page (and Section 3 if applicable). Section Section if applicable) of Cover Page (and 8.0 REFERENCES 8.0 REFERENCES 8.1 Governing 8.1 Governing NRC Generic Letter "Boraflex Degradation Is Spent Fuel Pool Storage Racks" Generic Letter Boraflex Degradation Is Spent Fuel Pool Storage Racks Report NET RACKLIFE Users Manual, Northeast Technologies Corp., March Report AEAT/R/NS/0084 Issue Report NET "RACKLIFE Users Manual", Northeast Technologies Corp., March 1996 Report AEAT/R/NS/0084 Issue 1 "Criticality Assessment of the Peach Bottom Spent Fuel Ponds with Degraded Broaflex Panels", AEA Technology Co., July 2000 Criticality Assessment of the Peach Bottom Spent Fuel Ponds with Degraded Broaflex Panels, July 2000 Technology Co.,