ML111151192
| ML111151192 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/25/2011 |
| From: | David Helker Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML111151192 (6) | |
Text
April 25, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Spent Fuel Pool Criticality Documents
Reference:
1)
Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, Spent Fuel Pool Criticality Documents, dated February 9, 2011 2)
Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, Spent Fuel Pool Criticality Documents, dated February 23, 2011 3)
Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, Spent Fuel Pool Criticality 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.
April 25, 2011 U.S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Spent Fuel Pool Criticality Documents
Reference:
1)
Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Spent Fuel Pool Criticality Documents," dated February 9, 2011 2)
Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Spent Fuel Pool Criticality Documents," dated February 23, 2011 3)
Letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Spent Fuel Pool Criticality 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.
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-004-990-2/3, Revision 8 (Boraflex Surveillance Using the Racklife Program).
If any additional information is needed, please contact Tom Loomis at (610) 765-5510.
Respectfully, David P. Helker Manager, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments:
1)
RT-R-004-990-2, Revision 8 (Boraflex Surveillance Using the Racklife Program)
- Page 12 of 14 2)
RT-R-004-990-3, 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, P8APS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland U.S. 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-004-990-2/3, Revision 8 (Boraflex Surveillance Using the Racklife Program).
If any additional information is needed, please contact Tom Loomis at (610) 765-5510.
Respectfully, David P. Helker Manager, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments:
1)
RT-R-004-990-2, Revision 8 (Boraflex Surveillance Using the Racklife Program) - Page 12 of 14 2)
RT-R-004-990-3, 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 R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland
jij. O J. a6ed (wel6oJd 04,ppeU atg 6u!sfl a3uemaIuns xejpog) 8 Uo!s!AOH -o66-vOO-U-iU
- j. iuawtpejw RT..R..004..990..2, Revision 8 (Boraflex Surveillance Using the Racklife Program)
Page 12 of 14
1 2 f jel2 o4 NOTE Operability Evaluation 10-007 (IR 1127773) and the associated Technical Evaluation (IR 864431-15, or current revision) are both based on a Boron Carbide loss of 45% relative to the minimum certified B-1O areal density of 0.021 g/cm2, which equals 0.01155 g/cm2.
Therefore, the minimum B-1O areal density of any in-service Boraflex panel must be greater than 0.01155 g/cm2.
RACKLIFE utilizes the nominal as-built B-10 areal density (0.0256 g/cm2) when calculating percent Boron Carbide (B4C) loss.
Therefore, the RACKLIFE Boron Carbide loss acceptance criterion that is equivalent to the Op Eval /
Tech Eval criteria is calculated as:
RACKLIFE I
B4C Loss
=
(1 (0.01155/0.0256))
= 54.88%
For conservatism, an acceptance criterion of 54.8% peak panel B4C loss will be used.
6.9.6 VERIFY that the peak panel B4C loss is less than 54.8%.
6.9.7.
EXIT the RACKLIFE program by clicking
- File, THEN Exit.
2 NOTE 10 007 (IR 112777
) and the 8 44 1, rent revi loss of 45 relative to o areal densi of 0.021 g/cm2, which the minimum B-10 den i y
Boraflex panel must be r than 0.01155 RACKLI (0.0 56 1
s.
criterion criteria the nominal as-built B-10 areal densi when calculat percent Boron Carbide (B4C) the RACKLIFE Boron Carbide loss i
lent to the Op Eval 1 Tech Eval culated as:
RACKL B4C Loss (1
(0.01155/0.0256) )
54.88 For conservatism, an B4C loss will be used.
criterion of 54.8% peak panel
.9.6 VERIFY that the peak is less than 54.8%.
B4C loss R
6.9.7.
EXIT the RACKLIFE program by clicking "File",
THEN "Exit".
tl i 40
. e5ij (wti6oJd a3ppeJ aqj 6U!Sfl a3uBflIaAJnS xaj4wo9) 9 UO!S!AOU C-066-1700-H-LU juawpejw RT..R..004-990-3, Revision 8 (Boraflex Surveillance Using the Racklife Program)
Page 13 of 14
RTR0049903 3
Rev.
8 Page 13 of 14 NOTE Operability Evaluation 10-007 (IR 1127773) and the associated Technical Evaluation (IR 864431-15, or current revision) are both based on a Boron Carbide loss of 45% relative to the minimum certified B-lO areal density of 0.021 g/cm2, which equals 0.01155 g/cm2.
Therefore, the minimum B-10 areal density of any in-service Boraflex panel must be greater than 0.01155 g/cm2.
RACKLIFE utilizes the nominal as-built B-10 areal density (0.0256 g/cm2) when calculating percent Boron Carbide (B4C) loss.
Therefore, the RACKLIFE Boron Carbide loss acceptance criterion that is equivalent to the Op Eval /
Tech Eval criteria is calculated as:
RACKLIFE B4C Loss
=
(1
(0.01155/0.0256))
= 54.88%
For conservatism, an acceptance criterion of 54.8% peak panel B4C loss will be used.
6.9.6 VERIFY that the peak panel B4C loss is less than 54.8%.
6.9.7.
EXIT the RACKLIFE program by clicking
- File, THEN Exit.
7.0 PROCEDURE COMPLETION Initial 7.1 Records Completion 7.1.1 COMPLETE Section 2 of Cover Page (and Section 3 if applicable)
8.0 REFERENCES
8.1 Governing 8.1.1 NRC Generic Letter 96-04 Boraflex Degradation Is Spent Fuel Pool Storage Racks 8.1.2 Report NET-092-04 RACKLIFE Users Manual, Northeast Technologies Corp.,
March 1996 8.1.3 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 RT-R-004 990-Rev.
8 Page 13 of 14 NOTE li Evaluation 10-007 (IR 1127773) and the associated Technical Evaluation (IR 864431-15, or current revis
) are both based on loss of 45 relative to the minimum fi B-10 areal densi of 0.021 g/cm2, which equals 0.01155 g/cm2. Therefore, minimum B-10 areal density of any in-ce Boraflex panel must be r
than 0.01155 g/cm2.
RACKLIFE utilizes the nominal as-built B-10 areal density (0.0256 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 B4C Loss (1 -
(0.01155/0.0256))
= 54.88%
For conservatism, an acceptance criterion of 54.8% peak panel B4C loss will be used.
6.9.6 6.9.7.
VERIFY that the peak panel B4C loss is less than 54.8%.
R EXIT the RACKLIFE program by clicking "File",
THEN "Exit".
CJI 7.0 PROCEDURE COMPLETION 7.1 Records Completion Initial 7. 1. 1
8.0 REFERENCES
COMPLETE Section 2 of Cover Page (and Section 3 if applicable).
8.1 Governing 8.1.1 8.1.2 8.1.3 NRC Generic Letter 96-04 "Boraflex Degradation Is Spent Fuel Pool Storage Racks" Report NET-092-04 "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