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{{Adams
#REDIRECT [[RS-13-076, Braidwood, Units 1 and 2, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acci]]
| number = ML13142A443
| issue date = 05/21/2013
| title = Braidwood, Units 1 and 2, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid
| author name = Kaegi G T
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000456, 05000457
| license number = NPF-072, NPF-077
| contact person =
| case reference number = RS-13-076
| document type = Letter
| page count = 6
| project =
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:Exeton Generation 10 CFR 50.54(f)
RS-13-076 May 21, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Braidwood Station, Units 1 and 2 Facility Operating License Nos.
NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457
 
==Subject:==
Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near
-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
 
==References:==
 
1.Exelon Generation Company, LLC 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task force Review of Insights from the Fukushima Dai-ichi Accident, dated November 27, 2012 (RS-12-160) 2.NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi
 
Accident, dated March 12, 2012 In Reference 1, Exelon Generation Company, LLC (EGC)provided the Braidwood Station, Units 1 and 2 flooding walkdown report in accordance with the NRC Request for Information (Reference 2).The Braidwood Station, Units 1 and 2 flooding walkdown report documented the plant walkdowns performed to verify that plant features credited in the current licensing basis for protection and mitigation from external flood events are available, functional, and properly maintained. Subsequent to these walkdown inspections it was identified that plant features
 
located in the Fuel Handling Building required flood hazard walkdowns. These additional inspections have been completed.
Exelon Generation 10 CFR 50.54(f) RS-13-076 May 21,2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
 
==Subject:==
 
==References:==
 
Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 1. Exelon Generation Company, LLC 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task force Review of Insights from the Fukushima Dai-ichi Accident, dated November 27, 2012 (RS-12-160)
: 2. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 In Reference 1, Exelon Generation Company, LLC (EGC) provided the Braidwood Station, Units 1 and 2 flooding walkdown report in accordance with the NRC Request for Information (Reference 2). The Braidwood Station, Units 1 and 2 flooding walkdown report documented the plant walkdowns performed to verify that plant features credited in the current licensing basis for protection and mitigation from external flood events are available, functional, and properly maintained.
Subsequent to these walkdown inspections it was identified that plant features located in the Fuel Handling Building required flood hazard walkdowns.
These additional inspections have been completed.
U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21, 2013 Page 2 This letter provides the results of the completed supplemental flooding walkdown inspections of plant features located in the Fuel Handling Building. The enclosed tables document the specific walkdown results for each of the subject plant features.
The results of the visual inspections during the supplemental Fuel Handling Building flooding walkdowns showed that one (1) feature meets the NEI 12-07 acceptance criteria. Table 1 provides the list of the one (1) feature that was immediately judged to be acceptable.
Table 2 provides the list of three (3) features that were not immediately judged as acceptable during the supplemental walkdowns. The table provides the tracking mechanism for Corrective Action Program (CAP) resolution of the identified conditions.
There were no findings identified as deficient per the current licensing basis. The findings that were documented using CAP have been resolved or will be resolved using the station's Corrective Action Program, No other findings challenge the current licensing basis, The supplemental Fuel Handling Building flooding walkdown record forms document the details of all observations for all flood features inspected, and are available for on-site review. Except as noted above, Fuel Handling Building flood protection features met the NEI 12-07 Supplemental Guidance acceptance criteria and were found to be in accordance with the site current licensing basis.
This letter contains no new regulatory commitments.
Should you have any questions concerning the content of this letter, please contact Ron Gaston at (630) 657-3359.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21st day of May 2013.
Respectfully, Glen T. Kaegi Director - Licensing
&Regulatory Affairs Exelon Generation Company, LLC
 
==Enclosures:==
 
1.Table 1 - Braidwood Station Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable 2.Table 2 - Braidwood Station Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21,2013 Page 2 This letter provides the results of the completed supplemental flooding walkdown inspections of plant features located in the Fuel Handling Building.
The enclosed tables document the specific walkdown results for each of the subject plant features.
The results of the visual inspections during the supplemental Fuel Handling Building flooding walkdowns showed that one (1) feature meets the NEI 12-07 acceptance criteria.
Table 1 provides the list of the one (1) feature that was immediately judged to be acceptable.
Table 2 provides the list of three (3) features that were not immediately judged as acceptable during the supplemental walkdowns.
The table provides the tracking mechanism for Corrective Action Program (CAP) resolution of the identified conditions.
There were no findings identified as deficient per the current licensing basis. The findings that were documented using CAP have been resolved or will be resolved using the station's Corrective Action Program. No other findings challenge the current licensing basis. The supplemental Fuel Handling Building flooding walkdown record forms document the details of all observations for all flood features inspected, and are available for on-site review. Except as noted above, Fuel Handling Building flood protection features met the NEI 12-07 Supplemental Guidance acceptance criteria and were found to be in accordance with the site current licensing basis. This letter contains no new regulatory commitments.
Should you have any questions concerning the content of this letter, please contact Ron Gaston at (630) 657-3359.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21 st day of May 2013. Respectfully, Glen T. Kaegi Director -Licensing
& Regulatory Affairs Exelon Generation Company, LLC
 
==Enclosures:==
: 1. Table 1 -Braidwood Station Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable
: 2. Table 2 -Braidwood Station Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21, 2013 Page 3 cc:Director, Office of Nuclear Reactor Regulation Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station, Units 1 and 2 NRC Project Manager, NRR - Braidwood Station Units 1 and 2 Illinois Emergency Management Agency - Division of Nuclear Safety u.s. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21,2013 Page 3 cc: Director, Office of Nuclear Reactor Regulation Regional Administrator
-NRC Region III NRC Senior Resident Inspector
-Braidwood Station, Units 1 and 2 NRC Project Manager, NRR -Braidwood Station Units 1 and 2 Illinois Emergency Management Agency -Division of Nuclear Safety U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21, 2013 Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable Table 1 - Braidwood Station, Units 1 and 2 Fuel Handling Building Su pp lemental List of Features Immediatel y Jud g ed as Acceptable
#Feature ID Number Buildin g Room BRW-35 Blockwall 5A-149 Fuel Handling Building Spent Fuel Pump Room 1 u.s. Nuclear Regulatory Commission Supplemental Response to 50.54{f) Letter NTTF Recommendation 2.3: Flooding May 21,2013 Enclosure 1 Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable Table 1 -Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable
# Feature 10 Number Buildin_9 Room 1 BRW -35 Blockwall 5A-149 Fuel Handling Building Spent Fuel Pump Room U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21, 2013 (2 pages)Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable Table 2 - Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable
#Feature ID #
Description Observation Component O p erabilit y Resolution Curb does exist;
" These gaps however, 3/8 gap have been BRW-32 El.
between curb and repaired per 401 Aux blockwall with lowest Work Orders 1 Building Concrete elevation of gap 401'-
" 1620680 and Personnel Curb (stairs) which is 8 16206$1 Access Unit 1 approximately 3
".Repairs were below maximum Yes -completed prior PMP level of El.
Documented in to the Summer 401.91'7 IR 01 4 3108.P P i M per od.Curb does exist;See discussionPrior to these however, 3/8" gap in Resolution repairs a between curb and column forecasted rain BRW-33 El.
blockwall with lowest event should 2 401 Aux Concrete gap elevation of have allowed Building Curb (stairs) 401'-8" which is
" ample time for Personnel approximately 3 compensatory Access Unit 2 below maximum measures if PMP level of El.
deemed 401.91'necessary.
U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTIF Recommendation 2.3: Flooding May 21,2013 Enclosure 2 (2 pages) Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable Table 2 -Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable
# Feature 10 # Description Observation Component Resolution Operability Curb does exist; These gaps however, 3/8" gap have been BRW-32 EI. between curb and repaired per blockwall with lowest 401 Aux Concrete elevation of gap 401 ,-Work Orders 1 Building 1620680 and Personnel Curb (stairs) 8" which is 1620681. Access Unit 1 approximately 3" Repairs were below maximum PM P level of EI. Yes-completed prior 401.91 ' Documented in to the Summer Curb does exist; JR 01473108.
PMP period. See discussion Prior to these however, 3/8" gap in Resolution repairs a between curb and BRW-33 EI. blockwall with lowest column forecasted rain event should 2 401 Aux Concrete gap elevation of have allowed Building Curb (stairs) 401 '-8" which is ample time for Personnel approximately 3" Access Unit 2 below maximum compensatory PM P level of EI. measures if 401.91 ' deemed necessary.
U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21, 2013 Table 2 - Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable
#Feature ID #
Description Observation Component Resolution O p erabilit y No air could be felt through the missing caulk between the pump room and the curved wall area, and grout appears to exist behind the RTV caulk. In the unlikely event water Spent Fuel Small areas of Yes -enters the Pit Pump missing RTV caulk Documented in pump room, the 3 BRW-34 Room around seal IR 01480471.
two missing Blockwall 5A-penetration 1 FB72 in See discussion caulk areas 148 blockwall in Resolution identified would column not allow an amount of water to enter the Auxiliary Building that would create significant consequences.
Work Order 1620682 to repair missing caulk has been completed.
U.S. Nuclear Regulatory Commission Supplemental Response to 50.54{f) Letter NTTF Recommendation 2.3: Flooding May 21,2013 Table 2 -Braidwood Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable
# Feature 10 # Description Observation Component Resolution Operability_
No air could be felt through the missing caulk between the pump room and the curved wall area, and grout appears to exist behind the RTV caulk. In the unlikely event water Spent Fuel Small areas of Yes-enters the Pit Pump missing RTV caulk Documented in pump room, the 3 BRW-34 Room around seal IR 01480471.
two missing Blockwall 5A-penetration 1 FB72 in See discussion caulk areas in Resolution identified would 148 blockwall column not allow an amount of water to enter the Auxiliary Building that would create significant consequences.
Work Order 1620682 to repair missing caulk has been completed.}}

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