RS-13-077, 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
| ML13141A594 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/21/2013 |
| From: | Kaegi G Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RS-13-077 | |
| Download: ML13141A594 (5) | |
Text
% ExeLon Generation I,)
RS-13-077 May 21, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
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-12-162) 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 Byron Station, Units 1 and 2 flooding walkdown report in accordance with the NRC Request for Information (Reference 2). The Byron 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.
1 Exelon Generation 10 CFR 50.54(f)
RS-13-077 May 21,2013 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
References:
Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 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
- 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-12-162)
- 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 Byron Station, Units 1 and 2 flooding walkdown report in accordance with the NRC Request for Information (Reference 2). The Byron 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.
Glen T. Kaegi 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 three (3) features meet the NEI 12-07 acceptance criteria. Table 1 provides this list of features that were immediately judged to be acceptable.
Table 2 provides the list of one (1) feature that was 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 that were found to be deficient per the current licensing basis. The findings that were documented using the CAP 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.
declare under penalty of perjury that the foregoing is true and correct. Executed on the 21st day of May 2013.
Respectfully, Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosures:
- 1. Table 1 - Byron Station Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable
- 2. Table 2 - Byron 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 three (3) features meet the NEI 12-07 acceptance criteria. Table 1 provides this list of features that were immediately judged to be acceptable.
Table 2 provides the list of one (1) feature that was 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 that were found to be deficient per the current licensing basis. The findings that were documented using the CAP 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 - Byron Station Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable
- 2. Table 2 - Byron 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 - Byron Station, Units 1 and 2 NRC Project Manager, NRR - Byron Station Units 1 and 2 Illinois Emergency Management Agency - Division of Nuclear Safety U.S. Nuclear Regulatory Commission Supplemental Response to SO.S4(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 - Byron Station, Units 1 and 2 NRC Project Manager, NRR - Byron 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 Byron Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable Table 1 - Byron Station Fuel Handling Building Supplemental List of Features Immediately Judge d as Acceptable Feature ID #
Building Room 1
BYR-40 Fuel Handling Building 401' Fuel Elevation Aux. Building Personnel Access Handling General Area Unit 1 (concrete curb/steps)
Building 2
BYR-41 Fuel Handling Building 401' Fuel Elevation Aux. Building Personnel Access Handling General Area Unit 2 (concrete curb/steps)
Building 3
Fuel BYR-42 Block Wall 5A-148 Handling Spent Fuel Pump Room Building U.S. Nuclear Regulatory Commission Supplemental Response to 50.54{f) Letter NTTF Recommendation 2.3: Flooding May 21,2013 Byron Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable Table 1 - Byron Station Fuel Handling Building Supplemental List of Features Immediately Judged as Acceptable Feature 10 #
Building Room 1
BYR-40 Fuel Handling Building 401' Fuel Elevation Aux. Building Personnel Access Handling General Area Unit 1 (concrete curb/steps)
Building 2
BYR-41 Fuel Handling Building 401' Fuel Elevation Aux. Building Personnel Access Handling General Area Unit 2 (concrete curb/steps)
Building 3
Fuel BYR-42 Block Wa1l5A-148 Handling Spent Fuel Pump Room Building
U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21, 2013 Byron Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable Table 2 - Byron Station Fuel Handling Building Supplemental List of Features Not Immediate) Judge d as Acceptable Feature ID Description Observation Component Resolution Operability In the unlikely event water enters the pump room, these penetrations appear that they will Yes -
still perform their function of Spent Fuel Documented in sealing between the piping and Pit Pump Small gaps around 2 seal IR block wall. No air could be felt 1
BYR-43 Room Block penetrations (2FB70C and See discus discussion pulling through the gaps from the Wall 5A-149 2FB71C) in the block wall in Resolution pump room to the curved wall column area, and grout exists behind the caulking. Gaps will be re-sealed to ensure integrity in accordance with the Byron Corrective Action Program.
1 U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Flooding May 21,2013 Byron Station, Units 1 and 2 Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable Table 2 - Byron Station Fuel Handling Building Supplemental List of Features Not Immediately Judged as Acceptable Feature 10 Description Observation Component Resolution Operability In the unlikely event water enters the pump room, these penetrations appear that they will Yes-still perform their function of Spent Fuel Documented in sealing between the piping and Small gaps around 2 seal block wall. No air could be felt BYR-43 Pit Pump penetrations (2FB70C and IR 01484292.
pulling through the gaps from the Room Block See discussion Wa1l5A-149 2FB71 C) in the block wall in Resolution pump room to the curved wall column area, and grout exists behind the caulking. Gaps will be re-sealed to ensure integrity in accordance with the Byron Corrective Action Program.