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12 2.6.1 Wolf Creek Lake Bathymetry | 12 2.6.1 Wolf Creek Lake Bathymetry | ||
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13 2.6.2 Recommendation | 13 2.6.2 Recommendation 2.3 Walkdown Results ............................... | ||
Results ............................... | |||
13 2.6.3 Site-Specific V isit .................................................................... | 13 2.6.3 Site-Specific V isit .................................................................... | ||
14 3.0 FLOOD HAZARD REEVALUATION ANALYSIS ........................................ | 14 3.0 FLOOD HAZARD REEVALUATION ANALYSIS ........................................ | ||
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==1.0 INTRODUCTION== | ==1.0 INTRODUCTION== | ||
1.1 PURPOSE AND SCOPE The United States Nuclear Regulatory Commission (NRC) issued a letter on March 12, 2012, pursuant to Title 10 of the Code of Federal Regulations (CFR), Section 50.54(f), related to the implementation of Recommendations 2.1, 2.3, and 9.3 from the Near-Term Task Force (NTTF), a portion of which calls for performing flood hazard reevaluations at all Nuclear Power Plants (NPP) in the United States (NRC, 2012a). On behalf of Wolf Creek Nuclear Operating Corporation (WCNOC), this Flood Hazard Reevaluation Report for the Wolf Creek Generating Station (WCGS) site provides the information required to address NRC Recommendation 2.1 with due consideration to the most recent guidance and regulations. | |||
AND SCOPE The United States Nuclear Regulatory Commission (NRC) issued a letter on March 12, 2012, pursuant to Title 10 of the Code of Federal Regulations (CFR), Section 50.54(f), related to the implementation of Recommendations 2.1, 2.3, and 9.3 from the Near-Term Task Force (NTTF), a portion of which calls for performing flood hazard reevaluations at all Nuclear Power Plants (NPP) in the United States (NRC, 2012a). On behalf of Wolf Creek Nuclear Operating Corporation (WCNOC), this Flood Hazard Reevaluation Report for the Wolf Creek Generating Station (WCGS) site provides the information required to address NRC Recommendation 2.1 with due consideration to the most recent guidance and regulations. | 1.2 LOCATION OF THE SITE The WCNOC operates the WCGS, which is located in Coffey County in eastern Kansas. The WCGS site is approximately 90 miles southwest of Kansas City, approximately 3.5 miles northeast of the city of Burlington, and approximately 3.5 miles east of the Neosho River and the main dam at John Redmond Reservoir (Figures 1-1 and 1-2). The WCGS site is located adjacent to Wolf Creek Lake (Coffey County Lake). Wolf Creek flows south into Wolf Creek Lake, which in turn drains into the Neosho River (U.S. Geological Survey [USGS], 2012a; 2012b).Wolf Creek Lake was established for station cooling, and was created by constructing an earthen dam across Wolf Creek. The location of the earthen dam is approximately four miles upstream of Wolf Creek's confluence with the Neosho River (Figure 1-2).1.3 SITE BACKGROUND AND HISTORY WCNOC is a joint venture of three owners: Kansas Gas and Electric Company, Kansas City Power & Light Company, and Kansas Electric Power Cooperative, Inc. The WCGS site has one Flood Hazard Reevaluation Report -50% Submittal 1 135031/14 Rev. 0 (February 10, 2014) P reactor, which is a Westinghouse Pressurized Water Reactor (PWR). The site has been in operation since the issuance of the license on June 4, 1985. The operating license for the WCGS expires on March 11, 2045 (NRC, 2013a).The Updated Safety Analysis Report (USAR) for the WCGS (WCNOC, 2013a) was revised in March 2013. In the USAR, two elevation datums are referenced; Mean Sea Level (MSL) (the National Geodetic Vertical Datum of 1929 (NGVD29)) | ||
and the Standardized Nuclear Unit Power Plant System (SNUPPS) datum. The SNUPPS datum is equivalent to the MSL elevation plus 900 feet (ft). At the WCGS site, MSL is equivalent to NGVD29, as stated in a design drawing. All elevations in this report are with reference to MSL, unless otherwise stated.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10 2014)2 FJC"4**JZ 2.0 FLOOD HAZARDS AT THE SITE Section 2.0 has been prepared in response to Request for Information Item L.a. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a) and documents results, as well as pertinent site information and detailed analyses related to the applicable flood hazards. Relevant Structures, Systems, and Components (SSC) important to safety and the Ultimate Heat Sink (UHS) are included in the scope of this reevaluation, including pertinent data concerning these SSCs. While the UHS is discussed separately, it is a safety-related SSC.2.1 DETAILED SITE INFORMATION Section 2.1 has been prepared in response to Request for Information Item I .a.i. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes detailed site information, present-day site layout, and elevations of pertinent SSCs important to safety, site topography, as well as pertinent spatial and temporal data sets.2.1.1 Design Site Information Design site information describes characteristics considered for the original licensing basis of the WCGS site. The original topography and design of site layout are shown in the USAR for the WCGS (WCNOC, 2013a, Figures 1.2-43 and 2.4-1). Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). Figure 2-1 shows the design layout of the WCGS site.The design locations of the safety-related structures, as well as other buildings and structures in the powerblock area are shown in Figure 2-1. A list of the primary safety- and non-safety-related structures at the WCGS site is provided in Table 2-1. A list of the existing design parameters found in the license document (WCNOC, 2013a) is included in Table 2-2.2.1.1.1 Site Topography and Drainage The WCGS site is located on a small peninsula on the northeastern side of Wolf Creek Lake (Figure 1-2). The lake is a reservoir that is retained behind an earthen dam, which was Flood Hazard Reevaluation Report 3 135031/14 Rev. 0 (February 10, 2014) P C constructed across Wolf Creek in order to provide cooling water for the WCGS. The headwater area of Wolf Creek lies north of the WCGS and the lake. The watershed area upstream of the dam is approximately 27.4 square miles (mi 2) (WCNOC, 2013a). The lake itself has a surface area of approximately 5,090 acres (approximately 8.0 mi 2) and a water storage capacity of about 111,280 acre-ft when it is at its normal water surface elevation of 1,087 ft (WCNOC, 2013a).Below the darn, Wolf Creek flows about four miles south-southwest to where it joins the Neosho River.The Neosho River is a relatively large river; its watershed covers approximately 6,300 mi 2 in Kansas. The Neosho River originates in east-central Kansas (Morris County) and flows southeast toward Humbolt, Kansas, and then southward into Oklahoma (Figure 1-1). It lies west and south of the Wolf Creek watershed. | |||
OF THE SITE The WCNOC operates the WCGS, which is located in Coffey County in eastern Kansas. The WCGS site is approximately 90 miles southwest of Kansas City, approximately | |||
northeast of the city of Burlington, and approximately | |||
east of the Neosho River and the main dam at John Redmond Reservoir (Figures 1-1 and 1-2). The WCGS site is located adjacent to Wolf Creek Lake (Coffey County Lake). Wolf Creek flows south into Wolf Creek Lake, which in turn drains into the Neosho River (U.S. Geological Survey [USGS], 2012a; 2012b).Wolf Creek Lake was established for station cooling, and was created by constructing an earthen dam across Wolf Creek. The location of the earthen dam is approximately four miles upstream of Wolf Creek's confluence with the Neosho River (Figure 1-2).1.3 SITE BACKGROUND AND HISTORY WCNOC is a joint venture of three owners: Kansas Gas and Electric Company, Kansas City Power & Light Company, and Kansas Electric Power Cooperative, Inc. The WCGS site has one Flood Hazard Reevaluation Report -50% Submittal 1 135031/14 Rev. 0 (February 10, 2014) P reactor, which is a Westinghouse Pressurized Water Reactor (PWR). The site has been in operation since the issuance of the license on June 4, 1985. The operating license for the WCGS expires on March 11, 2045 (NRC, 2013a).The Updated Safety Analysis Report (USAR) for the WCGS (WCNOC, 2013a) was revised in March 2013. In the USAR, two elevation datums are referenced; Mean Sea Level (MSL) (the National Geodetic Vertical Datum of 1929 (NGVD29)) | |||
and the Standardized Nuclear Unit Power Plant System (SNUPPS) datum. The SNUPPS datum is equivalent to the MSL elevation plus 900 feet (ft). At the WCGS site, MSL is equivalent to NGVD29, as stated in a design drawing. All elevations in this report are with reference to MSL, unless otherwise stated.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10 2014)2 FJC"4**JZ | |||
HAZARDS AT THE SITE Section 2.0 has been prepared in response to Request for Information Item L.a. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a) and documents results, as well as pertinent site information and detailed analyses related to the applicable flood hazards. Relevant Structures, Systems, and Components (SSC) important to safety and the Ultimate Heat Sink (UHS) are included in the scope of this reevaluation, including pertinent data concerning these SSCs. While the UHS is discussed separately, it is a safety-related SSC.2.1 DETAILED SITE INFORMATION Section 2.1 has been prepared in response to Request for Information Item I .a.i. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes detailed site information, present-day site layout, and elevations of pertinent SSCs important to safety, site topography, as well as pertinent spatial and temporal data sets.2.1.1 Design Site Information Design site information describes characteristics considered for the original licensing basis of the WCGS site. The original topography and design of site layout are shown in the USAR for the WCGS (WCNOC, 2013a, Figures 1.2-43 and 2.4-1). Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). Figure 2-1 shows the design layout of the WCGS site.The design locations of the safety-related structures, as well as other buildings and structures in the powerblock area are shown in Figure 2-1. A list of the primary safety- and non-safety-related structures at the WCGS site is provided in Table 2-1. A list of the existing design parameters found in the license document (WCNOC, 2013a) is included in Table 2-2.2.1.1.1 Site Topography and Drainage The WCGS site is located on a small peninsula on the northeastern side of Wolf Creek Lake (Figure 1-2). The lake is a reservoir that is retained behind an earthen dam, which was Flood Hazard Reevaluation Report 3 135031/14 Rev. 0 (February 10, 2014) P C constructed across Wolf Creek in order to provide cooling water for the WCGS. The headwater area of Wolf Creek lies north of the WCGS and the lake. The watershed area upstream of the dam is approximately 27.4 square miles (mi 2) (WCNOC, 2013a). The lake itself has a surface area of approximately 5,090 acres (approximately 8.0 mi 2) and a water storage capacity of about 111,280 acre-ft when it is at its normal water surface elevation of 1,087 ft (WCNOC, 2013a).Below the darn, Wolf Creek flows about four miles south-southwest to where it joins the Neosho River.The Neosho River is a relatively large river; its watershed covers approximately 6,300 mi 2 in Kansas. The Neosho River originates in east-central Kansas (Morris County) and flows southeast toward Humbolt, Kansas, and then southward into Oklahoma (Figure 1-1). It lies west and south of the Wolf Creek watershed. | |||
Flow in the Neosho River near the WCGS site is controlled by John Redmond Reservoir. | Flow in the Neosho River near the WCGS site is controlled by John Redmond Reservoir. | ||
Wolf Creek flows south-southwest and joins the Neosho River about four miles south of the Wolf Creek Dam and 7.1 miles downstream of the John Redmond Dam (Figure 1-2). Cottonwood Creek is a large tributary of the Neosho River and joins the river approximately six miles east of Emporia, Kansas, or approximately 14 miles northwest of the John Redmond Reservoir and Dam (WCNOC, 2013a).Long Creek flows from north to south and is located directly east and northeast of the Wolf Creek watershed (Figure 1-2). It too flows into the Neosho River. Altogether, the Long Creek watershed covers approximately 84 mi 2.Low topographic ridges separate the Wolf Creek watershed from the Long Creek and Neosho River watersheds (USGS, 2012b).The WCGS site lies in the Osage Plains physiographic section of the Central Lowland Province (WCNOC, 2013a). It is an area of low rolling hills with very gentle slopes. The WCGS site is positioned near the top of a low hill and has a grade elevation of 1,099.5 ft adjacent to buildings in the powerblock area. The floor elevation of safety-related buildings is 1,100 ft (WCNOC, 2013a). The powerblock area is flat. The ground surface slopes gently down to the Wolf Creek Lake on the western, southern, and eastern sides of the powerblock. | Wolf Creek flows south-southwest and joins the Neosho River about four miles south of the Wolf Creek Dam and 7.1 miles downstream of the John Redmond Dam (Figure 1-2). Cottonwood Creek is a large tributary of the Neosho River and joins the river approximately six miles east of Emporia, Kansas, or approximately 14 miles northwest of the John Redmond Reservoir and Dam (WCNOC, 2013a).Long Creek flows from north to south and is located directly east and northeast of the Wolf Creek watershed (Figure 1-2). It too flows into the Neosho River. Altogether, the Long Creek watershed covers approximately 84 mi 2.Low topographic ridges separate the Wolf Creek watershed from the Long Creek and Neosho River watersheds (USGS, 2012b).The WCGS site lies in the Osage Plains physiographic section of the Central Lowland Province (WCNOC, 2013a). It is an area of low rolling hills with very gentle slopes. The WCGS site is positioned near the top of a low hill and has a grade elevation of 1,099.5 ft adjacent to buildings in the powerblock area. The floor elevation of safety-related buildings is 1,100 ft (WCNOC, 2013a). The powerblock area is flat. The ground surface slopes gently down to the Wolf Creek Lake on the western, southern, and eastern sides of the powerblock. | ||
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The maximum allowable sediment volume in the UHS is limited to 130 acre-ft to provide sufficient surface area and volume to safely shut down and maintain shutdown of the plant (WCNOC, 2013a).Flood Hazard Reevaluation Report 5 135031/14 Rev. 0 (February 10, 2014) RZ 2.1.2 Present-Day Site Information Present-day site information describes changes to the WCGS site that have occurred since the original design of the site, which may have the potential to influence the reevaluation of hydrological and flooding hazards. Figure 2-2 shows the WCGS present-day site layout and topography. | The maximum allowable sediment volume in the UHS is limited to 130 acre-ft to provide sufficient surface area and volume to safely shut down and maintain shutdown of the plant (WCNOC, 2013a).Flood Hazard Reevaluation Report 5 135031/14 Rev. 0 (February 10, 2014) RZ 2.1.2 Present-Day Site Information Present-day site information describes changes to the WCGS site that have occurred since the original design of the site, which may have the potential to influence the reevaluation of hydrological and flooding hazards. Figure 2-2 shows the WCGS present-day site layout and topography. | ||
2.1.2.1 Site Topography All flooding analyses described in this flood hazard reevaluation report have been undertaken with consideration and implementation of current techniques, software, and methods used in present-day standard engineering practice to develop the flood hazard. Up-to-date topographic information from an October 2012 survey of the plant area and data are utilized in the generation of all of the applicable reevaluated flooding models. As such, any changes to site topography since the time of license issuance up to the date of the topographic data have been captured within this report.2.1.2.2 Description of Safety-Related Structures, Systems, and Components Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushimna Flooding Walkdown Report (WCNOC, 2012).The design locations of the safety and non-safety-related structures, in the powerblock area are shown in Figure 2-3.2.1.2.3 Description of the Ultimate Heat Sink The UHS is located within Wolf Creek Lake and is described in Section 2.1.1.3. No changes in the UHS since license issuance are noted in the USAR (WCNOC, 2013a) or the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012).Flood Hazard Reevaluation Report 6 135031/14 Rev. 0 (February | 2.1.2.1 Site Topography All flooding analyses described in this flood hazard reevaluation report have been undertaken with consideration and implementation of current techniques, software, and methods used in present-day standard engineering practice to develop the flood hazard. Up-to-date topographic information from an October 2012 survey of the plant area and data are utilized in the generation of all of the applicable reevaluated flooding models. As such, any changes to site topography since the time of license issuance up to the date of the topographic data have been captured within this report.2.1.2.2 Description of Safety-Related Structures, Systems, and Components Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushimna Flooding Walkdown Report (WCNOC, 2012).The design locations of the safety and non-safety-related structures, in the powerblock area are shown in Figure 2-3.2.1.2.3 Description of the Ultimate Heat Sink The UHS is located within Wolf Creek Lake and is described in Section 2.1.1.3. No changes in the UHS since license issuance are noted in the USAR (WCNOC, 2013a) or the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012).Flood Hazard Reevaluation Report 6 135031/14 Rev. 0 (February | ||
: 10. 2014) P C | : 10. 2014) P C 2.2 CURRENT DESIGN BASIS FLOOD ELEVATIONS Section 2.2 has been prepared in response to Request for Information Item 1 .a.ii. of NRC Recommendation | ||
DESIGN BASIS FLOOD ELEVATIONS Section 2.2 has been prepared in response to Request for Information Item 1 .a.ii. of NRC Recommendation | |||
: 2. 1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes the current design basis flood elevations for all flood causing mechanisms. | : 2. 1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes the current design basis flood elevations for all flood causing mechanisms. | ||
The current design basis, as presented in the USAR (WCNOC, 2013a), indicates that the site is not affected by flooding. | The current design basis, as presented in the USAR (WCNOC, 2013a), indicates that the site is not affected by flooding. | ||
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The sources of the makeup water to the cooling lake are Wolf Creek and the Neosho River. In reference to channel diversion in the USAR, there is no indication that Wolf Creek or its tributaries would be diverted from its present course of flowing into Wolf Creek Lake. Ice jams will also not cause diversion of flow because the jams do not prevent overbank flow. The ESWS intake is designed to prevent ice from jamming against it and cutting off inflow (WCNOC, 2013a, Section 9.2.1.2.2.2). | The sources of the makeup water to the cooling lake are Wolf Creek and the Neosho River. In reference to channel diversion in the USAR, there is no indication that Wolf Creek or its tributaries would be diverted from its present course of flowing into Wolf Creek Lake. Ice jams will also not cause diversion of flow because the jams do not prevent overbank flow. The ESWS intake is designed to prevent ice from jamming against it and cutting off inflow (WCNOC, 2013a, Section 9.2.1.2.2.2). | ||
As stated in the USAR, if the Wolf Creek flow was temporarily cut off, makeup water to the plant would still be available from the John Redmond Reservoir on the Neosho River. Due to the regional topographical conditions, it is unlikely that the upper Neosho River would be diverted from the John Redmond Reservoir due to ice jams or subsidence. | As stated in the USAR, if the Wolf Creek flow was temporarily cut off, makeup water to the plant would still be available from the John Redmond Reservoir on the Neosho River. Due to the regional topographical conditions, it is unlikely that the upper Neosho River would be diverted from the John Redmond Reservoir due to ice jams or subsidence. | ||
Therefore, it is unlikely that the Neosho River inflows would be completely cut off and affect the makeup water available to the cooling lake (WCNOC, 2013a).In addition, it is not expected that any potential morphological changes in Wolf Creek will affect any safety-related SSCs at the WCNOC site. As stated in the USAR, "there is no historic or topographic evidence indicating that flow in Wolf Creek can be diverted away from its present course. Local relief and the natural geomorphological condition preclude the likelihood of Wolf Creek and its tributaries discharging anywhere other than into the cooling lake" (WCNOC, 2013a, Section 2.4.10).2.3 FLOOD-RELATED CHANGES TO THE LICENSING BASIS Section 2.3 has been prepared in response to Request for Information Item 1 .a.iii of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes flood-related changes to the licensing basis and any flood protection changes (including mitigation) since license issuance.Flood Hazard Reevaluation Report 9 135031/14 Rev. 0 (February 10, 2014) P C | Therefore, it is unlikely that the Neosho River inflows would be completely cut off and affect the makeup water available to the cooling lake (WCNOC, 2013a).In addition, it is not expected that any potential morphological changes in Wolf Creek will affect any safety-related SSCs at the WCNOC site. As stated in the USAR, "there is no historic or topographic evidence indicating that flow in Wolf Creek can be diverted away from its present course. Local relief and the natural geomorphological condition preclude the likelihood of Wolf Creek and its tributaries discharging anywhere other than into the cooling lake" (WCNOC, 2013a, Section 2.4.10).2.3 FLOOD-RELATED CHANGES TO THE LICENSING BASIS Section 2.3 has been prepared in response to Request for Information Item 1 .a.iii of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes flood-related changes to the licensing basis and any flood protection changes (including mitigation) since license issuance.Flood Hazard Reevaluation Report 9 135031/14 Rev. 0 (February 10, 2014) P C 2.3.1 Description of Hydrological Changes and Flood Elevations The design basis flood elevations for the flood causing mechanisms that are applicable to WCGS are summarized in Table 2-3. The LIP flooding hazard was recently updated in 2013 (WCNOC, 2013b). The current LIP design basis is based on HMR No. 52, using a 6-hr distribution (WCNOC, 2013b). As presented in Table 2-3, the current LIP maximum flood elevation is 1,099.83 ft at Seismic Category I buildings. | ||
of Hydrological Changes and Flood Elevations The design basis flood elevations for the flood causing mechanisms that are applicable to WCGS are summarized in Table 2-3. The LIP flooding hazard was recently updated in 2013 (WCNOC, 2013b). The current LIP design basis is based on HMR No. 52, using a 6-hr distribution (WCNOC, 2013b). As presented in Table 2-3, the current LIP maximum flood elevation is 1,099.83 ft at Seismic Category I buildings. | |||
The previous design basis LIP was based on HMR No. 33, using the procedures outlined in EM- 1110-2-1411 to obtain a 6-hr distribution; this resulted in a maximum flood elevation of 1,099.86 ft around the powerblock (WCNOC, 2013a, Section 2.4.2.3.2). | The previous design basis LIP was based on HMR No. 33, using the procedures outlined in EM- 1110-2-1411 to obtain a 6-hr distribution; this resulted in a maximum flood elevation of 1,099.86 ft around the powerblock (WCNOC, 2013a, Section 2.4.2.3.2). | ||
A description of flood-related and flood protection changes since license issuance is provided in Section 2.3.2. Reevaluated flood elevations are described in Section 3.0 and the results are sumnmarized in Section 4.0. Up-to-date information and data regarding topography, buildings, structures, and hydrologic controls are utilized in the generation of all of the applicable reevaluated flooding models. As such, any changes to regional and site topography and hydrology since the time of license issuance have been captured within the current analysis.2.3.2 Description of Flood Protection Changes (Including Mitigation) | A description of flood-related and flood protection changes since license issuance is provided in Section 2.3.2. Reevaluated flood elevations are described in Section 3.0 and the results are sumnmarized in Section 4.0. Up-to-date information and data regarding topography, buildings, structures, and hydrologic controls are utilized in the generation of all of the applicable reevaluated flooding models. As such, any changes to regional and site topography and hydrology since the time of license issuance have been captured within the current analysis.2.3.2 Description of Flood Protection Changes (Including Mitigation) | ||
The flood protection system and flood mitigation measures described in the USAR (WCNOC, 2013a) and as observed and documented in the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) are specifically relevant to the flood hazard reevaluation analyses. | The flood protection system and flood mitigation measures described in the USAR (WCNOC, 2013a) and as observed and documented in the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) are specifically relevant to the flood hazard reevaluation analyses. | ||
Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushitna Flooding Walkdown Report (WCNOC, 2012). Safety-related SSCs that are credited in the Current Licensing Basis (CLB) for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate.According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." No changes since license issuance and no comments regarding adverse site conditions affecting flooding protection were noted in the report (WCNOC, 2012).Flood Hazard Reevaluation Report 10 135031/14 Rev. 0 (February 10, 2014) | Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushitna Flooding Walkdown Report (WCNOC, 2012). Safety-related SSCs that are credited in the Current Licensing Basis (CLB) for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate.According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." No changes since license issuance and no comments regarding adverse site conditions affecting flooding protection were noted in the report (WCNOC, 2012).Flood Hazard Reevaluation Report 10 135031/14 Rev. 0 (February 10, 2014) 2.4 CHANGES TO THE WATERSHED AND LOCAL AREA Section 2.4 has been prepared in response to Request for Information Item 1 .a.iv of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes changes to the watershed and local area since license issuance. | ||
TO THE WATERSHED AND LOCAL AREA Section 2.4 has been prepared in response to Request for Information Item 1 .a.iv of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes changes to the watershed and local area since license issuance. | |||
A description of the watershed at the time of license issuance and pertinent changes to the watershed since license issuance are presented in the following sections.2.4.1 Description of Watershed and Local Area at the Time of License Issuance The drainage area of the Wolf Creek watershed defined at the time of the license issuance was 27.4 mi2 .There are no gages located on the Wolf Creek watershed; therefore, no streamflow records are available. | A description of the watershed at the time of license issuance and pertinent changes to the watershed since license issuance are presented in the following sections.2.4.1 Description of Watershed and Local Area at the Time of License Issuance The drainage area of the Wolf Creek watershed defined at the time of the license issuance was 27.4 mi2 .There are no gages located on the Wolf Creek watershed; therefore, no streamflow records are available. | ||
Additional information regarding the Wolf Creek watershed and adjacent watersheds are presented in Section 2.1.1.1.2.4.2 Description of Any Changes to the Watershed and Local Area since License Issuance As previously discussed, changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). In addition, the flood reevaluation analysis deternmined that there were no significant changes to the watershed since the original design basis.The walkdown visual inspection conducted during the walkdown verified that there is reasonable assurance that the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The WCGS external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard. The purpose of the Recommendation | Additional information regarding the Wolf Creek watershed and adjacent watersheds are presented in Section 2.1.1.1.2.4.2 Description of Any Changes to the Watershed and Local Area since License Issuance As previously discussed, changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). In addition, the flood reevaluation analysis deternmined that there were no significant changes to the watershed since the original design basis.The walkdown visual inspection conducted during the walkdown verified that there is reasonable assurance that the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The WCGS external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard. The purpose of the Recommendation 2.3 walkdown is to verify the conformance with the CLB; the adequacy of the CLB will be addressed as part of the flood reevaluations if an integrated assessment is required.The original design site layout did not include a vehicle barrier system (VBS). A VBS has been added to the current WCGS site layout. The VBS configuration used in the reevaluation analysis is the configuration as of February 2013. Changes to the site layout that have occurred since license issuance and are captured in the reevaluation analysis.Flood Hazard Reevaluation Report 11 135031/14 Rev. 0 (February 10, 2014) P C The slope for the Wolf Creek Lake shoreline reported for the design basis is 30:1 (horizontal to vertical) (WCNOC, 2013a, Table 2.4-14). Based on the current topographic data used for the flood hazard reevaluation, the average shoreline slope is determined to be 46:1. The difference in slope is likely due to the method of computing an average slope for the shoreline, not due to significant change in the shoreline topography. | ||
All flooding analyses described in this flood hazard reevaluation report and described in Section 3.0 have been undertaken with consideration and implementation of current techniques, software, data, and methods used in present-day standard engineering practice to develop the flood hazard.2.5 CURRENT LICENSING BASIS FLOOD PROTECTION Section 2.5 has been prepared in response to Request for Information Item 1 .a.v. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes current licensing basis flood protection and pertinent flood mitigation features at the site.The safety-related facilities are not affected by the PMF in the cooling lake or by the LIP at the plant site and no flood protection requirements are necessary (WCNOC, 2013a). The Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012)identified the credited flood protection and mitigation features that are considered in the WCGS CLB to protect against the ingress of water to safety-related SSCs. These include topography, structures, floors, walls, penetrations, vaults, the forebay, doors, sump pumps, and sump pump motors. The ESWS pumphouse has pressure doors that are located at elevation 1,100.0 ft. These pressure doors are flood protection doors and are normally closed and under administrative control (WCNOC, 2013a).2.6 ADDITIONAL SITE DETAILS Section 2.6 has been prepared in response to Request for Information Item 1 .a.vi. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes additional site details, as necessary, to assess the flood hazard (i.e., walkdown results, etc.).Flood Hazard Reevaluation Report 12 135031/14 Rev. 0 (February 10, 2014) 2.6.1 Wolf Creek Lake Bathymetry During October and November 2009, the KBS performed a bathymetric Survey of Wolf Creek Lake. The survey (KBS, 2010) was carried out using an acoustic echo sounding apparatus linked to a global positioning system. Nearly 74,000 georeferenced depths were measured and used to create a digital bathymetric model of the reservoir (Figure 2-4). For a water surface elevation of 1,088.90 ft, the surface area and volume of the lake were 4,863 acres and 117,407 acre-ft, respectively (KBS, 2010). The maximum depth was 73.75 ft. As stated in the USAR (WCNOC, 2013a, Section 2.4.1.1), the lake has a surface area of 5,090 acres and a capacity of 111,280 acre-ft of water at its normal operating level. In June 1998, Coffey County assumed responsibility for managing public use of the lake. The lake is open for public use seven days a week from sunrise to sunset, weather, and reservoir levels permitting (KBS, 2010).2.6.2 Recommendation 2.3 Walkdown Results The Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) gives results of the walkdown, including key findings and identified degraded.non-conforming, or unanalyzed conditions, and includes detailed descriptions of the actions taken or planned to address these conditions. | |||
is to verify the conformance with the CLB; the adequacy of the CLB will be addressed as part of the flood reevaluations if an integrated assessment is required.The original design site layout did not include a vehicle barrier system (VBS). A VBS has been added to the current WCGS site layout. The VBS configuration used in the reevaluation analysis is the configuration as of February 2013. Changes to the site layout that have occurred since license issuance and are captured in the reevaluation analysis.Flood Hazard Reevaluation Report 11 135031/14 Rev. 0 (February 10, 2014) P C The slope for the Wolf Creek Lake shoreline reported for the design basis is 30:1 (horizontal to vertical) (WCNOC, 2013a, Table 2.4-14). Based on the current topographic data used for the flood hazard reevaluation, the average shoreline slope is determined to be 46:1. The difference in slope is likely due to the method of computing an average slope for the shoreline, not due to significant change in the shoreline topography. | |||
All flooding analyses described in this flood hazard reevaluation report and described in Section 3.0 have been undertaken with consideration and implementation of current techniques, software, data, and methods used in present-day standard engineering practice to develop the flood hazard.2.5 CURRENT LICENSING BASIS FLOOD PROTECTION Section 2.5 has been prepared in response to Request for Information Item 1 .a.v. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes current licensing basis flood protection and pertinent flood mitigation features at the site.The safety-related facilities are not affected by the PMF in the cooling lake or by the LIP at the plant site and no flood protection requirements are necessary (WCNOC, 2013a). The Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012)identified the credited flood protection and mitigation features that are considered in the WCGS CLB to protect against the ingress of water to safety-related SSCs. These include topography, structures, floors, walls, penetrations, vaults, the forebay, doors, sump pumps, and sump pump motors. The ESWS pumphouse has pressure doors that are located at elevation 1,100.0 ft. These pressure doors are flood protection doors and are normally closed and under administrative control (WCNOC, 2013a).2.6 ADDITIONAL SITE DETAILS Section 2.6 has been prepared in response to Request for Information Item 1 .a.vi. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes additional site details, as necessary, to assess the flood hazard (i.e., walkdown results, etc.).Flood Hazard Reevaluation Report 12 135031/14 Rev. 0 (February 10, 2014) 2.6.1 Wolf Creek Lake Bathymetry During October and November 2009, the KBS performed a bathymetric Survey of Wolf Creek Lake. The survey (KBS, 2010) was carried out using an acoustic echo sounding apparatus linked to a global positioning system. Nearly 74,000 georeferenced depths were measured and used to create a digital bathymetric model of the reservoir (Figure 2-4). For a water surface elevation of 1,088.90 ft, the surface area and volume of the lake were 4,863 acres and 117,407 acre-ft, respectively (KBS, 2010). The maximum depth was 73.75 ft. As stated in the USAR (WCNOC, 2013a, Section 2.4.1.1), the lake has a surface area of 5,090 acres and a capacity of 111,280 acre-ft of water at its normal operating level. In June 1998, Coffey County assumed responsibility for managing public use of the lake. The lake is open for public use seven days a week from sunrise to sunset, weather, and reservoir levels permitting (KBS, 2010).2.6.2 Recommendation | |||
Results The Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) gives results of the walkdown, including key findings and identified degraded.non-conforming, or unanalyzed conditions, and includes detailed descriptions of the actions taken or planned to address these conditions. | |||
The results of the walkdown observations were reviewed through site processes in accordance with Regulatory Issues Summary 2005-20, Revision I (WCNOC, 2012).Safety-related SSCs that are credited in the CLB for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate. | The results of the walkdown observations were reviewed through site processes in accordance with Regulatory Issues Summary 2005-20, Revision I (WCNOC, 2012).Safety-related SSCs that are credited in the CLB for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate. | ||
According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." The review of the walkdown concludes that the WCGS site"flood protection features would be capable of performing their intended flood protection function if subjected to a design basis flooding hazard. No flooding walkdown observations were deemed to be a deficiency per Section 3.8 of Nuclear Energy Institute (NEI) 12-07" (WCNOC, 2012).Flood Hazard Reevaluation Report 13 135031/14 Rev. 0 (February 10, 2014) 2.6.3 Site-Specific Visit A site visit was conducted on March 18 and March 19, 2013. The following areas at the site were observed and inspected: | According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." The review of the walkdown concludes that the WCGS site"flood protection features would be capable of performing their intended flood protection function if subjected to a design basis flooding hazard. No flooding walkdown observations were deemed to be a deficiency per Section 3.8 of Nuclear Energy Institute (NEI) 12-07" (WCNOC, 2012).Flood Hazard Reevaluation Report 13 135031/14 Rev. 0 (February 10, 2014) 2.6.3 Site-Specific Visit A site visit was conducted on March 18 and March 19, 2013. The following areas at the site were observed and inspected: | ||
* The powerblock area and area immediately surrounding the powerblock | * The powerblock area and area immediately surrounding the powerblock | ||
* The ESWS pumphouse" The cooling water discharge structure" The VBS The personnel also inspected portions of Wolf Creek Lake., Wolf Creek and its tributaries located north of Wolf Creek Lake. Additionally, photographs were taken of the site. These photographs were reviewed during the development of the flood hazard reevaluation analyses.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)14 RCZZ | * The ESWS pumphouse" The cooling water discharge structure" The VBS The personnel also inspected portions of Wolf Creek Lake., Wolf Creek and its tributaries located north of Wolf Creek Lake. Additionally, photographs were taken of the site. These photographs were reviewed during the development of the flood hazard reevaluation analyses.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)14 RCZZ 3.0 FLOOD HAZARD REEVALUATION ANALYSIS Section 3.0 has been prepared in response to Request for Information Item 1 .b. of NRC Reconrimendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Evaluation of the flood hazard for each flood causing mechanism should be based on present-day methodologies and regulatory guidance. | ||
HAZARD REEVALUATION ANALYSIS Section 3.0 has been prepared in response to Request for Information Item 1 .b. of NRC Reconrimendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Evaluation of the flood hazard for each flood causing mechanism should be based on present-day methodologies and regulatory guidance. | |||
Provide an analysis of each flood causing mechanism that may impact the site including local intense precipitation and on-site drainage, flooding in streams and rivers, dam breaches and failures, storm surge and seiche, tsunami, channel migration or diversion, and combined effects. Mechanisms that are not applicable at the site may be screened out; however, a justification should be provided. | Provide an analysis of each flood causing mechanism that may impact the site including local intense precipitation and on-site drainage, flooding in streams and rivers, dam breaches and failures, storm surge and seiche, tsunami, channel migration or diversion, and combined effects. Mechanisms that are not applicable at the site may be screened out; however, a justification should be provided. | ||
Provide a basis for inputs and assumptions, methodologies and models used including input and output files, and other pertinent data.3.1 | Provide a basis for inputs and assumptions, methodologies and models used including input and output files, and other pertinent data.3.1 | ||
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Consequently, the effects of wind-waves during the LIP were bounded by the effects of wind-waves during the PMF. Based on these reasons, no further analysis of wind-waves during an LIP event was required. | Consequently, the effects of wind-waves during the LIP were bounded by the effects of wind-waves during the PMF. Based on these reasons, no further analysis of wind-waves during an LIP event was required. | ||
Run-up from wind-waves in Wolf Creek Lake resulting from the PMF in Wolf Creek watershed is evaluated in Section 3.3.2.2.3. | Run-up from wind-waves in Wolf Creek Lake resulting from the PMF in Wolf Creek watershed is evaluated in Section 3.3.2.2.3. | ||
3.3.2 Flooding in Rivers and Streams River flooding at the WCGS site was evaluated with respect to the Wolf Creek watershed. | |||
in Rivers and Streams River flooding at the WCGS site was evaluated with respect to the Wolf Creek watershed. | |||
The Wolf Creek watershed was identified in the USAR (WCNOC, 2013a, Section 2.4.2.2) as the controlling watercourse for flood protection at the site. Therefore, it is included in the models for river flooding evaluation. | The Wolf Creek watershed was identified in the USAR (WCNOC, 2013a, Section 2.4.2.2) as the controlling watercourse for flood protection at the site. Therefore, it is included in the models for river flooding evaluation. | ||
The WCGS lies in the Wolf Creek watershed, which is bordered by the Long Creek watershed to the east and the larger Neosho River watershed to the west and south (Figure 1-2). In the analysis of flooding potential by rivers, the Neosho River and Long Creek watersheds were first screened to estimate the PMF in those watersheds and to determine whether their respective river channels and valleys are capable of containing the maximum flow rates resulting from a PMF.For this assessment, the total areas of the two watersheds were obtained. | The WCGS lies in the Wolf Creek watershed, which is bordered by the Long Creek watershed to the east and the larger Neosho River watershed to the west and south (Figure 1-2). In the analysis of flooding potential by rivers, the Neosho River and Long Creek watersheds were first screened to estimate the PMF in those watersheds and to determine whether their respective river channels and valleys are capable of containing the maximum flow rates resulting from a PMF.For this assessment, the total areas of the two watersheds were obtained. | ||
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Therefore, no "potentially critical" dams were identified, using the Volume Method (NRC, 2013b). All dams were either "inconsequential" or"4noncritical." The peak water level with failure of all upstream dams did not reach the Wolf Creek Lake Dam service spillway invert (i.e., 1,088 fi). The peak water level was 22.8 ft below plant grade (i.e., 1,099.5 ft) (Figure 3-15). As a result, no further consideration of debris or sediment at the WCGS site was required as part of the reevaluation analysis.For a 40-mph wind over water, the run-up associated with maximum wave heights was less than one foot (WCNOC, 2013a, Section 2.4.3.6.1). | Therefore, no "potentially critical" dams were identified, using the Volume Method (NRC, 2013b). All dams were either "inconsequential" or"4noncritical." The peak water level with failure of all upstream dams did not reach the Wolf Creek Lake Dam service spillway invert (i.e., 1,088 fi). The peak water level was 22.8 ft below plant grade (i.e., 1,099.5 ft) (Figure 3-15). As a result, no further consideration of debris or sediment at the WCGS site was required as part of the reevaluation analysis.For a 40-mph wind over water, the run-up associated with maximum wave heights was less than one foot (WCNOC, 2013a, Section 2.4.3.6.1). | ||
The maximum water level at the WCGS site with the failure of all upstream dams transferred without attenuation was below the Wolf Creek Lake Dam service spillway invert (i.e., 1,088 ft), providing a "freeboard" of 22.8 ft below plant grade (i.e., 1,099.5 fi) and 11.3 ft below the service spillway invert. Therefore, the potential impacts of wind-wave activity coincident with dam failure were dismissed. | The maximum water level at the WCGS site with the failure of all upstream dams transferred without attenuation was below the Wolf Creek Lake Dam service spillway invert (i.e., 1,088 ft), providing a "freeboard" of 22.8 ft below plant grade (i.e., 1,099.5 fi) and 11.3 ft below the service spillway invert. Therefore, the potential impacts of wind-wave activity coincident with dam failure were dismissed. | ||
3.3.4 Storm Surge The WCGS site is located more than 1,000 miles from the Pacific Ocean, approximately 935 miles inland from the Atlantic Coast, and approximately 600 miles inland from the Gulf of Mexico (USGS, 2013). The site is located adequately inland such that hurricanes and a Probable Maximum Hurricane (PMH) will not be a source of a potential flood hazard. Therefore, further consideration to storm surge flooding outlined in NRC NUREG/CR-7134 and NRC JLD-ISG-2012-06 (NRC, 2012b; 2013c) was not applicable to the WCGS site.Storm surge due to Probable Maximum Wind Storms (PMWS) and squall lines was also not applicable to the WCGS site, because the site is not located on the Great Lakes, as is discussed in ANSI/ANS-2.8 (ANS, 1992) and NRC JLD-ISG-2012-06 (NRC, 2013c). Therefore, according to NRC JLD-ISG-2012-06 guidance, determination of hydrostatic and hydrodynamic forces, debris, and water-borne projectiles, and effects of sediment erosion or deposition due to storm surge was not necessary because safety-related SSCs at the WCGS site were not affected from storm surge flood levels (NRC, 2013c).Flood Hazard Reevaluation Report 35 135031/14 Rev. 0 (Februar' | |||
: 10. 2014) 3.3.5 Seiche A seiche is defined as "an oscillation of the water surface in an enclosed or semi-enclosed body of water initiated by an external cause" in NRC NUREG/CR-7046 (NRC, 2011). To account for the potential of a seiche due to meteorological effects, the seiche periods for the length and width of Wolf Creek Lake were computed. | |||
Surge The WCGS site is located more than 1,000 miles from the Pacific Ocean, approximately 935 miles inland from the Atlantic Coast, and approximately 600 miles inland from the Gulf of Mexico (USGS, 2013). The site is located adequately inland such that hurricanes and a Probable Maximum Hurricane (PMH) will not be a source of a potential flood hazard. Therefore, further consideration to storm surge flooding outlined in NRC NUREG/CR-7134 and NRC JLD-ISG-2012-06 (NRC, 2012b; 2013c) was not applicable to the WCGS site.Storm surge due to Probable Maximum Wind Storms (PMWS) and squall lines was also not applicable to the WCGS site, because the site is not located on the Great Lakes, as is discussed in ANSI/ANS-2.8 (ANS, 1992) and NRC JLD-ISG-2012-06 (NRC, 2013c). Therefore, according to NRC JLD-ISG-2012-06 guidance, determination of hydrostatic and hydrodynamic forces, debris, and water-borne projectiles, and effects of sediment erosion or deposition due to storm surge was not necessary because safety-related SSCs at the WCGS site were not affected from storm surge flood levels (NRC, 2013c).Flood Hazard Reevaluation Report 35 135031/14 Rev. 0 (Februar' | |||
: 10. 2014) | |||
A seiche is defined as "an oscillation of the water surface in an enclosed or semi-enclosed body of water initiated by an external cause" in NRC NUREG/CR-7046 (NRC, 2011). To account for the potential of a seiche due to meteorological effects, the seiche periods for the length and width of Wolf Creek Lake were computed. | |||
In order to compute the seiche periods, the lake was assumed to be a rectangular basin with an averaged depth of the lake, which follows the methodologies outlined by Dean and Dalrymple (Dean and Dalrymple., 1991).Using the Dean and Dalrymple methodology for seiche periods for Wolf Creek Lake, the resulting seiche periods computed were 6.5 minutes for the lake's length and 38.7 minutes for the width of the lake. Seiching at these periods could only occur if an oscillatory force (pressure or wind) excited lake oscillations at one of the seiche periods. The periods calculated for lake oscillation could not be continuously forced by changes in overall weather conditions because these conditions typically fluctuate at time scales of 1 hr or more (Peinke et. al, 2004). Therefore, seiches due to meteorological effects are dismissed as a source of flooding at the WCGS.Seiches can also occur due to seismic effects and landslides. | In order to compute the seiche periods, the lake was assumed to be a rectangular basin with an averaged depth of the lake, which follows the methodologies outlined by Dean and Dalrymple (Dean and Dalrymple., 1991).Using the Dean and Dalrymple methodology for seiche periods for Wolf Creek Lake, the resulting seiche periods computed were 6.5 minutes for the lake's length and 38.7 minutes for the width of the lake. Seiching at these periods could only occur if an oscillatory force (pressure or wind) excited lake oscillations at one of the seiche periods. The periods calculated for lake oscillation could not be continuously forced by changes in overall weather conditions because these conditions typically fluctuate at time scales of 1 hr or more (Peinke et. al, 2004). Therefore, seiches due to meteorological effects are dismissed as a source of flooding at the WCGS.Seiches can also occur due to seismic effects and landslides. | ||
The WCGS site is situated in an area of low seismic hazards according to the USGS (USGS, 2012c). The occurrence of landslides in the area adjacent to Wolf Creek Lake is not considered possible due to the low relief of topographic features in the vicinity of the WCGS site. Therefore, potential seismic events and landslide were not expected to cause seiches on Wolf Creek Lake and, therefore, cause flooding at the WCGS site. Additionally, according to NRC JLD-ISG-2012-06 guidance, determination of hydrostatic and hydrodynamic forces, debris and water-borne projectiles, and the effects of sediment erosion or deposition due to seiche were not necessary because safety-related SSCs at the WCGS site are not affected from seiche flood levels (NRC, 2013c).3.3.6 Tsunami Following the guidance outlined in NRC NUREG/CR-6966 and NRC JLD-ISG-2012-06 (NRC, 2008; 2013c), a review was conducted of the National Oceanic and Atmospheric Administration's (NOAA) historic tsunami records that impacted the east coast of the United States and the Gulf of Mexico. The maximum historic water levels due to historic tsunami run-up recorded along the east cost of the United States and the Gulf of Mexico was 19.7 fi, which occurred at Daytona Beach, Florida, in 1992 (NOAA, 2013). Daytona Beach, Florida, is approximately 1,050 miles from the WCGS site (USGS, 2013), and the closest shoreline that Flood Hazard Reevaluation Report 36 135031/14 Rev. 0 (February 10, 2014) could be subjected to tsunami flooding is approximately 600 miles away. NRC NUREG/CR-6966 indicates that if regional screening identifies that the site region is not subject to tsunamis, no further analysis for tsunami hazards is required (NRC, 2008). Additionally, according to NRC JLD-ISG-2012-06 guidance (NRC, 2013c), the determination of the hydrostatic and hydrodynamic forces, debris and water-borne projectiles, and the effects of sediment erosion and deposition were not considered because the safety-related SSCs of the WCGS site were not subject to tsunami flood levels (NRC, 2013c).3.3.7 Ice-Induced Flooding Ice-induced flooding analysis for the WCGS site included an assessment of ice jams, frazil ice, and ice thickness. | The WCGS site is situated in an area of low seismic hazards according to the USGS (USGS, 2012c). The occurrence of landslides in the area adjacent to Wolf Creek Lake is not considered possible due to the low relief of topographic features in the vicinity of the WCGS site. Therefore, potential seismic events and landslide were not expected to cause seiches on Wolf Creek Lake and, therefore, cause flooding at the WCGS site. Additionally, according to NRC JLD-ISG-2012-06 guidance, determination of hydrostatic and hydrodynamic forces, debris and water-borne projectiles, and the effects of sediment erosion or deposition due to seiche were not necessary because safety-related SSCs at the WCGS site are not affected from seiche flood levels (NRC, 2013c).3.3.6 Tsunami Following the guidance outlined in NRC NUREG/CR-6966 and NRC JLD-ISG-2012-06 (NRC, 2008; 2013c), a review was conducted of the National Oceanic and Atmospheric Administration's (NOAA) historic tsunami records that impacted the east coast of the United States and the Gulf of Mexico. The maximum historic water levels due to historic tsunami run-up recorded along the east cost of the United States and the Gulf of Mexico was 19.7 fi, which occurred at Daytona Beach, Florida, in 1992 (NOAA, 2013). Daytona Beach, Florida, is approximately 1,050 miles from the WCGS site (USGS, 2013), and the closest shoreline that Flood Hazard Reevaluation Report 36 135031/14 Rev. 0 (February 10, 2014) could be subjected to tsunami flooding is approximately 600 miles away. NRC NUREG/CR-6966 indicates that if regional screening identifies that the site region is not subject to tsunamis, no further analysis for tsunami hazards is required (NRC, 2008). Additionally, according to NRC JLD-ISG-2012-06 guidance (NRC, 2013c), the determination of the hydrostatic and hydrodynamic forces, debris and water-borne projectiles, and the effects of sediment erosion and deposition were not considered because the safety-related SSCs of the WCGS site were not subject to tsunami flood levels (NRC, 2013c).3.3.7 Ice-Induced Flooding Ice-induced flooding analysis for the WCGS site included an assessment of ice jams, frazil ice, and ice thickness. | ||
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The reevaluation analysis and the design basis (WCNOC, 2013a) screened out ice formation as a potential flood hazard.3.3.8 Flooding Resulting from Channel Migration or Diversion The rivers and creeks in the vicinity of the WCGS site are the Neosho River, Wolf Creek, and Long Creek. A qualitative assessment of the streams and rivers in the vicinity of the WCGS site, in conjunction with the information presented in the USAR (WCNOC, 2013a), indicated that safety-related SSCs at the WCGS site would not be affected by diversion of flows from the Neosho River, Wolf Creek, or Long Creek.This hazard reevaluation also indicated that any potential diversion of cooling water would not adversely affect safety-related SSCs at the WCGS site. The cooling water is provided by Wolf Creek Lake, and the intake channel is protected from potential ice blockage by diffusing warmed water in front of the ESWS intake trash racks (WCNOC, 2013a). The UHS is contained by a Flood Hazard Reevaluation Report 38 135031/14 Rev. 0 (February 10, 2014) F C JZ submerged Seismic Category I dam in Wolf Creek Lake and is fully functional for safe shutdown of the WCGS site. The UHS will provide a sufficient volume of water to safely shut down and maintain shutdown of the WCGS site as long as the sediment volume in the UHS is limited to 130 acre-ft (WCNOC, 2013a, Section 2.4.11.6). | The reevaluation analysis and the design basis (WCNOC, 2013a) screened out ice formation as a potential flood hazard.3.3.8 Flooding Resulting from Channel Migration or Diversion The rivers and creeks in the vicinity of the WCGS site are the Neosho River, Wolf Creek, and Long Creek. A qualitative assessment of the streams and rivers in the vicinity of the WCGS site, in conjunction with the information presented in the USAR (WCNOC, 2013a), indicated that safety-related SSCs at the WCGS site would not be affected by diversion of flows from the Neosho River, Wolf Creek, or Long Creek.This hazard reevaluation also indicated that any potential diversion of cooling water would not adversely affect safety-related SSCs at the WCGS site. The cooling water is provided by Wolf Creek Lake, and the intake channel is protected from potential ice blockage by diffusing warmed water in front of the ESWS intake trash racks (WCNOC, 2013a). The UHS is contained by a Flood Hazard Reevaluation Report 38 135031/14 Rev. 0 (February 10, 2014) F C JZ submerged Seismic Category I dam in Wolf Creek Lake and is fully functional for safe shutdown of the WCGS site. The UHS will provide a sufficient volume of water to safely shut down and maintain shutdown of the WCGS site as long as the sediment volume in the UHS is limited to 130 acre-ft (WCNOC, 2013a, Section 2.4.11.6). | ||
The sources of the makeup water to the cooling lake are Wolf Creek and the Neosho River (WCNOC, 2013a, Section 2.4.8.2). | The sources of the makeup water to the cooling lake are Wolf Creek and the Neosho River (WCNOC, 2013a, Section 2.4.8.2). | ||
Significant morphological changes in the Neosho River are not expected to affect the water supply from the John Redmond Reservoir, and Wolf Creek was also not expected to diverge due to the topography in the area.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)39 RZYZZ | Significant morphological changes in the Neosho River are not expected to affect the water supply from the John Redmond Reservoir, and Wolf Creek was also not expected to diverge due to the topography in the area.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)39 RZYZZ 4.0 COMPARISON OF CURRENT AND REEVALUATED PREDICTED FLOOD LEVELS Section 4.0 has been prepared in response to Request for Information Item I .c. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide a comparison of current and reevaluated flood causing mechanisms at the site. Provide an assessment of the current design basis flood elevation to the reevaluated flood elevation for each flood causing mechanism. | ||
Include how the findings from Enclosure 4 of this letter (i.e., Recommendation 2.3 flooding walkdowns) support this determination. | |||
OF CURRENT AND REEVALUATED PREDICTED FLOOD LEVELS Section 4.0 has been prepared in response to Request for Information Item I .c. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide a comparison of current and reevaluated flood causing mechanisms at the site. Provide an assessment of the current design basis flood elevation to the reevaluated flood elevation for each flood causing mechanism. | |||
Include how the findings from Enclosure 4 of this letter (i.e., Recommendation | |||
walkdowns) support this determination. | |||
If the current design basis flood bounds the reevaluated hazard for all flood causing mechanisms, include how this finding was determined. | If the current design basis flood bounds the reevaluated hazard for all flood causing mechanisms, include how this finding was determined. | ||
4.1 COMPARISON OF CURRENT AND REEVALUATED FLOOD CAUSING MECHANISMS The flood causing mechanisms evaluated under the current design basis in the USAR include the effects of local intense precipitation, probable maximum flood on Wolf Creek Lake, including wave run-up at the site, seismically induced potential dam failure, probable maximum storm surge and seiche flooding, probable maximum tsunami flooding, ice flooding, and channel diversions (WCNOC, 2013a). The flood hazard reevaluation includes the same evaluations of the flooding mechanisms as presented in the current design basis, including a combined-effects flood. Note that the USAR terminology differs from the terminology used in current NRC guidance, but the same mechanisms are evaluated. | |||
OF CURRENT AND REEVALUATED FLOOD CAUSING MECHANISMS The flood causing mechanisms evaluated under the current design basis in the USAR include the effects of local intense precipitation, probable maximum flood on Wolf Creek Lake, including wave run-up at the site, seismically induced potential dam failure, probable maximum storm surge and seiche flooding, probable maximum tsunami flooding, ice flooding, and channel diversions (WCNOC, 2013a). The flood hazard reevaluation includes the same evaluations of the flooding mechanisms as presented in the current design basis, including a combined-effects flood. Note that the USAR terminology differs from the terminology used in current NRC guidance, but the same mechanisms are evaluated. | |||
The flooding mechanisms, from both the USAR and the reevaluation, are listed in Table 4-1.The conditions under which the flooding analyses were performed and the methods used to perform the analyses were slightly different between CLB analyses and the reevaluation analyses. | The flooding mechanisms, from both the USAR and the reevaluation, are listed in Table 4-1.The conditions under which the flooding analyses were performed and the methods used to perform the analyses were slightly different between CLB analyses and the reevaluation analyses. | ||
The differences are highlighted in Tables 4-1 through 4-4. Table 4-4 focuses on the additional parameters (i.e., flood duration, dynamic loads, debris loading, and sedimentation) that are required to be evaluated since the issuance of NRC Recommendation 2.1.Flood Hazard Reevaluation Report 40 135031/14 Rev. 0 (February 10, 2014) R C | The differences are highlighted in Tables 4-1 through 4-4. Table 4-4 focuses on the additional parameters (i.e., flood duration, dynamic loads, debris loading, and sedimentation) that are required to be evaluated since the issuance of NRC Recommendation 2.1.Flood Hazard Reevaluation Report 40 135031/14 Rev. 0 (February 10, 2014) R C 4.2 ASSESSMENT OF THE CURRENT DESIGN BASIS FLOOD ELEVATIONS TO THE REEVALUATED FLOOD ELEVATIONS The current design basis, as presented in the USAR (WCNOC, 2013a), indicates that the site is not affected by flooding. | ||
OF THE CURRENT DESIGN BASIS FLOOD ELEVATIONS TO THE REEVALUATED FLOOD ELEVATIONS The current design basis, as presented in the USAR (WCNOC, 2013a), indicates that the site is not affected by flooding. | |||
The WCGS site has a grade elevation of 1,099.5 ft, and a floor elevation of 1,100 ft.Local Intense Precipitation The maximum calculated water level near the safety-related buildings due to the LIP event is 1,099.83 ft (current design basis per USAR change request 2013-050 [WCNOC, 2013b]). During the LIP event, it is conservatively assumed in the design basis that the site drainage system is not functional. | The WCGS site has a grade elevation of 1,099.5 ft, and a floor elevation of 1,100 ft.Local Intense Precipitation The maximum calculated water level near the safety-related buildings due to the LIP event is 1,099.83 ft (current design basis per USAR change request 2013-050 [WCNOC, 2013b]). During the LIP event, it is conservatively assumed in the design basis that the site drainage system is not functional. | ||
The maximum design water level due to the LIP is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). As a result, the design basis does not include hydrostatic or hydrodynamic forces associated with flooding at safety-related SSCs. However, the design basis does include hydrostatic loads on safety-related structures for groundwater equivalent to plant grade (WCNOC, 2013a). The LIP (1-hr, 1 mi 2) rainfall of 19 in is part of the cumulative six-hour rainfall of 28.79 in used in the design basis. The LIP rainfall is determined using HMR No. 52 (WCNOC, 2013b).The reevaluated on-site ponding levels that result from LIP ranged from approximately 1,099.95 ft up to a maximum of 1,100.47 ft (Table 3-1). These values exceed the design water levels. The LIP rainfall depth used in the reevaluation was equivalent to the current design basis. Therefore, the existing roof loading evaluation considering precipitation rates and accumulation documented in the design basis is bounding.Potential pathways through which surface water runoff could reach safety-related SSCs include approximately 40 different doors, vaults, and manholes. | The maximum design water level due to the LIP is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). As a result, the design basis does not include hydrostatic or hydrodynamic forces associated with flooding at safety-related SSCs. However, the design basis does include hydrostatic loads on safety-related structures for groundwater equivalent to plant grade (WCNOC, 2013a). The LIP (1-hr, 1 mi 2) rainfall of 19 in is part of the cumulative six-hour rainfall of 28.79 in used in the design basis. The LIP rainfall is determined using HMR No. 52 (WCNOC, 2013b).The reevaluated on-site ponding levels that result from LIP ranged from approximately 1,099.95 ft up to a maximum of 1,100.47 ft (Table 3-1). These values exceed the design water levels. The LIP rainfall depth used in the reevaluation was equivalent to the current design basis. Therefore, the existing roof loading evaluation considering precipitation rates and accumulation documented in the design basis is bounding.Potential pathways through which surface water runoff could reach safety-related SSCs include approximately 40 different doors, vaults, and manholes. | ||
| Line 366: | Line 311: | ||
Although the effects of wind-wave action in the powerblock area are screened out as a significant contributor to the LIP flood hazard, it is understood that small wind-waves could occur on the transient flows around buildings during an LIP event. Additionally, building settlement may lower the elevation of an entryway below the design value of 1,100 ft. Therefore, an integrated assessment should consider any small differences between stillwater level and floor elevation. | Although the effects of wind-wave action in the powerblock area are screened out as a significant contributor to the LIP flood hazard, it is understood that small wind-waves could occur on the transient flows around buildings during an LIP event. Additionally, building settlement may lower the elevation of an entryway below the design value of 1,100 ft. Therefore, an integrated assessment should consider any small differences between stillwater level and floor elevation. | ||
This should be considered when evaluating the potential mitigation required for an LIP event. Removing the unused rail tracks or modifying the grading of the site near safety-related structures may improve site drainage and could be considered during an Integrated Assessment. | This should be considered when evaluating the potential mitigation required for an LIP event. Removing the unused rail tracks or modifying the grading of the site near safety-related structures may improve site drainage and could be considered during an Integrated Assessment. | ||
Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)49 | Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)49 5.0 INTERIM EVALUATION AND ACTIONS Section 5.0 has been prepared in response to Request for Information Item 1 .d. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide an interim evaluation and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of the integrated assessment. | ||
5.1 EVALUATION OF THE IMPACT OF THE REEVALUATED FLOOD LEVELS ON STRUCTURES, SYSTEMS, AND COMPONENTS Except for flooding levels due to an LIP event, the flooding levels of all other potential flood causing mechanisms, as presented in Section 3.0, do not exceed the elevations of the exterior entrances of SSCs at the WCGS site. The design basis did not include hydrostatic and hydrodynamic loads because the maximum calculated water level near the safety-related buildings due to the LIP event is 1,099.83 ft (WCNOC, 2013b), which is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). However, the design basis did consider hydrostatic loads due to groundwater levels equivalent to plant grade.For the reevaluation analysis, the most refined simulated conditions result in ponded water adjacent to Seismic Category I buildings with elevations above the plant floor elevation (1,100 fi) at several entrances. | |||
EVALUATION AND ACTIONS Section 5.0 has been prepared in response to Request for Information Item 1 .d. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide an interim evaluation and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of the integrated assessment. | |||
OF THE IMPACT OF THE REEVALUATED FLOOD LEVELS ON STRUCTURES, SYSTEMS, AND COMPONENTS Except for flooding levels due to an LIP event, the flooding levels of all other potential flood causing mechanisms, as presented in Section 3.0, do not exceed the elevations of the exterior entrances of SSCs at the WCGS site. The design basis did not include hydrostatic and hydrodynamic loads because the maximum calculated water level near the safety-related buildings due to the LIP event is 1,099.83 ft (WCNOC, 2013b), which is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). However, the design basis did consider hydrostatic loads due to groundwater levels equivalent to plant grade.For the reevaluation analysis, the most refined simulated conditions result in ponded water adjacent to Seismic Category I buildings with elevations above the plant floor elevation (1,100 fi) at several entrances. | |||
Additionally, water levels exceeded critical elevations at several manhole covers. The flood depths, associated durations, flow velocities, as well as hydrostatic and hydrodynamic forces that are computed in the reevaluation analysis are not bounded by the design basis LIP analysis. | Additionally, water levels exceeded critical elevations at several manhole covers. The flood depths, associated durations, flow velocities, as well as hydrostatic and hydrodynamic forces that are computed in the reevaluation analysis are not bounded by the design basis LIP analysis. | ||
Water levels computed in the reevaluation indicate potential flow of water into Seismic Category I buildings. | Water levels computed in the reevaluation indicate potential flow of water into Seismic Category I buildings. | ||
Debris loading and sedimentation during a LIP event were screened out in the reevaluation analysis.5.2 ACTIONS TAKEN TO ADDRESS FLOOD HAZARDS NOT COMPLETELY BOUNDED BY THE CURRENT DESIGN BASIS HAZARD Request for Information Item 1 .d. of NRC Recommendation | Debris loading and sedimentation during a LIP event were screened out in the reevaluation analysis.5.2 ACTIONS TAKEN TO ADDRESS FLOOD HAZARDS NOT COMPLETELY BOUNDED BY THE CURRENT DESIGN BASIS HAZARD Request for Information Item 1 .d. of NRC Recommendation 2.1 specifies that the flooding reevaluation contain an interim evaluation and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of the integrated assessment, if necessary (NRC, 2012a).Flood Hazard Reevaluation Report 50 135031/14 Rev. 0 (February 10, 2014) | ||
that the flooding reevaluation contain an interim evaluation and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of the integrated assessment, if necessary (NRC, 2012a).Flood Hazard Reevaluation Report 50 135031/14 Rev. 0 (February 10, 2014) | |||
Based on the results of the site walkdowns and the indicated ponding levels during a LIP event (exceeding doorway entrance elevations and design hydrostatic loads), interim actions are necessary to preliminarily evaluate the need for mitigation (e.g., sand bags), while an integrated assessment is conducted to further evaluate the need for mitigation in the case of a LIP event.The temporary mitigation measures for the interim action will consider parameters, such as the effect of small wind-waves (a few inches) that could occur on the transient flows around buildings during an LIP event and building settlement that may lower the elevation of an entryway below the design value of 1,100 ft. The integrated assessment and interim measures to mitigate ponding, during a LIP event, will be tracked by Wolf Creek's corrective action program.In addition, an interim action is required to evaluate whether mitigation is required to be put in place while the potential static and dynamic loading on the ESWS pumphouse due to water levels resulting from a design basis PMF is evaluated. | Based on the results of the site walkdowns and the indicated ponding levels during a LIP event (exceeding doorway entrance elevations and design hydrostatic loads), interim actions are necessary to preliminarily evaluate the need for mitigation (e.g., sand bags), while an integrated assessment is conducted to further evaluate the need for mitigation in the case of a LIP event.The temporary mitigation measures for the interim action will consider parameters, such as the effect of small wind-waves (a few inches) that could occur on the transient flows around buildings during an LIP event and building settlement that may lower the elevation of an entryway below the design value of 1,100 ft. The integrated assessment and interim measures to mitigate ponding, during a LIP event, will be tracked by Wolf Creek's corrective action program.In addition, an interim action is required to evaluate whether mitigation is required to be put in place while the potential static and dynamic loading on the ESWS pumphouse due to water levels resulting from a design basis PMF is evaluated. | ||
The integrated assessment and interim measures to mitigate potential static and dynamic loading on the ESWS pumphouse will be tracked by Wolf Creek's corrective action program.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)51 RZYZZ | The integrated assessment and interim measures to mitigate potential static and dynamic loading on the ESWS pumphouse will be tracked by Wolf Creek's corrective action program.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)51 RZYZZ 6.0 ADDITIONAL ACTIONS Section 6.0 has been prepared in response to Request for Information Item i.e. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide additional actions beyond Request for Information item I .d taken or planned to address flooding hazards, if any.At this time, there are no additional actions beyond Request for Information Item I .d. of NRC Recommendation 2.1 (Section 5.0) which have been taken or are planned to address flooding hazards at WCGS.Per the NRC guidance for performing the integrated assessment for external flooding, addressees are requested to perform an integrated assessment if the current design basis flood hazard elevation does not bound the reevaluated flood hazard elevation for all flood-causing mechanisms. | ||
ACTIONS Section 6.0 has been prepared in response to Request for Information Item i.e. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide additional actions beyond Request for Information item I .d taken or planned to address flooding hazards, if any.At this time, there are no additional actions beyond Request for Information Item I .d. of NRC Recommendation 2.1 (Section 5.0) which have been taken or are planned to address flooding hazards at WCGS.Per the NRC guidance for performing the integrated assessment for external flooding, addressees are requested to perform an integrated assessment if the current design basis flood hazard elevation does not bound the reevaluated flood hazard elevation for all flood-causing mechanisms. | |||
Furthermore, "The integrated assessment will evaluate the total plant response to the flood hazard, considering multiple and diverse capabilities such as physical barriers, temporary protective measures, and operations procedures." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February | Furthermore, "The integrated assessment will evaluate the total plant response to the flood hazard, considering multiple and diverse capabilities such as physical barriers, temporary protective measures, and operations procedures." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February | ||
: 10. 2014)52 RZ | : 10. 2014)52 RZ | ||
Revision as of 13:06, 11 May 2019
| ML14077A281 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/10/2014 |
| From: | Oskamp J A, Schubert J P Paul C. Rizzo Associates, Wolf Creek |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14077A278 | List: |
| References | |
| ET 14-0012, Project No. 13-5031 | |
| Download: ML14077A281 (107) | |
Text
Enclosure to ET 14-0012 Enclosure to ET 14-0012 Wolf Creek Nuclear Operating Corporation Flood Hazard Reevaluation Report, Revision 0 (106 pages) rjc4z ENGINEERS/COSULTANTS/CM WOLF CREEK NUCLEAR OPERATING CORPORATION FLOOD HAZARD REEVALUATION REPORT REVISION:
0 PAUL C. Rizzo ASSOCIATES, INC.500 PENN CENTER BOULEVARD PENN CENTER EAST, BUILDING 5, SUITE 100 PITTSBURGH, PENNSYLVANIA 15235 USA PROJECT No. 13-5031 FEBRUARY 10, 2014 WOLF CREEK NUCLEAR OPERATING CORPORATION FLOOD HAZARD REEVALUATION REPORT PROJECT No.: 13-5031 REVISION 0 FEBRUARY 10, 2014 PAUL C. Rizzo ASSOCIATES, INC.500 PENN CENTER BOULEVARD BUILDING 5, SUITE 100 PITTSBURGH, PENNSYLVANIA 15235 TELEPHONE:
(412) 856-9700 TELEFAX: (412) 856-9749 WWW.RIZZOASSOC.COM Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)RZYZ"'
APPROVALS Project No.: Report Name: 13-5031 Wolf Creek Nuclear Operating Corporation Flood Hazard Reevaluation Report Date: February 10, 2014 Revision No.: 0 Approval by responsible manager signifies that the document is complete, all required reviews are complete, and the document is released for use.Originator:
iDt FeL ;Zciq-Date Co-Originator:
Independent Technical Reviewer: Project Manager: Principal in Charge: JeffeytPl.
9'chif.ert Managing Principal Je fTy A. Osk , E.I.T.Enginqenng Associate II Daniel J. Barton, Jf.' P.E. f Vice President
-Iiastructure Engineering Ahmed "Jemie" Dababneh, Ph.D., P.E.Managipg Principal and Project Manager DanieTJ. Barton, J /, P.E. " Vice President
-Ir~rastructure Engineering Date Date/o-f, Date/6 -c Z"it)/Date Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)FJC""vZ CHANGE MANAGEMENT RECORD Project No.: Report Name: 13-5031 Wolf Creek Nuclear Operating Corporation Flood Hazard Reevaluation Report PERSON REVISION DESCRIPTIONS OF PRO N DATE DESCTIN OF AUTHORIZING APPROVAL'NO. CHANGES/AFFECTED PAGES CHNE _____CHANGE 0 February 10, 2014 N/A N/A N/A t 4 1-4 ++ I Notes: Person authorizing change shall sign here for the latest revision.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)Pcm"'14Z TABLE OF CONTENTS PAGE L IS T O F T A B L E S .............................................................................................................
iii L IST O F FIG U R E S .......................................................................................................
iv 1.0 IN TR O D U C T IO N ...............................................................................................
I 1.1 PURPO SE AND SCO PE ....................................................................................
1 1.2 L OCATION OF THE SITE .................................................................................
1 1.3 SITE BACKGROUND AND HISTORY ............................................................
1 2.0 FLOOD HAZARDS AT THE SITE ....................................................................
3 2.1 DETAILED SITE INFORMATION
.................................................................
3 2.1.1 Design Site Information
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3 2.1.2 Present-Day Site Information
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6 2.2 CURRENT DESIGN BASIS FLOOD ELEVATIONS
.........................................
7 2.3 FLOOD-RELATED CHANGES TO THiE LICENSING BASIS .............................
9 2.3.1 Description of Hydrological Changes and Flood E levations
.............................................................................
..10 2.3.2 Description of Flood Protection Changes (Including M itigation)
.............................................................................
..10 2.4 CHANGES TO THE WATERSHED AND LOCAL AREA ..................................
11 2.4.1 Description of Watershed and Local Area at the Time of L icense Issuance .......................................................................
11 2.4.2 Description of Any Changes to the Watershed and Local Area since License Issuance ....................................................
11 2.5 CURRENT LICENSING BASIS FLOOD PROTECTION
...................................
12 2.6 ADDITIONAL SITE DETAILS .....................................................................
12 2.6.1 Wolf Creek Lake Bathymetry
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13 2.6.2 Recommendation 2.3 Walkdown Results ...............................
13 2.6.3 Site-Specific V isit ....................................................................
14 3.0 FLOOD HAZARD REEVALUATION ANALYSIS ........................................
15 3.1
SUMMARY
OF RECOMMENDATION 2.1 ...................................................
15 3.2 SOFTW ARE U SED ....................................................................................
15 3.3 FLOOD CAUSING MECHANISMS
.............................................................
16 3.3.1 Local Intense Precipitation
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17 Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014) P C Y Z TABLE OF CONTENTS (CONTINUED)
PAGE 3.3.2 Flooding in Rivers and Streams ............................................
21 3.3.3 Dam Breaches and Failures ....................................................
32 3.3.4 Storm Surge .............................................................................
35 3.3.5 Seiche ...................................................................................
..36 3.3.6 T sunam i .................................................................................
36 3.3.7 Ice-Induced Flooding .............................................................
37 3.3.8 Flooding Resulting from Channel Migration or Diversion
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38 4.0 COMPARISON OF CURRENT AND REEVALUATED PREDICTED FLO O D LEV ELS ............................................................................................
40 4.1 COMPARISON OF CURRENT AND REEVALUATED FLOOD CAUSING M ECH AN ISM S ..........................................................................................
40 4.2 ASSESSMENT OF THE CURRENT DESIGN BASIS FLOOD ELEVATIONS TO THE REEVALUATED FLOOD ELEVATIONS
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41 4.3 SUPPORTING DOCUMENTATION
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45 4.3.1 Technical Justification of the Flood Hazard Analysis .................
46 4.3.2 Technical Justification of the Walkdown Results ...................
46 4.4 C ONCLUSIONS
........................................................................................
48 5.0 INTERIM EVALUATION AND ACTIONS ....................................................
50 5.1 EVALUATION OF THE IMPACT OF THE REEVALUATED FLOOD LEVELS ON STRUCTURES, SYSTEMS, AND COMPONENTS
....................................
50 5.2 ACTIONS TAKEN TO ADDRESS FLOOD HAZARDS NOT COMPLETELY BOUNDED BY THE CURRENT DESIGN BASIS HAZARD .............................
50 6.0 ADDITION AL ACTION S ..............................................................................
52 7.0 RE FERE N C E S ................................................................................................
53 TABLES FIGURES APPENDIX A -FLO-2D PRO SOFTWARE QUALIFICATIONS Flood Hazard Reevaluation Report ii 135031/14 Rev. 0 (February 10, 2014) P C LIST OF TABLES TABLE NO.TABLE 2-1 TABLE 2-2 TABLE 2-3 TABLE 3-1 TABLE 3-2 TABLE 3-3 TABLE 3-4 TABLE 3-5 TABLE 4-1 TABLE 4-2 TABLE 4-3 TABLE 4-4 TITLE LIST OF POWERBLOCK STRUCTURES AND THEIR ELEVATIONS EXISTING WOLF CREEK DESIGN PARAMETERS CURRENT DESIGN BASIS FLOOD ELEVATIONS DUE TO ALL FLOOD MECHANISMS WATER LEVELS AND PONDING DEPTHS DUE TO LOCAL INTENSE PRECIPITATION FLOODING AT OUTSIDE DOORS TO SEISMIC CATEGORY I BUILDINGS THAT ARE AT ELEVATION 1,100 FT DUE TO LOCAL INTENSE PRECIPITATION FLOODING FLOODING AT OTHER DOORS, HATCHES, MANHOLES, AND VAULTS FOR SAFETY-RELATED SSCs DUE TO LOCAL INTENSE PRECIPITATION FLOODING WATERSHED SUBBASIN CHARACTERISTICS AND HEC-HMS MODELING RESULTS
SUMMARY
OF HEC-HMS AND HEC-RAS SIMULATION CASES COMPARISON OF MODELING APPROACHES FOR CURRENT LICENSING BASIS AND FLOODING REEVALUATION COMPARISON OF CURRENT LICENSING BASIS AND FLOODING REEVALUATION ANALYTICAL INPUTS COMPARISON OF CURRENT LICENSING BASIS AND REEVALUATED FLOOD LEVELS COMPARISON OF VARIOUS FLOODING PARAMETERS BETWEEN THE CURRENT LICENSING BASIS AND THE FLOOD REEVALUATION Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)iii RZYZZ LIST OF FIGURES FIGURE NO.FIGURE 1-1 FIGURE 1-2 FIGURE 2-1 FIGURE 2-2 FIGURE 2-3 FIGURE 2-4 FIGURE 3-1 FIGURE 3-2 FIGURE 3-3 FIGURE 3-4 FIGURE 3-5 FIGURE 3-6 FIGURE 3-7 FIGURE 3-8 FIGURE 3-9 FIGURE 3-10 FIGURE 3-11 FIGURE 3-12 FIGURE 3-13 FIGURE 3-14 FIGURE 3-15 FIGURE 4-1 TITLE GENERAL LOCATION OF THE SITE SITE AREA MAP DESIGN SITE LAYOUT PRESENT-DAY SITE LAYOUT AND TOPOGRAPHY LOCATIONS OF BUILDINGS IN THE POWERBLOCK AREA WOLF CREEK LAKE WATER DEPTHS THE HHA DIAGRAM FOR LOCAL INTENSE PRECIPITATION FLOODING ANALYSIS FLO-2D INUNDATION MAP DUE TO LOCAL INTENSE PRECIPITATION THE HHA DIAGRAM FOR THE ANALYSIS OF FLOODING IN RIVERS AND STREAMS WOLF CREEK WATERSHED MAP SHOWING SUBBASINS PMP HYETOGRAPH FOR THE WOLF CREEK WATERSHED HEC-HMS MODEL FOR THE WOLF CREEK WATERSHED FLOOD LEVEL TIME HISTORY OF WOLF CREEK LAKE FOR THE ANALYSIS OF FLOODING IN RIVERS AND STREAMS HEC-RAS MODEL FOR THE WOLF CREEK WATERSHED FETCH LOCATIONS OVER WOLF CREEK LAKE THE HHA DIAGRAM FOR COMBINED-EFFECTS FLOODING ANALYSIS FLOOD LEVEL TIME HISTORY OF WOLF CREEK LAKE FOR THE ANALYSIS OF COMBINED-EFFECTS FLOOD LOCATION OF DAMS NEAR THE SITE THE JLD-ISG-2013-01 DIAGRAM FOR DETERMINING LEVELS OF ANALYSIS FOR DAM BREAK EVALUATION THE JLD-ISG-2013-01 DIAGRAM FOR THE ANALYSIS OF DAM BREACHES AND FAILURES USING THE "VOLUME METHOD" INUNDATION AREA CALCULATED USING "VOLUME METHOD" FOR DAM FAILURE ANALYSIS ASSUMING FAILURE OF ALL UPSTREAM DAMS DURATION OF FLOODING FOR THE LIP FLOOD ANALYSIS Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February
- 10. 2014)iv rjc_",,*4Z WOLF CREEK NUCLEAR OPERATING CORPORATION FLOOD HAZARD REEVALUATION REPORT
1.0 INTRODUCTION
1.1 PURPOSE AND SCOPE The United States Nuclear Regulatory Commission (NRC) issued a letter on March 12, 2012, pursuant to Title 10 of the Code of Federal Regulations (CFR), Section 50.54(f), related to the implementation of Recommendations 2.1, 2.3, and 9.3 from the Near-Term Task Force (NTTF), a portion of which calls for performing flood hazard reevaluations at all Nuclear Power Plants (NPP) in the United States (NRC, 2012a). On behalf of Wolf Creek Nuclear Operating Corporation (WCNOC), this Flood Hazard Reevaluation Report for the Wolf Creek Generating Station (WCGS) site provides the information required to address NRC Recommendation 2.1 with due consideration to the most recent guidance and regulations.
1.2 LOCATION OF THE SITE The WCNOC operates the WCGS, which is located in Coffey County in eastern Kansas. The WCGS site is approximately 90 miles southwest of Kansas City, approximately 3.5 miles northeast of the city of Burlington, and approximately 3.5 miles east of the Neosho River and the main dam at John Redmond Reservoir (Figures 1-1 and 1-2). The WCGS site is located adjacent to Wolf Creek Lake (Coffey County Lake). Wolf Creek flows south into Wolf Creek Lake, which in turn drains into the Neosho River (U.S. Geological Survey [USGS], 2012a; 2012b).Wolf Creek Lake was established for station cooling, and was created by constructing an earthen dam across Wolf Creek. The location of the earthen dam is approximately four miles upstream of Wolf Creek's confluence with the Neosho River (Figure 1-2).1.3 SITE BACKGROUND AND HISTORY WCNOC is a joint venture of three owners: Kansas Gas and Electric Company, Kansas City Power & Light Company, and Kansas Electric Power Cooperative, Inc. The WCGS site has one Flood Hazard Reevaluation Report -50% Submittal 1 135031/14 Rev. 0 (February 10, 2014) P reactor, which is a Westinghouse Pressurized Water Reactor (PWR). The site has been in operation since the issuance of the license on June 4, 1985. The operating license for the WCGS expires on March 11, 2045 (NRC, 2013a).The Updated Safety Analysis Report (USAR) for the WCGS (WCNOC, 2013a) was revised in March 2013. In the USAR, two elevation datums are referenced; Mean Sea Level (MSL) (the National Geodetic Vertical Datum of 1929 (NGVD29))
and the Standardized Nuclear Unit Power Plant System (SNUPPS) datum. The SNUPPS datum is equivalent to the MSL elevation plus 900 feet (ft). At the WCGS site, MSL is equivalent to NGVD29, as stated in a design drawing. All elevations in this report are with reference to MSL, unless otherwise stated.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10 2014)2 FJC"4**JZ 2.0 FLOOD HAZARDS AT THE SITE Section 2.0 has been prepared in response to Request for Information Item L.a. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a) and documents results, as well as pertinent site information and detailed analyses related to the applicable flood hazards. Relevant Structures, Systems, and Components (SSC) important to safety and the Ultimate Heat Sink (UHS) are included in the scope of this reevaluation, including pertinent data concerning these SSCs. While the UHS is discussed separately, it is a safety-related SSC.2.1 DETAILED SITE INFORMATION Section 2.1 has been prepared in response to Request for Information Item I .a.i. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes detailed site information, present-day site layout, and elevations of pertinent SSCs important to safety, site topography, as well as pertinent spatial and temporal data sets.2.1.1 Design Site Information Design site information describes characteristics considered for the original licensing basis of the WCGS site. The original topography and design of site layout are shown in the USAR for the WCGS (WCNOC, 2013a, Figures 1.2-43 and 2.4-1). Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). Figure 2-1 shows the design layout of the WCGS site.The design locations of the safety-related structures, as well as other buildings and structures in the powerblock area are shown in Figure 2-1. A list of the primary safety- and non-safety-related structures at the WCGS site is provided in Table 2-1. A list of the existing design parameters found in the license document (WCNOC, 2013a) is included in Table 2-2.2.1.1.1 Site Topography and Drainage The WCGS site is located on a small peninsula on the northeastern side of Wolf Creek Lake (Figure 1-2). The lake is a reservoir that is retained behind an earthen dam, which was Flood Hazard Reevaluation Report 3 135031/14 Rev. 0 (February 10, 2014) P C constructed across Wolf Creek in order to provide cooling water for the WCGS. The headwater area of Wolf Creek lies north of the WCGS and the lake. The watershed area upstream of the dam is approximately 27.4 square miles (mi 2) (WCNOC, 2013a). The lake itself has a surface area of approximately 5,090 acres (approximately 8.0 mi 2) and a water storage capacity of about 111,280 acre-ft when it is at its normal water surface elevation of 1,087 ft (WCNOC, 2013a).Below the darn, Wolf Creek flows about four miles south-southwest to where it joins the Neosho River.The Neosho River is a relatively large river; its watershed covers approximately 6,300 mi 2 in Kansas. The Neosho River originates in east-central Kansas (Morris County) and flows southeast toward Humbolt, Kansas, and then southward into Oklahoma (Figure 1-1). It lies west and south of the Wolf Creek watershed.
Flow in the Neosho River near the WCGS site is controlled by John Redmond Reservoir.
Wolf Creek flows south-southwest and joins the Neosho River about four miles south of the Wolf Creek Dam and 7.1 miles downstream of the John Redmond Dam (Figure 1-2). Cottonwood Creek is a large tributary of the Neosho River and joins the river approximately six miles east of Emporia, Kansas, or approximately 14 miles northwest of the John Redmond Reservoir and Dam (WCNOC, 2013a).Long Creek flows from north to south and is located directly east and northeast of the Wolf Creek watershed (Figure 1-2). It too flows into the Neosho River. Altogether, the Long Creek watershed covers approximately 84 mi 2.Low topographic ridges separate the Wolf Creek watershed from the Long Creek and Neosho River watersheds (USGS, 2012b).The WCGS site lies in the Osage Plains physiographic section of the Central Lowland Province (WCNOC, 2013a). It is an area of low rolling hills with very gentle slopes. The WCGS site is positioned near the top of a low hill and has a grade elevation of 1,099.5 ft adjacent to buildings in the powerblock area. The floor elevation of safety-related buildings is 1,100 ft (WCNOC, 2013a). The powerblock area is flat. The ground surface slopes gently down to the Wolf Creek Lake on the western, southern, and eastern sides of the powerblock.
This is an elevation drop of approximately 12.5 ft when the lake is at its normal operating level (1,087 fi; WCNOC, 2013a).Within a five-mile radius of the site, elevations range from highs of approximately 1,215 ft on hilltops to the north and northeast of the site down to approximately 985 ft near the confluence of Wolf Creek and the Neosho River, southwest of the site (Figure 1-2).Flood Hazard Reevaluation Report 4 135031/14 Rev. 0 (February 10, 2014) R C 2.1.1.2 Description of Safety-Related Structures, Systems, and Components The locations of the safety-related structures, including the Essential Service Water System (ESWS) pumphouse, are shown in Figure 2-1. A list of the WCGS site safety-related structures is provided in Table 2-1.2.1.1.3 Description of Wolf Creek Lake and the Ultimate Heat Sink Wolf Creek Lake was created by erecting an earthen darn across Wolf Creek just downstream of the WCGS site. Filling of the reservoir began in October 1980 and was complete in June 1982 (Kansas Biological Survey [KBS], 2010). The dam retaining Wolf Creek Lake is not a Seismic Category I dam and is not considered to be safety-related.
A service spillway is located on the east abutment of the cooling lake dam and is an uncontrolled concrete ogee-crested spillway with a crest elevation of 1,088 ft and a crest length of 100 ft. The auxiliary spillway is approximately 1,500 ft east of the service spillway and is an open cut spillway with a crest elevation of 1,090.5 ft and a crest length of 500 ft (WCNOC, 2013a). As stated in the USAR (WCNOC, 2013a, Section 2.4.1.1), the lake has a surface area of 5,090 acres and a capacity of 111,280 acre-ft of water at its normal operating level of 1,087 ft.The impoundment was initially filled and subsequently maintained with makeup water pumped from the nearby Neosho River (KB S, 2010). Wolf Creek Lake was designed to provide adequate cooling water to the WCGS during a fifty-year drought. The water level in the lake is normally sustained by the Wolf Creek watershed upstream of the lake. However, during dry months, it is sometimes necessary to pump water to the lake from the Neosho River, just below the John Redmond Reservoir (KBS, 2010). During times of flooding, the service and auxiliary spillways provide controlled release of water to prevent overtopping of the Wolf Creek Lake Dam.The description of the UHS in this section is in regards to the design basis of the UHS, as described in the USAR (WCNOC, 2013a). Any changes to the UHS are considered present-day information and are discussed in Section 2.1.2.3. The UHS is located within Wolf Creek Lake, created by the construction of a submerged Seismic Category I dam. The UHS provides water to the ESWS. The intake channel bottom in the UHS is at an elevation of 1,065 ft and locally slopes down to an elevation of 1,064 ft at the ESWS pumphouse.
The design water surface elevation of the UHS is 1,070 ft., which is five feet lower than the design minimum Wolf Creek Lake elevation.
The maximum allowable sediment volume in the UHS is limited to 130 acre-ft to provide sufficient surface area and volume to safely shut down and maintain shutdown of the plant (WCNOC, 2013a).Flood Hazard Reevaluation Report 5 135031/14 Rev. 0 (February 10, 2014) RZ 2.1.2 Present-Day Site Information Present-day site information describes changes to the WCGS site that have occurred since the original design of the site, which may have the potential to influence the reevaluation of hydrological and flooding hazards. Figure 2-2 shows the WCGS present-day site layout and topography.
2.1.2.1 Site Topography All flooding analyses described in this flood hazard reevaluation report have been undertaken with consideration and implementation of current techniques, software, and methods used in present-day standard engineering practice to develop the flood hazard. Up-to-date topographic information from an October 2012 survey of the plant area and data are utilized in the generation of all of the applicable reevaluated flooding models. As such, any changes to site topography since the time of license issuance up to the date of the topographic data have been captured within this report.2.1.2.2 Description of Safety-Related Structures, Systems, and Components Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushimna Flooding Walkdown Report (WCNOC, 2012).The design locations of the safety and non-safety-related structures, in the powerblock area are shown in Figure 2-3.2.1.2.3 Description of the Ultimate Heat Sink The UHS is located within Wolf Creek Lake and is described in Section 2.1.1.3. No changes in the UHS since license issuance are noted in the USAR (WCNOC, 2013a) or the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012).Flood Hazard Reevaluation Report 6 135031/14 Rev. 0 (February
- 10. 2014) P C 2.2 CURRENT DESIGN BASIS FLOOD ELEVATIONS Section 2.2 has been prepared in response to Request for Information Item 1 .a.ii. of NRC Recommendation
- 2. 1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes the current design basis flood elevations for all flood causing mechanisms.
The current design basis, as presented in the USAR (WCNOC, 2013a), indicates that the site is not affected by flooding.
The WCGS site has a plant grade elevation of 1,099.5 ft, and a floor elevation of 1,100 ft. The maximum calculated water levels near the safety-related buildings due to the Local Intense Precipitation (LIP) event range from 1,099.52 ft to 1,099.83 ft (WCNOC, 2013b). During the LIP event, it is conservatively assumed in the design basis that the site drainage system is not functional.
The maximum water level due to the LIP is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). The LIP (1-hour [hr], 1 mi 2) rainfall of 19 inches (in) is part of the cumulative six-hr rainfall of 28.79 in used in the design basis. The LIP rainfall is determined using Hydrometeorological Report Number 52 (HMR No. 52) (WCNOC, 2013b).To characterize the Probable Maximum Flood (PMF) for the Wolf Creek watershed and Wolf Creek Lake, a Probable Maximum Precipitation (PMP) distribution was developed and applied over the design watershed (of 27.4 Mi 2). The PMP was determined using HMR No. 33 (WCNOC, 2013a). The cumulative 48-hr duration PMP is 32.80 in (WCNOC, 2013a, Table 2.4.12), with the peak occurring at approximately 34 hrs.The Wolf Creek Lake dam has a service spillway and an auxiliary spillway.
Both spillways have uncontrolled crests, which are provided to pass floods up to and including the PMF (WCNOC, 2013a). The flood event simulated for the design basis includes the combined effects of a single PMP event preceded by a Standard Project Flood (SPF) event (which is 50 percent of the PMP), and an overland sustained wind speed of 40 miles per hour (mph) (WCNOC, 2013a, Section 2.4.2.2).
The peak flow rate in the design basis for the spillways is 22,845 cubic feet per second (cfs) (WCNOC, 2013a, Section 2.4.3.5).
The maximum water surface elevation in Wolf Creek Lake (i.e., the pool elevation) due to the PMF event is 1,095 ft at the plant site, which assumes a starting pool elevation of 1,088 ft (corresponding to the crest elevation of the service spillway for the Wolf Creek Lake Dam). The coincident wave activity of the PMF resulted in a maximum run-up of 0.8 ft at the plant site shore. The resulting run-up elevation was 1,095.8 ft when added to the PMF pool elevation (WCNOC, 2013a, Table 2.4-16).Flood Hazard Reevaluation Report 7 135031/14 Rev. 0 (February 10, 2014)
The maximum wave run-up elevation on the vertical wall of the intake structure of the ESWS is 1,100.2 ft. However, the intake structure for the ESWS is designed to withstand a high water elevation of 1,102.5 ft. As stated in the USAR, the only openings below elevation 1,102.5 ft are the pressure doors and the pump structure forebay opening. The pressure doors are located at elevation 1,100.0 ft. These doors are normally closed and under administrative control. The pump structure forebay normally contains water (WCNOC, 2013a).In regards to the PMF, backwater caused by the PMF in the Neosho River or Long Creek does not affect the site due to the topographic ridges between the site and the Long Creek and Neosho River valleys.Failure of dams located above John Redmond Reservoir will not adversely affect any safety-related facilities at the WCGS site (WCNOC, 2013a). In the most critical case, which postulates the domino-type failure of all four reservoirs (John Redmond, Marion, Cedar Point, and Council Grove) (Case b.3 of Section 2.4.4.1 of the USAR [WCNOC, 2013a]), the maximum flood stage of the Neosho River was estimated to be 1,044.55 ft at a distance of about five miles downstream from the John Redmond Dam (WCNOC, 2013a). As stated in the USAR, the topographic ridge between the Neosho River and Wolf Creek valleys below John Redmond Dam will separate the postulated flood levels in the Neosho River valley from any facilities at the site, with the exception of the cooling lake main dam. The maximum water elevation on the downstream slope of the Wolf Creek Lake Dam, due to the postulated combined maximum flood-causing events in the Neosho and Cottonwood River basins, is conservatively established at elevation 1,049.6 ft.This flood stage is well below surface grades of any Seismic Category I facilities at the site and is about 50 ft below the plant grade elevation of 1,099.5 ft (WCNOC, 2013a).Storm surge and seiche, tsunami, and ice-induced flooding were screened out as potential flooding events in the current design basis in the USAR (WCNOC, 2013a). The following lists the sections in the USAR where these flood mechanisms were screened out:* Probable maximum storm surge and seiche flooding:
Section 2.4.5* Probable maximum tsunami flooding:
Section 2.4.6* Ice effects: Section 2.4.7 Frazil ice is screened out in the design basis. Frazil ice is prevented by diffusing warmed water in front of the ESWS track racks (WCNOC, 2013a, Section 2.4.7.2).
The design basis states that Flood Hazard Reevaluation Report 8 135031/14 Rev. 0 (February 10, 2014) P C wanning lines divert heat to ensure that frazil ice does not block the ESWS trash racks (WCNOC, 2013a, Section 9.2.1.2.2).
There are two trains (Trains A & B) in the ESWS;therefore, the ESWS pumphouse has two redundant trains. Each train has its own independent warming system. There is a secondary system, a portable air bubbler system, which can also be placed at the ESWS pumphouse.
In addition, there is a procedure for the ESWS pumphouse for the prevention of frazil ice formation.
The sources of the makeup water to the cooling lake are Wolf Creek and the Neosho River. In reference to channel diversion in the USAR, there is no indication that Wolf Creek or its tributaries would be diverted from its present course of flowing into Wolf Creek Lake. Ice jams will also not cause diversion of flow because the jams do not prevent overbank flow. The ESWS intake is designed to prevent ice from jamming against it and cutting off inflow (WCNOC, 2013a, Section 9.2.1.2.2.2).
As stated in the USAR, if the Wolf Creek flow was temporarily cut off, makeup water to the plant would still be available from the John Redmond Reservoir on the Neosho River. Due to the regional topographical conditions, it is unlikely that the upper Neosho River would be diverted from the John Redmond Reservoir due to ice jams or subsidence.
Therefore, it is unlikely that the Neosho River inflows would be completely cut off and affect the makeup water available to the cooling lake (WCNOC, 2013a).In addition, it is not expected that any potential morphological changes in Wolf Creek will affect any safety-related SSCs at the WCNOC site. As stated in the USAR, "there is no historic or topographic evidence indicating that flow in Wolf Creek can be diverted away from its present course. Local relief and the natural geomorphological condition preclude the likelihood of Wolf Creek and its tributaries discharging anywhere other than into the cooling lake" (WCNOC, 2013a, Section 2.4.10).2.3 FLOOD-RELATED CHANGES TO THE LICENSING BASIS Section 2.3 has been prepared in response to Request for Information Item 1 .a.iii of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes flood-related changes to the licensing basis and any flood protection changes (including mitigation) since license issuance.Flood Hazard Reevaluation Report 9 135031/14 Rev. 0 (February 10, 2014) P C 2.3.1 Description of Hydrological Changes and Flood Elevations The design basis flood elevations for the flood causing mechanisms that are applicable to WCGS are summarized in Table 2-3. The LIP flooding hazard was recently updated in 2013 (WCNOC, 2013b). The current LIP design basis is based on HMR No. 52, using a 6-hr distribution (WCNOC, 2013b). As presented in Table 2-3, the current LIP maximum flood elevation is 1,099.83 ft at Seismic Category I buildings.
The previous design basis LIP was based on HMR No. 33, using the procedures outlined in EM- 1110-2-1411 to obtain a 6-hr distribution; this resulted in a maximum flood elevation of 1,099.86 ft around the powerblock (WCNOC, 2013a, Section 2.4.2.3.2).
A description of flood-related and flood protection changes since license issuance is provided in Section 2.3.2. Reevaluated flood elevations are described in Section 3.0 and the results are sumnmarized in Section 4.0. Up-to-date information and data regarding topography, buildings, structures, and hydrologic controls are utilized in the generation of all of the applicable reevaluated flooding models. As such, any changes to regional and site topography and hydrology since the time of license issuance have been captured within the current analysis.2.3.2 Description of Flood Protection Changes (Including Mitigation)
The flood protection system and flood mitigation measures described in the USAR (WCNOC, 2013a) and as observed and documented in the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) are specifically relevant to the flood hazard reevaluation analyses.
Changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushitna Flooding Walkdown Report (WCNOC, 2012). Safety-related SSCs that are credited in the Current Licensing Basis (CLB) for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate.According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." No changes since license issuance and no comments regarding adverse site conditions affecting flooding protection were noted in the report (WCNOC, 2012).Flood Hazard Reevaluation Report 10 135031/14 Rev. 0 (February 10, 2014) 2.4 CHANGES TO THE WATERSHED AND LOCAL AREA Section 2.4 has been prepared in response to Request for Information Item 1 .a.iv of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes changes to the watershed and local area since license issuance.
A description of the watershed at the time of license issuance and pertinent changes to the watershed since license issuance are presented in the following sections.2.4.1 Description of Watershed and Local Area at the Time of License Issuance The drainage area of the Wolf Creek watershed defined at the time of the license issuance was 27.4 mi2 .There are no gages located on the Wolf Creek watershed; therefore, no streamflow records are available.
Additional information regarding the Wolf Creek watershed and adjacent watersheds are presented in Section 2.1.1.1.2.4.2 Description of Any Changes to the Watershed and Local Area since License Issuance As previously discussed, changes to the site layout and SSCs related to flooding protection were evaluated as part of the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). In addition, the flood reevaluation analysis deternmined that there were no significant changes to the watershed since the original design basis.The walkdown visual inspection conducted during the walkdown verified that there is reasonable assurance that the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The WCGS external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard. The purpose of the Recommendation 2.3 walkdown is to verify the conformance with the CLB; the adequacy of the CLB will be addressed as part of the flood reevaluations if an integrated assessment is required.The original design site layout did not include a vehicle barrier system (VBS). A VBS has been added to the current WCGS site layout. The VBS configuration used in the reevaluation analysis is the configuration as of February 2013. Changes to the site layout that have occurred since license issuance and are captured in the reevaluation analysis.Flood Hazard Reevaluation Report 11 135031/14 Rev. 0 (February 10, 2014) P C The slope for the Wolf Creek Lake shoreline reported for the design basis is 30:1 (horizontal to vertical) (WCNOC, 2013a, Table 2.4-14). Based on the current topographic data used for the flood hazard reevaluation, the average shoreline slope is determined to be 46:1. The difference in slope is likely due to the method of computing an average slope for the shoreline, not due to significant change in the shoreline topography.
All flooding analyses described in this flood hazard reevaluation report and described in Section 3.0 have been undertaken with consideration and implementation of current techniques, software, data, and methods used in present-day standard engineering practice to develop the flood hazard.2.5 CURRENT LICENSING BASIS FLOOD PROTECTION Section 2.5 has been prepared in response to Request for Information Item 1 .a.v. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes current licensing basis flood protection and pertinent flood mitigation features at the site.The safety-related facilities are not affected by the PMF in the cooling lake or by the LIP at the plant site and no flood protection requirements are necessary (WCNOC, 2013a). The Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012)identified the credited flood protection and mitigation features that are considered in the WCGS CLB to protect against the ingress of water to safety-related SSCs. These include topography, structures, floors, walls, penetrations, vaults, the forebay, doors, sump pumps, and sump pump motors. The ESWS pumphouse has pressure doors that are located at elevation 1,100.0 ft. These pressure doors are flood protection doors and are normally closed and under administrative control (WCNOC, 2013a).2.6 ADDITIONAL SITE DETAILS Section 2.6 has been prepared in response to Request for Information Item 1 .a.vi. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a). Relevant site data to be considered includes additional site details, as necessary, to assess the flood hazard (i.e., walkdown results, etc.).Flood Hazard Reevaluation Report 12 135031/14 Rev. 0 (February 10, 2014) 2.6.1 Wolf Creek Lake Bathymetry During October and November 2009, the KBS performed a bathymetric Survey of Wolf Creek Lake. The survey (KBS, 2010) was carried out using an acoustic echo sounding apparatus linked to a global positioning system. Nearly 74,000 georeferenced depths were measured and used to create a digital bathymetric model of the reservoir (Figure 2-4). For a water surface elevation of 1,088.90 ft, the surface area and volume of the lake were 4,863 acres and 117,407 acre-ft, respectively (KBS, 2010). The maximum depth was 73.75 ft. As stated in the USAR (WCNOC, 2013a, Section 2.4.1.1), the lake has a surface area of 5,090 acres and a capacity of 111,280 acre-ft of water at its normal operating level. In June 1998, Coffey County assumed responsibility for managing public use of the lake. The lake is open for public use seven days a week from sunrise to sunset, weather, and reservoir levels permitting (KBS, 2010).2.6.2 Recommendation 2.3 Walkdown Results The Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) gives results of the walkdown, including key findings and identified degraded.non-conforming, or unanalyzed conditions, and includes detailed descriptions of the actions taken or planned to address these conditions.
The results of the walkdown observations were reviewed through site processes in accordance with Regulatory Issues Summary 2005-20, Revision I (WCNOC, 2012).Safety-related SSCs that are credited in the CLB for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate.
According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." The review of the walkdown concludes that the WCGS site"flood protection features would be capable of performing their intended flood protection function if subjected to a design basis flooding hazard. No flooding walkdown observations were deemed to be a deficiency per Section 3.8 of Nuclear Energy Institute (NEI) 12-07" (WCNOC, 2012).Flood Hazard Reevaluation Report 13 135031/14 Rev. 0 (February 10, 2014) 2.6.3 Site-Specific Visit A site visit was conducted on March 18 and March 19, 2013. The following areas at the site were observed and inspected:
- The powerblock area and area immediately surrounding the powerblock
- The ESWS pumphouse" The cooling water discharge structure" The VBS The personnel also inspected portions of Wolf Creek Lake., Wolf Creek and its tributaries located north of Wolf Creek Lake. Additionally, photographs were taken of the site. These photographs were reviewed during the development of the flood hazard reevaluation analyses.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)14 RCZZ 3.0 FLOOD HAZARD REEVALUATION ANALYSIS Section 3.0 has been prepared in response to Request for Information Item 1 .b. of NRC Reconrimendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Evaluation of the flood hazard for each flood causing mechanism should be based on present-day methodologies and regulatory guidance.
Provide an analysis of each flood causing mechanism that may impact the site including local intense precipitation and on-site drainage, flooding in streams and rivers, dam breaches and failures, storm surge and seiche, tsunami, channel migration or diversion, and combined effects. Mechanisms that are not applicable at the site may be screened out; however, a justification should be provided.
Provide a basis for inputs and assumptions, methodologies and models used including input and output files, and other pertinent data.3.1
SUMMARY
OF RECOMMENDATION 2.1 To respond to Phase I of NRC Recommendation 2.1 (NRC, 2012a) and the 2012 Appropriations Act, the NRC requested that each licensee provide a reevaluation of all appropriate external flooding sources, including the effects from local intense precipitation on the site, PMF on streams and rivers, storm surges, seiches, tsunamis, and dam failures.
A hazard evaluation should be performed for each reactor licensed under 10 CFR Part 50, including the spent fuel pool and the various modes of reactor operation.
The reevaluation should apply present-day regulatory guidance and methodologies being used for Early Site Permit (ESP) and Combined Operating License (COL) reviews. The reevaluation should employ current techniques, software, and methods used in present-day standard engineering practice to develop the flood hazard.3.2 SOFTWARE USED Software programs used in the flood hazard reevaluation included FLO-2D Pro (FLO-2D, 2012), the USACE HEC-HMS program version 3.5 (USACE, 2010a), the USACE HEC-RAS program version 4.1 (USACE, 2010b), USACE HMR52 program (USACE, 1987), ArcGIS 9.3 (ESRI, 2009), and ArcGIS 10.1 (ESRI, 2012).The FLO-2D Pro software is a volume conservation model, which routes fluid flow in one-dimensional (I D) channel flow, two-dimensional (2D) overland flow, or an interaction between the two model components (FLO-2D, 2012). The FLO-2D Pro software is an "effective tool for Flood Hazard Reevaluation Report 1 5 135031/14 Rev. 0 (February 10, 2014) delineating flood hazards or designing flood mitigation" (FLO-2D, 2012). The FLO-2D Basic model is the other model available from FLO-2D Software, Inc., and includes fewer features than the Pro model. The Basic model has been approved by Federal Emergency Management Agency (FEMA) for use in Flood Insurance Studies (FIS). The Pro model, though not specifically approved by FEMA, includes all the features of the Basic model, along with some additional features (e.g., storm drain interface with surface water, parallel processing capabilities, and expanded capabilities for simulating sediment transport) (FLO-2D, 2012). Additional qualifications of the FLO-2D Pro software are presented in Appendix A.3.3 FLOOD CAUSING MECHANISMS NRC NUREG/CR-7046 (NRC, 2011) recommends using a Hierarchical Hazard Assessment (HHA) method for evaluating the safety of SSCs. The HHA is a progressively refined, stepwise estimation of site-specific hazards that starts with the most conservative plausible assumptions consistent with available data. The HHA process proceeds as follows (NRC, 2011): a. Select one flood causing mechanism to be reanalyzed.
- b. Develop a conservative estimate of the site-related parameters using simplifying assumptions for a flood causing mechanism and perform the reevaluation.
- c. Determine if the reevaluated flood hazard elevation (from step b) is higher than the original design flood elevation for the selected flood causing mechanism.
If not, use this flood elevation for this causal mechanism for comparison of reevaluation against the current design basis.d. Determine if the site-related parameters can be further refined. If yes, perform reevaluation (repeat step c). If no, use this flood elevation for this causal mechanism for comparison of reevaluation against the current design basis.e. Determine if all flood causing mechanisms have been addressed.
If yes, continue to the following.
If no, select another flood causing mechanism (step a).For each flood causing mechanism, compare the final flood elevations from the hazard reevaluation against the current design basis flood elevations.
Using this comparison, determine whether the design basis flood bounds each reevaluated hazard.Flood Hazard Reevaluation Report 16 135031/14 Rev. 0 (February 10, 2014) P C Each potential flood causing mechanism has been evaluated using present-day methodologies and regulatory guidance.
Details regarding the considerations and outcome of the analyses regarding each flood causing mechanism are presented in the following sections.3.3.1 Local Intense Precipitation Sections 3.3.1.1 through 3.3.1.4 address the effects of LIP on the local area of the WCGS site.The HHA diagram for LIP flooding is presented in Figure 3-1.3.3.1.1 Local Intense Precipitation Rainfall NUREG/CR-7046 (NRC, 2011) states that "Local Intense Precipitation is a measure of the extreme precipitation at a given location." The LIP is "deemed equivalent to the 1 hr, 2.56-km 2 (1-mi 2) PMP at the location of the site" (NRC, 2011).For the WCGS site, an update of the LIP analysis was completed in January 2013, as described in USAR Change Request 2013-050 (WCNOC, 2013b). This LIP calculation uses the most up-to-date Hydrometeorological Report (HMR) applicable to the site, HMR No. 52 (National Weather Service [NWS], 1982). A hyetograph is established from the resulting rainfall depth calculated using the HMR No. 52 methodology.
The hyetograph subdivides the LIP distribution into five-minute intervals over a 6-hr duration, with the highest amount of rainfall falling within the first hr, as determined by using HMR No. 52 methodology.
The resulting 1-hr, 1-mi 2 LIP for the WCGS is 19.0 in. The cumulative 6-hr LIP is 28.79 in. This serves as the storm event from which local flooding within the powerblock area was evaluated.
The cumulative 6-hr LIP rainfall depth is compared to the USAR Change Request, which also utilizes HMR No. 52 methodology (WCNOC, 2013b).3.3.1.2 Effects of Local Intense Precipitation In accordance with the guidance presented in NRC NUREG/CR-7046 (NRC, 2011), the considerations addressed in the analysis of flooding resulting from LIP were:* Depth of Flooding* Duration of Flooding* Maximum Velocities
- Hydrodynamic and Hydrostatic Loads Flood Hazard Reevaluation Report 17 135031/14 Rev. 0 (February 10, 2014)
.Sedimentation
- Debris Loading Each of these considerations was evaluated based on the results of a detailed two-dimensional (2D) flood routing model that was developed for the WCGS site. This model, FLO-2D Pro (FLO-2D, 2012), represented all the topographical and man-made features (i.e., buildings, tanks, and structures) that significantly affect runoff at the WCGS site. The FLO-2D model represented the plant configuration as of February 2013.The output of the FLO-2D model includes water surface elevations, water depths., maximum water velocities, and the duration of flooding.
FLO-2D also computes the hydrostatic and hydrodynamic forces that the floodwater could exert on obstacles (e.g., buildings) within flooded areas. These results from FLO-2D directly address the requirements of NRC NUREG/CR-7046 (NRC, 2011). The potential for sedimentation and debris loading is evaluated outside of FLO-2D, based on FLO-2D output of depths, maximum velocities, and flow directions.
The extent of the FLO-2D model is illustrated in Figure 3-2. The model boundaries were established away from the powerblock area and safety-related SSCs in order to prevent boundary conditions from affecting flood levels evaluated within the powerblock area and to ensure the stability of the model. The FLO-2D domain covered an area of approximately one quarter of a square mile. The southern and western boundaries follow the surrounding roads (Figure 3-2).These roads form drainage divides, making an appropriate place for a model boundary.The eastern boundary of the model domain follows the edge of Wolf Creek Lake, including a narrow portion of the lake around the ESWS pumphouse and then extends north (to include areas that could contribute runoff into the FLO-2D domain). The northern boundary is placed to include areas that could contribute runoff toward the powerblock area.Six cases were simulated for the model area to investigate the effects of flooding from an LIP event: Case 1 was the most conservative, a steady state simulation with no infiltration losses and the VBS blocked (i.e., water is not allowed to flow through spaced between the VBS jersey barriers).
This is in accordance with the HHA method outlined in NRC NUREG/CR-7046 (NRC, 2011).Additionally, a relatively high Manning's roughness coefficient was used for this simulation.
The grid cell size was 15 ft for this simulation.
Flood Hazard Reevaluation Report 18 135031/14 Rev. 0 (February 10, 2014)
- Case 2 was built on the same FLO-2D grid as Case 1. However, the time-varying LIP distribution was applied. The VBS was partially unblocked in this case." Case 3 provided a sensitivity analysis for grid cell size by constructing a model with 20 ft grid cells that is otherwise equivalent to Case 2.* Case 4 was similar to Case 2, but applied lower Manning's roughness coefficients (toward the middle of recommended ranges) than Case 1 through 3." Case 5 was similar to Case 4. However, rainfall infiltration was accounted for using the Curve Number Method." Case 6 was the same as Case 5, except that the Manning's roughness coefficients for Case 6 were assigned based on the lower end of recommended ranges.In accordance with the approach of the HHA method (Figure 3-1), Case 1 was the most conservative case and the subsequent simulations were progressively refined. The results of the FLO-2D modeling show that the steady-state LIP distribution (Case 1) provided the most conservative estimate of flood levels. The other five cases provided similar results with some variations.
Case 6 was the most refined simulation.
The FLO-2D modeling results at buildings and tanks on the powerblock are summarized in Table 3-1. The maximum predicted flood depths for Case 6 are portrayed in Figure 3-2. The maximum predicted water surface elevations were between 1,099.95 ft and 1,100.47 ft adjacent to Seismic Category I buildings.
The greatest water level near safety-related buildings (elevation 1,100.43 ft) would occur next to the Auxiliary and Reactor Buildings (Table 3-1).Potential pathways through which surface water runoff could reach safety-related SSCs include approximately 40 different doors, vaults, and manholes.
Tables 3-2 and 3-3 present the potential pathways evaluated and the resulting flood elevations, duration of flood, and the dynamic and static loads for these pathways for Cases 5 and 6. To reduce any uncertainty associated with the choice of Manning's roughness coefficients, results from Cases 5 and 6 were used together to develop a list of potentially affected plant entrance locations.
Vaults/Hatches 7 through 16 are designed to be watertight, as discussed in the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012). In all simulations (Cases I through 6), floodwater exceeded entrance elevations at several potential flooding pathway locations to Seismic Category I structures.
This flooding was higher than flood levels that are reported in the design basis, which states that water levels during an LIP event do not exceed an elevation of Flood Hazard Reevaluation Report 19 135031/14 Rev. 0 (February 10, 2014.)
1,099.83 ft near safety-related buildings (WCNOC, 2013b). One site feature that significantly affects flood levels near safety-related SSCs is the old railroad track that approaches the east side of the Fuel Building.
The railroad track slows runoff from the east side of the powerblock and causes higher water levels near safety-related SSCs.Wolf Creek Lake is much larger than the area of interest for an LIP event. Therefore, the change in lake level due to an LIP event was evaluated with a hand calculation.
The water level in the lake was increased by 0.32 ft due to an LIP event, resulting in a final lake level of 1,088.32 ft, which is significantly lower than the flood elevation predicted when simulating the flooding effects of PMP in the entire watershed (see Section 3.3.2).The results of the reevaluated flooding event due to LIP are compared against the CLB in Section 4.2.3.3.1.3 Sedimentation and Debris Loading Coincident with Local Intense Precipitation Sedimentation and debris loading are screened out qualitatively as hazards during an LIP event in the powerblock area. This screening is based on the flow depths, flow velocities, and flow directions predicted in the FLO-2D model. Runoff depths and velocities are generally small (Tables 3-2 and 3-3) and do not constitute a credible hazard for sedimentation or debris loading.Additionally, runoff is generally directed away from safety-related SSCs, precluding any impact on the SSCs from sedimentation or debris loading.3.3.1.4 Wind-waves and Run-Up Coincident with Local Intense Precipitation Wave run-up is a process whereby waves can be generated by high wind velocities coincident with large storm events. The wind speed concurrent with the postulated wind-wave analysis is a two-year maximum sustained wind of 38.65 mph, calculated using procedures in the United States Army Corps of Engineers' (USACE) Coastal Engineering Manual (CEM) (USACE, 2008). Ponding depths in the powerblock area did not support the growth of wind-waves because ponding depths are relatively mild (approximately 1 to 2 ft; Figure 3-2). In addition, velocities were generally directed away from safety-related SSCs, preventing waves from reaching safety-related SSCs. Also, tall buildings within the powerblock area block wind. As a result, the various buildings and structures (including the VBS) shorten potential fetch lengths.Flood Hazard Reevaluation Report 20 135031/14 Rev. 0 (February 10, 2014)
The PMF causes higher water levels to occur in Wolf Creek Lake (see Section 3.3.2.2) than for LIP flooding.
Consequently, the effects of wind-waves during the LIP were bounded by the effects of wind-waves during the PMF. Based on these reasons, no further analysis of wind-waves during an LIP event was required.
Run-up from wind-waves in Wolf Creek Lake resulting from the PMF in Wolf Creek watershed is evaluated in Section 3.3.2.2.3.
3.3.2 Flooding in Rivers and Streams River flooding at the WCGS site was evaluated with respect to the Wolf Creek watershed.
The Wolf Creek watershed was identified in the USAR (WCNOC, 2013a, Section 2.4.2.2) as the controlling watercourse for flood protection at the site. Therefore, it is included in the models for river flooding evaluation.
The WCGS lies in the Wolf Creek watershed, which is bordered by the Long Creek watershed to the east and the larger Neosho River watershed to the west and south (Figure 1-2). In the analysis of flooding potential by rivers, the Neosho River and Long Creek watersheds were first screened to estimate the PMF in those watersheds and to determine whether their respective river channels and valleys are capable of containing the maximum flow rates resulting from a PMF.For this assessment, the total areas of the two watersheds were obtained.
NRC Regulatory Guide (RG) 1.59 (NRC, 1977, Appendix B) was followed to estimate peak PMF discharges for those two watersheds, based on the locations of the watersheds and the watershed drainage areas. It was determined that representative watershed cross-sectional areas are capable of containing the PMF peak discharges in those two watersheds.
Therefore, they were screened out as potential sources of flooding risk to the WCGS by PMF, and were not included in the flooding analysis of the Wolf Creek watershed area described in Section 3.3.2.2.NRC NUREG/CR-7046 (NRC, 2011) prescribes a methodology for determining the PMF based on the HHA method (Figure 3-3). As stated in NRC NUREG/CR-7046 (NRC, 2011), "The hierarchical hazard assessment
[HHA] is a progressively refined, stepwise estimation of site-specific hazards that evaluates the safety of SSCs with the most conservative plausible assumptions consistent with available data." The HHA method starts with the most conservative simplifying assumptions that maximize the hazards for the probable maximum event. If the most conservative assumptions do not result in site inundation, no further flood hazard assessment is required.
However, if the flood level of an assessed hazard may adversely affect any safety-related SSC, more refined hazard assessments are performed using site-specific data to Flood Hazard Reevaluation Report 21 135031/14 Rev. 0 (February 10, 2014) demonstrate whether SSCs are adequately protected from the adverse effects of severe floods (NRC, 2011).For the river flooding analysis, the Wolf Creek watershed was divided into five subbasins (Figure 3-4), which is consistent with the methods outlined in NRC NUREG/CR-7046 (NRC, 2011) for subbasin delineation and composite curve number evaluation.
Subbasins 1 through 3 represented watersheds upstream of Wolf Creek Lake. Part of Subbasin 4 represented the land from which runoff reaches Wolf Creek Lake directly.
Subbasin 5 represented the southern portion of the watershed that drains directly into Wolf creek downstream of the Wolf Creek Lake Dam. The delineated watershed ended at the confluence of Wolf Creek and the Neosho River.Subbasin 5 was delineated to model potential backwater effects from the Neosho River.The PMP for the Wolf Creek watershed was calculated using the USACE's HMR52 computer program (USACE, 1987), as described in Section 3.3.2.1.A watershed hydrologic response model (HEC-HMS) was developed to compute runoff hydrographs and runoff volumes for each subbasin for the PMP event (Section 3.3.2.2.1).
A stream course model (HEC-RAS) was then used to compute flood levels at representative points within the Wolf Creek watershed using the runoff rates from the HEC-HMS model (Section 3.3.2.2.2).
3.3.2.1 Probable Maximum Precipitation for Wolf Creek Watershed The PMP is "a deterministic estimate of the theoretical maximum depth of precipitation that can occur at a time of year over a specified area" as defined in NRC NUREG/CR-7046 (NRC, 2011).The PMP is estimated to determine the Probable Maximum Storm (PMS) event that generates the maximum direct runoff (or peak discharge) from the Wolf Creek watershed.
The HMR52 program is used to compute the PMP. The 72-hr duration cumulative rainfall is computed to be 36.70 in (Figure 3-5), per the guidance of NRC NUREG/CR-7046 (NRC, 2011).The maximum rainfall occurs at approximately 39 hrs after the beginning of the rainfall event.3.3.2.2 Probable Maximum Flood for Wolf Creek Watershed The river flooding for Wolf Creek watershed was performed using two different software packages.
The HEC-HMS modeling software was initially used to simulate a PMP storm in the Flood Hazard Reevaluation Report 22 135031/14 Rev. 0 (February 10, 2014)
Wolf Creek watershed and to calculate PMF flow rates emanating from each subbasin during the PMP event. Five cases were simulated and the results of each simulation are described in Section 3.3.2.2.1.
The HEC-RAS modeling software was used to evaluate water levels associated with the PMF in the Wolf Creek watershed.
Ten simulations were performed to evaluate the effects of a PMP event on the flood depths, duration, and average flow velocities in the watershed and Wolf Creek Lake. Cases 1 through 5 were run as steady-state simulations.
Case 6 was a more refined model, and represented a non-steady (i.e., transient) simulation of a PMP storm event and the resulting PMF in the watershed.
The results of these simulations are presented and discussed in Section 3.3.2.2.2.
The HEC-RAS Case 6 model results were considered to be the most refined modeling results of river flooding in this reevaluation per the HHA approach (NRC, 2011).The Case 6 HEC-RAS model was also used to evaluate wind-wave run-up (Section 3.3.2.2.3) and to calculate hydrostatic forces on the ESWS pumphouse (Section 3.3.2.2.3).
The effects of partially blocked spillways of the Wolf Creek Lake Dam by debris (Cases 7 through 9) and sedimentation in the lake (Case 10) are presented and discussed in Sections 3.3.2.2.4 and 3.3.2.2.5.
3.3.2.2.1 Water Level Due to Probable Maximum Flood Using HEC-HMS Model To evaluate the PMF for the Wolf Creek watershed, HEC-HMS modeling software was used to perform the first level of modeling.
The HEC-HMS model was set up using the five subbasins delineated for the watershed (Figure 3-4) and the PMP event (Figure 3-6). Physical characteristics of the five subbasins are listed in Table 3-4. Wolf Creek Lake was part of Subbasin 4. Subbasin 5 was included in the model to evaluate potential backwater effects that could occur downstream of Wolf Creek Lake. The HEC-HMS model was calibrated before running the PMF simulations.
Five different variations of the model input values and/or model conditions were utilized to create five different HEC-HMS cases, which are summarized in Table 3-5. The HEC-HMS model (Figure 3-6) was run for an eight-day period of time to capture the full effects of the PMF event on Wolf Creek Lake.The cases for the HEC-HMS model were based on the criteria documented in NRC NUREG/CR-7046 (NRC, 2011, Appendix B). Case I was the most unrefined case and the other cases are Flood Hazard Reevaluation Report 23 135031/14 Rev. 0 (February 10, 2014)PCk_.(
more refined. For Cases 3 through 5, the nonlinearity effect during the PMP event was taken into consideration by reducing the lag time by 33 percent and increasing the resulting peak discharge.
As stated in NRC NUREG/CR-7046 (NRC, 2011, Section 3.3.2), the recommended adjustments are "a 5-to-20-percent increase for the peak discharge and a 33-percent reduction in the lag time." Increasing the peak discharge by 20 percent resulted in a higher discharge than the discharge for Case 1 (the most conservative case). Therefore, a five percent increase in the peak discharge (i.e., the lower range suggested in NRC NUREG/CR-7046
[NRC, 2011 ]) was applied in Cases 3 through 5.The maximum water level predicted in Wolf Creek Lake (1,095.3 ft) resulted from the Case I model run, as expected because Case 1 is a steady-state simulation.
The results of Case 5 are considered to be the most refined of the HEC-HMS model runs. The hydrograph of the lake level for HEC-HMS Case 5 model run is presented in Figure 3-7. The Case 5 flow rates computed for each subbasin were used as input values for the HEC-RAS modeling, presented in Section 3.3.2.2.2.
3.3.2.2.2 Water Level Due to Probable Maximum Flood Using HEC-RAS Model In order to refine the flood analysis, HEC-RAS version 4.1 (USACE, 2010b) was used to simulate rainfall and runoff on Wolf Creek and Wolf Creek Lake. HEC-RAS can represent steady state and unsteady-state conditions accurately, as necessary for this reevaluation.
HEC-RAS is also used in NRC NUREG/CR-7046 (NRC, 2011) in examples similar to those encountered in the Wolf Creek watershed.
The purpose of the HEC-RAS model was to produce a more refined estimated of peak water level in Wolf Creek Lake during the PMF event and to evaluate the potential impact to flood levels in the lake if the spillway of the Wolf Creek Lake Dam was partially blocked by debris.The calibrated HEC-RAS model (Figure 3-8) included:* A reach representing Wolf Creek upstream of Wolf Creek Lake (i.e., Upper Reach)* Wolf Creek Lake* Wolf Creek Lake Dam* A reach representing Wolf Creek downstream of Wolf Creek Lake (i.e., Lower Reach)Flood Hazard Reevaluation Report 24 135031/14 Rev. 0 (February
- 10. 2014)
Ten HEC-RAS simulations (see Table 3-5) were performed to address the following NRC requirements:
- Flood levels* Flood duration* Flow velocities
- Debris loading and blockage of the flow* Sedimentation HEC-RAS Cases 1 through 6 addressed the level, duration, and velocities of the PMF flood.Cases 7 through 9 addressed debris loading and blockage of the spillways of the Wolf Creek Lake dam. Case 10 addressed sedimentation in Wolf Creek Lake.A diagram of the HEC-RAS model and the channel cross-sections created within the model area is presented in Figure 3-8. Wolf Creek Lake was represented as a storage area and the Wolf Creek Lake Dam was represented as an inline structure in the HEC-RAS model. The elevation-storage information for Wolf Creek Lake was obtained from the Bathymetric Survey of Wolf Creek Reservoir (Coffey County Lake), Coffey County, Kansas (KBS, 2010).The boundary conditions used in the HEC-RAS model setup included inflows, storage area initial conditions, and upstream and downstream slopes. Initial lake levels were set at, or just above, the lowest spillway crest elevation.
A normal flow condition was specified at the downstream ends of the model reaches. The stream slopes associated with this normal flow condition were set in the model using the topographic elevations along the last two downstream cross-sections.
A total of ten numerical simulations were conducted using the calibrated HEC-RAS model (Table 3-5). HEC-RAS Cases 1 through 5 used the peak flow rates from HEC-HMS Cases 1 through 5 as input values. These cases were run under steady-state conditions.
HEC-RAS Case 6 was run as an unsteady (i.e., transient) model, which is more realistic and more refined than the first five cases. The hydrograph of water level in the lake resulting from HEC-RAS Case 6 is presented in Figure 3-7. The peak water level in Wolf Creel Lake for Case 6 was 1,093.57 fi, which did not exceed the capacity of the spillways.
Flood Hazard Reevaluation Report 25 135031/14 Rev. 0 (February 10, 2014) 3.3.2.2.3 Wind-waves and Run-Up Coincident with Probable Maximum Flood Wave run-up associated with maximum flooding in the Wolf Creek Lake is evaluated and discussed in this subsection.
Wave run-up is a process whereby waves can be generated by high wind velocities coincident with storm events. Wave run-up is evaluated using procedures outlined in the USACE's CEM (USACE, 2008) at the following locations:
- Wolf Creek Lake Dam* Wolf Creek Lake shoreline (near the WCGS site)* Intake structure of the ESWS pumphouse According to the USACE CEM (USACE, 2008), "Fetch is defined as a region in which the wind speed and direction are reasonably constant." The longest fetch was determined for critical locations along the Wolf Creek Lake Dam, the Wolf Creek Lake shoreline, and at the intake structure of the ESWS pumphouse.
These locations and the fetch paths and fetch lengths used to calculate wave run-up are shown in Figure 3-9. These fetch lengths were used in the wave run-up analysis.
The Wolf Creek Lake Dam fetch was defined as the longest fetch that approaches the dam (Figure 3-9). For the Wolf Creek Lake shoreline, the fetch was defined at a critical location where the longest fetch approached nearest the WCGS site (Figure 3-9). For the intake structure of the ESWS pumphouse, Fetch I was chosen as the most feasible fetch.To perform the wind-wave analysis, the two-year return period maximum sustained wind (MSW) speed was calculated, using procedures defined in the USACE CEM (USACE, 2008).The two-year MSW speed was calculated to be 38.65 mph. Once the fetch and MSW were computed, the sustained overland wind speed (MSW) was converted to an overwater wind speed, because the wind is traveling over a body of water (i.e., Wolf Creek Lake). The overwater wind speed (46.38 mph) was calculated using procedures outlined in the USACE CEM (USACE, 2008).The peak PMF water level in Wolf Creek Lake (1,093.54 fi) obtained from the HEC-RAS Case 6 model (the most refined case) was used as the antecedent water level (or stillwater level) for the wind-wave analysis.
Equations from the USACE CEM (USACE, 2008, Figure 11-2-20) were used to calculate significant wave height and peak period.Flood Hazard Reevaluation Report 26 135031/14 Rev. 0 (February 10, 2014)
There are two general categories of run-up equations:
- 1. Equations for run-up on structures (steeper slopes)2. Equations for run-up on beaches (shallower slopes)Consequently, the wave run-up equations utilized for the intake structure of the ESWS pumphouse and for the Wolf Creek Lake Dam and the shoreline of Wolf Creek Lake differed.However, both run-up equations are for run-up levels exceeded by only two percent of the incident waves. The two-percent run-up (R 2%) equations were used because this is recommended in the USACE CEM (USACE, 2008, Part II Chapter 4). Field measurements of run-up have shown that the two percent run-up equation in the USACE CEM conservatively overestimates run-up by a factor of two, but is roughly an upper envelope of the data scatter (USACE, 2008, p.11-4-18).The equation recommended in the USACE CEM (USACE, 2008) for beaches was applied for computing the run-up level on the Wolf Creek Lake shoreline and the Wolf Creek Lake Dam, because the slopes where run-up occurs are relatively mild. The standard run-up equation for two percent run-up level beaches (USACE, 2008, Equation 11-4-29) was used for this analysis.The final computed wave run-up computed for the reevaluation were 7.01 ft, 0.83 ft, and 4.89 ft, resulting in elevations of 1,100.55 ft, 1,094.37 ft, and 1,098.43 ft for the Wolf Creek Lake Dam, Wolf Creek Lake shoreline, and the ESWS pumphouse, respectively.
The final wave run-up level on the Wolf Creek Lake Dam exceeded the crest of the dam of 1,100 ft (WCNOC, 2013a).However, the dam is not a safety-related structure.
In addition, the upstream slope of the Wolf Creek Lake Dam has riprap to protect against erosion from wind-wave activity (WCNOC, 2013a).The maximum run-up level for the Wolf Creek Lake shoreline did not exceed the design basis flood elevation of 1,095 ft (WCNOC, 2013a, Section 2.4.3.5).
The maximum estimated run-up level for the intake structure of the ESWS pumphouse did not exceed the design basis flood elevation of 1,100.2 ft (WCNOC, 2013a, Section 2.4.10). Therefore, the maximum anticipated wave run-up elevations at the Wolf Creek Lake shoreline and the ESWS pumphouse did not adversely affect any SSCs at the WCGS site.Flood Hazard Reevaluation Report 27 135031/14 Rev. 0 (February 10, 2014)
An evaluation of the effects of baffle dikes A and B and the breakwater (near the ESWS pumphouse) (Figure 3-9) on waves and wave run-up was also performed.
Baffle dikes A and B did not affect the fetches or wave set-up for the Wolf Creek Lake Dam, the Wolf Creek Lake shoreline, or the inlet structure of the ESWS pumphouse.
Near the ESWS pumphouse, the lake depth was shallow and the breakwater located near the ESWS pumphouse would cause waves to break even though it is submerged due to the PMF water level (the antecedent water level). As detennined from light detection and ranging (LiDAR) data, the top of the breakwater was approximately 1,092 ft. The antecedent lake water level was 1,093.54 ft. Therefore, any waves approaching the ESWS pumphouse and intake structure would break at the breakwater and reach the intake structure of the ESWS pumphouse with a smaller wave height than the wave height that approached the breakwater.
3.3.2.2.4 Effects of Spillway Blockage on the Maximum Wolf Creek Lake Level HEC-RAS Cases 7 through 9 considered varying levels of blockage of the spillways following the HHA approach (50 percent, 20 percent., and ten percent blockage of the service spillway, respectively, and ten percent of the auxiliary spillway) to provide a sensitivity analysis on the percent blockage of the spillways (Table 3-5) per NRC JLD-ISG-2013-01 (NRC, 2013b).Simulated peak water levels for Cases 7 and 8 exceeded the design basis elevation of 1,095.0 ft.However, Cases 7 and 8 were sensitivity cases and were not considered realistic due to the dimensions of the spillways (given in Section 2.1.1.3).
Case 9 did not exceed the design basis elevation of 1,095.0 ft.The unsteady flow case (Case 6, the most refined case) was used as the final case that was compared against the USAR because the design basis did not block the spillways and the case was considered the most realistic case due to the dimensions of the spillways and the history of debris production in the watershed.
The Case 6 peak water level of 1093.57 ft did not exceed the design basis elevation of 1,095.0 ft (WCNOC, 2013a, Section 2.4.3.5).3.3.2.2.5 Effects of Sedimentation in Wolf Creek Lake A HEC-RAS model run (Case 10) was performed to evaluate what effect sedimentation in Wolf Creek Lake might have on the water level in the lake during a PMF event. HEC-RAS Case 6 was used as the basis for this analysis.
In Case 10, the Wolf Creek Lake storage was adjusted to represent conditions after a sediment inflow volume of 1,080 acre-ft over 40 years. The predicted Flood Hazard Reevaluation Report 28 135031/14 Rev. 0 (February 10, 2014) maximum water level in the lake was 1,093.54 ft, which was the same elevation as determined for Case 6.3.3.2.2.6 Combined-Effects Flood Many flood-causing mechanisms can occur concurrently because they are not truly independent.
For example, floods from precipitation events may occur concurrently with an antecedent snowpack and wind-induced waves. The impact of a simultaneous occurrence of flood causing mechanisms was defined by the American Nuclear Society (ANS), ANSI/ANS-2.8-1992 (ANS, 1992), and later defined as "combined effect flooding" in NRC NUREG/CR-7046 (NRC, 2011).Three alternative combinations of flood causing events for precipitation floods are described in Section 9.2.1.1 of ANSI/ANS-2.8-1992 (ANS, 1992): Alternative I 1. Mean monthly (base) flow 2. Median soil moisture 3. Antecedent or subsequent rain: the lesser of (1) rainfall equal to 40 percent of PMP or (2)a 500-year rainfall 4. PMP 5. Two-year wind speed applied in the critical direction Alternative II 1. Mean monthly (base) flow 2. Probable maximum snowpack 3. Coincident 100-year snow season rain 4. Two-year wind speed applied in the critical direction Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)29 FeZ Alternative III 1. Mean monthly (base) flow 2. 100-year snowpack 3. Coincident snow season PMP 4. Two-year wind speed applied in the critical direction Alternative I analysis represents a flood based on summer meteorological conditions (maximum PMP). Alternative II and III analyses are based on winter conditions.
Due diligence requires a preliminary evaluation of the Probable Maximum Snow Accumulation (PMSA) and winter season PMP depths before Alternative II and III combined events can be screened out. The calculations to assess the impact of winter hydrometeorologic loadings show that the PMSA combined with a 100-year winter rainfall event (with total snowpack melting and no water losses, Alternative II) produced total runoff depths of 23.62 in to 26.94 in for Cottonwood Falls and Osage City, respectively.
This amount was significantly less than the PMP rainfall depth (36.70 in) calculated in Section 3.3.2.1. The calculation of an April PMP falling on a 100-year snowpack (Alternative III) produced a total water depth of 34.7 in, which was also less than the PMP rainfall depth (36.70 in) calculated in Section 3.3.2.1. As a result, the conservative estimates of combined snowmelt-rainfall runoff in winter months (Alternatives II and III) were screened out. Alternative I was deemed the most conservative combined-effects alternative to evaluate.3.3.2.2.6.1 Evaluation of Combined-Effects Flooding Using ANS Alternative I The HHA approach is followed for combined-effects flooding analysis, as shown in Figure 3-10.Two antecedent rain conditions prior to the PMP were evaluated in the flood hazard reevaluation:
- A 72-hr rainfall event with a total depth of 40 percent of the PMP* A 24-hr 500-year rainfall event The 40 percent PMP event was approximated by multiplying all PMP ordinates by a constant factor of 0.4. A 24-hr duration was used for the 500-year storm to be consistent with standard Flood Hazard Reevaluation Report 30 135031/14 Rev. 0 (February 10, 2014) industry practice.
The Soil Conservation Service (SCS) unit rainfall curves are typically set up for 24-hrs (Chow et. al, 1988, p. 461). Following the procedures laid out in NRC NUREG/CR-7046 (NRC, 2011), the storm with the lesser impact on peak discharge was utilized for combined-effect modeling.
After evaluating the two possible storm events, 24-hr 500-year rainfall event was utilized as the rainfall event preceding the PMP for combined-effect modeling.The combination of 500-year rainfall and PMP were then used to create a new rainfall hyetograph for modeling.The new storm hyetograph was used as input to the HEC-HMS Case 5 model. The Case 5 HEC-HMS model was run with the 500-year/PMP hyetograph combination to obtain the subbasin hydrographs for input to the HEC-RAS model.The HEC-RAS Case 6 model (Section 3.3.2.2.2) was then used to model the unsteady (transient) streamflow in the creek and water level in Wolf Creek Lake. The HEC-RAS combined-effects simulation yielded a maximum predicted water level in Wolf Creek Lake of 1,094.63 ft. This water level was higher than the predicted lake water level for the PMP alone, but was still less than the design basis flood elevation of 1,095 ft (WCNOC, 2013a, Section 2.4.3.5).3.3.2.2.6.2 Wind-waves and Run-up Coincident with Combined-Effects Flood The combined-effects flood level included maximum wave run-up calculated at key locations.
The maximum wave run-up computed for the Wolf Creek Lake Dam, the shoreline at the WCGS, and the ESWS pumphouse were 7.01 ft, 0.83 ft, and 4.89 ft, respectively (Section 3.3.2.2.3).
Thus, the combined-effects lake water levels of 1,101.64 ft, 1,095.46 ft, and 1,099.52 ft were computed for those three locations, respectively.
The maximum water surface elevation along the shoreline nearest to the powerblock, including the impact of wave action was 1,095.46 ft., providing a freeboard of 4.04 ft, with respect to the plant grade elevation of 1,099.5 ft (Figure 3-11), and was bounded by the design basis flood elevation including run-up of 1,095.8 ft (WCNOC, 2013a, Table 2.4-16).The maximum water surface elevation at the ESWS pumphouse, including the impact of wave action was calculated as 1,099.52 ft, providing a freeboard of 0.48 ft, with respect to the top of grade-level slab elevation of 1,100 ft and was bounded by the design basis flood elevation for the pumphouse of 1,100.2 ft (WCNOC, 2013a, Section 2.4.10).Flood Hazard Reevaluation Report 3 1 135031/14 Rev. 0 (February 10, 2014) 3.3.2.2.6.3 Effects of a Combined-Effects Flooding on Debris Loads If debris exists in Wolf Creek Lake, it was expected that the debris would be small (e.g., tree branches, etc.) and would not adversely affect the WCGS site because floodwaters do not rise to the plant grade elevation of 1,099.5 ft, and would not adversely affect the Wolf Creek Lake Dam due to the size of debris. It was expected that debris would not adversely affect the ESWS pumphouse because the intake structure is equipped with trash racks, which protect the ESWS pumphouse from debris (WCNOC, 2013a, Section 2.4.7.2).
Additionally, the baffle dikes and breakwater provide a defense for the ESWS pumphouse against debris that could be floating in Wolf Creek Lake due to a combined-effects flooding event. In addition, the flow of the floodwater would be southerly towards the main dam, not directed northeasterly around the WCGS site peninsula to the ESWS pumphouse.
3.3.3 Dam Breaches and Failures The potential flooding of the WCGS site due to breaches and failures of dams located upstream of the site was evaluated.
Except for the Wolf Creek Lake Dam, no other dams were listed in the USACE National Inventory of Dams (NID) database (USACE, 2013a) for the Wolf Creek watershed.
A total of 322 dams were been identified in the Neosho River watershed upstream and downstream of the Wolf Creek watershed.
These are shown in Figure 3-12.The evaluation of dam failure was performed using a quantitative assessment that screened out flooding hazards due to a dam breach using the storage level, distance from the WCGS site, and head differential.
The quantitative assessment utilized the Volume Method outlined in the NRC JLD-ISG-2013-01 guidance for dam failure analysis, "Guidance for Assessment of Flooding Hazards Due to Dam Failure" (NRC, 2013b). This assessment includes the following steps: 1. Obtain a list of dams from the USACE NID (USACE, 2013a).2. Identify which dams are "inconsequential" or downstream using watershed boundaries (USGS, 2013) and other sources of information (e.g., the Kansas Department of Agriculture
[KDA]) (KDA, 2011).3. Use the Volume Method to identify "noncritical" and "potentially critical" dams. The Volume Method outlined in Section 3 of NRC JLD-ISG-2013-01 (NRC, 2013b) is a simplified dam failure screening analysis.Flood Hazard Reevaluation Report 32 135031/14 Rev. 0 (February 10, 2014)
The Volume Method (i.e.., the "Screening" step presented in Figure 3-13) was used because it is the most conservative of the simplified methods listed in Section 3 of NRC JLD-ISG-2013-01 (NRC, 2013b). Figure 3-14 provides a more detailed illustration of steps within the Volume Method. Other more refined methods are available should the Volume Method identify any"potentially critical" dams.NRC JLD-ISG-2013-01 (NRC, 2013b) classifies dams as "inconsequential," "noncritical," or"potentially critical," as follows: " "Inconsequential" dams: "Dams identified by Federal or State agencies as having minimal or no adverse failure consequences beyond the owner's property may be removed from further consideration in the Recommendation 2.1 reevaluation.
Dams owned by licensees may not be removed. Other inconsequential dams may be removed with appropriate justification (e.g., if they can be easily shown to have minimal or no adverse downstream failure consequences)" (NRC, 2013b, p. 3-2)." "Noncritical" dams are dams that have little impact on flooding at the NPP site using a simplified analysis (NRC, 2013b, p. 1-3) (e.g., flood elevations below plant grade).* "Potentially critical" dams include all other upstream dams (NRC, 2013b, p.1-3).The Volume Method analysis represented a condition with the total upstream reservoir storage volume simultaneously transferred to the WCGS site without attenuation.
As part of the Volume Method, the volume of water required for antecedent flood conditions within a reach was first removed from the volume available for storing water from the upstream reservoirs.
NRC JLD-ISG-2013-01 (NRC, 2013b) recommends using the antecedent 500-year return period flood flow (RPFF).The Volume Method was used to determine the potential for flooding above the WCGS plant grade elevation of 1,099.5 ft (WCNOC, 2013a, Section 2.4.3.5).
NRC JLD-ISG-2013-01 (NRC, 2013b) uses the term "plant grade" in reference to simplified modeling approaches to screen flooding that result from the failure of all dams in the watershed upstream of the site. For this application, flooding above plant grade would require that backwater from flooding on the Neosho River would overtop the Wolf Creek Lake Dam. For debris and sediments along the Neosho River to enter the Wolf Creek Lake, flood levels along the Neosho River would need to exceed the service spillway crest elevation (i.e., 1,088 ft) of the Wolf Creek Lake Dam.Flood Hazard Reevaluation Report 33 135031/14 Rev. 0 (February 10, 2014)
The following steps were performed to evaluate the potential for flooding due to upstream dam failure at the WCGS site: 1. Topographic data was compiled and processed.
- 2. A list of dams within the Neosho River watershed was obtained.
The NID database included a total of 322 dams (Figure 3-12), including 91 downstream dams within the watershed area. The remaining 231 upstream dams have a total volume of 1,633,036 acre-ft.3. Downstream and "inconsequential" dams were screened out.4. Antecedent flow conditions along the Neosho River were estimated using the FEMA-reported 500-year RPFF at the City of Burlington (FEMA, 1996). The FEMA Flood Insurance Study (FIS) for the City of Burlington (FEMA, 1996) reported a 500-year RPFF for the Neosho River between the City Dam (upstream Corporate City Limits) and the downstream Corporate City Limits of 290,000 cfs, and provides a 500-year Return Period Flood Elevations (RPFE) profile along the 2.1-mile reach with floodwater elevations ranging between 1,022.5 ft to 1,026.3 ft.5. A steady-state HEC-RAS model was setup to represent the Neosho River firom 334.4 to 343.3 river miles upstream of the Neosho River mouth.6. The HEC-RAS model was calibrated to the reported 100-year and 500-year RPFE (FEMA, 1996) using the associated 100- and 500-year RPFF as an upstream boundary condition.
- 7. The calibrated HEC-RAS model was run using the proper antecedent flow conditions to compute the associated flood levels and the remaining available storage volumes below plant grade.8. "Noncritical" and "potentially critical" dams were identified.
The available water storage volume near the WCGS site for upstream dams (i.e., reservoirs) was calculated using the Spatial Analyst extension and 3D Analyst extension within ArcGIS. If the available storage cannot accommodate the volume of water stored in the upstream dams, then"potentially critical" dams were identified.
- 9. Potential debris, sediment loading, and waves, were addressed as necessary.
The 500-year RPFE profile along the 2.1 -mile reach with floodwater elevations ranged between 1,022.5 ft to 1,026.3 ft. Adding the volume of water stored in the 231 dams located in the upstream portion of the Neosho River watershed (i.e., 1,633,036 acre-ft) raised the floodwaters up to an elevation of 1,076.7 ft. The flood level of 1,076.7 ft in the Neosho River is less than the topographic ridge that separates the Neosho River from the Wolf Creek watershed.
Therefore, Flood Hazard Reevaluation Report 34 135031/14 Rev. 0 (February 10, 2014) P C floodwaters will not cross over to Wolf Creek Lake. However, floodwaters will flow up Wolf Creek from its confluence with the Neosho River. The dam break analysis shows the maximum backwater elevation to be 22.8 ft below the plant grade elevation and 11.8 ft below the Wolf Creek Lake Dam service spillway.
Therefore, no "potentially critical" dams were identified, using the Volume Method (NRC, 2013b). All dams were either "inconsequential" or"4noncritical." The peak water level with failure of all upstream dams did not reach the Wolf Creek Lake Dam service spillway invert (i.e., 1,088 fi). The peak water level was 22.8 ft below plant grade (i.e., 1,099.5 ft) (Figure 3-15). As a result, no further consideration of debris or sediment at the WCGS site was required as part of the reevaluation analysis.For a 40-mph wind over water, the run-up associated with maximum wave heights was less than one foot (WCNOC, 2013a, Section 2.4.3.6.1).
The maximum water level at the WCGS site with the failure of all upstream dams transferred without attenuation was below the Wolf Creek Lake Dam service spillway invert (i.e., 1,088 ft), providing a "freeboard" of 22.8 ft below plant grade (i.e., 1,099.5 fi) and 11.3 ft below the service spillway invert. Therefore, the potential impacts of wind-wave activity coincident with dam failure were dismissed.
3.3.4 Storm Surge The WCGS site is located more than 1,000 miles from the Pacific Ocean, approximately 935 miles inland from the Atlantic Coast, and approximately 600 miles inland from the Gulf of Mexico (USGS, 2013). The site is located adequately inland such that hurricanes and a Probable Maximum Hurricane (PMH) will not be a source of a potential flood hazard. Therefore, further consideration to storm surge flooding outlined in NRC NUREG/CR-7134 and NRC JLD-ISG-2012-06 (NRC, 2012b; 2013c) was not applicable to the WCGS site.Storm surge due to Probable Maximum Wind Storms (PMWS) and squall lines was also not applicable to the WCGS site, because the site is not located on the Great Lakes, as is discussed in ANSI/ANS-2.8 (ANS, 1992) and NRC JLD-ISG-2012-06 (NRC, 2013c). Therefore, according to NRC JLD-ISG-2012-06 guidance, determination of hydrostatic and hydrodynamic forces, debris, and water-borne projectiles, and effects of sediment erosion or deposition due to storm surge was not necessary because safety-related SSCs at the WCGS site were not affected from storm surge flood levels (NRC, 2013c).Flood Hazard Reevaluation Report 35 135031/14 Rev. 0 (Februar'
- 10. 2014) 3.3.5 Seiche A seiche is defined as "an oscillation of the water surface in an enclosed or semi-enclosed body of water initiated by an external cause" in NRC NUREG/CR-7046 (NRC, 2011). To account for the potential of a seiche due to meteorological effects, the seiche periods for the length and width of Wolf Creek Lake were computed.
In order to compute the seiche periods, the lake was assumed to be a rectangular basin with an averaged depth of the lake, which follows the methodologies outlined by Dean and Dalrymple (Dean and Dalrymple., 1991).Using the Dean and Dalrymple methodology for seiche periods for Wolf Creek Lake, the resulting seiche periods computed were 6.5 minutes for the lake's length and 38.7 minutes for the width of the lake. Seiching at these periods could only occur if an oscillatory force (pressure or wind) excited lake oscillations at one of the seiche periods. The periods calculated for lake oscillation could not be continuously forced by changes in overall weather conditions because these conditions typically fluctuate at time scales of 1 hr or more (Peinke et. al, 2004). Therefore, seiches due to meteorological effects are dismissed as a source of flooding at the WCGS.Seiches can also occur due to seismic effects and landslides.
The WCGS site is situated in an area of low seismic hazards according to the USGS (USGS, 2012c). The occurrence of landslides in the area adjacent to Wolf Creek Lake is not considered possible due to the low relief of topographic features in the vicinity of the WCGS site. Therefore, potential seismic events and landslide were not expected to cause seiches on Wolf Creek Lake and, therefore, cause flooding at the WCGS site. Additionally, according to NRC JLD-ISG-2012-06 guidance, determination of hydrostatic and hydrodynamic forces, debris and water-borne projectiles, and the effects of sediment erosion or deposition due to seiche were not necessary because safety-related SSCs at the WCGS site are not affected from seiche flood levels (NRC, 2013c).3.3.6 Tsunami Following the guidance outlined in NRC NUREG/CR-6966 and NRC JLD-ISG-2012-06 (NRC, 2008; 2013c), a review was conducted of the National Oceanic and Atmospheric Administration's (NOAA) historic tsunami records that impacted the east coast of the United States and the Gulf of Mexico. The maximum historic water levels due to historic tsunami run-up recorded along the east cost of the United States and the Gulf of Mexico was 19.7 fi, which occurred at Daytona Beach, Florida, in 1992 (NOAA, 2013). Daytona Beach, Florida, is approximately 1,050 miles from the WCGS site (USGS, 2013), and the closest shoreline that Flood Hazard Reevaluation Report 36 135031/14 Rev. 0 (February 10, 2014) could be subjected to tsunami flooding is approximately 600 miles away. NRC NUREG/CR-6966 indicates that if regional screening identifies that the site region is not subject to tsunamis, no further analysis for tsunami hazards is required (NRC, 2008). Additionally, according to NRC JLD-ISG-2012-06 guidance (NRC, 2013c), the determination of the hydrostatic and hydrodynamic forces, debris and water-borne projectiles, and the effects of sediment erosion and deposition were not considered because the safety-related SSCs of the WCGS site were not subject to tsunami flood levels (NRC, 2013c).3.3.7 Ice-Induced Flooding Ice-induced flooding analysis for the WCGS site included an assessment of ice jams, frazil ice, and ice thickness.
Review of the current Ice Jams Database (USACE, 2013b) indicated that only one ice jam has been recorded in the Neosho River Basin on February 1949, near the city of Council Grove, Kansas. Council Grove is approximately 50 miles northwest of the WCGS site, and upstream of the John Redmond Reservoir.
Potential ice jams upstream of the John Redmond Reservoir would not adversely affect the WCGS site because any potential floodwaters occurring due to release from the ice jam would be mitigated or dissipated before entering, or within, the John Redmond Reservoir or one of the other flood control facilities on the Neosho River.Additionally, the Neosho River is separated from the WCGS site by a topographic ridge (USGS, 2012b).In the event of an ice jam occurring on the Neosho River, at the confluence of Wolf Creek, downstream of the John Redmond Reservoir (although there is no record of such an ice jam), backwater effects would not affect the WCGS site as the confluence is over six miles from the WCGS site. Furthermore, no historical ice jams have been recorded in the Wolf Creek watershed (USACE, 2013b).Frazil ice can only occur in supercooled turbulent waters (USACE, 2002). Supercooled water is water that is cooled below the freezing point without freezing.
As presented in the USAR, frazil ice has the potential to form in Wolf Creek Lake when the water becomes supercooled, creating the potential to block the ESWS intake trash racks (WCNOC, 2013a). Supercooling in Wolf Creek Lake requires a large heat loss associated with low air temperatures, clear water, and clear nights (WCNOC, 2013a). Additionally, because the cooling heat transfer is at the surface of the water, strong winds are needed to mix supercooled water to a depth low enough to be drawn into the intake (WCNOC, 2013a).Flood Hazard Reevaluation Report 37 135031/14 Rev. 0 (February 10, 2014) P C In January 1996, the Train A ESWS intake trash racks became completely blocked by frazil ice (NRC, 1996). The frazil ice blockage was effectively cleared by sparging the trash racks with air (NRC, 1996). At the time of the blockage of the trash racks by frazil ice in January 1996, the ESWS warming flow was insufficient to prevent frazil ice from forming at the Train A trash racks (NRC, 1996). According to the current version of the USAR, WCGS has put in place a system to mitigate future potential frazil ice formation by diffusing warmed water in front of the ESWS intake trash racks (WCNOC, 201'3a). This technique of mixing warmed water with supercooled water is especially effective near water intakes, where the required quantity of warm water can be modest (USACE, 2002).Ice thickness was estimated by an analysis of Freezing Degree Days (FDD), defined as the difference between 32 degrees Fahrenheit
('F) and the average daily air temperature (USACE, 2004). The maximum estimated ice thickness on Wolf Creek Lake, based on the methodologies and equations in the Method to Estimate River Ice Thickness Based on Meteorological Data report (USACE, 2004), was approximately 20.60 in (1.72 ft) using the data from the Emporia Municipal Airport weather station, and approximately 19.14 in using data from the John Redmond Lake weather station.The bottom of the intake channel to the ESWS pumphouse is at elevation 1,065 ft, which is 22 ft below the normal operating level (1,087 ft) of Wolf Creek Lake. Thus, the bottom of the conservatively estimated ice thickness of 20.60 in (1.72 ft) would still be approximately 20.28 ft above the bottom of the intake channel to the ESWS pumphouse.
The reevaluation analysis and the design basis (WCNOC, 2013a) screened out ice formation as a potential flood hazard.3.3.8 Flooding Resulting from Channel Migration or Diversion The rivers and creeks in the vicinity of the WCGS site are the Neosho River, Wolf Creek, and Long Creek. A qualitative assessment of the streams and rivers in the vicinity of the WCGS site, in conjunction with the information presented in the USAR (WCNOC, 2013a), indicated that safety-related SSCs at the WCGS site would not be affected by diversion of flows from the Neosho River, Wolf Creek, or Long Creek.This hazard reevaluation also indicated that any potential diversion of cooling water would not adversely affect safety-related SSCs at the WCGS site. The cooling water is provided by Wolf Creek Lake, and the intake channel is protected from potential ice blockage by diffusing warmed water in front of the ESWS intake trash racks (WCNOC, 2013a). The UHS is contained by a Flood Hazard Reevaluation Report 38 135031/14 Rev. 0 (February 10, 2014) F C JZ submerged Seismic Category I dam in Wolf Creek Lake and is fully functional for safe shutdown of the WCGS site. The UHS will provide a sufficient volume of water to safely shut down and maintain shutdown of the WCGS site as long as the sediment volume in the UHS is limited to 130 acre-ft (WCNOC, 2013a, Section 2.4.11.6).
The sources of the makeup water to the cooling lake are Wolf Creek and the Neosho River (WCNOC, 2013a, Section 2.4.8.2).
Significant morphological changes in the Neosho River are not expected to affect the water supply from the John Redmond Reservoir, and Wolf Creek was also not expected to diverge due to the topography in the area.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)39 RZYZZ 4.0 COMPARISON OF CURRENT AND REEVALUATED PREDICTED FLOOD LEVELS Section 4.0 has been prepared in response to Request for Information Item I .c. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide a comparison of current and reevaluated flood causing mechanisms at the site. Provide an assessment of the current design basis flood elevation to the reevaluated flood elevation for each flood causing mechanism.
Include how the findings from Enclosure 4 of this letter (i.e., Recommendation 2.3 flooding walkdowns) support this determination.
If the current design basis flood bounds the reevaluated hazard for all flood causing mechanisms, include how this finding was determined.
4.1 COMPARISON OF CURRENT AND REEVALUATED FLOOD CAUSING MECHANISMS The flood causing mechanisms evaluated under the current design basis in the USAR include the effects of local intense precipitation, probable maximum flood on Wolf Creek Lake, including wave run-up at the site, seismically induced potential dam failure, probable maximum storm surge and seiche flooding, probable maximum tsunami flooding, ice flooding, and channel diversions (WCNOC, 2013a). The flood hazard reevaluation includes the same evaluations of the flooding mechanisms as presented in the current design basis, including a combined-effects flood. Note that the USAR terminology differs from the terminology used in current NRC guidance, but the same mechanisms are evaluated.
The flooding mechanisms, from both the USAR and the reevaluation, are listed in Table 4-1.The conditions under which the flooding analyses were performed and the methods used to perform the analyses were slightly different between CLB analyses and the reevaluation analyses.
The differences are highlighted in Tables 4-1 through 4-4. Table 4-4 focuses on the additional parameters (i.e., flood duration, dynamic loads, debris loading, and sedimentation) that are required to be evaluated since the issuance of NRC Recommendation 2.1.Flood Hazard Reevaluation Report 40 135031/14 Rev. 0 (February 10, 2014) R C 4.2 ASSESSMENT OF THE CURRENT DESIGN BASIS FLOOD ELEVATIONS TO THE REEVALUATED FLOOD ELEVATIONS The current design basis, as presented in the USAR (WCNOC, 2013a), indicates that the site is not affected by flooding.
The WCGS site has a grade elevation of 1,099.5 ft, and a floor elevation of 1,100 ft.Local Intense Precipitation The maximum calculated water level near the safety-related buildings due to the LIP event is 1,099.83 ft (current design basis per USAR change request 2013-050 [WCNOC, 2013b]). During the LIP event, it is conservatively assumed in the design basis that the site drainage system is not functional.
The maximum design water level due to the LIP is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). As a result, the design basis does not include hydrostatic or hydrodynamic forces associated with flooding at safety-related SSCs. However, the design basis does include hydrostatic loads on safety-related structures for groundwater equivalent to plant grade (WCNOC, 2013a). The LIP (1-hr, 1 mi 2) rainfall of 19 in is part of the cumulative six-hour rainfall of 28.79 in used in the design basis. The LIP rainfall is determined using HMR No. 52 (WCNOC, 2013b).The reevaluated on-site ponding levels that result from LIP ranged from approximately 1,099.95 ft up to a maximum of 1,100.47 ft (Table 3-1). These values exceed the design water levels. The LIP rainfall depth used in the reevaluation was equivalent to the current design basis. Therefore, the existing roof loading evaluation considering precipitation rates and accumulation documented in the design basis is bounding.Potential pathways through which surface water runoff could reach safety-related SSCs include approximately 40 different doors, vaults, and manholes.
Tables 3-2 and 3-3 present the potential pathways evaluated and the resulting flood elevations, duration of flood, and the dynamic and static loads for these pathways.
For the most refined simulated conditions (Cases 5 and 6), the maximum flood depth outside of an entrance to a Seismic Category I building on the powerblock (Auxiliary Building pressure door) was approximately 1.13 ft. The associated duration of flooding at this location was 1 hr (above a depth of 0.5 ft, Figure 4-1) with a corresponding Flood Hazard Reevaluation Report 41 135031/14 Rev. 0 (February 10, 2014) maximum velocity of 4.3 ft/s , a maximum hydrostatic force of 40 lb/fl, and a maximum hydrodynamic force of 29 lb/ft.For other doors, hatches, manholes, and vaults for safety-related SSCs, the simulated maximum flood depth was at an ESWS manhole (1.51 ft). The associated duration of flooding at this location was 8.5 hrs (above a depth of 0.5 ft) with a corresponding maximum velocity of 0.8 ft/s., a maximum hydrostatic force of 71 lb/fl, and a maximum hydrodynamic force of 3 lb/ft.The potential for sedimentation and debris loading on safety-related SSCs due to the LIP was screened out qualitatively due to the low flood flow velocities.
In addition, the flood flows were not in directions that would carry sediment from any potential sediment source into the powerblock area. Similarly, debris loading was screened out as a potential hazard for the WCGS site, with the additional basis that flows are shallow and could not carry larger debris objects into the powerblock area.Flooding in Rivers and Streams The normal operating level at the Wolf Creek Lake is 1,087 ft. Snyder's synthetic unit hydrograph was used for the design basis to determine that the peak flow rate for the spillways is 22,845 cfs (WCNOC, 2013a, Section 2.4.3.5) for a sequential flood event with an antecedent standard project flood followed by a PMP, which is analogous to a combined-effects precipitation flood event. The maximum water surface elevation in Wolf Creek Lake (i.e., the pool elevation) due to the design PMF event is 1,095 ft at the plant site, which occurs approximately 158 hrs after the start of the event (WCNOC, 2013a., Figure 2.4-23). The coincident wind-wave activity of the design PMF results in a maximum run-up of 0.8 ft at the plant site shore. The resulting design run-up elevation is 1,095.8 ft when added to the PMF pool elevation (Table 4-3). The design maximum wave run-up elevation on the vertical wall of the intake structure of the ESWS is 1,100.2 ft. The design basis does not include hydrostatic or hydrodynamic load calculations at the ESWS pumphouse associated with lake water levels. In addition, wave loads are not calculated on the ESWS pumphouse in the design basis.In the reevaluation, the simulated outflow from Wolf Creek Lake over the service spillway was 23,021 cfs. The maximum water level in the lake resulting from the PMF was 1,093.54 ft, which occurred approximately 47.5 hrs after the start of the event, and was less than the design value 1 The direction of the flow of the maximum velocity of 4.3 ft/s is away from the Auxiliary Building pressure door.Flood Hazard Reevaluation Report 42 135031/14 Rev. 0 (February 10, 2014) P C (1,095 ft). The shorter duration to the peak water level is not considered a controlling parameter since the reevaluated maximum water level was bounded by the design basis and no procedural actions are required by the site due to increases in lake level due to a PMF. The reevaluated lake levels including wind-generated wave run-up at the WCGS shoreline and the ESWS pumphouse were 1,094.37 ft and 1,098.43 fi, respectively (Table 4-3). The reanalyzed water levels, including wind-waves, were less than the design water levels (1,095.8 ft), which is less than the plant grade elevation (1,099.5 ft). Therefore, hydrodynamic and hydrostatic loads at the plant were not calculated for safety-related structures on the powerblock.
However, hydrostatic loads at the ESWS pumphouse were calculated, and the maximum static loads for the peak simulated water levels was 39,408 lb/ft. This represents a depth integrated force from the stillwater level to the bottom of the ESWS pumphouse (1,058.0 ft).The reevaluation analysis for the river hydraulic model included simulations representing potential debris build-up at the Wolf Creek Lake Dam auxiliary and service spillways.
The potential impact of debris was simulated with ten percent blockage of the auxiliary spillway and 50, 20, and ten percent blockage of the service spillway.
Peak water levels with 50 and 20 percent blockage of the service spillway exceeded the design basis PMF elevation of 1,095 ft.However, simulated peak water levels for 50, 20, or ten percent blockage of the service spillway did not exceed the plant grade elevation of 1,099.5 ft. The 50 percent and 20 percent cases (Cases 7 and 8) were not considered realistic due to the dimensions of the spillways.
It was expected that debris caused by runoff associated with the PMF would not adversely impact the intake structure of the ESWS pumphouse.
Additionally, the baffle dikes provide a defense for the ESWS pumphouse against debris that could be floating in Wolf Creek Lake due to the PMF. The source area for debris generation would essentially be limited to a small contributing area on the east side of the plant and it is expected that any debris generated by that area would be small in size (e.g., tree branches) and would not affect the ESWS pumphouse.
Furthermore, the intake structure is equipped with trash racks, which protect the ESWS pumphouse from loss of flow due to debris.The reevaluation analysis also included a simulation representing sediment build up within Wolf Creek Lake, which considered a loss in the capacity of Wolf Creek Lake due to sedimentation over a period of 40 years. This is equivalent to approximately 1,080 acre-ft of sediment.
The peak water levels with lake sediments did not exceed the design basis PMF elevation of 1,095 ft.Flood Hazard Reevaluation Report 43 135031/14 Rev. 0 (February 10 , 2014)
Combined-Effects Flooding The design water level for combined-effects flooding is 1,095.80 ft and 1,100.20 ft for the WCGS shoreline and the ESWS pumphouse, respectively (Table 4-3). which occurs approximately 158 hrs after the start of the event (WCNOC, 2013a, Figure 2.4-23). The analogous values determined during the reevaluation were 1,095.46 ft and 1,099.52, respectively, which occurs approximately 68 hrs after the start of the event. The reevaluated flood levels are less than, and bounded by, the design water levels.The design loads on the roofs of safety-related structures are based on a 100-year snowpack with the probable maximum winter precipitation superimposed on it, which results in the maximum combined loading calculated as 153 pounds per square foot (psf) (WCNOC, 2013a; Section 2.3.1.2.2).
Ground loads due to the all-winter snowfall were considered in the hazard revaluation using the event combinations of ANSI/ANS 2.8 (ANS, 1992) Alternatives II and III for the combined-effects flood. It was determined that the ground loading using the snow water equivalence method could reach was 169.4 psf, which is slightly higher than the design roof loading. However, the maximum reevaluated ground loading is due to an April event that only generated 4.3 in of snow (the remainder being due to coincident April rainfall) and is not considered to be equivalent to a roof load, because the total combined water and snow column would not be stored on the roofs. All other months (November through March) resulted in ground loadings that were less than the design roof loading. Therefore, it was determined that the design roof loadings bounded the reevaluated ground loadings.Dam Breaches and Failures Failure of dams located above the John Redmond Reservoir will not adversely affect any safety-related facilities at the WCGS site (WCNOC, 2013a). In the most critical case, which postulates the domino-type failure of the John Redmond, Marion, Cedar Point, and Council Grove Reservoirs, the maximum flood stage of the Neosho River was estimated to be 1,044.55 ft at a distance of about 5.0 miles downstream from the John Redmond Dam (WCNOC, 2013a, Case b.3 of Section 2.4.4.1).As stated in the USAR, the topographic ridge between the Neosho River and Wolf Creek valleys below John Redmond Dam will separate the postulated flood levels in the Neosho River valley from any facilities at the site, with the exception of the Wolf Creek Lake dam. The maximum Flood Hazard Reevaluation Report 44 135031/14 Rev. 0 (February 10, 2014) P C water elevation on the downstream slope of the Wolf Creek Lake Dam, due to the postulated combined maximum flood-causing events in the Neosho and Cottonwood River basins, is conservatively established at elevation 1,049.6 ft. This flood stage is well below surface grades of any Seismic Category I facilities at the site and is about 50 ft below the plant grade elevation of 1,099.5 ft (WCNOC, 2013a).The reevaluated flood level resulting from the failure of all dams upstream of the John Redmond Reservoir was 1,076.70 ft, which is substantially greater than the design value due to the more conservative method used (i.e., the Volume Method per JLD-ISG-2013-01), but still far less than plant grade elevation (1,099.5 ft) and the service spillway elevation for the Wolf Creek Lake Dam (1,088.00 ft). Therefore, dam failure was screened out for the reevaluation, as was done in the design basis.Storm Surge and Seiche, Tsunami, and Ice-Induced Flooding Storm surge and seiche, tsunami, and ice-induced flooding were screened out as potential flooding events in the current design basis in the USAR (WCNOC, 2013a). In the reevaluation, storm surge and seiche, tsunami, and ice-induced flooding were also screened out.Channel Diversion Channel diversion is screened out as a potential flooding event in the design basis. In the design basis, there is no indication that Wolf Creek or its tributaries would be diverted from its present course of flowing into Wolf Creek Lake. In addition, supply of makeup water to the plant is available to be pumped from the Neosho River, if the supply from Wolf Creek is temporarily cutoff. In the reevaluation analysis, channel diversion was similarly screened out and it was determined that safety-related SSCs at the WCNOC site would not be affected by the diversion of flows from the Neosho River, Wolf Creek, and Long Creek.4.3 SUPPORTING DOCUMENTATION Calculation briefs in support of the flood hazard reevaluation at the WCGS site have been prepared, on which the reevaluated flood levels are based. Additionally, the Wolf Creek Nuclear Operating Corporation Post Fukushimna Flooding Walkdown Report (WCNOC, 2012) provides further information regarding the design basis flood hazard levels, as well as flooding protection and mitigation features.Flood Hazard Reevaluation Report 45 135031/14 Rev. 0 (February 10, 2014)
According to the Wolf Creek Nuclear Operating Corporation Post Fukushirna Flooding Walkdown Report (WCNOC, 2012), safety-related SSCs that are credited in the CLB for protecting the plant from external flood hazards were identified, inspected, and evaluated to be adequate.
According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." 4.3.1 Technical Justification of the Flood Hazard Analysis All flooding reevaluation analyses described in this report have been undertaken with consideration and implementation of current techniques, software, and methods used in present-day standard engineering practice to develop the flood hazard. The technical basis for the various scenarios modeled under the HHA approach and the key assumptions utilized in the determination of the reevaluated flooding levels for each flood causing mechanism are discussed individually in Section 3.0.4.3.2 Technical Justification of the Walkdown Results With respect to the implementation and conclusions of the flooding hazard reevaluation, results from the Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report (WCNOC, 2012) have been taken into consideration.
According to the report (WCNOC, 2012), "The walkdown visual inspection has verified that there is reasonable assurance the flood protection features are available, functional, and capable of performing their specified functions as set forth in the CLB. The Wolf Creek external flood protection features are effective and able to perform their intended flood protection function when subject to a design basis external flooding hazard." Based on the reevaluated flood hazard results, the effects of flood levels that are not bounded by the CLB on the pertinent flood protection and mitigation features described in Section 2.6 and as identified in the Wolf Creek Nuclear Operating Corporation Post Fukushinma Flooding Walkdown Report (WCNOC, 2012) are provided below.Flood Hazard Reevaluation Report 46 135031/14 Rev. 0 (February 10, 2014)
Topography The walkdown evaluated the state of the current site layout and topography against the design basis. The hazard reevaluation evaluated all runoff during the LIP analysis using the current site layout and topography documented by a 2013 aerial and ground survey. No credit was taken for underground drainage.
Tables 3-1 through 3-3 indicate that peak ponding levels determined in the reevaluated LIP analysis result in a few potential propagation pathways to safe shutdown equipment mainly attributed to short duration ponding caused by the peak intensity of the rainfall and mild sloping of the site grading.Doors Credited pressure doors were evaluated during the flooding walkdown.
The hazard reevaluation determined localized ponding exceeding the design plant floor elevation of 1,100 ft at doors that are potential pathways to safety-related systems and components in the following structures:
Auxiliary Building, Communication Corridor Building, Fuel Building, Hot Machine Shop, Turbine Building, Condensate Storage Tank Pipe House, and the Refueling Water Storage Tank Valve House.Structures
/ Floors / Walls / Penetrations
/ Vaults The walkdown evaluated the current state of credited flood protection boundaries related to the hydrostatic design basis of plant grade. The hazard reevaluation determined localized ponding exceeding the design basis at Seismic Category I structures, as indicated in Table 3-1. Therefore, the hydrostatic design basis for Seismic Category I structures, which is based on the design groundwater level of plant grade (elevation 1,099.5 ft), inspected during the walkdown is not bounded for the following Seismic Category I structures:
Auxiliary Building, Control Building, Diesel Generator Building, Fuel Building, Reactor Building, Refueling Water Storage Tank, ESWS manholes (MHE1A, MHEIB, MHE3A, MHE3B, MHE4A, MHE4B, MHE5A, and MHE5), and the Emergency Fuel Oil Tank Access Vaults.ESWS Pumphouse and Forebay The credited flood protection features associated with the ESWS pumphouse were evaluated during the flooding walkdown.
The ESWS pumphouse forebay was considered restricted access Flood Hazard Reevaluation Report 47 135031/14 Rev. 0 (February 10, 2014) R Z az during the flooding walkdowns, but was inspected by divers as an SSC scheduled in the preventative maintenance program meeting the frequency requirements of NRC Regulatory Guide 1.127. The results of the hazard reevaluation for flood elevation, including wave run-up, are bounded by the design basis. Therefore, the evaluations performed during the walkdown are still applicable to the ESWS pumphouse.
Sump Pumps & Motors Credited sump pumps and motors in Seismic Category I buildings were evaluated during the flooding walkdown due to the design basis of controlling groundwater inleakage.
As discussed previously, the hazard reevaluation determined localized ponding exceeding the design plant floor elevation of 1,100 ft at potential pathways to safety-related systems and components.
The sump pumps are credited to control groundwater inleakage, not the propagation of water into the Seismic Category I buildings due to external ponding because the design basis determined there was no ponding exceeding the plant floor elevation.
The capacity of these pumps could be evaluated, if necessary, for handling water that enters the building due to ponding during the LIP event.
4.4 CONCLUSION
S The flood hazard reevaluation for the river flooding event is bounded by the design basis. In addition, the reevaluated combined-effects analysis is also bounded by the design basis.However, dynamic, static, and wave loads were not computed for the design basis of the ESWS pumphouse during river flooding.
Therefore, reevaluated loadings cannot be compared to design basis values. The reevaluation analysis of dam break, storm surge and seiche, tsunami, and ice flooding are screened out in the reevaluation and in the design basis.It has been determined that the current design basis flood levels do not bound the reevaluated hazard elevations for the LIP hazard. The maximum reevaluated flood level for LIP was 1,100.47 ft, which is above the plant floor entrance elevation of 1,100 ft, whereas the maximum design flood level for LIP flooding is 1,099.83 ft. Thus, the reevaluated LIP flood levels are approximately 0.64 ft higher than the CLB values. The highest level of floodwater in the reevaluated LIP flooding analysis occurs in the small alleyway between the Fuel Building, the Auxiliary Building, and the Hot Machine Shop. It is recommended that additional modeling of this area be performed during the Integrated Assessment to further evaluate the LIP flooding potential problem in this specific area.Flood Hazard Reevaluation Report 48 135031/14 Rev. 0 (February 10, 2014)
Although the effects of wind-wave action in the powerblock area are screened out as a significant contributor to the LIP flood hazard, it is understood that small wind-waves could occur on the transient flows around buildings during an LIP event. Additionally, building settlement may lower the elevation of an entryway below the design value of 1,100 ft. Therefore, an integrated assessment should consider any small differences between stillwater level and floor elevation.
This should be considered when evaluating the potential mitigation required for an LIP event. Removing the unused rail tracks or modifying the grading of the site near safety-related structures may improve site drainage and could be considered during an Integrated Assessment.
Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)49 5.0 INTERIM EVALUATION AND ACTIONS Section 5.0 has been prepared in response to Request for Information Item 1 .d. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide an interim evaluation and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of the integrated assessment.
5.1 EVALUATION OF THE IMPACT OF THE REEVALUATED FLOOD LEVELS ON STRUCTURES, SYSTEMS, AND COMPONENTS Except for flooding levels due to an LIP event, the flooding levels of all other potential flood causing mechanisms, as presented in Section 3.0, do not exceed the elevations of the exterior entrances of SSCs at the WCGS site. The design basis did not include hydrostatic and hydrodynamic loads because the maximum calculated water level near the safety-related buildings due to the LIP event is 1,099.83 ft (WCNOC, 2013b), which is below the plant floor elevation of 1,100 ft (WCNOC, 2013b). However, the design basis did consider hydrostatic loads due to groundwater levels equivalent to plant grade.For the reevaluation analysis, the most refined simulated conditions result in ponded water adjacent to Seismic Category I buildings with elevations above the plant floor elevation (1,100 fi) at several entrances.
Additionally, water levels exceeded critical elevations at several manhole covers. The flood depths, associated durations, flow velocities, as well as hydrostatic and hydrodynamic forces that are computed in the reevaluation analysis are not bounded by the design basis LIP analysis.
Water levels computed in the reevaluation indicate potential flow of water into Seismic Category I buildings.
Debris loading and sedimentation during a LIP event were screened out in the reevaluation analysis.5.2 ACTIONS TAKEN TO ADDRESS FLOOD HAZARDS NOT COMPLETELY BOUNDED BY THE CURRENT DESIGN BASIS HAZARD Request for Information Item 1 .d. of NRC Recommendation 2.1 specifies that the flooding reevaluation contain an interim evaluation and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of the integrated assessment, if necessary (NRC, 2012a).Flood Hazard Reevaluation Report 50 135031/14 Rev. 0 (February 10, 2014)
Based on the results of the site walkdowns and the indicated ponding levels during a LIP event (exceeding doorway entrance elevations and design hydrostatic loads), interim actions are necessary to preliminarily evaluate the need for mitigation (e.g., sand bags), while an integrated assessment is conducted to further evaluate the need for mitigation in the case of a LIP event.The temporary mitigation measures for the interim action will consider parameters, such as the effect of small wind-waves (a few inches) that could occur on the transient flows around buildings during an LIP event and building settlement that may lower the elevation of an entryway below the design value of 1,100 ft. The integrated assessment and interim measures to mitigate ponding, during a LIP event, will be tracked by Wolf Creek's corrective action program.In addition, an interim action is required to evaluate whether mitigation is required to be put in place while the potential static and dynamic loading on the ESWS pumphouse due to water levels resulting from a design basis PMF is evaluated.
The integrated assessment and interim measures to mitigate potential static and dynamic loading on the ESWS pumphouse will be tracked by Wolf Creek's corrective action program.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)51 RZYZZ 6.0 ADDITIONAL ACTIONS Section 6.0 has been prepared in response to Request for Information Item i.e. of NRC Recommendation 2.1, Enclosure 2 of the 10 CFR 50.54(f) letter (NRC, 2012a): Provide additional actions beyond Request for Information item I .d taken or planned to address flooding hazards, if any.At this time, there are no additional actions beyond Request for Information Item I .d. of NRC Recommendation 2.1 (Section 5.0) which have been taken or are planned to address flooding hazards at WCGS.Per the NRC guidance for performing the integrated assessment for external flooding, addressees are requested to perform an integrated assessment if the current design basis flood hazard elevation does not bound the reevaluated flood hazard elevation for all flood-causing mechanisms.
Furthermore, "The integrated assessment will evaluate the total plant response to the flood hazard, considering multiple and diverse capabilities such as physical barriers, temporary protective measures, and operations procedures." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February
- 10. 2014)52 RZ
7.0 REFERENCES
- 1. American Nuclear Society (ANS), 1992, "Determining Design Basis Flooding at Power Reactor Sites," ANSI/ANS-2.8-1992, La Grange Park, Illinois.2. Bechtel, 1987, Bechtel, Drawing C-1 C021 1(Q), "Emer. Fuel Oil Storage Tanks Conc.Neat Line & Reinf. Access Vault," Revision 0, 1987.3. Chow et. al, 1988, Chow, Ven Te, David R. Maidment, and Larry Mays, "Applied Hydrology," McGraw-Hill Book Company, 1988.4. Dean, R.G. and R.A. Dalrymple, 1991, "Water Wave Mechanics for Engineers and Scientists," World Scientific Publishing Co. Pte. Ltd., 1991.5. Environmental Systems Research Institute (ESRI), 2009, ArcGIS ArcMap 9.3 Computer Program, 2009.6. Environmental Systems Research Institute (ESRI), 2012, ArcGIS ArcMap 10.1 Computer program, 2012.7. Environmental Systems Research Institute (ESRI), 2013a, "US Topo Maps by National Geographic," Website: <http://goto.arcgisonline.com/maps/USATopoMaps>, Date Accessed:
December 24, 2013.8. Environmental Systems Research Institute (ESRI), 2013b, "World Street Map," Website:<http://goto.arcgisonline.com/maps/WorldStreetMap>, Date Accessed:
December 24, 2013.9. Environmental Systems Research Institute (ESRI), 2013c, "ArcGIS Imagery," Website:<http://www.arcgis.com/home/item.html?id=a5fef63517cd4a099b437e55713d'3d54>, Date Accessed:
October 18, 2013 10. Federal Emergency Management Agency (FEMA), 1996, "Flood Insurance Study, City of Burlington, Kansas, Coffey County, Community Number 200063," Revised: September 20, 1996.11. Federal Emergency Management Agency (FEMA), 2013, "Numerical Models Meeting the Minimum Requirement of National Flood Insurance Program," Website<http://www.fema.gov/national-flood-insurance-program-flood-hazard-mapping/numerical-models-meeting-minimum-requirement-0>, Date Accessed: September 4, 2013.12. FLO-2D Software, Inc. (FLO-2D), 2012, "FLO-2D Reference Manual," September 2012.Flood Hazard Reevaluation Report 53 135031/14 Rev. 0 (February 10, 2014) P C
- 13. Kansas Biological Survey (KBS), 2010, "Bathymetric Survey of Wolf Creek Reservoir (Coffey County Lake), Coffey County, Kansas," Applied Science and Technology for Reservoir Assessment (ASTRA) Program, Report 2009-12 (December 2009), Revised January 2010.14. Kansas Department of Agriculture (KDA), 2011, "Kansas Department of Agriculture Fact Sheet," Division of Water Resources, Water Structures Program, 2011.15. National Oceanic and Atmospheric Administration (NOAA), 2013, National Geophysical Data Center, "Historical Tsunami Event Database", Website:<http://www.ngdc.noaa.gov/hazard/
tsudb.shtml>, Date Accessed:
June 17, 2013.16. National Weather Service (NWS), 1982, "Application of Probable Maximum Precipitation Estimates
-United States East of the 1 0 5 th Meridian," Hydrometeorological Report No. 52: August 1982.17. Nuclear Regulatory Commission (NRC), 1977, "Design Basis Floods for Nuclear Power Plants," Regulatory Guide 1.59, Revision 2, Washington DC, 1977.18. Nuclear Regulatory Commission (NRC), 1996, "NRC Information Notice 96-36: Degradation of Cooling Water Systems Due to Icing," Date of Publication:
June 12, 1996, Website: <http://www.nrc.gov/reading-rm/doc-collections/gen-comm/info-notices/I 996/in96036.html>, Date Accessed:
September 3, 2013.19. Nuclear Regulatory Commission (NRC), 2008, "Tsunami Hazard Assessment at Nuclear Power Plant Sites in the United States of America," NUREG/CR-6966, PNNL-17397, NRC Job Code J3301, Washington, DC, August 2008.20. Nuclear Regulatory Commission (NRC), 2011, "Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America," NUREG/CR-7046, PNNL-20091, NRC Job Code N6575, Washington DC, November 2011.21. Nuclear Regulatory Commission (NRC), 2012a, "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," Washington DC, March 12, 2012.22. Nuclear Regulatory Commission (NRC), 2012b, "The Estimation of Very-Low Probability Hurricane Storm Surges for Design and Licensing of Nuclear Power Plants in Coastal Areas," NUREG/CR-7134, NRC Job Code N6676, Washington, DC, October 2012.23. Nuclear Regulatory Commission (NRC), 2012c, Guidance for Performing the Integrated Assessment for External Flooding," JLD-ISG-2012-05, NRC Interim Staff Guidance (ML1231 1A214), Washington DC, Revision 0, November 30, 2012.Flood Hazard Reevaluation Report 54 135031/14 Rev. 0 (February 10, 2014)
- 24. Nuclear Regulatory Commission (NRC), 2013a, "Wolf Creek Generating Station, Unit 1," Website: <http://www.nrc.gov/info-finder/reactor/wc.html>, November 16, 2012.Date accessed:
August 9, 2013.25. Nuclear Regulatory Commission (NRC), 2013b, "Guidance for Assessment of Flooding Hazards Due To Dam Failure," JLD-ISG-2013-01, NRC Interim Staff Guidance (ML13151 A153), Washington, DC, Revision 0, July 29, 2013.26. Nuclear Regulatory Commission (NRC), 2013c, "Guidance for Performing a Tsunami, Surge, or Seiche Hazard Assessment," JLD-ISG-2012-06, NRC Interim Staff Guidance (ML12314A412), Washington, DC, January 4, 2013.27. Peinke et. al, 2004, J. Peinke, S. Barth, F. Bottcher, D. Heinemann, and B. Lange,"Turbulence, a Challenging Problem for Wind Energy," Physica A, Volume 338 pp. 187-193, 2004.28. United States Army Corps of Engineers (USACE), 1987, "HMR52 Probable Maximum Storm (Eastern United States) User's Manual," USACE, Davis, California, April 1987.29. United States Army Corps of Engineers (USACE), 2002, "Engineering and Design, Ice Engineering," EM 1110-2-1612, Washington DC, October 30, 2002.30. United States Army Corps of Engineers (USACE), 2004, "Ice Engineering, Method to Estimate River Thickness Based on Meteorological Data," ERDC/CRREL Technical Note 04-3, June 2004.31. United States Army Corps of Engineers (USACE), 2008, "Coastal Engineering Manual," Engineer Manual 1110-2-1100, Washington, D.C., 2008.32. United States Army Corps of Engineers (USACE), 2010a, "Hydrologic Engineering Center (HEC), HEC-HMS Version 3.5 Computer Program Build 1417, Release Date: August 2010.33. United States Army Corps of Engineers (USACE), 2010b, Hydrologic Engineering Center (HEC), HEC-RAS Version 4.1 Computer Program, Release Date: January 2010.34. United States Army Corps of Engineers (USACE), 2013a, National Inventory of Dams, Website: <http://geo.usace.army.mil/pgis/fp=397:1:112429380233301>, Date Accessed:
November 4, 2013.35. United States Army Corps of Engineers (USACE), 2013b, "Ice Jams Database, Total Number of Events by River for the State of KS," Website:<http://rsgisias.crrel.usace.army.mil/apex/f?p=273:39:748147269460901::NO:
- P39_STA ST:KS>, Date Accessed:
June 19, 2013.36. United States Geological Survey (USGS), 2012a, "The National Map US Topo New Strawn Quadrangle, Kansas-Coffey Co. 7.5-Minute Series," 2012.Flood Hazard Reevaluation Report 55 135031/14 Rev. 0 (February 10, 2014)
- 37. United States Geological Survey (USGS), 2012b, "The National Map US Topo Burlington Quadrangle, Kansas-Coffey Co. 7.5-Minute Series," 2012.38. United States Geological Survey (USGS), 2012c, "Earthquake Hazards Program," Date of Publication:
November 1, 2012, Website:<http://earthquake.usgs.gov/earthquakes/states/kansas/history.php>, Date Accessed: June 19, 2013.39. United States Geological Survey (USGS), 2013, "National Map Viewer and Download Platform," Website: <http://nationalmap.gov/viewer.html>, Date Accessed:
June 27, 2013.40. Wolf Creek Nuclear Operating Corporation (WCNOC), 2012, "Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report," Enclosure to ET 12-003 1, November 2012.41. Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26, March 2013.42. Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-050, 2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)56 RZYZ TABLES Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)Fc"41YZ TABLE 2-1: LIST OF POWERBLOCK STRUCTURES AND THEIR ELEVATIONS STRUCTURE SAFETY- ELEVATION RELATED (ft)Auxiliary Building Yes 1,100.00 Communication Corridor No 1,100.00 Condensate Storage Tank, Pipe No/No 1,100.00 House Door Control Building Yes 1,100.00 Diesel Generator Building Yes 1,100.00 Emergency Fuel Oil Tanks and Yes 1,099.75 Access Vaults ESWS Access Vaults (4) Yes 1,098.75 ESWS Manholes (10) Yes 1,097.17-1,099.67 ESWS Pumphouse Pressure Doors Yes 1,100.00 ESWS Valve House Yes 1,100.25 Fuel Building Yes 1,100.00 Hot Machine Shop No 1,100.00 Radwaste Building No 1,100.00 Reactor Building, Tendon Gallery Yes/ No 1,100.27 Access Shaft Reactor Make-Up Water Storage No/Yes 1,100.00 Tank, Valve House Door Refueling Water Storage Tank, Valve Yes/Yes 1,100.00 House Door Turbine Building No 1,100.00 LT- 1 Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)58 FJC""`Z TABLE 2-2: EXISTING WOLF CREEK DESIGN PARAMETERS' DESIGN PARAMETER VALUE Plant Grade Elevation 1,099.5 ft Top of Slab Elevation for Safety-Related Structures 1,100.0 ft Top of Wolf Creek Darn Elevation 1,100.0 ft Crest Elevation of Wolf Creek Dam Main Spillway 1,088.0 ft Lowest Elevation of Exterior Entrances to any Safety- 1,097.17 ft Related Structure (ESWS manholes)Elevation of Service Water Intake Structure 2 1,058.0 ft Top of UHS Baffle Dike 1,094.0 ft Top of Submerged UHS dam 1,070.0 ft Local Intense Precipitation 28.79 in (6-hr cumulative rainfall)Probable Maximum Precipitation (for the watershed) 32.8 in (48-hr PMP)Design Precipitation Rate for Roof Drainage -19 in (in one hr)Maximum Water Level at the Site, Including Wave 1,095.8 ft Run-up Maximum Water Level at the ESWS Pumphouse 1,100.2 ft Wind Speed for Wave Run-up 40 mph (overland)
LT-2 NOTES: 1 Maximum flood levels for the powerblock area are at or below 1,099.83 fi, which does not cause flooding into any safety-related SSCs. As a result, flood durations were not evaluated in the design basis.2 The invert elevation of the sump of the ESWS pumphouse is 1,058.0 ft with a minimum design water surface elevation of 1,068.0 ft. The top of slab elevation of the operating deck of the ESWS facility is 1,100.0 ft. The centerline of the pump discharge line leaving the pumphouse is at elevation 1,091.5 ft. The intake structure of the ESWS pumphouse is designed to withstand a water elevation of 1,102.5 ft.3The design basis reports maximum snow loads on roofs. The load of the 48-hr winter PMP is 103.0, 98.8, 111.3, and 127.9 lb/ft 2 for the months of December, January, February, and March, respectively (WCNOC, 2013a, Section 2.4.2.3.3).
References:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26, March 2013.Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-050, 2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)59 FJC0Z TABLE 2-3: CURRENT DESIGN BASIS FLOOD ELEVATIONS DUE TO ALL FLOOD MECHANISMS FLOODING MECHANISM WATER LEVEL (ft)Local Intense Precipitation 1,099.83 Lake Flooding 1,095.00 2 Combined-Effects Flooding 1,095.80 /1,100.20 3 (WCGS Shoreline/ESWS Pumphouse)
Dam Failure Flooding on the Neosho River 1,044.55 4 Storm Surge and Seiche Flooding N/A'Tsunami Flooding N/A'Ice Flooding N/A'Channel Diversion Flooding N/A'NOTES: The highest estimated water level resulting from an LIP event is 1,099.83 ft, calculated near the safety-related buildings in the powerblock area (WCNOC, 2013b).2 The maximum PMF water level in Wolf Creek Lake is 1,095.00 ft. This stillwater level is assumed to be constant across the lake.3 Combined-Effects Flooding includes PMF flooding preceded by a standard project flood event (50 percent of PMP) and wave run-up. Water level of 1,095.80 ft is due to the maximum wind-wave run-up at the WCGS shoreline.
The maximum water level, including wave run-up, at the ESWS pumphouse is 1,100.20 ft (WCNOC, 2013a, Section 2.4.10).4 A water level of 1,044.55 ft is reported for the confluence of the Wolf Creek with the Neosho River, based on an unsteady flow model simulating a domino-type failure of the John Redmond, Council Grove, Cedar Point, and Marion Dams with standard project floods (50 percent of PMP).5 N/A = Not Applicable.
References:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26., March 2013.Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-050, 2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)60 RoYZ TABLE 3-1: WATER LEVELS AND PONDING DEPTHS DUE TO LOCAL INTENSE PRECIPITATION PEAK PONDING FLOOD HEIGHT BUILDING SAFETY- WATER RELATED? ELEVATION ABOVE 1,100 FT (ft) (ft)Auxiliary Building Yes 1,100.43 0.43 Communications Corridor No 1,100.19 0.19 Condensate Storage Tank No 1,100.36 0.36 Control Building Yes 1,099.95 0.00 Demineralized Water Storage Tank No 1,100.36 0.36 Diesel Generator Building Yes 1,099.96 0.00 Fuel Building Yes 1,100.40 0.40 Hot Machine Shop No 1,100.40 0.40 Radwaste Building No 1,100.24 0.24 Reactor Building Yes 1,100.43 0.43 Reactor Make-Up Water Storage Tank No 1,099.95 0.00 Refueling Water Storage Tank Yes 1,100.16 0.16 Turbine Building No 1,100.47 0.47 LT-4 Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)61 RZYZ'4 TABLE 3-2: FLOODING AT OUTSIDE DOORS TO SEISMIC CATEGORY I BUILDINGS THAT ARE AT ELEVATION 1,100 FT DUE TO LOCAL INTENSE PRECIPITATION FLOODING MAXIMUM FLOOD MAXIMUM MAXIMUM HYDROSTATIC MAXIMUM ELEVATION MAXIMUM DEPTH DURATION OF FLOOD VELOCITY FORCE' HYDRODYNAMIC FORCE'GROUND CRITICAL (ft it) (hours) f/)(onsFo) (Pounds/Foot)
DOOR NUMBER' ASSET NUMBER STRUCTURE DESCRIPTION ELEVATION ELEVATION (ft) (ft/s) (Pounds/Foot) 00 (ft) CASE' CASE' CASE 2 CASE 2 CASE 2 CASE 2 5 6 5 6 5 6 5 6 5 6 5 6 11195/11198 (Pressure Door/Alcove Door) 1099,33 1100.00 1100.47 1100.40 1.13 1.06 1.0 0.8 3.6 4.3 40 35 21 29 2 13011 Auxiliary Building Door 1099,40 1100.00 1099.96 1099.96 0.52 0.52 0.0 0.0 08 0.8 8 8 <1 <1 (Missile Door)3 10/10 Auxiliary Building Door 1099.44 1100.00 1099.95 1100.00 0.52 0.57 0.1 0.1 1.4 1.8 8 10 2 4 3 13012/13013 (Pressure Door/Alcove Door) 1099_44 _ _11 57_1. 80 4 33031 CommunicationCorridor 1098.98 1100.00 1100.15 1100.02 0.99 0.86 1.2 1.0 08 0.7 30 23 I <1 (Double Door/Hollow Core Door)5 33042 Communication Corridor 1099.34 1100.00 1100.17 1100.04 0.89 0.76 1.0 0.8 1.3 1.3 25 18 2 2 (Roll Up Door) _6 33043 CommunicationCorridor 1099.30 1100.00 1100.18 1100.05 0.95 0.82 1.1 1.0 1.7 1.9 28 21 4 6 (Hollow Core Door) 1 7 32013/32018 Control Building 1099.10 1100.00 1100.00 1099.91 083 0.74 1.0 0.9 1.0 1.2 21 17 <1 2 (Pressure Door/Alcove Door)8 52011 Diesel Generator Building 1099.35 1100.00 1099.89 1099.89 0.56 0.56 0.3 0.1 2.5 2.9 t0 10 8 11 (Missile Door)9 52031 Diesel Generator Building 1099.17 1100.00 1099.94 1099.96 0.63 065 0.6 0.5 1.3 1.9 13 13 3 5 (Missile Door)10 61011 Fuel Building 1099.07 1 l00.0 1099.85 109984 0.74 073 1.0 1.0 1.7 1.9 17 17 5 6 (Hollow Core Door)I1 61021 Fuel Building 1099.36 1100.00 1099.86 1099.86 0.50 0.50 0.1 0.0 1.2 0.8 8 8 2 <1 (Hollow Core Door)12 61022 Fuel Building 1099.58 1100.00 1100.12 1100.06 0.48 0.42 0,0 0.0 1.2 Lo 7 6 2 1 (Roll Up Door) 1 13 13342 Hot Machine Shop 1099.30 1100.00 1100.25 1100.25 0.98 0.98 0.9 0.6 4.2 4.5 30 30 29 33 (Hollow Core Door)14 13321 Hot Machine Shop 1099.29 1100.00 1099.95 1099.95 0.64 0.64 0.3 0.2 0.6 0.6 13 13 <1 <1 (Hollow Core Door)15 13322 Hot Machine Shop 1099.32 1100.00 1099.96 1099.97 0.63 0.64 0.2 0.1 1.0 11 13 13 I 2 (Roll Up Door)Stair T-2 16 43092 Stair 1099.35 1100.00 1100.19 1100.05 0.80 0.66 0.8 0.5 0.9 0.9 20 14 <1 <I (Hollow Cor Door)17 43102 Stair T-3 1099.35 1100.00 1100.23 1100.07 0.85 0.69 0.9 0.5 0.8 0.8 23 15 <I <1 (Hollow Core Door)LT- 12 Flood Haard R=oaton A Repa 62 135031/14 R. 0 (Febroa1, 1(2014 RZYZ TABLE 3-2: FLOODING AT OUTSIDE DOORS TO SEISMIC CATEGORY I BUILDINGS THAT ARE AT ELEVATION 1,100 FT DUE TO LOCAL INTENSE PRECIPITATION FLOODING (CONTINUED)
NOTES: Some of these doors are to non-Seismic Category I buildings that have entrances to Seismic Category I buildings behind them. The ESWS and pumphouse and miscellaneous yard buildings are not included in this table.2 Cases 5 and 6 include the following:
time-varying LIP distribution, infiltration, a grid cell size of 15 ft. simulation length of 10 hrs and an unblocked VBS. The Manning's roughness coefficients differ between the two cases, with Case 5 using coefficients in the middle of reconmenrded ranges and Case 6 using coefficients at the low end of recommended ranges.' Hydrostatic and hydrodynamic forces are reported m force per unit width. Multiplying the reported forces by the width of a structure or wall provides the total force exerted on the wall. Hydrodynamic forces act in the direction of flow velocity.
Consequently.
the reported hydrodynamic forces should be interpreted as s conservative estimate.
In cases where flow velocity is directed away from the building or tank (i.e., offthe roof and away from the building or tank), the hydrodynamic force acting on the door is zero.Flood Hazard Reevaluation Reporn 13503 1/14 Rev 0 tFebare 10. 2014)63 FAC"Z TABLE 3-3: FLOODING AT OTHER DOORS, HATCHES, MANHOLES, AND VAULTS FOR SAFETY-RELATED SSCs DUE TO LOCAL INTENSE PRECIPITATION FLOODING MAXIMUM FLOOD MAXIMUM FLOOD MAXIMUM DURATION OF FLOOD MAXIMUM VELOCITY HYDROSTATIC FORCE HYDRODYNAMIC VAULT/ ASSET GROUND CRITICAL ELEVATION DEPTH (hours) (ft/second)
FODROSTAT FOR HATCH AUMER STRUCTURE DESCRIPTION ELEVATION ELEVATION (ft) (fit) (Pounds[Foot)
FORC )NUMBR*' NUMBR (i) (~l)I I(Pounds/Foot)
NUMBER (ft) ft) CASE' CASE' CASE' CASE' CASE' CASE'5 6 5 6 5 6 5 6 5 6 5 6 1 91011 Condensate Storage Tank 1099.31 1100.00 1100.40 1100.35 1.09 1.04 1.9 2.0 3.0 3.6 37 34 12 17 Pipe House Door 2 Z055 Emergency Fuel Oil Tanks 1099.51 1099.75 1099.83 1099.82 0.36 0.35 0.0 0.0 0.7 0.6 4 4 <1 <1 and Access Vaults 3 ZI02A ESWS Access Vault Al 1097.95 1098.75 1098.10 1098.05 0.14 0.09 0.0 0.0 0.3 0.2 <1 <1 <1 <1 4 Z102C ESWS Access Vault A2 1098.31 1098.75 1098.56 1098.48 0.13 0.05 0.0 0.0 0.3 0.2 <1 <1 <1 <1 5 ZI02B ESWS Access Vault B I 1098.40 1098.75 1098.48 1098.48 0.07 0.07 0.0 0.0 0.2 0.2 <1 <1 <1 <1 6 ZI02D ESWS Access Vault B2 1098.45 1098.75 1098.67 1098.47 0.29 0.09 0.0 0.0 0.4 0.2 3 <1 <1 <1 7 MHEIA ESWS Manhole 1098.58 1099.67 1100.02 1099.92 1.51 1.41 8.5 8.3 0.8 0.8 71 62 3 I 8 MHEIB ESWS Manhole 1098.66 1099.67 1100.02 1099.92 1.49 1.39 8.0 7.8 0.9 1.0 69 60 I 1 9 MHE2A ESWS Manhole 1097.51 1098.17 1097.82 1097.72 0.31 0.21 0.0 0.0 0.5 0.7 3 I <1 <1 10 MHE2B ESWS Manhole 1097.80 1098.17 1097.84 1097.77 0.19 0.12 0.0 0.0 0.4 0.3 I <1 <1 <I 11 NIHE3A ESWS Manhole 1097.03 1097.17 1097.59 1097.51 0.27 0.19 0.0 0.0 0.6 0.4 2 I <I <1 12 MHE3B ESWS Manhole 1097.11 1097.17 1097.59 1097.51 027 0.19 0.0 0.0 0.6 0.4 2 I <1 <1 13 MHE4A ESWS Manhole 1096.79 1097.17 1098.14 1097.49 1.24 0.59 1.8 0.9 0.7 2.1 48 11 I 6 14 MHE4B ESWS Manhole 1096.89 1097.17 1098.14 1097.49 1.24 0.59 1.8 0.9 0.7 2.1 48 I 1 6 15 MHE5A ESWS Manhole 1097.81 1097.92 1098.37 1098.12 0.85 0.60 1.5 1.0 0.7 0.7 23 11 1 <1 16 MHE5B ESWS Manhole 1097.75 1097.97 1098.37 1098.12 0.85 0.60 1.5 1.0 0.7 0.7 23 I 1 1 <1 17 K1051 ESWS Pumphouse Pressure 1099.53 1100.00 1099.31 1(199.31 0.09 0.09 0.0 0.0 0.6 0.6 <1 <1 <1 <1 Door A 18 K1041 ESWS Pumphouse Pressure 1099.24 1100.00 1098.83 1098.83 0.08 0.08 0.0 0.0 0.7 0.7 <1 <1 <1 <1 Door B 19 Z093A ESWS Valve House Train A 1099.03 1100.25 1099.96 1099.87 0.82 0.73 1.0 0.8 0.9 0.9 21 17 1 1 20 Z093B ESWS Valve House Train B 1099.27 1100.25 1(199.96 1099.87 0.68 0.59 0.6 0.4 0.9 1.1 14 II 1 2 21 N/A Reactor Building Tendon 1099.22 1100.27 1100.26 1100.21 1.12 1.07 6.2 6.4 0.9 0.8 39 36 I <1 Gallery Access Shaft Reactor Make-up Water 22 91031 Storage Tank Valve House 1099.34 1100.00 1099.92 1099.91 0.59 0.58 0.1 0.1 1.9 2.6 I1 II 5 10 DooreTank Vaver taorag 1099.18 1100.00 1999.98 1100.01 0.79 0.82 1.0 0.8 2.0 2.2 19 21 6 9 I Tank Valve House Door-LT-10 Flood Hazard Rcvalualion Reporl 64 1350131114 Re-. 0 (1Febn`aa, I). 2014)R?-"*z TABLE 3-3: FLOODING AT OTHER DOORS, HATCHES, MANHOLES, AND VAULTS FOR SAFETY-RELATED SSCs DUE TO LOCAL INTENSE PRECIPITATION FLOODING (CONTINUED)
NOTES: ' Cases 5 and 6 include the following:
time-varying LIP distribution, infiltration, a grid cell size of 15 ft. simulation length of 10 hrs. and an unblocked VBS. The Manning's roughness coefficients differ between the two cases, with Case 5 using coefficients in the middle of reconmnended ranges and Case 6 using coefficients at the low end ofrecomtended ranges.2 Hydrostatic and hydrodynamic forces are reported in force per unit width. Multiplying the reported forces by the width of a structure or wall provides the total force exerted on the wall. Hydrodynamic forces act in the direction of flow velocity.
Consequently, the reported hydrodynamic forces should be interpreted as a conservative estimate.
In cases where flow velocity is directed away from the building or tank (i.e.. offthe roof and away from the building or tank), the hydrodynamic force acting on the door is zero.Vaults/Hatches 7 through 16 are designed to be watertight, as discussed in the IlloI]Creck Nuclear Operating Corpirrtt'ln Posl Fakushinia Flooding ll"alkdem-n Report (WCNOC, 2012).
Reference:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2012, "Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report," Enclosure to ET 12-0031, November 2012.Flood Haard Rcvalualon Report 65 1351131/14 R-v. 0 (F1bt6a-x
- 10. 20114)
TABLE 3-4: WATERSHED SUBBASIN CHARACTERISTICS AND HEC-HMS MODELING RESULTS RUNOFF 2 PRECIPITATION PEAK DRAINAGE AREA RUO LAG TIME DEPTHI 3 SBBSN (i) CURVE DPHRUNOFF 4 SUB BASIN (Mil) NUMBER1 (Minutes) (in) (cfs)SB1 7.035 92 47.30 36.70 50,817 SB2 2.470 90 31.05 36.70 21,131 SB3 1.934 85 44.77 36.70 14,246 SB4 16.250 92 23.08 36.70 151,880 SB5 3.450 82 85.97 36.70 17,932 LT-5 NOTES: SCS Runoff Curve Number after calibration 2 Lag time after calibration and reduction by 33 percent to account for non-linearity effects in accordance with guidance in NRC NUREG/CR-7046.
3 Precipitation depth is for the 72-hr PMP.4 Runoff hydrograph ordinates from HEC-HMS output are increased by five percent for Case 5.
Reference:
Nuclear Regulatory Commission (NRC), 2011, "Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America," NUREG/CR-7046, PNNL-20091, NRC Job Code N6575, Washington DC, November 2011.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (Februarv 10, 2014)66 RZYZZ TABLE 3-5:
SUMMARY
OF HEC-HMS AND HEC-RAS SIMULATION CASES RAINFALL RUNOFF ROUTING NONLINEARITY PERCENT CASE LOSSES TRANSFORMATION THROUGH EFFECTS SPILLWAY SEDIMENTATION (YES/NO) (YES/NO) CHANNELS (YESINO) BLOCKED_______ ___________ (YES/No) (YS o) BO EDYS/)HEC-HMS Modeling 1 No No No No 0 No 2 No Yes Yes No 0 No 3 No Yes Yes Yes No 4 Yes Yes Yes Yes 0 No 5 Yes Yes No Yes No HEC-RAS Modeling 1 No No No No 0 3 No 2 No Yes Yes No No 3 No Yes Yes Yes No 4 Yes Yes Yes Yes o3 No 5 Yes Yes No Yes 0 No 6 Yes Yes No Yes 0 No 7 Yes Yes No Yes 50/104 No 8 Yes Yes No Yes To/10 4 No 9 Yes Yes No Yes 10/i104 No 10 Yes Yes No Yes o3 Yes LT-6 NOTES: 1 Nonlinearity effects include a decrease in lag time by 33 percent, and an increase in peak discharge.
A five percent increase in discharge is used for Case 5 results as input into the HEC-RAS model.2 Routing through channels is not used in HEC-HMS Cases I and 5. However, channels are represented in the HEC-RAS simulations.
HEC-HMS simulated discharge from subbasins is used in the HEC-RAS simulations to avoid the potential of double accounting for delays in flow through channels.3 The spillways are assumed to be unobstructed.
4 The first number is the percent of the service spillway that is blocked. The second number is the percent of the auxiliary spillway that is blocked.Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)67 RJm*"ZZ TABLE 4-1: COMPARISON OF MODELING APPROACHES FOR CURRENT LICENSING BASIS AND FLOODING REEVALUATION I ANALYSIS CONSIDERATION REEVALUATED HAZARDS CURRENT LICENSING BASIS Local Intense Precipitation Calculation based on HMR No. 52 Calculation based on HMR No. 52 (LIP) values values LIP Flooding Characterization FLO-2D Model USACE HEC-RAS PMP for the Wolf Creek Calculation based on HMR No. 52 Calculation based on HIMR No. 33 Watershed values values PMP Rainfall Hyetograph Time period of 72 hrs with 48 hrs with I-hr increments 5-inimute increments 48_hrswith_1-hrincrements HEC-HMS was not used for the USAR analysis.
The USACE Rainfall-Runoff Model USACE HEC-HMS developed I-hr Snyder unit hydrographs for 3 subbasins scaled from the Neosho River watershed.
Transformation Method SCS Synthetic Unit Hydrograph Snyder's Unit Hydrograph Method Method PMF loss, transformation, and Include loss, transfornation, and Include loss and transformation, routig trouting through the channels and with routing through Wolf Creek routing through Wolf Creek Lake and darn. Lake and dam River Hydraulic Model USACE HEC-RAS USACE Water Surface Profiles 2 The Tennessee Valley Authority The Volume Method was used to TeTneseVle uhrt deterVoue Metho watersusaed t Software was used to compute the determine the water surface Dam Break Flooding elevation on Neosho River at the water surface elevation at the Wolf e onf oneek Noshofernte.
Creek confluence with the Neosho Wolf Creek confluence.
Rvr River.Combined Effects Flooding NUREG/CR-7046 and ANS, 1976 method______________________ANS,_1992_methods_______________
LT-8 NOTES: l Some of the mechanisms considered and the methodologies used in the reevaluation analysis were not entirely consistent with or required to be evaluated as part of the original design basis, and therefore direct comparisons is practicable in some cases.2 Stated in USAR Section 2.4.3.5 (WCNOC, 2013a).
References:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26, March 2013.Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-050, 2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)68 FJCY*Z TABLE 4-2: COMPARISON OF CURRENT LICENSING BASIS AND FLOODING REEVALUATION ANALYTICAL INPUTS ANALYTICAL INPUT REEVALUATED HAZARDS CURRENT LICENSING BASIS Local Intense Precipitation 19.0 in 19.0 in (1-hr, I mi 2 value)Probable Maximum Probabep atio m f36.70 in (72-hr PMP) 32.80 in (48-hr PMP)Precipitation for Watershed Wolf Creek Lake Dam outflow: Wolf Creek Lake Dam outflow: Input for River Hydraulics 23,813 cfs 22,845 cfs Model Wolf Creek Lake inflow: Wolf Creek Lake inflow: 215,128 cfs 82,089 cfs Spillway Elevations for Wolf Creek Lake Dam 1,088.0 ft / 1,090.5 ft 1,088.0 ft / 1,090.5 ft (Service / Auxiliary Spillways)
Maximum Sustained Overland 10-minute, 2-year 38.65 mph 40.00 mph 2 Wind Speed Maximum Sustained Overwater 10-minute, 2-year 46.38 mph 1 Not computed Wind Speed LT-9 NOTES: 'The maximum storm duration of HMR No. 33 (used in the design basis) is 48 hrs and the maximum storm duration of HMR No. 52 (used for the reevaluation analysis) is 72 hrs.2 Wind speed used for wave height calculation.
References:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26, March 2013.Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-050, 2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)69 FJC""4'4Z TABLE 4-3: COMPARISON OF CURRENT LICENSING BASIS AND REEVALUATED FLOOD LEVELS REEVALUATED WATER CURRENT LICENSING BASIS FLOODING MECHANISM LEVEL WATER LEVEL (ft) (ft)Flooding Due to Local Intense 1,100.47 1,099.83 Precipitation 1,100.47_1,099.83 Lake Flooding Due to PMF 1,093.54 1,095.00 Wave Run-up Coincident with Stillwater level + Stillwater level +PMF Wave Run-up Wave Run-up WCGS Shoreline 1,094.37 1,095.8 ESWS Pumphouse 1,098.43 1,100.2 1,076.70 ft on the Neosho River at confluence of Wolf 1,044.55 ft on the Neosho Creek based on River at confluence of Wolf Dam Failure Flooding Instantaneous Transport of Creek based on dynamic Reservoir Storage (Volume modeling Screening Method)Storm Surge and Seiche Flooding Dismissed Dismissed Tsunami Flooding Dismissed Dismissed Ice Flooding Dismissed Dismissed Channel Diversion Flooding Dismissed Dismissed Combined-Effects Flooding 500-yr rainfall + PMP + SPF + PMP + Wave Run-up Wave Run-up WCGS Shoreline 1,095.46 1,095.80 ESWS Pumphouse 2 1,099.52 1,100.20 LT-7 NOTES: PMP = Probable Maximum Precipitation, SPF = Standard Project Flood = 50 percent PMP.2 The intake structure for the ESWS Pumphouse is designed to withstand a high water elevation of 1,102.50 ft (WCNOC, 2013a, Section 2.4.10)
References:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26, March 2013.Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-050, 2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)70 FJC""*JZ TABLE 4-4: COMPARISON OF VARIOUS FLOODING PARAMETERS BETWEEN THE CURRENT LICENSING BASIS AND THE FLOOD REEVALUATION REEVALUATED FLOOD CURRENT LICENSING FLOOD CONDITION I BASIS HAZARD BASIS Local Intense Precipitation Flood Depth 1.51 ft' 0.33 ft" Flood Duration 8.5 hrs ' Not Computed 3 Maximum Flow Velocity 4.5 ft/s 4 Not Computed'Hydrostatic Loading 71 lb/ft' Not Computed 3 Hydrodynamic Loading 33 lb/ft 4 Not Computed-Flood Elevation with Debris Debris Screened Out 5 Not Computed Flood Elevation with Sedimentation Sedimentation Screened Out 5,6 Not Computed Probable Maximum Flood Flood Elevation 1,093.54 ft' 1,095.0 ft 7,8 Flood Duration Not Computed 3 Not Computed 3 Maximum Flow Velocity Not Computed Not Computed 3 Hydrostatic Loading 39,4099 Not Computed 10 Hydrodynamic Loading N/A " Not Computed Flood Elevation with Debris/Spillway 1,094.37 ft 12 Not Computed Blockage Flood Elevation with Sedimentation 1,093.54 ft' Not Computed 13 Combined-Effects Flooding Flood Elevation 14 1,095.46/1,099.52 ft 1,095.8/1,100.2 ft Flood Duration Not Computed Not Computed 3 Maximum Flow Velocity Not Computed 3 Not Computed 3 Hydrostatic Loading Not Computed Not Computed"'
Hydrodynamic Loading Not Computed Not Computed J LT- 11 NOTES: 'Simulated value at ESWS Manhole (Vault/Hatch No. 7, Table 3-3).2 This flood depth results in a maximum water elevation of 1,099.83 ft, which does not flood any safety-related SSCs (WCNOC, 2013b).3 Safety-related SSCs are not flooded, so the flood condition is not computed.'Maximum simulated value at Hot Machine Shop (Door No. 13, Table 3-2).5 These forces are screened out due to simulated low velocities and flow directions away from safety-related SSCs.6 These forces are screened out due to simulated shallow flood depths.7 The peak stage simulated for Wolf Creek Lake, not including the effects of wind-waves.
8 The CLB value is from the USAR (WCNOC, 2013a, Table 2.4-16).Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)71 R2on*z TABLE 4-4: COMPARISON OF VARIOUS FLOODING PARAMETERS BETWEEN THE CURRENT LICENSING BASIS AND THE FLOOD REEVALUATION (CONTINUED) 9 Hydrostatic forces are computed for the ESWS pumphouse only. This force is a depth integrated force for the ESWS pumphouse from the stillwater level down to the bottom of the ESWS pumphouse (elevation 1058.0 ft).'(0 The intake structure of the ESWS pumphouse can withstand a water elevation of 1,102.5 ft (WCNOC, 2013a, Section 2.4.10).Hydrodynamic forces are not applicable to the ESWS pumphouse because adjacent water is stagnant (i.e., Wolf Creek Lake). Hydrodynamic forces due to wind-waves are not computed in the reevaluation because wind-wave run-up levels in the reevaluation are bounded by the CLB run-up levels (1100.2 fi; WCNOC, 2013a, Section 2.4.10).12 This is the peak stage simulated for Wolf Creek Lake with ten percent of the auxiliary and service spillways blocked.'3 The maximum fill over a period of 40-years is provided in the USAR (WCNOC, 2013a).14 This flood elevation includes wind-wave effects for the WCGS site shoreline and the ESWS pumphouse.
References:
Wolf Creek Nuclear Operating Corporation (WCNOC), 2013a, "Updated Safety Analysis Report (USAR)," Wolf Creek Generating Station (WCGS) Unit 1, Revision 26, March 2013.Wolf Creek Nuclear Operating Corporation (WCNOC), 2013b, "Updated Safety Analysis Report (USAR) Change Request Number 2013-0501,2013." Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February
- 10. 2014)72 RZYZ`
FIGURES Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)FC4,Y1Z NWUT Legend Coordinate System: NAD 1983 State Plane Kansas South FIPS 1502 Feet Projecton:
Lambert Conformal Conic iiiia* Kansas City Figure 1-1 25 12.5 0 25 50 Miles RF: 1:1,166.670 A Wolf Creek Generating Station General Location of the Site+- Airport PREPARED FOR River/Stream
-Highways Wolf Creek Flood Hazard State Roads-Roads
Reference:
Background Source: ESRI 2013b, Environmental Systems Research Institute (ESRI), "World Street Map" Website :"255">httpllgoto.arcgisonline.comlmapslWord_StreetMap Date Accessed:
December 24, 2013 Reevaluation Report RC--- Paul C. Rizzo Associates, Inc.FJ--`ZENGINEERS/CONSULTANTS I CM Railroads 0 0.5 1 2 RF: 1:75,100 3 4 5 Miles Coordinate System. NAD 1983 State Plane Kansas South FIPS 1502 Feet Projectlon:
Lambert Conformal Conic Legend A WCGS -Wolf Creek Generating Station Figure 1-2 Site Area Map Note: Elevations are shown in meters.
Reference:
Image Source: ESRI 2013a, Environmental Systems Research Institute (ESRI), "US Topo Maps by National Geographic".
Website: http://goto.arcgisonline.com/mapslUSATopoMaps Date Accesed December 24, 2013 PREPARED FOR Wolf Creek Flood Hazard Reevaluation Report Paul C. Rizzo Associates, Inc.I
/CONSULTANTS/
CM I DRAWN BY I J.S.S. I CHECKED BY JML 1-30-14 CAD FILE JPS 1 14 NUMBER 13-5031 -A20 I 010614 I APPROVED BY 1 010614 1 JTPzr9J----- ----- -----//I,,) t £N---- ----------------------------------F-- A.7-.'7 I--------___ ___ A Iif'fL __'9 r\ _~§~j~W w.4 lr1 /-J i t J 0 .I ------------------------------
-i____ 1 FIGURE 2-1 DESIGN SITE LAYOUT V f 1 1 1 I [
REFERENCE:
WOLF CREEK NUCLEAR OPERATING CORPORATION (WCNOC), 2013a,"UPDATED SAFETY ANALYSIS REPORT (USAR) FIGURE 1.2-44," WOLF CREEK GENERATING STATION (WCGS) UNIT 1, REVISION 26 MARCH 2013, I PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORTPaul C. Rizzo Associates, Inc.ENGINEERS
/ CONSULTANTS
/ CM
-IRE Kt!INhi~~~~~~EWS PMPHOUSBi zIwsPu f'.vie~0 WOLF CREEK LAKE SCALE FIGURE 2-2 600 0 600 FEET PRESENT-DAY SITE LAYOUT AND TOPOGRAPHY LEGEND: PREPARED FOR" BUILDING WOLF CREEK FLOOD HAZARD REEVALUATION REPORT TOPOGRAPHIC CONTOUR (INTERVAL
= ONE FOOT)R -Paul C. Rizzo Associates, Inc.ENGINEERS
/ CONSULTANTS
/ CM 0-J LEGEND: 1.2.3.4.5.6.7.8.9.10.11.12.13.14.AUXILIARY BUILDING COMMUNICATION CORRIDOR CONDENSATE STORAGE TANK CONTROL BUILDING DIESEL GENERATOR BUILDING EMERGENCY FUEL OIL TANKS ESWS VALVE HOUSE FUEL BUILDING HOT MACHINE SHOP RADWASTE BUILDING REACTOR BUILDING REACTOR MAKE-UP WATER STORAGE TANK REFUELING WATER STORAGE TANK TURBINE BUILDING SCALE 100 0 100 FEET FIGURE 2-3 LOCATIONS OF BUILDINGS IN THE POWERBLOCK AREA PREPARED FOR NOTE: WOLF CREEK FLOOD HAZARD REEVALUATION REPORT I~h~Paul C. Rizzo Associates_
Ic.ENGINEERS
/ CONSULTANTS
/ CM BACKGROUND IMAGE MODIFIED FROM: GOOGLE EARTH, 2013.
0)LI Uoz 0 C N 20-~"A -m 0 wd y c/i m 0 wd 0 C14 z 0 0 0.5 1 1.5 2 I Miles LEGEND:* WOLF CREEK GENERATING STATION FIGURE 2-4 WOLF CREEK LAKE WATER DEPTHS PREPARED FOR KANSAS BIOLOGICAL SURVEY, 2010, "BATHYMETRIC SURVEY OF WOLF CREEK RESERVOIR (COFFEY COUNTY LAKE), COFFEY COUNTY, KANSAS," REPORT 2009-12 (REVISED JANUARY 2010).WOLF CREEK FLOOD HAZARD REEVALUATION REPORT RC1F Paul C. Rizzo Associates, Inc.ENGINEERS
/ CONSULTANTS
/ CM i DRAWN I J.S.S. I CHECKED BY I JML 11-30-14'CAD FILE BY 120713 APPROVED BY JPS 1-30-14 NUMBER 13-5031-Al E Us sit -seic data -torfn 0h oa ine s prciiato flodn FL0 0 S model$Stop Saft ofth S No A L Yes Stop. Use the most refined case for comparison to the design basis.No I I Yes FIGURE 3-1__MEENNNýTHE HHA DIAGRAM FOR LOCAL INTENSE PRECIPITATION FLOODING ANALYSIS PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT ry'J'N Paul C. Rizzo Assoc iates, Inc.I --- '--ENGINEERS
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/ CM 1.Maximum Water Depth (Feet)0.03 -0.10 0.11 -0.20 0.21 -0.30-0.31 -0.40 0.41-0.50 0.51- 0.60-0.61-0.70 071 -0.80 0.81 -0.90-0.91 -1.00-1.01 -1.20 1.21 -1.40 1.41-1.60 1.61- 1.80 1.81- 2.00 2.01 -3.00-3.01 -4.00 4.01 -5.00-5.01 -6.00> 6800-FLO-2D Boundary-FLO-2D Features N A 0 250 500 Feet I I I I I I FIGURE 3-2 FLO-2D INUNDATION MAP DUE TO LOCAL INTENSE PRECIPITATION PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT rQI? Paul C. Rizzo Associates, Inc.ENGINEE/RS/CONSULTANTS
/ CM I DRAWN BY I J.S.S. I CHECKED BY IJML 11-30-1 4 CAD FILE IJPS 1-30-141 NUMBER 13-5031-A3 I 120713 1 APPROVED RY NOTE: ar 1. INCLUDES MULTIPLE CASES IN SUPPORT OF POTENTIAL HHA CASES TO FOLLOW.*So. Safetof te S~No Us iespecuu~.ifm~ic data t I Yes Stop Ushems Yes No Il FIGURE 3-3 THE HHA DIAGRAM FOR THE ANALYSIS OF FLOODING IN RIVERS AND STREAMS PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT Ry~j Paul C. Rizzo Associates, Inc.ENGINEERS
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/ CM 0 0.5 1 2 3 4 5 Miles RF: 1:140,000 Coordinate System: NAD 1983 State Plane Kansas South FIPS 1502 Feet Projection:
Lambert Conformal Conic Legend A WCGS -Wolf Creek Generating Station SWolf Creek Subbasins
Reference:
Image Source: ESRI 2013a, Environmental Systems Research Institute (ESRI), "US Topo Maps by National Geographic".
Website:http://goto.arcgisonline.conmmaps/USATopoMaps Date Accesed December 24, 2013 Figure 3 -4 Wolf Creek Watershed Map Showing Subbasins PREPARED FOR Wolf Creek Flood Hazard Reevaluation Report[rCr Paul C. Rizzo Associates, Inc.ENGINEERS
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/ CM 0 w m-I Z 00I-I i C'I a..-u U 1.6 1.4 1.2 1.0 0.8 0.6 0.4 0.2 0.0 m 0 w 0 0~V)z 0 Time (hours)FIGURE 3-5 PMP HYETOGRAPH FOR THE WOLF CREEK WATERSHED PMP -PROBABLE MAXIMUM PRECIPITATION O.TE: THE TIME INCREMENT OF HYETOGRAPH IS FIVE MINUTES.PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT[y IPaul C. Rizzo Associates, Inc.ENGINEERS
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/ CM
-Y 0i.L0 LAJ uLJ 0oz 0'C f N bor-2-a-~ -~irmi-4 r 0 0L U-0L V.O 0 04J WCNOC Site E Reservoir Subbasin z 0:>Junction th.2 unebon- 4 NOT TO SCALE FIGURE 3-6 HEC-HMS MODEL FOR THE WOLF CREEK WATERSHED NOTE: THE HEC-HMS MODEL SHOWN IN THIS FIGURE INCLUDES SUBBASIN 5 (SUBBASIN BELOW WOLF CREEK DAM), WHICH IS NOT INCLUDED IN THE USAR (WCNOC, 2013a, P. 2.4-16) RUNOFF MODEL. SUBBASIN 5 IS USED IN THIS ANALYSIS TO DETERMINE POTENTIAL BACKWATER EFFECTS FROM DOWNSTREAM OF WOLF CREEK LAKE.PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT[-('-V? Paul C. Rizzo Associates, Inc.0 -'-- ENGINEERS
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/ CM 0 u')m o Z RESULTS FROM HEC-RAS MODEL (CASE 6)STAGE VERSUS TIME z 25,000 20,000 15,000 10,000 5,000 0 25,000 20,000' 15,000.~10,0005,000 0 0 2 4 Time (days)6 8 0 2 4 6 Time (days)8 FIGURE 3-7 FLOOD LEVEL TIME HISTORY OF WOLF CREEK LAKE FOR THE ANALYSIS OF FLOODING IN RIVERS AND STREAMS PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT Paul C. Rizzo Associates, Inc.ENGINEERS
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/ CM (A) RESULTS FROM HEC-HMS MODEL (CASE 5)(B) RESULTS FROM HEC-RAS MODEL (CASE 6)DISCHARGE VERSUS TIME
-I.0~L0 In ozj m 0 I Ni--M 2668.60=m.-P#9868.41*
SM,!3~~98*
7,~050.877
~'2157.63*
~~ui 374.540 Upper Reach Wolf Creek Lake Direction of Flow V)vij Ei ui 0 W 0.0-z 0 Lower Reach NOT TO SCALE FIGURE 3-8 HEC-RAS MODEL FOR THE WOLF CREEK WATERSHED PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT QPaul C. Rizzo Associates, Inc.ENGINEERS
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/ CM 0 0 r)w 02< z 0 Z-at',-, ~)0 Lii Lii 02 0ýQ-C Z Huut<L 15i NOTES: 1. IMAGE SOURCE: USGS, 2013, UNITED STATES GEOLOGICAL SURVEY (USGS),"NATIONAL MAP VIEWER," WEBSITE:<http://viewer.nationalmap.gov/viewer/>, DATE ACCESSED:
JUNE 27, 2013.2. THE SHORELINE OF THE WOLF CREEK LAKE CORRESPONDS TO A LAKE LEVEL OF 1093.54 FEET.FETCH LOCATIONS OVER WOLF CREEK LAKE PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORTPaul C. Rizzo Associates, Inc.ENGINEERS
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/ CM DRAWN J.S.S. I CHECKED BY BY 120713 APPROVED BY JML 11-30-14 CAD FILE JPS 11-30-14 NUMBER 13-5031-A4 Crat inu str fo cobie -effct mode~slg,phconsist~Eing of a 500-yea ranfl evn foloe byte MP Evaluate wae lee du t PII usn
- CR S Evaluate run-up on SSCs based on water level due to PIVIF Is the reeva uate flood hazard elevation greater han the curre levatio Stop. Safety of the SSCs is demonstrated.
0 -5 Us st-spcfcdt No. I Yes a FIGURE 3-10..v THE HHA DIAGRAM FOR COMBINED-EFFECTS FLOODING ANALYSIS PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT[~I~IPaul C. RizzoAssociates, Inc.PC-vzENGINERS
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/ CM
-I 00 0 It r j 1102 am o z o00c"OIV 1100 1098 S1096 1094 1092 1090 1088 1086 I.jJ T" I Um 0 wi 0L C-n-U 0 24 48 72 96 120 144 168 192 Time from Start of Combined Event (hours)zFIGURE 3-11 FLOOD LEVEL TIME HISTORY OF WOLF CREEK LAKE FOR THE ANALYSIS OF COMBINED-EFFECTS FLOOD PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT R -- Paul C. Rizzo Associates, Inc.ENGINEERS
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/ CM A WCGS site W Neosho Watershed Neosho Watershed Dams z WCGS -WOLF CREEK GENERATING STATION
REFERENCES:
- 1. IMAGE SOURCE: ESRI, 2013c, ENVIRONMENTAL SYSTEMS RESEARCH INSTITUTE (ESRI), "ARCGIS IMAGERY," WEBSITE: <http://www.arcgis.com/home/
item.html?id=o5fef63517cd4o099b437e55713d3d54>, DATE ACCESSED:
OCTOBER 18, 2013.2. HUC BASIN SOURCE: USGS, 2013, UNITED STATES GEOLOGICAL SURVEY (USGS), "NATIONAL MAP VIEWER AND DOWNLOAD PLATFORM," WEBSITE:<http://viewer.nationalmap.gov/viewer/>, DATE ACCESSED:
JUNE 27, 2013.3. USACE, 2013a, UNITED STATES ARMY CORPS OF ENGINEERS (USACE), NATIONAL INVENTORY OF DAMS, WEBSITE:<http//geo.usace.army.mil/pgis/
f?p=397:1:112429380233301:::::>, DATE ACCESSED:
NOVEMBER 4, 2013.FIGURE 3-12 LOCATION OF DAMS NEAR THE SITE PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT I7C4 Paul C. Rizzo Associates, Inc.ENGINEERS
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/ CM
-I.C14 L0 r'<:Di 0 Z I I I m 0 w 0 w I 0 U U c I-L 0.z LEGEND: ISG -INTERIM STAFF GUIDANCE
REFERENCE:
IMAGE SOURCE: NRC, 2013b, UNITED STATES NUCLEAR REGULATORY COMMISSION (NRC), "GUIDANCE FOR ASSESSMENT OF FLOODING HAZARDS DUE TO DAM FAILURE," JLD-ISG-2013-01, NRC INTERIM STAFF GUIDANCE (ML13151A153), WASHINGTON, DC, REVISION 0, JULY 29, 2013.FIGURE 3-13 THE JLD-ISG-2013-01 DIAGRAM FOR DETERMINING LEVELS OF ANALYSIS FOR DAM BREAK EVALUATION PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT~ Paul C. Rizzo Associates, Inc.ENGINEERS
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/ CM
-T 0i.L0 Lf)m 0 z I I I I Vys-I (I)-:~ ~m 0 L-)vi 04 z 3:)
REFERENCE:
FIGURE 3-14 THE JLD-ISG-2013-01 DIAGRAM FOR THE ANALYSIS OF DAM BREACHES AND FAILURES USING THE "VOLUME METHOD" PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORTPaul C. Rizzo Associates, Inc.ENGINEERS
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/ CM IMAGE SOURCE: NRC, 2013b, UNITED STATES NUCLEAR REGULATORY COMMISSION (NRC), "GUIDANCE FOR ASSESSMENT OF FLOODING HAZARDS DUE TO DAM FAILURE," JLD-ISG-2013-01, NRC INTERIM STAFF GUIDANCE (ML13151A153), WASHINGTON, DC, REVISION 0, JULY 29, 2013.
-I.0 tr)r)w-C)z 00I~J(J)LLJ Lii U)--mI 0 04 z 0 FIGURE 3-15 INUNDATION AREA CALCULATED USING'VOLUME METHOD" FOR DAM FAILURE ANALYSIS ASSUMING FAILURE OF ALL UPSTREAM DAMS PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT[rI-IPaul C. Rizzo Associates, Inc.ENGINEERS
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/ CM NOTE: IMAGE SOURCE: ESRI, 2013c, ENVIRONMENTAL SYSTEMS RESEARCH INSTITUTE (ESRI), "ARCGIS IMAGERY," WEBSITE: <http://www.arcgis.com/home/
item.html?id=a5fef63517cd4aO99b437e5571 3d3d54>, DATE ACCESSED:
OCTOBER 18, 2013.
I DRAWN BY I J.S.S. I CHECKEDLB I JML 1-30-14 I CAD FILE IJPS 1-30-14 NUMBER 13-5031-A22 I0129141 APPROVED BlY 1 012914 1 APPROVED BY Beginning of Rainfall (Peak Rainfall Intensity)
Flooding Deeper Than 0.5 ft at Some Doors to Safety-Related Buildings on the Powerblock 3 Flood Depths 3 Near Doors to Safety-related Buildings on the Powerblock Are Below 0.5 ft End of Rainfall Initiation of Site Preparation Procedures 1 4------ ------ -------- W -----------
I Period of Inundation 2 Recession of Water from Site 0 7 1 6 I I' I I-1/ ,I ,' <5 minutes! I* I I I Flooding Event Time (hours)NOTES: 1. NRC JLD-ISG-2012 (NRC, 2012C) USES THE PHRASE "SITE PREPARATION FOR FLOOD EVENTS" FOR CONDITIONS THAT, WHEN MET, INITIATE FLOOD PROCEDURES OR NOTIFICATION OF IMPENDING FLOOD. A MORE GENERAL TERM OF "INITIATION OF SITE PREPARATION PROCEDURES" IS USED HERE.2. THE TIMING OF FLOOD DEPTHS AT EACH DOOR IS UNIQUE. THE TIMES INDICATED ARE INTENDED TO BE REPRESENTATIVE AND BOUNDING OF THE DURATION OF FLOODING.3. 0.5 FT REPRESENTS THE DIFFERENCE BETWEEN THE GRADE ELEVATION (1,099.5 FT)AND THE FLOOR ELEVATION (1,100 FT) FOR BUILDINGS ON THE POWERBLOCK.
REEiRENCE:
NUCLEAR REGULATORY COMMISSION (NRC), 2012C, "GUIDANCE FOR PERFORMING THE INTEGRATED ASSESSMENT FOR EXTERNAL FLOODING," JLD-ISG-2012-05, NRC INTERIM STAFF GUIDANCE (ML12311A214), WASHINGTON DC, REVISION 0, NOVEMBER 30, 2012.FIGURE 4-1 DURATION OF FLOODING FOR THE LIP FLOOD ANALYSIS PREPARED FOR WOLF CREEK FLOOD HAZARD REEVALUATION REPORT FPaul C. Rizzo Associates, Inc.ENGINEERS
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/ CM APPENDIX A -FLO-2D PRO SOFTWARE QUALIFICATIONS Flood Hazard Reevaluation Report 135031/14 Rev. 0 (February 10, 2014)
FLO-2D PRO MODELING SOFTWARE QUALIFICATIONS The FLO-2D Pro computer program was developed by FLO-2D Software, Inc., Nutrioso, Arizona. FLO-2D Pro is a combined two-dimensional (2D) hydrologic and hydraulic model that is designed to simulate river overbank flows, as well as unconfined flows over complex topography and variable roughness, split channel flows, and urban flooding.
FLO-2D is a FEMA-approved software (FLO-2D, 2012). FLO-2D Pro is a physical process model that routes rainfall-runoff and flood hydrographs over unconfined flow surfaces using the dynamic wave approximation to the momentum equation.
The model has components to simulate riverine flow, including flow through culverts, street flow, buildings and obstructions, levees, sediment transport, spatially variable rainfall and infiltration and floodways.
Application of the model requires knowledge of the site, the watershed, and engineering judgment.
This software has been used to simulate local intense precipitation, propagation of storm surge, seiches, and riverine flow through overland flow and channels to establish stillwater levels at various flood hazard reevaluation project sites.The major design inputs to the FLO-2D Pro computer model are digital terrain model of the land surface, inflow hydrographs, and/or rainfall data, Manning's roughness coefficient, and soil hydrologic properties, such as the SCS curve number. The digital terrain model of the land surface is used in creating the elevation grid system over which flow is routed. The specific design inputs depend on the modeling purpose and the level of detail that is desired.This FLO-2D Pro Overland Flow component simulates overland flow and computes flow depth, velocities, impact forces, static pressure, and specific energy for each grid. Predicted flow depth and velocity between grid elements represent average hydraulic flow conditions computed for a small time step. For unconfined overland flow, FLO-2D applies the equations of motion to compute the average flow velocity across a grid element (cell) boundary.By using a 2D model, floodwater is routed in a natural manner without being "forced" to flow in predefined directions.
This allows for a more accurate flood analysis than is possible with one-dimensional (I D) models. The FLO-2D Reference Manual (FLO-2D, 2012) describes the FLO-2D model as follows: "FLO-2D is a physical process model that routes rainfall-runoff and flood hydrographs over unconfined flow surfaces or in channels using the dynamic wave Flood Hazard Reevaluation Report A-1 135031/14 Rev. 0 (February 10, 2014) RP CZ approximation to the momentum equation." Additionally, the FLO-2D Basic model is approved by FEMA for use in Flood Insurance Studies (FEMA, 2013; FLO-2D, 2012).NRC JLD-ISG-2013-01 (NRC, 2013a) provides guidance for dam failure analysis.
Within this guidance, the NRC comments about the advantages of 2D modeling methodologies.
These comments, though directed towards dam failure modeling within the context of NRC JLD-ISG-2013-01 (NRC, 2013a), provide a perspective on 2D modeling that is relevant for an LIP analysis as well. Section 9.1.2 of NRC JLD-ISG-2013-01 (NRC, 2013a) states: "In fact, flood flows through extremely flat and wide flood plains may not be modeled adequately as one-dimensional flow. Velocity of the flow across the floodplain may be just as large as that of flow down the channel. If this occurs, a two-dimensional flow model will better simulate the physical processes." Section 9.2 of NRC JLD-ISG-2013-01 (NRC, 2013a) states: "In general, as the flood plain widens, one-dimensional analysis becomes less reliable.Accurate estimates of flood elevation in areas of changing topography and near large objects (i.e. buildings and other structures) in the flow field will typically require localized two-dimensional analysis, in areas of particular interest or sensitivity." Section 9.2 of NRC JLD-ISG-2013-01 (NRC, 2013a) further gives the NRC staff position as: "For estimating inundation at or near a NPP [Nuclear Power Plant] site, two-dimensional models are generally preferred by the NRC staff. However, use of one-dimensional models may be appropriate in some cases. Therefore, use of one-dimensional models will be accepted on a case-by-case basis, with appropriate justification." As a 2D model that simulates rainfall runoff, FLO-2D is sufficient for meeting the guidance presented in NRC NUREG/CR-7046 (NRC, 2011) for flooding analyses.Flood Hazard Reevaluation Report A-2 135031/14 Rev. 0 (February 10, 2014) F C Y Z