L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident

PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident

ML14086A628
Person / Time
Site:	Prairie Island
Issue date:	03/27/2014
From:	Davison K Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-14-028
Download: ML14086A628 (40)

Text

(l Xcel Energy Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089-9642 L-PI-14-028 MAR 2 7

• 2014 10 CFR 50.54(f)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Operating License Nos. DPR-42 and DPR-60 PINGP Seismic Hazard and Screening Report (CEUS Sites). Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

References:

1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012, ADAMS Accession No. ML12056A046.

2. NRC Letter, "Endorsement of Electric Power Research Institute Final Draft Report 1025287, 'Seismic Evaluation Guidance,"' dated February 15, 2013, ADAMS Accession No. ML12319A074.

3. Electric Power Research Institute (EPRI) Report Number 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," dated November 2012, ADAMS Accession No. ML12333A170.

4. Nuclear Energy Institute (NEI) letter to NRC, "Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations," dated April 9, 2013, ADAMS Accession No. ML13101A379.

5. NRC Letter, "Electric Power Research Institute Final Draft Report XXXXXX,

'Seismic Evaluation Guidance: Augmented Approach for the Resolution of F~,Jkushima Near-Term Task Force Recommendation 2.1: Seismic,' As an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations," dated May 7, 2013, ADAMS Accession No.

M L 131 06A331 .

I Document Control Desk Page 2

6. NSPM Letter to NRC, "PINGP's Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated April 29, 2013, ADAMS Accession No. ML13120A058.

7. NSPM Letter to NRC, "NSPM's Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites," dated September 12, 2013, ADAMS Accession No. ML13256A069.

On March 12, 2012, the Nuclear Regulatory Commission (NRC) Staff issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 contains specific Requested Actions, Requested Information, and Required Responses associated with Near-Term Task Force (NTTF)

Recommendation 2.1, Seismic Evaluations. Enclosure 1 of Reference 1 requested each addressee in the Central and Eastern United States (CEUS) to submit a written response consistent with the requested seismic hazard evaluation information (items 1 through 7) by September 12, 2013. On February 15, 2013, the NRC issued Reference 2, endorsing the Reference 3 industry guidance for responding to Reference 1. Section 4 of Reference 3 identifies the detailed information to be included in the seismic hazard evaluation submittals.

On April 9, 2013, NEI submitted Reference 4 to the NRC, requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the EPRI (2004, 2006) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 5, the NRC agreed with the proposed path forward.

Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, submitted the description of subsurface materials and properties, and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) for the Prairie Island Nuclear Generating Plant (PINGP) in Reference 7.

The enclosure to this letter provides the Seismic Hazard Evaluation and Screening Report for PINGP in accordance with the schedule identified in Reference 4. This letter completes the commitment made by NSPM in the Reference 6 letter to submit the remaining information described in Section 4 of Reference 3.

If there are any questions or if additional information is needed, please contact Ms. Jennie Wike, Licensing Engineer, at 612-330-5788.

Document Control Desk Page 3 Summary of Commitments This letter proposes no new commitments and no revisions to existing commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on MAR . 2 7 2014

~~J~~

Kevin Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Director of Nuclear Reactor Regulation (NRR), US NRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC

ENCLOSURE Prairie Island Nuclear Generating Plant Units 1 and 2 Seismic Hazard Evaluation and Screening Report 36 Pages Follow

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report Table of Contents 1.0 Introduction ................................................................................................ .......................... 1 2.0 Seismic Hazard Reevaluation .............................. ................................................................ 2 2.1 Regional and Local Geology ............................................................................................. 2 2.2 Probabilistic Seismic Hazard Analysis .............................................................................. 3 2.2.1 Probabilistic Seismic Hazard Analysis Results ............ .... ........................................... 3 2.2.2 Base Rock Seismic Hazard Curves ............................................................................ 4 2.3 Site Response Evaluation ................................................................................................. 4 2.3.1 Description of Subsurface Material ............................................................................. 4 2.3.2 Development of Base Case Profiles and Nonlinear Material Properties ..................... 6 2.3.2.1 Shear Modulus and Damping Curves ......................................................... ........ 9 2.3.2.2 Kappa .......................*.......................................................................................... 9 2.3.3 Randomization of Base Case Profiles ......... ........................................ ...................... 10 2.3.4 Input Spectra ............................................................................................................. 10 2.3.5 Methodology ............................................................................................................. 11 2.3.6 Amplification Functions ............................................................................................. 11 2.3. 7 Control Point Seismic Hazard Curves ....................................................................... 15 2.4 Control Point Response Spectra ....................................................................................... 16 3.0 Safe Shutdown Earthquake Ground Motion ........................................................................ 18 3.1 SSE Description of Spectral Shape ................................................................................. 18 3.2 Control Point Elevation ........................................................... ..... .................................... 19 4.0 Screening Evaluation ..........................................................................................................20 4.1 Risk Evaluation Screening (1 to 10 Hz) ............... .. ............................................... ........... 20 4.2 High Frequency Screening (> 10 Hz) .............. ................................................................. 20 4.3 Spent Fuel Pool Evaluation Screening (1 to 10 HZ) ......................................................... 20 5.0 Interim Actions .............................................................................................. ...................... 20 6.0 Conclusions ...................................................................................................,..................... 21 7.0 References ................. ..................................... .. ..................................................................21 Appendix A ................................................................................................................................24

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report List of Tables 5

TABLE 2.3.1-1 ...........................................................................................................................

6 TABLE 2.3.2-1 ...........................................................................................................................

............... ............. 10 TABLE 2.3.2-2 ................................................................ ..............................

17 TABLE 2.4-1 .............................................................................................................................

............... ............... ..... 19 TABLE 3.1-1 ..........................................................................................

24 TABLE A-1a ..................... ..... ......................................................... ... ........................................

25 TABLE A-1b ..................................................................................................... .. .......................

............... . 26 TABLE A-1c ......................... .........................*............................................................

26 TABLE A-1d ..............................................................................................................................

............... ............... .. 27 TABLE A-1e ............................................................................... ...............

27 TABLE A-1f ...............................................................................................................................

............... ............... ............... ...... 28 TABLE A-1g ...........................................................................

29 TABLE A-2 ..................... ... ........................................................................................................

30 TABLE A2-b1 ............................................................................................................................

.............. 31 TABLE A2-b2 ............................................................ ..... .............................................

List of Figures Figure 2.3.2-1 ............. ............. ............. ............. ............. ............. ............. ............. . 9 12 Figure 2.3.6-1 ................................................................................ ...........................................

............... ............... ... 14 Figure 2.3.6-2 ..........................................................................................

16 Figure 2.3.7-1 .......... .................................................................................................................

............... ............... .. .. .. ............... . 18 Figure 2.4-1 ............ .. ............................................................

..... 33 Figure 1................................................................................................................. ...............

33 Figure 2 .....................................................................................................................................

............. 34 Figure 3 ........................................................................................................................

34 Figure 4 .....................................................................................................................................

ii

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report 1.0 Introduction Following the accident at the Fukushima Daiichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC Commission established a Near-Term Task Force (NTTF) to conduct a systematic review of NRC processes and regulations and to determine if the agency should make additional improvements to its regulatory system. The NTTF developed a set of recommendations intended to clarify and strengthen the regulatory framework for protection against natural phenomena. Subsequently, the NRC issued a 50.54(f) letter that requests information to assure that these recommendations are addressed by all U.S. nuclear power plants. The 50.54(f) letter requests that licensees and holders of construction permits under 10 CFR Part 50 reevaluate the seismic hazards at their sites against present-day NRC requirements. Depending on the comparison between the reevaluated seismic hazard and the current design basis, the result is either" no further risk evaluation or the performance of a seismic risk assessment. Risk assessment approaches acceptable to the staff include a seismic probabilistic risk assessment (SPRA), or a seismic margin assessment (SMA). Based upon the risk assessment results, the NRC staff will determine whether additional regulatory actions are necessary.

This report provides the information requested in items (1) through (7) of the "Requested Information" section and Attachment 1 of the 50.54(f) letter pertaining to NTTF Recommendation 2.1 for the Prairie Island Nuclear Generating Plant, located in Goodhue County, Minnesota. In providing this information, Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, followed the guidance provided in the Electric Power Research Institute (EPRI) guidance document titled "Seismic Evaluation Guidance: Screening , Prioritization, and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic" (Reference 7.3). The EPRI guidance document titled "Augmented Approach, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1:

Seismic" (Reference 7.11), has been developed as the process for evaluating critical plant equipment as an interim action to demonstrate additional plant safety margin, prior to performing the complete plant seismic risk evaluations.

The original geologic and seismic siting investigations for Prairie Island Nuclear Generating Plant (PINGP) were performed as described in Updated Safety Analysis Report (USAR) Section 2.5 and 2.6 (Reference 7.2) and USAR Section 1.2 (Reference 7.13) . PINGP was designed and constructed to comply with Northern States Power's, the predecessor to NSPM, understanding of the intent of the AEC (Atomic Energy Commission) General Design Criteria for Nuclear Power Plant Construction Permits, as proposed on July 10, 1967. Since the construction of the plant was significantly completed prior to the issuance of the February 20, 1971, 10 CFR 50, Appendix A General Design Criteria, the plant was not reanalyzed and the Final Safety Analysis Report (FSAR) was not revised to reflect these later criteria. However, the AEC Safety Evaluation Report acknowledged that the AEC staff assessed the plant, as described in the FSAR, against the Appendix A design criteria and "are satisfied that the plant design generally conforms to the intent of these criteria." Original plant (all plant structures except D5/D6 Diesel Generator Building) building seismic criteria are described in terms of the Operational Basis Earthquake (OBE) and Design Basis Earthquake (DBE). For the D5/D6 Diesel Generator Building, the seismic criteria are described in terms of the OBE and Safe Shutdown Earthquake (SSE). The DBE is synonymous with SSE. The DBE is based upon a maximum horizontal ground acceleration of 0.12 g and the response spectra are given on Plate 4.6 in USAR Appendix E (Reference 7.14, Section 12.2.1.3.5).

1

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report d in the SPID (Reference In response to the 50.54(f) letter and following the guidance provide ing purposes, a Ground Motion 7.3), a seismic hazard reevaluation was performed. For screen Response Spectrum (GMRS) was developed.

tions will be performed.

Based on the results of the screening evaluation, no further evalua 2.0 Seismic Hazard Reevaluation on the west bank of the PINGP is located within the city limits of Red Wing, Minnesota Section 2.2.1). PINGP is a low island terrace associated with Mississippi River (Reference 7.2, of the lowland by the Vermillion the Mississippi River flood plain. It is separated from other parts I uppermost bedrock unit at the River on the west, and by the Mississippi River on the east. The ion. Its thickness at this site is sandstone and is believed to be part of the Franconia format total measured thickness of the I location is unknown, but would be much less than 180 feet, the nia formation are several Franconia formation in complete sections. Underneath the Franco minor shale horizons.

hundred feet of lower Cambrian and Precambrian sandstone with I

is no evidence of ancient The plant is located in a region of very low seismic activity. There located approximately 6 and 13 inactive faulting within six miles of the site. Inactive faults are I faults in recent geological miles from the site. No activity has occurred along either of these and the regional tectonics, it times (Reference 7.2, Section 2.5.1). Based on the seismic history uake motion during the is anticipated that the site will not experience any significant earthq for expecting ground motion of economic life of the nuclear facility. Historically, there is no basis

, the plant is designed to respond more than a few percent of gravity. However, for conservatism

, with no loss of function.

elastically to earthquake ground motion as high as 6 percent gravity if ground motions reach as Provisions have also been made for safe shutdown of the reactor (Reference 7.2, Section 2.6.1 ).

high as 12 percent of gravity in the overburden soils at the site d in the PINGP Updated Safety Further detail on the seismic design basis for PINGP is provide 7.2).

Analysis Report (USAR) Sections 2.2, 2.5 and 2.6 (Reference 2.1 Regional and Local Geolo gy oldest bedrock in the Precambrian granite, gneiss, schist, and volcanics comprise the rock is overlai n by as much as 800ft of Paleozoic Minnesota-Wisconsin region. The basement ions origina lly presen t in the region have been sandstone, shale and dolomite. Younger format aphy has been develo ped on the exposed bedrock removed by erosion, and an irregular topogr parts of Wisconsin, bedrock is surface. Except for local areas in southeastern Minnesota and contrast, the extreme concealed under 100 to 300 feet of Pleistocene glacial drift. In g the site vicinity , is covere d by only a thin veneer of drift.

southeastern tip of Minnesota, includin referred to by glacial geologists.

It is therefore considered a part of the "driftless" area commonly Wisconsin, the unconsolidated In this driftless area of Minnesota and central and southwestern l soil (Reference 7.2, Section materials consist primarily of loess, recent alluvium, and residua 2.5.2).

2

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report alluvium ranges The site sub-surface soil consists of permeable sandy alluvium. The sandy the alluvial soils from 158 to 185 feet. Several hundred feet of sound sandstone underlie (Reference 7.2, Section 2.5.1).

a valley about three miles The Mississippi River flood plain near the plant area is confined within both sides of the valley to a wide. Rocky bluffs and heavily forested slopes rise abruptly from ding the valley reach elevations height of about 300 feet. The uplands immediately surroun deeply trenche d by numero us streams ranging from approximately 1000 to 1200 feet. They are emptying into the Mississippi River (Reference 7.2, Section 2.5.3).

2.2 Probabilistic Seismic Hazard Analysis 2.2.1 Probabilistic Seismic Hazard Analysis Results SPID (Reference 7.3), a In accordance with the 50.54(f) letter and following the guidance in the recently developed probabilistic seismic hazard analysis (PSHA) was completed using the SSC) for Nuclea r Central and Eastern United States Seismic Source Characterization (CEUS-Model (GMM) for the Facilities (Reference 7.4) together with the updated EPRI Ground-Motion de of 5.0 was used, as CEUS (Reference 7.5). For the PSHA, a lower-bound momen t magnitu specified in the 50.54(f) letter.

e of 400 miles I

For the PSHA, the CEUS-SSC background seismic sources out to a distanc

. This distanc e exceed s the 200 mile (320 km)

(640 km) around PINGP were included recommendation contained in Referen ce 7.19 and was chosen for comple teness. Background I sources included in this site analysis are the following:

1. Illinois Basin Extended Basement (IBEB) I

2. Mesozoic and younger extended prior- wide (MESE-W)

3. Midcontinent-Craton alternative A (MIDC_A) I

4. Midcontinent-Craton alternative B (MIDC_B)

5. Midcontinent-Craton alternative C (MIDC_C)

6. Midcontinent-Craton alternative D (MIDC_D) I

7. Non-Mesozoic and younger extended prior- narrow (NMESE-N)

8. Non-Mesozoic and younger extended prior- wide (NMESE-W) I

9. Study region (STUDY_R)

For sources of large magnitude earthquakes, designated as Repeated Large Magnitude I within 1,000 km of Earthquake (RLME) sources in Reference 7.4, the following sources lie the site and were included in the analysis:

I

1. Commerce

2. Eastern Rift Margin Fault northern segment (ERM-N)

3. Eastern Rift Margin Fault southern segment (ERM-S)

4. New Madrid Fault System (NMFS)

5. Wabash Valley 3

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report the mid-continent version of the updated For each of the above background and RLME sources, CEUS EPRI GMM was used.

2.2.2 Base Rock Seismic Hazard Curves ic hazard curves are not provided as Consistent with the SPID (Reference 7.3), base rock seism has been used. Seismic hazard curves the site amplification approach referred to as Method 3 contro l point elevation.

are shown below in Section 2.3.7 at the SSE 2.3 Site Response Evaluation 1 of the March 12, 2012, 10 CFR Following the guidance contained in Seismic Enclosure ence 7.3) for nuclear power plant sites 50.54(f) Request for Information and in the SPID (Refer c), a site response analysis was that are not founded on hard rock (defined as 2.83 km/se performed for PINGP.

2.3.1 Description of Subsurface Material terrace associated with the PINGP is located near Red Wing, Minnesota on an island used to create the site geologic profile at the Mississippi River flood plain. The basic information profile was developed using information PINGP is shown in Table 1 of Reference 7.7. This about 180ft (55 m) of soils overlying about 3,900 documented in Reference 7.7 and consists of ted in Refere nce 7. 7, the SSE Control Point is ft (1, 189 m) of firm sedimentary rock. As indica the surface.

defined at the surface, and the profile was modeled up to y from Reference 7.7:

The following description of the site properties is taken directl Mississippi River flood plain. It "Prairie Island is a low island terrace associated with the llion River on the west, and by is separated from other parts of the lowland by the Vermi ions range from approximately the Mississippi River on the east. Ground surface elevat I Other lowland areas near the 675 to 706 feet. Most of Prairie Island is under cultivation.

site are forested or covered by swamp vegetation.

I within a valley about three "The Mississippi River flood plain in this area is confined abruptly from both sides of the miles wide. Rocky bluffs and heavily forested slopes rise iately surrounding the valley I

valley to a height of about 300 feet. The uplands immed feet. They are deeply reach elevations ranging from approximately 1000 to 1200 trenched by numerous streams emptying into the Missis sippi River. I alluvial soils which were "The overburden materials at the site are permeable sandy recent river sedim entatio n. Preliminary borings deposited as glacial outwash and as 158 to 185 feet thick. The indicated that the overburden soils at the site vary from is sands tone and is believ ed to be part of the uppermost bedrock unit at the site at this locatio n is unkno wn, but would be much less Franconia formation. Its thickness onia formation in complete than 180 feet, the total measured thickness of the Franc l hundred feet of lower sections. Underneath the Franconia formation are severa horizons.

Cambrian and Precambrian sandstone with minor shale 4

Prairie Island Nuclea r Generating Plant Seismi c Hazard and Screening Report I "The final design called for dewatering the foundation area to elevation 642 ft, I the area using the excavation of the area to elevation 645 ft, and re-compacting and compacted to excavated material as fill. The fill was placed in three inch layers I ation of State Highwa y 100% maxim um density as determ ined by the Americ an Associ least 85% relative densit y-Officials Test Designation T 180- 57. This corresp onds to at the figure above which soils of this type will not liquefy. The fill was replaced and I founda tion slabs were placed."

compa cted to the appropriate elevations upon which the PINGP.

Table 2.3.1-1, below, shows the geotec hnical properties for the TABLE 2.3.1-1 nce 7.7)

Summ ary of Geotechnical Profile Data for the PINGP (Refere I

Shear Poisson's Soil/Ro ck Description Density Depth Wave Compr ession al Ratioc I (pcf)

Range Velocit y Wave Velocit y (fps) (fps)c

_{feet) 0 SSE control point (at --- --- --- --- I surface) 0.37b 0-50 8

Compa cted Site Fill 125b 2, 150b 4,750b I

compo sed of fine to Medium sand with gravel and occasional cobbles.

I 50-180 Pleisto cene Glacial 130 2,860 6,300 0.37 I (outwash of dense to very dense sand I with gravel) 180- Cambr ian and 150- 5,020 9,200 0.28 I Precambrian 155 4100 sandst one with minor I shale horizon s 170d 11200d 18,000d 0.18d 4100+ Precambrian granite basem ent rock Turbine, and Auxiliary Buildings varies NOTES : The bottom of the base mat of the combined Reactor, from 5 ft to 30ft below the surface elevation of the site.

a If thicknesses vary across site, indicate range in thickness.

excavation and compaction. Actual b Conservatively used from the 20-50 ft. soil column previous to values would be improved but are not reported in the USAR.

c Compressional-wave velocity and Poisson's ratio should be reported if those were the measurements taken at the site, and ranges in measur ements should be reported. If shear-wave velocity measurements were taken, with ranges reporte d , the compre ssional-wave velocities and Poisson's ratio are not needed.

dAssumed values as stated in USAR Appendix E, Plate 4.1.

5

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report 2.3.2 Development of Base Case Profiles and Nonlinear Material Properties unit weights Table 2.3.1-1 (Reference 7.7) shows the recommended shear-wave velocities and hy. As indicated in Referenc e 7.7, the SSE along with depth ranges and corresponding stratigrap compact ed fill with a thicknes s of 50ft (15 m)

Control Point is located at the surface at the top of m/s). Mean base-cas e shear-wa ve with an estimated shear-wave velocity of 2,150 ftls (655 2.3.1-1 to Precamb rian baseme nt at a depth velocities and unit weights were taken from Table on compres sional-w ave refractio n surveys of about 4,100 ft (1 ,250 m). The velocities are based and assumed Poisson ratios.

were used:

To accommodate epistemic uncertainty in shear-wave velocities two scale factors ne glacial outwash , reflecting measure d compres sional-1.25 for the compacted fill and Pleistoce 1.57 for the Cambria n and Precamb rian sandston e wave velocities and Poisson ration, and formation, reflecting assumed shear-wa ve velocities . Profiles extended to a depth below the I (P1, P2, SSE of 4,100 ft (1 ,250 m), randomized +/- 1,230ft(+/- 375 m). The base-case profiles and listed in Table 2.3.2-1. The depth randomi zation and P3) are shown in Figure 2.3.2-1 reflects+/- 30% of the depth and was included to provide a realistic broadening of the I sites rather than reflect actual random variation s to basement fundamental resonance at deep a footprint. The scale factors of 1.25 and 1.57 reflect a cr 1n of about shear-wave velocities across implies a 1.28 0.20 and 0.35, based on the SPID (Referen ce 7.3) 10th and 90th fractiles which I

scale factor on cr 11

• TABLE 2.3.2-1 I

Geologic Profile and Estimated Layer Thicknesses for PINGP Profile 1 Profile 2 Profile 3 Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) 0 1720 0 2687 0 2150 5.0 5.0 1720 5.0 5.0 2687 5.0 5.0 2150 5.0 10.0 1720 5.0 10.0 2687 5.0 10.0 2150 5.0 15.0 1720 5.0 15.0 2687 5.0 15.0 2150 5.0 20.0 1720 5.0 20.0 2687 5.0 20.0 2150 5.0 25.0 1720 5.0 25.0 2687 5.0 25.0 2150 5.0 30.0 1720 5.0 30.0 2687 5.0 30.0 2150 5.0 35.0 1720 5.0 35.0 2687 5.0 35.0 2150 5.0 40.0 1720 5.0 40.0 2687 5.0 40.0 2150 5.0 45.0 1720 5.0 45.0 2687 5.0 45.0 2150 5.0 50.0 1720 5.0 50.0 2687 5.0 50.0 2150 2860 5.0 55.0 2288 5.0 55.0 3575 5.0 55.0 5.0 60.0 2288 5.0 60.0 3575 5.0 60.0 2860 5.0 65.0 2288 5.0 65.0 3575 5.0 65.0 2860 5.0 70.0 2288 5.0 70.0 3575 5.0 70.0 2860 5.0 75.0 2288 5.0 75.0 3575 5.0 75.0 2860 5.0 80.0 2288 5.0 80.0 3575 5.0 80.0 2860 5.0 85.0 2288 5.0 85.0 3575 5.0 85.0 2860 6

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report Profile 2 Profile 3 Profile 1 Vs(ft/s) thickness(ft) depth (ft) Vs(ftls) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) 5.0 90.0 2288 5.0 90.0 3575 5.0 90.0 2860 5.0 95.0 2288 5.0 95.0 3575 5.0 95.0 2860 5.0 100.0 2288 5.0 100.0 3575 5.0 100.0 2860 5.0 105.0 2288 5.0 105.0 3575 5.0 105.0 2860 5.0 110.0 2288 5.0 110.0 3575 5.0 110.0 2860 5.0 115.0 2288 5.0 115.0 3575 5.0 115.0 2860 5.0 120.0 2288 5.0 120.0 3575 5.0 120.0 2860 5.0 125.0 2288 5.0 125.0 3575 5.0 125.0 2860 5.0 130.0 2288 5.0 130.0 3575 5.0 130.0 2860 5.0 135.0 2288 5.0 135.0 3575 5.0 135.0 2860 5.0 140.0 2288 5.0 140.0 3575 2860 5.0 140.0 5.0 145.0 3575 I

5.0 145.0 2860 5.0 145.0 2288 5.0 150.0 2288 5.0 150.0 3575 5.0 150.0 2860 5.0 155.0 2860 5.0 155.0 2288 5.0 155.0 3575 I 5.0 160.0 2288 5.0 160.0 3575 5.0 160.0 2860 2288 5.0 165.0 3575 5.0 165.0 2860 5.0 165.0 I 5.0 170.0 2288 5.0 170.0 3575 5.0 170.0 2860 5.0 175.0 2288 5.0 175.0 3575 5.0 5.0 175.0 180.0 2860 2860 5.0 180.0 2288 5.0 180.0 3575 I 10.0 190.0 3197 10.0 190.0 7881 10.0 190.0 5020 10.0 200.0 5020 5020 10.0 10.0 200.0 210 .0 3197 3197 10.0 10.0 200.0 210.0 7881 7881 I

10.0 210 .0 10.0 220.0 3197 10.0 220.0 7881 10.0 220.0 5020 10.0 230 .0 3197 10.0 230.0 7881 10.0 230.0 5020 10.0 240.0 3197 10.0 240.0 7881 10.0 240.0 5020 10.0 250.0 3197 10.0 250.0 7881 10.0 250.0 5020 10.0 260 .0 3197 10.0 260.0 7881 10.0 260 .0 5020 10.0 270.0 3197 10.0 270.0 7881 10.0 270.0 5020 10.0 280 .0 3197 10.0 280.0 7881 10.0 280.0 5020 10.0 290.0 3197 10.0 290.0 7881 10.0 290.0 5020 10.0 300.0 3197 10.0 300.0 7881 10.0 300.0 5020 10.0 310 .0 3197 10.0 310.0 7881 10.0 310 .0 5020 10.0 320.0 3197 10.0 320.0 7881 10.0 320.0 5020 10.0 330.0 3197 10.0 330.0 7881 10.0 330.0 5020 10.0 340.0 3197 10.0 340.0 7881 10.0 340.0 5020 10.0 350.0 3197 10.0 350.0 7881 10.0 350.0 5020 10.0 360.0 3197 10.0 360.0 7881 10.0 360.0 5020 10.0 370.0 3197 10.0 370.0 7881 10.0 370.0 5020 10.0 380.0 3197 10.0 380.0 7881 10.0 380.0 5020 10.0 390.0 3197 10.0 390.0 7881 10.0 390 .0 5020 10.0 400.0 3197 10.0 400.0 7881 10.0 400.0 5020 7

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Repor t Profile 2 Profile 3 Profile 1 depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) 10.0 410.0 3197 10.0 410.0 7881 10.0 410.0 5020 10.0 420.0 3197 10.0 420.0 7881 10.0 420.0 5020 10.0 430.0 3197 10.0 430.0 7881 10.0 430.0 5020 440.0 3197 10.0 440.0 7881 10.0 440.0 5020 10.0 10.0 450.0 3197 10.0 450.0 7881 10.0 450.0 5020 10.0 460.0 3197 10.0 460.0 7881 10.0 460.0 5020 470.0 3197 10.0 470.0 7881 10.0 470.0 5020 10.0 480.0 3197 10.0 480.0 7881 10.0 480.0 5020 10.0 10.0 490.0 3197 10.0 490.0 7881 10.0 490 .0 5020 500 .0 3197 10.0 500.0 7881 10.0 500.0 5020 10.0 154.9 654.9 3197 154.9 654.9 7881 154.9 654.9 5020 164.0 819.0 3197 164.0 819.0 7881 164.0 819.0 5020 164.0 983.0 3197 164.0 983.0 7881 164.0 983.0 5020 164.0 1147.0 7881 I

164.0 1147.0 5020 164.0 1147.0 3197 164.0 1311 .1 3197 164.0 1311 .1 7881 164.0 1311.1 5020 164.0 1475.1 5020 164.0 1475.1 3197 164.0 1475.1 7881 I

164.0 1639.2 3197 164.0 1639.2 7881 164.0 1639.2 5020 7881 164.0 1803.2 5020 164.0 1803.2 1967.2 3197 3197 164.0 164.0 1803.2 1967.2 7881 I

164.0 1967.2 5020 164.0 164.0 2131 .3 3197 164.0 2131.3 7881 164.0 2131 .3 5020 164.0 2295.3 5020 164.0 2295.3 3197 164.0 2295.3 7881 I 164.0 2459.4 3197 164.0 2459.4 7881 164.0 2459.4 5020 2623.4 3197 164.0 2623.4 7881 164.0 2623.4 5020 164.0 164.0 2787.5 5020 164.0 2787.5 3197 164.0 2787 .5 7881 I 164.0 2951 .5 7881 164.0 2951.5 3115.5 5020 5020 164.0 164.0 2951.5 3115.5 3197 3197 164.0 3115.5 7881 I 164.0 164.0 3279.6 3197 164.0 3279.6 7881 164.0 3279.6 5020 164.0 3443.6 3197 164.0 3443.6 7881 164.0 3443.6 5020 164.0 3607.7 3197 164.0 3607.7 7881 164.0 3607 .7 5020 164.0 3771 .7 3197 164.0 3771 .7 7881 164.0 3771.7 5020 164.0 3935.7 3197 164.0 3935.7 7881 164.0 3935.7 5020 164.0 4099.8 3197 164.0 4099.8 7881 164.0 4099.8 5020 3280.8 7380.6 9285 3280 .8 7380.6 9285 3280.8 7380.6 9285 I

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Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report Vs profiles for Prairie Island Site Vs (ft/sec) 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0

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Figure 2.3.2-1. Shear-w ave velocity profiles for PINGP site.

2.3.2.1 Shear Modulus and Damping Curves I I

available for the No site-specific nonline ar dynami c material properties for the soils were l (glacial outwash ) over the upper 180ft (55 m) was PINGP. The fill and firm soil materia assume d to have behavio r that could be modele d with either EPRI cohesio n less soil or I 7.3). The rock material Peninsu lar Range G/Gmax and hysteretic damping curves (Refere nce between 180ft (55 m) and 500ft (152 m) was assume d to have behavio r that could be modele d I potential for either case as either non-linear (model M1) or linear (model M2). To represe nt this modulus reduction in the top 320ft (97.5 m) of firm rock at the PINGP site, two sets of shear and hystere tic damping curves were used. Consist ent with the SPID (Reference 7.3), the EPRI I represent the upper soil and rock curves (model M1) were considered to be appropr iate to range nonlinearity likely in the materials at this site and Peninsu lar Range analyse s (firm rock) (model M2) was assumed to represe nt an equally (soil) and linear plausible alternative soil I

firm rock material, the low and rock response across loading level. For the linear analyse s of the strain damping from the EPRI rock curves were used as the constan t dampin g values in the I upper 500ft.

2.3.2.2 Kappa rock over hard For the PINGP profile of about 4,100 ft (1 ,250 m) of fill, soils and firm based on the low-stra in dampin g in the hystere tic reference rock, the estimat es of kappa were m) plus the assump tion of a constan t hysteretic dampin g curves over the top 500ft (152 ng firm rock profile in addition to a kappa value of dampin g of 1.25 (QS of 40) for the remaini an upper bound of 0.04 s (Refere nce 7.3). For base-ca se 0.006 s for hard rock conditioned with 9

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report profiles P1, P2, and P3, the kappa contributions from the profiles were 0.024 s, 0.036 s, and 0.015 s, respectively. The total kappa values, after adding the hard reference rock value of 0.006 s, were 0.030 s, 0.040 s (upper bound), and 0.021 s, respectively (see Table 2.3.2-2).

About the mean base-case (P1) the epistemic uncertainty in kappa is only approximately 3°/o, similar to that of corresponding firm rock velocities. While the epistemic uncertainty in kappa should be larger than that of velocity, additional epistemic uncertainty in profile damping (kappa) is accommodated at design loading levels through two sets of modulus reduction and hysteretic damping curves for the soils.

TABLE 2.3.2-2 Kappa Values and Weights Used for Site Response Analyses Velocity Profile Kappa (s)

P1 0.030 P2 0.040 P3 0.021 Velocity Profile Weights P1 0.4 P2 0.3 P3 0.3 G/Gmax and Hysteretic Damping Curves M1 0.5 M2 0.5 2.3.3 Randomization of Base Case Profiles To account for the aleatory variability in dynamic material properties that is expected to occur across a site at the scale of a typical nuclear facility, variability in the assumed shear-wave velocity profiles has been incorporated in the site response calculations. For the PINGP site, random shear wave velocity profiles were developed from the base case profiles shown in Figure 2.3.2-1. Consistent with the discussion in Appendix B of the SPID (Reference 7.3), the velocity randomization procedure made use of random field models which describe the statistical correlation between layering and shear wave velocity. The default randomization parameters developed in Reference 7.15 for the United States Geological Survey (USGS) "A" site conditions were used for this site. Thirty random velocity profiles were generated for each base case profile. These random velocity profiles were generated using a natural log standard deviation of 0.25 over the upper 50ft and 0.15 below that depth. As specified in the SPID (Reference 7.3), correlation of shear wave velocity between layers was modeled using the footprint correlation model. In the correlation model, a limit of+/- 2 standard deviations about the median value in each layer was assumed for the limits on random velocity fluctuations.

2.3.41nput Spectra Consistent with the guidance in Appendix B of the SPID (Reference 7.3), input Fourier amplitude spectra were defined for a single representative earthquake *magnitude (M 6.5) using 10

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report two different assumptions regarding the shape of the seismic source spectrum (single-corner and double-corner). A range of 11 different input amplitudes (median peak ground accelerations (PGA) ranging from 0.01 to 1.5 g) were used in the site response analyses. The characteristics of the seismic source and upper crustal attenuation properties assumed for the analysis of the PINGP site were the same as those identified in Tables 8-4, 8-5, 8-6 and 8-7 of the SPID (Reference 7.3), as appropriate for typical CEUS sites.

2.3.5 Methodology To perform the site response analyses for the PINGP site, a random vibration theory (RVT) approach was employed. This process utilizes a simple, efficient approach for computing site-specific amplification functions and is consistent with existing NRC guidance and the SPID (Reference 7.3). The guidance contained in Appendix 8 of the SPID (Reference 7.3) on incorporating epistemic uncertainty in shear-wave velocities, kappa, non-linear dynamic properties and source spectra for plants with limited at-site information was followed for the PINGP site.

2.3.6 Amplification Functions The results of the site response analysis consist of amplification factors (5% damped pseudo absolute response spectra) which describe the amplification (or de-amplification) of hard reference rock motion as a function of frequency and input reference rock amplitude. The d

amplification factors are represented in terms of a median amplification value and an associate standard deviation (sigma) for each oscillator frequency and input rock amplitude . Consisten t with the SPID (Reference 7.3) a minimum median amplification value of 0.5 was employed in the present analysis. Figure 2.3.6-1 illustrates the median and+/- 1 standard deviation in the predicted amplification factors developed for the eleven loading levels parameterized by the median reference (hard rock) peak acceleration (0.01g to 1.50g) for profile P1 and EPRI soil and rock G/Gmax and hysteretic damping curves. The variability in the amplification factors results from variability in shear-wave velocity, depth to hard rock, and modulus reduction and hysteretic damping curves. To illustrate the effects of nonlinearity at the PINGP soil site, Figure 2.3.6-2 shows the corresponding amplification factors developed with Peninsular Range G/Gmax (soil) and linear (firm rock) and hysteretic damping curves for soil (model M2). Figures 2.3.6-1 and 2.3.6-2 show only a relatively minor difference for the 0.5g loading level and below. Above I the 0.5g loading level, the differences increase mainly in frequencies above 10 Hz to 20 Hz.

Tabulated values of the amplification factors are provided in Appendix A.

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AM PL I FI C ~TIO N , PRRIRIE ISLAND 1 Ml P1K1 M 6. 5 .* 1 CORNER : PAGE 1 OF Z Figure 2.3.6-1 ~ Example suite of amplification factors (5% damping pseudo absolute acceleration spectra) developed for the mean base-case profile (P1 ), EPRI soil and rock modulus reduction and hysteretic damping curves (model M1), and base-case kappa at eleven loading levels of hard rock median peak acceleration values from 0.01 g to 1.50 g. M 6.5 and single-corner source model (Reference 7.3).

12

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report

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I Figure 2.3.6-2. Example suite of amplification factors (5% damping pseudo absolute acceleration spectra) developed for the mean base-case profile (P1), Peninsular Range modulus reduction and hysteretic damping curves for soil and linear site response for rock (model M2), and base-case kappa at eleven loading levels of hard rock median peak e

I acceleration values from 0.01 g to 1.50 g. M 6.5 and single-cor ner source model (Referenc 7.3) .

14

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2.3. 7 Control Point Seismic Hazard Curves The procedure to develop probabilistic site-specific control point hazard curves used in the present analysis follows the methodology described in Section 8 -6.0 of the SPID (Reference 7.3). This procedure (referred to as Method 3) computes a site-specific control point hazard curve for a broad range of spectral accelerations given the site-specific bedrock hazard curve and site specific estimates of soil or soft-rock response and associated uncertainties. This process is repeated for each of the seven spectral frequencies for which ground motion 15

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report equations are available. The dynamic response of the materials below the control point was represented by the frequency- and amplitude-dependent amplification functions (median values and standard deviations) developed and described in the previous section. The resulting control point mean hazard curves for PINGP are shown in Figure 2.3.7-1 for the seven spectral frequencies for which ground motion equations are defined. Tabulated values of mean and fractile seismic hazard curves and site response amplification functions are provided in Appendix A.

Total Mean Soil Hazard by Spectral Frequency at Prairie Island lE-2

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2.4 Control Point Response Spectra The control point hazard curves described above have been used to develop uniform hazard response spectra (UHRS) and the ground motion response spectrum (GMRS). The UHRS were obtained through linear interpolation in log-log space to estimate the spectral acceleration at each spectral frequency for the 1E-4 and 1E-5 per year hazard levels. Table 2.4-1 shows the UHRS and GMRS accelerations for a range of spectral frequencies. The 1E-4 and 1E-5 UHRS are used to compute the GMRS at the control point and are shown in Figure 2.4-1.

16

Prairie Island Nuclear Generatin g Plant Seismic Hazard and Screening Report TABLE 2.4-1 UHRS and GMRS for PINGP Freq. (Hz) 1o-4 UHRS (g) 1o-5 UHRS (g) GMRS (g) 100 3.63E-02 1.29E-01 6.01 E-02 90 3.65E-02 1.29E-01 6.02E-02 80 3.67E-02 1.29E-01 6.03E-02 70 3.71 E-02 1.30E-01 6.05E-02 60 3.76E-02 1.31 E-01 6.11 E-02 50 3.85E-02 1.34E-01 6.25E-02 40 4.06E-02 1.41 E-01 6.59E-02 35 4.24E-02 1.47E-01 6.89E-02 30 4.50E-02 1.57E-01 7.33E-02 25 4.88E-02 1.70E-01 7.94E-02 20 5.48E-02 1.95E-01 9.08E-02 15 6.27E-02 2.26E-01 1.05E-01 12.5 7.43E-02 2.70E-01 1.25E-01 10 7.55E-02 2.77E-01 1.28E-01 9 7.17E-02 2.57E-01 1.20E-01 8 7.00E-02 2.44E-01 1.14E-01 7 7.03E-02 2.39E-01 1.12E-01 6 7.54E-02 2.48E-01 1.17E-01 5 8.07E-02 2.56E-01 1.22E-01 4 8.03E-02 2.36E-01 1.14E-01 3.5 7.22E-02 2.03E-01 9.90E-02 3 6.15E-02 1.64E-01 8.08E-02 2.5 4.94E-02 1.24E-01 6.18E-02 2 4.81 E-02 1.16E-01 5.82E-02 1.5 4.51 E-02 1.03E-01 5.24E-02 1.25 4.37E-02 9.64E-02 4.94E-02 1 4.20E-02 8.90E-02 4.59E-02 0.9 4.18E-02 8.91 E-02 4.59E-02 0.8 3.97E-02 8.51 E-02 4.38E-02 0.7 3.75E-02 8.11 E-02 4.17E-02 0.6 3.61 E-02 7.86E-02 4.03E-02 0.5 3.30E-02 7.25E-02 3.72E-02 0.4 2.64E-02 5.80E-02 2.97E-02 0.35 2.31 E-02 5.07E-02 2.60E-02 0.3 1.98E-02 4.35E-02 2.23E-02 0.25 1.65E-02 3.62E-02 1.86E-02 0.2 1.32E-02 2.90E-02 1.49E-02 0.15 9.90E-03 2.17E-02 1.11 E-02 0.125 8.25E-03 1.81 E-02 9.29E-03 0.1 6.60E-03 1.45E-02 7.43E-03 17

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report Mean Soil UHRS and GMRS at Prairie Island 0.4 I I I

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Figure 2.4-1. Plots of 1E-4 and 1E-5 UHRS and GMRS at control point for PINGP response spectra).

I 3.0 Safe Shutdow n Earthqu ake Ground Motion I

(USAR).

The design basis "for PINGP is identified in the Updated Safely Evaluation Report 3.1 SSE Descrip tion of Spectra l Shape n can be All Class I structures and equipme nt were analyzed to assure that a safe shutdow earthqua ke) and 0.12 g (design made during ground accelerations of 0.06 g (operating basis basis or maximum earthquake) (Reference 7.14, Section 12.2.1.4) .

the response The OBE is based upon a maximum horizontal ground acceleration of 0.06 g and ke is based upon spectra are given in USAR, Appendi x E, Plate 4.5. The Design Basis Earthqua are given on a maximum horizontal ground acceleration of 0.12 g and the response spectra Diesel Generat or USAR, Appendi x E, Plate 4.6. However, the response spectra for the 05/06 18

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report Building design are based upon Regulatory Guide 1.60, Revision 1, spectra for maximum ground acceleration (zero period acceleration) of 0.06 g OBE and 0.12 g SSE (Reference 7.14, Section 12.2).

Only 0.5% and 1% damping values were used for original site design (Reference 7.9). The 5%

damping values were developed by analysis (Reference 7.1 0) from the original site spectra.

The 5o/a damped horizontal SSE is shown in Table 3.1-1.

Refer to PINGP USAR Section 2 (Reference 7.2), USAR Section 12 (Reference 7.14), and USAR Appendix E (Reference 7.6) for additional description on the SSE.

TABLE 3.1-1 SSE for PINGP (Reference 7.7)

Freq. (Hz) SA (g) 33 0.12 9 0.14 5 0.18 2.5 0.17 1 0.10 0.5 0.06 3.2 Control Point Elevation PINGP USAR does not explicitly define the SSE control point. The SSE control point elevation is defined at the surface per Table 1 of Reference 7.7, and is based on the site geologic profile at the PINGP.

The profile was modeled up to the surface, in accordance with Reference 7.7. For dynamic properties of soft rock layers, modulus and damping curves were represented with 2 models.

The first model used rock curves, the second model assumed linear behavior. These dynamic property models were weighted equally. For dynamic properties of fill and compacted sand layers, modulus and damping curves were also represented with 2 models. These dynamic property models were weighted equally. To model the profile, rock modulus and damping curves were paired with soil modulus and damping curves, and linear rock modulus and damping curves were paired with soil modulus and damping curves.

19

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report 4.0 Screening Evaluation In accordance with SPID Section 3 (Reference 7.3), a screening evaluation was performed as described below.

The horizontal GMRS determined from the hazard reevaluation is used to characterize the amplitude of the new seismic hazard at PINGP. The PINGP screening evaluation is based upon a comparison of the site-specific GMRS with 5% damped horizontal SSE.

4.1 Risk Evaluation Screening (1 to 10Hz)

In the 1 to 10Hz part of the response spectrum, the SSE exceeds the GMRS (Reference 7.1).

Therefore, a risk evaluation will not be performed for PINGP.

4.2 High Frequency Screening (> 10 Hz)

Above 10Hz, the SSE exceeds the GMRS (Reference 7.1). Therefore, a high frequency confirmation will not be performed for PINGP.

4.3 Spent Fuel Pool Evaluation Screening (1 to 10 HZ)

In the 1 to 10 Hz part of the response spectrum, the SSE exceeds the GMRS (Reference 7.1 ).

Therefore, a spent fuel pool evaluation will not be performed for PINGP.

5.0 Interim Actions Based on the screening evaluation, the expedited seismic evaluation described in Reference 7.11 will not be performed. PINGP screens out from this activity since the GMRS is less than the SSE between 1 and 10 Hz.

Consistent with NRC letter dated February 20, 2014 (Reference 7.21), the seismic hazard reevaluations presented herein are distinct from the current design and licensing bases of PINGP. Therefore, the results do not call into question the operability or functionality of SSCs and are not reportable pursuant to 10 CFR 50. 72, "Immediate notification requirements for operating nuclear power reactors," and 10 CFR 50.73, "Licensee event report system."

The NRC letter (Reference 7.21) also requests that licensees provide an interim evaluation or actions to demonstrate that the plant can cope with the reevaluated hazard while the expedited approach and risk evaluations are conducted. In response to that request, NEIIetter dated March 12, 2014 (Reference 7.12) provides seismic core damage risk estimates using the updated seismic hazards for the operating nuclear plants in the Central and Eastern United States. These risk estimates continue to support the following conclusions of the NRC Generic Issue (GI)-199 Safety/Risk Assessmen t (Reference 7.22):

20

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report

• Overall seismic core damage risk estimates are consistent with the Commission's Safety Goal Policy Statement because they are within the subsidiary objective of 1o- /year for core damage frequency.

4

• The Gl-199 Safety/Risk Assessment, based in part on information from the U.S.

Nuclear Regulatory Commission's (NRC's) Individual Plant Examination of External Events (IPEEE) program, indicates that no concern exists regarding adequate protection and that the current seismic design of operating reactors provides a safety margin to withstand potential earthquakes exceeding the original design basis.

that there The comparisons documented in the March 12, 2014, letter (Reference 7.12) show In addition, has not been an overall increase in seismic risk for the fleet of U.S. nuclear plants.

damage risk estimate s below the 1o-4/year all sixty-one of the CEUS sites have seismic core PINGP is threshold considered in the NRC 2010 Safety I Risk Assessment (Reference 7.22).

current included in the March 12, 2014, risk estimates. Thus, it can be concluded that the seismic design of PI NGP continues to provide a safety margin to withstan d potential 2010 Safety I earthquakes exceeding the seismic design basis, as was concluded in the NRC Risk Assessment (Reference 7.22).

6.0 Conclusions g

In accordance with the 50.54(f) request for information, a seismic hazard and screenin develope d solely for purpose of screenin g evaluation was performed for PINGP. A GMRS was for additional evaluations in accordance with the SPID.

d.

Based on the results of the screening evaluation, no further evaluations will be performe 7.0 References 7.1 Prairie Island Seismic Hazard and Screening Report, prepared by EPRI I LCI, Project Number 1041, dated December 18, 2013.

7.2 PINGP USAR, Section 02, Site and Environs , Revision 32.

tion 7.3 EPRI Report Number 1025287, "Seismic Evaluation Guidance: Screening, Prioritiza and Implementation Details (SPID) for the Resolution of Fukushima Near-Te rm Task n No.

Force Recommendation 2.1: Seismic," dated November 2012, ADAMS Accessio ML12333A170.

7.4 Technical Report, NUREG-2115, "Central and Eastern United States Seismic Source NRC, Characterization for Nuclear Facilities," EPRI, Palo Alto, CA, U.S. DOE, and U.S.

dated 2012.

21

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report 7.5 EPRI Report Number 3002000717, "EPRI (2004, 2006) Ground-Motion Model (GMM)

Review Project," dated June 2013.

7.6 PINGP USAR, Appendix E, Report of Environmental Studies, Geology, Hydrology and Seismology, Proposed Nuclear Power Plant Prairie Island Site Near Red Wing, Minnesota, Revision 32.

7.7 NSPM Engineering Change (EC) 22628, "Site Geological Profile for 10 CFR 50.54f Seismic Reevaluation."

7.8 Nuclear Energy Institute (NEI) letter to NRC, "Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations," dated April 9, 2013, ADAMS Accession No. ML13101A379.

7.9 John A. Blume and Associates, Engineers, Calculation No. JAB-PS-04, Earthquake Analysis: Reactor-Auxiliary- Turbine Building Response Acceleration Spectra, Revision 0.

7.10 Stevenson and Associates, Calculation No. 0004159-C-001, PINGP Floor Response Spectra, Revision 0.

7.11 EPRI Report Number 3002000704, "Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1 -Seismic, " dated May 2013, ADAMS Accession No. ML131078387.

7.12 NEI Letter to NRC, "Seismic Risk Evaluations for Plants in the Central and Eastern United States," dated March 12, 2014.

7.13 PINGP USAR Section 01, Introduction and Summary Description, Revision 32.

7.14 PINGP USAR Section 12, Plant Structures and Shielding, Revision 32.

7.15 Silva, W.J., Abrahamson, N., Toro, G., and Costantino, C. (1997). "Description and validation of the stochastic ground motion model", Report Submitted to Brookhaven National Laboratory, Associated Universities, Inc., Upton, New York 11973, Contract No.

770573.

7.16 USNRC NUREG-1407, "Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities," dated June 1991, ADAMS Accession No. ML063550238.

7.17 USNRC NUREG-1488, "Revised Livermore Seismic Hazard Estimates for Sixty-Nine Nuclear Power Plant Sites East of the Rocky Mountains," Final Report dated April 1994, ADAMS Accession No. ML052640591.

7.18 USNRC NUREG-1742, "Perspectives Gained From the Individual Plant Examination of External Events (IPEEE) Program," dated September 2001, ADAMS Accession No. ML021270070.

22

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report Define the Site-7.19 USNRC Regulatory Guide 1.208, "A Performance-Based Approach to Specific Earthquake Ground Motion," Revision 0.

X, 'Seismic 7.20 NRC Letter, "Electric Power Research Institute Final Draft Report XXXXX ion of Fukush ima Near-Term Evaluation Guidance: Augmented Approach for the Resolut ble Alterna tive to the March Task Force Recommendation 2.1: Seismic,' As an Accepta ations," dated May 7, 2013, ADAMS 12, 2012, Information Request for Seismic Reevalu Accession No. ML13106A331.

tion Pursuant to 7.21 NRC Letter, "Supplemental Information Related to Request for Informa 50.54(f) Regard ing Seismic Hazard Title 10 of the Code of Federal Regulations of the Near-Te rm Task Force Review of Insights Reevaluations for Recommendation 2.1 dated Februa ry 20, 2014, ADAMS Access ion No.

from the Fukushima Dai-ichi Accident,"

ML14030A046.

Seismic 7.22 NRC Generic Issue (GI) 199 Report, "Implications of Updated Probabilistic Existing Plants, Safety/Risk Hazard Estimates In Central And Eastern United States On Assessment," dated August 2010, ADAMS Accession No. ML100270639.

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Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report I

r Append ix A Mean and Fractile Seismic Hazard Curves I TABLE A-1a. Mean and Fractile Seismic Hazard Curves for PGA at PINGP MEAN 0.05 0.16 0.50 0.84 0.95 AMPS(g) 1.65E-02 6.73E-03 1.18E-02 1.64E-02 2.16E-02 2.49E-02 0.0005 1.18E-02 3.42E-03 7.66E-03 1.16E-02 1.62E-02 1.95E-02 0.001 2.74E-03 4.98E-04 1.05E-03 2.22E-03 4.43E-03 6.93E-03 0.005 1.04E-03 1.40E-04 2.96E-04 7.34E-04 1.64E-03 3.33E-03 0.01 5.29E-04 5.66E-05 1.25E-04 3.47E-04 8.47E-04 1.79E-03 0.015 1.43E-04 9.93E-06 2.13E-05 8.12E-05 2.42E-04 4.70E-04 0.03 5.48E-05 2.32E-06 5.58E-06 2.72E-05 9.24E-05 1.92E-04 0.05 2.64E-05 7.34E-07 2.16E-06 1.23E-05 4.43E-05 9.79E-05 0.075 1.58E-05 3.33E-07 1.18E-06 7.34E-06 2.64E-05 5.91 E-05 0.1 7.62E-06 1.15E-07 5.35E-07 3.52E-06 1.31 E-05 2.84E-05 0.15 1.99E-06 1.95E-08 1.29E-07 8.72E-07 3.52E-06 7.34E-06 0.3 0.5 6.49E-07 4.25E-09 3.52E-08 2.60E-07 1.18E-06 2.46E-06 2.39E-07 1.02E-09 1.02E-08 8.60E-08 4.31 E-07 9.51 E-07 I 0.75 1.1 OE-07 3.57E-1 0 3.73E-09 3.47E-08 1.95E-07 4.56E-07 1.

3.32E-08 1.08E-1 0 7.66E-1 0 8.35E-09 5.58E-08 1.44E-07 1.5

3. 3.16E-09 7.13E-11 8.72E-11 4.70E-10 4.31 E-09 1.44E-08 I 4.21 E-1 0 7.13E-11 7.77E-11 9.37E-11 4.90E-1 0 1.92E-09 5.

7.5 10.

6.97E-11 1.74E-11 7.13E-11 7.13E-11 7.13E-11 7.13E-11 8.12E-11 8.12E-11 1.20E-1 0 8.12E-11 3.57E-10 1.36E-1 0 I I

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Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report for 25 Hz at PI~GP TABLE A-1 b. Mean and Fractile Seismic Hazard Curves 0.05 0.16 0.50 0.84 0.95 AMPS(g) MEAN 8.72E-03 1.29E-02 1.74E-02 2.22E-02 2.57E-02 0.0005 1.74E-02 4.98E-03 8.98E-03 1.29E-02 1.74E-02 2.07E-02 0.001 1.30E-02 8.35E-04 1.60E-03 3.14E-03 5.66E-03 8.85E-03 0.005 3.69E-03 2.64E-04 5.27E-04 1.20E-03 2.53E-03 4.83E-03 0.01 1.62E-03 1.20E- 04 2.42E-04 6.26E- 04 1.42E-03 2.88E-03 0.015 9.09E-04 2.32E-05 4.90E-05 1.67E- 04 4.50E-04 8.35E-04 0.03 2.67E-04 5.75E-06 1.29E- 05 5.50E-05 1.69E- 04 3.09E-04 0.05 9.53E-05 1.82E-06 4.63E-06 2.32E-05 7.77E-05 1.46E-04 0.075 4.30E- 05 8.47E-07 2.46E-06 1.34E-05 4.56E-05 8.72E-05 0.1 2.53E- 05 3.05E-07 1.13E-06 6.54E-06 2.29E-05 4.25E-05 0.15 1.24E-05 5.91 E-08 3.28E-07 2.01 E-06 6.93E-06 1.23E-05 0.3 3.70E-06 1.87E-08 1.20E-07 7.66E-07 2.76E-06 4.77E-06 0.5 1.42E-06 6.26E-09 4.77E-08 3.19E-07 1.21 E-06 2.13E-06 0.75 6.16E-07 2.80E-09 2.35E-08 1.62E- 07 6.45E-07 1.15E-06 1 3.24E-07 1.5 1.19E-07 8.12E-10 7.77E-09 5.58E-08 2.35E-07 4.31 E-07 I 1.23E-1 0 8.00E- 10 6.36E-09 3.05E-08 6.45E-08 3 1.62E-08 5 2.86E-09 7.34E- 11 1.55E-1 0 9.37E- 10 4.90E-09 1.25E-08 I 7.13E-11 8.12E- 11 2.13E-10 1.01 E-09 2.88E-09 7.5 6.1OE-1 0 10 1.86E-1 0 7.13E-11 8.12E-11 1.02E-1 0 3.28E-1 0 9.65E-1 0 I

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Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report s for 10Hz at PINGP TABLE A-1c. Mean and Fractile Seism ic Hazard Curve 0.16 0.50 0.84 0.95 AMPS (g) MEAN 0.05 1.51 E-02 1.98E-02 2.46E-02 2.80E-02 0.0005 1.99E-02 1.29E-02 1.18E-02 1.60E-02 2.07E-02 2.39E-02 0.001 1.63E-02 9.51 E-03 2.88E-03 5.12E-03 8.00E-03 1.05E-02 0.005 5.46E-03 1.74E-03 1.04E-03 2.1OE-03 3.84E-03 5.83E-03 0.01 2.49E-03 5.66E-04 5.12E-04 1.13E-03 2.25E-03 3.73E-03 0.015 1.44E-03 2.68E-04 1.32E-04 3.52E-04 8.00E-04 1.40E-03 0.03 4.97E-04 6.54E-05 4.31 E-05 1.38E-04 3.52E-04 6.17E-04 0.05 2.08E-04 2.13E-05 1.72E-05 6.45E-05 1.79E-04 3.09E-04 0.075 1.01 E-04 8.23E-06 8.85E-06 3.73E-05 1.1 OE-04 1.90E-04 0.1 6.04E-05 4.07E-06 3.57E-06 1.72E-05 5.50E-05 9.79E-05 0.15 2.94E-05 1.46E-06 8.12E-07 4.56E-06 1.64E-05 3.05E-05 0.3 8.68E-06 2.46E-07 2.80E-07 1.72E-06 6.54E-06 1.23E-05 0.5 3.42E-06 6.26E-08 1.11 E-07 7.34E-07 2.96E-06 5.66E-06 0.75 1.55E-06 2.01 E-08 5.58E-08 3.79E-07 1.64E-06 3.19E-06

1. 8.49E-07 8.60E-09 1.79E-08 1.34E-07 6.54E-07 1.34E-06 1.5 3.39E-07 2.42E-09 1.77E-09 1.64E-08 1.04E-07 2.46E-07

3. 5.56E-08 2.22E-10 2.57E-1 0 2.57E-09 2.01 E-08 5.50E-08

5. 1.17E-08 8.12E-11 9.24E-11 5.12E-10 4.56E-09 1.40E-08 7.5 2.91 E-09 7.13E-11 8.12E-11 1.84E-1 0 1.44E-09 4.83E-09

10. 9.92E-1 0 7.13E-11 TABLE A-1 d. Mean and Fractile Seism ic Hazard Curve s for 5Hz at PINGP I AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 I 1.62E-02 2.10E-02 2.57E-02 2.92E-02 0.0005 2.11 E-02 1.40E-02 0.001 1.85E-02 1.13E-02 1.36E-02 4.25E-03 1.82E-02 7.34E-03 2.32E-02 1.11 E-02 2.68E-02 1.38E-02 I

0.005 7.68E-03 2.68E-03 0.01 3.71 E-03 8.98E-04 1.64E-03 3.33E-03 1.79E-03 5.83E-03 3.47E-03 7.77E-03 5.05E-03 I

0.015 2.14E-03 4.25E-04 8.12E-04 0.03 6.88E-04 9.51 E-05 1.98E-04 5.05E-04 1.11 E-03 1.90E-03 I 6.09E-05 1.79E-04 4.37E-04 7.55E-04 0.05 2.63E-04 2.80E-05 2.22E-05 7.55E-05 2.01 E-04 3.47E-04 0.075 1.16E-04 1.01 E-05 1.08E-05 4.07E-05 1.16E-04 2.01 E-04 0.1 6.46E-05 4.77E-06 3.84E-06 1.69E-05 5.27E-05 9.37E-05 0.15 2.85E-05 1.60E-06 7.34E-07 3.90E-06 1.40E-05 2.57E-05 0.3 7.35E-06 2.42E-07 2.22E-07 1.32E-06 5.12E-06 9.65E-06 0.5 2.67E-06 5.50E-08 8.12E-08 5.27E-07 2.19E-06 4.25E-06 0.75 1.14E-06 1.53E-08 3.84E-08 2.64E-07 1.16E-06 2.29E-06

1. 5.97E-07 6.36E-09 1.18E-08 9.11E-08 4.31 E-07 8.85E-07 1.5 2.24E-07 1.62E-09 1.11 E-09 1.01 E-08 5.91 E-08 1.44E-07

3. 3.30E-08 1.64E-1 0 1.84E-1 0 1.49E-09 1.05E-08 2.96E-08

5. 6.48E-09 8.12E-11 8.35E-11 3.05E-1 0 2.25E-09 7.13E-09 7.5 1.55E-09 7.13E-11 8.12E-11 1.25E-1 0 6.93E-10 2.39E-09

10. 5.19E-1 0 7.13E-11 26

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report d Curves for 2.5 Hz at PINGP TABLE A-1 e. Mean and Fractile Seismic Hazar 0.16 0.50 0.84 0.95 AMPS(g) MEAN 0.05 1.49E-02 1.95E-02 2.46E-02 2.80E-02 0.0005 1.97E-02 1.27E-02 1.13E-02 1.55E-02 2.07E-02 2.42E-02 0.001 1.60E-02 8.98E-03 2.88E-03 5.12E-03 8.00E-03 1.02E-02 0.005 5.45E-03 1.82E-03 1.01 E-03 2.16E-03 4.01 E-03 5.58E-03 0.01 2.49E-03 5.66E-04 0.015 1.35E-03 2.35E-04 4.43E-04 1.05E-03 2.25E-03 3.47E-03 I 8.35E-05 2.25E-04 5.42E-04 1.04E-03 0.03 3.39E-04 3.95E-05 0.05 9.72E-05 8.72E-06 2.04E-05 6.17E-05 1.55E-04 3.14E-04 I 6.09E-06 2.1 OE-05 5.91 E-05 1.1 OE-04 0.075 3.41 E-05 2.49E-06 0.1 1.66E-05 1.02E-06 2.53E-06 1.01 E-05 3.01 E-05 5.35E -05 2.13E-05 I

2.92E-07 7.77E-07 3.63E-06 1.18E-05 0.15 6.35E-06 0.3 1.40E-06 3.33E-08 1.16E-07 6.83E-07 2.64E-06 5.12E-06 I 2.92E-08 1.98E-07 8.72E-07 1.77E-06 0.5 4.62E-07 6.00E-09 0.75 1.85E-07 1.49E-09 9.24E-09 7.03E-08 3.42E-07 7.34E-07 I 3.84E-09 3.19E-08 1.69E-07 3.90E-07

1. 9.34E-08 5.58E-1 0 1.05E-09 9.79E-09 5.83E-08 1.49E-07 1.5 3.37E-08 1.67E-1 0 1.29E-1 0 9.51 E-1 0 7.23E-09 2.22E-08

3. 4.80E-09 8.12E-11 8.12E-11 1.74E-10 1.21 E-09 4.31 E-09

5. 9.19E-10 7.13E-11 7.77E-11 8.35E-11 2.88E-1 0 1.01 E-09 7.5 2.12E-10 7.13E-11 7.13E-11 8.12E-11 1.25E-1 0 3.57E-1 0

10. 6.87E-11 7.13E-11 d Curves for 1 Hz at PINGP TABLE A-1f. Mean and Fractile Seismic Hazar 0.16 0.50 0.84 0.95 AMPS(g) MEAN 0.05 8.85E-03 1.32E-02 1.84E-02 2.19E-02 0.0005 1.37E-02 6.36E-03 5.58E-03 8.98E-03 1.31 E-02 1.60E-02 0.001 9.30E-03 3.68E-03 1.05E-03 2.57E-03 4.77E-03 6.45E-03 0.005 2.90E-03 5.05E-04 3.09E-04 1.11 E-03 2.76E-03 4.19E-03 0.01 1.51 E-03 1.25E-04 1.29E-04 5.42E-04 1.69E-03 2.84E-03 0.015 8.88E-04 4.70E-05 2.07E-05 9.93E-05 4.37E-04 9.65E-04 0.03 2.41 E-04 6.64E-06 4.31 E-06 2.16E-05 1.02E-04 2.72E-04 0.05 6.36E-05 1.31 E-06 1.1 OE-06 5.75E-06 2.60E-05 7.66E-05 0.075 1.79E-05 3.28E-07 4.01 E-07 2.19E-06 9.65E-06 2.88E-05 0.1 6.71 E-06 1.16E-07 9.37E-08 5.42E-07 2.46E-06 7.03E-06 0.15 1.63E-06 2.64E-08 7.55E-09 5.58E-08 3.14E-07 8.35E-07 0.3 1.94E-07 1.69E-09 1.11 E-09 1.13E-08 7.77E-08 2.39E-07 0.5 5.39E-08 2.32E-10 2.72E-10 3.14E-09 2.68E-08 9.11 E-08 0.75 2.02E-08 8.98E-11 1.29E-1 0 1.21 E-09 1.20E-08 4.50E-08

1. 9.86E-09 8.12E-11 8.12E-11 3.28E-10 3.57E-09 1.51 E-08 1.5 3.38E-09 7.13E-11 7.89E-11 8.12E-11 3.73E-10 1.79E-09

3. 4.41E -10 7.13E-11 7.13E-11 8.12E-11 1.04E-1 0 3.28E-1 0

5. 8.00E-11 7.13E-11 7.13E-11 8.12E-11 8.12E-11 1.15E-10 7.5 1.79E-11 7.13E-11 7.13E-11 8.12E-11 8.12E-11 8.12E-11

10. 5.72E-12 7.13E-11 27

t Prairie Island Nuclear Generating Plan Seismic Hazard and Screenin g Rep ort P

mic Hazard Curves for 0.5 Hz at PING TABLE A-1g. Mean and Fractile Seis 0.50 0.84 0.95 MEAN 0.05 0.16 AMPS(g) 1.27E-02 4.63E-03 7.23E-03 1.02E-02 0.0005 7.47E-03 3.23E-03 4.63E-03 7.13E-03 8.98E-03 I 0.001 4.91 E-03 1.67E-03 2.68E-03 3.28E-03 4.77E-03 0.005 1.79E-03 1.32E-04 3.57E-04 1.40E-03 3.05E-03 I

8.23E-05 5.12E-04 1.82E-03 0.01 9.11E-04 2.39E-05 0.015 5.14E-04 7.45E-06 2.92E-05 2.16E-04 1.07E-03 1.95E-03 I 3.19E-05 2.25E-04 5.83E-04 3.57E-06 0.03 1.29E-04 3.28E-05 7.77E-07 1.29E-07 6.26E-07 5.83E-06 4.70E-05 1.53E-04 I 0.05 4.01 E-05 0.075 8.97E-06 2.84E-08 1.40E-07 1.32E-06 1.1 OE-05 1.40E-05 I

4.56E-08 4.56E-07 3.73E-06 3.23E-06 9.24E-09 0.1 0.15 6.91 E-07 1.74E-09 8.98E-09 9.65E-08 7.45E-07 3.19E-06 I 6.45E-09 6.00E-08 2.57E-07 0.3 5.36E-08 1.23E-1 0 5.42E-1 0 I 9.11E-10 1.1 OE-08 5.12E-08 0.5 1.21 E-08 8.12E-11 1.08E-1 0 2.32E-10 2.92E-09 1.69E-08 0.75 4.29E-09 7.13E-11 7.13E-11 8.12E-11 8.12E-11 1.16E-10 1.13E-09 7.55E-09 I

1. 2.07E-09 8.12E-11 3.19E-10 2.25E-09 1.5 7.10E-10 7.13E-11 7.23E-11 8.12E-11 8.23E-11 2.72E-1 0

3. 9.47E-11 7.13E-11 7.13E-11 8.12E-11 8.12E-11 9.24E-11

5. 1.77E-11 7.13E-11 7.13E-11 8.12E-11 8.12E-11 8.12E-11 7.5 4.06E-12 7.13E-11 7.13E-11 8.12E-11 8.12E-11 8.12E-11 7.13E-11

10. 1.32E-12 7.13E-11 I I

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I Prairie Island Nuclear Generating Plant Seism ic Hazard and Screening Report I

TABL EA-2 I

Amplification Functions for PINGP Media n Sigma PGA Media n AF Sigma ln(AF) 25Hz Media n AF Sigma ln(AF) 10Hz Media n AF Sigma ln(AF) 5Hz AF ln(AF) 1.13E-01 I

1.80E-01 2.09E -02 1.71E+OO 1.00E- 02 4.95E -02 1.36E+OO 1.07E+OO 8.25E -02 1.06E-01 1.30E- 02 1.02E-01 1.1 OE+OO 6.49E-01 9.00E -02 1.43E-01 1.90E- 02 9.99E -02 1.22E+OO 1.15E+OO 2.17E-01 8.24E -02 1.44E-01 1.69E+OO 1.67E+OO 1.20E-01 1.23E-01 I

1.85E-01 1.13E+OO 2.24E-01 9.64E -02 9.63E-01 8.84E-01 1.13E-01 1.18E-01 2.13E-01 4.43E-01 5.72E-01 5.22E-01 1.60E-01 1.72E-01 3.56E-01 1.12E+OO 2.29E-01 2.65E-01 1.64E+OO 1.29E-01 I 1.94E-01 2.33E-01 3.84E-01 1.62E+OO 1.35E-01 1.77E-01 5.23E-01 1.1OE+OO 2.92E-01 8.45E-01 8.20E-01 1.20E-01 1.21 E-01 6.76E-01 9.09E-01 S.OOE-01 S.OOE-01 1.79E-01 6.90E -01 1.09E+OO 2.36E-01 5.02E-01 1.61E+OO 1.41E-01 1.46E-01 I

3.91 E-01 2.38E-01 6.22E-01 1.59E+OO 8.61E-01 1.08E+OO 4.93E-01 8.01 E-01 1.21 E-01 1.21 E-01 1.15E+OO 1.73E+OO S.OOE-01 S.OOE-01 1.81 E-01 1.82E-01 1.27E+OO 1.06E+OO 2.43E-01 9.13E-01 1.55E+OO 1.58E-01 I 7.41E-01 7.67E-01 1.22E+OO 1.52E+OO 1.70E-01 1.03E+OO 2.44E-01 1.01 E+OO 1.28E+OO 7.42E-01 7.20E-01 1.21 E-01 1.20E-01 2.36E+OO 3.01E+OO S.OOE-01 S.OOE-01 1.76E-01 1.72E- 01 1.72E+OO 2.17E+OO 9.90E-01 2.40E-01 1.54E+OO 1.48E+OO 1.78E-01 1.86E-01 I

2.36E-01 1.85E+OO 1.45E+OO 1.55E+OO 7.02E-01 Media n 1.19E-01 Sigma 3.63E+OO S.OOE-01 Media n 1.68E-01 Sigma 2.61E+OO 9.57E-01 Media n AF Sigma ln(AF)

I AF ln(AF) 0.5 Hz 2.5 Hz 2.18E -02 AF 1.41E+OO ln(AF) 1.20E-01 1Hz 1.27E- 02 1.41E+OO 1.42E-01 8.25E -03 1.35E+OO 1.51E-01 1.45E-01 I

1.41E+OO 1.39E-01 1.96E- 02 1.35E+OO 7.05E -02 1.41 E+OO 1.20E-01 3.43E -02 3.02E -02 1.35E+OO 1.43E-01 1.21 E-01 5.51E -02 1.41E+OO 1.38E-01 1.18E-01 1.41E+OO 1.38E-01 5.11 E-02 1.36E+OO 1.42E-01 1.42E+OO 1.24E-01 9.63E -02 1.42E+OO 2.12E-01 1.41 E-01 1.42E+OO 1.38E-01 7.10E -02 1.36E+OO 3.04E-01 1.42E+OO 1.26E-01 1.36E-01 1.38E-01 9.06E -02 1.36E+OO 1.40E-01 1.43E+OO 1.28E-01 1.75E-01 1.43E+OO 3.94E-01 1.40E-01 1.38E-01 1.10E-01 1.36E+OO 1.44E+OO 1.29E-01 2.14E-01 1.43E+OO 4.86E-01 1.40E-01 1.38E-01 1.58E-01 1.37E+OO 1.30E-01 3.10E-01 1.44E+OO 7.09E-01 9.47E-01 1.45E+OO 1.46E+OO 1.32E-01 4 .12E-01 1.45E+OO 1.38E-01 2.09E-01 1.37E+OO 1.40E-01 I 1.39E-01 2.62E-01 1.37E+OO 1.41 E-01 1.34E-01 5.18E-01 1.46E+OO 1.19E+OO 1.43E+OO 1.47E+OO 1.47E+OO 1.35E-01 6.19E-01 1.46E+OO 1.39E-01 3.12E-01 1.38E+OO 1.41E-01 I I

29 I

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report l

Appendix A (Continued) ties Median Amplification Factors and Uncertain I on factors and uncertainties. I Tables and figures showing median amplificati ency range of 0.5 Hz to 25 Hz, with values up I These tables and figures concentrate on the frequ included for completeness.

to 100 Hz included, and a single value at 0.1 Hz I

l1 , Profile 1, for 2 PGA levels.

TABL E A2-b1. Median AFs and Sigmas for Mode PGA=0.194 I

Rock PGA=0.0495 M1 P1 K1 M1 P1 K1 med.

Freq .

(Hz) Soil SA med.

AF sigma ln(AF)

Freq.

(Hz) Soil SA AF sigma ln(AF) I 100.0 0.174 0.899 0.102 1.094 0.089 100.0 87.1 0.054 0.054 1.080 0.090 87 .1 0.175 0.878 0.102 I 75.9 0.175 0.843 0.103 75.9 0.054 1.058 0.090 66.1 0.176 0.777 0.104 66.1 0.055 1.014 0.091 57 .5 0.178 0.670 0.106 57.5 0.055 0.934 0.092 50.1 0.180 0.566 0.111 50.1 0.056 0.831 0.095 43.7 0.185 0.490 0.115 43 .7 0.057 0.734 0.099 0.674 0.107 38 .0 0.191 0.462 0.127 I 38.0 0.058 0.200 0.456 0.136 33.1 0.060 0.063 0.639 0.646 0.113 0.125 33 .1 28.8 0.211 0.481 0.147 I 28 .8 0.514 0.161 25.1 0.067 0.660 0.689 0.136 0.131 25.1 21.9 0.228 0.236 0.559 0.156 I 21.9 0.069 0.639 0.168 19.1 0.079 0.764 0.149 0.172 19.1 16.6 0.266 0.302 0.752 0.187 I 16.6 0.087 0.849 14.5 0.089 0.886 0.158 0.160 14.5 12.6 0.306 0.352 0.797 0.944 0.177 0.173 I

12.6 0.106 1.052 11.0 0.126 1.255 0.172 11.0 0.421 1.158 1.212 0.163 0.216 I

1.243 0.208 9.5 0.422 9.5 0.122 8.3 0.370 1.153 0.207 8.3 0.110 1.180 0.194 7.2 0.350 1.164 0.200 7.2 0.108 1.209 0.188 6.3 0.363 1.283 0.200 6.3 0.114 1.343 0.184 5.5 0.400 1.481 0.176 5.5 0.128 1.548 0.156 4.8 0.439 1.660 0.142 4.8 0.143 1.730 0.125 4.2 0.458 1.786 0.090 4.2 0.150 1.845 0.088 3.6 0.440 1.764 0.108 3.6 0.143 1.788 0.108 3.2 0.392 1.670 0.091 3.2 0.128 1.668 0.088 2.8 0.337 1.509 0.116 2.8 0.110 1.499 0.118 2.4 0.297 1.444 0.102 2.4 0.098 1.429 0.103 2.1 0.261 1.396 0.108 2.1 0.087 1.382 0.109 1.8 0.229 1.368 0.099 1.8 0.077 1.353 0.099 1.6 0.203 1.396 0.121 1.6 0.069 1.385 0.125 1.4 0.187 1.494 0.111 1.4 0.064 1.486 0.115 1.2 0.162 1.468 0.134 1.2 0.056 1.460 0.134 1.0 0.145 1.462 0.133 1.0 0.051 1.456 0.134 30

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report M1 P1 K1 Rock PGA=0.0495 M1 P1 K1 PGA=0.194 Freq. med. Freq. med.

(Hz) Soil SA AF sigma ln(AF) (Hz) Soil SA AF sigma ln(AF) 0.91 0.047 1.459 0.143 0.91 0.132 1.464 0.139 0.79 0.041 1.382 0.138 0.79 0.114 1.387 0.134 0.69 0.035 1.288 0.105 0.69 0.094 1.295 0.104 0.60 0.030 1.260 0.128 0.60 0.080 1.267 0.126 0.52 0.026 1.268 0.137 0.52 0.069 1.274 0.135 0.46 0.023 1.316 0.135 0.46 0.060 1.320 0.132 0.10 0.001 1.336 0.055 0.10 0.003 1.336 0.055 TABLE A2-b2. Median AFs and sigmas for Model2, Profile 1, for 2 PGA levels.

M2P1K1 PGA=0.0495 M2P1K1 PGA=0.194 Freq. med. Freq. med.

(Hz) Soil SA AF sigma ln(AF) (Hz) Soil SA AF sigma ln(AF) 100.0 0.055 1.110 0.084 100.0 0.182 0.937 0.095 87.1 0.055 1.097 0.085 87.1 0.182 0.916 0.096 75.9 0.055 1.074 0.085 75.9 0.183 0.879 0.096 66.1 0.056 1.030 0.086 66.1 0.184 0.811 0.097 57.5 0.056 0.949 0.087 57.5 0.186 0.700 0.100 50.1 0.057 0.845 0.090 50.1 0.189 0.594 0.104 43.7 0.058 0.748 0.093 43.7 0.195 0.517 0.109 38.0 0.059 0.687 0.101 38.0 0.203 0.489 0.120 33.1 0.061 0.653 0.106 33.1 0.213 0.486 0.129 28.8 0.064 0.661 0.119 28.8 0.227 0.516 0.145 25.1 0.069 0.677 0.130 25 .1 0.246 0.555 0.157 21.9 0.071 0.706 0.121 21.9 0.253 0.600 0.143 19.1 0.081 0.790 0.142 19.1 0.292 0.699 0.158 16.6 0.089 0.873 0.166 16.6 0.325 0.810 0.180 14.5 0.091 0.905 0.144 14.5 0.325 0.847 0.159 12.6 0.109 1.083 0.148 12.6 0.382 1.023 0.157 11.0 0.130 1.292 0.170 11.0 0.456 1.253 0.163 9.5 0.124 1.262 0.207 9.5 0.437 1.257 0.214 8.3 0.111 1.192 0.188 8.3 0.379 1.181 0.199 7.2 0.109 1.225 0.182 7.2 0.362 1.203 0.192 6.3 0.116 1.364 0.178 6.3 0.377 1.334 0.188 5.5 0.130 1.574 0.150 5.5 0.416 1.541 0.161 4.8 0.145 1.761 0.123 4.8 0.456 1.727 0.130 4.2 0.152 1.877 0.090 4.2 0.475 1.855 0.089 3.6 0.145 1.809 0.111 3.6 0.452 1.811 0.111 3.2 0.128 1.679 0.089 3.2 0.398 1.694 0.090 2.8 0.111 1.504 0.117 2.8 0.339 1.519 0.115 2.4 0.098 1.432 0.101 2.4 0.297 1.445 0.100 2.1 0.087 1.382 0.106 2.1 0.261 1.392 0.106 1.8 0.077 1.354 0.098 1.8 0.228 1.362 0.098 1.6 0.069 1.386 0.127 1.6 0.202 1.392 0.126 31

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report M2P1K1 PGA=0.0495 M2P1K1 PGA=0.194 Freq. med. Freq. med.

_(Hz) Soil SA AF sigma ln(AF) (Hz) Soil SA AF sigma ln(AF) 1.4 0.064 1.487 0.116 1.4 0.186 1.490 0.114 1.2 0.056 1.460 0.132 1.2 0.161 1.463 0.130 1.0 0.051 1.456 0.134 1.0 0.145 1.458 0.133 0.91 0.047 1.460 0.144 0.91 0.132 1.461 0.141 0.79 0.041 1.382 0.139 0.79 0.113 1.385 0.135 0.69 0.035 1.289 0.105 0.69 0.094 1.294 0.103 0.60 0.030 1.261 0.128 0.60 0.080 1.266 0.125 0.52 0.026 1.269 0.137 0.52 0.069 1.274 0.134 0.46 0.023 1.316 0.134 0.46 0.060 1.320 0.131 0.10 0.001 1.337 0.055 0.10 0.003 1.336 0.055 32

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report MlPlKl Rock PGA=0.0495 for Prairie Island 1E+1 r::

0

~

ro

.~ 1E+O 4-a.

E

<1:

1E-1 1E-1 1E+O 1E+1 1E+2 Frequency (Hz)

Figure 1. Amplification factors (median and median+/- sigma) plotted from Table A2-b1 for PGA 0.0495g.

MlPlKl PGA=0.194 for Prairie Island 1E+1 r::

0 ro ------- -------

• ~ 1E+O 4-a.

E

<1:

1E-1 1E-1 1E+O 1E+1 1E+2 Frequency (Hz)

Figure 2. Amplification factors (median and median+/- sigma) plotted from Table A2-b1 for PGA 0.194g.

33

Prairie Island Nuclear Generating Plant Seismic Hazard and Screening Report M2P1Kl PGA=0.0495 for Prairie Island 1E+1 c

0 rU

-~ 1E+O 4-r-

0..

E

<(

1E-1 1E-1 1E+O 1E+1 1E+2 Frequency (Hz)

Figure 3. Amplification factors (median and median.+/- sigma) plotted from Table A2-b2 for PGA 0.0495g.

M2P1Kl PGA=0.194 for Prairie Island 1E+1 c

0 rU

-~ 1E+O -----------

4-r-

0..

E

<(

1E-1 1E-1 1E+O 1E+1 1E+2 Frequency (Hz)

Figure 4. Amplification factors (median and median.+/- sigma) plotted from Table A2-b2 for PGA 0.194g.

34