W3F1-2013-0053, Entergys 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

Entergys 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 CE

ML13259A277
Person / Time
Site:	Waterford
Issue date:	09/12/2013
From:	Jacobs D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2013-0053
Download: ML13259A277 (9)

Text

Entergy Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6678 djacob2@entergy.com Donna Jacobs Vice President - Operations Waterford 3 W3F1-2013-0053 September 12, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Entergy'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 Waterford Steam Electric Station, Unit 3 (Waterford 3)

Docket No. 50-382 License No. NPF-38

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 (ML12053A340)

2.

NRC Letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2013 (ML12319A074)

3.

EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic (ML12333A170)

4.

NEI Letter to NRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (ML13101A345)

5.

NRC Letter, EPRI Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of 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 (ML13106A331)

6.

Entergy letter to NRC, Entergy'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 (ML13119A461)

W3F1 -2013-0053 Page 2 of 3

Dear Sir or Madam:

On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status.

Enclosure I 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 the NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to the NRC by March 31, 2014. In Reference 5, the NRC agreed with this recommendation. Reference 6 contained Entergy's commitment to follow the approach described in Reference 4.

The attachment to this letter contains the requested descriptions of subsurface materials and properties and base case velocity profiles for Waterford Steam Electric Station, Unit 3 (Waterford 3). The information provided in the attachment to this letter is considered an interim product of seismic hazard development efforts being performed for the industry by EPRI. The complete and final seismic hazard report for Waterford 3 will be provided to the NRC in our seismic hazard submittal by March 31, 2014 in accordance with Reference 5.

There are no new regulatory commitments identified in this submittal. Should you have any questions concerning the content of this letter, please contact Bryan J. Pellegrin, Licensing Manager (acting), at (504) 739-6203.

I declare under penalty of perjury that the foregoing is true and correct. Executed on September 12, 2013.

Sincerely, DJ/WH

Attachment:

Waterford Steam Electric Station, Unit 3, Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles

W3F1 -2013-0053 Page 3 of 3 cc:

Attn: Director, Office of Nuclear Reactor Regulation U. S. NRC RidsNrrMailCenter@nrc.gov Mr. Steven Reynolds, Regional Administrator (acting)

U. S. NRC, Region IV RidsRgn4MailCenter@nrc.gov NRC Project Manager for Waterford 3 Kaly. Kalyanam@nrc.gov NRC Senior Resident Inspector for Waterford 3 Marlone. Davis@nrc.gov

Attachment to W3FI -2013-0053 Waterford Steam Electric Station, Unit 3, Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles

Attachment to W3F1-2013-0053 Page 1 of 5 Waterford 3 site description:

The basic information used to create the site geologic profile at the Waterford Steam Electric Station, Unit 3 (Waterford 3), is shown in Table 1. This profile was developed using information documented in Ref. 1. As indicated in Table 1, the SSE Control Point is defined at elevation

-47 ft MSL, and the profile was modeled up to this elevation. For dynamic properties of sand and clay layers, modulus and damping curves were represented with 2 models. The first model used soil curves taken from Ref. 2, the second model used soil curves taken from Ref. 3 and Ref. 4. These dynamic property models were weighted equally.

The 3 base-case shear-wave velocity profiles used to model amplification at the site are shown in Figure 1. Profiles 1, 2, and 3 are weighted 0.4, 0.3, and 0.3, respectively. Thicknesses, depths, and shear-wave velocities (Vs) corresponding to each profile are shown in Table 2.

References

1. Entergy (2012). Site Geologic Conditions for Waterford 3 Steam Electric Station, Informal report transmitted to EPRI in July, 2012.

2. EPRI (1993). Guidelines for Determining Design Basis Ground Motions, Elec. Power Res.

Inst., Palo Alto, CA, Rept. TR-102293, Vol. 1-5.

3. Silva, W.J., N. A. Abrahamson, G.R. Toro, and C. Costantino (1996). Description and Validation of the Stochastic Ground Motion Model, Rept. submitted to Brookhaven Nati.

Lab., Assoc. Universities Inc., Upton NY 11973, Contract No. 770573.

4. Walling, M.A., W.J., Silva and N.A. Abrahamson (2008). "Nonlinear Site Amplification Factors for Constraining the NGA Models," Earthquake Spectra, 24 (1) 243-255.

Attachment to W3F1-2013-0053 Page 2 of 5 Table 1 Geotechnical profile for Waterford 3 site Depth Elev.

Soil Description Density Shear Compressional Poisson's

• Range (feet (pcf)

Wave Wave Velocity Ratio (feet)

MSL)

Velocity (fps)'

(fps) 0-55

+15 to Clay and silty clay with 111 N.A.

3000 +/-500 0.48

-40 silt and sand lenses (recent material)

(included for information only)

SSE

-47 control point 55 - 92

-40 to Stiff tan and gray fissured 119 850 5700 +/- 700 0.49

-77 clay 92 - 107

-77 to Very dense tan silty sand 125 925 5700 +/- 700 0.48

-92 107 - 123

-92 to Medium stiff gray clay 119 925 5700 +/- 700 0.49

-108 with silt lenses 123-131

-108 to Stiff dark gray clay -

104 1000 5700 +/-700 0.49

-116 organic 131-142

-116 to Soft to medium stiff tan 119 1000 5700 +/-700 0.49

-127 and gray clay with sand lenses 142-332

-127 to Very stiff clays with silts 119 1100-N.A.

0.48

-317 and sands 1150 332-515

-317 to Very dense sands and 119 to 1600-N.A 0.45

-500 silty sands 125 1650 1 Uphole Seismic Survey NOTES: The foundation for the nuclear island is at elevation -47 ft, MSL, at the top of the Pleistocene material. Top of grade is considered to be at elevation +15 ft, MSL.

Attachment to W3F1-2013-0053 Page 3 of 5 0

1000 20C 0

500 1000 1500 2000 2500 3000 3500 4000 4500 Vs profiles for Waterford Site Vs (ft/sec) 00 3000 4000 5000 6000 7000 8000 9000 10000

-Profile 1

-Profile 2

Profile 3 Figure 1. Vs profiles for Waterford 3 site

Attachment to W3F1-2013-0053 Page 4 of 5 Table 2 Layer thicknesses, depths, and Vs for 3 profiles, Waterford 3 site Profile 1 Profile 2 Profile 3 thickness depth Vs thickness depth Vs thickness depth Vs (ft)

(ft)

(ft/s)

(ft)

(ft)

(ft/s)

(ft)

(ft)

(ft/s) 0 850 0

680 0

1062 9.2 9.2 850 9.2 9.2 680 9.2 9.2 1062 9.2 18.5 850 9.2 18.5 680 9.2 18.5 1062 1.5 20.0 850 1.5 20.0 680 1.5 20.0 1062 8.5 28.5 850 8.5 28.5 680 8.5 28.5 1062 8.5 37.0 850 8.5 37.0 680 8.5 37.0 1062 7.5 44.5 925 7.5 44.5 740 7.5 44.5 1156 7.5 52.0 925 7.5 52.0 740 7.5 52.0 1156 8.0 60.0 925 8.0 60.0 740 8.0 60.0 1156 8.0 68.0 925 8.0 68.0 740 8.0 68.0 1156 8.0 76.0 1000 8.0 76.0 800 8.0 76.0 1250 11.0 87.0 1000 11.0 87.0 800 11.0 87.0 1250 12.7 99.7 1125 12.7 99.7 900 12.7 99.7 1406 12.7 112.3 1125 12.7 112.3 900 12.7 112.3 1406 7.7 120.0 1125 7.7 120.0 900 7.7 120.0 1406 8.8 128.8 1125 8.8 128.8 900 8.8 128.8 1406 8.8 137.7 1125 8.8 137.7 900 8.8 137.7 1406 12.7 150.3 1125 12.7 150.3 900 12.7 150.3 1406 12.7 163.0 1125 12.7 163.0 900 12.7 163.0 1406 12.7 175.7 1125 12.7 175.7 900 12.7 175.7 1406 12.7 188.3 1125 12.7 188.3 900 12.7 188.3 1406 12.7 201.0 1125 12.7 201.0 900 12.7 201.0 1406 12.7 213.7 1125 12.7 213.7 900 12.7 213.7 1406 12.7 226.3 1125 12.7 226.3 900 12.7 226.3 1406 12.7 239.0 1125 12.7 239.0 900 12.7 239.0 1406 12.7 251.7 1125 12.7 251.7 900 12.7 251.7 1406 12.7 264.3 1125 12.7 264.3 900 12.7 264.3 1406 12.7 277.0 1125 12.7 277.0 900 12.7 277.0 1406 18.3 295.3 1625 18.3 295.3 1040 18.3 295.3 2551 18.3 313.6 1625 18.3 313.6 1040 18.3 313.6 2551 18.3 331.9 1625 18.3 331.9 1040 18.3 331.9 2551 18.3 350.2 1625 18.3 350.2 1040 18.3 350.2 2551 18.3 368.5 1625 18.3 368.5 1040 18.3 368.5 2551 18.3 386.8 1625 18.3 386.8 1040 18.3 386.8 2551

Attachment to W3F1-2013-0053 Page 5 of 5 Table 2 (continued)

Profile 1 Profile 2 Profile 3 thickness depth Vs thickness depth Vs thickness depth Vs M*

(ft)

Cft/s)

(ft)

(ft)

(rids) ft) ft)

(ft/s) 18.3 405.1 1625 18.3 405.1 1040 18.3 405.1 2551 18.3 423.4 1625 18.3 423.4 1040 18.3 423.4 2551 18.3 441.7 1625 18.3 441.7 1040 18.3 441.7 2551 18.3 460.0 1625 18.3 460.0 1040 18.3 460.0 2551 40.0 500.0 2005 40.0 500.0 1283 40.0 500.0 3147 40.0 540.1 2005 40.0 540.1 1283 40.0 540.1 3147 40.0 580.1 2005 40.0 580.1 1283 40.0 580.1 3147 40.0 620.1 2005 40.0 620.1 1283 40.0 620.1 3147 40.0 660.1 2005 40.0 660.1 1283 40.0 660.1 3147 42.7 702.8 2005 42.7 702.8 1283 42.7 702.8 3147 42.7 745.4 2005 42.7 745.4 1283 42.7 745.4 3147 42.7 788.1 2005 42.7 788.1 1283 42.7 788.1 3147 65.6 853.7 2182 65.6 853.7 1396 65.6 853.7 3425 65.6 919.3 2182 65.6 919.3 1396 65.6 919.3 3425 65.6 984.9 2182 65.6 984.9 1396 65.6 984.9 3425 65.6 1050.6 2182 65.6 1050.6 1396 65.6 1050.6 3425 65.6 1116.2 2182 65.6 1116.2 1396 65.6 1116.2 3425 65.6 1181.8 2359 65.6 1181.8 1510 65.6 1181.8 3704 65.6 1247.4 2359 65.6 1247.4 1510 65.6 1247.4 3704 65.6 1313.0 2359 65.6 1313.0 1510 65.6 1313.0 3704 65.6 1378.6 2359 65.6 1378.6 1510 65.6 1378.6 3704 65.6 1444.3 2359 65.6 1444.3 1510 65.6 1444.3 3704 131.2 1575.5 2552 131.2 1575.5 1634 131.2 1575.5 4007 131.2 1706.7 2552 131.2 1706.7 1634 131.2 1706.7 4007 131.2 1838.0 2552 131.2 1838.0 1634 131.2 1838.0 4007 131.2 1969.2 2552 131.2 1969.2 1634 131.2 1969.2 4007 131.2 2100.4 2552 131.2 2100.4 1634 131.2 2100.4 4007 131.2 2231.7 2871 131.2 2231.7 1837 131.2 2231.7 4507 131.2 2362.9 2871 131.2 2362.9 1837 131.2 2362.9 4507 131.2 2494.1 2871 131.2 2494.1 1837 131.2 2494.1 4507 131.2 2625.4 2871 131.2 2625.4 1837 131.2 2625.4 4507 131.2 2756.6 2871 131.2 2756.6 1837 131.2 2756.6 4507 1246.5 4003.1 3054 1246.5 4003.1 1955 1246.5 4003.1 4795 3280.8 7283.9 9285 3280.8 7283.9 9285 3280.8 7283.9 9285