ML13263A217

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

ML13263A217
Person / Time
Site:	Pilgrim
Issue date:	09/12/2013
From:	Dent J Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13263A217 (10)

Text

'm Entergy Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 John A. Dent, Jr.

Site Vice President 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 Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35

REFERENCE:

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", 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", dated November, 2012 (ML12333A170)

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

5. NRC Letter, "Electric Power Research Institute 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 (PNPS Letter 2.13.039)

LETTER NUMBER 2.13.071

PNPS Letter 2.13.071 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. 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, 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 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, 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 Pilgrim Nuclear Power Station (PNPS). 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 PNPS will be provided to the NRC in our seismic hazard submittal by March 31, 2014 in accordance with Reference 5.

Should you have any questions concerning the content of this letter, please contact Mr.

Joseph R. Lynch, Manager, Licensing at (508) 830-8403.

This letter contains no new regulatory commitments.

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

Sincerely, JohnA.Dn Site Vice President JAD/rmb

Attachment:

Pilgrim Nuclear Power Station Subsurface Soil Profile Information for Development of New Site Specific Ground Motion Response Spectra

PNPS Letter 2.13.071 Page 3 of 3 cc:

Mr. William M. Dean Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-1415 U. S. Nuclear Regulatory Commission Director, Office of Nuclear Reactor Regulation One White Flint North 11555 Rockville Pike Rockville, MD 20852 Ms. Nadiyah Morgan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8C2A Washington, DC 20555 Mr. John Giarrusso Jr.

Planning, Preparedness & Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 U. S. Nuclear Regulatory Commission ATTN: Robert J. Fretz Jr.

Mail Stop OWFN/4A15A 11555 Rockville Pike Rockville, MD 20852-2378 U. S. Nuclear Regulatory Commission ATTN: Robert L. Dennig Mail Stop OWFN/10E1 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Pilgrim Nuclear Power Station

ATTACHMENT to PNPS Letter 2.13.071 Pilgrim Nuclear Power Station SUBSURFACE SOIL PROFILE INFORMATION FOR DEVELOPMENT OF NEW SITE SPECIFIC GROUND MOTION RESPONSE SPECTRA

Pilgrim Nuclear Power Station Subsurface Soil Profile Information for Development of New Site Specific Ground Motion Response Spectra The following information will serve as PNPS's September 12, 2013 submittal of soil profile data to the NRC in accordance with the Fukushima 50.54(f) Letter and associated EPRI guidance document (SPID).

Based on project schedule constraints, the soil profiles were received from the vendor, Lettis Consultants International (on behalf of EPRI), via email communication without formal report format or cover letter. The information is therefore considered to be an interim product of seismic hazard development efforts being performed for PNPS by EPRI. The complete and final seismic hazard report for PNPS will be provided to the NRC in the seismic hazard submittal by March 31, 2014.

This information is captured in PNPS plant records via Engineering Change EC46443.

The site geology and soil data used by EPRI for development of the soil profiles was provided to EPRI via Pilgrim Nuclear Power Station - Site Geologic Conditions for Input to EPRI Site Amplification Analysis, Rept. PNPS-SGC-01 Rev. 0 (listed as Reference 1 on the attached EPRI transmittal) which is also captured in PNPS plant records as an attachment to Engineering Change EC46443.

Page 1 of 6

From:

Nuta, Dragos A Sent:

Tuesday, June 25, 2013 1:27 PM To:

Small, David S; Mogolesko, Fred; Buckley, Steven M; Goodwin, Scott D Cc:

Drake, Richard S

Subject:

FW: Site description for Pilgrim and Vermont Yankee sites Attachments: Pilgrim site description.doc; Vermont Yankee site description.doc Gentlemen:

I am forwarding the site soil description input developed by Robin McGuire on behalf of EPRI for your sites.

Kimberly shall be issuing a template for the letters we have to send to NRC in September.

Rega rds, Dragos A. (Dan) Nuta Design Engineering - Civil/Structural Indian Point Energy Center GSB 3rd Floor Tel. : (914) 254-7722 From: Robin McGuire [1]

Sent: Tuesday, June 25, 2013 1:10 PM To: Nuta, Dragos A Cc: Richards, John Urichards@epri.com); Bob Kassawara (rkassawa@epri.com); Lewis, Stuart (slewis@epri.com)

Subject:

Site description for Pilgrim and Vermont Yankee sites

Dear Dan,

As part of our EPRI-sponsored contract, attached are site descriptions for the Pilgrim and Vermont Yankee sites (in Word format), which you can adopt to respond to NRC requests.

Thanks, Robin Robin K McGuire, Ph.D. P.E. N.A.E.

Senior Principal Lettis Consultants International, Inc.

4155 Darley Ave, Suite A Boulder, CO 80305 Tel. 303-945-4466

Lc011, sul uts IternAtion'al, Inc.

Page 2 of 6

Pilgrim Site Description The basic information used to create the site geologic profile at the Pilgrim Nuclear Power Station 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 a depth of 48 ft below ground surface, and the profile was modeled up to this depth. For dynamic properties of rock layers, modulus and damping curves were represented with 2 models. The first model used rock curves taken from Ref. 2, 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. 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. To model the profile, rock modulus and damping curves from Ref. 2 were paired with soil modulus and damping curves from Ref. 2, and linear rock modulus and damping curves were paired with soil modulus and damping curves from Ref. 3 and Ref. 4.

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. PNPS (2012). Pilgrim Nuclear Power Station -Site Geologic Conditions for Input to EPRI Site Amplification Analysis, Rept. PNPS-SGC-01 Rev. 0, 54 pp., 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). "NonlinearSite Amplification Factors for Constraining the NGA Models," Earthquake Spectra, 24 (1) 243-255.

Page 3 of 6

Table 1 Summary of Geotechnical Profile Data for Pilgrim Nuclear Power Plant Depth Elevation Soil/Rock Shear Wave Range Elevation Velocity (feet)

MSL Description (fps) 0

+22 ft Surface Grade 0 to 20

+22 ft to +2 ft Compacted Fill 675 20 to 48

+2 ft to -26 ft Compacted Fill 900 48

-26 ft Reactor Building Foundation (SSE control point) 48 to 90

-26 ft to -68 ft Glacial Outwash 1800 90 +

-68 ft and below Bedrock 6000 Page 4 of 6

Vs profiles for Pilgrim Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0

10 20 30 50 60

-Profile 1

60 Profile 2 70

• -80 Profile 3 90 100 110i 120 130 i

150 Figure 1 Vs profiles for Pilgrim site Page 5 of 6

Table 2 Layer thicknesses, depths, and Vs for 3 profiles, Pilgrim site Profile I Profile 2 Profile 3 thickness(ft) depth (ft)

Vs(ft/s) thickness(ft) depth (ft)

Vs(ft/s) thickness(ft) depth (ft)

Vs(ft/s) 0 1800 0

1440 0

2250 5.0 5.0 1800 5.0 5.0 1440 5.0 5.0 2250 5.0 10.0 1800 5.0 10.0 1440 5.0 10.0 2250 5.0 15.0 1800 5.0 15.0 1440 5.0 15.0 2250 5.0 20.0 1800 5.0 20.0 1440 5.0 20.0 2250 2.0 22.0 1800 2.0 22.0 1440 2.0 22.0 2250 5.0 27.0 1800 5.0 27.0 1440 5.0 27.0 2250 5.0 32.0 1800 5.0 32.0 1440 5.0 32.0 2250 5.0 37.0 1800 5.0 37.0 1440 5.0 37.0 2250 5.0 42.0 1800 5.0 42.0 1440 5.0 42.0 2250 4.0 46.0 6000 4.0 46.0 3822 4.0 46.0 9285 4.0 50.0 6000 4.0 50.0 3822 4.0 50.0 9285 5.0 55.0 6000 5.0 55.0 3822 5.0 55.0 9285 5.0 60.0 6000 5.0 60.0 3822 5.0 60.0 9285 5.0 65.0 6000 5.0 65.0 3822 5.0 65.0 9285 5.0 70.0 6000 5.0 70.0 3822 5.0 70.0 9285 5.0 75.0 6000 5.0 75.0 3822 5.0 75.0 9285 5.0 80.0 6000 5.0 80.0 3822 5.0 80.0 9285 5.0 85.0 6000 5.0 85.0 3822 5.0 85.0 9285 5.0 90.0 6000 5.0 90.0 3822 5.0 90.0 9285 5.0 95.0 6000 5.0 95.0 3822 5.0 95.0 9285 5.0 100.0 6000 5.0 100.0 3822 5.0 100.0 9285 5.0 105.0 6000 5.0 105.0 3822 5.0 105.0 9285 5.0 110.0 6000 5.0 110.0 3822 5.0 110.0 9285 5.0 115.0 6000 5.0 115.0 3822 5.0 115.0 9285 5.0 120.0 6000 5.0 120.0 3822 5.0 120.0 9285 4.4 124.4 6000 4.4 124.4 3822 4.4 124.4 9285 4.4 128.8 6000 4.4 128.8 3822 4.4 128.8 9285 4.4 133.2 6000 4.4 133.2 3822 4.4 133.2 9285 4.4 137.6 6000 4.4 137.6 3822 4.4 137.6 9285 4.4 142.0 6000 4.4 142.0 3822 4.4 142.0 9285 3280.8 3422.8 9285 3280.8 3422.8 9285 3280.8 3422.8 9285 Page 6 of 6