NG-13-0364, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites

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Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites
ML13256A097
Person / Time
Site: Duane Arnold 
(DPR-049)
Issue date: 09/11/2013
From: Richard Anderson
NextEra Energy Duane Arnold
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-13-0364
Download: ML13256A097 (9)


Text

NEXTera SER

,,- ý A R NO0L D September 11, 2013 NG-13-0364 10 CFR 50.54(f)

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op. License No. DPR-49 NextEra Energy Duane Arnold, LLC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Reaardina Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insiahts from the Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites

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

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

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NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Document Control Desk NG-1 3-0364 Page 2 of 3 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 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, 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.

The enclosed response contains the requested descriptions of subsurface materials and properties and base case velocity profiles for the Duane Arnold Energy Center. The information in the enclosure is considered an interim product of seismic hazard development efforts being performed for the industry by EPRI. NextEra Energy Duane Arnold, LLC will provide the complete and final seismic hazard reports to the NRC in our seismic hazard submittals by March 31, 2014 in accordance with Reference 5.

This letter contains no new regulatory commitments.

If you have any questions or require additional information, please contact Ken Putnam at 319-851-7238.

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

Executed on September 11, 2013 Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosure

Document Control Desk NG-13-0364 Page 3 of 3 cc:

Regional Administrator, USNRC, Region III Resident Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center

Attachment to NG-13-0364 NextEra Energy Duane Arnold, LLC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Reqarding 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 5 pages follow

Duane Arnold Site Description The basic information used by EPRI to create the site geologic profile at the Duane Arnold Energy Center is shown in the attached Figure 2.5-9 taken directly from Reference 1. The foundation of the Reactor Building is approximately 50 foot below grade, and this location is taken as the SSE Control Point. The profile was modeled up to this location. For dynamic properties of soft rock layers, modulus and damping curves were represented with two models. The first model used rock curves taken from Reference 2; the second model assumed linear behavior. These dynamic property models were weighted equally.

The three 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. Updated Final Safety Analysis Report for Duane Arnold Energy Center, Revision 22, May, 2013, Section 2.5.2, Vibratory Ground Motion.
2. EPRI (1993), Guidelines for Determining Design Basis Ground Motions, Electric Power Research Institute, Palo Alto, CA, Rept. TR-102293, Vol. 1-5.

Page 1 of 5

Vs profiles for Duane Arnold Site Vs (ft/sec) 3000 4000 5000 6000 0

1000 2000 7000 8000 9000 10000 0

200 400 600 800 1000 1200 C 1400 1600 1800 2000 2200 2400 2600 4-

-Prfile

-Profile 1

-Profile 2

Figure 1. Vs profiles for Duane Arnold Site Page 2 of 5

Table 2. Layer Thicknesses, Depths, And Vs For 3 Profiles, Duane Arnold Site Profile 1 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 8600 0

5477 0

9285 10.0 10.0 8600 10.0 10.0 5477 10.0 10.0 9285 10.0 20.0 8600 10.0 20.0 5477 10.0 20.0 9285 10.0 30.0 8600 10.0 30.0 5477 10.0 30.0 9285 10.0 40.0 8600 10.0 40.0 5477 10.0 40.0 9285 10.0 50.0 8600 10.0 50.0 5477 10.0 50.0 9285 10.0 60.0 8600 10.0 60.0 5477 10.0 60.0 9285 10.0 70.0 8600 10.0 70.0 5477 10.0 70.0 9285 10.0 80.0 8600 10.0 80.0 5477 10.0 80.0 9285 10.0 90.0 8600 10.0 90.0 5477 10.0 90.0 9285 10.0 100.0 8600 10.0 100.0 5477 10.0 100.0 9285 10.0 110.0 8600 10.0 110.0 5477 10.0 110.0 9285 10.0 120.0 8600 10.0 120.0 5477 10.0 120.0 9285 10.0 130.0 8600 10.0 130.0 5477 10.0 130.0 9285 10.0 140.0 8600 10.0 140.0 5477 10.0 140.0 9285 10.0 150.0 8600 10.0 150.0 5477 10.0 150.0 9285 10.0 160.0 8600 10.0 160.0 5477 10.0 160.0 9285 10.0 170.0 8600 10.0 170.0 5477 10.0 170.0 9285 10.0 180.0 8600 10.0 180.0 5477 10.0 180.0 9285 10.0 190.0 8600 10.0 190.0 5477 10.0 190.0 9285 10.0 200.0 8600 10.0 200.0 5477 10.0 200.0 9285 10.0 210.0 8600 10.0 210.0 5477 10.0 210.0 9285 10.0 220.0 8600 10.0 220.0 5477 10.0 220.0 9285 10.0 230.0 8600 10.0 230.0 5477 10.0 230.0 9285 10.0 240.0 8600 10.0 240.0 5477 10.0 240.0 9285 10.0 250.0 8600 10.0 250.0 5477 10.0 250.0 9285 10.0 260.0 8600 10.0 260.0 5477 10.0 260.0 9285 10.0 270.0 8600 10.0 270.0 5477 10.0 270.0 9285 10.0 280.0 8600 10.0 280.0 5477 10.0 280.0 9285 10.0 290.0 8600 10.0 290.0 5477 10.0 290.0 9285 10.0 300.0 8600 10.0 300.0 5477 10.0 300.0 9285 10.0 310.0 8600 10.0 310.0 5477 10.0 310.0 9285 10.0 320.0 8600 10.0 320.0 5477 10.0 320.0 9285 10.0 330.0 8600 10.0 330.0 5477 10.0 330.0 9285 10.0 340.0 8600 10.0 340.0 5477 10.0 340.0 9285 10.0 350.0 8600 10.0 350.0 5477 10.0 350.0 9285 10.0 360.0 8600 10.0 360.0 5477 10.0 360.0 9285 10.0 370.0 8600 10.0 370.0 5477 10.0 370.0 9285 10.0 380.0 8600 10.0 380.0 5477 10.0 380.0 9285 Page 3 of 5

Profile 1 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) 5.9 385.9 9285 5.9 385.9 5942 5.9 385.9 9285 26.0 412.0 9285 26.0 412.0 5942 26.0 412.0 9285 26.0 438.0 9285 26.0 438.0 5942 26.0 438.0 9285 26.0 464.0 9285 26.0 464.0 5942 26.0 464.0 9285 26.0 490.0 9285 26.0 490.0 5942 26.0 490.0 9285 26.0 516.0 9285 10.9 500.9 5942 10.9 500.9 9285 38.4 554.4 9285 53.6 554.4 5942 53.6 554.4 9285 38.4 592.9 9285 38.4 592.9 5942 38.4 592.9 9285 38.4 631.3 9285 38.4 631.3 5942 38.4 631.3 9285 38.4 669.7 9285 38.4 669.7 5942 38.4 669.7 9285 38.4 708.1 9285 38.4 708.1 5942 38.4 708.1 9285 57.8 766.0 9285 57.8 766.0 5942 57.8 766.0 9285 106.2 872.2 9285 106.2 872.2 5942 106.2 872.2 9285 151.3 1023.5 9285 151.3 1023.5 5942 151.3 1023.5 9285 164.0 1187.5 9285 164.0 1187.5 5942 164.0 1187.5 9285 164.0 1351.6 9285 164.0 1351.6 5942 164.0 1351.6 9285 164.0 1515.6 9285 164.0 1515.6 5942 164.0 1515.6 9285 164.0 1679.7 9285 164.0 1679.7 5942 164.0 1679.7 9285 164.0 1843.7 9285 164.0 1843.7 5942 164.0 1843.7 9285 164.0 2007.7 9285 164.0 2007.7 5942 164.0 2007.7 9285 164.0 2171.8 9285 164.0 2171.8 5942 164.0 2171.8 9285 164.0 2335.8 9285 164.0 2335.8 5942 164.0 2335.8 9285 164.0 2499.9 9285 164.0 2499.9 5942 164.0 2499.9 9285 3280.8 5780.7 9285 3280.8 5780.7 9285 3280.8 5780.7 9285 Page 4 of 5

0 100 200 300 i00.-

II 0?T 1:

1FTSCAL PROPERTIES ARE MEASURED VALUES UNLESS NOrFD 01HERWSSZ.