ULNRC-06030, Response to NRC Request for Information Pursuant to 10CFR50.54(T) Regarding Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-Ichi Accident - 1.5 Year Responses for Ceus Site

From kanterella
Revision as of 13:30, 4 November 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Response to NRC Request for Information Pursuant to 10CFR50.54(T) Regarding Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-Ichi Accident - 1.5 Year Responses for Ceus Site
ML13256A067
Person / Time
Site: Callaway Ameren icon.png
Issue date: 09/12/2013
From: Reasoner C
Ameren Missouri
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-06030
Download: ML13256A067 (9)
v • d • e


Text

~~

Cleve Reasoner Vice President Engineering WAmeren Ameren Missouri Callaway Energy Center T 573.676.8241 MISSOURI F 573.676.4056

...............................................................................................................................................................................................................................................

September 12, 2013 ULNRC-06030 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 10 CFR 50.54(t)

Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 AMEREN MISSOURI RESPONSE TO NRC REQUEST FOR INFORMATION PURSUANT TO 10CFR50.54(t) 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 RESPONSES FOR CEUS SITES

References:

1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(t) Regarding Recommendations 2.1, 2.3, and 9.3, ofthe Near-Term Task Force Review oflnsights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ML12053A340)
2. NRC Letter, Endorsement ofEPRI 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 ofFukushima 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 (ML13101A379)

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

........................................................................................................

                                                                                                                                                                                                                • Junction CC & Hwy 0

........................................................................................................ Fulton, MD 65251 AmerenMissouri.com

........................................................................................................ PO Box 620, MC CA*460

ULNRC-06030 September 12, 2013 Page2 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, the NRC agreed with this recommendation.

The attachment to this letter contains the requested descriptions of subsurface materials and properties and base case velocity profiles for Ameren Missouri. 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 reports for Ameren Missouri will be provided to the NRC in our seismic hazard submittals by March 31,2014 in accordance with Reference 5.

This letter contains no new regulatory commitments.

Should you have any questions concerning the content of this letter, please contact Scott Maglio, Regulatory Affairs Manager, at 573-676-8719.

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

Sincerely, Executed on: '1/J z./C:V 13

Cleveland Reasoner Vice President, Engineering Enclosure

ULNRC-06030 September 12, 2013 Page 3 cc: Mr. Steven A. Reynolds Acting Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office of Nuclear Reactor Regulation

  • U.S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738 Mr. Eric Leeds Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-13H16M Washington, DC 20555-0001 Mr. Jack Davis Director, Mitigation Strategies Directorate Office ofNuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

ULNRC-06030 September 12, 2013 Page4 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)

Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:

A. C. Heflin F. M. Diya C. 0 . Reasoner III L. H. Graessle S. A. Maglio T. B. Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)

Enclosure to ULNRC-06030 Callaway Site Description The basic information used to create the site geologic profile at the Callaway Nuclear Power Plant is shown in Figure 1. This information was documented in the Callaway FSAR Unit 2 (Ref. 1). As indicated in Figure 1, the nuclear island foundation level is at the top ofthe Graydon Chert Conglomerate unit, at a depth of approximately 37 feet, and this was taken as the SSE Control Point.

For purposes of site amplification calculations, the profile was modeled up to the SSE Control Point.

For dynamic properties of rock layers, modulus and damping curves were represented with 2 models.

The first model used rock curves taken from Reference 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 Reference 2, the second model used soil curves taken from Reference 3 and Reference 4. These dynamic property models were weighted equally. To model the profile, rock modulus and damping curves from Reference 2 were paired with soil modulus and damping curves from Reference 2, and linear rock modulus and damping curves were paired with soil modulus and damping curves from Reference 3 and Reference 4.

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

References

1. UniStar Nuclear Services (2009). FSAR Callaway Unit 2, Revision 2, Figure 2.5.2-19.
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 Natl. 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.

Page 1 ofS

Enclosure to ULNRC-06030 Vs [fps] Vs (fps) 0 3000 6000 9000 12000 0 3000 6000 9000 12000 0 ' '

- *~- - - - --- ---*---_l__ -- ------- -~~E~~

§) Nl FOUNDATION I ACCRETION-GLEY

.l::: _/._-- -~~--- - __1-r --- "(;[AciAI."riCL

- ~- - -- - - - --- -r----L - - -------- --

50 1 GRAYOONCHERT l2.337j I CONGLOMERATE 400 E§j. J ___ - BOFI.lW'..li'USAB.

-- -- -- - I J~.04!) SNYDERCREEKl

-- - -- - - - - - 1 - - - - - - - - -- ----

100 1@ill I SNYDER CREEK 2

  • ----.. ----- I *----------*

1 ls.JSSI 800 I CALLAWAY 150

-- ----------------- ~ ----- -----

1 COTTER I 1&.950 I I

JEFFERSON CITY1 g

-

J::.

a.

Q)

-- ----..l- - - --- ---- ---- J::.

c. 1200 0

G>

0 200 COTIER JEFFERSON CITY2 210 $

10

...... .6 lutsl 1600 E 250 Ul iii U)  :;

c. c w C. w 6" iii Q) 6 iii Q) 10 10 300 2000 350 I I:

Vs(fps)

-1~1

  • 0.05 0.05 0.15 0.25 0.35 *0.05 0.05 0.15 0.25 0.35

<11n{Vs) <11n{Vs)

Vs {lpsJ =Shear Wave Velocity of Soil or Rock Formation, in Feet per Second

<11n{Vs) =Coeff~eient of Variation (Logarithimic Standard Deviation) of Shear Wave Velocity Figure 1. Summary of Stratigraphy and Shear-Wave Velocity for Callaway Nuclear Power Plant Page 2 ofS

Enclosure to ULNRC-06030 Vs profiles for Callaway Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0

200

I

I 400 600 800 - Profile 1 g 1000

.r.

- Profile2 i

Q 1200

- Profile3 1400 1600 1800 2000 2200 Figure 2. Vs profiles for Callaway Nuclear Power Plant Page 3 ofS

Enclosure to ULNRC-06030 Table 1. Layer thicknesses, depths, and V s for 3 profiles, Callaway Nuclear Power Plant 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/~

0 2329 0 1864 0 2912 5.0 5.0 2329 5.0 5.0 1864 5.0 5.0 2912 5.0 10.0 2329 5.0 10.0 1864 5.0 10.0 2912 5.0 15.0 2329 5.0 15.0 1864 5.0 15.0 2912 5.0 20.0 2329 5.0 20.0 1864 5.0 20.0 2912 1.5 21.5 2329 1.5 21.5 1864 1.5 21.5 2912 5.0 26.5 2329 5.0 26.5 1864 5.0 26.5 2912 5.0 31.5 2329 5.0 31.5 1864 5.0 31.5 2912 6.6 38.1 4068 6.6 38.1 3255 6.6 38.1 5085 10.5 48.6 6037 10.5 48.6 4829 10.5 48.6 7546 1.4 50.0 3707 1.4 50.0 2966 1.4 50.0 4634 6.2 56.2 3707 6.2 56.2 2966 6.2 56.2 4634 6.2 62.4 3707 6.2 62.4 2966 6.2 62.4 4634 6.2 68.6 3707 6.2 68.6 2966 6.2 68.6 4634 9.4 78.0 8366 9.4 78.0 6693 9.4 78.0 9285 9.4 87.4 8366 9.4 87.4 6693 9.4 87.4 9285 9.4 96.9 8366 9.4 96.9 6693 9.4 96.9 9285 9.4 106.3 8366 9.4 106.3 6693 9.4 106.3 9285 6.8 113.1 6955 6.8 113.1 5564 6.8 113.1 8694 6.8 120.0 6955 6.8 120.0 5564 6.8 120.0 8694 9.6 129.6 6955 9.6 129.6 5564 9.6 129.6 8694 9.6 139.1 6955 9.6 139.1 5564 9.6 139.1 8694 11.1 150.2 8333 11.1 150.2 6667 11.1 150.2 9285 11.1 161.3 8333 11.1 161.3 6667 11.1 161.3 9285 11.1 172.4 8333 11.1 172.4 6667 11.1 172.4 9285 11.1 183.5 8333 11.1 183.5 6667 11.1 183.5 9285 11.1 194.6 8333 11.1 194.6 6667 11.1 194.6 9285 11.1 205.6 8333 11.1 205.6 6667 11.1 205.6 9285 11.1 216.7 8333 11.1 216.7 6667 11.1 216.7 9285 11.1 227.8 8333 11.1 227.8 6667 11.1 227.8 9285 11.1 238.9 8333 11.1 238.9 6667 11.1 238.9 9285 11.1 250.0 8333 11.1 250.0 6667 11.1 250.0 9285 25.0 275.0 8333 25.0 275.0 6667 25 .0 275.0 9285 25.0 300.0 8333 25.0 300.0 6667 25.0 300.0 9285 25.0 325.0 8333 25.0 325.0 6667 25.0 325.0 9285 25 .0 350.0 8333 25.0 350.0 5308 25.0 350.0 9285 25.0 375.0 8333 25.0 375.0 5308 25 .0 375.0 9285 25.0 400.0 8333 25.0 400.0 5308 25 .0 400.0 9285 Page 4 ofS

Enclosure to ULNRC-06030 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) 25 .0 425.0 8333 25.0 425.0 5308 25.0 425.0 9285 25.0 450.0 8333 25.0 450.0 5308 25.0 450.0 9285 25.0 475.0 8333 25.0 475.0 5308 25 .0 475.0 9285 25.0 500.0 8333 25.0 500.0 5308 25.0 500.0 9285 33.6 533.6 8333 33.6 533.6 5308 33.6 533.6 9285 33.6 567.2 8333 33.6 567.2 5308 33.6 567.2 9285 33.6 600.9 8333 33.6 600.9 5308 33.6 600.9 9285 33.6 634.5 8333 33.6 634.5 5308 33.6 634.5 9285 33.6 668.1 8333 33.6 668.1 5308 33 .6 668.1 9285 84.1 752.2 8333 84.1 752.2 5308 84.1 752.2 9285 84.1 836.2 8333 84.1 836.2 5308 84.1 836.2 9285 168.1 1004.3 8333 168.1 1004.3 5308 168.1 1004.3 9285 168.1 1172.4 8333 168.1 1172.4 5308 168.1 1172.4 9285 168.1 1340.5 8333 168.1 1340.5 5308 168.1 1340.5 9285 168.1 1508.7 8333 168.1 1508.7 5308 168.1 1508.7 9285 168.1 1676.8 8333 168.1 1676.8 5308 168.1 1676.8 9285 168.1 1844.9 8333 168.1 1844.9 5308 168.1 1844.9 9285 168.1 2013.0 8333 168.1 2013.0 5308 168.1 2013.0 9285 168.1 2181.1 8333 168.1 2181.1 5308 168.1 2181.1 9285 3280.8 5461.9 9285 3280.8 5461.9 9285 3280.8 5461.9 9285 Page 5 ofS

Retrieved from "https://kanterella.com/w/index.php?title=ULNRC-06030,_Response_to_NRC_Request_for_Information_Pursuant_to_10CFR50.54(T)_Regarding_Seismic_Aspects_of_Recommendation_2.1_of_the_Near-Term_Task_Force_Review_of_Insights_from_Fukushima_Dai-Ichi_Accident_-_1.5_Year_Responses_for_Ceus_Site&oldid=2058349"