ML20203J998

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Forwards Response to Item 5 to NRC RAI Dtd 971104,re North Anna ISFSI License Application
ML20203J998
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 12/16/1997
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Paperiello C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
97-667A, TAC-L22113, NUDOCS 9712220166
Download: ML20203J998 (8)


Text

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Y t Wmsir EixcTune ANi> POWEH CO%1PANY RscusinNo, %GINI A 2M61 December 16, 1997 Mr. Carl J. Paperiello, Director Serial No. 97-667A Office of Nuclear Material Safety and Safeguards NL&OS/MAE R1 U. S. Nuclear Regulatory Commission Docket No. 72-16 Washington, D. C. 20555 Gentlemen:

.YJBQlNIA ELECTRIC AND POWER COMPANY HQBTH ANNA INDFEENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

RESPONSE TO.REQUESI FOR ADDITIONAL INFORMAIJON (TACMOJ.21113)

Virginia Electric and Power Company (Virginia Power) submitted an application for the review and approval of a site-specific license for an independent spent fuel storage installation (ISFSI) at North Anna Power Station on May 9,1995 (Serial No.95-195).

The NRC provided a Request for Additional Information to Virginia Power on November 4,1997. Virginia Power responded to the Request for Additional Information, with the exception of item 5, in a letter dated November 24,1997 (Serial No.97-667). The response to item 5 is attached.

Please contact us if you have any questions or require additional information.

Very truly yours, M

James P. O'Hanlon Senior Vice President - Nuclear Attachments Commitments made by this letter:

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Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission, Mail Stop 0-6-G 22 Washington, D. C. 20555 United States Nuclear Regulatory Commission Attention: Document Control Desk ,

Washington, D. C. 20555.

Mr. M. J. Morgan

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. Al CHMENT1 Response To A Reque; For AdditionalInformation NRC Ouestion 5:

Background:

With regard to your soil liquefaction analysis, NUREG/CR-0098, NUREG-1407, and Generic Letter 88-20, Supplement 4, were developed and used to support the IPEEE and SEP programs but do not represent licensing standards for new facilities.

Request: Please provide a soll liquefaction analysis for the ISFSI based on the North Anna site design earthquake, in accordance with 10 CFR 72.102 requirements and the Standard Review Plan guidance (e.g., NUREG-0800 criteria on response spectra).

Altematively, demonstrate that the results of your previously submitted NUREG/CR-0098-based analysis is comparable or exceeds that obtained from an analysis based on Part 72.102 requirements and SRP guidance.

Virginia Power Response:

The NRC provided clarification in a November 18,1997 telephone conversation that the analysis based on Part 72.102 requirements and SRP guidance would be an analysis done in accordance with Regulatory Guide 1.60 using a .18g earthquake. The results of a comparison of our previously submitted NUREG/CR-0098 based response spectra to a Regulatory Guide 1,60 response spectra is provided in Attachment 2. The attached plot and the associated data points for the comparison of the response spectra for a Regulatory Guide 1.60 earthquake normalized to .18g and a NUREG/CR-0098 earthquake normalized to .3g shows that the NUREG/CR-0098 response spectra envelopes the Regulatory Guide 1.60 response spectra.

Therefore, the liquefaction analysis that was previously submitted is conservative with respect to the requirements of Part 72.102 and SRP guidance.

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I Attachment 2 Comparison of NUREG/CR-0098 Based Response Spectra To Regulatory Guide 1.60 Based Response Spectra -

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Control Palats for the RG I.60 and NUREG/CR-0098 Spectra RG 1.60 The RG 1.60 control points are obtained from the amplification factors given in this Reg. Guide.

A pga value of 0.18g is used. For 5% damping, the control points are as follows:

Frequency (hz.) Amplification Factor Amplified Acceleration (g) 2.5 3.13 0.56 9.0 2.61 0.47 33.0 1.0 0.18 NUREG/CR-0098:

The control points for the NUREG/CR-0098 median centered (50%) horizontal spectra are determined from the following information given in the NUREG:

v/a= 36 in/sec/g (for soil, where v is the velocity, a is acceleration); and ad/v2 = 6.0 (d is the displacement)

Based on this, the control Points for the median-centen.d spectra at 5% damping are as follows:

Frequency (hz.) Amplification Factor Amplified Acceleration (g) 1.678 2.12 0.636 7.886 2.12 0.636 33.33 1.0 0.30

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SYSta r CHECKED BY N DATE: /1~ bi 7 AMPLIFIED RESPONSE SPECTRUM VALUES

-FREQ(Hz) ACCEL (g) PERIOD FREQ (Hz) ACCEL (g) PERIOD 0.100 0.010 10.000 0.200 0.060 5.000 1.000 0.270 1.000 2.500 0.560 0.400 9.000 0.470 0.111 33.000 0.180 0.030 50.000 0.180 0.020 100.000 0.180 0.010 hI'lO, W 0' A

&tN f, N*f' SURRY/ NORTH ANNA RESPONSE SPECTRA DATABASE--ARS MODEL INFORMATION RG 1.60 Horiz. Ground ARS normalized to 0.189 pga and NUREG CR-0098 ground ARS normalized to 0.3g pga. Both at 5% Damping STRUCTURE: RG1.60 EQUIP DAMPING: 5.0%

UNIT: RG1.60 CURVE TYPE: Broadened DIRECTION: Horizontal FACTOR: 1.000

-ELEVATION: Free-Field (Ground) PEAK ACCEL (g): 0.560 EQ TYPE: Design basis earthqua::e EVAL ACCEL (g) :

SOURCE: RG1.60 NUM POINTS: 8 l PLOT LABEL: UXXXXHGRDD050B0050

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hf g 3 srstax, caserID BYt M7NDATEt81*Y~i7 AMPLIFIED RESPONSE SPECTRUM VALUES FREQ(Hz) ACCEL (g) PERIOD FREQ(Hz) ACCEL (g) PERIOD 0.100 0.015 10.000 0.200 0.062 5.000 0.506 0.196 1.976 1.020 0.394 0.980 1.678 0.636 0.596 7.886 0.636 0.127 10.120 0.561 0.099 17.090 0.425 0.059 23.065 0.363 0.043 29.604 0.318 0.034 33.333 0.300 0.030 100.000 0.300 0.010 Nutec C9-a#, nenkudf 0 3y & (g;l heiamkl,Yj.'def}

SURRY/ NORTH ANNA RESPONSE SPECTRA DATABASE--ARS MODEL INFORMATION RG 1.60 Horiz. Ground ARS normalized to 0.18g pga and NUREG CR-0098 ground ARS normalized to 0.3g pga. Both at 5% Damping STRUCTURE: NUREG 0098 EQUIP DAMPING: 5.0%

UNIT: NUREG 0098 CURVE TYPE: Broadened DIRECTION: Horizontal FACTOR: 1.000 ELEVATION: Free-Field (Ground) PEAK ACCEL (g) : 0.636 EQ TYPE: NUREG/CR-0098 EVAL ACCEL (g) :

SOURCE: Nt' REG 0098 NUM POINTS: 12 PLOT LABEL: UYYYYHGRDN050B0060