ML20043B051

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Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario
ML20043B051
Person / Time
Site: Beaver Valley
Issue date: 05/15/1990
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9005240123
Download: ML20043B051 (3)


Text

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e Be v r Vill:y Power St tion s.

shippingport. PA 15077-0004 JOHN D $..lt b&R talb 5916265 vice p....

ni. u c, o.our May 15.,1990 U. S. Nuclear Regulatory Commission Attn:

Document-Control Desk.

Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Primary Component Support Snubber Elimination Gentlemen:

During various telecons in March, 1990 between members of my staff and the NRC staff to discuss the subject request, the NRC staff requested

a. review of load case B/G for Beaver Valley Unit 2.

Attached is the additional information-requested.

If there are any questions on this matter, please contact my office.

Very truly yours,

. D. Sieber.

Vice President

(

Nuclear Group t

I cc:

Mr. J. Beall, Sr. kr.sident Inspector Mr. T. T. Martin, HRC Region I Administrator L

Mr. A. W. DeAgazio, Sr. Project Manager i

-f 0005240123 900515 ADOCKOSOOg2 FDR 7

gart e

///

s DUQUESNE LIGHT COMPANY Nuclear Group Beaver Valley Power Station Unit #2 ATTACHMENT Additional Information Regarding Primary Comoonent Sucoort Snubber Elimination The following presents additional information which was verbally-requested by the NRC Staff in

March, 1990.

fhis information references our previous submittals dated October 27,

1988, January 4, 1989, and February 24, 1989 which submitted WCAP-11923, WCAP-12093 and WCAP-12093, Supplement 1, respectively.

The above analyses are based on the revised loading configuration due.to large bore snubber elimination and reflect the current as-built condition of Beaver Valley Unit 2.

Review of Load Combination Case B/G The NRC Staff requested a review of load combination case B/G for Beaver Valley Unit 2.

The following discussion references information provided in Section 5 of WCAP-12093 and WCAP-12093,-

Supplement 1.

Load combination case B/G is a combination of cases B and G where:

Case B:

Normal operating case with stratification (36*F Delta T)

Case G:

Earthquake (SSE) loads superimposed with heatup or cooldown stratification (315'F Delta T)-

The leakage flaw size for case B at critical location-171 is 3.10.

inches.

Twice the leakage flaw size or 6.20 inches is used to determine the J applied value.

Referring-to figure 4 of WCAP

12093, Supplement 1,

"J Versus Flaw Size for Case C/G, Node 171" and applying the case B flaw size (6.20 in.); produces a J applied value of approximately 1250 in-lb./in for B/G.

This J Casg hich relates applied value is less than J max of 3000 in-lb/in w

to a

critical flaw size of-approximately B.5 inches.

Therefore, acceptability of Case B/G is demonstrated.

Review of Probability of Case B/G Event The load combination case B/G is equivalent to postulating the discovery of a

leakage flaw during normal' operation conditions, followed by a forced cooldown to Mode 5 (RCS temperature less than.

200*F) and while at a 315'F Delta T stratification condition,-the occurrence of a safe shutdown earthquake.

The probability of the 10-gnario occurringO is estimated to be on the order of above se to 1

X 10-per reactor year.

This is based on the 1

X combination of the following probabilities:

r ATTACHMENT Page 2 Small non-isg/ reactor year a) lable 14CA (comparable to leakage flav)

- 5.83 X 10~

b)

Equipment damage due to earthquake probab!11ty

- 1 X 10~3/ reactor year to 1 X 10~4/ react or year c)

The occurrence of a

315'F Delta T stcatification is on the e

order of 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during a forced coo)down event.

a x b x c conservatively yields 1.3 x 10'S/ reactor year As shown

above, the probability of a case B/G event is extremely small and does not represent a reH istic scenario. 1X10~{/ reactor A des gn basis LOCA is estimated to have a

probability of year.

Therefore, the probability of a case B/G event is much less than other events considered in the licensing basis for Beaver Valley Unit 2.

The more realistic cases of B/E and B/FF were performed and demonstrated acceptable in WCAP-12093, Supplement 1.

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