ML20137L841

Forwards Projected Values of Ref Temp for Pressurized Thermal Shock, in Response to 10CFR50.61, Fracture Touchness Requirements for Protection Against Pressurzed Thermal Shock Events

ML20137L841
Person / Time
Site:	Beaver Valley
Issue date:	01/21/1986
From:	Sieber J DUQUESNE LIGHT CO.
To:	Tam P Office of Nuclear Reactor Regulation
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8601280104
Download: ML20137L841 (6)

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'Af M Telephone (412) 393-6000 Nuclear Group

$ppingport, PA 15077-0004 Y '

Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Mr. Peter S. Tam, Project Manager Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Assessment of RT Values PTS Gentlemen:

In accordance with 10 CFR 50.61(b)(1), the attached reply submits projected values of RTPTS for the Beaver Valley Power Station, Unit No. 1 reactor vessel beltline region materials following four (4) cycles of operation and at end-of-life.

If you have any questions concerning this reply, please contact my office.

Very truly yours,

. .' b Senior Manager Nuclear Group cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077

~U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC- 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 0 One James River Plaza 23261 Richmond, VA g

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DUQUESNE LIGHT COMPANY Nuclear Group Beaver Valley Power Station, Unit No. 1 '

Reply to 10CFR50.61 Assessment of RTPTS Values for Beaver Valley Power Station, Unit No. 1 The Final Rule on Pressurized Thermal Shock as published in 10CFR50.61 requires the submittal of current and projected values of RTPTS for reactor vessel beltline region materials. Table I provides the values for the beltline region materials at the end of 3.6 Effective Full Power Years (EFPY). These values were calculated using the cumulative fluence from the first four cycles of operation. Beaver Valley Unit 1 is currently-in the fifth cycle of operation.

The projected RTPTS values for the beltline region materials at 32 EFPY of operation or end-of-life are included in Table II. Assuming our operating license expires after 40 years from the date of issuance, we do not expect to exceed 32 EFPY of operation. These values were calculated using the cumulative f,luence from the first four cycles of operation plus the projected fluence assuming the use of low leakage core loading ~ patterns until end-of-life.

Beaver Valley Unit I has implemented the low leakage core loading pattern since Cycle 3.

Table III provides the reactor vessel beltline region material properties used

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in the calculation of RTPTS. The property values for the shell plates are docketed values and were derived from vessel fabrication test certificates.

Weld chemistry values for' copper and nickel represent a best estimate mean value and rere obtained from the Westinghouse Owner's Group (WOG) Materials Data Base. The best estimate mean values represent the mean of all chemistry data with the same wire heat as in the Beaver Valley Unit 1 beltline region in

Reply to 10CFR50.61 Assessment of RTPTS Values for Beaver Valley Power Station,-Unit No. 1 Page 2 l

combination with any flux lot. Since flux lot does not effect the copper or nickel values, the chemistry values from the WOG Materials Data Base are applicable.

As shown in Table II, the projected end-of-life RTPTS values remain below the screening criteria in 10CFR50.61(b)(2) for all Beaver Valley Unit i beltline region materials. The most limiting material is lower shell plate B6903-1 which has a projected. RTPTS value of 258"F at 32 EFPY of operation. This value is 12*F less than the screening criterion of 270*F, therefore, a flux reduction program in accordance with 10CFR50.61(b)(3) is not required to be submitted.

TABLE I .

RTPTS VALUES FOR BEAVER VALLEY ~ UNIT 1 REACTOR VESSEL REGION MATERIALS FOLLOWING FOUR CYCLES OF OPERATION l____________ ...____________________________________________________________________________________l l Vessel Material l Copper l Nickel l Initial l Effective l Fluenge l RT S l l l (Wt. %) l (Wt. %) l Reference l ' Full Power l (n/cm ) l (* J l l_ l l l Temp.(*F) l Years l l l i____________________________________________________________________________________________________.

! Intermediate'Shell l 0.14 l 0.62 l 43 l 3.6 l 0.6x1019 l 166 l l Plate B6607-1 l l l l l l l i_.______ .__________________________________________________________________________________________e

! Intermediate Shell l 0.14 l 0.62 l 73 l 3.6 l 0.6x1019 l 196 !

l Plate B6607-2 l l l l l l l

.l____________________________________________________________________________________________________l l Lower Shell Plate l 0.20 l 0.54 l 27 l 3.6 l 0.6x1019 l 181 l l B6903-1 l l l j l l l e___________________________...________________________________________...___________________________i

! Lower Shell Plate l 0.14 l 0.57 l 20 l 3.6 l 0.6x1019 l 141 !

! B7203-1 l l l l l l l i.___.___________________________________________ ..._______________________________________________ i

! Intermediate Shell l 0.28 l 0.63 l -56 l 3.6 l 0.1x1019 l 101 !

l Longitudinal Weld 19-714A,8 l l l l l l l i_____________________ ..____________________________________________________________________________i

! Intermediate to Lower Shell ! 0.29 l 0.07 l -56 l 3.6 l 0.6x1019 l 119 !

l Circumferential Weld 11-714 l l l l l l l i_________________________________________ ...._____________ ._______________________________________i

! Lower Shell l 0.34 l 0.61 l- -56 l 3.6 l 0.1x1019 l 122 !

l Longitudinal Weld-20-714A,B l l l l l l l 4

TABLE II PROJECTED RTPTS VALUES FOR BEAVER VALLEY UNIT 1 REACTOR VESSEL REGION MATERIALS AT END-0F-LIFE l______________-_-_____________....... _________________________

...........___________._........_-__l l Vessel Material l Copper l Nickel l Initial l Effective l Fluenge l RTpys l l l (Wt. %) l (Wt. %) l Reference l Full Power l (n/cm ) l (*FJ l l l l l Temp.(*F) l Years l l l i____________________________________________________________________________________________________s

! Intermediate Shell l 0.14 l 0.62 l 43 l 32 l 4.5x1019 l 221 l l Plate B6607-1 l l l l l l l i__________________________________________ ......_____________________.___.. __________________ ..._

! Intermediate Shell l 0.14 l 0.62 l 73 l 32 l 4.5x1019 l 251  !

l Plate B6607-2 l l- l l l l l i_________________________ ....________________.__........._______ _____________ .. ________________

! Lower Shell Plate l 0.20 l- 0.54 l 27 l 32 l 4.5x1019 l 258.  !

l B6903-1 l l l l l l l

! Lower Shell Plate l 0.14 l 0.57 l 20 l 32 l 4.5x1019 l 194  !

l B7203-1 l l l l l l l e___________________________________________________________________________________________________ i

! Intermediate Shell .l 0.28 l 0.63 l -56 .l 32 l 0.75x10 19 l 173'  !

l Longitudinal Weld 19-714A,B !. l l l l. ~l l i____________________________________________________________________________________________________e

! Intermediate to Lower Shell l 0.29 l 0.07 l -56 l 32  ! 4.5x1019 l 203  !

l Circumferential Weld 11-714 l l l l l l l .

! Lower Shell  ! 0.34 l 0.61 l -56 l 32 l 0.75x10 19 l 209 l l Longitudinal Weld 20-714A,B l l l l l l l j.__________________________________......._________________________________________________________ ;

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TABLE III BEAVER VALLEY UNIT 1 REACTOR VESSEL BELTLINE REGION MATERIAL PROPERTIES Initial Reference Copper Nickel Temp. (a)

(Wt.%) (Wt.%) (*F)

Intermediate Shell Plate B6607-1:

Docketed Value: .14 .62 43 Intermediate Shell Plate B6607-2:

Docketed Value: .14 .62 73 Lower Shell Plate B6903-1:

Docketed Value: .20 .54 27 Lower Shell Plate B7203-2:

Docketed Value: .14 .57 20 Longitudinal Welds - Intermediate Shell 19-714A, B, Wire Heat 305424:

WOG Data Base Mean .28 .63 -56 Circumferential Weld - Intermediate to Lower Shell 11-714, Wire Heat 90136:

WOG Data Base Mean .29 .07 -56 Longitudinal Welds - Lower Shell 20-714A, B, Wire Heat 305414:

WOG Data Base Mean .34 .61 -56 Notes:

a) The initial RTPTS values for the plates are actual values. All other weld initial RT 50.61(b)(2)(i). PTS values are generic mean values defined by 10CFR i

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