ML20154Q083

Forwards Corrections to 860120 Pressurized Thermal Shock Submittal Updating Tables 1 & 4,per 860314 Discussions W/T Colburn & P Randall.WCAP-10638, Adjoint Flux Program for Point Beach..., Also Encl

ML20154Q083
Person / Time
Site:	Point Beach
Issue date:	03/14/1986
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, Lear G Office of Nuclear Reactor Regulation
Shared Package
ML20154Q088	List: ML20154Q083 ML20154Q100
References
CON-NRC-86-24, REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR TAC-59972, TAC-59973, VPNPD-86-131, VPNPO-86-131, NUDOCS 8603210027
Download: ML20154Q083 (3)

Text

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l Wisconsin Electnc eom coww 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 VPNPD-86-131 NRC-86-24 March 14, 1986 Mr. H. R. Denton, Director 1 Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. G. Lear, Project D'irector PWR Project Directorate No. A Gentlemen:

DOCKET NOS. 50-266 AND 50-301 CORRECTION TO PRESSURIZED THERMAL SHOCK (PTS)

SUBMITTAL DATED JANUARY 20, 1986 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 This letter corrects the subject submittal from Mr. C. W. Fay to Mr. H. R. Denton by providing updates to Table 1 and Table 4 (attached) . In Table 1, the correct weld wire heat number has been inserted for SA-1101, the circumferential weld - intermediate to lower shell. In Table 4, RTPTS values for SA-775/812, which were previously transposed under the SA-847 column, have been properly listed. The true RTPTS values for SA-847 have also been added. These changes were discussed with Messrs. T. Colburn and P. Randall of your staff on March 14, 1986. Also, as requested, we are providing background documentation from WCAP-10638, " Adjoint Flux Program for Point Beach Units 1 and 2", concerning the fluence calculations in our PTS submittal.

Thank you for bringing these errors to our attention. Please contact us if additional information is required.

Very truly yours,

/ e603210027 B60314

( 6C/ &[ DR ADOCK 050 g 6 C. W. Fay Vice President Nuclear Power Attachment Copy to NRC Resident Inspector \\\

i

s. -

TABLE 1 POINT BEACH UNITS 1 AND 2 REACTOR VESSEL BELTLINE REGION MATERIAL PROPERTIES UNIT I Cu Ni I (Wt.%) (Wt.%) (*F)

Intermediate Shell Plate A-9811:(c)[4,5] 0.20 d.056 -2(a)

Lower Shell Plate C-1423:(c)[5,6] 0.12 0.065 -20(a)

Axial Weld - Intermediate Shell SA 775/812:(d) 0.19 0.63 0(b)

Weld Wire Heat Nos. IP0815/IP0661 Linde 80 Flux Lots 8350/8304 Axial Weld - Lower Shell SA-847: I') 0.25 0.55 0(b)

Weld Wire Heat No. 61782 Linde 80 Flux Lot 8350 Circumferential Weld - Intermediate: I') 0.20 0.55 0(b) to Lower Shell SA-1101 Weld Wire Heat No. 71249 Linde 80 Flux Lot 8350 UNIT 2 Intermediate Shell Forging 123V500:(c)[8,9] 0.09 0.70 40(a)

Lower Shell Forging 122W195:(c)[9,10] 0.05 0.72 40(a)

Circumferential Weld - Intermediate: I') 0.26 0.60 0(b) to Lower Shell SA-1484 Weld Wire Heat No. 72442 Linde 80 Flux Lot 8579 NOTES:

(a) The initial RT values for plates and forgings are estimated according to BranchTechnic$kTPosition MTEB 5-2.[7]

(b) The initial RTN PTS rule at 10 NR 50.61 (b)(2)(fi). values for welds are generic mean values (c) The chemistry values for the shell plates and forgings were derived from  !

vessel fabrication test certificates and surveillance capsule chemistry measurements. I (d) The chemistry data for SA-775 was utilized sincr this will result in l I

a conservative PTS calculation for this weld. See Appendix A.

(e) The chemistry values for these welds were derived from searches in the WOG data' base [2] and represent the rounded, average /alues.

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9 TABLE 4 RT PTS VALUES FOR REACTOR VESSEL BELTLINE MATERIALS

• POINT BEACH NUCLEAR PLANT .

UNIT 1 A-9811** C-1423** SA-775/812** SA-847** SA-1101***

Intermediate Lower Axial Weld Axial Weld Circumferential Weld RTPTS(oF) Values At Shell Plate Shell Plate Inter. Shell Lower Shell Inter. to Lower Shell Present (12/1/85) 140.8 81.0 173.5 206.0 191.0 Current License Expiration 164.8 94.4 203.1 244.1 224.5 License Expiration, if License 167.4 95.8 207.1 249.1 Amendment No. 107 Approved 228.1 Original design EFPY value for 40' 168.8 96.6 208.9 251.5 years of operation (32 EFPY) 230.1 UNIT 2 123V500** 122W195** SA-1484***

Intennediate Lower Circumferential Weld RTPTS(oF) Values At Shell Forging Shell Forging Inter. to Lower Shell Present (12/1/85) 146.3 116.0 238.0 Current License Expiration 161.9 123.5 285.8 Original design EFPY value for 40 163.9 124.5 292.0 years of operation (32 EFPY) '

License Expiration, if License 164.2 124.6 292.9 Amendment No. 107 approved

• Predicted RT values assume a cumulative (lifetime) capacity factor of 80%.

PTS

• • Applicable PTS screening criterion - 270"F.

• • • Applicable PTS screening criterion - 300 F.

Pano 14 of 71

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