ML25036A213

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BFN SLRA Supplement 3 Enclosure 18
ML25036A213
Person / Time
Issue date: 02/07/2025
From:
Office of Nuclear Reactor Regulation
To:
References
CNL-24-081 TRP-142.5-6 Q1, 2
Download: ML25036A213 (1)
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Proprietary Information - Withhold Under 10 CFR § 2.390 Proprietary Information - Withhold Under 10 CFR § 2.390 CNL-24-081 ENCLOSURE 18 TRP-142.5-6 Q1, 2 - BWR Circumferential and Axial Welds (Proprietary)

(10 pages)

Title of Supplement Enclosure Document:

TRP-142.S-6, BWR Circumferential and Axial Welds Description of SLRA change(s) attached:

TRP-142.5-6 Ql, Q2 - SLRA Proprietary Section 4 on pages 4-44, 4-45, 4-46, 4-47, 4-48, and 4-49 are being revised to:

1.) Include EOI RT max & ART values and provide some additional description regarding the basis, and 2.) Discuss ISP items as the limiting material.

Page 1 of 1

TRP-142.5-6 Q1, Q2 - SLRA Proprietary ^Ž 4 Pages 4-44, 4-45, 4-46, 4-47, 4- -49

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0)

Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 4-44 BWRVIP-05 (Reference 4.8.21) provides the technical basis for the elimination of ASME Code,Section XI examination of reactor vessel circumferential welds and the reduction of examination of reactor vessel axial welds for BWRs. The scope and evaluation for BWRVIP-05 was limited to 40 years of plant operation.

Subsequently, BWRVIP-329-A (Reference 4.8.22) and the associated NRC SER (Reference 4.8.23) provide additional technical basis for reduction in inspection of reactor vessel circumferential welds and an assessment of axial weld integrity for extended operations of up to 80 years. BWRVIP-329-A (Section 5, Implementation) provides criteria for applicability based on plant-specific data. The circumferential weld examination relief analyses meet the requirements of 10 CFR 54.3(a). As such, they have been identified as TLAAs requiring evaluation for the subsequent period of extended operation.

TLAA Evaluation:

80-year unit-specific fluence values have been projected for each circumferential weld as described in Section 4.2.1.1. Using the inside surface (0T) fluence values for these welds, the BFN end of interval (EOI) maximum reference temperature (RTMAX) values have been determined for the limiting circumferential welds within the beltline for each unit. Additional EOI RTMAX values were determined for the limiting reactor vessel plate material for each unit because it was determined that flaws can also develop within the weld fusion zone between the weld and base metal.

Table 4.2.5-1, Table 4.2.5-2, and Table 4.2.5-3 calculate the limiting maximum reference temperatures, RTMAX, for ID surface values (i.e., 0T), which were calculated using unit-specific neutron fluence, material chemistry (copper content, nickel content, and chemistry factor), and RTNDT(U) for the BFN reactor vessel plates and circumferential welds. The EOI for BFN are unit-specific based on 50 EFPY for Unit 1, 64 EFPY for Unit 2, and 62 EFPY for Unit 3. The

(( Limiting RTMAX(°F) value is (( }} for the limiting plate and limiting circumferential weld. The EOI RTMAX values for all BFN reactor vessel plates and circumferential welds meet the acceptability criteria for limiting plates and circumferential welds in BWRVIP-329-A. Request for relief from circumferential weld examination will be made in accordance with 10 CFR 50.55a for NRC review and approval. The plant-specific information described above demonstrates that, at the end of the subsequent period of extended operation, the BFN Units 1, 2, and 3 circumferential beltline weld materials meet the applicability criteria for limiting plates and circumferential welds in BWRVIP-329-A. Although similar to the deterministic value Adjusted Reference Temperature (ART), the RTMAX criterion (as defined by BWRVIP-329-A) is a probabilistic value and therefore does not include the margin term (that accounts for uncertainty in the data). As the margin is always zero or greater, the ART always conservatively bounds the RTMAX value (higher values are more conservative). RTMAX is the criterion for BWRVIP-329-A, but ART has been included for information in the current evaluation, as ART is a commonly utilized parameter in vessel integrity assessment. Integrated Surveillance Program (ISP) data have been included directly in the evaluation as applicable to the specific vessel per ISP guidance. TLAA Disposition:

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Table 4.2.5-1, BFN Unit 1 Circumferential Weld Probability Analyses Unit 1 Limiting Parameter Unit 1 Limiting Plate Circumferential Weld Component No. Lower Intermediate Shell #1 Lower to Lower-6-139-19 Intermediate Girth Weld WF1 54 Heat / Lot Identification Number C2884-2 406L44 (Utilizing ISP Data} Copper Content (wt. %) 0.12 ~ 0.29 Nickel Content (wt.%) 0.53 ~ .69 Chemistry Factor (CF) (°F) 81.6 ~ 279.5 50 EFPY EOI Neutron Fluence 1. 09 E++8-X 1 Olli (f) (n/cm2) 1.34 -=-43 X 1018 RT NDT(U) (°F) 14 ~ 23.1 <Note 1) EOI b.RT NOT (°F) 39.0 +9-:-9121.4 EOI RT MAX (°F) = RTNDT(U) + ~ ~53.0 ~~144.5 b.RTNDT ~ lL fllllll fllllll EOI RTMAX < Limiting RTMAX? Yes Yes Adiusted Reference Temoerature (ART) (°F) = RTNDTIU) + b.RTNDT 87.0 204.0 + Margin Notes:

1. The EOI RTMAA-Plate 1.ialue of 110.7 °f for BfN Unit 1 from the laP is higher than the limiting plate from the BfN Unit 1 reactor vessel and meets the limiting R~

acceptability criteria for limiting plate in B\IVRVIP 32Q A. ~weld 1*1alue of 204.0 °f for Bf~l Unit 1 from the laP higher than the limiting circumferential v.ield from the BfN Unit 1 reactor vessel and meets the limiting RTw acceptability criteria for limiting circumferential welds in B\IVRVIP 32Q A.

1. A conservative RTNDT(U) was utilized to bound the weld evaluations for BFN Unit 1.

Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 4-45

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Table 4.2.5-2, BFN Unit 2 Circumferential Weld Probability Analyses Parameter Unit 2 Limiting Plate Unit 2 Limiting Circumferential Weld Component No. Lower Intermediate Shell Lower to Lower-

  1. 2 6-127-16 Intermediate Girth Weld Heat / Lot Identification Number C2467-1 D55733 Copper Content (wt. %)

0.16 0.09 Nickel Content (wt.%) 0.52 0.65 Chemistry Factor (CF) (°F) 112.4 116.8 64 EFPY EOI Neutron Fluence (f) (n/cm2) 1.69 ~ x 1018 1.34 ~ x 1018 RT NDT(U) (OF) -10 -40 EOI b.RT NOT (°F) 59.6 55.8 EOI RT MAX (°F) = RTNDT(U) + ~ 9.6 ~+15.8 b.RTNDT 11_ Lllllll Lllllll Limiting RTMAX (°F} EOI RTMAX < Limiting RTMAX? Yes Yes Adiusted Reference Temoerature (ART) (°F) = RTNDTIU) + b.RTNDT 83.6 71.6 + Margin Notes:

1. The EOI RT~plate ¥alue of 200.2 °F for BF~J Unit 2 froRl the ISP is higher than the circuR1ferential weld froRl the BFN Unit 2 reactor vessel and R1eets the liRliting RTMAA acceptaeility criteria for liRliting oirouR1ferential welds in BWR1/IP d29 /\.

Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 4-46

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Table 4.2.5-3, BFN Unit 3 Circumferential Weld Probability Analyses Parameter Unit 3 Limiting Plate Unit 3 Limiting Circumferential Weld Component No. Lower Shell #1 6-145-4 Lower to Lower-Intermediate Girth Weld Heat / Lot Identification Number C3222-2 D55733 Copper Content (wt. %) 0.15 0.09 Nickel Content (wt.%) 0.52 0.66 Chemistry Factor (CF) (°F) 105.6 117.1 62 EFPY EOI Neutron Fluence (f) (n/cm2) 1.29 ~ x 1018 1.29 ~ x 1018 RT NDT(U) (OF) 10 -40 EOI l!.RT NOT (°F) 49.6 55.0 EOI RT MAX (°F) = RTNDT(U) + ~ +59.6 ~ 15.0 b.RTNDT 1}_ a u a u Limiting RTMAX (°F} EOI RTMAX < Limiting RTMAX? Yes Yes Adiusted Reference Temoerature (ART) (°F) = RTNDT(U) + b.RTNDT 93.6 70.0 + Margin Notes: 1 The EOI RTA4AX.Plate val, Ie of 95 0 °F for BFN I I nit 3 from the ISP is higher than the limiting plate from the BEN I lnit 3 reactor vessel and meets the limiting R~ acceptability criteria for limiting plate in BVVRVIP 329 /\..

2. ~weld value of 142.3 °F for BFN Unit 3 from the ISP is higher than the limiting circ, Imferential weld from the BFN I lnit 3 reactor vessel and meets the limiting

~acceptability criteria for limiting circumferential welds in BWRVIP 329 A. 4.2.6 Reactor Vessel Axial Weld Failure Probability Analyses TLAA

Description:

BWRVIP-05 (Reference 4.8.21 ) provides the technical basis for the elimination of the ASME Code, Section XI examination of reactor vessel circumferential welds and the reduction of examination of reactor vessel axial welds for BWRs. The scope and evaluation of BWRVIP-05 was limited to 40 years of plant operation. Subsequently, BWRVIP-329-A (Reference 4.8.22) and the associated NRC SE (Reference 4.8.23) provide additional technical basis for an assessment of axial weld integrity for extended operations of up to 80 years. BWRVIP-329-A (Reference 4.8.22, Section 5, Implementation) provides criteria for applicability based on plant-specific data. Since these Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) 4-47 Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 4-48 RTMAX values have been determined for the limiting axial welds within the beltline for each unit. Additional EOI RTMAX values were determined for the limiting reactor vessel plate material for each unit because it was determined that flaws can also develop within the weld fusion zone between the weld and base metal (Reference 4.8.22). Table 4.2.6-1, Table 4.2.6-2, and Table 4.2.6-3 calculate the limiting maximum reference temperatures, RTMAX, for ID surface values (i.e., 0T), which were calculated using unit-specific neutron fluence, material chemistry (copper content, nickel content, and chemistry factor), and RTNDT(U) for the BFN reactor vessel plates and axial welds. The EOI for BFN are unit-specific based on 50 EFPY for Unit 1, 64 EFPY for Unit 2, and 62 EFPY for Unit 3. The (( }} Limiting RTMAX(°F) value is (( 

}} for the limiting plate and (( 
}} for the limiting axial weld. The EOI RTMAX values for all BFN reactor vessel plates and axial welds meet the acceptability criteria for limiting plates and axial welds in BWRVIP-329-A (Reference 4.8.22).

Although similar to the deterministic value Adjusted Reference Temperature (ART), the RTMAX criterion (as defined by BWRVIP-329-A) is a probabilistic value and therefore does not include the margin term (that accounts for uncertainty in the data). As the margin is always zero or greater, the ART always conservatively bounds the RTMAX value (higher values are more conservative). RTMAX is the criterion for BWRVIP-329-A, but ART has been included for information in the current evaluation, as ART is a commonly utilized parameter in vessel integrity assessment. Integrated Surveillance Program (ISP) data have been included directly in the evaluation as applicable to the specific vessel per ISP guidance. TLAA Disposition: 10 CFR 54.21(c)(1)(ii) - The Units 1, 2, and 3 reactor vessel axial weld failure probability analyses have been projected through the subsequent period of extended operation.

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Table 4.2.6-1, BFN Unit 1 Axial Weld Probability Analyses Parameter Unit 1 Limiting Plate Unit 1 Limiting Axial Weld Component No. Lower Intermediate Shell #1 Axial Welds ESW 6-139-19 Heat / Lot Identification Number C2884-2 Copper Content (wt. % ) 0.12 0.24 Nickel Content (wt.%) 0.53 0.37 Chemistry Factor (CF) (°F) 81.6 140.6 50 EFPY EOI Neutron Fluence (f) (n/cm2) 1.34 -=-43 X 1018 1.11 -=-43 X 1018 RT NDT(U) (°F) 14 23.1 (Note 1) EOI b.RT NOT (°F) 39.0 61.6 EOI RT MAX (°F) = RTNDT{U) + ~ 3.0 44&:4~84. 7 b.RTNDT -L*** ,?1-1m1t1ng RT MAX. °F. fllllll fllllll EOI RTMAX < Limiting RTMAX? Yes Yes Adiusted Reference Temoerature (ART) (°F) = RTNDTIU) + b.RTNDT 87.0 146.4 + Margin Notes:

1. The EOI RTMAA-plate vah,Ie of 110.7 °f for BfN Unit 1 fren:i the ISP is higher than the lin:iiting plate fron:i the BfN Unit 1 reactor vessel and n:ieets the lin:iiting R~

acceptability criteria for lin:iiting plate in B\IVRVIP 32Q A.

2. ~weld 1,1alue of 204.0 °f for Bf~J Unit 1 fron:i the ISP is higher than the lin:iiting axial weld fron:i the BfN Unit 1 reactor 1*1essel and n:ieets the lin:iiting R~

acceptability criteria for lin:iiting axial welds in B\IVRVIP 32Q A.

1. A conservative RT NDT<ui was utilized to bound the weld evaluations for BFN Unit 1.

Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Table 4.2.6-2, BFN Unit 2 Axial Weld Probability Analyses Parameter Unit 2 Limiting Plate Unit 2 Limiting Axial Weld Component No. Lower Intermediate Shell #2 Axial Welds ESW 6-127-16 Heat / Lot Identification Number C2467-1 -BF2ESW (Utilizing ISP Data} Copper Content (wt. %) 0.16 ~ 0.20 Nickel Content (wt.%) 0.52 ~ 0.33 Chemistry Factor (CF) (°F) 112.4 ~ 285.8 64 EFPY EOI Neutron Fluence (f) (n/cm2) 1.69 -=43 x 1018 1.39 -:43 X 1018 RT NDT(U) (OF) -10 23.1 EOI b.RT NOT (°F) 59.6 ~ 138.9 EOI RT MAX (°F) = RTNDT{U) + ~ 9.6 4aJ.,4~162.0 b.RTNDT ll_ Limiting RTMAX (°F} fllllll fllllll EOI RTMAX < Limiting RTMAX? Yes Yes Adiusted Reference Temoerature (ART) (°F) = RTNDT(U) + b.RTNDT 83.6 200.2 + Margin Notes:

1. The EOI RT~plate i.1ahJe of 200.2 °F for BFN Unit 2 from the ISP is higher than the axial weld from the BF~J Unit 2 reactor 11essel and meets the limiting RTW-acceptability criteria for limiting axial welds in BVVR\IIP 329 /\..

Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 4-49

Section 4 - TLAAs Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390 Table 4.2.6-3, BFN Unit 3 Axial Weld Probability Analyses Parameter Component No. Heat/ Lot Identification Number Copper Content (wt. % ) Nickel Content (wt.%) Chemistry Factor (CF) (°F) 62 EFPY EOI Neutron Fluence (f) (n/cm2) RT NDT(U) ( OF) EOI LlRT NOT ( °F) EOI RT MAX (°F) = RTNOT(U) + 6.RTNT 4l!l!W/l EOI RTMAX < Limiting RTMAX? Adiusted Reference Temoerature (ART) (°F) = RTNT(U) + 6.RTNDT + Margin Notes: Unit 3 Limiting Plate Lower Shell #1 6-145-4 C3222-2 0.15 0.52 105.6 1.29 E+48-X 1018 10 49.6 459.6 -ll Yes 93.6 Unit 3 Limiting Axial Weld Axial Welds ESW 0.24 0.37 140.6 1.34 E+48-X 10 18 23.1 67.2 90.3 Illllll Yes 152.0

1. The EOI R1i>AAX,_plate 1.ialue of 95.0 °F for BFJ Unit 3 from the ISP is higher than the limiting plate from the BFN Unit 1 reactor vessel and meets the limiting RTw.

acceptability criteria for limiting plate in BWRVIP 329 A. Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) Proprietary Information, Withhold from Public Disclosure Under 10 CFR 2.390}}

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