ML20029C575
| ML20029C575 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Perry, Fermi, Oyster Creek, Hope Creek, Grand Gulf, Cooper, Pilgrim, Susquehanna, Columbia, Brunswick, Limerick, River Bend, Vermont Yankee, Duane Arnold, Clinton, Quad Cities, Big Rock Point, LaSalle, 05000471, 05000472 File:Consumers Energy icon.png |
| Issue date: | 03/24/1994 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-92-01, NUDOCS 9403250066 | |
| Download: ML20029C575 (82) | |
Text
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March 24, 1994 MEMORANDUM FOR:
All NRR Project Directors THRU:
Robert A. Capra, Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation FROM:
Daniel G. Mcdonald, Senior Project Manager Lead Project Manager - MPA B-120 Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
SUBJECT:
GENERIC LETTER-(GL) 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL ~ INTEGRITY" (MPA B-120)
The subject GL is part of the staff's program to evaluate reactor. vessel structural integrity.
The Materials and Chemical Engineering Branch (EMCB) has completed its review of the licensees's responses to the GL. provides three lists of Boiling Water Reactor (BWR) plants which are arranged according to the three different review groups:
(1) plants with no open issues, (2) plants with at least one belt line material having uncertain end-of-life -(EOL) upper-shelf energy (USE), and (3) plants with belt 3
line material initial RT 'tter to be sent to the BWR licensees is' provided as values determined by a method not approved by the NRC. Asampleclosecutle.
Please replace the blank paragraph identified as " INSERT" in the sample closeout letter with the paragraph under one of the three groups to which the plant belongs.
Each closeout letter will include (as enclosures) 1 two tables of data including a key to the nomenclature used. This data was compiled based on each licensee's response (s) to Generic letter (GL) 92-01 and other information that has been previously docketed. These tables, along with a key to the nomenclature used in the tables, are provided as Enclosure 3.
The closeout letter notes that the information in the tables will be used for future NRC assessments of the licensee's reactor pressure vessel (s) unless we are informed within 30 days from the date of the letter of any discrepancies.
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Contacts:
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D. Mcdonald, LPH 504-1408 d(
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All NRR Project Directors March 24, 1994 for 8 of the 12 plants in Group 1, the licensees are only requested to verify the accuracy of the information in the tables provided with the closeout letters.
For the four plants in Group 1 that use the topical report NEDO-32205 as their licensing bases, the licensees need to provide confirmation of plant-specific applicability of the topical report to their plants (as specified in Appendix B of NED0-32205, Revision 1) and submit a request for approval of the topical report as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G, Paragraph IV.A.I.
These reviews will be plant-specific licensing actions.
For the plant in Group 2, the Project Manager is to request the licensee to submit a schedule for performing the equivalent margins analysis to resolve the issue of uncertain E0L USE for welds.
This submittal will be reviewed as a plant-specific licensing action.
For all of the plants in Group 3, General Electric (GE) is in the process of validating its methodology for resolving the initial RT,EWR Owners Group is determination issue and will document the results in a topical report.
The obtaining approval from its members to provide the GE topical report to the NRC staff for its review and approval.
Project Managers are to request that the licensees provide in their responses to the closeout letter their commitment to this effort or their plant-specific approaches to resolve this issue.
In addition, the licensees for 22 of the remaining plants in Group 3 which refer to topical report, NE00-32205, as their licensing bases, need to provide confirmation of the plant-specific applicability of the topical report to their plant (as specified in Appendix B of NED0-32205, Revision 1) and submit a request for approval of the topical report as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G, Paragraph IV.A.I.
These reviews will be plant-specific actions.
All BWR Project Managers are requested to use the date of the closeout letter as the licensing action complete date.
Please enter the date and accession number in WISP.
I will provide guidance on the implementation complete date shortly after the 30-day responses are received and EMCB determines that they are acceptable.
As noted in the letters, there will be some plant-specific followup effort which is the result of (but not part of) the GL 92-01 effort.
I request that the Project Managers provide me the TAC numbers they open for these plant-specific licensing actions.
I will assist EMCB in tracking the closure of these actions.
EMCB will issue a NUREG detailing the GL 92-01 effort and the status of all issues, including plant-specific actions, relating to reactor vessel structural integrity.
4
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l-All NRR Project Directors thrch 24, l994 l
l EMCB expects to provide similar closecut letters and tables for Pressurized Water Reactors by April 15, 1994.
Please contact me if you have any questions.
h Daniel G. Mcdonald, Senior Proj ct Manager Lead Project Manager - MPA B-120 l
Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Plants 2.
Closecut Letter 3.
Nomenclature and Tables cc w/ enclosures 1 and 2:
ADPR/NRR S. Varga J. Roe D. Crutfchfield DRPE/DRPW Assistant Directors DRPE/DRPW Project Managers Technical Assistant, DRPE Technical Assistant, DRPW l
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ENCLOSURE 1 GENERIC LETTER (GL) 92-01 REVIEW STATUS GROUP 1:
PLANTS WITH NO OPEN ISSUES Plant TAC Number
- Browns Ferry 2 M83439
- Browns Ferry 3 M83440 Clinton M83450 Grand Gulf 1 M83466 Millstone 1 M83482 Nine Mile Pt. 1 M83486 Nine Mile Pt. 2 M83487 Perry M83497
- Peach Bottom 3 M83496 Pilgrim 1 M83498 River Bend 1 M83503
- Vermont Yankee M83521 Plants that use the topical report, NE00-32205, Revision 1, as their licensing bases.
INSERT 1 (FOR PLANTS WITHOUT THE SYMBOL "*")
We request that you verify the information you have provided for your facility (ies) has been accurately entered in the data base.
No response is necessary unless an inconsistency is identified.
If no comments are received within 30 days from the date of this letter, the staff will consider your actions related to GL 92-01, Revision 1, to be complete.
INSERT 1*
(FOR THE 4 PLANTS WITH THE SYMBOL "*")
We request that, within 30 days, you provide confirmation of the plant-specific applicability of the topical report, NED0-32205, Revision 1, (as specified in Appendix B of that report) and submit a request for approval of the topical report as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G, Paragraph IV.A.l.
This review will be a plant-specific licensing action. We further request that you verify that the information you have provided for your facility (ies) has been-accurately entered in the data base.
If no comments are made in your response to the last request, the staff will use the information in the tables for future NRC assessments of your reactor pressure vessel. Once your confirmation of the topical report applicability and request for approval are received, the staff will consider your actions related to GL 92-01, Revision 1, to be complete.
. GROUP 2:
PLANT WITH AT LEAST ONE BELT LINE MATERIA 1 HAVING UNCERTAIN E0L USE WELD:
Plant TAC Number Big Rock Point M83435 INSERT 2 (BIG ROCK POINT)
As a result of our GL 92-01 review, the staff has identified one open issue for your plant.
The end-of-life (E0L) USE of the circumferential weld cannot be determined because the heat number of the weld wire used for fabricating that weld can not be traced and the surveillance weld is only representative of the axial welds. We request that you submit within 30 days a schedule for performing an equivalent margins analysis to resolve the issue of uncertain EOL USE for the circumferential weld.
Further, we request that you verify that the information you have provided for your facility has been accurately entered in the data base.
If no comments are made in your response to the second request, the staff will use the information in the tables for future NRC assessments of your reactor pressure vessel. Once your response is received and your schedule is determined to be satisfactory, the staff will consider your actions related to GL 92-01, Revision 1, to be complete.
The submittal of the equivalent margins analysis for the circumferential weld will be reviewed as a plant-specific licensing action.
GROUP 3:
PLANTS WITH BELT LINE MATERIAL INITIAL RT, VALUES uo DETERMINED BY VNVALIDATED METHOD ElLql.
TAC Number
- Browns Ferry 1 M83438
- Brunswick 1 M83441
- Brunswick 2 M83442
- Cooper M83455
- Dresden 2 M83458
- Dresden 3 M83459
- Duane Arnold M83460 Fermi 2 M83463
- FitzPatrick M83464
- Hatch 1 M83469 Hatch 2 M83470 l
- Hope Creek M83471
- Lasalle 1 M83475
- Lasalle 2 M83476
- Limerick 1 M83477
- Limerick 2 M83478
- Monticello M83485
- 0yster Creek M83490
- Peach Bottom 2 M83495
- Quad Cities 1 M83501
- Quad Cities 2 M83502 j
- Susquehanna 1 M83518
- Susquehanna 2 M83519
- WNP 2 M83527 Plants that use the topical report, NED0-32205, Revision 1, as their licensing bases.
INSERT 3 (FOR PLANTS WITHOUT THE SYMBOL "*")
As a result of our GL 92-01 review, the NRC staff has identified one open issue for your plant (s).
The initial RT values determined by General uoy Electric's (GE) initial methodology have not been validated and the BWR Owners Group topical. eport, GE-NE-523-109-0893, entitled, " Basis for GE RT wor Estimation Method," did not resolve the issue.
GE is in the process of validating its methodology for resolving the initial RT,dWR Owners Group is determination issue and will document the results in a topical report.
The obtaining approval from its members to provide the GE topical report to the NRC staff for its review and approval.
We request that you submit within 30 days a commitment to the BWR Owners Group effort or a schedule for a plant-specific analysis to resolve.this issue.
Further, we request that you verify that the information you have provided for your facility (ies) has been accurately entered in the data base.
If no comments are made in your response to the second request, the staff will use the information in the tables for
l l future NRC assessments of your reactor pressure vessel.
Once your commitment to the BWR Owners Group offort is received or your schedule for providing a plant-specific analysis is considered satisfactory, the staff will consider your actions related to GL 92-01, Revision 1, to be complete.
Plant-specific licensing action (s) will be initiated to resolve the RT issue for your plant (s) either by referencing the topical report when [t' is reviewed and y
approved or for reviewing your plant-specific analysis.
l JNSERT 3*
l (FOR PLANTS WITli THE SYMBOL "*")
1 l
As a result of our GL 92-01 review, the NRC staff has identified one open issue for your plant.
The initial RT values determined by General Electric's (GE) initial methodology hav,e not been validated and the BWR Owners j
wo Group report, GE-NE-523-109-0893, entitled, " Basis for GE RT,o,lidating its Estimation Method," did not resolve the issue.
GE is in the process of va I
methodology for resolving the initial RT,o, The BWR Owners Group is obtaining determination issue and will document the results in a topical report.
approval from its members to provide the GE topical report to the NRC staff for its review and approval. We request that you submit within 30 days a commitment to the BWR Owners Group effort or a schedule for a plant-specific analysis to resolve this issue.
Further, we request that you provide confirmation of the plant-specific applicability of the topical report, NEDO-32205, Revision 1, (as specified in Appendix B of that report) and submit a request for approval of the topical report as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G, Paragraph IV.A.1 We further request that you verify that the information you have provided for your facility (les) has been accurately entered in the data base.
If no comments are made in your response to the last request, the staff will use the information in the tables for future NRC assessments of your reactor pressure vessel.
Once you have (1) confirmed the applicability of the topical report, i
NED0-32205, Revision 1, to your plant (s), (2) submitted the request for approval, and (3) provided your commitment to the BWR Owners Group effort or a satisfactory schedule for providing a plant-specific analysis, the staff will consider your actions related to GL 92-01, Revision 1, to be complete.
l Plant-specific licensing action (s) will be initiated to resolve these issues.
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. l'g ENCLOSURE 2 L
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l-SAMPLE LETTER FOR CLOSE0VT OF GL 92-01
[DATE]
l Docket No.(s)
[ LICENSEE ADDRESSEE]
Dear [NAME]:
SUBJECT:
GENERIC LETTER (GL) 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," [ UTILITY], [ UNITS] (TAC NO.(s)
)
By letter (s) dated [
], [ utility] provided its response to GL 92-01, Revision 1.
The NRC staff has completed its review of your response (s).
Based on 'ts review, the staff has determined that [ utility] has provided the information requested in GL 92-01.
The GL is part of the staff's program to evaluate reactor vessel integrity for Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). The information provided in response to GL 92-01, including previously docketed information, is being used to confirm that licensees satisfy the requirements and commitments necessary to ensure reactor vessel integrity for their facilities.
1 A substantial amount of information was provided in response to GL 92-01, Revision 1.
These data have been entered into a computerized data base designated Reactor Vessel Integrity Database (RVID). The RVID contains the following tables: A pressurized thermal shock (PTS) table for PWRs, a pressure-temperature limit table for BWRs and an upper-shelf energy (USE) table for PWRs and BWR's. provides the PTS and/or pressure temperature table (s), Enclosure 2 provides the USE table (s) for your facility (ies), and Enclosure 3 provides a key for the nomenclature used in the tables.
The tables include the data necessary to perform USE, pressure-temperature limit, and RT evaluations.
These data were taken from your response (s) to GL 92-01 a$ previously docketed information. The information in the RVID for your facility (ies) will be considered accurate at this point in time and will be used in the staff's assessments related to vessel structural integrity.
References to the specific source of the data are provided in the tables.
[ INSERT]
The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, " Reactor Vessel Structural
. Integrity, 10 CFR 50.54(f)." The estimated average number of burden hours is 200 person hours for each addressee's response. This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.
This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, Project Manager PD/ Branch Division Office of Nuclear Reactor Regulation
Enclosures:
1.
Pressurized Thermal Shock or Pressure-Temperature Limit Table (s) 2.
Upper-Shelf Energy Table (s) 3.
Nomenclature Key cc w/ enclosures:
See next page
f Nomenclature and Tables j
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PRESSURE-TEMPERATURE' LIMIT TABLES AND USE TABLES FOR ALL BWR PLANTS NOMENCLATURE Pressure-Temperature Limits Table Column 1:
Plant name and date of expiration of license.
Column 2:
Beltline material location identification.
Column 3:
Beltline material heat number; for some welds that a single-wire or tandem-wire process has been reported, (S) indicates single wire was used in the SAW process, (T) indicates tandem wire was used in the SAW process.
Column 4:
End-of-life (E0L) neutron fluence at vessel inner wall; citeil directly from inner diameter (ID) value or calculated by using Regulatory Guide (RG) 1.99, Revision 2 neutron fluence attenuation methodology from the quarter thickness (T/4) value reported in the latest submittal (GL 92-01, PTS, or r/T limits submittals).
Column 5:
Unirradiated reference temperature.
Column 6:
Method of determining unirradiated reference temperature (IRT).
Plant-Sneq11Js This indicates that the IRT was determined from tests on material removed from the same heat of the beltline material.
MTEB 5-2 This indicates that the unirradiated reference temperature was determined from following MIEB 5-2 guidelines for cases where the IRT was not determined using American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III, NB-2331, methodology.
Generic This indicates that the unirradiated reference temperature was determined from the mean value of tests on material of similar types.
Column 7:
Chemistry factor for irradiated reference temperature evaluation.
Column 8: Method of determining chemistry factor Iable This indicates that the chemistry factor was determined from the chemistry factor tables in RG 1.99, Revision 2.
Calculated This indicates that the chemistry factor was determined from i
surveillance data via procedures described in RG 1.99, Revision 2.
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Column 9:
Copper content; cited directly from licensee value except when more than one value was reported.
(Staff used the average value in the latter. case.)
No Data This indicates that no copper data has been reported and the default value in RG 1.99, Revision 2, will be used by the staff.
Column 10: Nickel content; cited directly from licensee value except when more than one value was reported.
(Staff used the average value in the latter case.)
No Data This indicates that no nickel data has been reported and the default value in RG 1.99, Revision 2, will be used by the staff.
Upper Shelf Energy Table Column 1:
Plant name and date of expiration of license.
Column 2: Beltline material location identification.
Column 3: Beltline material heat number; for some welds that a single-wire or tandem-wire process has been reported, (S) indicates single wire was used in the SAW process.
(T) indicates tandem wire was used in the SAW process.
Column 4: Material type; plate types include A 5338-1, A 302B, A 302B Mod., and forging A 508-2; weld types include SAW welds using Linde 80, 0091,124,1092, ARCOS-85 flux, Rotterdam welds using Graw Lo, SMIT 89, LW 320, and SAF 89 flux, and SMAW welds using no flux.
Column 5:
E0L upper-shelf energy (USE) at T/4; calculated by using the E0L fluence and either the cooper value or the surveillance data.
(Both methods are described in RG 1.99, Revision 2.)
f1M This indicates that the USE issue may be covered by the approved equivalent margins analysis in the BWR Owners Group Topical Report:
NE00-32205, Revision 1.
Column 6:
EOL neutron fluence at T/4 from vessel inner wall; cited directly from T/4 value or calculated by using RG 1.99, Revision 2 neutron fluence attenuation methodology from the ID value reorted in the latest submittal (GL 92-01, PTS, or P/T limits submittals).
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Column 7: Unirradiated USE.
DB This indicates that the USE issue may be covered by the approved equivalent margins analysis in the BWR Owners Group Topical Report: NED0-32205, Revision 1.
Column 8: Method of determining unirradiated USE Direct for plates, this indicates that the unirradiated USE was from a transverse specimen.
For welds, this indicates that the unirradiated USE was from test date, 61%
This indicates that the unirradiated USE was 65% of the USE from a longitudinal specimen.
i Generic This indicates that the unirradiated USE was reported by the licensee from other plants with similar materials to the l
5,1tline material.
NRC aeneric This indicates that the unirradiated USE was derived by the staff from other plants with similar materials to the beltline material.
- 10. 30. 40. or 50 *F This indicates that the unirradiated USE was derived from Charpy test conducted at 10, 30, 40, or 50 *F.
Sury. Weld This indicates that the unirradiated USE was from the surveillance weld having the same weld wire heat number.
Eauiv. to Surv. Weld This indicates that the unirradiated USE was from the surveillance weld having different weld wire heat number.
Sister Plant This indicates that the unirradiated USE was derived by using the reported value from other plants with the same weld wire heat number.
Blank indicates that there is insufficient data to determine the unirradiated USE. These licensees will utilize Topical Report NED0-32205, Revision 1 to demonstrate USE compliance to Appendix G, 10 CFR Part 50, 4
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Summary File for Pressure-Temperature Limits 1
Plan'.
Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T, CF Fitt-Lower C3394-1 2.51E18
-10*F Plant 73.6 Table 0.11 0.56 Patrick Shell Specific
.EOL: 10/
Lower C3376-2 2.51E18 24'F '
Plant 91 Table 0.13 0.60 17/2014 Shett Specific Lower C3103 2 2.51E18
-2*f '
Plant 100 Table 0.14 0.60 Shell Specific Lower Int.
C3368-1 2.51E18
-10'F '
Plant 81.8 Table 0.12 0.54 Shell Specific Lower Int.
C3301-1 2.51E18
-18'F '
Plant 134 Table 0.18 0.60 Shell Specific Lower Int.
C3278 2 2.51E18
-10'F '
Plant 91 Table 0.13 0.60 Shell Specific Lower Int.
13253/
2.51E18
-50*F Plant 223.9 Table 0.26 0.87 Axial 12008 Specific Welds 1-233A/C Lower 27204/
2.51E18 22*F Plant 241.3 Table 0.25 0.99 Shell 12008 Specific Axial Welds 2 233A/C Cire. Weld 305414 2.51E18 50*F Plant 203.75 Table 0.33 0.59 1 240 Specific Reference for FitrPatrick 1RT, fluence, and chemical composition data are from.tuly 9, 1992, letter from R. E. Beedle (PASNY) to USNRC Document Control Desk, subject: Response to Generic Letter 92-01, Revision 1
' Additional information required to confirm value.
5 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material USE at 1/4T Unirrad.
Method of Ident.
Type EOL./E FPY Neutron USE Determin.
Fluence at Unirred.
EOL/EFPY USE FitzPatric Lower C3394 1 A 5338 1 75 1.7E18 86 65%
k Shett EOL:
Lower C3376-2 A 5338-1 66 1.7E18 77 65%
10/17/2014 Shell Lower C3103-2 A 5338-1 70 1.7E18 83 65%
Shell Lower Int.
C3368 1 A 5338 1 58 1.7E18 67 65%
Shell Lower Int.
C3301 1 A 5338-1 68 1.7E18 83 65%
Shell Lower Int.
C3278-2 A 5338 1 76 1.7E18 85 65%
Shetl Lower Int.
13253/
Linde 76 1.7E18 104 Direct Axial 12008 1092, SAW Welds 1 233A/C Lower 27204/
Linde EMA*
1.7E18 EMA' Shell 12008 1092, SAW Axial Welds 2 233A/C Cire. Weld 305414 Linde EMA' 1.7E18 EMA' 1-240 1092, SAW Reference for FitzPatrick Fluence, chemical composition, and UUSE data are from July 9, 1992, letter from R. E. Beedle (PASNY) to USNRC Document Control Desk, subject: Response to Generic Letter 92-01, Revision 1 l
i 2Licensee must confirm applicability of Topical Report NE00-32205, Rev.1 i
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Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY
- IRT, CF Nine Mile Upper P2074 2.21E18 28'F Plant 134.6 Table 0.20 0.48 Point 1 Shell Specific G 307-3 EOL1 Upper P2076 2.21E18 40*F Plant 173.85 Table 0.27 0.53 8/22/2009 Shell Specific G-307-4 Upper P2091 2.21E18 20'F Plant 148.85 Table 0.22 0.51 Shell Specific G-307-10 Lower P2112 2.21E18 36*F Plant 153.95 Table 0.23 0.51 Shell Specific G 8-1 Lower P2130 2.21E18
-3*F Plant 130.2 Table 0.18 0.56 Shell Specific G83 Lower P2130 2.21E18
-3*F Plant 130.2 Table 0.18 0.56 Shell Specific G 8-4 Lower Int.
86054 2.21E18
-50*F Generic 112.0 Table 0.22 0.20 Shell Axial Welds 2-564A/C Lower 1248 2.21E18
-50*F Generic 112.0 Table 0.22 0.20 Int./ Lower Shell Cire. Weld 3-564 Lower 86054 2.21E18
-50*F Generic 112.0 Teble 0.22 0.20 Shell Axial Welds 2 564D/F i
Reference for Nine Mile Point 1 Fluence, chemical composition, and IRT data are from July 2, 1992, letter from C. D. Terry (NMPCo) to USNRC Document Control Desk, subject: Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity,10 CFR 50.54(f)
l 6
Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material USE at 1/4T Unirrad.
Method of j
Ident.
Type EOL/EFPY Neutron USE Determin.
Fluence at Unfrrad.
EOL/EFPY USE Nine Mile Upper P2074 A 302B 53 1.44E18 65 65%
Point 1 Shell Mod.
J-307 3 EOL:
Upper P2076 A 302B EMA' 1.44E18 52 65%
8/22/2009
$ hell Mod.
G-307 4 Upper P2091 A 302B 50 1.44E18 63 65%
Shell Mod.
G 307-10 Lower P2112 A 3028 EMA' 1.44E18 53 65%
Shell Mod.
G-8-1 Lower P2130 A 302B 53 1.44E18 64 Direct Shell Mod.
G-8 3 Lower P2130 A 302B 53 1.44E18 64 Direct Shell Mod.
G 8-4 Lower Int.
86054 ARLOS B-5, 57 1.44E18 75' NRC Shell SAL' Generic Axial Welds 2-564A/C Lower 1248 ARCOS B 5, 57 1.44E18 75' NRC Int./ Lower SAW Generic Shell Circ. Weld 3 564 Lower 86054 ARCOS B 5, 57 1.44E18 75*
NRC Shell SAW Generic Axial Welds 2 564D/F Reference for Nine Mile Point 1 UUSE, chemical composition, and fluence data are from July 2, 1992, letter from C. D. Terry (NMPCo) to USNRC Document Control Desk, subject: Generic Letter 92 01, Revision 1, Reactor vessel Structural Integrity, 10 CFR 50.54(f)
Note: Unirradiated USE for welds are lower two standard deviation value f rom the surveillance weld 2Plant specific equivalent margins analysis has been approved by NRC.
3Generic value for welds fabricated by Combustion Engineering using Linde 1092, 0091 and 123 and Arcos B-5 fluxes (Ref:
Letter from S. Bloom, NRR, to T.L. Patterson, OPPD, dated December 3, 1993)
7 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
10 Neut.
I R T,,,
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T, CF Nine Mile
- 2 Shell C3065-1 1.72E18
-10'F Plant 37 Table 0.06 0.63 Point 2 Ring Specific EOL. : 10/
- 2 Shett C3121-2 1.72E18 0*F Plant 58 Table 0.09 0.65 21/2026 Ring Specific
- 2 Shell C3147-1 1.72E18 0*F Plant 74.45 Table 0.11 0.63 Ring Specific
- 1 Shell C3147-2 1.72E18 0*F Plant 74.45 Table 0.11 0.63 Ring Specifie
- 1 Shell C3066-2 1.72E18
-20*F Plant 44 Table 0.07 0.64 Ring Specific
- 1 Shell C3065-2 1.72E18 10*F Plant 37 Table 0.06 0.63 Ring Specific
- 2 Shell SP5657 1.72E18
-60*F Plant 95 Table 0.07 0.71 Axial Specific Welds BD/8F
- 2 Shelt SP5657 1.72E18
-60'F Plant 54 Table 0.04 0.89 Axial Specific Welds 80/BF
- 1 Shell SP62148 1.72E18
-50*F Plant 27 Table 0.02 0.82 Axial Specific Welds BA/BC
- 1 Shell SP62148 1.72E18
-40'F Plant 20 Table 0.01 0.70 Axial Specific Welds BA/BC Circ. Weld 4P7465 (S) 1.72E18
-60*F Plant 27 Table 0.02 0.82 Specific Cire. Weld 4P7465 (T) 1.72E18
-60*F Plant 27 Table 0.02 0.80 Specific Cire. Weld 4P7216 (S) 1.72E18
-50*F Plant 82 Table 0.06 0.85 Specific I
Cire. Weld 4P7216 (T) 1.72E18
-80*F Plant 54 Table 0.04 0.83 Specific Reference for Nine Mile Point 2 Fluence, chemical composition, and IRT data are from July 2, 1992, letter from C. D. Terry (NMPCo) to USNRC Document Control Desk, subject: Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity, 10 CFR 50.54(f)
NOTE: Nine Mile Point 2 has a margin that is specially calculated: M a 2 sqrt[(CF f f/w)' + 1001 I
7 Summary file for Upper Shelf Energy Plant Name Battllne Neat No.
Material USE at 1/41 Unirred.
Method of Ident.
Type EOL/EFPY Neutron USE Determln.
Fluence at Unirred.
EOL/EfPY USE Nine Mlle
- 2 Shell C3065-1 A 5338 1 83 1.18t18 94 Direct Point 2 Ring EOLI
- 2 Shell C3121 2 A 5338 1 63 1.18E18 71 Direct 10/21/2026 Ring r
- 2 shell C3147-1 A 5338 1 67 1.18E18 70 Direct Ring
- 1 Shell C3147 2 A 5338 1 76 1.18E18 86 Direct Ring
- 1 shell C3066 2 A 5338 1 71 1.18E18 80 Direct Ring
- 1 shell C3065 2 A 5339 1 74 1.18E18 83 Direct Ring
- 2 shell 5P5657 Linde 124, 74 1.18E18 85 Direct Anial SAW Welds BD/8F
- 2 Shell 5P5657 Lirxle 124, 78 1.18E18 88 Direct Axial SAW Welds RD/BF
- 1 Shell
$P62148 Linde 124, 78 1.18E18 88 Direct Anlal SAW Welds BA/BC
- 1 shell 5P62140 Linde 124, 85 1.18E18 96 Direct Axlal SAW Welds 1
BA/BC Cire. Weld 4P7465 (s)
Linde 124, 90 1.18E18 102 Direct SAW i
Circ. Weld 4P7465 (T)
Linde 124, 97 1.18E18 110 Direct SAW Cire. Weld 4P7216 (5)
Linde 124, 78 1.18E18 89 Direct SAW 1
Circ. Weld 4P7216 (T)
Linde 124, 87 1.18E18 98 Direct
{
SAW i
l BIittence for NIne Mlle PgJnL2 UUSE, chemical conposition, and fluence data are from July 2,1992, letter f rom C. D. Terry (NMPCo) to USNRC Document Control Desk, subjects Generic Letter 92-01, Revision 1, Reactor vessel structural Integrity, 10 CFR 50.54(f)
I l
I i
v.
r
l l
10 Summary File for Pressure-Temperature Limits x
Plant Beltline Heat No.
10 Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Nants Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,,,,
CF I
Hope Int. Shell 5K3025-1 3.4E17 19'F Plant 112.75 Table 0.15 0.71 Creek Specific EOL:
Int. Shell 5K2608 1 3.4E17 Plant 58 1able 0.09 0.58 4/11/2026 Speelfic Int. Shell 5K2698-1 3.4E17 19'F Plant 65 Table 0.10 0.58 Speelfic Lower Int.
SK2963-1 2 1.59E18
-10*F Plant 44 Table 0.07 0.58 Shell Speelfic Lower Int.
$K2530 1 2 1.59E18 19'F Plant 51 Table 0.08 0.56 Shell Speelfic Lower Int.
5K3238 1 2 1.59E18 7'F Plant 58 Table 0.09 0.63 Shell Specific Lower SK3230-1 2 1.59E18
-10*F Plant 44 Table 0.07 0.56 Shell Specific Lower 6C35-1 2 1.59E18 11*F Plant 58 Table 0.09 0.54 Shell Specific Lower 6C45 1-2 1.59E18 l'F Plant 51 Table 0.08 0.57 Shell Specific Axlat D53040 1.59E18
-30*F Plant 106.3 Table 0.08 0.63 Welds for Specific Lower Shell Cire. Weld D53040 1.59E18
-30*F Plant 106.3 Table 0.08 0.63 between Specific Lower-Int.
& Lower Shells Cire. Weld 055733 3.4E17
-40*f Plant 126.4 Table 0.10 0.68 between Specific Int. ard Lower Int.
Shells Axial D53040 3.4E17
-49'F Plant 126.4 Table 0.10 0.68 Welds for Specific Int. Shell LPCI 001-01205 2.3E17
-40*F Plant 27 Table 0.02 0.51 Notzte specific welds 504-01205 2.3E17
-31'F Plant 20 Table 0.01 0.51 Spectfic 519-01205 2.3E17
-49'F Plant 20 Table 0.01 0.53 Specific Reference for Hone Creek Fluence, chemical conposition, and IRT data are from June 30, 1992, letter from S. Mittenberger (PSEG) to USNRC Docunent Control Desk, subject: Response to Generic Letter 92-01, Revision 1, Reactor vessel Structural Integrity, 10 CFR 50.54(f)
WOTE: LPCI nottles have eight SMAW welds that were made of wires of three heat nuibers.
' Additional information required to confirm value.
I 1
10 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirrad.
EOL/EFPY USE Hope Creek Int. Shett SK3025 1 A 5338-1 EMA*
2.4E17 EMA*
EOL:
Int. Shell 5K2608-1 A 5338 1 EMA' 2.4E17 EMA' 4/11/2026 Int. Shell 5K2698-1 A 5338-1 EMA*
2.4E17 EMA' Lower Int.
5K2963-1-2 A 533B 1 67 1.1E18 75 Ofrect Shell Lower Int.
SK2530-1-2 A 5338-1 67 1.1E18 75 Direct Shell Lower Int.
SK3238-1-2 A 5338-1 EMA' 1.1E18 EMA*
Shell Lower SK3230-1-2 A $338-1 EMA' 1.1E18 EMA' Shell Lower 6C35-1-2 A 5338-1 EMA' 1.1E18 EMA*
Shell Lower 6C45-1-2 A 5338-1 67 1.1E18 75 Direct Shell Axial 053040 Flux type 117 1.1E18 135 Surv.
Welds for
between
- unknown, Weld Lower-Int.
SAW
& Lower Shells Cire. Weld D55733 Flux type 61 2.4E17 68 10'F data between
- unknown, Int and SAW Lower-Int.
Shells Axial D53040 Flux type 122 2.4E17 135 Sury.
Welds for
- unknown, Weld Int. Shell SAW LPCI 504-01205 SMAW EMA' 1.6E17 EMA' Nozzle 001 01205 Welds 579-01205 Reference for Hope Creek Fluence, chemical conposition, and IRT data are from Jtr.e 30, 1992, letter f rom S. Mitterberger (PSEG) to USNRC Doctanent Control Desk, subject: Response to Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity, 10 CFR 50.54(f)
NOTE: LPCI nottles have eight SMAW welds that were fabricated using weld wires of three heat nunbers.
2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1 i
l e
l I
11 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
IRi Method of Chemistry Method of 1Cu
%NL m
Name Ident.
- Ident, Fluence at Determin.
Factor Determin.
EOL/EFPY 1 R T,,,
CF Limerick Shell C7668 1 1.73E18 10*F Plant 81.2 Table 0.12 0.51 1
Course #1, specific 14 1 EOL: 10/
Shell C7698-2
- 1. 73E18 10'F Planc 72.8 Table 0.11 0.48 26/2024 Course #1 srecific 14-2 Shell C7688 2 1.73E18 10'F Plant 81.2 Table 0.12 0.51 Course #1 specific 14 3 Shell C7689-1 1.73E18 10*F Plant 72.8 Table 0.11 0.48 Course #2 specific 17-1 shell C7677-1 1.73E18 20*F Plant 73 Table 0.11 0.50 Course #2 specific 17-2 shell C7698-1
- 1. 73E 18 10'F Plant 72.8 Table 0.11 0.48 Course #2 specific 17-3/
Axial 662A746 1.73E18
-20'F Plant 41 Table 0.03 0.88 Welds specific Axial 1P4218 1.73E18
-50'F Plant 82 Table 0.06 0.89 Welds specific Cire. Weld 07L857/
1.73E18
-6*F Plant 41 Table 0.03 0.97 B101A27A specific Cire. Weld 09M057/
- 1. 73E 18
-32*F Plant 41 Table 0.03 0.89 C109A27A specific Cire. Weld 640892/
1.73E18 60*F Plant 122 Table 0.09 1.00 J424R27AE specific Cire Weld SP6736
- 1. 73E18
-60'F Plant 108 Table 0.08 0.96 specific Reference for Limerick 1 Plate Cu, P, Ni; IRT, and fluence data are from Table 5.3-5 of FSAR enclosed in November 11, 1992 letter (supplenental response to GL 92-01, Rev.1) to NRC. Weld Cu and P, and IRT data are from the same table.
l l
t Additional information required to confirm value.
11 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirrad.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirred.
EOL/EFPY USE Limerick 1-Shell C7688 1 A 5338-1 EMA' 1.2E18 EMA' Course #1, 14-1 EOL:
Shell C7698 2 A 5338 1 EMA' 1.2E18 EMA' 10/26/2024 Course #1 14-2 Shell C7688 2 A 5338 1 EMA' 1.2E18 EMA' Course #1 14-3 Shell C7689 1 A 5338 1 EMA' 1.2E18 EMA' Course #2 17 1 Shell C7677-1 A 5338*1 EMA' 1.2E18 EMA' Course #2 17-2 Shell C7698 1 A 5338-1 EMA' 1.2E18 EMA*
Course #2 17-3/
Antal 662A746 Flux type E MA' 1.2E18 EMA' Welds
Flux and EMA' 1.2E18 EMA' 8101A27A weld type unknown Cire. Weld 09M057/
Flux and EMA*
1.2E18 EMA' C109A27A weld type unknown Cire Weld 640892/
Flux and EMA' 1.2E18 EMA*
J424827AE weld type unknown Circ. Weld SP6756 Flux and EMA*
1.2E18 EMA' weld type unknown Reference for Limerick 1 Plate Cu, P, Ni; UUSE; and fluence data are f rom table 5.3-5 of FSAR enclosed in Noventer 11, 1992 letter to NRC (Supplemental to GL 92 01 response). Weld Cu and P, and IRT data are from 1
the same table, I
i l
2Licensee must confirm applicability of Topical Report NED0-32205, Rev. 1
12 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut..
I R T.,
Method of Chemistry Method of
%Cu
%Ni j
Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY 1 R T,,,
CF Limerick Shell 83312 1 1.73E18 10'F Plant 90.4 Table 0.13 0.58 2
Course #1 specific 14-1 EOL: 10/
Shell B3416-1 1.73E18 40'F Plant 101.25 Table 0.14 0.65 26/2024 Course #1 specific q
14 2 Shell C9621 2 1.73E18 22'F Plant 110 Table 0.15 0.60 Course #1 specific i
14-3 1
l Shell C9569 2 1.73E18 10*F Plant 73.1 Table 0.11 0.51 course #2 specific 17-1 l
Shell C9526 1 1.73E18 10'F Plant 73.6 Table 0.11 0.56 Course #2 specific 17-2 Shell C9526-2 1.73E18 10*F Plant 73.6 Table 0.11 0.56 Course #2 specific 17-3 Axial 432A2671/
1.73E18
-12'F
- Plant 54 Table 0.04 1.08 Welds H019A27A specific Anial 661A746/
1.73E18
-20'F Plant 41 Table 0.03 0.88-Welds H013A27A specific Cire. Weld 07L857/
1.73E18
-6'F Plant 41 Table 0.03 0.97 B101A27A specific Cire. Weld 09M057/
1.73E18
-32*F '
Plant 41 Table 0.03 0.89 C109A27A specifie j
Cire. Weld 03M014/
1.73E18
-34* F '
Plant 20 Table 0.01 0.94 C118A27A specific Cire. Wold 640892/
1.73E18
-60*F '
Plant 122 Table 0.09 1.00 J424827AE specific Reference for Limerick 2 Cu, Ni, and P; fluence, and IRT data are f rom Table 5.3 5 of the FSAR enclosed in Novenber 11, 1992 letter (Supplemental response to GL 92-01, Rev. 1) to NRC.
' Additional information required to confirm value.
m
==
12 Summary File for Upper Shelf Energy Plant Name Belt lIne Heat No.
Material 1/4T USE 1/4T Unfrred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unitrad.
EOL/EFPY USE L'merick i Shett 83312 1 A 5338 1 EMA' 1.2E18 EMA' Course #1 14-1 EOL:
Shell B3416-1 A 5338-1 EMA' 1.2E18 EMA' 10/26/2024 Course #1 14-2 Shell C9621-2 A 5338-1 EMA' 1.2E18 E MA' Course #1 14-3 Shell C9569-2 A 5338-1 EMA' 1.2E18 EMA' Course #2 17-1 Shell C9526-1 A 5338 1 EMA' 1.2E18 EMA' Course #2 17 2 Shell C9526-2 A 533B 1 EMA' 1.2E18 EMA' Course #2 17 3 Axial 432A2671/
SMAW EMA' 1.2E18 EMA' Welds H019A27A Axist 661A746/
SMAW EMA' 1.2E18 EMA' Welds H013A27A Cire. Weld 07L857/
SMAW EMA' 1.2E18 EMA' B101A27A Cire. Weld-09M057/
C109A27A Cire. Weld 03M014/
SMAW EMA' 1.2E18 EMA' C118A27A u re. Weld 640892/
SMAW EMA*
1.2E18 EMA' J424827AE Reference for limerick 2 Cu, NI, and P; fluence, and UUSE data are from Table 5.3 5 of the FSAR enclosed in Novenber 11, 1992 letter to NRC (Stpplemental to CL 92-01 response).
2Licensee must confirm applicability of Topical Report NED0-32205, Rev. I e
L..
13 1
Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
IRT.
Method of Chemistry Method of
%Cu
%NI l
Warn Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT,
CF m
Peach lower C2791-2 8.0E17
-8'F Plant 81.4 Table 0.12 0.52 Bottom 2 Shett specific EOL:
Lower C2761-1 8.0E17
-14*F Plant 73.4 Table 0.11 0.54 1/31/2008 Shell specific Lower C2873-2 8.0E17
-20'F Plant 82.4 Table 0.12 0.57 Shell specific Lower Int.
C2894 2 8.0E17
-20*F Plant 85.6 Table 0.13 0.42 shell specific Lower Int.
C2873-1 8.0E17
-6'F Plant 82.4 Table 0.12 0.57 Shelt specific Lower Int.
C2761-2 8.0E17
-20*F Plant 73.4 Table 0.11 0.54 Shell specific Axial 37C065 8.0E17
-45'F generic 109.25 Table 0.21 0.21 Welds Cire. Weld S-3986 8.0E17
-32'F Plant 82 Table 0.06 0.97 specific Reference for Peach Bottom 2 Fluence, chemical composition, and IRT data are from July 10, 1992, letter from G. J. Beck (PEco) to USNRC Document Control Desk, subject: Response to Generic Letter 92 01, Revision 1, " Reactor vessel Structural integrity, 10 CFR 50.54(f)"
Additional information required to confirm value.
13 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirrad.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirred.
EOL/EFPY USE Peach Lower C2791-2 A 302B EMA*
5.5E17 EMA' Bottom 2 shell Mod.
EOL:
Lower C2761-1 A 3028 EMA' 5.5E17 EMA' 1/31/2008 Shell Mod.
Lower C2873-2 A 302R EMA' 5.5E17 EMA' Shell Mod.
Lower Int.
C2894-2 A 302B E MA' 5.5E17 EMA' Shell Mod.
Lower Int.
C2873 1 A 3028 EMA*
5.5E17 EMA' Shell Mod.
Lower Int.
C2761-2 A 3028 74 5.5E17 82 65%
Shell Mod.
Axial 37C065 Flux type EMA' 5.5E17 EMA' Welds
- unknown, SAW Cire. Weld S 3986 Linde 124, E MA' 5.5E17 EMA' SAW Reference for Peach B &to jm Fluence, chemical composition, and UUSE data aro from July 10, 1992, letter from G. J. Beck (PECo) to USNRC Document Control Desk, subject: Response to Generic Letter 92-01, Revision 1,
" Reactor Vessel structural Integrity,10 CFR 50.54(f)"
PR EDB has no UUSE or IUSE for both the surveillance plate and weld 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
4 8
14 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT.,
CF Peach Lower C4689-2 7.2E17
-10*F Plant 82.2 Table 0.12 0.56 Bottom 3 Shell specific 6 146-1 EOL:
Lower C4684 2 7.2E17
-20'F Plant 90.4 Table 0.13 0.58 1/31/2008 Shell specific 6-146 3 Lower C4627-1 7.2E17
-20'F Plant 82.4 Table 0.12 0.57 Shell speelfic 6-146-7 Lower Int.
C2773-2 7.2E17 10*F Plant 103.95 Table 0.15 0.49 Shell specific 6-139-10 Lower Int.
C2775-1 7.2E17 10'F Plant 86.8 Table 0.13 0.46 Shell specific 6-139 11 Lower Int.
C3103-1 7.2E17 10*F Plant 100 Table 0.14 0.60 Shell specific 6 139 12 Int. Shell C4608 1 7.2E17 10*F Plant 82 Table 0.12 0.55 6-146 5 specific Int. Shell C4689-1 7.2E17 10*F Plant 82.2 Table 0.12 0.56 6 146 4 spectfic Int. Shell C4654-1 7.2E17 10*F Plant 73.5 Table 0.11 0.55 6-146 2 specific Lower to 3P4000 7.2E17
-50*F Plant 27 Table 0.02 0.96 Lower Int.
specific Shell Cire. Weld (DE)
Int. to 1P4217 7.2E17 50*F Plant 147.2 Table 0.11 0.96 Lower Int.
specific Shell Cire. Weld (EF)
Axial 37C065 7.2E17
-45'F generic 109.25 Table 0.21 0.21 Welds D1/3, E1/3, F1/3 i
Reference for Peach Bottom 3 Fluence, chemical composition, and IRT data are from July 10, 1992, letter f rom G. J. Beck (PEco) to USNRC Document Control Desk, subject: Response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity, 10 CFR 50.54(f)"
l 1
\\
l 14 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirred.
EOL/EFPY USE Peach Lower C4689 2 A 3028 EMA' 5.0E17 EMA' Bottom 3 Shell Mod.
61461 EOL:
Lower C4684 2 A 3028 EMA' 5.0E17 EMA' 1/31/2008 Shell Mod.
6 146-3 Lower C4627 1 A 3028 EMA' 5.0E17
[MA' Shell Mod.
6 146-7 Lower Int.
C2773-2 A 3028 EMA' 5.0E17 EMA' Shell Mod.
6-139 10 Lower Int.
C2775-1 A 3028 EMA' 5.0E17 EMA' Shell Mod.
6-139-11 Lower Int.
C3103-1 A 3028 79 5.0E17 89 65%
Shell Mod.
6 139 12 Int. Shell C4608-1 A 3028 E MA' 5.0E17 EMA' 6-146 5 Mod.
Int. Shell C4689-1 A 3028 EMA' 5.0E17 EMA' 61464 Mod.
Int. Shell C4654 1 A 3028 EMA' 5.0E17 EMA' 6 146-2 Mod.
Lower to 3P4000 Linde 124, 88 5.0E17 97 10'F data Lower Int.
Int to IP4217 Linde 124, 62 5.0E17 71 10'F data lower Int.
SAW Shell l
Cire. Weld
)
(EF)
Axist 37C065 Flux 82 5.0E17 99 Direct i
- unknown, D1/3, SAW E1/3, F1/3 l
Reference for Peach Bottojm l
Fluence, chemical composition, and UUSE data are from July 10, 1992, letter from C. J. Beck (PECo) to USNRC Doctsnent Control Desk, subjects Resronse to Generic Letter 92 01, Revision 1,
" Reactor Vessel Structural Integrity, 10 CFR 50.54(f)"
2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
.~
e 15 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%NI Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EfPY I R f,,,,
CF Susque-Lower Int.
7.7E17
-10*F Plant 58 Table 0.09 0.53 hanna 1
- Shell, C0803-1 specific 22-1 EOL:
Lower Int.
C0776 1 7.7E17 6*F Plant 80.6 Table 0.12 0.48 7/17/2022
- Shell, specific 1
22 2 Lower Int.
C2433 1 7.7E17 18'F Plant 65.3 Table 0.10 0.63
- Shell, specific 22-3 i
Lower 85083-1 7.7E17
-8'F Plant 94.6 Table 0.14 0.48 1
Shell specific 21 1 Lower C0770-2 7.7E17
-20'F Plant 95.5 Table 0.14 0.50 Shell specific 21-2 Lower C0814-2 7.7E17
-20*F Plant 88.3 Table 0.13 0.51 Shell specific 21-3 Weld 629616/
- 7. 7E17
-50*F Plant 54 Table 0.04 0.99 L320A27AG specific Weld 411L3071/
7.7E17
-50'F Plant 41 Table 0.03 0.93 L311A27AF specific Weld 494K2351/
7.7E17
-50*F Plant 54 Table 0.04 1.10 L307A27AD specific Weld 40150371/
7.7E17
-80'F Plant 41 Table 0.03 1.04 8504B27AE specific Weld 402K9171/
7.7E17
-50*F Plant 41 Table 0.03 0.96 K315A27AE specific Weld 402C4371/
7.7E17
-50'F Plant 27 Table 0.02 0.92 C115A27A specific Weld 412P3611/
7.7E17 80'F Plant 41 Table 0.03 0.93 J417B27AF specific Reference for Susouchanna 1 Fluence, chemical composition, and 1RT data are from July 10, 1992, letter from H. W. Keiser (PP&L) to C. L. Miller (USNRC), subject: Response to Generic Letter 92 01 NOTE: There are no weld direction (axial or circumferential) data. All welds are shielded metal arc welds (SMAW).
' Additional information required to confirm value.
15 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirrad.
Method of Ident.
Type at Neutron USE Determin.
[0L/EFPY Fluence at Unirred.
EOL/EFPY USE Susquehann Lower Int.
A 5338-1 E MA' 5.3E17 EMA' a1
- Shell, C0803 1 22 1 EOL:
Lower Int.
C0776-1 A 5338-1 EMA*
5.3E17
[MA' 7/17/2022
- Shell, 22-2 Lower Int.
C2433-1 A 5338-1 EMA' 5.3E17 EMA'
- Shell, 22-3 Lower B5083 1 A 5338-1 EMA' 5.3E17 EMA*
Shell 21-1 Lower C0770-2 A 533B 1 EMA' 5.3E17 EMA' Shell 21 2 Lower C0814 2 A 5338-1 EMA' 5.3E17 EMA*
Shell 21 3 Weld 629616/
SMAW EMA' 5.3E17 EMA' L320A27AG Weld 411L3071/
SMAW EMA' 5.3E17 EMA' L311A27AF Weld 494K2351/
SMAW EMA' 5.3E17 EMA' L307A27AD Weld 40150371/
SMAW EMA' 5.3E17 EMA' 8504B27AE Weld 402K9171/
SHAW EMA' 5.3E17 EMA' K315A27AE Weld 402C4371/
C115A27A Weld 412P3611/
SMAW EMA' 5.3E17 EMA' J417827AF Reference for Susauchenna 1 Fluence, chemical composition, and UUSE data are from July 10, 1992, letter from H. W. Keiser (PP&L) to C. L. Miller (USNRC), subject: Response to Generic Letter 92-01 NOTE: There are no weld direction (axial or circumferential) data. All welds are shielded natal are welds (SMAW).
2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
16 Summary File for Pressure-Temperature Limits Plant.
Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,
CF susque-Lower Int.
C2421-3 7.7E17 10'F Plant 93 Table 0.13 0.68 hanna 2
- Shell, specific 22 1 EOL:
Lower Int.
C2929-1 7.7E17 20*F Plant 92 Table 0.13 0.64 3/23/2024
- Shell, specific 22-2 Lower Int.
C2433-2 7.7E17 2*F Plant 65.3 Table 0.10 0.63 Shell.
specific 22-3 Lower 6C956-1 1 7.7E17
-20*F Plant 73.5 Table 0.11 0.55 Shell specific 21 1 Lower 6C980 1-1 7.7E17
-20*F Plant 65 Table 0.10 0.56 Shell specific 21-2 Lower 6C1053-1-1 7.7E17 10*F Plant 65 Table 0.10 0.58 Shell specific 21-3 Weld 629616/
7.7E17
-50'F Plant 54 Table 0.04 0.99 L320A2?AG specific Weld 624263/
7.7E17 20*F Plant 82 Table 0.06 0.89 E204A27A specific Weld 09M057/
7.7E17
-36*F Plant 41 Table 0.03 0.89 C109A27A specific f
Weld 494K2351/
7.7E 17 66*F Plant 51 Table 0.04 1.10 L307A27AC specific Weld 411L3071/
7.7E17
-50'F Plant 41 Table 0.03 0.93 L311 A27AF specific Weld 402K9171/
7.7E17
-50*F Plant 41 Table 0.03 0.96 K315A27AE specific Weld 40150317/
7.7E17
-80*F Plant 41 Table 0.03 1.04 B504B27AE specific Weld 412P3611/
7.7E17 80'F Plant 41 Table 0.03 0.93 J417B27AF specific Weld 402C4371/
7.7E17
-50'F Plant 27 Table 0.02 0.92 C115A27A spectfIc Weld 659N315/
7.7E17 70*F Plant 54 Table 0.04 1.00 F414B27AF specific Reference for Sue,auehanna 2 Fluence, chemical composition, and IRT data are from July 10, 1992, letter from H. W. Keiser (PP&L) to C. L. Miller-(USNRC), subject: Response to Generic Letter 92-01 i
' Additional information required to confirm value.
16 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T unirred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unitrad.
EOL/EFPY USE Susquehann Lower Int.
C2421 3 A 5338 1 E MA' 5.3E17 EMA' I
a2
- Shell, 22-1 EOL:
Lower Int.
C2929 1 A 5338-1 EMA*
5.3E17 EMA*
3/23/2024
- Shell, 22-2 j
Lower Int.
C2433 2 A 5338 1 EMA' 5.3E17 EMA'
- Shell, 1
I 22-3 Lower 6C956 1-1 A 5338-1 EMA*
5.3E17 EMA' Shell 21-1 Lower 6C980-1-1 A 5338-1 E MA' 5.3E17 EMA' Shell 21-2 Lower 6C1053-1 1 A 5338-1 EMA' 5.3E17 EMA' Shell 21-3 Weld 629616/
SMAW EMA' 5.3E17 EMA' L320A27AG Weld 624263/
SMAW EMA*
5.3E17 EMA' E204A27A Weld 09M057/
SMAW EMA' 5.3E17 EMA' C109A27A Weld 494K2351/
SMAW EMA' 5.3E17 EMA' L307A27AD Weld 411L3071/
SMAW EMA' 5.3E17 EMA' L311A27AF Weld 402K9171/
SMAW EMA' 5.3E17 EMA' K315A27AE Weld 401$0317/
[MA' 5.3E17 EMA' B504827AE Weld 412P3611/
SMAW EMA' 5.3E17 EMA' J417827AF Weld 402C4371/
SMAW EMA' 5.3E17 EMA' C115A27A Weld 659N315/
SMAW EMA' 5.3E17 EMA' F414827AF Reference for Susaaehanna 2 Fluence, chemical composition, and UUSE data are from July 10, 1992, letter from H. W. Keiser (PP&L) to C. L. Miller (USNRC), subjects Response to Generic Letter 92 01 2Licensee must confirm applicability of Topical Report NE00-32205, Rev.1
__-~
21 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY 1Ri CF m
Pilgrim Lower C-2957-1 1.39E18 10*F Plant 65 Table 0.10 0.48 Shell specific G3109-1 EOL:
Lower C-2957-2 1.39E18 10'F Plant 65 Table 0.10 0.47 6/8/2012 Shell specific G3109 2 Lower C 2973-1 1.39E18 10'F Plant 74.45 Table 0.11 0.63 Shell specific G3109-3 Lower Int.
C 2921-2 1.39E18
-10*F Plant 100 Table 0.14 0.60 Shell specific G3108 1 Lower Int.
C-2945-1 1.39E18
-10*F Plant 65.5 Table 0.10 0.65 Shell spectfic G3108 2 i
Lower Int.
C-2945-2 1.39E18
-10*F Plant 65.6 Table 0.10 0.66 Shell specific G3108 3 Lower Int.
27204 &
1.31E18 0*F Plant 1 73.2 Table 0.13 1.06 Axial 12008 specific Welds 1-338A/C Lower Int.
13253 1.31E18 0*F Plant 95 Table 0.07 0.72 to Upper specific Shell Cire. Weld 3-3398 Lower Int.
21935 1.31E18 0*F Plant 151.65 Table 0.13 0.71 to Lower specific Shell Cire. Weld 1-344 Lower 27204 &
1.31E18 0'F Plant 173.2 Table 0.13 1.06 Shell 12008 specific Axial Welds 2-338A/C Reference for Pilgrim IRT data are from August 30, 1993 to NRC (Response to GL 92-01 RAI).
Plate Cu data are from Appendix 1 to TR-60528 1 added on to the report at a later date.
Except for plate Cu data, Ni, Cu, P data are from " Pilgrim Nuclear Power Station Reactor Pressure Vessel Pressure Tenperature Limits," Technical Report TR 605281, Rev.1, June 26,1986 S data are from July 1,1992, letter from R. A. Anderson (BE) to USNRC Docunent Control Desk, subject: Response to Generic Letter 92 01 (There are no S data for the welds)
Fluence data are from April 16, 1991, letter from J. C. Tsacoyeanes (BE) to USNRC Document Control Desk, subject:
Pilgrim RPV Pressure Tenperature Limits
. ~..
21 Summary File for Upper Shelf Energy Plant Name Bettline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirred.
EOL/EFPY USE Pilgrim Lower C 2957 1 A 5338-1 67 9.9E17 76 65%
Shell G3109-1 EOL:
Lower C 2957 2 A 5338-1 70 9.9E17 79 65%
6/8/2012 Shett G3109 2 Lower C 2973-1 A 5338 1 64 9.9E17 72 65%
$hetL C3109 3 Lower Int.
C 2921 2 A 5338-1 70 9.9E17 81 65%
Shell G3108 1 Lower Int.
C-2945 1 A 5338-1 72 9.9E17 80 65%
shell G3108 2 Lower Int.
C 2945+2 A 5338-1 72 9.9E17 81 65%
Shell G3108-3 Lower Int.
27204 &
Linde 63 9.3E17 75' NRC Axial 12008 1092, SAW Generic Welds 1-338A/C Lower Int.
13253 Linde 99 9.3E17 113 Surv.
to Upper 1092, SAW Weld Shell Cire. Weld 3 3398 Lower Int.
21935 Linde 63 9.3E17 75' NRC to Lower 1092, SAV Generic Shell Cire. Weld 1-344 Lower 27204 &
Linde 63 9.3E17 75*
NRC Shell 12008 1092, SAW Generic Axist Welds 2+338A/C i
3Generic value for welds fabricated by Combustion Engineering using Linde 1092, 0091 and 124 and Arcos B-5 fluxes (Ref:
Letter from S. Bloom, NRR, to T.L. Patterson, OPPD, dated December 3, 1993)
i 22 Summary File'for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Untrred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirrad.
EOL/EFPY USE Reference for Pilorim The UUSE data for the surv. weld is from August 30, 1993 letter to NRC (Response to CL 92 01 RAI).
UUSE, Ni, Cu, P data are from " Pilgrim Nuclear Power Station Reactor Pressure Vessel Pressure Tenperature Limits," Techaical Report 79-60528-1, Rev. 1, June 26, 1986 Fluence data are from April 16, 1991, letter from J. C. Tsacoyeanes (BE) to USNRC Document Control Desk, subject: Pilgrim RPV Pressure Tenperature limits i
1 i
i
J-0 22 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
! R T.
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Df.termin.
EOL/EFPY I R T.,
CF vermont Location C3017-2 2.3E17 40'F Plant 74.45 Table 0.11 0.63 Yankee unknown specific 1-14 EOL:
Location C3116 2 2.3E17 30'F Plant 101.5 Table 0.14 0.66 3/21/2012 unknown specific 1-15 Location C2653 3 2.3E17 30'F Plant 90.7 Table 0.13 0.59 unknown specific 1-16 Location C2640-1 2.3E17 30*F Plant 83.15 Table 0.12 0.61 unknown specific 1-17 Welds SMAW 2.3E17
-70*F Generic 41 Table 0.03 0.95 Ref erence for Vermont Yankee Fluence datum is from July 3,1992, letter from J. P. Pelletier (VYNPC) to USNRC Doctsnent Control Desk, subject:
I Vermont Yankee Response to Generic Letter 92-01 Regarding Reactor Vessel Structural Integrity Chemical composition and IRT data are from licensee's response to RAI (GL 92-01) dated Septenber 24, 1993 l
23 Summary File for Upper Shelf Energy Plant Name Belt lIne Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at h
- con USE Determin.
EOL/EFPY fluence at Unirred.
EOL/EFPY USE Vermont Location C3017 2 A 533B-1 73 1.7E17 89 65%
Yankee unknown 1-14 EOL:
Location C3116-2 A 533B 1 65 1.7E17 71 40*F data 3/21/2012 unknown 1-15 Location C2653-3 A 5338-1 51 1.7E17 56 40*F data unknown 1-16 Location C2640-1 A 533B-1 EMA' 1.7E17 EMA' unknown 1-17 Welds Unknown E8018-G, 99 1.7E17 107 Surv.
SMAW Weld Reference for Vermont Yankee Plate heat nunbers and UUSE data are from Septecber 24, 1993 letter to NRC (Response to GL 92-01 RAl); the weld UUSE of 107 ft-lb (Atta. 3) is considered by the staff to be better than 125 ft-lb (Atta. 4).
Fluence datum is from July 3,1992, letter from J. P. Pelletier (VYNPC) to USNRC Docunent Control Desk, subject: Vermont Yankee Response to Generic Letter 92-01 Regarding Reactor Vessel Structural integrity 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1 i
t 29 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I RT.
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY 1 R T.,
CF Millstone Lower C1359-1 1.29E18 6'F Plant 146.15 Table 0.22 0.49 1
Shell specific G2001-1 EOL:
Lower B4928-1 1.29E18 10'F Plant 155.4 Table 0.23 0.52 10/6/2010 Shell specific G2001-3 Lower C1140-2 1.29E18 22*F Plant 143.8 Table 0.23 0.44 Shett specific G2001-5 Lower-int.
B5013-2 1.29E18
-4'F Plant 140.7 Table 0.21 0.49 Shell specific G2002 4 Lower-int.
C1079-1 1.29E18 26*F Plant 236.43 Calculated 0.19 0.51 Shell specific G2002 5 Lower-int.
C1140-1 1.29E18 20*F Plant 135.5 Table 0.21 0.45 shell specific G2002 6 Axial W5214 1.29E18
-20*F Plant 252 Table 0.21 1.20 Welds specific 1-073A/C Axial W5214 1.29E18
>0'F Plant 252 Table 0.21 1.20 Welds specific 2 073A/C Lower to 348009 1.29E18
-50*F Plant 200.78 Calculated 0.21 1.03 Lower-int, specific Cire. Weld Reference for Mittstone 1 Fluence, chemical composition, and IRT, data are f rom July 6,1992, letter f rom J. F. Opeka (NNECo) to USNRC 00ctsfent Control Desk, subject: Haddam Neck Plant; Millstone Power Station, Units 1, 2, and 3: Reactor vessel Structural Integrity, 10CFR50.54(f), (Generic Letter 92-01, Revision 1) i
30 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,,
CF Oyster Lower T1937-2 3.62E18 30'F Plant 79.45 Table 0.17 0.11 Creek Shell specific G-307-1 EOL: 12/
Lower T1937-1 3.62E18 21*F Plant 79.45 Table 0.17 0.11 15/2004 Shell specific G 308-1 Lower P2076-2 3.62E18 3'F Plant 173.85 Table 0.27 0.53 thell specific G-307-5 Lower int.
P2150-1 3.62E18 31*F Plant 138.2 Table 0.20 0.51 Shell specific G-8 6 Lower-int.
P2161-1 3.62E18 17'F Plant 139.4 Table 0.21 0.48 Shell specific G-8-7 Lower-int.
P2136-2 3.62E18 8'F Plant 120.7 Table 0.18 0.46 Shell specific G88 Lower 86054B 3.62E18
-50'F Plant 168 Table 0.35 0.20 Shell specific Axial Velds 2-564A/C Lower-int.
860548 3.62E18
-8'F plant 168 Table 0.35 0.20 Shell specific Axial Welds 2 564D/F Lower to 1248 3.62E18
-50*F Plant 112 Table 0.22 0.20 Lower-int.
specific Shell Cire. Weld 3-564 References for Oyster Creek The Ni value for weld 1248 is from September 7, 1993 letter to NRC (Response to GL 92-01 RAI).
Cu, and fluence data are from June 16, 1992, letter from A. W. Dromerick (USNRC) to Distribution (USNRC), subject:
Summary of Meeting regarding Reactor Vessel Upper Shelf Energy Analysis for the Oyster Creek Nuclear Generating Plant Ni, P, S; and IRT data are from January 11, 1991, letter from J. J. Barton (GPUN) to USNRC Document Control Desk, subject: Dyster Creek Nuclear Generating Station, Technical Specification Change Request No.194. Margin values for plates must be increased to account for a calculated by the licensee.
' Additional information required to confirm value.
31 Summary File for Upper Shelf Energy i
l Plant Name Beltline Heat No.
Materlet 1/4T USE 1/4T Unfrrad.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unfrred.
EOL/EFPY USE Millstone Lower C1359-1 A 3028 55 9.0E17 67 65%
1 Shell G2001-1 EOLt Lower B4928 1 A 302B 55 9.0E17 67 65%
10/6/2010 Shell G2001-3 Lower C1140-2 A 3028 61 9.0E17 75 65%
Shell G2001-5 Lower-int.
85013-2 A 302B 60 9.0E17 72 65%
shell G2002-4 Lower int.
C1079-1 A 3028 51 9.0E17 65 65%
Shell G2002-5 Lower-int.
C1140-1 A 3028 57 9.0E17 68 65%
I shell C2002-6 Axial W5214 Linde 90 9.0E17 112 Sister Welds 1092, SAW plant 1-073A/C Axial W5214 Linde 90 9.0E17 112 Sister Welds 1092, SAW plant 2-073A/C Lower to 34B009 Linde 73 9.0E17 98 Surv.
Lower-int.
1092, SAW Weld Cire. Veld 3 073 Reference for Millstone 1 The UUSE data for plate G2002-5 was determined by the staf f based on data reported in October 15, 1993 letter to NRC (Response to CL 92-01 RAI).
Fluence, chemical conposition, and UUSE data are from July 6,1992, letter from J. F. Opeka (NNEco) to USNRC Document Control Desk sLbjects Haddam Neck Pier;t; Millstone Power Station, Units 1, 2, and 3: Reactor vessel structural Integrity, 10CFR5f.54(f), (Generic Letter 92-01, Revision 1)
I
1 t
32 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unfrrad.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unfrrad.
EOL/EFPY USE Oyster Lower T1937 2 A 3028 1 53 2.36E18-64 65%
Creek Shell G 307-1 EOL: 12/
Lower T1937-1 A 3028-1 EMA' 2.36E18 60 65%
15/2004 Shett G-308 1 Lower P2076 2 A 3028 1 EMA' 2.36E18 62 65%
Shell G 307-5 Lower int.
P2150-1 A 3028 1 EMA' 2.36E18 53 65%
I shell G-8 6 Lower-int.
P2161-1 A 3028-1 EMA*
2.36E18 51 65%
shell G-8-7 Lower-int.
P2136-2 A 3028 1 53 2.36E18 65 65%
Shell i
G 8-8 Lower 86054B Arcos B 5, EMA' 2.36E18 EMA*
j Shell SAW Axial Welds 2-564A/c Lower-int.
86054B Arcos B 5, EMA' 2.36E18 EMA' Shell SAW Axial Welds 2 5640/F Lower to
.1248 Arcos B-5, EMA' 2.36E18 EMA*
Lower-int.
SAW Shell Cire. Weld 3 564 References for Oyster Creek UUSE, Cu, and fluence data are from June 16, 1992, letter from A. W. dromerick (USNRC) to Distribution (USNRC), subject: Sumary of Meeting regarding Reactor Vessel Upper Shelf Energy Analysis for the Oyster Creek Nuclear Generating Plant 2Licensee must confirm applicability of Topical Report NED0-32205, Rev. I 1
36 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Namo Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT,
CF Brunswick Lower C4500-2 1.95E18 10'F Plant 106.7 Table 0.15 0.54 1
Shell Speelfic EOL:
Lower C4550-2 1.95E18 10*F Plant 74 Table 0.11 0.60 9/8/2016 Shell Specific Lower Int.
C4489 1 1.95E18 10*F Plant 83 Table 0.12 0.60 Shell Specific Lower Int.
C4500-2 1.95E18 10'F Plant 82.4 Table 0.12 0.57 Shell Specific Nozzle Q201VW 1.60E17 40'F Plant 123 Table 0.16 0.82 N16A Specific Nozzle Q201VW 1.60E17 40*F Plant 123 Table 0.16 0.82 N16B Spectfic Axial
$3986 1.95E18 10*F Plant 68 Table 0.05 0.96 Welds Specific Cire. Weld 3P4000 1.95E18 10'F Plant 27 Table 0.02 0.90 Specific REFERENCES FOR BRUNSWICK 1:
Fluence and chernical composition data for N16A and N168 are from July 7,1993 letter to NRC (Response to GL 92 01 RAI).
Fluence is from February 15, 1990, letter f rom N.B. Le (USNRC) to L.W. Ewy (CP&L), Subject; Issuance of Arr endnent 140 to OPR 71 and Amendment 172 to DPR-62.
Chemical conposition and IRT data are from NEDC-24161, " Brunswick Steam Electric Station, Unit 1, Informatf or; m Reactor vessel Surveillance Program.
' Additional information required to confirm value.
38 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Untrred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirred.
EOL/EFPY USE Brunswick Lower C4500-2 A 5338 1 EMA*
1.42E18 EMA' 1
Shell EOL:
Lower C4550 2 A 5338 1 EMA' 1.42E18 EMA' 9/8/2016 Shell Lower Int.
C4489-1 A 5338 1 EMA' 1.42E18 EMA' Shell Lower Int.
C4500 2 A 5338 1 EMA*
1.42E18 EMA' Shell Nozzle Q201W A 508-2 EMA*
1.16E17 EMA*
N16A Nozzle Q2Q1W A 508-2 EMA*
1.16E17 EMA' N160 Axial 53986 Linde 124, EMA' 1.42E18 EMA' Welds SAW Cire. Weld 3P4000 Linde 124, EMA*
1.42E18 EMA' SAW REFERENCES FOR BRUNSWICK 13 Fluence and chemical conposition data for N16A and N168 are from July 7,1993 letter to NRC (Response to CL 92 01 RAI).
Fluence for all other materials is from February 15, 1990, letter from N. B. Le (USNRC) to L.
W. Eury (CP&L), subjects lasuance of Amendnent 140 to DPR-71 and Amendnent 172 to DPR-62.
Chemical conposition data for all other materials are from NEDC-24161, " Brunswick Steam Electric Station, Unit 1, Information on Reactor Vessel Surveillance Program.
2Licensee must confirm applicability of Topical Report NEDO-32205, Rev. I
37 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
IRT.
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,
CF Brunswick Lower C4535 2 1.95E18 10'F Plant 82.6 Table 0.12 0.58 2
Shell Specific EOL:
Lower C4550-1 1.95E18 10*F Plant 74 Table 0.11 0.60 12/27/
Shell Specific 2014 Lower Int.
C4487 1 1.95E18 10*F Plant 82.2 Table 0.12 0.56 Shell Specific Lower Int.
88496-1 1.95E18 10*F Plant 139.8 Table 0.19 0.58 Shell Specific Nozzle Q2Q1W 1.60E17 40'F Plant 123 Table 0.16 0.82 N16A Specific Nozzle Q201W 1.60E17 40'F Plant 123 Table 0.16 0.82 N168 Specific Axial S39S6 1.95F18 10*F Plant 68 Table 0.05 0.96 Welds Specific Cire. Weld 1P4218 1.95E18 10'F Plant 82 Table 0.06 0.87 Specific REFERENCES FOR BRUNSWICK 2:
Fluence and chemical composition data for N16A and N168 are from July 7, 1993 letter to NRC (Response to GL 92 01 RAI).
Fluence is from February 15, 1990, letter f rom N.B. Le (USNRC) to L.W. Ewy (CP&L), subject: lasuance of Ameninent 140 to DPR 71 and Amendnent 173 to DPR-62.
Chemical composition and IRT data are from NEDC-24157, " Brunswick Steam Electric Station, Unit 2, Information on Reactor Vessel Surveillance Program.
' Additional information required to confirm value.
i 0
0 39 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at Neutron USE Determin.
EOL/EFPY Fluence at Unirred.
EOL/EFPY USE Brunswick Lower C4535-2 A 5338-1 EMA' 1.42E18 EMA' 2
Shell EOL:
Lower C4550 1 A 5338 1 E MA' 1.42E18 EMA' 12/27/
Shell 2014 Lower Int.
C4487 1 A 5338 1 EMA' 1.42E18 EMA' Shell Lower Int.
B8496-1 A 533B-1 EMA' 1.42E18 EMA' Shell Nozzle Q2Q1W A 508-2 EMA' 1.16E17 EMA' N16A No22Le Q201W A 508-2 EMA' 1.16E17 EMA' N168 Axial S3986 Linde 124, EMA' 1.42E18 EMA' Welds SAW Cire. Weld 1P4218 Linde 124, EMA' 1.42E18 EMA' SAW REFERENCES FOR BRUNSWICK 2:
Fluence and chemical conposition data for W16A and N168 are from July 7,1993 letter to NRC (Response to GL 92 01 RAI).
Fluence for all other materials is from February 15, 1990, letter from N. B. Le (USNRC) to L.
W. Eury (CP&L), subjects issuance of Amendment 140 to DPR-71 and Amendnent 172 to DPR 62.
Chemical conposition data for all other material are from NEDC 24157, " Brunswick Steam Electric Station, Unit 2, Information on Reactor Vessel Surveillance Program.
2Licensee must confirm applicability of Topical Report NED0-32205, Rev,1
1 56 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Nants Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL I R T,,,
CF Hatch 1 Lower Int.
C4337 1 1.8E18 10'F Plant 127.5 Table 0.17 0.62 shell specific j
G 4803-7 EOL:
Lower Int.
C3985 2 1.8E18 10'F Plant 90.4 Table 0.13 0.58 8/6/2014 shell specific G 4804-1 Lower Int.
C4114 2 1.8E18 10'F Plant 93.5 Table 0.13 0.70 shell specific G-4804-2 Lower C4112-1 1.8E18 10'F Plant 92 Table 0.13 0.64 shell specific G 4805 1 Lower C4112-2 1.8E18 10*F Plant 92 Table 0.13 0.64 shell specific G-4805-2 Lower C4149 3 1.8E18 10*F Plant 98.65 Table 0.14 0.57 Shell specific G-4805-3 Lower Int.
IP2815 1.8E18
-10*F Plant 209.6 Table 0.27 0.76 Axist specific Welds 1 308G/J Lower Int.
IP2809 1.8E18
-10'F Plant 211.8 Table 0.28 0.76 Axial specific Welds 1 3080/J Lower 13253 1.8E18 10*F Plant 206.4 Table 0.27 0.74 shell specific Axial Welds 1 307A/C Lower 90099 1.8E18
-10'F olent 207 Table 0.17 1.00 Int./
specific.
Lower shell Cire. Weld 1-313 Lower 33A277 1.8E18
-10*F Plant 236 Table 0.23 1.00 Int./
specific Lower shell Cire. Weld 1-313 References for Hatch 1 Fluence, IRT, and chemical composition data are from July 2,1992, letter from J. T. Beckham, Jr. to USNRC Doctanent Control Desk, subject: Response to NRC Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity Weld flux data are from November 22, 1988, letter f rom W. G. Hairston (GPCo) to USNRC Doctaient Control Desk, subject:
Response to Generic Letter 88-11 Additional information required to confirm value.
59-Summary File for Upper Shelf Energy Plant Name Bettllne Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirred.
EOL USE Hatch 1 Lower Int.
C4337 1 A 5338 1 EMA' 1.3E18 EMA' Shell G 4803-7 EOL:
Lower Int.
C3985 2 A 5338-1 EMA*
1.3E18 EMA' 8/6/2014 Shell G 4804-1 Lower Int.
C4114-2 A 5338-1 86 1.3E18 90 65%
shell G-4804 2 Lower C4112-1 A 533B-1 EMA' 1.3E18 EMA' Shell G 4805-1 Lower C4112-2 A 5338-1 EMA' 1.3E18 EMA' Shell G-4805 2 Lower C4149-3 A 5338-1 E MA' 1.3E18 EMA' Shell G-4805 3 Lower Int.
Axial 1092, SAW Welds 1-308G/J Lower Int.
IP2809 Linde EMA' 1.3E18 EMA' Axfal 1092, SAW Welds 1 308G/J Lower 13253 Linde EMA' 1.3E18 EMA' Shell 1092, SAW Axial Welds 1 307A/c Lower 90099 Linde EMA' 1.3E18 EMA' Int./
0091, SAW Lower Shell Cire. Weld 1-313 Lower 33A277 Linde EMA' 1.3E18 EMA' Int./
0091, SAW Lower Shell Cire. Weld 1 313 l
l 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
1 60 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of
)
Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfered.
EOL USE References for Hatch 1 Fluence and chemical conposition data are from July 2,1992, letter from J. T. Beckham, Jr. to USNRC Document Control Desk, subject: Response to NRC Generic Letter 92-01, Revision 1, Reactor vessel Structural Integrity Plate UUSE datum is from the surveillance capsule report (NEDC-30997) l l
I
57 Summary File for Pressure-Temperature Limits Plant Bettline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Nl Name ident.
Ident.
Fluence at
- Determin, Factor Determin.
EOL IRT.
CF Hatch 2 Lower C8553 2 1.0E18 20'F Plant 51 Table 0.08 0.58 Shell specific G6603 1 EOL:
Lower C8553 1 1.0E18 24*F Plant 51 Table 0.08 0.58 6/13/2018 Shell specific C6603 2 Lower C8571-1 1.0E18 0*F Plant 51 Table 0.08 0.53 Shell specific G6603-3 Lower Int.
C8554-2 1.0E18
-10*F Plant 51 Table 0.08 0.58 Shell specific G6602-1 Lower Int.
C8554 1 1.0E18
-20'F Plant 51 Table 0.08 0.57 Shell specific C6602-2 Lower Int.
C8579-2 1.0E18
-4*F Plant 72.8 Table 0.11 0.48 Shell specific G6601-4 Lower 10137 1.0E18
-50'F Plant 154.5 Table 0.23 0.50 Shell specific Axist Welds 101 842 Lower Int.
51874 1.0E18 50'F Plant 138 Table 0.18 0.50 Shell specific Axial Welds 101-834 Lower /
4P6052 1.0E18
-50'F Plant 35.45 Table 0.07 0.03 Lower Int, specific shelt I
Cire. Weld l
301 871 Reference for Hatch 2 I
Fluence, IRT, and chemical composition data are from July 2,1992, letter from J. T. Beckham, Jr. to USNRC Document
)
Control Desk, subject: Response to NRC Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity i
' Additional information required to confirm value.
61 Sumary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Untrred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrred.
EOL USE Hatch 2 Lower C8553 2 A 5338 1 86 6.8E17 95 65%
shell G6603 1 EOL:
Lower C8553 1 A 5338-1 77 6.8E17 85 65%
6/13/2018 Shell C6603 2 Lower C8571-1 A 5338 1 64 6.8E17 71 65%
Shell c6603-3 Lower Int.
C8554-2 A 5338 1 84 7.2E17 93 65%
shell C6602 1 Lower Int.
C8554-1 A 5338 1 81 7.2E17 90 65%
Shell G6602-2 Lower Int.
C8579-2 A 5338-1 63 7.2E17 70 65%
Shell G6601-4 Lower 10137 Linde 87 6.8E17 108 10*F data Shell 0091, SAW Axial Welds 101 842 Lower Int.
51874 Linde 74 7.2E17 89 10*F data shell 0091, SAW Axlal Welds 101-834 Lower /
4P6052 Linde 112 7.2E17 126 10'F data Lower Int.
0091, SAW shell Cire. Weld 301 871 Et.ference for Hatch 2 Fluence, UUSE, and chemical conposition data are from July 2,1992, letter f rom J. T. Beckham, Jr. to USNRC Docunent Control Desk, subject: Response to NRC ceneric Letter 92 01, Revision 1, Reactor Vessel Structural Integrity Weld UUSEs are at 10'F; therefore, they are actually CVN values.
62 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL IRi CF m
Browns Lower A1009-1 1.24E18
-10*F Plant 95.5 Table 0.14 0.50 Ferry 1 Shell specific EOL: 12/
Lower B5864-1 1.24E18 20*F Plant 101.2 Table 0.15 0.44 20/2013 Shell specific Lower A0999-1 1.24E18
-20*F Plant 100 Table 0.14 0.60 Shell specific Int. Shell C2868 2 1 24E18 0*F Plant 58 Table 0.09 0.52 specific Int. Shell C2884 2 1.24E18 0*F Plant 81.4 Table 0.12 0.52 speciffe Int. Shell C2753 1 1.24E18
-20*F Plant 51 Table 0.08 0.50 specific Cire. Weld 406L44 1.24E18 20*F Plant 196.7 Table 0.31 0.59 WF-154 specific Axial Not 1.24E18 10*F Plant 142.5 Table 0.25 0.35 Welds available specific ES Reference for Browns Ferry i Fluence, IRT, and chemical conposition data are f rom July 7,1992, letter f rom R. H. Shell (TVA) to USNRC Document Control Desk, subject: Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)~ Response to NRC Generic Letter 92 01 (Reactor Vessel Structural Integrity)
J i
i
' Additional information required to confirm value.
4 0
66 Summary File for Upper Shelf Energy Plant Name Beltline Heat No, Material 1/4T USE 1/4T Unirrad.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirred.
EOL USE Browns Lower A1009-1 A 3028 EMA' 8.6E17 EMA' Ferry 1 Shell EOL 12/
Lower B5864 1 A 3028 EMA*
8.6E17 EMA' 20/2013 Shell Lower A0999-1 A 302B EMA' 8.6E17 EMA' Shell Int. Shell C2868-2 A 3028 84 8.6E17 94 65%
Int. Shell C2884-2 A 3028 68 8.6E17 77 65%
Int. Shell C2753-1 A 3028 EMA' 8.6E17 EMA' Cire. Weld 406L44 Linde 80, EMA*
8.6E17 EMA' WF-154 SAW Axial Not Linde 124, E MA' 8.6E17 EMA' Welds available ESW ES Reference for Browns Ferry 1 Fluence, weld UUSE, and chemical composition data are from July 7, 1992, letter from R. H.
Shell (TVA) to USNRC Document Control Desk, subject; Browns Ferry Nuclear Plant (BFN),
Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)--Response to NRC Generic Letter 92-01 (Reactor Vessel Structural Integrity) l i
2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1 m
63 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Nt:ne Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL I R T,.,
CF Browns Lower C2467-2 1.06E18 20*F Plant 112.4 Table 0.16 0.52 Ferry 2 Shell specific EOL:
Lower C2463-1 1.06E18
-20'F Plant 116.8 Table 0.17 0.48 6/28/2014 Shell specific Lower C2460-1 1.06E18
-20*F Plant 88.3 Table 0.13 0.51 Shell specific Int. Shell A0981 1 1.06E18 10*F Plant 9 7. 75 Table 0.14 0.55 specific Int. Shell C2467-1 1.06E18
-10*F Plant 112.4 Table 0.16 0.52 specific Int. Shell C2849 1 1.06E18 10*F Plant 73 Table 0.11 0.50-speelfic Cire. Weld D55733 1.06E18
-40'F Plant 116.75 Table 0.09 0.65 specific Axial Not 1.06E18 10'F Plant 142.5 Table 0.25 0.35 Welds available specific ES Reference for Browns Ferry 2 Fluence, IRT, and chemical composition data are f rom July 7,1992, letter f rom R. H. Shell (TVA) to USNRC Docunent Control Desk, subjects Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)-Response to NRC Generic Letter 92 01 (Reactor Vessel Structural Integrity) l I
9 67 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirred.
EOL USE Browns Lower C2467 2 A 302B EMA' 7.3E17 EMA' Ferry 2 Shell EOL:
Lower C2463 1 A 302B EMA' 7.3E17 EMA' 6/28/2014 Shell Lower C2460-1 A 302B EMA' 7.3E17 EMA' Shell Int. Shell A0981 1 A 302B 81 7.3E17 92 65%
Int. Shell C2467-1 A 3028 E MA' 7.3E17 EMA' int. Shell C2849-1 A 3028 EMA' 7.3E17 EMA' Cire. Weld 055733 YF-200, 127 7.3E17 145 Direct SAW Axial Not Linde 124, EMA' 7.3E17 EMA' Welds available ESW ES Reference for Browns Ferry 2 Fluence, UUSE, and chemical composition data are from July 7, 1992, letter from R. H. Shell (TVA) to USNRC Docunent Control Desk, subject: Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SON), and Watts Bar Nuclear Plant (WBN)-* Response to NRC Generic Letter 92 01 i
(Reactor Vessel Structural Integrity) i
)
2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1 w
64 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Nam Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL I R T, CF Browns Lower C3213-1 1.04E18
-30*F Plant 90.4 Table 0.13 0.58 Ferry 3 Shell speelfte EOL:
Lower C3222 2 1.04E18
-20'F Plant 105.6 Table 0.15 0.52 7/2/2016 Shell specific Lower C3217-2 1.04E18
-50*F Plant 101.5 Table 0.14 0.66 Shell specific Int. Shell C3188-2 1.04E18
-30*F Plant 65 Table 0.10 0.51 specific Int. Shell C3201-2 1.04E18
-30'F Plant 91 Table 0.13 0.60 specifle Int. Shell B7267-1 1.04E18
-20*F Plant 88.3 Table 0.13 0.51 specific Cire. Weld D55733/
1.04E18 40'F Plant 117.1 Table 0.09 0.66 051852 specific Axial Not 1.04E18 10'F Plant 142.5 Table 0.25 0.35 Welds available specific ES Reference for Browns Ferry 3 Fluence, IRT, and chemical conposition data are from July 7,1992, letter from R. H. Shell (TVA) to USNRC Document Control Desk, subject: Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (W8N) -Response to NRC Generic Letter 92-01 (Reactor vessel Structural Integrity)
68 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirrad.
Method of ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrred.
EOL USE Browns Lower C3213 1 A 3028 EMA' 7.2E17 EMA*
Ferry 3 Shell EOL:
Lower C3222-2 A 3028 EMA' 7.2E17 EMA' 7/2/2016 Shelt Lower C3217-2 A 3028 EMA' 7.2E17 EMA' Shell int. Shell C3188 2 A 3028 92 7.2E17 103 65%
Int. Shell C3201-2 A 3028 EMA' 7.2E17 EMA' Int. Shell 87267-1 A 3028 EMA*
7.2E17 EMA' Cire. Weld D55733/
YF-200, 171 7.2E17 195 Direct D51852 SAW Axial Not Linde 124, EMA' 7.2E17 EMA' Welds available ESW ES Reference for Browns Ferry 3 Fluence, UUSE, and chemical composition data are from July 7, 1992, letter from R. H. Shell (TVA) to USNRC Document Control Desk, subject: Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SON), and Watts Bar Nuclear Plant (WBN)--Response to NRC Generic Letter 92-01 (Reactor Vessel Structural Integrity) i 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
70 Sumary File for Pressure-Temperature Limits Plent Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY 1 R T,,
CF Big Rock No 19246 1 5.011E19 30'F Plant 80.712 Calculated 0.10 0.18 Point location specific identifi-cation S-5503-1 EOL:
No 19246-2 5.011E19 30'F Plant 80.712 Calculated 0.10 0.18 5/31/2000 location specific identifi-cation s-5503-2 No 19246-3 5.011E19 30'F Plant 80.712 Calculated 0.10 0.18 location specific identifi-cation s-5503-3 No 19246-4 5.011E19 30*F Plant 80.712 Calculated 0.10 0.18 location specific identiff-cation s-5503 4 Axial No data 5.011E19
-56'F Generic 140.68 Calculated 0.27 0.10 Welds Cire. Weld No data 5.011E19
-56'F Generic No data No data References for Bio Rock Point The fluence and UUSE data are from April 27, 1993 letter to NRC (Response to GL 92-01 RAI).
Chemical composition data are from June 12, 1978 letter from W. S. Skibitsky (CPCo) to D. L. Ziemann (USNRC), subject:
Big Rock Point Plant-Reactor Surveillance Program 1RT and chemical composition data are from January 10, 1990, letter from K. W. Berry (CPCo) to USNRC Docunent Control Desk, subject: Big Rock Point Plant Technical Specification Change Request
- Reactor Tenperature Limits Plate identification is from page 3 of July 29, 1977, letter from D. A. Bixel (USNRC) to Director of Nuclear Regulation (USNRC), subject: Big Rock Point and Palisades Plants, Response to Letter Dated May 20, 1977--Reactor Vessel Surveillance
74 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unfrrad.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirred.
EOL USE Big Rock No location 19246 1 A 302B 57 6.088E19 82 Direct Point identiff-cation S 5503 1 EOL:
No location 19246 2 A 3028 57 6.088E19 32 Direct 5/31/2000 identift-cation S 5503 2 No location 19246-3 A 3028 57 6.088E19 82 Direct identifi-cation S-5503 3 No location 19246 4 A 3028 57 6.088E19 82 Direct identifi-cation S 5503-4 Axial No data ARCOS B5 47 6.088E19 95 Surv.
Welds SAW Weld Cire Welds No data ARCOS B5 6.088E19 No data SAW References for Bin Rock Point the fluence and UUSE data are from April 27, 1993 letter to NRC (Response to GL 92 01 RAI)
Chemical composition data are from June 12, 1978 letter from W. S. Skibitsky (CPCo) to D. L.
l Ziemann (USNRC), subject: Big Rock Point Plant-Reactor Surveillance Program i
Base metal UUSE and orientation, and weld UUSE are from C. Z. Serran, Jr., and H. E. Watson,
" Mechanical Property and Neutron Spectral Analysis of the Big Rock Point Reactor Pressure Vessel," Nuclear Enaineerina and Desion, 11 (1970), pp. 393 415 j
Chemical conposition and fluence data are from January 10, 1990, letter from K. W. Berry (CPCo) to USNRC Doctsnent Control Desk, subject: Big Rock Point Plant Technical Specification Change Request--Reactor Tenperature Limits Plate identification is from page 3 of July 29, 1977, letter from D. A. Bixel (USNRC) to Director of Nuclear Regulation (USNRC), subject: Big Rock Point and Palisades Plants, Response to Letter Dated May 20,1977 -Reactor vessel Surveillance i.
71 i
Summary File for Pressure-Temperature Limits Plant Deltline Heat No.
ID Neut.
I R T.
Method of Chefnistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T, CF Fermi 2 Lower int.
C4564-1 6.5E17 12'F Plant 58 Table 0.09 0.55 Shell specific G-3703-5 EOL:
Lower Int.
C4574 2 6.5E17
+16'F Plant 65 Table 0.10 0.55 3/20/2025 Shell specific G 3705 2 Lower Int.
C4568 2 6.5E17
-12*F Plant 83.15 Table 0.12 0.61 Shell specific G-3705 3 Lower Int.
88614-1 6.5E17
-20*F Plant 83.15 Table 0.12 0.61 Shell specific G-3705-1 Lower C4540 2 6.5E17 10'F Plant 51 Table 0.08 0.62 Shell specific G-3706-1 Lower C4560-1 6.5E17
-10'F Plant 73.7 Table 0.11 0.57 Shell specific G 3706-2 Lower C4554-1 6.5E17 10*F Plant 82.2 Table 0.12 0.56 Shell specific G-3706-3 Lower 13253 and 6.5E17
-44'F Plant 223.9 Table 0.26 0.87 Shell 12008 specific Axial Welds 2-307A/C Lower Int.
33A277 6.5E17 50'F Plant 188.5 Table 0.32 0.50 Shell specific Axial Welds 15-30BA/D Lower /
10137 6.5E17 50'F Plant 236 Table 0.23 1.00 Lower Int.
speelffe Cire. Weld 1-313 Reference for Fermi 2 Fluence, IRT, and chemical composition data are from June 30, 1992, letter from W. S. Orser (DE) to UNSRC Docunent Control Desk, subject: Detroit Edison Response to Generic Letter 92-01, Rev.1
' Additional information required to confirm value, i
75 Summary File for Upper Shelf Energy Plant Name Beltline Heat No, Material 1/4T USE 1/4T Unirrad.
Method of Ident.
Type at EOL Neutron USE Determin.
Flu nee at Unirred.
EOL USE Fermi 2 Lower Int.
C4564 1 A 5338 1 68 4.5E17 74 65%
Shell G 3703 5 EOL:
Lower Int.
C4574 2 A 5338-1 71 4.5E17 78 65%
3/20/2025 Shell G-3705 2 Lower Int.
C4568 2 A 5338 1 70 4.5E17 77 65%
Shell G 3705 3 Lower Int.
B8614 1 A 5338-1 76 4.5E17 85 65%
Shell G 3705 1 Lower Shell C4540-2 A 5338 1 86 4.5E17 94 65%
G 3706 1 Lower Shell C4560-1 A 5338 1 91 4.5E17 101 65%
G 3706-2 Lower Shell C4554-1 A 5339 1 77 4.5E17 86 65%
G-3706-3 Lower Shell 13253 and Linde 60 4.5E17 75' NRC Axial Welds 12008 1092, SAW Generic 2 307A/C Lower Int.
33A277 Linde 124, 65 4.5E17 88 Shell Axial SAW 10*F date Welds 15-308A/D Lower /
10137 Linde 86 4.5E17 105 10'F data Lower Int.
0091, SAW Cire. Weld 1 313 Reference for Fermi 2 Fluence, UUSE, CVN, and chemical composition data are from June 30, 1992, letter from W. S.
Orser (DE) to USNRC Document Control Desk, subject: Detroit Edison Response to Generic Letter 92 01, Rev. 1 l
i
)
i 3Generic value for welds fabricated by Combustion Engineering using Linde 1092, 0091 and 124 and Arcos B-5 fluxes (Ref:
Letter from S. Bloom, NRR, to T.L. Patterson, OPPD, dated December 3, 1993)
\\.
72 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Ncn Ident.
Ident.
Fluence at Determ{n.
Factor Determin.
EOL/EFPY I R T,,
CF Monti-Lower Int.
C2220 1 5.15E18 0*F Plant 125.3 Table 0.17 0.58 cello Shell specific 1 14 EDL:
Lower int.
C2220-2 5.15E18 14*F Plant 125.3 table 0.17 0.58 9/8/2010 Shell specific l 15 Lower A0946 1 5.15E18 0*F Plant 98,2 Table 0.14 0.56 Shell specific t 16 Lower C2193-1 5.15E18 6*F Plant 118.5 Table 0.17 0.50 Shell specific l-17 Welds SMAW 5.15E18
-66'F generic 134.9 Table 0.10 0.99 Reference for Monticello Fluence, IRT, and chemical camposition data are frees July 6,1992, letter from T. M. Parker (MSP) to USNRC Doctament Control Desk, subject: Response to Generic Letter 92-01, Reactor Vessel Structural Integrity i
1 l
i
' Additional information required to confirm value.
76 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Materlet 1/4T USE 1/4T Untrrad.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrrad.
EOL USE Monti-Lower Int.
C2220 1 A 5338 1 EMA' 3,8E18 EMA' cello Shell 1 14 EOL:
Lower Int.
C2220 2 A 533B-1 56 3.8E18 71 65%
9/8/2010 Shell 1-15 Lower Shell A0946-1 A 533B 1 EMA' 3.8E18 EMA' I 16 Lower Shell C2193 1 A 5338 1 EMA' 3.8E18 EMA' I 17 Welds No date SMAW EMA' 3.8E18 EMA' Reference for Monticello Fluence, UUSE, and chemical compoaltion data are from July 6, 1992, letter from T. M. Parker (NSP) to USNRC Doct.snent Control Desk, subject: Response to Generic Letter 92-01, Reactor Vessel Structural Integrity
' Licensee must confirm applicability of Topical Report NEDO-32205, Rev. 1
79 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,,,,
CF Dresden 2 Lower Int.
B4065-1 3.6E17 20*F Plant 155.4 Table 0.23 0.52 Shell specific EOL:
Lower Int.
85764-1 3.6E17 10'F Plant 65 Table 0.10 0.49 1/10/2006 Shell speelfic Lower Int.
B4030-1 3.6E17 6'F '
Plant 143 Table 0.20 0.55 Shell specific Lower Int.
B4030-2 3.6E17
-2'F '
Plant 143 Table 0.20 0.55 Shell specific Lower A9128-2 3.6E17 10*F Plant 131 Table 0.20 0.45 Shell specific Lower 83990 2 3.6E17 12'F Plant 116.9 Table 0.18 0.42 Shell specific Lower A9128-1 3.6E17 10*F Plant 131 Table 0.20 0.45 Shell speelfic Lower Int.
PQ1092C 2 3.6E17 40*F Plant 93.4 Table 0.18 0.18 Shell specific Axial Welds Lower Int.
1P0661 3.6E17
-38'F Plant 162.1 Table 0.19 0.63 Shell specific Axial Welds Lower Int.
1P0815 3.6E17
-22'F
- Plant 122.2 Table 0.12 0.52 Shell specific Axial Welds Lower PQ1092C-2 3.6E17 40*F Plant 93.4 Table 0.18 0.18 Shell specific Axial Welds Lower 1P0815 3.6C17
-14*F Plant 159.2 Table 0.25 0.48 Shell specific Axial Welds 7
Lower Int.
71249 3.6E17 10*F Plant 167.3 Table i 0.21 0.62 to Lower specific Cire. Weld Reference for Dresden 2 The IRT for electroslag welds (heat nunt>er PQ 1092C-2) is from September 24, 1993 letter to NRC (Response to GL 92-01 RAI).
Chemical composition, IRT, and fluence data are from July 1, 1992, letter from M. A. Jackson (Ceco) to T. E. Murley (USNRC), schject: Dresden Station Units 2 and 3; Quad Cities Station Units 1 and 2; LaSalle County Station Units 1 and 2
' Additional information required to confirm value.
83 Summary File for Upper Shelf Energy Plant Name Bettllne Heat No.
Material 1/4T USE 1/4T Untrred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrred.
EOL USE Dresden 2 Lower Int.
B4065-1 A 3028 EMA' 2.5E17 E MA*
Shell EOL:
Lower Int.
85764-1 A 302B EMA*
2.5E17 E MA' 1/10/2006 Shell Lower Int.
B4030 1 A 3028 E MA' 2.5E17 EMA' Shell lawer Int.
D4030 2 A 302B EMA' 2.5E17 E MA' t
.c A9128-2 A 3028 E MA' 2.5E17 E MA' aell Lower 83990 2 A 302B E MA' 2.5E17 EMA*
Shell Lower A9128-1 A 302B EMA' 2.$E17 EMA' Shell Lower Int.
PQ1092C 2 Flux EMA' 2.5E17 EMA' Shelt
1P0661 Flux EMA' 2.5E17 EMA' Shell
- unkrawn, Axlal SAW Welds Lower Int.
1P0815 Flux EMA' 2.5E17 EMA' Shell
- unknown, Axlal SAW Welds Lower Int.
71249 Flux' E MA' 2.5E17 E MA' to Lower
- unknown, Cire. Weld SAW Reference for Dresden 2 Chemical conposition, UUSE, and fluence data are from July 1,1992, letter f rom M. A. Jackson
'. Ceco) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad Cltles Station Units 1 and 2; LaSalle County Station Units 1 and 2 2Licensea must confirm applicability of Topical Report NED0-32205, Rev, 1
80 Summary File for Pressure-Temperature Limits Plant Bettline Heat No.
10 Neut.
I R T.,
Method of Chemistry Method of
%Cu hl Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T.,
CF Dresden 3 Lower Int.
A0237-1 5.1E17 10*F Plant 151.05 Table 0.23 0.49 Shell specific EOL:
Lower Int.
85118 1 5.1E17 10*F Plant 146.15 Table 0.22 0.49 1/12/2011 Shelt specific Lower Int.
C1290 2 5.1E17 10'F Plant 103.95 Table 0.15 0.49 Shell specific Lower C1256-2 5.1E17
-10*F Plant 73 Table 0.11 0.50 Shell specific Lower B5159-2 5.1E17 0*F Plant 153.15 Table 0.24 0.47 Shell specific Lower C1182-2 5.1E17 10*F Plant 147.5 Table 0.22 0.50 Shell specific Lower Int.
PQ1300 5.1E17 40*F Plant 159.65 Table 0.30 0.33 and Lower Shell specific Axial Welds Lower Int.
299L44 5.1E17 0*F Plant 209.6 Table 0.29 0.72 to Lower Shell specific Cire.
Welds Reference for presden 3 The IRT for electrostag welds (heat nurber PQ-1300) is from September 24, 1993 letter to NRC (Response to GL 92-01 R Chemical conposition, IRT, and fluence data are from July 1,1992, letter from M. A. Jackson (CECO) to T. E (USNRC), subject:
. Murley Oresden Station Units 2 and 3; Quad Cities Station Units 1 and 2; LaSalle County Station Units 1 and 2
1
' Additional information required to confirm value
84 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Materlat 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirrad.
1 EOL USE Dresden 3 Lower Int.
A0237-1 A 3028 EMA' 3.5E17 EMA'
-~
Shell Mod.
j EOL:
Lower Int.
85118 1 A 3028 EMA' 3.5E17 EMA' l
1/12/2011 Shell Mod.
Lower Int.
C1290 2 A 3028 EMA' 3.5E17 EMA' Shell Mod.
Lower C1256-2 A 302B EMA' 3.5E17 EMA'
~-
Shell Mod.
Lower 85159-2 A 3028 EMA' 3.5E17 EMA' Shell Mod.
Lower C1182 2 A 3028 EMA' 3.5E17 EMA' Shell Mod.
Lower Int.
PQ1300 Flux EMA' 3.5E17 EMA*
and Lower
299L44 Flux EMA' 3.5E17 EMA' to Lower
- unknown, Shell SAW Cire.
Welds Reference for Dresden 3 Chemical corrposition, UUSE, and fluence data are from July 1, 1992, letter from M. A. Jackson (Ceco) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; ound cities Station Units 1 and 2; Lasalle County Station Units 1 and 2 I
i i
)
l
\\
l I
1 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
81 Summary File for Pressure-Temperature limits Plant Beltline Heat No.
ID Neut.
- IRT, Method of Chemistry Method of
%Cu
%Ni Nane Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T.,
CF ouad Lower Int.
C1505-2 3.5E17
-20'F Plant 126.4 Table 0.18 0.52 Citics 1 Shell specific EOL: 12/
Lower Int.
C1498-2 3.5E17
-30*F Plant 118.5 Table 0.17 0.50 14/2012 shell specific Lower Int.
A0931-1 3.5E17
-30*F Plant 95.95 Table 0.14 0.51 Shell specific Lower B5524-1 3.5E17 0'F Plant 179.65 Table 0.27 0.57 Shell specific Lower A0610-1 3.5E17
-20*F Plant 143.3 Table 0.21 0.51 Shell specific Lower C1485 2 3.5E17
-30'F Plant 152.5 Table 0.23 0.50 Shell specific Lower Int.
PQ1300 3.5E17 40*F Plant 159.65 Table 0.30 0.33 and Lower specific Shell Axial Welds lower Int.
PQ2563 3.5E17 40*F Plant 272 Table 0.35 1.00 and Lower specific Shell Axial Welds Lower Int.
72445 3.5E17
-28*F Plant 122 Table 0.10 0.60 to Lower specific Shell Cire. Weld Lower Int.
406L44 3.5E17
-10'F Plant 164 Table 0.22 0.58 to lower specific Shell Cire. Weld Reference for Quad Cities 1 The IRT for electrostag welds (heat numbers PQ-1300 and PQ-2563) is from September 24, 1993 letter to NRC (Response to GL 92 01 RAI)
Chemical cosmosition, IRT, and fluence data are from July 1,1992, letter from M. A. Jackson (Ceco) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad cities station Units 1 and 2; LaSalle County station Units 1 and 2
'Addicional information required to confirm value.
85 Summary File for Upper Shelf Energy R
Plant Name Belttine Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirrad.
EOL USE Quad Lower Int.
C1505 2 A 3028 E MA' 2.4E17 EMA' Cities 1 Shelt Mod.
EOL : 12/
Lower Int.
C1498-2 A 3028 EMA' 2.4E17 EMA' 14/2012 Shelt Mod.
Lower Int.
A0931-1 A 3028 E MA' 2.4E17 E MA' Shell Mod.
Lower 85524-1 A 3028 E MA*
2.4E17 E MA*
Shell Mod.
Lower A0610-1 A 3028 E MA' 2.4E17 EMA' Shell Mod.
Lower C1485-2 A 3028 EMA' 2.4E17 EMA' Shell Mod.
Lower Int.
PQ1300 Flux EMA' 2.4E17 EMA' and Lower
PQ2563 Flux EMA' 2.4E17 EMA' and Lower
72445 Flux EMA' 2.4E17 EMA' to Lower
- unknown, Shell SAW Cire. Weld Lower Int.
406L44 Flux E MA' 2.4E17 EMA*
to Lower
- unknown, Shelt SAW Cire. Weld Reference for Quad cities 1 Chemical composition, UUSE, and fluence data are from July 1,1992, letter from M. A. Jackson (Ceco) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad Cities Station Units 1 and 2; LaSatte County Station Units 1 and 2 i
i 1
i 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
i 82 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
10 Neut, I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,
CF Quad Lower Int.
C2753 2 4.9E17 10*F Plant 51 Table 0.08 0.50 cities 2 Shell specific EOL: 12/
Lower Int.
C2868 1 4.9E17 10*F Plant 51 Table 0.08 0.48 14/2012 shell specific Lower Int.
C3307-2 4.9E17 10*F Plant 82 Table 0.12 0.55 Shell specific Lower C1516 2 4.9E17 6'F Plant 108.2 Table 0.16 0.46 shell specific Lower C1501-2 4.9E17
-10*F Plant 123.55 Table 0.18 0.49 Shell specific Lower C1722 2 4.9E17 10*F Plant 97.3 Table 0.14 0.54 Shell specific Lower Int.
PQ-1300 4.9E17 40*F Plant 159.65 Table 0.30 0.33 and Lower specific Shell Axial Welds Lower Int.
S-3986 4.9E17
-42*F Plant 68 Table 0.05 0.96 to Lower specific shell Cire. Weld Reference for 00ad Cities 2 The IRT for electrostag welds (heat ntsnber PQ-1300) is from September 24, 1993 letter to NRC (Response to GL 92-01 RAI).
Chemical composition, IRT, and fluence data are from July 1,1992, letter from M. A. Jackson (Ceco) to T. E. Murley (UskRC), subject: Dresden station Units 2 and 3; Quad Cities station Unita 1 and 2; LaSalle County station units 1 and 2
9 1
' Additional information required to confirm value.
b
A 8
a 86 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
fluerce at Unirred.
EOL USE cuad Lower Int.
C2753-2 A 3028 EMA' 3.4E17 EMA' Cities 2 Shell Mod.
EOL: 12/
Lower Int.
C2868 1 A 3028 EMA' 3.4E17 EMA*
14/2012 Shell Mod.
Lower Int.
C3307-2 A 3028 EMA' 3.4E17 EMA' Shell Mod.
Lower C1516-2 A 3028 EMA' 3.4E17 EMA' Shell Mod.
Lower C1501-2 A 3028 EMA*
3.4E17 EMA' Shell Mod.
Lower C1722-2 A 3028 EMA' 3.4E17 EMA' Shell Mod.
Lower Int.
PQ-1300 Flux D4A' 3.4E17 EMA*
and Lower
5-3986 Flux EMA' 3.4E17 EMA*
to Lower
- unknown, Shell SAW Cire. Weld Reference for Quad Cities 2 Chemical composition, UUSE, and fluence data are from July 1, 1992, letter from M. A. Jackson (Ceco) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad cities Station Units 1 and 2; LaSalle county Station Units 1 and 2 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1 i
l 1
83 Summary File for Pressure-Temperature Limits Plant Beltline Heat Wo.
10 Neut.
IR T.
Method of Chemistry Method of
%Cu
%NI Want2 Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY I R T,,
CF LaSalle 1 Lower C5978 1 3.9E17 14*F Plant 73.8 Table 0.11 0.58 Shelt specific G 5603-1 EOL:
Lower C5578 2 3.9E17 23'F Plant 73.9 Table 0.11 0.59 5/17/2022 Sheti specific G-5603-2 Lower C5979 1 3.9E17 10*F Plant 83.9 Table 0.12 0.66 Shell specific G-5603 3 Lower Int.
C6345-1 3.9E17 20'F Plant 103.95 Table 0.15 0.49 Shell specific G 5604-1 Lower Int.
C6318-1 3.9E17
-20*F Plant 81.2 Table 0.12 0.51 Shell specific G 5604 2 Lower Int.
C6345-2 3.9E17
-20'F Plant 103.95 Table 0.15 0.51 Shell specific G-5604-3 i
Middle A5333-1 3.9E17
-10*F Plant 81.8 Table 0.12 0.54 Shell specific G 5605-1 Middle 80078-1 3.9E17
-10*F Plant 104.5 Tabte 0.15 0.50 Shell specific G-5605-2 Middle C6123 2 3.9E17
-10*F Plant 93 Table 0.13 0.68 Shell specific G 5605-3 l
Middle 305424 3.9E17
-50*F Plant 200.2 Table 0.30 0.64 Shelt specific Axial Welds 3-308A/C Middle 1P3571 3.9E17 30*F Plant 241 Table 0.37 0.75 Sheli specif(c Axial Welds 3-308A/C Lower Int.
305414 3.9E17
-50*F Plant 203.75 Table 0.33 0.59 Shell specific Axial l
(
4 308A/C Lower Int.
12008 3.9E17
-50*F Plant 208.7 Table 0.28 0.74 Shell specific Axial Welds 4-308A/C Lower 21935 3.9E17
-50*F Plant 177.2 Table 0.21 0.68 Shell specific Axial Welds 2 307A/C
' Additional information required to confirm value.
84 Sumary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%NI Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT,
CF Lower 12008 3.9C17
-50'F Plant 249 Table 0.27 1.00 Shell specific Axial Welds 2-307A/C Middle to 6329637 3.9E17
-50'F Plant 239 Table 0.24 1.00 Lower int.
specific Shell Circ. Weld 6-308 Lower to AP6519 3.9E17 60*F Plant 83.8 Table 0.18 0.06 Lower Int.
specific Shell Cire.
Weld 1 313 Reference for leSelle i Chemical conposition, IRT, and fluence data are from July 1,1992, letter from M. A. Jackson (CECO) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad cities station Unita 1 and 2; LaSalle County station Units 1 and 2
l l
1
\\
87 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirred.
EOL USE LaSalle 1 Lower C5978-1 A 5338 1 EMA' 2.5E17 EMA' Shell G-5603-1 EOL:
Lower' C5978 2 A 533B-1 EMA' 2.5E17 EMA' 5/17/2022 Shell G-5603 2 Lower C5979 1 A 5338-1 E MA' 2.5E17 EMA' Shell G-5603-3 Lower Int.
C6345 1 A 5338 1 EMA' 2.5E17 EMA' Shell G 5604 1 Lower Int.
c6318 1 A 5338 1 EMA*
2.5E17 EMA' Shell G 5604 2 Lower Int.
C6345 2 A 5338-1 EMA' 2.5E17 EMA' Shell C-5604 3 Middle A5333-1 A 5338 1 EMA*
2.5E17 EMA' Shell G-5605-1 Middle 80078-1 A 5338-1 EMA' 2.5E17 EMA' Shell G 5605 2 Middle C6123-2 A 5338 1 EMA' 2.5E17 EMA*
Shell G 5605-3 Middle 305424 Linde EMA' 2.5E17 EMA' Shell 1092, SAW Axial Welds 3-308A/C Middle iP3571 Linde EMA' 2.5E17 EMA*
Shell 1092, SAW Axial Welds 3 308A/C Lower Int.
305414 Linde EMA' 2.5E17 EMA*
Shell 1092, SAW Axial Welds 4-30BA/C Lower Int.
12008 Linde EMA' 2.5E17 EMA' Shell 1092, SAW Axial Welds 4-308A/C 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
(
~.
4.
88 Summary File for Upper Shelf Energy Plant Name Beltline Heat No, Material 1/4T USE 1/4T Unirrad.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence et Unirred.
EOL USE Lower 21935 Linde EMA' 2.5E17 EMA' Shell 1092, SAW Axial Welds 2 307A/C Lower 12008 Linde EMA' 2.5E17 EMA' Shell 1092, SAW Axial Welds 2 307A/C Middle to 6329637 Linde EMA*
2.5E17 EMA*
Lower Int.
1092, SAW Shell Cire. Weld 6 308 Lower to AP6519 Linde EMA' 2.5E17 EMA' Lower Int.
1092, SAW Shell Circ.
Weld 1-313 Reference for LaSalle 1 Chemical ccaposition, UUSE, and fluence data are from July 1,1992, letter from M. A. Jackson (CECO) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad Cities Station Units 1 and 2; LaSalle Comty Station Units 1 and 2 2Licensee must confirm applicability of Topical Report NE00-32205, Rev.1
85 Summary File for Pressure-femperature limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%NI Name ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT,
CF LaSalle 2 Lower C9425-2 4.2E17 30*F Plant 81.2 Table 0.12 0.51 Shell specific 21 1 Ect: 12/
Lower C9425 1 4.2E17 32*F Plant 81.2 Table 0.12 0.51 16/2023 Shell specific 21-2 Lower C9434-2 4.2E17 10'F Plant 58 Table 0.09 0.51 Shell speelfic 21-3 Lower Int.
C9481-1 4.2E17 10'F Plant 73 Table 0.11 0.50
- Shell, specific 22 1 2
Lower Int.
C9404-2 4.2E17 52*F Plant 44 Table 0.07 0.49
- Shell, speelfic 22-2 Lower Int.
C9601-2 4.2E17 10*F Plant 81 Table 0.12 0.50
- Shell, specific 22 3 Lower Int.
3P400 4.2E17
-50*F Plant 27 Table 0.02 0.89 Shell specific Axial Welds BA,B8,BC Lower 3P4966 4.2E17
-26'F Plant 41 Table 0.03 0.90 Shell specific Axial Welds BD, BE,lt F Cire. Veld SP6771 4.2E17 34*F Plant 54 Table 0.04 0.95 AB specific Reference for LaSa Qe_{
Chemical corr, position, IRT, and fluence data are from July 1, 1992, letter from M. A. Jackson (CECO) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; Quad cities Station Units 1 and 2; LaSalle County Station Units 1 and 2
' Additional information required to confirm value.
89 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrred.
E0L USE LaSalle 2 Lower C9425-2 A 5339-1 EMA' 2.9E17 EMA' Shell 21 1 EOL: 12/
Lower C9425 1 A 5338 1 EMA' 2.9E17 EMA*
16/2023 Shell 21 2 Lower C9434 2 A 5339 1 EMA' 2.9E17 EMA' Shell 21-3 Lower Int.
C9481*1 A 5338 1 EMA' 2.9E17 EMA*
- Shell, 22 1 Lower Int.
C9404-2 A 5338 1 EMA' 2.9E17 EMA'
- Shell, 22 2 Lower Int.
C9601 2 A 5338 1 EMA' 2.9E17 EMA'
- Shell, 22 3 Lower Int.
3P400 Linde 124, E MA' 2.9E17 EMA' Shell SAW Axial Welds BA,BB,8C Lower 3P4966 Linde 124, EMA' 2.9E17 EMA' Shell SAW Axial Welds BD,BE,BF Cire Weld 5P6771 Linde 124, EMA' 2.9E17 EMA'
, _AP SAW Reference for LaSalle 2 Chemical composition, UUSE, and fluence data are from July 1, 1992, letter from M. A. Jackson (Ceco) to T. E. Murley (USNRC), subject: Dresden Station Units 2 and 3; cuad Cities Station Units 1 and 2; LaSalle County Station Units 1 and 2 2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1
91 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
10 Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY 1 R T.,,
CF Duane Lower Int.
B0436-2 3.6E18 10'F Plant 111 Table 0.15 0.64 Arnold Shell specific 1 20 EOL:
Lower Int.
B0673-1 3.6E18 10'F Plant 110.25 Table 0.15 0.61 2/21/2014 Shell specific 1 21 Lower C6439 2 3.6E18 40*F Plant 58 Table 0.09 0.51 Shell specific 1-18 Lower 80402 1 3.6E18 40'F Plant 87.1 Table 0.13 0.47 Shell specific 1-19 Cire. Weld 09L853 3.6E18
-50*F Plant 41 Table 0.03 0.88 specific
{
Cire. Weld 07L669 3.6E18 50*F Plant 41 Table 0.03 1.02 specific Cire. Weld CTY538 3.6E18 50'F Plant 41 Table 0.03 0.83 specific i
Axial 43224521
- 3. 6E18
-50'F Plant 20 Table 0.01 0.98 Welds specific Axial 43220471 3.6E18
-50'F Plant 41 Table 0.03 0.91 Welds specific cteference for Duane Arnold Chemical conposition, some UUSE, IRT, and fluence data are f rom July 6,1992, letter f rom J. F. Franz, Jr. (IELEP) to T.
E. Murley (USNRC), subjects Response to NRC Generic Letter 92-01, Revision 1, " Reactor vessel Structural Integritya Licensee's response to GL 92 01 does not indicate which welds are in which shell, so all weld RT,.. calculations will be made for the thinner (4.47 in.) wall thickness.
1 l
' Additional information required to confirm value.
i
96 Summary File for Upper Shelf Energy Plant Name Bettline Heat No.
Material 1/4T USE 1/4T Unfrred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfr ad.
EOL USE Duane Lower Int.
80436-2 A 5338 1 72 2.75E18 87 65%
Arnold
- Shell, 1-20 EOL:
Lower Int.
60673-1 A 5338 1 103 2.75E18 107 65%
2/21/2014
- Shell, 1-21 Lower C6439 2 A 5338 1 EMA' 2.66E18 EMA' Shell 1 18 Lower 80402 1 A 5338-1 EMA' 2.66E18 EMA' Shell 1-19 Cire. Weld 09L853
$ MAW Cire. Weld CTV538
- E8018, EMA*
2.75E18 EMA' Welds SMAW Axial 43220471
- E8018, 89 2.75E18 103 10'F data Welds SMAV Rgference for Dunne Arnold Chemical conposition, WSE, and fluence data are from July 6,1992, letter f rom J. F. Franz, Jr. (IEL&P) to T. E. Murley (USNRC), subject: Response to NRC Ceneric Letter 92 01, Revision 1, " Reactor vessel Structural Integrity" Licensee's response to CL 92 01 does not indicate which welds are in which shell, so all weld WSE calculations will be made for the thinner (4.47 in.) wall thickness.
NOTE: It is not known which welds are in the lower shell. Therefore, I used the higher of the 1/4T EOL fluences, 2.75E18 n/cm', because it gave lower 1/4T EOL USEs, 2Licensee must confirm applicability of Topical Report NED0-32205, Rev. I
- ~_.
92 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRTm CF Perry
- 2 Shell C2557-1 5.4E18 10'F Plant 37 Table 0.06 0.61 plates specific EOL:
- 2 shell 86270-1 5.4E18
-30'F Plant 37 Table 0.06 0.63 3/18/2026 plates epecific
- 2 shell A1155-1 5.4E18
-10*F Plant 37 Table 0.06 0.63 plates specific Axist 627260/
5.4E18
-30'F Plant 82 Table 0.06 1.08 Welds 8322A27AE specific Axial 626677/
5.4E18
-20'F Plant 20 Table 0.01 0.85 Welds C301A27AF specific Axial SP62148/
5.4E18
-40'F Plant 27 Table 0.02 0.82 Welds 0331 speciffe Axial 624063/
5.4E18
-50*F Plant 41 Table 0.03 1.00 WeIds 0228A27A specific Axial 627069/
5.4E18 60*F Plant 20 Table 0.01 0.94 Welds C312A27A specific References for Perry Chemical conposition and 1RT are f rom the Perry i FSAR (Only #2 shell plates are in the neutron active zone)
Fluence datun is f rom September 14, 1990, letter from M. D. Lyster (CE) to USNRC Document Control Desk, subject:
Technical Specification Change Request--Reactor Pressure-Temperature Limits i
l I
l I
1
j 97 Sumary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirrad.
EOL USE Perry
- 2 Shell C2557-1 A 5338-1 64 3.74E18 84 Direct Plates EOL:
- 2 Shell B6270 1 A 5338-1 80 3.74E18 94 Direct 3/18/2026 Plates
- 2 Shell A1155-1 A 5338-1 99 3.74E18 114 Direct Plates Axlat 627260/
SMAW 88 3.74E18 104 Direct Welds 8322A27AE Axial 626677/
SMAW 77 3.74E18 90 Direct Welds C301A27AF Axial SP62140/
Flux 75 3.74E18 88 Direct Welds 0331
- unknown, SAW Axial 624063/
SMAW 89 3.74E18 105 Direct Welds D228A27A Axial 627069/
SMAW 95 3.74E18 112 Direct Welds C312A27A References for Perry Chemical conposition and UUSE are from the Perry 1 FSAR Fluence datum is from September 14, 1990, letter from M. D. Lyster (CE) to USNRC Docunent Control Desk, subject: Technical Specification Change Request--Reactor Pressure-Tenperature Limits
93 Summary File for Pressure-Temperature Limits k
Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni
}
Natu Ident.
Ident.
Fluence at Determin.
Factor Determin.
[
EOL/EFPY I R T, CF Clinton Shett C4363-2 6.9E18
-30'F Plant 37 Table 0.06 0.62 Course 2 specific EOL:
Shell C4380-2 6.9E18 20'F Plant 44 Table 0.07 0.63 9/29/2026 Course 2 specific i
Shell C4320-2 6.9E18
-20'F Plant 31 Table 0.05 0.64 Course 2 specific Shell A2758 1 6.5E17
-10'F Plant 65.4 Table 0.10 0.64 Course 1 specific Shell A2740-1 6.5E17
-30*F Plant 74.9 Table 0.11 0.66 Course 1 specific Welds 3P4955/
6.9E18
-50'F Plant 41 Table 0.03 0.93 0951(S) specific Welds 3P4955/
6.9E18
-60*F Plant 41 Table 0.03 0.89 0951(T) specific Welds 3P4955/
6.9E18
-20'F Plant 27 Table 0.02 0.95 0342(S) specific Welds 3P4955/
6.9E18
-20'F Plant 41 Table 0.03 0.90 0342(T) specific Welds 3P4955/
6.9E18
-60*F Plant 27 Table 0.02 0.97 3478(S) specific Welds 3P4955/
6.9E18
-60*F Plant 41 Table 0.03 0.90 3478(T) specific l
Welds SP6756 6.9E18
-60*F Plant 108 Table 0.08 0.96 specific Welds 76492 6.9E18
-30'F Plant 135 Table 0.10 1.08 specific References for Clinton Belttine radius is unsubstantiated dat m from Clinton Project Manager.
Beltline thickness, fluence, Ni for plates A2758-1 and A2740-1 are f rom July 25, 1990, letter from J. B. Hickman (USNRC) to J. C. Tsao (USNRC), subject: Request for Additional Information on Clinton Response to Generic Letter 88-11 All other data are from Clinton USAR.
l NOTE: There are only five beltline plates NOTE: There is no differentiation between axial and cire mferentia! welds, so they are all considered both exist and circumferential welds
o 98 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unfrrad.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrred.
EOL USE Clinton Shell C4363 2 A 5338-1 88 4.93E18 105 Direct Course 2 EOL:
Shell C4380-2 A 5338-1 86 4.93E18 102 Direct 9/29/2026 Course 2 Shell C4320 2 A 5338-1 78 4.93E18 93 Direct Course 2 Shell A2758 1 A $338 1 56 4.65E17 '
67 50'F data Course 1 Shell A2740 1 A 5330-1 60 4.65E17 T2 30'F data Course 1 Welds 3P4955/
Flux type 78 4.93E18 93 Direct 0951(S)
- unknown, SAW Welds 3P4955/
Flux type 67 4.93E18 80 Direct 0951(T)
- unknown, SAW Welds 3P4955/
Flux type 76 4.93E18 90 Direct 0342(S)
- unknown, SAW Welds 3P4955/
Flux type 80 4.93E18 95 Direct 0342(T)
- unknown, SAW Welds 3P4955/
Flux type 93 4.93E18 111 Direct 3478(S)
- unknown, SAW Welds 3P4955/
Flux type 87 4.93E18 104 Direct 3478(T)
- unknown, SAW Welds 5P6756 Flux type 103 4.93E18 126 Direct
- unknown, flux Core Welds 76492 Flux type 77 4.93E18 97 Direct
- unknown, SAW References for Clinton Fluence is from July 25, 1990, letter from J. B. Hickman (USNRC) to J. C. Tsao (USNRC),
subject: Request for Additional Information on Clinton Response to Generic Letter 88-11 All other data are from Clinton USAR.
NOTE: There are only five beltline plates
' Additional information required to confirm value.
l
98 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
]D Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Naru Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT.,
CF Cooper Lower int.
C2407-1 1.5E18
-10'F Plant 92.25 Table 0.13 0.65 shell specific G-2801 7 EOL:
Lower int.
C2331-2 1.5E18 10*F Plant 125.3 Table 0.17 0.58 12/18/
shell specific 2014 G-2802 1 Lower int.
C2307-2 1.5E18
-20'F Plant 162.8 Table 0.21 0.73 shell specifie G-2802-2 Lower C2274 1 1.5E18 14'F Plant 153 Table 0.20 0.68 shell specific G-2803-1 Lower C2307-1 1.5E18 0*F Plant 162.8 Table 0.21 0.73 shell specific G 2803-2 Lower C2274 2 1.5E18
-8'F Plant 153 Table 0.20 0.68 shell specific G-2803-3 Lower int.
27204 &
1.5E18
-50*F Plant 215.65 Table 0.19 0.97 shell 12008 specific axial welds 1-233A/C (T)
Lower to 21935 1.5E18
-50*F Plant 1 75.3 Tabte 0.20 0.69 lower-int, specific shell cire, weld 1-240 tower 12420 1.5E18
-50*F Plant 234.5 Table 0.22 1.02 shell specific axial welds 2 233A/C
References:
Chemical composition (copper (Cu] and nickel [NI)) for weld 2-233A/C, Ni for weld 1-240 and 1-233A/C are f rom February 25, 1993, letter f rom G. R. Horn (NPPD) to USNRC Docunent Control Desk, subject: Sutnittal of Reactor Vessel Surveillance Test Results.
IRT., data for weld 1 233A/C is from G. R. Horne letter of February 25, 1993, cited above.
Other chemical conposition, and other IRT, data are f rom July 1,1992, letter f rom G. R. Horn (NPPD) to USNRC Docunent Control Desk, subject: Response to Generic Letter 92-01, Revision 1.
' Additional information required to confirm value.
103 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unirred.
EOL USE Cooper Lower int.
C2407 1 A 5338 1 61 1.08E18 84 65%
shell G 2801 7 EOL:
Lower int.
C2331-2 A 5338-1 61 1.08E18 72 65%
12/18/
shell 2014 G-2802 1 Lower int.
C2307-2 A 5338-1 67 1.08E18 84 65%
shell G-2802-2 Lower C2274-1 A 5338-1 60 1.08E18 73 65%
shell G 2803 1 Lower C2307-1 A 5338-1 61 1.08E18 75 65%
shell G-2803-2 Lower C2274-2 A 5333 1 60 1.0BE18 72 65%
shell G-2803-3 Lower int.
27204 &
Linde 85 1.08E18 112
- Sury, shell 12008 1092, SAW Weld axial welds 1 233A/C Lower to 21935 Linde EMA' 1.08E18 EMA' lower int.
1092, SAW shell circ. weld 1-240 Lower 12420 Linde EMA' 1.08E18 E MA' shell 1092, SAW axial welds 2-233A/C
References:
Chemical composition (copper (Cu1 and nickel [Ni} } for weld 2-233A/C, Ni for weld 1-240 and 1-233A/C are from February 25, 1993, letter from G. R. Horn (NPPD) to USNRC Doctanent Control Desk, subjects Submittal of Reactor Vessel Surveillance Test Results.
Fluence, the UUSE of the surv. weid, and other chemical conposition data are from July 1,1992, letter from G. R. Horn (NPPD) to USNPC Document Control Desk, subject: Response to Generic Letter 92-01, Revision 1.
Plate UUSE data are from Table 7-1 of MDE-103 0986, which evaluated surveillance capsule 1.
2Licensee must confirm applicability of Topical Report NED0-32205, Rev. I 1
o O
e 99 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL/EFPY IRT,
CF Grand
- 2 Shell C2593 2 3.14E18
-30*F Plant 26 Table 0.04 0.59 Gulf 1 Plates specific EOL:
- 2 Shell C2594-1 3.14E18
-10'F Plant 26 Table 0.04 0.63 6/16/2022 Plates specific
- 2 Shell C2594 2 3.14E18 0*F Plant 26 Table 0.04 0.63 Plates specific
- 2 Shell A1224-1 3.14E18 0*F Plant 26 Table 0.04 0.65 Plates specific
- 2 Shell 627260 3.14E18
-30*F Plant 82 Table 0.06 1.08 Axial specific Welds
- 2 Shell
$P6214B 3.14E18
-50*F Plant 27 Table 0.02 0.82 Axial specific Welds
- 2 Shell 626677 3.14E18
-20*F Plant 20 Table 0.03 1.04 Axial specific Welds References for Grand Gulf 1 Fluence dattsn is f rom July 6,1992, letter from W. T. Cottle (EO) to USNRC Document Control Desk, subject: Response to Generic Letter 92 01, Revision 1
'he staf f asstsned that the fluence of 2.11E18 was the value at T/4 because the same fluence was reported in FSAR for T/4 location.
Chemical conposition and IRT data are from the Grand Gulf FSAR. (Only #2 shell plates are in the neutron active zone)
Ni contents for welds $P62148 and 627260 are found in attachment to February 28, 1989, letter from T. H. Cloninger (SER) to USNRC Document Control Desk, subject: Generic Letter 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations," Updated Information, AECM-89/0047 Ni content of weld 626677 is estimated at 1.00% per RG 1.99, Rev. 2
a 9
104 Summary File for Upper Shelf Energy I
' Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unfrrad.
Method of Ident.
Type et EOL Neutron USE Determin.
Fluence at Unfrred.
EOL USE Grand Gulf
- 2 Shell C2593 2 A 5338 1 90 2.11E18 102 Direct 1
Plates EOL:
- 2 Shell C2594-1 A 5338-1 88 2.11E18 100 Direct 6/16/2022 Plates
- 2 Shell C2594 2 A 5330-1 90 2.11E18 102 Direct Plates
- 2 Shell A1224 1 A 5338 1 143 2.11E18 162 Direct Plates
- 2 Shell 627260
- 2 Shell 5P62148 Linde 124, 80 2.11E18 91 Direct Axial SAW Welds
- 2 Shell 626677
- E8018, B4 2.11E18 95 Direct Axial SMAW Welds References for Grand Gulf 1 Chemical composition and UUSE data are from the Grand Gulf FSAR (only #2 shell plate are in the neutron active zone).
Fluence datum is from July 6,1992, letter from W. T. Cottle (EO) to USNRC Document Control Desk, subject: Response to Generic Letter 92 01, Revision 1.
The location of the fluence of 2.11E18 was not identified there. The staf f assumes the location to be T/4 because this same fluence was reported in FSAR for the T/4 location.
t 6.
105 Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL I R T,,,
CF River
- 2 shell C3138 2 6.64E18 9'F Plant 51 Table 0.08 0.63 Bend plates specific EOL:
- 2 shell C3054-1 6.64E18 20*F Plant 58 Table 0.09 0.70 8/29/2025 plates specific
- 2 shelt C3054-2 6.64E18 2*F Plant 58 Table 0.09 0.70 plates speelfic Axial 492L4871/
- 6. 64E18
-60*F Plant 54 Table 0.04 0.95 Weida A421827AE specific Axial 492L4871/
6.64E18
-50*F Plant 41 Table 0.03 0.98 Welds A421827AF specific Anlel SP6756 6.64E18
-50'F Plant 122 Table 0.09 0.92 Welds specific Reference for River jend chemical cooposition, fluence, and IRT data are from July 2,1992, letter from W. H. Odell (GSUCo) to USNRC Doctstient Control Desk, subject: River Bend--Unit 1, Docket No. 50 458 (Only #2 shell plates are in the neutron active zone) 1 l
l l
)
l
W 110 Summary File for Upper Shelf Energy Plant Name Beltline Heat No.
Material 1/4T USE 1/4T Unirred.
Method of Ident.
Type at EOL Neutron USE Determin.
Fluence at Unfrrad.
EOL USE River Bend
- 2 Shell C3138 2 A 533B 1 67 4.8E18 79 Direct Plate EoL:
- 2 Shell C3054-1 A $338-1 78 4.8E18 93 Direct 8/29/2025 Plate
- 2 Shell C3054-2 A 5338 1 80 4.8E18 95 Direct Plate Axial 492L4871 SMAW 132 4.8E18 157 Direct Welds Axial 492L4871 SMAW 110 4.8E18 130 Direct Welds Axial
$P6756 SAW 78 4.8E18 98 Direct Welds Reference for River Bend Chemical composition, fluence, and UUSE data are from July 2, 1992, letter from W. H. Odell (CSUCo) to USNRC Docunent Control Desk, subject: River Bend--Unit 1, Docket No. 50-458 r
r e
116 l
e Summary File for Pressure-Temperature Limits Plant Beltline Heat No.
ID Neut.
I R T, Method of Chemistry Method of
%Cu
%Ni Name ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL IRT,
CF m
WHP-2 Ring #1 C1272 1 1.4E18 28'F Plant 110 Table 0.15 0.60 specific EOL: 12/
Ring #1 C1273-1 1.4E18 20'F Plant 100 Table 0.14 0.60 3
20/2023 speeifie Ring #1 C1272 2 1.4E18 0*F Plant 110 Table 0.15 0.60 specific Ring #1 C1273-2 1.4E18 4*F Plant 100 Table 0.14 0.60 specific Ring #2 85301-1 1.4E18
-20*F Plant 95.5 Table 0.14 0.50 specific l
Ring #2 C1336-1 1.4E18 8'F Plant 91 Table 0.13 0.50 l
specific 4
Ring #2 C1337 1 1.4E18
-20'F Plant 105.05 Table 0.15 0.51 specific Ring #2 C1337-2 1.4E18
-20*F Plant 105.05 Table 0.15 0.51 specific Cire. Weld SP6756 (S) 1.4E18
-60*F Plant 122 Table 0.09 0.93 AB specific 5P6756 (T) 1.4E18
-50'F Plant 122 Table 0.09 0.92 specific i
3P4955 (S) 1.4E18
- 20*F Plant 41 Table 0.03 0.90 specific 3P4955 (T) 1.4E18
-20'F Plant 41 Table 0.03 0.95 specific Axist 3P4966 1.4E18
-26*F Plant 41 Table 0.03 0.85 Welds specific BA/BD Axist 3P4966 1.4E18
-26*F Plant 41 Table 0.03 0.85 Welda specific BE/BH References for WNP-2 l
IRT data for cire, welds are from the attachment to the response to RAI (GL 92-01) dated Septenter 21, 1993.
j Weld chemical conposition and IRT data are from Table 5.3 5 of Technical Specifications. Plate chemical conposition and l
IRT data are from Table 5.3-4 of FSAR.
Fluence datum is from page 5.3 5d of the WNP-2 FSAR (Amendnent 36, December 1985) l I
l i
i 1
' Additional information required to confirm value.
I w
e 122 Summary File for Upper Shelf Energy Plant Beltline Heat No.
Materlat 1/4T USE at 1/4T Unirred.
Method of i
Name Ident.
Type EOL Neutron USE Determin.
Fluence at Unirrad.
EOL USE WNP-2 Ring #1 C1272 1 A 5338 1 EMA' 9.4E17 EMA*
EOL:
Ring #1 C1273-1 A 533B-1 EMA*
9.4E17 EMA*
12/
20/2023 Ring #1 C1272 2 A 5338 1 EMA' 9.4E17 EMA*
Ring #1 C1273 2 A 5338-1 EMA' 9.4E17 EMA' Ring #2 B5301 1 A 5338 1 EMA' 9.4E17 EMA*
Ring #2 C1336 1 A 5338 1 E MA' 9.4E17 EMA' u-Ring #2 C1337-1 A 5338 1 EMA' 9.4E17 EMA' Ring #2 C1337-2 A 5338 1 EMA*
9.4E17 EMA' cire. Weld SP6756(S)
Linde 124 79 9.4E17 91 direct AB Cire. Weld SP6756(T)
Linde 124 84 9.4E17 97 direct AB Cire. Weld 3P4955(S)
Linde 124 81 9.4E17 90 direct AB Cire. Weld 3P4955(T)
Linde 124 86 9.4E17 95 direct AB Axial 3P4966 Linde EMA*
9.4E17 EMA*
Welds 124, SAW BA/B0 i
Axial 3P4966 Linde EMA' 9.4E17 EMA' Welds 124, SAW BE/BH References for WNP-2 UUSE data for cire welds are from the attachment to the response to RAI (GL 92 01) dated Septenber 21, 1993.
Weld chemical conposition data are from Table 5.3 5 of Technical Specifications. Plate chemical conpos tion and IRT data are from Table 5.3-4 of FSAR.
i Fluence datun is from page 5.3-5d of the WNP-2 FSAR (Amendnent 36, December 1985)
Plate UUSE data are from page B 3/4.4.6-1 of the WWP-2 Technical Specifications. There are no weld UUSE data.
2Licensee must confirm applicability of Topical Report NED0-32205, Rev.1 L
f
- s All NRR Project Directors thrch 24, 1994 EMCB expects to provide similar closecut letters and tables for Pressurized Water Reactors by April 15, 1994.
Please contact me if you have any questions.
Original signed by:
Daniel G. Mcdonald, Senior Project Manager Lead Project Manager - MPA B-120 Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
DISTRIBUTION:
1.
List of Plants Central File PDI-1 Reading 2.
Closecut Letter RAcapra DMcDonald 3.
Nomenclature and Tables NRR Licensing Assistants CHarwood, 12/D/23 RVillafranco, 12/H/7 KBohrer, 12/H/5 cc w/ enclosures 1 and 2:
EPoteat, 12/H/7 MBoyle ADPR/NRR JRHall, 13/H/24 PDR S. Varga J. Roe D. Crutfchfield DRPE/DRPW Assistant Directors DRPE/DRPW Project Managers Technical Assistant, DRPE Technical Assistant, DRPW
- See previous concurrence LA:PDI-l LeadPM:PDJhh*EMCB
- EMCB
- BC:EMCB TA:DRPE _
DMcDonaldm SSheng KWichman JStrosnider MBoyle h CVogan ae J3 / 01/94 O}/N94 03/17/94 03/17/94 03/18/94 3/G/94 TA:DRPW Lead PD:PDI-l JRHall980 RACapra /
l 'J /7//bk 9/$/94 0FFICIAL RECORD COPY FILENAME: MPA.MEM
-