ML17180A682
| ML17180A682 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle  |
| Issue date: | 04/14/1994 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| GL-92-01, GL-92-1, TAC-M83458, TAC-M83459, TAC-M83474, TAC-M83475, TAC-M83502, TAC-M83503, NUDOCS 9404210164 | |
| Download: ML17180A682 (21) | |
Text
1>-ll REG1;(
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Docket Nos. 50-237, 50-249 50-373, 50-374 and 50-254, 50-265 Mr. D. L. Farrar, Manager Nuclear Regulatory Services Conunonwealth Edison Company Executive Towers West 111, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Farrar:
April 14, 1994 u~~
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I
SUBJECT:
GENERIC LETTER (GL) 92-01, REVISION 1, "REACTOR VESSEL STRUCTURAL INTEGRITY," DRESDEN, UNITS 2 AND 3, QUAD CITIES, UNITS 1 AND 2, LASALLE, UNITS 1 AND 2, (TAC NOS. M83458, M83459, M83474, M83475, M83502, AND M83503)
By letters dated July 1, 1992, October 9, 1992, September 24, 1993, and
- October 22, 1993, Conunonwealth Edison Company (CECo) provided its response to GL 92-01, Revision 1.
The NRC staff has completed its review of your responses.
Based on its review, the staff has determined that CECo has provided the information requested in GL 92-01.
The GL is part of the staff's program to ev*a l uate 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 conunitments necessary to ensure reactor vessel integrity for their
- .. facilities.
. A substantial amo~unt of information was provided in response to GL 92-01, **
Revision 1. These data have been entered into a computerized database designated Reactor Vessel Integrity Database (RVIO). provides the pressure temperature tables, Enclosure 2 provides the Upper Shelf Energy (USE) tables for your facilities, 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 pts evaluations. These data
- were taken from your responses to GL 92-01 and previously docketed information.
The information in the RVID for your facilities 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.
As a result *of our GL 92-01 review, the NRC staff has identified one open issue for your plant. The initial RTNDT values determined by General Electric's (GE) initial methodology have not been validated and the BWR Owners Group report, GE-NE-523-109-0893, entitled, "Basis for GE RTNDT Estimation Method," did not resolve the issue.
GE is in the process of validating its
(\\, \\
methodology for resolving the initial RTNDT determination issue and,will D(f o
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9404210164 940414 I ! :.
PDR ADOCK 05000237 I
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~Mr. D. April 14, 1994 document the result in a topical report.
The BWR Owners Group is 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 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.I.
We further request that you verify that the information you have provided for your
- facilities has been accurately entered in the database. If no comments are made in you~ response to the last request, the staff ~ill use the information in the tables for future NRC assessments of your reactor pressure vessel.
Once you.have (1) confirm~d the applicability of the topical report, NED0-32205, Revision 1, to your plants~ (2) submitted th~ 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.
Plant-specific licensing actions will be initiated to resolve these issues.
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 burdeb hours 'is 200 person *hours for each addressee~s response. This estimate pertains only to the identified response-rel.ate~ matt.~rs and does not include the time required to implement actions. irequif"ed :by the reg1.,1lations.
This action is co~ered b~* the Office of_ Mana~_!;!m~~f ~nd_: Budget Clearance Numb~r 3150-0011, wh1ch exp1res June 30, 1994. *
- ,;i,
- ,i". Sincerely,
....~
~ '* ~~* '.,Ori.gina:l signed by:
John:_S. Stang, ProjeC:t Manager "t,*., *..
- ., ~ {.
,~,.* /' ProjeC:t :o~irectorate 111-2
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. '..*:. * *
- Divislon" qf*.. Reactor Projects - II I/IV
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. 'Offke of":Nuc.l~ar Reactor ReguTation
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Enclosures:
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I. Pres.sure-:; Temperature J:i miV:...'. * ~~.,.:-, '-/,..
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Upper-She 1 f 'Energy Jabl es
- 3.
Nomencl atur~ *Key i' '.*
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cc w/enclosurds:
See next page*:,
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- 1
. 1 DI STR I BUTI ON'.' '
"'.~Docket -Fi 1 e JZwolinski
~
AGody NRC" & Local PORs JRoe JStang BClayton,.RII I
- CHawes 3 OFC LA
- PDIII-2
- PM:PDill-2~
i:
JDyer OGC DMcDonald PM:PDIII-2
- PM: POI 11-2
- PDIIl-2 r/f CPatel ACRS ( 10)
SShen
- D: POI I 1-2 NAME CHAWES JSTANG AGODY,Jr.
CPATEL JOVER~
DATE 04 08 94
't i'f 94 94 COPY YES NO 0
YES NO
- See previous concurrence.
Mr. D. L. Farrar Commonwealth Edison Company cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. G. Spedl Plant Manager Dresden Nuclear Power Station 6500 North Dresden Road
- Morris, Illinois 60450-9765 U. S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 6500 North Dresden Road
- Morris, Illinois 60450-9766 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional *Administrator U. S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Illinois Department of Nuclea~ Safety Office of Nuclear Facility Safety
- 1035 Outer )ark Drive Springfield, Illinois 62704 Dresden Nuclear Power Station Unit Nos. 2 and 3
Mr. D. L. Farrar Commonwealth Edison Company cc:
Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and Electric Company P. O. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. Richard Bax Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North
'Cordova, Illinois 61242 Resident Inspector
~
U. S. Nuclear Regulatory Commission 22712 206th Avenue North
- Cordova, Illinois 61242 Chairman Rock Island County Board
. of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
. Rock Island, Illinois 61201
Mr. D. L. F~rrar Conunonwealth Edison Company cc:
Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Assistant Attorney General 100 West Randolph Street.
Suite 12*
Chicago, Illinois 60601 Reside.nt Inspector/LaSalle, NPS U. S. Nuclear Regulatory Conunission Rural Route No. 1 P. 0. Box 224 Marseilles, Illinois 61341 Chairman LaSalle County Board of Supervisors LaSalle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Commerce Conunission Leland Building 527 East Capitol Avenue Springfi~ld, Illinois 62706 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator U. S. NRC, Region III 801 Warrenville Road*
Li~le, Illinois 60532-4351 LaSalle Station Manager LaSalle County Station Rural Route 1 P.O. Box 220 Marseilles, Illinois 61341 LaSalle County Station Unit Nos. 1 and 2 Robert Cushing Chief, Public Utilities Division 111 i no is Attorney General 's Office
- 100 West Randolph Street Chicago, Illinois 60601 Michael I. Miller, Esquire Sidley and Austin One First National Plaza
- Chicago, Illinoi~ 60690 LaSalle Station Manager LaSalle County Station Rural Route 1 P. 0. Box 220 Marseilles, Illinois 61341
ENCLOSURE 11 79 Su11111ary File for Pressure-Temperature Limits Plant Bel tl ine Heat No.
JD Neut.
IRT-Method of Chemistry Method of
.ICU Xiii Name I dent.
Jdent *.
Fluence at Deten11in.
Factor Deterwin.
EOL/EFPY IRT-CF Dresden 2 Lower Int.
84065*1 3.6E17 2o*F I
Plant 155.4 Table 0.23 0.52 I
Shell SDM:iffc EOL:
Lower Int.
85764*1 3.6E17 1o*F I
Plant 65 Table 0.10 0.49 1/10/2006 Shell SDeCf ff c Lower Int.
84030*1 3.6E17 6*F I Plant 143 Tele 0.20 0.55 Shell
&DeCiffc Lower Int.
84030*2 3.6E17
- 2*F I Plant 143 Table 0.20 0.55 Shell SDeCiffc Lower A9128*2 3.6E17 1o*F I
Plant 131 Table 0.20 0.45
- Shell aiieciffc Lower 83990*2 3.6E17 12*F I
Plant 116.9 Table 0.18 0.42 Shell BDecfffc Lower A9128*1 3.6E17 to*F I
Plant 131 Table 0.20 0.45 Shell sDeciffc Lower Int.
PQ1092C*2 3.6E17 4o*F Plant 93.4 Table 0.18 0.18 Shell specific Axial Welds Lower lnt.
1P0661 3.6E17
- 38*F I
Plant 162.1 Table 0.19 0.63 Shell specific Axial Welds Lower lnt.
1P0815 3.6E17
- 22*F I 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
- o. 18 Shell specific Axial Welds.
Lower 1P0815 3.6E17
- 14.F I
Plant 159.2 Table 0.25 0.48 Shell specific Axial Welds Lower Int.
71249 3.6E17
- 1o*F I
Plant 167.3 Table 0.21 0.62 to Lower specific Circ. Weld Reference for Rresden Z The lRT for electroalag weldll Cheat rumer PQ 1092C*2> fa frm Septemer 24, 1993 letter to NRC (Response to GL 92*01 RAJ).
Chemical coq>oaitfon, lRT, and fluence data are frm July 1, 1992, letter from M. A. Jackson (CECo) to T. E. Murley (USNRC), slbject: Dresden Station Unfta 2 and 3; Quad Cftfea Station Units 1 and 2; Lasalle CCMtty Station Units 1 and 2
1Additional information required to confirm value.
80 Sunmary File for Pressure-Temperature Limits Plant Bel tl ine Heat No.
ID Neut.
IRT-Method of Chemistry Method of XCu
>>Ii Name ldent.
I dent.
Fluence at Determfn.
Factor Determin.
EOL/EFPY IRT-CF Dresden 3 Lower Int.
A0237*1 5.1E17 10°F Plant 151.05
. Table 0.23 0.49 Shell saecffic EOL:
Lower Int.
85118*1 5.1E17 1o*F Plant 146.15 Table 0.22 0.49 1/12/2011 Shell SDeCtfic Lower Int.
C1290*2' 5.1E17 10°F Plant 103.95 Table 0.15 0.49 Shell SDeCiffc Lower C1256*2 5.1E17
-1o*F Plant 73 Table 0.11 0.50 Shell SDeCfffc Lower 85159*2 5.1E17 o*F Plant 153.15 Table 0.24 0.47 Shell acecffic Lower C1182*2 5.1E17 10°F Plant 147.5 Table 0.22 0.50 Shell soecific Lower Int.
PQ1300 5.1E17 40°F Plant 159.65 Table 0.30 0.33 and Lower specific Shell Axial Welds Lower Int.
299L44 5.1E17 o*F I
Plant 209.6 Table 0.29 0.72 to Lower specific Shell Circ.
Welds Reference for Qresden ~
The IRT for electroalag welds Cheat ~r PG*1300) is frm Septent.r 24, 1993 letter to NRC (Response to GL 92*01 RAI).
Chemical c~ition, IRT, and fluence data are frOlll July 1, 1992, letter from M. A. Jackson (CECo) to T. E. Murley (USNRC), aLbject: Dresden Station Unfta 2 and 3; Quad Cities Station Unfta 1 and 2; LaSalle C~ty Station Units 1 and 2
1Additional information required to confirm value.
81 Summary F1le for Pressure-Temperature L1m1ts Plant Beltlfne Heat No.
ID Neut.
IRT-Method of Chemistry Method of XCu XNf Name I dent.
ldent.
Fluence at Detenafn.
Factor Detennfn.
EOL/EFPY IRT-CF Quad Lowr Int.
C1505-2 3.5E17
- 20°F Plant 126.4 Table 0.18 0.52 i
Cities 1 Shell SfM!Ciffc i
EOL:
12/
Lowr Int.
C1498*2 3.5E17
- JO*F Pl Mt 118.5 Table 0.17 0.50 14/2012 Shell llDltCiff c Lower Int.
A0931*1 3.5E17
- 30°F Pl Mt 95.95 Table 0.14 0.51 Shell snecfffc Lower 85524-1 3.5E17 0°F I
Plant 179.65 Table O.l1 0.57 i
J Shell SfM!Ciffc Lowr A0610*1 3.5E17
- 20°F Plant 143.3 Table 0.21 0.51 Shell eeciffc Lowr C1485*2 3.5E17
- 30°F Plant 152.5 Table 0.23 0.50 Shell snecffi c Lowr Int.
PG1300 3.5E17 40°F Plant 159.65 Table 0.30 0.33 and Lower specific Shell Axial Welds i
Lower Int.
PG2563 3.5E17 40°F Plant 272 Table o.~
1~00 and Lowr specific l
Shell Axial Welds Lower Int.
72445 3.5E17
-28°F I
Plant 122 Table 0.10 0.60 to Lowr specific Shell Circ. Weld
. Lower Int.
406L44 3.5E17
- 10°F I
Plant 164 Table 0.22 0.58..
I I
to Lower specific I
I Shell I
Cfrc. Weld 1
Reference for Quad t!Iies 1 l
The IRT for electroslag welds (hHt rud>era PQ-1300 and PQ-2563) fa frm Septed>er 24, 1993 letter to MRC (Response to GL 92*01 RAI)
Chemical coq:10&ition, IRT, and fluence date ere fra July 1, 1992, letter fra M. A. Jackson CCECo) to T. E. Murley (USNRC), subject: Dresden Station Units. 2 and 3; Quad Cities Station Units 1 and 2; LaSalle CCU1ty Station Units 1 and. '
I 2
I 1Add1tional information required to confirm value.
82 Su11111ary File for Pressure-Temperature Limits Plant Bel tl ine Heat No.
ID Neut.
IRT-Method of Chemistry Method of*
xcu Xiii Name ldent.
ldent *.
Fluence *t Detel'llin.
Factor Deter11in.
EOL/EFPY IRT-CF Quad LCMtr Int.
C2753*2 4.9E17 1o*F Plent 51 Table 0.08 0.50 Cities 2 Shell 11D11Ciflc EOL:
12/
LCMtr Int.
C2868*1 4.9E17 1o*F Plant 51 Table 0.08 0.48 14/2012 Shell 11D11Clflc LCMtr Int.
C3307-2 4.9E17 1o*F Plant 82 Table
- o. 12 0.55 Shell snec:lflc LCMtr C1516*2 4.9E17 6*F I
Plent 108.2 Table 0.16 0.46 Shell 11D11Cfffc Lower C1501*2 4.9E17
-1o*F Plant 123.55 Table
- o. 18 0.49 Shell Snl!Ciffc Lower C1722*2 4.9E17 10°F I
Plent 97.3 Table
- o. 14 0.54 Shell snec:fffc LCMtr Int.
PQ*1300 4.9E17 40*F Plant 159.65 Table 0.30 0.33 anc:t LOliler specific Shell Axial Welds LONer Int.*
S-3986 4.9E17
- 42°F Plant 68 Table 0.05 0.96 to Lower specific Shell Circ. Weld Reference for Quad ~fti!! ~
The JRT for electroslaa welds Cheat Nllt>er PQ-1300> fa frcm Septeat>er 24, 1993 letter-to NRC (Response to GL 92*01 RAI).
Chemical c~sltlon, JRT, anc:t fluence det* *r* from July 1, 1992, letter frca M. A. Jackson (CECo) to T. E. Murley CUSNRC), subject: Dresden Station Units 2 end 3; Quad Cities Station Units 1 end 2; LaSalle C~ty Station Units 1 end 2
1Additional information required to confirm value.
~
... ary File for Pressure-Tempera~e Limits Plant Beltllne Heet No.
ID Neut.
11n_
Method of Chemistry Method of XCu INI N11111e I dent.
I dent.
Fluence at Deten1in.
Factor Determin.
EOL/EFPY IRT-CF LaSalle 1 Lower C5978*1.
3.9E17 14°F I
Plant 73.8 Table 0.11 D.58 Shell specific G*5603*1 EOL:
Lower C5978*2 3.9E17 23°F I
Plant 73.9 Table 0.11 0.59 5/17/2022 Shell specific G*5603*2 LC*er C5979*1 3.9E17 10°F Plant 83.9 Table 0.12 0.66 Shell specific G*5603*3 LC*er 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
-2o*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 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 Table 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 Middle 305424 3.9E17
- 50°F Plant 200.2 Table 0.30 0.64 Shell specific Axial Welds 3*308A/C Middle 1P3571 3.9E17
- 30°F I
Plant 241 Table 0.37 0.75 Shell specific Axial Welds 3*308A/C Lower Int.
305414 3.9E17
-5o*F Plant 203.75 Table 0.33 0.59 Shell specific Axi*l Welds 4*308A/C LOMer Int.
12008 3.9E17
-so*F Plant 208.7 Table 0.28 0.74 Shttll specific Axi*l
-Welds 4*308A/C Lower 21935 3.9E17
-so*F Plant 177.2 Table 0.21 0.68 Shell specific Axial Welds 2*307A!C 1Additional information required to confirm value.
84 Su11111ary File for Pressure-Temperature Limits
(
Plant Beltl fne Heat No.
ID Neut.
IRT-Method of Chemistry Method of XCu XNf Name ldent.
Jdent.
fluence et Deter11fn.
Fector Determfn.
EOL/EFPY JRT-Cf I
Lower 12008 3.9E17
- 50°F Plant 249 Table 0.27 1.oo I
I Shell apecfffc Axf al
~
Welds 2*307A/C Middle to I 6329637 3.9E17
-so*F Plent 239 Teb~e 0.24 1.oo Lower Int.
apecfffc Shell i
Cfrc. Weldi*.
6*308 i
Lower to AP6519 3.9E17
- 60"f Plent 83.8 Table
- o. 18 0.06 Lower Int.
specific Shell Circ.
Weld 1*313 Reference f2r baSa! l! 1 Chemical caq>oaftfon, lRT, and fluence date ere from July 1, 1992, letter frOlll M. A. Jackson (CECO) to T *. E_. Murley (USNRC), a~jec:t: Dresden Station Units 2 end 3; Quad Cities Station Units 1 and 2; LaSalle CCU\\ty Station Units 1 end 2
85 Su11111ary File for Pressure-Temperature Limits I
Plant Belt line Heat No.
ID Neut.
IRT-Method of Ch*fatry Method of XCu XIII l
Name ldent.
ldent *.
Fluence at Detan1fn.
Factor Daten1in.
t EOL/EFPY IRT-CF leSlllle 2 LONer C9425*2 4.2E17 3o*F I
Plant 81.2 Table 0.12 0.51 Shell apecfffc 21*1 EOL:
12/
LONer C9425*1 4.2E17 32*F I
Plant 81.2 Table 0.12 0.51 16/2023.
Shell apeclflc 21*2 LONer C9434*2 4.2E17 1o*F Plant 58 Table 0.09.
0.51
~*
Shell apeclflc 21*3 LONer Int.
C9481*1 4.2E17 1o*F Plant 73 Table 0.11 0.50
- Shell, apeclffc 22*1 LONer Int.
C9404*2 4.2E17 52°F I
Plant 44 Table 0.07 0.49 Shell,.
apecfflc 22*2 LONer Int.
C9601*2 4.2E17 1o*F Plant 81 Table 0.12 0.50
- Shell, apecfflc 22*3 LONer Int.
.. 3P400 4.2E17
-5o*F Plant 27 Table 0.02 0.89 Shell apeclflc Axial Welds BA,BB,BC Lo..er 3P4966 4.2E17
-26*F I
Plant 41 Table 0.03 0.90 Shell apeclflc Axial Welds BO.BE.BF Cfrc. Weld 5P6771 4.2E17
- J4*F I
Plant 54 Table 0.04 0.95 AB llllll!Cf ff c Reference for LaSall! ~
ttiemical c~ftfon, IRT, and fluence data are from July 1, 1992, letter from M. A. Jackson CCECo) to T. E. Murley*
CUSNRC), al,j)ject: Dresden Station Unfta 2 and 3; Qued Cities St1tfon Unfta 1 and 2; L1Salle C~ty Station Units 1 and 2
'Additional ~nfonnation required to confinn value.
ENCLOSURE
~
83 Su11111ary File for Upper Shelf Energy Plant N-Bel tl fne Keet No.
Materiel 1/4T USE 1/4T Unfrrad.
Method of I dent.
Type et EOl Neutron USE Deter11f n.
Fluence *t Unfrrad.
EOL USE Dresden 2 Lower Int.
84065*1 A 3028 EMA' 2.5E17 EMA' Shell EOL:
Lower Int.
85764*1 A 3028 EMA' 2.5E17 EMA' 1/10/2006 Shell Lower Int.
84030*1 A 3028 EMA' 2.5E17 EMA' Shell Lower Int.
84030*2 A 3028 EMA1 2.5E17 EMA' Shell Lower A9128*2 A 3028
- EMA' 2.5E17 EMA' Shell Lower 83990-2 A 3028 EMA' 2.5E17 EMA' Shell Lower A9128*1 A 3028 EMA' 2.5E17 EMA' Shell Lower Int.
P01092C*2 Flux EMA' 2.5E17 EMA' Shell
1P0661 Flux BIA' 2.5E17 EMA' Shell.
- unknown, Axial SAW l
Welds Lower Int.
1P0815 Flux EMA' 2.5E17 EMA' Shell
EMA' Shell
- unknown, Axial SAW Welds Lower Int.
71249 Flux EMA' 2.5E17 EMA*
to Lower
- unknown, Cfrc. Weld SAW Reference for Rees~ ~
Chemical caq>OSftfan, WSE, end fluence dllt* ere from July 1, 1992, letter frm M. A. Jackson (CECO) to T. E. Murley (USNRC), Mbject: Dresden Statton Unfts 2 and 3; Quad Cftfes Statton Unfta 1 and 2; Laselle COU'\\ty St1tfon Units 1 end 2 2Licensee must confirm applicability of Topical Report NED0-32205, Rev. 1
84 Su11111ary File for Upper Shelf Energy
- Plant Name Beltl ine Heat No.
Material 1/4T USE 1/4T Uni rrad.
Method of ldent.
Type at EOL Neutron USE Determin.
Fluence at Unirrad.
EOL USE Dresden 3 LCNer Int.
AD237*1 A 3028 EMA" 3.5E17 EMA" Shell Mod.
EOL:
LCNer Int.
85118*1 A 3028 EMA" 3.5E17 EMA 1
1/12/2011 Shell Mod.
Lower Int.
C1290*2 A 3028 EMA" 3.5E17 EMA" Shell Mod.
Lower C1256*2 A 3028 EMA 1
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 1
3.5E17 EMA*
end Lower
~.
Shell ESW Axial Welds Loi.r Int.
299L44.
Flux EMA" 3.5E17 EMA" to Lower ll'lknown, Shell SAW Circ.
Welds Refecencs f2r gresden }
Chemical coq:IOSition, WSE, and fluenc:e data are frOlll July 1, 1992, letter from M. A. Jackson CCECo) to T. E. Murley CUSNRC), s~ject: Dresden Station Units 2 and 3; Quad Cities Station Units 1 and 2; LaSalle CCMa'lty Station Units 1 and 2 2Licensee must confirm applicability of Topical Report NED0-32205, Rev. I
85 Summary File for Upper Shelf Energy Plant Name Bel tl fne Heat No.
Material 1/4T USE 1/4T Unfrrad.
Method of Jdent.
Type at EOL Neutron US£ Oeter11in.
Fluence at Unirrad.
EOL USE Quad Lower Jnt.
C1505*2 A 3029 EMA" 2.4E17 EMA" Cities 1 Shell Mod.
EOL:
12/
Lower Jnt.
C1498*2 A 3029 EMA" 2.4E17 EMA" 14/2012 Shell Mod.
Lower Jnt.
A0931*1 A 3029 EMA" 2.4E17 EMA" Shell Mod.
Lower 95524*1 A 3029 EMA" 2.4E17 EMA" Shell Mod.
Lower A0610*1 A 3029 EMA" 2.4E17 EMA" Shell Mod.
Lower C1485*2 A 3029 w*
2.4E17 EMA" Shell Mod.
Lower Jnt.
PQ1300 Flux w*
2.4E17 EMA" and Lower
- rinown, Shell ESW Axial Welda Lower Jnt.
PQ2563 Flux EMA" 2.4E17 EMA" and Lower
- rinowt, Shell ESW Axial Welda Lower Jnt.
n445 Flux w*
2.4E17 EMA1 to Lower
- unknown, Shell SAW Circ. Weld Lower Jnt.
406L44 Flux EMA 1
2.4E17 EMA" to Lower
- unknown, Shell SAW Circ. Weld Bef1cmJEe f2r Gl:!!51 'f Sfl! l Ch*ical c~ltfon, WSE, and fluence date ere from.luly 1, 1992, letter from M. A *.lackson (CECO) to T. E. Murley (USNRC), MbJect: Dresden Station Units 2 and 3; Quad Cftles Station Unfts 1 end 2; LaSalle CCU\\tY Station lkllts 1 and 2 2Licensee must confirm applicability of Topical Report NED0-32205, Rev. I
86 Sunmary File for Upper Shelf Energy Plant N._
Bel tl lne Heat No.
Materiel 1/4T USE 1/4T Unlrrad.
Method of ldent.
Type et EOL Neutron USE Determin.
Fluence et Unlrrad.
EOL USE Quad LOMer 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 EMA" 3.4E17
- EMA" and Lower
s-.3986 Flux EMA" 3.4E17 EMA" to LC*er
&.nltt"*'1, Shell SAW Clrc. Wald Referenc1 f2r Quad ~isles z Chemical c~ition, WSE, and fluence data ere fre111 July 1, 1992, letter from M. A. Jackson (CECO) to T. E. Murley (USNRC), slbject: Dresden Station Units 2 and 3; Quad Cities Station Units 1.and 2; L11S11lle C°"'ty Statton Units 1 and 2 2L1censee must confirm applicability of Topical Report NED0-32205, Rev. 1
e e
87 Surrmary File for Upper Shelf Energy Plant Name 8eltl lne Heat No.
Material 1/4T USE 1/4T Unlrrad.
Method of ldent.
Type at EOL Neutron USE*
Determfn.
Fluence at Unfrrad.
EOL USE Lasalle 1 Lower C5978-1 A 5338*1 w*
2.5E17 EMA*
Shell G-5603*1 EOL:
Lower C5978*2 A 5338*1 w*
2.5E17*
EMA*
5/17/2022 Shell G-5603*2 Lower C5979*1 A 5338*1 w*
2.5E17 EMA*
Shell G*5603*3 Lower Int.
C6345*1 A 5338*1 w*
2.5E17 EMA1 Shell G-5604*1 Lower Int.
C6318-1 A 5338*1 w*
2.5E17 EMA 1
Shell G-5604*2 Lower Int.
C6345*2 A 5338*1 w*
2.5E17 w*
Shell G-5604*3 Middle A5333-1 A 5338*1 w*
2.5E17 EMA*
Shell G-5605*1 Middle 80078-1 A 5338*1 EMA1 2.5E17 EMA*
Shell G-5605-2 Middle C6123-2 A 5338*1 w*
2.5E17 EMA 1
Shell G-5605*3 Middle 305424 Linde w*
2.5E17 EMA*
Shell 1092, SAW Axial Welda 3*308A/C Middle 1P3571 Linde w*
2.5E17 EMA*
Shell 1092, SAW Axial Welds 3*3oaA/C Lower Int.
305414 Linde w*
2.5E17 EMA*
Shell 1092, SAW Axial Welda 4*308A/C Lower Int.
12008 Linde m*
2.5E17 w*
Shell 1092, SAW Axial Welda 4*308A/C 2Ucensee must" confirm appl1cab111ty of Topical Report N.ED0-32205, Rev. 1
88 Su11111ary File for Upper Shelf Energy Plant....
Beltlfne HHt llo.
Maiterf el 1/4T USE 1/4T Unfrrad.
Method of I dent.
Type et EOL Neutron USE Determfn.
Fluence et Unfrred.
EOL USE Lower 21935 Lfnde ENA 1
2.5E17 ENA*
Shell 1092, SAW Axfal Welda 2*307A/C Lower 12008 Lfnde ENA*
2.5E17 ENA*
Shell 1092, SAW Axfel Welda 2*307A/C Mfddle to 6329637 Linde ENA*
2.5E17 w*
Lower Jnt.
1092, SAW Shell Cfrc. Weld 6*308 Lower to AP6519 Linde ENA*
2.5E17 ENA*
Lower Int.
1092, SAW Shell Cfrc.
Weld 1*313 8!f!r!!JS! foe ~as1111 ]
Chemical caaipoaftfon, UUSE, and fluence data are from July 1, 1992, letter frm M. A. Jackson (CECo) to T. E. Murley CUSNRC), aW:>ject: Dresden Stetfon Unlts2 and 3; Quad Cftfes Station Units 1 and 2; LaSalle C~ty Station Units 1 and 2 2Licensee must confirm applicability of Topical Report NED0-32205, Rev. 1
e e
89 Sunvnary F1le for Upper Shelf Energy Plant Naa.
Bel tl fne Heat No.
Mllterf al 1/4T USE 1/4T Unfrred.
Method of ldent.
Type et EOL Neutron USE Deteratin.
Fluence at Unfrred.
EOL USE LaSalle 2 Lowr C9425*2 A 5339*1 w*
2.9£17 w*
Shell 21*1 EOL:
12/
Lowr C9425*1 A 5339*1 EMA" 2.9£17 EMA" 16/2023 Shell 21*2 Lowr C9434*2 A 5339*1 EMA" 2.9£17 EMA" Shell 21*3 Lowr Int.
C9481*1 A 5339*1 EMA" 2.9£17 EMA"
- Shell,
. 22*1 Lower Int.
C9404*2 A 5339*1 ENA 1
2.9£17 ENA 1
- Shell, 22*2 Lower Int.
C9601*2 A 5339*1 ENA1 2.9£17 ENA1
- Shell, 22*3 Lower Int.
3P400 Linde 124, w*
2.9£17 w*
Shell SAW Axial Welds BA Bil BC Lower 3P4966 Linde 124, EMA" 2.9£17 ENA1 Shell SAW Axial Welds BO,BE,BF Clrc. Weld 5P6n1 Linde 124, ENA 1
2.9£17 ENA 1
AB SAW Beferenc£ f2r* ba§gLL! i Chemical can.,osltlon, WSE, end fluence data are from July 1, 1992, letter frm M. A. Jackson (CECO) to T. E. Murley (USNRC), al.Cject: Dresden Station Units 2 and 3; Quad Cities Station Units 1 end 2; LaSalle C°"'tY Station Units 1 and 2 2L1censee must confirm appl1cabil1ty of Topical Report NED0-32205, Rev. 1
ENCLOSURE 3 Nomenclature and Tables
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 (EOL) neutron fluence at vessel inner wall; cited 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, PIS, or P/T limits submittals).
Column 5: Unirradiated reference temperature.
Column 6: Method of. determining unirradiated reference temperature (IRT).
- Pl ant-Soec if i c This indicates that the IRT was determined from tests on material removed from the same heat of the beltline material.
M!EB 5-2 This indicates that the unirradiated reference temperature was determined from following HIEB 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 u_nirradi ated 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 Table 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 surveillance data via procedures described in RG 1.99, Revision 2.