ML18059A960
| ML18059A960 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Palisades, Kewaunee, Byron, Braidwood, Prairie Island, Callaway, Cook, Zion  |
| Issue date: | 04/15/1994 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| GL-92-01, GL-92-1, TAC-M83436, TAC-M83437, TAC-M83443, TAC-M83444, TAC-M83445, TAC-M83453, TAC-M83454, TAC-M83474, TAC-M83491, TAC-M83499, TAC-M83500, TAC-M83732, TAC-M83744, NUDOCS 9404270382 | |
| Download: ML18059A960 (41) | |
Text
..
UNITED STATE$
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. ~1 April 15, i994 MEMORANDUM FOR:
All Region III Project Directors THRU:
Robert A. Capra, Director
~*
Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation FROM:
Daniel G. McDonald, Senior Project Manager Lead Project Manager -
MPA*~e:.120
SUBJECT:
Project Directorate 1-1 Division of Reactor Projects - 1/11 Offi~e of Nuclear Reactor Regulation GENERIC LETTER 92-01, REVISION 1, *REACTOR VESSEL STRUCTURAL INTEGRITY* (MPA 8-120)
The subject Generic Letter (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' responses to the GL. provides two inserts to be sent to licensees. Insert 1 is to be sent to plants with no open issues. Insert 2 is for Zion 2 to confirm that the end-of-life (EOL) upper shelf energy (USE) for the specified forging is greater than SO ft~lbs. A sample closeout letter to be sent to the PWR licensees is provided as Enclosure 2. Please replace the blank paragraph identified as *INSERT* in the sample closeout. letter with the paragraph under one of the two groups to which the plant belongs.
Each closeout letter will include (as enclosures} two tables of data including a key to the nomenclature used. This data was compiled based on each licensee's response(s} to 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.*
Contacts:
D. McDonald, LPM 504-1408 E *. Hackett, EMCB 504.:.2751
l'
,1 All Region-III Project Directors April 15, 1994
. For all plants, the licensees are requested to verify the accuracy of the infonnation in the tables provided with the closeout letters~,... For one plant in Group 1,.Zion 1, that uses the Topical Reports BAW-2178P arid BAW-2192P as its licensing basis, the licensee needs to provide confinnation of plant~
specific applicability of the topical reports to its plant 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. This review will be a plant-specific licensing action.
For Zion 2, the project manager (PM) should request the licensee to submit a schedule for perfonning the analyses necessary to resolve the issue.of uncertain EOL USE for the specified forging.
The sub~itt~l-will ~e.r~viewed as a plant-specific licensing action.
In addition, Zion 2 is ~ls~ re~uested to confinn the pl ant-speci fie appl icab11 ity of Topical Reports BAW-2178P and BAW-2192P and submit a request for approval of the topical reports as the basis for compl 1ance with 10 CFR Part 50, Appendix G, Paragraph IV.A.1. The review will be a plant-specific licensing action.
All PWR PMs are requested to use the date of the closeout letter as the licensing ac~ion complete date. Please enter the date in WISP.
I will provide guidance on the implementation complete date shortly after the 30-day responses are received and EMCB detennines that they are acceptable.
As noted in the 1 etters, there *will be some p 1 ant-speci fie fo 11 owup effort which 1s the result of (but not part of) the GL 92-01 effort. I request that the PMs 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. The NRC considers all of the material contained in the attached files to be public infonnation *. References considered proprietary by the licensee will be so designated.
All Region III Project Directors April 15, 1994 EMCB expects to provide similar closeout letters and tables for other Pressurized Water Reactors by April 29, 1994. Please contact me if you have any questions. This memorandum with its enclosurt!S is on the LAN (Filename:
S:\\MPAB-120.REG3) with the exception--of the tables. Each PM is to use the appropriate tables for his/her plant(s) which are provided with their project director's copy of this memorandum.
Enclosures:
- 1. List of Plants
- 2. Closeout Letter
- 3. Nomenclature and Tables cc w/enclosures 1 and 2:
ADPR/NRR S. Varga J. Roe D. Crutchfield DRPE/DRPW Assistant Directors Region Ill Project Managers
.Technical Assistant, DRPE Technical Assistant, DRPW
~el 'G4c~W~Manager Lead Project Manager - MPA B-120 Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
. GENERIC LETTER CGLl 92-01 REVIEW STATUS GROUP 1; PLANTS WITH NO OPEN ISSUES Plant Braidwood 1 Braidwood 2 *. '
Byron 1 Byron 2 Callaway D.C. Cook 1 TAC Number M8343d'
- Ma3437*
M8344!.
M8344~'
M83449' M8345Y M8345ft M8373Z M83474i M8349* -*
M83499 M8350()'
i. i D.C. Cook 2 Davis-Besse*
Kewaunee Palisades Prairie Island 1 Prairie Island 2
.Zion 1** *
.f.. M83744
'~.
INSERT 1 (FOR PLM.TS WITHOUT _THE:_SY~BOt ***>..
ENCLOSURE 1
- . f. ~ !...;
We request that you verify that the information you have provided for your*
facility(ies) has been accurately entered in the summary data files.
No response is necessary unless* an inconsistency 1s identified~ If no *coniilents are received within. *30 days from the date of this letter, the staff will consider your actions related to Gl"'92-0l~ Revision*!, to be_ complete and the staff will use the information ln 'fhe tables for future NRC assessnients of
. your reactor pre~sure: vesse 1 *
.INSERT l*
(FOR ZION 1 and DAVIS-BESSE)
- Ir.-.<
We request that, within 30 days, you provide confirmation of the plant-specific applicability of the Topical Reports BAW-2178P and BAW-2192P and submit a request for approval of the topical reports as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G, Paragraph IV.A.I.
To demonstrate that the topical reports are applicable to (Zion 1 or Dav1s-Besse), you must compare the limiting material properties for the (Zion-1 or Davis-Besse) vessel to the values reported in the topical reports. This review will be a plant-specific licensing action.
We further request that you verify that the information you have provided for your facility has been accurately entered in the summary data file. If no co11111ents 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 applicability of the topical reports and request for approval are received, the staff will* consider your actions related to GL 92-01, Revision 1, to be complete.
- GROUP 2; PLANTS REQUIRING APPIIIONAL PATA IO CONFIRM THAT THE USE AT EOL IS GREATER THAN 50 FT-LB Plant Zion 2
... ;i TAC Number M83745
- INSERT 2 for 21 on 2 *
- We request that, within 30 days, you provide confirmation of the plant-specific applicability of the Topical Reports; BAW-2178P and BAW-2192P and submit a request for approval of the topical reports as a bash for demonstrating compliance with 10 CFR Part SO, Appendix G, Paragraph IV.A.I *
. To demonstrate that the to.pi cal. reports are appl 1cable to* Zion* 2, you must.
compare the limiting material properties of the* Zion 2 reactor vessel to the.
values reported in the topical reports.
In addition, we have determined that additional data 1s required to confirm that the USE at EOL for forging ZV3855 1s greater than SO ft-lb because you have provided a generic mean value for the unirradiated USE from four similar forgings. This value does-not consider material var1ab11 ity among the forgings.
When the unirradiated USE for a particular forging has' not been determined, you can set the USE equal to-the lower tolerance limit calculated*
for the group of similar forgings.
The unirradia-ted* USE should be determined such that there exists 951 confidence that at least 9SI of the population 1s *.
greater than the lower tolerance limit. If the lower tolerance limit results in a projected USE.at EOL of 1 ess than SO ft-1 b, than you must demonstrate, in accordance with Appendix G, 10 CFR Part 50, that lower values of USE w111 provide margins of safety against fractu~e equivalent to those required by Appendix G of Section III.of the American* Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code).
We request that you submit with 30 days a schedule for performing these analyses.
- Further, we request that you verify that the information you have provided for your facility has been accurately entered in the sunnary file.
If no connents are made 1n your response to this request, the staff will use the information in the tables for future NRC assessments of your reactor pressure. vessel. Once your response 1s 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.
When your analyses are submitted, they will be reviewed as a plant-specific licensing action.
Docket No. (s)
[LICENSEE ADDRESSEE]
Dear [NAME]:
SAMPLE LETTER FOR CLOSEOUT OF GL 92-01
[DATE]
ENCLOSURE 2
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 its. review, the staff has determined that [ut11 ity] has provided the information requested in GL 92-01.
- The GL 1s 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 previou'sly docketed=
information, is being used to confirm that licensees satisfy the requirements and conmitments necessary to ensure reactor vessel integrity for their facilities.
A substantial amount.of information was provided tn response* to GL 92-01, Revision 1. These data have been entered into a computerized database designated the Reactor Vessel Integrity Database (RVID).
The RVID contains
_the following tables:-. A pressurized thermal shock (PTS) table for PWRs, a pressure-temperature limits table for BWRs and an upper-shelf energy (USE) table for PWRs and BWRs. provides the PTS 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 and RT ta evaluations.
- These data were taken from your response(s) to GL 92-01 ana previously docketed information. 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..
Enclosures:
- 1. Pressurized Thermal Shock Table(s)
- 2. Upper-Shelf Energy Table(s)
- 3. Nomenclature Key cc w/enclosures:
.. See next page Sincerely, Project Manager PD/Branch Division Office of Nuclear Reactor Regulation
Nomenclature and Tables
PRESSURIZED THERMAL SHOCK ANQ USE TABLES FOR All PWR PLANTS NOMENCLATURE Pressurized Thermal Shock Table Column 1: Plant name and date of expiration of license.
Column 2: Beltline material location identification.
Column 3: Beltl ine 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 submitJal (Gl 92-01, PTS, or P/T limits submittals).
Column 5: Unirradiated reference temperature.
Column 6: Method of determining unirradiated reference temperature (IRT).
Pl ant-Soeci fic Th1s indicates that the IRT was determined from tests on material removed from the same heat o.f -the-beltltne material.
MTEB 5-2 This indicates that the unirradiated reference temperature was determined from following MTEB 5-2 guidelines for cases where the IRT was not determined using -American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Sect ion 111, NB-2331, methodo 1 ogy.
Generic Th1s indicates that the unirradhted reference temperature was determined from the mean value of tests on material of similar types.
Column 7: Chemistry factor for irradiated reference temperature eva 1 uat ion.
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 Th1s indicates that the chemistry factor was determined from surveillance data via procedures described in RG 1.99, Revision 2. -
- 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 Pata 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 Pata 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:
Column 2:
Column.3:
- Plant name and date. of expiration of license.
Beltline material location identiftcat1on.
Beltline material heat number; for some welds that a single-wire or tandem-wire process has been reported," (S) ind1cat.es
- single wire was used in the SAW process.
(T) indicates tandem.
. wire was used in. the SAW process~
- Column 4:. Material type; plate types includ~ A-5338-1,*A 3028, A 3028 Mod., and.forghig A *so8~2; weld types include SAW welds using Linde 80, 0091, 124, 1092, ARCOS-BS flux, Rotterdam welds using Graw Lo, SMIT 89, LW 320, and SAF 89 flux, and SMAW Column 5:
welds using no flux.
EOL upper-shelf energy (USE) at T/4; calculated by using the EOL fluence and either the cooper value or the surveillance
~
data.
(Both methods are described in RG 1.99, Revision 2.)
IMA This indicates that the USE issue may be covered by the approved equivalent margins analysis in the B&W Owners Group Topical Reports:
BAW-2178P and BAW-2192-P.
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 reported in the latest submittal (GL 92-01, PTS, or P/T limits submittals).
Column 7: Unirradiated USE.
fl!!!
- This indicates that the USE issue may be covered by the approved equivalent margins analysis in the B&W Owners Group Topical Reports:
BAW-2178P and BAW-2192P.
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 unirradiat~d USE was from test date.
ill This indicates that the unirradiated USE was 651 of the USE from a longitudinal specimen.
Generic This indicates that the unirradiated USE was reported by the licensee from other plants with* similar materials* to the
- beltline material.
NRC generic This indicates that the unirradiated USE was derived by the staff from other plants with similar materials to the beltline mater~al.
- 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 numb.er.
Equiy. to Surv. Weld This indicates that the unirrad1ated 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.
Summary File for Pressurized Thermal Shock Plant Beltllne Heat No.
ldent.
ID Neut.
IRT..
Name I dent.
BraidNood Lowr t
Nozzle EOL:
10/17/
2026 Belt Forging Upper Shell Foraina Lower Shell Forafna WF645 Upper Clrc. Weld Fluenc:e at EOl/EFPY 5P*7016 49C344*1*1 3.03!19
/490313 490867*1/
49C813*1 H4491 3.03E19 WF562 442011 3.03E19 Middle Clrc. Weld WF653 31401 1.OOl17 Lower Clrc. Weld R1f1rencn 40*,
Method of Detel'llln.
IRT-Plant Specific Plant Specific Plant Specific Plant Specific Plant Specific Plant Specific Che11latry Factor 26 31 20 41 41 150.1 Method of Detel'llln.
CF Table Table Table Table Table o.o4 0.71 0.05 0.73 0.03 0.73 0.03 0.50 0.03 o.65*
0.19 0.56 Ch.. tcal c...-isftfona and initial RT.. date for ell.. terfala are fra11 the July 2, 1992 Letter fr1111 M.A. Jackson to T.E.
Hurley, s~Ject: Brefdwood Stetfon, Unf~a 1 *and. z.
Fluence data are frm WCAP-12685, *wlyafa of capsule U fr1111 the Coimarwealth Edison CGq*'IY Braidwood Unit 1 Reactor.
Vea.. l Surveillance Progr..,* A&.vuat, 1990. "'
~ ~:-..
Su11111ary File for Upper Shelf Energy Plant N-Beltline HHt No.
M*teri*l 1/4T USE 1/4T Unirr8d.
Method of Jd8nt.
Type
- t.EOL Neutron USE Deten1fn.
Fluence *t Unirr8d.
EOL usr Br*fdwood Lower 5P*7016 A 508*3 145 4.09!11 162 Direct 1
Nozzle Belt For11ir'9 EOL:
Upper 49CJ44~1-1 A 508*3 9J 1.66E19 111 Direct 10/17/
Shell
/49DJ&J 2026 Forging Lowr 490867*1/
A 508*3 117 1.66119 136 Direct Shell 49Cl13*1 Forafne WF-645 H4491 Linde 80, 7'5 4.09!11 87 Direct Upper SAW Circ. Weld WF*562 44201l Linde 80, 55 1.66119 70 Direct Middle SAW Cfrc. Weld WF-653 31401 Linde SO, 63 6.0GE16 79 Of rect Lowr SAW Clrc. Weld Blf!C!IDSD WS! d8t* for P,llte 49DCJ44*1*1i49DJ&J*1-t *re. fram th* July z; to T.E. ~ley, 5'.Gj~t: Br1idwood St1tton, Unit 1 8lld z...
1992 tett*er:. froif'M.~~.IKtaon Fluence d8te *r* fr* WCAP*12615, *wlysi1 of taplule U fr* C~lth Edison COlllplifty Br1idwood Unit 1 R*Ktor. v... el SUrvefllence Pr.oar*,* August 1990.
WSE d8t1 for the r-ining *terf*l* ire f.-- the Novelllber 19, 1993 letter fram T.w. Stq*in to T.E. Murley, * *** Br1fdwood St*tion Unit* 1 8lld Z, Response to*R~t for Addftfonel lnfol'lllltion R918rdfng UC Generic Letter 92*01.
EGL USI for... ld Vf-653...a calcul1ted 1aing RG 1.99, Rev. 2 *thodology.
Sunnary File for Pressurized Thermal Shock Plant Bel tl fne HHt Ito.
ID lteut.
IRT-Method of Ch*fstry Method of XCu Xllf Name
. !dent.
ldent.
Fluence at
- Dtttnaf n.
Factor Detenafn
- EOL/EFPY
!RT-CF Braidlilood Lower 5P*7056 6.82£18 30°F Plant 26 Table 0.04 0.90 2
Nozzle Specfffc Belt Forafna EOL:
Upper 490963*1*1 3.03£19
.3o*F Plant 20 Table 0.03.
0.71 12/18/
Shell
/495904*1*
Specfffc 2027 Forgir,g 1
Lower 500102*1*1 3.03E19
- 30°F Plant 37 Table 0.06 0.75 Shell
/50C97*1*1 Spscfffc For11in11 Upper H4498 6.82£18
- ]O*f Plant 41 Table 0.03 0.50 Cfrc. Weld Saec:fffc Middle 442011.
3.03E19 40°F.
Plant 41 Table 0.03 0.65 Cfrc. Weld Saec:f ffc Lo.,.r 1084*18 1.00E17
- 16°F Plant 54 Table
. 0.04 0.6 Clrc. Weld Specfflc WF*696 R!f!C~a Ch*fct1l c~ltlon and fnf tfel RT., dllt* for ell.. terfels ere frOll the Ju(y*2, 1992 letter frOll M.A. Jackson to T.E.
Murl9Y,
Subject:
Braidwood. Stetfon, unft 1 an 2 ***
Fluence dllte ere frOll WCAP*12845, *Anelysfs of ~le U fre111 the Comoiwlth Edfson Coqieny Brefdwood Unit 2 Reactor VesHl survefllenc* Progr*,* March, 1991.
c}.*.
Sunrnary File for Upper Shelf Energy Plant N-Beltltne Hqt No.
Materiel 1/4T US1!
1/4T Untrred.
Method of I dent.
Type et EOL Neutron USI!
Deten1i n.
Fl'*'Ce et Untrred.
EOL use Braidwood Lowr..
5P*7056 A 508*3 115 4.09!11 121 Direct 2
Nozzle Belt Forging EOL:
Upper 490963*1*1 A 508*3 94 1.66119 119 Direct 12/18/
Shell
/495904*1*
2027 Forging 1
Lower 500102*1*1 A 508*3 124 1.66119 150 Direct Shell
/50C97*1*1 For11ir,..
Upper "4491 Linde ao, 75 4.09!11 17 Direct Circ. Weld SAW WF645 Middle 442011 Linde 80, 55 1.66119 70 Direct Circ. Weld SAW Wf*562 Lower 1084*11 Linde SO, 63 6.00l16 71 Direct Ctrc. Weld SAW WF*696 B1f1cmsa LUSE date for plate 490963*1*1/495904*1*1 ere frOll the July Z, 1992 letter frOll... A. Jackson to T.E. Murley, Sl.Dject: Braidwood Statton, Units 1 end z...
Fluence data ere frOll WCAP*12845, *Mlilyala of Cepaule U frOll the C.>9Nwlth Edison COlllPMY Braidwood untt Z Reactor Vnael Surwillence Protr*,' March 1991.
LUSE data for the r-lnlng *tertela ere frOll the llCMllber 19, 19'] letter frOll T.w. Sh1plttn to T.E. Murley, * *** Braidwood Statton untta 1 end 2, Reaponae to R~t for AdcHttonel lnfo,...tion Retarding UC Generic Letter 92*01.
EOL USI! for weld WF~696.... *calculated using RG 1.99, Rev. Z *thodology. *
~-
- *..i *i**"****--.."'
Sunmary File for Pressurized Thermal Shock Plant Belt l lne HHt No.
ID Neut.
IRT_
Method of Chemistry Method of XCu XIII N-I dent.
I dent.
Fluence at Deten11n.
Factor Deten1ln.
EOLiEFPY IRT-CF Byron 1 Lower 123J211 2.159!19 30*,
Pl Mt 31 T8ble o.os 0.72 Nozzle Specific Belt Forging EOL:
Int. Shell 5P*5933
- 2. 159£19 40*F Pl Mt 31 T8ble o.os 0.73
. 10/31/
Forging Specific 2024 Lower 5P*5951 2.159£19 1o*F Plant 26 T8ble 0.04.
0.64 Shell Specfffc Forging WF*501 442011 2.159!19 1o*F Pl Mt 41 T8ble 0.03 0.63 Upper Specfffc Circ. Weld WF*336 442002 2.159£19
- ]O*F' Pl Mt 41 T8ble 0.03 0.46 Mf ddle Specfffc Clrc. Weld WF*472 31401
,.1.00E17 10*F Plant 164.65 T8ble 0.23 0.57 Lower Speclffc Clrc. Weld B1f1cm:s11 Ch*fcal c~ltlon end fnltlal RT-data are frcm the July 2. 1992 letter frcm M.A. Jackson to T.I. Murl..,, ~l.Dject:
Braidwood Station, unit 1 end z ***
Fluence data are from WCAP*13UO, Analysis of capsule x fr* the C~lth E~laon c~
lyron ~It 1 Reactor vessel Surveillance Progr*,* January,.1994
- Su11111ary File for Upper Sh~ 1 f Energy Plant N-Beltl_lne Heat No.
Material 1/4T USE 1/4T Unlrrad.
Method of ldlnt.
Type at EOL --
Neutron use Detel'llln.
Fluence at Unlrrad.
EOL USE Byron 1 LOtMr 123J211 A 508*2 11 t 1.179£19 131 ----
Direct Nozzle Belt Forging EOL:
Int. Shell 5P*5933 A 508*2 111 -
1.179£19 131 Direct 10/31/
Forging 2024 Lower 5P*5951 A 508*2
.120 1.179£19 150 Direct Shell Fora Ina WF*501 442011 Linde 80, 63 1.17'9!19 73 Direct Upper SAW Clrc. Weld Wf*336 442002 Linde 80, 60 1.179£19 74 Direct Middle SAW Clrc. Weld Wf*472 31401 Linde 80, 64 6.00!16 72 Direct Lower SAW Clrc. W.ld B1f1cm:sn WSE 'date for forging 5P*5933 are frcm the July 2, 1992 letter frcm... A. Jackson to T.E.
Murley, SW:IJect: Braidwood Station, Uni ta -1 and 2. _
Flu.nee data are frcm WCAP*13UO, Analyala of Cepsule X fr* the eo.in..ltta Edison COlllpM'f Byron Unit 1 R~actor VeaMl 5urvefll1nee Progr*,* Janu1ry 1994.
WSE date for the welda end Initial 11_ for weld Wf*501.-are fr* the NOWll!ber 19, 1993 letter frm T.W. s1.-1n to T.E. Murley, * *** Braidwood Station Unfta 1 end 2, R~
to R~t for Additional Information R.Prdlng NRC Generic Letter 92*01.
EOL USE for weld Wf*472 wu calculat1Cfuafng RG 1.99, Rev. 2 *thodology. EOL USE for weld Wf*336 wn calculated uafng RG 1.99, Rev. 2 uSU1lng the lower lfaltlng value of 0.51 cu. for welda.
WS! data for forgings 123J218 end 5P*5951 are fr* WCAP*11651, *Analyala of t.psule U frm the Coaaor...alth Edfaon Co. Byron Unit 1 Reactor v.... l Redlatlon lurwfll..:e Progr*,* Nov.mer, 1987.
EOL USE values for the forgings were calculated using RG 1.99, Rev. 2 and the lowr l hitting value of o.11_cu for platea end forgings
- Su11111ary File for Pressurized Thermal Shock Plant Beltllne H.. t Mo.
ID Neut.
11n_
Method of Ch*latry Method of XCu XNf N-I dent.
I dent.
Fluenc* et Detenain.
Fector Detenafn.
EOL/EFPY IRT-CP Byron 2,
Lower 4'*6107 6.82!11 1o*F Plant 31 Teble 0.05 0.74 Nozzle Specific Belt Fora Ina EOL:
Upper 490329*1*1 3.03£19
-2o*F Plent 20 Teble 0.01 0.70 11/6/.
Shell
/49C297*1*
Specfffc 2026 Forafna 1
Lowr 490330*1*1 3.03E19
-20*,
Plent 31 Teble 0.05
. 0.73 Shell
/49C291 Specific Foralna WF*S62 442011 6.12111 4Q*F Plent 41 Teble 0.03 0.65 Upper Specfffc Clrc. Weld WP*447 442002 3.03!19 1o*p Plent
- 61.
Teble D.05 0.62 Middle Specific Clrc. Weld WF*614 31401 1.00l17 40*p Plant 144.4 Teble
- o. 11 0.54 Lowr Specfffc Clrc. Weld B1f 1cmsa All ch*lcal composition and Initial u_ data are from the July 2, 1992 letter fr* M.A. Jaclcaon to T.E~...,.Ley,
Subject:
Bralca.ood Statton, Units 1 and 2.
Flu.nee data are from WCAP*12431, *wlY.ta*of Capsule U from the C_,....lth Edison CCllllPMY lyron Unft.2 Reactor Veuel Survel llence Progr*,* October 1919.
EOI. USE values for the RG 1.99, Rev. 2 end the lower l lmftfnt velue of 1.17.
Cu for plat* end fof'9fnp.
Fluence data for weld WF*614 fa from the J.,..ry 17, 1916 letter from G.L AlUander to H.R~ Denton, subject: Zion Statton unf ta 1 and 2; Byron Statton Unfta 1 end 2; lraldwood Statton Unf ta 1 end 2; Pressurized The,...l Shock
- Su11111ary File for Upper Shelf Energy Plant N-Beltl fne HHt No.*
Materfal 1/4T USE 1/4T Unlrrad.
Method of ldlnt.
Type at EOl Neutron USE Detenafn.
Fli.nce at Unfrrad.
EOl USE Byron 2 Lower 4P*61D7 A 508*2 131 4.D9E18 155 Df rect Nozzle Belt Forgfng EOl: 11/6/
Uppier 490329*1*1 A 508*2 117 1.66E19 149 Direct 2026 Shell
/49C297*1*
Forgfng 1
Lower.
490330*1*1 A 508*2 99 1.66E19 127 Direct Shell
/49C291*1*
Forafna 1
WF*562 442011 Linda 80, 60 4.D9E18 70 Ofrect Upper WI Clrc. Weld WF*447 442002" Lfnda 80, 53 1.66119 67.
Direct Middle WI Cf re. Weld Wf*614 31401 Lfnda IO, 67 6.00l16 74 Direct Lower WI Clrc. Weld Blf !CDD UUSE dat* for forgfnga 490330*1*1/49C291*1*1 are fra11 the July 2, 1992 letter fra11 M.A. Jackson to T.E. Murley, SWject: Brefdwood Station, Unfta 1 end 2.
Fl~* date; ~
UUSE. date for for9lnga 4P*6107 end 490329*1*1/49C297*1*1 ere fra11 WCAP*12431, "Analysis of Cepsul* u fra11 the C~lth Edfaan Collpeny Byron Unit 2 Reactor v.... l Surveillance Progr*,* October 191t. EOl USI values for the forgfnga...,.. calculated usfng RG 1.99, Rev. 2 end th* lower l i*itfng value of 0.11 CU for plat* end forgfnga.
UUSE date for the wldl.,.. fra11 the lovamer 19, 1993 Letter froii T.W. Simpkin to T.E. Murley,
- *** Braidwood Statton Unit* 1 end 2. Response to R...-t for Addftionel lnfo,...tfon Regarding NRC Generic Letter 92*01. EOl USI for wl~ Wf*614 wu calculated using RG 1.99, Rev. 2
- thodol_ogy.
Fl~* date for wld Wf*614 fa fra11 the.J.,..ry 17, 1986 letter fra11*G.L Alexender to H.R.
Denton, s~ject: Zfon Station units 1 end 2; Byron Station Units 1 end 2; Prnaurized Thermal Shock
- Su11111ary File for Pressurized Thermal Shock Plant Beltltne Neat No.
ID Neut.
1u_
Method of Ch*latry Method of ICu XMI N-I dent.
ldlnt.
Flu.nee et Deten1ln.
Factor Deten1ln.
EOl/EFPY IAT-CP Cellew.y Int. Shell 2.39119 4o*p Plent 26
. Teble 0.04 0.57 1
A2707*1 sa.etftc EOL:
Int. Shell 2.39119 10*,
Plent
.. 31 Teble -
0.05 0.59 10/18/
A2707*2 Specific 2024 Int. Shell 2.39119
-1o*p Plent 37 T.eble 0.06 0.61 A2707*3 Smcfffc Lower 2.39E19 50*,
Plent
- 26. 13'.-~*
~l'~lated 0.07 0.59 Shell Specific A27.oa*1 Lower 2.39119 1o*p Plent 31..
Teble....,.
0.05 0.57 Shell Specific A2708*2 Lower 2.39Et9 zo*p
.\\*.,
Phint 44
- ;Teble 0.07 0.59 Stiel l Specific A2708*3 Int. and 2.39119
- 6Q*p Plent 29.7 Teble 0.04 0.06 Lowr*.
Specific Shell Axial Welda G2.0J Int. to 90077,.
2.39119
'*6Q*p Plent 56.144 calculated o.~
0.07 Lower Specfffc Shell Clrc. Weld EJ.14 B1f 1rn11 Chemical Coq)Olftfon and IRT;,. are from Table A*3 of R.G. Lott, et.al, *Analysfa of Cepaule U from the Union Electric CGq)My Call..._y Unit 1 Reactor v... el Aedfatfon SUrwfllence Progr*,** WCAP*11374, Awfafon 1, W.Stlnghouae Electric Corporation, Pittsburgh, PA 15230, J...- 1917.
No heat rustler* were a~l fed for the shell and lnteNldlate and lowr uflil shell welds.
Fluent* data ere froie Table 6-14 of wi:AP-12946 and Oecllliler 11, 1991, letter from D. P. Schnell CUECo> to USNAC DOCUDent Contro.l Deak, subject: Aevf1fon to Technical Specification 3/4.4.9 Pr.. aure T1111peratUl'e Ll*fta.
Sunnary File for Upper Shelf Energy Plant N-Beltl lne Heet No.
.._terlel 1/4T USE 1/4T unlrred.
Method of ldlnt.
Type at EOL Neutron USE Deter11tn.
Fluence at unlrred.
EOL USE CallaN8y 1 Int. Shell R2707*1 A 5338*1 62 1.435E19 78 Direct EOL:
Int. Shell R2707*2 A 5331*1 79 1.435E19 100 Direct 10/18/
2024 Int. Shell R2707*3 A 5331*1 79 1.435E19 99 Direct Lower R2708*1 A 5331*1 65 1.435E19 az Direct Shell Lower R2708*2 A 5331*1 a
1.435119 105 -
Direct Shell
- Lower R2708*3 A 5338*1 80 1.435119 101 Direct Shell Int. and Not Not 113 1.435E19 143 Direct Lower provided provided Shell Axlel
- Welda,
~ '
G2.03 Int. to 90077 Linde 124, 87 1.435119 112 Direct Lowr SAW Shell
~..
Clrc.
'.1;*
- Weld, El.14
. :"'..;-* ~*..,
.T '*;,
Blf ICIDSD J
WSE dete ere fr* Teble A*3 of R. G. Lott et el, *wl.,Sls of Cepsule U fr* the union Electric CGq)MY CelllN8Y unit 1 Reector v.... l Redletfon SUrvefllance Progr*,* WCAP*11374,
- Revision 1, W.Stlnghouse Electric Corporetlon, Pittsburgh, PA 15230,,,.... 1917 Fluence dete ere fr* Teble 6*14 of WCAP-12946 Md Decllllber 18, 1991, letter fr* D. f. Schnell CUECo) to.USIRC Doamnt Control Desk, ujects Revision.to Tec:hnlcel Spec:fflcetlon 3/4.4.9 Pressure T~eture Ll*fta
- Sunmary File for Pressurized Thermal Shock Plant Beltlfne N*t No.
ID Neut.
IRT-Method of Che111I a try Method of xcu XIII I dent
- ldent.
Fluanc:e *t.
DettMlln.
Factor DeteMlln.
EOL/EFPY IRT-Cf D. C.
Nozzle C3594 1.41E19.
- 2*F MTEI 5*2 93.1 Table 0.14 0.46 Cook 1 Sllel l 84405*1 EOL:
Nozzle C3594 1.41E19 34*f MTEB 5*2 93.25 Table 0.14 0.45 10/25/
Shell 2014 84405*2 Nozzle
. C3812 1.41E19 40*,
MTEI 5*2 94.6 Table 0.14 0.41 Shell 84405*3 Int. Shell C1260 1.41E19 5*,
Pl1nt 81.4 Table 0.12 0.52 84406-1 S-.elffc Int. Shell C3506 1.41E19 JJ*f Pl1nt 104.5 Table 0.15 0.50 84406*2 s-.elflc Int. Shell C3506.
1.41E19 40*,
Pl1nt 102.94 calculated 0.15 0.49 84406*3 SDKlflc Lowr C3929 1.41119 za*,
Pllnt 91.1'5 Table 0.14 0.55 Shell Specific 84407*1 Lowr C3932 1.41E19
-12*,
Pl1nt 82.1 Table 0.12 0.59 Shell Specific-*
84407*2 Lowr C3929 1.41119 31*,
Pl1nt 95.5 Table 0.14 0.50 Shell Specific
.r, 84407-3 Nozzle 13253 1.41E19
-56.,
Generic 206.4 Table 0.27 0.74 Shell and Axlel 1zooa en.
Welda 1-442 Nozzle/
20291 1.41119 Generic 232 Table 0.35 0.74 Int. Shell Clrc. weld 8*442 Int. to 1P3571.
1.41119 Generic 219 Table 0.31 0.74 Lo..er Shell Cfrc~ weld 9*442 Int. Shell 13253 1.41!19 Generic 206.4 Table 0.27 0.74 Axial and Welda 12008 (T) 2*442A/C LCMtr 13253 1.41E19
- 56.,
Generic 206.4 Table 0.27 0.74 Shell and Axial 12ooa en Welda 3*442A/C
Sunnary File for Pressurized Thermal Shock Plant Belt line HHt No.
ID Neut.
IRT-Method of Ch*i1try Method of xcu XNf II-I dent.
,.,t.
Flu.nee et Oeten1fn.
Fec:tor Deten1fn.
EOL/EFPY
!RT-CF B!lf!IC~ll D.C. Cook 1 All date except u noted below were from the July 13, 1992 letter from E.E. Fftzpetrfct to T.E. Murley, "Donald c. Coat Nuclear Plant Units 1 and 2 *** Generic Letter 92*01, Revision 1, Reactor v.. ael Structural Integrity.*
Infol'lll9tfon regerdlj,g chemical c~ftfon, fnftfel ar_ Ind *thodology of deten1fnetlon for the WSI! for the weldl.,...
from the Novemer. 29, 1993 letter from E.E. Fitzpatrick to T.E. Murley, "Donald c. Coolc Nuclear Plant Units 1 end 2 ***
Response to Request for Additional Info,,.tlon for Generic Letter 92*01, Revision 1.*
110 velue for I cu of weld 8*442 wea provided, therefore the default value of 0.35 waa used.
The WSI! valuee for weldl 1*442, 2*442 end 3*442 represent an llRC staff calculated average of o.c. Coolc Ind Slater plant data (McGuire, Unit 1 end Dleblo Canyon, Unit 2> for weld
... 1 re huts containing heat nos. 13253 end 12008 *.
~-
- '-.;Qr f.*,-
Sunmary F;le for Upper Shelf Energy Plant N-Belt line Heat No.
Material 1/4T USE 1/4T untrrad.
Method of I dent.
Type at EOI.
Neutron USI Deten1fn.
Fl..nc:e at Unf rrlld.
EOL.
usr D. C. Cook Nozzle C3594 A 5331*1 61 8.47118 87 651 1
Shell 84405*1 EOI.:
Nozzle C3594 A 5338*1 72 8.47118 92 651 10/25/
Shell..
2014 84405*2 Nozzle C3872 A 5331*1 63 8.47111 ao 651 Shell 84405*3 Int. Shell C1260 A 5331*1 66 8.47!18 a
Dfrect 84406*1 Int. Shell C3506 A 5331*1 74 8.47!18 96 Dfrect 84406*2 Int. Shell C3506 A 5331*1 76 8.47!18 91 Dfrect**
84406*3 Lower Shell C3929 A 5331*1 ao 8~47!11 103 Dfrect B44D7*1 Lower Shell C3932 A5331*1 101 8.47118 126 Dfrec:t B44D7*2 Lower Shell C3929 A 5331*1 84 8.47!18 108 Dfrect B44D7*3 Nozzle 13253 Linde 66 8.47!11 108 NRC Shell Axfel end 1092, SAW Generic Welda 1200I (T) 1*442 Nozzle/int.
20291 Lfnde
.-. (14 8.47111 no Slater Shell Cfrc.
1092, SAW Plant Weld 9.442*
Int. to tp~n*
Lfnde
,6_1
- 1.47111 105 Slater Lower Shell 1092, SAW" Pl1nt Clrc. Weld, 9*442 Int. Shell 132" Linde 66 8.47118 108 NRC Axf*l Welda end 1092, SAW Generic 2*442A/C 1200I (T)
LOMer Shel l 13251 Linde 66 8.47111 108 NRC Axf*l Welda end 1092, SAW Generic 3*442A/C 12008 (T)
- -*~*I'..
Plant 11-Beltlfne ldlnt.
Befer!QCD o.c. Cook 1 Su11111ary File for Upper Shelf Energy Hut 110.
Material Type 1/4T USE at EOL 1/4T Untrred.
Neutron USE Fl~* et EOL Method of Detenain.
Unfrred.
USE All data except u noted below... re frcm the July 13, 1992 letter frcm E.E. Fltzs-trtc:k to T.E.
Murley, "Oonald c. Cook lluc:lear Plant Untta 1 and 2 *** Generic: Letter 92*01, Revision 1, Reactor Vessel Structural Integrity.*
lnfoCllatlon regarding wsr and Mthodology of detenalnatton for the WSE for the.,.lda ere frcm the llOV!llber 29, 1993 letter frcm E.I. Ff tzs-trtc:k to T.E. Murley, -Donald c. Cook lluc:lear..
Plant Units 1 end 2 *** Response to R~t for Additional lnfonnatlon for Generic Letter 92*01, Revision 1. llo value for l cu of... ld 8*442 wu provided, therefore the default value of D.35 wu used.
The wse valun for... lda 1*442, 2*442 and 3*442 repreunt the lllC ataff c:alculeted average of o.c. Coot and Slater Plent data <McGuire, Unit 1 and Dlablo Cenyan, Unit 2) for weld wire huts containing heat nos. 13253 end 12008.
- "'I *.
- The WSE for welds 9*442 ta from WCAP-12119, *wlyata of the Maine Yri* Ructor v.... l Second Wall Capsule located at zs3*,
- Mardi 1991 *
. The WSE for welds 8*442 ta from WCAP*10786, the Report f~ SUrvetllance capsule U from McGuire Unit 1.
Su"'11ary File for Pressurized Thermal Shock
- Plant Bel tl tne Heat Mo.
ID Neut.
IRT..
Method of Ch*tatry Method of ICU XNt I dent
- ldent.
Fluence It 01terwtn.
Fector Deterwtn.
EOL/EFPY IRT-CF
- o. c.
Int. Shell C5556*2
- 1. 71E19 sa*F Plent 108.9 Tmble 0.15 0.51 Coote 2 10-1 soec:tffc EOL:
Int. Shell C5521*2 1.71!19 38*f Plent 102.61 calculated 0.14 0.51 12/23/
10*2 Specific 2017 Lowr C5540*2
- 1. 71!11
-20*,
Plent 74.6 Tmble
- o. 11 0.64 Shell Spectftc 9-1 Lowr C5592*1
- 1. 71E11
-2o*F Plant 100 Tmble 0.14*
0.60 Shell Spectffc 9-2 Int. Shell 53916 9.02!11
.35*,
Plant 64.4 calculated 0.05 0.91 Axt al Specfffc Welda Lowr 53916 6.63E11
- J5*F Plant-
. c 64.4 calculated 0.05 0.91 Shell Spectftc:'-.
- , *f Axt al Welda Ctreu1.
53916 1.71119
.35*,
Plant 64.4 calculated 0.05 0.91 Weld SOectftc Blf1cm:sa lntttal RT-and ch*tcal c~ttton for the plet* and are from th*.luly 13, 1992 letter frm E.E. Fttzpatrlck to J.E.
Murley, -Donald C. Cook MuclHr Plant 1Jntt1 1 and 2 *** Genertc Letter 92*01, levfafon 1, Rnctor V*nl Structural lntegrtty.*
Updated fluenc:.., ch*tcal c~ttton, tnttt*l RT-and calcul1ted ch*t*try factors are frm the Aprtl 12, 1993 Lett.,.
- from E.E. Fl tzpatrtck to T.E.* Murley, -Donald C. Cook Nuclear Plant untt 2 *** Updated Reference Tmperature and Preuurtzed The,...l Shock Anllyaee.*
SuD1Dary File for Upper Shelf Energy.
Pl1nt N-Beltl tne Heat No...
Material 1/4T USE 1/4T Unlrrad.
Method of ldlnt.
Type at EOl Neutron USI!
Detel'lltn.
FlUlnCe at Unlrrad.
~.: ~...
EOl USI!
D. C. Cook Int. Shell C5556*2 A 5338*1 67.5 1.02£19 90 Direct 2
10*1 Ea&.:
Int. Shell C5521*2 A 5331*1 58.4 1.02119 86 Direct 12/23/ -
10-2 2017 Lowr Shell C5540-2 A 5331*1 aa.1 1.02119 110 Direct 9-f Lowr Shell C5592*1 A 5331*1 71.4 1.02119 103 Direct 9-2 Int. Shell S3986 Linde 124 64 5.38118 Direct Axial Wel'da SAW Lowr Shell S3986 Linde 124 65 3.95111 Direct*
AXtal Welds SAV
r Clrc. Weld S3986 Linde 124, 62 1.02119 77 Direct SAii Blf ICDD --.
WSE data for the plat* and.,.lda are fl'Oll the July 15, 1992 letter fl'Oll I.E. Fftzpetrlck to T.E. Murl..,, "Doneld c. Coot Nuclear Pl8nt Unit* 1 and 2 *** Generic Letter 92*01, Revlalon 1, Reector v.. sel Structural Integrity.my lnfoiii.tlon regarctlng th* *ttiodology of detel'lllnetlon f.or* the Wll of-plat.. C5556-Z, C5540*2, and C5592*1 I* fro11 th* llCMll!ber 29, 1993 letter, frcm 1.1. Fftzpetrlck to T.1. Murl..,, "Doneld
- c. Cook Nuclear Plants Units 1 and 2 *** leaponae to R~t for ~ltlonel lnfol'lletlon for Generic Letter 92*01, Revision 1.
.": Updated flUlnC.. are fro11 the April 12, 1993 letter fro11 I.E. Fitzpatrick to T.E. Murl..,,
"Donald Cook lluclur Plant Unit 2 *** Updatad Reference Te11perature and Pr.. aurlzad Th.,...l Shock Analyaea.*
. - *.. /).
- -A:
Plant Beltl ine N-I dent.
Davia*
Nozzle Besa*
Belt Fora Ina EOL:
Sunmary File for Pressurized Thermal Shock HHt llo.
I dent.
123Y317 C~I 203>
ID lieut.
Fluenc* at EOl/EFPY 1.50E18 1.07!19 IRT-50*F 20.~
Method of Dete111fn.
IRT-Plant Specific Plant Ch*iatry Fec:tor 26 26 Method of ICu Oete111in.
CF Table
' 0.04 Table 0.04 0.61 0.77 Upper 4/22/2017 Shell 123X244 (AICJ 233)
Specific Forafna Lowr Shell Forging Upper/
Lowr Shell Clrc. Weld WF* 182* 1 Nozzle Belt/Upper Shell Circ. Weld (outside 911)
WF-233 Nozzle lelt/Upper Shell Circ. Weld
( fr1afde 9X)
WF*232 R1f 1cm:a 5P4086 CBCC 241) 821144 T29744 8T3914 1.07!19 1.07119 1.50111
'* *:~:--.::
50*F Plant 20.00 calculated. 0.02 0.81 Specfffc 2*F Plant C.lculated 0.24 0.63 Spec ff le Generic 203.4 Table 0.29 0.61 Generic 168.6
-Table 0.11 0.64 The ch~fcal ~Gq)09ition, flu.nee, and IRT-data are fr* July 1, 1992, letter fram D. c. Shelt*;., CTECo) to USNRC Docunent Control Dnk, al.bject: ReaponM to lllC_ ~ic L*~~~ 92*01, Revision 1, R*tCH' v.... l StructU..al lntegr_fty, for the Davia-a.... Nuclea_r,_ Powr. Station.-..
... --~~
- -**-+**
~l
.. -~.
- _r ** ;.
-.... 1*..., :.
~-,.
_.-.-=:.
Sunnary File for Upper Shelf Energy Plant N-Beltlfne Heet No.
Meterfel 1/4T USE 1/4T Unlrred.
- Method of ldent.
Type at EOL Neutron USI Deten1fn.
FlUMCe et Unfrred.
EOl USI Devfa*
Nozzle 12JY317 A 508*2 119 9.0l!17.
134 Direct BH**
Belt (ADI 203)
For11tna EOL:
Upper 123X244 A 508*2 119 6.43111 144 Direct 4/22/2017 Shell (AIC.I 233)
For11tna Lower*
5P4086.
A 508*2 1112- -
6.431!11 111 Direct Shell (BCC 241)
Fora Ina
- ..,. Linde 80~..
~_:,:~ '*..
Upper/.. :.-". 121T44
- .. 6.43111..*..
- .1~.. -.....
Dts:ect
- Lower WI Shell
- c.*v,J... Circ. Weld WF*182*1
- it*"'"'
Nozzle T29744° Linde 80,. *.
. *. --~*OEti;
.~\\
- .'P.'f: ~.~lc Belt~..-.
.. SAW i"rn****-=* *",.
Shell Circ. Weld
<outs I*
~o:.** *-
911), WF*
m Nozzle m914 Linde ID, -*
9.0l17 -*
Generic Belt/Upper SAW Shell Circ. Weld
<Inside 91), WF*
232 B1f 1cm:sa The ch*lc*l coiiposltlon, and fliance date ire frcm July 1, 1992, letter frcm D. c. Shelton
<TECO) to USNRC D~t Control Deak, 9'.Gject: Response to llRC Generic Letter 92*01, Revision 1, Reector v.... l Structur1l lnt9grity, for th* Devis*..... luclur Power St1tlon.
The WSEa for fortlnaa ADI 203, ICC 241 end AK.I 233 end weld VF*112*1 ire frcm IWl*2125, which described the -lyala of aurvelllence capsule D
- 2L1censee must confirm app11cab111ty of Topical Reports BAW-2178P and BAW-2192P
Sunmary File for Pressurized Thermal Shock Plant 8eltllne H.. t lo;*
ID lleut.
IRT-Method of Ch*fatry Method of XCu Xlf I dent.
I dent.
Fluence et Dettl'llin.
Factor Detel'llin.
EOl/EFPY IRT-CF IC~
Int. Shell 12ZX208VA1 3.21E19 6Q*F Pltnt 13.23 C.lculeted 0.06 llA (0.71) llA Forging Specific 8*6306 EOL:
Lowr 123X167VA1 3.21E19 20*,
Pltnt 13.12 C.lculeted 0.06 llA (0.75) llA 12/21/
Shell Specific 2013 Forging 8*6307 Int. to IP3571 3.21119
- 56.,
Generic 191.27 calculeted*
(0.28) llA C0.75) IA Lower Shell
~.,.. _,..
cire. Weld RtflC!DCI
-. i --..r*... ; *:,. H
~
Ch*icel coq:ioaition, fluence, h~t -~~~ ~ 1itr...;' data are fr.Giii. July -z, 1'99z* c.it9t'~fr.ait'°C~I. Steimerdt C\\llSCo> to USllRC D~t Contr:ol Dnk, s\\DJect: IC.....,.. lluclur POMar,..Plant,.Ructo.r,ve...t,Stn.ict~"l "i"nt~rity.
Meet IUllber for int. to lower shell circ.... ld from J\\a19 4, 1993 letter from C.R
- Steim*rdt (\\llSCo) to USllRC Docuim'lt Control Dnk, subject:., RHCtOI'. V~e.l $truct~el,Integrity *... **3 :*
- _*:11
,.;\\..,..,;\\
.*.* r*.
Su11111ary File for Upper Shelf Energy Plant N-Beltllne Heet No.
Meter I el 1/4T USE 1/4T unlrred.
Method of ldlnt.
Type et EOL Neutron USI Deter11I n.
Fli.nce et unlrred.
EOL USI Int. Shell 122X208VA1 A 508*2 90
- 2. 17E19 92 65X Forging 8*6306 EOL:
Lower 123X167VA1 A 508*2 95 2.17'9!19
'11 65X 12/21/
Shell 2013 Forging 8*6307
- -.**--to*.
Int. to IP3571 Linde 71
- 2. 17E19 126 Direct Lowr 1092, SAW Shell
-*i ~:..,,.
Ci i
Clrc. Weld-
~
Btftrerst
.o..<-:-:t;***
Ch*lcel c~ltlon, fluence, hqt...-...., Ind WSI det* ere from.luly 2, 1992, letter from
- c. R *. ~telnh*rdt (WPSCo) to USNRC D~t Control D~, MJect:,, ic........ lluclur P~
.,.. Plent, Ructor v.... l Structurel Integrity.
Hqt n.lllbera for Int. to lower shell clrc. wld from.aune 4, 1993 letter from c.1. Stefnherdt~
CWPSCo) to USllRC D~t Control D*t, Mjec:t: Ructor V..S.l Structur*l Integrity.
Sunmary File for Pressurized Thermal Shock Plant Beltlfrw Hut 110.
ID lleut.
IRT-Method of Che11f1try Method of XCu XIII I dent.
. ldlnt.
FlUlnce at Deter11fn
- Factor Deter11f n.
EOl./EFPY IRT-CF Palisadn Platn C*1279 2.69£19
- 10*F Plent 152.71 calculeted 0.24 0.51 D*3803*1 Smefffc EOL:
Pletn A*0313 2.69119 o*F MTEI 5*2 160.4 Teble 0.24 0.52 3/14/2007 D*3803*2 Pletn C*1279 2.691-19 o*F MTl!I 5*2 152.71 calculated 0.24 0.50 D*3803*3 Plat*
C*130I 2:69119 o*F MTl!I 5*2 121.1 Teble
- o. 19 0.41 D*3804*1 Plat*
C*130I 2~'69119 o*p MTD 5*2 131 Teble
- o. 19 0.50 D*3804*2'**i' Plat**
8*5294:,,,....,,-... 2.69119-..*.,' ' o*P.....
MTEI 5~2 12 Teble
- o. 12 0.55 D*3804*3
- :"~ '. *:.., ~
Cfrc. Weld 27204 2.69119
- 56*f Generic 229 Teble 0.21 1.00 9*112
.* *.,*,j
-:.:**~ ':..
Int. Shell W5214...... ".,.. 1.91E11
- 56.,
Generic 225.2 Teble
'0.20 1.oz Axlel Welda 2*112A/C i.$2,14...
'. ~*1.9.11;9
.**~56.,
Lower
.~I Generic.
225.Z TMtle 0.20 1.02 Shell Axfel~*
Welda 3*112A/C Lower 348009 1.911!19
- 56*f i:..rtc 196.65 TMtle
- o. 17 0.91 Shell Axf el Welda 3*112A/C Blf ICl!l!ia Ch*fcel campoaftfan and IRT-for the plet* and llT-for the... lda ere from.luly 3, 1992, letter from G. B. Slade (CPCo) to USNRC D~t Control Desk, ujects Pelf.... Plent**Ructor v.... l Structurel lnt.. rlty**Response to Generic Letter 92*01, R..,fafan 1 Chemical campoaftfan for... lda flbrfcated uelne W5Z14... ld Mire fa reported fn
- February 23, 1994 letter from D.W.
Ch*fcal c~ftfan for... ld flbrlcated using 343009 and 27204... lda Mire and fh*nc* date ere from.lurw 5, 1992 letter from G.I. Sleds <CPC> to USllRC.
Plant N-Palfsadn EOL:
3/14/2007
':':1
-***.(
Su11111ary File for Upper She 1 f Energy hltlfne I dent.
Plat..
D*3803*1 Plat..
D*3803*2 Plat..
D*3803;,;J
- Plat..
. D~3804*~*1*.
Plat..
- o-3804*2*
Platn D-3804*3 Cfrc~:Weld 9*112 HHt No.
C*1279 A*0313 C*1279 C*130I C*130I
~ t 1*5294
- Int:* Shell'* - V5Z14 **
AXl1l *Welda 2*112A. c Materf1l Type A 3021 Moc:f.
A 3021 Mod.
A 3D2I
- Mod *......
A 3021
- MOct. "
- ~'*..
1/4T USE It. EOL 61 5.9.-.;J, **.;
62:,t*'
~~;EJ_;*.~~:.. *~
a-!'
1/4T Neutron
'luence at EOL 1.6151!19 1.615119 1.615119
~lrred.
USI 90 17
~ ** r, 91 1.615119 72.. -
.' ~
Method of Deterwfn *
- ~trredo USI.'
Dfrect Dfrect Direct Direct A 3021 Mod *....
52.., i ! '"'
' 1.615119 76 Dfrect A 3021 Mod
- Linde 124, SAW 56 R:
- ..,,_ ** ?.*
'Lfnde '
- 64
- 1092, SAW 1.615119 h615119
- 1,;141119--1-111*-*
If *ter Plent
-state Plll'lt-:.
~ *..
- -***,._.,~.....
Loe.lit Sllel'l
. 34I009 ***
' tfncte*******
1092, SAW
- n-*** ** **-** -*... h-141119--* **HZ---.......,.- "stater -~. --***.
AXlll' Velda
,~; ~
- .. ;:_ ;:45
- ii 9 Plant 3*112A. c Lower Shell vsz14*-**
- t,;tncte *** -
64
- 1;-147119****-.,.,,,...... _.,,... *Slater
. AXf1l*- Wilda
.. ~.. ';
1092, SAii 3*112 A/C
'..*2~
.,. i ~
Plant Chemical caqMISftlon and wld WSI dllt* *re fro11 July 3, 1992, letter fram G. I. Slide CCPCo>
to USUC D~t Control Deaic, uject: P1ltladn Plant**Reactor v.... l ltructur1l Integrity*
~*eapor19e*~to Geft!lr.fc i..u.... 92*Cl1* a.w.t,.fon,,t_,_
..., r,,.-"."*"'**.,;
- .*.~..,.. *q'
,--?, '*<<***.,*.. -.,
- .*::i~lJf.:\\.
"im.:~~~
- .f--.:~1.:-*.t*:1'~*"*i
-1'~.~~.-r:
- ....,.,:*.-~.;
...,~ *::
~**"d" -:-,:!*.ff".\\t' WSla for th* pl*t*.... frGll A~t 31, 1990, letter frGll G *** Slide (CPCo) to USlllC D~t Control Deak, ujec:t: P1llladn Plant**Upper Shelf Energy In Raector leltllne
- *-.. j ;~."
The percent.drop fn iJsl for pl1tn D*JIOJ*1, *2 and *3...-. calcul1ted uafng tr-VWM and longitudinal surwtllm dlte-fram-pl*t* D.l'JI03r1-,:;Wilcl1<wte,:Jrredf1tect.ln ~*.A*240 and V*290.
The percent drop In USI.... calculated using the *thodology In Section 2~2 of RG 1.99, Rev. Z.
1~; ~ent drop fn U. f;~ ~l*a~;_ D*3804*1,*2, ~
- ~3; ~~.. ~~l~l1ted"uatng ~~. *thodology in Section 1.Z of RG 1.99, Rev. z.
.. '.. ~.*;.
- ..... * ~* ~~
Sunnary F11e for Pressurized Thermal Shock Pl1nt Bel tl.lne
.Hee~.Mo.* _,___
ID. Neut.
1deni~ -- - **
1dlnt.
Ffu.nce *t Eot./EFPY IRT-.
Method of Chtm.il*try __.
Method of XCu Xllf Prefrfe Island 1 EOL:
8/9/2013 Int. Shell For:gl_ng...
CC>
Lowr Shell....
Fortini.
CD>
21918/
-~-~-
21887/
38530 Clrc. Weld 1752 4.50219
.. ~
4.50e19
- Deter.In.
IRT-14*,
Plent Specific
'"":**I
- 4*F.: *. :.,.
'MTEl*5.z*--
I
.13.,
. ;*tint Smcfffc Fector Det.n.fft~*
CF 46.415..
calculated 0.06 0.72 44 Tlbl'e *---*
0.01*
0.66
.. ~
61.503 ca(ci:itiitid 0.1, 0.17 Btfecencn
"'1".1*0. ** ~ - * **~-..::.... -
.... -,... _______,_,.... -.--**-.:.* *.t-** :.:--,,..:._ **
Flu.tee, IRT-for al'l: *terf1la,.and. ch*fcal C0111P01ftfo1'.t~ta. for FJltlff.IP c _*"!'. f~L.~~~Y._6, __ 1992, let~er from T. "*
Parker CNSP) to USllRC D~t Cont~l Desk, MJact1 Response to Generfc Letter 92*01, luc:tor Vff8'l Structural lntetrfty.
Ch*fcal COlllPOlftlon value.fOf! F.orglng D end the clrCUlferentlat weld. an... f.rom ~
.. 24 *... 1"3.-l*Cter to MRC <Responae to GL 92*01 RAJ).
HHt rum.rs for Forgfng c _fa from Jmry 10,* 1916 letter from D. Musolf <*SP> to usuc D~
Control. Desk, ~Jact:
A....-,t of Preuurlzed*Therml Shock Reference T..-rature In Accordlnce. MIU.. 10 CR 50, lectlan 50.61.*
- Ch*tatry factors for.. Forgfng c en:1'*th* ctl'Nder~t'tal weld" were dat.,.;tnecff'rom the plent.'* eurwlllence progr* (6 data for Forging C _., 3 data for the ctrCUlference weld).
- >l";
-*~
.. --.~... *-~;***
Sunmary F11e for Upper Shelf Energy Pl.,,t N-leltlfne HHt No.
M*terlel 1/4T USI 1/4T IA'\\lrred.
Method of ldlnt.
Type et EGL Neutron USI Detel'llln.
Fl'*'Ce et...,........
IA'\\I rred.
EGL USl*o Prelrle Int. Shell 21911/
A 508*3 122 3.41E19 143 Direct lala. t, For1fna 31566 CC>
~.
- t EGL: * :
Lowr Shell 21U7/
A 508*3 100 J.41E19 134 Direct 8/9/2013 forafno CD>
38530 Cfrc.**Veld 1752*";'.
lMP; SAW 50*,.
J.41119 71
- .*. *.*r~
lurv *
.:.~*; ~- ~ c Veld BlflCW**
'*.: i#"~ * -;
- -~j-*
- ;..; l :* : ~-
unlrredlit.d* ~
iffelf. ftf"IV. cwsu dat* for *ttii tntenilldfece*-lhin fort'fiij ri the....
cf ramferentf'al... ld, andch*fQl cmpoaftfon data for the lntal'lledf*t* and lowr nll for1lnaa and clramferentl*l... ld are In July 6, 1~; letter from T. "* Parlcar CNSP) to USllRC DOC\\lient Control Deale, ufecti ReSPonM "to GW;;tc
- Lettiitt* 92~01; 1aact0r ve...l itructuriil *
. ~ lntetrlty.
. -.1'-:f
- i,; ~:- ; ::
~ ~
- He*t rumer for forglng*c and WSI dat* for forging D fa from,,...,.., 10, 1986, letter from D.
. Nuaolf CNSP) to USlllC D~t Control Dask, uJect: Aaaa*~ of Pwfzed Therwal Shock Rafer,MQ T41!1P8r*tur* f.n Accordlnce wf th 10 c~ ~~r_t so, hlctfon 50.61.
-~
The 1/4T flUllftCe Prafrta* 1aland 1 fa 'from Merch Jt>; 1994 letter to lllC *.
\\: *-~.
r
- *~r-,*:
i :~I~ *. ~
- ~i
- "*~* 'iir
~ *.
.'... J *.*
.... ;:.,~;i..;...
..i ~- i!
... ~~;
- .. :q....... ;.. *"":,_
'j\\O: ~~*.
c:'" ~ *** -*
- i*;
Su11111ary File for Pressurized Thermal Shock Plant Beltl fne HHt lo.
l!Fbut.
IRT._
Method of Ch*fatry MethOd of ICu Xllf N-I dint.
Jdlnt.
fl...nce *t Detert1fn.
factor Deterwfn.
i EOl/Ef PY IRT-CP Prefrfe Int. Shell 22829 4.5~1~.
14*p Plant
.~t..
..!~l*_.
O.Qf
'0.7' Island 2 forging.
spectifc
- *.. *r*
CC>
-~i.*
-*. y EOL:
Lowr 22642 4.5E19 2.2*p Plant 55.307 calculated 0.09
. 0.10 I
10/29/
Shell
. -~lffc I
. 2014 forgf ng CD>
Cfrc. Weld 2721 4.5119
-11*p Plant
.. 61.~....
,~.. ~cu~eted o.~
0.10 s-u1c:
81f1cmsli fl...:* and IRT_ det* for :the. cfrMf_erentfal *ld are from.July 6, 1992;, liifter_ f.-.*:1. "*.. Parker_ (ISP) to USNRC o~t control D*k, 9'bjec:t: Respanae to Generfc Letter 92*01, Reector V~l ltructur*l rntegrfty.*
.~
~.,
- Ch*fcel cmpoaftfon velues and IRT-date for forgfnge c ~._D are f.-. I~
24, 19:9J letter 'to UC CR*ponu to GL 92*01 RAI ).
~.
Ch*fcel coqiosf tf on valU.. for the gfl'C\\llferentfal *ld are averages from date fn GL 92*01 responM and PTI aattt*l dated,,.,..ry 10, 1986.
-~
~
-'.rf *. *.,:*.'.*-
~~:. ~--,,
~ -~
Sunmary File for Upper Shelf Energy Plant II-'* leltlfne HHt llO.
Material 1/4T use 1/4T unlrr8d.
Method of I dent.
Type at EOL Neutron use Detenaln.
Fl\\m1Ce at unlrrad.
EOL use Prairie Int. Shell 22829 A 508*3 14 3.01119 112 Direct Island 2 Fortln111 CC>
EGL:
Lowr Shell 22642 A 508*3 87 3.01E19 106 Direct 10/'lf/
Forgfng CD) 2014 Cf re. Weld 2721 I.It 89, SAW 61 3.01E19 103 SUrv.
Weld lllf ICIDED Fl\\m1Ce and ch*fcal COlllpOSftlon data are from July 6; 1992, letter from T. M. Parter CllSP) to USUC D~t Control Deak, 8'bject: Response to Generfc Letter 92*01, Re.c:tor v.... l Structural Integrity.
WSI for lower allell forgfng CD> and cfrC\\llferentfal weld fa from July 6, 1992, letter from T.
M. Parter ClllP) to USlllC D~t Control Deak, uject: Reaponae to Generic Letter 92*01, R..ctor v.... l Structural lntegrfty.
WSI for fnt.,...fate shell forgfng CC> fa from Table A*1 of WCAP*1134l.
Tiie ua at EGL for the cfrC\\llferentlal weld...a baaed on surveillance data and.,.. reported fn 11owimer 24, 199'3 letter to llRC CRnponae to GL 92*01 uu.
Su~ry File for Pressurized Thermal Shock Pl.,,t Beltlfrw Heat...
ID Neut.
IRT-Method of Cll*fatry Method of ICu
- t I dint.
ldlnt.
Fl--=e at
Datan1fn
- Factor Detenafn.
ECIL/lfPY IRT-CF Zf on 1 For1tng AU 102 a.65111 zo**
Plant 12 Table 0.06 o.a Spacfffc EGL:
Int. Shell C3795*2 1.73119
-10**
Plant ao.a Table 0.12 0.49 4/6/2013 S-fffc Int. Shell 17135*1 1.73119
.zo**
Plant 79 C.lculated
- o. 12 0.49
'-fffc Lowr 87123*1 1.7'31!19
-20**
Plant 87.4 Table*
- o. 13 0.41 Shell S-fffc Lowr C3799*2 1.73119
.zo**
Plant 1G3.4 Table 0.15 D.50.
Sllel l Smiefffc WP*154 406L44 a.65111
.5*p Generic 1U.09 C.lculated 0.31 0.59
~r Cfrc. Weld WP* 7'0 72105 1.7SE19
- 26**
lllC 199 **
C.lculated O.D 0.59 Mfddle
'-"fc t
Cfrc. Weld Int. Axfal IT176Z 6.29111
.5*p
'-"fc 152.25 Table 0.20 0.55c
- Welda
.f:!*.
Int. Axfal IT176Z 6.29111
.5*p GeMl'fc 152.25' Table 0.20 0.55 Welda WP*4 Lowr IT176Z 6.29111
.5*p GeMl'fc 152.zs Table 0.20 0.55 Axfal Welda B1t1cencas Ch*fcal COlllPOlftfon and 111... actpt for the Mfddle circ. Weld data are frcm.luly 2, 1992, letter from M. A. Jackaon
<CECo> to T. E. Murl9Y (URIC). ujacts lrafMod ltatfon, ~fta 1 and 2; ayron Statton, ~fta 1 and 2; Zion Statton*
~f~a*1 and.2 Fluancea are from llAW*21~
The..uit of nfctel for AU 102 -. reported fn the lkMllmr 19, 199J letter frcm*r.11. Sfll!pkfn (CECo> to.T.E. Murl9Y
<USUC).
IRT-for Mfddle*Cfrc. Weld,.,,.70~.. daterafnad frcm.,. 8PPf'OYad *thod fn **February 22, 19" letter frOll C.Y.
Shf ratf <USQC> to D.L Farrar <CJC).
Cll*fatry Factor for Middle Cfrc Weld,.,,.70,.... calculated from Zion 1 and 2 surwfll~ data that waa reported fn BAW 1803, Rev. 1.
Ch*fatry Factor for Upper Cfrc. Weld, "'*154.,.. calculated from Pofnt leech 2 aurwfll~* data that i.aa reported fn BAY 1803, Rev. 1.
The Pofnt leech 2.. ld aurwfll~* *terfel.,.. fabrfcatfng th*._heat of Mfre ** uHd to fabricate WF*154.
Swmaary F11e for Upper Shelf Energy Pl.nt.._ leltllne H.. t llo.
Mliterfel 1/4T Ull 1/4T
~frred.
Method of ldlnt.
Type at EGL lleutran Ull Deterafn.
Fl~at
~lrred.
EGL Ull Zion 1
'oralna AU 102 A 508-Z 113
- 5. 19!11 134 Direct EOL:
Int~ Shell CJ79S*Z A 5JJl*1 52 1.04119 66 Generic 4/6/Z01J Int. Shell 17135-1 A 5331*1 90 1.04119 117 Direct LOMet' 171ZJ-1 A 5331*1 1.04119 66 Generic Shell LOMet' CJ7'99-Z A 5331*1 50 1.04119 Generic Shell W*154 406L44 Lindi*, -*
5.19!11 -*
Upper SAW Clrc. Weld vr-10 72105 Lindi ao, ***
1.04119 -*
Middle IAll Clrc. Weld Int. AXlal IT1762 Lindi 80, -*
J.71111 -*
Welds SAW.
vr-1 Int. AXlel IT1762 Lindi ** -*
J.71111 -*
Welds IAll vr*4 LOMet' IT1762 Lindi*, -*
J.71111 -*
AX I al WI Welds vr-1 Btf *rwn WSI* for plate 171D*1 reported In IAll-ZClll
,l~aref... Ull-2166 WSI dlta for AU 102 forgtr-. reported In........ "* 1993 letter f... T *"* 11.Pdn (CICO) to T.I. MurllY (..C).
WSI valws for Plat* CS79S*Z, 171D*1.,. C3199-Z -. cM9f'llfned,,.. dst1 f,.. al8f lar n.. value la 1 tolerance l l*ft wltll 951 confidence tllat at plat* r.ported. fn Ull-10064IP.
l... t 951 of tile papulettan la.,...t.,. tllan the tolerence ll*lt1 (n. ~%-Ko where: %*91ft-lb, K
- 3.187, o
- 7. 87) 2L1censee must confirm app11cab111ty of Topical Reports BAV-2178P and BAW-2192P
\\
.... v.
Swmnary F11e for Pressurized Thermal Shock Pl8nt Beltlfne
.... t lo.
ID 119ut.
IRT-Method of Ch..tatry Metllod of ICu ldlnt.
ldlnt.
Fluence et Deteratn
- fec:tor Detentfn.
EOL/lfPY IRT-CP Zion Z Lowr 1.Y 3155 1.45111 10**
Plent SI Teble 0.09 0.66 lloul*
Specfftc Belt forafna EOL:
Lowr ll029-1 1.69119
-10**
Plent 11.z Teble 0.12 0.51 11/14/
Shell Specific 2013.
L...,.
C4007*1 1.69119 10**
Plent 17.67 C.lculeted 0.12 O.SJ Shell S-fffc Int. Shell ll006*1 1.69119 10**
Plent 11.1 Teble 0.12 0.54 S-fflc Int. Shell ll04CM 1.69119
-10**
Plent 96.4 Teble*
0.14 0.52 Smcfffc WP*200 IZ1T44 1.45111 Generic 177.95 Teble 0.24 0.61*
ltoul*
Belt to Int. Shell Ctrc. Weld SA*1769 71249 1.69119 Generic 112 Teble 0.26 0.61 Int. to Lowr Shell Cfrc. Weld WP*29 72102 6.04111 Generic 174.1 Teble O.ZJ 0.61 Lowr Int.
Shell Axt*l Weld WP*70 72105 6.04811
- 26**
lllC 199 **
C.lculeted 0.35 0.59 Int. Shell Generic Axt*l Welda Blfm:ences Ch*tcel CCllllpOSftton end 111_ dlta.,.. frcm.luly Z, 1992, letter frcm ** A *.iaca.i (CICO) to T. I. Murley CUSllRC>,
uJec:ta Bretdwood Statton, ~tta 1 end 2; tyre ltatfon, ~f ta 1 end 2; Zion Statton, ~fta 1 end 2 Fl&mtee data are frcm UW-2166 IRT-for Int. Shell Axial Ueldll UP*70,.,.. ~entfned frcm an* epp Ov.d *thod tn a Pebr'ulry 22,. 1994 letter from c. Y.
Shtrekf (ualC) to D.L.......... (CIC)
- Ch*t*try Pec:tor. for* Int. Shell Axial Ueldl, WP*70.,.. celculated fl'Clli zton 1 and 2 surwtllance data th*t wn reported llAW 1IOJ, Rev. 1
- Sunnary File for Upper Shelf Energy PlMt II-leltlfne H*t llo.
. Material 1/4T US1 1/4T lillrrad.
,..tflod of ldlnt.
Type at EOL Neutron Ull Oeterwln.
PlUMCe at lillrrad.
EOL Ull Zion Z Lo.r 1.Y JISS A 50l*Z
. 104 5.07111 1247 Generic Nozzle Salt Forti..
EOL:
Lo.r ll8029*1 A 5331*1 1.01119 11 651 11/14/
Shell 2013 Lower C4007*1 A 5331*1 76 1.01119 Direct Shell Int. Shell 88006*1 A SJJl*1 1'0 1.01119 6SI Int. Shell B804CM A 5331*1 n
1.01119 9Z 6SI WP*ZOO 8Z1T44 Lindi 80, -*
!1.07111 -*
llozzle*
SAW
. Salt to Int. Shell Clrc. Weld SA*1769 71249 Lindi 80, -*
1.01119 -*
Int. to SAii Lo.r Shell Clrc. Weld WF*29 72102 Lindi 80,...
3.63111 -*
Lo.r SAii Shell Axial Weld WP*1'0 721GS*
Lindi m, -*
3.63111 Int. Shell Ull Axial W.ldl B1f 1caa WSI da~a for plate ID0*1 la frcm YCAP*12396 Fl'*'!:* data are frcm UW-21'6 WSI for fOl'll,. 1.Y 3l5S not av8lllble. Value reported* In the -.. wlue frcm four *l*I lar fortlnga that are docmm\\tad In UW-10046P 7Additional information required to confirm value 2License* must confirm applicability of Topical Reports BAW-2178P and BAW-2192P