ML18064A487
| ML18064A487 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/30/1994 |
| From: | Gamberoni M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9412020219 | |
| Download: ML18064A487 (52) | |
Text
/
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20556-0001 November 30, 1994 LICENSEE:
Consumers Power Company FACILITY:
Palisades Nuclear Plant
. \\
SUBJECT:
PALISADES COMPLIANCE WITH PRESSURIZED THERMAL SHOCK SCREENING CRITERIA A meeting was held at NRC Headquarters on November 21, 1994, between Consumers Power Company and the NRC to discuss results of tests performed on weld samples from the Palisades retired steam generators and their effect on Palisades' compliance with the pressurized thermal shock (PTS) screening criteria in 10 CFR 50.61. The meeting handout is provided as Attachment 1 and a list of attendees is provided as Attachment 2.
Background
In February 1994, Consumers Power Company submitted to the NRC information relative to Palisades' compliance with the PTS screening criteria. The submittal also contained Consumers' plan to use samples from welds in the Palisades retired steam generators to determine chemical.and physical properties of the welds in the Palisades reactor vessel.
An interim Safety Evaluation (SE) was published on July 12, 1994, which concluded, based on the information presented in the February submittal, the Palisades reactor vessel would reach the PTS screening criteria in 2004.
In addition, the SE stated that this conclusion could change based on the results of the tests performed on the retired steam generator weld samples.
On November 1 and 2, 1994, Consumers contacted the NRC with preliminary results of the chemistry analysis performed on the steam generator weld samples.
The telephone call is summarized in a docketed conference call record dated November 3, 1994.
Additionally, Consumers submitted information to the NRC on November 8, 10, and 18, 1994, which summarized testing results and conclusions at the time of those correspondences. The November 21 meeting was a presentation by the licensee of the information provided in these submittals and is summarized below.
,.Contact:
Marsha Gamberoni, NRR 504-3024
.. -*1
(
9412020219 941130 I
PDR ADOCK 05000255 P
PDR 0.~000'51
'. '.' I
- Chemistry Factor (CF)
Palisades most limiting reactor vessel material is an axial weld fabricated from wire heat No. W5214.
Palisades performed chemical analysis on samples from th*riee welds in the retired steam generators that were fabricated using the same wire heat number.
Because of the method used to fabricate the steam generator welds, Palisades treated the samples as if they came from one weld and calculated the average of all the samples.
The results are an average copper value of 0.297 and an average nickel value of 1.101.
When these values are incorporated into the industry database, the best-estimate copper value
~or Palisades axial weld is 0.217 and a best-estimate nickel value is 1.02.
These values are used to determine a chemistry factor of 234°F.
Initial RTllDT Although Palisades performed mechanical property testing of the steam generator weld samples, the licensee concluded that the data was not credible and is continuing to use the generic value of -56°F {10 CFR 50.61) for the initial RT~or* Palisades' conclusion that the material testing results are not credible is based on the effects of thermal aging, change in drop weight test methodology, and post-weld heat treatment *. Since Palisades is using the generic unirradiated reference temperature, a margin {M) value of 66°F is specified by 10 CFR 50.61.
Fluence {f)
- Using the equation provided ir.i 10 CFR 50.61 and the above initial RTNDP M and CF values, Palisades solved for f and arrived at a screening criteria fluence va.lue of 1.49 x 1019 n/cm2*
The remaining effective full power days {EFPDs) before reaching the screening criteria was calculated using an end of cycle 10 cumulative fluence of 1.25 x 1019 n/cm2 and a cycle 9 fluence addition rate of 1.73 x 1015 n/{cm2 - EFPD). Additionally, 232 EFPDs have elapsed since the beginning of cycle 11 through October 31, 1994.
Using this information, Palisades estimated that 1,155 EFPDs remain before reaching the screening criteri.a.
Using the 1,155 EFPDs and a 75% capacity factor, Palisades estimates 4.21 years before reaching the screening criteria and provides a new date of January 1999.
Future Actions Based on the January 1999 screening criteria limit, Palisades plans to submit its plan for operation through end of its current license within the next year.
In addition, Palisades presented a number of short-term actions which included further analysis and evaluation of the steam generator weld samples and submitting a site-specific surveillance plan using the available re,present.ative industry data on W5214 welds. Long-term actions being considered were also presented.
- During the presentation the staff asked a number of questions.
Some of the questions that were asked and will need to be addressed during future communications include:
treatment of the three steam generator welds as one, appropriate weighing of all the chemistry values, comparison of welds used in the industry database, {i.e., fabrication method and location of samples},
further analysis to support the thermal aging issue, variability in initial RTNor as well as irradiated values, and upcoming IO-year inservice inspection.
If there are any questions regarding this meeting summary, contact Marsha Gamberoni at {30I) 504-3024.
Attachments:
As stated (2) cc w/att:
See. next page DISTRIBUTION:
See attached list*
Original signed by
. Marsha Gamberoni, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation DOCUMENT NAME:
G:\\WPDOCS\\PALII21.SUM To receive a copy of this document, Indicate In.the box: "C" = Copy without attachment/enclosure "N" = No copy OFFICE LA:PD31 PM:PD31 NAME CJamerson DATE ll/ZS/94 1I/2G/94 ll/Z8/94 OFFICIA RECORD COPY
Consumers Power Company cc:
Mr. Kurt M. Haas Plant Safety and licensing Director Palisades Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Mr. Thomas J. Palmisano Plant General Manager Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 Mr. Robert A. Fenech Vice President, Nuclear Operations Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 M. I. Miller, Esquire Sidley & Austin 54th Floor One First National Plaza Chicago, Illinois 60603 Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road lisle, Illinois 60532-4351 Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room l - Capitol Building Lansing, Michigan 48913 Palisades Plant U.S. Nuclear Regulatory Conunission Resident Inspector Office Palisades Plant 27782 Blue Star Memorial Highway Covert, Michigan 49043 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0. Box 30195 Lansing, Michigan 48909 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.
Washington DC 20037 Alora Davis Commitment Tracking System Coordinator Palisades Plant Consumers Power Company 27780 Blue Star Memorial Highway Covert, Michigan 49043-9530 Michigan Department of Attorney General Special Litigation Division 630 Law Building P.O. Box 30212 Lansing, Michigan 48909 November 1994
J
'*.,,.'1.
DISTRIBUTION FOR PALISADES MEETING
SUMMARY
w/attachments 1 & 2:
~
PUBLIC PD31 Rdg
~,
M. Gamberoni
,k W. Kropp, Region III
~ J. Strasma, Region III
..,_. M. Parker w/attachment 2 only:
W. Russell/F. Miraglia R. Zimmerman J. Hannon C. Jamerson OGC E. Jordan, D/AEOD P. T. Kuo S. Sheng A. Hsi a R. Laufer N. Dudley C. Carpenter T. Koshy L. Shao M. Mayfield D. Bessette C. Troutman J~ Kennedy J. Roe W. Russell J. Taylor J. Mil ho an A. Thadani B. Sheron J. Strosnider G. Holahan R.C. Jones, Jr.
L. Lois B. McCabe C. Fairbanks B. Elliot C. Hsu G. Lainas R. Hermann S. Malik A. Wi 1 ford M. Vagins ACRS (4) cc:
Licensee & Service List (with all attachments)
DATED:
November 30, 1994
,',\\~
PALISADES NUCLEAR PLANT REACTOR VESSEL INTEGRITY PROJECT STATUS NOVEMBER 21, 1994
Palisades Nuclear Plant Reactor Vessel Integrity Status Meeting AGENDA I. INTRODUCTION II. OVERVIEW OF CURRENT DOCKETED PLAN Fluence and RV Chemistry ISER Basis Project Plan Provided 2/23/94 Area of Focus for Present Concerns Ill.
CURRENT STATUS
{.
- SG Weld Samples SG Weld Test Results chemistry material properties Credibility of Results similarities/differences w I RV welds:
material properties comparison w / Industry data Projected RT PTs Conclusions Compensating Issues IV.
NEXT ACTIONS Near Term Long Range Plan
- CLOSING Bob Fenech Ken Powers Bud Gerling Ken Powers Bob Fenech
INTRODUCTION t
I-1
Palisades Nuclear Plant Reactor Vessel Integrity Program Steering Committee
- Dave Joos, Senior VP CPCo
- Bob Fenech, VP Nuclear Operations Tom Palmisano, Palisades Plant General Manager
- Ken Powers, Engg. & Mods. Manager
- Kurt Haas, Plant Safety & Licensing Director
- Jack Hanson, Design Engg. Support Manager Project Team Full-Time Members:
- Bud Gerling, Reactor & Safety Analysis Manager
- John Kneeland, RVI Project Engineer
- Guy Packard, Reactor Physics Supervisor
- George Goralski, Nuclear Fuels Supervisor
- Dick Smedley, Licensing Engineer
- Bill Beckius, NPAD Rx Engg. Specialist Part-Time Members:
Rolfe Jenkins, Design Engg. Supervisor Jerry Nordby, Welding Engineer Phil Flenner, NPAD Dorothy Peterson, Procurement Dr. Bill Pavlichko, Energy Supply Services Industry Members:
West.
- AT!
Arnie Fero, Radiation Enggg. & Analysis Steve Byrne, RV Integrity Engineer Dr. Gareth Gage, Materials Performance; Dr. Neal Irvine, Executive V.P.;
Dr. Ron McElroy, Reactor Materials Bill Server, President; Tim Greisbach, Director Technical Services
- In attendance 11/21/94 I-2
II. OVERVIEW OF CURRENT DOCKETED PLAN
~*
II-1
ASSUMPTIONS/COMMITlVIENTS SUPPORTING INTERIM SER Fluence Palisades will continue to utilize Discrete Ordinate Methodology (DOT/DORT) for fluence calculations
. Calculations will continue to be performed by reputable vendor Future fluence rates will remain at or below the cycle 9 calculated value for all welds, which is the value utilized in both the 6-5-92 and 2-23-94 PTS submittals II-2
CHEMISTRY Best estimate copper concentration determined using a weighted average of available measurements Single arc weld weighted once Tandem arc welds weighted twice Best estimate nickel concentration determined using a straight average of available measurements Weld Wire Heat#
1.02%
Additional chemistry measurements to be taken from the retired steam generators and incorporated into the above averages II-3
- PROJECT PLAN PROVIDED 2/23/94 II-4
- "*1**ule IWll 10 1-1 1-1 I
VI A
Supipl-nt*I 9u1welllance
- 109.... u*lng
,....... try,....
IPJ Deli. I and c** HS P Projected llOL AT,_
r:
&/\\/U, Ill/ti end l/H SulmhlAlll
- rojected llO&. n -
- in.....,....
n
- _,,,. Weld Se,mple* P1cm
- t*r*d ***..
Oenereaore Claeat.,_
llSllt
- Dbt***
a.-**trr and l*lt lal llT -
Dae IHI
- ojected 90L
- ol**d n,.
- ojected aoa. aT...
.Ian llH
....,,,,.d Projected SOL aT....
.......... HH l'/\\l.1::/\\11.::: 11~:/\\l'TOll VF:::sF:I. l'Ro.n:c*r PLAN IHl'U:Hl*:NTATION t'l.llW l*IAliRAH Da~< IHS Place Chalrl'J' Te1M1lle lpecl-n*
In Teet
- eAClDI'
- olved P1otected aoL *T "'
....... llltt
.June lttt
- I ace Charp,-
and Ten*lle lpecl-n* In ho Cap*ulee on **ll*ade*
- cto1 llal' IHI
!lrpeic:l-ne hem.., I c-**
Teet lrpecl-n*
from -.,, J Cepeule Dae IHI
- b.,,,
II P*rl lclpate In Piiot AnnHlln,..
Progr.. U.lnt
- h*... n1a *Ill
- ct or lhl'U
...,,_, llH Aeactot" V****I Anneel PeHlbll ltr 9ludr thl'u
.Jun. ""
Anneal Ir O.*l&able Janua1 r Joo I
- ot111nue lteac*tor V****I I* V****I In II**** I lnhanc:ed Pluem:* llata Oe1M1 at ton
.J*nua 1 W' I t9t 1h1u Janua1r a
r------~~~~-1 jobtain t"yL*la 11 Ila&* ol Flue1u*e Ja11ua1y lit*
If *c*****W" UI........ bl*
uaa Crcla II Pluenc;a I u* ltll to IOL *awlaa p101actad SOL *T tl'I Valuaa
.Jwta ltt*
u lle*habla II** Ultra Lo* 1.e.....,.
ro1a IHI
D
, Remove Weld
- Samples from
- Retired Steam
- Generators i(Heat Nos jW5214&
- 34B009) l I
l I obtain I
I Chemistry I and initial I jRT NOT I
I I
i I
I y 1
1
- Projected EOLRTPTS II-6
III. CURRENT STATUS 111-1
SGA W5214 SGB 34800g s* c III-3
W5214 WELD DATA From extensive and thoroughly researched weld chemistry information from other plant surveillance programs, and weld sample programs, and CE laboratory records.
6-5-92 and 2-23-94 CPCo Submittals document available W5214 information which was the basis for our 2004 interim SER.
W5214 chemistry information included 16 total sources:
2 Cu Sources 9
Ni Sources 5
Cu & Ni Sources The SIG Samples expand the available W5214
- chemistry sources by one additional Cu & Ni Source.
III-5
W5214 Weld Data Averaging
% Copper
% Nickel Material ID 1 T
0.20 Material ID 2 0.94 II II 0.20 Material ID 3 1.20 HBR2-Torus T
0.159 Material ID 4 1.00 0.159 Material ID 5 1.05 IP2 Surveillance 0.20 Material ID 6 1.12 IP3 Surveillance T 0.16 Material ID 7 0.97 0.16 Material ID 8 0.92 IPJ Nozzle Cut 0.15 Material ID 9 0.99
~*
HBR2 Surveillance 0.34 Material ID 10 1.13 OC1 Surveillance 0.285 HBR2-Torus 0.99 Palisades SIG T
0.297 IP2 Surveillance 1.03 0.297 IP3 Surveillance 1.12 IP3 Nozzle Cut 1.09 Average 0.217 HBR2 Surveillance 0.66 Palisades SIG 1.101 Average 1.02 "T' Denotes Tandem Weld III-6
RESULTS OF DROP WEIGHT TEST ON S/G SAMPLES 11-9-94
- 1.
Palisades Steam Generator A, Weld 1-951 Weld Filler RACO 3 NI 200 NDTT = -20 "F Specimen Identification 1
2 3
4 5
6 7
8 9
10 Heat W5214 N7753A Flux Type 1092 1092 Test Temperature
('F)
-80
-50
-40
-30
-20 0
-10
-10
-20
-20
- 2.
Palisades Steam Generator B, Weld 1-951 Weld Filler RACO 3 NI 200 NDTI.. -50 'F Specimen Identification 1
2 3
4 Heat 348009 N7753A Flux Type 1092 1092 Test Temperature
('F)
-80
-50
-40
-40 III-7 Break or Non-Break.
Break Break Break Break Break Non-Break Non-Break Non-Break Non-Break Non-Break Break.
or Non-Break Break Break Non-Break Non-Break
PALISADES CHARPY V-NOTCH TEST DATA MATERIAL: LINDE 1092 SAW HEAT NO: 5214 120.00 *..------,.---.,----...,...----.,r-----r---~--....--..--......--------.
c v 100.00 ~--t----1----+---- ---
N E
N 80.00 - ---if-----+-----t-E R
G y
60.00 -*--+-----t---- 1----~--.1~--1---------
F T
40.00. ----t-----t---+---
- A---1--*------ -
L B s PALISADES CVN DATA
-PALISADES CVN FIT 0.00 -r-...--.-~...,......,.--r-l~r-r"""T-r~-r-T-r--l-.-r-r-M--r-r-.--r-+-r-,--,--r-t-r-,...-r-~'"T""""T"-r-r--t-"T-r-r~
-200.00 -150.00 -100.00
-50.00 0.00 50.00 100.00 150.00 200.00 250.00 300.00 TEMPERATURE IN DEGREES F
CHARPV V-NOTCH TEST DATA MATERIAL: LINDE 1092 SAW HEAT NO: 348009 PALISADES 140 ----------------------------------------------------------
c 120 v
N E
N 100
-~------
--- ---------+---------*--** ---- ------------------
E 80
- ___________._ __ _
R G
y 60 -------<-----------....---- ________.__ _______ ---------------*-
F T
L B
40-*---
s 20*--
PALISADES CVN DATA PALISADES CVN FIT
- -------------~---- *-------------- **--
O-L--------.i...--------i-__,.------+-..------.--+-....-r_,.. __ -+-~~---+-~--,...-t-t
-200
-100 0
100 200 300 400 500 TEMPERATURE IN DEGREES F
I I
- CREDIBILITY OF RESULTS III-10
1-t 1-t 1-t I
Weld Seam No.
Source Weld Wire Heat No.(s)
Ni-200 Heat No.
Flux Type Flux Lot No.(s)
Detailed Weld Procedure Reference Procedure PWHT (Total Hours Above l I00°F)
PALISADES VESSEL BELTLINE WELD FABRICATION DETAILS/
CANDIDATE WELD FABRICATION DETAILS W**
2-112 A;B,C 3-112 A,B,C 9-112 1.. 951 A,B,C Reactor Vessel Reactor Vessel Reactor Vessel Axial Weld Axial Weld Circumferential Palisades Intermediate Shell Lower Shell Weld SIG No. 1 W5214 W5214 27204 W5214 3480009 N7753A N7753A N7753A Linde 1092 Linde 1092 Linde 124 Linde 1092 3617 3692,3617 3687 3617 A
B c
D x
x y
x 14.75 14 12.75 17.4
~
~
1=951 A,B,C Palisades S/G No. 2 3480009 N7753A Linde 1092 3708 E
x 9.5
t-1 t-1 t-1 I.....
N 140.00 c v 120.00 N
E 100.00 N
E R
80.00 G
y F
60.00 T
L 40.00 B
s 20.00 0.00 CHARPY V-NOTCH TEST DATA MATERIAL: LINDE 1092 SAW HEAT NO: 5214 PALISADES VS INDUSTRY RESULTS
- INDUSTRY CVN FIT A
PALISADES CVN DATA
--PALISADES CVN FIT
-200.00 -150.00 -100.00
-50.00 0.00 50.00 100.00 150.00 200.00 250.00 300.00 TEMPERATURE IN DEGREES F
I....
w 140 c 120 v
N E
N E
R G
y F
T L
B 100 80 60 40 s 20 0
-200 CHARPY V-NOTCH TEST DATA MATERIAL: LINDE 1092 SAW HEAT NO: 348009 PALISADES VS MILLSTONE
-100 0
MILLS CVN DAT PALISADES CVN DATA 100 200 300 TEMPERATURE IN DEGREES F 400 500
CHARPY DATA
SUMMARY
W5214 Delta T shift@ 30 ft-lbs= 31.2 °F Delta T shift @ 50 ft-lbs = 38.8 ° F Upper Shelf Energy Shift= -12. 7 ft-lbs 34B009 Delta T shift @ 30 ft-lbs = -9. 7 °F Delta T shift @ 50 ft-lbs = 28. 7 ° F Upper Shelf Energy Shift= -5.5 ft-lbs III-14
SG Weld vs. RV Weld SIMILARITIES
- 1. Same Weld Wire Heat as RV, Flux Type, Welding Procedure, Fabricated during same time period in same shop.
- 2. SG Weld Chemistry is representative of RV Chemistry; Data is no more representative of RV than IP-2, IP-3, HBR
SG Weld vs. RV Weld DIFFERENCES
- 1. Different Heat Treatment RV 14 hrs @ > 1100°F 8.5" Thick SG A" 17 hrs @ > 1100°F 4.75" Thick SG "B" 9 hrs
@ > 1100°F 4.75" Thick
+ 30°F shift in 1-RTNDT from Millstone Point III-16
SG Weld vs. RV Weld DIFFERENCES
- 4. SG Weld W5214 Drop Weight Data Inside breaks vs. outside breaks lower I-RT vs. slightly higher I-RT
- 5. ASTM Standard Change in Drop Weight specimen preparation
- 6. Palisades Thermal Capsule shows 28°F Shift in Charpy Data
@ Operating Pressures & Temperature III-17
H H
H I......
00 Basis of Current SER Data for Limiting Weld Heat No. W5214 Nickel Content =
Copper Content==
Yields a CF =
1.02%
0.201 %
225°F Screening Criteria Fluence Value -
- 1. 76
- 1019 n/cm2 End of Cycle 9 Cumulative Fluence -
- 1. 19
- 1019 n/cm2 Cycle 9 Fluence addition rate =
- 1. 73
- 1015 n/(cm2-EFPD) 6.31
- 1017 n/(cm2-EFPY)
Assuming a 75% capacity factor the PTS screening criteria is reached in the year 2004.
1-4 H
H I.....
Impact of Steam Generator Chemistry Data Data for Limiting Weld Heat No. W5214 Nickel Content =
Copper Content =
Yields a CF =
1.02%
0.217%
234°F Screening Criteria Fluence Value -
1.49
- 1019 n/cm2 End of Cycle 10 Cumulative Fluence -
1.25
- 1019 n/cm2 Cycle 9 Fluence addition rate =
- 1. 73
- 1015 n/(cm2-EFPD) 6.31
- 1017 n/(cm2-EFPY)
Using cycle 9 fluence addition rate for cycle 11 fluence leaves the Plant with 1155 EFPD's. Assuming a 75% capacity factor the PTS screening criteria is. reached in mid January 1 999..
CONCLUSIONS
- SG Weld Material Properties (Initial RTNDT) Not Representative of Reactor Vessel; Generic Value of -56°F should continue to be used - considered to be consistent with clarification to 10CFRS0.61 b.2.i
- Projected RTPTs shows screening criteria will not be exceeded until January, 1999 III-20
COMPENSATING ISSUES
- 1. RV Condition
- 2. Fluence Reductions/Conservatisms
- 3. Operator Actions III-21
6.e+10
~
~ 5.e+10 m
~
,,, 4.e+10 c g
- J Q) z 3.e+10 2.e+10 0
5 Historical Flux Distributions 10 15 20 25 30 Angle in Degrees 35 40 45 N
N I
H H
H
JI"/
OPERA TOR ACTIONS
- 1. EOP Review conducted to ensure actions consistent in regard to minimizing potential consequences from PTS events.
- 2. Additional training to be provided to operators to heighten awareness, sensitivity to PTS events.
- 3. Actions being taken to maintain safety injection water source temperature as high as practicle.
III-23
IV. NEXT ACTIONS IV-1
NEAR TERM ACTIONS Actions Underway
- Additional Chemistry Samples at AEA
- Independent Analysis of Chemistry Values Actions Under Consideration:
- l\\f.icrostructure analysis of SG samples
- Anneal of SG samples
- Additional Charpy Tests
- Fracture Toughness Analysis
- Evaluate Usability of Existing Palisades Surveillance Material
=> Decision on Surveillance Material Plan by 1/15/95 Plant Specific Surveillance Plan
=> Submit Plan by 3/1/95 IV-2
LONG RANGE ACTIONS S'l 11LL UNDER CONSIDERATION
- Additional Flaw Data at 10 Year ISi
- RV Weld Samples
- Methods to Better Define Our Fluence
- Lower Leakage Core Design
- RV Pre-Stress Bands
- RG 1.154 Analysis
- RV Anneal IV-3
H <:
I
~
CONSUMERS POWER COMPANY
- PALISADES NUCLEAR PLANT Schedule for Palisades Reactor Vessel Integrity Project Plans DESC~IPTION SG WELD TESTS PLANT SPECIFIC INTEGRATED SURVEILLANCE PROGRAM DOE ANNEALING DEMONSTRATION PRE-STRESS BAND STUDY ANNEALING STUDY RG 1.154 CONSIDERATION 50.61 SCREENING DATES 1996 1997 OUTAGE NOTE#1:
1998 OUTAGE
~
Based upon 111941 Submillll 11/18/1994 1999
\\J See NOTE 11 lfl
..t.
V. CLOSING V-1
APPENDIX A A-1
SGA W5214/SGB 348009 6
1 DIA.
ELD SAMPLE 6* DIA.
A-2
i Sample ID Descriptions Seams A and B i
/- A Steam Generator
,r-- Seam I
/
.. r-- Slice
/
/,.
1 Sample Position A/SG/A/2/X SeamC
.- A Steam Generator
/
,- Sample Slice 1-A Steam Generator I
/
Sample Position
/
./ /~ Sample Position
/
/
/
! /
/
!_-' //
/
.- Sample Slice I
A1/1/X AR/1/X SAMPLE POSITION 10............
u 24mm (X) i 12.065cm I
y 4SmmM I I
i z
24mm (Z) I i
00 A-3
A-4
Industry Correlation Coefficient is 0.8349 Estimate of Upp er Shelf= 116.8 95°/o Confidence Band (2 sigma) = 27 30 ft-lb Transition Temperature = -78.8° F,
95 % Confidence Band (2 sigma) = 58° F 50 ft-lb Transition Temperature= -44.6° F 95 % Confidence Band (2 sigma) = 38 ° F A-9
CHARPY DATA STATISTICS 34B009 Palisades Correlation Coefficient is 0.87 Estimate of Upper Shelf= I 04.8 95°/o Confidence Band (2 sigma) = 12 30 ft-lb Transition Temperature = -60.9° F 95 °/o Confidence Band (2 sigma)= 24.3° F 50 ft-lb Transition Temperature= -22.5° F 95 °/o Confidence Band (2 sigma)= 22° F A-10 L
f I'
Industry Correlation Coefficient is 0.8412 Estimate of Upper Shelf= 110.3 95% Confidence Band (2 sigma)= 21 30 ft-lb Transition Temperature= -51.2° F 95 % Confidence Band (2 sigma) = 59° F 50 ft-lb Transition Temperature= -24.2° F 95 o/o Confidence Band (2 sigma) = 29 ° F A-11
I
- i>
I,_.
I I I
en c:
- 11111
!I r-r-
~
- z n.....
r-n 0
~C> ~
en ""' --t -
- ,u c
r-0 z
~
I VI en en C>
- z
~ -
'.II:
r-0 en u
I I
w.11 W-llO tecP r-------: /ullel Noule
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(
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Accelerated
,--Core Support Barrel A-240 I
____, \\ lnle
\\Noule
\\
\\ J I
I
/"
V~ n ~
-Reactor Vessel Wall W-260 ol Wall 0
W-80 z
(/)
,.c
>I:
"II r-111 cn-:U
> (/).,,
- U~'V c1110
'V (/) :e 0,.111
>,-:U
-t>o mz
.,.o I:,,,..
z
\\
\\
\\
\\.....
[nlarged Plan View Wall W-280 A
.., Wall
' W-290
'... I I
I I
- ~,
I
~
7 7 7 I
Jherma
-JJO I
I
,/
I I
d1 lhermal Capsules Auembly Acceleraled Capsule--..
Assembly Wall Ci11Jsule-Assembly Elevation View
~
\\,.
)
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LIST OF ATTENDEES MEETING ON RESULTS OF TESTS PERFORMED ON WELD SAMPLES FROM PALISADES RETIRED STEAM GENERATORS AND THERE EFFECT ON PALISADES' COMPLIANCE WITH THE PRESSURIZED THERMAL SHOCK SCREENING CRITERIA M. Gamberoni P. T. Kuo S. Sheng A. Hsia R. Laufer N. Dudley C. Carpenter T. Koshy L. Shao M. Mayfield D. Bessette C. Troutman J. Kennedy J. Roe W. Russell J. Taylor J. Milhoan A. Thadani B. Sheron J. Strosnider G. Holahan R.C. Jones, Jr.
- l. Lois B. McCabe C. Fairbanks B. Elliot C. Hsu G. Lainas R. tlermann S. Malik A. Wilford M. Wagins November 21, 1994 CPCO R. Smedley R. Fenech D. Joos K. Haas J. Hanson K. Powers G. Packard W. Beckius J. Kneeland R. Gerling BG&E C. Hardini R. Hardies BETCHEL W. Hopkins T. Sutter ATI Consulting W. Server T. Griesbach OTHER AFFILIATIONS P. Leombruni, ABB R. McElroy, AEA Technology D. Lohman, WPSC L. Connor, STS R. Carter, EPRI T. Huminski, Duquesne Light K. Cozens, NEI D. Palmrose, INEL M. Breck, NUS R. Nanstad, ORNL P. Gunter, NIRS