ML20132G937
| ML20132G937 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/17/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20132G920 | List: |
| References | |
| NUDOCS 9612270088 | |
| Download: ML20132G937 (70) | |
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4 COMED l
BYRON UNIT 2 COMMERCIAL OPERATION: AUGUST 21,1987
]
STEAM GENERATOR EDDY CUP. RENT INSPECTION REPORT CYCLE 6 REFUELING OUTAGE (B2R06)
AUGUST OCTOBER 1996 Comed P.O. Box 767 Chicago,IL 60690 Byron Nuclear Power Station 4450 North German Church Road Byron,IL 61010
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f Documentation Completed Date: December 17,1996 9612270088 961217 PDR ADOCK 05000455 G
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TABLE OF CONTENTS 1
i 1.01NTRODUCTlON..................................................................................................................................1 2.0
SUMMARY
..........................................................................................................................................1 3.0 CERTIFICATIONS................................................................................................................................2 i
3.1 PROCEDURES /fMAMINATIONS/ EQUIPMENT..
.2 i
3.2 PERSONNEL.,
.. 2 4.0 EXAMINATlON TECHNIQUE AND EXAMIN ATION SCOPE............................................................... 3 4.1 INITIAL EXAMINATIONS...
.3 4.2 ADDITIONAL EXAMINATIONS..
.3 4.3 RECORDING OF EXAMINATION DATA.
.. 4 4.4 WITNESS AND VERIFICATION OF EXAMINATION.
.4 5.0 EXA MIN ATION RESU LTS.............................................
...............................................................4 5.1 INDICATIONS FOUND.
.4 6.0REPAlRS...............................................................................................................................................6 i
7.0 D O C U ME NTA*il O N.....................................................................
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8.0 FIG U RES/TA B LE S/ATTA C H M ENTS.................................................................................................... 1 i
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BYRON NUCLEAR POWER STATION
{
(B2R06) SG EDDY CURRENT REPORT 1
'1
1.0 INTRODUCTION
Byron Station Unit 2 operates with four Westinghouse Model D-5 recirculating steam generators in the four loop pressurized water reactor system. The steam generators contain thermally treated inconel-600 U-tubes that have a nominal outside diameter of 0.750 inches and a nominal thickness of 0.043 inches. See Figure 2 for a diagram of the Model D-5 Steam Generator configuration.
In compliance with Byron Station Technical Specification 3/4.4.5 and ASME Section XI (lWB 2500-1, Exam Category B-O, item B16.20),1983 Edition through Summer 1983 Addenda, Steam Generator (SG) eddy current examinations were conducted by Framatome Technologies during the Unit 2 Cycle 6 refueling outage beginning August 8,1996 through October 5,1996. The following inspections were performed during this outage:
- 100% Full length Bobbin inspection in each SG
- 25% top of tubesheet (Hot Leg)- Rotating Pancake Coil inspection in each SG
- 25% row 1 and 2 U-Bend Plus-Point inspection in each SG
(
- 25% Preheater expansion region in SG A - Rotating Pancake Coil Inspection 2.0
SUMMARY
Unit 2 shut down on August 8,1996 as a result of a primary to-secondary leak of approximately 120 GPD that was detected in SG A (D2F17). As a result of shutting the unit down early, it was decided to enter the refueling outage early. Consequently, the scheduled refuel eddy current inspection for this unit started earlier than originally planned. The tube that leaked was inspected (with eddy current and video probes). It was determined that a foreign object had caused the leak. The foreign object was removed from the SG and it was analyzed to determine its origin. The foreign object damaged four tubes in SG A, all of which were subsequently plugged.
An additional 26 tubes were repaired as a result of the normal eddy current inspections. Tables 2.1 represents the total number of tubes that were repaired during B2R06 and the reasons why they were p
repaired.
TABLE 2.1 Tubes Repaired during B2R06 Mode of Degradation SG A SG B SG C SG D Total Anti-Vibration Bar (AVB) Wear 3
8 5
3 19 Loose Part Degradation' 4
0 0
0 4
Preventative 4(")
2(")
1(*)
0 7
l Totals 111 10-6-
i3' L30 Notes:
i
' All four tubes in SG A were plugged as a result of the damage incurred due to the loose part that shut l
the unit down for B2F17.
These four tubes were plugged due to indications detected from approximately 2C+2.03" through 2C+5.00". in SG A.
Tube 1-2 in SG B was preventatively plugged due to a geometry change on the inside of the tube that caused the probe to skip over a section of tubing, thus not allowing a complete exam in the U-Bend p:\\sec\\stsup\\jkl\\ rep _9od. doc Page 1
1 BYRON NUCLEAR POWER STATION (B2R06) SG EDDY CURRENT REPORT region. Tube 20-57 in SG B was plugged as a result of an indication that exhibited a volumetric indication at 2C+0.76".
' Tube 22-29 in SG C was plugged as a result of an indication that exhibited a volumetric indication at 1 H+0.75".
3.0 CERTIFICATIONS 3.1 Procedures / Examinations / Equipment 3.1.1 The examination and evaluation procedures used dur:ng the eddy current inspection were approved by personnel qualified to Level 31 in accordance with the 1984 Edition of SNT-TC-1A. The procedures were approved in accordance with both Framatome and Comed Procedures.
3.1.2 The examinations, equipment, and personnel were in compliance with the requirements of the Framatome QA Manual for Inservice inspection, Byron Station Technical Specification 4.4.5, the 1983 Edition through Summer 1983 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code, and industry standards.
3.1.3 Certification packages for examiners, data analysts, and equipment are available at l
Byron Station. Table 1 of Section 7.0 lists all those personnel who performed, supervised, or evaluated the data during this inspection.
3.1.4 MlZ-30 equipment was used in the acquisition of the eddy current data and Eddynet 1
95 software was used in the analysis of the data.
3.2 Personnel 3.2.1 The personnel who performed the eddy current inspections were qualified to Level I and Level 11 in accordance with the 1984 Edition of SNT-TC-1A. The Level I personnel performed the inspections under the direct supervision of Level 11 personnel.
3.2.2 The personnel who performed the data analysis were qualified to a minimum of Level 11, with special analysis training (llA) in accordance with the 1984 Edition of SNT-TC-1 A, Framatome and Comed procedures.
3.2.3 All eddy current data analysts analyzing data in accordance with Generic Letter 95-03 were qualified in accordance with EPRI Appendix G for Qualified Data Analysts.
3.2.4 All eddy current analysts were trained and tested in both bobbin eddy current data and Rotating Pancake Coil (RPC)/Plus-Point data. The analysts were required to achieve a score of 80% or greater on this site specific demonstration exam.
3.2.5 The eddy current analysis was subject to two independent analyses. Primary analysis of all data was performed by Framatome Technologies and Rockridge Technologies. An independent company, Zetec, performed the secondary analysis.
p:\\sec\\stsup\\jkt\\ rep.90d. doc Page 2
BYRON NUCLEAR POVER STATION (B2R06) SG EDDY CURRENT REPORT Discrepancies between the two parties required Level ill concurrence between both parties har the final resolution.
4.0 EXAMINATION TECHNIQUE AND EXAMINATION SCOPE 4.1 Initial Examinations 4.1.1 All inservice tubes were inspected full length utilizing a 0.610" bobbin coil in accordance with Appendix H requirements. For rows 1-3 U-Bend regions,0.590" probes were utilized to achieve the complete full tube inspection.
4.1.2 Approximately 25% (1143 tubes) of all tubes in each SG were inspected with MRPC 3-coil probe at the secondary tubesheet interface on the hot leg only. These examinations were performed 2" above to 2" below the secondary tubesheet interface. This inspection was performed in response to NRC Generic Letter 95-03.
No indications were found as a result of this inspection.
4.1.3 Approxirrately 25% (34 tubes ) of the tubes in the preheater in steam generator A were nispected Ltilizing a 3 coil RPC probe, consisting of a 0.115" mid range pancake coil, an axial coil and a circumferential coil. This inspection was performed in response to NRC Generic Letter 95-03. No indica ^ ions were found as a result of this inspection.
4.1.4 Approximately 25% (57 tubes) of all U-Bend rows 1 and 2 in each steam generator were inspected utilizing a standard U-Bend Plus-Point probe. This inspection was performed in response to NRC Generic Letter 95-03. No indications were found as a result of this inspection. However, tube 1-2 in SG B was preventatively due to a geometry change on the inside of the tube that caused the probe to skip over a section of tubing, thus not allowing a complete exam in the U-Bend region.
4.1.5 All examinations were performed in accordance with Framatome procedure (54-1S1-400-01) and Comed surveillances and eddy current guidelines.
Note: See Figure 1 for tube sheet maps of the inspections performed during C?.R06.
4.2 Additional Examinations 4.2.1 Approximately 25% of tubes containing dents greater than 5.0 volts as sized by bobbin inspection were examined with an RPC probe consisting a 0.115" standard pancake coil, an axial coil, and a circumferential coil. This inspection was performed in response to NRC Generic Letter 95-03. No indications were found as a result of this inspection.
4.2.2 All indications in tubes that received an I-code (three letter analysis code that ends with the letter I) as called by bobbin coil analysis were further reviewed utilizing a standard 3-coil RPC probe containing a 0.080" pancake coil, axial coil, and a circumferential coil.
l-codes may be indications including Non-Quantifiable Indications (NQl), Free-Span Indications (FSI), Mixed Residual Indications (MRI),
p:\\sec\\stsup\\jkl\\ rep,90d. doc Page 3 I
BYRON NUCLEAR POWER STATION i
(B2R06) SG EDDY CURRENT REPORT Distorted Tubesheet Indications (DTI), and Distorted Roll Transition Indications (DRI).
4.3 Recording of Examination Data i
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4.3.1 Results of the eddy current data analysis were recorded on optical disks. The data i
was then loaded into the FTI's Eddy Current Data Management System (TUBAN 11).
This system was used to track the proper examination of all tubes and it was also used to generate the final eddy current report summaries.
4.4 Witness and Verification of Examination 1
4.4.1 Eddy current inspections were witnessed and/or verified by the Authorized Nuclear inservice inspectom Mr. J. Hendricks and T. Nuoffer of the Hartford Steam Boiler Inspection and insurance Company of Hartford Connecticut, Chicago Branch,2443 Warrenville Road, Suite 500, Lisle, Illinois 60532-9871.
5.0 EXAMINATION RESULTS The inspection results were found to be similar in each of the four steam generators. Based on all of the inspections identified in Section 4.0 of this report, Byron repaired a total of 30 tubes by using the inconel-690 mechanical plugs. Summarized below are the modes of degradation found during the B2F17/B2R06 outages.
5.1 Indications Found 5.1.1 Anti-Vibration Bar (AVB) Wear - This mode of degradation represented the highest mode (total number of indications detected) of active degradation found out of all of the types found during this inspection. A total of 799 indications were found that contained AVB wear.. As a result,19 tubes were removed from service based on the Technical Specification criteria of repairing tubes greater than or equal to 40%
Through-Wall (TW). See chart below which shows the distribution of AVB wear indications by each SG.
p:\\sec\\stsup\\jkl\\ rep _9od. doc Page 4
a BYRON NUCLEAR POWER STATION (B2R06) SG EDDY CURRENT REPORT AVB WEAR INDICATIONS IN EACH STEAM GENERATOR 120 100
~~
g
_ _' 84 84 _-
m f a<20% TU 66_ _
5 e20-29% TW i 40 0 30-39% 1YV O
gy= 40*4Tw]
20 0
SG A SG B SG C SG D STEAM GENERATOR 5.1.2 Foreion Object Wear - A total of four tubes were removed irom service as a result of the foreign object that caused the leak in SG A. The size of this object was 1.7" x 1.2" x 0.055" and it was triangular shaped. Analysis of this object revealed that it was thermal cutting debris from a 12-18" diamete, pipe. One of the four tubes (16-110) had a 100% TW indication, another tube (15-110) contained a 56% TW indication, and the other two tubes (15-109 & 15-111) were plugged as result of non-quantifiable volumetric indications found by RPC.
5.1.3 Other Reoairable Tubes - A total of seven additional tubes were repaired due to other reasons not mentioned above. Below is a summary of the additional tubes repaired.
SG A - Four tubes were plugged due to Outer Diameter (OD) originating indications detected from approximately 2C+2.03" through 2C+5.00". During the initial bobbin inspection, these tubes were identified to have possible sludge / object signals. As a result of detecting this signal, these tubes were both RPC inspected and visually inspected to further quantify this signal. Upon further review, it was determined that there were no loose parts in the area, however scale / deposit build up on the four tubes was found. One tube (49-74) was given the freespan Indication (FSI) bobbin code with a corresponding single volumetric indication (SVI) RPC code while the other three tubes (46-67,47-66, & 48-74) were classified as freespan differential (FSD) indications, generally a non-repairable condition per the Comed guidelines.
However, due to the scale / deposit build up discovered on all four tubes and the FSI-SV1 classification of one of the tubes, all tubes were plugged. The three tubes (46-67,47-66, & 48-
- 74) were preventatively plugged.
SG B - One of the tubes (1-2) in SG B was preventatively plugged due to a geometry change on the inside of the tube that caused the probe to skip over a section of tubing, thus not allowing a complete exam in the U-Bend region. The other tube (20-57) in SG B was plugged as a result of an indication that exhibited an OD originating volumetric indication at 2C+0.76".
During the initial bobbin inspection, this indication could not be quantified and was assigned a Non-p:\\sec\\stsup\\jkl\\ rep _90d. doc Page 5
BYRON NUCLEAR POWER STATION (B2R06) SG EDDY CURRENT REPOR T Quantifiable Indication (NQl) code. Bobbin historical review was conducted to determine growth from previous inspections. This review indicated that this indications exhibited minimal growth in both phase and amplitude. RPC was performed in this tube to further characterize this indication. This indication was i
determined to be non-crack like and dispositioned as a volumetric indication (SVI) per the Comed guidelines. As a result of both reviews (historical and RPC), it was determined to remove this tube from service.
SG C - The tube (22-29) plugged in SG C was plugged as a result of an indication that exhibited an OD originating volumetric indication at 1H+0.75". During the initial bobbin inspection, this indication could not be quantified and was assigned a Non-Quantifiable Indication (NQl) code. Bobbin historical review was conducted to determine growth from previous inspections. This review indicated that this indications exhibited minimal growth in both phase and amplitude. RPC was performed in this tube to further characterize this indication. This indication was determined to be non-crack like and dispositioned as a volumetric indication (SVI) per the Comed guidelines. As a result of both reviews (historical and RPC), it was determined to remove this tube from service.
- Note: See chart below for tubes repaired during B2R06 by steam generator.
REPAIRABLE INDICATION TYPES IN EACH STEAM GENERATOR 8
8 7
6
~~
5 m
4 4 '
5 AVB WEAR l h4
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3 Ui 3 h eLOOSE PART 2
2
,00THERs 1
0 SG A SG B SG C SG D STEAM GENERATOR 6.0 REPAIRS Repairs were conducted in accordance with ASME Section XI,1983 Edition through Summer 1983 Addenda for plugging. Attachment 2 of this report documents all repairs performed for each steam generator by using the NIS-2s. All repairs were performed using inconel-690 mechanical plugs. Also, all repairs were done in accordance with Framatome approved procedures. Table 6.1 depicts the repairs conducted during B2R06.
TABLE 6.1 REPAIRS CONDUCTED SG A SG B SG C SG D TOTAL Tubes Plugged 11*
10 6
3 30 Tube 16-110 had a cable stabilizer installed in the Cold Leg prior to plugging.
p:\\sec\\stsup\\jkhrep_9od. doc Page 6
BYRON NUCLEAR POWER STATION (B2R06) SG EDDY CURREnlT REPORT Note: Table 3 is a listing of all tubes repaired during B2R06. Figure 5 displays the tubesheet maps of all j
tubes plugged during B2R06.
7.0 DOCUMENTATION All original optical disks have been provided to Comed and are maintained at Byron Station. The final data sheets and pertinent tube sheet plots are contained in the Framatome Byron Unit 2 Final Outage Report, August 1996, and are also maintained at Byron Station.
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i BYRON NUCLEAR POWER STATION l
(B2R06) SG EDDY CURRENT REPORT 8.0 FIGURESITABLES/ ATTACHMENTS i
8.1 Figure 1 A: 2A SG Inspection Scope Figure 1B: 2B SG inspection Scope Figure 1C: 2C SG Inspection Scope Figure 1D: 2D SG Inspection Scope
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8.2 Figure 2: Model D-5 Support Configuration 8.3 Figure 3A: 2A AVB Wear Indications Figure 3B: 2B AVB Wear Indications Figure 3C: 2C AVB Wear Indications Figure 3D: 2D AVB Wear Indications 8.4 Table 1: Personnel Certification List 8.5 Table 2A: 2A SG ASME Form NIS-BB Table 28: 2B SG ASME Form NIS-BB Table 2C: 2C SG ASME Form NIS-BB Table 2D: 2D SG ASME Form NIS-BB 8.6 Attachment 1: ASME Form NIS-1 8.7 Attachment 2A: 2A SG ASME Form NIS-2 B: 2B SG ASME Form NIS-2 C: 2C SG ASME Form NIS-2 l D: 2D SG ACME Form NIS-2 8.8 Table 3:
SG Tubes Repaired 8.9 Figure 4A: 2A SG Tubes Plugged During B2ROG j
Figure 4B: 2B SG Tubes Plugged During B2R06 j
Figure 4C: 2G SG Tubes Plugged During B2R06 Figure 4D: 2D SG Tubes Plugged During B2R06 I
i
BYRON NUCLEAR POWER STATION (B2R06) SG EDDY CURRENT REPORT 8.1 Figure 1 A/B/C/D: 1 A/B/C/D SG Inspection Scopes (See Attached):
- 1) Figure 1A.1:
2A SG Bobbin inspection Scope
- 2) Figure 1A.2:
2A SG HL RPC TTS Inspection Scope
- 3) Figure 1A.3:
2A SG U-Bend Plus-Point Inspection Scope
- 4) Figure 1 A.4:
2A SG Pre-Heater Section RPC Inspection Scope Steam Generator B:
- 1) Figure 18.1:
2B SG Bobbin Inspection Scope
- 2) Figure 18.2:
28 SG HL RPC TTS Inspection Scope
- 3) Figure 18.3:
2B SG U-Bend Plus-Point inspection Scope i
- 1) Figure 1C.1:
2C SG Bobbin Inspection Scope
- 2) Figure 1C.2:
2C SG HL RPC TTS Inspection Scope
- 3) Figure 1C.3:
3C SG U-Bend Plus-Point inspection Scope Steam Generator D:
- 1) Figure 1D.1:
2D Bobbin inspection Scope
- 2) Figure 1D.2:
2D SG HL RPC TTS Inspection Scope
- 3) Figure 1D.3:
2D SG U-Bend Pius-Point Inspection Scope i
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-- - - - -. ~
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Figure 1A.1: 2A SG Bottin Inspection Scope All Tubes inspected - Bobbin.
B2R06 t
S/C A Byron SteCon Unit 2 Total Tulpes i 4678 Teeen Salented 4578 od of Servios ( ): N/A
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Table 1: Personnel Certifications EXPutATM DATE 2 NO,
- >Mn a COIFAIGY AWAG rALEVEL
@A (Y#f) E
> CERT' VISION
. ADEI :
1 Bames Robert Framatome AN l11 Y
8/8/98 11/26/96 Y
2 Bndgforth, W.D. (*)
Framatome AN llA Y
3/14/97 2/19/97 Y
3 Cooper, Lawrence Framatome AN llA Y
3/6/97 2/15/97 Y
4 Johnson, K. L (*)
Framatome AN llA Y
2/24/97 11/6/96 Y
5 Korkowski, Edward Framatome AN llA Y
1/20/99 10/30/96 Y
6 Kovalesky, Thomas Framatome AN IM Y
11/10/97 1/10/97 Y
7 Loer, M. S.
Framatome AN llA Y
4/3/97 2/15/97 Y
8 Martm, Alfred Framatome AN llA Y
2/8/97 1/10/97 Y
9 Ohver, John Framatome AN llA Y
3/15/97 8/14/97 Y
10 Pamsh, John Framatome AN IM Y
12/17/96 8/14/97 Y
11 Porter, Mchael Framatome AN llA Y
2/21/97 3/7/97 Y
12 Rearc. Thomas Framatome AN llA Y
3/15/97 2/18/97 Y
13 Schhcht. Wayne Framatome AN llA Y
3/3/97 2/20/97 Y
14 Schwenn, J. S.
Framatome AN llA Y
1/6/97 6/5/97 Y
15 Washbum, Tereses Framatome AN llA Y
9/8/96 6/13/97 Y
j 16 Bowen, Edward Rockridge AN llA Y
12/17/96 9/24/96 Y
17 Caperello, Matthew Rockndge AN llA Y
7/12/98 6/19/97 Y
18 Defthppis Nck Rockridge AN llA Y
2/9/99 6/9/97 Y
19 Dugas. Kenneth Rockndge AN llA Y
7/29/97 1/22/97 Y
l 20 Fuller, Curtrs Rockndge AN llA Y
8/20/99 6/16/97 Y
21 Gortemdier, Cheryl Rockndge AN til Y
1/11/97 8/18/97 Y
22 Hall, Kerry Rockridge AN
!!A Y
5/11/98 6/14/97 Y
f 23 Herrara, Gerald Rockridge AN llA Y
2/7/98 6/13/97 Y
24 Holden, Thomas Rockridge AN lil Y
9/17/97 8/14197 Y
25 Janet, Jerome Rockridge AN llA Y
2/8/98 3/18/97 Y
26 Jones, Mark Rockridge AN llA Y
11/23/97 1/8/97 Y
27 Kerson, Chuck Rockndge AN llA Y
12/17/96 12/10/96 Y
l 28 Lofgren Robert Rockridge AN llA Y
12/8/96 11/9/96 Y
29 Merriam, Rchard Rockndge AN 111 Y
11/7/97 8/12/97 Y
30 Mut, Anthoi,y Rockridge AN llA Y
1/24/98 9/24/96 Y
31 Nethercott, James Rockridge AN IIA Y
2/9/98 6/16/97 Y
32 Raybum, Donald Rockridge AN llA Y
8/4/98 6/9/97 Y
33 ShitWey, David Rockridge AN llA Y
7/13/98 12/4/96 Y
34 Alspaugh, Kenneth (*)
Zetec AN llA Y
12/11/98 12/26/96 Y
35 Darrah, Jerry Zetec AN lil Y
1/21/94 11/28/96 Y
36 Driessen, Nathan Zetec AN liA Y
1/20/98 11/20/96 Y
37 Farenbaugh, Neil Zetec AN lil Y
7/22/97 2/12/97 Y
38 Ferdenand, Mutiael Zetec AN llA Y
6l23/98 2/19/97 Y
39 Ginther, Charles Zetec AN til Y
11/?i38 SMi/97 Y
40 Gray, Wayne Zetec AN lil Y
1/25/99 3/11/97 Y
41 isakson, Mchael Zetec AN llA Y
12/17/96 3/18/97 Y
42 Lucier Lewis Zetec AN til Y
11/22/98 7/26/96 Y
Page 1 of 2
Table 1: Personnel Certifications ERPORATION DATE : ?
NO, un>NARE COMPANY
-2 ANfAQ &
LEVEL
< QDA (YtN) e iCERT' 1 VISION
~ ANil 43 Mayer. Daniel Zetec AN llA Y
8/18/97 1/4/97 Y
44 Nelson, David Zetec AN til Y
12/15/98 6/3/97 Y
45 Nrssely Raymond Zetec AN ll!
Y 4/29/97 12/7/96 Y
46 Notch, Paul Zetec AN llA Y
12/17/96 2/26/97 Y
47 O'Laughhn, Mechsel Zetec AN llA Y
1/21/97 3/13/97 Y
48 Rachiatore, Jeffrey Zetec AN lil Y
9/2/98 5/2/97 Y
49 Schmrtz, Kenneth Zetec AN llA Y
1/20/98 2/1/97 Y
50 Tanner, Douglas Zetec AN til Y
5/20/99 6/30/97 Y
51 Almond, David (*)
1/29/99 1/29/97 Y
52 Cotado. Lawrence Framatome AQ llA Y
2/8/97 8/27/96 Y
53 Conner, Mchael Framatome AQ 11 N
7/24/99 2/19/97 Y
54 Farrar, Curtis (*)
1/29/99 1/29/97 Y
55 Jett, Richard Framatome AQ lt N
2/24/99 1/23/97 Y
56 Johnson, Albert Framatome AQ lt N
1/24/99 1/23/97 Y
57 Keyes.Les Framatome AQ l
N 3/7/99 7/7/97 Y
58 Pendergrass Robert Framatome AQ llA N
3/14/97 1/28/97 Y
59 Pertuns, Ray Framatome AQ ilA N
9/17/98 8/7/97 Y
60 Phelps. Mchael Framatome AQ IT N
1/12/98 1/21/97 Y
61 Taylor, Steven Framatome AQ l
N 11/17/97 8/1/97 Y
62 Womack, J. (*)
Framatome AQ l
N 1/24/99 1/23/97 Y
63 Ashford, Gary (*)
Rockndge AQ 11 N
11/24/96 12/7/96 Y
64 Bautisita, Mark Rockridge AQ l
N 6/22/98 6/7/97 Y
65 Bolanos, Juan Rockridge AQ l
N 2/16/99 2/1/97 Y
66 Boreliz, M:chael Rockridge AQ 11 N
12/15/98 8/7/97 Y
67 Davis, Grant Rockndge AQ l
N 2/3/98 12/6/96 Y
68 Johnson, P_arry Rockridge AQ 11 N
8/14/99 8/12/97 Y
69 Klenfeld, Stephen Rockridge AQ 11 N
7/26/98 7/28/97 Y
70 Largey, Charles Rockndge AQ 11 N
6/27/97 6/8/97 Y
71 No' ton, Ncholas (*)
Rockndge AQ l
N 3/1/99 12/3/96 Y
72 Ready,Sean Rockndge AQ 11 N
6/27/97 6/23/97 Y
73 Saw=_alos. Ncholas Rockndge AQ l
N 6/15/98 3/22/97 Y
74 Vaughn, James (*)
Rockndge AQ l
N 2/16/99 1/18/97 Y
75 Vouyioukas. Kosta Rockndge AQ l
N 2/3/98 12/5/96 Y
76 Vouyunskas. Kosta Rockridge AQ 11 N
8/1/99 12/5Si Y
77 Webb, Mcabel Rockndge AQ l
N 3/1/99 12/3/96 Y
78 Wnght. Jason Rockridge AQ l
N 3/1/99 11/30/96 Y
79 Wnght, Kevin (*)
Rockndge AQ llA N
1/24/98 11/5/96 Y
80 Chnstoe. Joel Zetec AQ 11 N
1/24/98 1/4/97 Y
81 Huff Walter Zetec AQ 11 N
6/16/98 6/5/97 Y
82 Leuenberg, Anthony Zetec AQ l
N 1/12/99 12/4/96 Y
- See reviewed personnel certificatsons from the B1R07 Refueling Outage (April-June 1996)
Page 2 of 2
~_.
___ _ _ _ _. _ _ _ _ _ _. _.... _ _. _ _ _ _. _ _. _ _.. _. _..... _. ~...... _. _.
Tcble 2A: 2A ASME Fcrm NIS-SS Sheet 1 of 5 I
t l
Form NIS4B SECTION XI-DIVISION 1 i
f FORM NIS4B TU3E EXAMINATION REPORT f
EDDY CURRENT EXAMINATION RESULTS l
Site: Byron Station, Unit 2 Steam Generator: 2RC018A l
Test Frequency: 20,130,300,500 kHz Date:
12/5/96 1
i
% Tube Wall f
Row Column Penetration Origin Location l
}
15 110 56 ODI TSC+1.09 j
19 5
18 ODI AV4
)
j 20 6
17 ODI AV4 I
i 20 64 19 ODI AV1 i
l 22 109 20 ODI AV4
[
1 23 109 20 ODI AV4 l
j 25 8
15 ODI AV4 25 8
28 ODI AV3 j
25 106 19 ODI AV1 t
26 106 15 ODI AV1 v
26 107 19 ODI AV2 l
26 107 26 0 01 AV3 l
27 18 23 ODI AV1 27 85 31 ODI AV2 i
27 104 21 ODI.
AV2 27 106 31 ODI AV1 i
I 27 106 34 ODI AV3 l
27 106 27 ODI AV2
]
28 99 18 ODI AV1 1
1 l-28 104 18 0 01 AV4 l
l 28 105 20 ODI AV3 28 105 24 ODI AV4 29 10 35 ODI AV3 l
29 12 20 ODI AV3 29 12 21 ODI AV2 i
29 13 26 ODI AV3 I
30 69 23 ODI AV2
}'
30 70 15 0 01 AV2 30 103 27 ODI AV2 30 105 25 ODI AV2 3-31 12 22 ODI AV4 j'
31 12 24 ODI AV3 j
31 14 22 ODI AV4 31 14 23 ODI AV3 31 67 18 ODI AV4 f
31 101 30 ODI AV2 31 101 33 ODI AV3 31 103 30 0 01 AV3 4
i 31 103 27 ODI AV2 32 76 16 ODI AV3 34 14 23 ODI AV2 34 14 16 ODI AV3 34 90 26 ODI AV3
- 35 15 19 ODI AV4 s
4
- Note: This is a computer generated form.
Tcble 2A: 2A ASME Fcrm NIS CB Sheet 2 of 5 i
j Form NIS-BB l
SECTION XI DMSION 1
}
FORM NIS-88 TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS i
Site: Byron Station, Unit 2 Steam Generator: 2RC01BA l
' Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall 1-Row Column Penetration Origin Location 35 15 23 ODI AV3 35 16 27 ODI AV3 35 16 29 ODI AV2 i
j 35 100 21 ODI AV3 1
36 15 20 0 01 AV3 36 15 26 ODI AV4 1
3 l
36 16 39 ODI AV2 J
36 18 24 ODI AV2 1
l 36 18 24 ODI AV3 i
36 21 16 ODI AV4 36 21 22 0 01 AV3 l
36 95 15 ODI AV3 36 96 23 ODI AV2
)
37 17 31 ODI AV3 37 18 19 ODI AV4 37 18 22 ODI AV2 i
37 19 19 ODI AV4 37 19 21 ODI AV1 l
37 19 23 ODI AV3 1
i.
37 20 24 ODI AV3 37 20 17 ODI AV2 37 21 18 ODI AV3
?
37 23 30 ODI AV3 l
37 23 31 ODI AV2 37 23 19 ODI AV4 l
37-98 36 ODI AV3 l.
37 98 37 0 01 AV2 37 99 22 ODI AV3 38 16 23 ODI AV4 38 16 28 0 01 AV3 38 19 25 ODI AV3 1
38 19 25 ODI AV4 38 20 16 ODI AV3 j
38 20 31 ODI AV2 38 20 25 ODI w/4 4
38 20 26 ODI AV1 38 21 22 ODI AV3
)
38 21 24 ODI AV1 38 22 24 ODI AV2 3
38 23 26 ODI AV1 38 23 30 ODI AV4 38 23 34 ODI AV3 1
38-24 23 ODI AV3 38 24 29 ODI AV2
- Note: This is a computer generated form.
j Table 2A: 2A ASME Ferm NIS-BD Sheet 3 of 5 4
Form NIS-BB SECTION XI-DIVISION 1 1
FORM NIS-BB TUBE EXAMINATION REPORT J
EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BA l
Test Frequency: 20,130,300,500 kHz Dele:
12/6/96
)
3'
% Tube Wall Row Column Penetration Origin Location 38 26 23 ODI AV2 j
38 27 20 ODI AV3
)
38 30 27 ODI AV3 38 30 17 ODI AV2 I
38 30 17 ODI AV4
~
38 34 15 ODI AV3 38 63 15 ODI AV4 38 68 15 ODI AV3 38 68 18 ODI AV1 l
38 66 37 ODI AV2 i
j 38 72 27 ODI AV3 38 73 27 ODI AV3 I
38 98 24 ODI AV1 38 98 15 ODI AV3 d
38 98 34 ODI AV2 39 17 22 ODI AV3 39 19 36 ODI AV3 39 19 38 0 01 AV4 39 19 40 ODI AV2 i
39 21 23 ODI AV4
?
39 21 34 ODI AV3 39 23 17 ODI AV2 39 23 18 ODI AV1 39 23 30 ODI AV3 39 85 18 ODI AV2 39-89 28 ODI AV3 f
39 89 32 0 01 AV2 39 89 24 ODI AV4 39 94 20 ODI AV1 39 94 34 ODI AV3 39 94 15 ODI AV2 I
39 96 15 ODI AV4 39 96 17 ODI AV3 39 97 16 ODI AV4 39 98 36 ODI AV4
]
39 98 42 ODI AV3 40 19 23 ODI AV2 4
40 19 29 ODI AV4 j
40 21 32 ODI AV3 4
40 21 39 ODI AV2
{
40 21 25 ODI AV4 40 46 21 ODI AV3 40 46 18 ODI AV1 40 64 16 ODI AV1 l
l U
- Note: This is a computer generated form.
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Tchle 2A: 2A ASME Fcrm NIS-B3 Sheet 4 of 5 i
Form NIS-BB j
SECTION XI-DIVISION 1 4
)
l FORM NIS-BB TUBE EXAMINATION REPORT l
EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BA j
4 Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location 40 66 21 ODI AV1 I
40 82 18 ODI AV3 4
40 82 29 ODI AV2 40 85 21 ODI AV3 40 90 17 ODI AV4 40 90 26 0 01 AV3 4
40 90 27 ODI AV2 40 91 27 ODI AV3 40 92 20 ODI AV3 40 Fi 20 ODI AV2 40 95 25 ODI AV2 40 95 30 ODI AV3 40 95 33 ODI AV4 40 95 23 ODI AV1 41 20 20 ODI AV2
)
41 20 29 ODI AV4 41 20 34 ODI AV3 41 22 36 ODI AV2 41 33 17 ODI AV2 i
41 33 24 0 01 AV3
(
a 41 84 23 ODI AV3
)
41 85 22 ODI AV3 41 87 21 ODI AV4 41 87 25 ODI AV3 1
41 87 29 ODI AV2 41 88 21 ODI AV2 41 91 20 ODI AV2 r
41 91 25 ODI AV3 41 92 15 ODI AV3 41 92 26 ODI AV2 41 92 28 ODI AV4 41 93 38 ODI AV2 41 93 20 0 01 AV1 41 93 24 ODI AV4 41 93 31 ODI AV3 41 95 32 ODI AV4 41 95 17 ODI AV2 41 95 28 0 01 AV3 42 21 20 ODI AV4 42 25 18 ODI AV2 42 25 26 ODI AV4 42 25 34 ODI AV3 43 34 24 ODI AV2 43 34 29 ODI AV3
- Note: This is a computer generated form.
. _. ~. _ -. _..
Table 2A: 2A ASME Fcrm NIS-83 Sheet 5 of 5 i
i-2 Form NIS-8B i
SECTION Al. DIVISION 1
+
i
- FORM NIS-BB TUBE EXAMINATION REPORT j
EDDY CURRENT EXAMINATION RESULTS j
Site: Byron Station, Unit 2 Steam Generator: 2RC01BA
)
Test Frequency: 20,130,300,500 kHz Date:
12/5/96 4
% Tube Wall Row Column Penetration Origin Location 43 34 34 ODI AV4
=
44 23 18 ODI AV4 2
44 59 17 ODI AV3 44 81 31 ODI AV2 l
l 44 81 22 ODI AV3 44 88 20 ODI AV4
)
44 88 31 ODI AV3 44 90 26 ODI AV2 44 90 34 ODI AV3 45 24 25 ODI AV3 45 24 30 ODI AV4 45 25 20 ODI AV3 l
45 25 22 ODI AV4 i
45 28 32 ODI AV4 45 28 34 ODI AV3 45 30 27 ODI AV4 i
45 30 34 ODI AV3 45 30 40 ODI AV2 l
45 89 24 ODI AV4 46 64 31 ODI AV3 46 64 32 0 01 AV4 46 89 23 ODI AV4 47 28 19 ODI AV4 47 59 20 ODI AV1 47 61 20 ODI AV3
]
48 56 15 ODI AV4 48 56 28 ODI AV3 49 51 16 ODI AV4 I
I
- Note: This is a computer generated form.
j i
.,I
-_.m.___._.._._._..__
_._..._..__.s TAILE 28: 23 ASME Farm NIS-83 Sheet 1 of 7 t
Fonn NIS-88 SECTION XI-DIVISION 1 r
FORM NIS-BB TUSE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location i
10 39 19 ODI AV4
?
18 48 34 ODI AV1 f
23 106 15 ODI AV2 23 108 34 ODI AV2 24 106 15 ODI AV2 24 107 18 ODI AV3 24 107 18 ODI AV2 1
24 108 26 ODI AV4 25 103 26 0 01 AV2 25 104.
26 ODI AV2 25 107 23 ODI AV2 25 107 24 ODI AV3 i
25 108 29 ODI AV4 26 10 15 ODI AV2 26 10 17 ODI AV3 26 105 31 ODI AV3 26 107 16 ODI AV2 j
27 10 15 ODI AV2
]
27 31 18 ODI AV4 27 105 30 ODI AV2 27 105 17 ODI AV4 27 105 16 ODI AV1 27 105 15 ODI AV3 28 11 19 -
0 01 AV4 28 11 23 ODI AV2 28 11 37 ODI AV3 28 12 20 ODI AV2 28 27 15 ODI AV2
~~
28 27 18 ODI AV3 28 29 15 ODI
~ AV2 28 29 16 ODI AV3 28 32 15 ODI AV2 28 37 23 ODI AV3 28 79 16 ODI AV3 28 99 18 ODI AV2 28 102 23 0 01 AV3 28 103 15 ODI AV2 28 103 25 ODI AV3 28 104 24 ODI AV2 28 104 21 ODI AV3 28 105 28 ODI AV2 28 105 40 ODI AV1 29 15 15 ODI AV2 29 15 16 ODI AV4 J
- Note: This is a computer generated form.
.= -
i
}
TA"LE 28: 23 ASME Fcrm NIS-BB Sheet 2 of 7 2
' Form NIS-BB 3
SECTION ? - OlVISION 1 FORM NIS-BB TUBE EXAWilNATION REPORT i-EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/5/03 1
6 l
% Tube Wall Row' Column Penetration Origin Location i
29 98 15 ODI AV4 29 98 20 ODI AV2 29 105 24 0 01 AV2 l
29 105 26 ODI AV4 i
30 13 24 ODI
_AV3 30 14 16 ODI AV3 30 99 17 ODI AV3 30 101 15 ODI AV1 30 102 21 ODI AV3 30 102 32-ODI AV2 30 105 33 ODI AV4 31 12 25 ODI AV4 31 12 19 ODI AV1 31 12 23 ODI AV3 31 13 19 ODI AV1
- 31 13 22 ODI AV4 31 15 29 ODI AV2 31 16 17 ODI AV3 31 17 18 ODI AV3 31 17 21 ODI AV2 31 34 18 ODI AV3 31 102 22 ODI AV3 32 12 27 ODI AV2 32 28 21 0 01 AV3 32 28 30 ODI AV2 32 32 33 ODI AV3 32 39 16 ODI AV4 32 40 23 ODI AV3 32 40 15 ODI AV4 32 40 20 ODI AV2 32 98 15 ODI AV3 33 13 23 ODI AV1 33 14 12 ODI AV3 33 14 18 ODI AV4 33 14 34 ODI AV2 33 14 37 ODI AV1 33 72 21 ODI AV3 33 97 35 ODI AV3 33 99 29 ODI AV2 33 99 25 ODI AV3 33 99 19 ODI AV4 33 99 21 ODI AV1 t.
33 102 19 ODI AV1 33 102 41 ODI AV4
- Note: This is a computer generated form.
TASLE 28: 2B ASME Fcrm NIS-BB sheet 3 of 7 4
i Form NIS-BB SECTION XI DIVISION 1 FORM NIS-BB TUBE EXAMINATION REPORT a
EDDY CURRENT EXAMINATIC'N RESULTS i
l Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location 34 14 19 ODI AV3 34 16 17 ODI AV3 34 16 19 ODI AV4 34 17 22 ODI AV3 34 19 20 ODI AV3 34 26 24 ODI AV3 34 30 19 ODI AV3 34 33 24 ODI AV2 34 36 15 ODI AV3 34 36 23 ODI AV2 34 39 21 ODI AV2 34 99 15 ODI AV3 34 100 15 ODI AV3 4
35 14 19 ODI AV3 35 15 33 ODI AV2 l
35 16 28 ODI AV3 35 96 24 ODI AV3 3
35 97 36 ODI AV3 35 98 15 ODI AV1 35 98 24 ODI AV4 35 98 19 ODI AV3 35 99 17 ODI AV3 I
35 99 24 ODI AV4 f
35 100 19 ODI AV3 35 100 22 ODI AV4 35 100 25 ODI AV2 35 101 37 ODI AV3 35 101 33 ODI AV4 36 16 34 ODI AV3 36 16 18 ODI AV4 36 16 26 ODI AV2 36 17 15 ODI AV3
)
36 17 24 ODI AV2 36 18 21 ODI AV3 36 18 23 ODI AV2 36 20 25 ODI AV2 36 23 23 ODI AV2 I
36 78 22 ODI AV3 i
36 88 17 0 01 AV3 I
36 94 14 0 01 AV4 36 94 23 ODI AV2
~
36 95 19 COI AV1 36 95 40 OL'l AV3 36 97 41 ODI AV2 4
- Note: This is a computer generated form.
I TACLE 28: 23 ASME F:rm NIS-BB sheet 4 of 7 Form NIS4B SECTION XI. OlVISION 1 i
FORM NIS-BB TUBE EXAMINATlON REPORT I
4 EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/5/96 j
% Tube Wall j
i Row Column Penetration Origin Location j
l 36 97 43 ODI AV1 t
36 97 38 ODI AV4 36 97 44 ODI AV3 i
37 83 20 ODI AV2 37 90 17 ODI AV2 l
3 O
A 37 93 28 ODI AV3 I
37 94 17 ODI AV2 37 95 22 ODI AV3 37 95 16 ODI AV4 4
38 44 22 ODI AV1
~
3 38 44 33 ODI AV2
)
38 44 33 ODI AV3 38 44 37 ODI AV4 i
i 38 71 35 ODI AV3 j
38 71 16 ODI AV1 38 71 22 ODI AV2 i
38 93 19 ODI AV3 1
l 38 93 16 ODI AV4
)
38 93 18 ODI AV2 1
38 95 28 0 01 AV2 38 95 31 0 01 AV3 j
38 95 31 ODI AV1 1
38 95 32 ODI AV4 38 96 33 ODI AV4 38 96 28 -
ODI AV2 i
38 96 26 ODI AV1 38 96 18 ODI AV3 4
i 39 19 35 ODI AV3 39 19 36 ODI AV2 5
39 19 18 ODI AV4 l --
39 20 19 ODI AV2 39 21 19 ODI AV2
)
39 21 22 ODI AV3 39 26 23 ODI AV2 j
39 26 15 ODI AV3 i
39 39 22 ODI AV2 1
39 88 18 ODI AV2 I
39 92 73 ODI AV4 39 93 19 ODI AV4 39 93 23 ODI AV3 f
39 94 32 ODI AV3 39 94 20 ODI AV2 1
' Note: This is a computer generated form.
4 s
=
TACLE 2B: 2B ASME Fcrm NIS-BB Sheet 5 of 7 Fonn NIS-BB SECTION XI-DIVISION 1 t
FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location 39 B4 20 ODI AV4 3
39 95 25 ODI AV2
]
39 95 25 ODI AV3 39 95 21 ODI AV4 39 96 16 ODI AV4 39 96 18 ODI AV1 i
39 96 35 ODI AV2 40 18 22 ODI AV1 40 18 36 ODI AV2 40 18 36 ODI AV3 40 20 28 ODI AV2 40 20 31 ODI AV3 3
40 20 22 ODI AV4 40 24 21 ODI AV2 40 26 18 ODI AV2 40 27 20 0 01 AV3 40 34 25 ODI AV2 40 59 15 ODI AV4 40 59 18 ODI AV3 40 61 25 ODI AV2 40 61 38 ODI AV3 40 61 26 ODI AV4 40 88 21 0 01 AV2 40 91 23 ODI AV2 l
40 92 32 ODI AV3 40 94 34 ODI AV2 1
40 95 15 ODI AV3 40 95
'19 ODI AV4 41 43 23 ODI AV1 41 43 23 ODI AV2 41 43 33 ODI AV3 41 56 19 ODI AV1 i
41 56 32 ODI AV3
)
j 41 56 39 ODI AV2 1
41 59 42 ODI AV3 41 59 20 ODI AV2 i
41 85 16 ODI AV2 41 87 20 ODI AV3 41 87 24 ODI AV2 1
41 93 24 ODI AV4 41 93 25 ODI AV2 41 93 28 ODI AV3 41 95 20 ODI AV1 41 95 30 ODI AV3
' Note: This is a computer generated form.
. r l
l TACLE 23: 23 ASMf! Fcrm NIS *3 Sheet 6 of 7 Foca NIS-8B i
SECTON XI-DIVISION 1 FORM NIS4B TUBE EXAMINATION REPORT i
EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/6/96
% Tube Wall Row Column Penetration Origin Location 41 95 36 ODI AV2 42 30 19 ODI AV1 42 30 35 ODI AV3 42 31 19 ODI AV2 42 31 18 ODI AV3 42 35 33 ODI AV4 42 35 38 ODI AV3 42 35 42 ODI AV2 42-36 15 ODI AV2
- 42 37 32 ODI AV3 42 37 27 ODI AV2 42 44 30 ODI AV3 42 68 19 ODI AV2 42 68 19 ODI AV3 42 84 16 ODI AV2 42 84 17 ODI AV3-42 86 19 ODI AV2 42 89 33 ODI AV1 -
42 89 27 ODI AV2 42 89 28 ODI AV3 43 25 23 ODI AV2 43 25 15 ODI AV4 43
- 25 18 ODI AV3 43 -
29 21 0 01 AVI 43 29 38 ODI AV2-43 91 23 ODI AV3 43 92 21.
ODI AV3 44 26 33 ODI AV2 I
44 45 24 ODI AV3 44 76 16 ODI AV3 44 76 18 ODI AV2 44 80 23 ODI AV4 44 80 32 ODI AV2 44 80 44 ODI AV3 44 85 24 ODI AV2 44 85 29 ODI AV4 44 85 33 0 01 AV3 44 90 21 ODI AV4-44 90 35 0 01 AV3 45 26 31 ODI AV2 45 26 38 ODI AV3 45 26 25 ODI AV4 45 29 15 ODI AV4 45 32 20 ODI AV2
- Note: This is a computer generated form.
f TACLE 22: 2B ASME Fcrm NIS-83 Sheet 7 of 7 Form NIS4B i
SECTION XI. DIVISION 1 I
I FORM NIS4B TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS
. Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130,300,500 kHz Date:
12/6/96 l
% Tube Wall Row Colamn Penetration Origin Location 45 32 26 ODI AV3 45 36 -
21 ODI AV3 45 36 25 ODI AV4 45 83 20 ODI AV3 45 83 21 ODI AV4 45 83 26 ODI AV2 45 84 20 ODI AV3 45 84 42 ODI AV2
~
45 86 23 0 01 AV3 45 86 25 ODI AV2 45 89 23 ODI AV3 45 89 28 ODI AV2 47 27 24 ODs AV3 47 27 34 ODI AV4 47 27 24 ODI AV2 47 56 22 ODI AV2 47 76 15 ODI 02C+0.46 49 51 15 ODI 07C i
i
- Note: This is a computer generated form.
4 Y
TAELE 2C: 2C ASME Ferm NIS-BB Sheet 1 of 5 Form NIS-BB SECTION XI-DIVISION 1 i
FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BC Test Frequency: 20,130,300,600 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location 22 6
18 ODI AV1 22 6
18 ODI AV4 i
23 6
29 ODI AV4 i.
25 105 18 ODI AV2 25 106 21 ODI AV1 25 107 26 ODI AV4 25 108 19 ODI AV1 25 108 23 ODI AV2 25 108 24 ODI AV3 26 8
19 ODI AV2 26 9
15 ODI AV2 26 9
19 ODI AV3 26 9
28 ODI AV4 26 85 21 ODI AV2 27 34 17 ODI AV3 27 106 34 ODI AV3 27 106 23 ODI AV2 28 35 19 0 01 AV4 28 35 22 ODI AV3 28 84 27 ODI AV3 28 103 32 ODI AV3 29 11 21 ODI AV1 29 29 20 ODI AV3 29 29 26 ODI AV2 29 38 16 ODI AV3 29 40 19 ODI AV3 29 40 19 ODi AV2
_30 35 25 ODI AV3 30 99 15 ODI AV2 30 104 15 ODI AV3 30 105 18 ODI AV4 31 12 27 ODI AV3 31 14 30 ODI AV1 31 14 35 ODI AV3 31 50 18 ODI AV1 31 77 15 ODI AV2 31 82 21 ODI AV3
+
31 86 16 ODI AV3 32 13 25 ODI AV3 32 13 18 ODI AV2 1
32 28 15 ODI AV2 32 28 19 ODI AV3 32 73 17 ODI AV3 32 74 20 ODI AV3
- Note: This is a computer generated form.
i TA!LE 2C: 2C ASME Fcrm NIS-BB Sheet 2 of 5 Form NIS-88 SECTION XI DIVISION 1 -
i k
s FORM NIS-88 TUBE EXAMINATION RFPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator 2RC018C Test Frequency: 20,130,300,500 kHz Date:
12/6/96 a
j'
% Tube Wall i
Row Column Penetration Origin Location i
32 79 17 ODI AV2 l
32 79 22 ODI AV3
]
32 82 28 ODI AV2 32 83 17 ODI AV1 32 83 24 ODI AV3 32 100 18 ODI AV3 j
33 39 17 ODs AV2
]
33 39 15 ODI AV3 1
33 81 21 ODI AV3 1
33 81 15
. ODI AV4 33
-103 16 ODI AV4 34 16 16 ODI -
AV3 j
34 27 28 ODI AV2 j
34 29 19 ODI AV3 34 29 20 ODI AV2 4
34 85 16 ODI AV2 l
34 92 16 ODI AV3 1
34 92 22 ODI AV2
- 34 94 20 ODI AV2 34 95 16 ODI AV2 h
35 18 21 0 01 AV2 35 22 22 ODI AVI 35 22 25 ODI AV3 l
35 25 28 ODI AV2 1
35 25 25 ODI AV3 j
35 30 23 ODI AV?.
35 82 24 ODt AV3 l
35 85 15 ODI AV1-i; -
35 85 24 ODI AV2 1
35 85 34 ODI AV3 f
35 86 16 ODI AV1 j.
35 86 35 ODI AV2 35 87 16 ODI AV3 35 88 19 0 06 AV3 35 95 26 ODI AV2
{
35 96 15 ODI AV4 j
35 96 19 ODI AV2 36 19 16 ODI AV2 36 19 29 ODI AV3 i
36 20 18 ODI AV2 33 20 23 ODI AV3
}
36 21 33 ODI AV3 36 22 18 ODI AV2 36 22 25 ODI AV3 1
1
- Note: This is a computer generated form.
4
)
TACLE 2C: 2C ASME Fcrm NIS-BB Sheet 3 of s i
Form NIS-BB SECTION XI-DIVISION 1 l
l FORM NIS-BB TUBE EXAMINATION REPORT 1
EDDY CURRENT EXAMINATION RESULTS l
Site: Byron Station, Unit 2 Steam Generator: 2RC01BC 44t Frequency: 20,130,300,500 kHz Date:
12/5/96 l
% Tube Wall Row Column Penetration Origin Location 36
.4 15 ODI AV1 3
l 36 24 30 ODI AV3 36 25 22 ODI AV2 36 27 21 ODI AV3 36 31 40 ODI AV3 36 31 19 ODI AV2 36 80 22 ODI AV3 36 81 15 ODI AV3 36 93 17 0 01 AV2 36 94 17 0 01 AV2 36 96 26 ODI AV2 37 17 23 ODI AV1 37 20 18 ODI AV2 3
37 23 17 ODI AV2 37 34 18 ODI AV3 37 84 18 ODI AV3 4
37 99 16 ODI AV4 37 99 28 ODI AV3 37 99 37 ODI AV2 35 16 ODI AV2 38 16 26 ODI AV1 38 22 20 ODI AV3 38 22 21 ODI AV2 38 22 27 ODI AV1 38 25 15 ODI AV3 38 25 17 ODI AV1 J
38 25 27 ODI AV2 I
38 62 20 ODI AV2 38 62 21 ODI AV3 38 99 20 ODI AV2 39 17 16 ODI AV3 39 18 18 ODI AV2 4
I 39 18 23 ODI AV4 39 18 41 ODI AV3 39 19 25 ODI AV3 39 20 28 ODI AV2 39 25 19 ODI AV1 39 26 19 ODI AV3 39 35 31 ODI AV2 39 35 32 ODI AV3 39 38 20 ODI AV3 39 49 24 ODI AV2 I
39 79 18 ODI AV1 39 79 23 ODI AV4
- Note: This is a computer generated form.
TACLE 2C: 2C ASME Fcrm NIS-B3 Sheet 4 of 5 i
Form NIS-BB SECTION XI DIVISION 1 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BC Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location 39 79 40 ODI AV2 39 79 41 0 01 AV3 39 83 25 0 01 AV2 39 93 22 0 01 AV4 39 94 17 ODI AV3 39 94 21 ODI AV2 40 21 19 ODI AV3 40 21 36 ODI AV2 40 62 39 ODI AV1 40 62 42 ODI AV3 40 62 32 ODI AV4 40 62 46 ODI AV2 s
40 83 26 ODI AV3 40 83 29 ODI AV2 40 86 16 ODI AV2 40 90 17 ODI AV2 40 90 18 ODI AV3
- 40 93 15 ODI AV2 40 93 17 ODI AV1 40 93 30 ODI AV3 40 95 32 ODI AV3 40 95 23 ODI AV1 41 21 38 ODI AV2 41 21 20 ODI AV3 41 26 19 ODI AV2 41 26 19 ODI AV3 41 27 16 ODI AV2 41 38 21 ODI AV1 41 38 41 ODI AV2 41 38 41 ODI AV3 41 63 29 ODI AV2 41 79 22 ODI AV3 1
41 84 17 ODI AV3 41 85 17 ODI AV3 41 88 21 ODI AV2 41 88 20 ODI AV3 41 89 34 0 01 AV3 41 89 28 ODI AV4 41 69 23 ODI AV2 41 89 27 ODI AV1 41 92 17 ODI AV4 41 92 34 ODI AV3 42 23 15 ODI AV3 42 25 20 ODI AV3
- Note: This is a computer generated form.
i TA5LE 2C: 2C ASME Fcrm NIS-BB Sheet 5 of 5 1
Form NIS-88 SECTION XI-DIVISION 1 FORM NIS-88 TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station Unit 2 Steam Generator: 2RC018C Test Frequency: 20,130,300,500 kHz Date:
12/5/96 1
1-
% Tube Wall
]
Row Column Penetration Origin Location 1,
42 29 18 ODI AV2 2
42 29 26 ODI AV3 l
42 86 28 ODI AV3 42 86 3C ODI AV2 42 86 20 ODI AV1 42 89 35 ODI AV3 42 90 15 ODI AV4 42 90 32 ODI AV3 42 93
-19 0 01 AV4 i.
42 93 21 ODI AV2 i
42 93 33 ODI AV1 42 93 35 ODI AV3 l'
42 94 25 ODI AV4 j~
42 94 35 ODI AV3 j
43 30 16 ODI AV3 3
43 34 17 ODI AV3 j
43 36 15 0 01 AV4 43 36 24 ODI AV3 43 93 28 ODI AV1 43 93 30 ODI AV2 i
43 93 25 0 01 AV3 44 74 18 0 01 AV4 f.
44 74 25 ODI AV3 44 74 29 ODI AV-i 48 35 6
ODI 02C+0.4 1
48 36 18 ODI 02C+u.47 l
49 59 14 ODI AV2 j.
49 59 15 ODI AV3 49 73 7
ODI 07C g.
l e
4 1
)
4
- Note: This is a computer generated form.
i
TACLE 2D: 2D ASME F::rm NIS-B3 Sheet 1 of 3 Form NIS-BB SECTION XI. DIVISION 1 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BD Test Frequency: 20,130,300,500 kHz Date:
12/6/96
% Tube Wall j
Row Column Penetration Origin Location l
20 5
15 ODI AV4 23 7
16 ODI AV3 25 50 28 ODI AV2 25 108 -
18 ODI AV1 25 108 23 ODI AV4 26 70 17 ODI AV3 26 70 25 ODI AV2 26 107 21 ODI AV3
~
25 ODI AV4 28 28 28 36 20 ODI AV2 28 78 20 ODI AV3 28 102 18 ODI AV3 29 102 15 ODI AV3 30 11 37 ODI AV3 30 11 17 ODI AV4 30 103 24 ODI AV2 1
31 13 20 ODI AV3 31 13 16 ODI AV1 31 14 15 ODI AV4 31 44 21 ODI AV3 31 44 34 ODI AV2 31 50 23 ODI AV3 31 84 25 0 01 AV2 31 103 20 ODI AV2 31 103 21 CDI AV3 31 104 20 ODI AV3 32 79 15 ODI AV3 34 87 21 ODI AV3 34 97 16 ODI AV3 34 97 27 ODI AV2 34 98 23 ODI AV3 34 99 17 ODI AV3 34 99 37 ODI AV4 34 100 16 ODI AV3 35 14 20 ODI AV4 35 14 23 ODI AV3 35 17 26 ODI AV2 35 20 26 ODI AV2 35 47 15 ODI AV4 35 92 21 ODI AV2 35 95 32 ODI AV2 36 17 22 ODI AV2 36 18 15 ODI AV2 36 21 15 ODI AV1
- Note: This is a computer generated form.
l l
J
TA!LE 2D: 2D ASME Fcrm NIS-B3 Sheet 2 of 3 4
l l
Form NIS-BB 1
SECTION XI-DIVISION 1 FORM NIS-B3 TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS Site: Byron Station, Unit 2 Steam Generator: 2RC01BD Test Frequency: 20,130,300,500 kHz Date:
12/5/96
% Tube Wall Row Column Penetration Origin Location 36 21 21 ODI AV2 36 37 22 ODI AV3 36 37 30 ODI AV2 36 82 21 ODI AV3 36 82 21 ODI AV4 36 82 30 ODI AV2 36 83 25 ODI AV2 36 84 19 ODI AV2 36 95 17 ODI AV3 36 100 16 ODI AV4 37 33 25 ODI AV3 37 33 26 ODI AV2 37 41 20 ODI AV3 37 41 40 ODI AV2 37 41 23 ODI AV4 37 42 15 ODI AV3 37 42 35 ODI AV2 38 25 15 0 01 AV2 i
38 25 23 ODI AV3 38 85 27 ODI AV3 l
38 85 41 ODI AV2 38 85 22 ODI AV4 1
39 18 25 ODI AV3 39 27 15 ODI AV3 39 72 21 ODI AV2 39 72 25 ODI AV3 39 80 20 0 01 AV3 39 90 30 ODI AV4 40 22 17 ODI AV4 40 22 17 ODI AV3 40 25 17 0 01 AV3 40 26 15 ODI AV3 40 28 18 ODI AV3 40 29 15 ODI AV4 40 29 21 ODI AV3 40 29 31 ODI AV2
]
40 33 18 ODI AV2 40 33 22 ODI AV3
]
40 76 25 ODI AV2 l
40 90 20 ODI AV4 l
40 92 16 ODI AV3 41 20 20 ODI AV1 41 20 29 ODI AV2 41 32 17 ODI AV3
' Note: This is a computer generated form.
. ~ _.
' ~
TABLE 2D: 2D ASME Ft:rm NIS-BB Sheet 3 of 3 Form NIS-BB SECTION XI DIVISION 1 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS I
Site: Byron Station, Unit 2 Steam Generator: 2RC01BD Test Frequency: 20,130,300,500 kHz Date:
12/6/96 I
% Tube Wall j
Row Column Penetration Origin Location 41 33 17 ODI AV3 41 33 25 ODI AV2
.l 41 60 15 ODI AV1 41 60 16 ODI AV2 41 79 15 ODI AV1 41 79 26 ODI AV4 41 79 37 ODI AV2 41 79 45 ODI AV3 41 80 26 ODI AV1
- 41 86 18 ODI AV2 3
41 86 31 ODI AV3 1
42 36 32 ODI AV2 42 36 24
. ODI AV3 l
43 22 18 ODI AV1
)
43 22 22 ODI AV2 i
43 34 25 ODI AV1 l
43 34 28 ODI AV4 j
43 34 33 ODI AV2 43 34 39 0 01 AV3 44 92 15 ODI AV1
)
44 92 24 0 01 AV2 46 89 16 0 01 AV4 47 56 19 ODI AV3
]
47 56 30 ODI AV4 48 59 24 :
ODI AV3 48 59 19 ODI AV4 I
- Note: This is a computer generated form.
ATTACHMENT 1 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 1. Owner:
Commonwealth Edison Comnany Chicago. Illinois (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station Byron. Illinnois (Name and Address of Plant)
- 3. Plant Unit:
Two (2)
- 4. Owner Certificate of. Authorization (if required):. N/A
- 5. Commercial Service Date: 08/21/87
- 6. National Board Number for Unit:
N-200
- 7. Components Inspected Component or Manufacturer or Manufacturer or State or Province National Board No.
Appurtenance Installer Installer Serial No.
No.
2RC01BA Westinghouse 2095 U-201435 15 2RC01BB Westinghouse 2096 U-201436 16 2RC01BC Westinghoue 2097 U-201437 17 2RC01BD Westinghouse 2098 U-201438 18 i
l I
Note: This is a computer generated form
- --.~
i FORM NIS-1 (Back) 8.
Examination Dates 8/8/% to 9/5/%
9.
InspectionInterval from 8/21/87 to 8/21/97
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
Refer to the Attached Eddy Current Report
- 11. Abstract of Conditions Noted Refer to the Attached Eddy Current Report 1
{
- 12. Abstract of Corrective Measures Recommended and Taken Refer to the Attached Eddy Current Report We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
1r Certificate of Authorization No. (if applicable)
Not Anolicable Expiration Date. Not Anoticable Date At /f 19 96 Signed For ComFd By M
/
Owner
}
CERTIFICATE OF INSERVICE INSPECTION i
I, the undersigned, holding a valid commission issued by the National Board of Boiler an/ 4-p d Pressure Vessel Ins State or Province of I//du s and employed by //EDJ'fo. of //s / [r have inspected the components described in this Owner's Report during the period f/p/$
to f4/#6, and state that to the best of my knowledge and belief, the Owner has performed exammations ind taken corrective 4neasures described in this Owner's i
Report in accordance with the requirements of the ASME Code,Section XI.
l By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liab!c in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
AnlGe4 2" 82 Commissions
/24 - /o,ZSY In([Fctqfs Signature National Board, State, Province, and Endorsements alv,
19 94 Date /,
i Note: This is a computer generated form
NC. 9 (U(8
, A:
2A SG ASME Form NIS-2 FORM NIS.2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI g,g i
1 owner Commonwanith Fdienn Cnmnnny oete 3
N One First National Pin 7m Chienno. IL 80890 sheet of Aseems
- 2. Plant Bvmn NitcJaar Anwar Rfnfinn Unit me 4450 N. German Church Rd Rvmn il 81010 N
N Asereas Repeer Orsoneast6en P.O. No., Joo No., etc.
- 3. Work Performed by Framatome Technologies Type Code symbos siemp Not anolicable Authorization No.
Not nnnlienhlo 155 Mill Ridge Rd., Lynchburg, VA 24502 se,iretion pote wn, Anniirohi, Ame.e.
RC (Reactor Coolant)
- 4. Identification of system
- 5. (e) Applicebee Construction Code ASME Sect. ill ig 71 Edition, S72, W74* Addende 1355.1493-1 CodeCase (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 '83. S*83 1484,1528
- 6. Identification of Componente Repeired or Replaced and Replacement Componente f
4 ASME Code f
dettonal
- Repelred, Stamped Name of Name of Manufacturer poord Other Year
- Replaced, (Yes Component Manufacturer Serlei No.
No.
Identification Built or Replacement or No) i M f; WO~
w AT MM
/980 BRM Vff b
I
- 7. oesen,,iono,w.,u Pul66Eb 17)BES AS ustEbDA/ SUPPLEMENTAL SHEET
- 8. Tests Co Hydrostatic Pneumatic O Nominei Operating Pressure g.
Other O Prs==ure poi Test Temp.
'F b
f - g /gj NOTE: supplemental sheets in form of iets, sketches, or drawings may be used, provided (1) slae is 8% in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each sheet, end (31 a,ach sheet is numbered and the number of sheses is recorded et the top of thle forrn.
(12/82)
This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017
- W'74 Apparahia for NS-2331(D), NS-2332 (A)(2), NS-4334.1,4334.2. NS-4335.1,4335.2,4335.3
. ~. - - -.. _.
N d
i T
i 6J})b Q t V/ '
FORM Nit 2 (Back) l
- 9. Romeras l
AspHeen6e adenutesturer's Date neeeru to me esteenee 1
i
)
4 CERTIFICATE OF COMPLlANCE conforms to tne rules of the We certify that tne statements mese in the report are correct and this recent or resi..;---
ASME Code,Section XI.
N Type Code symboi Stamp
/[
Empiration Deas
/
Certificate of or6 ant No.
4
/M#
Date 13 Signed ye ompero passense, Titse
~
t I/
/
%./ V CERTIFICATE OP INSERVICE INWECTION vJY N*
//A&
the compononu W
/ddz N lIn c'. d /
home M
. and stoes met E
to in this Owner's Report dwing the paried eis to me meet of my knowiedge and neuef, stw owner nos perfonned eneminatione end tenon encreetive mea Owner's Report in assortience une the soeverernente of the ASME Code, Sestion XI.
By signing this certificoes noteher the inspessor nor his employer makes any warroney, espress eneminations and sorrsethe mesones doesnted in this Ousner's Report. Furthermore, neither the inspecto shall be liehle in any menner for any personal iniury or property siemage of a loss of erry kind arisi inspection.
ll l!'l5 5 Y
$, bl Comuniee6 ens eaet nei 0 o, stow, er.mne.. e,w anee,.e.ne.no p
in. se r. o ne u.o 0/dd'd 3,
je VA os.
nue25 I
j
~
=
.. 0: FORM NIS-2 SUPPLEMENTAL SHEET
{
1.Omr: ComEG Page 2 o/[
One First Natonal Plaza
[/
Dale _9/4/96
)
ChiceDo,IL 60600 Unit L
j
- 2. Plant: Byron Nuclear Power Station NWR. 960008775-03 4450 North German Church Road P.O. No., WR No., etc.
Byron,IL 61010 l
- 3. Work Performed By Framatorne Technologies, Inc Type Code Symbol Stamp: Not Applicable 155 Mill Ridge Rd.
Authonzahon No.: Not Apphcable Lynchburg, VA 24502 Expiration Date: Not Apphcable
- 4. Idenhfceton of System: RC (Reactor Coolant)
- 5. (a) Apphcable Constructen Code: ASME Sect. Ill,1971 Ed., S72,'W74 Addenda l
1464,1528,1355,1493 1 Code Case (b) Apphcable Edition of Sechon XI Utilized for Repairs or Replacements: 1983/S83
- 6. Identarcation of Components Repaired or Replaced and Replacement Components:
i Count so now col Lag see w Msgr Comments j
1 A
16 110 Hot 9518-3-870 Framatome 2
A 16 110 Cold 9518-3-875 Framatome 3
A 15 109 Hot 9518-3-898 Framatome 4
A 15 109 Cold 9518-3-890 Framatome 5
A 15 110 Hot 9518-3-850 Framatome
)
6 A
15 110 Cold 9518-3-800 Framatome 7
A 15 111 Hot 9518-3-814 Framatome 8
A 15 111 Cold 9518-3-813 Framotome 9
A 39 19 Hot 9518-3-848 Framatome 10 A
39 19 Cold 9518-3-862 Framatome 11 A
39 98 Hot 9518-3-885 Framatome 12 A
39 98 Cold 9518-3-829 Framatome 13 A
45 30 Hot 9518-3-825 Framatome i
14 A
45 30 Cold 9518-3-812 Framatome 15 A
49 74 Hot 9518-3-830 Framatome 16 A
49 74 Cold 9518-3-893 Framatome 17 A
48 74 Hot 9518-3-899 Framatome 18 A
48 74 Cold 9518-3-840 Framatome 19 A
47 66 Hot 9518-3-886 Framatome 20 A
47 66 Cold 9518-3-803 Framatome 21 A
46 67 Hot 9518-3-839 Framatome 22 A
46 67 Cold 9518-3-896 Framatome l
I i
i l
l l
- W74 e to unit to NB-2331 (D), NB-2332 (A)(2), NB-4332, NB-4334.1, NS-4334.2,4335.1,4335.2,4335.3 This is a computer generated form.
( B:
l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Commonwealth 1:dienn Onmnnnv pege Nome i
/
1 One First National Pinta. Chir nnn il 80800 sheet of 1
Aseren
- 2. Plant Bvmn Nur Immr Anwar Mtatinn Unit
~.-
Asereas
~
NM[? Gb@R7Ti7'.b3 4450 N. German Church Rd Rvron 11_81010 Rese6r Organisetlen P.Q. No, JoD No., etc.
- 3. Work Perfonned py Framatome Technolooies Type Com symnot stamp Not anolicable Authortastion No.
Not annlit nhtm j
155 Mill Ridge Rd., Lynchburg, VA 24502 g,,ir,3.e on,e wn, Annii,,,si,
.r e
RC (Reactor Coolant)
- 4. identification of system
- 5. (e) Appicebee Construction Code ASME Sect. lll 39 71 Edition, S72. W74* Addende 1355.1493-1 cae,c,,
(b) Applicable Edition of Section XI Utillaed for Repairs or Raploosments 19 '83. S'83 1484,1528 NN0 N Yf!'S
- 6. Identificaticin of Components Repaired or Replaced and Rep 6ecoment Components AWAE Code Net 6onal
- Repaired, teamped Name of None of Manufacturer Board Other Year Replaced.
(Yes Component Menutesturer Serial No.
No.
Identifloation Built of Replacement ofNo) y p
f N
$0$$
h lUb[kD Vl>6Es A5 LfsrFh ON Feux>uws Pact.
- 7. Description of work
- 8. Tests Conducted: Hydrostatic Pneumatic O Nominal Operat6ng Pressure O Other Pressure poi Test Temp.
'F Y$ N WO0 h NOTE: pp6emental sheets in form of lists, sketches, or drowings mey be used, provided til sine is 8% in. x 11 in., (2) Informe.
tion in items 1 through 6 on this report is included on each shoot, and (3) each sheet is numbered and the number of sheses is recorded et the top of this form.
\\
(12/82)
This Form (E00030) may be otsteined from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 "W '74 Apphcab6e for NS-2331(D), NS-2332 (A)(2), NS-43341,4334.2, NB4135.1,4335.2. 4335.3
J J
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FORM NIS-2 (BacM ff h$N h$]-Gb
- 9. Romeras
)
Aposicense uenuteesurers cote neoerts to ese esteenes d
i i
i 4
1 CERTIFICATE OF COMPLIANCE l
We certify that the statements mese in the report are correct and this conforms to the rules of the ASME Code,Section XI.
Type Code Symbol Stamp BIN /
/
Espiret6on Date Certificate uthor ion No.
b 13 Signed Date e Dessonas, Title 07 70 t
/' /
CERTIFICATE OF INSERVICE INDECTION 2
of ed r rowinos 84>Md 828tpAFM&f
[
have the components deseribed
/ I #0
. and stets that in this Owner's Repob dur6ng the period
[I[/b to to the best of my knowledge and belief, the Owner has performed esemMoons and taken correcthe measures esecribed in this Owner's Report in sonordance with the requirements of the ASME Code,Section XI.
By signing this cortrficato norther the insposeer nor his employer meties any worrenty, expressed or implied, concermne the emorninesions and corrective measures desented in this Owner's Report. Furthermore, neither the inspector nor his empiover shall be liable in any menner for sny personal injury or property damage or a loss of any kind arising from or connected with this inspection.
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'. D: FORM NIS-3 SUPPLEMENTAL SHEET
- 1. Owner: Comed Pago 2 e#2 One First National Plaza Date _9/tW96 Chicago,IL 60690 Unit L
- 2. Plant: Byron Nuclear Power Stabon NWR. 960006767-03 l
4460 North German Church Road P.O. No., WR No., etc.
3 Byron,IL 61010 l
- 3. Work Performed By: Framotome Techrwoges, Inc Type Code Symbol Stamp: Not Apphcable l
155 Mill Ridge Rd.
Authonzaten No.: Not Apphcab6e i
Lynchburg, VA 24502 Empiraten Date: Not Appicable
- 4. Identtreaten of System: RC (Reactor Coolant) i
- 5. (a) Apphcable Construchon Code: ASME Sect. til,1971 Ed., S72, *W74 Addenda 1464,1526,1355,1493-1,1*ascode Case Poyp g (b) Apphcable Edition of Sechon XI Utilized for Repers or oplacements 1963/S63 l
l
- 6. Idenbreation of Components Repaired or Repieced and Replacement Components l
Count SG Row Col Leg ser #
Migr Comments 1
B 1
2 Hot EA64-3-1013 Framatome I
2 B
1 2
Cold EA64-3-1060 Framatome 3
B 20 57 Hot EA64-3-1019 Framatome 4
B 20 57 Cold EA64-3-1004 Framatome 5
B 28 105 Hot EA64-3-1077 Framatome 6
B 28 105 Cold EA64-3-1011 Framatome
]
7 B
33 102 Hot EA64-3-1018 Frematome 8
B 33 102 Cold EA64-3-1006 Framatome 9
B 36 95 Hot EA64-3-1079 Framatome 10 B
36 95 Cold EA64-3-1010 Frematome 11 B
36 97 Hot EA64-3-1020 Framatome 12 B
36 97 Cold EA64-3-1012 Framatome 13 B
41 59 Hot EA64-3-1015 Framatome 14 B
41 59 Cold EA64-3-1003 Framatome i
15 B
42 35 Hot EA64-3-1016 Frematome 16 B
42 35 Cold EA64-3-1005 Framatome 17 B
44 80 Hot EA64-3-1014 Framatome 18 8
44 80 Cold EA64-3-1009 Framatome 19 8
45 84 Hot EA64-3-1017 Framatome 20 B
45 84 Cold EA64-3-1008 Framatome l
i i
I i
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- 1. Owner Commonwamith Friicnn onmnnnv o,te Name
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One First National Pin 7n Chienno IL 80890 sheet of Ameen b
- 2. Plant Rvron Nnelmar Anwar Af stinn unit
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[^MO d3 4450 N. German Church Art Rvmn il 81010 AeWees Repeer Orgentaatten P.O. No., Joo No., etc.
- 3. Work Performed by Framatome Technologies Type Code symbol stamp Not anoticable Authorization No.
Not anntienble 155 Mill Ridge Rd., Lynchburg, VA 24502 e,,i,,, ion o.
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Aserous
- 4. Identification of System RC (Reactor Coolant)
- 5. (e) Appicaces Construction Code ASME Sect. til 39 71 Edition, S*72. W74* Addende 1355.1493-1 cae Case (b) Applicente Edition of Section XI Utillaed for Repairs or Replacements 19 '83. S*83 1 84 15,28 33 a3uln lN
- 6. Identification of Components Repa6 red or Repneced and Replacement Components
' ' ' ' ~
AsME com Nettonal
- Receired, Stamped Name of Name of Manufacturer Board Other Year
- Replaced, (Yes C.vnponent Manufacturer Seriel No.
No, identification Built or Replacement or No) 2C SYF.AA4 WE.577Af6' cwsmait uoxe 2097
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- 8. Tests Conducted: Hydrostetic O Pneumatic Nominst Operating Pressure Oiher O Proesure pel Test Temp.
- F 0 k 4 1"a)ti W 0)f lists, sketches, or drawings eney be used, provided (1) sine is 8 NOTE: Sapp 6 ansets in form o tion in items 1 through 6 on this report is included on each shoot, and (3) each sheet is numbered and the number of sheses is recorded at the top of this form.
(12/82)
This Form (E000303 mov be obtained from the Order Dept., ASME,346 E. 47th St., New York, N.Y.10017
- W '74 Appl 6 cable for NS-2331(D), NB-2332 (A)(2), NB-4334.1,4334.2, NB-4335.1,4335.2,4335.3
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FORM NIS 2 (Beck)
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- 9. Memerts moo -e-tem-s os e.eoe,,,,.. e,es,,se l
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I I
l CERTIFICATE OF COMPLIAgeCE We cortsfy that the statements mees in the report see correct and this conforms to the rules of the ASME Code.Section XI.
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Type Coos Symmet stemo Y
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,se,ed me _ dese,.ed 1
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i to the test of my knesstesse and belief, the owner has performed seemheteene one taken oorvoetive measures desershe Owner's Mooort in assordenas with the reevirements of the ASME come, saetten XI.
By signine this samfieses nenhor the enesseeer nor his emptever makes any suerrenty, enernesed or imo ise, s s
l esaminettons and oorrestive ensentes desenhed in thee ousner's Report. Furthermore, neeer me insenster nor his empl shall be tiente in any momer for one pereenet inivry or property domess or a less of any kinal ordeine from or conn inspection.
Nl' /ASY
$ h/YllW Commineione wetensi seere, stein, Prewmee, one s neernemome r
snessiera sienseure 03m/A 3
,, 96 os.
(12/82)
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_ _..l D: FORM NIS-3 SUPPLEMENTAL SHEET
- 9. Owner: Comed Page 2 c// D One First National Plaza Date,,_9896 Chicago,IL 60690 Unit L
- 2. Plant: Byron Nuclear Power Station NWR. 960006799-03 l
4450 North German Church Road P.O. No. WR No., etc.
Byron,IL 61010
- 3. Work Performed By: Framotome Technologes, Inc Type Code Symbol Stamp: Not Applicable 155 Mill Ridge Rd.
Authonzehon No.: Not Appicable Lynchburg, VA 24502 Exprabon Date: Not Apple =Na i
- 4. Identificatm of System: RC (Reactor Coolant) 4 I.
- 5. (a) Apphcaba Construohon Code: ASME Sed. Ill,1971 Ed., S72,'W74 Addenda I
1464,1528,1355,1493-1 Code Case (b) Apphceble Edition of Sechon XI Utliized for Repests or Replacements 1983/S83 i
1
- 6. Identirmaton of Components Repared or Replaced and Replacement Components l
9 Count SG Row Col Leg Ser #
Mfgr Comments 1.
C 22 29 Hot EA64-3-1073 Framatome i
2 C
22 29 Cold EA64-3-1075 Frematome 3
C 36 31 Hot EA64-3-1076 Framatome 4
C 36 31 Cold EA64-3-1071 Framatome
}
5 C
39 18 Hot EA64-3-1078 Framatome j
6 C
39 18 Cold EA64-3-1074 Framatome j
7 C
39 79 Hot EA64-31085 Framatome 8
C 39 79 Cold EA64-3-1072 Framatome i
9 C
40 62 Hot EA64-3-1089 Framatome 10 C
40 62 Cold EA64-3-1073 Framatome 11 C
41 38 Hot EA64-3-1080 Framatome 12 C
41 38 Cold EA64-3-1081 Framatome 1
i 1
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2D SG ASME Form NIS 2 FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Commonwanith Fdienn Onmnnnv oste N
One First National Pin 7n Chiennn IL 80890 sheet of Aseress
- 2. Pl,nt Bvmn Nncianr Anwar Rfnfinn Unit
.m.
4450 N. German Church Rd Bvmn. IL 81010 A/
N3 Amoreen Roos 6r Organisation P.O. No., Job No., etc.
- 3. Work Performed by Framatome Technolooies Type code symbol siemp Not sonlicable Authortretion No.
Not annlienhia 155 Mill Ridge Rd., Lynchburg, VA 24502 Empiretion Date hint Annlinnhia Amorees
- 4. Identification of system RC (Reactor Coolant)
- 5. (e) Applicable construction code ASME Sect. lll ig 71 Edition, S'72 W74* Addendo 1355.1493-1 code case (b) Applicable Edition of Section XI Utilized for Repairs or Rapiscements 19 '83. S'83 1484,1528 identification of Components Repe6 red or Replaced and Raolacement Components ASME Code National
- Repaired, Stemped Name of Name of Menufacturer Board Other Year
- Rapieced, (Yes C ;;.a.:
Manufacturer Sortet No.
No, identification Built or Replacement or No)
D e zn (?
2071
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/910 AWG h!S PLUGGEh ~7~0825 /4S US' reb OAl fcu6W/A4 946S
- 1. Deecription of work
- 8. Tests Conducted: Hydrostatic 0 Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp.
'F 4 M t{t w 0 }
emental shoots inl form o lists, sketches, or drawings may be used, provided (1) slae is 8% in.
N tion i items 1 through 8 on this report is included on each sheet, and (3) each shoot h numbered end the number of sheets is recorded at the top of this form.
(12/82)
Thle Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017
- W 74 Appicable for NB-2331(D;, NB-2532 (A)(2), NS-4334.1,4334.2, No-4335.1,4335.2,4335.3
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CERTIFICATE OF COMPl. LANCE j
i We certify that the statements moos in the report are correct and this conforms to the rules of the l
ASME Code, Section Xl.
l 4
Type Code Symnoi stamp
/M'N//"
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Empiretion Date Certificate of Au isetto e.
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CERT.FlCATE OF INSERVICE INDECTION 4
M a welid aemmW.a issued tuy the ional of do6ter and Prenewe Vessel I m one the Seses j
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or Provines of h
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in mis Owave Rep [rt dur6ng the period
[YW ensi stese est to j
to the test of my knousteelse and tuotief, the Owner has perforried seeminettone end taken corrective measures described in sie j
Owner's Report in ecoordense vnth the requirements of the ASME Code, Seatten XI.
Sy segning this eartsfieses neither the Imagessor nor his employer mehee any worrenty, espreessel or 6mp66ed, conearneng the I
seeminations and corrective messeres essented in mio Owner's Report. Furthermore, neither me inspeetor nor his emo6 eyer shell be lietdo in any manner for any pereenal injury of property damage or a loss of any kind arising from or connected with sie j
inspection.
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1.Ownnc Comed Pm2 vb Z-One First National Plaza Date _9Ml/96 Chicago,IL 60000 Unit 1,
4
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- 2. Plant: Byron Nuclear Power State NWR. 960008805-03 4450 North German Church Road P.O. No., WR No., etc.
Byron,IL 61010 -
- 3. Work Performed By Frematome Technologes, Inc Type Code Symbol Stamp: Not Applicable 155 Mill Ridge Rd.
Authortzaten No.: Not Applicable Lynchburg, VA 24502 Expiraten Date: Not Applicable
- 4. Idenbreaten of System: RC (Reactor Coolant)
- 5. (a) Applicable Construction Code: ASME Sect. Ill,1971 Ed., S72,'W74 Addende 1464,1528,1355,1493 1 Code Case (b) Applicable Edition of Secten XI Utilized for Repairs or Replacements 1983/S83
- 6. Identarcation of Components Repaired or Replaced and Replacement Components i
Count SG Row Col Leg ser #
Mfgr Comments 1
D 37 41 Hot EA64-3-1000 Framatome 1
2 D
37 41 Cold EA64 3-998 Framatome 3
D 38 85 Hot 9518-3-808 Framatome 4
D 38 85 Cold EA64-3-999 Framatome i
5 D
41 79 Hot EA64-3-996 Framatome 1
6 D
41 79 Cold EA64-3-997 Framatome i
i i
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Tabi) 3: SG Tubes R: paired 1
1 l
l NO. EMB yunii - CUi.
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15 109 DTI-SVI TSC+0.00 B2F17 (Foreign Object) 1-2 A
15 110 56 %
TSC+1.09 B2F17 (Foreign Object) 3 A
15 111 SVI TSC+0.11 B2F17 (Foreign Object) j 4
A 16 110 NQl-SVI TSC+1.17 B2F17 (Foreign Object) - Leaking Tube 5
A 39 19 42%
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6 A
39 98 42 %
AV3+0.00 AVB Wear i
7 A
45 30 40%
AV2+0.00 AVB Wear 8
A 46 67 Preventative 02C+3.39 Preventative - Sludge Build up l
9 A
47 66 Preventative 02C+3.43 Preventative - Sludge Build up 10 A
48 74 Preventative 02C+2.06 Preventative - Sludge Build up j
l 11 A
49 74 FSI-SVI 02C+5.19 FSI-SV1 - Sludge Build up l
Steam Generator B NO, SNB ROW COL m IND 3 Location 7 :--
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1 B
1 2
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2 B
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4 B
33 102 41 %
AV4+0.00 AVB Wear 5
B 36 95 40%
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6 B
36
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AV3+0.00 AVB Wear 7
B 41 59 42%
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8 8
42 35 42%
AV2+0.00 AVB Wear 9
8 44 80 44 %
AV3+0.00 AVB Wear 10 B
45 84 42%
AV2+0.00 AVB Wear l
i-Steam Generator C l!
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1 C
22 29 NQl-SVi 01H+0.75 NQl-SVI I
2 C
36 31 40%
AV3+0.00 AVB Wear 3
C 39 18 41 %
AV3+0.00 AVB Wear 4
C 39 79 40%
AV2+0.00 AVB Wear 41%
AV3+0.00 AVB Wear 5
C 40 62 42%
AV3+0.00 AVB Wear 46 %
AV2+0.00 AVB Wear 6
C 41 38 41 %
AV2+0.00 AVB Wear 41 %
AV3+0.00 AVB Wear Steam Generator D 10 0. SNB ROUF COL e SID 5 8 a eaan s e m
Comuments-1 D
37 41 40%
AV2+0.00 AVB Wear 2
D 38 85 41 %
AV2+0.00 AVB Wear
~~
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41 79 45%
AV3+0.00 AVB Wear Page1
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