View source for BSEP 09-0123, Response to Request for Additional Information Regarding Third 10-year Inservice Inspection Interval Requests for Relief RR-42, RR-43, RR-44, and RR-45

{{Adams
| number = ML093340344
| issue date = 11/20/2009
| title = Response to Request for Additional Information Regarding Third 10-year Inservice Inspection Interval Requests for Relief RR-42, RR-43, RR-44, and RR-45
| author name = Mentel P
| author affiliation = Carolina Power &amp; Light Co, Progress Energy Carolinas, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000325
| license number = DPR-071
| contact person = 
| case reference number = BSEP 09-0123, TAC ME1143, TAC ME1144, TAC ME1145, TAC ME1146
| document type = Letter type:BSEP
| page count = 69
| project = TAC:ME1143, TAC:ME1144, TAC:ME1145, TAC:ME1146
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:Progress Energy NOV 2 0 2009 SERIAL: BSEP 09-0123 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

==Subject:==
Brunswick Steam Electric Plant, Unit No. 1 Renewed Facility Operating License No. DPR-71 Docket No. 50-325 Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Interval Requests for Relief RR-42, RR-43, RR-44, and RR-45 (NRC TAC Nos. ME1143, ME1144, ME1145, and ME1146)

==Reference:==
Letter from Phyllis N. Mentel to U.S. Nuclear Regulatory Commission, ProposedAlternativefor the Third 1O- Year Inservice Inspection Program, dated April 27, 2009 (ADAMS Accession Number ML091260502)
Ladies and Gentlemen:
By letter dated April 27, 2009, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted four 10 CFR 50.55a requests for the Brunswick Steam Electric Plant, Unit No. 1. On September 23, 2009, the NRC provided an electronic version of a request for additional information (RAI) concerning the proposed Inservice Inspection Program alternatives. The response to this RAI is enclosed.
No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184.
Sincerely, Pqhyy lis N. Mentel Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P0 Box 10429 Kr&#xfd;C-A Southport, NC 28461

Document Control Desk BSEP 09-0123 / Page 2 WRM/wrm

==Enclosure:==
Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Interval Requests for Relief RR-42, RR-43, RR-44, and RR-45 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. Jack M. Given, Jr., Bureau Chief North Carolina Department of Labor Boiler Safety Bureau 1101 Mail Service Center Raleigh, NC 27699-1101

BSEP 09-0123 Enclosure Page 1 of 9 Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Interval Requests for Relief RR-42, RR-43, RR-44, and RR-45

===Background===
By letter dated April 27, 2009, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted four 10 CFR 50.55a requests for the Brunswick Steam Electric Plant (BSEP), Unit No. 1. On September 23, 2009, the NRC provided an electronic version of a request for additional information (RAI) concerning the proposed Inservice Inspection Program alternatives. The response to this RAI follows.
NRC Question 1 Request for Relief RR-44, ASME Code, Section XI, Examination Category B-A, Items B 1.22 and B1 .30, Pressure Retaining Welds in Reactor Pressure Vessel (RPV)
RPV Bottom Head Meridional Welds (1 B 11 -RPV-J31 and 11B 11 -RPV-J42)
The licensee stated that no access was possible to the portions of the meridional welds located inside the vessel support skirt, and that control rod drive (CRD) housings would interfere with examinations in this area. However, access to this region (inside the RPV support skirt) is typically available through man-ways to enable maintenance work on the CRD housings to occur, as necessary. Further information is needed to provide an adequate basis for impracticality.
: 1. Provide further information (descriptions, sketches, measurements, etc.) to show that no access to these welds from the inside of the RPV support skirt area is possible.
: 2. State whether 100% of the "accessible" portion (outside of the vessel support skirt) of these welds was examined. If less than 100% of the ASME Code-required volume was examined for the accessible portion of the welds, provide cross-sectional coverage plots to show the volume coverage obtained for each of these welds.
: 3. In the written description, the licensee stated that "[Ultrasonic Testing] UT examination was performed using personnel and examination procedures qualified to the ASME Code, Appendix VIII, as administered by the [Electric Power Research Institute (EPRI)]
Performance Demonstration Initiative (PDI)." However, it is unclear what angles were used or if the examinations used shear or longitudinal waves.
: 4. Please clarify the ultrasonic sound beam modes and insonification angles used for all ultrasonic examinations.
: 5. State whether the accessible portions of the welds was examined from both sides.

BSEP 09-0123 Enclosure Page 2 of 9
: 6. State whether any indications were discovered as a result of these examinations, and how these indications were dispositioned.
Response to NRC Question 1-1 Typically, any control rod drive (CRD) maintenance activity is performed through access provided from under the vessel at the CRD flanges. The area inside the reactor support skirt manway provides access to the upper portions of the CRD housings. This inside area contains 137 CRD housings, 43 in-core penetrations, and one bottom head drain line. The housings are 6 inches in diameter and the distance between each of the housings is only 6 inches. The elevation between the reactor vessel and insulation, within the man-ways, ranges from approximately 4 feet at the outer diameter to approximately 12 inches at the center of the reactor. This does not allow physical access. The CRD housings also limit the total amount of reactor vessel support skirt weld volume which can be examined. This congestion is illustrated in the attached drawings and picture (i.e., Attachment 1).
Response to NRC Question 1-2 100 percent of the accessible portion of these welds, outside of the reactor pressure vessel support skirt, was examined.
Response to NRC Question 1-3 A 600 longitudinal search unit was used in accordance with requirements of the American Society of Mechanical Engineers (ASME) Code, Appendix VIII, as administered by the EPRI PDI.
Response to NRC Question 1-4 As stated in the response to Question 1-3 above, a 60' longitudinal search unit was used in accordance with requirements of the ASME Code, Appendix VIII, as administered by the EPRI PDI.
Response to NRC Question 1-5 The accessible portions of the welds were examined from both sides. As stated in the response to Question 1-2 above, 100 percent of the accessible portion of these welds was examined.
Response to NRC Question 1-6 No recordable indications were observed during these examinations.

BSEP 09-0123 Enclosure Page 3 of 9 NRC Question 2 RPV Shell-to-Flange Weld (1B111 -RPV-F 1 and 1B 11 -RPV-F2)
The licensee stated that the "design configuration/restriction makes compliance with the ASME Code-required examination coverage requirements impractical." However, this general statement is unclear and insufficient to adequately demonstrate impracticality.
: 1. Provide detailed descriptions (text and supporting sketches with dimensions, as necessary) of the interferences to applied UT techniques.
: 2. Based on the limited information in the sketch provided by the licensee, it is assumed that these examinations were performed from the outside surface of the RPV. Discuss whether ASME Code volumetric coverage could be increased by applying nondestructive examination (NDE) from the inside surface of the RPV.
: 3. On the coverage calculation sheet, the licensee provided some information pertaining to the UT techniques applied. However, it is unclear whether the angles shown represent shear or longitudinal waves. Please clarify the UT sound beam modes and insonification angles used for all UT examinations.
: 4. State whether any indications were discovered as a result of these examinations, and how these indications were dispositioned.
Response to NRC Question 2-1 The shell-to-flange configuration is a structural discontinuity comprised of a ring segment welded to a flange segment. The flange segment is thicker than the ring segment and this creates a transition on the outside diameter (OD) surface. This OD transition limits the physical scanning area of the transducer. Loss of contact between the part and the ultrasonic transducer occurs when trying to scan over the transition. No ultrasound enters the part once loss of contact occurs. The sketch previously provided in Enclosure 3 in CP&L's letter dated April 27, 2009 (i.e., Figure 2, for 1B11-RPV-F1, F2), depicts the OD transition and the transducer limitations.
In addition to the sketch previously provided in Enclosure 3 of CP&L's letter dated April 27, 2009, additional drawings and sketches are being provided in the enclosed Attachment 2.
Response to NRC Question 2-2 These examinations were performed from the outside surface, in calendar year 2000, using the industry-accepted technology that was available. At that time, the technology for examination from the inside surface was still emerging and was not yet considered proven technology for commercial application.

BSEP 09-0123 Enclosure Page 4 of 9 Response to NRC Question 2-3 These examinations were performed with the following insonification angles (i.e., nominal) and modes of propagation:
00 Longitudinal 450 Shear 600 Shear Response to NRC Question 2-4 No recordable indications were observed during these examinations.
NRC Question 3 Request for Relief RR-42, ASME Code, Section XI, Examination Category B-D, Item B3.90, Full Penetration Welded Nozzles in Vessels, RPV Nozzle-to-Vessel Welds The licensee stated that "Due to the design of these welds it was not feasible to effectively perform a volumetric examination of "essentially 100 percent" of the required volume. The nozzle-to-vessel welds are accessible from the vessel plate side of the weld and are examined to the extent practical." In addition, the licensee's table only lists "examination limited due to nozzle configuration" as a basis. However, these general statements are not adequate to fully demonstrate impracticality.
: 1. Provide full and detailed descriptions of how the nozzle designs limit examinations to the shell side, and why 100% of the ASME Code-required volumes from the accessible side could not be performed.
: 2. On the coverage calculation sheets, the licensee provided some information pertaining to the UT techniques applied. However, it is unclear whether the angles shown represent shear or longitudinal waves. Please clarify the UT sound beam modes and insonification angles used for all ultrasonic examinations.
: 3. State whether any indications were discovered as a result of these examinations, and how these indications were dispositioned.
Response to NRC Question 3-1 The nozzle design at BSEP does not allow for examination on the nozzle side of the weld. The outside blend radius of the nozzle forgings varies from 2.75 inches to 5 inches on the nozzles in question. The curvature of the surface prevents the transducer from maintaining contact and proper coupling. Attachment 3 provides drawings of nozzle forgings showing the nozzle curvature and weld preparation that is typical on all nozzles.

BSEP 09-0123 Enclosure Page 5 of 9 Response to NRC Question 3-2 These examinations were performed with the following insonification angles (i.e., nominal) and modes of propagation.
0' Longitudinal 450 Shear 600 Shear Response to NRC Question 3-3 The N3C nozzle-to-shell weld had one indication that was classified as subsurface and was evaluated as acceptable.
NRC Question 4 Request for Relief RR-45, ASME Code, Section XI. Examination Category B-H, Item B8.10, Integral Attachments for Vessels, Reactor Pressure Vessel
: 1. Include a detailed description (text or sketches, as needed) of the interference caused by the stabilizer ring, demonstrating lack of access to the bottom of these lug welds.
: 2. As applicable, discuss any additional NDE techniques that could be used to verify structural integrity of the welds. For example, discuss whether a visual VT-1 examination could have been performed to augment the limited surface examination.
: 3. State whether any indications were discovered as a result of these examinations, and how these indications were dispositioned.
Response to NRC Question 4-1 The bottom weld of the reactor pressure vessel stabilizer lug is located at approximately the same level as the top of the shield wall. The stabilizer supports extend from the welded lug at the reactor vessel to the shield wall. Plant Drawing FP-9527-5098, a copy of which is provide in , shows the relationship between the bottom of the welded attachment and the top of the shield wall. Section A-A of the Stabilizer Bracket drawing (i.e., CB&I Drawing No. 46, a copy of which is provided in Attachment 4) shows the configuration of the welded bracket. As can be seen from the photographs also provided in Attachment 4, there is very limited access to the welded attachment and there is virtually no access to the bottom portion of the attachment.
Response to NRC Question 4-2 Additional NDE methods were not performed on the lug itself, however, a VT-3 has been performed on the entire support assembly in accordance with requirements of the ASME Code, Section XI, Examination Category F-A. There were no recordable indications associated with the VT-3 examinations.

BSEP 09-0123 Enclosure Page 6 of 9 Response to NRC Question 4-3 There were no recordable indications associated with these examinations.
NRC Question 5 Request for Relief RR-43, ASME Code, Section XI, Examination Category R-A, Item R1.20, Pressure Retaining Piping Welds The licensee has requested relief from examining 100% of the ASME Code-required volumes for thirty-two (32) ASME Code Class 1 piping welds covered under a risk-informed ISI (RI-ISI) program.
: 1. State the total number of ASME Code Class 1 piping welds included in the overall risk-informed program and the number of welds scheduled for examination so that the 32 limited examinations can be assessed within the scope of all examinations being implemented.
: 2. Confirm that all other ASME Code Class 1 piping examinations in the risk-informed ISI program have been completed in accordance with ASME Code volumetric requirements.
: 3. A number of the welds in RR-43 state that the weld was examined multiple times during the third inspection interval and/or that this is an additional weld not originally scheduled for examination. Please clarify the reason for each examination of these welds during the third inspection interval (i.e. normally scheduled ISI examination, sample expansion, supplemental examination coverage, etc.).
For Request for Relief RR-43, the licensee has provided only general information regarding the impracticality of obtaining ASME Code-required volumetric coverage by stating "due to configuration this is a one-sided examination." Other limited descriptions are provided for each weld, such as configuration, however, insufficient information has been included to adequately demonstrate impracticality.
: 4. Include descriptions (written and/or sketches, as necessary) of the interferences to applied volumetric techniques for each weld in RR-43.
: 5. State the ultrasonic sound beam modes and insonification angles used for all ultrasonic examinations.
: 6. Show cross-sectional coverage plots to describe ASME Code volumes examined.
: 7. State whether any indications were discovered as a result of these examinations, and how these indications were dispositioned.

BSEP 09-0123 Enclosure Page 7 of 9 Response to NRC Question 5-1 BSEP was at the end of the first period of the third inspection interval when risk-informed inservice inspection (RI-ISI) was approved (i.e., ADAMS Accession Number ML013320632) and implemented (i.e., see the discussion in paragraph 3, page 2 of the NRC Safety Evaluation).
Up until this point (i.e., the end of the first period of the third inspection interval), 27.7 percent of the examinations required by the ASME Code, Section XI had been completed for Examination Category B-F and B-J piping welds. Beginning in the second period of the third interval, the components selected by the RI-ISI process replaced those formerly selected in accordance with the ASME Code, Section XI criteria. Since 27.7 percent of the examinations had been completed during the first period of the third interval, 72.3 percent of the RI-ISI examinations were performed during the second and third periods. Under the RI-ISI program, 67 Class 1 piping welds are required to be examined over a complete 10-year interval. Due to the mid-interval implementation of RI-ISI, 49 welds were required to be examined to complete the remainder of the interval. Of those 49 welds examined, BSEP is seeking relief on 32 welds.
Response to NRC Question 5-2 All other ASME Code Class 1 piping examinations in the RI-ISI Program have been completed in accordance with ASME Code volumetric requirements.
Response to NRC Question 5-3 Typically, these multiple examinations are augmented examinations performed to satisfy augmented programs, such as the programs for BWRVIP-75-A or NUREG-0619. In some instances, components are selected for multiple examinations based on industry concerns or Operating Experience. The information for these additional examinations was only provided as supporting information that the welds in question were receiving additional examinations. This additional information was not intended to suggest that additional coverage was achieved.
Response to NRC Question 5-4 Descriptions of the interferences (i.e., the configurations) were originally provided in , pages 8-14 of CP&L's letter dated April 27, 2009. Table 2 from Enclosure 2 of CP&L's letter dated April 27, 2009, has been revised to include a column that describes the access limitation that interfered with the volumetric examination.
Response to NRC Question 5-5 Sound beam modes and insonification angles vary based on the component and the requirements of the procedure used. The sound beam modes and insonification angles used are in compliance with the requirements of ASME Code, Section XI, Appendix VIII. Attachment 5 provides a copy of Table 2 from CP&L's letter dated April 27, 2009, which has been amended to include sound beam modes and insonification angles.

BSEP 09-0123 Enclosure Page 8 of 9 Response to NRC Question 5-6 Coverage plots are included in the original examination data and the volumes were summarized in Enclosure 2, Table 2 and pages 8-14 of CP&L's letter dated April 27, 2009. Except for one carbon steel weld, the ultrasonic examinations of welds in the R-A Category, that are limited, were for austenitic components. These components were examined using an ultrasonic examination procedure based on the requirements of "PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds UT-PDI-2." This procedure states, "Where dual side access is not possible, the examination shall be performed from a single side of the weld." In situations where components were limited to single side access due to configuration (i.e., as described in Table 2), BSEP has only taken credit for 50 percent of examination. Attachment 6 provides information showing the cross-sectional coverage plots for the volumes examined.
Response to NRC Question 5-7 No recordable indications were detected during these examinations.
NRC Question 6 For Welds 1B2142-4-FWRFWB6 and 1B21PS2A3A3-24-SWJ Contained In Request for Relief RR-43 ASME Code, Section XI, Examination Category R-A, Item 1.20, Elements not subject to a damage mechanism, requires a volumetric examination as specified in Table 1 of ASME Code Case N-578-11 Risk-Informed Requirementsfor Class 1, 2, 3, PipingMethod B, Section XI, Division 1. Magnetic particle examination (MT) is not an approved volumetric NDE method. It is unclear why the licensee has submitted the subject welds, and the limited MT examinations, as part of RR-43. Please clarify the intent of including these examinations in ASME Code, Section XI, Examination Category R-A.
If a volumetric examination was performed in addition to the MT examination:
: 1. Describe the volumetric NDE (UT or Radiography (RT)) with equipment used, details of the listed obstructions (size, shape, proximity to the weld, etc.) to demonstrate accessibility limitations.
: 2. If UT examination was applied, state the UT sound beam modes and insonification angles used for all UT examinations.
: 3. Show cross-sectional coverage plots to describe ASME Code volumes examined.
: 4. State whether any indications were discovered as a result of these examinations, and how these indications were dispositioned.
I ASME Code Case N-578-1 has not been approved for use in Regulatory Guide 1.147, Revision 15 "Inservice Inspection Code Case Acceptability." Licensees use Table I of ASME Code Case N-578-1 as guide to establish their inspection sample and examination categories for their RI-ISI programs.

BSEP 09-0123 Enclosure Page 9 of 9 Response to NRC Question 6-1 The MT examinations associated with these welds were performed as ASME Code, Section XI, Examination Category B-J exams prior to the implementation of RI-ISI and were included in the RR-43 request for this reason. With the implementation of RI-ISI, surface exams were no longer required.
The ultrasonic examinations associated with these welds were performed with no limitations encountered. No relief from UT examination requirements is needed; therefore, a list of the UT equipment used is not included herein.
Response to NRC Question 6-2 As stated in Response 6-1, the ultrasonic examinations associated with these welds were performed with no limitations encountered. These examinations were performed as ASME Code, Section XI, Examination Category B-J exams prior to the implementation of RI-ISI and were included for this reason. With the implementation of RI-ISI, surface exams were no longer required. No relief from UT examination requirements is needed; therefore, the UT sound beam modes and insonification angles used are not included herein.
Response to NRC Question 6-3 As stated in Response 6-1, the ultrasonic examinations associated with these welds were performed with no limitations encountered. These examinations were performed as ASME Code, Section XI, Examination Category B-J exams prior to the implementation of RI-ISI and were included for this reason. With the implementation of RI-ISI, surface exams were no longer required. No relief from UT examination requirements is needed; therefore, cross-sectional coverage plots describing the ASME Code volumes examined are not included herein.
Response to NRC Question 6-4 No recordable indications, either UT or MT, were detected during these examinations.

BSEP 09-0123 Attachment 1 [For NRC Question 1]
Items attached include the following:
: 1. Plant Drawing FP-9527 50208, CRD As-Built. with J-weld locations added
: 2. Plant Drawing FP-9527-5014, Bottom Head Dollar Assembly
: 3. Plant Drawing FP-5609, Sheet 1C, Reactor Assembly
: 4. Plant Drawing C-24004, Sheet 2-1, ISI Isometric Drawing
: 5. Photograph - Upper CRD Welds

Upper CRD welds at the manway. RV can be seen in the background.
Insulation support can be seen below.
I

BSEP 09-0123 Attachment 2 [For NRC Question 2]
Items attached include the following:
: 1. Plant Drawing FP 9527-5012, Elevations Miscellaneous Attachments
: 2. Excerpt from Plant Drawing FP 9527-5013 showing Seam F detail.
: 3. Excerpt from Plant Drawing showing Flange Seam F weld preparation

BSEP 09-0123 Attachment 3 [For NRC Question 3]
Items attached include the following:
: 1. Plant Drawing FP-9527-5003, Recirculation Inlet
: 2. Plant Drawing FP-9527-5049, x28 Nozzle lA/B Assembly

BSEP 09-0123 Attachment 4 [For NRC Question 4]
Items attached include the following:
: 1.      Plant Drawing FP-9527-5098
: 2.      Photograph - Shield Wall and Insulation
: 3.      Stabilizer Bracket Drawing
: 4.      Photograph -Stabilizer Support
: 5.      Photograph - Support and Reactor Vessel

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/covering support
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-overing welded attachment.
                                          ,learance between
                                          'V and shield wall

BSEP 09-0123 Attachment 5 [For NRC Question 5]
Items attached include the following:
: 1. Updated Table 2 from CP&L letter dated April 27, 2009

BSEP 09-0123 Attachment 5 Page 1 of 4 TABLE 2 Ultrasonic ASME                                 Technique ASME      ASME    Code Case                            S=Shear Wave IWB-2500  IWB-2500    N-578-1                           L=Longitudinal Weld           Category  Item No. Item No. Description Coverage        Wave                   Limitation Access limited to pipe side 1B32RECIRC-28-A-9BC-1      B-J      B9.31     R1.20  Pipe - WOL        50%    350 S, 450 S, 600 L of weld only due to weldolet to pipe weld configuration.
Access limited to pipe side 1B32RECIRC-28-A-15BC-1     B-J      B9.31     R1.20  Pipe - WOL       42.7%   35' S, 45' S, 600 L of weld only due to weldolet to pipe weld configuration Access limited to elbow side 1B32RECIRC-28-A-1 1        B-J      B9.11     R1.20  Elbow - Pump      50%    450 S, 60&deg; L        of weld only due to elbow to pump weld configuration.
Access limited to pipe side 1B32RECIRC-28-A-12BC       B-J      B9.31     R1.20  Pipe - WOL       41.3%   350 S, 45' S, 60' L of weld only due to weldolet to pipe weld configuration Access limited to elbow side IB32RECIRC-28-A-8          B-J      B9.11     R1.20  Elbow - Pump      50%    450 S, 600 L        of weld only due to elbow to pump weld configuration.
Access limited to pipe side B-J      B9.31     R1.20  Pipe - SOL        50%    450 S, 600 L        of weld only due to 1B32RECIRC-22-AM-5BCA                                                                             sweepolet to pipe weld
_configuration.
Access limited to pipe side 1B32RECIRC-28-A-9          B-J      B9.11     R1.20  Valve - Pipe      _50%   450 S, 600 L        of weld only due to pipe to valve weld configuration.
Access limited to pipe side 1B11N8A-JPI-FWR122-1      B-J       B9.11     R1.20  SE - Pipe         50%    450S,700&deg;           of weld only due to pipe to safe end weld configuration, pipe fitting, and weld crown.

BSEP 09-0123 Attachment 5 Page 2 of 4 TABLE 2 Ultrasonic ASME                                  Technique ASME      ASME    Code Case                            S=Shear Wave IWB-2500  IWB-2500    N-578-1                           L=Longitudinal Weld         Category  Item No. Item No. Description Coverage          Wave               Limitation Access limited to pipe side B-J      B9.11     R1.20  Pipe - SOL        50%    350 S, 450 L, 60- L of weld only due to 1B32FFE-12-FWRRB14A                                                                              sweepolet to pipe weld configuration.
Access limited due to safe B-J      B9.11     R1.20  SE -SE           86.7%   35- S, 45- L, 600 L    endODmter.
1B21N4D-5-FWN4D315-3                                                                            end OD taper.
IB21N4D-5-SW1-2          B-F       B5.10     R1.14  SE -Pipe         84.8%   35&deg; S, 45- L, 60- L Adjacent weld crown Access limited to pipe side IB32FFE-12-FWRRAIOA       B-J      B9. 11    R1 .20 Pipe- SOL         50%    45 0 S, 600 L       of weld only due to sweepolet to pipe weld configuration.
Access limited to pipe side 1B32RECIRC-22-AM-4        B-J      B9.11     R1.20  Pipe - Tee       43.2%   450 S, 60- L        of weld only due to pipe to tee weld configuration.
Access limited to pipe side 1B32RECIRC-22-BM-5        B-J      B9.11     R1.20  Pipe - Valve      50%    450 S, 60- L        of weld only due to pipe to valve weld configuration.
Access limited to pipe side 1B32RECIRC-28-A-13        B-J      B9.11     R1.20  Pipe - Valve      50%    450 S, 600 L        of weld only due to pipe to valve weld configuration.
Access limited to pipe side 1B32RECIRC-28-A-5         B-J      B9.1 1    R1.20  Pipe - Tee        50%    450 S, 60 L         of weld only due topipe to tee weld configuration.
Access limited to elbow side 1B32RECIRC-28-B-11        B-J      B9.11     R1.20  Elbow - Pump      50%    450 S, 600 L        of weld only due to elbow to
_pump  weld configuration.

BSEP 09-0123 Attachment 5 Page 3 of 4 TABLE 2 Ultrasonic ASME                                  Technique ASME      ASME    Code Case                            S=Shear Wave IWB-2500  IWB-2500    N-578-1                            L=Longitudinal Weld         Category  Item No. Item No. Description Coverage         Wave                  Limitation Access limited to pipe side 1B32RECIRC-28-B-12BC      B-J       B9.31     R1.20  Pipe - WOL        50%    350 S, 450 S, 600 L  of weld only due to weldolet to pipe weld configuration Access limited to pipe side 11B32RECIRC-28-B-1 5BC    B-J       B9.31     R1.20  Pipe - WOL        50%    350 S, 450 S, 60' L  of weld only due to weldolet to pipe weld configuration Access limited to pipe side IB32RECIRC-28-B-2         B-J       B9.11     R1.20  Pipe - WOL        50%    45- S, 600 L         of weld only due to weldolet to pipe weld configuration Access limited to pipe side IB32RECIRC-28-B-9         B-J       B9.11     R1.20  Valve - Pipe      50%    450 S, 600 L         of weld only due to pipe to valve weld configuration.
Access limited to pipe side 1B32RECIRC-28-B-9BC       B-J       B9.31     R1.20  Pipe - WOL        50%    35' S, 450 S, 60' L  of weld only due to weldolet to pipe weld configuration.
Access limited to pipe side 1B32RECIRC-28-B-16        B-J       B9.11     R1.20  Pipe - Tee        50%    450 S, 600 L         of weld only due to pipe to tee weld configuration.
Access limited to pipe side 1B32RS2B2-10-FWB39        B-J       B9.11     R1.20  Pipe - Tee        50%    450 S, 600 L         of weld only due to pipe to tee weld configuration.
Access limited to pipe side G31 15--15-FWRWCUB2A     B-F       B5.130    R1.20  Valve - Pipe      50%    350 S, 600 S, 700 L, of weld only due to pipe to i400 L, 600 L, 70&deg; L valve weld configuration.
Access limited to pipe side B-J       B9.11     R1.20  Pipe - SOL        50%    45- S, 60&deg;L          of weld only due to IB32FFG-12-FWRRAI IA                                                                               sweepolet to pipe weld configuration.

BSEP 09-0123 Attachment 5 Page 4 of 4 TABLE 2 Ultrasonic ASME                                     Technique ASME      ASME      Code Case                                S=Shear Wave IWB-2500  IWB-2500     N-578-1                                L=Longitudinal Weld          Category  Item No. Item No.       Description Coverage          Wave               Limitation Access limited to pipe side IG31PCI-1-FWRWCUCIA         B-J      B9.11       R1.20    Nozzle - pipe      50%     450 S, 600 L     of weld only due to nozzle to pipe weld configuration.
IE21FF-8-FWICS30            B-J      B9.11       R1.20    Elbow - elbow     84.4%    450 S            Support inteference Access limited to pipe side of weld only due to 1B32RECIRC-22-AM-3BCA       B-J      B9.31       R1.20    Pipe - SOL         35%     45&deg; S, 60 L      sweepolet to pipe weld configuration and adjacent weld overlay Access limited to pipe side B-J      B9.3.1      R1.20    Pipe - SOL         50%     450 S, 600 L     of weld only due to IB32RECIRC-22-AM-3BCB                                                                                 sweepolet to pipe weld
_configuration.
Misc. structural B9.11       R1.20                     66% MT    N/A                 su rtsran 1B214-2-4-FWRFWB6           B-J A     B-                          I                  5%
50% NIT I
IN/A supports/grating IWhip restraint IB2iPS2A3-24-SWJ      I     B-J      B9.12  I    R1.20  11

BSEP 09-0123 Attachment 6 [For NRC Question 5]
Cross-Sectional Examination Coverage Plot Information

n WI.SDtnE IMfT S U ATIOC&Lm WESDYNE INTERNATIONAL, SYSTEM:       RECIRC WELD NO IB32RECIRC         WALL THICKNESS PROFILE SHEET                                                              A-9 BC-1 UT EXAMINATION DATA SHEET NO.:                      2 Page 5 of 5 Position             900   1800   270(                                Wel w,_                   *Weld Edge (0
                                          '-i                          .Ceniir~ne TOE*                       N           _/ _F_ _                   1     4    '
CL                      /A TOE                        /I              -"     _       S_ide                               ;6   Side-9      iFLOW CROWN HEIGHT:                    0.050y           DIAMETER:                     7.0" Nom.
CROWN WIDTH:                       1.3"           WELD LENGTH:                     22.0Z LONGSEAM:                          n/a            ISO. DRWG. #                C-24004-19-1 PROFILE AREA                                                        AX-US =
                        .T&Cs taken from previous data              AX-DS= ) 00 CR-US= 0 CR-DS-- t00
                                                                               - 0o0       divided by 4      %
9 rLcva.J EXAMINER:                                          LEVEL          Z7       DATE:        -
EXAMINER:        p           3 j*                  LEVEL                   DATE:
REVIEWER:                                          LEVEL         ,          DATE:
REVIEWER:                                          LEVEL        _           DATE:
Authorized Inspection Agency   _______DATE

SWSDYnE IlN T  a NATI  DN   L.yn WESDYNE INTERNATIONAL,                                 LLC SYSTEM:     RECIRC WELD NO IB32RECIRC         WALL THICKNESS PROFILE SHEET                                                                                 A-15 BC-i UT EXAMINATION DATA SHEET NO.:                              2 Page        5      o4      5 0       900   18(r    2700                                       5Wd ofd 5e Wo2 Position_
                       - ~ ~ ** 1     5We270
                                                /                             .  ~C oni~~n
                                                                                                                   *'Weld Edges TOE-~25"                                         TI           *:*jrn !* 2.5"T a*    -AI:      Tba CLr TOE*         46                  N                                   M    73                          6~d     -          i CL             _                  /
TOE*~                                                   __:___i.____  Sid          =_-
9                  ---                                                     FLOW CROWN HEIGHT:                          Flush                  DIAMETER:                           7.0" Nom.
CROWN WIDTH:                            .700'                 WELD LENGTH:                           22.0" LONGSEAM:                                n/a                  ISO. DRWG. #                     C-24004-19-1 PROFILE AREA                                                                 AX-US                 70.6 T&C's taken from previous data                AX-DS=                  0 CR-US=               100 CR-DS=                 0
                                                  .09 P'9v                   1170.6                          divided by 4 = 42.7%
EXAMINER:                                                      LEVEL    ____DATE:                       3-9 6    -0.;2 EXAMINER:                          --                          LEVEL                       DATE:       ___,___
REVIEWER:                        -                             LEVEL   jj         -"       DATE:       _J. g-'--
REVIEWER:                          . z__&#xfd;                      LEVEL        g              DATE:           _-q,*
Authorized Inspection Agency        '       fa.                           Doo Dc 2

SITE:  Brunswick Nuclear Plant UNIT: 1        REPORT NO.:
&#xb6;       :J GE Nuclear Energy I           COVERAGE PLOT PROJECT:      8112R1                            R-UU 1832RECIRC-28-A-1 I  CONFIG3URATION:    ELBOW            FLOW PUMP SYSTEM L3EIRCULATION              COMPONENT 1IDNO.:
L4. T" Ld&#xfd;"DR&#xfd;AW.y       -  LEVEL GE RIVIEWED~
7 LEVEL 6-A46&#xfd; DATE DATE I/ 'aalCa
                                                /
                                                /   oEQcCuO OEQCNE~

I[ ,......
rSDyMIo..AL            E                 WESDYNE INTERNATIONAL, LLC SYSTEM:        RECIRC WELD NO 1B32RECIRC          WALL THICKNESS PROFILE SHEET                                                                       A-12BC UT EXAMINATION DATA SHEET NO.:                        2 Page 5 of 5 Position       Or     90    180       2700        "                                                 *Wetd Edge 1                                                    C enlirine 2-                                    i..        *      -.2.50         ,:           2.5"-      --
TOE*:           4  1          N                        I        Ell      a'     4-- .F 5'      61 F-51 i       ;3--
TO'-              -j            /-                                                I"n TO E" *                          .      .--                        S iad e                                   Sid e 9*                                                                  -FLOW CROWN HEIGHT:                        Flush              DIAMETER:                       7.0" Nom.
CROWN WIDTH:                         .800"              WELD LENGTH:                      22.0" LONGSEAM:                             nla               ISO. DRWG. #                  C-24004-19-1 PROFILE AREA                                                                AX-US            0 T & C's taken from i*. previous data              AX-DS=
CR-DS=          65.1 100 SCR-US=         100 2  A2 JW   ,                          O          .                          165.1    divided by 4 =41.3%
EXAMINER:                                                 LEVEL         .          DATE:    .--          '
EXAMINER:                                                 LEVEL                    DATE:
REVIEWER:                                                 LEVEL       _            DATE:       S     .
REVIEWER:                                                 LEVEL       j            DATE:      ,
  /                 Authorized Inspection Agency           A "m/-
a                        DATE           '-

WWESDYNE                                         INTERNATIONAL,LC SYSTEM:   RECIRC WELD NO IB32RECIRC-28-A-8 WALL THICKNESS PROFILE SHEET UT EXAMINATION DATA SHEET NO.:                    2 Page 4        of 4 Position      0-    90W  180-    270     .                   wold                *Weld     Edge t   "T             ,/            ' ,,     Centr~lne         ,
TOE*                        N     A21[-1M-                            -       ,   -
TOE*          1Sie:-S                                                                         d
___                     FLOW CROWN HEIGHT:                   Flush      DIAMETER:                   28 Noam.
CROWN WIDTH:                    1.95"      WELD LENGTH:                  93" LONGSEAM:                        nla       ISO. DRWG. #              C-24004-19-1 PROFILE AREA                                                X-US=          100 AX-DS=           0
                                 ~                 ~       CR-US-          100 CR-DS-           0 2D0    divded by 4 = 50%
7j*1 EXAMINER:                                    LEVEL     ,DATE:
EXAMINER:                                    LEVEL      7          DTE:             REVIEWER:                                    LEVEL     -           DATE:      -  7 O&#xfd; REVIEWER:                                    LEVEL
* DATE:        Z=
Authorized Inspection Agency                         DATE

SITE: Brunswick Nuclear Plant  UNIT: 1..           REPORT NO.:
PROJECT:      B112RI                                  R-017 FT
                                                                                        *l.ow SWEFP.O-I PiP..      .           ,... EEP-O-QLFT   .
COMPONENT ID NO.: 1B32RECIRC-22-AM-SBCA  CONFIGURATION:
f
                                                                             ~w~P ~Lcr PIPL 7-T ljr

WALSSITE:                                                                                                                 runck Nuclear P.lnl                                                      UNIT: 2                                                REPORT NO.:
GE Nuclear En.ergy                                                                PROFILE SHEET                                                                                              PRoject:              B213R1 SYSTEM: RECIRCULATION                                                            COMPONENT ID NO.:                                           1 B32RECIRC-28-A-9 P*OSTION                ol              9          l180          270*            PROCEDURE NO.:                                      GE-UT-225 V3 REV 0 1                 N/A              N/A         N/A            N/A 2                  N/A             N/A         N/A            N/A CROWN WIDTH: 1.75" 3                 1.4$             N/A         N/A            N/A NOM DIAMETER:                                  28" 4                 1.25             N/A         NIA            N/A WELD LENGTH:                                        '8" 6                 1.35              N/A        N/A            N/A                                                                                                                                                                                                                                FLOW I.                 I...                                                           ....                                                                       "                               ..
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NudSsr Supplemental Report                                        Report No.:
UT-06-023 OGG"&-;a0n  Gonosvo Page:   .2-3 of     " Id Summary No.: I-JPI-034-RI ExamIner: Stevermer, Aaron                                 Level: If-PDI   Reviewer: James Delbuss3A                          Date: _______ 6 Examiner: VanRuler, Chrtstop'er .."    *-/    .    .       Level: Il-PDI She Review:. Patrick Peter                           Dale:
Other NIA                                              Level:  WA    ANII Review: RayXAcomb     ,OU ,/rco,.*              Date:
Comments:
Sketch or Photo: KSharedddea*Scenned Oatalt2BltNSA-JPI.FWR1222.tpg SAIF   LCAJO 1'; f'
* GE NuclearE               COVERAGE PLOT                                     BI12R1                    R-023 Y                   COPROJECT:
1832FFE-12-FWRR514A      CONFIGURATION;     SWEFP-0-LET plw PIPE ECIRULAIONCOMPONENTIDNO.:
SYSTM:
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                                       /7 r
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    .A      lItIt                                                NUCLEAR POWER "PuIpI Attachment to: U) 09 k UTSheet No. i, Z.,13 Page (       of ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Supplement D Weld Number: /.oZ.t*.*D           W.v qI,0 -
Interfering Condition: .. r, ,      .vn     T       /
Size of Interfering Condition:   "
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                                           ,FLOW
                                                                                          -if-4O  EA1b EXAMINER _                               "
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ABB COMBUSTION ENGINEERING Ai lIt 1                                                     NUCLEAR POWER "pEiPi                                                              Attachment to:*     c"    C, UT Sheet No. t, 1, Page j&    of $5 ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Supplement D Weld Number: /gZi_/V/-D             -AX-9%WI- 7_
Interfering Condition:      .<EE 9-COWt Size of Interfering Condition:   _J&#xfd;S_. Li'O    I/l Distance from Weld Centerline:       /. /-
Distance form Datum Point 0.0:          S'E-*Lowl Reference Drawing Number:       C_ ?_q*             SY=Er /V/-/
5q Comments and Sketches: (include extent of exam coverage not completed)
            .<Axt ENML                                 FL c %w                             p/P25 EXAMINER              7/                                             LEVEL         DATE    _______
EXAMINER                             ",                              LEVEL   "_    DATE _'-"ou REVIEWER       "..                                                  LEVEL I1y      DATE  1,7-00
                                                                     '                        DATE Authorized Inspf 0,1 on AgencyvfZ-,2/1/

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Page 4-      of ULTRASONIC EXAMINATON SCAN UMITATION REPORT Supplement D WelINumber   on-dit ioJn -3 Interfering Condition:
Size of Interfering Condition:
Distance from Weld Centedine:
Distance form Datum Point 0.0:
Reference Drawing Number:
Comments and Sketches: (include extent of exam coverage not completed)
Sw EeP--LT             FLOW    .,            P1 PL EXAMINER                                                    LEVEL        DATE  3&/00 EXAMINER         ,         \ ,)/A/                          LEVEL -dYL& DATE      A,)9 REVIEWER       "Q:&#xfd;                                         LEVEL 3iM:   DATE  3-4"6 Authorized           i
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ABB COMBUSTION ENGINEERING PA, It   lplpI It                                           NUCLEAR POWER Attachment to:  U"TOCo     .,
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ULTRASON[C MAMINATIQN SCAN UMFFATON REPORT Suplement D WeldNumber        ,83zR'*s.*t.p.   -z.z-(Am-q Interfering Condition: SiN6.,E 1LoE- 4Ce!.S.
Size of Interfering Condition: 36 ,-
Distance from Weld Centedine:       ,H/4 Distance form Datum Point 0.0:      v/,4 Reference Drawing Number: r-.-2,*o            Sh't, Zj-I Rev. z Comments and Sketches: (include extent of exam coverage not completed)
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                                                                                                    "-i w'.Es-o t4c.ArEi    air 4ciw ger' EXAMINER.                                                       LEVEL   -      DATE 3-2o1 EXAMINER.                                                       LEVEL-         DATE   7--c'--
REVIEWER                                                        LEVEL 3Pt     DATE "-,0 Authorized h                                                                   DATE "       "
(lz S-("-00

ABB COMBUSTION ENGINEERING AL MIII                                                  NUCLEAR POWER
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Size of Interfering Condition:   Y&AL-'2/"     V'V Distance from Weld Centertine:     _       LrLOW rZE Distance form Datum Point 0.0: YL-" PZ-Z'L4--"
Reference Drawing Number: (L-Zo' -               f,/,  - ZZ-/    jvZ.
Comments and Sketches: (include extent of exam coverage not completed)
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EXAMINER     7                                                  LEVEL         DATE    3-:e-REVIEWER                                                        LEVEL    . DATE      -"0 Authorized Insp"    i Agency                                                  DATE

ABB COMBUSTION ENGINEERING NUCLEAR POWER
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ULTRASONIC EXAMINATION SCAN UMIfATION REPORT Supplement D Weld Number: lasz          e*ae    4 za -. Is Interfering Condition:   ,
Size of Interfering Condition:       _
Distance from Weld Centedine: fzy- *ewW Distance form Datum Point 0.0:
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M0 Z)6K10V-V                    DFe ,4 L/AL11E,      CW   0-CC W' Cl*,. .CCAJ               7.
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EXAMINER                                   , W A9/ 4&r-Z               LEVEL a            DATE   e   - Z 9-o EXAMINER                        "  c., .                               LEVEL         *L   DATE    .- 2.t-o)
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Page    4      of 4 ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Supplement D Weld Number: 183VZ,(C/Rc-26-A-5 Interfering Condition: 77F-Size of Interfering Condition: A/A Distance from Weld Centerline:
                                    . 80l Distance form Datum Point 0.0:    00 3Q Reference Drawing Number: C -,-4'1, Srw      /9-/
Comments and Sketches: (include extent of exam coverage not completed)
FoKw" p';t *-55 EXAMINER                                                    LEVEL    IT   DATE     3-3-0.2 EXAMINER                                                    LEVEL A____ DATE        ,,I,*
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Authorized I rspec  Agency                                                DATE  _______C

ABB COMBUSTION ENGINEERING AL Of It PUMPl                                                  NUCLEAR POWER Attachment to: *
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Reference Drawing Number: L_-       Z.4bo4- Stir  zo - !, _-.
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Page   -    of S; ULTRASONIC EXAMINATION SCAN MMITATION REPORT Supplement D Weld Number: 1,3 3z        e',Zel. 2i -a-. JC Interfering Condition:               _
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Authorized Inspection Agency&4,/       1     ,*  4eX/ -                     DATE i     "     Z.
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* of ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Supplement D Weld Number:       /Z?-_        f_5r&,
                                 - K-ZS-f         -"-_58, Interfering Condition:   ,_,'p*              -
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IUD9    )"/A!?   L-2C.A' *C        0o4&#xfd; Z8      COnL   61A                                              /
EXAMINER                                                              LEVEL       DATE    3.
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GE Nucleer Energy                           WALL THICKNESS                   PROFILE SHEET C~RIGINAL WHENH Yms IMapRIWI IN R;D        FORM NO. UT        TH rroject    Carolina Power & Light                                            Id1SP W eld                  Sheet No. 9- 0(-2 BSEP - UNIT 1                                                 UT Examination Data Sheet No.           R-,Qc(-
ISI-88 SN-402 Record Thickness Measurements As                                                          Weld                     *Weld Edge Indicated, Including Weld Width,                                            -   2.5"    Cen  rine       2.5" Edge-To-Edge At 00.
n2            4*
00&deg;      2700 Position                           2770-Fi              00 7
El       , -.-  '.-I El        1.-3(0 El El                                                                             FLOW CROWN        HEIGHT:                   /                               DIAMETER:                   _'__"
CROWN WIDTH:                                             7             WELD LENGTH:           83 Examined by4:                                 Re                                              eviewed by       [ l pproved by Level                    Date                  Level -,,-Daote_-__--_                     L&#xfd; &#xfd;e        Dote Recorded  by:
L                                              E]SUPPLEMENTAL            DATA ATTACHED                 Page 2-        of  9

I          IABB                                 COMBUSTION ENGINEERING i ElI.1                                                         NUCLEAR POWER Attachment to :         )    .> ,
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Page   4   of-ULTRASONI EXAMAON SCAN UMIrATION REPORT Supplement WeldNumber:          32ee.*L-,-,-l Interfering Condition: V'ALVE Ccw*i.ec4ATIoe' Size of Interfering Condition:     SeeT      ?J.zWj Distance from Weld Centerline: see- 8*LLbwL Distance form Datum Point 0.0: see aLc,*j Reference Drawing Number: r.- 24 004-            swr z - I*, 2gv. I Comments and Sketches: (include extent of exam coverage not completed)
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I1I II        *,                                        ABB COMBUS*ION NUCLEAR POWER   ENGINEERING Attachmentto:  U'T"O5*
UT Sheet No. Z,5 Page   S  of S ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Supplement 0 Weld Number         /,?_z        _       _ -?-    '*L- iC/_
Interfering Condition:     P'PC                          T                                                           5D, Size of Interfering Condition:                  ,5c,_                                                              _Er Distance from Weld Centerline:         Sei---/  ffY-*L*O&-
Distance form Datum Point 0.0:          _sjE            ,
Reference Drawing Number:          t-  7--4no/   _s'&zr- zo-1 ;rev Comments and Sketches: (include extent of exam coverage not completed) if &WdL L LJ          &'VP/( LSAPAE         Zlnz-i D~       k,       Lt    0-0J509?     cLF   L.TLVK-      IOOL~k LOVERA6E PLoT REIEE                                                  LEE ISIDT EXAMINER        ''J             -       .T-.,,        ;.,.,       ,,       LEVEL        DATE :--,
EXMNE                                                 EVL        DATE */F    ::
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UT Sheet No. I,-
Page A     of   4-ULEASONI     EXAMIN SCAN UMITATION REPOrr Supplement D Wekd Number:      te,3,-,cwc        2B Interfering Condition:   o     ,-,                  ,
Size of Interfering Condition:     t-bc       1.36to%
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Distance form Datum Point 0.0: s              - seD.*-&#xfd; Reference Drawing Number.         C..z4_
                                      ,, 2-4.              ztor. ,>Iv.
Comments and Sketches: (include extent of exam coverage not completed)
                                                                                     ~I EXAMINER                             /.                              LEVEL     1        DATE   lK EXMNRw                                                           LEVEL ".........* DATE    ...    ,<,
REVIEWER                                                             LEVEL     -7r- DATE     1 Authorized Inpe&#xfd;                 c arg D T sd -(,--o

ABB COMBUSTION ENGINEERING PA'1lPlW        It                                             NUCLEAR POWER Attachmentto:  07TO6P.
UTSheetNo.  , -
Page 4     of ULTASONIC EXAMINATION SCAN LIMITATION REPORT Supplement D Weld Number:      912_   *-2.&  - io - PJW83cj Interfering Condition: c-otaiueAnorj       ap "T-re Size of Interfering Condition:   -SEe a EL. w Distance from Weld Centerline: se'        Be-'t,,j Distance form Datum Point 0.0: 6c e3        czow Reference Drawing Number:        L--240o4        -w-r. 1 Comments and Sketches: (include extent of exam coverage not completed)
(_.) 4'.      " Ar EX7r ?odA/T B.
PIPE EXAMINER c*       .S:e )
* LEVEL ---  DATE   ,       !
EXAMINER                                                           LEVEL      DATE  c34/(2 REVIEWER                                                           LEVEL_     DATE         ,
Authorized npcion Agncy                           /i'&#xfd;  -~                    DATE

            .i-dw                                               Stipplemental Report                                      Report No.:   UT.06-078 Gencsaom                                                                                                           Page:
SummaryNo.: 1-RWC-493-Rl                                    /
Examiner: Gronewold, Douglas M.       C                     Level:  1l-PDI    Reviewer: James DelbussoffA,+/-    4_W    s         Date: X Examiner:   MA                                              Level:   N'A   Site Review:. Patrick Peterso*:,*nr&#xfd;--,,             Date:-
Other: mWA                                               Level:  NIA   ANII Review: Ray Acomb                               Date:____
Comments:
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WESD     O          E                 WESDYNE INTERNATIONAL, SYSTEM:     RECIRC WELD NO             IB32FFG        WALL THICKNESS PROFILE SHEET                                                          FWRRA11A UT EXAMINATION DATA SHEET NO.:                  2 I
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270' Page 4 of 4
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