Text

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
	ML093340344
Person / Time
Site:	Brunswick
Issue date:	11/20/2009
From:	Mentel P; Carolina Power & Light Co, Progress Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BSEP 09-0123, TAC ME1143, TAC ME1144, TAC ME1145, TAC ME1146
	Download: ML093340344 (69)
	v • d • e

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

Subject:

Reference:

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 1 0-Year Inservice Inspection Interval Requests for Relief RR-42, RR-43, RR-44, and RR-45 (NRC TAC Nos. ME1143, ME1144, ME1145, and ME1146)Letter from Phyllis N. Mentel to U.S. Nuclear Regulatory Commission, Proposed Alternative for 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 Southport, NC 28461 KrýC-A 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 1 0-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 1 B 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 Attachment 4, 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 Enclosure 2, 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 1 B2142-4-FWRFWB6 and 1 B21PS2A3A3-24-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 Requirements for Class 1, 2, 3, Piping Method 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 1 C, 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 I I S! 4 A]VE~!LL 5-TAe I ~*PJ~ECi4 TO-:~CeOTN I~J <~I1t~.N F(L- A,.o 1I*~1/rw..:./YNj;T$TC,~K Ylý- L I- < I (L ~'~~LO~L~'&.L cL*ie~~4~~J~PEA I (ecr~ ~'~t--~ --2 V YI~WAA vessei covering the 3tabilizer Support ncluding the learance between ipport and shield MIl

UWllIl I-iL JppUrL dubbI lI cLateral Support extending from wleshield wall to 4A, welded attachment

/covering support the .. ..... o fShield W all lwelded attachment 1

Stabilizer support xtending from RV ton of shield wall I %JJ Vt 11 IOUI=LIUI I-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° 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 1B32RECIRC-22-AM-5BCA B-J B9.31 R1.20 Pipe -SOL 50% 450 S, 600 L of weld only due to 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° 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 1B32FFE-12-FWRRB14A B-J B9.11 R1.20 Pipe -SOL 50% 350 S, 450 L, 60- L of weld only due to sweepolet to pipe weld configuration.

Access limited due to safe 1B21N4D-5-FWN4D315-3 B-J B9.11 R1.20 SE -SE 86.7% 35- S, 45- L, 600 L end ODmter.end OD taper.IB21N4D-5-SW1-2 B-F B5.10 R1.14 SE -Pipe 84.8% 35° 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, 60 0 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° L valve weld configuration.

Access limited to pipe side IB32FFG-12-FWRRAI IA B-J B9.11 R1.20 Pipe -SOL 50% 45- S, 60° L of weld only due to 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 1 B32RECIRC-22-AM-3BCA B-J B9.31 R1.20 Pipe -SOL 35% 45° S, 60 L sweepolet to pipe weld configuration and adjacent weld overlay Access limited to pipe side I B32RECIRC-22-AM-3BCB B-J B9.3.1 R1.20 Pipe -SOL 50% 450 S, 600 L of weld only due to sweepolet to pipe weld_configuration.

Misc. structural 1 B214-2-4-FWRFWB6 B-J B9.11 R1.20 66% MT N/A su rtsran A B- I I 5% supports/grating IB2iPS2A3-24-SWJ I B-J B9.12 I R1.20 11 50% NIT IN/A IWhip restraint BSEP 09-0123 Attachment 6 [For NRC Question 5]Cross-Sectional Examination Coverage Plot Information n WI.SDtnE WESDYNE INTERNATIONAL, IMfT S U ATIOC&Lm SYSTEM: RECIRC WELD NO IB32RECIRC WALL THICKNESS PROFILE SHEET A-9 BC-1 UT EXAMINATION DATA SHEET NO.: 2 Page 5 of 5 Position (0 900 1800 270( Wel *Weld Edge'-i w,_.Ceniir~ne TOE* N _/ _F_ _ 1 4 'CL /A TOE -" /I _ S_ i de ;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 LEVEL DATE: REVIEWER:

LEVEL , DATE: REVIEWER:

LEVEL _ DATE: Authorized Inspection Agency _______DATE SWSDYnE WESDYNE INTERNATIONAL, LLC IlN T a NATI DN L.yn SYSTEM: RECIRC WELD NO IB32RECIRC WALL THICKNESS PROFILE SHEET A-15 BC-i UT EXAMINATION DATA SHEET NO.: 2 Page 5 o4 5 Position_

0 900 18(r 2700 Wo2 d 5W ofd 5e-~ ~ ** 5We270 *'Weld Edges 1 / .~C oni~~n TOE-~25" jrn 2.5"T TI CLr -A I: Tba TOE* 46 N M 73 6~d -i CL _ /TOE*~ Sid =_- __:___i.____

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LEVEL ____DATE:

3-9 6 -0.;2 EXAMINER:

--LEVEL DATE: ___,___REVIEWER:

-LEVEL jj -" DATE: _J. g-'--REVIEWER:

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ELBOW FLOW PUMP L4. T" Ldý" -DRýAW.y LEVEL LEVEL 6-A46ýDATE'aalCa I / oEQcCuO GE RIVIEWED~7 DATE / / OEQCNE~

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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 previous data AX-DS= 65.1CR-DS= 100 SCR-US= 100 2 A , O 2 JW .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 a "m/- 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

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LEVEL DATE: Z=Authorized Inspection Agency DATE SITE: Brunswick Nuclear Plant UNIT: 1..PROJECT: B112RI REPORT NO.: R-017 SWEFP.O-I FT COMPONENT ID NO.: 1B32RECIRC-22-AM-SBCA CONFIGURATION:

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Stevermer, Aaron Examiner:

VanRuler, Chrtstop'er

.." / ..Other NIA Level: If-PDI Level: Il-PDI Level: WA Reviewer:

James Delbuss3A She Review:. Patrick Peter ANII Review: RayXAcomb ,OU UT-06-023.2-3 of " Id Date: _______ 6 Dale: Date: Comments: Sketch or Photo:

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GE Nuclear E COVERAGE PLOT Y COPROJECT:

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..r, , .vn T /Size of Interfering Condition:

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Ai lIt 1"pEiPi ABB COMBUSTION ENGINEERING NUCLEAR POWER 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:

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_'__" CROWN WIDTH: 7 WELD LENGTH: 83 Examined by4: Re eviewed by l [ pproved by Level Date Level -,,-Daote_-__--_

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.i-dw St Gencsaom SummaryNo.:

1-RWC-493-Rl

/Examiner:

Gronewold, Douglas M. C Examiner:

MA Other: WA ipplemental Report Report No.: Page: UT.06-078 Date: X Date: -Date:____Level: 1l-PDI Level: N'A Level: NIA Reviewer:

James DelbussoffA,+/-

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v t e Letter Sequence Response to RAI
TAC:ME1143, (Open) TAC:ME1144, (Open) TAC:ME1145, (Open) TAC:ME1146, (Open)
Initiation Request, Request Acceptance... Administration Questions Answers 20 November 2009 Results Approval... Other: ML092720935, ML100960547
MONTHYEAR2009-09-23 [Table View]

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

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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

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