RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
| ML072820584 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Limerick, Clinton, Quad Cities, LaSalle |
| Issue date: | 10/05/2007 |
| From: | Cowan P AmerGen Energy Co, Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-07-20507, FOIA/PA-2010-0209, RS-07-134 | |
| Download: ML072820584 (101) | |
Text
www.exeloncorp.com An Exelon Company AmerCen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 N ucl ear Exelon Generation 4300 Winfield Road Warrenville, IL 60555 10 CFR 50.55a October 5,2007 RS-07-134 2 1 30-07-20507 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Clinton Power Station Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
References:
- 1) Letter from P. B. Cowan (ExelodAmerGen) to U. S. Nuclear Regulatory Commission, dated April 19, 2007
- 2) Letter from C. Gratton (U. S. Nuclear Regulatory Commission) to C. M. Crane, dated September 5,2007 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) and AmerGen Energy Company, LLC (AmerGen) requested relief from specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, on the basis that the proposed alternative provides
Response to Request for Additional Information Relief Request - BWRVIP Requirements October 5,2007 Page 2 an acceptable level of quality and safety. Specifically, this proposed alternative concerns the use of the Boiling Water Reactor Vessel and lnternals Project (BWRVIP) guidelines in lieu of specific ASME Code Requirements.
In a conversation with the U. S. Nuclear Regulatory Commission staff on August 24, 2007, a request for additional information was discussed. The U. S. Nuclear Regulatory Commission provided that request for additional information in the Reference 2 letter. Attachment 1 is our response to that request.
In addition to Attachment 1, the following attachments are being provided: - This attachment provides inspection histories for the Exelon/AmerGen facilities, as requested in questions 1 and 3.
Attachments 3 and 4 - These attachments provide revisions to the original relief request as provided in Reference 1. These revisions are the result of the request for additional information, and additional clarifications concerning shroud support plate gussets for the LaSalle County Station, Unit
- 1. Revision bars in the margin identify these changes.
There are no commitments contained in this letter.
If you have any questions, please contact Tom Loomis, 61 0-765-551 0.
Very truly yours, Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC AmerGen Energy Company, LLC Attachments:
1 ) Response to Request for Additional Information
- 2) Inspection Histories
- 3) Attachment 3, Revision 1, Use of BWRVlP Guidelines in Lieu of Specific ASME Code Requirements
- 4) Attachment 4, Revision 1, Comparison of Code Examination Requirements to BWRVIP Examination Requirements cc:
Regional Administrator - NRC Region I Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Limerick Generating Station NRC Senior Resident Inspector - Oyster Creek Generating Station NRC Senior Resident Inspector - Peach Bottom Atomic Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station File No. 06039 Response to Request for Additional Information
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING A REQUEST FOR RELIEF TO USE THE BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT GUIDELINES AS AN ALTERNATIVE TO CERTAIN REQUIREMENTS OF SECTION XI OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE FOR INSERVICE INSPECTION (ISl) OF REACTOR VESSEL INTERNAL (RVI) COMPONENTS FOR CLINTON POWER STATION UNIT 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 LASALLE COUNTY STATION, UNITS 1 AND 2 LIMERICK GENERATING STATION, UNITS 1 AND 2 OYSTER CREEK GENERATING STATION PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 QUESTION:
(1)
In a letter dated October 1, 2003, Entergy Nuclear Operations Inc. (Entergy), the licensee of the Vermont Yankee Nuclear Power Station (VYNPS), submitted a similar relief request in which the licensee proposed to implement the BWRVIP guidelines in lieu of ASME Section XI requirements for the VYNPSs RVI components. In a supplemental letter dated January 22, 2004, (ADAMS-Accession Number ML040690734), Entergy submitted details of the inspections for the RVI components that are consistent with the BWRVIP inspection guidelines. The Nuclear Regulatory Commission (NRC) staff, in its safety evaluation (SE) dated September 19, 2005, approved the VYNPSs relief request.
The NRC staff requests that the licensee (Amergen-Exelon) provide inspection requirements and inspection frequencies for the following units similar to those addressed in VYNPSs (Agency wide Document Access and Management System (ADAMS) Accession No. ML040690734). This information will enable the staff to perform an effective review of the BWRVIP inspection criteria that will be implemented by the licensee.
(1) Clinton Power Station, Unit No. I (2) Dresden Nuclear Power Station, Units 2 and 3 (3) LaSalle County Station, Units 1 and 2 (4) Limerick Generating Station, Units 1 and 2 (5) Oyster Creek Generating Station (6) Peach Bottom Atomic Power Station, Units 2 and 3 (7) Quad Cities Nuclear Power Station, Units 1 and 2 RESPONSE: contains the Inspection Histories for each of the ExelonIAmerGen BW R facilities listed above. These summaries provide, on a component-by-component basis, the inspection methods utilized, the inspection frequency to date, and the results of the inspections.
QUESTION :
(2) Deleted
RESPONSE
Response to Request for Additional Information Relief Request - BWRVIP Requirements Page 2 (3)
Identify whether the following RVI components in each of the units specified in question (1) have previously experienced cracking due to stress corrosion cracking (SCC), intergranular stress corrosion cracking (IGSCC), irradiation-assisted stress corrosion cracking (IASCC) or cyclic loading and identify the extent of cracking. Also provide information regarding the inspection methods and inspection frequencies that were used thus far, and the corrective actions that were taken when degradation was identified in these RVI components.
RESPONSE
Core plate hold-down bolts Top guide grid beams and hold-down assemblies Core shroud welds Core shroud support welds Core spray piping Core Spray nozzle and thermal sleeve Core spray spargers Jet pump assembly and Jet pump beams Jet pump diffuser Jet pump riser welds and thermal sleeves CRD guide tube CRD stub tube In-core housing Dry tube Instrument penetrations Vessel ID brackets LPCl couplings Fuel support castings CRD nozzle Steam dryer Moisture separator Surveillance capsule specimen holder Lower plenum Feed water sparger Refer to the Inspection Histories (Attachment 2), for the inspection frequencies to date, methods, and results. This table also contains the identified corrective actions. The information provided reflects the compilation of the BWRVlP 120 day reports. Corrective actions and inspections performed prior to the BWRVIP were implemented to the requirements of ASME Section XI, as applicable.
QUESTION:
(4)
The NRC staff requests that the licensee identify whether there are any furnace-sensitized stainless steel vessel attachment welds associated with the RVI components in the plants identified in question (1). It is requested that the licensee provide an explanation regarding the type of inspection program and any additional augmented inspection program that are implemented for any existing furnace-sensitized stainless steel attachment welds in these BWR units.
Response to Request for Additional Information Relief Request - BWRVIP Requirements Page 3
RESPONSE
Exelon/AmerGen BW R plants have developed inspection programs for reactor vessel interior attachments in accordance with BW RVI P-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines". This BWRVIP Inspection and Evaluation Guideline contains inspection requirements for both non-sensitized and furnace-sensitized interior attachment welds. The furnace-sensitized welds require an EVT-1 versus a VT-3 or VT-1 (depending on location), for the non-sensitized welds. Each Exelon/AmerGen BW R plant follows the appropriate inspection requirements for their respective attachment welds. Accordingly, there are no additional augmented inspections performed on interior attachment welds beyond those specified in BWRVIP-48-A.
QUESTION:
(5)
In a letter dated October 7, 2005, Entergy Nuclear Operations Inc., the licensee of the James A. FitzPatrick Nuclear Power Plant, submitted a similar relief request (ADAMS Accession No. ML052900075) which included the following BW RVI P reports. To maintain consistency, the staff requests that the licensee include the following BWRVIP reports in its response, and make a commitment that it will comply with the inspection requirements specified in these reports.
(1) BWRVIP-25, "BWR Core Plate Inspection and Flaw Evaluation Guidelines."
(2) BW RVIP-27-A, "BW RVlP Standby Liquid Control System/Core Spray/ Core Plate AP Inspection and Flaw Evaluation Guidelines."
(3) BWRVIP-I 38, "BWRVIP Updated Jet Pump Beam Inspection and Flaw Evaluation."
RESPONSE
Although Exelon/AmerGen, as a member of the BWRVIP, has committed to follow the BWRVIP Guidelines, these BWRVIP reports were not listed in the original relief request since they were considered to be unrelated to ASME Section XI Code Examination Categories B-N-1 and 8-N-2, which are the categories of the Code from which relief is being sought. Exelon/AmerGen continues to consider the reports to be unrelated to the ASME Section XI code examination Categories B-N-1 and B-N-2. However, for consistency with similar relief requests, these reports are listed in the revised relief request (Attachment 3). Wording in Attachment 3, "Proposed Alternative", has also been revised to reflect this point.
QUESTION:
(6)
The NRC staff requests that the licensee confirm whether NUREG-061 9, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets.
RESPONSE
Exelon/AmerGen BWR plants inspect the Feedwater spargers in accordance with the Alternate BWR Feedwater Nozzle Inspection Program, GE-NE-523-A71-0594-A, Rev. 1. This alternate program was approved for use by BWR facilities in the NRC Safety Evaluation dated March 10, 2000, "Final Safety Evaluation of BWR Owner's Group Alternate Boiling Water Reactor (BWR) Feedwater Nozzle Inspection (TAC No. MA6787)." This alternative program requires a visual inspection of the
Response to Request for Additional Information Relief Request - BWRVIP Requirements Page 4 Feedwater sparger (including the tee welds and end brackets) at a specific frequency, depending on thermal sleeve / sparger design, that is the same as the inspection requirements of NUREG-061 9.
QUESTION:
(7)
In Table 1 of Attachment A of the submittal dated April 19, 2007, the licensee indicates that VT-3 inspection will be performed per the BWRVIP-48 report, "BWR Vessel Internal Project, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines," on the lower surveillance specimen holder bracket welds that are within the beltline region. However, Table 3-2 of the BWRVIP-48 report requires VT-1 examination per Table IWB-2500-1, Item Number B13.20 of ASME Section XI. Therefore, the NRC staff requests that the licensee revise Table 1 of Attachment A of the submittal dated April 19, 2007, to substitute VT-1 for VT-3 for the lower surveillance specimen holder bracket welds that are within the beltline region.
RESPONSE
The Table 1 of Attachment 3 has been corrected to reflect the VT-1 visual inspection method.
QUESTION :
(8)
In Table 1 of Attachment A of the submittal dated April 19, 2007, the licensee indicates that the shroud support leg weld (H12) will be inspected per the requirements specified in the staff's SE for the BWRVIP-38 report, "BWR Vessel Internal Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines." However, the staff's final SE for the BWRVIP-38 report indicates that when inspection tooling and methodologies are developed that allow the welds in the lower plenum to be accessible, the guidelines will state that the licensee will inspect these welds with the appropriate non-destructive examination (NDE) methods in order to establish a baseline for these welds. Consistent with these requirements, the NRC staff, therefore, requests that the licensee revise Table 1 of Attachment A of the submittal dated April 19, 2007, to include a commitment that the shroud support leg weld HI 2 will be inspected with the appropriate NDE methods in order to establish a baseline for these welds when the inspection tooling and methodologies permit such an inspection.
As stated in Section 5 ("Proposed Alternative") of Attachment A to the relief request, "In addition, where BWRVIP guidance in existing BWRVIP documents has been supplemented or revised by subsequent correspondence approved by the BWRVIP Executive Committee, the most current BWRVIP approved guidance will be implemented". This is part of the basic commitment to utilize the BWRVIP guidelines that Exelon/AmerGen and all domestic BWR facilities have made. A footnote has been added to Table 1 of Attachment 3 to emphasize this point.
QU ESTlON :
(9)
Top guide grid beams are prone to IASCC when they are exposed to a neutron fluence value greater than 5 X lo2' n/cm2 (E >I MeV). Top guide grid beams could be exposed to a neutron fluence value greater than this threshold value where by the probability of multiple failures of top guide grid beams is enhanced. Therefore, the NRC staff requests that the licensee provide the method of inspection and inspection frequency for the BWR units' top guide grid beams that may potentially be exposed to a neutron fluence value greater than the threshold value during the current IS1 interval.
Response to Request for Additional Information Relief Request - BWRVIP Requirements Page 5
RESPONSE
Currently, Exelon/AmerGen BWR facilities perform inspection of the Top Guide Assembly in accordance with BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines".
However, there are no current programs for inspection of the grid beams. AmerGen's Oyster Creek plant also performs additional inspections of the top guide since indications have been identified on the grid beams. The BWRVIP is presently working on updated guidance for inspection of the Top Guide, which focuses on grid beam inspections. When approved by the BWRVIP Executive Committee, Exelon and AmerGen plants will implement these new requirements.
QUESTION:
(10)
Section 4.1 item 5 of the BWRVIP-100-A report, "Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds," states that fracture toughness values of stainless steel materials that are exposed to a neutron fluence value greater than 1 X lo2' n/cm2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVI P-76 report, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines." Identify whether the core shroud welds and base materials in the BWR units identified in question (1) will be exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E >I MeV) during the current IS1 interval.
Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are not consistent with the BWRVIP-100-A report, the staff requests that the licensee confirm the following:
The inspection frequency and strategy for welds that will be exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) during the current IS1 interval will be evaluated taking into account the lower fracture toughness values that are specified in the BW RVI P-1 00-A report.
Several of the core shroud welds at each of the Exelon and AmerGen facilities will experience high neutron exposure during the current IS1 Interval (fluence values > 1 X lo2' n/cm2 (E > I MeV)). The inspection frequency and strategy for welds that will be exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) during the current IS1 interval will be evaluated taking into account the lower fracture toughness values that are specified in the BWRVIP-100-A report if necessary, or the material subjected to these higher fluence levels will be assumed to be cracked through-wall in the engineering eva I uat ion.
QUESTION:
(1 1)
According to Section 2.0 of the BWRVIP-76 report, core shroud welds shall be inspected every 6 years when the enhanced visual test (EVT-1) method is used for one-sided weld inspections, and shall be inspected every 10 years when the subject welds are examined with the ultrasonic test method. The inspection frequency for the core shroud welds (HI through H7) as indicated in Table 1 of the submittal dated April 19, 2007, is not consistent with the aforementioned requirement. Therefore, the NRC staff requests that the licensee revise the inspection frequency requirement for the subject welds in Table 1 of the submittal.
Response to Request for Additional Information Relief Request - BWRVIP Requirements Page 6
RESPONSE
Table 1 of Attachment 3 has been revised to comply with the BWRVIP-76 report for the welds HI through H7 asshown on page 7.
QUESTION:
(1 2)
Table 2 of the submittal dated April 19, 2007, indicates that four core shroud vertical welds at the Oyster Creek Generating Station were not inspected during the 2006 refueling outage as required by the BWRVIP-76 report guidelines. The NRC staff requests that the licensee provide technical justification for not performing the scheduled inspections and its plans for performing future inspections of these welds.
RESPONSE
As a result of the missed re-inspections, Oyster Creek has developed a "Deviation Disposition" in accordance with Exelon/AmerGen procedures. This Deviation Disposition is supported by a technical justification for performing the subject re-inspections one outage later than originally required. This Deviation Disposition was submitted to the BWRVIP as required by the guidance, and notification of the deviation was sent to the NRC on April 27, 2007 via AmerGen Letter No 2130-07-20493. has been revised to reflect this submittal.
Inspection Histories
Plant:
Clinton 2/2006 (CIRIO)
~
Components in BWRVIP Scope Core Spray Piping EVT-1 One weld each P ~ c,
P4d and P8. NRI.
A-PR, A-ADR, A-BDR, B-PR, B-CDR, and B-DDR piping welds. NRI.
VT-1 A&B-P8. NRI.
EVT-1 A-BP~c, A-BP4d, A-APB(PBl), A-BPB(PB2). NRI.
Core Spray Sparger 10/2000 Attachment Welds A-PR, A-ADR, A-BDR, B-PR, B-CDR, and B-DDR piping welds. NRI.
EVT-I and NRI REACTOR INTERNALS INSPECTION HISTORY (Cl R07) 2/2004 Date or Frequency of VT-1 EVT-1 and NRI.
Ins-pection 10/2000 (CI R09) 2/2006 (C 1 R07)
VT-1 EVT-1 NRI.
2/2004 (Cl R09) 10/2000 (CI R07) 2/2004 (CI R09) 2/2006 (Cl R10)
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspection Method Used VT-3 Guide Rod Support Brackets, Steam Dryer Hold Down Brackets and Steam Dryer Support Brackets per ASME Section XI. NRI.
Several Steam Dryer Support Brackets have contact marks and several do not. Clinton will be Monitoring this condition.
Surveillance Sample BracketsSection XI inspection was NRI. However, both lower tack welds on 2 of the baskets were found cracked. Evaluated for continued operation.
These baskets will be evaluated again in C1 R10.
No change identified in Several Steam Dryer Support Bracket contact points.
No indications identified. Guide rods and brackets were inspected to look for any damage caused by steam separator lower bracket. NRI.
Inspected surveillance sample baskets at 3" and at 1'77" with previously identified cracks. No change was observed.
Lower Bracket @ 0 degrees. Inspected previously identified EVT-1 VT-1 EVT-1 VT-1 VT-1 UT EVT-1 Performed UT on the identified piping welds on both High Pressure Core Spray and low Pressure core Spray piping systems. Two flaw indications, one on each B-P2 and C-P2 welds, were identified. Evaluated for 2 cycles operation per Core Spray Flaw Evaluation Handbook. Examined welds include P2, P3a&b, P4a&b, P5 and P6.
P4c and P4d. No recordable indications (NRI).
~
VT-1 UT A&B-P8. NRI.
Performed UT of piping welds on both High Pressure and Low Pressure Core Spray systems. Two existing flaw indications, one on each BP2 and CP2 welds, were identified to have increased in length. Welds were evaluated and accepted for two additional cycles of operation. One additional flaw on weld DP2 was also identified and evaluated for two cycles of operation.
No other indications identified.
1 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Clinton Components in BWRVIP Scope Core Shroud Shroud Support SLC Date or Frequency of Inspection 4/2002 (C1 R08) 2/2006 (C1 R10) 10/2000 (C1 R07) 2/2004 (C1 R09) 2/2006 (C1 R10)
NA Inspection Method Used UT EVT-1 UT VT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Performed UT of all Horizontal Welds. In addition, some vertical welds screened-in per BW RVIP-76 criteria.
Coverage:
Weld Number H1 H2 H3 H4 upper side H4 lower side H5 upper side H5 lower side H6A H6B H7 v11 v12 V13 V14 Yo of Examined Lenqth 59.7%
67.4%
66.7%
97.1 Yo 19.0%
18.7%
16.4%
25.6%
26.5%
95.2%
95.o%
100%
87.0%
87.0%
Flaw extents were identified as follows:
Weld Number Yo of Examined Lenqth Flawed H1 H2 H3 H4UPP H4Low H5UPP H5Low H6A H6B H7 v11 v12 V13 V14 0%
0%
19.1%
97.2%
74.0%
15.3%
0%
0%
5.4%
0%
0%
0%
0%
0%
Prior to startup, an Engineering Evaluation was performed to justify ultimately two cycles of operation.
4 Tie Rods installed in 2/2006 (Cl R10).
Inspection performed as required by BWRVIP-76. NRI.
EVT-1 of H8 and H9 welds for >lo% length per BWRVIP-38.
No indications identified.
UT of H9 weld for 100% length from outside the Reactor wall. No indication was identified.
VT-1 examined the Access Hole Cover assembly per GE SIL 462. No indications identified.
H8 Weld No indications identified.
Injection is through Core Spray 2 of 76
REACTOR INTERNALS INSPECTION HISTORY 4/2004 (C1 R09) 2/2006 (C1 RIO)
Plant:
VT-3 VT-1 VT-1 best effort Components in BWRVIP Scope Jet Pump Assembly LPCI Couplings Lower Plenum Steam Dryer Inspection 10/2000 I EVT-1 C1 R07 C1 R08 2/2004 4/2002 EVT-1 (C1 R09)
VT-1 UT I VT-l 2/2006 (C1 R10) 4/2002 (Cl R08) 2/2004 (C1 R09) 2/2006 (C1 R10) 4/2002 (C1 R08) 4/2002 (C1 R08)
EVT-1 EVT-1 EVT-1 EVT-I or VT-3 (as applicable)
VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Performed EVT-1 of 50% of the High Priority RS-3 welds.
NRI.
Performed EVT-1 of 50% of the Medium Priority RS-1 welds.
NRI.
Performed EVT-1 of remaining 50% of High Priority RS-3 welds. NRI.
50% of Inlet Mixer IN-I and IN-2 welds. NRI.
50% of the Riser Brace RB-la,b,c,d and RB-2a,b,c,d. NRI.
50% of the RS-2. RS-6. RS-7. RS-8. and RS-9 welds. NRI.
50% of the WD-1 Wedge Bearing Surface, NRI.
50% of the Sensing Lines. NRI.
UT was performed on all 20 Diffusers with 100% coverage of welds: AD-I. AD-2. DF-1. DF-2. and DF-3. NRI.
Sample inspection of WD-1 Wedge Bearing Surfaces on four ournos. NRI.
Examined Loop C except weld 6-6b. NRI.
Examined all welds on Loops A and 6 and weld 6-6bs on Loop C. NRI.
Examined Loop A, all welds. NRI.
Examined seventeen (1 1%) per BWRVIP-47, CRDGT-1, 2, 3 and pin. NRI.
Performed VT-3 of Steam Dryer Tie Rods. No indications identified.
The existing crack on drain channel #8 to the skirt was measured 7-5/8(later designated V16). No change from the previous outages. Clinton has been monitoring this crack since C1 R01.
Steam dryer Drain Channel # 8 to the Skirt (V16) is now 8-3/4 in lenath.
The V16 cracking was repaired using under water welding.
Per SIL direction performed a best-effort VT-1 all banks, cover plates, end panels, hoods, drain channels, the skirt, top and tie-bars from outside.
All welds examined from outside.
- 1) An indication was observed in the drain channel base material, away from the weld. The indication appears to be a minor mechanical deformation. This indication was evaluated for continued operation.
- 2) Two (2) indications were observed in the dryer bank 5 horizontal weld H3. These indications are located under tie rods 28 and 30. They are 12.75 and 2.25 long. These indications were repaired by stop drilling.
- 3) A linear indication was observed in the dryer upper guide at 0 deg. This indication is 1.6 long. This indication was evaluated for continued operation.
- 4) Several linear indications were observed in the dryer upper support ring face. They are located at various locations and degrees. These were evaluated for continued ooeration.
All vertical drain channel welds were reinforced from 1/8 to W durina C1 RIO.
3 of 76
REACTOR INTERNALS INSPECTION HISTORY Components in BWRVIP Scope I
j Inspection I Ins ection Frequency Of Method Used Top Guide 1
2/2004 I VT-3 Plant:
Clinton Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Performed VT-3 of the Top Guide hold-down assembly bolts Vessel (C1 R09) and nuts. NRI.
10/2000 VT-3 Vessel interior to ASME XI. NRI.
(C1 R07) 2/2004 (C1 R09)
Nuclear Instrument Dry-tubes VT-3 Vessel interior to ASME XI. NRI.
I Four IRMs examined as recommended in SIL. NRI.
I VT-3 4/2002 I
(ClR08) 2/2004 (C1 R09) 2/2006 VT-1 4 IRM and 4 SRM. One indication identified on SRM D evaluated by GE for operating one cycle. Other tubes were NRI.
Four IRM, one SRM and four LPRM tubes were examined.
VT-3 I
NRI.
SRM D drv tube was replaced.
I vT-3 Steam Separator 10/2000 I
(ClR07) 4 of 76 Examine overall condition of Steam Separator (50%). Not ASME or SIL driven. NRI.
2/2004 (C1 R09)
VT-3 Examine overall condition of Steam separator (second 50%).
One minor dent identified.
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Date or Frequency of Inspect ion 10/1995 D2R14 1980s-D2RI 3 Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Components in BWRVIP Scope Core Spray Piping VT-1 IEB 80-1 3. No flaws identified.
VT-1 VT-1 (1 MIL) of piping and welds in annulus.
Indications observed at one lower elbow to riser weld (3P4c) and two collar to shroud pipe welds (3 and 4P8a) in 1995. All flaw lengths verified with UT. Full structural margins met on all three flawed welds for one additional cvcle. No repairs performed.
UT Initiated BWRVIP-18 recommendations. Examined piping using the GE CSI-2000 UT device. Identified three previously unidentified flaws (1 P5, 2P8a and 3P4d) for a total of six flaws. Previously identified flaws were determined to be of the same or less extent than originally sized. 1 P5 and 2P8a were not visually verified. All flaws were analyzed for two additional cvcles of ooeration with no reoairs reauired.
3/1998 D2R15 EVT-1 Examined undemonstrated welds P8a and P4d locations with EVT-1 to supplement UT. No additional flaws identified.
10/2000 D2R16 EVT-1 UT, EVT-1 Examined Core Spray Piping: P8a and P4d, at all four locations. Previous indications have been found on the Core Spray Elbow to Collar on the 260" Downcomer. The noted crack growth was bounded by the previous flaw evaluation and the BWRVIP-18 crack arowth value.
GE CSI-2000 inspected a complete Target Set and a sample of P4 welds. No new flaws. Growth within Fracture Mechanics Evaluation predictions. Performed EVT-1 of undemonstrated welds.
10/2001 D2R17 10/2003 D2R18 EVT-1 Examined undemonstrated welds P8a and P4d locations with EVT-1 at all four downcomer locations.
Crack growth was bounded by the previous flaw evaluation.
VT-1 Excessive grinding exam of 1 -4P4a and b. Flaws are unchanaed.
11/2005 D2R19 UT Examined a complete Target Set and a sample of P4 piping welds using the GE CSI-2000 system. No new flaws were identified. Flaws were again analyzed for two additional cycles of operation with no repairs required. Flaws were again analyzed for two additional cycles of operation, however repairs are projected to be necessarv after D2R21.
EVT-1 Examined undemonstrated welds P8a and P4d locations with EVT-1 to supplement UT.
No new flaws identified.
EVT-1 25% (2) piping bracket assembly welds. NRI.
5 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Date or Frequency of Inspection 1980s to D2R15 Inspection Method Used VT-1 EVT-1 (CSVT-1 ),
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections IEB 80-13 VT-1 of sparaers and tee-boxes. NRI.
3/1998 D2R16 Initiate BWRVIP-18 recommendations. Examined 100% of tee-box cover plate welds (Sl), tee-box to sparger arms (S2), and sparger end caps (S4) and brackets (SB) to EVT-1. NRI.
Examined spargers nozzles (S3a and b) and the sparqer pipinq to VT-1. NRI.
VT-1 10/2001 D2R17 EVT-1, VT-1 EVT-1 100% S1; S2a, b; S4a, b. NRI.
VT-1 50% S3a, b. NRI.
VT-1 100% (12) SB. NRI.
11/2005 D2R19 EVT-1, VT-1 EVT-1 100% S1; S2a, b; S4a, b. NRI.
VT-1 50% S3a, b. NRI.
VT-1 100% (12) SB. NRI.
4/1994 D2R15 VT-1 Section XI inspections of jet pump riser brace, dryer, feedwater sparger, core spray, and surveillance capsule holder brackets, performed once per interval.
NRI 3/1998 D2R16 MVT-1 Inspected Core Spray Brackets per BWRVIP recommendations. NR I.
10/2000 D2R17 VT-1 100% (6) Surveillance Capsule Bracket lower attachments. NR I.
VT-3 100% (4) Dryer Lugs. NRI.
100% (6) Guide Rod Attachments. NRI.
100% (6) Surveillance Capsule Bracket upper attachments. N R I.
10/2003 D2R18 EVT-1 EVT-1 100% (4) Dryer Lugs. NRI.
Eight Core Spray piping bracket welds. NRI.
Eiaht feedwater sparaer end-brackets. NRI.
VT-1 Eight feedwater sparger end-brackets. NRI.
EVT-1 100% (8) feedwater sparger end bracket to vessel attachments. NRI.
EVT-1 100% (8) feedwater sparger end bracket pin tack weld. NRI.
EVT-1 25% (2) core spray piping bracket to vessel attachments. N R I.
EVT-1 100% (4) steam drver wall support has. NRI.
1 ll2005 D2R19 EVT-1 VT-1 VT-1 100% (8) feedwater sparger end bracket lug.
NRI.
VT-1 feedwater sparger repair at 240". RI. Hole in the weld of the repaired nozzle. Accepted as-is.
6 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Components in BWRVIP Scope Core Shroud Date or Frequency of Inspection 8/1995 D2R14 03/1998 D2R15 10/1999 D2R16 10/2001 D2R17 11/2005 D2R19 Inspection Method Used EVT-1 and UT NA VT-1, VT-3 UT/EC EVT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Performed examinations per BWRVIP Guidelines of all shroud repair design reliant structures prior to installation of the shroud repair). Inspection of shroud consisted of EVT-1 of all ring segment welds (accessible surfaces), EVT-1 of between 43% and 72% of the length of each vertical weld between H1 &
H2 from OD surface (ID not accessible), UT of between 30% and 50% of the length of each of the 6 beltline vertical welds, EVT-1 of between 43% and 72% of the length of 2 of the 3 vertical welds between H6 & H7 from OD surface (ID not accessible), and UT of 35% of the length of the remaining vertical weld between H6 and H7. NRI.
Installed repair hardware(4 GE designed tie-rod assemblies) to structurally replace the shroud horizontal welds H1 throuah H7.
Shroud repair hardware inspected per GE recommendations. NRI.
Examined shroud vertical welds V14, V15, V16, V17, V18, and V19 using the TEIDE 2 manipulator per BWRVIP-76 for a repaired shroud. This tool employs both ultrasonic and eddy current probes. NRI.
Obtained coverages were:
V14: 80.1%
V15:
80.1%
V16:
83.4%
V18:
62.8%
V17:
52.6%
V19: 58.0%
Performed one-sided EVT-1 of all vertical welds outside of the beltline with 100% coverage including welds V5. V6. V7. V26. V27 and V28. NRI.
Examined 100% (1 6) Ring Segment Welds from the OD. NRI. Coverage was 100% except for the following:
V9:
85%
VII: 95%
V20: 0% (inaccessible due to JP diffuser) v21:
90%
V24:
0% (inaccessible due to JP diffuser)
Attempted EVT-1 of shroud vertical welds V29, V30, V31, V32. These welds are located below H7 and are beyond the scope of BWRVIP-76.0% coverage was achieved due to Jet PumD interference.
7 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Date or Frequency of Inspection Components in BWRVIP Scope Inspection Method Used VT-I and EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Performed 10 year shroud tie rod examination of all four tie rods consistent with GE recommendations and considering industry experience:
0 EVT-1 of the clevis pin to verify if bottomed in slot and checking contact area for movement. NRI.
VT-1 of stabilizer assembly contact between the RPV wall and upper contact, mid support, and lower contact. RI @ 20 and I10 degrees.
Accepted as-is.
spring to tie-rod connection, upper spring jacking bolts and tie rod nut. NRI.
VT-I of contact of the stabilizer assembly between the shroud and upper and lower springs. NRI.
VT-1 of retainer devices at lower support, lower VT-1 of the core date wedae contact. NRI.
Shroud Support 3/1993 D2R13 UT UT examined shroud support plate for radial flaws around thin creviced Access Hole Covers. Performed mior to redacement. NRI.
NA Access hole cover proactively replaced with GE mechanical desian.
8/1995 D2R14 EVT-1 EVT-1 of H8 and H9 for approx 12" at 4 locations of shroud repair hardware attachment areas. NRI.
VT-1 VT-1 of both replacement access hole cover assem blies. NRI.
10/1999 D2R16 EVT-1 Initiate BW RVIP-38 recommendations for Core Support Structures. Examined H8 and H9 welds. NRI.
10/2003 D2R18 VT-1
~~
~ _ _ _
VT-1 of both replacement access hole cover assemblies. NRI.
11/2005 D2R19 EVT-1 EVT-1 H8 & H9 from 132-177'. NRI.
VT-3 VT-3 H9 100% accessible areas, NRI.
SLC 11/2005 D2R19 Enhanced VT-2 Safe end and nozzle examined. NRI.
Jet Pump Assembly 8/1995 D2R14 VT-1 Hold down beams, beam bolt keepers, lock-plates and retainers; restrainer wedges, stops, and adjusting screws, clamp bolts and keepers; riser brace assemblies, adapters and baffle plate welds, sensing lines and sensing line brackets per various SILS.
Latest inspections were in 1995, with no reportable indications (NRI). Inspect 100% every other (even numbered) outage.
Diffuser to baffle plate welds on all 20 iet wrnps. NRI.
3/1998 D2R15 EVT-1 examined Jet Pump Riser Welds RSTI, 2, 3, 4 and 5 on OD on all ten risers. Riser to JP Pair 15/16 has 1-1/2" long crack in elbow HAZ at RS-1.
Evaluated for two cycles of operation without repair.
NRI all others.
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REACTOR
~NTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Components in BWRVIP Scope Date or Frequency of Inspection 10/1999 D2R16 Inspection Method Used EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Initiated sample examinations per BWRVIP-41 including High and Medium Priority welds on the Riser Braces, Restrainer Brackets, and Mixers. Minor Indications were noted that did not require repair.
JP Diffuser EVT-1 High/Med Priority welds per BWRVIP-41 samde and inspection reauirements. NRI VT-1 Initiated sample examinations per BWRVIP-41 on Inlet boltinq and main wedges (WD-1). NRI.
10/2001 D2R1-7 EVT-1 Examined a sample of RB-4 welds (Riser Brace Leaf at RPV). Identified JP#9, upper Rb 4 weld cracked.
Scope expanded to 100%. No other indications.
Measured known RS-1 crack on riser 15/16. No change in last two cycles.
Examined restrainers for set-screw qaps. NRI.
VT-1 UT This outages scope completes the first 6 Year BW RVIP-41 Inspection Interval. Examined Jet Pumps
- 2, 3, 4, 5, 8, 9, 12, 13, 14, 15, 18 and 19 with the Areva UT device. NRI 10/2003 D2R18 VT-1 VT-I 100% (20) WD-I. NRI.
VT-1 100°/~ (8) Jet Pump Sensing Line Clamps. RI (2). Teeth not fullv enqaqed. Accepted as-is.
VT-3 VT-3 100% (20) Jet Pump Bream Tooth Engagement.
NRI.
Measured fkwon JP#%/16 RS-1. No change in length.
Identified DUD piece Dresent on JP#5/6.
~ ~-
EVT-1 of the last of theMedium Priority 50% sample also comdeted. NRI.
NA Installed 19 Riser Brace Mitigation clamps and one Riser Brace Rer,air clamr, on JP#9.
11/2005 D2R19 EVT-1 Examined sample of RS-1, 2, 3, 4 and 5. RI on JP15/16 RS-1 verified no change since last inspection.
Examined AS-I, 2 on JPs 8,9 and AS-I on JP 19.
NRI.
VT-I Examined 100% WD-1. NRI.
Examined 100% JP Sensing Line Clamps. Rls (2) for ratchet teeth engagement. Accept as-is.
Examined 100% JP Riser Brace Clamps. Rls (8) for ratchet teeth engagement. Accept as-is.
JP 11 Aux wedae on vessel side. NRI Jet pump beams have been UT examined each outage using technique capable of detecting cracking at throat and ears. One beam found cracked at ear in 1995 and was replaced.
Jet Pump Beams 8/1995 D2R14 and prior UT UT examined 100% of Jet Pump Beams. NRI.
311998 D2R15 10/1999 D2R16 UT UT UT examined 100% of Jet Pump Beams, NRI.
10/2001 D2R17 UT UT examined 100% of Jet Pump Beams, NRI.
Replaced all 20 Jet Pump Beams with Group 3 10/2003 D2R18 NA weldless keeper beams.
9 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Components in BWRVIP Scope Date or Frequency of InsrJection Inspection Method Used Summarize the Following Information:
inspection Results, Repairs, Replacements, Reinspections 11/2005 D2R19 VT-3 Examined 100°/o of JP beams for ratchet tooth enaaaement. NRI.
LPCl Couplings NA Lower Plenum 8/1995 D2R14 VT-1 11 CRD guide tube lower assembly welds, 2 CRD guide tube upper assembly welds, and 4 CRD guide tube alignment ear welds, NRI.
14 CRD housing to CRD stub tube welds, 14 CRD stub tube to RPV bottom head welds, 3 CRD housing tube to housing cap welds, NRI.
4 incore guide tube to housing welds, 4 incore housing to RPV bottom head welds, 4 incore guide tube stabilizers. NRI.
10/2001 D2R17 EVT-1 and VT-3 5% inspected (9) per BWRVIP-47, CRDGT-1,2,3 and tin. NRI.
Steam Dryer 10/2003 D2R18 VT-I best effort Performed inspections in accordance with the guidance in SIL 644 S1.
Several Rls were identified requiring modification to the outer hoods as well as repairs to several tie bars.
11/2005 D2R19 VT-1 best effort Performed BWRVIP-139 required inspections as well as inspections of high-stress areas as determined by GE models. Internal start-up instrumentation piping was also examined.
Several RI were identified including Four of six gusset feet tip (adjacent to R2 weld), ranging from 7 to 11 5.
Cracking was ground out and a weld repair performed.
Gusset feet extensions were designed and installed to transfer the stress riser to the mid-support ring.
Vertical guide cracking (2) at 220. Both cracks (2.5-5 in length) were stop-drilled.
Remainder of indications were accepted as-is for one cvcle of operation.
Top Guide 8/1995 D2R14 VT-1 Examine beam surfaces around cell in five cells, all four alignment assemblies, and rim to bottom plate weld at the four aliqnment assembly locations. NRI.
10/1999 D2R16 EVT-1 Initiated BWRVIP-26 recommendations. Examined Top Guide Alignment Pins at 90 and 270 and Rim to Lower Plate Weld. NRI.
10/2003 DIZR18 Em-1, VT-1 Examine the alignment assemblies at O, 180 and 270 welds (EVT-1) and alignment pin (VT-l), NRI.
11/2005 D2R19 EVT-1 Top guide rim weld at 235 on the outboard side of cell 03-30. NRI.
Vessel 10/2001 D2R17 UT Examined vertical welds SCl A, SC1 B, SCl D, SC2D, SC3C, SC3D, SC3E, SC4A, SC4B, SC4C, SC4D, SC4E AND SC4-FLG, NRI.
10/2003 D2R18 UT Examined vertical welds SC1 C, SC2A, SC2B, SC2C, SC3A, SC3B. NRI.
10/2001 D2R17 VT-3 Examined vessel cladding from the steam dam to the vessel flange, NRI.
10 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden Unit 2 Date or Frequency of lnsnection Components in BWRVIP Scope I 11/2005 D2R19 Nuclear Instrument Dry-tubes Steam Separator 11/2005 D2R19 Inspection Method Used VT-3 VT-1 VT-1 VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Examined vessel cladding from the steam dam to the vessel flange, NRI.
Examined SRM and IRM drv tubes. NRI.
Examined 3 IRM dry tubes. NRI.
Examined shroud head bolt pin and window condition.
RI identified minor wear that was evaluated as-is for continued operat ion.
Examined eight standpipe to shroud head welds and eight gusset to rinq welds, NRI.
11 of 76
REACTOR
~NTERNALS INSPECTION HISTORY NA VT-1 /VT-3 Plant:
Dresden 3 surface and HAZ of cladding. NRI.
Performed Core Spray Lower Sectional Replacement (all four downcomers) eliminating welds 1 -4P4c, 1 -4P4d, 1 -
4P8a, 1 -4P8b, 1 -4P5, 1 -4P6, 1 -4P7.
Core Spray Lower Sectional Replacement Scope Core Spray Piping Core Spray Sparger VT-1 Date or Frequency of attachment weld, pad surface and HAZ of cladding. NRI.
IEB 80-13 (1 MIL) VT-1 of spargers and tee-boxes. NRI.
Inspection 1980's Through EVT-1, VT-3 EVT-1, VT-3 EVT-1 VT-1 1994 Examined tee-box cover plate welds (Sl), tee-box to sparger arms (S2), and sparger end caps (S4) to EVT-1.
NRI.
Examined spargers nozzles (S3) and the sparger piping Per BWRVIP-18: EVT-1 of all S1, S2 and S4. VT-1 of 50% of S3. NRI.
Sparger to End Cap Welds: 1S4 (7')), 1S4 (183'), 2S4 (7'), 2S4 (183'), 3S4 (3'), 3S4 (187'), 4S4 (3", 4S4 (187'). NRI.
Nozzle Tack Welds: 3S3 (1 87-260Q), 3S3 (260-003'),
-All 12 sparger brackets and bracket to shroud welds.
NRI.
-Core Spray Lower Sectional Replacement (all four downcomers) eliminating inspection of the following welds: 1 -4S1, 1 -4S2a-b.
to VT-3. NRI.
4S3 (187-290'), 4S3 (290-003'). NRI.
4/97-R14 2/99-R 1 5 9/00-R16 10/02-R17 10/04-R18 1 1/06 - R19 1980's Through 1994 4/97-R 14 1 O/OO-R 1 6 10/04 - R18 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspection Method Used VT-1 UT/EVT-1 EVT-1 IEB 80-13 (1 MIL) VT-1 of piping and welds in annulus.
Indications observed at two lower elbow to pipe welds 2P4c and 4P4c. These welds were repaired using GE designed clamps.
UT Baseline inspections per BWRVIP-18 of all piping circ welds in annulus. Repairs removed and not reinstalled.
EVT-1 of any piping welds in annulus inaccessible to scanner. Additional flaws identified on 1, 2 and 3P8a welds.
EVT-1 examined undemonstrated welds P8a and P4d on all four downcomers. Installed a "bumper" repair on 1 P8a at the 80" downcomer.
UT/EVT-1 I UT of "Target" welds and EVT-1 of all undemonstrated VT-1 EVT-1 I welds. Also EVT-1 of welds made inaccessible from repair installed on the 80" downcomer including 1 P7, 1 P ~ c,
1 P4d, 1 P8a and b. Welds 2P4c and 4P4c exhibited flaw growth as predicted by Flaw Evaluation.
Six P4 welds for presence of "excessive grinding". NRI.
All undemonstrated welds P8a and P4d and long seams on thermal collars, NRI Examined piping welds 1P1, 2P1, 1P2, 2P2, 1P3, 2P3, 3P3,4P3,2P4a, 2P4b.
Eight Core Spray Piping brackets, attachment weld, pad EVT-1
- VT-1 of all accessible bolting, keepers, ratchets and latch springs. NRI
- VT-3 of all repair hardware. NRI Examined piping welds: 1P1, 2P1, 1P2, 2P2, 1P3, 2P3, 3P3, 4P3, 3P4a, 3P4b and two piping brackets, 12 of 76
Plant:
REACTOR INTERNALS INSPECTION HISTORY Dresden 3 Components in BWRVIP Scope Attach m en t Welds Core Shroud Date or Frequency of Inspection 4/94-R 1 3 10/00-R16 10/02-R17 10/04-R18 11/06-R19 4/94-R 1 3 4/97-R 1 4 2/99-R15 1 O/OO-R 1 6 10/04-R18 Inspection Method Used VT-1 VT-1 EVT-1 EVT-1 VT-1 VT-3 EVT-1 VT-1 EVT-1 and UT EVT-1 and UT NA VT-1 UT EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, ReinspectionsSection XI inspections of jet pump riser brace, dryer, feedwater sparger, core spray, and surveillance capsule holder brackets, performed once per interval. NRI.
ASME Section XI B-N-2, surveillance capsule holder attachments in beltline. All six sets examined. NRI.
BWRVIP-48 attachments: four dryer lugs, eight feedwater sparger end-brackets, eight Core Spray Piping brackets, attachment weld, pad surface and HAZ of cladding. NRI Four steam dryer wall support lugs, lug to pad, and pad to vessel attachment welds. Eight feedwater sparger lug to vessel attachment welds. NRI.
Eight feedwater sparger end-bracket lug assemblies. NRI Examined attachment welds for two Core Spray piping brackets and all four steam dryer wall support lugs in accordance with ASME Section XI. NRI Inspected piping bracket to piping weld and bracket to vessel attachment weld on 2 core spray piping brackets.
NRI Inspected all of the end bracket pins for tack weld and pin wear. RI -Wear identified between head of pin and bracket on four brackets. Justified operation for one cycle.
Inspected sparger repair hardware from D2R18 isokinetic Drobe retrieval. NRI Inspections per SIL 572, extensive indications in circumferential welds.
Inspected all shroud repair design reliant structure prior to installation of comprehensive repair (4 G E designed tie-rod assemblies). Inspections consisted of EVT-1 of all ring segment welds (accessible surfaces), UT for minimum ligament of all vertical welds accessible to scanner and EVT-1 for minimum ligament on all accessible surfaces of all vertical welds not accessible to the scanner.
Installed four tie-rod shroud repair assemblies and four core plate wedges.
Examined all four tie-rod assem blies and core plate wedges at locations specified by the manufacturer (GE).
Examined a 40" segment of H4 to assist in shroud qualification of Core Spray Repair. NRI.
Examined Ring Segment Welds V1 -V4 (Shroud Head RSWs), V8-Vl3 (Top Guide RSWs), and V20-V25 (Core Plate Support RSWs). Historical indications at V23 and V25 revealed no apparent change since last inspection in R14 (indications are not in HAZ. All other RSWs NRI.
13 of 76
Plant:
REACTOR INTERNALS INSPECTION HISTORY Dresden 3 Components in BWRVIP Scope Date or Frequency of Inspection 11/06 - R19 Shroud Support 4/94-R 1 3 2/99-R 1 5 r I
R18 I 11'06-R19 SLC Jet Pump Assembly 10/02 - R17 11/06-R19 4/94-R 1 3 Inspection Method Used UT EVT-1 VT-3, EVT-1 UTA/T-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1,
VT-3 PT PT VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections GE utilized the Telescoping Shroud Scanner to perform UT on Shroud vertical welds V5-V6, V14-VI9, V26-V28.
Coverage obtained as follows:
V5 - 80.4%
V6 - 34.8%
V14 - 66.8%
V15 - 75.6%
V16 - 80.4%
V17 - 77.9%
V18 - 95.5%
V19 - 69.8%
V26 - 13.7%
V27 - 69.4%
V28 - 57.6%
One indication identified on V27 (1.8' in length).
Indication acceptable for continued operation in accordance with BWRVIP-76.
Performed one-sided EVT-1 exam inations on vertical welds. NRI. Coverage as follows:
V29 - 40% (between H7 and H8 welds)
V30 - 0% (between H7 and H8 welds)
V31 - 30% (between H7 and H8 welds)
V32 - 0% (between H7 and H8 welds)
Performed GE recommended inspections of shroud repair hardware. Scope included inspections to address susceptible areas based on indications found at Hatch.
One RI identified due to retainer clip not engage. This retainer clip is redundant and did not reauire repair.
V7 - 40%
Access hole cover VT/UT for circ and radial flaws. NRI.
Examined H8 and H9 for about 12" at 4 locations of shroud repair hardware attachment areas. NRI.
Per BWRVIP-38: Examined H8 and H9 between Jet Pumps 20 and 1 (312"-357"). NRI. Requirements for this inspection cycle are satisfied. NRI.
Welds on Access Hole Covers at 155" and 335". The D3 AHC's have not been repaired. NRI.
Examined H8 and H9 between Jet Pumps 10 and 11 VT-3 of accessible areas of H9 and EVT-I of 10% of H9 (between Jet Pumps 10 and 11). NRI.
(1 32'4 77"). NRI.
PT of surface of Safe-end extension and safe-end to nozzle weld. NRI.
PT of surface of Safe-end extension and safe-end to nozzle weld. NRI.
Hold down beams, beam bolt keepers, lockplates and retainers; restrainer wedges, stops, and adjusting screws, clamp bolts and keepers; riser brace assem blies, adapters and baffle plate welds, sensing lines and sensing line brackets per various SILS.
Prior to R13, visually inspect 100% of upper areas of each Jet Pump including beam retainers every other outaae.
14 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden 3 Components in BWRVIP Scope Date or Frequency of Inspection 4/94-R 1 3 4/97-R 1 4 2/99-R 1 5 10/02-R17 03/03- 03 M 09 10/04-R18 Inspection Method Used VT-1 EVT-1 EVT-1 VT-I EVT-1 VT-1 VT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections
~
~~
Riser brace arm to yoke welds on three upper (secondary) riser braces found cracked. Repairs are not required. No other reportable indications.
Diffuser to baffle plate welds on all twenty jet pumps. NRI.
All ten RS-1, 2, 3, 4 and RS-5. NRI.
Initiate BWRVIP-41:
Medium Priority: 50% of DF-1, MX-1, MX-3 and IN-5 welds. All twenty RB-I, 2, RS-8 and RS-9. NRI.
High Priority: 50% of DF-2, AD-I, 2 and 3. NRI.
Examined all twenty WD-1 locations. NRI.
Repeat examination of four DF-2 welds to improve coverage. NRI.
Five RS-9 and 10 riser to secondary brace yoke welds, NRI. Eleven secondary brace RB-3 welds per ASME XI and BWRVIP-48. NRI.
Verified acceptable restrainer set-screw gaps when replaced beams (reference Jet Pump Beams section of this report). Aux wedges installed two set-screw locations.
The other locations were NRI.
Examined jet pump sensing line clamps on jet pumps 1, 2,3, 10, 11, 12, 13,&20.
Examined all twenty WD-1 locations. Noted normal movement of wedges 11 & 20 with no abnormal wear. All other wedges NRI.
Examined AS-I (set-screw gaps) on five jet pumps: 8 (Vessel Side, Shroud Side), 9 (VS,SS), 11 (SS), 12 (VS,SS), 20 (VS,SS). No unacceptable gaps were identified (all less than 0.01 0).
Examined AS-2 (set-screw tack welds) on five jet pumps:
8 (VS, SS), 9 (VS,SS), 11 (SS), 12 (VS, SS), 20 (VS,SS).
Lack of fusion of tack welds was identified on jet pumps and set screws: 9 (VS), 11 (SS), & 13 (VS). Indications noted on the tack welds for 9 and 13 were accepted as-is for one-cycle. Jet pump 11 had a set screw missing from its housing. The set-screw was retrieved and an auxiliary wedge was installed. Also discovered during the inspection of jet pump 11 was a poor quality tack weld on the swing-gate keeper. The condition of the bolt keeper was accepted for one cycle.
The auxiliary wedge installed during D3M09 on jet pump 13 was examined and historical cracking was re-identified on the set screw mounting block. This indication is historical and was caused by the ejection of the inlet-mixer following the failure of a beam-bolt. The indication has been accepted as-is. Also discovered on jet pump 13 was a gap between the vessel side restrainer bracket and the swing gate. The condition of the bracket and swing aate was acceDted for one cvcle.
Examined RS-10 & -1 1 on jet pumps: 2, 3, 4, 12, & 13.
NRI.
Examined RS-1, 2, & 3 on five jet pump pairs: 1/2, 3/4, 9/10, 11/12. 13/14. NRI.
15 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden 3 Components in BWRVIP Scope Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Date or Frequency of Inspection UT Examined MX-3a&b, DF-1, -2 & -3 and AD-I, -2 on jet pumps: 2, 3, 4, 5, 8, 9, 12, 13, 18, & 19. NRI.
EVT-1 Examined RB-1 & 2 on jet pumps: 1, 2, 3,4, & 20. NRI Examined RS-4 & 5 on jet pump pairs: 9/10, 11/12, 13/14.
NRI Examined RS-8 & 9 on jet pump pairs: 1/2, 3/4, 5/6. NRI Examined MX-I and IN-5 on jet pumps: 1, 2, 3, 4, 5, 11, 12, 13, 14, 15. NRI Examined aux wedge on JP 11. RI for slight wear on JP 11 aux wedge. Justified continued operation for one cycle.
Examined main wedge WD-1 on JPs 1,2,3,4, and 11 for wedae wear. NRI.
11/06 - R19 VT-1 NA
- Installed new ratchet style swing gate on JP 11 to address degraded keeper tack weld identified in R18.
- Staked threads due to cracked tack welds (found in D3R18) and installed aux wedges on JP 9 vessel side and JP 13 vessel side set screws.
Jet Pump Beams 4/94-R 1 3 UT Jet pump beams are UT examined each outage using technique capable of detecting cracking at throat and ears. Original group 1 beams.
Examined all beams. Two beams with indications replaced. Balance NRI.
Examined all beams. NRI.
Two beams with indications replaced with group 2 style beams. Balance NRI.
Replaced all 17 original beams with weld-less keeper group 3 beams.
Examined 17 group 3 beam bolt retainer mechanisms (weld-less keeper) to ensure all keepers were engaged.
NRI.
Examined 3 (not replaced in D3M09) welded keeper style beams. BB-1 and BB-2 on Jet Pumps 5 8, and 13. NRI.
Pre-emptively replaced ageing beams on JPs 5, 8 and 13 rather than UT examine.
ICH/RPV-1 and ICHGTACH-1, two inspected from cell H7. NRI.
4/94-R 1 4 UT 2/99-R 1 5 10/00-R16 UT UT NA 10/04-R18 VT-3 10/04 - R18 EVT-1 NA 11/06-R19 LPCl Couplings Lower Plenum NA 4/97-R14 MVT-1 MVT-I 4/97-R14 10/00-R16 EVT-1 Per BWRVIP-47: examined CRGT-1,2 and 3 on D10.
NRI.
Examined 9 CRGT-1, 2 and 3 and FS/GT-ARPIN.NRI.
This completes first 5% in 6 years.
10/02-R17 EVT-1 and VT-3 16 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden 3 Components in BWRVIP Scope Date or Frequency of Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspection 10/04-R18 VT-3 Bottom Head Drain cleaning project created access for the following exam inat ions:
- Examined eight Stub Tube to Vessel Welds (ST/RPV-1) and eight Stub Tube to CRD Housing Welds (CRDH/ST-
- 1) in cells: F7, G6, G7, G8, H7, H8, H9, J8. NRI.
- Inspected two locations for Core Plate to Stiffener Plate Stitch welds: G7 & G8 beam welds. NRI.
- Examined two locations for Stiffener Plate to Stiffener Rods welds: G7 and H8 beam tie rods. NRI.
- Examined exterior surfaces including outer hoods, historical repair areas, tie bars and attachment welds, four lifting assemblies, four hold down assem blies, two man way covers, cover plates, fourteen gussets, upper ring welds, vertical guide welds, outlet plenum lower horizontal welds, outlet plenum vertical welds, and perforated plates. Multiple indications identified, including structural fatigue flaws in the outer hood areas. Outer hoods modified to repair cracking.
- Examined interior surfaces including: drain channel welds, supports, vertical and horizontal plates, support ring, horizontal cross beams, and horizontal cross beam gussets. Initial start-up steam sample probe discovered missing. Probe located and retrieved from steam separator. Multiple non-structural indications also noted.
Best effort VT-1 Steam Dryer Top Guide 10/04-R18 VT-3 Examined interior and exterior skirt. Indications noted.
11/06 - R19 4/94-R 1 3 Best Effort VT-1 Performed VT-1 inspection of outer hood welds on old dryer where previous indications had been identified and repaired. NRI.
NA VT-1 Installed new dryer.
Examined beam intersections in five cells in response to industry experience. NRI.
Per BWRVIP-26, baseline examined all four top guide alianment assemblies. NRI.
4/97-R 1 4 VT-1 EVT-1 Examined rim to bottom plate weld at the four aligner assemblv locations. NRI.
10/00-R16 10/04-R18 VT-1 Examined 0 and 270 top guide alignment assemblies.
NRI.
EVT-1 Examined rim weld 11. NRI.
VT-1 EVT-1 EVT-1 Examined 909 and 1 802 top guide alignment assem blies.
NRI.
Examined rim to bottom plate weld at 909 and 1809. NRI.
11/06 - R19 Examined rim weld from cell 03-34. NRI Vessel 10/02 - R17 10/04-R18 UT Examined vertical welds SC1 A, SC1 C, SC2B, SC3A, SC3B, SC3C, SC3D, SC4A, SC4B, SC4C, SC4D. NRI.
- Examined vertical welds SCI B, SC2A, SC2C, SC3A, UT VT-3 SC3B. NRI. Satisfies third interval Section XI inspection requirements.
- Examined two original vessel construction base metal repair areas in beltline as required by Section XI. NRI.
Inspected cladding in accordance with ASME Section XI.
NRI.
17 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Dresden 3 Inspection Method Used Frequency of Ins ection 1 1/06 - R19 VT-3 5 I 4/94-R 1 3 VT-1 11/06-R19 VT-1 10/04-R18 VT-1 r
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspected the reactor vessel cladding from the shroud flange to the reactor flange in accordance with ASME Section XI. NRI Identified one cracked dry tube (24-37). Replaced.
Examined every other outage to date. Per Reutter-Stokes recommendations, have not reached manufacturers service life.
Examined two SRM and four IRM dry tubes from 3 sides to meet SIL 409. NRI Examined shroud head bolt pin and window condition. RI identified minor wear that was evaluated as-is for con tin ued ope rat ion.
Examined eight standpipe to shroud head welds and eight gusset to ring welds, NRI.
Components in BWRVIP Nuclear Instrument D ry-t u bes Steam Separator 1 18 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
LaSalle 1 L1 R10 (2004)
L1 R09 (2002)
Components in BWRVIP Scope EVT-1 EVT-1 Visual examination of those core spray piping welds for which UT technique is not demonstrated. No indications.
Visual examination of those core spray piping welds for which Core Spray Piping L1 R08 (1 999)
Core Spray Sparger Attachment Welds examination in L1 R10.
Visual examination of those core spray piping welds for which EVT-1 Core Shroud LlR11 (2006)
L1 R10 (2004)
Inspection LlR11 (2006)
UT No indications.
Visual examination of 50% of the core spray sparger welds.
No indications.
Visual examination of 50% of the core spray sparger welds.
EVT-1 EVT-1 LlR11 (2006)
~
EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Re-sized flaws on BP4a, DP5, and DP6. Flaw evaluation performed and welds scheduled for examination in L1 R12.
Visual examination of those core spray piping welds for which UT techniaue is not demonstrated. No indications.
I No indications.
Visual examination of 50% of the core spray sparger welds.
No indications.
Ultrasonic examination of 34 welds for which the UT technique is demonstrated. Re-sized flaws on BP4a, DP5, and DP6.
Flaw evaluation performed and welds scheduled for examination in L1 R l l.
I EVT-l L1 R08 (1 999)
Visual examination of 50% of the core spray sparger welds.
No indications.
UT technique is not demonstrated. No indications.
Ultrasonic examination of the welds for which the UT technique is demonstrated. Re-sized flaws on BP4a, DP5, and DP6. Flaw evaluation performed and welds scheduled for EVT-1NT-1 IVT-3 EVT-1 (See jet pump and core spray sections for those attachment welds.) Visual examination of 2 guide rod attachment welds, 12 feedwater sparger attachment welds, and both the upper and lower surveillance capsule welds at three locations. No indications.
Visual examination of the steam dryer support lug at 185" where wear was observed last outaae. No chanae in the wear.
UT technique is not demonstrated. No indications.
Visual examination of 50% of the core spray sparger welds.
LlR11 (2006)
L1 R07 (1 996)
UT UT L1 R09 (2002)
LlR11 (2006)
LlR10 (2004) I EVT-1NT-1 NT-3 (See jet pump and core spray sections for those attachment welds.) Visual examination of 4-steam dryer support lug welds, 2 feed water sparger attachment welds, and both the upper and lower surveillance capsule welds at three locations.
The steam dryer support lug at 185" showed signs of wear and was accepted for one cycle.
(See jet pump and core spray sections for those attachment welds.) Visual examination of 4 steam dryer support lug welds. No indications.
UT of welds H3, H4, H6, and H8 (LaSalle-specific numbering).
Coverage on H6 and H8 was less than 50%, and a site-specific flaw evaluation was performed and re-inspection is in 6 years. Note that 100% of the accessible areas were not examined, and a Deviation Disposition was submitted.
Indications were less than 10% on each weld.
UT of welds H3, H4, H5, H6, and H8 (LaSalle-specific numbering). No indications noted except on H4, where indications were 3.0%. Next insDection in 2006.
19 of 76
REACTOR INTERNALS INSPECT~ON HISTORY Inspection Method Used EVT-1 VT-3 EVT-1 I Plant:
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspectiom Visual examination of 8 shroud support plate gusset welds.
No indications.
Visual exam of 100% of the accessible portion of the top of H9 and both access hole covers. No indications.
Visual examination of 11 shroud support plate gusset welds.
No indications.
LaSalle 1 EVT-1 UT EVT-1 EVT-1 Components in BWRVIP Scope Visual examination of approximately 20% of H8a. No indications.
Ultrasonic examination of 100% of the H9 weld from the vessel outside diameter. No indications.
Visual examination of 6 shroud support plate gusset welds.
No indications.
Visual exam ination of approximately 2% of H8a, 23% of the too of H9. and both access hole covers. No indications.
Shroud Support VT-1 VT-2 VT-2 PT SLC Visual examination of both access hole covers. No indications.
Visual examination during the system leak test. No indications.
Visual examination during the system leak test. No indications.
Surface examination. No indications.
Jet Pump Assembly VT-2 VT-2 Date or Frequency of Inspection LlR11 (2006)
Visual examination during the system leak test. No indications.
Visual examination during the system leak test. No indications.
The hold-down beams on jet pumps 5,6,9 and 10 were LlR11 (2006)
EVT-1 L1 R10 (2004) proactively replaced with low stress beams.
Visual examination of RB-2 welds on 6 oumos. NRI.
L1 R10 (2004)
VT-3 EVT-1 VT-1 L1 R09 (2002)
The slip joint clamps on jet pumps 5, 6, 9 and 10 were upgraded to a new style.
Visual examination of the 16 old style slip joint clamps installed in the previous outage. No indications.
Visual examination of RB-1 on 12 jet pumps and RB-2 on 6 jet pumps. No indications.
Visual examination of WD-1 on 20 jet pumps. No change in the wear identified in L1 R10.
L1 R08 (1 999)
Visual examination of RS-3 on 5 pumps. No indications.
BB-1, BB-2, and BB-3 areas of all 20 hold-down beams.
L1 R07 (1 996)
EVT-1 VT-3 LlR11 (2006)
Indications at BB-1 on Jet Pump 15 resulted in replacement of this beam with a low stress beam. When the inlet mixer for Jet Pump 19 was replaced, the beam was proactively replaced.
Visual examination of RS-3 on 5 risers. No indications.
Best effort examination of the inaccessible welds AD-1, AD-2, and DF-3 on all 20 iet oumos. No indications.
L1 R10 (2004)
EVT-1 EVT-1 EVT-1 L1 R09 (2002)
Visual examination of DC-3 on 8 pumps. No indications.
Visual examination of DF-1 on 11 Jet Pumps. No indications.
Visual examinations of DF-2 on 2 Jet Pumps. No indications.
L1 R08 (1 999)
L l R l l (2006)
EVT-1 EVT-1 EVT-1 L1 R10 (2004)
Visual examination of RS-1 welds on all 10 risers. No indications.
Visual examination of RS-2 welds on 5 risers. No indications.
Visual examination of RS-3 on 5 risers. No indications.
Installation of riser brace clamps on the risers for jet pumps 5/6 and 9/10 to reDair the RS-9 flaws identified in L1 R10.
20 of 76
REACTOR INTERNALS INSPECTION HISTORY EVT-1 EVT-1 Plant:
I Visual examination of RS-6 and RS-7 on 10 jet pumps. No indications.
Visual examination of RS-8 on all 20 jet pumps. No Components in BWRVIP Scope EVT-1 Jet Pump Assembly continued indications.
Visual examination of RS-9 on all 20 jet pumps. Indications Date or Frequency of Inspection EVT-1 L1 R09 (2002) found on 3 jet pumps (5, 6 and 9). Flaw evaluation performed and required the installation of a repair in L1 R l l.
Visual examination of IN-1 on 11 iet w m m. No indications.
L1 R08 (1 999)
Inspection Method Used Visual examination of IN-2 on 11 jet pumps. No indications.
Visual examination of MX-2 on 11 jet pumps. No indications.
Visual examination of RB-1 on 19 of the jet pumps. No indications.
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections EVT-1 VT-1 VT-1 EVT-1 Visual examination of RB-2 on 18 jet pumps. No indications.
Visual examination of WD-1 on 20 jet pumps. Wear identified on 10 jet pumps. Wear accepted as-is on 9 jet pumps; inlet mixer for jet pump 19 replaced with a different inlet mixer.
Visual examinations of 10 auxiliary wedges installed in previous outages. No indications.
Installed auxiliary wedges at the following vessel side locations: jet pumps 4, 12, 13, 14, 15, 16, and 19. Installed auxiliary wedges at the following shroud side locations: jet pumps 1, 3,4. 12, 14, and 16.
Visual examination of the strain relief welds on the 10 risers.
No indications.
Slip ioint clamtx were installed on all 20 iet r>umr> inlet mixers.
VT-3 VT-1 UT Visual examination of WD-1 on 4 jet pumps. No indications.
Installed auxiliary wedges at the following vessel side location:
jet pump 6. Installed auxiliary wedges at the following shroud side location: 11.
Visual examination of 2 auxiliary wedges installed in previous outages. No indications.
UT of 10 jet pump beams at the BB-1 and BB-2 locations. No indications.
EVT-1 EVT-1 Visual examinations of DF-2 on 10 Jet Pumps. No indications.
Visual examination of RS-1 welds on 5 risers. No indications.
EVT-1 EVT-1 EVT-1 EVT-1 I Visual examination of DF-1 on 10 Jet Pumps. No indications.
Visual examination of RS-2 welds on 5 risers. No indications.
Visual examination of RS-3 on 5 risers. No indications.
Visual examination of RS-6 and RS-7 on 10 jet pumps. No indications.
EVT-1 EVT-1 Visual examination of RS-8 on 10 jet pumps. No indications.
Visual examination of RS-9 on 10 jet pumps. No indications.
EVT-1 EVT-1 EVT-1 EVT-1 I Visual examination of IN-1 on 10 iet w m m. No indications.
Visual examination of IN-2 on 10 jet pumps. No indications.
Visual examination of MX-2 on 10 jet pumps. No indications.
Visual examination of RB-1 on 10 of the jet pumps. No indications.
EVT-1 Visual examination of RB-2 on 10 of the jet pumps. No indications.
21 of 76
REACTOR INTERNALS INSPECTION HISTORY VT-1 VT-3 UT VT-1 EVT-WT-3/VT-1 EVT-l/VT-3/VT-1 VT-3 VT-3 VT-3/EVT-1 Plant:
replaced.
Auxiliary wedges installed at the following vessel side locations: jet pumps 1, 5, 7, 8, and 10. Auxiliary wedges installed at the following shroud side location; jet pumps 6.
Gaps at the vessel side set screw were identified on 1 pump and accepted without installation of an auxiliary wedge for one cycle. Gaps at the shroud side side screw were identified on 1 pump and accepted without installation of an auxiliary wedge for one cycle.
The temporary auxiliary wedges installed on the vessel and shroud side of jet pump 9 were replaced with permanent auxiliary wedges. The wear on WD-1 was accepted for an o t h e r c yc I e.
Visual examination of WD-1 on 2 jet pumps with wear observed on jet pump 9. Flaw evaluation determined acceptable for one cycle.
UT of all 20 jet pump holddown beams at BB-1; one indication on #9 beam; beam replaced.
A gap was identified on the vessel side set screw of jet pump 9, and temporary wedges were installed at both set screws on jet pump 9.
Visual examination of four locations on all three couplings. No indications.
Visual examination of four locations on all three couplings. No indications.
Areas below the core plate made accessible due to the removal of the inlet mixers for jet pumps 5, 6, 9 and 10. Areas include CRD/ST-1, bottom of H9, and ICH/RPV-1. No indications.
Areas below the core plate made accessible due to the removal of the inlet mixer for jet pump 19. Areas include CRD/ST-1, bottom of H9, and ICH/RPV-1. No indications.
Visual examination of the fuel support guide tube pins (FWGT-ARPIN-1) at 20 locations, CRGT-1 at 20 locations, CRGT-2 at 21 locations. and CRGT-3 at 21 locations. No indications.
Components in BWRVIP Scope LPCl Couplings Lower Plenum Date or Frequency of Inspection L1 R07 (1 996)
L1 R10 (2004)
L1 R08 (1 999)
LlR11 (2006)
L1 R10 (2004)
L1 R09 (2002)
L1 R08 (1 999)
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspection Method Used VT-3 Visual examination of WD-1 on 20 jet pumps. Due to wear observed in LIR07, the inlet mixer on jet pump 9 was replaced and the wedge was oversized, and the restrainer bracket was machined to accommodate the larger wedge. To prevent flow imbalance, the inlet mixer on jet pump 10 was proactively VT-3 Visual examination of the fuel support guide tube pins (FS/GT-ARPIN-1) at 19 locations, the CRGT-1 at 19 locations. No indications.
22 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
LaSalle 1 Components in BWRVIP Scope Steam Dryer Top Guide Vessel Date or Frequency of Inspection L1 R11 (2006)
L1 RIO (2004 L1 R10 (2004)
L1 R08 (1 999)
L1 R10 (2004)
L1 R09 (2002)
Inspection Method Used EVT-1 VT-1 VT-3 VT-1 VT-3 VT-3 VT-3 VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Re-inspection of lower guide bracket at 180" and hood A plate 5 where previous indications existed and were stop drilled. No new indications.
All welds on the half of the dryer between 180" and 360":
access hole cover, drain channels, vertical welds and horizontal welds. No new indications. Indications at V13-270 and V14-170 were re-examined and there was no growth.
Visual exams on the end panels and welds; one indication on bank 9, bank 2 which was stop drilled, and one previous indication on bank D bank 4 and there was no growth. All four lifting lugs and their brackets (previous indications at five locations with no growth), 100°/~ of tie rods (1 0 previous indications unchanged), 100% of tie bars Visual examination of upper and lower guide brackets with an indication on the lower guide at 180" which was stop drilled, all horizontal welds, all horizontal plates (hood A plate 5 indication was stop drilled), hood F plate 1 (previous indication did not arow). 100% of the tie bars Visual examination of two c-clamps; no indications.
Visual examination of four c-clamps; no indications.
Inspection of the general condition of the RPV interior surface from the RPV closure flange elevation to the Steam Dam, 360" around the RPV interior. NRI.
Inspection of the general condition of the cladding at the Steam Dam elevation. 360" around the RPV interior. NRI.
Inspection of the general condition of the RPV interior surface from below the core date to the shroud support Plate. NRI.
Inspection of the general condition of the RPV interior surface from the RPV closure flange elevation to the Steam Dam, 360" around the RPV interior. NRI.
Inspection of the general condition of the cladding at the Steam Dam elevation, 360" around the RPV interior. NRI.
23 of 76
REACTOR INTERNALS INSPECTION HISTORY I
Plant:
LaSalle 2 Scope Core Spray Piping Core Spray Sparger Attach m en t Welds Coreshroud (Note: LaSalle has two beltline horizontal welds and thereby unique desianation).
Date or Frequency of Inspect ion L2Rll (2007)
L2R10 (2005)
L2R09 (2003)
L2R08 (2000)
L2R11 (2007)
L2R10 (2005)
L2R09 (2003)
L2R08 (2000)
L2R11 (2007)
L2R10 (2005)
L2R09 (2003)
L2R08 (2000)
L2R11 (2007)
L2R10 (2005)
L2R07 (1 996)
L2R06 (1 995)
Inspection Method Used EVT-1 EVT-1 UT EVT-1 EVT-1 UT EVT-1.
VT-1 EVT-1 VT-1 VT-1 EVT-1 VT-1 EVT-1 EVT-1 VT-3 VT-1 EVT-1 EVT-1 VT-1 VT-3 VT-1 VT-3 UT UT UT Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Visual examinations of core spray piping welds for which the UT is not demonstrated. No indications (NRI).
8 piping brackets; NRI.
UT of 34 welds; APl, AP2, AP3, AP4a, AP4b, AP5, AP6, AP7, AP4c, AP8b, BP3, BP4a, BP4b, BP5, BP6, BP7, BP4c, BP8b, CP1, CP2, CP3, CP4a, CP4b, CP5, CP6, CP7, CP4c, DP3, DP4a, DP4b, DP5, DP6, DP7 and DP4c. Existing flaw on BP5 re-sized with no growth. All others NRI.
Welds for which UT is not demonstrated: AP1, AP4d, AP8a, BP5, BP4d, BP8a, CP1, CP4d, CP8a, CP8b, DP4d, DP8a, and DP8b. NRI.
2 core spray piping brackets; NRI.
Visual examinations of those core spray piping welds for which the UT technique is not demonstrated. No indications.
UT for those welds for which the UT tool is qualified.
8 piping brackets; NRI.
S3D-a, S3D-b and S3D-c from 352 to 88" and S3C-a, S3C-b and S3C-c from 7.5 to 88"; one bent sparger nozzle deflector; all others NRI. Bent nozzle accepted for one cycle.
SlA, S2A (Left and right), S4A, SlB, S2B (Left and right),
S4B, S1 C, S2C (Left and right), S4C, S1 D, S2D (Left and right), S4D. NRI.
6 sparger brackets; NRI.
S3A-a and S3A-d from 268 to 008" and S3D-a and S3D-b from 352 to 268; NRI 6 sparger brackets; NRI.
Visual inspection of half of the core spray sparger welds. NRI.
6 sparger brackets; NRI.
100% of all sparger welds. NRI.
12 sparger brackets. NRI.
(See jet pump and core spray sections of this report.)
Steam dryer attachment welds, four locations, NRI Upper bracket attachment welds for surveillance baskets at three locations, NRI.
Lower bracket attachment welds for surveillance baskets at three locations. Basket disengaged at 120" location and accepted for one cycle. All others NRI.
All feedwater sparger attachment welds; NRI.
All feedwater sparger attachment welds; NRI.
Steam dryer attachment welds, four locations, NRI Guide Rod attachments at 0" and 180; NRI.
Upper surveillance capsule brackets at three locations: NRI.
Lower surveillance capsule brackets at three locations; NRI.
Surfaces of the shroud for ASME Section XI. NRI.
UT of welds H3, H5, H6, and H8 All welds are NRI.
UT of H5, H6, and H8. NRI.
UT of H3, H4, H5, H6, and H8. NRI.
24 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
LaSalle 2 L2R11 (2007)
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspection Fr:$
Of )I Method Used lnsoection VT-3 Access Hole Covers at 0 and 180" for ASME Section XI. NRI Accessible portions of the top of the shroud support plate for VT-1 VT-3 ASME Section XI. NRI.
Top of H9 weld (accessible locations) for ASME Section XI.
NRI Access Hole Covers at 0 and 180"--NRI Inspection of the general condition of the RPV interior surface L2R10 (2005)
L2R09 (2003)
EVT-1 UT VT-3 H8a weld (BWRVIP weld H8) for >1O0/&-NRI UT of 100% of H9 from the RPV OD. NRI.
Inspection of the general condition of the RPV interior surface from the RPV closure flange elevation to the Steam Dam, 360" around the RPV interior. NRI.
Inspection of the general condition of the cladding at the steam dam elevation. 360" around the RPV interior. NRI.
from the RPV closure flange elevation to the Steam Dam, 360" around the RPV interior. NRI.
Inspection of the general condition of the cladding at the steam dam elevation, 360" around the RPV interior. NRI.
Examined RPV cladding from below core plate to shroud sutmort date due to removal of the inlet mixers. NRI.
L2R11 (2007)
L2R10 (2005)
VT-3 C-clamp at 0". NRI VT-3 Accessible portions of the top guide for ASME Section XI. NRI C-clam ~s at 4 locations--N R I L2R11 (2007) VT-2 I
I Visual inspection of the partial penetration weld to the bottom head durina the Section XI svstem leak test. NRI.
L2R10 (2005)
L2R09 (2003)
UT VT-2 VT-2 PT Surface examination. NRI.
UT of the partial penetration weld and heat affected zone.
NRI.
Visual inspection of the partial penetration weld to the bottom head during the Section XI system leak test. NRI.
Visual inspection of the partial penetration weld to the bottom head during the Section XI system leak test. NRI.
L2R10 (2005)
L2R08 (2000)
L2R11 (2007)
VT-2 VT-1 Visual inspection of the partial penetration weld to the bottom head during the Section XI system leak test. NRI.
WD-I wedges on all 20 pumps; 7 wedges/rods showed minor VT-3 VT-1 25 of 76 wear; accepted-as-is. Auxiliary wedges installed at four locations on 3 pumps to compensate for observed gaps.
Examination of ratchet teeth engagement on 13 jet pump hold down beams due to fitup issues in the previous outage. NRI All 20 inlet mixers were replaced with new inlet mixers with labyrinth seals in the slip joint area, and with new non-stellite main wedges. New hold down beams were installed on 17 pumps. After replacement, three point contact verified at all locations (AS-I shroud side, AS-I vessel side, and WD-1).
NRI.
I L2R09 (2003)
VT-1 Replacement of 3 beams. After a review of material certification paperwork that identified them as Group 1 beams, three holddown beams were replaced with low stress beams.
WD-1 on 3 pumps; NRI.
Installed 3 aux. Wedges to ensure three point contact for three wmm.
REACTOR INTERNALS INSPECTION HISTORY UT VT-3 Plant:
UT exam of 10 beams at the BB-1 and BB-2 locations. NRI.
Exam of WD-1 on all 20 pumps; NRI. Exam of all set screw to LaSalle 2 EVT-1 Date or Frequency of Inspection L2R08 (2000) belly band contact points; installed 7 auxiliary wedges to maintain three point contact; all others NRI.
AD-2 on 6 pumps; NRI.
DF-1 on 10 w m m : NRI.
L2Rll (2007)
EVT-1 L2R10 (2005)
DF-2 on 10 pumps; NRI.
DF-3 on 10 pumps; NRI.
AD-2 on 4 Dumm: NRI.
L2R09 (2003)
EVT-1 L2R08 (2000)
IN-1 on 10 pumps; NRI.
IN-2 on 10 pumps; NRI.
AD-2 on 6 mmw)s: NRI.
L2Rll (2007)
DF-3 on 6 pumps; NRI.
Re-sized flaw on RS-1 c on 19/20; no change in length.
RS-1 on 2 risers: NRI.
L2R09 (2003)
EVT-1 L2R08 (2000)
RB-1 on 12 jet pumps; NRI.
Examined strain relief welds on all 10 risers. NRI Re-sized flaw on RS-1 c on 19/20: no chanae in lenath.
L2R07 (1 996)
UT L2Rll (2007)
MX-2 on 4 pumps; NRI.
RS-6/7 on ten pumps; NRI.
UT exam of MX-2 on 6 tmmtx: NRI.
L2R10 (2005)
VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections
/I Inspection Method Used RS-1 on all ten risers; two indications; one on the 1/2 riser and the second on the 19/20 riser; both accepted for two cycles.
RS-2 on all ten risers. NRI.
RS-3 on all ten risers. NRI.
VT-1 other welds NRI.
All welds recommended by SIL 644 Revision 1 for a curved hood dryer on the 270" side of the dryer, horizontal bank welds on both the 90" and 270" sides, all four lifting lugs; lifting EVT-1 AD-2 on 4 pumps; NRI.
DC-3 on 10 wmos: NRI.
DF-1 on 4 pumps; NRI.
DF-2 on 4 pumps; NRI.
DF-3 on 4 c)umtx: NRI.
DF-1 on 6 pumps; NRI.
DF-2 on 6 wmm: NRI.
RS-2 on 3 risers; NRI.
RS-3 on 5 risers; NRI.
RS-6/7 on 10 iet wmm: NRI.
RS-8/9 on all 20 jet pumps; NRI.
RB-1 on 10 jet pumps; NRI.
I RB-2 on all 20 iet c)umtx: NRI.
EVT-1 Re-examined flaws on two RS-1 welds; that on the 1/2 riser was determined to be non-relevant; those on the 19/20 riser were re-sized. with no chanae since L2R07 (1 996).
EVT-1 All welds recommended by BWRVIP-139 and SIL 644 Revision 2 for a curved hood dryer on the 90" side of the dryer, tie rods on both sides, upper support ring external surfaces, upper and lower guide at 180", (indication on the lower guide bracket accepted for one cycle), lifting lugs and lifting assembly brackets at 45 and 135", and 18 tie bars. Previous indications on tie bars reviewed and no change in sizes. All 26 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
LaSalle 2 L2R10 (2005)
Components in BWRVIP Scope VT-3 Vessel L2R09 (2003)
L2R10 (2005)
Lower Plenum VT-3 VT-1 Inspection of the general condition of the cladding at the Steam Dam elevation, 360" around the RPV interior. NRI.
Examined all areas below the core plate made accessible by I Other L2R09 (2003)
Inspection Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections assembly brackets at 225" and 315" locations, and all tie bars.
Indications found on three tie bars and accepted for one cycle.
and bottom head cladding. NRI for all twenty locations.
Visual examination of the fuel support guide tube pins (FS/GT-ARPIN-1) at 4 locations, CRGT-1 at 4 locations, CRGT-2 at 21 VT-3 / EVT-1 Upper strap on lifting assembly at 215" found broken and was removed. All other welds NRI.
L2R08 (2000) locations, and CRGT-3 at 21 locations. No indications.
Visual examination of the fuel support guide tube pins (FS/GT-VT-3 Inspection of the general condition of the RPV interior surface from the RPV closure flange elevation to the Steam Dam, 360" around the RPV interior. NRI.
L2R11 (2007)
ARPIN-1) at 14 locations, CRGT-1 at 15 locations. No indications.
Removal of the surveillance capsule basket from 120" due to a broken spring.
VT-3 disassembly of 20 jet pumps. Areas examined included CRD/ST-1, ST/RPV-1, H8a, H9, H10, HI 1, H12, ICH/RPV-1, 27 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update 1987 to 1996 Components in BWRVIP Scope Core Shroud VT-1 Shroud Support 2002 Core Spray Piping UT & EVT-1
~~
Date of Inspection 1994 1996 2006 1987,1990, &
1994 Inspection Method Used VT-3 UT UT VT-3 1998 VT-3 UT & CSVT-1 Inspection Results, Repairs, Replacements, Reinspections VT-3 examination of OD of welds H-1, H-2, H-3, H-4, H-5, H-6, and H-7.
No indications identified.
Baseline Category "B' UT examinations of welds H-3, H-4, H-5 and H-7 per BWRVIP-01, Rev. 1. Minor indications identified on H-3.
No indications identified on H-4, H-5 and H-7.
Category " B welds were re-examined by UT. Due to the identification of cracking, the scope was expanded and the shroud reclassified as a Category "C". All horizontal welds except H1 were UT examined from two sides using Phased-Array on most ring (H2 LKUP, H3 LKDN and H6 LKDN) locations. Recently demonstrated H1 emersion technique looking down was not successful.
Vertical welds V-15, 16, 17 and 18 in the beltline screened-in and were UT examined from ID.
Vertical welds V-7 and 8 at the top guide and V-25 and 26 below the core plate also screened-in and were visually examined from the shroud OD.
VT-3 examination of H-8 and H-9 welds from annulus. No indications identified.
VT-3 examination of both access hole covers and welds. No indications identified.
50% of shroud legs @ lo", 30°, 60" Azimuths and 50% of annulus floor. No indications identified.
VT-3 examination of both access hole covers and welds. No indications identified.
Visual examination of H-8 and H-9 welds from annulus at 0 and 180 Degree azimuths.
No indications identified.
Visually examined H-8 from annulus at 0" and 180" and UT examined 10% of H9. One indication was identified on H9 that was acceptable to the requirements of IWB-3000.
EVT-1 and VT-1 examination of both access hole covers and welds. No indications identified.
Enhanced VT-1 (1 mil resolution) examination performed every refueling outage on piping and welds per IEB 80-1 3. No indications identified.
UT baseline and visual of piping.
No indications identified.
UT all creviced welds plus 25% sample of P4(c) welds. One indication was identified on P3bA (- 3.1 inches). No other indications were identified.
EVT-1 of un-demonstrated welds P4dB, P4dC, P4dD, P8aA, P8aB, P8aC, and P8aD.
No indications identified.
Page 28 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update Date of inspection inspection Results, Repairs, Replacements, Reinspections Components in BWRVIP Scope Core Spray Piping Brackets Core Spray Sparger Core Spray Sparger Brackets Inspect ion Met hod Used EVT-1 2004 EVT-1 of previous P3bA indication. No change in identified length.
EVT-1 of un-demonstrated welds P4dA, P8aA, P8aB, P8aC, and P8aD. No indications identified.
UT of previous P3bA indication (- 2.8 inches - no change) and most other creviced welds. UT equipment issues on 10 of 24 welds and alternatively EVT-1 examined. No new indications identified.
UT & EVT-1 2006 EVT-1 of un-demonstrated P4dB, P8aA, P8aB, P8aC, and P8aD. Two indications were identified on P8aC as weld discontinuities that were likely opened up from construction.
No other indications were identified.
VT-1 examination performed every refueling outage on piping and welds per IEB 80-13. No indications identified.
Examined all eight brackets (PBl through PB8).
No indications identified.
1987 to 1996 VT-1 CSVT-1 1998 2000 EVT-1 Examined brackets PB1 and PB2.
No indications identified.
2002 EVT-1 EVT-1 Examined brackets PB3 and PB4.
No indications identified.
Examined brackets PB5 and PB6.
No indications identified.
Examined brackets PB7 and PB8. PB7 was identified with indications on the two upper bolts. In each case, one of two tack welds was found to be cracked. No other indications identified.
Enhanced VT-1 (1 mil resolution) examination performed every refueling outage on piping and welds per IEB 80-13. No indications identified.
EVT-l/CSVT-l all spargers.
No indications identified.
Examined A and B sparger welds S1, S2a,b, S3a,b and S4a,b. No indications identified.
VT-1 of S3 on B sparger and EVT-1 of S1,2 and 4 on C and D soaraers. No indications identified.
2004 2006 EVT-1 1987 to 1996 VT-1 1998 2000 EVT-1 & CSVT-1 EVT-1 &
VT-I EVT-1 &
VT-1 2002 2004 EVT-1 &
VT-1 VT-1 of S3 on C sparger and EVT-1 of S1,2 and 4 on A and B spargers. No indications identified.
VT-1 of S3 on D sparger and EVT-1 of S1,2 and 4 2006 1987 to 1996 EVT-1 VT-1 on C and D spargers. No indications identified.
VT-1 examination performed every refueling outage on piping and welds per IEB 80-13. No indications identified.
Examined all brackets (SB1 through SB12). No indications identified.
CSVT-1 1998 2000 VT-1 Examined brackets SB1, SB2, SB3, SB10, SB11 and SB12. No indications identified.
Examined brackets SB4, SB5, SB6, SB7, SB8, and SB9. No indications identified.
Examined brackets SB1, SB2, SB3, SB10, SB11, and SB12. No indications identified.
2002 2004 VT-1 VT-1 Page 29 of ?6
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update Components in BWRVlP Top Guide (Rim, etc.)
Core Plate (Rim, etc.)
Date of Inspection 2006 1987 1990 1994 1998 2000 2004 1998 1987, 1990,81 1994 1998 2000 2002 Inspection Method Used VT-1 VT-3 VT-3 VT-1 &
VT-3 VT-1 &
VT-3 VT-3 VT-3 VT-3 VT-3 MVT-1 EVT-I&
VT-1 EVT-1 &
VT-1 inspection Results, Repairs, Replacements, Reinspections Examined brackets SB4, SB5, SB6, SB7, SB8, and SB9. SB8 was found slightly deformed, no other indications identified.
VT-3 examination of accessible welds and surfaces.
No indications identified.
VT-3 examination of accessible welds and surfaces.
Also, VT-3 examination of 32 wedges, bolts, and keepers. No indications identified.
VT-1 examination of accessible welds and surfaces at core locations 14-31, 22-23, 22-39, 30-1 5, 30-47, 38-23, 38-39, and 46-31. Also, VT-3 examination of 32 wedges, bolts, and keepers.
No indications identified.
VT-1 of grids 30-31 and 34-35. Also, VT-3 surfaces and welds (0"-180") including wedges, bolts and keepers. No indications identified.
C-Clamps at O", go", 180" and 270". No indications identified.
C-Clamps at O", go", 180" and 270". No indications identified.
VT-3 welds and surfaces, including 17 hold down boltdnuts and 7 fuel support castings. No indications identified.
N/A, SLC connects to Core Spray System.
VT-3 examination of all jet pump components No indications identified.
Examined welds RB-la, b, c, d, RB-2a, b, c, d, RS-DF-1, DF-2, AD-1 and AD-2 for JP1/2, JP3/4, JP5/6, JP7/8 and JP9/10. Also, JP19/20 RS-3 weld was examined. No indications identified.
Em-1 examined RB-la, b, c, d and RB-2c on JP11/12; RB-la, b, d and RB-2a, b, c, and d on JPl5/16; RS-1, RS-2, RS-3 RS-6/7, RS-8/9 for JP11/12 and JP15/16; RS-1, RS-2, RS-3 RS-6/7 for JP13/14; and IN-4, MX-2, DF-1, DF-2, AD-1 and AD-2for JP11, JP12, JP13, JP14and JP15. No indications identified.
1, RS-2, RS-3 RS-6/7, RS-8/9, IN-4, MX-2, WD-I, VT-1 examined WD-1 for JP11, JP12, JP13, JP14 and JP15. No indications identified.
EVT-1 examined welds RB-la, b, c, d and RB-2a, b, c, d on JP13/14; RB-2a, b, and d on JP11/12; IN-4, MX-2, DF-1, DF-2, AD-1 and AD-2 for JP16; RB-lc for JP15/16; and RS-3 for JPI 7/18 riser. No indications identified.
VT-1 examined WD-1 for JPI, JP2, JP13, and JP14.
No indications identified.
EVT-1 examined RS-8/9 on all ten risers due to scope expansion from an indication identified on JP13/14 RS-9 weld (-0.38 inches). No other indications identified.
Page 30 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update Components in BWRViP ScoDe Jet Pump Beams Date of Inspection 2004 2006 1994 2004 inspection Method Used EVT-1, &
VT-1 EVT-1, VT-1, &
VT-3 UT UT inspection Results, Repairs, Replacements, Reinspections EVT-1 examined RS-3 and RS-6/7 for JP#1/2, JP#3/4, JP#7/8, and JP#9/10; RS-3 for JP#19/20; RB-la, b, c, d, RB-2a, b, c, d, RS-I, RS-2, RS-6/7, RS-8/9, IN-4, MX-2, DF-1, DF-2, AD-1 and AD-2 for JP17/18. No indications were identified.
Re-examined previous indication JP13/14 RS-9 by EVT-1. No change in flaw length.
VT-1 examined WD-1 on JP16, JP17, and JP18.
Initially, suspected wedge movement on JP18 prompted an investigation into the condition of the setscrews. Both tack welds on the shroud side set screw were cracked on JP18. The setscrew was staked and an auxiliary wedge installed.
No other indications were identified.
EVT-1 examined RS-1 and RS-2 on JP3/4, JP5/6, JP7/8, JP9/10, and JP19/20; RS-3 on JP11/12, JP13/14 and JP15/16; RB-1 a, b, c and d on JP7/8, JP9/10, JP11/12; RB-2a, b, c and d on JP1/2, JP7/8 and JP9/10; RS-6/7 on JP5/6, JP13/14, and JP15/16; IN-4 on JP9, JP11, and JP16; MX-2 on JP9; DF-2 on JP6, JP7, JP9, and JP10; AD-1 on JP6, JP7, and JP9; AD-2 on JP6 and JP7. No indications identified.
EVT-1 examined previous indication at JP13/14 RS-
- 9. No change in flaw length.
VT-1 examined all twenty WD-1, AS-1 and AS-2 locations in response to wear identified on Li2R08 during 2005. Gaps were identified on vessel side setscrews of JP4, JP7, JP9, JP13, JP15, JP19, and JP20. Cracked tack welds were identified on shroud side setscrews of JP8, JP12, JP14, JP17, JP18, and JP19. Slip Joint Clamps were proactively installed on all twenty Jet Pumps. Five auxiliary wedges installed: two at JP13 (pre-emptive due to RS-9 flaw), two at JP14 (pre-emptive due to RS-9 flaw), and one at JP15 (vessel side only due to 23 mil gap).
No other indications identified.
VT-1 examined auxiliary wedge previously installed at JP18 shroud side setscrew. No indications identified.
UT baseline of replacement hold-down beams.
No indications identified.
UT examined BB-1, 2, and 3 for all jet pump beams.
One indication identified in BB-2 region of JP#4.
This beam was changed out during the same refuel outage with a Group 3 style beam. No other indications identified.
Page 31 of 76
REACTOR INTERNALS INSPECTION HISTORY 1998 Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update No indications identified.
VT-3 of CRDs at core loc. 54-49,48-55,50-51,42-VT-3 Components in BWRVIP Scope 2000 Jet Pumr, Diffuser and 34-27. No indications identified.
Examined CRGT-1,2,3 and FS/GT-ARPIN-1 at core EVT-l&
CRD Guide Tube 2004 Date of Inspection No indications identified.
Examined CRGT-1,2,3 and FS/GT-ARPIN-1 at 10-EVT-1 &
2006 CRD Stub Tube 1990 34-43, and 46-1 1. No indications identified.
1992 VT-2 VT-2 examination from vessel exterior on 100% of 1992 1996 1994 penetrations once per interval, in excess of Section XI. No indications identified.
VT-2 examination from vessel exterior on 100% of VT-2 Inspection Method Used VT-3 VT-3 VT-2 VT-3 penetrations. No indications identified.
VT-3 of tube to housing and tube to RPV weld at core loc. 54-49, 48-55,50-51, 42-59, 30-31, 30-34, 34-35, 26-31, 34-31, 26-27, 30-27, and 34-27. No indications identified.
VT-2 examination from vessel exterior on 100% of Denetrations. No indications identified.
VT-3 In-Core Housing VT-3 penetrations. No indications identified.
1992 VT-2 VT-2 examination from vessel exterior on 100% of Inspection Results, Repairs, Replacements, Reinspections VT-3 examined BB-1, BB-2, and BB-3 on replacement beam for JP4. No indications identified.
See Jet Pump Assembly VT-3 examination of replacement CRDs at core locations 10-23, 14-1 9, 14-23, 14-31, 18-43, 18-55, 22-1 1, 22-39, 22-47, 26-03, 26-1 1, 26-27, 30-23, 30-3530-55,34-23, 34-37, 34-31, 34-39, 38-07, 38-54-31.
23,38-31, 38-35, 38-39,42-19, 46-1 1, 46-39, and No indications identified.
VT-3 examination of control rod assembly at core locations 30-1 1,22-55, 54-23, 38-07, 38-55, and 22-07. No indications identified.
1996 VT-3 examination of replacement CRDs at core locations 02-43, 10-1 9, 10-39, 14-39, 18-23, 18-39, 38-35, 38-41, 42-1 5,42-55, 50-43, 54-1 9, and 58-
- 31.
20-35,26-27, 26-31, 30-47, 34-31, 34-47, 38-1 9, XI. No indications identified.
VT-2 examination from vessel exterior on 100% of VT-2 1998 2006 I
I I 59, 30-31, 30-34, 34-35,26-31, 34-31, 26-27, 30-27, penetrations. No indications identified.
VT-3 of housing and weld to RPV at core loc. 48-53, 32-29, 24-29,24-33, and 32-33.
No indications identified.
VT-2 examination from vessel exterior on 100% of penetrations. No indications identified.
VT-3 VT-2 I
I VT-3 I locations 30-55, 38-31 and 38-39.
I I VT-3 I 39, 18-27, 18-35, 26-43, 30-1 5, 30-47, 34-1 5, 34-1 9, 1998 2000 I2006 I VT-2 I VT-2 examination from vessel exterior on 100% of I
I I penetrations once per interval, in excess of Section Page 32 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update VT-1 Date of Inspection 48-13, and 16-1 3 (IRM's). No indications identified.
VT-1 examination of 4 dry tubes.
1989 VT-1 1992 No indications identified.
VT-1 examination of dry tubes at core locations: 24-37 (IRM), and 40-21 and 38-23 (SRM).
1994 VT-1 2004 No indications identified.
Examined SRMs at 16-45 and 40-21 and IRMs at 2006 N/A 1990 24-29, 24-37, 32-37 and 48-13. Dry tube 24-29 identified as not fully engaged with the top guide.
No other indications identified.
Replaced dry tubes SRMs 16-21 and 40-45 and 1996 2006 VT-2 VT-1 & VT-3 VT-1 & VT-3 1987 to 1996 penetrations once per interval, in excess of Section XI. No indications identified.
VT-2 examination from vessel exterior once per interval. No indications identified.
VT-1 or VT-3 performed on all ID bracket welds once per interval per Section XI.
No indications identified.
Examinations include brackets on the steam dryer-4, jet pump riser-I 0, core spray-8, surveillance 1998 VT-1 & VT-3 2000 sample-2, and guide rod-I. No indications identified.
VT-1 examination of two Core Spray Piping 2002 EVT-1, VT-1 & VT-2004 Brackets at 15 degrees and 85.5 degrees. VT-3 examination of one Guide Rod Bracket at 180 degrees. No indications identified.
Jet Pump support pads on JP15/16 and JP17/18, Inspection Method US@d 11 Inspection Results, Repairs, Replacements, Reinspections EVT-1, VT-1 & VT-3 VT-3 No indications identified.
Jet Pump support pads on JP 1/2, 3/4, 7/8 and 19/20, Feedwater Sparger End Brackets at 125",
175", 185" and 235", and the Steam Dryer support lug at 184" and Core Spray Brackets at 195" and 247.5". No indications identified.
VT-3 examination of accessible portions of dry tubes at core locations 16-45, 40-45, 40-21, 16-21, (SRM'S), 16-53, 48-53,24-37, 32-37, 32-29, 24-29, VT-3 VT-2 IRMs 24-29,24-37,48-13, and 48-53. Plan to replace second half in 2008.
VT-3 examination of interior attachment of instrument nozzles N16A through D, N12A through D, and N i l A & B. No indications identified.
PT examination performed on all instrument nozzle to safe end welds once per interval, per Section XI (includes NIO Core Differential Pressure penetration). No indications identified.
VT-2 examination from vessel exterior on 100% of 3
Feedwater Sparger End Brackets at 5", 55", 65" and 115", and Steam Dryer support lugs at 4" and 94", and Core Spray Brackets at 112.5" and 165".
Page 33 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 1 - Spring 2006 Update Components in BWRViP Scope LPCl Coupling Steam Dryer Date of inspection 2006 1987, 1990, &
1994 1998 2000 2002 2004 1998 2000 2002 2004 2006 inspection Method Used EVT-1, VT-1 & VT-3 VT-3 MVT-1 EVT-1, VT-I, & VT-3 EVT-1 &VT-3 EVT-1, VT-1, &
VT-3 VT-I & VT-3 VT-1 VT-1 & VT-3 VT-1 & VT-3 n-1 Inspection Results, Repairs, Replacements, Reinspections Jet Pump support pads on JP 5/6,9/10,11/12 and 13/14, Feedwater Sparger End Brackets at 245",
295", 305" and 355 ", Guide Rod lugs at 0" and 180" and the Steam Dryer support lug at 274" and Core Spray Brackets at 274.5" and 345". No indications identified.
VT-3 examination of all 4 couplings. No indications identified.
All of N-17A and B. No indications identified.
All of N-I 7C and D. No indications identified.
N17A, locations 45-3b, 6a, 6b, 6c and 6d. No indications identified.
N17A, locations 45-8a, 8b, 8c, 8d and 12 and all of N17B. No indications identified.
VT-1 examined the steam dryer drain channel welds. No indications identified.
VT-3 examined the overall condition of the steam drver. No indications identified.
VT-1 examined the steam dryer drain channel welds. No indications identified.
VT-I examined the steam dryer drain channel welds. Stain identified on drain channel SDDC4c.
No other indications identified.
VT-3 examined the overall condition of the steam dryer. No indications identified.
VT-1 examined cover plate welds, outer bank hood seam welds, drain channel welds, and previous support ring indications. One support ring bolt was found with old mechanical deformation/damage and left as-is. Minor IGSCC previously identified on the support ring. No other indications identified.
VT-3 examined steam dryer tie bars. During examination of tie bars, one cam nut was found to be protruding from end bank number 6. This cam nut was staked during the same outage.
Performed BWRVIP-139 inspections of cover plates SDCP la-b and 7a-b, top and bottom hood SDBH la-b, 2a-b, 3a-b, 4a-b, 5a-b, and 6a-b, end bank welds SDEB la-d and 2a-d, lifting lugs, support ring and cam nut tack welds. Minor IGSCC identified on the support ring and tack weld cracking on cam nuts. No other indications identified.
Page 34 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update
~~
Components in BWRVIP Scope Core Shroud Shroud Support /
Access Hole Covers Date or Frequency of InsDection 1999 (2R05) 2005 (2R08) 2007 (2R09) 1991 (2R01) 1993 (2R02) 1995 (2R03) 1999 (2R05) 2003 (2R07) 2005 (2R08)
Inspection Method Used UT UT EVT-1 EVT-1 VT-3 VT-3 VT-3 EVT-1 VT-3 UT VT-3 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections A UT baseline of H-3, H-4, H-5 and H-7 was performed. H-4 was the only shroud weld examined from two-sides.
Indications identified on I.D. of H-3, H-5, and on O.D. of H-3, H-4, and H-5. No indications identified at H-7. Scope expanded to include UT of all remaining circumferential welds (H-1, H-2, and H-6). Indications identified on I.D. of H-1, H-2, and H-6 and on O.D. of H-1. Shroud was reclassified as a Category C, un-repaired shroud.
Full structural margin was calculated using one cycle of crack growth. Structural analysis was re-performed in 2R06 and again in 2R07. Re-examination was scheduled for H-1, H-2, H-3, H-4, and H-6 in 2R08 per site-specific evaluations. H-5 and H-7 are scheduled for re-examination in 2R10.
UT was performed on H-1 and H-6 from one-side with approximately 60% coverage. A two-sided UT was performed on H-2, H-3, and H-4 with approximately 60-63% coverage.
Approx 21 -5% of the ring-side scans were obtained for H-2 and H-3 with a new phased array technique.
Due to equipment problems, vertical welds could not be screened by UT per BWRVIP-76. As a result, all vertical welds were assumed to "screen in", and an EVT-1 was performed on these welds from the shroud OD. Reinspection of the vertical welds, either UT or two-sided EVT-1, is scheduled for 2007(2R09).
Fuel was removed from areas surrounding the shroud vertical welds, and an EVT-1 examination was performed from the ID and the OD surfaces of the shroud on four vertical welds V15, V16, V17, and V18. No indications were identified.
Another analysis of the indications found in 2R08 (2005) on horizontal welds H1, H2, H3, H4, and H6 was performed to demonstrate that structural margins are maintained until 2009 (2R10). The analysis demonstrated acceptable safety factors are maintained and a reinspection by UT is scheduled for 2R10.
VT-3 examination of accessible portions of H-8 and H-9 welds from annulus. VT-3 examination of both access hole covers and welds. No indications identified.
VT-3 examination of shroud support leg welds at Azimuth 300 deg through disassembled jet pump #18. No indications identified.
VT-3 examination of both access hole covers and welds. No indications identified.
EVT-1 examination 10% of the weld H-8 & H-9 length; in areas of 0 & 180 deg access hole covers. No indications identified.
VT-3 examination of both access hole covers and welds. No indications identified.
UT of 10% of weld H-9 length. No indications identified.
VT-3 examination of both access hole covers and welds. No indications identified.
EVT-1 examination of 10% of weld H-8 length. No indications identified.
Page 35 of 76
REACTOR INTERNALS INSPECTION HISTORY Limerick Generating Station, Unit 2 - Spring 2007 Update Plant:
I Fret ate or uency of Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Components in BWRVIP Scope Inspection Method Used VT-1 Inspection 2007 (2R09)
VT-I examination of both access hole covers and welds. All three welds were examined on the 180 deg Top Hat. No indications identified.
Best effort VT-1 / VT-3 of the lower side of H-8 and H-9, and six shroud support legs (3 welds H10, H I 1, H l 2 on each leg) were examined via access through the disassembly of Jet Pumps 1, 12, and 17. No indications were identified.
Enhanced VT-1 (1 mil resolution) examination performed every refueling outage on piping and welds per IEB 80-13. No indications identified.
Best effort VT-1 /VT-3 Core Spray Piping 1991 (2R01)-
1995 (2R03)
VT-1 1997 (2R04)
EVT-1 EVT-1 (1/2 mil resolution) examination of welds per IEB 80-13 and BWRVIP-18 baseline. No indications identified.
UT examination of welds (P1 thru P8) per BWRVIP-18 baseline UT. No indications identified.
EVT-1 supplemental examination on P4dA, P4dB, P4dC, P4dD, P8aA, P8aB, P8aC, and P8aD. No indications 1999 (2R05)
EVT-1 of P4dA, P8aA, P8aB, P8aC, and P8aD. No indications 2001 (2R06)
EVT-1 identified.
2003 (2R07)
UT UT examination of welds (P1 thru P8) with the exception of P4a. P4b. P4d and P8a welds. No indications identified.
EVT-1 EVT-1 of P4dB, P8aA, P8aB, P8aC, and P8aD. No indications identified.
2005 (2R08)
EVT-1 EVT-1 of P4dA, P4dC, P8aA, P8aB, P8aC, and P8aD. No indications identified.
UT examination of P1, P2, P3a, P3b, P4b, P5, P6, P7, and P8b welds was performed. No indications were identified.
EVT-1 of the far side of PI, P2, P3a, P3b, P4b, and P8b welds, as well as an EVT-1 examination of P4dD and P8a welds was performed.
2007 (2R09)
UT EVT-1 A small piece of raised metal was identified and evaluated as acceptable on the P8aC weld. Also, a small indentation on the collar near the P8aD weld was identified and evaluated as acceptable.
EVT-1 of 2 piping support brackets PB-7 & PB-8. No indications identified.
Core Spray Piping Brackets 1999 (2R05)
EVT-1 2001 (2R06)
EVT-1 EVT-1 of 2 piping support brackets PB-7 and PB-8. No indications identified.
2003 (2R07)
EVT-1 EVT-1 of 3 piping support brackets PB-4, PB-5, and PB-6. No indications identified.
2005 (2R08)
EVT-1 EVT-1 of 3 piping support brackets PB-1, PB-2, and PB-3. No indications identified.
EVT-1 of 2 piping support brackets PB-7 and PB-8. No indications identified.
Enhanced VT-1 (1 mil resolution) examination performed 2007 (2R09)
EVT-1 VT-1 Core Spray Sparger 1991 (2R01) -
1995 (2R03) every refueling outage on piping and welds per IEB 80-1 3. No indications identified.
EVT-1 (1/2 mil resolution) examination of welds per IEB 80-13 1997 (2R04)
EVT-1 and BWRVIP-18 baseline. No indications identified.
1999 (2R05)
EVT-1 EVT-1 examination of welds SlA, SlB, S2aA, S2bA, S2aB, S2bB S4aA, S4bA, S4aB, and S4bB per BWRVIP-18. No indications identified.
Page 36 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Date or Frequency of Inspection Components in BWRVIP Scope VT-1 VT-1 examination of welds S3aXXA, S3bXXA, and S3dXXA on nozzles 1A thru 65A. No indications identified.
Core Spray Sparger (continued) 2001 (2R06)
EVT-1 EVT-1 examination of welds S l C, S1 D, S2aC, S2bC, S2aD, S2bD, S4aC, S4bC, S4aD, and S4bD per BWRVIP-18. No indications identified.
VT-1 VT-1 examination of welds S3aXXB, S3bXXB, and S3dXXB on nozzles 1B thru 65B. VT-1 examination of welds S3c4B, S3d46, S3c62B, and S3d62B. No indications identified.
EVT-1 examination of welds SlA, SlB, S2aA, S2bA, S2aB, S2bB S4aA, S4bA, S4aB, and S4bB per BWRVIP-18. No indications identified.
VT-1 examination of welds S3aXXC, S3bXXC, and S3dXXC on nozzles 1C thru 65C. No indications identified.
EVT-1 examination of welds SlA, SlC, SlD, S2aA, S2aC, S2bC, S2aD, S2bD, S4aA, S4bA, S4aB, S4bB, S4aC, S4bC, S4aD, and S4bD per BWRVIP-18. No indications identified.
VT-1 examination of welds S3aXXD, S3bXXD, and S3dXXD on nozzles 1D thru 650. VT-1 examination of welds S3c4D, S3d4D. S3c62D. and S3d62D. No indications identified.
2003 (2R07)
VT-1 2007 (2R09)
EVT-1 EVT-1 of SlA, SlB, S2aA, S2aB, S2bA, S2bB, S4aA, S4aB, S4bA, and S4bB was performed. No indications were identified VT-1 VT-1 examination of welds S3aXXA, S3bXXA, and S3dXXA on nozzles 1A thru 65A was performed. No indications identified.
VT-1 examination of sparger brackets SB1, SB2, and SB3. No indications identified.
VT-1 examination of sparger brackets SB4 through SBl2. No indications identified.
Core Spray Sparger Brackets 1999 (2R05)
VT-1 2001 (2R06)
VT-1 2003 (2R07)
VT-1 VT-1 examination of sparger brackets SB1 through SB6. No indications identified.
2005 (2R08)
VT-1 VT-1 examination of sparger brackets SB7, SB8, and SB9.
One indication, a slightly bent sparger bracket, was identified on SB8 and was evaluated as acceptable.
VT-1 examination of sparger brackets SBl, SB2, SB3, SB4, SB5, SB6, SB8, SB10, SB11, and SB12 was performed.
VT-1 2007 (2R09) 1991 (2R01)
The middle bracket of SB5 was identified as being offset to the right of the top bracket. This was evaluated as acceptable.
SB8 was re-inspected with no change in condition from 2R08.
VT-3 examination of accessible welds and surfaces. No indications identified.
VT-3 examination of accessible welds and surfaces. No indications identified.
Top Guide (Rim, etc.)
VT-3 1993 (2R02)
VT-3 1995 (2R03)
VT-1 VT-1 examination of accessible welds and surfaces at cells 14-23, 22-31, 22-39, 38-23, and 38-47.
VT-3 examination of 32 wedges, bolts, and keepers. No indications identified.
VT-3 examination of surfaces at cell locations 26-27 & 30-31 and VT-3 examination of radial restraints, 32 wedges, bolts, and keepers. No indications identified.
VT-3 examination of all four Top Guide C-Clamps. No indications identified.
VT-3 VT-3 1999 (2R05) 2005 (2R08)
VT-3 Page 37 of 76
REACTOR INTERNALS INSPECTION HISTORY Limerick Generating Station, Unit 2 - Spring 2007 Update Plant:
Date or Frequency of Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspection Method Used Components in BWRVIP Scope Inspection 1995 (2R03)
VT-3 VT-3 examination of accessible welds and surfaces at core locations 14-23, 22-31,22-39, 38-23, and 38-47. No indications identified.
VT-3 examination of accessible welds & surfaces at core plate 1999 (2R05)
VT-3 location 30-31. No indications identified.
N/A, SLC connects to Core Spray System.
I (See summary of Instrument Penetrations)
VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
VT-3 examination of all 20 Jet Pump assemblies. No indications id en t if ied.
VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
Jet Pump Assembly
~
1991 (2R01) 1993 (2R02)
VT-3 VT-3 1995 (2R03)
VT-3 1999 (2R05)
VT-3 UT UT examination of all 20 Jet Pump hold down beams per BWRVIP-41. No indications identified.
EVT-I examination of welds RS-I, RS-2 and RS-3 per EVT-I EVT-1 BWRVIP-41 on Jet Pumps 11 - 20. No indications identified.
EVT-1 examination of RB-1 and RB-2 welds on Jet Pumps 1 -
2001 (2R06)
- 4.
EVT-1 examination of IN-4 and MX-2 welds on Jet Pumps 2 -
- 4.
EVT-1 examination of RS-1, RS-2, RS-6, RS-7, RS-8, and RS-9 welds of Jet Pumps 3 - 4. No indications identified.
EVT-1 examination of welds RS-I and RS-2 welds on Jet Pumps 1, 2, 5, and 6.
EVT-1 examination of RS-3 welds on Jet Pumps 1 - 10.
EVT-1 examination of welds RS-6, RS-7, RS-8, and RS-9 on Jet Pumps 1,2,5,6, and 1 I - 14.
EVT-1 examination of IN-4 and MX-2 on Jet Pumps 1, 5, 6, and 11 - 14. No indications identified.
2003 (2R07)
EVT-1 2005 (2R08)
UT UT examination of all 20 Jet Pump hold down beams (69-1, BB-2, and BB-3) per BWRVIP-41. Supplemental EVT-1 of the BB-2 location on Jet Pumps 1 and 2 due to UT fixture seating issues on the 90-degree placement only. No indications identified.
EVT-1 EVT-1 examination of RS-3 welds on Jet Pumps 11 - 14.
EVT-1 examination of RB-1 welds on Jet Pumps 7 through 10.
EVT-I examination of RB-2 welds on Jet Pumps 7 and 8.
EVT-1 examination of RS-1, RS-2, RS-6, and RS-7 welds of Jet Pumps 7 - 10.
EVT-1 examination of IN-4 and MX-2 welds of Jet Pumps 7 and 8.
EVT-1 examination of RS-8 and RS-9 welds of Jet Pumps 1 -
4,7 - 14, and 17 - 20.
No indications identified.
Page 38 of 76
REACTOR INTERNALS INSPECTION HISTORY I
Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update Components in BWRVIP
~
Jet Pump Assembly (Continued)
Date or Frequency of InsDection 2005 (2R08)
(Con tin ued) 2007 (2R09) 2007 (2R09)
(Continued)
Inspection Method Used VT-1 EVT-1 VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections A m-I examination of 8 wedges (WD-1 on Jet Pumps 2,6 -
10, 16, and 18) in the original scope identified significant wedge wear. The scope was expanded to all remaining wedges and setscrew gaps (AS-I and AS-2) were measured on all 20 Jet Pumps. Jet Pumps 1, 2, 4, 8, 10 - 14, 17, 19, and 20 showed main wedge wear and set screw gaps were identified on all Jet Pumps with the exception of Jet Pump 3, 6, and 7. The largest setscrew gap was 31 mils on Jet Pump 18 (with no wear). For those wedges that had identified wear, MX-7, WD-2a/b, RS-8, and RS-9 welds were examined with no further degradation identified. Jet Pump slip joint clamps were installed on all 12 Jet Pumps with identified wear. Also, 13 Auxiliary wedges were installed where gaps exceeded the acceptance criteria.
EVT-1 inspection was performed on the RS-6 welds of JP 1, 9, 11, 17, and 19 and on the RS-7 welds of JP 2,4, 8, 12, 14, and 20.
EVT-1 inspection was performed on the RS-8 and RS-9 welds of JP 1/2, 3/4, 7/8, 9/10, 1 1/12, 13/14, 17/18, and 19/20.
EVT-1 inspection was performed on RB-2 welds on JP 9/10, and RB-1 and RB-2 welds on JP 15/16. Also, RB-la and RB-Ic welds on JP 17/18 were examined by EVT-I.
EVT-1 inspection was performed on RS-1 and RS-2 welds on JP 17/18.
No indications were identified.
A VT-1 examination of all 20 main wedges (WD-1) was performed. The main wedges associated with JP 1, 12, 17, and 20 were replaced with an oversized wedge and the corresponding restrainer brackets were resurfaced. 10 of 12 jet pumps with previously identified wedge wear from 2R08 showed minor additional wedge wear in 2R09 even though a slip joint clamp was installed. JP 9 main wedge was identified with new wedge wear (low) but had no wedge wear identified in the previous cycle.
All setscrews were inspected for gaps, except for JP 14. Gaps were identified on the vessel side of JP 4, 5, 7, 9, and 20 with the largest gap being 0.030 inch (JP 7).
For those wedges that had newly identified wedge wear (JP 9) or additional wedge wear (JP 1,2,4, 8, 11, 12, 14, 17, 19, and 20), the MX-7, WD-2a/b, RS-6 or RS-7, RS-8 and RS-9 welds, as applicable, were examined as required expanded scope.
Minor wedge rod wear was identified on JP 2, 4, 9, 11, and 19.
No other indications were identified.
Page 39 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Date or Frequency of Inspection Components in BWRVIP Jet Pump Assembly VT-3 A VT-3 examination was performed on all previously install Auxiliary Wedges (AW) and Slip Joint Clamps (SJC).
Minor wear was identified on the AW installed on JP 1, 10, 11, and 13.
Aux wedges were removed and not reinstalled on JP 1 and 17.
Aux wedges were installed on both the vessel side and shroud side of JP 2,4, 11, 14, and 19. One aux wedge was installed on the vessel side of JP 7 and 9, and one was installed on the shroud side of JP 12 after reassembly identified a 0.043 inch gap*
Jet Pump SJC were inspected by VT-3 with no indications and were installed on JP 3, 5, 6, 7, 9, 15, 16, and 18. All 20 jet w m t x now have a SJC installed.
(Continued) 1991 (2R01)
VT-3 VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
1993 (2R02)
VT-3 VT-3 examination of all 20 Jet Pump assemblies. No VT-3 examination of all 20 Jet Pump assemblies. No VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
indications identified.
1995 (2R03)
VT-3 1999 (2R05)
VT-3 indications identified.
EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on 2001 (2R06)
EVT-1 Jet Pumps 2 - 4. No indications identified.
Jet Pumps 1, 5, 6, and 11 - 14. No indications identified.
Jet PumDs 7 and 8. No indications identified.
EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on 2003 (2R07)
EVT-1 2005 (2R08)
EVT-1 2007 (2R09)
EVT-1 EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on VT-3 examination of control rod assemblies at core positions JP 9, 10, and 15. No indications identified.
22-1 4 and 14-31. No indications identified.
1991 (2R01)
VT-3 1993 (2R02)
VT-3 VT-3 examination of control rod assembly at core location 34-
- 07. Minor scratches noted.
AccePtable for continued service.
1995 (2R03)
VT-3 VT-3 PSI examination of replacement CRDs at core locations and 54-35. No indications identified.
06-1 9, 10-27, 10-47, 14-39, 18-03, 18-1 5, 18-55,22-35, 22-39, 30-51, 34-47, 38-1 5, 38-27, 38-39, 42-43, 46-39, 46-43, 50-1 5, 1999 (2R05)
VT-3 VT-3 examination of CRD guide tube accessible surfaces of 26-27 from ID and 30-31 from OD. No indications identified.
CRD guide tube welds were examined at core locations 06-19, 06-43, 18-43, 22-31, 30-23, 30-39, 38-31, 42-1 9, 42-43, and 54-43. This includes a VT-3 of CRGT-1 welds, an EVT-1 of CRGT-2 and CRGT-3 welds, and a VT-3 of CR/FS/GT -
ARPIN-1 welds for the above locations. No indications identified.
2003 (2R07)
EVT-1 /VT-3 I
2007 (2R09)
EVT-1 /VT-3 CRD guide tube welds were examined at core locations 18-27, 18-35,26-27, 42-27, and 42-35. This includes an EVT-1 of CRGT-2 and CRGT-3 welds. A VT-3 of the CRGT-1 and ARPIN-1 welds was credited via CRB removaVreinstallation orocedure. No indications identified.
Page 40 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update I
Inspect ion Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Date or Frequency of Inspection 1993 (2R02)
Components in BWRVIP tub 1 ube VT-3 VT-3 examination of stub tube to vessel weld and stub tube to housing weld at azimuth 300 deg. No indications identified.
VT-3 examination at core location 30-31, 30-35, 26-31 & 34-
- 31. No indications identified.
Best effort VT-1 / VT-3 of stub tube to vessel welds and stub tube to housing welds at core locations 02-39, 02-43, 06-47, 10-1 1, 14-07, 14-1 1, 38-59, 42-59, and 46-55 were examined via access through the disassembly of Jet Pumps 1, 12, and
- 17. No indications were identified.
VT-3 examination of housings, guide tubes, stabilizers &
housing to RPV welds at core locations 24-29 & 32-29. No indications identified.
1999 (2R05)
VT-3 2007 (2R09)
Best effort VT-1 /VT-3 1999 (2R05)
VT-3 In-Core Housing Dry Tube
~
1995 (2R03)
VT-1 VT-1 examination of accessible portions of upper 2 feet of dry tube at core locations 16-21, 40-21, 40-45,24-29, 24-37, and 32-37. No indications identified.
VT-1 examination of accessible portions of upper 2 feet of dry tube at core locations 24-29 & 32-29. No indications identified.
1999 (2R05)
VT-1 2005 (2R08)
VT-1 VT-1 examination of accessible portions of upper 2 feet of dry tube at core locations 16-1 3, 16-21, 16-45, 24-29, 40-21, and 48-1 3. No indications identified.
2007 (2R09)
Replaced IRM 24-29, 24-37, 32-39, 48-53, and SRM 16-45, 40-21 were replaced with new universal style dry tubes. The remaining 6 are scheduled for replacement in 2009 (2R10).
VT-3 examination of interior attachment of instrument nozzles NIIA, NUB, and N12A through N12D. No indications identified.
PT examination performed on all instrument nozzle to safe end welds once per interval, per Section XI (Includes N10 Core Differential Pressure Penetration). No indications identified.
Instrument Penetrations 1991 (2R01)
VT-3 PT 1999 (2R05) 1991 (2R01)
UT/PT VT-1 NT-3 UT & PT examination of jet pump instrument nozzle to safe end N8A & N8B. No indications identified.
VT-1 or VT-3 performed on all ID bracket welds once every other outaae Per Section XI. No indications identified.
1993 (2R02)
VT-1 NT-3 VT-1 or VT-3 performed on all ID bracket welds once every other outaae oer Section XI. No indications identified.
1995 (2R03)
VT-1 /VT-3 VT-1 or VT-3 performed on all ID bracket welds once every other outage per Section XI. No indications identified.
VT-1 or VT-3 performed on all ID bracket welds once every other outage per Section XI. No indications identified.
VT-3 examination of feedwater sparger brackets (5, 55, 65, 1 15, 125, 175, 185, 235, 245, 295, 305 & 355 DEG), including bracket weld to RPV. No indications identified.
EVT-1 examination of feedwater sparger brackets at 5 degrees and 175 degrees, and core spray sparger brackets at 274.5 degrees and 345 degrees. No indications identified.
EVT-1 examination of feedwater sparger brackets at 65 degrees and 1 15 degrees; core spray sparger brackets at 165 degrees, 195 degrees, and 247.5 degrees; steam dryer support brackets at 4 degrees and 94 degrees; and jet pump riser brace arm attachment welds at jet pumps 1/2, 3/4, 5/6, 1 1/12, and 13/14. No indications identified.
VT-1 examination of the 30 degree surveillance sample holder attachment to vessel weld. No indications identified.
1997 (2R04)
VT-1 /VT-3 1999 (2R05)
VT-3 2001 (2R06)
EVT-1 2003 (2R07)
EVT-1 VT-1 Page 41 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update Date or Frequency of lnsnection Summarize the Following information:
Inspection Results, Repairs, Replacements, Reinspections Components in BWRVIP Scope inspection Method Used 2005 (2R08)
EVT-1 EVT-1 examination of feedwater sparger brackets at 55 degrees and 125 degrees; core spray sparger brackets at 15 degrees, 85.5 degrees, and 112.5 degrees; and jet pump riser brace arm attachment welds at jet pumps 7/8 and 9/10. No indications identified.
Vessel ID Brackets (Continued)
VT-3 VT-3 examination of guide rod bracket attachment welds at 0 degrees and 180 degrees. No indications identified.
EVT-1 examination was performed for core spray piping brackets at 274.5 Az. and 345 Az, feedwater sparger end brackets at 185 Az. and 235 Az., and jet pump riser brace arm attachment welds at JP 15/16. No indications were identified.
VT-1 examination was also performed on jet pump riser brace arm attachment welds at JP 15/16 (for Code credit), and at the upper and lower surveillance specimen brackets at 120 Az.
and 300 Az.
2007 (2R09)
EVT-1 VT-1 VT-3 VT-3 examination was also performed on core spray piping brackets at 274.5 Az. and 345 Az, and feedwater sparger end brackets at 185 Az. and 235 Az.(for Code credit). No indications were identified.
1991 (2R01)
VT-3 VT-3 examination of all 4 couplings.
No indications identified.
LPCl Coupling 1995 (2R03)
VT-3 VT-3 examination of all 4 couplings.
No indications identified.
1999 (2R05)
VT-3 VT-3 examination of all 4 couplings.
No indications identified.
EVT-1 examination of 'C' and 'Dl LPCl45-3b welds. No indications identified.
EVT-1 examination of 'A' and '6' LPCl 45-3b welds and EVT-1 examination of 'A', 'B', 'C', and ID' LPCl 45-12 welds. No indications identified.
EVT-1 examination of 'A', 'B', 'C', and ID' LPCl 45-3b and 45-12 welds. No indications identified.
VT-3 examination of 'Dl LPCl 45-6a through 45-6d welds. No indications identified.
2001 (2R06)
EVT-1 2003 (2R07)
EVT-1 2005 (2R08)
EVT-1 VT-3 VT-1 VT-1 examination of 'Dl LPCl45-8a through 45-84 welds. No indications identified.
2007 (2R09)
EVT-1 EVT-1 examination of 'C' and 'D' LPCl couplings (45-3b and 45-1 2) welds was performed. No indications identified.
VT-3 examination of 'C' LPCl 45-6a through 45-64 welds. No VT-3 indications identified.
VT-1 examination of 'C' LPCl 45-8a through 45-84 welds. No VT-1 VT-3 indications identified.
VT-3 examination of overall Steam Dryer assembly. Linear indications were identified in the support ring during the VT-1 of the adjacent drain channel welds. These indications were accepted by engineering evaluation.
UT examination performed to determine baseline crack depth of indications observed visually between 0 degree azimuth and 41 degree lifting eye during 2R03. Results show crack to be 0.384 inches in depth. These indications were accepted by Steam Dryer Steam Dryer (Continued) 1995 (2R03) 1997 (2R04)
UT engineering evaluation.
VT-3 examination of overall Steam Dryer assembly. No VT-3 indications identified.
Page 42 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Limerick Generating Station, Unit 2 - Spring 2007 Update 2001 (2R06)
Components in BWRVIP Scope VT-1 Inspection 2005 (2R08)
VT-1 I VT-3 2003 (2R07) 1 VT-l 2007 (2R09)
Best Effort 1 VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections VT-3 examination of overall Steam Dryer assembly.
Examination revealed cracking in upper support ring at 135 degree and 315 degree lifting lugs. These indications were accepted by engineering evaluation.
VT-1 examination of Steam Dryer Drain Channel welds. No indications identified.
VT-3 examination of overall Steam Dryer assembly. No indications identified.
VT-1 examination of Steam Dryer Drain Channel welds. No indications identified.
VT-1 examination of Steam Dryer Drain Channel welds. VT-1 examination of Steam Dryer Hood Bank #1 and Bank #6 seam welds. VT-1 examination of Steam Dryer Cover Plate welds at 90 degree and 270 degree. No indications identified.
Performed Best Effort VT-1 inspections of bottom hood seam welds (SDBH la-b, 2a-b, 3a-b, 4a-b, 5a-b, 6a-b), end bank welds (SDEB la-d, 2a-d, 3a-d, 4a-d, 5a-d, 6a-d), guide bracket at 0 Az (SDGB), hood vertical seam welds (SDHS 2b-d, 3b-d, 4b-d, 5b-d), hood reinforcement welds (SDHSR 2a-d, 3a-d, 4a-d, 5a-d), welds on all four lifting rods (SDLRx la-c, 2a-b, 3a-b, 4a-b, CP, LE, TW), man way welds (SDMW a-d),
plenum partition welds (SDPP 2a-b, 3a-b, 4a-b, 5a-b), support ring (SDSR), and tie bars (SDTB 1-5, 8-9, 17, 22-24).
Minor IGSCC identified on the support ring and evaluated as acceptable. A small piece of raised metal was identified on SDTB 3 and evaluated to be acceptable. One indication approximately 1.5 inches in length was identified and evaluated as acceptable on SDHS4c weld near the intersection of the bottom of the hood seam and the horizontal joining plate. No other indications identified.
Page 43 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Ovster Creek Generatinq Station Components in BWRVIP Scope Steam Dryer Core Shroud Date or Frequency of Inspection Fall 2006 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1996 Inspection Method Used Visual EVT-1 None None EVT-1 UT EVT-I Visual Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Re-inspect Steam Dryer Indications identified during previous outages.
EVT-1 cracks in hold-down area from 1 R19.
VT-1 all 4 lifting lugs and EVT-I indications on 135 deg. lug.
BW RVIP-139 required inspections (top side) completed.
New fatigue indications were identified that required repair.
Dryer repair project completed with 2 areas stop drilled and one crack in center baffle date was cut out.
V-9 inspection of ID and OD. Two horizontal indications (transverse to the weld) were found adjacent to vertical weld on the ID surface. The indications were 2.75 and 1 inch in length and 30 and 35 inches above horizontal weld H5. A technical evaluation was com pleted to use-as-is.
VT-3 Tie-Rods at 170 deg, 220 deg and 310 deg. No findings.
VT-I of Upper Bracket to Shroud Ledge interface on all 10 Tie Rods. No findings.
No Examinations Required.
No Examinations Required.
V-3, V-4, V-15 and V-16. This was a one sided exam from the OD. No findings.
V-7, V-8, V-10 and V-12.
V-11 I.D. Seven tie-rod assemblies baseline inspected.
V-10 exhibited minor OD cracking away from the heat-affected zone. This cracking is believed to be associated with handling lugs that were welded during construction and removed after installation. All other inspected vertical welds were found free of indications. With the inspections performed in 16R and 17R, all accessible vertical welds in the shroud core region are complete.
The following vertical welds could not be located. V-3, V-4, V-15 and V-16.
Inspected per BWRVIP-07. Three of ten tie rods inspected, no change from installation. EVT-1, OD of V-9 and V-1 1,
(120 total). V-9 exhibited 3 small axial cracks in HAZ on the OD totaling 1.75. The ID of V-9 was free of axial cracks.
A number of small transverse cracks were found on the OD and ID of V-9. V-11 was free of any indications. Analysis showed structural margin maintained.
44 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Ovster Creek Generatina Station Components in BWRVIP Scope Shroud Support Core Spray Piping Date or Frequency of Inspection Fall 1994 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1996 Fall 1994 Fall 2006 Fall 2004 Fall 2002 Inspection Method Used Ultrasonic and visual Visual None UT Visual Visual Visual Visual Visual Visual Visual Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspected per BWRVIP-01 and 03. Cracks were detected in the Shroud welds H2, H4, H6A, and H6B. Lack of fusion was detected in H3 weld and visual cracks on the ID surface.
The Tie Rod modification was installed. Base line visual performed of the tie rods.
EVT-1 of 7 Lug / Clevis pin assemblies - #1, #18, #19, #23,
- 24, #32 and #33.
No examinations required.
30% UT of H-9 from the OD (Drywell).
UT inspected H-9 weld in Nozzle N1 A, N1C and N1 E bioshield openings. Found one 4 long indication in the N1 E nozzle area. This service induced indication is in the bottom side of the H9 weld and does not penetrate into the base metal of the RPV.
25% of H-9, cleaning performed and EVT-1 inspection completed. This completes 100%
inspection of the H-9 weld. No findings.
25% of H-9, cleaning performed and enhanced VT-1, no findings 25% of H-9, (different area then the 1994 inspection),
cleaning performed and enhanced m-1, no findings.
25% of H-9 cleaning performed and enchanted VT-1, no findinas.
EVT-1 of annulus piping fillet welds (all 10). No findings.
EVT-1 of 25% shroud attachment welds - Pipe Bracket PB 103.5 deg. No findings.
EVT-1 of 25% sample butt welds: P4bA, P4cA, P2A, P4g/aA, P4g/bA, P4hA, P4iC, P4g/aC, P4g/bC, P4hC, P4bB, P4eB, P4fB, P4gB and P4hB. No findings.
Accessible portions of the annulus piping welds were cleaned using a nylon brush and visual inspections performed utilizing the EVT-1 technique. All accessible portions of the following piping welds were visually inspected:
L-3, L-3A, L-4, L-20A, L-13A, L-5, L-7, L-8, L-10, L-11, and L-12 U-3, U-3A, U-4, U-l5A, U-24A, U-7, U-8, U-9, U-1 0, U-1 1, U-12, U-16, and U-17 100% of annulus pipe brackets at 15, 105, 195 and 285.
No findings.
Em-1 of all creviced welds in the annulus piping = U3, U3A, U4, U15A + U24A; L3, L3A, L4, L13A + L20A.
45 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Ovster Creek Generatinq Station Components in BWRVIP Scope Core Spray Sparger Date or Frequency of InsDection Fall 2000 Fall 1998 Fall 1996 Fall 1 994 Fall 2006 Fall 2004 Inspection Method Used Visual Visual Visual Visual and air test Visual Visual Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections EVT-1 of a 25% sample (1 1 welds) of the butt welds (non-creviced) not inspected in 17R or 18R:
U1,U15,U17,U18,U19,U20 L1,L9,L13,L16,L20 Inspect 100% of annulus pipe brackets (1 5", 105", 1 95" and 285")
No Findings.
Accessible portions of the annulus piping welds were cleaned using a nylon brush and visual inspections performed utilizing the EVT-1 technique. All accessible portions of the following piping welds were visually inspected:
L3, L3A, L4, L6, L13A, L14, L15 and L20A U3, U3A, U4, U7, U8 and U15A 100% of annulus pipe brackets 15", 105" 195" and 285".
No findings.
All creviced welds in the annulus piping; sample (25%) of the non-creviced welds in the annulus piping:
L2, L9, L10, L1 1, L12, L13, L17, L18, L19 and L20 U2, U5, U6, U13, U14, U15, U21, U22, U23and U24 Sample (25%) of pipe brackets 285', 195' Inspected per BWRVIP- 03. Cleaning of all accessible weld/HAZ surface and performed enhanced VT-1. No findings.
Inspected VT-1, (1 mil wire). No change to pinhole weld defect detected in slip joint in 1992. Note: Pinhole weld defect detected in 1992 in System I. Analysis showed structural margin maintained.
EVT-1 Sparger Pipe End Cap welds S4C - 60 deg., S4C -
240 deg., S4D - 60 deg., and S4D - 240 deg. No findings.
EVT-1 "T" box cover plate welds - SlC, S2C (LH), S2C (RH),
S1 D, S2D (LH) and S2D (RH). No findings.
VT-1 spray nozzles - S3a, S3b, S3c-B. No findings.
VT-1 of 50% of the sparger bracket welds - SB - 026,091, 120, 179, 240, 300, and 359 deg. No findings.
Inspected all sparger repair clamps. No findings.
Inspected end cap welds S4A-60, S4A-240, S4B-60, and S4B-240. No findings. Inspected sparger brackets SB-055, 065, 150, 208, 235, 271 and 330. No findings 46 of 76
Plant:
REACTOR INTERNALS INSPECTION HISTORY Ovster Creek Generatinq Station Components in BWRVIP Scope Top Guide Date or Frequency of Inspection Fall 2002 Fall 2000 Fall 1998 Fall 1996 Fall 1 994 1978 - 1980 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Inspection Method Used Visual and Air Test Visual and Air Test Visual and Air Test Visual and air test Visual and Air Test Visual Visual Visual Visual Visual None.
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections VT-1 all spargers, nozzles, end cap welds and repair clamps.
No findings.
No new leaks were identified during the Air Test.
All sparger end cap welds were cleaned and EVT-1 inspected. No findings.
VT-1 of spargers, repair clamps, and nozzles. No findings.
No new leaks were identified during the Air Test.
All sparger repair clamps, both spargers.
Inspected per BWRVIP-03. Cleaned end cap welds and performed enhanced VT-1. No findings. Tee box welds are clamped and not accessible to clean or visual. Performed VT-1, (1 mil wire), of sparger piping and nozzles. No findings.
Performed VT-1, (1 mil wire) of sparger piping and nozzles.
No findings.
(2) Cracks in sparger piping. Repair clamps installed.
Note: Cracking found in sparger in 1978; repaired with clamps. Sparger has been inspected and air tested every outage since then; report submitted to NRC for approval for restart every outage.
EVT-1 of selected known flaws in grid beams: #4, VT-3 and VT-6. One area showed no growth, while the other two had grown between 0.25" and 0.75" from the 2002 outage to the 2006 outage. A flaw evaluation was performed to use-as-is.
VT-1 of top guide hold down bolts at 303 and 123 degrees.
No findings.
EVT-1 of VT-6 crack showed no measurable growth. Could not visually locate two other existing UT indications.
EVT-1 of two existing cracks measured in 18R outage (#3 and #5). No change to crack length identified.
Top guide hold down bolt assembly VT-3 at 33" and 213".
Top guide beam to rim fillet welds VT-I at 33" and 213". NO findings.
VT-1 of two existing cracks (#3 and #5) with cleaning. Both cracks measured on both sides. Crack #5 showed approx.
1" growth. Crack #3 showed no measurable growth.
Not required for this outage by analysis.
47 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Ovster Creek Generatina Station Components in BWRVIP Scope Core Plate Jet Pump Assembly Jet Pump Diffuser SLC Date or Frequency of Inspection Fall 1 996 Fall 1994 Fall 1 992 Fall 1991 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1996 Fall 1994 NA NA Fall 2006 Fall 2004 Fall 2002 Fall 2000 Inspection Method Used Ultrasonic 100% grid beams Visual Visual Visual None Visual Visual Visual Visual Visual NA NA UT VT-2 pressure test Visual / PT VT-2 pressure test Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections 12 indications emanating from notches detected at intersections of cross members. 5 of the 6 cracks on bottom side of member at mid span detected. Removed sample from beam with crack to investigate root case.
[Under side of Top Guide] Three additional vertical cracks were detected at mid span locations. Disposition use as is.
[Under side of Top Guide] Two additional vertical cracks were detected at mid span location. Disposition use as is.
[Under side of Top Guide] A vertical crack was detected at mid span location. Disposition use as is.
No exams were required.
No wedge inspections required. Inspected in-core guide tube plugs 04-29, 20-37, and 12-21. No findings.
No inspections needed. Wedges replace hold down bolt inspections.
Visually inspected all 8 wedges to verify integrity after first cycle of operation. All wedges found as installed.
Wedges installed. No further exams of core plate were performed.
Inspected top portion only of 18 hold down bolt that were na inspected in fall 1994 and top periphery section at bolt locations. No findings.
Inspected 18 hold down bolt tops only and top periphery at bolt locations inspected. No findings.
NA
~~~
~~
NA PDI - UT the Liquid Poison Nozzle N12 / SE. No findings.
Inspected insulated nozzle from drywell.
No leakage observed.
PT of Liquid Poison Nozzle - No Indications. Inspect insulated nozzle from drywell during RPV pressure test. No leakage observed.
Inspected insulated nozzle from drywell.
No leakage observed.
48 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Ovster Creek Generatinq Station Components in BWRVIP Scope CRD Guide Tube CRD Stub Tube Date or Frequency of Inspection Fall 1 998 Fall 1996 Fall 1 994 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1996 Fall 1994 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1 996 inspection Method Used VT-2 during Code pressure test.
No Inspection Performed.
No Inspection Performed.
EVT-1, VT-3 EVT-1, VT-3 EVT-1, VT-3 VT-1, VT-3 VT-3 No inspection Performed.
No Inspection Performed None None VT-1 VT-1 VT-2 pressure test No inspection Performed.
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Not made accessible for direct exam.
Not made accessible.
Not made accessible.
Inspected 4 guide tubes. No findings.
Inspected 4 guide tubes. No Findings.
Inspect 1 guide tube (46-43) removed to support stub tube inspection. No findings.
2 guide tubes. No findings.
15, no findings.
Not made accessible.
Not made accessible.
No inspections required.
No inspections required.
Visual Inspection of 2 stub tubes found leaking at bottom head in Fall 2000 (42-43 and 46-39). No indications noted.
None made accessible.
2 stub tubes found leaking at bottom head (42-43 and 46-39). Performed UT of CRD housing to stub tube welds (J weld) and area of housing to be rolled. No indications. Roll repaired both leaking housings.
Not made accessible.
49 of 76
REACTOR ~NTERNALS INSPECTION HISTORY Plant:
Oyster Creek Generatinq Station Components in BWRVIP Scope In-Core Housing Dry Tube Instrument Penetrations Vessel ID Brackets Date or Frequency of Inspection Fall 1 994 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1 998 Fall 1996 Fall 1994 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1 996 Fall 1 994 Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1 998 Fall 1 996 Fall 1994 Fall 2006 Fall 2004 Fall 2002 Inspect ion Method Used No Inspection Performed No inspection performed No inspection performed No inspection performed No inspection perf orm ed Replacement Visual Visual Visual Visual Visual Visual Visual EVT-1 EVT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Not made accessible.
Not made accessible.
Not made accessible.
Not made accessible.
Not made accessible.
Replaced 4 Dry tubes due to service life: IRM-11, 17, 18 and S R M-24.
VT-1 of SRM 24 found tube not fully engaged in top guide.
VT-1 of IRM 17 and IRM 18 found both tubes bowed.
No inspections required.
VT-1 five dry tubes. One found slightly bent - use as is. No findings on others.
VT-1 one dry tube, no findings VT-1 one dry tube, no findings.
VT-1 four dry tubes, no findings.
VT-2 exam from vessel exterior.
No findings.
EVT-1 both Guide Rod Brackets.
EVT-1 all 3 Surv. Spec. Brackets.
No findings.
Inspected all 4 dryer support brackets.
No findings.
All feedwater sparger attachment brackets.
Both guide rod attachment brackets.
All surveillance sample brackets (30, 210 and 300 degree locat ions)
No indications on attachment welds.
50 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Ovster Creek Generatinq Station Components in BWRVIP Scope LPCl Coupling Fuel Support Casting Date or Frequency of Inspection Fall 2000 Fall 1998 Fall 1996 Fall 1994 NA Fall 2006 Fall 2004 Fall 2002 Fall 2000 Fall 1998 Fall 1996 Fall 1994 Note: All indications left "as is" were an; Inspection Method Used EVT-I VT-1 NA Visual Visual Visual Visual Visual Visual Visual Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections All 4 dryer support brackets. Observed wear indications on brackets. No indications on attachment welds.
All feedwater attachment brackets inspected. No indications on attachment welds.
Cracks observed on feedwater sparger to end bracket welds (non-safety-related component) on 2 ends.
VT-1 of accessible portions of weld on guide rod brackets, steam dryer brackets, surveillance sample brackets. All attachment welds; no findings.
NA None inspected.
None inspected.
None inspected.
VT-3 (2) support casting. No findings.
VT-3 (24) support castings. No findings.
VT-3 (25) support castings. No findings.
VT-3 (1 7 ) support castings. No findings.
yzed and structural margins were acceptable for continued service.
51 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope Core Shroud Shroud Support Date or Frequency of Inspection 1994 1996 2002 1992 1994 1998 Inspection Method Used UT & VT UT UT VT-3 VT-3 VT-1 UT EVT-1 Summarize the Following information:
Inspection Results, Repairs, Replacements, Reinspections Comprehensive UT Baseline of some Category C circumferential welds (H-2, H-3, H-4, and H-5) per BWRVIP-01, Rev. 0.
Partial UT baseline of welds H-1, H-6, and H-7, w/ partial Enhanced VT-1 of H-6 OD.
Exams per BWR-VIP Core Shroud NDE Uncertainty and Procedure Standard, dated November 21, 1994.
Indications identified on ID of H-1, H-3, H-4, and H-6, and OD of H-4 and H-5.
Full structural margins calculated using two cycles of crack growth for comprehensively examined welds, one cycle for welds with limited exams.
No indications identified on H-2 and H-7.
Comprehensive UT of welds H-1, H-6 and H-7 per BWRVIP-01, Rev. 1.
Exams per BWRVIP-03.
Indications identified on ID of welds H-1, H-6 and H-7, on OD of weld H-1.
Full structural margins calculated using two cycles of crack growth.
Reexam inations planned per BW RVI P-76 Comprehensive UT of welds H-1 through H-7 per BWRVIP-
- 76.
Indications identified on each weld.
UT of Vertical welds V-1 through V-4.
No indications identified.
Reexaminations scheduled per BWRVIP-76.
VT-3 examination of support leg stub welds.
No indications identified.
VT-3 examination of welds H-7, H-8, and shroud support cyl inder.
No indications identified.
VT-3 of accessible portions of H-8 weld between Jet Pump
- 1 and #lo.
No indications identified.
VT-1 examination around perimeter of 0 deg. access hole cover.
No indications identified.
UT examination of both access hole covers. No indications identified.
EVT-1 examination of both AHCs. No indications identified.
EVT-1 of 10% of shroud support weld H-8, top side, no indications identified.
EVT-1 of 10% of shroud support weld H-9, top side, no indications identified.
52 of 76
REACTOR I NTERN ALS I NS PECTION H ISTORY Plant:
Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope Core Spray Piping Core Spray Sparger Date or Frequency of InsDection 2000 2002 2004 1980 to 1996 1996 1998 2000 2002 2004 2006 1980 to 1994 Inspection Method Used EVT-1 VT-3 UT EVT-1 VT-3 VT-1 (1 mil)
VT-1 (1/2 mil)
EVT-1 &UT EVT-1 EVT-1 &UT EVT-1 EVT-1 & UT VT-1 (1 mil)
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections EVT-1 examination of both AHCs. No indications identified.
VT-3 of accessible portions of H-9 weld between 0" and 180" Azimuth. No indications identified.
UT of 10% of H-9 weld length from OD of vessel.
No indications identified.
EVT-1 of > 10% of shroud support weld H-8, top side, between jet pumps 10 - 11 and 1 - 20. No indications identified.
VT-3 of accessible portions of H-9 weld between 180" and 360". No indications identified Enhanced VT-1 (1 mil resolution) performed on piping and welds each refueling outage per IEB 80-13, No indications identified.
EVT-1 (1/2 mil resolution) performed on annulus piping welds per BWRVIP-18.
Cracking identified in " B Header tee-box cover plate weld (P2B).
UT performed to characterize indication.
Evaluation demonstrated structural margin for one operating cycle.
Reinspection per BWRVIP-18, using UT technique. EVT-1 used to supplement UT. No new indications identified. P2B weld reexamination yielded additional margin.
EVT-1 of nine (9) piping welds not previously UT'd, and of six (6) pipe brackets and attachment welds. No indications identified.
Reinspection per BWRVIP-18, using UT technique (28 welds). EVT-1 used to supplement UT (6 welds). EVT-1 on two (2) support brackets.
No new indications identified.
P2B weld indication reexamination revealed minimal growth.
EVT-1 of twelve (12) piping welds not accessible for UT inspection. No indications identified Reinspection per BWRVIP-18, using UT technique (24 welds). EVT-1 used to supplement all one-sided UT (12 welds). EVT-1 only on eight (8) pipe welds and six (6) support brackets.
P2B weld indication reexamination revealed no growth. New 9/16 indication identified visually at intersection of P3B1 and P2B welds.
Enhanced VT-1 (1 mil resolution) performed on piping and welds each refueling outage per IEB 80-13, Cracking discovered at tee-box to sparger pipe weld ("B' Sparger, 1982), bolted repair clamp installed.
No other indications identified.
53 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope Top Guide (Rim, etc.)
Core Plate (Rim, etc.)
SLC Date or Frequency of Inspection 1998 2000 2002 2004 2006 1976 to 1994 1987 1994 1996 1996 1992 1998 2002 Inspection Method Used VT-3 &
MVT-1 EVT-1 VT-1 VT-1, EVT-1 VT-I, EVT-I VT-1, EVT-1 VT-3 UT VT-3 VT-3 VT-3 PT PT & UT PT Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Reinspections per BWRVIP-18, no indications identified.
EVT-1 of selected sparger welds per BWRVIP-18. No indications identified.
VT-I of sparger tee-box repair clamp, and approx. 50% of sparger "C" and "D" nozzles and drains.
VT-1 of eleven (1 1) sparger brackets and welds. No indications identified.
VT-1 of six (6) sparger support brackets, one (1) tee box repair clamp, and 50% of sparger "A" and "6" nozzles and drains.
EVT-1 of seven (7) sparger pipe welds.
No indications identified.
VT-I of six (6) Sparger support bracket welds, one (1) sparger drain, and 50% of nozzles on spargers "C" and "D".
EVT-1 of fifteen (15) Sparger pipe welds.
No indications identified.
VT-I of six (6) sparger support brackets, one (1) tee box repair clamp, and 50% of sparger "A" and "B" nozzles and drains.
EVT-1 of eight (8) sparger pipe welds.
No indications identified.
VT-3 exam every other refueling outage per Section XI. No indications identified.
UT examination performed of specific cells.
No indications identified.
Visual (VT-3) examination of 4 cells (48-41, 08-25, 24-1 7, and 24-25), per SIL 554.
No indications identified.
Visual (VT-3) of 2 aligner pins (0 deg. And 270 deg.), per SIL 588.
No indications identified.
VT-3 examination of all accessible hold down bolts (cell 16-57, and area at 0 and 270 deg. Azimuth.
No indications identified.
Surface (PT) examination of nozzle to safe end weld per Section XI.
No indications identified.
PT and UT of N10 nozzle to safe-end, no indications identified.
Extended dwell time Liquid Penetrant examination of entire safe end.
No indications identified.
54 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope Jet Pump Assembly Jet Pump Diffuser Date or Frequency of P
Ins ection 2006 1976 - 1996 1981 1994 1996 1998 2000 2002 2004 2006 1998 2000 Inspection Method Used PT VT-3 VT&UT VT VT MVT-1 UT EVT-1 EVT-1 EVT-1 UT VT-1 VT-1, EVT-1, VT-3 MVT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Extended dwell time Liquid Penetrant examination of entire safe end.
No indications identified.
Visual VT-3 of all jet pump components performed every other refueling outage.
/T and UT examination performed on all 20 hold down beams. No indications identified.
Restrainer bracket wedge misalignment and wear identified on several wedges.
Evaluations found condition acceptable without repair.
One restrainer bracket set screw tack weld found cracked.
Evaluations found condition acceptable without repair.
Restrainer bracket wedge conditions and set screw tack welds remain unchanged, condition acceptable without repair.
MVT-1 of: RS-1 weld on all 10 risers, RS-2 & RS-3 welds on 6 of 10 risers. No indications identified.
UT of all 20 hold down beams. No indications identified.
EVT-1 of adjusting screw tack weld (jet pump 7) and RS-2 &
RS-3 on 5 of 10 risers. No indications identified.
EVT-1 of fifty (50) Medium priority weld locations.
EVT-I of transition region of two (2) hold down beams.
No indications identified EVT-1 of forty one (41) medium priority welds, to complete 50% baseline inspections. No indications identified.
UT performed on all twenty (20) hold down beams (3 zones, BB-1, BB-2, and BB-3). No indications identified.
VT-1 on all twenty (20) Inlet Mixer main wedges. Thirteen (13) jet pumps exhibited additional wear at main wedge-to-restrainer bracket interface. Performed expanded scope of inspections on these jet pumps. Set screw gaps identified at five (5) jet pumps. No additional problems identified. Installed eight (8) slip joint clamps and three (3) set screw auxiliary spring wedges, to mitigate wear believed to be caused by vibration.
VT-1 of twenty (20) WD-1 locations. EVT-1 of five (5) IN-4 welds, and two (2) riser braces-to-vessel attachment welds.
VT-3 of eight (8) Slip Joint Clamps and three (3) Auxiliary Spring Wedges. Expanded EVT-1 scope on three (3) jet pumps due to WD-1 findings.
MVT-1 of: AD-1 & AD-2 welds on 12 of 20 pumps, AD-3A & B welds on 11 of 20 pumps, and DF-2 weld on 10 of 20 pumps.
No indications identified.
EVT-1 of AD-1, -2, -3a, -3b, and DF-2 on jet pumps 1 through
- 10. No indications identified.
55 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope CRD Guide Tube CRD Stub Tube In-Core Housing Dry Tube In strum en t Penetrations LPCl CouPlina Vessel ID Brackets Date or Frequency of Inspection 2002 2004 2006 1992 2002 2006 1992 1992 1994 1997 1976 to present 1976 to present 2000 2002 Inspection Method Used EVT-1 EVT-1 UT VT-3 EVT-1, VT-3 EVT-1, VT-3 VT-3 VT-3 VT-1 N/A PT VT-1 or VT-3 EVT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections EVT-1 of ten (10) High priority weld locations.
No indications identified.
EVT-1 of eleven (1 1) medium priority weld locations, to complete 50% baseline inspections.
No indications identified UT of ninety eight (98) Diffuser / Adapter welds and six (6)
Inlet Mixer welds. One 2 indication found on DF-2 weld, JP
- 17.
VT-3 examination of housings accessible from fuel cells 26-31 and 30-27. No indications identified.
EVT-1 of three (3) welds on each of ten (10) Guide Tubes (locations 50-31, 42-1 1,42-23, 42-51, 38-27, 38-35, 38-51, 34-23, 34-39, and 30-31). Some flow interference with exam in at ions.
VT-3 equivalent of anti-rotation pin on ten (10) Guide Tube locat ions.
No indications identified EVT-1 of fifteen (15) CRGT welds, VT-3 of five (5) CRGT welds, verification of seventeen (1 7) CRGT alignment pins.
One sliahtlv bent Pin identified. No other indications identified.
VT-3 examination of stub tube welds accessible from fuel cells 26-31 and 30-27.
No indications identified.
VT-3 examination of housings accessible from fuel cells 26-31 and 30-27.
No indications identified.
All Dry Tubes replaced in 1984 VT-1 examination of IRM Dry Tube 2D, at core location 37-
- 32.
All IRM and SRM tubes replaced w/ Wide Range Monitoring tubes in 1997. No inspections required.
PT examination performed on all instrument nozzle to safe end welds once per interval, per Section XI.
No indications identified.
N/A for this olant VT-1 and VT-3 of all ID bracket welds performed once per interval per ASME Section XI. No indications identified.
EVT-1 of six (6) Core Spray piping brackets. No indications identified.
EVT-1 of two (2) Core Spray piping brackets, two (2) Steam Dryer support brackets, and five (5) Jet Pump Riser brackets attach m en t welds.
No indications identified.
56 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope Steam Dryer Steam Separator Date or Frequency of Inspection 2004 2006 2002 2004 2006 2006 Inspection Method Used EVT-1 VT-3 EVT-1, VT-3, VT-1 VT-1, VT-3 VT-1 VT-1 VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections EVT-1 of two (2) Steam Dryer support brackets and three (3)
Jet Pump riser brace attachment welds.
VT-3 of four (4) Steam Dryer hold down brackets and three (3) lower surveillance brackets. No indications identified.
EVT-1 / VT-3 of twelve (12) Feedwater Sparger attachment bracket welds.
EVT-1 / VT-1 of two (2) Jet Pump riser brace-to-vessel welds.
No indications identified.
Minor anomalies incidentally identified on several FW Sparger bracket pins.
VT-I of all drain channel welds. VT-1 of upper and lower dryer bank tie bar welds and baffle plate welds. VT-3 of dryer bank end and top covers, and instrument tubing and supports.
One (1) central bank upper tie bar severed, and one (1) instrument tube support-to-baffle plate broken. Broken tie bar and instrument tube removed from dryer. New, stiffer tie bars welded to central dryer banks.
VT-1 of five (5) replaced central bank upper tie bars, ten (10) original bank upper tie bars, and outer bank hoods @ internal reinforcing plates and end plate welds, per SIL 644, Supp.1.
No indications identified.
Completed all remaining BWRVIP-I 39 recommended inspections on seventy four (74) locations. One small indication (7/16) identified at base of drain channel vertical weld. No other indications identified.
VT-1 examinations performed on a sample of upper and lower shroud head bolt support ring gussets. 12 of 24 lower ring gussets revealed degradation. No indications on upper support ring gussets. Indications acceptable for continued service.
57 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Components in BWRVIP Scope Core Shroud Shroud Support Date or Frequency of Inspection 1993 1995 1999 2005 1993 1999 2001 2005 Inspection Method Used VT-1 UT UT UT VT-1 EVT-1 UT EVT-1 VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Enhanced VT-1 (1 mil resolution) (100% ID of H-3, H4,
& V-3) portions OD of H-1, H-2, H-3, H-4, H-5, H-6, and Prior to BW RVI P-01, Circumferential Indications on ID of H-3 and H-4 (Plate side, not ring side)
Short circumferential indications on ID of V-3 weld.
Evaluation of indications showed full structural margins for one operating cycle.
H-7 Comprehensive UT Baseline of all Category "C" circumferential welds (H-1 through H-7).
Baseline per BWRVIP-01, Rev. 1.
Exams per BWR-VIP Core Shroud NDE Uncertainty and Procedure Standard, dated November 21, 1994.
Indications identified on ID of H-1, H-3, H-4, and H-5.
Full structural margins calculated using two cycles of crack growth.
No indications identified on H-2, H-6, and H-7.
UT Examination on welds H-3 & H-4. Re-identified indications on both welds. Extent of indications within existing structural analysis.
Two-sided UT of all 7 horizontal welds (H1 thru H7) and 4 vertical welds (V3 thru V6). No indications at H2, H7, V4-V6 or ring side of any weld. One minor indication near V3.
indications at H1, 1-13, H4, and H5 correlated with those previously identified. One indication at H6 (new). One deep indication at H4. Characterized as thru-wall. Review of previous data (1 995 and 1999) also characterized indication as thru-wall at that time. EVT-1 on OD surface did not identify any indications.
Enhanced VT-1 (1 mil resolution), of portions of H-8
- weld, No indications identified.
VT-1 examination around perimeter of both access hole
- covers, No indications identified.
10 % of weld length of welds H-8 &
H-9 examined.
No indications identified.
10% of H-9 weld length from vessel O.D.
No indications identified.
> 10% of H-8 weld, between jet pump banks, in area of AHCs.
Accessible length of H-9 between 0 and 180 degrees.
No indications identified.
58 of 76
REACTOR
~NTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Components in BWRVlP Scope Core Spray Piping Core Spray Sparger
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Date or Frequency of Insr>ection 1980 to present 1985 1993 1995 1997 1999 2001 2003 2005 1980 to present 1999 2003 Inspection Method Used VT-1 (1 mil)
VT-1 EVT-1 VT-1 VT-1 EVT-1 VT-1 EVT-1 EVT-1 VT-1 (1 mil)
EVT-1 VT-1 EVT-1 VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Enhanced VT-1 (1 mil resolution) performed on piping and welds each refueling outage per IEB 80-13, Cracking discovered at tee-box to header pipe weld.
Welded repair plates installed on both header tee-boxes.
Cracking identified in downcomer slip joint (weld P-5),
evaluation demonstrated structural margin for one operating cycle.
Additional cracking identified in 3 of 4 downcomer slip joint welds (P-5), repair clamps installed on all 4 downcomers to repair flawed welds.
4 Downcomer repair clamps, no indications identified.
All annulus piping welds, no indications identified.
VT-1 Examination of A, B, C & D Downcomer Repair Clamps & both Header Teebox welded repairs.
No indications identified.
All target welds plus 25 % sample of piping butt welds examined.
No indications identified.
VT-1 of both header tee box welded repairs, no indications identified.
EVT-1 of all target welds plus 25% sample of butt welds examined. No indications identified.
Four downcomer repair clamps.
Four Header Tee Box strong back repair plate welds.
EVT-1 of all target welds plus 25% sample of butt welds.
No indications identified.
Four Header Tee Box strong back repair plate welds.
EVT-1 of all target welds plus 25% sample of butt welds.
No indications identified.
Enhanced VT-1 (1 mil resolution) performed on piping and welds each refueling outage per IEB 80-13, No indications identified.
Examination performed on all Sparger Pipe welds.
Examination performed on all Brackets, Drains and 50 O h of Nozzles.
No indications identified.
Examination performed on all Sparger Pipe welds.
Examination performed on all Brackets, Drains and 50 YO of Nozzles.
No indications identified.
59 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Components in BWRVIP Scope Top Guide (Rim, etc.)
Core Plate (Rim, etc.)
SLC Jet Pump Assembly Date or Frequency of Inspection 1987 1993 1995 1976 to present 1997 1995 1997 1997 2003 1974 to present 1981 1997 Inspection Method Used UT VT-3 VT-3 VT-3 VT-3 VT-1 VT-3 VT-1 UT PT & UT PT VT-3 VT&UT VT-3 CSVT-1 (MVT-1)
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections UT examination performed on 40 cells.
No indications identified.
Visual (VT-3) examination of 9 cells (02-1 9, 46-1 1, 42-59, 58-1 9, 02-39, 10-51, 18-03, 22-03, and 58-35), per SIL 554.
No indications identified.
Visual (VT-3) of 3 cells (14-23, 22-31, and 46-23) per SIL 554.
No indications identified.
VT-3 examination every other refueling outage per Section XI.
No indications identified.
Top Guide Grid examined from above, no indications identified.
Adjacent aligner pins at 180 and 270 deg.(per VIP-26), no indications identified.
VT-3 examination of hold down bolt retainers planned, deferred to 1997.
Examined 18 of 34 bolts/retainers from above. No indications identified.
UT of nozzle to safe end planned for 1997, per BWRVIP recommendations.
PT & UT of nozzle to safe-end weld, no indications identified.
Extended dwell time PT of SLC nozzle to safe end weld and entire safe end.
No indications identified.
Visual VT-3 of all jet pump components performed every other refueling outage.
No indications identified.
VT and UT examination performed on all 20 hold down beams/
One beam found to be cracked, replaced with new style
- beam, All beams replaced with new style beam and reduced preload in 1988.
VT-3 all 20 jet pump assemblies (all parts),including CSVT-1 (MVT-1) of 10 riser braces, including all welds.
No indications identified.
CSVT-1 (MVT-1) all 10 thermal sleeve to riser elbow welds, plus UT on pumps I / 2, 9/10, 13/14 due to indications on thermal sleeve side of these welds.
MVT-1 on welds RS-2 & RS-3 of three risers w/
indications @ 30, 150, and 300 degrees.
Evaluation of indications justified continued operation for part cycle.
60 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE
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Components in BWRVIP Scope Jet Pump Diffuser CRD Guide Tube Date or Frequency of Inspection 1999 2001 2003 2005 1985 Inspection Method Used UT EVT-1 EVT-1 VT-1 EVT-1 UT VT-1 EVT-1 VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Examinations performed on all 20 hold down beams.
Reportable indications observed on hold down beam for jet pump # 20. Beam replaced.
No other indications identified.
Examination of high priority Adapter welds on Jet Pumps 1-1 0.
Reportable indications on welds (AD-3b ) of Jet pumps 2
& 10. BWRVIP -41 evaluation resulted in use-as-is disposition. Expanded examinations to weld AD3b on Jet Pumps 11 -20. No other indications identified.
EVT-1 examination of high priority Diffuser Shell to Tailpipe Welds ( DF-2) of Jet Pumps 1-1 0. No indications identified.
Examination of Riser welds RS-2 & RS-3 of Jet Pump Assemblies 2, 3 & 4.
No indications identified.
Reexamined weld AD-3b on Jet Pumps 2 & 10.
indications remain bounded by existing flaw evaluation.
All 20 WD-I locations examined. 16 high priority and 45 medium priority welds on inlet mixers, diffusers, and riser braces also examined. No indications identified.
VT-I of all twenty hold down beam ratchet lock keepers (replaced in 2001). VT-1 all twenty WD-1 main wedge locations, since all inlet mixers were removed in 2001, Two auxiliary spring wedges installed in 2001, and the RS-1 repair clamp on JP 1 & 2 and 13 & 14.
No indications identified.
Reexamination of indication at RS-I weld on JP 9 & 10.
Minimal change in flaw size. Structural reevaluation completed for continued acceptability.
104% of High priority welds completed.
72% of Medium priority welds completed No indications identified.
Indication identified in backing ring below AD-3a weld on JP 18. Structural evaluation found acceptable for continued operation.
Two-sided UT of all diffuser and adapter welds (1 00) from I.D. Identified 4 small OD originating indications associated with the AD-3b fillet weld (2 previously ID'd).
Structural and leakage evaluation proved acceptability for numerous operating cycles.
VT-1 of five main wedges. No wear identified.
EVT-1 of 16 medium priority welds. No indications identified.
EVT-1 of 3 existing indications. No appreciable change in indication size.
See Jet Pump Assembly.
VT-3 PSI examination of 4 replacement CRD housings.
61 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Components in BWRVIP Scope CRD Stub Tube In-Core Housing Dry Tube Instrument Penetrations
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Date or Frequency of InsDection 1987 1991 1999 2003 2005 1991 1991 1997 1976 to present Inspection Method Used VT-3 VT-3 VT-3 EVT-1 EVT-1 VT-3 EVT-1 VT-3 VT-3 VT-3 N/A PT Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections VT-3 examination of one of replaced housings.
No indications identified.
VT-3 examination of housings accessible from fuel cells 26-31 and 30-27.
No indications identified.
VT-3 examination on Guide Tube welds CRGT-1 &
Alignment Pin weld (Core Locations: 14-1 5, 14-31, 14-47, No indications identified.
18-1 9, 18-27, 18-35, 18-43, 26-1 1, 34-35, 42-1 9)
EVT-1 examination on Guide Tube welds CRGT-2 & 3 (Core Locations:l 4-1 5, 14-31, 14-47, 18-1 9, 18-27, 18-No indications identified.
35, 18-43, 26-1 1, 34-35, 42-1 9)
Best effort EVT-1 on Guide Tube welds CRGT-2 & 3 (Core locations: 10-35, 22-27, 22-35, 30-23, 30-31, 30-39, 38-27, 38-31, 38-35, and 42-31) No indications identified.
VT-3 examination on Guide Tube welds CRGT-1 &
Alignment Pin weld (Core Locations: 10-35, 22-27, 22-35, 30-23, 30-31, 30-39, 38-27, 38-31, 38-35, and 42-31) No indications identified.
EVT-1 on Guide Tube welds CRGT-2 & 3 (Core locations: 22-39, 38-39, 14-35, 46-35, 46-27, 22-23, and 26-1 1) No indications identified. CRGT-3 (22-39) later disqualified.
VT-3 examination on Guide Tube welds CRGT-I &
Alignment Pin weld (Core Locations: 22-39, 38-39, 14-35, 46-35, 46-27, 22-23, and 26-1 1) Alignment pin weld also at 14-27 and 38-23. No indications identified.
VT-3 of accessible portions of 12 stub tubes (30-35, 26-No indications identified.
35, 22-35, 22-31, 22-27, 26-27,26-23, 30-23, 34-23, 34-27, 34-31, 30-31).
VT-3 of housings accessible from fuel cells 26-31 and No indications identified.
30-27.
All Dry Tubes replaced in 1985.
All IRM and SRM tubes replaced w/ Wide Range Monitoring tubes in 1997. No inspections required.
PT examination performed on all instrument nozzle to safe end welds once per interval, per Section XI.
No indications identified.
62 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Components in BWRVIP Scope Vessel ID Brackets LPCl Coupling Steam Dryer Date or Frequency of Inspection 1997 2001 1976 to present 1997 1999 2001 2003 2005 2003 2005 Inspection Method Used PT PT VT-1 or VT-3 VT-1 EVT-1 EVT-1 VT-1 VT-3 EVT-1 & VT-3 EVT-1 EVT-1 VT-3 VT-1 VT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections PT nozzle to safe-end (coupling) & safe-end to pipe welds on 2 nozzles. (N12A & N12B). No indications identified.
PT nozzle to safe-end (coupling) welds on 2 nozzles.
(NIIA & N16A). No indications identified.
VT-1 and VT-3 of all ID bracket welds performed once per interval No indications identified.
All 10 Jet Pump riser brace to vessel welds, no indications identified.
EVT-1 examination performed on 8 Core Spray Bracket Pads @ 15, 117, 123, 165,195,237,243 & 345 AZ.
No indications identified.
EVT-1 exam ination performed on 4 Feedwater Sparger brackets @ 4, 56, 64, and 116 Az., 3 Jet Pump Riser Braces @ 90,120, and 150 AZ., and 2 Steam Dryer Support Brackets @ 4, and 94 AZ. No indications identified.
Lower Surveillance Specimen brackets at 30", 120", and 300".
Upper Surveillance brackets at 30", 120", and 300".
Guide Rod brackets at 0" and 180".
Steam Dryer support brackets at 184" and 2-74'.
Jet Pump riser brace to vessel welds JP 9/10 and JP 1 3/14.
No indications identified.
8 Feedwater sparger bracket welds and 16 jet pump riser brace welds. No indications identified.
N/A for this dant VT-3 of the entire top of the dryer (including all upper tie bars) and the 2 outer bank hoods and cover plates.
VT-1 of 5 new central bank upper tie bars (added in 2001), 2 stop-drilled indications at the lower guide rod followers, and all GE SIL 644, Supp. 1 locations on outer bank hoods.
No indications identified. All previous repairs were satisfactory.
Completed all remaining BWRVIP-I 39 recommended insw>ections (68 locations). No indications identified.
63 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 1 I Components Scope in BWRVIP 11 Frequency of /I Inspection Method Used Ins ection I Coreshroud 04/94 I EVT-1 and UT 03/96 I (BWRVIP-76)
~~
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspections per SIL 572, indications in circumferential welds.
Inspections per BWRVIP Guidelines of all Shroud repair design reliant hardware prior to installation of comprehensive repair (4 GE designed tie-rod assemblies).
Inspection of shroud consisted of Em-1 of all ring segment welds (accessible surfaces), EVT-1 of vertical welds between H1 & H2 OD surface 100% (ID not accessible), UT of all 6 beltline vertical welds >30%
length/weld, and EVT-1 of vertical welds between H6 & H7 OD surface >25% length/weld (ID not accessible).
No Reportable Indications.
I l1lg8 Shroud Repair Hardware (BW RVlP Letters 2006-1 12 and 2006-220) 1 o/oo 11/02 04/05 05/07 05/07 UT Future inspections to be in accordance with BWRVIP-76; Reinspection of Repaired Core Shrouds.
Shroud repair hardware inspected per GE recommendations. No Reportable Indications.
Inspected shroud vertical welds V-14 through V-19, inclusive, in accordance with BWRVIP-76. One recordable indication on V-19 was acceptable to EOI under BW RVIP-76.
EVT-1 EVT-1 EVT-1 EVT-1, VT-3 6 vertical welds from the OD per BWRVIP-76.
No indications. The steam dam above the shroud flange had impact damage evaluated as acceptable as-is for indefinite continued operation.
Examined Ring Segment Welds V1 -V4 (Shroud Head RSWs), V8-Vl3 (Top Guide RSWs), and V20-V25 (Core Plate Support RSWs). NRI, but indications notes in HAZ of shroud horizontal weld H-05-OD near core plate support RSWs. (Horizontal welds structurally replaced by shroud tie rod repair).
Examined three shroud vertical welds Inaccessible for UT Inspection to gain additional coverage (V17, V18, V19).
NRI Examined 6 vertical welds from the OD (V-05, V-06, V-07, EVT-1 of all tie rod upper support vertical faces, VT-3 of high-stressed fasteners and other contact points, and overall VT-3 per BWRVIP Letters 2006-1 12 and 2006-220.
Also, VT-3 of core plate wedges adjacent to repair hardware.
No reDortable indications.
V-26, V-27, V-28). NRI 64 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 1 Components in BWRVIP Scope Shroud Support (BW RVI P-38)
Core Spray Piping (BWRVIP-18)
Date or Frequency of Inspection 3/96 1 o/oo 03/05 05/07 1980 to 1994 04/96 11/98 1 o/oo 11/02 03/05 Inspection Method Used EVT-1 EVT-1 EVT-1 N/A VT-1 (1 mil)
EVT-1 Auto UT EVT-1 EVT-1 UT EVT-1 EVT-1
-~
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections EVT-1 of H8 and H9 for approx 12" at 4 locations of shroud repair hardware attachment areas.
Access hole covers; VT/UT in 1992, circumferential indications observed, permanent repair installed.
Inspected H8 and H9 adjacent to AHC at JP# 10 & 11 in accordance with BWRVIP-38. No reportable indications.
Inspected H8 and H9 adjacent to JP# 7 & 20 from annulus top side. Also inspected H8 and H9 adjacent to JP# 7 &
20 from bottom side through disassembled jet pumps.
No inspections performed.
IEB 80-13/NUREG of piping and welds in annulus.
Indication previously observed during 1994 on T-box was permanently repaired in 1996. Repair examined 11/98 with no reportable indications.
EVT-1 performed to intent of BWRVIP-18 in 1996.
Indications observed at two lower elbow welds, full structural margins on non-repaired welds.
Future inspections per BWRVIP-18.
GE CSI-2000 with supplemental EVT-1 for unqualified welds (P8a & P4d). Identified one new flaw at P4d 110' downcomer similar to previously identified flaws at the P4(
260' & 290' downcomers. All flaws were evaluated for at least 48 months of operation with full structural margins without repairs. Previously identified flaws were determined to be of less extent than originally sized.
Inspected P8a and P4d welds @ 4 downcomers in accordance with BWRVIP-18. Existing flaws at P4d welds at 11 O',
260' and 290' downcomers showed no discernable change from 1998 inspection.
BWRVIP-18 UT examination of all accessible welds (32).
During the previous outage, indications were observed on welds 2P4D, 3P4D, and 4P4D (2 separate indications) and these were re-inspected this outage. A new indication was also observed on 3P4D that was not observed in the earlier outage. All were evaluated as acceptable for at least one cycle.
BWRVIP-18 EVT-1 on 12 welds inaccessible to UT.
Confirmed indications on welds identified by UT. No other indications. Re-inspected T-Box repair; no indications. The core spray piping bracket clamp at 125" was found loose.
This condition was accepted as-is with a recommendation for reexamination.
Lower Elbow to Shroud Pipe Welds 1 P4d, 2P4d, 3P4d, 4P4d. NRI on 1P4d. No change in indications on 2P4d, 3P4d, 4P4d since last exam in 2002 (R17).Collar Weld to Shroud Pipe Welds 1P8a, 2P8a, 3P8a, 4P8a. NRI. Best 65 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 1 Scope Core Spray Sparger (BWRVIP-18)
Date or Frequency of Insnection 05/07 1980 to 1994 04/96 11/98 11/02 03/05 05/07 Inspection Method Used VT-1, VT-3 UT EVT-1 VT-1 (1 mil)
EVT-1 or VT-3 EVT-1 MVT-1 EVT-1 of Sl,S2, &
S4;VT-1 Of S3:VT-1 of brackets N/A EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections effort on 4P8a. Separator lugs and tie rods limited views on lower half. Supplemental visual to disposition UT indication in base metal from R17. NRI Welds BPI, BP2, BP3,2P2, 2P3, 3P3 at Tee Box repair (clamp interferes with EVT-1). NRI UT Examination of 36 welds (32 welds in target set plus non-demonstrated exams on P8A welds). Sized previous indications on 2P4d, 3P4d and 4P4d with little or no change from previous. New indications on 2P4a and 4P4a that could not be confirmed visually.
Inspected 16 P4 welds; four P8a welds; 3P6, 2p3 and 3P3, BPI and BP2 at Tee Box repair; Tee Box repair clamp.
Measured indications on 2P4d, 3P4d and 4P4d with no change from previous.
IEB 80-13 of welds on sparger. No indications found.
EVT-1 performed to intent of BWRVIP-18, on T-box cover plate welds, T-box to sparger welds, end cap welds and bracket welds. VT-3 of spargers and nozzles.
Future inspections per BWRVIP-18.
End caps, cover plates and tee branch welds were EVT-1 examined. All sparger connections and bracket welds were MVT-1 examined. No reportable indications.
Examined all 20 S1, S2, and S4 sparger welds, 50% of the S3a, b & c nozzle welds, and all 12 sparger brackets.
Examined for IEB 80-13 and BWRVIP-18. No indications.
No examinations performed.
Examined all 20 S1, S2, and S4 sparger welds. No indications.
66 of 76
Plant:
REACTOR INTERNALS INSPECTION HISTORY Quad Cities Unit 1 Components in BWRVIP Scope Top Guide (Rim, etc.)
(BW RVIP-26)
Core Plate (Rim, etc.)
Jet Pump Assembly (BWRVIP-41)
Date or Frequency of lnsoection 03/94 04/96 11/98 1 o/oo 11/02 03/05 N/A 11/98 05/07 03/94 04/96 04/96 11/98 11/98 1 o/oo Inspection Method Used VT-1 VT-1 VT-1 EVT-1 VT-3 EVT-1, VT-1 N/A VT-I VT-3 VT-1 VT-1 UT VT-1 EVT-1 EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections VT-1 of 4 cells. No indications.
VT-1 of alignment assemblies. No indications.
VT-1 of alignment assemblies and adjacent rim welds. No reportable indications.
Inspected accessible areas of location 11 in accordance with BWRVIP-26. No reportable indications.
Examined 9 pin welds (FS/GT-ARPIN-1) per BWRVIP-47. No Indications.
Alignment pin assemblies at O9 and 270% NRI.
EVT-1 of rim weld. Numerous machined holes identified in the horizontal plate adjacent to the rim weld similar to those found on Unit 2.
Installed core plate wedges in conjunction with comprehensive shroud repair 1996.
Wedges inspected in conjunction with shroud repair hardware. No reportable indications.
Wedges inspected in conjunction with shroud repair hardware. No reportable indications.
Hold down beams, beam bolt keepers, lockplates and retainers; restrainer wedges, stops, and adjusting screws, clamp bolts and keepers; riser brace assemblies, adapter and baffle plate welds, sensing lines and sensing line brackets per various SILS. Latest inspections were in 1994. No reportable indications.
Diffuser to baffle plate welds examined. No reportable indications.
Jet pump riser brace to riser weld at JP 5/6 repaired 1994, repair examined 1996 and 1998, no changes noted.
Diffuser to baffle plate welds examined. No reportable indications.
One jet pump beam replaced 1986 due to indication. Jet pump beams are UT examined each outage using technique capable of detecting cracking at throat and ears.
No subsequent indications.
Inspected all 20 jet pump assem blies. Identified indication at JP7/8 riser brace to riser weld. Repair installed 4/99.
Inspected jet pump riser welds RS-I,-2 &-3. Visually identified 3 indications at JP 19/20 RS-1 weld.
Subsequently sized indications with UT. The RS-1 weld was evaluated for at least 24 months of operation with full structural margin without repair.
Inspected >50% of high priority welds (DF-2, AD-3a,b, AD-1 &AD-2) in accordance with BWRVIP-41. One 67 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 1 Components in BWRVIP Scope CRD Guide Tube (BW RVIP-47)
Date or Frequency of Inspection 11/02 03/05 05/07 11/02 03/05 05/07 Inspection Method Used EVT-1 EVT-1 VT-1, VT-3 EVT-1 VT-1, VT-3 VT-1, VT-3 on EVT-1 on N/A N/A CRGT-1; CRGT-2 & 3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections recordable indication at JP-16 backing ring adjacent to AD-3a,b oriented axially across backing ring. Expanded sample to include 100% of AD-3a,b welds. Inspected BWR-3 beams at 16 jet pumps with UT (ends and center) in accordance with BW RVIP-41. No reportable indications. The RS-1 weld at JP 19/20 was permanently repaired.
EVT-1 of DF-2, ADS-a&b, AD-1, AD-2 for all 20 jet pumps (except DF-2 on JP 11 ; EVT-1 of RB-1 and RB-2 of pumps 3,4, 9, 10, 11, and 15-20; EVT-1 of risers on jet pumps 3/4, 9/10, 1 1/12, 15/16, 17/18, and 19/20; EVT-1 of MX-2, MX-3a&b, and MX-4 on pumps 4,5,9, 10, 11, 14/18 and 20; EVT-1 of MX-1 and DF-1 for pumps 6-1 1, 14-18 and 20; EVT-1 on the risers of pumps 3/ 4, 9/10, 1 1/12, 15/16, 17/18, and 19/20; VT-1 of AS-1 and AS-2 on pumps 5,7,8, and 20, VT-of wedges on jet pumps 16 and 20, VT-1 of clamp at RS-1 on jet pumps 19/10, and VT-3 of existing repair hardware at IN-5 on pumps 6-1 1, 14-17 and 20.
One indication was found on JP 2 at AD-3b and two indications were found on JP 7 at AD-3b.
Jet pump sensing line clamps were installed on 8 jet pumps (1, 2, 3, 10, 11, 12, 13, 20).
Risers: Six RS-1 welds, five RS-2 welds, and all ten RS-3 welds due to limited exams previously. Examined RS-4 and RS-5 on riser 11/12. Re-examined RB-1 b on JP3, RB-2b on JPI 1 and RB-2a on JP 20. All NRI.
Mixers: Examined MX-2 in JP 11 and 14. Examined MX-3a&b on 17 & 18. NRI.
Diffuser/Adapter: Examined high priority welds, including 11 AD-1, 12 AD-2, 12 AD-3a,b, and 11 DF-2 (reinspection of JP2, JP7, JP16 known flaws). One additional branch noted on JP16 indication compared to previous exam in 2000. No discernable change in previous indications on JP2 and JP7. No other RI.
Reinspected repair on Jet Pump 19/20 RS-1. NRI Re-measured previous indications at AD-3a,b on JP2, JP7 and JP 16. No changes.
Inspected all main wedges with no unusual wear noted.
Insoected one aux wedae and set screw. NRI.
Examined 9 sets of guide tube welds (CRGT-1, CRGT-2, and CRGT-3) and one additional weld (CRGT-2) per BWRVIP-47. No Indications.
No inspections performed.
No inspections performed.
68 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 1 Components in BWRVIP (BW RVIP-47)
I In-Core Housing (BWRVIP-47)
IRMISRM Dry Tubes (SIL 409)
Standby Liquid Control (BWRVIP 27)
Instrument Penetrations Vessel ID Brackets (BWRVIP-49)
RVI P-48)
Date or Frequency of Inspection N/A N/A 03/94 03/96 10/00 11/02 04/05 04/05 N/A 03/94 04/05 05/07 N/A Inspection Method Used N/A N/A VT VT MVT-1 VT-1 PT N/A VT-1 andVT-3 VT-1, VT-3 VT-3 EVT-1, VT-3 VT-1, VT-3 EVT-1, VT-3 VT-3 EVT-1, VT-3 N/A Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections N/A N/A Replaced 2 dry tubes 1994.
Replaced 5 dry tubes in 1996.
Inspected original dry tubes at 7 locations. No recordable indications.
Examined 5 dry tubes. Verified plungers engaged at Top Guide. No Reportable Indications.
All remaining original dry tubes (5) replaced.
Nozzle To Safe End, N10-F1. NRI N/A Section XI inspections of jet pump riser brace, dryer, feedwater sparger, core spray, and surveillance capsule holder brackets, performed once per interval. VT-3, or VT-1 if in beltline region. No indications noted.
Examined two Moisture Separator shroud guide rod support brackets. Minor gouges and bent top pins. No changes since previous inspection in 11/03 (F51).
Examined two steam dryer guide rod support brackets upper and lower (four inspections). NRI Examined four steam dryer wall support lugs. NRI Examined six upper and six lower surveillance sample bracket attachments to RPV and sample holders. NRI except for one sample holder that was not engaged in the lower bracket. Bracket was re-engaged during the outage.
Examined eight feedwater sparger end-bracket assemblies. Five of eight had less than three protruding threads. Tightened and applied additional tack welds.
Examined eight feedwater sparger lug to vessel attachment welds. NRI.
Examined four steam dryer wall support lugs (WSL). Rub markslgouges from dryer lifting noted on cladding at three Df the four WSLs.
Re-examined one bent Moisture Separator guide rod sueeort bracket. No chanae since 2003.
Not applicable to this plant.
69 of 76
Plant:
REACTOR INTERNALS INSPECTION HISTORY Quad Cities Unit 1 Components in BWRVIP Scope Steam Dryer (SIL 644, BWRVIP-139)
Feedwater Spargers (NUREG 0619)
Date or Frequency of InsDection 03/05 05/06 05/07 1982 1986 1989 1992 1996 1998 2002 04/05 05/07 Inspection Method Used Best effort VT-1, VT-3 Best Effort VT-1, VT-3 Best Effort Manual UT VT-1, VT-3 Manual UT Manual UT Manual UT Manual UT UT (GERIS)
UT (GERIS)
EVT-1 /VT-3 VT-1, VT-3 VT-1, VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections The steam dryer was originally scheduled to be replaced during Q1 R18, but was not ready in time (the dryer was later replaced in May 2005). The following inspections were then performed during Q1 R18:
Examined exterior surfaces including outer hoods, historical repair areas, tie bars and attachment welds, four lifting assemblies, four hold down assemblies, two man way covers, cover plates, gussets, upper ring welds, vertical guide welds, outlet plenum lower horizontal welds, outlet plenum vertical welds, and perforated plates.
Previous indications were identified that had been repaired, stop drilled or dispositioned to use as is in 2003.
Additional indications were noted in the perforated plates.
Examined interior surfaces including: drain channel welds, supports, vertical and horizontal plates, support ring, horizontal cross beams, and horizontal cross beam gussets. Previous indications were identified that had been repaired, stop drilled, or dispositioned to use as is in 2003. New indications were observed in dryer bank vertical welds and vertical struts in the ID.
Examined interior and exterior skirt. Indications noted.
Dryer was repaired and returned to service prior to replacement in May 2005.
Performed baseline inspection of new steam dryer installed in June 2005 per BWRVIP-139 and GE recommendations. NRI Performed inspection steam dryer per BWRVIP-139 and GE recommendations. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. Acceptable.
UT of all four N4 nozzles and inner radii. Acceptable.
Examined all 8 Sparger end brackets per NUREG-0619 program and BWRVIP-48. No indications.
Visual inspection of sparger flow holes and welds. Slight distortion noted in one flow hole. A small piece of wire found in one flow hole. All FW sparger end bracket stop nuts were run up and tacked welded into place.
Examined all 8 Sparger end brackets. Top of pins are wearing into top side of bracket on 3 end brackets.
Performed VT-I of flow holes. NRI.
70 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 2 Components in BWRVIP Scope Core Shroud (BW RVIP-76)
Shroud Support (BW RVI P-38)
Shroud Repair Hardware (BWRVIP Letters 2006-112 and 2006-220)
Date or Frequency of Ins-pection 04/95 03/97 01/00 02/02 03/04 04/06 04/95 01/00 04/06 04/06 Inspect ion Method Used EVT-1 and UT EVT-1, VT-3 ET/UT EVT-EVT-EVT-1 EVT-1 EVT-1 EVT-1 EVT-1, VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Inspections per BWRVIP Guidelines of all shroud repair design-reliant hardware prior to installation of comprehensive repair (4 GE designed tie-rod assemblies). Inspection of shroud consisted of EVT-1 of all ring segment welds (1 00% of accessible ring surfaces examined), EVT-1 of vertical welds between H1 & H2 OD surface >35% length/weld (ID not accessible), UT of all 6 beltline vertical welds >30%
length/weld, and EVT-1 of vertical welds between H6 & H7 OD surface >22% length/weld (ID not accessible). Approximately 51" of 356" examined at the core plate support ring weld (HAZ of H5) had indications (H5 isstructurally replaced by comprehensive shroud repair). All other areas examined had No Reportable Indications. Performed EVT-1 on all shroud vertical welds adjacent to beltline (six verticals, 100% of accessible OD surfaces). NO Reportable Indications.
Performed VT-3 of all four tie-rod assemblies. One reportable indication related to original installation of locking device at upper spring, not service induced. Properly latched locking device.
Performed automated volumetric examination (TEIDE 2 tooling) of shroud vertical welds V-14 through V-19 in accordance with BWRVIP-03, BWRVIP-07 and BWRVIP-63. No Reportable Indications.
6 vertical welds from the OD per BWRVIP-76.
No indications.
Examined six welds, including 3 welds inaccessible to UT and three with only single side access. No reportable indications.
Ring segment vertical welds. Since the location of the welds was not known, examined 100% of the ring segments.
No reportable indications in vertical welds. Indications adjacent to weld H-5 were noted; however, the shroud tie rods structurally replaced this weld.
EVT-1 of H8 and H9 for approx 10" -12" at 4 locations of shroud repair hardware attachment areas.
Access hole covers; VT/UT in 1991, circ indications observed and permanent repair installed 1993.
Performed visual examination of H8 and H9 in accordance with BWRVIP-38 adjacent to AHC between jet pumps #20 - #1 (e.g.
at least 10% of total circumference examined). No Reportable Indications.
Examined >lo% of H8 and H9 from annulus adjacent to AHC between jet pumps #10 - #11. No Reportable Indications.
EVT-1 of all tie rod upper support vertical faces, VT-3 of high-stressed fasteners and other contact points, and overall VT-3 per BWRVIP Letters 2006-1 12 and 2006-220. Also, VT-3 of core plate wedges adjacent to repair hardware.
71 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 2 Components in BWRVIP Scope Core Spray Piping (BWRVIP-18)
Core Spray Sparger (BWRVIP-18)
Date or Frequency of inspection 1980's to 1996 03/97 01 /oo 02/02 03/04 04/06 1980's to 1996 03/97 01 /oo 02/02 04/06 Inspection Method Used VT-1 (1 mil)
UT, EVT-1 EVT-1 UT EVT-1 on Piping EVT-1 UT EVT-1 VT-1 (1 mil)
CSVT-1, VT-3 N/A EVT-1 of S1, s2, & s4; VT-1 of s3:
VT-1 of brackets EVT-1 of S1, s2, & s4; VT-1 of s3:
VT-1 of brackets Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections No reportable indications.
IEB 80-13/NUREG of piping and welds in annulus. No indications observed.
UT or EVT-1 performed in accordance with BWRVIP-18. Two indications (1.60" and 2.25" in length) observed at slip joint (PS), evaluated for at least 48 months of hot operation.
Performed visual examination of P4d and P8a(4 connections) and P2 at both T-boxes in accordance with BWRVIP-18. No Reportable I nd icat ions.
BWRVIP-18 UT examinations of all accessible welds (32). No relevant indications.
BWRVIP-18 EVT-1 on 5 welds inaccessible to UT. No indications.
Examined 100% of P8a & P4d target welds.
No relevant indications.
BWRVIP-18 UT examinations of all accessible welds (32). No relevant indications.
Examined two P4a, one P4b, one P ~ c,
four P4d, two P8a and two P8b welds. No relevant indications.
IEB 80-1 3/NUREG of welds on sparger. No indications found CSVT-1, VT-3 performed in accordance with BWRVIP-18, geometry tolerant. No Reportable Indications.
No examinations performed.
Examined 50% sparger nozzles, 100% of the S3a, S3b, & S3c nozzle welds, and 100% of S1, S2 and sparger bracket welds.
Examined for IEB 80-13 and BWRVIP-18.
No indications.
Examined 50% sparger nozzles, 100% of the S3a, S3b, & S3c nozzle welds, and 100% of S1, S2 and sparger bracket welds.
No Reportable Indications.
72 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 2 Components in BWRVIP Scope Top Guide (Rim, etc.)
(BW RVIP-26)
Core Plate (Rim, etc.)
(BW RVIP-25)
SLC (BW RVIP-27)
Jet Pump Assembly (BW RVIP-41)
Date or Frequency of Inspection 04/95 04/97 01/00 02/02 03/04 N/A 04/06 01/00 03/04 03/93 04/95 04/97 01/00 02/02 Inspection Method Used VT-1 VT-1 N/A EVT-1, VT-1 EVT-1 N/A VT-3 UT PT VT-1 VT-1 UT UT/EVT-1 UT/ET or EVT-1 EVT-1, VT-I
~
~~
~~~
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections VT-1 of 5 cells. No indications.
VT-1 of alignment assemblies. No indications.
VT-1 of alignment assemblies and adjacent rim weld. No Reportable Indications.
No examinations performed.
Inspected 2 alignment assemblies (VT-1) and accessible rim welds (EVT-I) per BWRVIP-26. No indications.
Inspected two Guide Aligner Pins and rim welds at adjacent locations. No recordable indications.
Core Plate Wedges installed 4/97.
Examined core plate wedges as part of shroud repair (tie rod) inspections. No Reportable Indications.
Performed augmented (non PDI) volumetric examination of nozzle to safe-end weld. No Reportable Indications.
Performed surface examination of Nozzle To Safe End weld.
No ReDortable Indications.
JP#7 and JP#18 set screws backed out, repaired and tack welded.
Hold down beams, beam bolt keepers, lock plates and retainers; restrainer wedges, stops, and adjusting screws, clamp bolts and keepers; riser brace assemblies, adapter and baffle plate welds, sensing lines and sensing line brackets per various SILS. NO Reportable Indications. Inspect 100% every other outage.
Performed UT examination of jet pump beams. JP#7 beam rejectable indication at center hole region. Beam replaced.
Performed UT examination of jet pump beams using technique capable of detecting cracking at throat and ears. NO Reportable Indications. Performed visual examination of RS-1,-2,-3 riser welds. NO Reportable Indications.
Performed examinations of at least 50% of the medium and high priority jet pump assembly welds in accordance with BWRVIP-41 using combination of automated (e.g. TEJET tooling) volumetric and visual techniques. JP#15 observed possible wedge (WD-1) movement, expanded inspection to include restrainer components, with no relevant indications. All other components No Reportable Indications.
Jet pump beams were replaced on 18 jet pumps. EVT-1 and VT-1 of 18 beams; pre-and post replacement (pumps 7 and 18 not replaced because they already had BWR-4 style beams)
A gap was identified on jet pump 1, and a setscrew was missing on jet pump 7. Auxiliary wedges were installed at these 73 of 76
Plant:
REACTOR
~NTERNALS INSPECTION HISTORY Quad Cities Unit 2 Components in BWRVIP Scope Jet Pump Diffuser (BW RVI P-41)
Fuel Support Alignment Pin welds (BW RVIP-47)
CRD Stub Tube in-Core Housina Date or Frequency of Inspection 03/04 04/06 04/95 01/00 04/97 02/02 03/04 04/06 02/02 03/04 04106 NIA NIA Inspection Method Used EVT-1 VT-1 EVT-1, VT-1 VT-1 N/A VT-3 VT-1, VT-3 on CRGT-1; EVT-1 on CRGT-2 & 3 EVT-1, VT-3 EVT-1, VT-3 VT-1, VT-3 VT-3 VT-3 NIA N/A Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections locations. Additionally, the set screws on pumps 7 and 18 and the riser braces for jet pumps 17 and 18 were inspected.
Jet pump sensing line clamps were installed on 8jet pumps (1, 2, 3, 10, 11, 12, 13, 20)
Examined 50% of jet pump high priority welds (AD-1, AD-2, DF-2, AD-3a, AD-3b, RS-1, and RS-2, RS-3). Examined a mix of jet pump medium priority welds (MX-1, MX-2, MX-4, RB-1, RB-No reportable indications.
2, RS-4, RS-5, RS-8, RS-9).
Examined all 20 jet pump WD-1 main wedges.
Found very minor wedge movement on 2 jet pumps, severe movement on one jet pump, and one actuating rod resting against - and wearing into - the guide sleeve. All evaluated for another cycle.
EVT-1 of 17 high-priority RS-1, RS-2 and RS-3 welds. VT-1 of all 20 main wedges (WD-1).
Found signs of wedge movement on four jet pumps. Replaced the restrainer gate and installed a mitigating slip joint clamp as planned on the pump with the most severe movement. No significant change since 2004 on the other jet pumps. The other jet pumps were evaluated for another cycle.
Diffuser to baffle plate welds examined. No reportable indications.
See Jet Pump Assembly.
Performed visual examination of CRGTs G-7 and H-8 while removed from core.
No Reportable Indications.
Examined 6 sets of guide tube welds (CRG CRGT-3) per BWRVIP-47. No Indications.
Examined 3 sets of guide tube welds (CRG 1, CRGT-2, and CRGT-3).
No Indications.
- 1, CRGT-2, and Examined 4 sets of guide tube welds (CRGT-1, CRGT-2, and CRGT-3) and FSIGT-ARPIN per BWRVIP-47.
No Indications.
Examined 6 pin welds (FSIGT-ARPIN-1) per BWRVIP-47. NO Indications Examined 3 pin welds (FS/GT-ARPIN-1). No Indications Examined 4 pin welds (FS/GT-ARPIN-1). No Indications N/A 74 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Quad Cities Unit 2 Components in BWRVIP Scope Dry Tube (GE SIL-409 and BW RVIP-47)
Feedwater Spargers (BWRVIP-48)
Instrument Penetrations (BW RVI P-49)
Vessel ID Attachments (BW RVI P-48)
Date or Frequency of Inspection 04/97 01/00 02/02 03/04 04/06 1983 1986 1990 1993 1995 02/02 2004 04/06 04/97, 01/00, 02/02, 03,04, 04/06 04/95 02/02 03/04 Inspection Method Used VT VT MVT-1 Manual UT Manual UT Manual UT Manual UT UT (GERIS)
VT-1 UT (GERIS)
VT-1, VT-3 VT-2 VT-1, VT-3 VT-1, EVT-1, VT-3 VT-1, EVT-1, VT-3 Summarize the Following Information:
inspection Results, Repairs, Replacements, Reinspections Replaced 6 dry tubes 1997. Dry tubes examined every other outage. Plunger engagement verified each outage.
Verified plungers engaged at Top Guide. NO Reportable Indications.
Examined 6 dry tubes. Indications observed on 5 dry tubes, and authorized for one additional cycle of operation.
None required. All original dry tubes have been replaced.
No inspections required.
UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI UT of all four N4 nozzles and inner radii. NRI Examined all Feedwater Spargers. Examined per NUREG-061 9 program and BWRVIP-48.
No indications.
UT of all four N4 nozzles and inner radii. Acceptable.
VT-3 overall condition and VT-1 bracket welds of all FW sparger end brackets.
Three FW sparger end brackets showed signs of wear where the pins had worn into the brackets. All stop pin nuts were welded to the tins as a me-Planned measure.
VT-2 system leakage test. Acceptable.
Section XI inspections of jet pump riser brace, dryer, feedwater sparger, core spray, and surveillance capsule holder brackets, performed once per interval. VT-3, or VT-1 if in beltline region.
No Reportable Indications.
Inspected 8 core spray brackets, 4 feedwater sparger brackets, and 4 steam dryer wall support brackets per BWRVIP-48. No indications.
Examined dryer support lugs and surveillance specimen brackets, with no reportable indications.
Examined steam separator and steam dryer guide rod bracket welds. One separator guide rod was bent, but the welds had no reportable indications.
Examined feedwater sparger end brackets. One FW sparger end bracket pin was missing a lower nut. A new nut was welded into place.
75 of 76
Plant:
REACTOR INTERNALS INSPECTION HISTORY Quad Cities Unit 2 Components in BWRVIP Scope RPV Internal Surf aces (Cladding )
(ASME B.N.l)
LPCl Coupling Steam Dryer (GE SIL-644 and BW RVI P-139)
Date or Frequency of Inspection 04/06 02/02 03/04 N/A 02/02 03/04 04/06 Inspection Method Used EVT-1, VT-3 VT-3 VT-3 N/A VT-3 Best Effort VT-1, VT-3 Best Effort VT-1, VT-3 Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Performed BWRVIP-48 and ASME code inspections of four steam dryer wall support lugs. All four lugs sustained some damage during May 2005 installation of new steam dryer, but all lugs acceptable as-is. No recordable indications in welds.
VT-3 visual examination for ASME Section XI, B-N-1 of RPV internal surfaces for 360 degrees between steam dam and flange. No indications.
VT-3 visual examination for ASME Section XI, B-N-1 of RPV internal surfaces for 360 degrees between steam dam and shroud support plate flange. No indications.
Not applicable to Quad Cities.
The dryer was modified to accommodate the Extended Power Uprate. The modification installed a mechanical device on the outlet of the dryer chevrons that would more uniformly distribute the velocity through the dryer and increase moisture removal.
General Condition Inspection (VT-3) of general top-view post-modification. No indications.
Conducted the following inspections per GE SIL-644 S1:
Best effort VT-1 inspections of 100% external vertical and horizontal welds, tie bars, and perforated plates; Best effort VT-1 inspections of 100% internal vertical and horizontal hood welds, struts and supports, plates, drain channels; VT-3 inspections of dryer skirt welds (internal and external).
Repaired indications in drain channel-to-skirt welds and tie bar welds, and at outer hood gussets and a stiffener plate added after previous dryer failures.
Also found indications (acceptable as-is) at the following locat ions :
Internal struts, vane assembly end plate supports, internal hood welds, guide channels, one drain channel, a hold down assembly tack weld, and perforated plate welds.
Performed baseline inspection of new steam dryer installed in May 2005 per BWRVIP-139 and GE recommendations.
Inspection scope expanded due to indications found in vane bank end plates, gussets, and damage to skirt.
The following damage was attributed either directly or indirectly to a lifting event during the original attempt to install the dryer in May 2005: fatigue cracks and distortion in the dryer skirt and base plate support lug cutouts, fatigue crack in a gusset attached to a vane assembly end plate, and a cracked latch box.
The following indications were attributed as noted: lifting eyes rotated (design weakness), stress relief cracking in vane assembly plates (original construction issue), and distortion in perforated plates (original construction issue).
76 of 76 Revision 1 Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative in Accordance with 10 CFR 50,55a(a)(3)(i)
Clinton Power Station Dresden Nuclear Power Station, Units 2 and 3 LaSalle County Station, Units 1 and 2 Limerick Generating Station, Units 1 and 2 Oyster Creek Generating Station Peach Bottom Atomic Power Station, Units 2 and 3 Quad Cities Nuclear Power Station, Units 1 and 2 Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
Clinton Power Station Second Dresden Nuclear Power Station, Units 2 and 3 Fourth LaSalle County Station, Units 1 and 2 Third Limerick Generating Station, Units 1 and 2 Third 3yster Creek Generating Station Fourth Peach Bottom Atomic Power Station, Unit 2 Fourth Peach Bottom Atomic Power Station, Unit 3 Fourth Quad Cities Nuclear Power Station, Units 1 and 2 Fourth ASME Code Component(s) Affected
- 1.
- 2.
- 3.
ASME Section XI, Class 1, Examination Categories B-N-1 (Interior of Reactor Vessel) and B-N-2 (Welded Core Support Structures and Interior Attachments to Reactor Vessels), Code Item Nos. B13.10 - Vessel Interior, 813.20 - Interior Attachments within Beltline Region, B13.30 - Interior Attachments beyond Beltline Region, and 813.40 - Core Support Structure.
Applicable Code Edition and Addenda
PLANT 1 INTERVAL END START EDITION 1989 Edition, no addenda January 1,2000 December 31,201 C 1995 Edition, through 1996 Addenda January 20,2003 January 19,2013 2001 Edition, through 2003 Addenda October 1,2007 September 30,201:
2001 Edition, through 2003 Addenda February 1,2007 January 31,2017 1995 Edition, through 1996 Addenda October 15,2002 October 14,201 2 2001 Edition, through 2003 Addenda (Final edition to be determined) 2001 Edition, through 2003 Addenda (Final edition to be determined) 1995 Edition, through 1996 Addenda November 5,2008 November 4,201 8 August 15,2008 August 14,201 8 March 10,2003 March 9,2013 Applicable Code Requirements ASME Section XI requires the examination of components within the Reactor Pressure Vessel. These examinations are included in Table IWB-2500-1 Categories B-N-1 and B-N-2 and identified with the following item numbers:
B 13.10 Examine accessible areas of the reactor vessel interior each period by the VT-3 method (B-N-I).
B 13.20 Examine interior attachment welds within the beitline region each interval by the VT-1 method (B-N-2).
I Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative,
Page 2 B 13.30 Examine interior attachment welds beyond the beltline region each interval by the VT-3 method (B-N-2).
B 13.40 Examine surfaces of the welded core support structure each interval by the VT-3 method.
These examinations are performed to assess the structural integrity of components within the boiling water reactor pressure vessel.
4. Reason for Request
In accordance 10 CFR 50.55a(a)(3)(i), Exelon Generation Company, LLC (Exelon) and AmerGen Energy Company, LLC (AmerGen) are requesting a proposed alternative to the Code requirements provided above on the basis that the use of the BWRVIP guidelines discussed below will provide an acceptable level of quality and safety.
The BW RVI P Inspection and Evaluation (I&E) guidelines have recommended aggressive specific inspection by BW R operators to completely identify material condition issues with BWR components. A wealth of inspection data has been gathered during these inspections across the BW R industry. I&E guidelines focus on specific and susceptible components, specify appropriate inspection methods capable of identifying real anticipated degradation mechanisms, and require re-examination at conservative intervals. In contrast, the code inspection requirements were prepared before the BWRVIP initiative and have not evolved with BWR inspection experience.
Use of this proposed alternative will maintain an adequate level of quality and safety and avoid unnecessary inspections, while conserving radiological dose.
- 5. ProDosed Alternative In lieu of the requirements of ASME Section XI, the proposed alternative is detailed in attached Table 1 for Examination Category B-N-1 and B-N-2.
Exelon and AmerGen will satisfy the Examination Category B-N-1 and B-N-2 requirements as described in Table 1 in accordance with BWRVIP guideline requirements. This relief request proposes to utilize the identified BWRVIP guidelines in lieu of the associated Code req u i re m e n ts, in c I u d i n g exam in at i o n method, exam i nation vo I u m e, f req ue n c y, train in g,
successive and additional examinations, flaw evaluations, and reporting.
el and i l
~
~
~
~
~
a
~
~
el i nes" BWRVI P-l8-A, "BWR Core Spray lnternals Inspection and Flaw Evaluation Guidelines" BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines" BW RVI P-38, "BW R Shroud Support Inspection and Flaw Evaluation Guidelines" BWRVIP-41, Revision 1 "BWR Jet Pump Assembly Inspection and Flaw Evaluation BWRVlP-42-A, "LPCI Coupling Inspection and Flaw Evaluation Guidelines" BWRVI P-47-A, "BWR Lower Plenum Inspection and Flaw Evaluation Guidelines" G u id e I i n es I'
I Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative,
Page 3
- 6.
I I
- 7.
BW RVI P-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines" BWRVl P-76, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines" (replaced BWRVIP-01, -07, and -63)
The attached Table (Table 1) compares present ASME Examination Category B-N-1 and B-N-2 requirements with the above current BWRVIP guideline requirements, as applicable, to BWR/2 through BWW6 units.
In addition, where guidance in existing BWRVIP documents has been supplemented or revised by subsequent correspondence approved by the BWRVIP executive committee, the most current 6W RVI P approved guidance will be implemented. Therefore, the attached Table only represents a current comparison.
Any deviations from the referenced BWRVIP Guidelines for the duration of the proposed alternative will be appropriately documented and communicated to the NRC, per the BW RVI P Deviation Disposition Process. Current Exelon/AmerGen deviations from the subject guidelines above are summarized in Table 2.
Inspection services, by an Authorized Inspection Agency, will be applied to the proposed alternative actions of this relief request.
Basis for Use BW Rs now examine reactor internals in accordance with BW RVI P guidelines. These guidelines have been written to address the safety significant vessel internal components and to examine and evaluate the examination results for these components using appropriate methods and reexamination frequencies. The BW RVI P has established a reporting protocol for examination results and deviations. The NRC has agreed with the BWRVIP approach in principal and has issued Safety Evaluations for these guidelines (see References 2 - 12 below). Therefore, use of these guidelines, as an alternative to the subject Code requirements, provides an acceptable level of quality and safety and will not adversely impact the health and safety of the public.
As additional justification, Attachment 4 ("Comparison of Code Examination Requirements to BWRVIP Examination Requirements") provides specific examples which compare the inspection requirements of ASME Code Item Numbers B13.10, B13.20, B13.30, and B13.40 in Table IWB-2500-1, to the inspection requirements in the BWRVIP documents. Specific BWRVIP documents are provided as examples. This comparison also includes a discussion of the inspection methods. These comparisons demonstrate that use of these guidelines, as an alternative to the subject Code requirements, provides an acceptable level of quality and safety and will not adversely impact the health and safety of the public.
Duration of Proposed Alternative The duration of the alternative is for the remainder of the interval specified above for each affected unit.
I Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative Attac hrnent 3, Page 4
- 8. Precedence A similar relief request was approved for Vermont Yankee Nuclear Power Station as discussed in Reference 1.
- 9. References
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
Letter from U. S. Nuclear Regulatory Commission (USNRC) to Entergy Nuclear Operations, "Safety Evaluation of Relief Request RI-01, Vermont Yankee Nuclear Power Station (TAC NO. MC0690)", dated September 19, 2005 Letter USNRC to BWRVIP, dated April 27, 1998, "Final Supplement to the Safety Evaluation of the Boiling Water Reactor Vessel lnternals Project, BWRVIP-07 Report (TAC NO. M94959)"
Letter USNRC to BWRVIP, dated October 6, 1999, "Staff Reevaluation of Table 1 in the BWRVIP-07 Report (TAC NO. M94959)"
Letter USNRC to BWRVIP, dated September 6, 2005, "NRC Approval Letter of BWRVl P-l8-A, "BWR Vessel and lnternals Project Boiling Water Reactor Core Spray lnternals Inspection and Flaw Evaluation Guideline" I' Letter USNRC to BWRVIP, dated September 9, 2005, "NRC Approval Letter of BWRVIP-26-A, "BWR Vessel and lnternals Project Boiling Water Reactor Top Guide Inspection and Flaw Evaluation Guidelines" I' Letter USNRC to BWRVIP, dated July 24, 2000, "Final Safety Evaluation of the "BWR Vessel and lnternals Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38)," EPRl Report TR-108823 (TAC NO. M99638)"
Letter USNRC to BWRVIP, dated February 4, 2001, "Final Safety Evaluation of the "BWR Vessel and lnternals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (BWRVIP-41)," (TAC NO. M99870)"
Letter USNRC to BWRVIP, dated September 9, 2005, NRC approval letter of BWRVIP-42-A, "BW R Vessel and lnternals Project Boiling Water Reactor Low Pressure Coolant Injection and Flaw Evaluation Guidelines" Letter USNRC to BWRVIP, dated September 9, 2005, "NRC Approval Letter of BW RVI P-47-A, "BW R Vessel and lnternals Project Boiling Water Reactor Lower Plenum Inspection and Flaw Evaluation Guidelines" I' Letter USNRC to BWRVIP, dated July 25, 2005, "NRC Approval Letter of BWRVIP-48-A, "BWR Vessel and lnternals Project Vessel ID Attachment Weld Inspection and Flaw Evaluation Guideline" 'I Letter USNRC to BWRVIP, dated August 20, 2001, "Final Safety Evaluation of the "BWR Vessel and lnternals Project, Shroud Vertical Weld Inspection and Evaluation Guidelines (BWRVIP-63)," (TAC NO. MA601 5)"
I Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative,
Page 5 12% Letter us
$aft
I Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative Attachment Page 6 TABLE 1 I Guidance Requirements (')
I I
Comparison of A ME Examination C :egory B-N-1 ai ASME Exam I B-N-2 Requirc ients With BWRV Applicable BWRVIP Document ASME Item No. Table IWB-2500-1 B13.10 BWRVIP Frequency I
Exam ASME Exam Scope ASME Frequency Component Reactor Vessel Interior Accessible Areas (Non-specif ic)
VT-3 Each period BWRVIP-18, 26, 38, 41, 42,
- 47. 48. 76 Overview examinations of components during BWRVIP examinations satisfy Code VT-3 inspection requirements.
B13.20 Interior Attachments Within Beltline - Riser Braces Accessible Welds BW RVIP-48 Table 3-2 Riser Brace Attachment EVT-1 VT-1 Each 10-year Interval 100% in first 12 years, 25% during each subsequent 6 years Each 1 0-year Interval VT-1 Lower Surveillance Specimen Holder Brackets Interior Attachments Beyond Beltline - Steam Dryer Hold-BW RVI P-48, Table 3-2 Table 3-2 BWRVIP-48 Bracket Attachment Bracket Attachment B13.30 VT-3 Each 10-year Interval VT-3 Each 1 0-year Interval Accessible Welds down Brackets Guide Rod Brackets VT-3 Each 1 0-year Interval BW RVI P-48, Table 3-2 Table 3-2 Table 3-2 Table 3-2 BW RVIP-48, BW RVI P-48, BW RVIP-48, Bracket Attachment Bracket Attachment Bracket Attachment EVT-1 Each 1 0-year Interval Steam Dryer Support Brackets Feedwater Sparger Brackets EVT-1 Each 1 0-year Interval Core Spray Piping Brackets EVT-1 Bracket Attachment Every 4 Refueling Cycles Each 1 0-year Interval Upper Surveillance Specimen Holder Brackets BW RVIP-48, Table 3-2 Bracket Attachment VT-3 Shroud Support (Weld H9) applicabk i klcl trd in g gussets where BWRVIP-38, 3.1.3.2, Figures 3-2 and 3-5 EVT-1 or UT Maximum of 6 years for EVT-1, Maximum of 10 years for UT Weld H9'2' ir-ncftadir-ly gussets (where applicable)
Weld H12 (Rarely Accessible)
Shroud Support Legs (H12)
Welds BWRVIP-38, 3.2.3 When accessible Per BWRVIP-38 NRC SER (7/24/00),
inspect with appropriate method (4)
Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative Attachment Page 7 ASME Item No. Table I W B-2500-1 Component ASME Exam Scope ASME Exam ASM E Frequency Applicable BWRVIP Document BWRVIP Exam BWRVIP Exam Scope BWRVIP Frequency 61 3.40 Inteegraity Welded Core Support Structure Accessible Surfaces VT-3 Each 10-year Interval BWRVIP-38, 3.1.3.2, Figures 3-2, 3-5 EVT-I or UT Based on as-found conditions, to a maximum 6 years for one side EVT-I, 10 years for UT ~viaeite accessible Based an as-fsund conditions, $a a maximum 6 years far one side EW-?
I 10 yslars far UT trJhere accsssibie Maximum 6 years for one-sided EVT-1, 10 years for UT Shroud Support and Leg Welds including gussets a5 applicable Welds HI-H7 as applicabie Shroud Horizontal welds BW RVI P-76, 2.2.1 EVT-1 or UT Shroud Vertical welds BW RVIP-76, 2.3, Figure 3-3 Vertical and Ring Segment Welds as aDolicak&
EVT-1 or UT Shroud Repairs (3)
BW RVIP-76, Section 3.5 Tie-Rod Repair VT-3 Per repair designer recommendations Der BW RVI P-76.
NOTES:
- 1) This Table provides only an overview of the requirements. For more details, refer to ASME Section XI, Table IWB-2500-1, and the appropriate BWRVIP document.
- 2) In accordance with Appendix A of BWRVIP-38, a site specific evaluation will determine the minimum required weld length to be examined.
- 3) Shroud repairs are currently installed on both units at Dresden and Quad Cities, and on the single units at Oyster Creek and Clinton.
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Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative Attachment A Page 8 PLANT LaSalle County Station, Unit 1 Oyster Creek Generating Station BWRVIP DOCUMENT BW RVI P-76 BW RVI P-76 LETTER DATE TO USNRC Letter from S. R. Landahl (Exelon Generation Company, LLC) to U. S.
Nuclear Regulatory Commission, dated April 27, 2006 DEVIATION 100% of the accessible areas of the LaSalle County Station Unit 1 core shroud was not examined in the L1 R11 outage in February 2006.
However, sufficient coverage of the accessible areas were examined, an engineering evaluation was performed and the results indicate the Unit 1 shroud retained sufficient structural margin and should be re-examined in six years.
Per BWRVIP-76 re-inspection guidelines, a one-sided visual examination technique requires reexamination in 6 years as compared to a two-sided visual or volumetric technique, which can achieve a 10-year reexamination frequency.
Contrary to this requirement, the four vertical welds were not reexamined in 1 R21 (2006) as required by the BWRVIP-76 guidance for single-sided examination.
APPLICABILITY This deviation does not impact the basis for use of this relief request.
This deviation does not impact the basis for use of this relief request.
Comparison of Code Examination Requirements to BWRVIP Examination Requirements Clinton Power Station Dresden Nuclear Power Station, Units 2 and 3 LaSalle County Station, Units 1 and 2 Limerick Generating Station, Units 1 and 2 Oyster Creek Generating Station Peach Bottom Atomic Power Station, Units 2 and 3 Quad Cities Nuclear Power Station, Units 1 and 2
ATTACHMENT 4 COMPARISON OF CODE EXAMINATION REQUIREMENTS TO BWRVIP EXAMINATION REQUIREMENTS The following discussion provides a comparison of the examination requirements provided in ASME Code Item Numbers B13.10, 813.20, B13.30, and B13.40 in Table IWB-2500-1, to the examination requirements in the BW RVIP guidelines. Specific BWRVIP guidelines are provided as examples for comparisons. This comparison also includes a discussion of the examination methods.
- 1. Code Requirement - 813.10 - Reactor Vessel Interior Accessible Areas (B-N-1)
The ASME Section XI Code requires a VT-3 examination of reactor vessel accessible areas, which are defined as the spaces above and below the core made accessible during normal refueling outages. The frequency of these examinations is specified as the first refueling outage, and at intervals of approximately 3 years, during the first inspection interval, and each period during each successive 1 0-year Inspection Interval. Typically, these examinations are performed every other refueling outage of the Inspection Interval. This examination requirement is a non-specific requirement that is a departure from the traditional Section XI examinations of welds and surfaces. As such, this requirement has been interpreted and satisfied differently across the domestic fleet. The purpose of the examination is to identify relevant conditions such as distortion or displacement of parts; loose, missing, or fractured fasteners; foreign material, corrosion, erosion, or accumulation of corrosion products; wear; and structural degradation.
Portions of the various examinations required by the applicable BWRVIP Guidelines require access to accessible areas of the reactor vessel during each refueling outage. Examination of core spray piping and spargers (BWRVIP-W-A), top guide (BWRVIP-26-A), jet pump welds and components (BWRVIP-41, Rev. I), interior attachments (BWRVIP-48-A), core shroud welds (BWRVIP-76), shroud support (BWRVIP-38), LPCl couplings (BWRVIP-42-A),
and lower plenum components (BWRVIP-47-A) provides such access. Locating and examining specific welds and components within the reactor vessel areas above, below (if accessible), and surrounding the core (annulus area) entails access by remote camera systems that essentially perform equivalent VT-3 examination of these areas or spaces as the specific weld or component examinations are performed. This provides an equivalent method of visual examination on a more frequent basis than that required by the ASME Section XI Code. Evidence of wear, structural degradation, loose, missing, or displaced parts, foreign materials, and corrosion product buildup can be, and has been observed during the course of implementing these BW RVI P examination requirements. Therefore, the specified BWRVIP Guideline requirements meet or exceed the subject Code requirements for examination method and frequency of the interior of the reactor vessel. Accordingly, these BWRVIP examination requirements provide an acceptable level of quality and safety as compared to the subject Code requirements.
- 2. Code Requirement - B13.20 - Interior Attachments Within the Beltline (B-N-2)
The ASME Section XI Code requires a VT-1 examination of accessible reactor interior surface attachment welds within the beltline each 10-year interval. In the boiling water reactor, this includes the jet pump riser brace welds-to-vessel wall and the lower
I Comparison of Code to BWRVIP Requirements Attachment Page 2 surveillance specimen support bracket welds-to-vessel wall. In comparison, the BWRVIP requires the same examination method and frequency for the lower surveillance specimen support bracket welds, and requires an EVT-1 examination on the remaining attachment welds in the beltline region in the first 12 years, and then 25% during each subsequent 6 years.
The jet pump riser brace examination requirements are provided below to show a comparison between the Code and the BW RVlP examination requirements.
ComDarison to BWRVIP Requirements - Jet PumD Riser Braces (BWRVIP-41, Rev. 1 and BW RVI P-48-A)
The ASME Code requires a 100% VT-1 examination of the jet pump riser brace-to-reactor vessel wall pad welds each 10-year interval.
The BWRVIP requires an EVT-1 examination of the jet pump riser brace-to-reactor vessel wall pad welds the first 12 years and then 25% during each subsequent 6 years.
BWRVIP-48-A specifically defines the susceptible regions of the attachment that are to be examined.
The Code VT-1 examination is conducted to detect discontinuities and imperfections on the surfaces of components, including such conditions as cracks, wear, corrosion, or erosion.
The BWRVIP enhanced VT-1 (EVT-1) is conducted to detect discontinuities and imperfections on the surface of components and is additionally specified to detect potentially very tight cracks characteristic of fatigue and inter-granular stress corrosion cracking (IGSCC), the relevant degradation mechanisms for these components. General wear, corrosion, or erosion although generally not a concern for inherently tough, corrosion resistant stainless steel material, would also be detected during the process of performing a BWRVIP EVT-1 examination.
The Code VT-1 visual examination method requires (depending on applicable Edition) that at a maximum distance of 2 feet, a 1/32" black line can be resolved or a letter character with a height of 0.044 inches can be read. The BWRVIP EVT-1 visual examination method requires resolution of a 1/2 mil (0.0005 inch) wire on the examination surface. The jet pump riser brace configuration for each plant varies with vessel manufacturer (B&W, CB&I, etc.)
and generation (BWR/3-BWR/6). BWRVl P-48-A includes diagrams for each configuration and prescribes examination for each configuration.
The calibration standards used for BWRVIP EVT-1 exams utilize the Code characters and the 0.0005" wire, thus assuring at least equivalent resolution compared to the Code.
Although the BWRVIP examination may be less frequent, it is a more comprehensive method. Therefore, the enhanced flaw detection capability of an EVT-1, with a less frequent examination schedule provides an acceptable level of quality and safety to that provided by the ASME Code.
- 3. Code Requirement - B13.30 - Interior Attachment Beyond the Beltline Region (B-N-21 The ASME Section XI Code requires a VT-3 examination of accessible reactor interior surface attachment welds beyond the beltline each 10-year interval. In the boiling water
I Comparison of Code to BWRVIP Requirements Attachment Page 3 reactor, this includes the core spray piping primary and supplemental support bracket welds-to-vessel wall, the upper surveillance specimen support bracket welds-to-vessel wall, the feedwater sparger support bracket welds-to-reactor vessel wall, the steam dryer support and hold down bracket welds-to-reactor vessel wall, the guide rod support bracket weld-to-reactor vessel wall, the shroud support plate-to-vessel wall, and ~~~~~
~~~~~~~
~~~~~~~.
BWRVIP-48-A requires as a minimum the same VT-3 examination method as the Code for some of the interior attachment welds beyond the beltline region, and in some cases specifies an enhanced visual examination technique EVT-1 for these welds. For those interior attachment welds that have the same VT-3 method of examination, the same scope of examination (accessible welds), the same examination frequency (each 10 year interval) and ASME Section XI flaw evaluation criteria, the level of quality and safety provided by the BWRVIP requirements are equivalent to that provide by the ASME Code.
I For the core spray primary and secondary support bracket attachment welds, the steam dryer support bracket attachment welds, the feedwater sparger support bracket attachment welds, and the shroud support plate-to-vessel welds, as applicable, the BWRVIP Guidelines require an EVT-1 examination at the same frequency as the Code, or at a more frequent rate. Therefore, the BWRVIP requirements provide the same level of quality and safety to that provided by the ASME Code.
The core spray piping bracket-to-vessel attachment weld is used as an example for comparison between the Code and BW RVI P examination requirements as discussed below.
Comparison to BWRVIP Requirements - Core Spray pipinq Bracket Welds (BWRVIP-48-A)
The Code examination requirement is a VT-3 examination of each weld every 10 years.
The BWRVIP examination requirement is an EVT-1 for the core spray piping bracket attachment welds with each weld examined every four cycles (8 years for units with a two year fuel cycle).
The BWRVIP examination method EVT-1 has superior flaw detection and sizing capability, the examination frequency is greater than the Code requirements, and the same flaw evaluation criteria are used.
The Code VT-3 examination is conducted to detect component structural integrity by ensuring the components general condition is acceptable. An enhanced EVT-1 is conducted to detect discontinuities and imperfections on the examination surfaces, including such conditions as tight cracks caused by IGSCC or fatigue, the relevant degradation mechanisms for BWR internal attachments.
Therefore, with the EVT-1 examination method, the same examination scope (accessible welds), an increased examination frequency (8 years instead of 10 years) in some cases, the same flaw evaluation criteria (Section XI), the level of quality and safety provided by the BWRVIP criteria is superior than that provided by the Code.
- 4. Code Requirement - B13.40 - lnteqrallv Welded Core Support Structures (B-N-2)
The ASME Code requires a VT-3 examination of accessible surfaces of the welded core support structure each 10-year interval. In the boiling water reactor, the welded core support structure has primarily been considered the shroud support structure, including the
I Comparison of Code to BWRVIP Requirements Attachment Page 4 shroud support plate (annulus floor) the shroud support ring, the shroud support welds, rhe shroud itself is considered part of the welded core support structure. Historically, this requirement has been interpreted and satisfied differently across the industry. The proposed alternate examination replaces this ASME requirement with specific BWRVIP guidelines that examine susceptible locations for known relevant degradation mechanisms.
~~~~~~~
and the shroud support legs (if accessible). In later designs, the The Code requires a VT-3 of accessible surfaces each 10-year interval.
The BWRVIP requires as a minimum the same examination method (VT-3) as the Code for integrally welded Core Support Structures, and for specific areas, requires either an enhanced visual examination technique (EVT-1) or volumetric examination (UT).
BW RVI P recommended examinations of integrally welded core support structures are focused on the known susceptible areas of this structure, including the welds and associated weld heat affected zones. As a minimum, the same or superior visual examination technique is required for examination at the same frequency as the code examination requirements. In many locations, the BWRVIP guidelines require a volumetric examination of the susceptible welds at a frequency identical to the Code requirement.
Where shroud repair tie-rods have been installed (Dresden, Quad Cities, Oyster Creek and Clinton), the BWRVl P referenced examinations are the same as the Code requirements.
Shroud repair tie-rod examinations are recommended in BWRVIP-76 and have the same basic VT-3 method of examination, the same scope of examination (accessible surfaces),
the same examination frequency (each 10 year interval) and the same flaw evaluation criteria. Therefore, the BWRVIP requirements provide a level of quality and safety equivalent to that provided by the ASME Code. Additionally, the repair vendor has provided site-specific examination recommendations to address the unique features of each repair.
For other integrally welded core support structure components, the BWRVIP requires an EVT-1 or UT of core support structures. The core shroud is used as an example for comparison between the Code and BWRVIP examination requirements as shown below.
ComDarison to BWRVIP Requirements - BWR Core Shroud Examination and Flaw Evaluation Guideline (BWRVIP-76)
The Code requires a VT-3 examination of accessible surfaces every 10 years.
The BWRVIP requires an EVT-1 examination from the inside and outside surface where accessible or ultrasonic examination of each core shroud circumferential weld that has not been structurally replaced with a shroud repair at a calculated end of interval (EOI) that will vary depending upon the amount of flaws present, but not to exceed ten years.
The BWRVIP recommended examinations specify locations that are known to be vulnerable to BW R relevant degradation mechanisms rather than all surfaces. The BW RVI P examination methods (EVT-1 or UT) are superior to the Code required VT-3 for flaw detection and characterization. The BWRVIP examination frequency is equivalent to or more frequent than the examination frequency required by the Code. The superior flaw detection and characterization capability, with an equivalent or more frequent examination frequency
I Comparison of Code to BWRVIP Requirements Attachment Page 5 I
and the ~~~~~~~~~~
flaw evaluation criteria, results in the BWRVlP criteria providing a level of quality and safety equivalent to or superior to that provided by the Code requirements.