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 Nucl ear 4300 Winfield Road Exelon Generation Warrenville, IL 60555 4300 Winfield Road Warrenville, IL 60555 10 CFR 50.55a October 5,2007 RS-07-134 2 130-07-20507 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/AmerGenfacilities, 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, 610-765-5510.
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
Attachment 1 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 Attachment 1 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.
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
RESPONSE
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 Attachment 1 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 RVIP-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 RVIP 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, "BWRVlP 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-0619, "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 Attachment 1 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-0619.
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 H I 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.
QUESTlON:
(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 Attachment 1 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 BWRVIP-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 1021n/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 1021n/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 RVIP-100-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 1021n/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 evaIuation.
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 Attachment 1 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 H I through H7 asshown on page 7.
QUESTION:
(12) 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.
Attachment 2 Inspection Histories
REACTORINTERNALS INSPECTION HISTORY Plant: Clinton
~
Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Ins-pection Core Spray Piping 10/2000 UT Performed UT on the identified piping welds on both High (C 1R07) 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.
EVT-1 P4c and P4d. No recordable indications (NRI).
~
VT- 1 A&B-P8. NRI.
2/2004 UT Performed UT of piping welds on both High Pressure and (Cl R09) 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.
EVT-1 One weld each P ~ cP4d , and P8. NRI.
A-PR, A-ADR, A-BDR, B-PR, B-CDR, and B-DDR piping welds. NRI.
2/2006 VT- 1 A&B-P8. NRI.
(CIRIO) EVT-1 A-BP~c,A-BP4d, A-APB(PBl), A-BPB(PB2). NRI.
A-PR, A-ADR, A-BDR, B-PR, B-CDR, and B-DDR piping welds. NRI.
Core Spray Sparger 10/2000 EVT-I and NRI (Cl R07) VT- 1 2/2004 EVT-1 and NRI.
(CI R09) VT-1 2/2006 EVT-1 NRI.
Attachment Welds 10/2000 VT-3 Guide Rod Support Brackets, Steam Dryer Hold Down (CI R07) Brackets and Steam Dryer Support Brackets per ASME Section XI. NRI.
2/2004 EVT-1 Several Steam Dryer Support Brackets have contact marks (CI R09) and several do not. Clinton will be Monitoring this condition.
VT- 1 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 C1R10.
2/2006 EVT-1 No change identified in Several Steam Dryer Support (Cl R10) Bracket contact points.
VT- 1 No indications identified. Guide rods and brackets were inspected to look for any damage caused by steam separator lower bracket. NRI.
VT- 1 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 1 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Clinton Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection Core Shroud 4/2002 UT Performed UT of all Horizontal Welds. In addition, some (C1R08) vertical welds screened-in per BW RVIP-76 criteria.
Coverage:
Weld Number Yoof Examined Lenqth H1 59.7%
H2 67.4%
H3 66.7%
H4 upper side 100%
H4 lower side 97.1Yo H5 upper side 19.0%
H5 lower side 18.7%
H6A 16.4%
H6B 25.6%
H7 26.5%
v11 95.2%
v12 95.o%
V13 87.0%
V14 87.0%
Flaw extents were identified as follows:
Weld Number Yo of Examined Lenqth Flawed H1 0%
H2 0%
H3 19.1%
H4UPP 97.2%
H4Low 74.0%
H5UPP 15.3%
H5Low 0%
H6A 0%
H6B 5.4%
H7 0%
v11 0%
v12 0%
V13 0%
V14 0%
Prior to startup, an Engineering Evaluation was performed to justify ultimately two cycles of operation.
2/2006 4 Tie Rods installed in 2/2006 (Cl R10).
(C1R10) Inspection performed as required by BWRVIP-76. NRI.
Shroud Support 10/2000 EVT-1 EVT-1 of H8 and H9 welds for > l o % length per BWRVIP-38.
(C1R07) No indications identified.
2/2004 UT UT of H9 weld for 100% length from outside the Reactor (C1R09) wall. No indication was identified.
VT- 1 VT-1 examined the Access Hole Cover assembly per GE SIL 462. No indications identified.
2/2006 EVT-1 H8 Weld No indications identified.
(C1R10)
SLC NA Injection is through Core Spray 2 of 76
REACTORINTERNALS INSPECTION HISTORY Plant:
Components in BWRVIP Inspection Summarize the Following Information:
Scope Inspection Results, Repairs, Replacements, Reinspections Jet Pump Assembly 10/2000 I EVT-1 Performed EVT-1 of 50% of the High Priority RS-3 welds.
C1R07 NRI.
4/2002 EVT-1 Performed EVT-1 of 50% of the Medium Priority RS-1 welds.
C1R08 NRI.
2/2004 Performed EVT-1 of remaining 50% of High Priority RS-3 (C1R09) 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.
VT- 1 50% of the WD-1 Wedge Bearing Surface, NRI.
50% of the Sensing Lines. NRI.
UT UT was performed on all 20 Diffusers with 100% coverage of welds: AD-I. AD-2. DF-1. DF-2. and DF-3. NRI.
LPCI Couplings 2/2006 (C1R10) 4/2002 I VT-l EVT-1 Sample inspection of WD-1 Wedge Bearing Surfaces on four ournos. NRI.
Examined Loop C except weld 6-6b. NRI.
( C l R08) 2/2004 EVT-1 Examined all welds on Loops Aand 6 and weld 6-6bs on (C1R09) Loop C. NRI.
2/2006 EVT-1 Examined Loop A, all welds. NRI.
(C1R10)
Lower Plenum 4/2002 EVT-I or Examined seventeen (11%) per BWRVIP-47, CRDGT-1, 2, (C1R08) VT-3 (as 3 and pin. NRI.
applicable)
Steam Dryer 4/2002 VT-3 Performed VT-3 of Steam Dryer Tie Rods. No indications (C1R08) 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 C1R01.
4/2004 VT-3 Steam dryer Drain Channel # 8 to the Skirt (V16) is now 8-(C1R09) 3 / 4 in lenath.
The V16 cracking was repaired using under water welding.
VT- 1 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.
2/2006 VT-1 best All welds examined from outside.
(C1RIO) effort 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 C1RIO.
3 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant:
Components Clinton in BWRVIP Scope I FrequencyOf Ins ection j Inspection Method Used I Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Top Guide 1 2/2004 I VT-3 Performed VT-3 of the Top Guide hold-down assembly bolts (C1R09) and nuts. NRI.
Vessel 10/2000 VT-3 Vessel interior to ASME XI. NRI.
(C1R07) 2/2004 VT-3 Vessel interior to ASME XI. NRI.
Nuclear Instrument Dry-tubes I (C1R09) 4/2002 (ClR08) I VT-3 I Four IRMs examined as recommended in SIL. NRI.
2/2004 VT- 1 4 IRM and 4 SRM. One indication identified on SRM D (C1R09) evaluated by GE for operating one cycle. Other tubes were NRI.
2/2006 VT-3 Four IRM, one SRM and four LPRM tubes were examined.
I I NRI.
SRM D drv tube was replaced.
Steam Separator I 10/2000 (ClR07) 2/2004 vT-3 VT-3 Examine overall condition of Steam Separator (50%). Not ASME or SIL driven. NRI.
Examine overall condition of Steam separator (second 50%).
(C1R09) One minor dent identified.
4 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Core Spray Piping 1980s-D2RI3 VT- 1 IEB 80-13. No flaws identified.
10/1995 D2R14 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.
3/1998 D2R15 UT Initiated BWRVIP-18 recommendations. Examined piping using the GE CSI-2000 UT device. Identified three previously unidentified flaws (1P5, 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. 1P5 and 2P8a were not visually verified. All flaws were analyzed for two additional cvcles of ooeration with no reoairs reauired.
EVT-1 Examined undemonstrated welds P8a and P4d locations with EVT-1 to supplement UT. No additional flaws identified.
10/2000 D2R16 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.
10/2001 D2R17 UT, EVT-1 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.
10/2003 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
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden Unit 2 Date or Inspection Summarize the Following Information:
Frequencyof Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 1980s to D2R15 VT- 1 IEB 80-13 VT-1 of sparaers and tee-boxes. NRI.
3/1998 D2R16 EVT-1 (CSVT- Initiate BWRVIP-18 recommendations. Examined 1), 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.
VT- 1 Examined spargers nozzles (S3a and b) and the sparqer pipinq to VT-1. NRI.
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 VT- 1 Section XI inspections of jet pump riser brace, dryer, D2R15 feedwater sparger, core spray, and surveillance capsule holder brackets, performed once per interval.
NRI 3/1998 MVT-1 Inspected Core Spray Brackets per BWRVIP D2R16 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. NR 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.
1ll2005 D2R19 EVT-1 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. NR I.
EVT-1 100% (4) steam drver wall support has. NRI.
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
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Core Shroud 8/1995 D2R14 EVT-1 and UT 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.
NA Installed repair hardware(4 GE designed tie-rod assemblies) to structurally replace the shroud horizontal welds H1 throuah H7.
03/1998 D2R15 VT-1, VT-3 Shroud repair hardware inspected per GE recommendations. NRI.
10/1999 D2R16 UT/EC 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%
V17: 52.6%
V18: 62.8%
V19: 58.0%
10/2001 D2R17 EVT-1 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.
11/2005 D2R19 EVT-1 Examined 100% (16) 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
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection VT-I and EVT- Performed 10 year shroud tie rod examination of all 1 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.
VT-1 of retainer devices at lower support, lower 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 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 assemblies. 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- Safe end and nozzle examined. NRI.
2 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.
8 of 76
REACTOR~NTERNALSINSPECTION HISTORY Plant: Dresden Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 10/1999 D2R16 EVT-1 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). IdentifiedJP#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.
VT- 1 Examined restrainers for set-screw qaps. NRI.
10/2003 D2R18 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 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.
EVT-1 Measured f k w o n 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 8/1995 D2R14 UT Jet pump beams have been UT examined each and prior outage using technique capable of detecting cracking at throat and ears. One beam found cracked at ear in 1995 and was replaced.
311998 D2R15 UT UT examined 100% of Jet Pump Beams. NRI.
10/1999 D2R16 UT UT examined 100% of Jet Pump Beams, NRI.
10/2001 D2R17 UT UT examined 100% of Jet Pump Beams, NRI.
10/2003 D2R18 NA Replaced all 20 Jet Pump Beams with Group 3 weldless keeper beams.
9 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used inspection Results, Repairs, Replacements, Reinspections InsrJection 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- 5% inspected (9) per BWRVIP-47, CRDGT-1,2,3 and 3 tin. NRI.
Steam Dryer 10/2003 D2R18 VT-I best Performed inspections in accordance with the effort guidance in SIL 644 S1.
Several Rls were identified requiring modificationto the outer hoods as well as repairs to several tie bars.
11/2005 D2R19 VT-1 best Performed BWRVIP-139 required inspections as well effort 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 115.
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, SC1B, SCl D, SC2D, SC3C, SC3D, SC3E, SC4A, SC4B, SC4C, SC4D, SC4E AND SC4-FLG, NRI.
10/2003 D2R18 UT Examined vertical welds SC1C, 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
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections lnsnection Nuclear Instrument Dry-I 11/2005 D2R19 VT-3 VT- 1 Examined vessel cladding from the steam dam to the vessel flange, NRI.
Examined SRM and IRM drv tubes. NRI.
tubes VT- 1 Examined 3 IRM dry tubes. NRI.
Steam Separator 11/2005 D2R19 VT- 1 Examined shroud head bolt pin and window condition.
RI identified minor wear that was evaluated as-is for continued operation.
Examined eight standpipe to shroud head welds and eight gusset to rinq welds, NRI.
11 of 76
REACTOR~NTERNALSINSPECTION HISTORY Plant: Dresden 3 Date or Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection Core Spray Piping 1980's Through VT- 1 IEB 80-13 (1 MIL) VT-1 of piping and welds in annulus.
1994 Indications observed at two lower elbow to pipe welds 2P4c and 4P4c. These welds were repaired using GE designed clamps.
4/97-R14 UT/EVT-1 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.
2/99-R15 EVT-1 EVT-1 examined undemonstrated welds P8a and P4d on all four downcomers. Installed a "bumper" repair on 1P8a at the 80" downcomer.
9/00-R16 UT/EVT-1 I UT of "Target" welds and EVT-1 of all undemonstrated I welds. Also EVT-1 of welds made inaccessible from repair installed on the 80" downcomer including 1P7, 1P ~ c1,P4d, 1P8a and b. Welds 2P4c and 4P4c exhibited flaw growth as predicted by Flaw Evaluation.
10/02-R17 VT- 1 Six P4 welds for presence of "excessive grinding". NRI.
All undemonstrated welds P8a and P4d and long seams on thermal collars, NRI 10/04- R18 EVT-1 Examined piping welds 1P1, 2P1, 1P2, 2P2, 1P3, 2P3, 3P3,4P3,2P4a, 2P4b.
Eight Core Spray Piping brackets, attachment weld, pad surface and HAZ of cladding. NRI.
NA 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.
11/06 - R19 VT-1/VT-3 Core Spray Lower Sectional Replacement
- VT-1 of all accessible bolting, keepers, ratchets and latch springs. NRI
- VT-3 of all repair hardware. NRI EVT-1 Examined piping welds: 1P1, 2P1, 1P2, 2P2, 1P3, 2P3, 3P3, 4P3, 3P4a, 3P4b and two piping brackets, attachment weld, pad surface and HAZ of cladding. NRI.
Core Spray Sparger 1980's Through VT- 1 IEB 80-13 (1 MIL) VT-1 of spargers and tee-boxes. NRI.
1994 4/97-R14 EVT-1, VT-3 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 to VT-3. NRI.
1O/OO-R 16 EVT-1, VT-3 Per BWRVIP-18: EVT-1 of all S1, S2 and S4. VT-1 of 50% of S3. NRI.
10/04 - R18 EVT-1 Sparger to End Cap Welds: 1S4 (7')), 1S4 (183'), 2S4 (7'), 2S4 (183'), 3S4 (3'), 3S4 (187'), 4S4 (3", 4S4 (187'). NRI.
VT-1 Nozzle Tack Welds: 3S3 (187-260Q),3S3 (260-003'),
4S3 (187-290'), 4S3 (290-003'). NRI.
-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.
12 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden 3 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Attachment Welds 4/94-R 13 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.
10/00-R16 VT- 1 ASME Section XI B-N-2, surveillance capsule holder attachments in beltline. All six sets examined. NRI.
10/02-R17 EVT-1 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 10/04- R18 EVT-1 Four steam dryer wall support lugs, lug to pad, and pad to vessel attachment welds. Eight feedwater sparger lug to vessel attachment welds. NRI.
VT- 1 Eight feedwater sparger end-bracket lug assemblies. NRI 11/06-R19 VT-3 Examined attachment welds for two Core Spray piping brackets and all four steam dryer wall support lugs in accordance with ASME Section XI. NRI EVT-1 Inspected piping bracket to piping weld and bracket to vessel attachment weld on 2 core spray piping brackets.
NRI VT- 1 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 Core Shroud 4/94- R 13 EVT-1 and UT Inspections per SIL 572, extensive indications in circumferentialwelds.
4/97- R 14 EVT-1 and UT Inspected all shroud repair design reliant structure prior to installation of comprehensive repair (4 GE 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.
NA Installed four tie-rod shroud repair assemblies and four core plate wedges.
2/99-R15 VT- 1 Examined all four tie-rod assemblies and core plate wedges at locations specified by the manufacturer (GE).
1O/OO-R 16 UT Examined a 40" segment of H4 to assist in shroud qualification of Core Spray Repair. NRI.
10/04- R18 EVT-1 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
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden 3 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection 11/06 - R19 UT 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.
EVT-1 Performed one-sided EVT-1 examinations on vertical welds. NRI. Coverage as follows:
V7 - 40%
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)
VT-3, Performed GE recommended inspections of shroud EVT-1 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.
Shroud Support 4/94-R 13 UTA/T-1 Access hole cover VT/UT for circ and radial flaws. NRI.
EVT-1 Examined H8 and H9 for about 12" at 4 locations of r
shroud repair hardware attachment areas. NRI.
2/99-R 15 EVT-1 Per BWRVIP-38: Examined H8 and H9 between Jet Pumps 20 and 1 (312"-357"). NRI. Requirements for this inspection cycle are satisfied. NRI.
EVT-1 Welds on Access Hole Covers at 155" and 335". The D3 AHC's have not been repaired. NRI.
I R18 EVT-1 Examined H8 and H9 between Jet Pumps 10 and 11 (132'4 77"). NRI.
SLC I 11'06-R19 10/02 - R17 EVT-1, VT-3 PT VT-3 of accessible areas of H9 and EVT-I of 10% of H9 (between Jet Pumps 10 and 11). NRI.
PT of surface of Safe-end extension and safe-end to nozzle weld. NRI.
11/06-R19 PT PT of surface of Safe-end extension and safe-end to nozzle weld. NRI.
Jet Pump Assembly 4/94- R 13 VT- 1 Hold down beams, beam bolt keepers, lockplates 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.
Prior to R13, visually inspect 100% of upper areas of each Jet Pump including beam retainers every other outaae.
14 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden 3 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection ~ ~~
4/94-R 13 VT- 1 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.
4/97-R 14 EVT-1 All ten RS-1, 2, 3, 4 and RS-5. NRI.
2/99-R15 EVT-1 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.
VT- I Examined all twenty WD-1 locations. NRI.
10/02-R17 EVT-1 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.
03/03-0 3M09 VT- 1 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.
10/04- R18 VT- 1 Examined jet pump sensing line clamps on jet pumps 1, 2,3, 10, 11, 12, 13,&20.
EVT-1 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 0.010).
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 & -11 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
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden 3 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections 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 11/06 - R19 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 VT- 1 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.
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 13 UT Jet pump beams are UT examined each outage using technique capable of detecting cracking at throat and ears. Original group 1 beams.
4/94- R 14 UT Examined all beams. Two beams with indications replaced. Balance NRI.
2/99-R15 UT Examined all beams. NRI.
10/00-R16 UT Two beams with indications replaced with group 2 style beams. Balance NRI.
NA Replaced all 17 original beams with weld-less keeper group 3 beams.
10/04- R18 VT-3 Examined 17 group 3 beam bolt retainer mechanisms (weld-less keeper) to ensure all keepers were engaged.
NRI.
10/04 - R18 EVT-1 Examined 3 (not replaced in D3M09) welded keeper style beams. BB-1 and BB-2 on Jet Pumps 5 8 , and 13. NRI.
11/06-R19 NA Pre-emptively replaced ageing beams on JPs 5, 8 and 13 rather than UT examine.
LPCl Couplings NA Lower Plenum 4/97-R14 MVT-1 CRD Stub Tube, CRD H7. NRI.
4/97-R14 MVT-I ICH/RPV-1 and ICHGTACH-1, two inspected from cell H7. NRI.
10/00-R16 EVT-1 Per BWRVIP-47: examined CRGT-1,2 and 3 on D10.
NRI.
10/02-R17 EVT-1 and Examined 9 CRGT-1, 2 and 3 and FS/GT-ARPIN.NRI.
VT-3 This completes first 5% in 6 years.
16 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant: Dresden 3 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 10/04-R18 VT-3 Bottom Head Drain cleaning project created access for the following examinations:
- 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.
Steam Dryer 10/04- R18 Best effort - Examined exterior surfaces including outer hoods, VT- 1 historical repair areas, tie bars and attachment welds, four lifting assemblies, four hold down assemblies, 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.
VT-3 Examined interior and exterior skirt. Indications noted.
11/06 - R19 Best Effort Performed VT-1 inspection of outer hood welds on old VT-1 dryer where previous indications had been identified and repaired. NRI.
NA Installed new dryer.
Top Guide 4/94- R 13 VT- 1 Examined beam intersections in five cells in response to industry experience. NRI.
4/97- R 14 VT- 1 Per BWRVIP-26, baseline examined all four top guide alianment assemblies. NRI.
EVT-1 Examined rim to bottom plate weld at the four aligner assemblv locations. NRI.
10/00-R16 VT- 1 Examined 0 and 270 top guide alignment assemblies.
NRI.
EVT-1 Examined rim weld 11. NRI.
10/04- R18 VT- 1 Examined 909and 1802top guide alignment assemblies.
NRI.
EVT-1 Examined rim to bottom plate weld at 909 and 1809. NRI.
11/06 - R19 EVT-1 Examined rim weld from cell 03-34. NRI Vessel 10/02 - R17 UT Examined vertical welds SC1A, SC1C, SC2B, SC3A, SC3B, SC3C, SC3D, SC4A, SC4B, SC4C, SC4D. NRI.
10/04- R18 UT - Examined vertical welds SCI B, SC2A, SC2C, SC3A, 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.
VT-3 Inspected cladding in accordance with ASME Section XI.
NRI.
17 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Dresden 3 r
Components in BWRVIP 5IFrequency of Ins ection 11/06 - R19 Inspection Method Used VT-3 Summarizethe 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 Nuclear Instrument 4/94- R 13 VT- 1 Identified one cracked dry tube (24-37). Replaced.
Dry-tubes Examined every other outage to date. Per Reutter-Stokes recommendations, have not reached manufacturers service life.
11/06-R19 VT- 1 Examined two SRM and four IRM dry tubes from 3 sides to meet SIL 409. NRI Steam Separator 10/04- R18 VT- 1 Examined shroud head bolt pin and window condition. RI identified minor wear that was evaluated as-is for 1 continued operation.
Examined eight standpipe to shroud head welds and eight gusset to ring welds, NRI.
18 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: LaSalle 1 Components in BWRVIP Inspection Summarize the Following Information:
Scope I Inspection Results, Repairs, Replacements, Reinspections Core Spray Piping LlR11 (2006) UT Re-sized flaws on BP4a, DP5, and DP6. Flaw evaluation performed and welds scheduled for examination in L1R12.
LlR11 (2006) EVT-1 Visual examination of those core spray piping welds for which UT techniaue is not demonstrated. 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 L1R l l .
L1R10 (2004) EVT-1 Visual examination of those core spray piping welds for which UT technique is not demonstrated. No indications.
L1R09 (2002) EVT-1 Visual examination of those core spray piping welds for which 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 examination in L1R10.
L1R08 (1999) EVT-1 Visual examination of those core spray piping welds for which UT technique is not demonstrated. No indications.
Visual examination of 50% of the core spray sparger welds.
No indications.
Core Spray Sparger LlR11 (2006) EVT-1 Visual examination of 50% of the core spray sparger welds.
No indications.
L1R10 (2004) EVT-1 Visual examination of 50% of the core spray sparger welds.
No indications.
L1R09 (2002) EVT-1 Visual examination of 50% of the core spray sparger welds.
L1R08 (1999) I EVT-l No indications.
Visual examination of 50% of the core spray sparger welds.
No indications.
Attachment Welds LlR11 (2006) EVT-1NT- (See jet pump and core spray sections for those attachment 1IVT-3 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.
EVT-1 Visual examination of the steam dryer support lug at 185" where wear was observed last outaae. No chanae in the wear.
LlR10 (2004) I EVT-1NT- (See jet pump and core spray sections for those attachment 1NT-3 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.
Core Shroud LlR11 (2006) UT UT of welds H3, H4, H6, and H8 (LaSalle-specificnumbering).
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.
L1R07 (1996) UT 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
REACTORINTERNALS INSPECT~ON HISTORY Plant: LaSalle 1 Date or Components in BWRVIP Scope Shroud Support Frequencyof Inspection LlR11 (2006)
I Inspection Method Used EVT-1 Summarize the Following Information:
Inspection Results, Repairs, Replacements,Reinspectiom Visual examination of 8 shroud support plate gusset welds.
No indications.
LlR11 (2006) VT-3 Visual exam of 100% of the accessible portion of the top of H9 and both access hole covers. No indications.
L1R10 (2004) EVT-1 Visual examination of 11 shroud support plate gusset welds.
No indications.
L1R10 (2004) EVT-1 Visual examination of approximately 20% of H8a. No indications.
L1R09 (2002) UT Ultrasonic examination of 100% of the H9 weld from the vessel outside diameter. No indications.
L1R08 (1999) EVT-1 Visual examination of 6 shroud support plate gusset welds.
No indications.
L1R08 (1999) EVT-1 Visual examination of approximately 2% of H8a, 23% of the too of H9. and both access hole covers. No indications.
L1R07 (1996) VT- 1 Visual examination of both access hole covers. No indications.
SLC LlR11 (2006) VT-2 Visual examination during the system leak test. No indications.
L1R10 (2004) VT-2 Visual examination during the system leak test. No indications.
PT Surface examination. No indications.
L1R09 (2002) VT-2 Visual examination during the system leak test. No indications.
L1R08 (1999) VT-2 Visual examination during the system leak test. No indications.
Jet Pump Assembly L l R l l (2006) The hold-down beams on jet pumps 5,6,9 and 10 were proactively replaced with low stress beams.
EVT-1 Visual examination of RB-2 welds on 6 oumos. NRI.
Installation of riser brace clamps on the risers for jet pumps 5/6 and 9/10 to reDair the RS-9 flaws identified in L1R10.
The slip joint clamps on jet pumps 5, 6, 9 and 10 were upgraded to a new style.
VT-3 Visual examination of the 16 old style slip joint clamps installed in the previous outage. No indications.
EVT-1 Visual examination of RB-1 on 12 jet pumps and RB-2 on 6 jet pumps. No indications.
VT- 1 Visual examination of WD-1 on 20 jet pumps. No change in the wear identified in L1R10.
EVT-1 Visual examination of RS-3 on 5 pumps. No indications.
L1R10 (2004) UT BB-1, BB-2, and BB-3 areas of all 20 hold-down beams.
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.
EVT-1 Visual examination of RS-3 on 5 risers. No indications.
VT-3 Best effort examination of the inaccessible welds AD-1, AD-2, and DF-3 on all 20 iet oumos. No indications.
EVT-1 Visual examination of DC-3 on 8 pumps. No indications.
EVT-1 Visual examination of DF-1 on 11 Jet Pumps. No indications.
EVT-1 Visual examinations of DF-2 on 2 Jet Pumps. No indications.
EVT-1 Visual examination of RS-1 welds on all 10 risers. No indications.
EVT-1 Visual examination of RS-2 welds on 5 risers. No indications.
EVT-1 Visual examination of RS-3 on 5 risers. No indications.
20 of 76
REACTORINTERNALS INSPECTION HISTORY Plant:
Date or Components in BWRVIP Scope Frequencyof Inspection Inspection Method Used EVT-1 UI Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections Visual examination of RS-6 and RS-7 on 10 jet pumps. No Jet Pump Assembly indications.
continued EVT-1 Visual examination of RS-8 on all 20 jet pumps. No indications.
EVT-1 Visual examination of RS-9 on all 20 jet pumps. Indications found on 3 jet pumps (5, 6 and 9). Flaw evaluation performed and required the installation of a repair in L1R l l .
EVT-1 Visual examination of IN-1 on 11 iet w m m . No indications.
EVT-1 Visual examination of IN-2 on 11 jet pumps. No indications.
EVT-1 Visual examination of MX-2 on 11 jet pumps. No indications.
EVT-1 Visual examination of RB-1 on 19 of the jet pumps. No indications.
EVT-1 Visual examination of RB-2 on 18 jet pumps. No indications.
VT- 1 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.
VT- 1 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.
EVT-1 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.
L1R09 (2002) VT-3 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.
VT- 1 Visual examination of 2 auxiliary wedges installed in previous outages. No indications.
L1R08 (1999) UT UT of 10 jet pump beams at the BB-1 and BB-2 locations. No indications.
EVT-1 I Visual examination of DF-1 on 10 Jet Pumps. No indications.
EVT-1 Visual examinations of DF-2 on 10 Jet Pumps. No indications.
EVT-1 Visual examination of RS-1 welds on 5 risers. No indications.
EVT-1 Visual examination of RS-2 welds on 5 risers. No indications.
EVT-1 Visual examination of RS-3 on 5 risers. No indications.
EVT-1 Visual examination of RS-6 and RS-7 on 10 jet pumps. No indications.
EVT-1 Visual examination of RS-8 on 10 jet pumps. No indications.
EVT-1 Visual examination of RS-9 on 10 jet pumps. No indications.
EVT-1 I Visual examination of IN-1 on 10 iet w m m . No indications.
EVT-1 Visual examination of IN-2 on 10 jet pumps. No indications.
EVT-1 Visual examination of MX-2 on 10 jet pumps. No indications.
EVT-1 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
REACTORINTERNALS INSPECTION HISTORY Plant:
Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 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 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.
VT- 1 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 another cyc Ie.
VT-3 Visual examination of WD-1 on 2 jet pumps with wear L1R07 (1996) observed on jet pump 9. Flaw evaluation determined acceptable for one cycle.
UT UT of all 20 jet pump holddown beams at BB-1; one indication on #9 beam; beam replaced.
VT-1 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.
LPCl Couplings L1R10 (2004) EVT-WT- Visual examination of four locations on all three couplings. No 3/VT-1 indications.
L1R08 (1999) EVT-l/VT- Visual examination of four locations on all three couplings. No 3/VT-1 indications.
Lower Plenum LlR11 (2006) VT-3 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.
L1R10 (2004) VT-3 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.
L1R09 (2002) VT-3/EVT-1 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.
L1R08 (1999) 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
REACTORINTERNALS INSPECTION HISTORY Plant: LaSalle 1 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Steam Dryer EVT-1 Re-inspection of lower guide bracket at 180" and hood A plate L1R11 (2006) 5 where previous indications existed and were stop drilled. No new indications.
VT- 1 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.
VT-3 Visual exams on the end panels and welds; one indication on L1RIO (2004 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 (10 previous indications unchanged), 100% of tie bars VT- 1 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 Top Guide L1R10 (2004) VT-3 Visual examination of two c-clamps; no indications.
L1R08 (1999) VT-3 Visual examination of four c-clamps; no indications.
Vessel L1R10 (2004) 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.
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.
L1R09 (2002) 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.
Inspection of the general condition of the cladding at the Steam Dam elevation, 360" around the RPV interior. NRI.
23 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: LaSalle 2 Date or Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Core Spray Piping L 2 R l l (2007) EVT-1 Visual examinations of core spray piping welds for which the UT is not demonstrated. No indications (NRI).
EVT-1 8 piping brackets; NRI.
L2R10 (2005) UT 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.
EVT-1 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.
L2R09 (2003) EVT-1 Visual examinations of those core spray piping welds for which the UT technique is not demonstrated. No indications.
L2R08 (2000) UT UT for those welds for which the UT tool is qualified.
EVT-1 . 8 piping brackets; NRI.
Core Spray Sparger L2R11 (2007) VT- 1 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.
EVT-1 SlA, S2A (Left and right), S4A, SlB, S2B (Left and right),
S4B, S1C, S2C (Left and right), S4C, S1 D, S2D (Left and right), S4D. NRI.
VT- 1 6 sparger brackets; NRI.
L2R10 (2005) VT- 1 S3A-a and S3A-d from 268 to 008" and S3D-a and S3D-b from 352 to 268; NRI 6 sparger brackets; NRI.
L2R09 (2003) EVT-1 Visual inspection of half of the core spray sparger welds. NRI.
6 sparger brackets; NRI.
L2R08 (2000) VT- 1 100% of all sparger welds. NRI.
EVT-1 12 sparger brackets. NRI.
Attachment Welds L2R11 (2007) (See jet pump and core spray sections of this report.)
L2R10 (2005) EVT-1 Steam dryer attachment welds, four locations, NRI VT-3 Upper bracket attachment welds for surveillance baskets at three locations, NRI.
VT- 1 Lower bracket attachment welds for surveillance baskets at three locations. Basket disengaged at 120" location and accepted for one cycle. All others NRI.
EVT-1 All feedwater sparger attachment welds; NRI.
L2R09 (2003) EVT-1 All feedwater sparger attachment welds; NRI.
L2R08 (2000) VT- 1 Steam dryer attachment welds, four locations, NRI VT-3 Guide Rod attachments at 0" and 180; NRI.
Upper surveillance capsule brackets at three locations: NRI.
VT- 1 Lower surveillance capsule brackets at three locations; NRI.
Coreshroud L2R11 (2007) VT-3 Surfaces of the shroud for ASME Section XI. NRI.
I (Note: LaSalle has two L2R10 (2005)
L2R07 (1996)
UT UT UT of welds H3, H5, H6, and H8 All welds are NRI.
UT of H5, H6, and H8. NRI.
beltline horizontal welds L2R06 (1995) UT UT of H3, H4, H5, H6, and H8. NRI.
and thereby unique desianation).
24 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: LaSalle 2
$' ':F r Of lnsoection
)I Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections L2R11 (2007) 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 ASME Section XI. NRI.
Top of H9 weld (accessible locations) for ASME Section XI.
NRI L2R10 (2005) VT- 1 Access Hole Covers at 0 and 180"--NRI 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.
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.
EVT-1 H8a weld (BWRVIP weld H8) for >1O0/&-NRI L2R09 (2003) UT UT of 100% of H9 from the RPV OD. NRI.
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.
Inspection of the general condition of the cladding at the steam dam elevation. 360" around the RPV interior. NRI.
L2R11 (2007) VT-3 C-clamp at 0". NRI Accessible portions of the top guide for ASME Section XI. NRI L2R10 (2005) VT-3 C-clam~s at 4 locations--NR I L2R11 (2007) VT-2 I UT Visual inspection of the partial penetration weld to the bottom head durina the Section XI svstem leak test. NRI.
UT of the partial penetration weld and heat affected zone.
I NRI.
L2R10 (2005) VT-2 Visual inspection of the partial penetration weld to the bottom head during the Section XI system leak test. NRI.
L2R09 (2003) VT-2 Visual inspection of the partial penetration weld to the bottom head during the Section XI system leak test. NRI.
PT Surface examination. NRI.
L2R08 (2000) VT-2 Visual inspection of the partial penetration weld to the bottom head during the Section XI system leak test. NRI.
L2R11 (2007) VT-1 WD-I wedges on all 20 pumps; 7 wedges/rods showed minor wear; accepted-as-is. Auxiliary wedges installed at four locations on 3 pumps to compensate for observed gaps.
VT-3 Examination of ratchet teeth engagement on 13 jet pump hold down beams due to fitup issues in the previous outage. NRI L2R10 (2005) VT-1 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).
I NRI.
L2R09 (2003) 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.
VT- 1 WD-1 on 3 pumps; NRI.
Installed 3 aux. Wedges to ensure three point contact for three wmm.
25 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: LaSalle 2
/I Date or Inspection Summarize the Following Information:
Frequency of Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection L2R08 (2000) UT UT exam of 10 beams at the BB-1 and BB-2 locations. NRI.
VT-3 Exam of WD-1 on all 20 pumps; NRI. Exam of all set screw to belly band contact points; installed 7 auxiliary wedges to maintain three point contact; all others NRI.
L 2 R l l (2007) EVT-1 AD-2 on 6 pumps; NRI.
DF-1 on 10 w m m : NRI.
L2R10 (2005) EVT-1 AD-2 on 4 pumps; NRI.
DC-3 on 10 wmos: NRI.
DF-2 on 10 pumps; NRI.
DF-3 on 10 pumps; NRI.
L2R09 (2003) EVT-1 AD-2 on 4 Dumm: NRI.
DF-1 on 4 pumps; NRI.
DF-2 on 4 pumps; NRI.
DF-3 on 4 c)umtx: NRI.
IN-1 on 10 pumps; NRI.
IN-2 on 10 pumps; NRI.
L2R08 (2000) EVT-1 AD-2 on 6 mmw)s:NRI.
DF-1 on 6 pumps; NRI.
DF-2 on 6 w m m : NRI.
UT DF-3 on 6 pumps; NRI.
L 2 R l l (2007) Re-sized flaw on RS-1c on 19/20; no change in length.
EVT-1 RS-1 on 2 risers: NRI.
RB-1 on 12 jet pumps; NRI.
L2R10 (2005) EVT-1 Examined strain relief welds on all 10 risers. NRI Re-sized flaw on RS-1c on 19/20: no chanae in lenath.
RS-2 on 3 risers; NRI.
RS-3 on 5 risers; NRI.
RS-6/7 on 10 iet w m m : 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.
L2R09 (2003) 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 (1996).
MX-2 on 4 pumps; NRI.
RS-6/7 on ten pumps; NRI.
L2R08 (2000) UT UT exam of MX-2 on 6 tmmtx: NRI.
L2R07 (1996) VT-1 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.
L 2 R l l (2007) 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 other welds NRI.
L2R10 (2005) VT- 1 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 26 of 76
REACTOR INTERNALS INSPECTION HISTORY Plant: LaSalle 2 Components in BWRVIP Inspection Summarizethe Following Information:
Scope 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.
Upper strap on lifting assembly at 215" found broken and was removed. All other welds NRI.
Vessel L2R10 (2005) 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.
L2R09 (2003) VT-3 Inspection of the general condition of the cladding at the Steam Dam elevation, 360" around the RPV interior. NRI.
Lower Plenum L2R10 (2005) VT-1 Examined all areas below the core plate made accessible by disassembly of 20 jet pumps. Areas examined included CRD/ST-1, ST/RPV-1, H8a, H9, H10, H I 1, H12, ICH/RPV-1, and bottom head cladding. NRI for all twenty locations.
L2R09 (2003) VT-3 / EVT-1 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 locations, and CRGT-3 at 21 locations. No indications.
L2R08 (2000) VT-3 Visual examination of the fuel support guide tube pins (FS/GT-ARPIN-1) at 14 locations, CRGT-1 at 15 locations. No indications.
I Other L2R11 (2007) VT-3 Removal of the surveillance capsule basket from 120" due to a broken spring.
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Limerick Generating Station, Unit 1 Spring 2006 Update Components in BWRVIP Inspection Method Date of Inspection Inspection Results, Repairs, Replacements, Reinspections Scope Used Core Shroud 1994 VT-3 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.
1996 UT 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.
2006 UT Category " B welds were re-examined by UT. Due to the identification of cracking, the scope was expanded and the shroud reclassifiedas 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.
Shroud Support 1987,1990, & VT-3 VT-3 examination of H-8 and H-9 welds from 1994 annulus. No indications identified.
VT-3 examination of both access hole covers and welds. No indications identified.
1998 VT-3 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.
Core Spray Piping 1987 to 1996 VT- 1 Enhanced VT-1 (1 mil resolution) examination performed every refueling outage on piping and welds per IEB 80-13. No indications identified.
UT & CSVT-1 UT baseline and visual of piping.
No indications identified.
2002 UT & EVT-1 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-demonstratedwelds P4dB, P4dC, P4dD, P8aA, P8aB, P8aC, and P8aD.
No indications identified.
Page 28 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 1 Spring 2006 Update Components in BWRVIP Inspection Method Date of inspection inspection Results, Repairs, Replacements, Reinspections Scope Used 2004 EVT-1 EVT-1 of previous P3bA indication. No change in identified length.
EVT-1 of un-demonstratedwelds P4dA, P8aA, P8aB, P8aC, and P8aD. No indications identified.
2006 UT & EVT-1 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.
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.
Core Spray Piping 1987 to 1996 VT- 1 VT-1 examination performed every refueling outage Brackets on piping and welds per IEB 80-13. No indications identified.
1998 CSVT-1 Examined all eight brackets (PBl through PB8).
No indications identified.
2000 EVT-1 Examined brackets PB1 and PB2.
No indications identified.
2002 EVT-1 Examined brackets PB3 and PB4.
No indications identified.
2004 EVT-1 Examined brackets PB5 and PB6.
No indications identified.
2006 EVT-1 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.
Core Spray Sparger 1987 to 1996 VT-1 Enhanced VT-1 (1 mil resolution) examination performed every refueling outage on piping and welds per IEB 80-13. No indications identified.
1998 EVT-1 & CSVT-1 EVT-l/CSVT-l all spargers.
No indications identified.
2000 EVT-1 & Examined A and B sparger welds S1, S2a,b, VT-I S3a,b and S4a,b. No indications identified.
2002 EVT-1 & VT-1 of S3 on B sparger and EVT-1 of S1,2 and 4 VT- 1 on C and D soaraers. No indications identified.
2004 EVT-1 & VT-1 of S3 on C sparger and EVT-1 of S1,2 and 4 VT- 1 on A and B spargers. No indications identified.
2006 EVT-1 VT-1 of S3 on D sparger and EVT-1 of S1,2 and 4 on C and D spargers. No indications identified.
Core Spray Sparger 1987 to 1996 VT-1 VT-1 examination performed every refueling outage Brackets on piping and welds per IEB 80-13. No indications identified.
1998 CSVT-1 Examined all brackets (SB1 through SB12). No indications identified.
2000 VT- 1 Examined brackets SB1, SB2, SB3, SB10, SB11 and SB12. No indications identified.
2002 VT- 1 Examined brackets SB4, SB5, SB6, SB7, SB8, and SB9. No indications identified.
2004 VT- 1 Examined brackets SB1, SB2, SB3, SB10, SB11, and SB12. No indications identified.
Page 29 of ?6
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 1 Spring 2006 Update Components in BWRVlP Inspection Method Date of Inspection inspection Results, Repairs, Replacements, Reinspections Used 2006 VT- 1 Examined brackets SB4, SB5, SB6, SB7, SB8, and SB9. SB8 was found slightly deformed, no other indications identified.
Top Guide (Rim, etc.) 1987 VT-3 VT-3 examination of accessible welds and surfaces.
No indications identified.
1990 VT-3 VT-3 examination of accessible welds and surfaces.
Also, VT-3 examination of 32 wedges, bolts, and keepers. No indications identified.
1994 VT-1 & VT-1 examination of accessible welds and surfaces VT-3 at core locations 14-31, 22-23, 22-39, 30-15, 30-47, 38-23, 38-39, and 46-31. Also, VT-3 examination of 32 wedges, bolts, and keepers.
No indications identified.
1998 VT-1 & VT-1 of grids 30-31 and 34-35. Also, VT-3 surfaces VT-3 and welds (0"-180") including wedges, bolts and keepers. No indications identified.
2000 VT-3 C-Clamps at O",go", 180" and 270". No indications identified.
2004 VT-3 C-Clamps at O", go", 180" and 270". No indications identified.
Core Plate (Rim, etc.) 1998 VT-3 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.
1987, 1990,81 VT-3 VT-3 examination of all jet pump components 1994 No indications identified.
1998 MVT-1 Examined welds RB-la, b, c, d, RB-2a, b, c, d, RS-1, RS-2, RS-3 RS-6/7, RS-8/9, IN-4, MX-2, WD-I, 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.
2000 EVT-I& E m - 1 examined RB-la, b, c, d and RB-2c on VT-1 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.
VT-1 examined WD-1 for JP11, JP12, JP13, JP14 and JP15. No indications identified.
2002 EVT-1 & EVT-1 examined welds RB-la, b, c, d and RB-2a, b, VT- 1 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
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 1 Spring 2006 Update Components in BWRViP inspection Method Date of Inspection inspection Results, Repairs, Replacements, Reinspections ScoDe Used 2004 EVT-1, & EVT-1 examined RS-3 and RS-6/7 for JP#1/2, VT- 1 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.
2006 EVT-1, EVT-1 examined RS-1 and RS-2 on JP3/4, JP5/6, VT-1, & JP7/8, JP9/10, and JP19/20; RS-3 on JP11/12, VT-3 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.
Jet Pump Beams 1994 UT UT baseline of replacement hold-down beams.
No indications identified.
2004 UT 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
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 1 Spring 2006 Update Components in BWRVIP Inspection Method Date of Inspection Inspection Results, Repairs, Replacements, Reinspections Scope Used 2006 VT-3 VT-3 examined BB-1, BB-2, and BB-3 on replacement beam for JP4. No indications identified.
Jet Pumr, Diffuser See Jet Pump Assembly CRD Guide Tube 1990 VT-3 VT-3 examination of replacement CRDs at core locations 10-23, 14-19, 14-23, 14-31, 18-43, 18-55, 22-11, 22-39, 22-47, 26-03, 26-11, 26-27, 30-23, 30-3530-55,34-23, 34-37, 34-31, 34-39, 38-07, 38-23,38-31, 38-35, 38-39,42-19, 46-1 1, 46-39, and 54-31.
No indications identified.
1992 VT-3 VT-3 examination of control rod assembly at core locations 30-11,22-55, 54-23, 38-07, 38-55, and 22-07. No indications identified.
1994 VT-3 VT-3 examination of replacement CRDs at core locations 02-43, 10-19, 10-39, 14-39, 18-23, 18-39, 20-35,26-27, 26-31, 30-47, 34-31, 34-47, 38-19, 38-35, 38-41, 42-15,42-55, 50-43, 54-19, and 58-31.
No indications identified.
1998 VT-3 VT-3 of CRDs at core loc. 54-49,48-55,50-51,42-I I I 59, 30-31, 30-34, 34-35,26-31, 34-31, 26-27, 30-27, and 34-27. No indications identified.
2000 EVT-l& Examined CRGT-1,2,3 and FS/GT-ARPIN-1 at core I I VT-3 I locations 30-55, 38-31 and 38-39.
No indications identified.
2004 EVT-1 & Examined CRGT-1,2,3 and FS/GT-ARPIN-1 at 10-I I VT-3 I 39, 18-27, 18-35, 26-43, 30-15, 30-47, 34-15, 34-19, 34-43, and 46-11. No indications identified.
CRD Stub Tube 1992 VT-2 VT-2 examination from vessel exterior on 100% of penetrations once per interval, in excess of Section XI. No indications identified.
1996 VT-2 VT-2 examination from vessel exterior on 100% of penetrations. No indications identified.
1998 VT-3 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.
2000 VT-2 VT-2 examination from vessel exterior on 100% of Denetrations. No indications identified.
I2006 I VT-2 I VT-2 examination from vessel exterior on 100% of penetrations. No indications identified.
In-Core Housing 1992 VT-2 , VT-2 examination from vessel exterior on 100% of I I I penetrations once per interval, in excess of Section XI. No indications identified.
1996 VT-2 VT-2 examination from vessel exterior on 100% of penetrations. No indications identified.
1998 VT-3 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.
2006 VT-2 VT-2 examination from vessel exterior on 100% of penetrations. No indications identified.
Page 32 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 1 Spring 2006 Update Date of Inspection US@d Method Inspection 1 Inspection Results, Repairs, Replacements, Reinspections 1989 VT-3 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, 48-13, and 16-13 (IRM's). No indications identified.
1992 VT-1 VT-1 examination of 4 dry tubes.
No indications identified.
1994 VT-1 VT-1 examination of dry tubes at core locations: 24-37 (IRM), and 40-21 and 38-23 (SRM).
No indications identified.
2004 VT- 1 Examined SRMs at 16-45 and 40-21 and IRMs at 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.
2006 N/A Replaced dry tubes SRMs 16-21 and 40-45 and IRMs 24-29,24-37,48-13, and 48-53. Plan to replace second half in 2008.
1990 VT-3 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.
1996 VT-2 VT-2 examination from vessel exterior on 100% of penetrations once per interval, in excess of Section XI. No indications identified.
2006 VT-2 VT-2 examination from vessel exterior once per interval. No indications identified.
1987 to 1996 VT-1 & VT-3 VT-1 or VT-3 performed on all ID bracket welds once per interval per Section XI.
No indications identified.
1998 VT-1 & VT-3 Examinations include brackets on the steam dryer-4, jet pump riser-I0, core spray-8, surveillance sample-2, and guide rod-I. No indications identified.
2000 VT-1 & VT-3 VT-1 examination of two Core Spray Piping Brackets at 15 degrees and 85.5 degrees. VT-3 examination of one Guide Rod Bracket at 180 degrees. No indications identified.
2002 EVT-1, VT-1 & VT- Jet Pump support pads on JP15/16 and JP17/18, 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".
No indications identified.
2004 EVT-1, VT-1 & VT- Jet Pump support pads on JP 1/2, 3/4, 7/8 and 3 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.
Page 33 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 1 Spring 2006 Update Components in BWRViP inspection Method Date of inspection Inspection Results, Repairs, Replacements, Reinspections Scope Used 2006 EVT-1, VT-1 & VT- Jet Pump support pads on JP 5/6,9/10,11/12 and 3 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.
LPCl Coupling 1987, 1990, & VT-3 VT-3 examination of all 4 couplings. No indications 1994 identified.
1998 MVT-1 All of N-17A and B. No indications identified.
2000 EVT-1, VT-I , & VT- All of N-I7C and D. No indications identified.
3 2002 EVT-1 &VT-3 N17A, locations 45-3b, 6a, 6b, 6c and 6d. No indications identified.
2004 EVT-1, VT-1, & N17A, locations 45-8a, 8b, 8c, 8d and 12 and all of VT-3 N17B. No indications identified.
Steam Dryer 1998 VT-I & VT-3 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.
2000 VT- 1 VT-1 examined the steam dryer drain channel welds. No indications identified.
2002 VT-1 & VT-3 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.
2004 VT-1 & VT-3 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.
2006 n-1 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 l a - 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
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2
~~
- Spring 2007 Update Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections InsDection Core Shroud 1999 (2R05) UT 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.
2005 (2R08) UT 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.
EVT-1 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).
2007 (2R09) EVT-1 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.
Shroud Support / 1991 (2R01) VT-3 VT-3 examination of accessible portions of H-8 and H-9 welds Access Hole Covers from annulus. VT-3 examination of both access hole covers and welds. No indications identified.
1993 (2R02) VT-3 VT-3 examination of shroud support leg welds at Azimuth 300 deg through disassembled jet pump #18. No indications identified.
1995 (2R03) VT-3 VT-3 examination of both access hole covers and welds. No indications identified.
1999 (2R05) EVT-1 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 VT-3 examination of both access hole covers and welds. No indications identified.
2003 (2R07) UT UT of 10% of weld H-9 length. No indications identified.
VT-3 VT-3 examination of both access hole covers and welds. No indications identified.
2005 (2R08) EVT-1 EVT-1 examination of 10% of weld H-8 length. No indications identified.
Page 35 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update I ate or Components in BWRVIP Inspection Summarize the Following Information:
Fret uency of Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection 2007 (2R09) VT- 1 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 Best effort VT-1 / VT-3 of the lower side of H-8 and H-9, and VT-1 /VT-3 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.
Core Spray Piping 1991 (2R01)- VT- 1 Enhanced VT-1 (1 mil resolution) examination performed 1995 (2R03) every refueling outage on piping and welds per IEB 80-13. No indications identified.
1997 (2R04) EVT-1 EVT-1 (1/2 mil resolution) examination of welds per IEB 80-13 and BWRVIP-18 baseline. No indications identified.
1999 (2R05) UT UT examination of welds (P1 thru P8) per BWRVIP-18 baseline UT. No indications identified.
EVT-1 EVT-1 supplemental examination on P4dA, P4dB, P4dC, P4dD, P8aA, P8aB, P8aC, and P8aD. No indications identified.
2001 (2R06) EVT-1 EVT-1 of P4dA, P8aA, P8aB, P8aC, and P8aD. No indications 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.
2007 (2R09) UT UT examination of P1, P2, P3a, P3b, P4b, P5, P6, P7, and P8b welds was performed. No indications were identified.
EVT-1 EVT-1 of the far side of P I , P2, P3a, P3b, P4b, and P8b welds, as well as an EVT-1 examination of P4dD and P8a welds was performed.
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.
Core Spray Piping 1999 (2R05) EVT-1 EVT-1 of 2 piping support brackets PB-7 & PB-8. No Brackets indications identified.
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.
2007 (2R09) EVT-1 EVT-1 of 2 piping support brackets PB-7 and PB-8. No indications identified.
Core Spray Sparger 1991 (2R01) - VT- 1 Enhanced VT-1 (1 mil resolution) examination performed 1995 (2R03) every refueling outage on piping and welds per IEB 80-13. No indications identified.
1997 (2R04) EVT-1 EVT-1 (1/2 mil resolution) examination of welds per IEB 80-13 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
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection VT-1 VT-1 examination of welds S3aXXA, S3bXXA, and S3dXXA on nozzles 1A thru 65A. No indications identified.
Core Spray Sparger 2001 (2R06) EVT-1 EVT-1 examination of welds S l C, S1D, S2aC, S2bC, S2aD, (continued) 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.
2003 (2R07) EVT-1 EVT-1 examination of welds SlA, SlB, S2aA, S2bA, S2aB, S2bB S4aA, S4bA, S4aB, and S4bB per BWRVIP-18. No indications identified.
VT- 1 VT-1 examination of welds S3aXXC, S3bXXC, and S3dXXC on nozzles 1C thru 65C. No indications identified.
2005 (2R08) EVT-1 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 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.
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.
Core Spray Sparger 1999 (2R05) VT- 1 VT-1 examination of sparger brackets SB1, SB2, and SB3. No Brackets indications identified.
2001 (2R06) VT- 1 VT-1 examination of sparger brackets SB4 through SBl2. No indications identified.
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.
2007 (2R09) VT- 1 VT-1 examination of sparger brackets SBl, SB2, SB3, SB4, SB5, SB6, SB8, SB10, SB11, and SB12 was performed.
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-inspectedwith no change in condition from 2R08.
Top Guide (Rim, etc.) 1991 (2R01) VT-3 VT-3 examination of accessible welds and surfaces. No indications identified.
1993 (2R02) VT-3 VT-3 examination of accessible welds and surfaces. No indications identified.
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 VT-3 examination of 32 wedges, bolts, and keepers. No indications identified.
1999 (2R05) VT-3 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.
2005 (2R08) VT-3 VT-3 examination of all four Top Guide C-Clamps. No indications identified.
Page 37 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: -
Limerick Generating Station, Unit 2 Spring 2007 Update Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections 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.
1999 (2R05) VT-3 VT-3 examination of accessible welds & surfaces at core plate I location 30-31. No indications identified.
N/A, SLC connects to Core Spray System.
(See summary of Instrument Penetrations)
Jet Pump Assembly 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 indications identified.
1995 (2R03) VT-3 VT-3 examination of all 20 Jet Pump assemblies. No indications ident ified.
1999 (2R05) VT-3 VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
UT UT examination of all 20 Jet Pump hold down beams per BWRVIP-41. No indications identified.
EVT-I EVT-I examination of welds RS-I , RS-2 and RS-3 per BWRVIP-41 on Jet Pumps 11 - 20. No indications identified.
2001 (2R06) EVT-1 EVT-1 examination of RB-1 and RB-2 welds on Jet Pumps 1 -
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.
2003 (2R07) EVT-1 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 1I - 14.
EVT-1 examination of IN-4 and MX-2 on Jet Pumps 1, 5, 6, and 11 - 14. No indications identified.
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
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Method Used Inspection Results, Repairs, Replacements, Reinspections
~
InsDection 2005 (2R08) VT- 1 A m-Iexamination of 8 wedges (WD-1 on Jet Pumps 2,6 -
Jet Pump Assembly (Continued) 10, 16, and 18) in the original scope identified significant (Continued) 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.
2007 (2R09) EVT-1 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, 11/12, 13/14, 17/18, and 19/20.
EVT-1 inspection was performed on RB-2 welds on JP 9/10, I
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.
2007 (2R09) VT- 1 A VT-1 examination of all 20 main wedges (WD-1) was (Continued) 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
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection VT-3 A VT-3 examination was performed on all previously install Auxiliary Wedges (AW) and Slip Joint Clamps (SJC).
Jet Pump Assembly (Continued) 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.
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 indications identified.
1995 (2R03) VT- 3 VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
1999 (2R05) VT-3 VT-3 examination of all 20 Jet Pump assemblies. No indications identified.
2001 (2R06) EVT-1 EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on Jet Pumps 2 - 4. No indications identified.
2003 (2R07) EVT-1 EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on Jet Pumps 1, 5, 6, and 11 - 14. No indications identified.
2005 (2R08) EVT-1 EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on Jet PumDs 7 and 8. No indications identified.
2007 (2R09) EVT-1 EVT-1 examination of DF-1, DF-2, AD-1, and AD-2 welds on JP 9, 10, and 15. No indications identified.
1991 (2R01) VT-3 VT-3 examination of control rod assemblies at core positions 22-14 and 14-31. No indications identified.
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 06-19, 10-27, 10-47, 14-39, 18-03, 18-15, 18-55,22-35, 22-39, 30-51, 34-47, 38-15, 38-27, 38-39, 42-43, 46-39, 46-43, 50-15, and 54-35. No indications identified.
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.
2003 (2R07) EVT-1/VT-3 CRD guide tube welds were examined at core locations 06-19, 06-43, 18-43, 22-31, 30-23, 30-39, 38-31, 42-19, 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 I identified.
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
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection tub 1ube 1993 (2R02) VT-3 VT-3 examination of stub tube to vessel weld and stub tube to housing weld at azimuth 300 deg. No indications identified.
1999 (2R05) VT-3 VT-3 examination at core location 30-31, 30-35, 26-31 & 34-
- 31. No indications identified.
2007 (2R09) Best effort Best effort VT-1 / VT-3 of stub tube to vessel welds and stub VT-1 /VT-3 tube to housing welds at core locations 02-39, 02-43, 06-47, 10-11, 14-07, 14-11, 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.
In-Core Housing 1999 (2R05) VT-3 VT-3 examination of housings, guide tubes, stabilizers &
housing to RPV welds at core locations 24-29 & 32-29. No indications identified.
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.
~
1999 (2R05) VT- 1 VT-1 examination of accessible portions of upper 2 feet of dry tube at core locations 24-29 & 32-29. No indications identified.
2005 (2R08) VT- 1 VT-1 examination of accessible portions of upper 2 feet of dry tube at core locations 16-13, 16-21, 16-45, 24-29, 40-21, and 48-13. 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).
Instrument Penetrations 1991 (2R01) VT-3 VT-3 examination of interior attachment of instrument nozzles N I I A , NUB, and N12A through N12D. No indications identified.
PT 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.
1999 (2R05) UT/PT UT & PT examination of jet pump instrument nozzle to safe end N8A & N8B. No indications identified.
1991 (2R01) VT- 1NT-3 VT-1 or VT-3 performed on all ID bracket welds once every other outaae Per Section XI. No indications identified.
1993 (2R02) VT- 1NT-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.
1997 (2R04) 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.
1999 (2R05) VT-3 VT-3 examination of feedwater sparger brackets (5, 55, 65, 115, 125, 175, 185, 235, 245, 295, 305 & 355 DEG), including bracket weld to RPV. No indications identified.
2001 (2R06) EVT-1 EVT-1 examination of feedwater sparger brackets at 5 degrees and 175 degrees, and core spray sparger brackets at I
274.5 degrees and 345 degrees. No indications identified.
2003 (2R07) EVT-1 EVT-1 examination of feedwater sparger brackets at 65 degrees and 115 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, 11/12, and 13/14. No indications identified.
VT- 1 VT-1 examination of the 30 degree surveillance sample holder attachment to vessel weld. No indications identified.
Page 41 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update Date or Components in BWRVIP inspection Summarize the Following information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements, Reinspections lnsnection 2005 (2R08) EVT-1 EVT-1 examination of feedwater sparger brackets at 55 Vessel ID Brackets degrees and 125 degrees; core spray sparger brackets at 15 (Continued) 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.
VT-3 VT-3 examination of guide rod bracket attachment welds at 0 degrees and 180 degrees. No indications identified.
2007 (2R09) EVT-1 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 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.
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.
LPCl Coupling 1991 (2R01) VT-3 VT-3 examination of all 4 couplings.
No indications identified.
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.
2001 (2R06) EVT-1 EVT-1 examination of 'C' and 'Dl LPCl45-3b welds. No indications identified.
2003 (2R07) EVT-1 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.
2005 (2R08) EVT-1 EVT-1 examination of 'A', 'B', 'C', and ID' LPCl 45-3b and 45-12 welds. No indications identified.
VT-3 VT-3 examination of 'Dl LPCl 45-6a through 45-6d welds. No indications identified.
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 45-12) welds was performed. No indications identified.
VT-3 VT-3 examination of 'C' LPCl 45-6a through 45-64 welds. No indications identified.
VT- 1 VT-1 examination of 'C' LPCl 45-8a through 84 welds. No indications identified.
Steam Dryer 1995 (2R03) VT-3 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.
1997 (2R04) UT UT examination performed to determine baseline crack depth Steam Dryer of indications observed visually between 0 degree azimuth and (Continued) 41 degree lifting eye during 2R03. Results show crack to be 0.384 inches in depth. These indications were accepted by engineering evaluation.
VT-3 VT-3 examination of overall Steam Dryer assembly. No indications identified.
Page 42 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Limerick Generating Station, Unit 2 - Spring 2007 Update Components in BWRVIP Inspection Summarize the Following Information:
Scope 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.
2001 (2R06) VT-1 VT-1 examination of Steam Dryer Drain Channel welds. No indications identified.
2003 (2R07)
I VT-3 VT-3 examination of overall Steam Dryer assembly. No indications identified.
2005 (2R08) 1 VT-l VT-1 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.
2007 (2R09) 1 Best Effort VT-1 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
REACTORINTERNALS INSPECTION HISTORY Plant: Ovster Creek Generatinq Station Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Steam Dryer Fall 2006 Visual Re-inspect Steam Dryer Indications identified during previous outages.
EVT-1 cracks in hold-down area from 1R19.
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.
Core Shroud Fall 2006 EVT-1 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.
Fall 2004 None No Examinations Required.
Fall 2002 None No Examinations Required.
Fall 2000 EVT-1 V-3, V-4, V-15 and V-16. This was a one sided exam from the OD. No findings.
Fall 1998 UT V-7, V-8, V-10 and V-12.
EVT-I 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.
Fall 1996 Visual Inspected per BWRVIP-07. Three of ten tie rods inspected, no change from installation. EVT-1, OD of V-9 and V-11, (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
REACTORINTERNALS INSPECTION HISTORY Plant: Ovster Creek Generatina Station Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection Fall 1994 Ultrasonic and Inspected per BWRVIP-01 and 03. Cracks were detected in visual 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.
Shroud Support Fall 2006 Visual EVT-1 of 7 Lug / Clevis pin assemblies - #1, #18, #19, #23,
- 24, #32 and #33.
Fall 2004 None No examinations required.
Fall 2002 UT 30% UT of H-9 from the OD (Drywell).
UT inspected H-9 weld in Nozzle N1A, N1C and N1E bioshield openings. Found one 4 long indication in the N1E 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.
Fall 2000 Visual 25% of H-9, cleaning performed and EVT-1 inspection completed. This completes 100%
inspection of the H-9 weld. No findings.
Fall 1998 Visual 25% of H-9, cleaning performed and enhanced VT-1, no findings Fall 1996 Visual 25% of H-9, (different area then the 1994 inspection),
cleaning performed and enhanced m - 1 , no findings.
Fall 1994 Visual 25% of H-9 cleaning performed and enchanted VT-1, no findinas.
Core Spray Piping Fall 2006 Visual 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.
Fall 2004 Visual 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-10, U-11, U-12, U-16, and U-17 100% of annulus pipe brackets at 15, 105, 195 and 285.
No findings.
Fall 2002 Visual E m - 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 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections InsDection EVT-1 of a 25% sample (11 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 (15", 105", 195" and 285")
No Findings.
Fall 2000 Visual 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 Fall 1998 Visual non-creviced welds in the annulus piping:
L2, L9, L10, L11, 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 Fall 1996 Visual weld/HAZ surface and performed enhanced VT-1. No findings.
Inspected VT-1, (1 mil wire). No change to pinhole weld Fall 1994 Visual and air defect detected in slip joint in 1992. Note: Pinhole weld test defect detected in 1992 in System I. Analysis showed structural margin maintained.
Core Spray Sparger Fall 2006 Visual 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),
S1D, 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.
Fall 2004 Visual 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
REACTORINTERNALS INSPECTION HISTORY Plant: Ovster Creek Generatinq Station Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Visual and Air VT-1 all spargers, nozzles, end cap welds and repair clamps.
Fall 2002 Test No findings.
No new leaks were identified during the Air Test.
All sparger end cap welds were cleaned and EVT-1 Visual and Air Fall 2000 inspected. No findings.
Test VT-1 of spargers, repair clamps, and nozzles. No findings.
No new leaks were identified during the Air Test.
Visual and Fall 1998 All sparger repair clamps, both spargers.
Air Test Inspected per BWRVIP-03. Cleaned end cap welds and Visual and air Fall 1996 performed enhanced VT-1. No findings. Tee box welds are test clamped and not accessible to clean or visual. Performed VT-1, (1 mil wire), of sparger piping and nozzles. No findings.
Visual and Fall 1994 Performed VT-1, (1 mil wire) of sparger piping and nozzles.
Air Test No findings.
(2) Cracks in sparger piping. Repair clamps installed.
Visual 1978 - 1980 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.
Top Guide Fall 2006 Visual 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.
Fall 2004 Visual 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.
Fall 2002 Visual EVT-1 of two existing cracks measured in 18R outage (#3 and #5). No change to crack length identified.
Fall 2000 Visual 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.
Fall 1998 None. Not required for this outage by analysis.
47 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Ovster Creek Generatina Station Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection Fall 1996 Ultrasonic 12 indications emanating from notches detected at 100% grid intersections of cross members. 5 of the 6 cracks on bottom beams side of member at mid span detected. Removed sample from beam with crack to investigate root case.
Fall 1994 Visual [Under side of Top Guide] Three additional vertical cracks were detected at mid span locations. Disposition use as is.
Fall 1992 Visual [Under side of Top Guide] Two additional vertical cracks were detected at mid span location. Disposition use as is.
Fall 1991 Visual [Under side of Top Guide] A vertical crack was detected at mid span location. Disposition use as is.
Core Plate Fall 2006 None No exams were required.
Fall 2004 Visual No wedge inspections required. Inspected in-core guide tube plugs 04-29, 20-37, and 12-21. No findings.
Fall 2002 Visual No inspections needed. Wedges replace hold down bolt inspections.
Fall 2000 Visual Visually inspected all 8 wedges to verify integrity after first cycle of operation. All wedges found as installed.
Fall 1998 Wedges installed. No further exams of core plate were performed.
Fall 1996 Visual 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.
Fall 1994 Visual Inspected 18 hold down bolt tops only and top periphery at bolt locations inspected. No findings.
Jet Pump Assembly NA NA NA ~~~ ~~
Jet Pump Diffuser NA NA NA SLC Fall 2006 UT PDI - UT the Liquid Poison Nozzle N12 / SE. No findings.
Fall 2004 VT-2 pressure Inspected insulated nozzle from drywell.
test No leakage observed.
Fall 2002 Visual / PT PT of Liquid Poison Nozzle - No Indications. Inspect insulated nozzle from drywell during RPV pressure test. No leakage observed.
Fall 2000 VT-2 pressure Inspected insulated nozzle from drywell.
test No leakage observed.
48 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Ovster Creek Generatinq Station Date or Summarize the Following Information:
Components in BWRVIP inspection Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection Fall 1998 VT-2 during Not made accessible for direct exam.
Code pressure test.
Fall 1996 No Inspection Not made accessible.
Performed.
Fall 1994 No Inspection Not made accessible.
Performed.
CRD Guide Tube Fall 2006 EVT-1, Inspected 4 guide tubes. No findings.
VT-3 Fall 2004 EVT-1, VT-3 Inspected 4 guide tubes. No Findings.
Fall 2002 EVT-1, VT-3 Inspect 1 guide tube (46-43) removed to support stub tube inspection. No findings.
Fall 2000 VT-1, VT-3 2 guide tubes. No findings.
Fall 1998 VT-3 15, no findings.
Fall 1996 No inspection Performed. Not made accessible.
Fall 1994 No Inspection Performed Not made accessible.
CRD Stub Tube Fall 2006 None No inspections required.
Fall 2004 None No inspections required.
Fall 2002 VT- 1 Visual Inspection of 2 stub tubes found leaking at bottom head in Fall 2000 (42-43 and 46-39). No indications noted.
Fall 2000 VT- 1 None made accessible.
VT-2 pressure 2 stub tubes found leaking at bottom head (42-43 and 46-test 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.
Fall 1998 No inspection Fall 1996 Performed. Not made accessible.
49 of 76
REACTOR~NTERNALSINSPECTION HISTORY Plant: Oyster Creek Generatinq Station Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Fall 1994 No Inspection Not made accessible.
Performed In-Core Housing Fall 2006 No inspection Not made accessible.
performed Fall 2004 No inspection Not made accessible.
performed Fall 2002 No inspection Not made accessible.
performed Fall 2000 No inspection Not made accessible.
Fall 1998 performed Fall 1996 Fall 1994 Dry Tube Fall 2006 Replacement Replaced 4 Dry tubes due to service life: IRM-11, 17, 18 and SR M-24.
Fall 2004 Visual 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.
Fall 2002 Visual No inspections required.
Fall 2000 Visual VT-1 five dry tubes. One found slightly bent - use as is. No findings on others.
Fall 1998 Visual VT-1 one dry tube, no findings Fall 1996 Visual VT-1 one dry tube, no findings.
Fall 1994 Visual VT-1 four dry tubes, no findings.
Instrument Fall 2006 Visual VT-2 exam from vessel exterior.
Penetrations Fall 2004 No findings.
Fall 2002 Fall 2000 Fall 1998 Fall 1996 Fall 1994 Vessel ID Brackets Fall 2006 EVT-1 EVT-1 both Guide Rod Brackets.
EVT-1 all 3 Surv. Spec. Brackets.
No findings.
Fall 2004 EVT-1 Inspected all 4 dryer support brackets.
No findings.
Fall 2002 EVT-1 All feedwater sparger attachment brackets.
Both guide rod attachment brackets.
All surveillance sample brackets (30, 210 and 300 degree locations)
No indications on attachment welds.
50 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Ovster Creek Generatinq Station Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Fall 2000 EVT-I 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-relatedcomponent) on 2 ends.
Fall 1998 VT- 1 VT-1 of accessible portions of weld on guide rod brackets, Fall 1996 steam dryer brackets, surveillance sample brackets. All Fall 1994 attachment welds; no findings.
LPCl Coupling NA NA NA Fuel Support Casting Fall 2006 Visual None inspected.
Fall 2004 Visual None inspected.
Fall 2002 Visual None inspected.
Fall 2000 Visual VT-3 (2) support casting. No findings.
Fall 1998 Visual VT-3 (24) support castings. No findings.
Fall 1996 Visual VT-3 (25) support castings. No findings.
Fall 1994 Visual VT-3 (17 ) support castings. No findings.
Note: All indications left "as is" were an; 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 Date or Components in BWRVIP Inspection Summarize the Following information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Core Shroud 1994 UT & VT 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.
1996 UT 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.
Reexaminations planned per BWRVIP-76 2002 UT 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.
Shroud Support 1992 VT-3 VT-3 examination of support leg stub welds.
No indications identified.
VT-3 examination of welds H-7, H-8, and shroud support cylinder.
No indications identified.
1994 VT-3 VT-3 of accessible portions of H-8 weld between Jet Pump
- 1 and #lo.
No indications identified.
VT- 1 VT-1 examination around perimeter of 0 deg. access hole cover.
No indications identified.
UT UT examination of both access hole covers. No indications identified.
1998 EVT-1 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
REACTORINTERNALS I NSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections InsDection 2000 EVT-1 EVT-1 examination of both AHCs. No indications identified.
VT-3 VT-3 of accessible portions of H-9 weld between 0" and 180" Azimuth. No indications identified.
2002 UT UT of 10% of H-9 weld length from OD of vessel.
No indications identified.
2004 EVT-1 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 VT-3 of accessible portions of H-9 weld between 180" and 360". No indications identified Core Spray Piping 1980 to 1996 VT- 1 Enhanced VT-1 (1 mil resolution) performed on piping and (1 mil) welds each refueling outage per IEB 80-13, No indications identified.
1996 VT- 1 EVT-1 (1/2 mil resolution) performed on annulus piping welds (1/2 mil) 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.
1998 EVT-1 & U T Reinspection per BWRVIP-18, using UT technique. EVT-1 used to supplement UT. No new indications identified. P2B weld reexamination yielded additional margin.
2000 EVT-1 EVT-1 of nine (9) piping welds not previously UT'd, and of six (6) pipe brackets and attachment welds. No indications identified.
2002 EVT-1 & U T 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.
2004 EVT-1 EVT-1 of twelve (12) piping welds not accessible for UT inspection. No indications identified 2006 EVT-1 & UT 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.
Core Spray Sparger 1980 to 1994 VT- 1 Enhanced VT-1 (1 mil resolution) performed on piping and (1 mil) 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 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 1998 VT-3 & Reinspections per BWRVIP-18, no indications identified.
MVT-1 2000 EVT-1 EVT-1 of selected sparger welds per BWRVIP-18. No indications identified.
VT- 1 VT-I of sparger tee-box repair clamp, and approx. 50% of sparger "C" and "D" nozzles and drains.
VT-1 of eleven (11) sparger brackets and welds. No indications identified.
2002 VT-1, EVT-1 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.
2004 VT-I, EVT-I 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.
2006 VT-1, EVT-1 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.
Top Guide (Rim, etc.) 1976 to 1994 VT-3 VT-3 exam every other refueling outage per Section XI. No indications identified.
1987 UT UT examination performed of specific cells.
No indications identified.
1994 VT-3 Visual (VT-3) examination of 4 cells (48-41, 08-25, 24-17, and 24-25), per SIL 554.
No indications identified.
1996 VT-3 Visual (VT-3) of 2 aligner pins (0 deg. And 270 deg.), per SIL 588.
No indications identified.
Core Plate (Rim, etc.) 1996 VT-3 VT-3 examination of all accessible hold down bolts (cell 16-57, and area at 0 and 270 deg. Azimuth.
No indications identified.
SLC 1992 PT Surface (PT) examination of nozzle to safe end weld per Section XI.
No indications identified.
1998 PT & UT PT and UT of N10 nozzle to safe-end, no indications identified.
2002 PT Extended dwell time Liquid Penetrant examination of entire safe end.
No indications identified.
54 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Components in BWRVIP Scope P Date or Frequencyof Ins ection Inspection Method Used Summarize the Following Information:
Inspection Results, Repairs, Replacements,Reinspections 2006 PT Extended dwell time Liquid Penetrant examination of entire safe end.
No indications identified.
Jet Pump Assembly 1976 - 1996 VT-3 Visual VT-3 of all jet pump components performed every other refueling outage.
1981 VT&UT /T and UT examination performed on all 20 hold down beams. No indications identified.
1994 VT 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.
1996 VT Restrainer bracket wedge conditions and set screw tack welds remain unchanged, condition acceptable without repair.
1998 MVT-1 MVT-1 of: RS-1 weld on all 10 risers, RS-2 & RS-3 welds on 6 of 10 risers. No indications identified.
UT UT of all 20 hold down beams. No indications identified.
2000 EVT-1 EVT-1 of adjusting screw tack weld (jet pump 7) and RS-2 &
RS-3 on 5 of 10 risers. No indications identified.
2002 EVT-1 EVT-1 of fifty (50) Medium priority weld locations.
EVT-I of transition region of two (2) hold down beams.
No indications identified 2004 EVT-1 EVT-1 of forty one (41) medium priority welds, to complete 50% baseline inspections. No indications identified.
UT UT performed on all twenty (20) hold down beams (3 zones, BB-1, BB-2, and BB-3). No indications identified.
VT- 1 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.
2006 VT-1, EVT- VT-1 of twenty (20) WD-1 locations. EVT-1 of five (5) IN-4 1, VT-3 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.
Jet Pump Diffuser 1998 MVT-1 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.
2000 EVT-1 EVT-1 of AD-1, -2, -3a, -3b, and DF-2 on jet pumps 1 through
- 10. No indications identified.
55 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection 2002 EVT-1 EVT-1 of ten (10) High priority weld locations.
No indications identified.
2004 EVT-1 EVT-1 of eleven (11) medium priority weld locations, to complete 50% baseline inspections.
No indications identified 2006 UT UT of ninety eight (98) Diffuser / Adapter welds and six (6)
Inlet Mixer welds. One 2 indication found on DF-2 weld, JP 17.
CRD Guide Tube 1992 VT-3 VT-3 examination of housings accessible from fuel cells 26-31 and 30-27. No indications identified.
2002 EVT-1, VT-3 EVT-1 of three (3) welds on each of ten (10) Guide Tubes (locations 50-31, 42-11,42-23, 42-51, 38-27, 38-35, 38-51, 34-23, 34-39, and 30-31). Some flow interference with examinations.
VT-3 equivalent of anti-rotation pin on ten (10) Guide Tube locations.
No indications identified 2006 EVT-1, VT-3 EVT-1 of fifteen (15) CRGT welds, VT-3 of five (5) CRGT welds, verification of seventeen (17) CRGT alignment pins.
One sliahtlv bent Pin identified. No other indications identified.
CRD Stub Tube 1992 VT-3 VT-3 examination of stub tube welds accessible from fuel cells 26-31 and 30-27.
No indications identified.
In-Core Housing 1992 VT-3 VT-3 examination of housings accessible from fuel cells 26-31 and 30-27.
No indications identified.
Dry Tube All Dry Tubes replaced in 1984 1994 VT- 1 VT-1 examination of IRM Dry Tube 2D, at core location 37-32.
1997 N/A All IRM and SRM tubes replaced w/ Wide Range Monitoring tubes in 1997. No inspections required.
Instrument 1976 to PT PT examination performed on all instrument nozzle to safe Penetrations present end welds once per interval, per Section XI.
No indications identified.
LPCl CouPlina N/A for this olant Vessel ID Brackets 1976 to VT-1 or VT- VT-1 and VT-3 of all ID bracket welds performed once per present 3 interval per ASME Section XI. No indications identified.
2000 EVT-1 EVT-1 of six (6) Core Spray piping brackets. No indications identified.
2002 EVT-1 EVT-1 of two (2) Core Spray piping brackets, two (2) Steam Dryer support brackets, and five (5) Jet Pump Riser brackets attachment welds.
No indications identified.
56 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 2,2006 UPDATE Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 2004 EVT-1 EVT-1 of two (2) Steam Dryer support brackets and three (3)
Jet Pump riser brace attachment welds.
VT-3 VT-3 of four (4) Steam Dryer hold down brackets and three (3) lower surveillance brackets. No indications identified.
2006 EVT-1, VT- EVT-1 / VT-3 of twelve (12) Feedwater Sparger attachment 3, VT-1 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.
Steam Dryer 2002 VT-1, VT-I of all drain channel welds. VT-1 of upper and lower VT-3 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-baffleplate broken. Broken tie bar and instrument tube removed from dryer. New, stiffer tie bars welded to central dryer banks.
2004 VT- 1 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.
2006 VT-1 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.
Steam Separator 2006 VT- 1 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
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Date or Components in BWRVIP Inspection Method Summarizethe Following Information:
Frequency of Scope Used Inspection Results, Repairs, Replacements, Reinspections Inspection Core Shroud 1993 VT- 1 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 H-7 Prior to BW RVIP-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.
1995 UT 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.
1999 UT UT Examination on welds H-3 & H-4. Re-identified indications on both welds. Extent of indications within existing structural analysis.
2005 UT 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 (1995 and 1999) also characterized indication as thru-wall at that time. EVT-1 on OD surface did not identify any indications.
Shroud Support 1993 VT-1 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.
1999 EVT-1 10 % of weld length of welds H-8 &
H-9 examined.
No indications identified.
2001 UT 10% of H-9 weld length from vessel O.D.
No indications identified.
2005 EVT-1 > 10% of H-8 weld, between jet pump banks, in area of AHCs.
VT-3 Accessible length of H-9 between 0 and 180 degrees.
No indications identified.
58 of 76
REACTOR~NTERNALSINSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE
-~ ~
Date or Summarize the Following Information:
Components in BWRVlP Inspection Method Frequency of Scope Used Inspection Results, Repairs, Replacements, Reinspections Insr>ection Core Spray Piping 1980 to VT- 1 Enhanced VT-1 (1 mil resolution) performed on piping present (1 mil) and welds each refueling outage per IEB 80-13, 1985 Cracking discovered at tee-box to header pipe weld.
Welded repair plates installed on both header tee-boxes.
1993 Cracking identified in downcomer slip joint (weld P-5),
evaluation demonstrated structural margin for one operating cycle.
1995 Additional cracking identified in 3 of 4 downcomer slip joint welds (P-5), repair clamps installed on all 4 downcomers to repair flawed welds.
1997 VT- 1 4 Downcomer repair clamps, no indications identified.
EVT-1 All annulus piping welds, no indications identified.
1999 VT- 1 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.
2001 VT- 1 VT-1 of both header tee box welded repairs, no indications identified.
EVT-1 EVT-1 of all target welds plus 25% sample of butt welds examined. No indications identified.
2003 VT- 1 Four downcomer repair clamps.
EVT-1 Four Header Tee Box strong back repair plate welds.
EVT-1 of all target welds plus 25% sample of butt welds.
No indications identified.
2005 EVT-1 Four Header Tee Box strong back repair plate welds.
EVT-1 of all target welds plus 25% sample of butt welds.
No indications identified.
Core Spray Sparger 1980 to VT- 1 Enhanced VT-1 (1 mil resolution) performed on piping present (1 mil) and welds each refueling outage per IEB 80-13, No indications identified.
1999 EVT-1 Examination performed on all Sparger Pipe welds.
VT- 1 Examination performed on all Brackets, Drains and 50 O h of Nozzles.
No indications identified.
2003 EVT-1 Examination performed on all Sparger Pipe welds.
VT-1 Examination performed on all Brackets, Drains and 50 YO of Nozzles.
No indications identified.
59 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Date or Components in BWRVIP Inspection Method Summarize the Following Information:
Frequency of Scope Used Inspection Results, Repairs, Replacements,Reinspections Inspection Top Guide (Rim, etc.) 1987 UT UT examination performed on 40 cells.
No indications identified.
1993 VT-3 Visual (VT-3) examination of 9 cells (02-19, 46-11, 42-59, 58-19, 02-39, 10-51, 18-03, 22-03, and 58-35), per SIL 554.
No indications identified.
1995 VT-3 Visual (VT-3) of 3 cells (14-23, 22-31, and 46-23) per SIL 554.
No indications identified.
1976 to VT-3 VT-3 examination every other refueling outage per present Section XI.
No indications identified.
1997 VT-3 Top Guide Grid examined from above, no indications identified.
VT- 1 Adjacent aligner pins at 180 and 270 deg.(per VIP-26), no indications identified.
Core Plate (Rim, etc.) 1995 VT-3 VT-3 examination of hold down bolt retainers planned, deferred to 1997.
1997 VT- 1 Examined 18 of 34 bolts/retainers from above. No indications identified.
SLC 1997 UT UT of nozzle to safe end planned for 1997, per BWRVIP recommendations.
PT & UT PT & UT of nozzle to safe-end weld, no indications identified.
2003 PT Extended dwell time PT of SLC nozzle to safe end weld and entire safe end.
No indications identified.
Jet Pump Assembly 1974 to VT-3 Visual VT-3 of all jet pump components performed every present other refueling outage.
No indications identified.
1981 VT&UT 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.
1997 VT-3 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 CSVT-1 (MVT-1) all 10 thermal sleeve to riser elbow (MVT-1) 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
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE
~ ~~
Date or Components in BWRVIP Inspection Method Summarize the Following Information:
Frequencyof Scope Used Inspection Results, Repairs, Replacements, Reinspections Inspection 1999 UT 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.
EVT-1 Examination of high priority Adapter welds on Jet Pumps 1-10.
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 1-10. No indications identified.
Examination of Riser welds RS-2 & RS-3 of Jet Pump Assemblies 2, 3 & 4.
No indications identified.
2001 EVT-1 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.
2003 VT- 1 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.
EVT-1 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.
2005 UT Two-sided UT of all diffuser and adapter welds (100) from I.D. Identified4 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 VT-1 of five main wedges. No wear identified.
EVT-1 of 16 medium priority welds. No indications identified.
EVT-1 EVT-1 of 3 existing indications. No appreciable change in indication size.
Jet Pump Diffuser See Jet Pump Assembly.
CRD Guide Tube 1985 VT-3 VT-3 PSI examination of 4 replacement CRD housings.
61 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE
~
Date or Components in BWRVIP Inspection Method Summarize the Following Information:
Frequency of Scope Used Inspection Results, Repairs, Replacements,Reinspections InsDection 1987 VT-3 VT-3 examination of one of replaced housings.
No indications identified.
1991 VT-3 VT-3 examination of housings accessible from fuel cells 26-31 and 30-27.
No indications identified.
1999 VT-3 VT-3 examination on Guide Tube welds CRGT-1 &
Alignment Pin weld (Core Locations: 14-15, 14-31, 14-47, 18-19, 18-27, 18-35, 18-43, 26-11, 34-35, 42-19)
No indications identified.
EVT-1 EVT-1 examination on Guide Tube welds CRGT-2 & 3 (Core Locations:l4-15, 14-31, 14-47, 18-19, 18-27, 18-35, 18-43, 26-11, 34-35, 42-19)
No indications identified.
2003 EVT-1 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 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.
2005 EVT-1 EVT-1 on Guide Tube welds CRGT-2 & 3 (Core locations: 22-39, 38-39, 14-35, 46-35, 46-27, 22-23, and 26-11) No indications identified. CRGT-3 (22-39) later disqualified.
VT-3 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 26-11) Alignment pin weld also at 14-27 and 38-23. No indications identified.
CRD Stub Tube 1991 VT-3 VT-3 of accessible portions of 12 stub tubes (30-35, 26-35, 22-35, 22-31, 22-27, 26-27,26-23, 30-23, 34-23, 34-27, 34-31, 30-31).
No indications identified.
In-Core Housing 1991 VT-3 VT-3 of housings accessible from fuel cells 26-31 and 30-27.
No indications identified.
Dry Tube 1997 N/A All Dry Tubes replaced in 1985.
All IRM and SRM tubes replaced w/ Wide Range Monitoring tubes in 1997. No inspections required.
Instrument 1976 to PT PT examination performed on all instrument nozzle to Penetrations present safe end welds once per interval, per Section XI.
No indications identified.
62 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Peach Bottom Atomic Power Station, Unit 3 2005 UPDATE Date or Components in BWRVIP Inspection Method Summarize the Following Information:
Frequency of Scope Used Inspection Results, Repairs, Replacements,Reinspections Inspection 1997 PT PT nozzle to safe-end (coupling) & safe-end to pipe welds on 2 nozzles. (N12A & N12B). No indications identified.
2001 PT PT nozzle to safe-end (coupling) welds on 2 nozzles.
( N I I A & N16A). No indications identified.
Vessel ID Brackets 1976 to VT-1 or VT-1 and VT-3 of all ID bracket welds performed once per present VT-3 interval No indications identified.
1997 VT- 1 All 10 Jet Pump riser brace to vessel welds, no indications identified.
1999 EVT-1 EVT-1 examination performed on 8 Core Spray Bracket Pads @ 15, 117, 123, 165,195,237,243 & 345 AZ.
No indications identified.
2001 EVT-1 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.
2003 VT-1 Lower Surveillance Specimen brackets at 30", 120", and 300".
VT-3 Upper Surveillance brackets at 30", 120", and 300".
Guide Rod brackets at 0" and 180".
EVT-1 & VT-3 Steam Dryer support brackets at 184" and 2-74'.
EVT-1 Jet Pump riser brace to vessel welds JP 9/10 and JP 13/14.
No indications identified.
8 Feedwater sparger bracket welds and 16 jet pump riser 2005 EVT-1 brace welds. No indications identified.
LPCl Coupling N/A for this dant Steam Dryer 2003 VT-3 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 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.
2005 VT- 1 Completed all remaining BWRVIP-I 39 recommended insw>ections(68 locations). No indications identified.
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REACTORINTERNALS INSPECTION HISTORY I Plant:
Components Scopein BWRVIP 1 Quad Cities Unit 1 Frequencyof Ins ection
/I Inspection Method Used
~~
Summarize the Following Information:
Inspection Results, Repairs, Replacements, Reinspections I Coreshroud 04/94 I EVT-1 and UT Inspections per SIL 572, indications in circumferential I (BWRVIP-76) 03/96 EVT-1 and UT 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 E m - 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).
I o/oo l1lg8 1 UT No Reportable Indications.
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.
11/02 EVT-1 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.
04/05 EVT-1 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 05/07 EVT-1 Examined 6 vertical welds from the OD (V-05, V-06, V-07, V-26, V-27, V-28). NRI Shroud Repair 05/07 EVT-1, VT-3 EVT-1 of all tie rod upper support vertical faces, VT-3 of Hardware high-stressedfasteners and other contact points, and (BWRVlP Letters overall VT-3 per BWRVIP Letters 2006-112 and 2006-220.
2006-112 and 2006- Also, VT-3 of core plate wedges adjacent to repair 220) hardware.
No reDortable indications.
64 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 1
-~
Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements,Reinspections Inspection Shroud Support 3/96 EVT-1 EVT-1 of H8 and H9 for approx 12" at 4 locations of (BW RVIP-38) shroud repair hardware attachment areas.
Access hole covers; VT/UT in 1992, circumferential indications observed, permanent repair installed.
1o/oo EVT-1 Inspected H8 and H9 adjacent to AHC at JP# 10 & 11 in accordance with BWRVIP-38. No reportable indications.
03/05 EVT-1 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.
05/07 N/A No inspections performed.
Core Spray Piping 1980 to 1994 VT-1 (1 mil) IEB 80-13/NUREG of piping and welds in annulus.
(BWRVIP-18) Indication previously observed during 1994 on T-box was permanently repaired in 1996. Repair examined 11/98 with no reportable indications.
04/96 EVT-1 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.
11/98 Auto UT GE CSI-2000 with supplemental EVT-1 for unqualified EVT-1 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.
1o/oo EVT-1 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.
11/02 UT 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.
EVT-1 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.
03/05 EVT-1 Lower Elbow to Shroud Pipe Welds 1P4d, 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
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 1 Date or Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Insnection 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 VT-1, VT-3 Welds BPI, BP2, BP3,2P2, 2P3, 3P3 at Tee Box repair (clamp interferes with EVT-1). NRI 05/07 UT 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.
EVT-1 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.
Core Spray Sparger 1980 to 1994 VT-1 (1 mil) IEB 80-13 of welds on sparger. No indications found.
(BWRVIP-18) 04/96 EVT-1 or EVT-1 performed to intent of BWRVIP-18, on T-box cover VT-3 plate welds, T-box to sparger welds, end cap welds and bracket welds. VT-3 of spargers and nozzles.
Future inspections per BWRVIP-18.
11/98 EVT-1 End caps, cover plates and tee branch welds were EVT-1 MVT-1 examined. All sparger connections and bracket welds were MVT-1 examined. No reportable indications.
11/02 EVT-1 of Examined all 20 S1, S2, and S4 sparger welds, 50% of the Sl,S2, & S3a, b & c nozzle welds, and all 12 sparger brackets.
S4;VT-1 Of Examined for IEB 80-13 and BWRVIP-18. No indications.
S3:VT-1 of brackets 03/05 N/A No examinations performed.
05/07 EVT-1 Examined all 20 S1, S2, and S4 sparger welds. No indications.
66 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 1 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections lnsoection Top Guide (Rim, etc.) 03/94 VT- 1 VT-1 of 4 cells. No indications.
(BWRVIP-26) 04/96 VT- 1 VT-1 of alignment assemblies. No indications.
11/98 VT- 1 VT-1 of alignment assemblies and adjacent rim welds. No reportable indications.
1o/oo EVT-1 Inspected accessible areas of location 11 in accordance with BWRVIP-26. No reportable indications.
11/02 VT-3 Examined 9 pin welds (FS/GT-ARPIN-1) per BWRVIP-47. No Indications.
03/05 EVT-1, VT-1 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.
Core Plate (Rim, etc.) N/A N/A Installed core plate wedges in conjunction with (BWRVIP-25) comprehensive shroud repair 1996.
11/98 VT-I Wedges inspected in conjunction with shroud repair hardware. No reportable indications.
05/07 VT-3 Wedges inspected in conjunction with shroud repair hardware. No reportable indications.
Jet Pump Assembly 03/94 VT- 1 Hold down beams, beam bolt keepers, lockplates and (BWRVIP-41) 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.
04/96 VT- 1 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.
04/96 UT 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.
11/98 VT- 1 Inspected all 20 jet pump assemblies. Identified indication at JP7/8 riser brace to riser weld. Repair installed 4/99.
11/98 EVT-1 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.
1o/oo EVT-1 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 Date or Summarize the Following Information:
Components in BWRVIP Inspection Frequency of Inspection Results, Repairs, Replacements, Reinspections Scope Method Used Inspection 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.
11/02 EVT-1 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, 11/12, 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 6-11, 14-18 and 20; EVT-1 on the risers of pumps 3/ 4, 9/10, 11/12, 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 6-11, 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).
03/05 EVT-1 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-1b 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.
VT-1, VT-3 Reinspected repair on Jet Pump 19/20 RS-1. NRI 05/07 EVT-1 Re-measuredprevious indications at AD-3a,b on JP2, JP7 and JP 16. No changes.
VT-1, VT-3 Inspected all main wedges with no unusual wear noted.
Insoected one aux wedae and set screw. NRI.
CRD Guide Tube 11/02 VT-1, VT-3 on Examined 9 sets of guide tube welds (CRGT-1, CRGT-2, (BWRVIP-47) CRGT-1; and CRGT-3) and one additional weld (CRGT-2) per EVT-1 on BWRVIP-47. No Indications.
CRGT-2 & 3 03/05 N/A No inspections performed.
05/07 N/A No inspections performed.
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REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 1 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequencyof Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection N/A N/A N/A (BWRVIP-47)
I In-Core Housing N/A N/A N/A (BWRVIP-47)
IRMISRM Dry Tubes 03/94 VT Replaced 2 dry tubes 1994.
(SIL 409) 03/96 VT Replaced 5 dry tubes in 1996.
10/00 MVT-1 Inspected original dry tubes at 7 locations. No recordable indications.
11/02 VT- 1 Examined 5 dry tubes. Verified plungers engaged at Top Guide. No Reportable Indications.
04/05 All remaining original dry tubes ( 5 ) replaced.
Standby Liquid Control 04/05 PT Nozzle To Safe End, N10-F1. NRI (BWRVIP 27)
Instrument N/A N/A N/A Penetrations (BWRVIP-49)
Vessel ID Brackets 03/94 VT-1 andVT- Section XI inspections of jet pump riser brace, dryer, RVIP-48) 3 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.
04/05 VT-1, VT-3 Examined two Moisture Separator shroud guide rod support brackets. Minor gouges and bent top pins. No changes since previous inspection in 11/03 (F51).
VT-3 Examined two steam dryer guide rod support brackets upper and lower (four inspections). NRI EVT-1, VT-3 Examined four steam dryer wall support lugs. NRI VT-1, VT-3 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.
EVT-1, VT-3 Examined eight feedwater sparger end-bracket assemblies. Five of eight had less than three protruding threads. Tightened and applied additional tack welds.
VT-3 Examined eight feedwater sparger lug to vessel attachment welds. NRI.
05/07 EVT-1, VT-3 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.
N/A N/A Not applicable to this plant.
69 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 1 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections InsDection Steam Dryer 03/05 Best effort The steam dryer was originally scheduled to be replaced (SIL 644, BWRVIP- VT-1, VT-3 during Q1R18, but was not ready in time (the dryer was 139) later replaced in May 2005). The following inspections were then performed during Q1R18:
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.
05/06 Best Effort Performed baseline inspection of new steam dryer VT-1, VT-3 installed in June 2005 per BWRVIP-139 and GE recommendations. NRI 05/07 Best Effort Performed inspection steam dryer per BWRVIP-139 and VT-1, VT-3 GE recommendations. NRI Feedwater Spargers 1982 Manual UT UT of all four N4 nozzles and inner radii. NRI (NUREG 0619) 1986 Manual UT UT of all four N4 nozzles and inner radii. NRI 1989 Manual UT UT of all four N4 nozzles and inner radii. NRI 1992 Manual UT UT of all four N4 nozzles and inner radii. NRI 1996 Manual UT UT of all four N4 nozzles and inner radii. NRI 1998 UT (GERIS) UT of all four N4 nozzles and inner radii. Acceptable.
2002 UT (GERIS) UT of all four N4 nozzles and inner radii. Acceptable.
EVT-1/VT-3 Examined all 8 Sparger end brackets per NUREG-0619 program and BWRVIP-48. No indications.
04/05 VT-1, VT-3 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.
05/07 VT-1, VT-3 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
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Ins-pection Core Shroud 04/95 EVT-1 and Inspections per BWRVIP Guidelines of all shroud repair design-(BW RVIP-76) UT 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 (100% 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.
03/97 EVT-1, VT-3 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.
01/00 ET/UT 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.
02/02 EVT- 6 vertical welds from the OD per BWRVIP-76.
No indications.
03/04 EVT- Examined six welds, including 3 welds inaccessible to UT and three with only single side access. No reportable indications.
04/06 EVT-1 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.
Shroud Support 04/95 EVT-1 EVT-1 of H8 and H9 for approx 10" -12" at 4 locations of (BWRVIP-38) shroud repair hardware attachment areas.
Access hole covers; VT/UT in 1991, circ indications observed and permanent repair installed 1993.
01/00 EVT-1 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.
04/06 EVT-1 Examined >lo% of H8 and H9 from annulus adjacent to AHC between jet pumps #10 - #11. No Reportable Indications.
Shroud Repair 04/06 EVT-1, VT-3 EVT-1 of all tie rod upper support vertical faces, VT-3 of high-Hardware stressed fasteners and other contact points, and overall VT-3 (BWRVIP Letters 2006- per BWRVIP Letters 2006-112 and 2006-220. Also, VT-3 of 112 and 2006-220) core plate wedges adjacent to repair hardware.
71 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections inspection No reportable indications.
Core Spray Piping 1980's to VT-1 (1 mil) IEB 80-13/NUREG of piping and welds in annulus. No (BWRVIP-18) 1996 indications observed.
03/97 UT, EVT-1 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.
01/oo EVT-1 Performed visual examination of P4d and P8a(4 connections) and P2 at both T-boxes in accordance with BWRVIP-18. No Reportable Indications.
02/02 UT BWRVIP-18 UT examinations of all accessible welds (32). No relevant indications.
EVT-1 on BWRVIP-18 EVT-1 on 5 welds inaccessible to Piping UT. No indications.
03/04 EVT-1 Examined 100% of P8a & P4d target welds.
No relevant indications.
04/06 UT BWRVIP-18 UT examinations of all accessible welds (32). No relevant indications.
EVT-1 Examined two P4a, one P4b, one P ~ cfour , P4d, two P8a and two P8b welds. No relevant indications.
Core Spray Sparger 1980's to VT-1 (1 mil) IEB 80-13/NUREG of welds on sparger. No indications found (BWRVIP-18) 1996 03/97 CSVT-1, VT- CSVT-1, VT-3 performed in accordance with BWRVIP-18, 3 geometry tolerant. No Reportable Indications.
01/oo N/A No examinations performed.
02/02 EVT-1 of S1, Examined 50% sparger nozzles, 100% of the S3a, S3b, & S3cs2, & s4; nozzle welds, and 100% of S1, S2 and sparger bracket welds.
VT-1 of s3: Examined for IEB 80-13 and BWRVIP-18.
VT-1 of No indications.
brackets 04/06 EVT-1 of S1, Examined 50% sparger nozzles, 100% of the S3a, S3b, & S3cs2, & s4; nozzle welds, and 100% of S1, S2 and sparger bracket welds.
VT-1 of s3: No Reportable Indications.
VT-1 of brackets 72 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 2
~ ~~ ~~~
Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection Top Guide (Rim, etc.) 04/95 VT- 1 VT-1 of 5 cells. No indications.
(BWRVIP-26) VT-1 of alignment assemblies. No indications.
04/97 VT- 1 VT-1 of alignment assemblies and adjacent rim weld. No Reportable Indications.
01/00 N/A No examinations performed.
02/02 EVT-1, VT- Inspected 2 alignment assemblies (VT-1) and accessible rim 1 welds (EVT-I) per BWRVIP-26. No indications.
03/04 EVT-1 Inspected two Guide Aligner Pins and rim welds at adjacent locations. No recordable indications.
Core Plate (Rim, etc.) N/A N/A Core Plate Wedges installed 4/97.
(BW RVIP-25) 04/06 VT-3 Examined core plate wedges as part of shroud repair (tie rod) inspections. No Reportable Indications.
SLC 01/00 UT Performed augmented (non PDI) volumetric examination of (BWRVIP-27) nozzle to safe-end weld. No Reportable Indications.
03/04 PT Performed surface examination of Nozzle To Safe End weld.
No ReDortable Indications.
Jet Pump Assembly 03/93 VT- 1 JP#7 and JP#18 set screws backed out, repaired and tack (BWRVIP-41) welded.
04/95 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, adapter and baffle plate welds, sensing lines and sensing line brackets per various SILS. NO Reportable Indications. Inspect 100% every other outage.
04/97 UT Performed UT examination of jet pump beams. JP#7 beam rejectable indication at center hole region. Beam replaced.
01/00 UT/EVT-1 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.
UT/ET or Performed examinations of at least 50% of the medium and EVT-1 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.
02/02 EVT-1, VT-I 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
REACTOR~NTERNALSINSPECTION HISTORY Plant: Quad Cities Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 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) 03/04 EVT-1 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-2, RS-4, RS-5, RS-8, RS-9).
No reportable indications.
VT- 1 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.
04/06 EVT-1, VT-1 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.
Jet Pump Diffuser 04/95 VT- 1 Diffuser to baffle plate welds examined. No reportable (BWRVIP-41) indications.
01/00 N/A See Jet Pump Assembly.
CRD Guide Tube 04/97 VT-3 Performed visual examination of CRGTs G-7 and H-8 while (BWRVIP-47) removed from core.
No Reportable Indications.
02/02 VT-1, VT-3 Examined 6 sets of guide tube welds (CRG - 1, CRGT-2, and on CRGT-1; CRGT-3) per BWRVIP-47. No Indications.
EVT-1 on CRGT-2 & 3 03/04 EVT-1, VT-3 Examined 3 sets of guide tube welds (CRG 1, CRGT-2, and CRGT-3).
No Indications.
04/06 EVT-1, VT-3 Examined 4 sets of guide tube welds (CRGT-1, CRGT-2, and CRGT-3) and FSIGT-ARPIN per BWRVIP-47.
No Indications.
Fuel Support 02/02 VT-1, VT-3 Examined 6 pin welds (FSIGT-ARPIN-1) per BWRVIP-47. NO Alignment Pin welds Indications (BWRVIP-47) 03/04 VT-3 Examined 3 pin welds (FS/GT-ARPIN-1). No Indications 04106 VT-3 Examined 4 pin welds (FS/GT-ARPIN-1).No Indications CRD Stub Tube NIA NIA N/A in-Core Housina NIA N/A 74 of 76
REACTORINTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 2 Date or Components in BWRVIP Inspection Summarize the Following Information:
Frequency of Scope Method Used inspection Results, Repairs, Replacements, Reinspections Inspection Dry Tube 04/97 VT Replaced 6 dry tubes 1997. Dry tubes examined every other (GE SIL-409 and outage. Plunger engagement verified each outage.
BWRVIP-47) 01/00 VT Verified plungers engaged at Top Guide. NO Reportable Indications.
02/02 MVT-1 Examined 6 dry tubes. Indications observed on 5 dry tubes, and authorized for one additional cycle of operation.
03/04 None required. All original dry tubes have been replaced.
04/06 No inspections required.
Feedwater Spargers 1983 Manual UT UT of all four N4 nozzles and inner radii. NRI (BWRVIP-48) 1986 Manual UT UT of all four N4 nozzles and inner radii. NRI 1990 Manual UT UT of all four N4 nozzles and inner radii. NRI 1993 Manual UT UT of all four N4 nozzles and inner radii. NRI 1995 UT (GERIS) UT of all four N4 nozzles and inner radii. NRI 02/02 VT- 1 Examined all Feedwater Spargers. Examined per NUREG-0619 program and BWRVIP-48.
No indications.
2004 UT (GERIS) UT of all four N4 nozzles and inner radii. Acceptable.
04/06 VT-1, VT-3 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.
Instrument Penetrations 04/97, 01/00, VT-2 VT-2 system leakage test. Acceptable.
(BWRVIP-49) 02/02, 03,04, 04/06 Vessel ID Attachments 04/95 VT-1, VT-3 Section XI inspections of jet pump riser brace, dryer, feedwater (BWRVIP-48) sparger, core spray, and surveillance capsule holder brackets, performed once per interval. VT-3, or VT-1 if in beltline region.
No Reportable Indications.
02/02 VT-1, EVT- Inspected 8 core spray brackets, 4 feedwater sparger brackets, 1, VT-3 and 4 steam dryer wall support brackets per BWRVIP-48. No indications.
03/04 VT-1, EVT- Examined dryer support lugs and surveillance specimen 1, VT-3 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
REACTOR INTERNALS INSPECTION HISTORY Plant: Quad Cities Unit 2 Date or Components in BWRVIP Inspection Summarizethe Following Information:
Frequency of Scope Method Used Inspection Results, Repairs, Replacements, Reinspections Inspection 04/06 EVT-1, VT-3 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.
RPV Internal 02/02 VT-3 VT-3 visual examination for ASME Section XI, B-N-1 of RPV Surfaces (Cladding) internal surfaces for 360 degrees between steam dam and (ASME B.N.l) flange. No indications.
03/04 VT-3 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.
LPCl Coupling N/A N/A Not applicable to Quad Cities.
Steam Dryer 02/02 VT-3 The dryer was modified to accommodate the (GE SIL-644 and Extended Power Uprate. The modification installed a BWRVIP-139) 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.
03/04 Best Effort Conducted the following inspections per GE SIL-644 S1:
VT-1, VT-3 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-skirtwelds 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 locations:
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.
04/06 Best Effort Performed baseline inspection of new steam dryer installed in VT-1, VT-3 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
Attachment 3 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
Attachment 3 Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
- 1. ASME Code Component(s) Affected 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.
2. Applicable Code Edition and Addenda
PLANT 1 INTERVAL EDITION START -
END Clinton Power Station Second 1989 Edition, no addenda January 1,2000 December 31,201C Dresden Nuclear Power 1995 Edition, through 1996 Fourth January 20,2003 January 19,2013 Station, Units 2 and 3 Addenda LaSalle County Station, 2001 Edition, through 2003 Third October 1,2007 September 30,201:
Units 1 and 2 Addenda Limerick Generating 2001 Edition, through 2003 Third February 1,2007 January 31,2017 Station, Units 1 and 2 Addenda 3yster Creek Generating 1995 Edition, through 1996 Fourth October 15,2002 October 14,2012 Station Addenda 2001 Edition, through 2003 Peach Bottom Atomic Addenda Fourth November 5,2008 November 4,201 8 Power Station, Unit 2 (Final edition to be determined) 2001 Edition, through 2003 Peach Bottom Atomic Addenda Fourth August 15,2008 August 14,2018 Power Station, Unit 3 (Final edition to be determined)
Quad Cities Nuclear 1995 Edition, through 1996 Power Station, Units 1 Fourth March 10,2003 March 9,2013 Addenda and 2
- 3. 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 Attachment 3, 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 BWRVIP Inspection and Evaluation (I&E) guidelines have recommended aggressive specific inspection by BWR 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 requirements , incIuding examination method, examination vo Iume, f requency, training, successive and additional examinations, flaw evaluations, and reporting.
el and i l ~ ~ ~ ~ ~ a ~ ~
el ines" BWRVIP-l8-A, "BWR Core Spray lnternals Inspection and Flaw Evaluation Guidelines" BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines" BW RVIP-38, "BWR Shroud Support Inspection and Flaw Evaluation Guidelines" BWRVIP-41, Revision 1 "BWR Jet Pump Assembly Inspection and Flaw Evaluation GuideIines I' BWRVlP-42-A, "LPCI Coupling Inspection and Flaw Evaluation Guidelines" BWRVIP-47-A, "BWR Lower Plenum Inspection and Flaw Evaluation Guidelines"
I Use of BWRVIP Guidelines in Lieu of Specific Attachment 3, ASME Code Requirements Proposed Alternative Page 3 BW RVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines" BWRVlP-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 RVIP 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 RVIP 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.
- 6. Basis for Use BW Rs now examine reactor internals in accordance with BW RVIP 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 RVIP 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 I 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.
I 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.
- 7. 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 Attachrnent 3, ASME Code Requirements Proposed Alternative Page 4
- 8. Precedence A similar relief request was approved for Vermont Yankee Nuclear Power Station as discussed in Reference 1.
- 9. References
- 1. 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
- 2. 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)"
- 3. Letter USNRC to BWRVIP, dated October 6, 1999, "Staff Reevaluation of Table 1 in the BWRVIP-07 Report (TAC NO. M94959)"
- 4. Letter USNRC to BWRVIP, dated September 6, 2005, "NRC Approval Letter of BWRVlP-l8-A, "BWR Vessel and lnternals Project Boiling Water Reactor Core Spray lnternals Inspection and Flaw Evaluation Guideline" I'
- 5. 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'
- 6. 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)"
- 7. 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)"
- 8. Letter USNRC to BWRVIP, dated September 9, 2005, NRC approval letter of BWRVIP-42-A, "BWR Vessel and lnternals Project Boiling Water Reactor Low Pressure Coolant Injection and Flaw Evaluation Guidelines"
- 9. Letter USNRC to BWRVIP, dated September 9, 2005, "NRC Approval Letter of BWRVIP-47-A, "BWR Vessel and lnternals Project Boiling Water Reactor Lower Plenum Inspection and Flaw Evaluation Guidelines" I'
- 10. 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
- 11. 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. MA6015)"
I Use of BWRVIP Guidelines in Lieu of Specific Attachment 3, ASME Code Requirements Proposed Alternative Page 5 12% Letter us $aft
I Use of BWRVIP Guidelines in Lieu of Specific Attachment ASME Code Requirements Proposed Alternative Page 6 TABLE 1 Comparison of A ME Examination C :egory B-N-1 ai I B-N-2 Requirc ients With BWRV I Guidance Requirements (')
I I I
ASME Item Applicable No. Table IWB-2500-1 B13.10 Component Reactor Vessel Interior ASME Exam Scope Accessible Areas ASME Exam VT-3 ASME Frequency Each period BWRVIP Document BWRVIP-18, BWRVIP Exam Scope BWRVIP Exam I BWRVIP Frequency Overview examinations of components during BWRVIP (Non-specific) 26, 38, 41, 42, examinations satisfy Code VT-3 inspection requirements.
- 47. 48. 76 B13.20 Interior Attachments Within Accessible Welds VT- 1 Each 10-year BWRVIP-48 Riser Brace EVT-1 100% in first 12 Beltline - Riser Braces Interval Table 3-2 Attachment years, 25% during each subsequent 6 years Lower Surveillance Specimen BWRVIP-48, Bracket VT- 1 Each 10-year Interval Holder Brackets Table 3-2 Attachment B13.30 Interior Attachments Beyond Accessible Welds VT-3 Each 10-year BWRVIP-48 Bracket VT-3 Each 10-year Interval Beltline - Steam Dryer Hold- Interval Table 3-2 Attachment down Brackets Guide Rod Brackets BWRVIP-48, Bracket VT-3 Each 10-year Interval Table 3-2 Attachment Steam Dryer Support BWRVIP-48, Bracket EVT-1 Each 10-year Interval Brackets Table 3-2 Attachment Feedwater Sparger Brackets BWRVIP-48, Bracket EVT-1 Each 10-year Interval Table 3-2 Attachment Core Spray Piping Brackets BWRVIP-48, Bracket EVT-1 Every 4 Refueling Table 3-2 Attachment Cycles Upper Surveillance Specimen BWRVIP-48, Bracket VT-3 Each 10-year Interval Holder Brackets Table 3-2 Attachment Shroud Support (Weld H9) BWRVIP-38, Weld H9'2' EVT-1 or UT Maximum of 6 years iklcltrd ing gussets where 3.1.3.2, ir-ncftadir-ly for EVT-1, Maximum applicabk Figures 3-2 and gussets (where of 10 years for UT 3-5 applicable)
Shroud Support Legs (H12) (Rarely BWRVIP-38, Weld H12 Per BWRVIP- When accessible Accessible)
Welds 3.2.3 38 NRC SER (7/24/00),
inspect with appropriate method (4)
Use of BWRVIP Guidelines in Lieu of Specific Attachment ASME Code Requirements Proposed Alternative Page 7 ASME Item Applicable ASME Exam ASM E BWRVIP Exam BWRVIP No. Table Component ASME Exam BWRVIP BWRVIP Frequency Scope Frequency Scope Exam IW B-2500-1 Document 613.40 Inteegraity Welded Core Accessible VT-3 Each 10- BWRVIP-38, Shroud Support EVT-I or UT Based on as-found Surfaces Support Structure year Interval 3.1.3.2, and Leg Welds conditions, to a Figures 3-2, 3-5 including maximum 6 years for gussets a5 one side EVT-I, 10 applicable years for UT ~viaeite accessible Shroud Horizontal welds BWRVIP-76, Welds H I - H7 EVT-1 or UT Based an as-fsund 2.2.1 as applicabie conditions, $aa maximum 6 years far one side EW-? 10 I yslars far UT trJhere accsssibie Shroud Vertical welds BWRVIP-76, Vertical and EVT-1 or UT Maximum 6 years for 2.3, Figure 3-3 Ring Segment one-sided EVT-1, 10 Welds years for UT as aDolicak&
Shroud Repairs (3) BWRVIP-76, Tie-Rod Repair VT-3 Per repair designer Section 3.5 recommendations Der BWRVIP-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.
I 4) when ~ ~ s ~~o~~~~~~ ~ ~and t ~j ~~ n t h areo~ ~ ~~ they ~ willo~be ~t~~~~~~
~ ~j to ~~~~~b~~~~
~
~ a b ~~ s e ~~ ~~ ~ en of~ these
~ welds,
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Use of BWRVIP Guidelines in Lieu of Specific Attachment A ASME Code Requirements Proposed Alternative Page 8 PLANT BWRVIP DOCUMENT LETTER DATE TO USNRC DEVIATION APPLICABILITY LaSalle County BWRVIP-76 Letter from S. R. Landahl (Exelon 100% of the accessible areas of the This deviation does Station, Unit 1 Generation Company, LLC) to U. S. LaSalle County Station Unit 1 core not impact the basis Nuclear Regulatory Commission, shroud was not examined in the for use of this relief dated April 27, 2006 L1R11outage in February 2006. request.
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.
Oyster Creek BWRVIP-76 Per BWRVIP-76 re-inspection This deviation does Generating Station guidelines, a one-sided visual not impact the basis examination technique requires for use of this relief reexamination in 6 years as compared request.
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 1R21 (2006) as required by the BWRVIP-76 guidance for single-sided examination.
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 10-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 RVIP 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 RVIP-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). BWRVlP-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-I 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.
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 RVIP 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
~~~~~~~ and the shroud support legs (if accessible). In later designs, the 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.
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).
BWRVIP 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 BWRVlP 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 RVIP 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.