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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage ML20086B4041995-06-29029 June 1995 ISI Summary Rept Ano,Unit 1,Outage 1R12 ML20070G8611994-07-15015 July 1994 ISI Summary Rept for Arkansas Nuclear One,Unit 2 Outage 2R10 ML20063A8491994-01-17017 January 1994 ISI Summary Rept,Ano Unit 1 Outage 1E11 ML20059L7191993-11-12012 November 1993 Steam Generator Tubing ISI Rept for Eleventh Refueling Outage ML20046A5731993-07-22022 July 1993 Addendum to Unit 1 Outage Summary Rept for Cycle 9. ML20046A6161993-07-22022 July 1993 Addendum to Unit 1 ISI Outage Summary Rept for Cycle 10. ML20046A6211993-07-22022 July 1993 Addendum to Unit 2 ISI Outage Summary Rept for Cycle 9. ML20127J5701993-01-18018 January 1993 ISI Summary Rept for Arkansas Nuclear One,Unit 2 Outage 2R9 ML20104B3021992-09-0303 September 1992 Inservice Insp Summary Rept,Arkansas One,Unit 1,Outage: 1R10 2CAN079205, SG Tubing Inservice Insp Rept, Mar 1992 Forced Outage (2F92-1)1992-07-14014 July 1992 SG Tubing Inservice Insp Rept, Mar 1992 Forced Outage (2F92-1) ML20096H2701992-05-20020 May 1992 Steam Generator Tubing Inservice Insp Rept for Tenth Refueling Outage ML20079D6231991-07-15015 July 1991 Inservice Insp Outage Summary Rept 2CAN019110, Annual Rept of Steam Generator Tube Inservice Insps - 1990, Ltr Rept Submitted to NRC Document Control Desk1991-01-29029 January 1991 Annual Rept of Steam Generator Tube Inservice Insps - 1990, Ltr Rept Submitted to NRC Document Control Desk ML20073L7311991-01-0707 January 1991 Inservice Insp Outage Summary Rept of Arkansas Nuclear One, Unit 1 ML20012C8611990-03-13013 March 1990 Inservice Insp Program Vol 18 Seventh Refueling Outage Exam Data. ML20012C8381990-03-13013 March 1990 Inservice Insp Program Vol 17 Seventh Refueling Outage Rept. ML20246F9501989-08-24024 August 1989 Inservice Insp Rept for 880216-22.Insp Satisfied Min Inservice Insp Frequency as Outlined in Tech Spec 4.4.5.3. Tubes Inspected Full Length from Cold Leg Channel Head W/ Bobbin Coil Probe 2CAN038706, Steam Generator Tubing Inservice Insp Rept for Fifth Refueling Outage.Minor Tube Wall Degradation Indications Observed in Steam Generators a & B.No Plugged or Defective Tubes Found1987-03-25025 March 1987 Steam Generator Tubing Inservice Insp Rept for Fifth Refueling Outage.Minor Tube Wall Degradation Indications Observed in Steam Generators a & B.No Plugged or Defective Tubes Found 1CAN028703, Steam Generator Tubing Inservice Insp Rept for Seventh Refueling Outage1987-02-0404 February 1987 Steam Generator Tubing Inservice Insp Rept for Seventh Refueling Outage ML20154H9451986-02-20020 February 1986 Steam Generator Tubing Inservice Insp Rept for 2R4 Refueling Outage ML20073M9491983-04-18018 April 1983 Inservice Insp Rept for 821210-830225.Rept Describes Exam of Tubes in once-through Steam Generators a & B ML19320A4511979-08-0808 August 1979 Inservice Insp Rept on Steam Generator Tubes for Refueling Outage 3 1998-07-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
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ARKANSAS NUCLEAR ONE - UNIT TWO STEAM GENERATOR TUBING INSERVICE INSPECTION REPORT FOR 2R4 REFUELING OUTAGE o
INSPECTION
SUMMARY
An inservice eddy current inspection was performed on a selected sample of tubes in the Arkansas Nuclear One Unit Two Steam Generators "A" and "B" during the period from March 22, 1985 through March 25, 1985. Since the previous test was concluded in October, 1983, the inspection frequency requirement (24 months per Technical Specification 4.4.5.3.a) was satisfied.
The inspection was conducted in accordance with Technical Specifications 4.4.5.1 and 4.4.5.2. The sample included a 3% random sample from the steam generators with exceptions as provided in Technical Specifications 4.4.5.2.a and 4.4.5.2.b.
In total, approximately 4.7% (399 tubes) of the tubes in the "A" steam generator and 4.7% (401 tubes) of the tubes in the "B" steam generator were inspected from the hot leg side. All but 7 of the 399 tubes tested in the "A" steam generator and all but 9 of the 401 tubes tested in the "B" steam generator were tested full length. The remaining 16 tubes were tested, at a minimum, over the U-bend and down the cold leg past the #11 and #10 drilled support plates. The multi-frequency method of eddy current testing was utilized during this inspection accumulating dent, flaw, and sludge depth data simultaneously. Details of the inspection methodology and equipment used are given in the attachment.
INSPECTION RESULTS Minor tube wall degradation indications were observe 1 during the data analysis for both ' A" steom generator and "B" steam generator in both the hot and cold leg sides. No defective tubes (2 40% throughwall degradation) were found.
Tables 1 and 2, attached, give a complete list of tube wall indications found in the "A" and "B" steam generators.
WP860134 PAGE 1 2
8603100410 860220 PDR ADOCK 05000368 G PDR i
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TABLE 1 LIST OF TUBES CONTAINING INDICATIONS S/G "A" IIOT SIDE LINE R0W % INDICATION LOCATION 73 121 < 20 #4+8" 89 59 < 20 #8+12" 103 91 < 20 #4+11.2" 103 91 < 20 #4+24" 103 91 23 #5+.9" 103 91 < 20 #5+19.4" 107 91 < 20 #5+6.1" 107 91 35 #5+18.2" LIST OF TUBES CONTAINING INDICATIONS S/G "A" COLD SIDE LINE ROW % INDICATION LOCATION 105 135 < 20 #4+21" 105 135 < 20 #8+12.9" WP860134 PAGE 2 L
TABLE 2 LIST OF TUBES CONTAINING INDICATIONS l S/G "B" HOT SIDE LINE R0W % INDICATION LOCATION 78 132 < 20 #1+2.7" 92 86 < 20 #3+7.5" 93 69 28 #6+18.9" 93 83 < 20 #1+14.9" 93 89 < 20 #2+21.6" 96 82 < 20 #5+1" 97 73 < 20 #2+9.1" 105 135 21 16.7" from #3BW 107 117 24 11.1" from #1BW LIST OF TUBES CONTAINING INDICATIONS S/G "B" COLD SIDE LINE R0W % INDICATION LOCATION 93 69 < 20 #0+7.5" 122 20 < 20 #1+13.1" 110 32 < 20 #6+5.6 NOTE: BW stands for Bat Wing which is a vertical support at the top of the steam generator.
WP860134 PAGE 3 L
ATTACHMENT METHODOLOGY The inspection program satisfied the requirements of the USNRC Regulatory Guide 1.83, Revision 1, (July 1975), " Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes." The inspection program was conducted in accordance with approved vendor-supplied procedures and the ANO-2 Technical Specifications.
The inspection program consisted of utilizing multi-frequency eddy current techniques to collect steam generator tube dent and defect data with the testing f requencies of multi-frequency eddy current tester setup as follows:
- Channel 1 Frequency at 400 KHz
- Channel 2 Frequency at 200 KHz
- Upper Mixer for Minimum Tube Support Plate Response
- Channel 3 Frequency at 400 KHz (low gain)
- Channel 4 Frequency at 100 KHz ABS While conducting the inspection, the signal generated by the eddy current probe was fed into an eight channel tape recorder which recorded on magnetic tape all four frequencies (two channels each) of the multi-frequency tester.
Channel No. 1 of the eddy current test was set at 400 KHz. Based on past experience, this frequency provides for optimum response for tubing of the diameter and wall thickness of that used in the A:iO-2 steam generators. The 400 KHz frequency constitutes a data base for these steam generators to which future inspections can be compared. The sensitivity of this channel was adjusted to allow for calibration to a standard containing known defects.
Channel No. 2 of the eddy current tester was set at 200 KHz. The output of this channel and the 400 KHz output from Channel No. I was fed into the upper mixers unit for the purpose of suppressing the tube support plate signals. A section of drilled carbon steel plate simulating the tube support plate was placed over the calibration standard. The mixer was then adjusted such that the signal generated by the tube support plate was eliminated. After adjustment and calibration, the output of the mixer provided only the signal originating within the tube itself. Therefore, any flaw indication generated by the tube in the area under the tube support plate would be more easily detectable.
Channel No. 3 of the eddy current tester was set at 400 KHz for detection of denting. The sensitivity of this channel was adjusted to a dent standard signal of known dimension.
Channel No. 4 of the eddy current tester was set at 100 KHz absolute. This data provides additional information to aid in defect detection and analysis.
The data from the inspection program was recorded on magnetic tape and on strip charts. These recordings were analyzed to evaluate the extent of tube t
wall anomalies and the results were recorded.
WP860134 PAGE 4
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EQUIPMENT The complete eddy current inspection system can be broken down into two categories, inspection equipment and probe positioning equipment. The eddy current inspection equipment consists of:
- Zetec MIZ-12 Multi-Frequency Eddy Current Tester with dual mixers 4 Channel Strip Chart Recorder (Gould 2400) or equivalent 8 Channel Hewlett-Packard Magnetic Tape Recorder or equivalent
- Eddy Current Test Probes (A560SF) or equivalent
- Calibration Standards (Defect Standard per ASME Section XI plus Dent Standard)
- A Supply of Magnetic Tape and Strip Chart Paper
- Zetec Digital Data Analyzer (DDA-4)
The probe positioning and drive system consists of:
- SM-4 Positioner and Templates
- A Closed Circuit Television System
- A Probe Drive Mechanism
- A Communication System Special sensing probes fabricated f or the specific tubing to be tested and designed to negotiate the bends in the tubing are used. The probes are attached to nylon . tubing which is used to insert and withdraw the probe. The instrument leads and a stainless steel safety wire pass through the nylon tube.
The probe insertion and withdrawal mechanism is a device which ensures a constant probe speed when recording the eddy current test results. This is important in that accurate location of any eddy current indication is dependent on constant probe speed since tube length is correlated with strip chart speed.
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The probe positioning device (SM-4) is a remote control mechanical arm which can be pcsitioned to feed the probe into any tube in the steam generator. It consists of a mounting stanchion and two mechanical arms driven by stepping motors. A remote camera and lighting system is mounted on the SM-4 allowing the operator to see probe insertion and to identify the tube being tested. A tube sheet template is installed and removed in sections and is held in place on the tube sheet by template plugs which are forced into particular tubes.
The SM-4 and templates provide a fast and easy means of positioning the probe and identifying the tube being tested. Test speed and probe positioning accuracy is of benefit when using this system on a large testing program.
ECT EQUIPMENT OPERATION The MIZ-12 multi-frequency eddy current tester uses eddy currents as the probing media to measure variations in effective conductivity and/or permeability of the tube being tested. In non-magnetic materials, such as Inconel, conductivity is usually the only significant variable. When the effective conductivity decreases due to a discontinuity in the tube wall, the test coil voltage increases in direct relationship with the effective conductivity change. Thus, the amount of increase in coil voltage is related to the size of the discontinuity. The coil voltage is sinusoidal, thus it can be described with a single vector having magnitude and phase. The MIZ-12 system provides a method for reading out two quadrature components of the test coil voltage vector. In addition, the MIZ-12 multi-frequency eddy current tester is a highly versatile and compact eddy current inspection system. Utilizing a " Time Sharing" technique, the operator may test at up to four (4) frequencies simultaneously. The MIZ-12 contains two mixing circuits, giving the operator the ability to subtract out most undesirable data (i.e., noise, support signals, etc.). The CRT display allows the operator to view the mixer output as well as the test signals.
The response from the eddy current tester is fed through the memory oscilloscope to the tape recorder and then to the strip chart recorder. Audio input (microphone) is also provided to record the identity of the tube being tested at the start of each test. The recorded data can be analyzed with the aid of the Zetec DDA-4 digital data analyzer.
The defect and dent calibration standards used were ANO-85-1000 and ANO-85-1001 in-line standards. They are 3/4 0.D., Inconel-600 tubing with .048-inch average wall thickness including artificial (machined) defects and dents. The standards were made in accordance with the ASME Code,Section XI.
The data from the inspection program was recorded on magnetic tape and on strip charts. These recordings were analyzed to evaluate the extent of tube wall anomalies.
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