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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML20197J3891997-12-18018 December 1997 25th Year Physical Surveillance of Palisades Npp ML20217C2571997-12-16016 December 1997 Review of Neutron Fluence Data for Palisades Reactor Pressure Vessel ML18067A6351997-07-0909 July 1997 Excerpt from Ampacity Evaluation for Open Air Cable Trays W/Percent Fill Greater than 30% of Useable Cross Sectional Area. ML18067A6381997-07-0909 July 1997 Excerpt from Ampacity Evaluation for Continuously Energized Power Cables Routed Through Fire Stops, Revision 1 ML18067A6371997-07-0808 July 1997 Excerpt from Ampacity Evaluation for Duct Runs Containing Continuously Energized Power Cables, Revision 1 ML18067A6361997-06-26026 June 1997 Excerpt from Ampacity Evaluation for Continuously Energized Power Cables in Open Air Conduits, Revision 1 ML18066A8581997-01-31031 January 1997 Rev 2 to C-PAL-96-1063-01, Operability Assessment for Transient Conditions at Palisades Nuclear Plant in Response to GL 96-06. ML18065B0471996-07-12012 July 1996 TR on Use of Mcbend Code for Calculation of Neutron Fluences in PVs of Lwrs. ML18065A7571996-05-22022 May 1996 Rev 1 to IPEEE Rept, Per GL 88-20 ML20108C1671996-04-0101 April 1996 Nonproprietary Version of Fluence Calculations for Palisades Plant ML18065A5971996-03-23023 March 1996 Evaluation of Effects of Fire on West Wall of Turbine Lube Oil Room Adjacent to Pipe Tunnel Between TB & FW Purity Bldg. ML18065A6011996-03-22022 March 1996 Evaluation of Effects of Fire on West Wall of CCW Pump Room (Fire Area 16). ML20100D7491996-01-18018 January 1996 Rev 0 to Evaluation of Effects of Fire on West Wall of TB Lube Oil Room Adjacent to Pipe Tunnel Between TB & FW Purity Bldg ML18065A4481995-12-14014 December 1995 Radiological Consequences for Palisades Max Hypothetical Accident & Loss of Coolant Accident. ML18064A8321995-06-30030 June 1995 IPE of External Events (Ipeee). ML20085H2801995-05-23023 May 1995 Security Investigation Rept ML18064A7801995-05-19019 May 1995 Rept of SQUG Assessment at Palisades Nuclear Plant for Resolution of USI A-46. ML20078P7021995-01-27027 January 1995 Investigative Rept ML18064A4121994-08-22022 August 1994 Pressure-Temp Curves & LTOP Setpoint Curve for Max Reactor Vessel Fluence of 2.192 X 10^19 Neutrons/cm^2. ML20070J8001994-07-15015 July 1994 Final Rept Containment Sump Check Valves Weld Overlay Repair Implementation Evaluation Palisades Nuclear Plant ML18059B0041994-04-0505 April 1994 Rev 1 to EDG Fuel Supply Sys Storage Tank Tornado Protection Overview of EDG Fuel Supply Sys, Incorporating CARB Comments of 940318 & 24 ML20064E5301994-03-0606 March 1994 Evaluation of Effectiveness of Code Case N-504-1 Repair for Proposed Root Causes for Containment Sump Suction Check Valves ML20064E4451994-03-0505 March 1994 Check Valve Leak Root Cause,Engineering Analysis & Repair/Replacement Options ML18059A5161993-10-31031 October 1993 Nonproprietary Exam...Sections of Pressurizer PORV Line Safe-End Failure from Palisades Nuclear Generating Station. ML20058P1361993-10-31031 October 1993 Crack Propagation Analysis for Circumferential Cracks in Alloy 600 Nozzle Safe-Ends ML18059A4821993-10-25025 October 1993 Evaluation of Potential Interference Between TE-0102 Nozzle & Thermowell. ML18059A4831993-10-25025 October 1993 Structural Evaluation for Machined Thermawell for TE-0101. ML20059D8811993-10-23023 October 1993 Justification of Weld Mods to Pressurizer Temperature Nozzles for TE-0101 & TE-0102 ML18059A4811993-10-22022 October 1993 Acceptability of Partial Severing of TE-0101 Nozzle. ML18059A4801993-10-19019 October 1993 Structural Analysis of Temperature Nozzle Weld Mods for Consumers Power Palisades Pressurizer. ML18059A4791993-10-15015 October 1993 Half Bead Welding for Mods to TE-0101 & TE-0102. ML18059A4221993-10-0707 October 1993 Pressurizer Safe End Crack Engineering Analysis & Root Cause Evaluation. ML18059A3751993-08-31031 August 1993 Rev 1 to Palisades Cycle 11:Disposition & Analysis of SRP Chapter 15 Events. ML18059B0191993-07-31031 July 1993 Detailed Site Study,Berrien County,Mi, Final Rept ML18064A4271993-06-30030 June 1993 Wind Tunnel Predictions of Control Room Intake Concentrations from Three Sources of Radioactive Materials at Palisades Nuclear Power Plant, (CPP-Project 93-0907) ML18058B8661993-05-13013 May 1993 Resolution of Anchor Bolt Design Issues. ML18058B3911992-12-21021 December 1992 Cycle 11:Disposition & Analysis of Standard Review Plan Chapter 15 Events. ML18058B4281992-11-30030 November 1992 Vols 1,2 & 3 of Palisades Nuclear Plant Ipe. ML18058A5391992-06-16016 June 1992 Twentieth Yr Physical Surveillance of Palisades Nuclear Plant. ML20086P8551991-12-0909 December 1991 Criticality Safety Analysis for Palisades Spent Fuel Storage Pool NUS Racks ML20086P8571991-12-0909 December 1991 Criticality Safety Analysis for Palisades New Fuel Storage Array ML18057B3521991-10-31031 October 1991 Large Break Loca/Eccs Analysis W/Increased Radial Peaking & Reduced ECCS Flow. ML18057A8591991-03-31031 March 1991 Benchmarking & Validation of In-House DOT Calculation Methodology. ML20081K7741990-08-14014 August 1990 Incore Detector Algorithm (Pidal) Analysis of Quadrant Power Tilt Uncertainties ML18057A2611990-06-11011 June 1990 Simulator Certification Submittal. 1999-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested 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 ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
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REVIEW OF H.A.F.A. INTERNATIONAL, INC.
INSTRUMENTED INSPECTION TECHNIQUE BY DR. MARVIN A. HAMSTAD PROFESSOR OF MECHANICAL ENGINEERING UNIVERSITY OF DENVER Date Ft:!. I::., 2-8 11 ft1 Dr. Marvin Hamstad
REVIEW OF HAFA'S IIT BY M.A. HAMSTAD Introduction At.the request of H.A.F.A. International, Inc. I have carried out an extensive review of the acoustic inspection technique as used by HAFA for the purposes Bf leak detection on power plant secondary pipe lines and the associated steam generators. The review was based on the following sources of information: 1) Final reports for tests performed for DLC, TED, CPC, and ORC (see Appendix I for listing); 2) Other technic~l documents provided by HAFA (see Appendix I; 3) The "Acoustic Emission Handbook" published by the American Society for Nondestructive Testing; 4) Discussions with HAFA employees and the manufacturers of the primary acoustic measuring systems; 5) List of "Task Group on Acoustic Problems Compilation of Concerns Raised"; and 6) Finally my own experience based on being continuously involved with acoustic emission technology for 18 years.
Findfngs First, the acoustic inspection technique does indeed detect leaks that occur.during the acoustically monitored increased pressure levels in the presence of normal plant start-up noise. This result is consistent with the extensive laboratory work by HAFA as well as the experience of many others over the last 20-25 years who have reported detecting leaks with acoustic emission techniques.
Second, the field application of acoustic leak detection requires systematic procedures that are consistent with the physics which governs the wave propagation from the leak source to the location where the acoustic monitoring sensors are located. If such an approach is followed, then not only are leaks detected at opportune locations (i.e., close to the acoustic sensor
REVIEW OF HAFA'S IIT BY M.A. HAMSTAD location) but also at locations between the positions of the acoustic sensors.
My ~xamination shows that the standard lead break calibration technique used by HAFA along with-reasonable sensor spacings does provide assurance that leaks (with acoustic_strengths equivalent or greater than the levels of those examined in the laboratory, in plant development tests, and in field tests to date) will be detected in the field. Current HAFA practice emphasizes a lead break on the pipe near the base of each acoustic waveguide. These lead breaks are carried out prior to the pressure test. HAFA uses this data primarily to verify the particular channel at which the lead break was made. This approach checks the sound transmission of: i) the adhesive from the pipe to the waveguide; ii) the waveguide (with welded conical sections); and iii) the adhesive between the waveguide and the sensor. It also checks the sensor and the subsequent electronics for the associated channel of the acoustic measurement system. In my opinion the data from these lead breaks also provides the information to check the sensitivity of the sensor to leaks
- located some distance from the sensor. By examining lead break calibration data I determined the amplitudes at the adjacent sensors and found them to be consistent with the values to be expected for reasonable sensor spacings.
Because of the importance of this additional verification, I recommend that in future reports HAFA include this information (which already exists) in a condensed fashion. If this recommendation is followed, then the wave propagation characteristics of the material between sensor locations will be clearly documented.
Third, since the acoustic test critically depends on maintaining sensitivity throughout the whole test, I have examined HAFA approaches towards assuring maintenance of sensitivity. Their approach has been three-fold: i) use of the response of adjacent sensors to normal changes in plant operating conditibns; ii) use of simulated leak sources; and iii) in some cases post-test 2
REVIEW OF HAFA'S IIT BY M.A. HAMSTAD lead bre~ks. These approaches are important due to the potential for the test conditions to disturb the sensitivity. There are at least three potential things that could happen: i) temperature rise resulting in loss of acoustic transmission due to an adhesive change or failure; ii) vibrations resulting in fracture of an adhesive bond; and iii) temperature effects on the sensors and/or preamplifiers. My findings indicate that the HAFA approaches are effective in finding extreme losses in sensitivity. The data from HAFA laboratory tests indicates that significant changes are unlikely. An extremely conservative approach would be to make more use of a few simulated sources that could be operated on demand during the test. These sources need to meet the requirement of a constant injection of acoustic energi that won't be changed by temperature rise, vibration, loss of pressure head, etc. Use of such sources would demonstrate that all channels had not been changed in a similar fashion by plant operation (e.g., higher temperature).
Fourth, the next critical link is the electronic instrumentation. HAFA has taken the approach of requiring certification of the instrumentation from the manufacturer. A conservative approach indicates that it is desirable for HAFA to check certain parts of the instrumentation and to establish their own calibration and certification approaches. These checks and calibrations should center on checking that channels are identical within certain limits. Two checks deserve special mention because they are most important in HAFA's measurements. These are the floating threshold and the root mean square (rms) measurements. Details of these checks and recommendations have been presented to HAFA under separate cover. My findings at the present time do not indicate that leaks have not been found due to instrumentation problems. But, the instruments need to be checked and an in-house procedure established.
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REVIEW OF HAFA'S IIT BY M.A. HAMSTAD Fifth, the analysis of the acoustic data forms the next link. I have
- examined-HAFA approaches along with their four-fold leak criteria. The use of both event type__data as well as the basic rms data provides internal checks.
Also the requirement that the all four conditions be met is consistent with both laboratory data and actual leaks found in the field. I have only one concern wi~h respect to these criteria. That is whether a quantitative number can be applied to the rate of events in the narrow amplitude band that is indicative of a leak. Another observation concerning the analysis procedures deals with the so-called first arrival data .. This data is determined by means of a so-called lockout time. Without getting to deeply into the technical details, the problem is that each event does not hit a consistent number of sensors. I believe data closer to what really happens could be obtained with a much lower value than the 20,000 s currently used. Curreatly first hit data is not a part of the four conditions which must be met, so the decision about what lockout time to use is not critical.
Sixth, in my review one aspect of the test environment needs to be checked. This aspect is the change in temperature during the test. *A conservative approach requires that each part of the acoustic test system be verified over its operating temperature range. Appendix II outlines these tests. Again I do not expect the results of these tests to change results to date, but a prudent approach requires these checks.
Seventh, I believe a review such as this should address limitations of the technique. The one key limitation, which can occur, is when background noise is very high the acoustic technique cannot detect leaks because the leak signal is then small in comparison to the background noise level. To date the large background levels have occurred at low pressure levels, and because of this fact they have not hidden leak noise throughout a whole test. There are only two approaches to overcome high background levels. The first is to move
REVIEW OF HAFA'S !IT BY M.A. HAMSTAD sensors_closer together. The second is to use a higher frequency bandpass .
- Both of these approaches are limited solutions. Prior to future applications at high frequency bandpasses of for example 400-600 kHz, the additional losses need to be more extensively characterized in the laboratory. Then such tests can be carried out with sensitivity equivalent to that for the 100-300 kHz bandpass when required.
Conclusion
- 1) The detailed examination of the HAFA acoustic leak detection approach indicates that there are no fundamental reasons why the technique does not detect leaks with high sensitivity in the test environments encounter to date.
- 2) The recommendations in this report refer primarily to additional checks to provide additional assurance.
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REVIEW OF HAFA'S IIT BY M.A. HAMSTAD APPENDIX I REFERENCES
- 1. Nondestructive Testing Handbook (Volume 5), 2nd ed., edited by Ronnie K.
Miller and Paul Mcintire. Columbus: American Society for Nondestructive Testing, 1987.
- 2. HAFA !IT-Acoustic Users Manual, July 18, 1988.
- 3. Topical Report HAFA 135 (P-A), December 1985.
- 4. HAFA Final Test Report - !IT-Acoustic Testing on Orange and Rockland Utilities' Lovett Station No. 3 Hot Reheat Line, January 6, 1989.
- 5. HAFA Final Report, Volume I - Main Steam Line IIT Acoustic Leak Test at Davis-Besse Nuclear Power Station, January 31, 1989.
- 6. HAFA Test Summary Report on Acoustic Emission Leak Detection on Main Steam Piping Systems, Main Feedwater Piping Systems, Steam Generator Slowdown Piping Systems (Volume I) to Duquesne Light Company, May 6, 1988.
- 7. HAFA Report on High Temperature Adhesive Evaluation (Toledo Edison Company) July 29, 1989. *
- 8. HAFA Internal Report on High Temperature Adhesive Acoustic Evaluation (Consumers Power Company) October 17, 1988.
- 9. Memorandum from A. Wehrmeister to H. Askwith and R. Milke.
Subject:
Real-Time Acoustic Analysis - Confirmation with DLC Data (October 13, 1988).
- 10. Memorandum from A. Wehrmeister to H. Askwith, et al.
Subject:
Real-Time Aco~stic Analysis (September 16, 1988).
- 11. HAFA Operating Procedures OP 12.12.
Subject:
Calibration of Test and Measuring Equipment (November 5, 1985).
- 12. HAFA Maintenance Procedure MP-1-06.
Subject:
Ears Equipment Calibration Procedures (January 3, 1989).
- 13. HAFA Report to Duquesne Light Company (BVPS) on Safety Injection Accumulator Acoustic Emission Examination (Procedure: IIT 11.13),
December 16, 1987.
- 14. HAFA Report to Duquesne Light Company (BVPS) on Safety Injection Accumulator Acoustic Emission Examination (Procedure: IIT 11.14),
December 16, 1987.
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