IR 05000409/1986010

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Insp Rept 50-409/86-10 on 860724-0828.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp Activities,Licensee Action on Generic Ltr 84-11 & DHR Pump Suction Line Repair
ML20209G856
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 09/10/1986
From: Danielson D, David Jones
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20209G855 List:
References
50-409-86-10, GL-84-11, NUDOCS 8609150090
Download: ML20209G856 (6)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-409/86010(DRS)

Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue - South Lacrosse, Wisconsin 54601 Facility Name: Lacrosse Boiling Water Reactor Inspection At: Lacrosse Site, Genoa, Wisconsin Inspection Conducted: July 24-25 and August 7-8, 12-14, 26-28, 1986

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Inspector: . Jones 7-/O-8 (,

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'O Approved By: D. H. Danielson, Chief Materials and Processes Date Sectica Inspection Sunnary Inspection on July 24-25 and August 7-8, 12-14, 26-28, 1986 (Report No. 50-409/86010(DRS))

Areas Inspected: Routine unannounced inspection of inservice inspection (ISI)

' activities, licensee action on NRC Generic Letter 84-11 and the decay heat removal pump suction line repair. This report addresses the following module numbers: 73755, 73051, 73052, 37701, 55700 and 5770 Resul ts: No violations or deviations were identified.

U 8609150090 860910 PDR ADOCK 05000409 G PDR

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DETAILS Persons Contacted Dairyland Power Cooperative (DPC)

  • R. Wery, QA Supervisor P. Sampson, ISI Coordinator D. Rybarik, Mechanical Engineer Factory Mutual Engineering D. Kiltenen, ANII The inspector also contacted and interviewed other licensee and contractor employee * Denotes those present at the final exit intervie . Inservice Inspection (ISI) General This is the fifth outage of the second ten year pla DPC performed the surface nondestructive examination (NDE) of the small diameter piping and contracted with Southwest Research Institute (SWRI), to perform the augmented ultrasonic examination (UT) of stainless steel piping welds and with Materials Quality Services. (MQS) to perform the UT of the reactor vessel and Class 2 radiographic examination (RT), in accordance with ASME Section XI, 1974 Edition, Summer 1975 Addend The SWRI NDE personnel responsible for performing the UT examinations of the stainless steel piping welds had successfully passed the EPRI Detection Practical Examinatio Program / Procedure Review

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The NRC inspector reviewed the following program / procedures:

  • SWRI " Ten-Year Inservice Examination Plan far Class 1 Components of Lacrosse Boiling Water Reactor, Second Inspection Interval."
  • SWRI, " Project Plan for the 1986 Inservice Examination

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of the Lacrosse Boiling Water Reactor," 86-DLC-LBR-1-1- * DPC, Visual Examination by Direct or Remote Viewing, QACP-1.1, Issue _ - - - - - . . . - . .- , .-

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  • DPC, Liquid Penetrant Examination Solvent Removable Color Contrast Method, QACP 1.2, Issue * SWRI, Manual Ultrasonic Examination of Pressure Piping Welds, NDT-600-3, Revision 62, Devs. 6, * SWRI, Manual Ultrasonic Examination of Small-Diameter Piping Welds, NDT-600-39, Revision 5, Dev. 1
  • SWRI, Manual Ultrasonic Examination of Thin Wall Piping Welds, NDT-800-36, Revision 35, Dev. * MQS, Calibration and Certification of UT Equipment, 22.A.11, Revision * MQS, UT Exam-General RequirementsSection XI, 22.A.600-575, Revision * MQS, UT Exam of Class 1 and Class 2 Ferritic Vessel Welds, 22.A.615-575, Revision * MQS, UT Exam of Nozzle Inner Radius Sections, 22.A.639-S75, Revision * MQS, Penetrant Examination Visible Dye, 23.A.100-575, Revision No violations or deviations were identifie c. NDE Personnel Certifications The NRC inspector reviewed NDE Personnel Certifications in accordance with SNT-TC-1 No violations or deviations were identifie d. Material and Equipment Certification The NRC inspector reviewed the certification documents, relative to the following items:
  • Ultrasonic instruments, transducers

No violations or deviations were identifie e. Data Review The NRC inspector reviewed report documentation relative to the following:

  • Ultrasonic examination

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No violations or deviations were identifie . Status of Inspections of BWR Stainless Steel Piping (Generic Letter 84-11)

Augmented examinations in accordance with NUREG 0313 guidelines currently include 97 welds which also fall under Generic Letter 84-11 requirement Eighty six of these welds were inspected during Outages 5 (1985) and 6 (1986) by EPRI qualified ultrasonic inspection personnel. No cracking was note In addition to the welds currently included in the augmented examination schedule, DPC has identified 133 welds which meet Generic Letter 84-11 requirements for inspection. A sample of these welds will be inspected during the 1987 outag . Decay Heat Removal Pump Suction Line Repair General While in the hot shutdown mode following a reactor trip, which occurred July 16, 1986, seepage was observed through two small cracks near a purge port plug in the 8 inch, 304 stainless steel decay heat suction line. Preliminary results of the metallurgical analysis indicates that the area surrounding the purge port plug was at least partially sensitized and that the cracks were as a result of stress corrosion. An 11.307 inch section of the decay I heat suction line was removed and replaced by a section of 304L stainless steel pip Westinghouse-Power Cutting (W-PC) was contracted by DPC to perform the pipe replacement. Scuthwest Research Institute (SWRI) and Materials Quality Services (MQS) were contracted to perform the nondestructive examinations. SWRI performed the ultrasonic examination of the weld utilizing EPRI qualified personne Heat sink welding was used to perform the repair. Heat sink welding is performed by running water through the piping after the root has been completed. The remaining weld is then performed while the water is running through the pipe. The advantage in using heat sink welding is to induce a state of residual compressive stresses on the ID of the pipe. Compressive stresses aid in mitigating stress corrosion cracking. DPC is currently in a 3 1/3 year inspection interval, however, NRR is currently reviewing the heat sink welding procets to determine the extent of credit that will be given for this stress improvement process. Pending the outcome of this review by NRR, this will remain an open item (409/86-10-01).

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' Procedure Review The NRC inspector reviewed the following procedures:

  • DPC, Repair of 8-inch Decay Heat Pump Suction Pipe Leaks, M-56-01, Issue * DPC, Liquid Penetrant Test Procedure, QACP-1.2, Issue * MQS, Radiographic Examination of Welds, 20.A.1 - Summer 1975, Revision * SWRI, Manual Ultrasonic Examination of Pressure Piping Welds, NDT-600-3, Revision 6 * W-PC, Welding Procedure Specification, WPS 9803, Revision No violations or deviations were identifie Personnel Certifications The NRC inspector reviewed the following personnel certifications:
  • Welding No violations or deviation were identifie Material and Equipment Certification The NRC inspector reviewed the certification documents, relative to the following items:
  • Ultrasonic instrument, transducers
  • Liquid penetrant materials No violations or deviations were identifie Document / Data Review

The NRC Inspector reviewed documentation / data relative to the i following:

  • Traveler packages
  • Joint process control sheet

> * Maintenance request

  • Ferrite scan
  • Ultrasonic test reports
  • Radiographic test reports and film No violations or deviations were identifie _ _ _ _ _ _ _ _ _ _ _ . _-- _ _ - . - _ , . - - _

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5. Open Item Open items are matters which have been discussed with the licensee, which will be reviewed further oy the inspector, and which involves some action on the part of the NRC or licensee or bot An open item disclosed during this inspection is discussed in paragraph 4a.

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6. Exit Interview The inspector met with site representatives (denoted in persons contacted paragraph) at the conclusion of the inspection. The inspector summarized scope and findings of the inspection noted in this report. The inspector

also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietary.

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