IR 05000409/1979007
| ML19269E158 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/27/1979 |
| From: | Danielson D, Livermore H, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19269E157 | List: |
| References | |
| 50-409-79-07, 50-409-79-7, NUDOCS 7906260589 | |
| Download: ML19269E158 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/79-07 Docket No. 50-409 License No. DPR-45 Licensec: Dairyland Power Cooperative 2615 East Avenue - South La Crosse, WI 54601 Facility Name:
la Crosse Boiling Water Reactor Inspection At:
La Crosse Site, Genoa, Wisconsin Inspection Cor. ducted: April 9-11, 1979
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Inspectors:
D W
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.H Liverm U N kyne...,lh~
4 njy Approved By:
D.
. Danielson, Chief Engineering Support Section 2 Inspection Sun: mary Inspection on April 9-11, 1979 (Report No. 50-409/79-07)
Areas Inspected: QA/QC program, implementing procedures', observation of work activities and review and evaluate nondestructive examination (NDE) data and reports of inservice inspection; peripheral throud replacement. The inspect *on involved a total of 28 inspector-hours onsite by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Dairyland Power Cooperative (DPC)
H. Jorgensen, Loss Prevention Specialist, State Authorized Inspector (AI)
The inspectors also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview.
Functional or Program Areas Inspected 1.
General Information DPC requested Southwest Research Institute (SWRI) to develop a.
and perform the inservice inspection program in.ccordance with ASME Section XI, 1974 Edition, Summer 1975 Addenda.
b.
This is the ninth outage for LACBWR.
The next outage will be in approximately one year.
The AI was hired as the third party by the State of Wisconsir.
c.
for the ISI.
2.
Review of Program The inspectors established through review and discussion a.
with the licensee representatives that the program require-ments for ISI were in accordance with ASME Section XI, 1974 Edition, Summer 1975 Addenda.
b.
The Project Plan for the 1979 ISI of th2 LACBWR, 79-DLC-LER-1-1-0, Copy No. 4, April 1979, is as per Purchase Order No.
A68830 and "10 Year ISI Plan, LACBWR," dated April 1976.
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c.
The SWRI Nuclear Quality Assurance Program Manual No. 96 provided the implementation of QA/QC measures responsive to NRC requirements.
No items of noncompliance or deviations were identified within the areas reviewed.
3.
Review of Procedures The following procedures that are applicable to this activity were reviewed.
Visual Examination of Nuclear Reactor Components by Direct a.
or Remote Viewing, SWRI-NDT-900-1, Rev. 42, July 11,1978.
b.
Manual Ultrasonic Examination of Thin Wall Piping Welds, SWRI-NDT-800-36, Rev. 22, March 9, 1979.
c.
Mechanized Ultrasonic Examination of Ferritic Vessels 2 1/2" or Greater in Thickness, SWRI-NDT-700-6, Rev. 1, July 26, 1978.
d.
Manual Ultrasonic Examination of Pressure Retaining Round Nuts 2" or Greator in Diameter, SWRI-NDT-600-19, Rev. 26, March 8, 1979.
Manual Ultrasonic Examination of Pressure Vessel Welds, e.
SWRI-NDT-600-15, Rev. 39, February 28, 1979.
f.
Special Process Control NQAP-11-1, Rev. 1, March 1977.
g.
NDE Qualification, Training, Examination and Certification, IX-AG-1-1, August 1974.
h.
Deviations to Nuclear Field Services Section Operating Procedures, IX-FE-101-1, September 1976.
1.
Weld Joint Identification Marking on Nuclear Power Plant Piping, IX-FE-103-1, February 1977.
j.
Measuring and Recording Search Unit Location and Maximum Signal Amplitude Data During Ultrasonic Weld Examinations, 1X-FE-104-2, March 1978.
k.
Recording Data from Direct Visual Liquid Penetrant and Magnetic Particle Examination of Welds, IX-FE-105-0, September 1978.
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1.
Measuring and Recording Search Unit Location and Signal Amplitude Data During Ultrasonic Examinations of Pressure Vessel Welds, IX-FE-109-1, February 1978.
" Black Light" Intensity Measurements, IX-FE-llO-0, January m.
1978.
Onsite NDT Records Control, X-FE-101-0, March 1976.
n.
Control of Nuclear Inspection Equipment XIII-AG-101-0, June o.
1977.
p.
Manual Ultrasonic Examination of Vessel-to-Nozzle Inner Radius Sections, SWRI-NDT-600-11, Rev. 28, March 8, 1979.
q.
Manual Ultrasonic Examination of Nuclear Reactor Pressure Vessel Flange Ligaments, SWRI-NDT-600-5, Rev. 27, March 6, 1979.
Manual Ultrasonic Examination of Pressure Piping Welds, r.
SWRI-NDT-600-3, Rev. 52, March 9, 1979.
Fluorescent Magnetic Particle Examination, SWRI-NDT-300-2, s.
Rev. 25, March 6, 1979.
Liquid Penetrant Examination Color Contrast Method, t.
SWRI-NDI-200-1, Rev. 46, February 14, 1979.
LACBWR, Special Test Procedure, ISI 10 Year System Test u.
Procedure, SPT-79-01, REv. O, February 19, 1979.
No items of noncompliance or deviations were identified within the procedures reviewed.
4.
Observation of Work and Work Activities The inspector observed work and had discussions with SWRI a.
personnel during review of the ISI activities.
These observations included calibrations, preparation of welds performance of the examinations and the documentation.
b.
Fluorescent magnetic particle examination was observed being performed on the reactor head flange nuts and studs.
Liquid penetrant and ultrasonic examinations were observed being performed on the Boron Injection Core Spray System piping welds.
No items of noncompliance or deviations were identified in areas witnessed.
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5.
Data Review and Evaluation Review of the data files for the following systems demonstrated that the QA/QC and technical requirements were met.
The specified information was available for ultrasonic (UT) liquid penetrant (PT), magnetic particle (MT) and visual (VT) examinations performed.
a.
Reactor Pressure Vessel and Closure Head b.
8" Decay Heat System Suction Piping 6" Decay Heat System Discharge Piping c.
d.
4" Core Spray System Piping 4" and 6" Feedwater System Piping e.
f.
2 1/2" Born Injection System Piping No items of noncompliance or deviations were identified.
6.
Material and Equipment Certification The inspector examined and verified the adequacy of the ultrasonic calibration standards, preparation of weldments and certification documents relative to the following items.
a.
Ultrasonic Couplant - batch No. TB-09058-3 b.
Magnetic Particles - batch No. 78F020 c.
Liquid Penetrant Materials - batch No. 7H151 Penetrant
- batch No. 7LO68 Developer
- batch No. 7K043 Cleaner d.
Various ultrasonic calibration blocks, instruments and
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transducers, also magentic particle instruments.
No items of noncompliance or deviations were identified.
7.
NDE Personnel Certifications The inspectors reviewed the following SWRI personnel certifi-cations in accordance with SNT-TC-1A, 1975 Edition.
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Name Methods Levels J. Brode VT-UT I
"
MT-PT I (Limited)
H. Clark PT-VT-MT-UT II
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UT I
A. Clay VT-MT I (Limited)
"
PT-UT I
C. Cotton VT-PT-UT I
A. Jaschke VT-PT-UT-MT I (Limited)
No items of noncompliance or deviations were identified.
8.
Peripheral Shroud Replacement During the 1977 refueling outage, visual inspection of the a.
LACBWR reactor internals by DPC resulted in the discovery of two cracks in the peripheral shroud.
The larger of the two cracks in the shroud completely severed the 1.5" ligiment support on one end of an upper louver.
The second crack was in a similar location but extended only partially across the ligiment.
The louver and associated shroud ligiment in the vicinity of the through crack was removed for metallurgical examination.
This examination was performed by Battelle Columbus Laboratories. They con-cluded that the failures in the shroud were initiated by mechanical defects in the weld passes where the horizontal and weld defects provided severe notches that raised the level of cyclic stresses above the levels required to initiate and proprogate fatique cracks.
Battelle, in addition, recommended that a planned replacement and redesign of the shroud should be implemented. DPC, therefore, requested Nuclear Energy Services (NES) to design a new shroud to replace the existing one, b.
The principle changes to the peripheral shroud are (1)
reduced potential for stress-corrosion cracking because of the substitution of 304L S/S materials for the original 304 S/S, (2) increase of approximately 50% in the wall thickness of the shroud, (3) providing hold down gusset on the louvers to reduce the possibility of fatique failure due to vibration.
The modifications increase the margin of safety for structural integrity of the core internals, The shroud was fabricated by Nuclear Components Incorporated c.
(NCI), Great Barrington, Massachusetts, in accordance with ASME Section III, Div. 1, 1977 Edition with no Addenda.
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d.
The welding and NDE vere performed in accordance with ASME Section IX, V and III,1977 Edition with no Addenda and the NES Specification for the Fabrication and Inspection of the LACBWR Replacement Peripheral Shroud No. 80A1807. Rev. 1, September 19, 1978.
e.
The inspectors examined the velding of the shroud and reviewed the following procedures.
(1) NCI Process and Inspection Procedure LACBWR Replacement Peripheral Shroud No. NCI-PO-111778-1B, Rev. O, November 21, 1978.
(2) NCI, Receiving Inspection NCI-R1-061173-1B, Rev. 2, June 11, 1973.
(3) NCI, Liquid Penetrant Test Procedure for Water Washable Visible Color Contrast Type Materials of Method B-1 of SE-165, NCI-PT-110878-1S, Rev. 1, November 21, 1978.
(4) NCI, Cleaning Procedure, NCI-CL-052375-1L, Rev. O, May 23, 1975.
(5) NCI, Visual Inspection, NCI-VI-012276-1S, Rev. O, January 23, 1976.
f.
The inspectors also reviewed welding and welder qualifica-tions, visual and dimensional examinations, chemical analysis and tensile results, welding wire and material certifications, liquid penetrant record report dated March 21, 1979, NCI Manufacturing and QA audit by DPC dated December 15, 1978, NES Manufacturing and QA audit by DPC dated December 14, 1978, acetone certification for let No. 66553, and Magnaflux materials penetrant batch No. 78C018 and developer batch No. 7H099.
g.
The inspectors determined that applicable weld procedures and weld material were used, appearance of weld surface was acceptable.
No items of noncompliance or deviations were identified.
Exit. Interview The inspectors met with Mr. H. Towsley, QA Supervisor, at the conclusion of the inspection. The inspectors summarized the scope and findings of the inspection noted in this report.
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