IR 05000454/1990004
| ML20033F376 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/05/1990 |
| From: | Danielson D, Jeffrey Jacobson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20033F374 | List: |
| References | |
| 50-454-90-04, 50-454-90-4, NUDOCS 9003200216 | |
| Download: ML20033F376 (7) | |
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U.-S. NUCLEAR REGULATORY COMMISSION REGION 111 Report No. 50-454/90004(DRS)
Docket No. 50-454 License No. NPF-37 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Byron Station - Unit 1 Inspection At: Byron Site, Byron, IL 61010-9750 Inspection Conducted: January 16 through February 16, 1990 b/
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J.'. 4aco on-Date o d W sfl u d ! b
'fo Approved By:
D. H. Danielson, Chief Date'
Materials and Processes Section Inspection Summary inspection on January 16 through February 16, 1990 (Report No. (50-454/90004(DRS))
Areas Inspected: Routine, announced safety inspection of the licensee's inservice inspection (ISI) activities including review of program (73051),
procedures (73052), work activities (73753), and inspection data (73755).
Results:
No violations or deviations were identified.
Based on the results of the inspection, the NRC inspector noted the following:
The licensee adequately demonstrated the ability to properly implement
the ISI program.
Personnel involved in the ISI effort appeared knowledgeable, well trained,
and competent.
Applicable procedures were well stated and workable,
Management was involved in the ISI activities in an effective manner.
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DETAILS 1.
Persons Contacted Commonwealth Edison Company (Ceco)
- R. Pleniewicz, Station Manager R. Ward, Technical Superintendent
- F. Flahive, Technical Staff Supervisor
- D. Wozniak, Site Project Manager
- J. Harkness, 151 Group Leader
- M. Kennedy, ISI Engineer
- J. Smith, ISI Engineer
- M. Snow, Regulatory Assurance Supervisor D. Winchester, Quality Assurance Engineer E. Little, Regulatory Assurance
- K. Orris, Regulatory Assurance EBASCO J. Sengenberger, Site Supervisor B. Focer, Level 11 (NDE) )
J. Newgard, Level 11 (NDE V. Gruno, level 11 (NDE)
T. Speide, Level 11 (NDE)
U. S. Nuclear Regulatory Commission (U. S. NRC)
W. Kropp, Senior Resident inspector
.The NRC inspector also contacted other licensee and contractor employees.
- Denotes those participating in the exit interview on February 16, 1990.
2.
Inservice Inspection (ISI)
a.
Review of Program (73051)
.EBASCO, Babcock and Wilcox (B&W), and CECO performed the ISI in accordance with ASME Section XI, 1983 Edition, Summer 1983 Addenda.
There was sufficient organizational staff to ensure that acceptable ISI work was performed. Where ASME requirements were determined to be impracticable, specific relief requests were requested from the Office of Nuclear Reactor Regulation (NRR). The NRC inspector reviewed the specific relief requests including the related correspondence between the licensee and the NRC.
During the course of program implementation, the licensee identified two feedwater nozzle welds which had not been previously examined during the preservice inspection activities. These welds were subsequently examined and the baselines established.
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b.
Review of Procedures and Personnel Certification (73052)
(1) EBASCO Procedures
" Ultrasonic Examination of Class 1 and 2 Piping Welds
Joining Similar and Dissimilar Materials", No. BY-UT-583-1, Revision 1.
" Ultrasonic Examination of 4.5" Diameter, 35" Long Carbon
Steel Reactor Coolant Pump Studs", No. BY-UT-583-6, Revision 0.
" Ultrasonic Straight Beam Examination of Piping _ Welds",
No. BY-UT-583-7, Revision 0.
" Ultrasonic Examination of Flange Ligament Areas of
Reactor Pressure Vessels", No. BY-UT-583-9, Revision 0,
" Ultrasonic Straight Beam Examination of RPV Shell to
Flange Welds", No. BY-UT-583-9, Revision 0.
" Ultrasonic Examination of Class 1 and 2 Bolts and Studs",
No. BY-UT-583-10, Revision 0.
" Ultrasonic Examination of Reactor Pressure Vessel and
Steam Generator Safe End Welds", No. BY-UT-583-11, Revision 0.
" Ultrasonic Manual Examination of Reactor Coolant Pump
Flywheels", Revision 0.
" Magnetic Particle Examination of Welds and Bolting",
No. BY-UT-583-1, Revision 0.
" Liquid Penetrant Examination", No. BY-PT-583-1,
Revision 0.
" Procedure for Inspection System Performance Checks",
No. BY-UT-CP-2, Revision 0.
" Ultrasonic Manual Examination of Class 1 and 2 Vessel Welds including Reactor Pressure Vessel Welds", No.
BY-UT-583-2, Revision 0.
" Ultrasonic Examination of Class 1 and 2 Vessel Welds Less Than or Equal to 2 Inches", No. BY-UT-583-4, Revision 0.
" Remote Visual Examination of the Reactor Vessel
Internals", No. BY-VT-583-5, Revision 0.
The above procedures were found to be in accordance with the ASME Code,1983 Edition with Sumer 1983 Addenda.
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(2) EBASCO Personnel Certifications NAME ASNT LEVEL J. Sengenberger Ill N. Bollingmo
B. Focer
G. Valentine
P. Nash
J. Newgard
R. Niziol
T. Oddson
D. Roeters
T. Spelde I
The above certifications were found to be in accordance with SNT-TC-1A(ASNT).
(3) B&W Procedures
"Multifrequency Eddy Current Examination of.750" 0D
x.044" Wall RSG Tubing for ASME Examination and Wear at Tube Support Plates", No. 1S1-424, Revision 15.
" Eddy Current Examination of Tubing by the Absolute
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Multicoil (8x1) Technique", No. 151-425,. Revision 11.
" Technical Procedures for the Evaluation of Eddy Current
Data of Nuclear Grade Steam Generator Tubing", No, 151-460, Revision 14.
" Technical Procedure for the Evaluation of Eddy Current
Data for Debris and Sludge in Steam Generators", No, ISI-462, Revision 4
" Technical Procedure for the Evaluation of Eddy Current
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Data Generated from the Multielement Probe" No. 151-463, Revision 6.
" Technical Procedure for the Evaluation of Eddy Current
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Data of Nuclear Grade Steam Generator Tubing for Wear Fretting", No. ISI-464, Revision 2.
" Technical Procedure for Use of the Automatic Data Screening System for Evaluation of Nuclear Steam Generator Tubing Eddy Current Data w/ attached B&W Drawing 1166888A, Revision 5", No. ISI-472.
" EDDY-360/RDAU System Operating Procedure", No.1S1-510,
Revision 8.
" Process Specification for Shot Peening.750" SG Tubes",
No. 51-1159413, Revision 3.
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" Field Procedure for Remote Shot Peening of SG Tubes",
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No. 1163035A, Revision 12.
" Operating Instruction for Shot Peening", No. 1163038A, Revision 7.
Eddy current examination procedures were found to be in accordance with the ASME Code,1983 Edition with Suniner 1983 Addenda, NRC Regulatory Guide 1.83 dated July 1975, and Code Case N-401.
(4) B&W Personnel Certifications
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NAME ASNT LEVEL L. Colado
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L. Cooper
J. Gardner
E. Korkowski IT G. Livesay
T. Mitchell
J. Oliver I
H. Smith III The above certifications were found to be in accordance with SNT-TC-1A(ASNT).
c.
Observation of Work Activities (73753)
The NRC inspector observed the following ultrasonic examinations of the main steam and feedwater systems:
Components Weld IMS01CC-32.76" C1, FW-161 1FW87CB-6" C3, FW-322 C7, FW-317 C5, FW-371 1FW87CC-6" C2 L
1FW81BC-6" C2 1FW81BB-6" C1.01, FW-1168 In addition, the inspector observed a magnetic particle examination of weld C3, FW-329 on line 1FW87CC-6". The above work activities were found to be performed in accordance with applicable Codes and procedures.
Modification No. M6-1-88-060 was performed to add a recirculation flush line to the pump No lAF01PA suction line to mitigate the buildup of silt from the essential service water system.
The NRC inspector reviewed the work package, NDE records, and observed application of a freeze seal and performance of the ASME Section 111 hydrostatic test.
The work activities associated with this modification were found to be in accordance with approved procedures and applicable Codes.
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d.
Review of Examination Data (73755)
During the course of evaluating UT indications in the root of weld
f FW-109 on the safety injection system, the licensee reviewed the original construction radiographs. During this review, a rejectable slag indication was noted on the film. While the UT indications were identified as acceptable root geometry, a decision was made to remove the slag. The NRC inspector examined both the construction film and the repair film and found the repair to be acceptable.
Magnetic particle examination of the "A" steam generator feedwater piping (1FWO3DA-16")disclosedlinearindicationsonthe16" diameter piping adjacent to welds FW-229 and FW-230. The NRC inspector reviewed the System Materials Analysis Department Report No. M-425-90 and found the reconinendation for defect removal to be prudent. The defects were subsequently ground out successfully,
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In addition to the steam generator tube eddy current inspections, 56 l
hot leg tube plugs considered susceptible to cracking were removed
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and replaced with Inconel Type 690.
In an effort to further mitigate tube degradation, rows 1 and 2 were stress relieved in the U-bend area during the outage. To further reduce the susceptibility
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of cracks in the tubes, shot peening was performed on approximately 29" of the ID of each tube, including approximately 2" above the tube sheets on the cold leg side of steam generators A, B, C, and D.
Extensive operating experience with PWR steam generators-indicates that the primary side of the roll transition area of the tubes is i
susceptible to Intergranular Stress Corrosion Cracking (IGSCC).
IGSCC requires a combination of tensile stress, susceptible material, and an aggressive environment. Elimination of any one of these conditions prevents IGSCC from occurring. The~ purpose of shot
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peening is to remove the tensile stress on the inside diameter i
surface of the tube and replace it with compressive stress.
Shot peening is a cold working process whereby an item is bombarded with round shot (in this case Type 316 stainless steel) leaving the i
surface in a residual compressive state. The system is an automated process thereby providing uniformity and repeatability.
The corrosion testing performed to qualify this process demonstrates that primary side IGSCC in the tube roll transition areas is effectively eliminated for the design life of the steam generators.
The NRC inspector reviewed a sample of both the UT and ET evaluations as well as the activities described above and found the evaluations to be conservative.
No violations or deviations were identifLc.
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3, Exit Interview (30703)
The inspector met with site representatives (denoted in Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely information 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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