IR 05000255/1979014
| ML18044A563 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 01/15/1980 |
| From: | Danielson D, Key W, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18044A562 | List: |
| References | |
| 50-255-79-14, NUDOCS 8002250684 | |
| Download: ML18044A563 (12) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-255/79-14 Docket No. 50-255 Licensee:
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:
Palisades Nuclear Generating Plant Inspection At:
Palisades Site, Covert, Michigan Southwest Research Institute San Antossio, Texas License No. DPR-20 Inspection Conducted:
September 17 - 20, October 17 - 19, 24, 30, November 7, 30, December 6, 10, 1979, and January 7-9, 1980 c0~~
~-D.Ward~
Approved By: ~nielson, Chief Engineering Support Section 2 Inspection Summary r'
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1/1.l/5b I
Inspection on September 17 - 20, October 17 - 19, 24, 30, November 7, 30, December 6, 10, 1979, and January 9, 1980 (Report No. 50-255/79-14)
Areas Inspected:
QA/QC program, implementing procedures, observation of work activities, and review and evaluation of nondestructive examination (NDE) data and reports of inservice inspection (!SI); IE Bulletin 79-13 and IE Bulletin 79-17 activities. This inspection involved a total of 70 inspection hours onsite by two NRC inspectors and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at Southwest Research Institut Results:
No items of noncompliance or deviations were identifie bg'Lf
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Persons Contacted Consumers Power Company (CPCo)
J. Lewis, Plant Manager B. Harshe, Senior Engineer R. Vincent, Senior Engineer R. Kropp, General Engineer DETAILS G. Petitjean, Technical Engineer S. Samson, Technical Engineer, (ISI Coordinator)
E. Mccurdy, QC Engineer R. Looper, Level III Inspector
- E. Martiniz, Level III Inspector, (Technical Supervisor NDT)
R. Pacific, Level II Inspector L. Flasche, Welding Engineer J. Taylor, Senior Welding Engineer
- J. Kendziora, NDT Analyst Hartford Steam Boiler Engineering and Insurance Company (HSBE)
C. Ansorge, Authorized Nuclear Inspector (ANI)
M. Wolters, Authorized Nuclear Inservice Inspector (ANII)
S. Rathburn, Authorized Nuclear Inspector (ANI)
Michigan Department of Labor A. Kozlowski, Supervisor, Boiler Division Southwest Research Institute (SWRI)
- W. Flach, Director-Department of Engineering Services
- L. Albrecht, Manager of Quality Assurance
- D. Rosow, Manager, Nuclear Field Services
- J. Godwin, Technical Liaison Group Supervisor
- M. Gonzalez, Research Engineer-QA The inspectors also contacted and interviewed other licensee and con-tractor employee *Denotes those present at the final exit interview at the site on January 9, 1980, and January 8, 1980, at SWR Licensee Action on IE Bulletins The NRC forwarded IE Bulletin 79-13 titled, "Cracking in Feedwater System Piping" and IE Bulletin 79-17 titled, "Pipe Cracks in Stagnant Borated Water Systems", for specific action to be taken.
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- Being the plant was shutdown for its normal refueling outage, nonde-structive examination (NDE) were performed on the "A" and "B" steam generators (SG) nozzle to pipe and pipe to pipe welds; "A" SG, weld No. 251, 256, and 258 through 263 and "B" SG, weld No. 251, 255, 256, 256A, and 257 through 26 Radiographs of welds 257 through 262 on the "B" SG and RT of welds 259 through 262 on the "A" SG revealed varying degrees of linear indications in all the weld Radiographs of welds No. 251, 255, 256 and 256 A on the "B" SG and welds No. 251, 256, and 258 on the "A" SG were all found to be acceptabl The licensee made the decision to cut the nozzle weld at No. 263, and weld No. 258 on the "A" SG and replacing the spoo Also cutting the nozzle weld at No. 262 and weld No. 257 on the "B" SG and replacing the spool. Ultrasonic examination conducted prior to cutting revealed unacceptable indications als Functional or Program Areas Inspected General Letter dated July 13, 1979, to Mr. J. G. Keppler from Mr. D. R. Hoffman (Response to item 5 of IE Bulletin 79-13) Letter dated July 30, 1979, to Mr. J. G. Keppler from D. R. Hoffman (Response to IE Bulletin 79-13 items that would be inspected)
The AN! was contracted to be on site for the IS! and Bulletin in-spection CPCo performed the weldin Power Cutting Inc., performed the cutting and prepared the end prep Cooperheat, Inc., performed the preheat and postheat treatmen CPCo performed the NDE contracting Trans-Eastern Inspection, Inc.,
Southwest Research Institute, CONAM Inspection and Ultrasonic Testing Engineers, and Consultants, Inc. for the !SI, and IE Bulletins 79-13 and 79-1 Approximately 2200 "A" SG tubes were found to have 14 unacceptable tube tubes were ET and found to have nine
- unacceptable tubes were plugge eddy current examined (ET) and Approximately 1850 "B" SG unacceptable tube All the The next outage will be approximately summer 1981.
- 3 - Procedures/Manuals The following procedures and manuals were reviewed: CPCO, !SI No. 6 Outage Plan, Revision 1, August 16, 1979 CPCo, Inservice Inspection Specification No. M-150, Revision 4 (Southwest Research Institute) CPCo, Inservice Inspection Specification No. M-150B, Revision 2, (System Protection Laboratory Services) CPCo, Color Contrast Solvent Removable Liquid Penetrant Examina-tions, NDT-PT-03, Revision 2, January, 197 CPCo, Radiographic Examination of Welds, NDT-Rl-01, Revision 2, April, 197 CPCo, Direct Visual Examination, NDT-VT-03, Revision 2, January, 197 CPCo, A and B Steam Generator Feedwater Pipe Removal, 79-FWS-132, Revision O, October 197 CPCo, Steam Generator Eddy Current Examination of Tube/Sleeve Assemblies, NDT-ET-03, Revision 2, July 29, 197 CPCo, Steam Generator Dent Region Eddy Current Examination, NDT-ET-04, Revision 2, July 26, 197 CPCo, Eddy Current Examination of Sleeves for Steam Generator, NDT-ET-05, Revision 1, July 26, 197 CPCo, Steam Generator Multifrequency Eddy Current Examination, NDT-ET-06, Revision O, September 12, 197 CPCo, Shielded Metal Arc Welding (SMAW) SM-1-1, Revision 1, December 1977, SM-1-3, Revision O, December 1977, and SM-3-3, Revision O, December 197 CPCo, Automatic Tube Plugging Equipment Operating Procedures, PCS-M-34, Revision 2, June 197 CPCo, Automatic Gas Tungsten Arc Welding,.AGT-F43TP-F43TS-SG2, Revision 1, August 1979, and AGT-F43TP-F43TS-SG3, Revision 1, August 197 CPCo, Technical Specification No. 4.14, Augmented Inservice Inspection Program for Steam Generators, Amendment No. 33, January 9, 197 *
- CPCo, General Wedling Process Standards, M-MSM-8, Revision 0. CPCo, Gas Tungsten Arc Welding (GTAW), GT-1-1, Revision 4, December 1977 and GT-1-3 Revision O, February 1978; GT-F43TP-F43TS-PALSG1, Revision 1, August 1979 and GT-F43TP-F43F-F43TS-PALSG, Revision 2, August 197 CPCo, Program Plan for the 1979 Palisades Steam Generator Tubing Examining, NDT-PP-2, Revision 1, Section 5.1, July 17, 197 CPCo, Steam Generator Dent Magnitude Data Evaluation, N NDT-G-03, Revision 2, July 26, 197 CPCo, Positioner and Associated Equipment for Steam Generator, NDT-G-04, Revision 1, July 26, 197 CPCo, Standard Eddy Current Dent Magnitude and Sludge Depth Examination, NDT-ET-02, Revision 2, July 26, 197 CPCo, Special Process Procedure for Welding Material Storage, WMS-1, Revision 1, December 10, 197 CPCo, SMAW, SM-1-1, Revision 1, December 21, 197 CPCo, GTAW, GT-1-1, Revision 4, December 21, 1977.
SWRI, Special Procedure for Manual Ultrasonic Examination of Austenitic Components with High Acoustic Attenuation Properties, NDT-800-17, Revision 18, February, 197 SWRI, Manual Ultrasonic Examination of tThin Wall Piping Welds, NDT-800-36, Revision 21, March 197 a SWRI, Ultrasonic Examination of Reactor Coolant Pump Flywheels NDT-800-43, Revision 2, March 197 b SWRI, Visual Examination of Nuclear Reactor Components by Director on Remote Viewing, NDT-900-1, Revision 42, July, 197 c SWRI, Manual Ultrasonic Examination of Pressure Piping Welds, NDT-600-3, Revision 52, March, 197 d SWRI, Manaul Ultrasonic Examination of Vessel Support Skirt Attachment Welds, NDT-600-16, Revision 21, March, 197 e SWRI, Manual Ultrasonic Examination of Pressure-Retaining Studs and Bolts 2" or Greater in Diameter Containing Access Holes, NDT-600-18, Revision 26, March, 1979.
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- f SWRI, Manual Ultrasonic Examination of Pressure-Retaining Round Nuts Two Inches or Greater in Diameter, NDT-600-19, Revision 26, March, 197 g SWRI, Manual Ultrasonic Examination of Pressure-Retaining Welds in Austenitie Regenerative Heat Exchangers, NDT-600-30, Revision 10, March, 197 h SWRI, Mechanized Ultrasonic Examination of Ferritic Vessels 2 1/2 inches or Greater in Thickness, NDT-700-6, Revision 1, July, 197 i SWRI, Manual Ultrasonic Examination of Nuclear Reactor Pressure Vessel Flange Ligaments, NDT-600-5, Revision 27, March, 197 jj. SWRI, Manual Ultrasonic Examination of Vessel to Nozzle Inner Radius Sections, NDT-600-11, Revision 28, March, 197 k SWRI, Manual Ultrasonic Examination of Pressure Vessel Welds, NDT-600-15, Revision 39, March, 197.
SWRI, Fluorescent Magnetic Particle Examination, NDT-300-2, Revision 24, March, 197 m SWRI, Liquid Penetrant Examination Color Contrast Method, NDT-200-1, Revision 46, February, 197 n SWRI, Dry Powder Magnetic Particle Examination, NDT-300-1, Revision 16, January, 1979 o SWRI, Visual Examination of Support Members and Structures for Piping, Valves, and Pumps by Direct or Remote Viewing, NDT-900-4, Revision 19, August, 197 p SWRI, Nondestuctive testing Personnel Qualification, training, Examination and Certification (1968 Edition SNT-TC-lA) lX-AG-1-1, August 8, 197 q SWRI, Special Process Control (1975 Edition SNT-TC-lA) NQAP 11-1, Revision 1, March 3, 197 r SWRI, Certification of Visual Examination Personnel, NDT-100-2, Revision 3, September 10, 197 s Cooperheat, Inc., Groveport, Ohio Preheat and Postheat Treatment, No. CH0086, Revision A, October 17, 197 No items of noncompliance or deviations were identifie.
Personnel Qualifications
The following personnel certifications were reviewed:
CPCo NAME ET VT UT PT MT RT E. Martinez III III III III R. Pacific II II II II R. Stafford II II II II J. Kendziora II II II R. Kahle II II D. Cardwell II F. Herring III III III III III III D. Zeigler I
CO NAM NAME ET VT UT PT MT RT R. Peterson III III III III P. Christensen I
M. Sippel I
K. Erickson II
B. Creech III III III III III UTEC NAME ET VT UT PT MT RT F. Gorsira III R. Clements II F. Beverly I
Trans-Eastern Inspection, In NAME ET VT UT PT MT RT R. Looper III III III III III III T. Reimel II J. Deangelis II SWRI NAME ET VT VT PT MT RT T. Trude I
R. Bendele II I
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L. Villa I
D. Fournell W. Jorgensen R. Fine W. Wilson S. Todd J. Smith R. Niemeyer I
P. Nash D. Kling II P. Gaines M. Ehnstrom E. Boyd W. Walker S. Walker II R. Shimkus W. Minton W. Schick F. Masao Y. Satake M. Yusa M. Seo T. Collins J. Godwin CPCo, Welding Personnel NAME G. Premo M. Lee J. Lauria E. Smela II I
II I
I I
II I
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II I
II III III III II I
III II II I
II I
II I
II I
II I
II I
II III II II II I
III N II II I
II II II I
II II III III I
III I
II I
I I
II I
I I
III III III I
III No items of noncompliance or deviations were identifie.
Material and Equipment Certification III The following material and equipment certifications were reviewe Pipe, 30 ft., 18" diameter, schedule 60, Ht. 93515 7 ft., 18" diameter, schedule 60, Ht. 81303 7 ft., 18" diameter, schedule 60, Ht. L64602 ° Elbows (4), 18" diameter schedule 80, Ht. 6CCO Bare wire - 3/32", E70S2, Ht. L40165 1/8", E70S2, Ht. 065020
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- Coated electrodes - 3/32", 7018, Ht. 432A3271 1/8", 7018, Ht. 40186282 Magnaglux materials and pyrometer Developer batch - 784005 Penetrant batch - 70074 Cleaner batch - 70086 Ultrasonic couplant, Dow Chemical Glycerine - batch 977 Various ultrasonic transducers, calibration blocks and instru-ment Radiographic densitometer and density stri Magnetic particle machines, yoke #WL-1-1 and WL-1-2 also the co.ntour probe #444 No items of noncompliance or deviations we.re identifie.
Removal of Pipe Weld 261, transition piece (safend) "B" SG was cut out and sent to Westinghouse Testing Laboratory for metallurgical examinatio The result was corrosion fatigu The decision was made to cut adjacent to welds 263 and 258 machining through the welds eliminating weld 263, the end weld, making up a spool piece for SG "A", also cutting adjacent to welds 262 and 257 eliminating weld 262, the end weld, and making up a spool piece for SG "B".
Visual (VT) and liquid penetrant (PT) examinations were performed on the outside diameter (OD) and inside diameter (ID) of the SG nozzle "A" and "B" and connecting pipin The examinations revealed pitting and some linear indications in the nozzle The nozzles were satisfactorily repaired by welding or blendin No items of noncompliance or deviations were identifie.
Observation of Work and Work Activities The following activities were observed: Blending of the ID because of excessive root reinforcemen SG
"B", weld /116 In-process welding of weld /1258, SG "B" and /f259, SG "A"
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No items of noncompliance or deviations were identified.
Data and Audit Review The following documents were reviewed: Audits HSBE of ISI and Bulletin 79-13 CPCo of ISI,Bulletins 79-13 and 79-17 CPCo of SWRI-ISI Data Review for ISI,Bulletins 79-13 and 79-17 NDE data for radiographic, ultrasonic, liquid penetrant, visual, and magnetic particle examinations Post weld heat treatment stripe charts Water chemistry and summary of borated water sampling Hydrostatic testing No items of noncompliance or deviations were identified.
Radiography The inspector reviewed the radiographs of the following welds in accordance with lE Bulletin 79-13, Line No. FWS-18-FW Weld N Steam Generator B
B B
B B
A A
A A Southwest Research Institute The inspector made a trip to Southwest Research Institute in San Antonia, Texas for the purpose of reviewing nondestructive examination personnel certifications, including experience and four NDE personnel
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certification procedure When SWRI submits a, "Statement of Certi-fication," for an NDE individual to the licensee, it is not complete or is there enough information available to evaluat The following items are found in reviewing the SWRI, "Statement of Certification,"
of their NDE personne SWRI NDE personnel are certified in accordance with the requirements of one of the following procedure SWRI, Nondestructive testing Personnel Qualification, training, Examination and Certification (1968 Edition SNT-TC-lA) lX-AG-1-1, August 197 SWRI, Special Process Control (1975 Edition SNT-TC-lA) NQAP 11-1, Revision 1, March 197 SWRI, Certification of Visual Examination Personnel, NDT-100-2, Revision 3, September 197 SWRI, Visual Examination of Nuclear Reactor Components by Direct or Remote Viewin NDT-900-1, Revision 47, August 197 Very seldom are there one of the above procedures found on site, there-fore the certifications can not be evaluated without the procedure of the requirements on how the personnel were certifie The licensee have audit reports stating that NDE certifications and procedures have been reviewed at SWRI, but the individuals that have conducted the audits very seldom review the certifications when submited by SWRI for a specific job on site, and.do not have copies of the pro-
.cedures to refer to if they were to review the certification The, "certification limitations (if any)," stated on the certifica-tion are always blank when there is not a limitatio The blank area should have the word,"NONE," if there is not a limitatio The, "Signed," area on the certification does not state if the indivi-dual is a Level III but does state his title in the compan In re-viewing the certification at the site it is not known who administrated the test or if the Level III Examiner was qualified because his tests are not always at the sit "Training," on the certification states classroom laboratory hours are combined and the examination grad The methods are not stated and without a procedure to refer too one can not say the hours are in ac-cordance with the procedur "Educational History," on the certification states name of high school, any additional, the major field of study, years and degre In some cases it would be dificult to know the city and state of the
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school and if the person is a graduate. If a person is a graduate of a high school or certain type of college it could reflect the experience neede The precedure states the education neede "Employment History," on the certification states, date employed, previous NDT related, company and year SWRI does not state amount of experience in an NDE method on the certification when employed by SWR The documented experience is located at SWRI and the procedure for the amount of experience required is at SWRI als The inspector has reviewed certifications where part of the education is the ex-perience which should be stated in the procedur The certification should state all the NDE experience to time of certification, includ-ing, company, city, state, method, month and years to and fro "Visual Acuity and Color Perception test," on the certification states, date, correction required and verified b The eye test does not state if the Jaeger VI was given, the type of color test or who gave the tes The four above procedures will be on site or can be obtained by calling Larry Albrecht at SWRI 512-684-511 The, "Statement of Certification," Form QA-11-4 shall be revised and will be in SWRI QA Manual approximatly the end of March, 198 At that time all SWRI NDE personnel experience shall be documented on the form up to their certification dat Approximatly all NDE personnel shall be recertified by written examination by the end of the Summer, 198 No items of noncompliance or deviations were identifie.
Conclusion RIII will review the licensee's written response to IE Bulletin 79-13 and 79-17 upon receip These are unresolved item IE Bulletin 79-13 (255/79-14-1) and IE Bulletin 79-17 (255/79-14-2)
No items of noncompliance or deviations were identifie Unresolved Items Unresolved items are matters about which !Bore information is required in order tQ ascertain whether they are acceptable items, items of noncom-pliance, or deviation The unresolved items disclosed during the in-spection are discussed in Paragraph 1 Exit Interview The inspector met with site and SWRI representation at the conclusion of the inspection The inspector summarized the scope and findings of the inspections noted in the report.
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