IR 05000498/1993010
| ML20035A986 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/26/1993 |
| From: | Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20035A982 | List: |
| References | |
| 50-498-93-10, 50-499-93-10, NUDOCS 9303300311 | |
| Download: ML20035A986 (10) | |
Text
{{#Wiki_filter:' . - . t . APPENDIX U.S. NUCLEAR REGULATORY COMMISSION <
REGION IV
, Inspection Report: 50-498/93-10 , 50-499/93-10 Operating Licenses: NPF-76 NPF-80 i ' Licensee: Houston Lighting & Power Company P.O. Box 1700 Houston, Texas 77251 Facility Name: South lexas Project, Units 1 and 2 Inspection At: Matagorda County, Texas Inspection Conducted: March 8-12, 1993 Inspector: C. E. Johnson, Reactor Inspector, Maintenance Section, Division of
Reactor Safety Approved: M ct4 W 3/zz/f3 , Dr. D?le A. Powers, Chief, Maintenance Section 'Date Divis.an of Reactor Safety Insoection Summary , Areas Insoected (Unit 1): No inspection'of Unit I activities was performed.
Areas Inspected (Unit 2): Routine, announced ' inspection of the inservice.
, inspection program and implementing work activities.
, Results (Unit 1): Not applicable.
- Rfsults (Unit 21:
Ine inservice inspection program was well~ defined (Section 2.1).
- Inservice inspection procedures contained sufficient details and
, instructions to enable the satisfactory performance of the examinations (Section 2.2).
, The inservice inspection program was being effectively implemented
(Section 2.3).
Nondestructive examination personnel were well qualified (Section 2.4).
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. -2- , ! Summary of Inspection Findinos:
None , Attachments: Attachment 1 - Persons Contacted and Exit Meeting
. Attachment 2 - Documents Reviewed and Examinations Observed
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. ! ! . ' -i ! -3-DETAILS I , i 1 PLANT STATUS l During this inspection period, South Texas Project, Unit 2, was in the first week of the third refueling outage (2RE03).
2 INSERVICE INSPECTION PROGRAM (ISI) (73753) i The objective of this inspection was to ascertain whether the performance of ISI examinations, and the s: pair and replacement of Class 1, 2, and 3 pressure retaining components were performed in accordance with tha Technical Specifications and the applicable ASME Boiler and Pressure Vessel Code.
Correspondence between the NRC Office of Nuclear Reactor Regulation and the licensee concerning relief requests was reviewed. Other requirements imposed by the NRC and industry initiatives were also evaluated.
' 2.1 Proaram ' 2.1.1 Discussion The inspector met with the ISI staff engineer to discuss the ISI program and scheduled examinations. The responsibilities, interfaces and requirements for the administrative control of the examinations and testing. activities associated with the ISI program were described in Interdepartmental Procedure - IP-3.04Q, " Inservice Inspection Program," Revision 4.
The inspector also- , reviewed the " Examination Plan for the 199342RE03 Inservice Inspection of ~ Welds and Components Supports," including four. examination plan changes, dated February 1993.
Change No. 4 to the examination plan was of interest because it deferred examination of the reactor pressure vessel closure head nuts pending NRC approval of Relief Request RR-ENG-12.
This relief request was initiated because of a noncited violation documented in NRC Inspection > Report 50-498/92-28; 50-499/92-28. The licensee elected to perform ultrasonic , tecnnique (UT) examination on the nuts rather than magnetic particle technique (MT) examination. Typically, a fluorescent MT examination is - performed on threaded areas because of its suitability for discrimination of flaw indications in the root of the threads. Due to the poor viewing angle and the limited access to the nut inreaded surface with the MT equipment and l black light, the licensee believed that a technically adequate MT examination ! cannot be performed.
The inspector reviewed the alternate method of examination (i.e., UT) proposed by the licensee. The licensee believed that the UT method of examination was sufficient to achieve the required results. The examination will be performed after NRC review of the relief request. No other changes to the program were made. Changes that were made to the plan were properly documente q j r . > . - -4- ! , ! The examinations listed in the plan constituted the third ISI of the first
10-year inspection interval for Unit 2.
The examination plan referenced applicable ISI documents and described the ISI programs and how they should be ! implemented. This plan provided the scope of examinations to be performed and
other supporting documents such as weld identification figures and procedures.
The examination plan consisted of four Appendices: P Appendix A, " Inservice Inspection Tables for Welds";
, Appendix B, " Inservice Inspection Tables For Component Supports";
Appendix C, " Weld Identification Figures"; and
Appendix D, " Nondestructive Examination Procedures."
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2.1.2 Conclusions The inspector determined that the ISI program was well defined. Review of the l ISI plans and schedule indicated that the licensee had also established a good
inspection plan.
, 2.2 ISI Procedures and Records Review l 2.2.1 Discussion ! The inspector reviewed the nondestructive examination (NDE) procedures associated with the type of ISI examinations being performed for consistency i with the requirements of the 1983 Edition of ASME Code Section XI. The procedures were observed to contain sufficient details and instructions to ! enable the satisfactory performance of the examinations.
The NDE reports were properly completed and tu'rned in for review and approval - by the certified Level-III NDE supervisor and design engineer.
i Procedures and records that were reviewed are listed in Attachment 2.
l 2.2.2 Conclusions
l ISI procedures had sufficient details and instructions to enable the satisfactory performance of the examinations. Records of the NDEs were complete and required approvals had been made.
, ' 2.3 ISI Work Activities . 2.3.1 Discussion . The inspector observed the maintenL:ae shop code repir:ement work involving the replacement of an aluminum-bronze cast flange with an aluminum-bronze , wrought flange. The inspector's brief review of the work and the associated traveler package indicated that the work was being performed in accordance i with the work instructions and associated procedures.
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. - .,. - ? - ' < . ' . . - i-5- , , The inspector observed three different methods of NDE of various components as f discussed in the following sections. The specific NDEs observed are listed in
Attachment 2.
j [ 2.3.1.1 Volumetric Examination The inspector observed manual UT examination of four circumferential welds, ! which were located in the safety-related portion of the feedwater system, and
six reactor pressure vessel closure head studs.
Prior to the UT examination, ' the inspector witnessed the UT calibration, which was performed as required by l procedure. The NDE personnel performed the UT calibration using the . appropriate calibration block for the material, thickness, and diameter. The ! appropriate search unit wedge for angle-beam examinations with the refracted i shear wave of 45 degrees was used, as specified by procedure, for ferritic j pressure piping welds.
Several calibrations were made for the reactor , pressure vessel closure head studs because of their unique geometry. The
inspector verified the instrument settings, the frequency of the search unit, and that the distance amplitude correction curves had been properly prepared and used.
All ca'.;brations were performed before the UT examinations began.
, The NDE personnel were observed performing the scanning for the
circumferential welds on the feedwater system.
Scanning overlap was performed ! well, and in accordance with procedures. No indications were noted during the .; UT examination of the feedwater pipe circumferential welds or the reactor i pressure vessel closure head studs.
2.3.1.2 Surface Examinations .., The inspector witnessed liquid penetrant technique (PT) examinations on two [ circumferential welds located in the reactor coolant system, within the upper elevations of the pressurizer room.
The penetrant material was verified by
the inspector as the correct material. Surface conditions were examined before and after the PT examinations by the NDE personnel performing-the ' inspections. The penetrant was appropriately applied to the surfaces by brushing.
The NDE personnel performed the application of the developers, the ! ! PT examinations, and the documentation of results in accordance with approved procedures.
, The inspector also witnessed wet-fluorescent MT examinations on the outer surfaces of the reactor pressure vessel closure head studs. The examination
' was performed in a darkened area inside the reactor containment building by contractor personnel from General Technical Services. The method of-i application, evaluation, and documentation was performed in accordance with
approved procedures.
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2.3.1.3 Visual Examination l ! The third method of NDE testing observed was the visual technique
examination-(VT-3). This inspection was of three Class 2 component supports and was perfoned to determine the mechanical and structural condition of _ ,
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. ' . ~ . , -6-components supports. The NDE personnel looked for the presence of debris, loose parts (such as bolts), wear, and corrosion.
The NDE technician performed his duties as required by the procedures.
2.3.2 Conclusions The NDE personnel were effectively implementing the ISI examination program as required by procedures and the Code. Also, the equipment and material used for the NDEs were verified as meeting the certification requ1renients specified in the applicable procedures.
2.4 ISI Personnel Qualifications and Certifications 2.4.1 Discussion The inspector verified that personnel, performing the ISI examinations were certified in accordance with NDE Procedure NDEP 1.0, " Qualification And Certification Of Nondestructive Examination Personnel," Revision 3.
The inspector determined by review of personnel certification records, verification of work experience, training, and test scores that personnel were qualified. Site and contractor personnel were determined to be qualified to perform their duties in accordance with both Procedure NDEP 1.0 and the requisite industry standard (i.e., SNT-TC-1A). The inspector's discussions with site and contractor personnel involved in ISI work activities confirmed their familiarity with the necessary duties.
2.4.2 Conclusions NDE personnel performing the ISI examinations were well qualified in accordance with procedures and the requisite industry standard.
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. . ' . .. ATTACHMENT 1 , 1 PERSONS CORTACTED 1.1 Licensee Personnel
- R. Beverly, Senior Consulting Engineer - Inservice Inspection R. Busby, Inservice Inspection Coordinator
- M. Chakravorty, Executive Director, Nuclear Safety Review Board
- H. Coughlin, Senior Licensing Engineer
- R. Dally-Piggott, Engineering Specialist, Licensing
- D Dec.ver, General Manager, Nuclear Assurance
- K. Do, Rotating Engineer
- R. Gangluff, Acting Manager, Technical Services
- M. Hardt, Director, Nuclear Division
- A. Harrison, Supervising Engineer, Nuclear Licensing
- S. Head, Deputy Licensing Manager
- R. Hettua, Senior Staff Specialist, Maintenance
- S. Hubbard, Quality Control Supervisor
- J. Labuda, Fire Protection Coordinator
- D, Leazar, Manager, Plant Engineering
- H. Pacy, Manager, Design Engineering
- A. Pathak, Consulting Engineer
- K. Poling, Training Manager Assistant
- R. Rehkugler, Director, Quality Assurance
- J. kosen, Vice President, Nuclear Engineering
- J. Soward, Manager, Nuclear Quality Control and Material Testing L. Speiss, Hondestructive Examination Specialist, Level-III D. Stuhler, Hondestructive Examination Specialist, Level-II C. Suhler, Nondestructive Examination Specialist, level-II
- D. Wiegand, Staff Engineering Specialist, Fire Protection
- D. Wohleber, Director, Records Management System and Administration
- C. Younger, Staff Engineer, Inservice Inspection 1.2 Factory Mutual Enoineerina B. Russell, Authorized Nuclear Inservice Inspector 1.3 General Technical Services E. Sadler, Nondestructive Examination Specialist, Level-II R. Wolf, Nondestructive Examination Specialist, Level-II 1.4 NRC Personnel R. Evans, Resident Inspector
- A. Singh, Reactor Inspector, Plant Support Section, Division of Reactor Safety J. Tapia, Senior Resident Inspector In addition to the personnel listed above, the inspector contacted other personnel during this inspection perio.
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- Denotes personnel that attended the exit meeting.
2 EXIT MEETING An exit meeting was conducted on March 12, 1993. During this meeting, the inspector sumarized the scope and findings of the inspection. The licensee did not identify as proprietary, any information provided to, or reviewed by the inspector.
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. . .. ! . ATTACHMENT 2 . 1 DCCUMENTS REVIEWED
! Interdepartmental Procedures IP-3.04Q, " Inservice Inspection Program," Revision 4 Nondestructive Examination Procedures l NDEP 6.2, " Color Contrast Solvent Removable Liquid Penetrant Enmination for
ASME XI PSI /ISI," Revision 4 ' NDEP 9.3, "ASME XI Examination for VT-1 and VT-3," Revision 1 NDEP 7.2, " Wet Fluorescent Magnetic Particle for ASME Section XI PSI /ISI," i Revision 0
NDEP 4.0, " Ultrasonic Examination," Revision 3 NDEP 1.0, " Qualification and Certification of Nandestructive Examination Personnel," Revision 3 NDEP 7.1, " Dry Powder Magnetic Particle Examination For ASME XI PSI /ISI," Revision 3 , Ultrasonic Technical Instruction UTI-002, " Manual Ultrasonic Examination of Ferritic Pressure Piping Welds," Revision 2 ~ UTI-010, " Manual Ultrasonic Examination of the Center-Drilled Hole Surface in ' Pressure Retaining Studs Greater Than 2 Inches in Diameter," ! Revision 0 UTI-015, " Manual Ultrasonic Examination of Reactor Pressure Vessel Closure Head Studs," Revision 1 2 EXAMINATIONS OBSERVED f __gld Method Descriotion W Sumrnary NL Component /Line 106270 3-RC-2015-3
PT Elbow to Pipe 106310 3-RC-2015-7
PT Elbow to Pipe , ' 500880 18-FW-2014-2
UT Pipe to Valve 500900 18-FW-2014-3
UT Valve to Pipe 500920 18-FW-2014-4
UT Pipe to Pipe 502700 18-FW-2018-3
UT Valve to Pipe ' 265100 SI-2106-RR72 VT-3 Component Support 265200 SI-2106-RR73 VT-3 Component Support 265300 SI-2106-RR69 VT-3 Component Support 005302 Closure Bolting MT,UT Closure Stud 2B , 005405 Closure Bolting MT,UT Closure Stud 58 005408 Closure Boiting MT,UT Closure Stud 8B . , !
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005411~ Closure Bolting _ MT,UT Closure Stud 11B
005414 Closure Bolting MT,UT Closure Stud 148 005417 Closure Bolting MT,UT Closure Stud 17B ( UT Calibration Sheets ' CAL-93-0016 CAL-93-0017 ! CAL-93-0018 i CAL-93-0019
CAL-93-0021 ! ' CAL-93-0022
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