IR 05000445/1993037

Insp Repts 50-445/93-37 & 50-446/93-37 on 931012-15.No Violations Noted.Major Areas Inspected:Isi Activities

ML20059B251
Person / Time
Site:	Comanche Peak
Issue date:	10/22/1993
From:	Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20059B250	List: IR 05000445/1993037 ML20059B246
References
50-445-93-37, 50-446-93-37, NUDOCS 9310280107
Download: ML20059B251 (6)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Inspection Report: 50-445/93-37 50-446/93-37 Licenses: NPF-87 NPF-89 ,

Licensee: TU Electric -

Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas Facility Name: Comanche Peak Steam Electric Station, Units 1 and 2 Inspection At: ulen Rose, Texas Inspection Conducted: October 12-15, 1993 Inspectcrs: L. E. Ellershaw, Reactor Inspector, Maintenance Section Division of Reactor Safety R. C. Stewart, Reactor Inspector, Maintenance Section Division of Reactor Safety Approved: NW /0/22./93 Dale A. Powers, Chief, Maintenance Section

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Da'te Division of Reactor Safety Inspection Summary Areas Inspected (Unit 1): Routine, announced inspection of inservice inspection activitie Areas Inspected (Unit 2): No inspection of Unit 2 was performe Results (Unit 1):

• The inservice inspection program was comprehensive and well organized (Section 2).

• Nondestructiv'e examination procedures and personnel were approved and certified, respectively, in accordance with Sections V and XI of the ASME Code (Section 2). -l

• Nondestructive examinations were performed in accordance with approved procedures and by certified personnel (Section 2). -i

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-2-t Results (Unit 2): Not applicabl ,

Attachments:

. Attachment - Persons Contacted and Exit Meeting

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. -3-DETAILS 1 PLANT STATUS

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During this inspection period, Unit I was in a cold shutdown condition for Refueling Outage .

2 INSERVICE INSPECTION - OBSERVATION OF WORK AND WORK ACTIVITIES (73753)

The objectives of this inspection were to ascertain whether inservice i examinations, repair, and replacement of Class 1, 2, and 3 pressure retaining components were. performed in accordance with the Technical Specifications, the ,

applicable ASME Code, correspondence between the Office of Nuclear Reacto Regulation and the licensee concerning relief requests, and requirements imposed by NRC/ industry initiative .1 Discussion The licensee had established Procedure STA-703, " Inservice Inspection Program," Revision 6, to provide responsibilities, directions, and .;

instructions to control the inservice inspection program plan. The inspectors reviewed inservice inspection plan, " Comanche Peak Steam Electric Station, l Unit 1, ASME Section XI Inservice Inspection Program Plan," Revision 0, for the first 10-year interval. The interval covered the _ period from August 13, 1990 (commercial operation date) to August 12, 2000. Revision 0 of_the program plan, in which the licensee committed to the requirements of Section XI of the 1986 Edition (no addenda) of the ASME Code, had been approved by the Office of Nuclear Reactor Regulation on October 1,1992. Revisions 1 and 2, submitted on September 14, 1992, and May 5,1993, respectively, have not yet received approval from the Office of Nuclear Reactor Regulation. The revisions did not change any technical requirements, but merely reflected completion of examinations performed during previous outages, or postponement of scheduled examinations with allowable substitutions being identified. In addition, the revisions also included relief requests initiated and submitted by the license The inspectors noted during the review, that the licensee had committed to perform augmented examinations addressed in the following NRC documents:

• Regulatory Guide 1.14, " Reactor Coolant Pump Motor Flywheel Integrity," Revision 1;

• NUREG-0797, " Safety Evaluation Report Relating to the Operation of CPSES, Units 1 and 2, Supplemental Safety Evaluation Report 12, Safety Injection Pump Shrouds";

• NRC Bulletin 88-09, " Thimble Tube Thinning on Westinghouse Reactors";

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• MEB 3-1, " Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment"; and

• Regulatory Guide 1.150, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations."

Review of the inservice examination schedule, dated October 9,1993, showed ,

that the augmented examination regarding integrity of the; reactor coolant pump motor flywheel was scheduled to be performed during this outage. The schedule also identified a total of 408 examinations to be performed on 362 component For each identified component, the schedule provided the method (s) of examination, ASME Code category, and applicable examination procedur The inspectors were informed that the performance of inservice examinations had been contracted with the Nuclear Services Division of Westinghouse Electric Corporation. There were a total of 15 nondestructive examination procedures identified in the examination schedule, all of which had been developed by Westinghouse and, in accordance with Procedure STA-703, reviewed and/or approved by the licensee and the Authorized Nuclear Inservice Inspector. The inspectors were provided the names and applicable qualification / certification packages of the seven nondestructive examination persons who were on site and designated to perform all of the scheduled inservice nondestructive examinations during Refueling Outage The inspectors observed the inservice inspection activities associated with the nondestructive examination of four pipe welds in the safety injection system, two supports and two welded attachments on the letdown heat exchanger ia the chemical and_ volume control system, and two welds in the reactor coolant system. The inspectors were informed that no'ASME Code Section XI repair or replacement activities had been scheduled for Refueling Outage The inspectors observed liquid penetrant examinations performed on the following three welds: reactor vessel ..ozzle to safe end weld (Loop 3 hot -

leg) identified as TBX-1-4300-1; reactor coolant pipe to safe end weld (Loop 3 hot leg) identified as TBX-1-4300-2; and safety injection pipe to reducer weld identified as TBX-2-2565-36. Procedure TX-ISI-11, " Liquid Penetrant Examination for Comanche Peak Steam Electric Station," Revision 4, and Field Change Request FC-001 were used during the performance of these examination The inspectors observed ultrasonic examinations performed on the following three welds: TBX-2-2530-29 and TBX-2-2530-30, both of which were safety injection pipe to valve welds; and TBX-2-2581-4, which was a safety injection pipe to reducer weld. Procedure TX-ISI-207, " Ultrasonic Examination Procedure for Similar and Dissimilar Metal Welds in Austenitic Stainless Piping Systems for Comanche Peak Steam Electric Station," Revision 2, was used for the performance of these examination The inspectors observed the performance of visual examinations of two supports and welded attachments on the letdown heat exchanger, identified as TBX-1--

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4505-H17 and TBX-1-4505-H18, in which Procedure TX-ISI-8, " Visual Examination for Comanche Peak Steam Electric Station," was used. The examinations were observed to be performed in full accordance with the requirements of the nondestructive examination procedures and the 1986 Edition of Section XI of the ASME Code. The inspectors noted that the Authorized Nuclear Inservice Inspector was actively engaged in observation / review of inservice inspection activitie ,

The inspectors performed an in-depth review of the three procedures used to perform the above examinations and verified that requirements specified in Sections V and XI of the 1986 Edition of the ASME Code had been properly addressed. In addition, the inspectors verified that the examiners who performed the above examinations were certified as being qualified Level II examiners for the examination method, in accordance with the requirements of the American Society for Non-Destructive Testing Recommended Practice, SNT-TC-1A. For the liquid penetrant examinations, the inspectors also verified that procedure limitations were met for surface temperature (by measurement), and that penetrant material contaminant levels were acceptable (by review of certified material test reports). For the ultrasonic examinations, the inspectors verified by observation, the calibration of the ultrasonic system, temperature measurements of the calibration blocks and components, establishment of distance amplitude curves, and that the examination covered the required volume. The inspectors also reviewed the certification packages applicable'to the ultrasonic calibration blocks used for the above examinations (i.e., calibration block TBX-9 for welds TBX-2-2530-29 and -30, and calibration block TBX-49 for weld TBX-2-2581-4). Each package contained a certified material test report, i dimensional data sheet, letter of compliance, and a Westinghouse Nuclear ;

Services Division quality release form. The inspectors determined that the appropriate calibration block was used for each examinatio '

The records generated for the above examinations had not been through the complete review and approval cycle at the time this inspection was complete However, Procedure STA-703 clearly defined the requirements and responsibilities for licensee evaluation and final review and approval of all examination record package .2 Conclusion ,

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The licensee'sSection XI inservice inspection program plan was found to be comprehensive, well organized, and was being properly implemente Nondestructive examination procedures had been approved and were found to ;

appropriately address ASME Code requirements for the specific examination process. The Level II examiners were found to be properly certified as being qualified for the specific examination process observed. The observed j nondestructive examinations were performed in accordance with approved '

procedures,Section XI of the ASME Code, and the approved inservice inspection program pla .j l

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. ATTACHMENT 1 1 PERSONS CONTACTED

- Licensee Personnel

• J. DeBonis, Inservice Inspection Coordinator

• B. Hartman, Senior Engineer, Mechanical Codes and Standards

• T. Hope, Manager, Regulatory Compliance

• B. Mays, Supervisor, Mechanical Codes and Standards

• J. Muffett, Manager, Technical Support and Design Engineering

• B. Snellgrove, Supervisor, Quality Control

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• D. Snow, Engineer, Site Licensing

• C. Terry, Vice President, Nuclear Operations J. Ragan, Level III Nondestructive Examination Examiner 1.2 Westinghouse Nuclear Services Division N. Bollingmo, level II Nondestructive Examination Examiner W. Halley, Level II Nondestructive Examination Examiner G. Morini, Field Services Coordinator ,

L. Volkmann, Level II Nondestructive Examination Examiner 1.3 Hartford Steam Boiler Insurance and Inspection Company

• J. Hair, Resident Authorized Nuclear Inspector and Authorized Nuclear .

Inservice Inspector ,

1.4 NRC Personnel

• K. Xennedy, Resident Inspector In addition to the personnel listed above, the inspectors contacted other personnel during this inspection period,

• Denotes personnel that attended the exit meetin ,

2 EXIT MEETING An exit meeting was conducted on October 15, 199 During this meeting, the i inspectors reviewed the scope and findings of the report. The licensee did not express a position on the inspection findings documented in this repor ,

The licensee did not identify as proprietary any information provided to, or i reviewed by, the inspector i l

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