IR 05000244/1993002
| ML17263A300 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/19/1993 |
| From: | Gray E, Patnaik P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17263A299 | List: |
| References | |
| 50-244-93-02, 50-244-93-2, NUDOCS 9305250057 | |
| Download: ML17263A300 (16) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION
REGION I
REPORT NO.
DOCKET NO.
- LICENSE NO.
LICENSEE:
FACILITY:
INSPECTION AT:
93-02 50-244 DPR-18 Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 R. E. Ginna Nuclear Power Plant Ontario, New York INSPECTION DATES:
March 23-27, 1993 LEAD INSPECTOR:
APPROVED BY:
Prakash Patnaik, Reactor Engineer, Materials Section, Engineering Branch, DRS Fil Edwin H. Gray, Chief, Materials Section, Engineering Branch, DRS Date Date 5'305250057 9305iB PDR ADOCK 05000244 G
PO C l
AREA INSPE TED: An announced inspection was conducted of the licensee's inservice inspection program and the steam generator tube eddy current examination program.
The inspection was conducted to ascertain whether the programs and the nondestructive examination activities conformed to applicable requirements and procedures.
R1+~T:
Within the "areas inspected, the licensee's inservice program was found to comply with the 1986 ASME Section XI Code and the regulatory requirements.
The nondestructive examinations, including the eddy current examination of steam generator tubes, complied with licensee's procedure DETAILS 1.0 INSERVICE INSPECTION (ISI) (INSPECTION PROCEDURE 73753)
1.1 Sc',ope Inservice inspection by ultrasonic, magnetic particle, liquid penetrant and visual examinations is performed to ensure integrity of nuclear power plant components.
An inservice inspection is mandated by the ASME Boiler and Pressure Vessel Code,Section XI, and is essential to" promote health and safety.
1.2 Program Review The licensee has developed the third ten-year inspection plan to cover inservice inspection from the start of the inspection interval on January 1, 1990, to December 31, 1999.
The applicable code for this interval is the 1986 edition of the ASME Code,Section XI. The licensee also developed an examination schedule for the outage which outlined the components for examination, the type of examination required and the examination procedure to be used.
A review of the outage examination schedule indicated that the licensee's ten-year plan is being adequately implemented and the requirements of the applicable ASME Section XI Code are being met.
However, the inspector noted that the Code Class 3 nonintegral component supports were not specifically designated for examination by visual inspection (VT3). There are 472 pipe supports in the Class 3 pipe systems of which 141 are integral (welded to the piping) supports, plus 18 pipe snubbers that are inspected visually per VT3. The Ginna program provides for VT inspection of an integral support past the integral support boundary near the pipe to the load bearing point of attachment such as structural steel. This provides for visual examination of the nonintegral portion of pipe supports to an extent in excess of that required by the ASME Code due to the high percentage of integral Class 3 pipe supports. Additionally, the licensee has implemented an augmented visual inspection of 10% of the service water and auxiliary feedwater Class 3 nonintegral pipe supports for the 1993 outage and the following four refuel outages.
The inspector had no further questions in this area.
A review of the scope of examination for integral supports for Class 3 systems was found to be satisfactory.
The inservice inspection program and the activities are primarily controlled by the following administrative procedures.
Performance and Review Describes the process and the individual of Inservice Inspections responsibilities involved in the performance and Proc. No. QMEIS 1009, Rev. 0 review of inservice inspection.
Documentation and Control of Inservice Inspection Activities Proc. No. QMEIS 1007, Rev. 0 Describes the responsibilities and the documentation process which implement the ISI program.
The scheduling and assignment of ISI examinations, as well as the evaluation process and records requirement, are contained within these procedures.
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Preparations for ISI Describes the process and the individual Activities responsibilities involved in the preparation of the Proc. No. QMEIS 1008, Rev. 0 documentation for the annual inservice inspection.
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Processing of Acceptable Describes the process and the individual Inservice Examinations responsibilities involved in the processing of ISI Proc. No. QMEIS 1010, Rev. 0 documentation for acceptable examinations.
Rejectable Examination Results (Code Service Induced Degradation)
Proc. No. QMEIS 1012, Rev.
Describes the process and the individual responsibilities involved in the processing of ISI documentation for rejectable examinations
resulting from Code Service Induced Degradation.
Rejectable Examination Results (Not Service Induced)
Proc. No. QMEIS 1011, Rev.
Describes the process and the individual responsibilities involved in the processing of ISI documentation for rejectable examinations which
are not service induced.
A review of each procedure indicated that the licensee has adequate control over the inservice inspection program and the activities.
1.3 Observation of Work
The inspector observed radiography of containment fan cooler piping that was field fabricated to replace the existing piping. The radiography work progressed with proper safety considerations.
The inspector performed surveillance of the darkroom facility on site and reviewed sample radiographs to ascertain filmquality and licensee's interpretation of radiographs.
These were found to be satisfactory.
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The inspector observed automatic ultrasonic examination of the feedwater piping (14B-FW-900-1A) weld F4 and manual ultrasonic examination of the following welds on the safety injection system:
3A-SI-1501 Weld 19 3B-SI-1501 Weld 9 V
.5 In all cases, the examinations were performed in accordance with the applicable ultrasonic examination procedure.
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The inspector observed and reviewed evaluation of data by the licensee's analyst on main steam 24B-MS-600 Weld "A" using the automated UT system.
The plotting was performed using Raytrace Version 2.0 computerized system for plotting ultrasonic reflectors.
The data evaluation by the licensee was found to be satisfactory.
1.4 tnservice Inspection Data Review Ultrasonic examination data on the following welds were reviewed for accuracy and completeness.
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Residual Heat Removal Line 8FF-AC-151 Weld 7, Tee-to-Cap
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Residual Heat Removal Line 8FF-AC-151 Weld 9, Tee-to-Cap
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Residual Heat Removal Line 8D-AC-601 ID-5, Valve-to-Tee
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Residual Heat Removal Line 8X-AC-601 ID-2A, Pipe-to-Tee
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Residual Heat Removal Line 10A-AC-601 ID-16, Pipe-to-Elbow The following Nondestructive Examination (NDE) Procedures applicable to above welds were reviewed and found to comply with the ASME Code.
NDE-200-1 Rev. 5 Liquid Penetrant Examination Color-Contrast, Solvent Removable Method NDE-600-17 Rev. 0 Manual Ultrasonic Examination of Pressure Piping Welds from 0.2 to 0.6 Inch Wall Thickness NDE-600-14 Rev.
Automated Ultrasonic Examination of Austenitic and Ferritic Pressure Piping 1.5 Conclusion Based on review of examination records, procedures and interviews with personnel, the ISI program at Ginna was found to meet the requirements of the 1986 edition ASME Code,Section XI, and the NRC regulation.0 STEAM GENERATOR EDDY CURRIWT EKAMINATION(IP /3753)
2.1 Scope The steam generator eddy current examination is performed by the licensee to ensure integrity of steam generator tubes and, hence, the reactor coolant pressure boundary.
This examination was performed during the March 1993 outage to comply with the requirements of the Technical Specification.
2.2 Findings During the March 1993 outage, the licensee performed extensive eddy current examination of both steam generators.
The inspection program was directed to examine all possible defect locations to ensure integrity of steam generator tubes.
The following outlines the examination plan for each steam generator (S/G).
In i nPr m
Bobbin coil examination of hot leg Hot leg plugs and sleeves MRPC of roll transition 2520 tubes 119 1250 E'813 tubes 240 1813 MRPC of support plate intersection Bobbin coil examination of cold leg
894
723 MRPC of B&Wplugs and dents at
. 6th cold support
36 MRPC of U-bends 165 144 The inspector witnessed the Motorized Rotating Pancake Coil (MRPC) examination of the tube sheet roll transition.
This involved the data acquisition, analysis and data management.
The examination personnel followed approved procedures and data analysis guideline.
Licensee's coordination of contractor's activities on eddy current examination was satisfactory.
2.3 Conclusion For those areas inspected, the eddy current examination met the requirements of the NRC Regulatory Guide 1.83 and the Technical Specificatio.0 ENTRANCE AND EXITMEETINGS Members of the licensee's management were informed of the scope and the purpose of this inspection at the entrance meeting on March 23, 1993.
The findings of the inspection were presented to and discussed with members of the licensee's management at the conclusion of the inspection on March 27, 1993.
A list of attendees at the exit meeting is provided in Attachment 1 to this report.
Attachment:
Attendees at NRC Exit Meeting
ATI'ACHMENTl AITFM3EES AT NRC EXIT MEETING R
h tr a
an Elec 'c tion Michael J. Saporito Paul A. Lewis Michael J. Davison Frank A. Klepacki Vhlliam L. McCoy Joseph A. %iday Manager, Materials Engineering and Inspection Services Senior Engineering Assistant - NDE Engineering Assistant - NDE Assistant Engineer - ISI Department Manager, Quality Performance Plant Manager cl Re I t mmi i n Thomas A. Moslak Senior Resident Inspector, Ginna
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