IR 05000313/1978007
| ML19320A090 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/13/1978 |
| From: | Gilbert L, Randy Hall, Herman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320A076 | List: |
| References | |
| 50-313-78-07, 50-313-78-7, NUDOCS 8004140699 | |
| Download: ML19320A090 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-313/78-07 Docket No. 50-313 License No. DPR-51 Licensee: Arkansas Power and Light Company Post Office Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One, Unit 1 Inspection at: ANO, Unit 1 Site, Russellville, Arkansas
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Inspection Conducted: March 1-3, 1978 l.
Inspectors:
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La L. D. Gilbert, Reactor Inspector, Engineering Date Support Section (Paragraphs 1, 4, 5 and 6)
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- d ~g R. A. Hermann, Reactor Inspector, Engineering
, Date Support Section (Paragraphs 2 and 3)
Reviewed:
7 $. lv 2[/3M T. F. Westerman, Principal Inspector, Reactor Date 0;.crations and Nuclear Support Branch
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i Approved:
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T1. E. Hall, Chief, Engineering Support Section
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Inspection Summary:
Inspection on March 1-3, 1978 (Report No. 50-313/78-07)
Areas Inspected:
Routine, announced inspection involving the inservice
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inspection activities; the nondestructive examination program for sur-veillance of the decay heat and reactor building spray stainless steel
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schedule 10 piping; and the modification to the decay heat stainless steel piping system. The inspection involved forty-nine inspector-hours by two NRC inspectors.
Eesults:
No items of noncompliance or deviations were disclosed.
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Oh DETAILS 1.
Persons Contacted Principal Licensee Employees
- J. W. Anderson, Plant Manager
- G. H. Milla, Assistant Plant Manager
- L. Alexander, QC Supervisor
- B. L. Bata, QA Engineer
- C. Shively, Performance Engineer
- D. Hamlin, QC Inspector F. B. Foster, Assistant Maintenance Supervisor Other Personnel Factory Mutual Engineering
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D. C. Brown, Resident Representative B&W Construction Company L. Syverson, Group Leader R. Nelson, QC Supervisor G. Abell, Technical Specialist W. R. Johnson, Senior Welding Engineer C. L. Gray, Field Engineer
- Denotes those present at the exit interview.
2.
Inservice Inspection - Observation of Work Activities a.
Observation of NDE Examinations The perfonnance of eddy current examination of "A" steam
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generator tubes 137-44, 46, 48, 50, 52, 54, 58, 60, 61, 62, 64, and 65 was witnessed by the inspector and found consistent with Babcock & Wilcox (B&W) Procedure ISI 401, Revision 7 which implements the requirements of Regulatory Guide 1.83.
The inspector witnessed the interpretation of eddy current test data for "A" steam generator tubes 137-68 and 70 and found the interpretation consistent with the above stated requirements.
The results of the examination of "A" steam generator were that 5 tubes required plugging (indications in excess of 40%
of the wall thickness) and that 6 tubes contained reportable
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indications (greater than 20% of the wall thickness).
The inspector verified that the additional testing required by-2-w
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Regulatury Guide 1.83 when tubes requiring plugging are found had been performed.
A total of 21% of the tubes in "A" steam generator had been examined.
b.
Observation of Repair Related Activities
' he' inspector reviewed AP&L procedures 1401.04, Revision 2,
"0TSG Tube Plugging Procedure" and 1401.24,.avision 0, "0TSG Tube Removal Maintenance Procedure" which are the controlling procedures for the repair activity.
The B&W Quality Control Procedure Manual for ANO, Revision 0 which included General,
Welding, NDE, Inspection and Explosive Welding Procedures for the steam generator tube plugging and removal activity was also reviewed and found consistent with the requirements of
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the ASME B&PV Code, Sections XI, V and IX.
The inspector also reviewed B&W FCA No. 04-2489 which provided detailed infoma-tion on tube selection and removal.
The inspector was infomed
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that per the requirements of AP&L procedure 1401.04 an additional B&W FCA will be prepared including the specific tubes to be plugged after the tube removal is completed.
The inspector observed the mock-up assembly for training the welders for the manual GTAW seal welds and reviewed the qualification of the welders for GTAW and explosive welding.
The inspector discussed the repair and inspection activities as well as the qualification i
and development of the explosive welding procedure with the B&W O
Sr. Welding and Field Engineers.
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No items of noncompliance or deviations were identified.
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3.
Inservice Inspection - Review of Records The inspector checked '.he ISI plan for this outage and detemined that all the scheduled work had been completed or rescheduled for later in the 10 year inspection interval.
The inspector reviewed the following records for the automated remote ultrasonic inspec-tions perfomed.
i Fig. 1.3.2 Vessel to Flange Circle Seam WR-19 Segment 86 to 7 Fig. 4.4.122 1A Hot Leg Circle Seam Nozzle to Pipe 19 to 32 Fig. 1.9.1.1 Threaded Ligament Vessel Flange MX-7 The calibration and examination records included examination equip-
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ment, calibration blocks, evaluation and review of the results and
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limits of the examination. The inspector determined the method and-3-
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extent of the examinations were consistent with the ISI program, applicable procedures and the ASME B&PV Code,Section XI,1971 edition including 1972 Summer Addenda.
The inspector reviewed the records for Fig. 4.4.9-1A1, Suction Line, Circle Seam WJ85 and Fig. 4.4.192 Pressurizer Spray Line, SL-12 and determined that recalibration results were consistent with initial calibrations, exam data was properly recorded and reviewed by a qualified examiner and the evaluation of the data was consistent with the procedure.
During the 1978 outage, two welds examined contained indications which exceeded applicable ASME Section XI requirements.
The welds, Figures C2.1.3 and C2.1.4, are in the main steam line and were also identified during the 1977 outage. The indications were evaluated and a determi-nation made that the indications were geometrical.
In addition, a code allowable but recordable indication was found in Figure 4.1.86.
The indication is 3600 intennittent with a maximum amplitude of 50%
DAC.
The inspector witnessed the verification of examination and calibration data by B&W computer system. The system verifies data interims of equipment and personnel qualifications and other code specified requirements such as calibration range and acceptance criteria.
No items of noncompliance or deviations were identified.
4.
Surveillance of Decay Heat and Reactor Building Spray Piping A radiography surveillance program was implemented by the licensee because of stress corrosion cracking experience in certain heats of stainless steel pipe that had been welded into the decay heat and reactor building spray systems reported in Abnormal Occurrence Report No. 50-313/74-11c.
The inspector selected six of the decay heat weld joints radiographed as part of the surveillance program to detect stress corrosion cracking or pitting. The radiographs for the following decay heat lines and weld joints were reviewed for radiographic technique and cracking and
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pitting.
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Line No.
Weld No.
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7DH-10 FW29A
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70H-12 FW69H l
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No cracking of the sensitized piping was eiident in the radiographs and the pitting that was rejected in five af the six weld joints radiographed was evaluated as not having changed from that reported in the baseline radiographs.
The radiography confonned to USA Standard Code for Pressure Piping, Nuclear Power Piping, USAS B31.7.
No items of noncompliance or deviations were identified.
5.
Modification of Decay Heat Piping During this outage, a decay heat valve in Line No. 70H-6 was replaced by a valve with a new design for improved functional operation. Th stainless steel piping connected to the valve was also being replaced with low carbon stainless steel pipe to eliminate the existing high carbon and sensitized material reported as defective in Abnonnal Occurrence Report No. 50-313/74-11c.
Three completed welds in line 7DH-6 were visually inspected. No welding was in progress; therefore, the inspector selectively reviewed the weld records and radiographic film for five weld joints in Line No. 70H-6 (FW71, FW88, FW90, SW93 and SW105).
The stainless steel pipe was welded using Bechtel Weld Procedure No. P8-T-Ag, Revision 9.
The welding and inspection confonned to the USA Standard Code for Pressure Piping, Nuclear Power Piping, USAS B31.7.
No items of noncompliance or deviation were identified.
6.
Exit Interview The inspectors met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on March 3,1978.
The i
inspectors sumarized the scope and findings of the inspection.
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