IR 05000010/1978012
| ML19340A817 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/17/1978 |
| From: | Danielson D, Lee E K, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A814 | List: |
| References | |
| 50-010-78-12, 50-10-78-12, 50-249-78-11, NUDOCS 8009040646 | |
| Download: ML19340A817 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-010/78-12; 50-249/78-11 Docket No.50-010; 50-249 License No. DPR-2; DPR-25 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Dresden Nuclear Power Station, Units 1 and 3 Inspection At: Dresden Site, Morris, IL Inspection Conducted: March 2, 6, 8-10, 29 and 30, 1978 Inspectors:
E. W. K.
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K. D. Ward d///
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Approved By:
D. H. Danielson, Chief M// 7/7/
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Engineering Support Section Inspection Summary Inspection on March 2, 6, 8-10, 29 and 30, 1978 (Reports No.
50-010/78-12; No. 50-249/78.11)
Areas Inspected: Unit 1 HPCI System Demineralized Water Storage Tank welding activitien, records and procedures. Unit 3 ISI " kick-off" meeting, procedures, work activities and records; replacement of portion of the 3" CRD return line; NDE of 4" Recirculation Bypass lines, Feedwater and CRD return line nozzles; removal of CRD return line nozzle thermal sleeve; repair of CRD return line no2.zle) pipe support and restraint systems. The inspection involved a total of 65 onsite inspection-hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted Licensee Employees
- D.
Farrar, Technical Staff Supervisor
- G.
E. Groth, Station Construction Engineer S. Harris, Technical Staff Engineer
- T.
Jansen, Technical Staff Engineer
- J.
Kotowski, Technical Staf f Engineer
- R.
Kyrouac, Quality Control Engineer J. Martin, Technical Staff Engineer
- G. W. Reardanz, QA Coordinator
- B.
R. Shelton, Administrative Assistant
- B.
B. Stephenson, Station Superintendent W. Witt, Level 3 Examiner Lambert, McGill and Thomas, Inc.
E. Thomas, Level 3 Examiner Rartford Steam Boiler and Insurance Company
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F. Roose, Authorized Nuclear Inspector
- Denotes those present at the exit interview.
Functional or Program Areas Inspected 1.
HPCI System Safety Related Structure Welding
The Unit 1 Demineralized Water Storage Tank is being field fabri-
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cated by Chicago Bridge and Iron Company (CB&I) to ASME Code,Section III, 1974 Edition including Summer 1975 Addenda. The purpose of this inspection was to observe work activities and to randomly review procedures to ascertain that the Code, NRC and specification requirements were met.
The following documents were reviewed:
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a.
CB&I welding procedures No. WPS-E308/61459, No. WPS-E309/61459 and their procedure qualification records, b.
Sargent and Lundy Engineers Specification No. K-3157.
c.
CB&I procedure No. FClN, Rev.1.
d.
CB&I procedure No. RTP-61459.
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e.
Stoody Company Product Certifications No. 557-75 and No. 3114-74.
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Five CB&I welders qualification.
g.
Three CB&I NDE personnel qualification.
h.
Radiograph films of weld joint No.14A-1.
The inspectors observed a portion of the welding of the bottom
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ring to floor plate and second to third ring circumferential welds. The inspectors determined that (1) applicable weld procedure and weld material were used, (2) appearance of weld surface was acceptable and (3) work area was reasonably clean and free of weldrod stubs.
No items of noncompliance and deviations were identified.
2.
Special Inspection - 4" Recirculation Bypass Lines, Feedwater and CRD Return Line Nozzles a.
Four Inch Recirculation Bypass Lines All welds on the 4" Recirculation Bypass lines (loops A
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and B) were examined by UT utilizing Commonwealth Edison Company (CECO) procedure No. NDT-C-2, Rev.10.
The inspector reviewed.the UT reports and noted that numerous indications exceeding 100% DAC were reported. The indications were evaluated by the examiner as configuration geometry.
b.
Feedwater Nozzles All four feedwater nozzle inner radii and bores were examined by UT utilizing CECO procedures No. NDT-C-24, Rev. 3 and No. NDT-C-25, Rev. 1.
The inspector reviewed the UT reports and noted that no recordable indications were reported except one indication was reported on each of the bores of nozzles A and D.
Both the indication were 60% DAC and identified when performing " Scan C."
The indications were evaluated as spots in the cladding.
c.
CRD Return Line Nozzle i
The CRD return line nozzle inner radius was examined by UT utilizing CECO procedure No. NDT-C-26, Rev. 2.
The inspector reviewed the UT report and noted that no recordable indications were identified.
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The inspector determined that the reports mat the applicable procedure requirements and they were reviewed by the CECO
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OAD Level III inspector and Authorized Inspector.
No items of noncompliance or deviations were identified.
3.
Removal of CRD Return Linh Thermal Sleeve and Repair of CRD Return Line Nozzle During a visual examination of the CRD return line thermal sleeve, several crack-like indications were identified at the bottom of the thermal sleeve retaining ring. The licensee decided to remove the thermal sleeve, the retaining ring and PT the nozzle inner radius and the area below the nozzle. Numerous linear indications were identified by PT.
The indications were located in an area between 160 to 200 and approximately 12" below the nozzle centerline. The length of the indications varied from 1/8" to 6" and were orientated both radially and circumferential1y. All the indications were removed by grinding. Final measurement after grinding indicated that the deepest ground out area was on the reactor vessel wall approximately 5" below the nozzle. The total depth was determined to be 27/32" of which 17/32" was in the base metal.
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The inspector reviewed the documents under Work Request No.
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9173. The documents included travelers, and work and NDE procedures. The inspector determined that the documents are acceptable.
No items of noncompliance or deviations were identified.
4.
Replacement of Portion of the 3" CRD Return Line During UT of CRD return line welds, an indication of 100% DAC was found on the pipe side heat-affected zone of the pipe to safe-end weld. The indication was believed to be a crack on the inside surf ace on the pipe, having a length of approxi-mately 1/2" long located at about 80. The licensee decided to replace the portion of the line from the safe-end to pipe weld to the first 90 elbow with a new section of pipe and a 90 elbow.
The inspector reviewed the replacement package under Work Request No. 2356. The documents included traveler, weld inspection records, material certifications, and welding and NDE procedures. The inspector determined that the documents met the applicable code and procedural requirements.
No items of noncompliance or deviations were identified.
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5.
Review of Inservice Inspection (ISI) Program
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The inspectors reviewed the Dresden 3, Spring 1973, ISI program and the 10 year ISI plan.
It was determined the ISI program has been approved and both the ISI program and the ISI plan met the requirements of the Technical Specification and/or the 1971 ASME B&PV Code Section XI including Summer 1971 Addenda.
It was further determined that examinations to date have exceeded the minimum code reqtirement for the 2/3 inspection interval.
No items of noncompliance or deviations were identified.
6.
Review of ISI Procedures The inspectors reviewed eight ultrasonic examination procedures, two dye penetrant examination procedures, one visual examination procedure, four NDE personnel qualifications, two ultrasonic
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instrument calibrations and eight transducer certifications.
It was determined that the above documents met the 1971 ASME B&PV Code,Section XI, including Summer 1971 Addenda and procedural requirements.
No items of noncompliance or deviations were identified.
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7.
Observation of ISI Work Activities
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The inspectors observed the following work activities:
a.
Ultrasonic examination and calibration of Feedwater Nozzle B inner radius and bore. No reportable indication was found.
b.
Ultrasonic examination of loop A Core Spray System Welds No. 10-6 and No. 10-K-7A.
No reportable indication was found on weld No. 10-6.
Two indications (85% and 60% DAC)
were found on weld No.10-K-7A.
The indications were evaluated by the examiner as outside and inside diameter geometry.
c.
Ultrasonic examination of RPV head to flange weld. One indication (20% DAC) was found and evaluated by the examiner as slight inclusion in the weld, d.
PT examination of Shutdown Cooling System weld No.16K16.
No reportable indication was found.
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The inspector determined that the above examinations were con-ducted in accordance with.the applicable procedures.
It was
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further determined that personnel performing the examinations were qualified and that the equipment used was calibrated.
No items of noncompliance or deviations were identified.
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8.
Review of ISI Records i
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The inspector reviewed five ultrasonic examination, four liquid penetrant examination and four visual examination reports. The
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reports reviewed were PPV longitudinal weld, Main Steam nozzle weld, Recirculation System piping weld, safe-end to RPV nozzle
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weld, RPV head ciudding and piping welds in the HPCI and Shutdown Cooling systems. The inspector determined that:
(1) the reports
I were reviewed by the licensee and the Authorized Inspector, (2) the applicable procedural. requirements were met and (3) no
defects were identified.
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a 9.
Surveillance of Pipe Support and Restraint Systems
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a.
Review of Program and Procedures
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The inspector reviewed procedures No. DMP-212, Rev. 2 and
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No. DTS-020-1, Rev. 2.
It was determined that the procedures are acceptable and met the Technical Specification requirements.
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b.
Observation (
The inspector independently inspected five (5) hydraulic
anubbers inside the drywell, four (4) spring hangers inside i
the drywell and one (1) mechanical snubber inside the drywell and the associated supporting structures for the above items.
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The inspector determined that (1) deformation or forced bending are not evident, (2) bolts and nuts appeared to be tight and secure. (3) spring hangers appeared to be in their
appropriate positions, (4) fluid in the hydraulic snubbers does not appear to be leaking and (5) deterioration and
corrosion are not noticeable except on the pipe attachments
of spring hangers No. B3-3002 and No. B3-3203. The I
inspector noted that the pipe attachments of the above spring
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hangers are badly rusted and flaking was also noted.
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c.
Review of Records
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The inspector reviewed the hydrsulic snubbers inspection reports performed on March 11 and 20,1978. It was deter-mined that the inspections were conducted in accordance with the Technical Specification and procedure requirements, d.
Hydraulic Snubber Replacement Program The licensee planned to replace all hydraulic snubbers inside the drywell with mechanical units manufactured by Pacific Scientific Company. During this outage, fourteen 10 KIP units were replaced. No welding is required for the replacement of the 10 KIP units.
No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives at the cor.clusion of the inspection on March 30, 1978. The inspector summarized the scope and findings of the inspection. The licensee acknowledged the information and stated that rust on components referenced in paragraph 9b will be cleaned and inspected prior to returning Unit 3
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to power.
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