IR 05000304/1981022
| ML20041E697 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/22/1982 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20041E696 | List: |
| References | |
| 50-304-81-22, NUDOCS 8203110256 | |
| Download: ML20041E697 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION III
Report No. 50-304/81-22
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Docket No. 50-304 Licenaa No. DPR-48 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:
Zion Station, Unit 2
. Inspection At:
Zion site, Zion, IL
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Inspection Conducted: October 13-14, 1981 and February 3-4, 1982 Inspector:
J. K
// M war Approved By:
D. H. Danielson, Chief G/.0h8*
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Materials and Processes Section-
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j Inspection Summary
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Inspection on October 13-14, 1981 and February 3-4, 1982 (Report No. 50-304/81-22)
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Areas Inspected: Observation of inservice inspection activities. Review of ISI documentation, certification of materials, equirment, and personnel.
This inspection involved a total of 16 inspector-hours by one NRC inspector.
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Results: Of the areas examined, no items of noncortpliance were identified.
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8203110256 820223 PDR ADOCK 05000304 G-PDR
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DETAILS Persons Contacted Commonwealth Edison Company (CECO)
- K. Grasser, Plant Superintendent
- K. Kofrom, Assistant Plant Superintendent
- C.
Solich, ISI Coordinator M. Madigan, Assistant ISI Coordinator Hartford Steam Boiler (Hartford)
J. Hislevy, Authorized Nuclear Inspector j
Westinghouse Electric Corporation (W)
S. Zastrow, ISI Engi,eer (Tool)
R. Haines, ISI Tool Operator Functional or Program Areas Examined 1.
Inservice Inspection (ISI) Program l
The ISI program for this the first interval, third period, first out-
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age for Unit 2 was reviewed for conformance to NRC, ASME Section XI
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1974, Summer 1975 Addenda, and Plant Technical Specifications 4.2.1.
The following areas and components were scheduled to be examined
during this outage.
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a.
Reactor Vessel
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(2) Outlet nozzle to shell weld (3) Outlet nozzle to safe end welds (4) Legaments between threaded stud holes b.
Pressurizer c.
Piping e.
Pressure Retaining Bolting f.
Reactor Coolant Pumps l
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Regenerative Heat Exchangers h.
Seal Water Injection Filters r
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Volume Control Tank j.
Reactor Coolant Filters k.
Seal Water Return Filters 1.
Integrally Welded Supports 2.
Personnel Certifications The following personnel certification records were reviewed for conformance to NRC and ASME Code requirements.
a.
Westinghouse Electric Corporation Name UT PT VT ET J. W. Bell IIR II W. F. Stock IIA R. A. Vollmer II S. J. Beehner II R. D. Rehak I
K. D. Stewart I
G. F. Testa II R. R. Cottrell I
Zetec Name UT PT VT ET R. S. Emery IIA J. D. Siegel IIA A. S. Neff IIA Sonic Systems Name UT P.'
VT J. Carson I
I II R. W. Curl I
I II J. F. Halley I
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L. McClain II II II R. McCalin II II M. Roberts II II II R. Spivey II II II S. Stanford I
I No items of noncompliance or deviations were identified.
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3.
Equipment and Materials The following equipment and materials used during this inspection period were examined for NRC and ASME Code certifications and cali-bration requirements.
a.
Ultrasonic Equipment Manufacturer Model S/N Sonic MK-1 01056E Sonic MK-1 731001 Sonic MK-1 781304 Sonic MK-1 784522
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Sonic MK-1 784523 Couplant Sonotrace 40 Batch No. 8005/8003 Ultragel II Batch No. 3176 Transducers f
Manufacturer Frequency, MH Size S/N
Panametrics 2.25 1.0" 30956 Panametrics 5.0 0.375" 35347 Aerotech 2.25 1.0" J24929 Aerotech 2.25 0.5 x 1.0" S790338 Aerotech 2.25 0.500" E18124
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Aerotech 5.0 0.375" F18124
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Aerotech 2.25 0.250" I23729 Aerotech 5.0 0.250" K08031 Aerotech 2.25 0.5 x 1.0" 00833T
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Aerotech 2.25 0.250" F07912 b.
Eddy Current Equipment Vector Analyzer Module III S/N-023 l
MIZ-12 Mixer S/N-162 MIZ-12 Mixer S/N-163 In line Standards S/N-I-30W/0100 Absolute Standards Heat No. NX-7735/QR-1335-7 H.P Unit No. 3968AZ-1 A/N-0538 c.
Liquid Penetrant Materials Mfg. Spotcheck Type Batch No.
Penetrant SKL-HF/s 81B080 Developer SKD-NF 79L004 SKD-S 60114 L-4-
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Mfg. Spotcheck Type Batch No.
Cleaner SKC-NF 79J083 Zyglo SKC-NF/ZC-7 80M078 No items of noncompliance or deviations were identified.
4.
Observation of Activities The inspector observed examinations of the following items being pe rfo rmed.
a.
Weld No. 8 CVCS letdown delay system Dwg. COM-2-2540 Calibration block - CWE-15 b.
Weld No. 5 and 6 8" By-pass Dwg. Com-1-4105 Calibration block CWE-10 c.
Weld SDM Reactor Coolant Pipe Calibration Block CWE-1-e-1488-3.030T d.
Loop No. 4, 2" Fill Dwg. 1-4409 c.
Welds 80580/8034D (visual examination)
No items of noncomplinace or deviations were identified.
5.
Documentation Review The following documentation of items examined during this-outage were reviewed.
Steam Generator eddy current examination results.
"A" Generator 1724 tubes of this generator were examined to the 7th support.
128 were examined for the full length.
Of those examined, 10 tubes were plugged.
"C" Generator
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1755 tubes of this generator were examined to the 7th support.
133 tubes were examined for the full length. Of those examined, 3 tubes were plugged.
Eddy current examinations of generator tubing was performed using the multifrequency EC method with 400 KHz-100KHz and 10KHz for differential examination and 100KHz for absolute examination.
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- RHR Hot leg, loop 1, 8" Welds No. 8 and 10, ultrasonic examination
Calibration Block CWE-10 Sketch - COM-1-4103 Results - No indications Loop 1, By pass, 8"
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Welds No. 5 and 6, ultrasonic examination Calibration Block - CWE-10 Sketch - COM-1-4105 Results - No indications Loop 1, 2" drain
Welds No. 9, 13, 28, 33, 39, 42, Liquid Penetrant Examination Sketch - COM-1-4112
Results - No recordable indications Loop 1, Reactor Coolant Pipe, 31" Welds No. SDM, 6DM, Ultrasonic Examination Calibration Block CWE-1 Sketch COM-1-4200
Results - No indications.
Loop 3, Reactor Coolant Pipe, 31" Welds No. SDM
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Calibration Block - CWE-1 Sketch - COM-1-4300 Results - No indications i
Loop 3, Accum S1S, 10" Welds No. 8, 9, 10, Ultrasonic examination Calibration Block CWE-7
Sketch - COM-1-4301 j
Results - No indications.
Loop 4, RHR Cold Leg, 8"
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I Weld No. 16, Ultrasonic Examination Calibration Block - CWE-10 Sketch - COM-1-4403 Results - No indications Pressurizer Surge, 14" Weld No. 4, Ultrasonic Examination Calibration Block - CWE-4 Sketch COM-1-4500 i
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Results - No indications
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Pressurizer Safety, 6" Weld No. 1, Ultrasonic Examination Calibration Block CWE-3
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Sketch - COM-1-4501 Results - No indications-6-J
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Loop 1, 2, 3, and 4, Steam Generators Welds No. 1-2, 1-3, 2-5, 3-6, 4-8, Ultrasonic Examination Calibration Block - CWE-27 Sketch COM-2-1100 Results - No indications Steam Generator Manway Bolts Loop 1 and 4, Ultrasonic Examination Bolts - 1-B2 through 1-B12 1-B15 through 1-B20 1-B23 through 1-B40 4-B1 through 4-B20 4-B25 through 4-B39 Sketch, COM-2, 1100 Results - No indications Volume Control Tank Weld No. I and 2 Calibration Block CWE-23 Areas Examined 190* through 196 from centerline Sketch - COM-2-1200 Results - No indications Loop 1 Feedwater, 16" Weld No. 14 and 15, Ultrasonic Examination Calibration Block CWE-3 Sketch - COM-2-2101 Results - No indica' ions Loop 2, Main Steam, 34" Weld No. 11, Ultrasonic Examination Calibration Block - CWE-32 Sketch - COM-2-2200 Results - No indications Recirculation Sump to RHR - 14" Weld No. 18, Ultrasonic Examination Calibration Block - CWE-5 Sketch - COM-2-2501 Results - No indications RHR Hot Leg Injection, 12" Welds No. 9, 10, 18, 20, 21, 22, and 23 Calibration Block - CWE-6 t
Sketch - COM-2-2510 l
Results - No indications RilR Pump Discharge, 14" Weld No. 19 Calibration Block - CWE-5 Sketch - COM-2-2521 Results - No indications
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Exit Interview.
The inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on February 4, 1982. The
inspector summarized the purpose and findings of the inspection and dis-
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cussed the upcoming program for the Unit 2 outage.
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