. . U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-295/85025(DRS);50-304/85026(DRS) Docket No. 50-295; 50-304 License No. DRP-39; DPR-48 Licensee: Commonwealth Edison Company P.O. Box 767 - Chicago, IL 60690 Facility Name:. Zion Nuclear Power Station, Units 1 & 2 Inspection At: Zion site, Zion, IL Inspection Conducted: July 16 and 17, 1985 Inspector: W [/ f Date' Mwb h ! Approved By: D. H. Danielson, Chief Materials and Processes Section Date Inspection Summary Inspection on July 16 and 17 1985 (Report No. 50-295/85025(DRSh 50-304/85026(DRS)) Areas Inspected: Unannounced safety inspection to review the inservice inspection program, procedures, and examination documentation from the last refueling outages of Units 1 and 2. This inspection involved a total of 14 inspector-hours onsite by one NRC inspector. Results: No violations or deviations were identified. 8500070066 850001 DR ADOCK O g5
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Facility Name:. Zion Nuclear Power Station, Units 1 & 2
Inspection At: Zion site, Zion, IL
Inspection Conducted: July 16 and 17, 1985
Inspector: W [/ fDate'
Mwb h !Approved By: D. H. Danielson, ChiefMaterials and Processes Section Date
Inspection Summary
Inspection on July 16 and 17 1985 (Report No. 50-295/85025(DRSh50-304/85026(DRS))Areas Inspected: Unannounced safety inspection to review the inserviceinspection program, procedures, and examination documentation from the lastrefueling outages of Units 1 and 2. This inspection involved a total of 14inspector-hours onsite by one NRC inspector.Results: No violations or deviations were identified.
* Denotes those attending either the exit / entrance meetings or both.
2. Inservice Inspection (ISI), Unit 1
a. ISI Program
The inservice inspection for this first period, first outage of thesecond interval started on January 1,1965 and extended throughJune 10, 1985.
The program was developed in accordance with Plant TechnicalSpecifications Section 4.3 and is based on Section XI of the 1980Edition of the ASME B&PV Code including the Winter 1981 Addenda,
b. Procedures
Examinations were performed by Westinghouse Electric Corporation (W)in accordance with the following approved (W) procedures:
OPS-NSD-101, Revision 5.
Preservice/ Inservice Inspection Documentation
NSD-ISI-10, Revision 6.
Qualification of Manual Ultrasonic Equipment
ISI-11, Revision 10.
Liquid Penetrant Examination
ISI-41, Revision 5.
Manual Ultrasoni: Examination of Reactor Coolant Pump Flywheels
ISI-47, Revision 4.
Manual Ultrasonic Examination of Welds in Vessels
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151-70, Revision 2..
Magnetic Particle Examination4
ISI-206, Revision 1.
Manual Ultrasonic Examination of Welds
c. Qualification Records
The inspector reviewed certification records for the NDE examinationpersonnel listed below.
Name Method / Level'
UT PT VT MT4
N. A. Bolling II II II II
J. R. DeMailo II II II"
S. A. Sabo I I I,
| R. R. Sebacher II II II
T. R. Swartz I II IT. L. Stephens II II II
K. E. Ciampa II II IIR
d. Equipment and Material Certification
The certification records of the examination equipment listed belowwere reviewed by the inspector:
(1) UT Instruments
Mfg. Model S/N
Sonic MK-1 08018ESonic MK-1 08078ESonic MK-1 11222ESonic MK-I 05940E
Magnaflux Power 8A (Red) Batch No. 83H002Magnaflux AC Yoke, Model Y6, S/N-WNSD-002
e. Examination Records
The inspector reviewed the reports identified below of examinationsi performed during this refueling outage in accordance with the ISI
program.,
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Report / Sketch f:o. Weld No.
CWE-1-3100 4.1 S/G.
CWE-1-4100 5, 6, 7, 9, 10, 17, 18, 20.
Reactor Coolant System Piping
CWE-1-4101 1.
CWE-1-4103 3,4,5,6,7,8.
CWE-1-4104 16, 17, 18, 23, 24, 25, 26.
CWE-1-4111 1&2.
CWE-1-4302 41 & 42.
-CWE-1-4502 1.
CWE-2-1100 - 3-9.
CWE-2-2522 62 & 69.
CWE-1-4106 valve IRC 8073A (Bolts).
CWE-1-4112/U52 RCValveIRC8035(studs & nuts).
CWE-1-2100 (Pressurized) 10.
No violations or deviations were identified.
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3. Inservice Inspection, Unit 2
This interval 1, period 3, outage 3 started on March 30, 1984 andextended through July 2, 1984. Class 1 and 2 Components and Piping wereexamined and addy current examination was performed on approximately 900steam generator tubes 100% through the u-bend from the hot leg.
a. ISI Program
The inservice inspection for this refueling outage was performed inaccordance with Plant Technical Specification, Section 4.3 and wasbased on ASME B&PV Code Section XI, 1974 Edition including the i
Summer 1975 Addenda. ,
The program included examinations of welds in the components andpiping listed below:
Class-1
Reactor Vessel.
Pressurizer.
Steam Generators.
Pumps / Valves.
Class-2
Pressure Vessels.
Piping Systems.
Pumps / Valves.i
b. Procedures
The licensee approved Westinghouse examination procedures listedbelow were reviewed by the inspector:
Manual Ultrasonic Examination of Circumferential and LongitudinalButt Welds in Ferritic Vessels of 2 1/2" Thickness and Greater
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a
151-70, Revision 1.
Magnetic Particle Examination'
ISI-203, Revision 2.
Manual Ultrasonic Examination of Full Penetration Circumferentialand Longitudinal Butt Welds
RV-ISI-01, Revision 1.
Reactor Vessel Inspection Program Preparation and DocumentationI
c. Qualification and Certifications
Certification records of the examination personnel and equipmentlisted below were reviewed by the inspector for conformance to thereferenced codes, standards, and NRC requirements:
The inspector determined from his review of ISI documentation forthe last Unit 1 & 2 outages, that the examinations performed were inaccordance with the approved inspection program and met the require-ments of the referenced codes, standards, and NRC requirements.
5. Exit Interview
The inspector met with licensee site representatives (denoted in PersonsContacted paragraph) at the conclusion of the inspection on July 17, 1985.The inspector summarized the scope and findings of the inspection notedin this report. The inspector also discussed the likely informationalcontent of the report with regard to documents or processes reviewedduring the inspection. The licensee did not identify any such documents /