IR 05000295/1978022
| ML19263C121 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/04/1979 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19263C120 | List: |
| References | |
| 50-295-78-22, NUDOCS 7902070073 | |
| Download: ML19263C121 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-295/78-22 Docket No. 50-295 License No. DPR-39 Licensee: Commonwealth Edison Company P. O.
Box 767 Chicago, 11 60690 Facility Name:
Zion Nuclear Station, Unit 1 Inspection At:
Zion Site, Zion, IL Inspection Conducted: October 3-5 anc November 8-9, 1978
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Inspector:
k'. J. Key gh ff'/7'
s Approved By:c D. F. Daniel' son ~, Chief t/ql,y)
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f Engineering Support Section 2 Inspection Summary Inspection on October 1-5 and November 8-9, 1978 (Report No. 50-295/78-22)
_ Areas Inspected:
Inservice Inspection: review of program, review of procedures, observation of work and work activities, and data review and evaluation.
The inspection involved a total of 40 onsite inspectien-hours by one NRC inspector.
Results:
5, items of noncompliance or deviations were identified.
7902070073
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pETAILS Persons Contacted
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Commonwealth Edison Company (CECO)
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Soth, Administrative Assistant B. Shannon, Technical Staff, ISI Coordinator C. Silich, Technical Staff Engineer
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R. Kuhner, Quality Assurance Inspector
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J. Marianyi, Technical Staff Supervisor
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P. Lelder, Assistant Supervisor Hartford Steam Boiler Company J. Mislevy, Authorized Inspector Wesringhouse Electric Corporation (W)
B. J. Lefebure, Pvsject Manger
- Denotes those attending tne exit interview.
Functional or Program Areas Inspected 1.
Inservice Inspection (ISI) Program The RIII inspector reviewed the ISI program for this outage of Unit No. 1, and determined the following:
The ISI program had been reviewed and approved by the a.
licensee.
b.
Adequate QA requirements were established and approved to cover ICI activities including:
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Qualification of Personnel (2)
Examination Reports (3)
Acceptance Criteria (4)
Identification of components covered by the ISI program (5) Work and inspection procedures were established, reviewed, approved, and controlled.
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(6) Documents relating to ISI activities were generated, reviewed, and controlled in accordance with the licensees Quality Assurance Manual.
(7)
Examination procedures include control and calibration
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of equipment.
(8) The ISI program specifies the NDE to be performed, that records of activities are to be legible and retrievable, and refers to identification of materials and components important to safety.
The scope of inservice inspection includes the areas to c.
be examined in accordance with the requirements of ASME Section NI, 1974 Edition including Summer 1975 Addeada.
d.
The inspect 1un intervals and extent of examinations for the first 10 year period are in accordance with ASME Section XI IW3 2600 and Plant Technical Specification 4.2.1.
The ISI program specifies NDE personnel qualifications and e.
that QC inspectors will meet the requirements of R.G.l.58, SNT-TC-1A, and ANSI, S45.2.6.
No items of noncompliance or deviations were identified.
2.
Procedure Review The Nuclear Services Division of Westinghouse Electric Corporation has been contracted by the licensee to develop procedures and perform ISI examinations for the first inspection interval. The RIII inspector reviewed the following NDE procedures and deter-mined that they are in compliance with ASME Section XI require-ments.
In addition, they wer2 revicwed and approved by the licensee.
Technical requirements were specified for each examination method used.
Inspection Procedure:
OPS-SSD-101, Revision 5.
a.
Titled:
Preservice and Inservice Docuzentation.
b.
Inspection Procedure:
ISI-8, Revision 7.
Titled: 'lisual Inspection Procedure.
c.
Inspection Procedure:
NSD-ISI-10, Revision 4.
Titled: Prese vice and Inservice Examination Manual Ultrasonic Equipment Qualification.
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d.
Inspection Procedure:
ISI-11, Revision 9.
Ti t l e<' :
Liquid Penetrant Examination Procedure, In'spection Procedure:
ISI-15, Revision 6.
c.
Titled: Ultrasonic Examination of Studs, Bolts and Nuts.
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Inspection Pr,cedure:
151-41, Revision 4.
Titled:
Manual Ultrasonic Testing of Reactor Coolant Pump Flywheel, g.
Inspection Procedure:
ISI-47, Revision 2.
Titled:
Mar.ual Ultrasonic Examination of Circumferenti il and Longitudinal Butt Welds in Ferritic Vessels of 2.5 Inch Thick and Greater.
h.
Inspection Porcedure:
ISI-87, Revision O.
Titled:
Reactor Ves,el Internal Drive Rod Assembly Survey.
i.
Inspection Procedure:
ISI-205, Revision 2.
Titled: Manual Ultrasonic Examination of Full Penetration Circumferential and Ingnitudinal Butt Welds.
No items of noncompliance or deviations were identified.
3.
Ob_servation of Work and Work Activities Liquid Penetrant Inspection ( P'l )
a.
The RIII inspector observed PT and VT examination of the recirculation loop No.
2, 1.5 inch, Safety Injection System Boron Injection Tank line, welds 20 through 26.
VT exami-nation of t hese welds was perf ormed af ter cleani.1g and prior to PT examination.
These examinations were performed in accordance with procedure ISI-8 and IS! 11.
All welds are identified on DWC CWE-1-4216.
Some indications were noted and recorded on two forge fittings.
These were believed to be scratches caused during removal of insulation.
The areas were flapped with an emery whee!, dressed with a file, reexamined and found to be clear.
'I b e following PT materials were used during the examination.
Magnaflux Cleaner - SKC-S-56033 Magnaflux Penetrant - SKL-HF/S-6A035 Magnaflux Developer - SKD-S-6D144-4-
b.
Ultrasonic (UT) Examination, Steam Generator Weld The RIII inspector observed calibration and longitudinal beam examination of the channel head to tube sheet weld
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No. 1 on steam generator No. 1.
Seven inches of this weld was examined (100 inches to 107 inches from the
"0" reference point, the centerline of the hot leg manway).
This weld is identified in the ISI program as item No. 25, IWB-2600, B3.1.
UT examination was performed in accordance with procedure No. ISI-47 (DWG. No. CWE-1-3100) using the following equipment.
I.ccrument, Sonic 301, S/N-7310012.
Couplant - Ultragel.
Transducer - S/N-D24850, 1 inch, 2.25 Mhz.
Calibration Block - CWE-24, S/N-123W339, 5 inch.
The weld was also shear wave examined.
The inspector observed calibtr. tion of the instrument for the examination.
Instrument, Sonic MK-1, S/N-755109 Couplant - Ultragel Transducer - 0.50 inch X 1.00 inch, 2.25 Fmz, 60 S/N-B16817-600 Calibration Block CWE 24, S/N-123V339, 5 inch.
No recordable indications were noted during examination of this portion of the weld.
c.
Ultrasonic Examination (RHR System)
Inc Rlil inspector observed UT shear wave examination of the recirculation loop No. 2, 8 inch stainless steel RHR return line, weld No. 29.
Due to indications noted during the last examination, one hundred (100%) percent of this weld was examined in accordance with Procedure No. ISI 205, Dwg. CWE-1, 4204.
Indications were noted and recorded during the examination ranging from 20. to 80% of calibration in various locations around the circumference of the weld.
The licensees Level III examiner was present during the examination performed by the (W) Level III examiner.
It is not believed that the indications noted during the examination warrant removal at this time, however, it was-5-
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suggested, and the licensee representative agreed, that
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this weld will be removed during the next refueling ootage new spool.
The following equip;.ua and replaced wit i a was used during the examination.
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Instrument, Branson Model 301, S/N-72101 Calibration Block - S/5-P004, Material ASTM-A-376, type 316, schedule 140, 8" stainless steel pipe.
Transducer - Arotech-Gamma, 050 inch, 45, 2.25 Mhz S/N-016230, Shoe C.O.0-8.25 Couplant - Ultragel d.
Calibration Blocks The licensee is in the process of replacing calibration blocks and setting up a new system of identification and storage requirements.
The RIII inspector observed the condition of the blocks and verified material certifications on the following blocks:
Block No.
Size Heat No.
Thickness CWE-13 6" sch. 160 2631-4-2
.719" CWE-15 6"sch. 40 M-9950
.272" CWE-11 8" sch. 80 139(24
.528" CWE-5 14" sch. 40 14085
.438" CWE-17 4" sch. 120 M6108
.438" CWE-24 5 x 16.5 - 6 x 6,W 123V339 CWF-12 8" sch. 40S M0937
.322" CKE-18 3" sch. 160 26896
.438" e.
Eq u i pp.en t and Material Certificati2tj The RIII inspector observed and verified certification on the following equipment, and determined that ASMF Code and NRC requirements were being met.
Ultrasonic Instruments Sonic, Model MK-1, S/N-731001 Sonic, Model MK-1, S/N-780603 Sonic Mcdel MK-1, S /N-755109-6-
Transducers S/ h-013012, 2. 25 Mhz. 0.250" S/N-013014, 1.0 Mhz. 0.5" S/N-014575, 5.0 Mhz. 0.5"
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S/N-015912, 1.0 Mhz. 1.0" S/N-24600, 2.25 Mhz. 0.5 x 0.125" S/N-C18817, 2.25 Mhz. 1.0" S/N-C08885, 2.25 Mhz. 0.50 0x.50" S/N-D24850, 2.25 Mhz. 1.0" Couplant - Ultragel, Batch No. 4477 f.
NDE Personnel Oualification The RIII inspector verified qualification records of the following personnel, and determined that the requirements of SNT-TC-lA and ANSI N45.2.6 were being met.
Westinghouse Electric Corporation (W)
B. J. Lefebure - Level III P. E. Bukes - Level II R.
B. Weber - Level II Sonic Systems International (Sonic)
B. J. Aston - Level II T. M. Jones - Level III J.
Furr - Level I J. L. Cannizzo - Level II W. McKnight - Level 1 T. E'Ren - Level I Peabody Testing Services (Peabody)
R. L'febure - Level II E. Gressing, Jr. - Level II Nuclear Energy Services, Inc., CONAM Inspection nivision (CONAM) (Eddy Current Examination)
B. D. Marlow - Level III A. D. McConnell - Level II R. E. Marlow - Level II J. Bergsten - Level II A. F. Bertelson - Level II No items of noncompliance or deviations were identified.
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4.
Data Review and Evaluation The RIII inspector reviewed t'.ie following records and results of examinations performed during this outage for Unit No. 1.
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Reactor Vessel
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Program item No. 4 Ref erence ASME Section XI, IWB-2600, Bl.2 Closure Head Meridional Weld No. 4, 563.5" from 0 Dwg. CWE-1-1300 Weld type-Butt Extent of examination, 5 to 6 inches from 0 reference adjacent te weld No. 6.
Ultrasonic examination procedure No. ISI-47, Revision 2.
Visual examination procedure No. ISI-8, Revision 7.
Calibration Block, S/N-CWE-26, Et. No. 123V339 UT instrument - Sonic MK-1, S/N-731001 Transducer, Straight beam examination, S/N-D24850, size, 1", frequency, 2.25 Mhz.
Transducer. Axial scan, S/N-B16817, 0.5 x 1.0",
frequency - 2.25 Fmz, 60 Circumferential scan, used the same transducer.
b.
Steam Generator No. 1 Program item No. 10 Reference ASME Section XI IWB-2600, B3.1 Channel Head to Tube Sheet Weld No. 1-1 Dwg. CVE-1-3100 Weld type-Butt Extent of examination, 177" CW to 184" from 0 reference (Centerline of hot leg manway)
Ultrasonic examination procedure, No. ISI-47, Revision 2 Visual examination procedu e, No. ISI-8, Revision 7.
Ca.libration Block, S/N-CWE-24, Ht. No. 123V339 UT instrument, Sonic MK-1, S/N-755109 Transducer, straight beam examination, S/N-D24850
,1.0 inch, frequency - 2.25 Mhz.
Transducer, Axial scan, S/N-S750612, 0.5 x 1.0",
frequency - 2.25 Mhz, 45 Same equipment used for circumfrential scan.
c.
Auxiliary System Piping Program item No. 26 Reference ASME Section XI IWB-2600, B4.5 Loop No. 1,14" RHR take of f, welds 16 and 17
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Dwg. DWE-1-4101 Weld type-Butt Ultrasonic examination procedure No. 151-205, Revision '.
Visual examination procedure No. ISI-8, Revision 7.
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Calibration Block, S/N-CWE-4, Ht. No. 8393
Ultrasonic instrument, Sonic MK-1, S /N755109 Transducer, straight beam, S/N-J05737, size 0.375, frequency - 5 Mhz.
Transducer,Axialscan,SfN-H04504, size 0.5",
frequency, 2.25 Mhz, 45 Same equipment used for circumferential scan.
Program item No. 33 Ref erence ASME Section XI, IWB-2600, b4. 5 Six inch Pressurizer Safety welds 6 and 7 Dwg. No. CWE-1-4502 Weld type-Circumferntial butt Calibration Block, S/N-CWE-13, Ht. No. 2631-4-2 Ultrasonic instrument, Sonic MK-1, S/N-755109 Transducer, straight beam, S/N-J05737, size 0.375",
frequency, 5.0 Mhz.
Transducer, Axial scan, S/N-016230, size 0.5",
frequency, 2.25 Mhz., 45 Same equipment used for circumferential scan.
d.
Branch Connection Program item No. 34 Reference ASME Section XI, IWB-2600, B4.7 Loop No. 2.3" RTD Return weld No. 1BC Dwg. CWE-1-4205 Liquid Penetrant Procedure No. ISI-ll, Revision 7 Visual examination Procedure, No. ISI-8, Revision 7 Penetrant Materials Spot Check, Penetrant, Batch No. 5E067 Spot Check, Developer, Batch No. SE052 Spot Check Cleaner, Batch No. SLO 33 e.
Reactor Coolant Pump (loop No. 2)
Program item No. 72 Reference ASME Section XI, IWB-260C, B5.1 Closure Flange Bolting, (Bolts 1 through 24)
Deg. CWF-1-5100 24 Bolts 4.32 inch diameter, 30.5" long.
Ultrasonic examination procedure No. ISI-15, Revision 6.
Ultrasonic instrument, Sonic MK-1, S/N-755109 Calibration Block, S/N-CWE-28, Ht. No. 121707 Transducer, S/N-D24850, size, 1",
frequency - 2.25 Mhz.
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Reactor Ca_olant Pumy__Fl ywheel (loop No. 2)
Program item No. 76 Ref erence ASME Section XI, IWB-2600, B5.9 Loop No. 2, Flywheel
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Dwg. CWE-1-5100 Ultrasonic examination procedure No. ISI-41, Revision 4 Ultrasonic instrument, Sonic MK-1, S/N-755109 Transducer, S/N-J05821, periphery scan, size 3/4",
frequency - 2.25 Mhz.
Transducer, gage hole probe, S/N-24600, size 0.5 x 1" frequency - 2.25 Mhz.
g.
Circumferential Butt Welds Program item No. 101 Reference ASME Section XI, IWB-2600, C2.1 Eight inch SlS and CVCS system Weld Nos. 6, 8, 18 and 19 Dwg. CWE-2-2530 Ultrasonic examination procedure, No. 1S1-2G5, Revision 2.
Calibration Block, S/N-12, Ht. No. M0937 Ultrasonic instrument, Sonic MK-1, S/N-781304 Transducer, straight beam, S/N-J12706, size 0.5",
frequency - 5.0 Mhz.
Transducer, Axial scan, S/N-013172, size 0.5",
frequency - 2.25 Mhz.
Same equipment used for circumferential scan.
h.
y;._ Instruments The following data sheets on the identified UT instruments were available and reviewed.
In s t run.en t, S/N-731001 Horizontal linerity data sheet Vertical linerity data sheet Amplitude Control data sheet 1r.s t rumen t, S/N-780603 Horizontal linerity data sheet Vertical linerity data sheet Amplitude Control dats sheet Instrument, S/N-755109 Horizontal linerity data sheet Vertical linerity data sheet Amplitude Control data sheet
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No items of noncompliance or deviations were identitiec.
5.
Steam Generator Eddy Current Examination (ET)
The Rill inspector reviewed records of eddy current examination a.
of Unit No. 1 Steam Generator 1B, performed by Nuclear Entry Services Inc., CONAM Inspection Division, in accordance with Technical Specification 4.3.1.B.
The extent of examination was as follows.
Defect examination of 500 tubes through the U-bend, inlet side at 400 KHZ and outlet side 145 tubes at 400 KHZ.
Denting examination of 350 tubes through the top support, 250 tubes flow slots and outer perpheral at 400 KHZ.
Sludge examination 144 tubes through first support at 25 KHZ.
No rejectable indications were ident1'ied.
b.
The following equipment was used in the performance of gener-ator ET examination.
(1) Tube standard S/N 82-I, Inconel, Heat treat No. 8786, 7/8" OD x.048" wall (2)
Tube standard S/N 64, Inconel, Heat treat No. 6108, 7/8" OD x.051" wall (3)
Dent standard S/N 69, Inconel, Heat treat No. 8939, 7/8" OD x.050" wall (4)
Eddy Current Multitest, Automation Ind. Model E:I300, S/N-466, last calibrated August 11, 1978.
(5)
Eddy Current Multitest, Automation Ind Model EM3300, S/N-005, last calibrated July 14, 1978.
(6) Brush Recorder, Gould Model 220, S/N-13715, last cali-brated July, 21, 1978.
(7)
Brush Recorder, Gould Model 220, S/N 1'.563, last cali-brated June 30, 1978.
(8)
FM Tape Recorder, Zetec Model 2300s, S/N-002, last cali-brated June 19, 1978.
(9) FM Tape Recorder, Zetec Model 2300S, S/N-092, last cali-brated June 19, 1978.
(10) FM Tape Recorder, Zetec Model 2300S, S/N-165, last cali-brated June 19, 1978.
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(11) Vector Analyzer, Zetec Model 2, S/N-003, last calibrated
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July 14, 1978.
No items of noncompliance or deviations were identified.
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Exit Interview The RIII inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on November 9, 1978.
The inspector sumn rized the scope and findings of the inspection.
The re-lace-r ment of weld No. 29 in the eight inch loop 2 of RHR return line during the next refueling outage was discussed in detail.
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