IR 05000295/1981003
| ML20003E493 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/20/1981 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20003E490 | List: |
| References | |
| 50-295-81-03, 50-295-81-3, NUDOCS 8104030684 | |
| Download: ML20003E493 (8) | |
Text
{{#Wiki_filter:. _ .. _ _ _ . . r O U.S. NUCLEAR REGULATORY COMMISSION . OFFICE OF INSPECTION AND INFORCEMENT
REGION III
Report'No. 50-295/81-03 ' Dochet No. 50-295 License No. DPR-39 Licensce: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Zion Station, Unit 1 t Inspection At: Zion Site, Zion, IL Inspection Conducted: January 13, 20, and February '17-19,1981 Mhem.%!Nw ,/ 1 Inspector: k'. J. Key O'10/* # "t* , / .DYAb-h~ .
3 bL j?/ Approved By: - D. H. Danielson, Chief C Materials and Processes Section Inspection Sammary- , Inspection on-January 13, 20, and February -17-19,- 1981 (Report No.
50-295/81-03) Areas-Inspected: Inservice ir.spection program, procedure amendments, and ' review of documentation of e) tination; observation of steam generator .manway flange repair. The.it.pection involved.a total of 40 onsite inspector-hours by one NRC inspector.
Results: 'No items of noncompliance or deviations were identified.
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__ _ _ . . DETAILS Persons Contacted Commonwealth Edison Company (Ceco)
- K. L. Graesser, Plant Superintendent
- R.
E. Shannon, ISI Coordinator .
- C.
Solich, Assistant ISI Coordinator
- B. - Harl, Quality Assurance Supervisor T. Lukins, Quality Control Supervisor J. Mathews, Quality Control Engineer
- Denotes those present at the exit interview.
Licensee Action on IE Bulletins IE Bulletin No. 79-13 'During the fall 1979 refueling outage the licensee was requ: red to perform radiographic examination of all feedwater piping connected to the steam generators. This resulted in repairs having to be made. The results of
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which are documented in IE-Report No. 50-295/79-22; 50-30*/79-24 .uring this outage, radiographic' examination of the repairs was performed.
laese were reviewed by the -inspector.for conformance to ASME Code and Regulatory' commitments.
Steam Generator IA Line 1FWO14-H1-N15-16" Field Weld No.J430-Steam Generator IB Line 1FWO22-H1-N22-16" Field Weld No'. 457-082-A88/458 Steam Generator IC-Line IFWO17-H1-N13 Field Weld No.-439 Steam Generator'1D Line IEWO11-H1-N15-16" Field Weld No'. 448 ~ =This closes' followup activities re, lated to IE' Bulletin No. 79-13.
'IE' Bulletin'No.'80-08: ~ - As La result of' NRC examinations performed and documented in IE Report No.
' -50-295/80-15;;50-304/80-15; and actions _taken by the licensee, documented' . . -{2 - -
- _ - .- .- ' - . . in their August 15, 1980 response to Region III office, activities required by IE Bulletin 30-08 are closed.
Functional or Program Areas Examined 1.
Inservice Inspection Program Review (ISI) The inspector reviewed the ISI program for this third period of the first interval for Unit No. 1.
Items to be examined were in accordance with Plant Technical Specification, Section 4.2.1 and the requirements of ASME Section XI, 1974 Edition, including Summer 1975 Addenda.
Components and welds in the following systems were scheduled to be examined during this refueling outage: a.
Pressurizer welds b.
Steam generator welds and tubes _c.
Various systems piping welds d.
Pressurizer retaining bolting e.
Excess letdown heat exchangers f.
Residual heat exchangers . g.
Volume control tanks ~ h.
Reactor coolant filters 1.
Reactor coolant piping , No items of noncompliance or deviations.were identifie L .2.
ISI Procedures Review , The inspector reviewed the approved procedures for performing inservice examin3tions for revisions / amendments. Procedure ISI-70, Magnetic Particle Ex.aination, was amended to reflect the use of wet magnetic examination method as well as the dry method.
No items.of noncompliance or deviations were identified.
3.
Personnel Certification and Qualification Review The following. personnel records were reviewed by the inspector for compliance to 5RC'and ASME Code requirements: Commonwealth Edison Company-(Ceco) Name RT E E M VT _ T. I.ukens.
III II II II ~C.'Ginn~ II II J. Booth II II II.
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. . Superior Industrial X-Ray (SIX) R. T. Hueter II II II II II S. A. Turner II II II II II D. McMullin II II II Westinghouse Electric Company J.. Bell IIR II IIA J. Cannizzo II Il II R. Spivey II II II D. Brockey II II II R. McClain II II R. Curl I I II-S. Stanford I I No items of noncompliance or deviations were identified.
4 '. Equipment and Materials The following equipment and materials used to perform ISI - examinations was examined ~ by the inspector for calibration and certification requirements: Ultrasonic ' Inst ruments Sonic MK-1 S/N 60712E Sonic MK-1 S/N 00869E Sonic MK-1-S/N 774415 Sonic MK-1-S/N 780603 Sonic MK-1 S/N 780605 Transducers-Panametrics 5.0 MHZ .375" S/N 24144 Arotech.
2.25 MHZ 1" S/N 17923 Arotech 2.25 MHZ .5 x 1.0" S/N 00833T Arotech 2.25 MHZ .5 x 1.0" -S/N 00836T Arotech 2.25 MHZ .5" S/N L17988 - Arotech - 5.0 MHZ .250" S/N J25986 Arotech'- 2.25 MHZ .375 x.750" S/N B16931 Arotech.
-5.0 MHZ .375" S/N L22842-Arotech 5.0 MHZ .250" .S/N J18931
- Arotech 1.0 MHZ.
1.0" S/N G17034-Arotech.
2.25 MHZ . 5 LS/N 107955 - UT.Couplant,-Sonotrace 40,-Batch No.'s 8003/8005 - 4 -- _ - -
. . Liquid Penetrant Materials-Penetrant, Magnaflux, SKL-HF/S, 6A035 Developer, Magnaflux, SKDS-60144/SKD-NF, 79 LOO 4 Cleaner, Magnaflux, SKC-S, 79C014/SKC-NF, 80G032 No items of noncompliance or deviations were identified.
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Documentation' Review The following records of exawinations performed during the outage were examined during this inspection: a.
Pressurizer Welds 1 thru 9, Ultrasonic Examination . Calibration Block No. CWE-24 b.
Steam generator No. 1, 2, 3, 4 Butt welds 1-1 through 4-1, ultrasonic examination Calibration block No. CVE-24 c.
Accumulator SIS, 10" loop _No. I Butt' welds 14-16, ultrasonic examination Calibration block No. CWE-36 . d.- PER cold leg 8" loop No.1 Butt velds No'. 23-25, ultrasonic examination Calibration block No. 10 e.
RTD Return 3" ' Butt welds 17-20, ultrasonic examination Calibration block No. CWE-18 'f.
Loop 2, 2" drain line Welds No. 31 through 35, penetrant examination g.
SIS, BIT line.
Veld No. 12 h.
R.C. piping-Weld No. 5DM, penetrant examination 1.
R.C.' piping , eld No. 6DM, penetrant examination W ~ j.
RHR hot leg, loop 3 Weld No. 37-42, ultrasonic examination- . Calibration block No. CWE-10-5-- . m.. mm . m -..... -.m.-. a d
. k.
Reactor coolant piping, 29"-31" Weld No. 6 (DM) loop 4 Visual examination 1.
Pressurizer surge line, 14" Weld No. 5 through No. 7, ultrascnic examination Calibration block, CWE-4 m.
Pressurizer safety line Weld No. IDM Visual and penetrant examin, tion n.
. Volume' control tank Welds No. 2WS through 4WS Visual and penetrant examination o.
Reactor. coolant filter Weld No. 3WS Visual and penetrant examination p.
M.S. loop 2 . Weld No. 2, visual examination q.
Recirculation sump to RHR 18" Weld No. 10, 11, ultrasonic examination Calibration block CWE-2 No items of noncompliance or deviations were identified.
.6.
Steam Generator Tube, Eddy Current Examination During the manth of December 1980, an increase in the Alpha and Beta activity was noted by the chemistry department on the secondary side of IB steam generator.
- The - surveillance monitoring system showed a slight increase in March 198,0, with steady increases through October, and.the greatest increase
. in December 1980.
It' was calculated that leakage to the secondary, side ranged between 19 and 45 GPD until the unit was shut down on January _ 15, 1981.
'On~ January 23, 1981, the IB generator manway cover was removed, and the ' secondary side hydrostaticif tested at 600 psi. No evidence of.
leakage was detected in the channelhead during this test.
Eddy current (EC) examination of^about 99%~of the tubes through the first support was performed on the IB generator, with no indication detected. Steam Generator IC was also examined through the first- -support with no indications recorded.
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, . - EC examination through the "U" bend on generators IB and IC was performed with the following results. Of 2600 tubes examined on - IB. generator 20 tubes were plugged. Of the 2600 tubes examined on IC generator, 5 tubes were plugged, with most of the plugged tubes: located in rows 1 and 2.
Examination of generators IA and ID was limited to rows 1 and 2, with no indications recorded.
The following tubes in steam generator IC were plugged: Row Column
69 1-63'
43
66
66 The following tubes in steam generator IB were plugged: LRow Column
1-
8 2.
2
2:
2
2
2-14
15-
17
-24 2-46 -- 2'
'
- 2
2
2-79-2
- 80
.33
-35
29 32-During the installation of generator manway covers, the licensee - -observed.a crack in the: clad surface. of the manway flange on generator IB..The area was liquid penetrant! examined revealing an indication approximately.1/2" long. The complete flange and the remaining' Unit 1 Lsteam generators were penetrant examined revealing:no other indications.
The. licensee generated Discrepancy Report No. 22-1539 and Work Request-No. Z11339 for making repairs.
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_ ._. ... . Westinghouse Electric Corporation, Tampa, Florida, was contracted to perform repair activities using their procedures following review and approval by the licensee.
On February 17, 1981, the indication was excavated to a depth of approximately 1/16", then penetrant examined. The indication was still present. On February 18, 1981, the area was further excavated to a depth of approximately 1/8" x 5/8" long and penetrant examined, showing the indication removed.
The area was welded in accordance with (W) procedures and machived to assure a true gasket seating surface.
No. items of noncompliance or deviations were identified.
Exit -Inte rview 'The inspector met with licensee personnel (denoted in Persons Contacted Paragraph) at the conclusion of the inspection on February 19, 1981.
The . inspector summarized the scope and findings of the inspection.
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