IR 05000304/1990009
| ML20043C231 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/30/1990 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20043C227 | List: |
| References | |
| 50-304-90-09, 50-304-90-9, NUDOCS 9006040258 | |
| Download: ML20043C231 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 111 Report No.: 50-304/90009(DRS) Docket No.: 50-304 License No.: HPF-48 Licensee: Caunonwealth Edison Company Pun Office Box 767 0hmto, IL 60690 Facility Name.
Pion Station, Unit 2 Inspection At: lion Site, Zion, IL 60099 Inspection Conuncef: April 2-4, 26, 30; and May 2, 9-10, and 22, 1990 3,/*,gn.,/ MN#
Inspector: K. L. m a Date 5/3eho D.1?%k f r-+~ Approved By: t-Danielson, Chief Date Mettn als and processes Section Inspection Summjgj; Ins ection on bro 2-4, 26, 30; and May 9-10, and 22, 1990 (Report No.
- T47%UDFI0d7 Areas Inspecte?.T Routine, unannounced safety inspection of inservice inspection USTI activities including review of programs (73051), procedures (73052), observation of work activities (73753), and data review (73755); and of an independent measurements inspection.
Results: No violations or deviations were identified. Based on the results of the inspection, the NRC inspector noted the following: The licensee's ISI program, procedures, work activities, nondestructive
examination results and interpretation were in compliance to tne ASME Code, Section XI, 1980 Edition, Winter 1981 Addenda.
The licensee demonstrated a positive commitment to assure the reliability
of the steam generators.
Stm generator transition girth weld indications, found by nondestructive examination (NDE) were dispositioned in accordance with the ASME Code, Section XI, 1980 Edition, Winter 1981 Addenda, n 9006040258 900530 PDR ADOCK 05000304 Q PDC
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- 1.
Persons-Contacted ' hf Connonwealth Edison Company (Ceco) 1's**
- T. Saksefski, Regulatory Assurance--
~, q~
- T. Rieck, Technical Superintendent J
- R. Wolf..ISI-Group Leader
- J.?Vost, Quality Control =
' 7' i T.. Joyce, Station Manager . ^
R.'Tolentino, 151 Engineer h R. Sunners, Engineering' Assistant- '
- .
U.LS. Nuclear Regulatory Commission (U. S. NRC) ' ' N' ,
- C. Patel.. Project Manager, NRR-
'
- R.:Leemon, Resident Inspector i
1J. Smith, Senior Resident inspector
A. Bongiovanni, Resident inspector [j H. Kerch Reactor. Inspector (Region 1) - ' R. Harris,ReactorInspector-(RegionI) [ W Mingus,'NDE Technician (NRC Contractor) ! -D. Wiggins, NDE Technician (NRC Contractor) [. F Westinghouse ElectMc Corporation (W) (.,
- E. Jackson, Steam Generator Service Manager Conam Inspection Service'(CONAM)
,, - M. Gortemiller, Level 111 Analyst, ET Hartford Steam Boiler Inspection and Insurance Company-(HSB)' , P.: Fisher, Supervisor, ANil The NRC~ inspector also_ contacted and interviewed other licensee and' ' contractor employees.
- Denotes those present at the exit interview on May 22, 1990.
- 2.
InserviceInspection(151), Unit 2
a.- General During the period of April 30 through May 11, 1990, an onsite ' i_ndependent measurements inspection was conducted on both Units 1 and 2.
This inspection was conducted by NRC Region I inspectors and - ' contracted nondestructive examination (NDE) personnel. The purpose of this. inspection' was to verify the adequacy of the licensee's NDE ,
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,_ _ _.... -.. . - ., . ' program during plant modifications. This was accomplished by duplicating, as near as possible, those examinations required by Code and regulations, and evaluating the results. The examination i results are documented in Region 1 inspection Reports No.
50-295/90012 and No. 50-304/90012.
b.
Review of programs (73051) Combustion Engineering (CE) personnel performed the eddy current examinations (ET), and Conam inspection, Inc. (CONA14) performed the WestinghouseElectricCorporation(W) performed analysis of the data.
An independent analysis was then , performed the by CE and Zetec.
remainder of the 151 program in accordance with ASt4E Section XI,1980 , Edition, Winter 1981 Addenda, c.
Review of Procedures (73052) All 151 procedures were approved by the Authorized Nuclear Inservice Inspector (AN11) and were reviewed by the NRC inspector. The manual pulse echo detection instruments and transducers of various angles, sizes, and frequencies were used. The NDE was performed in accordance with ASt4E Section V,1980 Edition, Winter 1981 Addende, d.
Data Review and Evaluations (73755) (1) General The data for the following examinations was within the criteria as outlined in the applicable NDE procedures and ASt4E Code requirements. The NRC inspector's review included examination of documents relating to NDE equipment, data, and evaluations.
(2) Eddy Current Examinations (ET) The L tec 1412-16A data acquisition and the Zetec DDA-14 Analysis Systein was used to conduct the ET. The ET included 100% of all steam generator tubes from the hot leg tube end to the seventh support plate in the cold leg. The results were as follows: Steam Total This Outage Total All Outages Generator Plugged Sleeved Plugged Sleeved A
82 225
B
0
0
17
57
D
0
0 All of the new steam generator tube plugs were type (W) Inconel
- 690 and the instalhd welded sleeves were fabricated by CE, i
_
. l . The eddy current examination (100%) program exceeded Technical Specification requirements, which requires sampling in accordance with Technical Specification Table 4.3.B.1.
(3) ExaminationofSteamGeneratorGirthWelds(Unit 2) Westinghouse (W)performedtheultrasonicexaminations(UT) on the steam generator upper shell to transition cone girth weld #6 on all four steata generators. The unacceptable indications found by (W) were verified by a Ceco Level 111 UT individual.
The following are the steam generator results: (a) 2A Steam Generator
Six indications were found by exttrnal UT.
One of these indications was verified as a surface ~ indication by internal MT and was removed as a boat sample. The results of the boat sample analyses will be submitted with the Zion Unit 2 report to flRR at a later date.
tione of the subsurface indications exceeded 50% DAC, hence no fracture mechanics work was required.
(Over ~ 50% DAC is unacceptable by UT.)
(b) 2B Steam Generator
Twenty indications were found by external UT.
~ Fourteen of these indications were verified as
surface indications by internal MT and were removed by grinding and blending.
Two of the subsurface indications exceeded 50% DAC ~ and were satisfactorily dispositioned by fracture mechanics.
(c) 2C Steam Generator
Eight indications were found by external UT.
- Seven of these indications were verified as surface
indications by internal MT and were removed by grinding and blending.
- None of the subsurface indications exceeded 50% DAC,
hence, no fracture mechanics work was required.
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, , (d) 2D Steam Generator 1, Twenty-two indications were found by external UT.
~ Nine of these indications were verified as surface
indications by internal tit and were removed by grinding and blending.
- Eight of the subsurface indications exceeded 50% DAC
and were satisfactorily dispositioned by fracture mechanics.
CECO extended the above recording beyond the ASl4E Code requirements. Ceco informed NRR that the indications were, in most cases, approximately 1" deep and 1" long.
In an effort to obtain additional information that may help identify the root cause of the indications, hardness tests were performed on the girth welds and the surrounding area. The results will be submitted to NRR also, e.
Observation of Work Activities (73753) The NRC inspector observed work activities and had discussions with personnel during the 151 activities.
These observations included the following: (1) NRC NDE van personnel performing various 151 activities.
(2) CE personnel utilizing the till-18A multi-frequency and the DDA-4 analyzer system.
(3) CE personnel performing ed6y current examinations on the tubes of the 4 steam generators.
(4) Ceco 1.evel 111 personnel performing ultrasonic examinations with the "P SCAN" instrument to size and verify the indications found in the girth welds.
(5) CONA14 personnel performing a second independent evaluation on the eddy current examinations.
(6) Westinghouse personnel performing visual examinations on the internals of the reactor vessel using a mini-submarine.
(7) Westinghouse personnel performing ultrasonic examinations on the steam generator upper shell to transition cone girth welds
- 3-6 steam generator "A"; #4-6 steam generator "B"; and #2-6 steam generator "C".
The NRC inspector reviewed the qualifications and certifications of ali inspection personnel on site to ensure conformance with SNT-TC-1A.
No violations or deviations were identified.
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'TheNRC(inspector'metwith. site 1 representatives (denotedinParagraph'1).
i . /.at the conclusion'of the~ inspection on May 22, 1990. The NRC. inspector-m ' sumerizedLthe scope and findings-of the,inspectionLnoted in this report.- '- ' n-aThe=NRC inspector:alsoLdiscussed the likely' informational content of4the.
.. s v? inspection report with regard to-documents or, processes: reviewed by.the-j
- NRCinspectorduringtheinspection.:.The' licensee'didnotidentifyanyi
, 1 such documents / processes as proprietary.
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