IR 05000457/1990013
| ML20043A387 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/14/1990 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20043A386 | List: |
| References | |
| 50-457-90-13, NUDOCS 9005220002 | |
| Download: ML20043A387 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 111 Report No.:
50-457/90013(DRS)
Docket No.:
50-457 License No.:
NPF-77 Licensm -
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:
Braidwood Station - Unit 2 Inspection At:
Braidwood Site, Braceville, IL Inspection Conducted:
April 17, 23, ud May 7,1990 Inspector:
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K. D. Ward IIate
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Approved By: xN[u TL[(w~
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D. H. Danielson, Chief Date Materials and Processes Section Intpection Sunmary Inspection on April l'7, 23, and May 7, 1990 (Report No. 50 -457/90013(DRS))
Areas Inspected: ' Routine, unannounced safety 16spection of inserv1ce ins U51) activities including review of programs (73051), procedures (73052)pection
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observation of work activities (73753), and data review (73755).
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Re su l t 5,:
No yiolations or deviations were identified.
Based on the results of the inspectior, the NRC inspector noted the following:
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The ISI program planning was adequate and was completed approximately a week ahead of schedule.
The ISI co1 tractor personnel were very knowledgeable, and utilized stite of t'1e art equipment.
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The tubes in steam generators (SGs) A, G, C, and D were all found
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acceptable by eddy current examinations (ET) except for two tubes in SG "C" that were subsequent'y mechanically plugged.
The remote reactor vessel ultrasonic examinations were found to be
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acceptable on all of the eight welds examined.
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Per:ons Contacted Commonwealth Edison Company (Ceco)
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- R. Querio, Station Manager
- D. O'Brien, Technical Superintendent y
- K. Kofron, Production Superintendent
- D. Cooper, Technical Staff Supervisor
- R. Francoeur, 151 Group Leader
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- S. Notter, Quality Assurance Engineer
- E. Carrell, Regulatory Assurance
- P Holland, Regulatory Assurance T
- M. Sears, Technical Staff, ISI
- C. Barrett, Technical Staff, ISI U. S. Nuclear Regulatory Commission (V. S. NRC)
T. Tongue, Seninr Resident inspector T. Taylor, Resident Inspector
- J. Hopkins, Resident Inspector
E8ASCO Services Incorporated (EBASC0)
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J. Sr:,genberger, NDE Supervisor The NRC inspector also contacted and interviewed other licensee and contractor personnel.
- Denotes those present at the exit iterviev on May 7,1990.
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2.
Inservice Inspection (ISI) Unit 2 Review of Program (73051)
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EBASCO, Wi tinghouse Electric Corporation (W), and CECO personen1 performed the ISI program in accordance with ASME Section XI, 1983 Edition, Summer 1983 Addenda.
The staff size was sufficient to ensure that the ISI work was adequately perforred. Where ASME requirements were determined to be impractical, specific relief j
requests were submitted to NRR in writing.
The flRC inspector reviewed
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the specific relief requests including the related correspondence betweeti the licensee and the NRC. The NRC inspector reviewed audits /suc"eillances of ISI activities conducted by qualified personnel to verify comp: ance with the ISI program.
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Review of.' Procedures (73052).
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.All applicable ~ISI procedures were approved byLthe ANII and were:
reviewed by the NAC inspector.1The? ultrasonic _ examination (UT.)
n1 manual pulse echo detectioniinstruments and transducers of various:
angles, sizes and~ frequencies were used. The' nondestructive:.
o examinationslNDE)were-performedinaccordance.with.ASMESectio'n.V, J
i 1983 Edition. Summer 1983 'ddenda.;
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Data Review'andLEvaluation (73755)
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The examination: data was with'in:the criteriacas outlined in-.
d thejapplicableNDE:pr'ocedureiLand:ASME Code-. requirements.
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NRC. inspector 's review included examination of! documents W
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l relative to NDE! equipment fdata,1and evaluations.
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(2) Eddy Current Examinations!(ET):
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.Westinghouseutiliz5 dab'bbin:coilforthe Dasic eu misiation; o
and also used'a motorized =rotatingipancake! coil.(MRPC): probe.
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The ET operation was controlled.using:the modified MIZ-18
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software.-'A second independent evaluation wis.performe'd by%an-
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analyst ~ from W.
The' examination.whs performed in both the/hoti d
I and cold legs! with' thefexamination-originating jn'the' hot ? leg.-
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TheNRCihspectorrefiMedtheETreportsand'found:them
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acceptable.. The totalin~ umber of-tubes plugcjedj in each steam '
generator (SG) includin'g i actory and baseline. plugging is 'as
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SG!
- Factory
, Baseline'<
This Outage:
~10tal, Plugs.
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During this outage, all: the SGmecnanictil. plugs were W-i N
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Inconel 600. 'No sleeving was tierf anned this outage.'
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'(?). Remote Reactor Vessel Ultrescmic E a:rijiations (UT))
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F:ive degree andetwent9fdeIchae mdde si.hle element transducers l
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, were used tci examine the outlet nozzle to Shell welds. Beams-i
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.were! directed towards the vessel: centerline and scanning was-j
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i i-performed axially, Saile end wolds'were examined using 65, degree m
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loncitudinal inode dualz lement transducers.- Scanning was
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G per}ormed axially and circumferential1y. < H.o mnacceptable;
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g:o indica *tions were detected in the above examinations.
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The following welds were examined:-
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2RV-01-006 Nozzle-to' Upper Shell weld at 22 degrees vessel _
- Nozzle _ to; Upper Shell: weld at_158 degrees' vessel:
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.Nozzleito Upper Shell-weld ati202 degraes vessel-2RV-01-013
. Nozzle.to Upper.Shell weld at 338. degrees vessel 2RV-01-022 Nozzle:to Safe End at:22 degrees vessel
2RV-01-025 Nozzle to Safe;End at 158 degrees' vessel'
2RV-01-026" Nozzle to Safe End'at(202 degrees vessel
- 2RV-01-029 Nozzle to Safe End'at 338 degrees vessel
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'd. ' ' Observation of Work Activities (73753)
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The'NRC inspector observed work activities and had discussions.with..
J personnel,during thelISI activities. These observations' included the:
following:-
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(1)1 -EBASCOpersonnelperforsingmageticparticleexaminations.-(MT)
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on welds #2FW-11-18'and #2FW-11-19, both-onL11ne-~#2FW8213A-6".
'(2)' EBASCO personnel perfa ming ultrasu..ic examinations (UT)!on_ welds ~
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'#14.01, #11, #5, and i4, all on-line #2FW81AA-6, and welds '
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- 04-10 and #04-11 on line #2MS143AA-12.s
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(3) -Ceco _ personnel performing visual examinations on the~inside
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diameter of the nozzle welds (as stated in: Paragraph.2.c.(3)).,
An underwater mini-sub with a' television' camera was used in
'4 conjunction'with video' tape recorders.to examini these welds
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from inside the reactor. vessel.
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The NRC inspector reviewed the qualifications andicertifications of7 all. inspection personnel on site performing ISI:to ensure conformance:
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with SNT-TC-1A.
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N) violations or deviations-were identified.
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Exit Interview (30703)
The NRC inspector met with licensee repccsentatives (denoted inLParagraph
'f 1) at the conclusion of the inspection:on May 7,1990. _ The. NRC? inspector
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summarized the scope:and findings of the-inspection:noted inothis report.-
1; The NRC inspector'also discussed'the likely11nformational content of the-
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inspection report with regard to-documents or processes reviewed'by:the, M
'NRC inspector during the inspection. Tha licensee-did not identify any;
U-such-documents or processes as proprietary.
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