IR 05000374/1990005
| ML20043C239 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/30/1990 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20043C237 | List: |
| References | |
| 50-374-90-05, 50-374-90-5, NUDOCS 9006040266 | |
| Download: ML20043C239 (5) | |
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U.1S. NUCLEAR-REGULATORY COMMISSION.-
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REGION Ill
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Report No.:-- 50-374/90005(DRS)
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' Docket No.: i.50-374'-
License No.: -.NPF-18
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- Licensee
- -CommonwealthEdisonCompany-Post Office 4 Box'767 a
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Chicago, IL_ 60690
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Facility-- Name: LaSalle County Station, Unit 2
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Inspection At: _ LaSalle vite, Marseilles, IL 61341
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LInspection Conducted:
April 18 and.24; May 8 and 21, 1990 i
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~ Inspector: MM MM 8M/[fd
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K. b. Ward Date
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-Approved By:
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D. H.-Danielson,-Chief
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< Materials-and Processes Section j
. Inspection' Summary
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q Inspection on April'18 and 24; May 8 and 21,1990-(Report No. 50-374/90005(DRS);
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' Areas Inspected:. Routine, unannounced safety-inspection of, inservice a
. inspection <(ISI) activities: including review of programs-(73051), procedures-
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L(73052), observation.of work ~ activities (73753),'and' data review (73755).
Results: No violations'or deviations were identif.ied. Based on the results" d
_of the inspectio_n, the-NRC i_nspector noted the following-
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, Management was involved ~in the ISl' activities in an' effective manner.
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Ultrasonic examinations which identified midplate segregates-.in the'.
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reactor pressure vessel were performed by qualified personnel and.in accordance:with: ASME Sections-XI and. V-of the: Code; j
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LWell' stated and explicit procedures were used to' install a' temporary
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-clamp for the #15 jet pump sensing line.
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A, DETAILS Li f:..
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! Persons' Contacted
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'Consnoriwedith' Edison Company (CECO)
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--*GODiederich,StationManager
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. *W.-)Huntington, Technical-Superintendent
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- W. Betourne, Quality Assurance Superintendent -
(*T. Hammerich,-Regulatory Assurance
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- J. Giesker,. Technical-Staff Supervisor-
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- A. Kochis,' Technical Staff Engineer
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s*M. Oclon,1 echnical-Staff /ISI-
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U. S. Nuclear Regulatory Consnission (U. S. NRC)
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- T.. Tongue, Senior: Resident inspector
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R. Kopriva, Resident Inspector.
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- Hartford Steam Boiler Inspection'and-Insurance Company-(HSB)
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-*J. Tetreault,'AHil
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' General Electric Company--(GE)
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T. Brinkman,i Level III
The-NRC? inspector-also contacted and interviewed other licensee andL i
contractor employees. -
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- Denotes'those present'at the exit interview on May'21, 1990.
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Inservice Inspection (ISI), Unit 2 l
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- Reviewtof Program (73051)
if GE and_ Ceco personnel perfo'rmed the:ISI program in accordance with d
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' ASME Section XI, 1980 Edition, Winter 1980 Addenda. 'The-sampling.
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- 1-inspection-plan for-addressing-intergranular stress corrosion..
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cracking' (IGSCC)Econcerns was in accordance with-Generic Letter (GL) 88-01. A11 23 weldssinspected in accordance with GL.88-01 were
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found to be acceptable. The licensee did not make a request for-
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relief from the ASME Code.this outage. The NRC. inspector reviewed audits /surveillances-of ISI activities conducted by qualified q
personnel to verify compliance with the ISI program.-
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. Review of Procedures (73052)
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All applicable.ISI procedures were approved _by the,ANIl and were'
reviewed by the NRC-inspector. The GE smart ultrasonic system and?
manual; pulse. echo UT detection instruments with' transducers of
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various-angles, sizes, and frequencies were used. The nondestructive y
examinations (NDE) were performed;in'accordance with ASMELSection V, p
1980 Edition, Winter 1980 Addenda.,
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Data'ReviewandEvaluations(73755)
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(1)_. General.
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F The following examination data was within the criteria.as-
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outlined in the applicable NDE procedures and ASME Tode requirements. The.NRC-inspector's review included examination
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of documents relating to NDE equipment, data,Tand evaluations.
-(2)~ReactorPressureVesse1~HeadCladCracking(Unit 2)-
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Intense visual, liquid. penetrant, and-ferrite: examine.tions were performed by CECO and GE.1S1 personnel on the Unit 2; upper head
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Lin response to GE letters RICSILs 050 and 051 dated April 23,-1900,-
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and May 3. -1990. These examinations were performed on selected
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m areas of the inner cladding surfaces.
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automatic process LCEco stated that the head was>very smooth and-uniform.-- Areas that were clad using a manual-. process a_nd:then_-
blended, i.e., full-penetration. welds, were also smooth and
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showed no evidence of heavy! grinding.
Past and.present: ultrasonic examinations were performed on 2/3 of:the headito f.lange,_.
dollar, and four. meridian: welds. The reports showed no visible.
j evidence of mismatch at any weld joints, and'no indications _were-
detected during the nondestructive examinations.-
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CECoalsosentateam'ofSargentandLundy(S&L)andjGEengineers
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to the. Chicago Bridge and. iron (CB&I)'~ f acility' in-Houston, Texas, to review the original fabrication records. tin addition,_
a review of-available records-was conducted at>the.GE facility:.
i in San Jose, California. The_ records" search / review at.CB&I'andL l
GE showed no evidence of major rework in the welds or the t5
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cladding surfaces. Ceco believes..that these examinations f
satisfy the requierments for-GE's letters RICSils 050 and 051.
HRR was informed by CECO of the above activities and concurred
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with this conclusion.
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q A meeting was held by CECO on May 21, 1990, for the purpose of-i developing an inspection plan for Unit l'.
The inspection plan j
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included the reactor-vessel head, vessel-to-flange weld, and the
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upper shell region. CECO committed to the NRC to inspect these.
i areas because of the cracks found recently in the Quad Cities, Unit 2 reactor head.-
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ld.; 10bservation of' Work Activities (73753).
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- The NRC: inspector observed work activities in progress and W
had discussions with personnel riuring the observation of ISI-
. activities. 4These" observations' included _the following:
- (1)- A GE individual performing a liquid penetrant examination on weld-#RH-2009-12, Line #3RH;40CB-16".
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L(2) ;A-GE individual ~ performing a magnetic particle examination
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on weld.#RH-2009-13, Line #2RH-40CB-16".-
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(3) A CECO QA-individual performing: surveillance of EBASCO
. personnel performing NDE.
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L" (4). Observed by video, GE individuals performing ultrasonic examinations on welds-inside~the reactor pressure vesseli o ' - r'
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(RPV)usingtheGEautomatedRPV_inspectionsystem(GERIS)'.
L Longitudinal wave examination'of weld metal and shear wave examinations in two directions:using two beam angles:were C
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performed. Midplate_ segregates were recorded during the-intervice inspection that were acceptable in accordance
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with;ASME Section XI,' Paragraph IWB 3000, and ASME Section-
sg V,-Article 4, 1980 Edition, Winter 1980 Addenda. Ultrasonic:
^ reflectors showed a very close similarity between the present reflectors and the reflectors recorded during the; L
baseline preservice inspections. -These segregates are--
characterized as metallurgical / geometric in-nature and are.
f 5all in.the base material -
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Midplate segregates are caused by: a concentration of alloying
~ lements in specific regions, which. result in differences in e
the' metallurgical structure due to:variationsLin chemical
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composition. These variations 1 form during original. ingot /
solidification'and are concentrated inithe. top center of Lo
'the ingot. As the ingot gets rolled into plate, these segregates;are spread out through the center section of_the plate. These inclusions are found parallel to the plate ~
surfaces and are_often called stringers.
NRR was informed by Ceco of-the above activities and concurred.with this_
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conclusion.-
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(5) Observed by video, CECO individuals performing visual l
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examinations (VT) of the vessel internals using a
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y Westinghouse miniature underwater TV camera in conjunction with video tape recorders recording the examinations. The
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VT revealed cracks in the attachment welds between the-
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sensing line and the lowest sensing line bracket for the
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- 15 jet. pump.
VT of the welds on the remaining sensing line brackets for this jet pump showed no indications.= An
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analysis by GE determined that if this condition was left
"as is" for the next cycle, additional damage including a
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- break'in the sensing-line itself may result '. Therefore, GE recommended that a temporary clamp be installed during_ this outage and:a permanent modification be prepared'for i
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installation during the next outage. T1e nonsafety-related)
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clamp was installed and will. provide support for the_
cracked bracket that. holds the jet pump sensing _line to;the
- 15 jet pump diffuser. NRR was-informed by Ceco of the
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above activities and concurred with this conclusion.
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(6) GE personnel were observed performing visual examinations E
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on the steam dryer using a ~ Westinghouse miniature underwater =
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TV camera from inside the reactor vessel. -The video tapes y
recorded during these examinations were reviewed by the NRC
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inspector, Ceco. GE,-the ANII, and were discussed with the-
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-NRR' staff.~:GE determined that the cracks were acceptable
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.for one more ' cycle of operation and did not need to be-repaired before startup. CECO and NRR concurred with'GE's-conclusion. All the indications were near the top or_ the e
bottom of the support ring, and were similar to known cracks in several other steam dryer support rings at other
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nuclear power plants.
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The NRC inspector reviewed the qualifications and certifications of.-
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- all inspection personnel on site performing ISI to ensure conformance-
with SNT-TC-1A.
The personnel performing Ui in accordance with
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GL 88-01-were qualified at the Electric Power Research Institute
(EPRI).forIGSCC.
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Exit Interview The NRC inspector met with site representatives (denoted in Paragraph 1)
at the' conclusion of the inspection on May:21, 1990. The NRC inspector i
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t summarized the scope and findings of the inspection noted-in: this report.
The NRC inspector also discussed 1the likely informational content-of the inspection report with regard-to documents or processes reviewed by the i
NRC inspector during the inspection..The licensee did-not identify any j
such documents / processes as proprietary.
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