IR 05000373/1992022

Insp Rept 50-373/92-22 on 920915,1026-28,1102-05,20 & 1207.No Violations Noted.Major Areas Inspected:Review of Programs,Data,Procedures,Observation of Work Activities & Review of Erosion/Corrosion Program

ML20126B466
Person / Time
Site:	LaSalle
Issue date:	12/09/1992
From:	Jeffrey Jacobson, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20126B458	List: IR 05000373/1992022 ML20126B455
References
50-373-92-22, NUDOCS 9212220100
Download: ML20126B466 (7)

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U. S. NUCLEAR REGULATORY COMMISSION REOIOli III Report No. 50-373/92022(DRS) License No. NPF-11 Docket No. 50-373 Licensee: Commonwealth Edison Company l Opus West III -l 1400 Opus Place '

Downers Grove, IL 60515 Facility Namet LaSalle County Station, Unit 1 Inspection At: LaSalle Site, Marseilles, IL 61341 Inspection Conducted: September 15, October 26-28, November 2-5, 20, and December 7, 1992 October 26-November 5, 1992 (Region I)

Inspectof: b a, I t<c M /% /t-t-si D W#r / g Date (

Accompanied By: J. M. Jacobson, DRS (November 4, 1992)

L. Sage, IDNS (September 15, October 30, November 5, 10-11, and Decomiper 7, 1992)

Approved e'v') /2-f-7L J./K. Jacob on, chief! Date MeYeri is nd Processes Section Inanection <01nmary Inspection on Sentember 15, October 26-20. November 2- . and December 7, 1992; October 26-November 5, 1992 (Reaion I) (Report No. 50-373/92022(DRS)1-Areas Insnectedt. Routine, unannounced safety inspection of inservice inspection (ISI) activities-including review of programs (73051) , data (73755), procedures (73052), observation of work activities (73753), review of the. erosion / corrosion.(E/C)

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program (49001), and selected areas inspected by the NRC mobile NDE laboratory personnel.

9212220100 921215-PDR ADOCK 05000373 G PDR  :

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Inspection Summary 2 i l

l Resultdn lio violations or deviations were identified. based on '

the results of the inspection, the liRC inspector noted the following:

• Management was_ involved in the ISI and the E/C activities in an effective manne * The nondestructive examination personnel had adequate expertise to perform their function '

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All activities were controlled by well stated and defined- '

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DETAILS

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I Persons __Cantacted l Commonwealth Edison Company (Ceco)_

• Schmeltz, Project Superintendent

• M. Oclon, Technical Staff, ISI Group Leader l

• Lockwood, Regulatory Assurance Supervisor

• A. Kochis, ISI and E/C Coordinator

• D. Carlson, NRC Coordinator / Regulatory Assurance Diederich, Acting Site Vice President / Station Manager Iluntington, Technical Superintendent Silich, QC Supervisor bottingham, Chemistry Supervisor Richards, Station Quality. Verification Enginee Shields, Nuclear Licensing Administrator Jacobs, QC Inspector l

l St _ Nuclear Reculatory Comminplon (NRC)

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• !! ills, Senior Resident Inspector C. Phillips, Resident Inspector Jacobson, Chief, Materials & Processes Section, RIII Modes, Chief, Mobile NDE Labora*ory, RI l R. liarris, NDE Technician, RI l

P. Peterson, NDE Technician, RI Mingus, NDE Technician (NRC Contractor) Bryant, NDE Technician (NRC Contractor)

i D. Smith, Materials Engineer, NRR l

l Illinois Department of Nuclear Safety (IQHEL l l l

• Sage, llead, code Compliance Section

• Roman, Resident Inspector liartf ord Steam Boiler Inspection and -Insurance Comnany (11SB).  :

• Tetreault, ANII

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Conam Inspection (Conam) Ross, Site Supervisor i The NRC inspector also contacted and interviewed other licensee and contractor employee * Denotes those present at the exit interview on December 7, 199 l l

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. Inaprvice Inspection Egngcal A pro-ISI mooting was hold at the oito September 15, 1992, to discuss the scopo, schedule and any potential problem areas associated with the inservice inspection (ISI) activitic Erogram Review (73051)

Personnel from CECO performed the ISI in accordanco  !

with ASME Section XI, 1980 Edition, Winter 1980 i Addenda. No intergranular stress corrosion cracking ,

(IGSCC) susceptible wolds were examined this outag ' '

Where ASME requirements woro datormined to b impractical, specific relief requests were submitted to '

the Office of Nuclear Reactor Regulation (NRR) in >

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writing. The NRC inspector reviewod the specific-rollof requests including the related-correspondence betwoon the licensee and the NRC. The NRC inspector reviewed Audits / Field Monitoring Reports No. 01-92-11-059 and No. 01-92-10-073 and surveillances of the ISI program activitics performed by CECO. The audits and surveillanco efforts woro found to be acceptable and performed by qualified personnel. Organizational staffing for the ISI program was found to be acceptable  ;

and the services of an-Authorized Nuclear Inservico Inspector (ANII) woro procured from Hartford Steam .

Boiler Inspection and Insuranco Compan 'l

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The NRC inspector also reviewed the qualifications and cortifications of all inspection personnel performing ISI to ensure conformance with SNT-TC-1 Procedure Review (73052)

All applicablo ISI proceduros were approved by the ANII and were reviewed by the NRC inspector. The ISI proceduros woro found to be in accordance with ASME ,

Section V, 1980-Edition, Winter 1980 Addenda.- Data Review (73755)

The examination data was found to be in accordance with-the applicable ISI proceduros and ASME Code requitomonto. The NRC-inspector reviewed documents related to nondestructivo examination' equipment, data, and ovaluation .

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(1) Egnetor Vessel closurg_ Studs Dased on the cracking found on the Dresden Station reactor closure studs, CECO made a commitment to the NRC to perform both volumetric and surface examinations of reactor closure studs during this refueling outage. Ceco completed the required volumetric examination by performing " Enhanced End-Shot" ultrasonic examination of 100% (68) of" the reactor vessel closure studs. Ceco also completed the required surface examination using the wet fluorescent magnetic particle examination method on 12 studs. The five studs removed each outage to allow-for the installation of the

" Cattle-Chute" were also examined using the fluorescent magnetic particle examination metho No unacceptable indications were detected in any of the studs examine (2) Reactor Vessel Head Based on the indications found on the Quad Cities .

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Station reactor head, CECO made a commitment to the NRC to perform a visual examination of the interior of the reactor head during this refueling outag This visual examination was completed and no evidence of cracking or other detrimental conditions were discovered, including no unusual rust or corrosio e. Observations of Work Activities (73753)

The NRC inspector observed work activities and had discussions with personnel during the ISI activitie These observations included the-following:

(1) Ultrasonic,_ magnetic particle, and radiographic examination of wolds located on a piping subassembly fabricated by Ceco for the reactor water cleanup system. All examinations were performed to procedures meeting Code requirement Subsequent to the examinations performed by Ceco, NRC-technicians ultrasonically examined the piping subassembly weld In an effort to optimize the examination, a transducer with a foreshortened shoe was selected. This transducer permitted better access to weld No. 41-51 (elbow to valve)

and resulted.in the detection of an indication which had not been recorded by the CECO examinatio .

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Following the NRC examination, Ceco re-examined the weld using a transducer similar to tha one used by HRC, recorded the indication, and ovaluated it as beam redirection and wold joint geometr While the NRC oncouragos the optimization of examination techniques to improve the detection of indications and serve as an aid in ovaluation of subsequent ISI, it should be noted that the initial examination performed by Ceco met Code requirement (2) CECO personnel performing visual examinations (VT)

using an underwater TV camera on the followings (a) HP and LP core spray spargers and sparger  !

nozzle '

(b) Access hole covers (ultrasonic examinations were also performed, finding-the covers acceptable).

(3) GE personnel performing VT from inside the reactor vessel using an underwater TV camera. The tapes were reviewed by the NRC inspector and the results were discussed with the NRR staff by the licensc Some cracking was noted in the steam dryor -'

assembly; however, no significant changos were noted since the last outage, and~no repairs wore require No violations or deviations were identifie . Erosion / Corrosion-(E/C) Activities (49001)

Commonwealth Edison Company began their erosion / corrosion (E/C) program in 1988. A formalized procedure and administrative-controls were established to ensure continued long term implementation of an E/C monitoring program for piping and components.(Reference NRC Inspection Report-N /91026(DRS)). -

For this refueling outage, Ceco selected an inspection of approximately 21 components,_ utilizing tho'EPRI_Chec, Chocmate computer program. Of_the 21 components examined,_

all wero found to be acceptable. Due to loaks in the heater drain valves, four valves _that were not in the E/C program were ultrasonically examined. The:following are the e results:

Nos. 1HD0538 and L-14675: Minor E/C noted, area ground smooth and valve internals replaced with a new style to ~

prevent future damag li - - - _ _ . . . _ ._ _ _ _ _a ._ _ _ .. .-

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Nos. 1HD053C and L-14676: No significant E/C note Valve internals replaced with a new style to prevent future damag *

No. 1HD056A and L-14677: Through-wall E/C note Valve body and internals replaced with new styl *

Nos. 1H0056C and L-14679: No significant E/C noted.-

Valve internals replaced with a new style to' prevent future damag The NRC inspector reviewed the E/C program, procedures, NDE certifications, data from previous inspections, and observed Ceco and Conam personnel performing ultrasonic thickness examinations of piping components on the extraction steam -

syste No violations or deviations were identifie . EXLt Interview (30703)

The NRC inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection and summarized the scope and findings of the inspection noted in this report. The NRC inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during -

the inspection. The licensee did not identify such documelits/ processes as proprietar _

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