IR 05000254/1992024

Insp Rept 50-254/92-24 on 921006-1215.No Violations Noted. Major Areas Inspected:Isi Activities,Programs,Data, Procedures,Observation of Work Activities,Review of Erosion/ Corrosion Program & Facility Modifications

ML20126F251
Person / Time
Site:	Quad Cities
Issue date:	12/22/1992
From:	Jeffrey Jacobson, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20126F246	List: IR 05000254/1992024 ML20126F243
References
50-254-92-24, NUDOCS 9212300177
Download: ML20126F251 (6)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-254/92024(DRS) License No. DPR-29 Docket No. 50-254 Licensco: Commonwealth Edison Company Opus West III 1400 Opus Place Downers Grove,IL 60515 Facility Name: Quad Cities Station, Unit 1 -

Inspection At: Quad cities Site, Cordova, IL Inspection Conducted: October 6 through December 15, 1992 Inspector: 7I N,4' ///u K. D. Ward Date Accompanied By: Sage, Illinois Department of Nuclear Safety (October 28-29, and December 15, 1992)

Approved B : bo A ~s / L*d'-

J . J, . Sac ' son, Chief Date M'tc ial and Processes Section Inspection Summary -

InspeqLign_ conducted on October 6-9. 20-21, and December 15, 1992 (ReDort No. 50-2 54 / 9J 024 (DRS) )

breas Inspepted: 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)

program (49001), and racility modifications (37701).

Results: No violations or deviations were identified. Based on the results of the inspection, the NRC inspector noted the following:

The licensee adequately demonstrated the ability to properly implement the modifications, E/C, and ISI program *

The ISI, E/C and modification personnel were very knowledgeable, and utilized state of the art equipmen *

Management was involved in the ISI, E/C and modification activities in an effective manne gDR ADOCK 05000254 PDR

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I DETAILS

? Persons contacted  ;

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G2pmonwealth Edison Company (CEcol

• R. Bax, Station Manager i

• G. Knapp, ISI/IST Group Leader

• J. Wethington, Assistant Technical Staff Supervisor

- *T. Kuksuk, ISI Coordinator i

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• R. Ruesch, E/C Coordinator

=D. Kanakares, Regulatory Assurance V. Goetz, Technical Staff U. S. Nuclear Reaulatory Commission (NRC).

• Taylor, Senior Resident Inspector Shine, Resident Inspector P. Prescott, Resident Inspecto Illir.ois Department of Nuclear Safety (IDNS)

• Sage, Code Compliance Engineer Conam Inspection. In D. Kutschkau, Level II Uartford Steam Boiler Inspection and Insurance Company (HSB)

G. Bosley, ANII The NRC inspector also contacted and interviewed other licensee and contractor employee l

• Denotes those present during the exit interview on December 15, 199 . Inservice Insoection (ISI) Unit 1 Procram Review (73051)

Personnel from CECO and GE performed the ISI in: - 4 accordance'with ASME Section XI, 1980. Edition, Winter 1980 Addenda. The sampling inspection plan;fo addressing intergranular stress corrosion cracking (IGSCC) was in accordance with Generic Letter (GL).88-0 The welds examined in accordance-with-GL 88-01-were found to be acceptable. The licensee did not make.

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a request for relief from the ASME Code for this

outage. The NRC inspector reviewed Audit No. 4/92-10-

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007 and surveillances of the ISI program performed by CEC The audit and surveillance afforts were found to be acceptable and performed by qualified personne Organizational staffing for the ISI program was founa to be acceptable and the services of an Authorized Nuclear Inservice Inspector (ANII) were procured from Hartford Steam Boiler Inspection and Insurance Compan The NRC inspector also reviewed the qualifications and certifications of all inspection perconnel performing ISI to ensure conformance with SNT-TC-1 b. Ihtog_qd. ure Review (730fal All applicable ISI procedures were approved by the ANII and were reviewed by the NRC inspector. The ISI procedures were found to be acceptable a.,d in accordance with ASME Section V, 1930 Edition, Winter 1980 Addenda, c. Datt1_Revi ew (73755)

The examination data was within the criteria as outlined in the applicable HDE procedures and ASME Code requirements. The IDNS inspector reviewed VT, PT and UT examination data. All data was within ASME Code requirements and any indications were appropriately dispositione ObservatioIg_gf Work Activities (?3753)

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

(1) CECO and GE personnel performing visual examinations (VT) from inside the reactor vessel using an underwater TV camer The tapes were reviewed by the NRC inspector and the IDNS inspecto This review included the following:

(a) jet pump defuser to adapter we]d (b) shroud holddc an bolt lower guide pin (c) shroud access hole covers (AHC). Cracks woro observed in the vertical crevices of both AHC weld Ultrasonic examinations showed circumferential cracks with several areas completely through wall. The repair consisted of electric discharge machining a circular cut through the entire thickness of

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the shroud support plate at '. diameter tha removed the original AHC, the weld, and l associated heat affected zon The new cover l plate was bolted in place with six J-bolts

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that were tack welded to prevent loosenin The repair was designed in accordance with ASME Section III, Subsection NG, and -!

installed per CECO's ASME Section XI repair and replacement program. Examination of the repair will be performed during future  !

refueling outage (2) CECO personnel performing visual examinations of 32 CRD bolt Two bolts were found to be '

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unacceptable because of corrosio (3) GE personnel performing ultrasonic examinations ,

(UT) on pipe to safe end weld No. 02M-F2. This weld was in the recirculation system. Ultrasonic exa inations were also observed on pipe welds N F-S5 and No. 32F-F4. These welds were in the '

feedwater syste The IDNS inspector observed UT on pipe welds N S3, No. 105-54, and No. 105-F5 and liquid penetrant examinations on pipe weld No. 105-F18'

and associated longitudinal welds. .These welds were in the shutdown cooling syste (4) GE personnel performing magnetic. particle extlinations on pipe wolds No. 30B S17, No. 30B S16, No. 30B S14 and No. 30B S13. These welds were in the main steam system. The ANII also '

performed a surveillance of these activities.

l No violations or deviations were identified.

, Erosion / Corrosion (E/C) Activities (49001)

Commonwealth Edison Company began their E/C program in 198 .

A formalized procedure and administrativa controls were established to ensure continued long term implementation of an E/C-monitoring program for piping and components (Reference NRC Inspection Report No. 50-265/91022(DRS)).

For this refueling outage, Ceco' selected-an inspectionL sample of approximately 34~ components, utilizingithe EPRI chec, Checmate computer program. Of the 34 components examine d, 1 was unacceptable and repaired this outage. The NRC inspector reviewed the E/C program, procedures' NDE ,

certifications, data from previous inspections, and observed Conam personnel performing ultrasonic-thickness examinations

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e on piping components on the extraction and feedwater systems. The IDNS inspector also observed data analysis being performe To date, several components and pipe sections have been repaired / replaced an a result of the E/C progra No violations or deviations were identifie . MollLLcations (37701) liigh Prencure Cnolant Injection (HPCI) Turbine Exhaust Line External Vacuum Breaker Line Modification Np d 4-1-91-013B The modification consisted of a new 4" vacuum breaker line, external to the torus and two new motor-operated gate valves for containment isolation purposes. The modification replaced the existing 2" internal line and two unisolable check valves. To complete the configuration of the new vacuum breaker line, four 4" check valves and six local leak rate testing (LLRT) tap lines with seven 3/4" globe valves were installe Implementation of this modification included all piping / support additions and rework as well as all new electrical cables / components and instrument The NRC inspector observed Stone and '%bster personnel performing cutting, fitting, and weldi.1 operations, and visually examined the completed wor The NRC inspector also reviewed work requests, ciswings, weld data sheets and other related documentatisn. The modification was in accordance with ASHM Section XI, and was found to be acceptabl No violations or deviations were identifie Water Level Instrumentation System (RVWIJEl dqdificatiqn No. M4-1-87-059A and B The purpose of this modification was to minimize the effect of reference column water boil-off on the "A" and "B" RVWLIS loops in a post-LOCA or high drywell temperature conditio This modification involved the installation of a new condensing chamber and a new condensate reservoir in each RVWLIS loo The reference leg piping from the new condensing chambers and the new conGensate reservoirs were rerouted, limiting the vertical drop to less than two feet inside the drywell. The reference leg piping from both loops were routed through penetrations No. X-108 (loop "A")

and No. X-109 (loop "B"). The variable leg was

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rerouted inside the drywell in order to eliminate the tie-in to the reference Icg. The piping at penetrations No. X-49-A&D ("A" loop), and No. X-28A&D ("B" loop) was capped outside the drywel The NRC inspector observed Stone and Webster personnel performing cutting, fitting, and welding operations, and visually examined tha completed modification. The i NRC inspector also reviewed work requests, drawings, weld data sheets and other related documentation. The i modification was in accordance with ASME Section XI and l found to be acceptabl j No violations or deviations were identifie i I

5. " Ki.t_JJ1t;_qr_ view ( 3 07 0 3 )

The NRC inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection ano l summarized the scope and findings of the inspection noted in

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this report. The NRC inspector also discussed the likely l informational content of the inspection report with regard

! to documents or processes reviewed by the inspector during the inspectio The licensee did not identify any such documents / processes as proprietary.

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