IR 05000374/1993034

Insp Rept 50-374/93-34 on 930916-1124.No Violations or Deviations Noted.Major Areas Inspected:Isi Activities, Including Review of Programs,Procedures,Observation of Work Activities,Data Review & Erosion/Corrosion Activities

ML20058H851
Person / Time
Site:	LaSalle
Issue date:	12/06/1993
From:	Jeffrey Jacobson, Schapker J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20058H800	List: IR 05000374/1993024 IR 05000374/1993034
References
50-374-93-24, NUDOCS 9312130244
Download: ML20058H851 (4)

Text

.~ .. . .. --- . . . .. --

,

..

..  !

l

)

' U. S. NUCLEAR REGULATORY COMMISSION l

l- REGION Ill >

I

Report No. 50-374/93024(DRS) j

-

Docket No. 50-374 License No. NPF-18 Licensee: Commonwealth Edison Company j Executive Towers West III .i 1400 Opus Place, Suite 300 Downers Grove, IL 60515 l j

Facility Name: LaSalle County Station - Unit 2 l

Inspection At: Marseilles, IL 61341 Inspection Conducted: September 16 through November 24, 1993 .

Inspecth 1 CLca> u d c x h-c 4)

(

.)'Schapker /, Date 1

,- , , , ,

Approved Byr l J. M

[h h cmyh i

/ L 4 -i 3 Date i

( Mate /JactbsongChiefrials\and vrocesses Section  !

,

f -;

inspection Summary inspection on September 16 through November 24 1993 (Recort N /93024(DRS))

Areas inspected: Routine, unannounced safety inspection of inservice )

inspection (151) activities including review of programs (73051), procedures  :

(73052), observation of work activities (73753), data review (73755), and  !

erosion / corrosion (E/C) activities (49001). j Results: No violations or deviations were identified. Based on the results -

of the inspection, the NRC inspector noted the following i i

The licensee improved radiological conditions for the ISI inspectors in f performance of their dutie <

The E/C program for this outage appeared to be nonconservative due to 'l the number of components inspecte )

i

!

l

l

w 9312130244 931206 )

PDR ADOCK-05000374 L" '

G 3-

__

_ _ _ -_ . .. ._ _ . . _ .._ _ . _ . . _ _ __ _ _ _

,

'

-

1 i i i

!

, -t l

DETAILS ' Persons Contacted Commonwealth Edison Company (CECO) i l

• Santic, Maintenance Superintendent

• Ragan, Systems Engineering Supervisor

• Crawford, Work Control Superintendent

• Arnold, Regulatory Assurance

• Williams, Regulatory Assurance 1

• Kochis, ISI Coordinator

• O'Connell, ISI Component Support Coordinator

• Silich, QC Supervisor i l * Hynes, Site Quality Verification

• M. Oclon, SEC Programs Group Leader

'

• R. Vincer, Training

• S. Henderson, Maintenance Staff J. Lockwood, Regulatory Assurance Supervisor  !

D. Carlson, NRC Coordinator / Regulatory Assurance j B. Wilson, Corporate Level III J. Burns, Regulatory Assurance Administrator U. S. Nuclear Reaulatory Commission (NRC)

• Hills. Senior Resident Inspector i * Phillips, Resident Inspector  ;

lllinois Department of Nuclear Safety (IDNS)

!

• J. Roman, Resident inspector -

• L. Sage, Code Compliance Engineer  !

! Hartford Steam Boiler Inspection and Insurarice (HSB)

4. Tetreault, ANII The NRC inspector also contacted and interviewed other licensee and contractor employee * Denotes those present at the exit interview conducted November 24 199 . -Inservice Inspection (151) General 1'

A pre-ISI meeting was held at the site on September 17, 1993. The l scope and schedule of the next ISI was discussed, along with any possible problems associated with the ISI activities, r 1 l

.

- . . _ , _ _ . , . _ . , ,

,,

~

j

. Review of Proaram (73051)

Personnel from CECO performed the ISI in accordance with ASME Section XI, 1980 Edition, Winter 1980 Addenda. Where ASME requirements were determined to be impractical, specific. relief-requests were submitted to the Office of Nuclear Reactor Regulation (NRR) in writing. The NRC inspector reviewed specific relief requests including the related correspondence between the licensee'and the NRC. The NRC inspector reviewed.the HSB audit of the ISI activities and found it acceptable. _ No Ceco' audit. or surveillances of the ISI program were conducted during this outag The sampling inspection plan for addressing intergranular stress corrosion cracking was reviewed and found to be in accordance with Generic letter (GL) 88-01. All welds' examined in accordance with GL 88-01 were found to be acceptabl Procedure Review (73052)

All applicable 151 procedures were reviewed and approved by the-Authorized Nuclear Inservice Inspector (ANil). The NRC inspector reviewed prncedures utilized during ooservation of ISI work activities. The 151 procedures were found to be in accordance with ASME Section V,1980 Edition, Wir.:er 1980 Addend ISI Data Review (73755)

The NRC inspector reviewed documents related to nondestructive examination equipment, data, and evaluations. The examination data met the applicable ISI procedures and ASME Code requirements.- Observation of Work Activities (73753)

The NRC inspector observed work activities and interviewed personnel during the ISI activities. These observations included the foll ning:

(1) (ECo personnel performing ultrasonic examination on feedwater nozzles 2-HR-4A, 43, dC. 4D, 4E, and 4 Examinations included the nozzle bores, lands and inner radius in accordance with CECO's ccamitment to NUREG-061 (2) CECO personnel performing ultrasonic examination on the residual heat removal weld No. WN-44-166 pipe to valve 2E51-f06 (3) Ceco personnel performing remote visual examination of the following reactor vessel internal components:

high pressure core spray and low pressure core spray spargers feedwater spargers

- - _ - _ - -

.-

.~

surveillance material sample baskets jet pump No. 5 and 15 clamps core spray piping The NRC inspector reviewed the qualifications and certifications of all inspection ' personnel performing ISI examinations to ensure conformance to SNT-TC-1A. Overall staffing for the ISI program

,

was found to be adequat The NRC inspector noted an improvement in radiological conditions for the examination of the feedwater nozzles. This improvement was due to better chemical flushing and additional shieldin . Erosion / Corrosion Proaram (49001)

CECO's erosion / corrosion (E/C) program was formally implemented in 1988 in response to NRC Bulletin 87-01. Additional guidance from GL 88-13 and EPRI-NP-3944 was added to the progra A formalized corporate ;

procedure (N0D-TS.7) and site specific procedure (LTS-600-20, Revision 2) with administrative controls were established to ensure contiaued long term implementation of the E/C progra An inspection sample is selected prior to every refueling outage utilizing the EPRI Chec, Checmate computer program These programs consider such variables as the effects created by poor geometry, high fluid velocity, moisture content, temperature, chemistry, and component material. The stages 1 and 2 evaluations for the components ultrasonically inspected during the outage were performed utilizing the CEECALC computer program, which determines whether a component requires immediate replacement / repair, reinspection at the next refueling outage, or reinspection at some future dat The NRC inspector reviewed the E/C program, procedures, and data for this outage. The number of components examined this outage appeared'io be low. The NEC inspector reviewed the inspection data from outages 2 through 4 and observed a declining trend in the number of inspection Although the number of components should decrease with the evolution of the E/C program, the numbers inspected are below the average of most utilities by factors of 2 er 3. The licensee informed the inspector that a remodeling of the riant's systems and components will be performed in the near futuce, and that the number of components to be inspected the next outage is expanding under the current progra . Exit Interview The NRC inspector met with licensee representatives (denoted in Section 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 any such docoments/ processes as-proprietar _ _ _ _ _ _ _