IR 05000298/1998021

From kanterella
Jump to navigation Jump to search
Insp Rept 50-298/98-21 on 981005-09.No Violations Noted. Major Areas Inspected:Third 10-yr Interval Inservice Insp Program,Including GE Reactor Insp Sys Automated Ultrasonic Exams of Reactor Vessel Circumferential Weld
ML20155D402
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/29/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20155D393 List:
References
50-298-98-21, NUDOCS 9811030212
Download: ML20155D402 (8)


Text

t i

\ l I

l

,

ENCLOSURE

l

'

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket No.: 50-298-License No.: DPR 46 j

<

l Report No.: 50-298/98-21 l

Licensee: Nebraska Public Power District l Facility: Cooper Nuclear Station i

Location: P.O. Box 98 j Brownville, Nebraska Dates: October 5-9,1998 I Inspector: Claude E. Johnson, Senior Reactor inspector, Maintenance Branch Accompanied By: Vitali Chevtchenko, Gosatomnadzor of Russia Eva Hickey, Pacific Northwest National Laboratory 1 Svetlana Sidorchouk, Gosatomnadzor of Russia Approved By: Dr. Dale A. Powers, Chief, Maintenance Branch Division of Reactor Safety ATTACHMENT: SupplementalInformation l-

!

l

~

050ohh9g PDR

..

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

-

l l

'

2-l EXECUTIVE SUMMARY Cooper Nuclear Station l NRC Inspection Report 50-298/98-21 This inspection was a routine, announced inspection of activities associated with the third 10-year interval inservice inspection program, including the General Electric reactor inspection system automated ultrasonic examinations of the reactor vessel circumferential and longitudinal welds. This inspection covered a 1-week period from October 5-9,199 Maintenance .

  • The third 10-year interval inservice inspection program was well defined and implemented the requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1989 Edition, no addenda. The licensee clearly identified, in the third 10-year intervalinservice inspection program plan, the ASME Code Class components to be examined. The licensee appropriately submitted relief requests in accordance with the  !

requirements of 10 CFR 50.55(a)(3) and (g)(5) for those Code Class weld examinations where 100 percent of full examination coverage was not achieved (Section M1,1).

. The refueling bridge and equipment were in good visual condition. Foreign material I exclusion area controls for the reactor building refueling floor were good. Water clarity of the fuel pool during the installation of the General Electric reactor inspection system (automated ultrasonic examination of the reactor pressure vessel circumferential and longitudinal seam welds) was excellent (Section M2).

  • Management oversight for the installadon of the General Electric reactor inspection system was good, in that effective guidance and communications were noted (Section M4).

Plant Succort

. The overall housekeeping for the reactor building refueling floor was good (Section M2).

, . ._- _ __ .-

3-l l

Report Details l

l l

Summary of Plant Status l During this inspection period, the plant was in Refueling Outage 18.

l M1 Conduct of Maintenance 1 l M Inservice inspection Proaram Plan and Schedule

Insoection Scoce (73753)

1 The inspector performed a limited review of the licensee's " Third Ten Year Interval l l Inservico inspection Program Plan and Schedule," Revision 1.1. The inspector also !

l reviewec' the second 10 year interval inservice inspection program because of I numerous deficiencies identified by the licensee in Condition Report 94-1123. In addition, the inspector reviewed inspection documentation from the second and third 10-year intervalinservice inspection programs to determine if the licensee had submitted relief requests when less than 100 percent of any Code Class weld examination could not be accomplishe l Observations and Findinas l The inspector found that the third 10-year interval inservice inspection program at Cooper Nuclear Station was well defined and had generally implemented the i requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1989 Edition, no addenda. The inspector found that the licensee had performed an extensive and detailed review of the second 10-year interval inservice inspection program, which documented findings and recommendations. The inspector was informed by the licensee's staff that the findings and recommendations were incorporated into the ;

l second 10-year interval inservice inspection program. The inspector found that both the I second and third 10-year interval inservice inspection program documentation was i

current and appropriately managed.

,

The program plan for the third 10-year interval, first period, documented both inservice ,

'

l an 'sugmented inspections, and the methods of nondestructise examinations to be l performed. The licensee's staff clearly identified, in the third 10-year interval inservice inspection program plan, the ASME Code Class components to be examine l l

l The inspector determined that the licensee had submitted relief requests for those Code l Class weld examinations where less than 100 percent of full examination coverage was not achieved. The inspector specifically concluded that the licensee was complying with the requirements of 10 CFR 50.55(a)(3) and (g)(5).

!

<

l

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

.

.

4 Conclusions The third 10-year interval inservice inspection program at Cooper Nuclear Station was well defined and had generally implemented the requirements of Section XI of the l ASME Boiler and Pressure Vessel Code,1989 Edition, no addenda. The licensee's i staff clearly identified, in the third 10-year interval inservice inspection program plan, the ASME Code Class components to be examined. The licensee appropriately submitted relief requests in accordance with the requirements of 10 CFR 50.55(a)(3) and (g)(5) for i those Code Class weld examinations where less than 100 percent of full examination coverage was not achieve M2 Maintenance and Material Condition of Facilities and Equipment Inspection Scope (73753)

In the course of verifying the installation of the General Electric reactor inspection l

'

system (GERIS), the inspector examined the material condition of the refueling bridge and hois Observations and Findinas The inspector noted that the reactor building refueling bridge and equipment were in i good visual condition. During the installation of the GERIS, the bridge and hoist were l used extensively. The GERIS 2000 was designed and used for automated ultrasonic examinations of the reactor pressure vessel circumferential and longitudinal seam welds from the inner diameter, with a minimum impact on other refueling activitie The inspector noted that the licensee had established good foreign material exclusion area controls for the reactor building refueling floor. Water clarity of the fuel pool during the installation of the GERIS was excellent. The overall housekeeping on the reactor building refueling floor was goo Conclusions The visual material condition of the refueling bridge and equipment were good. Foreign I material exclusion area controls for the reactor building refuelir'g floor were good.

'

Water clarity of the fuel pool during the installation of the GERIS was excellent.

I

- . .

.__ _ . _ _ . _ _ _ . _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _

.

.

-

5-l i

l M3 - Maintenance Procedures and Documentation

!

M Nondestructive Examination Procedures

{

. a.' Insoection Scooe (73753) j l

<

' The inspector reviewed nondestructive examination (NDE) procedures identified in the I Attachment, to determine if these documents were developed in accordance with regulatory and applicable ASME code requirement ]

1 Observations and Findinas The inspector found that the NDE procedurea reviewed contained sufficient detailed instruction to perform the intended examinations, and were in compliance with regulatory and applicable ASME Code requirements. The inspector noted that th licensee had reviewed and approved the contractor's procedures to be used at the >

, Cooper Nuclear Station, and had maintained good control over applicable NDE procedure Conclusions l

4  : The inspector concluded that NDE procedures were in compliance with regulatory and

"

applicable ASME code requirements, and that the licensee had maintained good control over contractor NDE procedure M4 Maintenance Staff Knowledge and Performance

, Insoection Scooe (73753)

.

The inspector assessed NDE personnel knowledge and performance through observation of work activitie Observations and Findinas The inspector observed NDE personnel calibrate ultrasonic test equipment prior to performing examinations in the field. Calibrations were conducted appropriately and documented on calibration '

data sheets. The inspector did not identify any -

' discrepancie .

The inspector observed three nondestructive examinations performed on the main

-

-

steam reactor nozzle welds. The first two examinations were conducted on Weld MSB-BJ-111 (nozzle-safe end) and they included an ultrasonic and a magnetic particle examination. The third examination observed by the insoector was an ultrasonic examination performed on Weld NVIR BD-N3A (inner radius). The inspector noted that NDE personnel performed the examinations in accordance with a0 proved procedures, and were knowledgeable of the various techniques used.

.

,sy+- y- y . ._- p ..ay 4 % - , ,.--,, - - y --7i--,,-w w

. - - _ -- - .- _- - . - - -

'

.

i l

i-6-The inspector observed the installation of the GERIS 2000 equipment. Installation l activities were performed satisfactorily with minor problems noted. The installation of j the GERIS was performed by experienced personnel. The inspector noted that l management oversight for the installation of the GERIS equipment was good, in that I effective guidance and communications were noted. The inspector did not note any significant problems during the installation of the GERIS. This activity was well planne i Conclusions Nondestructive examination personnel performed the examinations in accordance with approved procedures and were knowledgeable of the various techniques use Management oversight for the installation of the GERIS was good, in that effective guidance and communications were noted, M5 Maintenance Staff Training and Qualification Insoection Scoce (73753)

l The inspector reviewed 19 NDE personnel certification and qualification record Observations and Findinas t

'

The inspector noted tnat 2 of the 19 NDE personnel were Level Ill certified. The personnel records indicated that the NDE personnel were qualified to perform the examinations they were assigned. The inspector verified for each of these personnel that the qualification and certification record properly reflected the employer, the person certified, the specific methods qualified, the level of certification, the effective period of certification, and the annual visual acuity and color vkinn examinatio The inspector determined that NDE personnel designated as qualified to perform the examinations were properly certified according to the industry Standard ASNT-TC-1 Conclusions

, The inspector concluded that NDE personnel were pr:perly ':ertified in accordance with

'

industry Standard ASNT-TC-1 M8 Miscellaneous Maintenance issue (92902)

M8.1 [ Closed) Followuo item 50-298/9718-01: Adequacy of licensee's program to review and disposition GE service advice letters. The inspector verified that the licensee implemented a procedure change to Procedure 0.10, " Operating Experience Program,"

to ensure that service advice letters were clearly identified as documents to be included in the operating exoerience program for review and disposition. The inspector concluded that the licensc9's corrective actions were appropriat . . . _ . . . - _.__.__-_ .._ _ . . _ . - . _ , _ _ _ __ _ .. _ _ .

.

-7-V. Manaaement Meetinas X1 Exit Meeting Summary The inspector presented the inspection results to members of licensen management at the conclusion of the inspection on October 9,1998. The licensee acknowledged the findings presente The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identifie ,

i

l

>

-

_ - . ..

. -- . - . - .. . . .

l

.-

ATTACHMENT SUPPLEMENTAL INFORMATION l l

PARTIAL LIST OF PERSONS CONTACTED l Licensee j

< i

'

M. Bohling, Quality Assurance Auditor P. Donahue, Engineering Services Department Manager M. Friedman, Senior Staff Engineer, Engineering Services Department C. Gaines, Maintenance Manager B. Houston, Licensing Manager D. Kunsemiller, Consultant, Licensing D. Madsen, Senior Licensing Engineer M. Peckham, Plant Manager M. Roup, Quality Assurance Auditor R. Schultz, Senior Program Engineer, Engineering Services Department l J. Sumpter, Licensing Supervisor Contractor J. Hewett, General Electric, Project Manager NRC V. Gaddy, Acting Senior Resident inspector T. Meadows, Senior Reactor Engineer l

INSPECTION PROCEDURES USED 73753 Inservice inspection ITEMS CLOSED Closed 50-298/9718-01 IFl Adequacy of licensee program to review and disposition GE service advice letters

.

-_

,

.

.

-2-LIST OF DOCUMENTS REVIEWED Fall 1998 Outage Third 10-Year Interval, First Period Inservice Inspection Pipe and Augmented Inspection Plan, Revision 0 GENE-523-008-0194 Cooper Nuclear Station RPV Flaw Evaluation Handbook, September 1998, prepared by GE Nuclear Energy, Revision 1 NLS980133, inspection of Reactor Vessel Shell Welds Cooper Nuclear Station August 31,1998 GE-ADM-2007 Procedure For Assembly, Installation and Removal of The GERIS 2000 ID Upper Guide Ring in The RPV, Revision 0 UT-CNS-300V3 Procedure for Manual Ultrasonic Examination of Reactor Vessel Assembly Welds, Revision 0 386HA480 Certification of Nondestructive Test Personnel, Revision 16 Administrative Procedure Change Process, Revision 0 Procedure 0.4A UT-CNS-104VO Procedure for Manual Ultrasonic Planar Flaw Sizing, Revision 2 GE-ADM-2006 Procedure for Assembly, installation and Removal of the GERIS 2000 ID Lower Guide Ring in the RPV, Revision 0 GE-UT-700 Procedure for the Examination of Reactor Pressure Vessel Welds with the GERIS 2000, Revision 2 UT-CNS-208V2 Procedure for Automated Ultrasonic Examination of Similar and Dissimilar Metal Piping Welds, Revision 0 UT CNS-102V1 Procedure for Manual Ultrasonic Examination of Similar and Dissimilar Metal Piping Welds, Revision 0 UT-CNS-106V1 Procedure for Manual Ultrasonic Examination of Ferritic Piping and Vessel Welds 2' and Less in Thickness, Revision 0