IR 05000458/1989010

Insp Rept 50-458/89-10 on 890327-0406.No Violations or Deviations Noted.Major Areas Inspected:Review of Inservice Insp,Welding & Associated Documents & Procedures.Mod to RHR Sys Also Reviewed

ML20247L154
Person / Time
Site:	River Bend
Issue date:	05/09/1989
From:	Chaudhary S, Harris R, Kerch H, Oliveri M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20247L132	List: IR 05000458/1989010 ML20247L128
References
50-458-89-10, NUDOCS 8906020097
Download: ML20247L154 (11)

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U.S. NUCLEAR' REGULATORY COMMISSION REGION In  :

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, ^ Report No. 89-10 Docket N License No.:.NPF-47

. Licensee: - Gulf States Utilities

, - P.O.-Box 2951

Beaumont, Louisiana' 77734 Facility Name: . . River Bend a Inspection At: St-. Francisville, LA

. Inspection. Conducted: March 27 through April 6, 1989 Inspectorsi 9 89

.H. W. Kerch,. Senior Reactor Engineer date q 4~ f h R. H. Harris, NDE Technician '

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i M.7A. Oliveri, NDE Technician date

' Approved by: m k9/&i I 5. K. Chnudhary, Chief, Materials, and 'date Proc? ues Section, EPB, DRS,: Region I Ins)ection Summary and Conclusions: A routine announced inspection was conducted at liverbend-Nuclear Power Station on March 27 through April 6, 1989. ~(Report No. 50-458/89-10). The NRC conducted an independent measurement inspection using the NRC mobile non-destructive examination (NDE) laboratory. The inspection focused'on' review of Inservice Inspection (ISI), welding, and associated documents and procedures. Modifications to the Residual Heat Removal System (RHS) also were reviewe i

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The following were examinations and reviews performed by the NRC during this

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inspection:

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Radiographic examinations -

6 pipe weldments Liquid Penetrant examinations - 14 pipe weldments

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4 pipe weldments Visual examinations -

25 pipe weldments Hangers examinations -

11 supports

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ISI program ISI staffing

Procedures -

44 procedures Conclusion: Based on this inspection, there was a concern dealing with iradequate surveillance of NDE contractors (Section 3.0) was identified. In addition, the inspector discussed with the licensee the problem of radiation levels in the area of the biological shield wall. The observed radiation levels in this area are very high, particularly for a new plant, and if not properly controlled will result in high man rem utilization for inservice inspection and other plant personnel. Overall the ISI program at River Bend was found adequat I l

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DETAILS

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1.0; Persons Contacted (30703)

Gulf States Utilities (GSU)E

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'*J. C. Deddens Sr. Vice President :

• M. F. Sankovich ' Engineering Manager

• H. Odell: Administration Manager

• L. A. Engcam- . Licensing Director

• K. E. Suhr11 Project Manager

• T..C. Croure QA Manager

• L. Curra L.0. STE Representative l'-

• James Cook Licensing

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E. M. Cargill Director RAD Program 1:. W. Walling- ISI Coordinator

• J. B. ,Blakley ISI Supervisor Garland Maha Welding. Engineer

• Roger Carlyle ISI Coordinator

• G . 1( . Henry Quality Operations Mark Felfner Nuclear Licensing

• Carl W.' Walker Quality Control Glenn W. Siry Coordinator-Stone and Webster Engineering Corp. (SWEC)

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'C. D. Jones: ISI Coordinator U. S. Nuclear Regulatory Commission R. C. Stewart RIV Resident L. D. Gilbert RIV Reactor Inspector W. B. Jones RIV Resident Inspector

• H. W. KerchL RI Reactor Inspector M. A.-Oliveri RI NDE Technician

~*R . H. Harris RI NDE Technician

,. *C. ' E. Johnson - RIV Reactor Inspector l

The above, asterisks indicate personnel. who were present at the exit meetin The inspector also contacted other administrative and technical personnel

'during the inspection.

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4 ti 2.'0 -Independent Measurements - NRC Non6 structive Examination and Quality y Records Review of Safety Related Systems Duringl the period of March 27 through April 6,1989 an onsite independent inspection was conducted at Riverbend Nuclear Power Station. The inspection was. conducted by NRC regional based'and contract inspectors. The objectives

of this inspection were to. assess the adequacy of the licensee's inservice

. inspection program,' welding quality control program, pipe modification

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program and control.of the "As-' Built". configuration of pipe hanger / support This was accomplished by reperforming a sample of examinations required of the licensee by regulations and codes, and evaluating the results of these

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4 examination .1 -Nondestructive Examination (NDE)

Visual Examination (57050)

Twenty-five (25) safety related pipe weldments and adjacent base material.(1/2 inch on either side of the weld) were visually examined in accordance with NRC procedure NDE-10, Rev. O, Appendix A, and associated site QC documents, isometrics, and as-built drawing Selected during this inspection were ASME Class 1, 2 and 3 pipe weldments from the Low Pressure Core _ Spray (CSL), Service Water (SWP),

r and Residual Heat Removal (RHS) Systems. The examination was performed.specifically to identify any cracks or linear indications, gouges, leakage, arc ~ strikes with craf ers, or corrosion, which may infringe upon the minimum pipe wall thickness. Mirrors, flash lights and weld gauges were used to aid in the inspection and evaluation of the weldment Results: The welding and overall workmanship of items inspected were satisfactory. No violations were identifie Visual Inspection Hanger / Support (57050)

Eleven (11) safety related hanger / supports were visually inspected per NRC procedure NDE-10, Rev. O, Appendix A and B in conjunction with site QC documents, and isometric drawings. Included in this inspection were hanger / supports selected from the Service Water (SWP),

Reactor Water Cleanup (WCS), Main Steam Drain (DTM), Core Spray (CSH),

Standby Liquid Control (SLS), and the Feedwater (FWS) Systems. In

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the area of welds, the accessible surface area and adjacent base metal for a distance of one-half inch on either side of the weld was examine In the area of component integrity, specific attributes looked for were proper installation, configuration of supports, evidence of mechanical or structural damage, corrosion, and bent, missing or broken members. The following is a list of specific hanger / supports inspecte i

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SYSTEM SUPPORT / HANGER CLASS DRAWING Feedwater- PSSP2020A2 2 BZ17GP Feedwater PSSP2004A2 2 BZ17HC Main. Steam PSSP2048A1 1 BZ31QR Main Steam PSSP2062A1 1 BZ31RE

' Service Water PSR3043A3 3 BZ019AC Service Water PSST 6043A3 3 BZ019XL Water Cleanup PSST 2064A2 2 BZ074GS Core Spray PSSP2017A2 2 BZ83S Core Spray PSSH2034A2 2 BZ83AP -

Standby Liquid Co PSSP3118A2 2 BZ75BU Core Spray PSR2038A2 2 BZ83AT Results: The welding and overall workmanship of items inspected were sati sfacto ry. No violations were identifie LIQUID PENETRANT EXAMINATION [57060)

Fourteen (14) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye, solvent removable method per NRC procedure NDE-9,

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Rev 0, in conjunction.with the licensee's procedure QCI-3-13 Rev. Included in this inspection were ASME Class 2 carbon steel weldments selected from the Core Spray (CSL) Syste Results: The surface areas examined were properly prepared for the examination. No violations were identifie MAGNET PARTICLE EXAMINATION (57070)

Two (2) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the direct contact method, with dry powder as the examination medium. The examination was performed in accordance with NRC procedure NDE-6, Rev. O in conjunction with the licensee's procedure QCI-3-12, Rev. Included in this examination were ASME Class 2 weldments selected frem the Low Pressure Core Soray (CSL) Syste Results: No violations were identifie ULTRASONIC EXAMINATION Four (4) sarety related pipe weldments were ultrasonically examined using a Krautkramer USL48 ultrasonic flaw detector in accordance with NRC procedure NDE-1, Rev. O, the itcensee's procedure QCI-3.27 Rev. 2 and associated isometric drawings and QC documentatio Instrument calibration (linear verification) was performed using NRC procedure NDE-2, Rev. O. A distance amplitude corrected curve (DAC)

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was constructed using the' licensee's calibration standards RBS-29 and RBS-09. To assure repeatability of the ultrasonic examination,

~ instrument settings and search units (transducers) were matched as-. ;

close as possible to those indicated by licensee's' ultrasonic data !

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report Included in-this examination were ASME class 1 and 2  !

weldments selected from the Core Spray (CS) Syste Results: -Data collected by the NRC was compared to that taken by the j

' licensee. No violations were identifie ' RADIOGRAPHIC EXAMINATION (57090)'

, 'Six (6) safety. related pipe weldments were ' examined using an Iridium 192 source. The. technique and procedure used were in accordance with'NRC procedure, NDE-5, Rev. O the licensee's procedure, QCI-3.29, Rev. I and associated radiographic data' reports. Included in this examination were ASME class 2 and 3 weldments selected from the Service Water (SWP) and Residual Heat Removal (RHS) System Results: Radiographs of Service-Water system piping disclosed several areas below required minimum wall thickness. Review of NRC radiographs are'as follows:

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.SWP-3103-1339 SW5: Film area'A has an indication not previously identified or dispositioned by the licensee. It was verified during this inspection that the indication is a surface defect, acceptable by cod SWP-3103-1339 SW4: Film area B has an area.of 50% through wall corrosio 'SWP-3103-1339 SW3: Satisfactor SWP-3103-1339 SW2: Satisfactor SWP-3103-1339 SW1: A foreign object, which appears to be a piece of tubing was identified. Film area B has an area of 50% through wall corrosio ' The issue of service water system corrosion is addressed. in NRC Region IV Inspection Report 89-16. These radiographic inspections were performed in support of Region IV's evaluation of this issu . 3.0 Inservice Inspection ISI (73753)

River Bend's ISI program is in its first ten year interval, second re-fueling outag River Bend's ISI program was prepared and is implemented by the

. licensee. The ISI program incorporates the requirements of the ASME Boiler L and Pressure Vessel Code,Section XI 1980 Edition through the Winter of i 1981 addenda.

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The' inspector reviewed the following documents to ascertain compliance with applicable sections of the ASME code, regulatory requirements, and-licensee: commitment .

~ Current.10 year ISI program' .

Second refueling outage. inspection schedule

f r_ Relief request *

Examination data for:

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'10 ultrasonic weld examinations, out of which four (4) welds were selected for re-examination by the NR * .7 Magnetic Partial weld examinations, out of which two (2)

welds;were selected for.re-examination by the NR Liquid Penetrant weld examinations, out of which fourteen-(14) welds were selected for re-examination by the NR i i

Visual exaraination of 25 supports, out of which eleven (11)

supports were selected for re-examination by the NR , Results: ' Based on'the above reviews and' discussions with cognizant

.QA/QC personnel, the following observations were made:

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E During'this' inspection, the licensee site quality personnel have not been performing surveillance nor re-examinations of ISI activities in order to effectively assess the contractor's ISI activitie Cognizant quality management agreed that;there could be improvement in this area and took positive. steps to improve the site's quality 1 . surveillance of ISI contractors. The day following these discussions, there was evidence of quality involvement in ISI contractor activitie . Quality' management also has committed to formally proceduralize the quality surveillance and re-examinations of cite ISI contractors activities-by site quality personne Organization and Staffing of River Bend's ISI program (73753)

River Bend's engineering manager has the prime responsibility for development, implementation, documentation and coordination of the ISI progra ,!

The ISI examinations are performed by the following contractors:

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Rockwell International Rocketdyne performs the Automatic Vltrasonic examinations on the reactor vesse i t .

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_Ebasco Services Incorporated-participates _as a Rockwell subcontractor and performs the manual ultrasonic examinations on pipin During this inspection, Rockwell International had not started any ultra-sonic' examinations. Rockwell had performed quality surveillance of-their subcontractor, Ebasco. Ebasco had completed several examinations during-this outage. All NDE documentation reviewed by NRC and welds re-examined by NRC were found satisfactory. Based on the above, the inspector concluded that River Bend's ISI program is adequately staffed and augmented by contract personnel to execute the ISI progra .

Results: No violations were identifie ISI Concern The- radiation levels in the. biological shield wall area were very high,

.particularly for a new facilit It was felt that a more aggressive ALARA program should have~been utilized in preparation for the ISI examinations of the reactor vessel nozzles based on site man rem predicted levels. 'This concern was carried to the licensee during the exit interview'for this inspection and to Region IV management. Other

, facilities performing these same nozzle ultrasonic examinations use an automatic ultrasonic _ system rather than a manual system due to ALARA concerns. Subsequent to this inspection, Region IV sent a health physics inspector to follow up on this issu .0 REVIEW OF SITE NDE PROCEDURES AND MANUALS The following procedures were reviewed in the regional office during this inspection period for compliance to the licensee's FSAR commitments, applicable codes, standards, and specification GULF STATES UTILITIES COMPANY (GSU)

procedure Title Number / Revision Magnetic Particle Examination QCI-3.12 REV. 2 Liquid Penetrant Examination QCI-3.13 REV. 5 Visual Examination-VT-1 QCI-3.23 REV. 3 Visual Examination VT-2 QCI-3.24 REV. 2 Visual Examination VT-3 0C1-3.25 REV. 4 Visual Examination VT-4 QCI-3.26 REV. 3 Ultrasonic Examination of Similar L and Dissimilar Pipe Welds QCI-3.27 REV. 2 Ultrasonic Thickness Measurement QCI-3.28 REV. 2

. Radiographic Examination Requirements QCI-3.29 REV. 1 Magnetic Particle Examination Florescent Method QCI-3.35 REV. 1 Visual Examination VT-1 and VT-3 of Reactor Pressure Vessel (RPV) Internals QCI-3.38 REV. 0

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Procedure Title Number / Revision Florescent Penetrant Examination 0C1-3.39 REV. O Pipe Support Specification 228.310 XI Program Organization and Responsibilities RBNP-042 EBASCO SERVICES, IN Procedure Title Number / Revision Ultrasonic Examination Procedure for the Sizing of IGSCC GS-VT-W81-7 REV. 2 Liquid Penetrant Examination GS-PT-W81-1 REV. 3 Magnetic Particle Examination of Welds and Bolting GS-MT-W81-2 REV. 2 Visual Examination VT-1 GS-VT-W81-1 REV. 1 Visual Examination VT-2 GS-VT-W81-2 REV. 2 Visual Examination for Mechanical and Standard Condition of Components and There Supports GS-VT-W81-3&4 REV. 1 Ultrasonic Examination of Class 1&2 Piping Welds Joining Similar and Dissimilar Materials GS-UT-W81-3 REV. 2 Ultrasonic Examination for the Detection of Intergranular Stress Corrosion Cracking GS-UT-W81-4 REV. 3 Ultrasonic Examination of Pressure Retaining RPV Studs 2 Inches or Greater with Bore Holes GS-UT-W81-5 REV. 3 Ultrasonic Manual Examination of Class 1&2 Polts and Studs GS-UT-W81-6 REV. 2 UT Manual Examination of Class 1 Reactor Vessel Welds Covered by Regulatory Guide 1.150 GS-UT-W81-8 REV. 2 Ultrasonic Examination for Nozzle Inner Radius GS-UT-W81-11 REV. O ROCKWELL INTERNATIONAL Quality Field Procedure N315QFP000001 Results: No violations were identifie .0 Attachments: Attachment No. 1 is a tabulation of specific pipe weldments and components examine .0 Unresolved Items: Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or violations. An unresolved item is discussed in Section 3.0 of this report.

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7.0 Management Meetings (30703)

i Licensee management was informed of the scope and purpose of the inspection at the entrance meeting on March 28, 1989. The findings of the inspection were discussed with the licensee representatives during the course of the inspection and presented to licensee management at the exit meeting on April 6,1989 (see paragraph 1.0 for attendees). At no time during the  ;

inspection was written material provided to the licensee by the inspecto l No proprietary information was involved within the scope of this inspectio )

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INDEPENDENT MEASUREMENTS PROGRAM ATTACHMENT 1 L . SITE: RIVERBEND UNIT 1 DATE: 03/ 27/89 THRU 04/07/89 l

! ' ISO /DWG- WELD ID CL. PT MT RT UT VI ACC REJ COMMENTS t

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