IR 05000482/1990008
| ML20043G245 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/24/1990 |
| From: | Harris R, Kerch H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20043G243 | List: |
| References | |
| 50-482-90-08, 50-482-90-8, NUDOCS 9006200087 | |
| Download: ML20043G245 (15) | |
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i-U.S. NUCLEAR REGULATORY COMMISSION
REGION I
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Docket No.
50-482_,
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Report No.
90-08 License No. NPF-42 Licensee: Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66837 Facility Name: MolfCreek-InspectiJn At:
Burlinoten, kansas Inspection Conducted: April 2 through April 12. 1990 Inspectors:
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4. W. Kerch, Project Manager NDE, Materials &
/ dat'e'
Pro esses Sectio, EB, DRS
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b Y J C.)
R'. H. Ha'rris, NDE Technician, Materials &
date Processes,ection, EB, DRS
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b J. R. 6trosnider, Chief, Materials & Processes date Section, Engineering Branch, DRS Inspection Summary and Conclusions: An announced inspection was conducted at the Wolf Creek fiuclear Power Station on April 2 through April 12, 1990 using the NRC mobile nondestructive examination (NDE) laboratory.
The inspection focused on activities related to the inservice inspection, erosion / corrosion and plant modification programs.
Two unresolved items, as described below, were identified during this inspection.
90-08-01 Procedure 80A9068. Rev. 6, paragraph 7.2.B, for qualification of NDE
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personnel does not appear to meet the closed book section i
requirements of SNT-TC-1A (See Section 3.0).
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l 9006200087 900611 PDR ADOCK 05000482 O
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-90-08-02 Use of a 1. " diameter ultrasonic calibration block during inspection
L of.the 4" diameter pipe side of weld 1-AE-04-FW90' (See Section 2.5).
In addition, the inspectors identified two concerns that should receive manage-
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ment attention.. The first involves the effectiveness of radiation surveys performed on equipment being removed from radiologically controlled areas (see Section 4.0). This concern will be evaluated by Region IV personnel. The second concern involves the effectiveness of techniques being used to conduct L
trosian-corrosion inspections (see Section 2.6).
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DETAILS
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1.0 PERSONS CONTACTED (30703)
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Wolf Creek Nuclear Operating Corporation (WCNOC)
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- J. Lutz, Licensing
- G. D. Boyer, Plant Manager J. A. Bailey, Vice President, Operations
- M. G. Williams, Manager, Plant Support
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- R. K. Lewis, Supervisor, Results Engineer
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- S. Wideman, Licensing Specialist
- W. M. Lindsay, Manager, Quality Assurance
- C. E. Parry, Director Quality
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- H. K. Chernoff, Supervisor, Licensing
- R. S. Benedict, Manager, Quality Control J. E. Hall, Quality Control Supervisor 0. Maynard, Regulatory Services R. W. Holloway, Manager, Maintenance R. D. Flannigan, Manager M. Dinglor, Manager A. Payne, Supervisor-G. P. Robertson, NDE Level III G. Grell, QC Inspector
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Nuclear Energy Services (NES)
- S. Larson Site Engineer D. A. Murdock, NDE Level III i
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U.f. Nuclear Regulatory Commission M. E. Skow, Resident Inspector, RIV A. Singh, Reactor Inspector, RIV
- Denotes those attending entrance and exit meeting.
The above listed personnel were present at, the exit meeting.
The inspector also contacted other administrative and technical personnel during the-inspectio F
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2.0 INDEPENDENT MEASUREMENTS - NRC NDNDESTRUCTIVE EXAMINATION AND QUALITY litCORDS REVIEW OF SATETY RELATED SYSTEMS During the period of April 2 through April 12, 1990, an onsite independent inspection was conducted at the Wolf Creek Nuclear Power Station.
The inspec-tion was conducted by NRC regicnal based inspectors. The objectives of this inspection were to assess the adequacy of the licensee's inservice inspection program, welding quality control program, pipe modification program, program for maintaining the "as-built" configuration of pipe hangers and supports and the erosion-corrosion program.
This was accot:plished by repeating examinations required of the licensee by regulatioris n d codes and comparing the results of the NRC and licensee inspections.
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2.1 Nondestructive Examination (NDE)
2.2 Visual Examination (57050)
Fourteen (14) safety related pipe weldments and adjacent base material (1 inch l
on either side of the weld) were visually examined in accordance with NRC
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procedure NDE-10, Rev.1, Appendix A, the associated site procedure for visual
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examination of pipe systems and attached components, QC documents, isometrics
and as-built drawings.
Included in this inspection were ASME Class 2 and ANSI
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B31.1 pipe weldments selected from the feedwater (FW), pressurizer (PZR) and I
steam blowdown (SB) systems. The examinations were performed specifically to j
identify any cracks er linear indications, gouges, leakage, are strikes with j
craters, or corrosion, which may infringe upon the minimum pipe wall
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thickness.
Mirrors, flashlights and weld gauges were used to aid in the l
inspection and evaluation of the weldments, j
i Results: The welding and overall workmanship inspected were satisfactory. No k
violations were identified.
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2.3 Visual Inspection of Hangers and Supports (57050)
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During this inspection eighteen (18) safety related hangers and supports were
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visually inspected using NRC procedure NDE-10, Rev. 1, Appendix A and B in conjunction with licensee procedures QCI 11.1-001 Rev. 8 for Section XI Visual Examinations and QCI 12.1-604 Rev. 4 for Inspection of ASME/ ANSI Welds, QC documents and associated drawings.
Included in this inspection were ASME l
Class 2 and 3 hangers and supports selected from the component cooling water
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(CCW), fuel pool cleanup (FPC), chemical volume control (CVC), residual heat j
removal (RHR), standby diesel (SD), high pressure coolant injection (HPCI) and
essential service water (ESW) systems.
In the area of welds, the accessible
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surface area and adjacent base metal for a distance of one-half inch on either i
side of the weld was examined.
Specific attributes looked for were proper l
installation, configuration or modification of supports; evidence of mechanical
or structural damage; and corroded, bent, missing or broken members. Attachment j
1 is a list of specific hangers and supports inspected.
Results: Welding and overall workmanship were acceptable.
No violations were I
identified.
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2.4 Radiographic Examination / Review (57090)
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Eight (8) safety related pipe weldments were radiographed using an Iridium 192 source. The technique and procedures used were in accordance with NRC Procedure NDE-5, Rev. 1 in conjuncticn with the licensee's procedures, ADM 03-003, Rev, 2, Radiography Guidelines and QCI 12-1-508, Rev. 3, Radiographic Examination of Welds and Components and associated drawings and radiographic data reports.
Included in this inspection were ASME Class 2 and ANSI B31.1 pipe weldments selected from the steam generator blowdown (SGB) and pressurizer (PZR) systems.
Results: No violations were identified.
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2.5 Ultrasonic _Examinatien (57080)
Six (0) safety related pipe weldments were ultrasonically examined using a KrautAramer USL-48 ultrasonic flaw detector in accordance with NRC Procedure NDE-1, Rev. O, the licensee's procedure entitled Ultrasonic Examination for Preservice and Inservice Examination and associated drawings and ultrasonic test data.
Instrument calibration (linear verification) was performed using NRC Procedure NDE-2, Rev. O.
A distance amplitude correction curve (DAC) was constructed using the licensee's calibration standards number 124 and number 119.
Included in this examination were ASME Class 2 weldments selected from the main feedwater (AE) system.
Results: No violations were identified. The inspectors determined that during the repair and preparation of some pipe welds, the licensee determined some areas were below the minimum wall thickness.
Consequently, an area of "2 to 3" on either side of some of the butt welds had weld buildup. Because of the weld metal build-up, a radiograph (M13AE04/F018 R3) of one of the welds _ being examined by ultrasonic testing was reviewed by the NRC inspector and the centerline location as marked on the pipe and weld surface was verified as correct.
During the NRC reexamination of weld 1-AE-04-FW900, the NRC questioned the use of a 14" diameter calibration block being used on the 4" diameter pipe side, a 4" diameter calibration block should be used.
This item is considered unresolved pending licensee's review of the qualification of this calibration and NRC review (50-282/90-08-02).
2.6 Erosion-Corrosion Inspections (57080)
Ten (10) pipe components were examined for erosion-corrosion using a Nova D-100 digital thickness gauge.
The method and procedures used were in accordance with NRC Procedure NDE-11, Rev. 0; the licensee's procedure ADM 08-212 Rev. 2 Erosion-Corrosion Monitoring Program; and associated quality assurance records.
The erosion-corrosion examinations were performed on selected pipe components to determine if wall thinning was present.
The thickness measurements were
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taken at predetermined locations on the systems selected and were on a 1 or 2 inch square grid depending on the size of the pipe or component. The components examination for erosion-corrosion were selected from the Essential Service Water (ESW) System.
Results: The results of this examination revealed isolated areas that appeared to have pits or material anomalies (see Attachmer.t 3).
Thickness measurements taken by the NRC inspectors were compared to those taken by the licensee to verify areas which may be below minimum wall thickness.
Because of the two different instruments used in taking ineasurements (NRC used a Nova D100 d',gital gage the licensee used a Krautkramer USD-10 Ultrasonic Flaw Detector) there were areas that required further investigation, this was accomplished by having the NRC inspector and the licensee's inspector take the two instruments and compare the individual thickness readings.
Using the digital thickness gage
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the indications were easily found and duplicated, however, the Ultrasonic Flaw detector could not find the same indications. The indications identified did not appear to be significant enough to threaten the integrity of the components.
However, the issue was identified to licensee management so that they can review % effectiveness of the techniques being used in the erosion-corrosion prop am and take any appropriate corrective actions.
3.0 INSERVICE INSPECTION ISI (73753)
The inspector reviewed the following to ascertain compliance with applicable ASME Code requirements, licensee commitments and regulatory requirements.
Facility Technical Specifications
Vendor Work Plan, Rev. 2
ISI Program Plan, Rev. 2a
NDE Examination Data Reports
ISI exemptions for Wolf Creek ISI Program
In accordance with 10 CFR 50.55a(g), 1983 Edition, the licensee ISI program for the current ten year interval is required to meet the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through the Winter 1981 addenda.
In the areas reviewed by the inspector the plan meets the requirements of the ASME Section XI, 1980 Edition through Winter 81 addenda.
All documents and procedures reviewed by the inspector were properly controlled by the licensee.
Organization and Staffing of the ISI Program The inspector determined that Wolf Creek's Results Engineering Group has the l
prime responsibility for coordinating and conducting the ISI program. Their i
responsibility includes scheduling inspections, developing procedures and providing qualified inspection personnel. Wolf Creek's ISI program is performed i
by the following NDE personnel:
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Ultrasonic, magnetic particle and liquid penetrant examinations are
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performed by Nuclear Energy Services (NES).
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i-i Radiographic and Section XI.isual examinations are performed by licensee
personnel.
The inspector concluded that Wolf Creek's ISI program was adequately staffed by site personnel and augmented by contract personnel to properly execute Wolf Creek's ISI program.
No violations were identified.
Qualification of ISI NDE Personnel The inspector reviewed the qualification and certification records for Nuclear Energy Services M ES) personnel, Results:
NES's Procedure 80A9068, Rev. 6, paragraph 7.2.B for qualification of NDTpersonnel does not appear to meet the requirements of SNT-IC-1A for closec book examinations.
Procedure 80A9068 states in the specific examination section that applicable codes, specifications and procedures may be provided to the personnel being tested.
The inspector questioned whether the closed book requirement of SNT-TC-1A was being satisfied. A conclusive determination could not be made by the inspector because the actual tests were not available on site.
Recent ASNT inquiries 89-1 and 89-2 provide guidelines for satisfying the closed book requirements.
Conversation with NES Level III indicated that the next revision to this procedure would include the closed book requirement.
This item is considered unresolved pending licensee's action and NRC review (50-482/90-08-01).
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Witness of ISI Examination During this inspection the inspector witnessed the reexamination by NES
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personnel using ultrasonic, testing of weld 1-AB-01-5017-E.
Also the ultrasonic examination calibrations for reactor welds CH-101-104-8 and C were observed.
_Re sult s : No violations were identified.
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4.0 RAD-PROTECTION On Sunday, April 8, 1980, at approximately 4:00 PM, after NRC radiographic operations, the radiography source and all radiographic equipment were stored
in cordoned off area of the fuel room.
Prior to removal of the equipment from i
the-fuel room, Health Physics was notified and a health physics technician came to the fuel room to survey the equipment prior to release from the radiological-ly controlled area.
The NRC observed that the technician performed a smear test on only the radiographic camera and released all equipment. This included I
rolls of tape, number belts, penetrameters, shims, tape measure, two high radia-tion signs, markers, etc. No survey of any equipment other than the source camera was performed. Other than the surver oerformed by the NRC contractor on their own. equipment, all equipment was, sut equently, released without further Health Physics examinations and moved off site on April 12, 1990.
This problem was discussed at the exit and, subsequently, turned over to Region IV personnel.
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5.0 REVIEW OF SITE NDE PROCEDURES AND MANUALS The following procedures were reviewed in the regional office during this inspection period for compliance with the licensee's FSAR commitments and app?icable codes, standards and specifications:
Wolf Creek Nuclear Operating Corporation Inservice Inspection Nondestructive Examination Procedures
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Procedure Title Number / Revision
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Section XI Visual Examination 001-11.1-001 Rev. 8 Inspection of ASME/ ANSI Welds 001-12.1-604 Rev. 4 Pressure Test Examination 0C1-11.2-001 Rev. 3
Magnetic Particle Examination 0C1-12.1-502 Rev. 5 Liquid Penetrant Examination QC'-12.1-501 Rev. 5 Ultrasonic 1hickness Examination 001-12.1-E03 Rev. 5 Erosion / Corrosion Monitoring Program ADM 08-212 Rev. 2 Ultrasonic Examination for Preservice and Inservice Examination 001-12.1-504 Rev. 5
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Ultrasonic Examination of Piping System 83A2417 Rev. 0 l
Radiography Guidelines ADM 03-003 Rev. 2 Radiographic Examination of Welds and Components 001-12.1-508 Rev. 3 Radiographic Review and Interpretation QCI-12.1-505 Rev. 2
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Results: No violations were identified.
6.0 ATTACHMENTS
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Attachment 1 is a tabulation of specific pipe weldments examined and the results. Attachment 2 is a tabulation of specific hangers and supports examined and the results. Attachment 3 is a tabulation of specific components examined for erosion-corrosion.
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7.0 UNRESOLVED ITEMS Unresolved items are matters which require additional information in order to ascertain whether they are acceptable items or violations.
Two unresolved items are identified in this report (See Sections 2.5 and 3.0).
8.0 MANAGEMENT MEETINGS (30703)
Licensee's management was informed of the scope and purpose of the inspection at the entrance interview on April 3, 1990.
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 interview (see paragraph 1.0 for attendee's). At no time during the inspection was written material provided to the licensee by the inspector.
The licensee did not indicate that proprietary information was involved within the scope of this inspection.
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' ATTACHMENT #1 INDEPENDENT MEASUREMENTS INSPECTION SHEET 1 OF 1 l. *.,
SITEt, WOLF CREEK NDE PIPING /WELDMENTS DATE: 4/02-4/13/90 ISO /DWG WELD ID SYS CL.
RT MT PT UT VT ACC REJ COMMENTS
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M-13AE04 S014-A FW
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X X
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M-13AE04 FW-900 FW
X X
X X
M-13AE04 F043 FW
X X
X X
l M-13AE04 F021 FW
X X
X X
M-13AE04 F018 FW
X X
X X
WELD WIDTH 6" I
M-13AE04 F019 FW
X X
X X
177-HCB FW209 FW
X X
X 115-BCB PW3368 FW
X X
X 176-DCB FW208 FW
X X
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442 DCD PW857 SGB B31 X
X X
442 DCD PW2062 SGB B31 X
X X
442 DCD PW2063 SGB B31 X
X X
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442 DCD PW2064 SGB B31 X
X X
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442 DCD PW866 SGB B31 X
X X
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TOTAL
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-ATTACHMENT #2 INDEPENDENT MEASUREMENTS INSPECTION SHT 1 OF 1-
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CITEt, WOLF CREEK HANGER / SUPPORT DATE 4/02-4/13/90
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.DWG/ ISO HANGER / SUPPORT.
SYS CL CAT ACC REJ COMMENTS M-06EG07 C003/134 CCW
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M-06EM02 H004/134 HPCI
X M-06EC04 R035/1611 FPC
X M-16EG26 R002/142 CCW
X M-16KJ01 R015/511 SD
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M-16KJ01 R008/511 SD
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M-16EF08 H001/511 ESW
X M-16EF15 C005/341 ESW
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M-06EF05 R019/111 ESW
X M-06EG24 R008/111 CCW
X M-16BG15 R010/113 CVC
X M-06EF05 R017/141 ESW
X M-06EG24 H002/141 CCW
X M-06EF06 C053/142 ESW
X M-16EJ06 H503/122 RHR
X M-06BG01 C009/122 CVC
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M-06EG18 R005/621 CCW
X M-16EG02 R005/141 CCW
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. ATTACHMENT'# 3 EROSIOM/ CORROSION EXAMINATION SHT 1 OF 1
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' SITE ' WOLF CREEK DATE: APRo 90 LINE PIPE / COMPONENT SYSTEM AREA COMMENTS CG-020-HBD 6" PIPE / PIPE SERVICE WATER 01454 EA-030-HDD 10" PIPE / PIPE SERVICE WATER 01452 EA-013-HDB 6"
PIPE / ELBOW SERVICE WATER 00157 EA-013-HDB 6"
PIPE / ELBOW SERVICE WATER 00158 EA-017-HDB 6"
PIPE / ELBOW SERVICE WATER 00159 EB-062-HSD 10" ELBOW / PIPE SERVICE WATER 01453 EA-009-HBD 10" PIPE / VALVE SERVICE WATER 00153 EA-057-HBD 20" PIPE / PIPE SERVICE WATER 01451 EA-DO8-HBD 10" PIPE \\ PIPE SERVICE WATER 01455 EA-040-HBD 18" PIPE / ELBOW SERVICE WATER 01450
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' ATTACHMENT #33 INDEPENDENT MEASUREMENTS INSPECTION PAGE 1 OF 4 SITE: WOLF CREEK EROSION / CORROSION DATE: 4/02-4/13/90
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ISO \\DWG WELD /PART ACC REJ SYS CL.
COMMENTS M-13EA07 01452 X
B C
D E
F G
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.350.345.350.360
.360.355
.345.360.365.365
.345.345.355.360.370.355.350.360.370.370
.350.350.350.360.360.355.350.360
.360.370
.350.350.355.365.360.355.350.365.370.375
.350.350.350.360.365.360.355.360.375
.370
.350.360.355.360.365.350.350.360.365.370
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.360.360.360.365.365.360.365.350.360.360
i.355
.360.350.365.370.355.345.360.365.370
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.360.360.360.365.370.345.350.360.360.365 10.350.355.360.355.365.350.350.350.355.360
.350.350.350.365.365.355.350.355.350.360
.360.360.360.365
.370.355.350.350.350.360 13.365.355.360.365
.190.360.355.350.350.360 l
COMPONENT: EA-030-HBD 6" PIPE / PIPE GRID = 1" SQ.
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g-ATThCRMENT #33 INDEPENDENT MEASUREMENTS INSPECTION PAGE 2 OF 4 SITE: WOLF CREEK EROSION / CORROSION DATE: 4/02-4/13/90 ISO \\DWG WELD /PART ACC REJ SYS CL.
COMMENTS M-13EA05 01454 X
> CCW TDCfA B
C D
E F
G H
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K L
M N
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.275.275.280.280.280.280.290.290.300.300.300.300.280.280
.275.270.275.280.285.290.290.295.300.295.295.290.290.290
.270.275.280.285.285.290.290.300.300.300.295.290.290.290
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.280.275.280.280.290.295.290.290.295.290.300.290.290.290
.280.265.270.285.280.280.290.290.290.290.295.290.290.295
.285.290.280.280.270.290.290.285.290.290.295.295.290.290
.290.295.280.280.280.285
.285.290.285.285.290.295.290.155
.285.295.280.280.280.280.280.295
.290.290.285.290.290.290
290.300.285.280.280
.280.285.290.290.285.290.285.285.285
295.285.280.280.285.285.290.290.280.280.300.295.295.950
285.285.270.280.280.280.290.285.285.290.300.295
.295.295
280.275.270.280.280.280.290.290.290.295.295.295.300.295 i
285.275.280.280.280.280.290.290.293.295.295.300.300.295 l
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COMPONENT: CG-020-HBD 6 PIPE / PIPE i
GRID = 1" SQ.
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-ATTACEMENT #33 INDEPENDENT MEASUREMENTS INSPECTION PAGE 3 OF 4 SITE: WOLF CREEK EROSION / CORROSION DATE: 4/02-4/13/90 ISO \\DWG WELD /PART ACC REJ SYS CL.
COMMENTS M-13EA08 01451 X
B C
D E
F G
H I
J K
L M
N
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.360.375.375.385.395.395.390.400.395.395.395.395.395.390
.365.385.375.375.395.395.390.395.395.395.395.395.395.395
360.395.385.395.395.395.395.400.385.395.395.395.395.400
.390.395.395.395.395.400.395.400.400.395.400.390.395.150
.395.395
.400
.410.400.395
.400.400.400.395
.400.390.395.395
.395.395
.385.385.395.395.405.400.400.<00.400.395.390.390
.395
.400.400.400'.395 4395.400.395.400.400.395.395
.390.395 l
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COMPONENT: EA-057-HBD 20" PIPE / PIPE GRID = 2" SQ.
THICKNESS MEASURED THROUGH PAINT
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'ATT CHMENT #33 INDEPENDENT MEASUREMENTS INSPECTION PAGE 4 OF 4 SITE: WOLF CREEK EROSION / CORROSION DATE: 4/02-4/13/90
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ISO \\DWG WELD /PART ACC REJ SYS CL.
COMMENTS
M-13EA07 01450 X
B C
D E
F G
H I
J K
L M
N 1-
.155.160.375.380.380.375.380.380.375.375.375.370.355.370
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.375.195.375.385.375
.375.380.385.375.365.355.355.365.365
.370.365.385.385.140.385.375
.155.385
.375.375.365.355
.370
.370-.365.375
.385.385
.385.375.380.385.375.370.360.365.375
.375.385.390.385.150.375.370.375
,,252.355.360.360.365.365 6 ' 390.375.385.375.155.375. 380'.385.195
.370.365.365.360.360
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.385
.255
.380.380.395
.385.385.385.380.375.375.365.360.365
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12
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COMPONENT:-EA-040-HBD 18" PIPE / ELBOW GRID = 2" SQ.
UNDERLINED MEASUREMENTS ARE LOCALIZED AREAS THAT DO NOT MOVE WHEN THE TRANSDUCER IS MOVED MIN. WALL THICKNESS.328" l
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