IR 05000315/1986014
| ML17326B244 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/04/1986 |
| From: | Danielson D, David Jones, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17326B243 | List: |
| References | |
| 50-315-86-14, 50-316-86-14, NUDOCS 8606100291 | |
| Download: ML17326B244 (11) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-315/86014(DRS);
50-316/86014(DRS)
Docket Nos.
50-315; 50-316 Licens'es No.
American Electric Power Service Corporation Indiana and Michigan Electric Company 1 Riverside Plaza Columbus, OH 43216 Facility Name:
D.
C.
Cook Nuclear Plant, Units 1 and 2 Inspection At:
D.
C.
Cook site, Bridgman, MI Inspection Conducted:
March 17-20, April 10-11, and May 14-16, 1986 Inspectors
.
E.
Jones Date
.
D. Ward (April 10-11, 1986)
Date Approved By:
D.
HE Danielson, Chief Materials and Processes Section Date Ins ection Summar Ins ection on March 17-20 A ril 10-11 and Ma 14-16 1986 Re orts No.50-315 86014(DRS)
50-316 86014 DRS Areas Ins ected:
Routine, unannounced inspection of inservice inspection (ISI procedures, work activities, nondestructive examination (NDE) personnel certifications and ISI data; of a chemical and volume control system (CVCS)
modification (Unit 2); and to followup on an LER.
Results:
No violations or deviations were identified.
BbObi0029i BbOb04 PDR ADOCK 050003i5 G
DETAILS 1.
Persons Contacted Indiana and Michi an Electric Com an IM
"W. Smith, Jr., Plant Manager
"A. Blind, Assistant Plant Manager, Maintenance
"B. Svensson, Assistant Plant Manager, Operations
"J. Stietzel, Quality Control (QC) Superintendent
"R. Otte, ISI Supervisor
"J. Rutkowski, Staff Assistant E. Horse, Training Coordinator M. Ferguson, Design Change Coordinator American Electric Power Service Cor oration (AEPSC S.
Deluca, Service Engineer Southwest Research Institute (SwRI R. Fine, Team Leader D. York, Inspection Engineer Ha naflux MN J. White, Site Leadman Catal tic Industrial Maintenance Com an (CIMCO)
B. Howeth, Mechanical Superintendent/Welding Engineer Factor Mutual En ineerin D. Young, Authorized Nuclear Inservice Inspector U.
S. Nuclear Re ulator Commission NRC
"B. Jorgenson, Senior Resident Inspector J. Heller, Resident Inspector C. Wolfsen, Resident Inspector The inspector also contacted and interviewed other licensee and contractor employees.
"Denotes those present at the final exit interview on May 16, 198.
License Event Re ort LER Followu 3.
(Closed)
LER 315/85-45, Revision 1, Steam Generator/Pressurizer Enclosure-Form Plate Evaluation.
The inspector verified that reporting requirements had been met, causes had been identified, corrective action appeared appropriate, generic applicability had been considered, and the LER forms were complete.
This LER identified attachments that were made to the steel form plates which form an integral part of the inner surface of the pressurizer and steam generator concrete enclosures in both Units 1 and 2.
The form plates were not intended to be utilized for attachments.
An evaluation was performed of the adequacy of attachments made to the form plates, adequacy of attachment of"the form plates to the concrete enclosure, and material certifications.
The evaluations revealed that the anchorage for the form plates were capable of car rying their own weight plus the attached equip-ment without loss of structural integrity.
However, it was decided to enhance the attachment of these form plates by adding additional anchors.
Inservice Ins ection Unit 2 General Information This is the seventh outage of the first ten-year interval.'Indiana and Michigan Power Company (I8N) contracted with Mestinghouse (M) to perform the steam generator eddy current (ET) inspection and with Southwest Research Institute (SwRI) to perform the ultrasonic examinations.
The balance of the ISI was performed by MN.
The ISI was performed in accordance with ASHE Section XI, 1974 Edition, Minter 1975 Addenda, with the exception of the ET inspection which was performed in accordance with ASME Section XI, 1980 Edition, Minter 1981 Addenda.
Westinghouse performed the eddy current examinations, Zetec performed the data evaluation, and Conam performed the third party evaluation.
IQl had no specific relief requests to the NRC in the program.
Eddy current examination was performed on steam generators 21, 22, 23, and 24, and the following tubes were plugged:
Steam Generator No.
Row 12, Column
Row 13, Column
Row 14, Column
Row 17, Column 13 Row ll, Column 14 Row 23, Column 14 Row 29, Column 14 Row 25, Column 16 Row 13, Column 19 Row 3,
Column 22 Row 16, Column 23 Row 6,
Column 24 Row ll, Column 24 Row 17, Column 30 Row 23, Column 31 Row 19, Column 34 Row 12, Column 35 Row 29, Column 42 Row 13, Column 60 Row 5,
Column 74 Row 4,
Column 77
~
~
L ff
Steam Generator No.
Row 12, Row 17, Row 24, Row 5,
Row 6,
Row 5,
Row 6,
Row 5,
Row 13, Row 27, Row 2,
Row 27, Row 12, Row 13, Column
Column
Column 12 Column 17 Column 17 Column 21 Column 21 Column 24 Column 26 Column 53 Column 55 Column 55 Column 56 Column 56 Row Row Row Row Row Row Row Row Row Row Row Row Row Row 25, 28, 9,
2 21,ll 44, 20,
40, 25,
16, Column 56 Column 56 Column 57 Column 57 Column 28 Column 28 Column 33 Column 35 Column 37 Column 38 Column 39 Column 41 Column 43 Column 45 Row 12, Row 20, Row 12, Row 12, Row 18, Row 7,
Row 23, Row 7,
Row 10, Column 48 Column 53 Column 60 Column 63 Column 63 Column 64 Column 65 Column 66 Column 66 Row 17, Row 15, Column 85 Column 86 Row 15, Column 66 Row 7,
Column 68 Row 3,
Column 78 Steam Generator No.
Row 3,
Row 3,
Row 40, Row 23, Row 6,
Row 15, Column
Column 19 Column 26 Column 27 Column 28 Column 28 Row 2,
Row 8,
Row 26, Row 15, Row 41, Row 7,
Row 27, Row 7,
Row 10, Row 15, Row 8,
Row 10, Row 7,
Row ll, Column 29 Column 29 Column 29 Column 30 Column 30 Column 33 Column 34 Column 36 Column 36 Column 36 Column 38'olumn38 Column 40 Column 41 Row 24,.Column
Row 34, Row
. 5, Row'll, Row 4,
Row 14, Row 10, Row 14, Row 12, Row 4,
Row 11, Row 4,
Row 21, Row 16, Row 17, Row 16, Row 23, Row 3,
Row 11, Row ll, Row 17, Row 12, Column 41 Column 42 Col umn.44 Column 46 Column 46 Column 47 Column 47 Column 48 Column 51 Column 51 Column 52 Column 52 Column 55 Column 57 Column 59 Column 60 Column 61 Column 61 Column 61 Column 62 Column 63 Row 17, Row 19, Row 20, Row 14, Row 22, Row 15, Row 17, Row 13, Row 17, Row 14, Row 18, Row 16, Row 2,
Row 15, Row 10, Row 12, Row 13, Row 5,
Row 9,
Row 13, Row 31, Column 63 Column 63 Column 63 Column 64 Column 64 Column 65 Column 65 Column 66 Column 67 Column 68 Column 68 Column 69 Column 71 Column 71 Column 73 Column 73 Column 73 Column 76 Column 76 Column 79 Column 80 Steam Generator No.
Row 6,
Row 22, Row 24, Row 29, Row 16, Row 20, Row 19, Row 23, 6,
Column 18 Column 33 Column 34 Column 37 Column 39 Column 54 Column 57 Column 57 Column 59 Row 15, Row 22, Row 9,
Row 15, Row 22, Row 14, Row 16, Row 20, Column 59 Column 61 Column 62 Column 63 Column 63 Column 64 Column 64 Column 64 Row 13, Row 20, Row 9,
Row 24, Row 21, Row 23, Row 21, Row 14, Column 66 Column 68 Column 69 Column 69 Column 73 Column 73 Column 75 Column 91
~
~
(w L
b.
Pro ram/Procedure Review The inspector reviewed the following ISI procedures:
SWRI, 1986 Inservice Examination Plan for selected components of the Donald C.
Cook Nuclear Plant, Unit 2.
SWRI, Recording Indications from Ligaments, Bolting, Piping and Vessel Weld Examinations, IX-FE-117-4, Revision 4, CS-1 SWRI, Measuring and Recording Search Unit Data during Ultrasonic Exams of Pressure Vessel Welds, IX-FE-119-0, Revision
SWRI, Onsite NDE Records Control, X-FE-101-3, Revision
SWRI, Control of Nuclear Inspection Equipment and Materials, XIII-AG-101-2, Revision
SWRI, Data Storage=and Retrieval, XVII-AG-101-1, Revision 1, CS-2 SWRI, Manual Ultrasonic Examination of Pressure Piping Welds, SWRI-NDT-600-3, Revision
SWRI, Manual Ultrasonic Examination of Nuclear Reactor Pressure Vessel Flange Ligaments, SWRI-NDT-600-5, Revision 35, Deviation 12 SWRI, Manual Ultrasonic Examination of Reactor Coolant Pump Flywheels, SWRI-NDT-600-6, Revision
SWRI, Manual Ultrasonic Examination of Vessel-to-Nozzle Inner Radius Sections, SWRI-NDT-600-11, Revision 40, Deviation 7 SWRI, Manual Ultrasonic Examination of Pressure Vessel Welds, SWRI-NDT-600-15, Revision 57, Deviation 12 SWRI, Manual Ultrasonic Examination of Pressure Vessel Welds, SWRI-NDT-600-15, Revision
SWRI, Manual Ultrasonic Examination of Pressure Retaining Studs and Bolts 2" or Greater in Diameter Containing Access Holes, SWRI-NDT-600-18, Revision
SWRI, Manual Ultrasonic Examination of Pressure Retaining Round Nuts Two Inches or Greater in Diameter, SWRI-NDT-600-19, Revision
SWRI, Manual Ultrasonic Examination of Thin Wall Vessel Welds, SWRI-NDT-600-26, Revision
SWRI, Manual Ultrasonic Examination of Pressure Retaining Welds in Heat Exchangers, SWRI-NDT-600-30, Revision
SWRI, Manual Ultrasonic Examination of Pressure Vessel Welds Greater Than 0.4 Inches and Less Than 2.5 Inches in Thickness, SWRI-NDT-600-33, Revision 7, Deviation
4 SWRI, Manual Ultrasonic Examination of Small Diameter Piping Welds, SWRI-NDT-600-39, Revision
~
SWRI, Special Procedure for Manual, Ultrasonics Examination of Austenitic Components with High Acoustic Attenuation Properties, SWRI-NDT-800-17, Revision 27, Deviation
SWRI, Manual Ultrasonic Examination of Thin Wall Piping Welds, SWRI-NDT-800-36, Revision 31 W, Hands-On Lower Hard Roll Tool, AEA-327(81), Revision 4 W, Control of Field Service Activities, OPR-610-3, Revision
W, Post-Activity Sign-Off for Area Cleanliness, MRS 2.2.2 Gen-6-,. Revision
W, Steam Generator Tube Sheet Marking, MRS 2.2.2 Gen-12, Revision
W, Mechariical Plugging of.Steam Generator Tubing and Tube Holes, MRS 2.3.2 Gen-13, Revision
W, Digital Multi-Frequency Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing, MRS 2.4.2 Gen-28, Revision
W, SM-10W Operating Procedure, MRS 2.4.2 Gen-30, Revision
~
I88, Liquid Penetrant Examination for Nuclear and Non-Nuclear Welds and Components,
gHP 50.50 NDE.001, Revision
I88, gC Visual Weld Examination,
gHP 7091 NDE.001, Revision
I88, Visual Examination VT-l, VT-3, and VT-4, 12 gHP 7091 NDE.003, Revision
ILM, Magnetic Particle Examination Procedure for Nuclear, Non-Nuclear and Structural Materials Using Prods, Longitudinal, Circular and Yoke Methods, 12 gHP 5050 NDE.002, Revision 4 IVI, Magnaflux guality Services Test and Inspection Procedure 20.A. 1 - Summer 1982 Radiographic Examination of Welds, 12 gHP 5050.SP.002, Revision
No violations or deviations were identified.
h
c.
Material and E ui ment Certification The NRC inspector reviewed the certification documents relative to the following items:
Ultrasonic Instruments, Calibration Blocks, Transducers and Couplant Liquid Penetrant Materials and Equipment Magnetic Particle Materials and Equipment Eddy Current Equipment No violations or deviations were identified.
d.
NDE Personnel Certifications and Observation of >lork Activities The NRC inspector reviewed NDE personnel certifications in accordance with SNT-TC-1A The NRC inspector also observed the work and had discussions with personnel during the following examinations:
Eddy Current Examinations of Steam Generators 21 and 22 in accordance with W Procedure No.
MRS 2.4.2 Gen-28, Revision 1,
"Digital Multi-frequency Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing" Ultrasonic Calibration for the Pressurizer Nozzle-to-Lower Head Meld No. 14"-2-RC-21, in accordance with SWRI Procedure No. 600-15, Revision 57, Deviation 12,
"Manual Ultrasonic Examination of Pressure Vessel Melds" e.
Liquid Penetrant Examination of Field Melds 2, 7, and 20, 4"
CVCS line in the Mest Pump Charging Room, in accordance with ILM Procedure No.
QHP 50.50 NDE.001, Revision 6, "Liquid Penetrant Examination for Nuclear and Non-nuclear Welds and Components" No violations or deviations were identified.
Data Review The NRC inspector reviewed report documentation relative to the following:
Ultrasonic Examinations Liquid Penetrant Examinations
~
~
'
Magnetic Particle Examinations Eddy Current Examinations Steam Generator No.
24 Feedwater Ring J-Tube Examination Report (UTaVT)
Radiographic Examination No violations or deviations were identified.
4.
Chemical and Volume Control S stem (CVCS Modification - Unit 2 a ~
General b.
This constitutes the final phase of the CVCS modification which was begun in Unit 1 'and covered in NRC Report No. 50-315/85015.
The modification to the CVCS was undertaken as a result of commitments made to the NRC, to insure reactor reactivity control and coolant makeup control in 'the event of fire.
The modification provides a permanent inter-unit CVCS cross-tie line at the discharge header of the centrifugal charging pumps.
During a design base accident the charging pumps are used for safe shutdown.
The cross-tie will provide for using the charging pumps from the unit unaffected by a hypothetical fire for alternative safe shutdown.
The cross-tie line consists of four inch piping with manually operated valves and local flow indication.
A four inch branch line connects the cross-tie to the inlet of each unit's BIT tank, and a three inch cross connection is made to the RCP seal injection path.
Review of Procedures The inspector reviewed the following procedures that were used to accomplish this modification:
CIMCO, General Welding Requirements, SP-4200-500(N),
Revision
CIMCO, Welding Procedure Specification (WPS),
SS(N)-1020 for P8-T-FG-A8, Revision
MX, Radiographic Examination of Welds, General Requirements, 20.A. 100, Winter 1983, Revision 1 MX, Radiographic Examination of Welds, 20.A. 131, 1983 Edition, Revision
I88, Visual Examination - VT1, VT3, and VT4, 12 gHP 7901 NDE.003, Revision
ILM, Magnetic Particle Examination Procedure for Nuclear, Non-nuclear, and Structural Materials Using Prods, Longitudinal, Circular and Yoke Methods, 12 gHP 5050 NDE.002, Revision,4
IQf, Liquid Penetrant Examination for Nuclear and Non-nuclear Welds and components, 12 gHP 5050 NDE.001, Revision
No violations or deviations were identified.
c.
Data Review The inspector reviewed report documentation relative to the following:
Meld Examination and Acceptance Records No violations or deviations were identified.
5.
Exit Interview The inspector met with site representatives (denoted in Persons Contacted paragraph)
at the conclusion of the inspection.
The inspector summarized the scope and findings of the inspection noted in this report.
The 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 documents/processes as proprietary.