IR 05000315/1985015
| ML17321A879 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/29/1985 |
| From: | Danielson D, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17321A878 | List: |
| References | |
| 50-315-85-15, 50-316-85-15, IEB-82-01, IEB-82-02, IEB-82-1, IEB-82-2, IEB-83-06, IEB-83-6, NUDOCS 8509040089 | |
| Download: ML17321A879 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION III
Report Nos.
50-315/85015(DRS);
50-316/85015(DRS)
Docket Nos.
50-315; 50-316 License Nos.
American Electric Power Service Corporation Indiana 8 Michigan Power Company 1 Riverside Plaza Columbus, OH 43216 Facility Name:
D.
C.
Cook Nuclear Power Plant, Units 1 8
Inspection At:
D.
C.
Cook Site, Bridgman, Michigan Inspection Conducted:
May 21-23, June 26-27, and August 7-9, 13-15, 1985 Inspector
.
E. Jones Date Approved By:
D.
H. Danielson, Chief Materials and Processes Section Ins ection Summar g z<Z<
Date Ins ection on Ma 21-23 June 26-27 and Au ust 7-9 13-15 1985 Re ort Nos.
50-315 85015 DRS
. 50-316 85015 DRS
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f1'E Bulletins; inservice inspection (ISI) procedures, work activities, Nondestructive Examination (NDE) personnel certifications and data; Chemical and Volume Control System (CVCS) modification (Unit 1); and leak and eddy current examination of steam generator (SG) 23, Unit 2.
The inspection involved a total of 64 inspector"hours onsite by one NRC inspector.
Results:
No violations or deviations were identifie '
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DETAILS 1.
Persons Contacted Indiana 8 Michi an Electric Com an (IQl
~Pl. Smith, Plant Manager
"J. Stietzel, gC Superintendent
"R. Otte, ISI Supervisor E. Morse, Training Coordinator A. Blind, Assistant Plant Manger M. Ferguson, Design Change Coordinator American Electric Power Service Cor
.
AEPSC)
"M. Horvath, gA Supervisor Catal tic Industrial Maintenance Com an (CIMCo J. Edgell, Mechanical Superintendent/Melding Engineer Mestin house M
D. Obazenu, Eddy Current Coordinator R. Schaeffer, Lead Data Coordinator B. Stock, Analyst Southwest Research Institute SMRI B. Clayton, Supervisor Ma naflux MX J. Ouelette, Site Leadman The inspector also contacted and interviewed other licensee and contractor employees.
"Denotes those present at the exit interview.
2.
Licensee Action on IE Bulletins (Closed)
IE Bulletin (315/82-01-BB, 315/82-01-1B, 315/82-01-2B, 316/82-01-BB, 316/82-01-1B, 316/82-01-2B):
IE Bulletin 82-01, Revision 1, and Revision 1, Supplement 1, "Alteration of Radiographs of Melds in Piping Subassemblies."
This bulletin did not apply to this plant and was for information only.
The inspector verified that the licensee management received the IE Bulletin and that it was reviewed for applicability.
This item is considered close ~
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(Closed)
IE Bulletin (315/82-02-BB, 316/82-02-BB):
"Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants."
The inspector reviewed the licensee's final response dated Oecember 28, 1983.
ILM listed the instances of leakage of bolted closures in the Reactor Coolant Pressure Boundary and the corrective actions taken for Units 1 and 2.
Procedures applicable to the IE Bulletin were reviewed by I88 and updated as necessary to fulfill the requirements of this bulletin.
Bolted closures, identified within the scope of the bulletin, were examined and revealed no degradation.
This item is considered closed.
(Closed)
IE Bulletin (315/83-06-BB, 316/83-06-BB):
IE Bulletin 83"06,
"Nonconforming Materials Supplied by Tube-Line Corporation."
The inspector reviewed the licensee's final response dated November i8, 1983.
I8M reviewed the lists of purchasing and receiving companies given in Attachments 2 and 3 to the bulletin and the station purchase orders to determine if any ASME Code materials had been furnished by Tube-Line to any of the vendors identified in the attachments for shipment to 0.
C.
Cook.
The results of ILM's reviews revealed that no Tube-Line supplied materials has been furnished to D.
C.
Cook for use in safety-related systems.
This item is considered closed.
3.
Inservice Ins ection Unit 1 a 4 General Information Indiana and Michigan Power Company (IQ1) contracted with Westinghouse (W) to perform the steam generator eddy current (ET) inspection and with Southwest Research Institute (SWRI)
to perform the ultrasonic examination (PAR Exam) of the reactor vessel.
The balance of the ISI was performed by I@1, SWRI and Magnaflux.
The ISI was performed in accordance with ASME Section XI, 1974 Edition, Winter 1975 Addenda, with the exception of the ET inspection which was performed in accordance with ASME Section XI, 1980 Edition, Winter 1981 Addenda.
Eddy current examination was performed on steam generators ll, 12, 13 and 14, and the following tubes were plugged:
STEAM GENERATOR NO.
STEAM GENERATOR NO.
Row Column Row Co1umn
36
29
28
25
19
36
68
80
18
19
16
17
37
39
41
43
86
p e
STEAM GENERATOR NO.
STEAM GENERATOR NO.
Row
37
40
33 Column
47
51
61 Row
13
20
Column
39
47
b.
Pro ram/Procedure Review The inspector reviewed the following ISI procedures:
SldRI, Nuclear, quality Assurance Program Manual, Revision 2, Incorporating Change
'MRI, 1985 Inservice Examination Plan for Selected Components, of the Donald C.
Cook Nuclear Plant, Unit 1 SMRI, Plan for Mechanized Ultrasonic Examination of Selected Components at Donald C.
Cook Nuclear Plant, Unit 1, May 1985 SMRI, Deviations to Nuclear Project Operating Procedures, IX-FE-101, Revision
SMRI, Meld Joint Identification Marking on Nuclear Power Plant Piping, IX-FE-103, Revision
SMRI, Recording Data from Direct Visual, Liquid Penetrant and Magnetic Particle Examinations, IX-FE-116, Revision 0, Change
SWRI, Onsite NDE Records Control, X-FE-101, Revision
SWRI, Recording Indications from Ligaments, Bolting, Piping and Vessel Meld Examinations, IX-FE-117, Revision
,I SMRI, Control of Nuclear Inspection Equipment and Materials, XIII-AG-101, Revision
SMRI, Data Storage and Retrieval, XVII-AG-101, Revision
SMRI, Manual Ultrasonic Examination of Pressure Piping Melds, SHRI-NDT-600-3, Revision
SHRI, Manual Ultrasonic Examination of Pressure Retaining Melds in Heat Exchangers, SMRI-NDT-600-30, Revision
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SMRI, Special Procedure for Manual Ultrasonics Examination of Austenitic Components with High Acoustic Attenuation Properties, SWRI-NDT-800-17, Revision
SMRI, Manual Ultrasonic Examination of Thin Mall Piping Melds, SMRI-NDT-800-36, Revision
SMRI, Visual Examination of Nuclear Power Plant Components by Direct or "Remote Viewing, SWRI-NDT-900-1, Revision 51 SMRI, Visual Examination of Nuclear Reactor Internals by Direct or Remote Reviewing, SMRI-NDT-900-2, Revision
SMRI, Mechanized Ultrasonic Examination of Vessel Melds Less than 2.5 Inches in Thickness and Piping Melds, SMRI-NDT-700-5, Revision
SMRI, Mechanized Ultrasonic Examination of Ferritic Vessels Greater than 2.5 Inches in Thickness, SMRI-NDT-700-6, Revision
SMRI, Visual Examination of Nuclear Power Plant Components by Direct or Remote Viewing, SMRI-NDT-900-1, Revision
M, Control of Field Service Activities, OPR 610-3, Revision
M, Post-Activity Sign-off for Area Cleanliness, MRS 2.2.2 GEN-6, Revision
M, Steam Generator Tubesheet Marking, MRS 2. 2. 2 GEN-12, Revision
M, Mechanical Plugging of Steam Generator Tubing and Tube Holes, MRS 2.3.2 GEN-13, Revision
M, Digital Multi-Frequency Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing, NRS 2.4.2 GEN-28, Revision
M, Remotely Operated Service Arm (ROSA) Series 51 S/G Operating Procedure, P-SE-ATS-84-038, Revision
M, ROSA No Entry Single Probe Flip Flop Eddy Current Tool (Series 51 S/G),
P-SE-ATS-84-047, Revision
M, ROSA Mechanical Plug Installation Tool (Series
S/G) Field Procedure, P-SE-ATS-84-048, Revision
W, ROSA No Entry Helium Sniffer End Effector (Series
and 51 F S/G),
P-SE-ATS-84-076, Revision
M, Mechanical Plugging Using the Limited Access Plug Installation Tool, SE-SG-83-010, Revision
II
I&M, Liquid Penetrant Examination for Nuclear and Non-Nuclear Melds and Components,
gHP 5050 NDE.001, Revision
I&M, 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 I&M, Visual Examination - VT 1, 12 gHP 5050 NDE.024, Revision
No violations or deviations were identified.
c.
Material and E ui ment Certification The inspector reviewed the certification documents relative to the following items:
(1)
Ultrasonic instruments, calibration blocks, transducers and coupl ant (2)
Liquid penetrant materials (3)
Magnetic particle materials and equipment (4)
Eddy current equipment No violations or deviations were identified; d.
NDE Personnel Certifications and Observation of Mork Activities The inspector reviewed NDE personnel certifications in accordance with SNT-TC-lA, 1975/1980 Editions.
The inspector also observed the work and had discussions with personnel during the following examinations:
Eddy current examination of S/G 14, Row 2 - Column 37; and S/G 13, Rows 27-33 and 35 - Column 37; and Rows 27-34 - Column 38.
The examination was performed in accordance with 8 Procedure MRS 2.4.2 GEN-28, Revision 0, "Digital Multi-Frequency Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing."
Ultrasonic examination (Par Exam) of reactor vessel inlet nozzle to shell at 293~; in accordance with SMRI Procedure NDT-700-6, Revision 25, "Mechanized Ultrasonic Examination of Ferritic Vessels Greater than 2.5 Inches in Thickness."
No violations or deviations were identified.
4.
Leak and Edd Current Examination of Steam Generator
Unit 2 On July 16, 1985, Unit 2 was shutdown to investigate primary-to-secondary system leakage, and two tubes were plugged in S/G 23.
Shortly after
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synchronizing the unit on August 2, 1985, and commencing power increase, primary-to-secondary leak indications in the No.
23 S/G recurred and the decision was made to return the unit to cold shutdown.
The leak rate for the first shutdown did not exceed the technical specification limit for primary-to-.secondary system leakage and the leak rate for the second shutdown was not quantified.
During this outage Mestinghouse performed the eddy current examinations, Zetec performed the data evaluation and Conam performed the third party evaluation.
This work'as performed in accordance with ASME Section XI, 1980 Edition, Minter 1981 Addenda.
The procedure used was Westinghouse MRS 2.4.2 GEN-28, Revision 0, "Digital Multi-Frequency Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing."
All of the data from the 1984 and July 1985 S/G examination was reviewed and any tubes in question were re-examined.
Approximately 1,552 tubes were inspected, full-length, and 35 tubes were plugged.
No violations or deviations were identified.
5.
Chemical and Volume Control S stem CVCS) Modification - Unit 1 a.
General 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 a 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.
b.
Review of Procedures The inspector reviewed the following procedures that were used to accomplish this modification:
CIMCO, General Melding Requirements, SP-4200-500(N),
Revision 4 CIMCO, Melding Procedure Specification (MPS), SS(N)-1020 for P8-T"F6-A8, Revision
NX, Radiographic Examination of Melds General Requirements, 20.A.100, Minter 1983, Revision
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NX, Radiographic Examination of Melds General Requirements, 20.B.100-1984, Revision
I88, Visual Examination - VT 1, 12 gHP 5050 NDE.024, Revision
1 IM, Liquid Penetrant Examination for Nuclear and Non-Nuclear Melds and Components, 12 gHP 5050 NDE.001, Revision
No violations or deviations were identified.
c.
Review of Records Re orts and Certifications The inspector reviewed the following documentation items and determined that the applicable requirements of gC/gA commitments have been met.
Material Certification NDE Melder qualification Records Meld Examinations and Acceptance Records NDE Personnel qualification Certification Final Test Reports Fabrication and Inspection Records No violations or deviations were identified.
6.
Exit Interview The Region III inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on August 15, l985.
The inspector summarized the purpose and'findings of the inspection.
The licensee representatives acknowledged this information.
The inspector also discussed the likely informational content of the 'inspection report with regard to documents or processes reviewed during the inspection.
The licensee representatives did not identify any such documents/processes as proprietar 'l f
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