IR 05000237/1987002
| ML17199G636 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/08/1987 |
| From: | Danielson D, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17199G635 | List: |
| References | |
| 50-237-87-02, 50-237-87-2, GL-84-11, NUDOCS 8706160287 | |
| Download: ML17199G636 (14) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-237 /87_002.(DRS)
Docket No. 50-237 Licensee:
Commonwealth Edison Company P. 0. Box 767 Chicago, IL 60690 Facility Name:
Dresden Station, Unit 2 Inspection At:
Dresden site, Morris, Illinois Inspection Conducted:
November 14, and December 9, 1986, License No. DPR-19 January 13-15, February 4-6, 10-12, 18-20, 24-26, March 3-5, 10-12, 26, April 1-3, 28, and May 5-7, 12-15, 19-21, 1987 Inspector:
Approved By:
D. H. Danielson, Chief Materials and Processes Section Inspection Summary 0/ <f/1'7 Date Inspection on November 14, and December 9, 1986, January 13-15, February 4-6, 10-12, 18-20, 24-26, March 3-5, 10-12, 26, April 1-3, 28, and May 5-7, 12-15, 19-21, 1987 (Report No. 50-237/87002(DRS))
Areas Inspected:
Routine unannounced inspection of Inservice Inspection (ISI)
work activities, including Generic Letter 84-11 inspections, cheek plate modifications, weld overlays, feedwater piping thickness measurements, and Unit 2 Mark I containment Temporary Instruction 2515/85 review (73501, 73052, 73753, 73755, 37701, 55700, 57700, 25585).
Results:
No violations or deviations were identified.
8706160287 870608 PDR ADOCK 05000237 G
- DETAILS Persons Contacted Commonwealth Edison Company (CECo)
- G. Svendson, !SI Coordinator M. Horbaczewski, IS! Engineer - SNED K. Knudtson, Engineer-Modifications Group M. Kusnik, Mechanical Maintenance Engineer C. Anderson, QC Inspector
- E. Armstrong, Engineer-Modifications Group General Electric (GE)
D. Hooper, Project Manager T. Brinkman, Level III Supervisor V. Krueger, Foreman Hartford Steam Boiler Inspection and Insurance Company P. Fisher, Authorized Nuclear Inservice Inspector (ANII) Supervisor R. Motquin, ANII B. Dellota, ANII Nute ch J. Smith, Site Superintendent W. W. Pope R. Schelling, QC Superintendent J. Maloney, Project Superintendent Personnel Present At Dresden Pre-IS! Meeting J. Doyle, QC Supervisor, CECo R. Hylka, QC, CECo W. Witt, Level III, CECo SMAD M. Horbaczewski, !SI Engineer, CECo SNED G. Svendsen, !SI Coordinator, CECo D. Hooper, Project Manager, GE P. Fisher, ANII Supervisor, Hartford D. Jones, Reactor Inspector, USNRC The inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the final exit interview on May 21, 198 **
- Followup on Licensee Event Reports Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specification (Closed) LER 87001-00:
Ultrasonic testing indications found on Unit 2 primary system piping due to intergranular stress corrosion crackin The preceding LER was reviewed against the criteria of 10 CFR 2, Appendix C, and the incident described met all of the following requirement The event was identified by the licensee, The event was an incident that, according to the current enforcement policy, met the criteria for Severity levels IV or V violations, The event was appropriately reported, The event was corrected (including measures to prevent recurrence within a reasonable amount of time), and The event was not a violation that could have been prevented by the licensee 1s corrective actions for a previous violatio No violations or deviations were identified in this are.
Inservice Inspection (ISI)-Unit 2 General A Pre-ISI Meeting was held at the site on November 14, 1986, (See Attendance List, Paragraph 1).
The purpose of the meeting was to discuss the upcoming Unit 2 IS CECo performed the visual examination and contracted with GE to perform the ultrasonic (UT) magnetic particle (MT), liquid penetrant (PT),
and the balance of the visual examinations (VT) in accordance with ASME Section XI, 1977 Edition, Summer 1979 addend This is the third outage of the second Ten-Year Pla CECo identified 222 welds that met the NRC Generic Letter 84-11 criteria for reinspection, and a sample of 63 welds was selecte The sample was expanded by.45 welds when indications were found in Recirculation Line Weld No. PD5-020 and Reactor Water Cleanup Line (RWCU) Weld No. 1201-8-1 The GE NOE personnel responsible for the ultrasonic examinations have successfully passed the EPRI detection practical examinatio ** *
RWCU Line Weld No. 1201-8-12 was weld overlayed (See Paragraph 5 of this report), and it was decided by CECo, after evaluation by Nutech, to monitor Recirculation Line Weld No. PD5-02 Plan/Procedure Review The inspector reviewed the following Plan/Procedures:
CECo, Inservice Inspection Plan, DTP 2, Revision e CECo, Nondestructive Testing (Inservice Inspection) OAP 11-8, Revision *
CECo; 11 Ultrasonic Examination of Weld Overlay Repaired Pipe Weld Joints
, NDT-C-37, Revision *
CECo, 11Magnetic Particle Examination for A.S.M.E.Section XI Class IWB and IWC Components for Nuclear Stations 11, NDT-B-1, Revision *
CECo, 11 Preservi ce and Inservi ce Ultrasonic Inspection of Similar and Dissimilar Metal Pipe Welds at Nuclear Stations 11,
NDT-C-2, Revision 1 *
CECo, 11 Ultrasonic Inspection of the Vessel Nozzle Inner Radii at Nuclear Stations
, NDT-C-10, Revision 10.
CECo, 11 Ultrasonic Inspection of Flange Ligaments Between Threaded Bolt Holes
, NDT-C-11, Revision 1 *
CECo, 11 Ultrasonic Examination of Reactor Vessel Welds to NRC Reg. Guide 1.150 for Boiling Water Reactors 11, NDT-C-30-79, Revision *
CECo, 11 Beam Spread and Refracted Angle Determination to NRC Reg. Guide 1.150 for Boiling Water Reactors 11, NDT-C-31-79, Revision *
CECo, 11 Nonaqueous Red Dye Liquid Penetrant Examination for Section XI Class IWB and IWC Components for Nuclear Stations 11,
NDT-D-2, Revision *
CECo, 11Visual Examination - Welds, Pressure Retaining Bolting, and Component Internals
, VT-1-1, Revision *
CECo, 11Visual Examination - System Hydrostatic and Leak Tests 11,
VT-2-1, Revision *
CECo, 11Visual Examination - Component Supports 11, VT-3-1, Revision 1.
No violations or deviations were identifie * NOE Personnel Certifications and Observations of Work Activities The NRC inspector reviewed NOE personnel certifications in accordance with SNT-TC-l *
The NRC inspector also observed and had discussion with personnel during the following work activities:
Ultrasonic calibration and examination of Isolation Condenser Line 2-1302-14, Welds 14-6, 14-6A, and 14-7, in accordance with CECo Procedure NDT-C-2, Revision 15, 11 Preservice and Inservice Ultrasonic Inspection of Similar and Dissimilar Metal Pipe Welds at Nuclear Stations.
- Ultrasonic calibration for examination of Control Rod Drive Housing Weld 02-31 in accordance with CECo Procedure NDT-C-8, Revision 0, "Ultrasonic Inspection of Control.Rod Drive Tube to Flange Weld, Boiling Water Reactors.
- Liquid Penetrant Examination of Isolation Condenser Return Line 2-1303-12 Welds 12-10 (Pipe-to-Elbow) and 12-11 (Elbow-to-Pipe) in accordance with CECo Procedure NDT-0-2, Revision 4, 11 Nonaqueous Red Dye Liquid Penetrant Examination for Section XI Class IWB and IWC Components for Nuclear Stations", NDT-D-2, Revision *
Magnetic Particle Examination of HPCI Turbine Exhaust-to-Torus Line 2-306-24-19 (Pipe-to-Elbow) in accordance with CECo Procedure NDT-B-1, Revision 2, 11Magnetic Particle Examination for A.S.Section XI Class IWB and IWC Components for Nuclear Stations,
NDT-B-1, Revision No violations or deviations were identifie Review of Data, Material and Equipment Certifications The NRC inspector reviewed the following documents and determined that the applicable QA/QC requirements were met:
ISI Data Report *
Ultrasonic Instruments, Transducers, and Couplant Certification *
Liquid Penetrant, Cleaner and Developer Certification *
Magnetic Particle Materials and Equipmen No violations or deviations were identified.
- Cheek Plate Modification Genera 1 A cheek plate is a structural attachment used in non-orthagonal beam connection It is a flat plate connection, between two I-beam webs, used to stabilize the beam upper flange in conjunction with a seat angl The Unit 2 drywell structural framing (tangential-to-radial beams) connections utilizing cheek plates were found to have deficiencies, by the licensee, during a walkdown to determine the as-built condition and interferences prior to the installation of a structural steel framing modificatio These deficiencies were noted as missing welds, cracked welds, missing connection bolts, and missing cheek plate A repair program was initiated to correct the deficiencies by welding the cheek plates, or installing new plates and replacing any missing bolt W. A. Pope, Inc. was contracted to perform the modification Review of Procedure
- The NRC inspector reviewed the following procedur *
Pope, 11Welding Procedure Specification Shielded Metal Arc Welding Structural Steel: SM 1.1. AWS, 11 Revision No violations or deviations were identifie Review of Records, Reports and Certifications The NRC inspector reviewed the following documentation items and determined that the applicable requirements of QA/QC commitments have been met:
Fabrication/Installation Travele *
Weld Data Shee *
Welder Qualification Record *
NOE Personnel Certification *
NOE Report No violations or deviations were identifie.
Weld Overlays General Piping weld overlay is an automatic GTAW process which deposits a multipass/multilayer weld build up, with water in the pipe to provide favorable stress patterns to further inhibit IGSCC, as well as to mechanically strengthen the are CECo coordinated the effort
..
with Nutech providing technical assistance, GAPCO supplying the equipment, supervision and training, and W. A. Pope providing the personnel and logistical suppor The weld overlays were performed on six weld Weld No. 8-12 was overlayed as a result of ISI findings and the other five were overlayed to provide additional weld thickness to permit surface conditioning to facilitate ultrasonic inservice inspection activitie Review of Procedures/Specifications The NRC inspector reviewed the following procedures/specifications:
Nutech, 11Technical Specification - Application and Examination of Weld Overlays - Dresden Unit 2 11, CEC-79-202, Revision *
CECo, 11 liquid Penetrant Examination 11 NDT-0, Revision 1 *
CECo, 11 liquid Penetrant Acceptance Criteria for Welds, ASME Section III 11, NDT-01, 11Addendum 11, Revision *
CECo, 11 Ultrasonic Examination 11 NDT-C, Revision 1 *
POPE, 11Gas Tungsten Arc Welding and Shielded Metal Arc Welding; PS to PB; Open Root 11 GT-SM 8.8 OR, Revision *
POPE, 11Welding Procedure Technique Sheet 11, GT-SM 8.8 OR, Revision No violations or deviations were identifie Review of Records, Records, and Certifications The NRC inspector reviewed the following documentation items and determined that the applicable requirements of QA/QC commitments have been met:
Fabrication/Installation Record *
NOE Report *
Welder Qualification Record *
NOE Personnel Certification No violations or deviations were identifie Observation of Work Activities The NRC inspector observed and had disussions with personnel during the following work activity:
Ultrasonic Calibration and Examination of Recirculation Line Weld PD19-Dl4 overlay in accordance with CECo Procedure NDT-C37, Revision 1, 11 Ultrasonic Examination of Weld Overlay Repaired Pipe Weld Joints 11 *
No violations or deviations were identifie.
!EN 86-106-Feedwater and Main Steam Piping Thickness Measurements CECo performed ultrasonic thickness measurements on the feed pump discharge, and portions of the feedwater suction line The feedwater regulating station piping thickness measurements were completed as a result of earlier effort Analysis was performed on the measurement data and it was determined by the licensee that the piping minimum wall thickness had not been compromise.
Mark I Modifications General Additional suppression pool hydrodynamic loads associated with a postulated Loss-Of-Coolant Accident (LOCA) were identified during large-scale testing of an advanced design pressure-suppression containment (Mark III).
These additional loads, which had not explicitly been included in the original Mark I containment design, result from the dynamic effects of drywell air and steam being rapidly forced into the suppression pool (Torus).
Because these hydrodynamic loads had not been considered in the original design of the Mark I containment, a detailed reevaluation of the Mark I containment system was require As a result of the reevaluation, structural modifications were required to restore the originally intended design-safety margin These structural modifications included the following items:
Drywell-to-Wetwell (Torus) Differential Pressure Contro *
Suppression Pool Temperature Monitoring Syste *
Downcomer Bracin *
Vent Header Deflecto *
Safety-Relief Valve (SRV) Quencher *
Stiffening of Torus Attached Pipin *
Torus Support Reinforcemen The following paragraphs address the inspection requirements of NRC Temporary Instruction 2515/85, which was issued to verify satisfactory completion of licensee actions concerning the Mark I Progra * Programmatic Review The NRC inspector reviewed previous inspection reports covering programmatic inspections performed during the modification The reports were reviewed to verify the inspection coverage of the following areas:
Torus Support Reinforcemen *
Torus Internal Modificatio *
Torus Attached Pipin The result of the review is outlined in the following matrix:
- TORUS SUPPORT REINFORCEMENT I
I I
I I I
I 12 I I
I REPORT NO. 50-237/
1-0 I I
I
,_....
I* I I
I INSTALLATION SPECIFICATIONS IX I I
I DESIGN DOCUMENTS IX I I
I CONTRACT & PROCUREMENT DOCUMENTS IX I I
I DRAWINGS IX I I
I PROCEDURES IX I I
I PERSONNEL CERTIFICATIONS & QUALIFICATIONS IX I I
I MATERIAL CERTIFICATIONS IX I I
I OBSERVATIONS FABRICATION7INSTALLATION ACTIVITIES IX I I
I INSTALLATION, INSPECTIONS & OTHER QUALITY RELATED DOCUMENTSIX I I I I I
- NOT PREVIOUSLY NSPECTED TORUS INTERNAlS MODIFICATIONS I
I I I I I I
I~ I~ 12 I I
REPORT NO. 50-237/
l 1 I 1 j-o I I
.......
.......
,_...
I INll-'l*I INSTALLATION SPECIFICATIONS IX I I I I
DESIGN DOCUMENTS IX I I I I
CONTRACT & PROCUREMENT DOCUMENTS I I IX I I
DRAWINGS IX I I I I
PROCEDURES IX I I I I
PERSONNEL CERTIFICATIONS & QUALIFICATIONS IX I I I I
MATERIAL CERTIFICATIONS I I IX I I
OBSERVATIONS FABRICATION7INSTALLATION ACTIVITIES IX IX I I I
INSTALLATION, INSPECTIONS & OTHER QUALITY RELATED DOCUMENTSIX I I I I I I
- NOT PREVIOUSLY INSPECTED I TORUS ATTACHED PIPING I
I I I I I I I I I~ IR5 I~ I~ I~ I~ 12 I REPORT NO. 50-237 I I * I * I * I * I * I I 1-o I N N 0 I-' N I-'
,_...
,
.......,
....... '°' jN j-.....i 11.0 I * I INSTALLATION SPECIFICATIONS I
IX I I I I I I DESIGN DOCUMENTS IX IX IX IX IX I I I CONTRACT & PROCUREMENT DOCUMENTS I I I I I I IX I DRAWINGS IX I I I I I I I PROCEDURES I
IX I I IX I I I PERSONNEL CERTIFICATIONS & QUALIFICATIONS I I I I I I IX I MATERIAL CERTIFICATIONS I I I I I I IX I OBSERVATIONS FABRICATION/INSTALLATION ACTIVITIES I I I I I I IX I INSTALLATION, INSPECTIONS & OTHER QUALITY RELATED DOCUMENTS I IX IX IX IX IX I I
- NOT PREVIOUSLY INSPECTED 10 Technical Specification Review (1) Suppression Pool Temperature Monitoring System The Suppression Pool Temperature Monitoring System was modified to provide an average and local pool temperature indication and alarms in the control roo Sixteen thermocouples are installed around the torus, one in each torus bay, with a set of eight thermocouples on the inner circumference, and another set of eight thermocouples on the outer circumference forming two independent channel The PUAR identified eight thermocouples to be placed around the torus, however, ATWS concerns prompted the installation of sixteen thermocouple The NRC inspector visually verified the final installation of the thermocouple The installation was consistent with the location and placement given in the PUAR and drawing The individual thermocouples are continuously recorded in the control room, for each channel, by means of Tracor Westronics Strip Charts, and annunciators provide indication of abnormal condition The strip charts are reviewed 1-2 times per shift by the operator The temperature limits given in the technical specifications are consistent with those in the PUAR, and the instrumentation alarm setpoints are consistent with the temperature limits given in the technical specification (2)
Drywell to Wetwell Differential Pressure Control At Dresden the drywell/torus differential pressure control system is also known as the pumpback syste The purpose of the system is to maintain a drywell to torus differential pressure of equal to, or greater than 1 psid, in order to decrease or eliminate any damage to the torus structural internals in the event of a blowdow The differential pressure minimizes the water level in the downcomer piping and thus reduces the water slug upon pressurizatio The NRC inspector reviewed the drywell to wetwell differential pressure control system and determined that the differential pressure control limits of equal to or greater than 1 psid are consistent with the PUA Control room instrumentation consists of a Research Incorporated drywell/torus DP controller with instrument warning lights and dial for indicatio Surveillance requirements are that the pressure differential between the drywell and suppression chamber be recorded at least once each shif \\ *
Design Modification Review (1)
Downcomer Bracing The modification consisted of replacing the existing downcomer bracing (2 x 2 x 1/4 angles) with new downcomer bracing (2 1/2 11 diameter pipe) which has a greater structural capacit The NRC inspector reviewed the following fabrication drawings to verify that the modifications met the PUAR commitments:
Phillips, Getschow Co., Bl375-2-AA
Phillips, Getschow Co., B1375-2
Phillips, Getschow Co., 81375-1
Nutech, 81589 The NRC inspector also reviewed the following QA records to assure that the appropriate procedures were used during installation:
Weld Data Sheet
Visual Examination Check List (2)
Vent Header Deflector The modification consisted of the installation of 20 11 diameter pipe supported by 1 11 thick connection plates that are welded to the vent header support collar plate The deflectors shield the vent header from pool swell impact loads which occur during the initial phase of a OBA even The NRC inspector reviewed Phillips, Getschow C Fabrication Drawing No. B-1373-2AA to verify that the modification met the PUAR commitment The NRC inspector also reviewed the following QA records to assure that the appropriate procedures were used during the installation:
Weld Data Sheet
Magnetic Particle Inspection Report
..
(3)
SRV Quenchers The modification consisted of the installation of 2 - 12 inch perforated and end-capped stainless steel pipes, oriented along the torus bay longitudinal axis, at the ends of the ramshead, and the associated support The NRC inspector reviewed the following Phillips, Getschow Co., fabrication drawings to verify that the modifications met the PUAR commitments:
81370-2-AA
81370-2-88
81370-2-CC
81370-2-00
81370-2-EE The NRC inspector also reviewed the weld data sheet to assure that the appropriate procedures were used during the installatio (4)
Torus Attached Piping Penetration Stiffeners The modification consisted of pipe sections installed as sleeves to reinforce the penetration nozzles, with support arms extended radially from the pipe sleeves to pad plates attached to the suppression chamber shel The NRC inspector reviewed the Nutech Drawing M-3233-02 to verify that the modifications met the PUAR commitment The NRC inspector also reviewed the weld joint control traveler to assure that the appropriate procedures were used during the installatio (5) Torus Support Reinforcement This modification consisted of the addition of 16 saddle type supports welded to the torus shell, at the torus ring girder The NRC inspector reviewed the following QA records to assure that the appropriate procedures were used during the installation:
Drawings
NOE Reports - UT, MT, VT, PT 13 *
Master Checklist
Shop Checklist
Alteration Checklist Visual Inspection The NRC inspector inspected the final installation of the following modifications to the requirements of the design drawings:
(1) Vent Header Deflector (2) Torus Attached Piping Penetration Stiffeners (3) Torus Support Reinforcement Exit Meeting The inspector met with site representatives (denoted in persons contacted paragraph) at the conclusion of the inspectio The inspector summarized the scope and findings of the inspection noted in this repor The inspector also discussed the likely informational content of the inspection report with regard to documents of processes reviewed by the inspector during the inspectio The licensee did not identify any such documents/processes as proprietar