IR 05000249/1985025
| ML17195B017 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/05/1985 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17195B016 | List: |
| References | |
| 50-249-85-25, NUDOCS 8511140119 | |
| Download: ML17195B017 (10) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-249/85025(DRS)
Docket No. 50-249 Licensee:
Commonwealth Edison Company P. 0. Box 767 Chicago, IL 60690 License No. DPR-25 Facility Name:
Dresden Nuclear Power Station, Unit 3 Inspection At:
Dresend site, Morris, IL Inspection Conducted:
~
August 19-21 and October 15-18, 1985 Inspector:
Approved By:
W. J. Key J\\-~~~
~~-'Danielson, Chief Materials and Process Section Inspection Summary Date Inspection on August 19-21, 1985 and October 15-18, 1985 (Report No.50-249/85025(DRS))
Areas Inspected:
Unannounced, routine inspection of activities related to inservice inspection of piping systems and the replacement of IGSCC susceptible pipin This inspection involved a total of 54 onsite hours by one NRC inspecto Results:
No violations or deviations to NRC requirements were identified.
8511140119 851106 PDR ADOCK 05000249 G
- DETAILS Persons Contacted Commonwealth Edison Company (CECo)
- D. J. Scott, Station Manager
- J. Wujcica, Production Superintendent
- D. Aonm, Compliance Administrator
- W. Pietryga, Operating Engineer
- R~ A. Fuessner, Services Superintendent
- R. Hylka, ISI Coordinator
- W. Witt, NOE - III SMAD
- B. Wilson, NOE - SMAD
- T. Haaker, NDE - III SMAD
- M. Horbalzewski, NSD - QA
- D. Zoloty, QA LaSalle Station
- J. C. Renwick, RPR Assistant Superintendent
- P. Richardson, Project Manager
- D. Runner, Product Manager
- B. Schuetz, Sales
- C. Moreno, NDE Project Engineer
- R. Kusy, Supervisor, NDE Systems Hartford Steam Boiler and Insurance Company
- P. Fisher, INII Supervisor
- Denotes those attending the entrance and exit meeting **Denotes those attending the pre-outage meetin.
Inservice Inspection (ISI) Activities, Unit 3 General The licensee awarded the contract for ISI examinations and pre-service base line examinations to Combustion Engineering Incorporated for this refueling outag On October 15, 1985, a pre-outage meeting was held at Dresden sit The licensee, ISI contractor, the inspection agency and the NRC attended this meetin The examinations scheduled under the ISI program include the pre-service baseline examinations required on piping installed as part of the Recirculation Piping Replacement (RPR) program, augmented inspections on piping not being replaced, and the inspections required by NRC Generic Letter 84-1 *
- Scheduled Examinations The following scheduled examinations are to be performed in accordance with the Unit 3 Technical Specifications and Section XI of the ASME Boiler and Pressure Vessel Code, 1977 Edition Summer 1979 Addenda, and the second ten year program for Unit ISI Examinations Code Category B-D B-E B-G-2 B-J B-K-1 B-N-1 and 2 Code Category C-B Class 1 Parts To Be Examined 1. Recirculation inner radius and nozzle-vessel Weld (1 ea. 12
)
1. Neutron instrument penetration (2 ea.)
2. CRD nozzle penetrations (8 ea.)
Bolting 2 11 and smaller 1. CRD housing flanges (23 ea.)
Piping Circumferential Welds 1. CRD 4 11 (1 ea.)
2. SID cooling 14 11 and 16 11 (1 ea.)
3. ISO Condenser 14 11 (1 ea.)
4. HPCI 10 11 (1 ea.)
5. Main stream 6 11 (1 ea.) 8 11 (1 ea.)
11 (3 ea.)
6. Feedwater 12 11 (1 ea.)
7. SID cooling 16 11 BPC (1 ea.)
Integrally Welded Attachments 1. Recirculation (2 ea.)
2. SID cooling (1 ea.)
3. HPCI (2 ea.)
4. Main steam (2 ea.)
5. Feedwater (1 ea.)
Reactor Interior Attachments and Core Support Structure Class 2 Parts To Be Examined Nozzle Welds in Vessel 1. ISO condenser 8 11 and 12 11 (1 ea.)
Code Category C-F F-B B-C Augmented Inspections Parts To Be Examined Piping Circumferential Welds 1. Scram discharge volume 8 11 (2 ea.)
2. SID cooling 16 11 (1 ea.)
3. Core spray 12 11 (3 ea.)
4. LPCI 14 11 (1 ea.), 16 11 (1 ea.)
and 18 11 (6 ea.)
5. HPCI 10 11 (3 ea.), 14 11 (2 ea.), and
11 (1 ea.)
6. LPCI 18 11 BPC (2 ea.)
3A LPCI Heat Exchange Beam Supports 1. Scram discharge volume (4 ea.)
2. ISO Condenser (2 ea.)
3. Core spray (2 ea.)
4. LPCI (6 ea.)
5. HPCI (4 ea.)
6. Diesel Service Water (3 ea.)
(1)
UT feedwater nozzle bores, inner radius, and safe ends per NUREG-0619 (4 ea. 12 11 )
(2)
Recirculation piping replacement preservice base lin *
Recirculation system weld (34 ea. - 12 11 ), (10 ea. - 22 11 ),
(24 ea. - 28 11 )
LPCI system weld (3 ea. - 14 11 ), (2D ea. - 16 11 )
Shutdown coo 1 i ng system we 1 d (1 ea. - 8 11), (1 ea. - 12 11 ),
(7 ea. - 16 11 )
Cleanup system we 1 d (1 ea. - 6 11 ), (11 ea. - 8 11 )
A and 8 core spray system we 1 d (12 ea. - 10 11 )
Jet pump instrument safe end weld (4 ea. - 4 11 )
Component support integrally welded attachment *
Overhaul of M02-202-58 and 1501-26 (3)
Inspection of 3A and 38 recirculation pump suction splitter per G,E, Sil No. 415, Category (4)
__J
- *
Isolation condenser supply (5 ea. - 1411 )
A core spray (3 ea. - 1011)
B core spray (3 ea. - 1011)
Reactor head vent (3 ea. - 411)
Reactor head instrument (2 ea. - 611)
Reactor head spray (2 ea. - 611)
Reactor head spray (2 ea. - 611)
Inservice InsQection (ISI) Procedures Examinations scheduled for this refueling outage and RPR program are to be performed in accordance with the approved procedures listed belo These procedures were reviewed by the NRC inspecto *
NDT-B-1, Revision 2, dated March 1984, Magnetic Particle Examination For ASME Section XI Class IWB and IWC Components For Nuclear Station *
NDC-C-2, Revision 15, dated December 1984, Preservice and Inservice Ultrasonic Inspection of Similar and Dissimilar Metal Pipe Welds at Nuclear Station NDT-C-10, Revision 9, dated December 1984, Ultrasonic Inspection of the Inner Radius of the Nozzel-To-Vessel Junction at Nuclear Station *
VT-1-1, Revision 2, dated May 1985, Visual Examination-Welds, Pressure Retaining Bolting, and Component Internal *
VT-2-1, Revision 1, dated May 1985, Visual Examination-System Hydrostatic and Leak Test *
VT-3-1, Revision 1, dated May 1985, Visual Examination-Component Support *
VT-4-1, Revision l, dated May 1985, Visual Examination, Snubbers, Shock Absorbers, Spring and Constant Load Type Support *
DNT-C-30-79, Revision 0, dated July 1982, Ultrasonic Examination of Reactor Vessel Welds to NRC Regulatory Guide 1.150 for Boiling Water Reactor *
NDT-C-22, Revision 0, dated February 1984, Ultrasonic Examination of Cylindrical Forgings.
NDT-C-31-79, Revision 0, dated August 1982, Beam Spread and Refracted Angle Determination to NRC Regulatory Guide 1.150 for Boiling Water Reactor *
NDT-D-2, Revision 4, dated January 1983, Non-Aqueous Red Dye Liquid Penetrant Examination for Section XI Class IWB and IWC Components for Nuclear Station Combustion Engineering procedures for the base line examinations on piping systems being replaced by the RPR project have not been reviewed and approved by the license No violations or deviations were identifie.
Recirculation Pipe Replacement Project (RPR) General During the 1983 refueling outage for Unit 3 inservice inspection identified several welds in stainless steel pressure boundary piping with crack indications that were attributed to Intergranular Stress Corrosion Cracking (IGSCC).
Repairs to the identified welds were made by applying weld metal overlay to the outside surface of the weld and a section of the base material on each side of the wel In a letter from the NRC dated March 15, 1984, the licensee was ordered to submit plans for inspection and/or modification including replacement of the recirculation piping 90 days prior to the start of the next Unit 3 refueling outag The licensee committed to making permanent repairs by replacing the IGSCC susceptible piping, safe-ends, some drywell penetrations and portions of other systems with IGSCC susceptible piping during the fall 1985 Unit 3 outag Any piping not replaced would be examined in accordance with NRC Generic Letter 84-1 The licensee contracted Impell Corporation of Bannockburn, Illinois to design, plan, engineer and assist in the execution of the piping replacement activitie Chicago Bridge and Iron (CBI) was selected as the Installe A management team comprised of CECO, Impell and CBI personnel were organized to plan and execute the piping replacement activitie During May 1985 the licensee made a presentation to the NRC on the pipe replacement project detailing the project organization, schedule and the major contractors for accomplishing the work starting in October 1985 and extending through July 198 Selected stainless steel piping in the systems listed below are scheduled for replacement during this outage:
Reactor Recirculation (RRCI)
Shut Down Cooling (SOC)
Core Spray (COSP)
Control Rod Drive Return (CRD)
Jet Pump Instrumentation Flanges
Low Pressure Coolant Injection (LPCI)
Other replacement design items are being evaluated by Impell, these include the following:
(1) Snubber and Support Reduction (2) Safe End and Thermal Liner Replacement (3) Design Code Upgrade (4) Piping Configuration Upgrade (5) Existing Piping Insulation Specifications The IGSCC pipe replacement project plan requires that Impell prepare and issue the procurement specifications listed below:
(1) Material and fabrication specification for nuclear grade stainless steel piping and fitting (2) Material specification for structural steel for replaced and modified drywell structural stee (3) Material specification for replaced or modified pipe support (4) Material specification for small bore piping and tubing which is modifi~d or replace (5) Specification for recirculation system ventur (6) Material specification for replacement thermowell (7) Specification for containment bellow (8) Specification for onsite building (9) Specification for decontamination services and waste processin (10)
Specification for miscellaneous valve (11) Specification for replacement insulatio (12) Specification for waste disposa (13) Material specifications for other major items, as require (14) Specification for personnel and equipment interlock During the course of this inspection the NRC inspector selected the specifications listed below for review:
No. 0595-010-S-02, Revision 0, Specification for Seamless Nuclear Grade Stainless Steel Piping and Fitting *
No. 0595-010-S-29, Revision 1, Specification for the Dresden Unit 3 IGSCC Piping Replacement Project Welding Guidelin *
No. 0595-010-S-30, Revision 1, Guidelines for In-process Nondestructive Examinatio *
No. 0595-010-S-24, Revision 1, Specification for Testing, Inspection, and Nondestructive Examinatio *
Commonwealth Edison Company Standard Quality Article *
No. 0595-010-S-Ol, Revision 1, Specification for the Removal and Replacement of the IGSCC Susceptible Piping Dresden Station Unit Procedures Some procedures for the removal and installation of IGSCC related piping for Unit 3 have been developed, reviewed, approved and issued, others are still in the review and approval proces The NRC inspector reviewed the approved CBI procedures listed below for conformance to specifications, referenced codes, and NRC requirement Other contractors and their procedures will be reviewed during future inspection *
TARCUP, Revision 2 Temporary Attachment, Removal, and Cleanup
GR3N, Revision 1 Repair Procedure for Weld Root Nonconformities in Type 316NG Piping System *
MP-1, Revision 1 Marking Procedure for Location of Weld Root *
RH, Revision 1 General Rigging and Handling Procedur *
TA, Revision 0 Tool Accountabilit.
- .f I
"
RRPA, Revision 1 Field Removal of Loop 11A 11 Recirculation Pipin *
RIPS, Revision 0 Removal and Installation of Pipe Supports, Hangers, Whip Supports and Snubber *
SH9X, Revision 2 Packaging, Shipping, Site Storage and Control of Nuclear Product Item *
AP5, Revision 1 Radiography Procedure
PT14X, Revision 2 Liquid Penetrant Examination Procedure Color Contrast, Solvent Removal Wet Developer Class 1 Nuclear Product *
MTllX, Revision 3 Magnetic Particle Examination Procedure Continuous Yoke, Visible Particles Class 1 Nuclear.Product *
GWPS - GTAVJX, Revision 1 General Welding Procedure Specificati-0n for the Gas Tungsten Arc Proces *
CWP-C8B, Revision 1 Welding Qualification
CWP-C9, Revision 0 Materi a 1 Contro 1
CBI Nuclear Quality Assurance Manual for ASME Section III Products Revision 0, Addendum Number 1, Piping System Replacement and Associated Wor This addendum is divided into three sections covering CBI pipe replacement activities Section 1, applies to all project wo~ Section 2, limited to interference removal and replacemen Section 3, limited to customer directed wor Quality Assurance Program The licensee has established a corporate Quality Assurance program within the RPR organiiation to control activities performed by CECo during the pipe replacement projec Both site and corporate QA personnel are involve Corporate QA personnel are responsible for the review and approval of CBI and suppliers QA programs, pre-award
.
_,.
surveys, review of procurement documents and for performing audits of suppliers, Impell, CBI and site activitie Site QA personnel are responsible for the review and acceptance of CBI procedures, witnessing of inspection and hold points, review and acceptance of corrective actions of nonconformance reports and field change requests, review for acceptability of site initiated procurement documents, audit and surveillances of site activities, receipt inspection of CECo procurements and the maintenance of Quality Assurance record An audit schedule has been developed and implemented for auditing the RPR contractors for the duration of the projec.
Exit Interview The inspector met with licensee representatives (denoted in Persons Contacted paragraph) at the conclusion of this inspection on October 18, 198 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 or processes reviewed by the inspector during the inspectio The licensee did not identify any such documents/processes as proprietary.
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