IR 05000413/1980018
| ML19347B203 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/03/1980 |
| From: | Celey J, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19347B204 | List: |
| References | |
| 50-413-80-18, 50-414-80-18, NUDOCS 8010140034 | |
| Download: ML19347B203 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION
o y e REGION il - [[ g 101 MARIETTA ST., N.W., SUITE 3100 % ATLANTA, GEORGI A 30303 Report Nos. 50-413/80-18 and 50-414/80-18 Licensee: Duke Power Company 422 South Church Street i Charlotte, NC 28242 _ Facility Name: Catawba Nuclear Station Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Catawba site near Rock Hill, South Carolina Inspector: ( gfu 9-3-8O J.L? e Date Signed Approved by: C II ! O A. R. Herdt, Section Chief, RCES Branch Date' Signed
SUmfARY , Inspection on July 21-25, 1980 ' Areas Inspected This routine, unannounced inspection involved 36 inspector-hours onsite in the areas of safety related piping (Unit 1), safety related pipe welding (Units 1 & 2), material handling and storage, review of radiographic film (Units 1 & 2), and reactor coolant pressure bountry pipe welding (Units 1 & 2).
Results No items of noncompliance or deviations were identified.
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~ ~ . - . _ - -. - - -.. - . ~ - . i s ! ! DETAILS 1.
Persons Contacted l ' Licensee Employees
- R. L. Dick, Vice President Construction
- D. G. Beam, Project Manager D. L. Freeze, Project Engineer wJ. C. Shropshire, QA Engineer (QAE) Mechanical, Weldirg
- R. A. Morgan, Senior QA Engineer
- S. W. Dressler, Senior Construction Engineer D. Gadd, Welding Engineer l
D. Llewellyn, Welding Engineer
- L. R. Davision, Senior QC Engineer T. Mills, Supervisor Mechanical Engineer J. Turner, Supervisor QC Other licensee employees contacted included 10 construction craftsmen, and 2 technicians.
Other Organizations l
- J. W. Koska, Jr., Authorized Nuclear Inspector (ANI)
- C. F. Toegel, ANI J. Hrabosky, Westinghouse Representive
- Attended exit interview
, l l 2.
Exit Interview l , ! The inspection scope and findings were summarized on July 25, 1980 with l those persons indicated in Paragraph I above. The unresolved item discussed in paragraph 7.b was identified in the exit interview as a noncompliance.
The licensee was notified of the change on August 19, 1980.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve nonconpliance or deviations.
New unresolved items identified during this 'intpection are discussed in paragraph 7.a. and 7.b.
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5.
Independent Inspection Effort
! a.
Construction Progress (Units I and 2) , . The inspector conducted a general inspection of the Unit I and 2 con-i tainments, auxiliary building, pipe rabrication shop, Unit I and 2 turbine buildings and the fuel storage building to observe construc-tion progress and construction activities such as welding, filler
material handling and control, housekeeping and storage, b.
Reactor Coolant Pump Installation The inspector observed in process work on the installation of number 4 Main Coolant Pump.
Work was being accomplished in accordance with , ' Catawba Procedure CP-451, " Installation of the Reactor Coolant Pumps and Motors".
The inspector witnessed the heating and tightening of fasteners 11192, 11210, 11277 and 11209 during the second pass. These fasteners attach the pump casing to the main flange.
} Receiving Warehouse Outside Pipe and Fitting Storage c.
a The inspector performed a general inspection of the receiving warehouse i outside storage to observe storage conditions such as preservation, drainage slopes, unsatisfactory material segregation and marking and . l identification.
Within the areas examined there were no items of noncompliance or deviations
identified.
6.
Inspector Follow-up Item
l (Closed) Inspector Follow-up Item 50-413/80-02-01; Liquid Penetrant Developer , l Application S'.andards. This item concerns the licensee need for standardiza-l tion when applying a thin uniform coat of developer on welds under examination.
. The inspector observed an encased training mockup of metal plates with each plate having a varying degree of developer applied to their surface. These samples were then grouped into three categories: (1) test plates which were - ' rejectabl A.e to an insufficent coat of developer; (2) test plates which had a sat-.actory coat of developer were labeled acceptable; and (3) test plates whose developer application was to heavy, were designatea unaccept- . able. In addition the licensee had made a portfolio using photographs of the test samples.
Thh book was entitled " Liquid Penetrant Workmanship
Sample No. 1" and will be used as a future reference and training aid for ~ determining whether adequate developer has been applied in the area of , interest for bright or shiny metal surfaces.
This item is considered i closed.
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] 7.
Safety Related Piping Observation of Work and Work Activities (Unite 1 and 2)
j The inspector observed non-welding and welding activities for safety related ) piping out'ide of the reactor coolant boundary. The applicable code for ' installation of safety related piping is the ASME Boiler and Pressure Vessel Code,1974 edition plus addenda through summer 1974.
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. p 2 ___ ~ . ' -3-Observation on Non-Welding Activities a.
Observation of specific work activities were conducted to determine conformance, where applicable, with inspection and/or work procedures, installation specifications and drawings.
The followirg pipe runs were selected for inspection because interferences and insufficical clearances were noted in these installations: System / Component Class Size Procedure & Drawing Valve # 1 FW-47 B 8" Installation Inspec-tion Procedure M-8 Drawing Numbers CN-1680-48 R-4 l CN-1491-FW003 CN-1491-WL 047 Pipe Upstream of B 2" Procedure M-8 Dwg weld joint 1 BB-CN-1680-48 R-4 Dwg l 10-15 CN 1491-BB008 l The inspector observed an 8" diameter ASME Class B Refueling Water System Valve (1 FW-47) which when operated the valve position indicator i would contact a nonsafety related Class E liquid waste and recycle ! system pipe (1 WL-647-17). This interference prevented normal valve operation.
The inspector also noted a safety related ASME Class B steam generator blowdown & recycle system pipe (upstream of weld joint IBB-10-15) which was in contact with a nonsafety related Class E liquid waste and recycle system pipe (WL).
The inspector performed an installation inspection on both the safety . related ASME Class B piping and the non-safety related Class E piping.
' In both instances the liquid waste & recycle system pipe (WL) was not installed within the plus or minus 1 inch erection tolerance specified i
on dwg no. CN-1680-48 Rev. 4.
In addition to the pipe to pipe contact ' l and the valve to pipe contact the inspector noted through conve:3ations l with the licensee's design and stress analysis engineering personnel l that there are no procedural requirements that would insure a minimum ' i design pipe clearance should the safety related pipe experience thermal motion or a seismic event. The inspector also reviewed the licensee's Piping System Installation and Inspection Procedure M-8 which applied to ASME Class A, B, C, piping systems and procedure M-55 which applied i to Duke Class E piping systems. This review revealed that there were l no requirements to perform an installation inspection on Class E piping. The inspector also noted that with the exception of Class A piping, there were no procedural attributes to insure that valve operating interferences and inadequate pipe clearances would be in-spected on the final system / structure and mechanical walk through inspection. The licensee indicated that they would investigate fur-ther into the matter. The inspector stated that the above would be an unresolved item and identified as 50-413/80-18-01, 50-414/80-18-01; " Pipe Design and Inspection Clearance Requirements".
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Observation of Welding Activities The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various stages of weld comple-tion for the following weld joints: Joint Unit # Class Size Stage of Completion INS-29-9
B 8" sch.
Fitup 2RN-153-22
B 4" sch.
Fitup INV-200-9
B 3" sch. 160 Root Pass IWL-1225-5
C 4" sch.
Root Pass - INV-326-5
B 3" sch.
Root Pass 2RN-61-8
B 4" sch. 40 Fitup For the above welds, the inspector reviewed applicable weld data sheets, weld rod issue slips, welder qualification, weld identification, joint preparation and alignment. Welders were also questioned concerning the parameters of the welding procedure.
One welder who had completed the root layer for an ASME Class C weld joint 1 WL-1225-5 was observed when welding with a shielding gas flow meter that was not registering any flow.
Leakage could be observed across the seat of the flow meter and the weld appeared to be satis-fa cto ry.
When the welder set the flow meter on 12 CFH the shielding gas flow was too great to weld.
In addition the ball in the flow meter would not drop when the switch on the torch was released. The welding procedure required a minimum shielding gas flow of 15 CFH of argon.
The licensee's immediate corrective action was to have the flow meter replaced. The licensee is reviewing their procedures as it related to defective welding equipment and verification of welding procedure parameters prior to welding. This item will be identified as unresolved item number 50-413/80-18-02, " Verification of Welding Procedure Parameters Prior to Welding".
c.
Review of Radiographs (Units 1 & 2) The applicable ccie for radiography is the 1977 edition of the ASME Boiler and Pressure Vessel Code Section V Article I and 2 with addenda through summer 1978. The inspector reviewed radiographs of selected Class B welds to verify conformance to code and procedural requirements.
Radiographs and weld history sheets for the following welds were reviewed: Weld No.
Unit Size Class . INV-37-3
3"X.437" B 2NV-144-2
3"X.437" B 2NV-144-3
3"X.437" B 2KC-178-2
4"X.237" B . W
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3"y.437" B 2NV-142-2
3"X.437" B 2NV-84-9
3"X.437" B 2NV-153-6
4"X.237" B 2NV-154-9
3"X.216" B 2NV-147-5
3"X.437" B In the areas inspected, no items of noncompliance or deviations were identified.
8.
Reactor Coolant Pressure Boundary Piping (Welding) Observation of Work and Work Activities (Units 1 & 2) The inspector observed field welding of reactor coolant pressure boundary piping at various stages of weld completion.
The applicable code for reactor coolant pressure boundary pipe welding is ASME Boiler and Pressure Vessel Code, Section III, 1974 edition plus addenda through summer 1974.
In process field welds in various stages of f abrication were randomly selected for observation in order to determine whether welding, QC inspec-tion and NDE were consistent with code and procedural requirements. Welds selected for this work effort were as follows: Fabrication Weld No.
Size System Stage INC-190-11 6"X.718" Reactor Coolant Fitup INC-190-11 6"X.718" Reactor Coolant Root Layer INC-190-11 6"X.718" Reactor Coolant Final Layer 2NI-61-5 10" sch140 Safety Injection Fitup 1NC-43-3 1 1/2"X.351" Reactor Coolant Final layer . Within the areas examined, there were no items of noncompliance or deviations ' identified.
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