IR 05000445/1981013
| ML20031D019 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/15/1981 |
| From: | Randy Hall, Clay Johnson, Roberds J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031D007 | List: |
| References | |
| 50-445-81-13, 50-446-81-13, NUDOCS 8110090215 | |
| Download: ML20031D019 (6) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION OFFICF 0F INSPECTION AND ENFORCEMENT
REGION IV
Report: 50-445/81-13; 50-446/81-13 Dockets: 50-445; 50-44'3 Category A2 Licensee:
Texas Utilities Generating Company 2001 Brysa Tower Dallas. Texas 75201 Facility Name:
Comanche Peak, Units 1 and 2 Inspection at:
Comanche Peak Site, Glen Rose, Texas Inspection Conducted: August 17-25 and September 1, 1981 Inspector:
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h_C.E. Johnson,ReactorInspector,Engineeringandhaieriais Dite'
Section (Paragraphs 1. 2, 3.a, 3.b, 3.c, 3.d, 3.e, 4, & 5)
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- p. Roberds, Reactor Inspector Aide, Engineering and Materials Dste'
Section (Paragraphs 1, 2, 3.a, & 3.e)
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Approved: g R. E. Hall, Acting Chief, Engineering and flaterials Section Vate Inspection Summary Inspection Conducted August 17-25 and September 1, 1981 (Report No. 50-445/81-13 50-446/81-13)
Areas Inspected:
Routine, unannounced inspection of construction activities including a site tour and observation of work and review of records for safety-related pipe support and restraint systems in Unit 1.
The inspection involved 42 inspector-hours by one NRC inspector and 36 inspector-hours by one NRC inspector aide.
Results:
No violations or deviations were identified.
6.10090215 810921 FOR ADOCK 05000445 O
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DETAILS 1.
Persons Contacte_d v
Principal Licensee Personnel
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- R. G. Tolson, Site QA Supervisor Other Personnel
- J.-V, Hawkins, Project QA Manager, Brown & Root (B&R)
- J. T. Merritt, Manager, Engineering & Construction, TUSI J. P. Patton, QC Mechanical Superintendent, B&R
j G. Willis, ASME QC Mechanical Senior Superintendent, B&R J. Ragan, QE Manager, B&R
l R. Michels, QA Specialist Supervisor, TUGC0 M. Welch, Quality Engineering, TUGC0
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T. Hood, DCC Supervisor, B&R
R. Stepp, Warehouse Foreman, B&R R. Williams, Drafting Supervisor, B&R
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The NRC inspector also interviewed other licensee and contractor
employees during the course of the inspection.
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- Denotes those attending the exit interview.
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2.
Site Tour l
The NRC inspector toured the Units 1 and 2 Reactor Buildings, Safeguards Buildings, and Auxiliary Building to observe construction in progress and
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j to inspect housekeeping.
No violations or deviations were identified.
l 3.
Safety-Related Pipe Support and Restraint Systems _
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Review of Procedures t
The NRC inspector reviewed applicable procedures to ascertain whether
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procedures and instructions pertaining to safety-related pipe supports i
were approved by authorized licensee personnel.
All procedures re-j viewed by the NRC inspector were approved by authorized licensee
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personnel.
The '.iRC inspector also determined that the procedures i
reviewed establ'shed the technical adequacy of activities pertaining
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to safety-related pipe supports.
fhere were several procedures that j
gave tables, charts, illustrations, and tolerances for different
type supports.
Procedures reviewed by the NRC inspector are listed i
below:
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QI-QAP-ll.1-28, Rev. 7, " Inspection of Installation of ASME l
Component Supports, Class 1, 2, & 3"
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CP-CPM-9.10, Rev. 3, " Fabrication and Installation of ASME -
Related Components Supports" CP-CPM-9.14, Rev. 0, " Installation of Pipe Supports Containing Lubrite Plates"
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CP-CPM-9.9, Rev. O, "NNS -' Seismic Category II Supports" CI-CPM-6.10-1, Rev. O, " Inspected Item Removal Notice for Component Supports" CPM-9.ll, Rev. O, " Verification of Upset Threads in NPSI -
Supplied Sway Struts" CP-CPM-9.12, Rev. 0, " Reinstallation of Spherical Bearings on Sway Struts and Snubbers" CP-QAP-15.1, Rev. O, " Field Control of Inspection Status of Items and Materials" CP-QAP-18.05, Rev. O, " Inspection Reports" QI-QAP-11.1-33, Rev. 0, " Pre-Turnover Walkdown Inspection Criteria" No violations or deviations were identified.
b.
Observation of Work The NRC inspector toured the warehouse yard to examine the storage conditions of the dynamic pipe ~upports.
The QA related supports were stored inside a warehous
? NRC inspector selected a total of ten mechanical snubbers of different load classifications, and checked shaft travel for smoothness by simulating normal operation by pulling and pushing the snubber shaft; also simulated unit activation by sudden movement.
The NRC inspector checked the stroke length of each particular size snubber.
The NRC inspector also visually examined other component supports in the warehouse.
There are no hydraulic snubbers utilized at this facility.
The NRC inspector toured the construction area and visually examined at random completed pipe supports in the safety-related areas.
The NRC inspector noticed that there were many sway strut supports that needed adjustments.
Brackets on the pipe support clamps examined were not parallel to each other as required by procedure.
The NRC inspector questioned the type of measures used to control the proper adjustments and settings on pipe supports after completion and sign off by QC.
The licensee had previously identified this as a problem and informed the NRC inspector that they were in the process of incorporating the verification of inspection of Class 1, 2, and 3 pipe supports into Procedure QI-QP-11.13-1, Rev. 1, "As-Built Piping Verification Instructions." This procedure will encompars the-3-
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verification of correct pipe v.pports, adjustments, and correct load settings.
The licensee also informed the NRC inspector and Resident Reactor inspector that Class 5 pipe supports would also be addressed in Procedure QI-QP-ll.13-1, Rev. 1.
This procedure is being revised to incorporate these changes, however, it has not been completed to date.
This, item will be listed as an unresolved item until a subsequent inspection is performed in this area.
The NRC inspector also identified a spring hanger support that did not conform to the design drawing.
Af ter inquiring about thit
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matter, the licensee informed the N C inspector and the Resident Reactor inspector that this support had been voided, but later informed the NRC inspectors that it would be utilized.
QC had not signed off on the hanger package because of the incompleteness.
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However, there was a discrepancy in the numbering system of the
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support.
The number on the support is CT-1-038-018-C525, whereas the licensee states that NPS records show it to be CT-1-038-418-C57.S.
l This item will also require additional information and will be listed
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as an unresolved item.
c.
Verification of As-Built Condition The NRC inspector randomly chose five completed as-built design drawings from the Drafting Section and examined the hanger package l
contents.
Hangers examined are listed below:
j CC-1-143-701-E63R, Component Water Cooling System l
CC-1-143-705-E63R, Component Water Cooling System CC-1-087-008-A33R, Component Water Cooling System
CC-1-068-Oll-S33K, Component Water Cooling System CC-1-146-Oll-543R, Component Water Cooling System Upon completion of review of the hanger packages, the NRC inspector visually verified that the as-built conditions were comparable to the as-built design drawings.
The fillet weld requirements, contained on the individual pipe hanger drawings attached to the Multiple Weld Data Card, were compared by the NRC inspector to those found on the completed pipe supports in the field.
Weld sizes were also measured by the NRC inspector.
No violations or deviations were identified.
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d.
Review of Records j
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The NRC inspector selected a total of ten completed hanger packages.
Each package contained individual pipe support records.
The hanger packages reviewed are listed below:
' CC-1-120-001-A43R, Component Water Cooling System AF-1-009-017-533R,_ Auxiliary Feedwater System FW-1-105-005-562R, Feedwater System AF-1-001-702-533R, Auxiliary Feedwater System -
AF-1-001-701-533R, Auxiliary Feedwater System BR-X-027-001-A53R, Boron Recycle System FW-1-095-002-C62R, Feedwater System
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FW-1-98-002-C62R, Feedwater System
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FW-1-096-037-C62R, Feedwater System FW-1-099-005-C625, Feedwater System The records reviewed contained all forms and documents required by procedure, such as the Multiple Weld Data Card and the Material Identification Log.
The records also specified the type and classification of the support or restraint system, and did comply with appropriate drawings.
The location and spacing met licensee's specifications and were verified by QA/QC.
Welding material used corresponded with the Material Identification Log.
The records confirmed that the specifications and installation procedures and the required scope of QA/QC inspections were met.
No violations or deviations were identified.
i e.
Welder Qualifications In conjunction with a visual inspection and examination of ASME Class II and III component supports, the NRC inspector conducted a review of the applicable records relative to Welding Procedure Specification (WPS) and Welder Performance Qualification records.
As a result of the review of the Welder Performance Qualification records, it was noted by the NRC inspector that a cross reference of the welder's symbol to the identity of the welder, who was not listed on the current Welder Qualification Matrix was not readily available in the records vault.
However, records of all assigned symbols relative to welder's identification were maintained in the
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Welding Engineering office.
Even though there was no procedure designating storage area, the NRC inspector and Resident Reactor inspector indicated to the licensee that a cross reference of welder's identification and their assigned symobls should be main-tained in the records vault to assure traceability.
The licensee agreed to develop a cross reference of welder's identification and u
their assigned symbols and maintain them in the records vault.
The NRC inspector reviewed Weld Procedure No. 11032 and six Welder Performance Qualification records, relative to essential variables.
Those items reviewed by the NRC inspector were found to be in com-pliance with Section IX of the ASME Boiler and Pressure Vessel Code.
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No violations or deviations were identified.
4.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations.
Two unresolved items are identified in
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paragraph 3.b.
2 5.
Exit Interview
An exit interview was conducted September 1, 1981, at the Comanche Peak site with personnel denoted in paragraph 1 and R. G. Taylor (NRC Resident
Reactor Inspector).
At this exit interview, the NRC inspectors summarized
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the scope of the inspection and their findings.
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