IR 05000445/1979002
| ML19276E478 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/17/1979 |
| From: | Crossman W, Gilbert L, Randy Hall NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19276E476 | List: |
| References | |
| 50-445-79-02, 50-445-79-2, 50-446-79-02, 50-446-79-2, NUDOCS 7903140263 | |
| Download: ML19276E478 (6) | |
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U..S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-445/79-02; 50-446/79-02 Docket No. 50-445; 50-446 Category A2 Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name:
Comanche Peak, Units 1 & 2 Inspection at: Comanche Peak Site, Glen Rose, Texas Inspection conducted: January 8-10, 1979 Inspectors:
///7/79 L. D. Gilb'ert', Reactor Inspector, Engineering Date '
Support Section (Paragraphs 1, 2, 3, 4 & 8)
///7/79
[,-A.B'Rosenberg,ReactorInspector, Engineering
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Uate '
Support Section (Paragraphs 5, 6 & 7)
A. O. Ik4 1/37/74 A. B. Beach, Reactor Inspector, Engineering Date Support Section (Paragraphs 5, 6 & 7)
Reviewed: O s. 9?C N,( G n 0:
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R. G. Taylor, Resident Inspector, Projects Section Date Approved: 'Mff,9ddb9n -
/ /D/79 AtW. A. Crossman, Chief, Projects Section Date
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// Y ll/7l79
[mR. E. hah, Chief, Engirieering Support Section Date '
7903140263
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Inspection Summary:
Inspection on January 8-10, 1979 (Report No. 50-445/79-02; 50-446/79-02)
Areas Inspected: Routine, unannounced inspection of construction activi-ties including observation of work activities related to welding of reactor coolant piping (Unit 1); observation of work activities related to welding safety related piping (Unit 1); review of records related to safety related piping (Unit 1); observation of work activities related to containment concrete placements (Units 1 and 2); observation of work activities for containment penetrations (Unit 1); and review of records related to cable tray supports (Unit 1).
The inspection' involved sixty-nine inspector-hours on site by three NRC inspectors.
Results:
No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Employees
- R. G. Tolson, TUGCO, Site QA Supervisor
- J. V. Hawkins, TUGC0/G&H, Product Assurance Supervisor
- J. B. George, TUSI, Project General Manager
- D. E. Deviney, TUGCO, QA Technician Other Personnel
- H. O. Kirkland, Project General Manager, Brown & Root (B&R)
J. W. Field, Civil Inspector, B&R K. W. Silverthorne, Mechanical QC Supervisor, B&R R. C. Barber, Welding Engineer, Gibbs & Hill The IE inspectors also interviewed other contractor employees during the course of the inspection.
- denotes those attending the exit interview.
2.
Site Tour The IE inspectors walked through the various areas of the site to observe construction activities in progress and to inspect house-keeping.
No items of noncompliance or deviations were identified.
3.
Reactor Coolant Pressure Boundary Piping - Unit 1 The IE inspector observed the root weld of field welds FW-7 and FW-8, Drawing BRP-RC-1-520-2. These two butt joints are the connecting welds between the reactor coolant pump, pipe spool and~ reactor vessel for l oop 1.
The welds were made using the automatic gas tungsten-arc welding machine and WPS F99028R-1. The root welding was accomplished from the inside of the pipe.
It was verified that the welders were qualified to Section IX of the ASME B&PV Code.
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In the areas inspected for the two root welds, no discrepancies from the requirements of Section III of the ASME B&PV Code were noted.
No items of noncompliance or deviations were identified.
4.
Safety Related Piping - Unit 1 a.
Observation of Work The IE inspector observed the root weld of field weld FW-3A, Drawing BRP-CT-1-SB-11-0 and welding of the third pass on field weld FW-9, Drawing BRP-CT-1-SB-03-2 in the containment spray system. These welds were being made using the manual gas tungsten-arc welding process and WPS 88023R-4.
The same weider worked cn both joints and it was verified that he was qualified to Section IX of the ASME B&PV Code.
In the areas inspected, no discrepancies from the requirements of Section III of the ASME B&PV Code were noted.
No items of noncompliance were identified.
b.
Review of Records The IE inspector selectively reviewed the receiving records for three containment spray pipe spools and one residual heat removal pipe spool. The spool pieces were identified as CT-1-SB-16-2, CT-1-RB-46-1, CT-1-RB-28-6, and RH-1-SB-19-3.
The manufacturing documentation, piping material certifications, weld material certifications, and nondestructive evaluation records were reviewed and found to be consistent with Sections II and III requirements of the ASME BSPV Code in the areas inspected.
No items of noncompliance or deviations were identified.
5.
Containment Concrete a.
Containment Dome - Unit 1 The IE inspectors observed activities relating to concrete placenent in the containment dome (placement number 101-8805-10).
Specific areas observed included placement preparation as well as concrete placement techniques, concrete production tests, and batch plant activities.
Review of field records-4-
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for concrete temperature, air entrainment, and slump indicated that results were within the acceptance tolerances.
The areas inspected were found to be in accordance with Gibbs and Hill Specification 2323-SS-9.
The IE inspectors also observed concrete curing activities relative to a concrete placement in the containment dome (placement nurnber 101-8805-09). The inspectors reviewed the Daily Curing Verification Reports and discussed the curing procedures with the civil inspector in charge of curing activi-ties. All observed activities were found to be in accordance with Brown & Root Procedure QI-QP-ll.0-11, " Cold Weather Concreting."
b.
East Containment Walls - Unit 2 The IE inspectors observed activities relating to a concrete placement in the containment interior wall (placement number 201-4812-002). Concrete placement preparation activities were observed, as well as concrete placement techniques and concrete inspection activities during placement.
Testing at the placement location was observed to meet acceptance criteria.
Inspection activities observed were found to be in accordance with the Brown & Root Procedure QI-QP-11.02.
No items of noncompliance or deviations were identified.
6.
Cable Tray Support - Unit 1 The IE inspectors reviewed welding and fabrication records relative to cable tray support No. 2513 for the Unit No. 1 Safeguards Building.
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Records reviewed included:
Inspection Reports Weld Material Control Records Welder Qualification Records Inspector Qualification Records QC Surveillance Records QA Surveillance Records-5-
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Records reviewed did not reveal any discrepancies with the Gibbs and Hill Specification 2323-SS-16B.
No items of noncompliance or deviations were identified.
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7.
Containment Penetration - Unit 1 The IE inspectors observed preparations for final visual inspection and RT of weld FW-40 on a piping penetration in the containment liner (line MII-4). Wald Data Card 05953 was reviewed.
The observed activ-ities were found to be in accordance with the Brown & Root Welding Procedure 11010, Rev. 2.
No items of noncompliance or deviations were identified.
8.
Exit Interview The IE inspectors met with licensee representatives (denoted in para-graph 1) and R. G. Taylor (NRC Resident Inspector) at the conclusion of the inspection on January 10, 1979.
The IE inspectors summarized the purpose, and scope of the inspection and their findings.
The licensee representatives had no questions regarding the areas in-spected.
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