ML19305B660
| ML19305B660 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/28/1980 |
| From: | Crossman W, Gilbert L, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19305B649 | List: |
| References | |
| 50-416-79-29, 50-445-79-31, NUDOCS 8003200045 | |
| Download: ML19305B660 (1) | |
See also: IR 05000445/1979031
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U. S. NUCLEAR REGULATORY COMMISSION
0FFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-445/79-31; 50-446/79-29
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 and 2
Inspection at:
Comanche Peak Site, Glen Rose, Texas
Inspection conducted:
ecember 18-20, 1979, and January 15-18, 1980
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Inspectors:
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R". C. StewarE;%edctor Inspector, frojects Section
(Date '
(paragraphs 1, 2, 4, 5, 6 & 7)
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L. D. Gilbert, Reactor Inspector, Engineering Support
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Section (paragraph 3) (January 15-18, 1980, only)
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Approved:
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W. A. Crossman, Chief, Projects Section
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R. E. Hall, Chief , EngineeYing Support @ction
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Inspection Summary:
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Inspection on December 18-20, 1979, and January 15-18, 1980 (Report No.
50-445/79-31; 50-446/79-29)
Areas Inspc-*ed:
Routine, unannounced inspection of construction activities
including site tour; observation of work and review of records for Unit I
safety-related welding of Reactor Coolant Pressure Boundary piping; observation
of work and review of records and procedures related to protection of installed
safety-related components; and the review of records relative to protection of
the Unit 1 reactor vessel internals.
The inspection involved sixty-six inspector-
hours by two NRC inspectors.
Results: Of the five areas inspected, no items of noncompliance were found in
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four areas. One apparent item of noncompliance was found in one area (infraction -
failure to follow welding procedures
paragraph 3.a).
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DETAILS
1.
Persons Contacted
Principal Licensee Personnel
- J. George, TUSI, Project General Manager
- R. Tolson, TUGCO, Site QA Supervisor
- J. Merritt, TUSI, Engineer and Construction Manager
- D. Deviney, TUGCO, Operations QA Supervisor
J. Hawkins, B&R/G&H, QC Supervisor
R. Fleck, TUSI/G&H, Operations
Other Personnel
D. Doyle, B&R, QC Inspector
D. Lindhurst, B&R, Pipe Foreman
J. Cockfield, B&R, Millwright QC Inspector
H. Johnston, B&R, QC Electrical Inspector
R. Cormears, B&R, QA Surveillance Supervisor
The IE inspectors also interviewed other '.icensee and contractor personnel
including members of engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Site Tour
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The IE inspectors toured the Units 1 and 2 Reactor Buildings and Auxiliary
Building to observe construction activities in progress and to inspect
housekeeping.
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No items of noncompliance or deviations were identified.
3.
Reactor Coolant Pressure Boundary Piping
a.
Observation of Work
The IE inspector, in the process of observing the fit-up and alignment
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of a socket weld, identified as FW-13 on Drawing BRP-SI-1-RB-025,
Revision 1, noted that the type 308 weld material being used for tack
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welding was not of the type specified in the Welding Procedure Specifi-
cation (WPS) 88023, Revision 8, Interim Change Notice 1.
The WPS
specifies that type 316 weld material shall be used for welding type
316 base material to type 304 base material.
In the case of weld FW-13,
the valve is type 316 and the pipe is type 304.
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At the time of the inspection, no other Class 1 welds were being
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fit-up or welded in the area for observation by the IE inspector.
Failure to follow the WPS with respect to type of weld mater al
appears-to bs in noncompliance with the requirements of 10 CFR
Part 50, Appendix B, Criterion V.
b.
Review of Records
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The IE inspector selectively reviewed documentation of receiving
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inspections, welding material test reports, welder qualifications,
nondestructive tests, and QC inspection personnel certifications
for compliance with the ASME B&PV Code requirements for the following
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' Drawing
BRP-RC-1-520-1-2
W-1 and W-32
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BRP-SI-1-RB-056
W-11 and W-12
BRP-SI-1-RB-06-7
W-61
BRP-SI-1-RB-10-0
W-1
BRF-RC-1-RB-26-1
W-1
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No items of noncompliance or deviations were identified.
4.
Reactor' Vessel ~ Internals - Review of Quality Records
During this inspection, the IE inspector conducted a review of the B&R
record files relative to storage and maintenance of the reactor vessel
internals.
Documents included in the review were the B&R Procedure
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- QI-MCP-10.1, Revision 0, " Mechanical Equipment Storage Maintenance,"
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dated May 19, 1979; TUSI Procedure QI-QP-11.3.12; and Construction
Procedure MCP-10, "Scorage and Maintenance of Mechanical and Electrical
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Equipment," Revision 4, dated June 14, 1979. QA/QC inspection records
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reviewed included the period September 2, 1977, through December 4, 1979.
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It was observed by the IE inspector that inspection and maintenance
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requirements were conducted in accordance with the manufacturer'.-
reconsnendations and the licensee procedures.
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No items of noncompliance or deviations were identified.
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5.
Safety-Related Components - Observation of Work and Work Activities
During this inspection, the IE inspector conducted a walk-thru and
inspection of the Unit 1 Containment Building and Auxiliary Building
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to observe installation and prctection of safety-related components.
In addition to a general observation, the IE inspector selected four
motor control valves installed in the primary coolant system for specific
observation and records review.
Valves slected were: 12" GM 88SEH 0007A;
10" GM78FHN 0008A; 10" GM88FHN 0002B; and 10" GM78FHN 0007.
Observations
were made of each of the installed valves with a comparative review of
the requirements prescribed by B&R Construction Procedure, " Storage and
Storage Maintenance of Mechanical and Electrical Equipment," MCP-10,
Revision 4, dated June 14, 1979, and TUSI Procedure QI-QP-ll.3.31, dated
January 5,1980.
It was observed by the IE inspector that both mechanical
and electrical protection is being maintained in accordance with the pres-
cribed procedures.
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No items of noncompliance or deviations were identified.
6.
Safety-Related Components - Review of Quality Records
During this inspection, the IE inspector conducted a review of the licens-
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ee s records of inspection activities relative to the protection of safety-
related components after installation.
Inspection records were reviewed in
conjunction with requirements prescribed by B&R Procedure, " Mechanical
Equipment Storage and Maintenance," QI-MCP-10.1, Revision 0, dated May 19,
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1979, and TUSI Procedure QI-QP-ll.3.31, dated January 5,1980. Records
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selected for review included inspection records of components observed by
the IE inspector as having been installed in the Unit 1 Containment Building,
i.e., motor control valves No. GM88SEH 0007A, GM78FHN 0008A, GM88FHN 0002B,
and GM78FHN 0007.
The records reflect inspection activities were conducted
in accordance with procedural requirements.
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No items of noncompliance or deviations were identified.
7.
. Exit Interview
The IE inspectors met with licensee representatives (denoted in paragraph
1) and R. G. Taylor (NRC Resident Reactor Inspector) on January 18, 1980,
and summarized the purpose, scope and findings of the inspection.
The
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licensee representative acknowledged the statement and the item of concern
included in the details of paragraph 3.a.
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