ML20211F578
| ML20211F578 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 01/27/1978 |
| From: | Crossman W, Randy Hall, Tapia J, Renee Taylor NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20150F241 | List:
|
| References | |
| FOIA-85-378 50-498-78-01, 50-498-78-1, 50-499-78-01, 50-499-78-1, NUDOCS 8610310203 | |
| Download: ML20211F578 (6) | |
See also: IR 05000498/1978001
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U. S. NUCLEAR REGULATORY C0!WISSION
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0FFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
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Report No. 50-498/78-01; 50-499/78-01
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Docket No. 50-498; 50-499
Category A2
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Licensee: Houston Lighting and Power Company
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Post Office Box 1700
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Houston, Texas
77001
Facility flame: South Texas Project, Units 1 & 2
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Inspection at:
South Texas Project, Matagorda County Texas
Inspection conducted:
January 10-13, 1978
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Inspectors:
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"*R.' G.'Taylorf, Reactor Inspector, Projects Section
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(Paragraphs 1, 2, 3 & 6)
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Afd. I. Tapia, Reactor Inspector-Intern, Engineering
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Support Section (Paragraphs 4 & 5)
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Other
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Accompanying
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Personnel:
W. A. Crossman, Chief, Projects Section~
W. G. Hubacek, Reactor Inspector, Projects Section
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Approved:
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I W. A. Crossman, Chief,pProjects Section
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R. E. Hall, Chief Engineering Support Section
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8610310203 860930
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GARDE 85-378
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Inspection Summary:
Inspection on January 10-13,1978 (Report No. 50-498/78-01; 50-499/78-01)
Routine, announced inspection involving follow up on status
Areas Inspected:
of structural steel column repair activities; review of material properties in
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Unit 1 containment liner; observation of concrete placecent activities in Units
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1 and 2;'and review of records of concrete placements for Unit 1.
The inspection
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involved fifty-one inspector hours by two NRC inspectors.
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Results: Of the five areas inspected, no items of noncompliance or deviations
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were identified in four. Two apparent items of noncompliance (two infractions -
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failure to follow procedures for concrete placements) were. identified.
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DETAILS
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Persons Contacted
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Principal Licensee Personnel
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- W.* N. Phillips, Project Quality Assurance Manager
- S. A. Viaclovsky, Site Quality Assurance Supervisor
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- L. D. Wilson, Lead Quality Assurance Specialist
- T. K. Logan, Lead Quality Assurance Engineer
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R. A. Frazar, Manager-Quality Assurance
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- F. D. Asbeck, Construction Supervisor
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D. G. Long, Quality Assurance Engineer
D. Douglas, Quality Assurance Engineer
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Other Personnel
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- C. L. Crane, Brown & Root Construction Project Manager
- T. Schreeder, Jr., Brown & Root Quality Control Supervisor
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T. J. Foley, Pittsburgh-Des Moines Site QA Manager
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J. G. Munisteri, Brown & Root Senior Vice President
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T. H. Gammon, Brown & Root Quality Assurance Manager
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- denotes those attending the exit meeting.
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2.
Containment Liner Materials - Unit 1
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The IE inspector randomly selected six (6) containment liner plates as
indicated below from the cylindrical portion for examination of certified
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material test reports and other applicable site documents. The plates
selected were from rings nine through seventeen since randomly selected
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platesinphefloorandthefirsteightringshadbeenpreviouslyThe certified mate
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examined..I.
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and physical properties of each plate complied with the requirements of
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SA-285 for Grade A material as required by project specification
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2C269SS006F, " Steel Liner Work for Reactor Containcent Structures," and
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as allowed by ASME,Section III, Division 2 in Table 1-2.2 which in turn
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is referenced in paragraph 3.8.1.2.1 of the PSAR.
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Plate Identification
Material Identification
Mill Heat Number
I706
802W66380
2058-5
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22510-8
1736
822W50670
24512-11
1767
802X67350
26514-13
1816
802X79290
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1/ Inspection Report 50-498/77-01; 50-498/77-05
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28516-8
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802X79290
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29517-7
6781
802A59730
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No items of ncncompliance or deviations were identified in this area
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of the inspection.
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3.
Structural Steel Coluen Repairs - 10 CFR 50.55(e) Item
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The inspector reviewed the status of repair work relative to the
structural steel columns fabricated by.LAMCO for use in the steam
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generator and reactor coolant pump support systems. The technical
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aspects of the repairs were reported in the licensee's letter dated
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November 11, 1977, to RIV.
IE inspectors reviewed applicable repair
procedures and observed the work during inspections 50-498/77-11 and
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50-498/77-13.
During this inspection, it was found that weld defects,
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incurred in the original fabrication, have been removed from all nine-
teen columns involved.
Repair welding and nondestructive examinations
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have been completed on fifteen of the columns with fourteen having re-
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ceived a final post weld stress relief. The inspector had no further
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questions on this matter.
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Concrete Placement Activities
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The inspector observed the consolidation of one lift of' pumped concrete
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in placements No. FH1-W20 and FH2-W8. Both placements are interior
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walls in the respective Unit 1 and Unit 2 Fuel Handling Buildings.
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Consolidation of the concrete was being performed by 3 inch diameter
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internal vibrators with a minimum frequency of 9,000 hertz.
The distance
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between insertions of the vibrators was observed to be in excess of the
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2-1/2 feet required by Brown & Root quality control procedure STP-QCp-4.4,
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April 1,1976, " Concrete Inspection." (This procedure invokes American
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Concrete Institute Standard ACI-309-72, " Recommended Practice for
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Consolidation of Concrete," which states in section 7.1, " Procedure
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for Internal Vibration,""that the distance between insertions should
generally be about 1-1/2 times the radius of action." The radius of
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action is defined in Table 5.1.4 of ACI-309-72.
For the given vibrator
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diameter and frequency, the radius of action is 20 inches. Therefore,
the recommended distance between insertions is 30 inches or 2-1/2 feet.)
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During the placement of the first lift of concrete in placement No.
FH2-WS, the Brown & Root quality corttrol inspector indicated that the
acceptance criteria for internal v'ibrator spacing was from 4 to 5 feet.
He was unaware of the requirement for vibrator spacing contained in the
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construction and quality control procedures. This confinted the obser-
vation made by the NRC inspector of vibrator spacing of up to four feet.
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The average daily temperature during placement No. FH2-WD was 40 digrees
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Fahrenheit. The ambient temperature as observed by the inspector at the
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commencement of the placement was approximately 35 degrees Fahrenheit.
The Brown & Root construction procedure No. A040KPCCP-4, Revision. 3,
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requires that if the ambient temperature is from 30 to 45 degrees Fahren-
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heit, the minimum temperature of the concrete when delivered to the pour
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location must be at least 50 degrees Fahrenheit. The first Concrete Test
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Load Ticket No. 03680, indicated a concrete temperature at pour location
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of 46 degrees Fahrenheit. The concrete was placed. Upon notification
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by the inspector, the licensee issued a Deficiency Report.
These findings
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represent noncompliance with the requirements related to the accomplish-
ment of activities affecting quality in accordance with documented proce-
dures. Specifically, these findings represent noncompliance with the
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conditions of Criterion V of Appendix B to 10 CFR 50.
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Review of Concrete Records
A review was conducted of quality assurance records relative to place-
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ment No. CSI-W7.
This placement is the seventh 10 foot lift in the
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Unit 1 containment from elevation +47 feet to +57 feet. The following
records were reviewed:
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Curing Inspection Card
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Concrete Inspection Books (4)
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Special Pre-pour Checklist and Pour Card
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Post-tensioning Sheathing Inspection Report
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Concrete Test Load Tickets (12)
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Daily Batch Plant Operation Report
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Batch Record Summary
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Moisture Content of Aggregates Reports (6)
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Moisture Adjustment and Batch Weights Reports (3)
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Batch Plant Equipment Inspection Report
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Field Testing Summary
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The records reviewed appeared to be consistent with project specifi-
cations 2A01C5001-F, " Concrete Supply," and 2A010CS028-E, " Concrete
Construction."
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No items of noncompliance or deviations were identified.
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6.
Exit Interview
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The inspectors met with licensee representatives (denoted in paragraph
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1) at the conclusion of the inspection on January 13, 1978. The in-
spectors summarized the scope of the inspection and their findings.
The licensee representatives acknowledged understanding the findings
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but' made no commitments. Mr. W. G. Hubacek was introduced to the
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licensee representative as the replacement for Mr. Taylor as the
Project Inspector for the South Texas Project effective on January 16,
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1978.
It was explained that the assignment changes were being made
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in accordance with IE policy governing duration of such assignments.
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The licensee was requested to direct all infonnal contacts to Mr. Hubacek
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effective immediately.
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