IR 05000373/1979002
| ML19282C276 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/08/1979 |
| From: | Hawkins F, Hayes D, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282C269 | List: |
| References | |
| 50-373-79-02, 50-373-79-2, 50-374-79-02, 50-374-79-2, NUDOCS 7903220466 | |
| Download: ML19282C276 (4) | |
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U.S. NUCL# ' REGULATORY COMMISSION
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OFFICE OF
.PECTION AND ENFORCEMENT
REGION III
Report No. 50-373/79-02; 50-374/79-03 Docket No. 50-373; 50-374 License No. CPPR-99; CPPR-100 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
La Salle County Station Units 1 and 2 Inspection At:
La Salle Site, Seneca, Illinois Inspection Conducted:
January 11, 1979
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Inspectors:
J. H. Neisler
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Approved By:
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Projects Section
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Inspection Summary
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Inspection on January 11, 1979 (Report No. 50-373/79-02; 50-374/79-03)
Areas Inspected: Licensee action on previous findings (Units 1 and 2);
status of reported 50.55(e) items involving containment tendon buttonhead
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cracking (Units 1 and 2) and RHR, HPCS, and LPCS pump deficiencies
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(Units 1 and 2).
The inspection was terminated because of adverse
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weather conditions. The inspection involved a total of 10 inspector-hours onsite by two NRC inspectors.
Results:
Of the three areas inspected, no apparent items of noncom-pliance were identified.
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DETAILS Persons Contacted Principal Licensee Employees L. J. Burke, Site Project Superintendent T. Quaka, Site QA Supervisor L. Tapella, QA Engineer M. Lohman, Field Engineer K. Steele, Field Engineer R. T. Rose, Project Structural Engineer Walsh Construction Company M. R. Dougherty, QA Supervisor Licensee Action on Previously Reported Items (Open) Reportel 10 CFR 50.55(e) item (373/78-XX-06, 374/78-XX-05): Cracks in Tendon Buttonheads exceed specifications.
Licensee investigation of the buttonhead splitting and its resolution is continuing.
In conjunction with this inspection, the RIII inspector reviewed the results of work completed to date.
The licensee had further extended the initial 5% inspec. ion for splitting of Unit I shop end buttonheads to include a minimum of 5% Unit 2 shop end buttonheads. Unit I and Unit 2 each contain a total of 308 tendons (188 horizontal and 120 vertical). Measurements of buttonhead dimensions using a Go-NoGo gauge and buttonhead splits / slips using both leaf and wire feeler gauges were performed by representatives in Inryco, Inc., Walsh Construction Company, Sargent and Lundy, and Commonwealth Edison Company in accordance with Inryco Specification 1610.
Go-NoGo gauge measurements were performed on Unit 2 shop end buttonheads with visual inspection being performed on Unit 1 buttonheads because of their inaccessability due to stressing.
To date, a total of 45 Unit I tendons have been inspected for shop end buttonhead size (visual) and crack influences.
This total included thirty "B" series vertical tendons and fifteen horizontal tendons.
Fourteen of these were found to be acceptable.
The remaining 31 tendons each contained varying numbers of buttonheads with splits greater than 0.060" and slips at 30 -45 greater than 0.002", and one tendoa contained one wire with an undersize buttonhead.
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Fifteen Unit 2 tendons were also inspected for shop end buttonhead size
(Go-NoGo gauge) and crack influences. All Unit 2 tendons inspected
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were A, B, or C series vertical tendons.
These tendons contained varying ngmbers of buttonheads with splits greater than 0.060", slips at 30 -45 greater than 0.002" and wires with undersize buttonheads.
On December 12, 1978, Commonwealth Edison personnel from La Salle performed an audit in Inryco, Inc.
As a result of the audit (#1-78-61),
Inryco suspended fabrication of post-tensioning tendons for all Commonwealth Edison nuclear projects.
This stop work order will remain in effect until mutual resolution of the deficiencies identified during the audit are arrived at.
Inryco, Inc., in conjunction with Commonwealth Edison Company, has developed a " Proposed Test Program for Buttonhead Split Criteria."
Tests specified in the proposed program will be performed on wire samples with buttonheads failing the Inryco Spec 1610 criteria.
Performance tests included as part of the Proposed Test Program include the following:
1.
Ninety wire tendon static tensile test in accordance with ACI/ASME Section III, Division II, Section CC2463.1.
2.
High cycle dynamic tensile test in accordance with ACI/ASME Section III, Division II, Section CC2463.2 using a 30 wire sample.
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Low cycle dynamic tensile test in accordance with ACI/ASME Section III, Division II, Section CC2463.3 using a 90 wire sample.
This item remains open and will be reviewed further during a subsequent inspection.
(Open) Reported 10 CFR 50.55(e) item (373/78-XX-03, 374/78-XX-04):
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Deficiencies in demensional tolerences on RHR, HPCS and LPCS pumps.
Licensee records show that deficiencies have been corrected on Unit 1 pumps. Unit 2 pump deficiencies are partially corrected and will be complete upon receipt of remaining parts from pump manufacturer.
Further review of this item will be performed during a subsequent inspection.
Functional or Program Areas Inspected 1.
Inspection of Constructien Activities During this inspection, the inspector toured the Unit 1 and 2 reactor buildings, control rooms, turbine buildings, fuel indling areas, and storage warehouses for safety related materials and components.
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In the Unit I reactor building the inspector observed cleaning n'
the reactor cavity and fuel pool. Work in this area is to completed this week with filling of the pool and cavity preiected to begin during the week of January 15, 1979.
The inspector noted that a barrier consisting of a chain link fence had been erected to isolate the fuel handling areas from the remainder of the plant. Access to the fuel handling areas was limited to authorized personnel only.
Entrances were locked or through gates guarded by personnel from the site security force.
Control rod and control rod drive components, safety related snubbers, and electronic and electrical equipment requiring controlled temperature storage are stored in heated warehouses.
2.
Meeting with Site Management The inspector discussed status of construction for Units 1 and 2 with site management.
Items discussed were:
a.
Replacement at thermal sleeves and safe ends, Unit 1.
The procedure for safe end blocking is available and current projections are that blocking of the safe ends for cutting will begin about January 22, 1979.
The cutting procedure has been submitted for approval.
The licensee plans to start cutting the safe ends on or about February 1.
b.
Turnover from station construction to station operations.
As of the date of the inspection, 35 turnover packages had been submitted by station construction, 23 packages had been reviewed by the Quality Assurance department, and 18 packages had been accepted by station operations.
c.
Diesel generator tests.
Standby diesel generator 1A has been operated, but as of this date the required diesel start tests identified in NRC Regulatory Guides have not been performed.
3.
Exit Interview Due to adverse weather conditions, it was necessary to terminate the scheduled inspection early; therefore, an onsite exit was not conducted. The Project Inspector discussed the inspection results with Mr. L. J. Burke, Site Project Superintendent, by telephone on January 17, 1979.
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