IR 05000373/1980029
| ML19332A772 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/25/1980 |
| From: | Erb C, Neisler J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19332A768 | List: |
| References | |
| 50-373-80-29, 50-374-80-18, NUDOCS 8009180280 | |
| Download: ML19332A772 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Reports No. 50-373/80-29; 50-374/80-18 Docket Ncs. 50-373; 50-374 Licenses No. CPPR-99; CPPR-100 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: LaSalle County Station, Units 1 and 2 Inspection At: LaSalle Site, Marsailles, IL Inspection Conducted: July 8-10, 1980 l.tc 4 D8 d /f N Inspectors:
J. H. Neisler
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C. C. Williams, Chief NJ/ M / ffa Projects Section 2 f ~[
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Inspection Summary Inspection on July 8-10, 1980 (Reports No. 50-373/80-29; 50-374/80-18)
Areas Inspected: Unit I suppression pool weld NDE. Observation of work inside Unit 2 RPV. T.I.P. system welding Unit 1, Unit 1 RPV holddown bolts.
Licensee action relative to 10 CFR 50.55(e) items, unresolved items, and IE Bulletins. Observation of work activities involving electrical components, Unit 2.
The inspection involved a total of 40 inspector hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified during this inspection.
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DETAILS Persons Contacted
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Principal Licensee Employees L. J. Burke, Site Project Superintendent
- T. E. Quaka, Site QA Supervisor
- G. E. Groth, Station Construction R. T. Rose, Lead Structural Engineer K. Steele,, Lead Electrical Engineer
- E. Wendorf, Station Construction
- L. H. Tapella, QA Engineer
- D. J. Skoza, QA Engineer
- J. W. Gieseker, Station Construction R. Prince, QA Weld Engineer Contrattor and Other Personnel R. Ouzts, QA Manager, HP Foley Company J. Courtney, Site Manager, Reactor Controls, Inc.
H. Phillips, QC Supervisor, Reactor Controls, Inc.
R. Spencer, Internals Supervisor, Reactor Controls, Inc.
V. Trickle, QA Supervisor, Chicago Bridge and Iron M. Wherry, QC Supervisor, Morrison Construction Co.
Licensee Action on Previously Identified Items (Closed) Unresolves item (50-373/79-13-03) Site system turnover procedures.
Revision 7, dated April 11, 1980 of procedure LSU 100-2 " Release for Pre-op Testing" requires the closure or acceptable disposition of all holds, NCR's and unresolved items for contractors and licensees. Each turnover package is firct reviewed by the cognizant construction engineer and then by a quality assurance engineer. Deficiencies are recorded and inserted in a computer punch list. When the deficiency is cleared, an input to the computer removes that deficiency from the punch list. This item is considered closed.
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(Open) 10 CFR 50.55(e) item (50-373/79-XX-02) Laminations in A588 grade B steel plate in bottom ring of plant exhaust stack. Affected ring and suppvii.
ring have been replaced. Welds have been nondestructi::17 ::::incd eithar UT, MT, or RT depending upon their locations and code requirements. Three
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welds were rejected by NDE personnel and are not yet repaired. This item remains open pending repair and acceptance of the three rejected welds.
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Section 1 Prepared by J. H. Neisler
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Reviewed by C.'C. Williams, Chief Projects Section 2 Electrical Components Unit 2 4160 Volt Switchgear The 4160 volt switchgear observed during this inspection had been installed and energized prior to the inspection. The inspector reviewed receiving inspection reports, installation records, and inspection checklists for panels 2AP045, Bus 241Y and 2AP06E, Bus 242Y, division 1 and division 2 respectively. Test reports on_ hand include physical and electrical quali-fication tests. Report of seismic data is on site. Records indicate that the test included the panel with circuit breakers and accessories installed.
The seismic test reports have been reviewed and accepted by the architect /
engineer.
480 Volt Switchgear The inspector visually inspected the installation of 480 volt motor control centers 2AP20E, Bus 235Y and 2AP22E Bus 236Y. Termination of cables in the 480 volt switchgear area was in progress at the time of the inspection.
Workmen were using the proper size and type of strippers, lugs, and crimpers.
Calibration stickers on the crimpers indicated that calibrations were current.
The inspector reviewed receiving inspection reports, installation records, and inspection checklists for the 480 volt switchgear. Test reports on site include physical and electrical qualification tests.
The 480 volt unit substation transformers 235Y and 236Y documentation package includes test data for short circuit tes'g ippulse test, insulation tests, and high potential tests. The report of seismic tests has been reviewed and accepted by the architect / engineer.
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Diesel Generators Unit 2 The inspector observed installation activities involving the Unit 2 diesel generators. Diesel generator 2DG01K was selected for documentation review.
Documentation reviewed by the inspector included receiving inspection report, quality records, high potential test results, insulation resistance test
~(megger) results,' factory tests, and-starting tests. The unit has been
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factory load tested at 100%'and 110% loads. Documentation of the starting reliability tests show.that the unit has been tested to 300 starts.
No items of noncompliance or deviations were identified in the above area.
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Inspection and Enforcement Bulletins
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IE Bulletin 79-14' Seismic Analysis for As-Built Safety Related Piping Systems.
Licensee has submitted response to the bulletin'. Additional information was requested by NRR under the program of performing an independent confirmatory
"as-built" piping analysis for each plant undergoing an operating license review. Per letter Olin-Parr (NRR) to D. L. Peoples (CECO) dated November 15,-
1979, the analysis for LaSalle will be performed by Oak Ridge National Laboratories. Additional information requested by NRR has been submitted by'the licensee. No further action by Region III inspectors is anticipated.
This bulletin is considered closed.
- IE Bulletin 80-08 Examination of Containment Liner Penetration Welds.
Licensee's response states that penetrations of the flued head design are used in LaSalle. This was verified by the inspector. The applicable code for LaSalle penetrations in the ASME 1970 code with no addenda. All butt welds.were radiographically examined. Review of CB&I radiography reports for Unit'l indicate that all final welds meet code requirements. The inspector's review of reader sheets and RT reports of NDE performed on Unit 2 indicate that penetration butt welds meet the 1974 code requirements.
This bulletin is considered closed.
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O Section II Prepared by C. M. Erb
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Reviewed by D. H. Danielson, Chief Engineering Support Section 2
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1.
Suppression Pool - Unit I NDE records for CBI work on the suppression pool wall plates were a.
examined. The welds were identified as to procedure and welder together with the NDE performed. Vacuum Box, Penetrant Test and radiography where possible were indicated. The records also indicated if repair were required.
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Radiograph for welds No. E and F, elevation 686' and 684' were examined and found to be acceptable to ASME Code Class-MC.
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At the present time, there are 13 qualified welders to Section IX ASME Code. The RT procedure used was RT-2X revision 1 and the base material is 1/4" thick welded froe both sides.
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Welds to the KWU Quencher were made by Morrison, as were the base plate to base welds. These welds had a satisfactory appearance and were of stainless steel to stainless steel base metals.
A backing ring was used with weld from one side only. The NDE consisted of Penetrant Examination and visual on the root and final weld.
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Records on welds No. 3823 and No. 3827 welded to Procedure P8-19LS and with visual by 13L2 and Penetrant Test by 10L2 were examined.
No items of nonconformance or deviations were identified.
2.
Traveling in Core Probes - Unit 1 There are five drive units for the T.I.P. System. Each T.I.P. utilizes a carbon steel 1 1/2" X.145 wall pipe to penetrate the biologic shield.
Radiographs of welds No. 42 through 46 inclusive, which are the first welds outside the biological shield in 1 1/2" pipe were examined. All had acceptable welds to ASME Code except No. 46 which had been rejected and was to be repaired. These welds are made using the GTAW process.
No items of noncompliance or deviations were identified.
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NDE for Scram Discharge System - Unit 2 i
j Radiographs for FW32RI, and FW31 in 8" X.500 wall carbon steel scram l
discharge pipe were examined and found to be acceptable.
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.These welds were produced by Reactor. Controls, Inc. (RCI) and radio-graphed to Procedure RT-2-NP Revision 0 by con Am.
The welds meet.
the radiographic requirements of ASME Section III 1974 edition, summer 1975 addenda.
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No items of noncompliance or deviations were identified.
4.
Reactor Vessel Holddown Bolts The reactor vessel holddown bolts,-nuts, cnd washers for Unit I were supplied by Lanco' Industries, Inc. to the licensee through General Electric. Company. When certifications.were requested to assure com-
.pliances with bolt specification A3TM-A-490, a 2QC No. 246 was supplied along with certifications for the chemical analysis of the stud material used. AISI 4142 was used for bolt manufacture and AISI-4340 for the nuts and washers. Certification or data was not supplied to show that bolts, nuts, and washers met ASTM A-490-for heat treatment and mechanical properties. The licensee is taking steps to obtain this information.
This item is unresolved pending inspector's review of evidence that bolts, nuts, and washers meet the requirements of ASTM A-490 for heat treatment and mechanical properties.
(50-373/80-29-01)
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. An unresolved item disclosed during this inspection is discussed in Section II, paragraph 4 of this report.
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Exit Interview The inspectors met.with licensee representatives (denoted under Persons Contacted) at-the conclusion of the inspection on July 10, 1980. The inspectors summarized the scope,of the inspection and the findings which were acknowledged b, the licensee.
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