IR 05000373/1979032
| ML19256E552 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/03/1979 |
| From: | Key W, Neisler J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19256E548 | List: |
| References | |
| 50-373-79-32, 50-374-79-22, NUDOCS 7911080026 | |
| Download: ML19256E552 (6) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-373/79-32; 50-374/79-22 Docket No. 50-373; 50-374 License No. CPPR-99; CPPR-100 Licensee: Commonwealth Edison Company P. C.
Box 767 Chicago, IL 60590 Facility Name: La Salle County Station, Units 1 and 2 Inspection At: La Salle Site, Marseilles, Illinois Inspection Conducted:
September 5-6, 1979 Inspectors:
J. H. Neisler
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M,1
/O-9-79 W. J. Key
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Accompanied By:
J. Romero - Ochoa, C.N.S.N.S. (Mexico) Reactor Inspector M/5/7Z Approved By:
C. C. Willia.ns Projects Section 2
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h h2 D. H. Danielson, Chief
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Engineering Support "ection 2 Inspection Summary Inspection on September 5-6, 1979 (Report No. 50-373/79-32; 50-374/79-22)
Areas Inspected:
Inspection of work activities and review of documentation relative to the installation of fire seals in Unit 1 penetrations.
Review of radiographs relative to reactor recirculation system thermal sleeve safe end modification on Unit 1.
Observation of work activities and review of quality assurance documentation relative to reactor recir-culation and feedwater cipe welding in Unit 2.
The inspection involved a total of 24 inspector haurs by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted Principal Licensee Personnel
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L. J. Burke, Site Project Superintendent T. E. Quaker, Site QA Supervisor W. Reidy, QA Engineer D. J. Skoza, QA Engineer E. R. Wendorf, Station Construction B. J. McAndrew, Station Construction G. E. Groth, Station Constructica
- J. W. Gieseker, QA Engineer
- R. T. Rose, Project Structural Engineer Contractor and Other Personnel R. E. Spencer, Site Manager, General Electric Company T. K. Mulligan, Welding Supervisor, General Electric Company D. N. Bryant, QC Superviscr, General Electric Company C. T. Brenson, QA Engineer, General Electric Company R. C. Shulz, QC Supervisor, Morrison Consstuction Company
- M. Wherry, QC Morrison Construction Company
- K. Kranz, Welding Supervision, Morrison Construction Company M. R. Dougherty, QA Supervision, Walsh Construction Company
- Denotes those who did not attend exit interview.
Licensee Action on Previously Reported Items (Closed) Unresolved Item (373/79-18-01; 373/79-12-01): Relaxation tolerances for quencher embed stud tension tests. Fielt Change FCR638 as reviewed and approved by Sargent & Lundy and SNED established relaxation tolerances for tension test on the quencher embed studs.
(Closed) Report 10 CFR 50.55(e) (373/78-XX-06; 374/78-XX-05): Licensee reported occurance of cracks in containment post tensioning tendon wire button heads that exceed the limits specified by the tendon fabricator (Inland-Ryerson) in their Specification 1610. Licensee and fabricator conducted a test program to determine the impact of cracked buttonheads on the the ultimate tensile etrength of the installed tendons. The test program included:
1.
More than 200 single wire static tensile tests.
2.
Ten single wire high-cycle dynamic tests.
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A full 90 wire tendon low-cycle dynamic test and subsequent static tensile tests.
4.
Two full 170 wire tendon low-cycle dynamic test and subsequent static tensile test.
5.
Two 30 wire tendon high-cycle dynamic tests.
The inspector's review of details of the above tests as given in Inryco Report " Investigation of Buttonhead Defects" dated March 9, 1979, deter-mined that cracks the size of those observed at La Salle had no appreciable effect on the ultimate tensile strength of the tendon and that test data indicates no failures occurred below the 240,000 psi guaranteed ultimate tensile strength of the tendon material. This item is considered closed.
Program or Functional Areas Inspected 1.
Unit 2 Feedwater Piping The inspector observed welding being performed on the joint between the feedwater pipe and the nozzle extension at the N-16 feedwater nozzle. Welding was being performed in accordance with the approved qualified WPS. The inspector verified that the welder's qualification to perform work under the WPS was current. Weld data package at work location was complete within the scope of work completed. Data sheets indicate that QC and authorized inspector hold points had been established and observed.
The inspector reviewed qualification records of six welders and two weld inspectors employed by Morrison Construction Company (MCCo).
Qualifications were in accordance with applicable codes for the work perfo rmed.
The inspector reviewed pipe weld data reports of MCCo:
a.
Feedwater pipe welds; FW247, FW248, FW302, and FW303.
b.
Reactor Recirculation pipe welds; RR653, RR652, RR654, RR655, RR666, and RR667.
No noncompliances or deviations were identified in this area.
2.
Pipe Penetration Fire Seals The inspector observed the installation of silicone foam fire seals in three pipe penetrations. Before application of the silicone foam to the penetration, the contractor quality control supervisor performed densityof15.8lb./ft. gest.which was within the 15-23 lb./ft.g foam the density acceptance The test, No. 527, indicated specified 1294 057-3-
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in Tech-Sil Specification NP8-XFF. A review of previous tests
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indicated all f am installed in the penetrations to be within the 15-23 lb./ft.3 limits.
The inspector reviewed training and qualification records for Tech-Sil quality control inspection personnel, and records and certifications for foam applicator / installers.
No items of noncompliance or deviations were identified.
3.
Review of Residual Heat Removal System Radiograph On August 21, 1979, the RIII office received a telephone call suggesting that the NRC take a close look at radiographs of piping in the R. H. System.
The caller mentioned the B-2 heat exchange as having pipe cracks which do not show up because of very bad radiographic work. The caller questioned the quality of the radiographs, and the film results. And that he would provide more data when contacted by the NRC.
The caller was contacted by an inspector from the RIII office on September 5, 1979, at which time the inspector was informed that the caller could not provide, at that time, specific joint identification numbers.
On September 6, 1979, the following radiographs of welds in the R. H.
System were screened by the RIII.
a.
Weld No. RH460, Isometric - 1RH02AA Film Position 0-10 - Porasity code 10-20 - meets code 20-30 - meets code 30-40 - meets code 40-50 - meets code 50-0 - meets code Density range 2.3 to 3.0, Penetrameter 2.47..
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Weld No. RH472 Film Position 0-12 - meets code 12-24 - meets code 24-36 - meets code 36-48 - meets code
48-0 - meets code Density range 2.67 to 3.26, Penetrameter 2.75 1294 058
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Weld No. RH466, Isometric - 1RH02AB, Pipe to Valve
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Film Position 0-12 - meets code 12-24 - meets code 24-36 - meets code 36-48 - meets code 48-0 - meets code Density range 2.88 to 3.22, Penetrameter 2.84 d.
Wald No. RH765 C(B) (Drywell), Isometric - 1RH59AA, Pipe to Pipe Film Position 0-9 - meets code 9-18 - meets code 18-27 - meets code 27-0 - meets code Density range 2.26 to 2.87, Penetrameter 2.61 Weld No. RH764 (Drywell), Isometric 1RH59AA Pipe to Pipe e.
Film Position 0-9 - meets code 9-18 - meets code 18-27 - meets code 27-0 - meets code Density range 2.90 - 3.20, Penetrameter 2.55 f.
Weld No. RH763 (Drywell), Isometric - 1RH59AA Pipe to Pipe Film Position 0-9 - meets code 9-18 - meets code 18-27 - meets code 27-0 - meets code Density range 2.45 to 2.75, Penetrameter 2.4 Further review of this : natter will be conducted during a future inspection.
(373/79-32-01)
No items of noncompliance or deviations were identified.
4.
Radiographic Review The following radiographs of welds modifying the reactor vessel recircualtion nozzle safe ends were reviewed by the inspector and determined to meet ASME Section III requirements.
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Nozzle Weld Report No.
N2A
48 N2B
80 N2C
26 N2D
76 N2E
36 N2F
35 N2G
27 N2H
37 N2J
54 N2K
46 No items of noncompliance were identified in this area.
Exit Interview The inspectors met with licensee representatives at the conclusion of the inspection on September 6, 1979. The inspectors summarized the scope and findings of the inspection. The licensee acknowledged the findings as reported herein.
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