IR 05000373/1979034
| ML19262A617 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/24/1979 |
| From: | Barrett P, Neisler J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19262A612 | List: |
| References | |
| 50-373-79-34, 50-374-79-23, NUDOCS 7912070162 | |
| Download: ML19262A617 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-373/79-34; 50-374/79-23
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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, Marseilles, IL Inspection Conducted: October 2-4, 1979
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P. A. Barretf
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J. H. Neisler l.Q,.
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Approved By:
C. C. Williams, Chief
/ t /:14 / 75r Projects Section 2
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Inspection Summary Inspection on October 2-4, 1979 (Report No. 50-373/79-34; 50-374/79-23)
Areas Inspected:
Review of nondestructive examinations peri.;med on RHR pipe welds, Unit 1.
Observation of work activities relative to recircu-lation system safe end thermal sleeve modification, Unit 2.
Observation of work performed on cooling lake spillway. Observation of electrical activities relative to cable tray fill, conduit and 250 volt battery /dc power system. The inspection involved a total of 30 inspector-hours by two NRC inspectors.
Resuly: No items of noncompliance or deviations were identified during this inspection.
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DETAILS
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Persons Contacted Principal Licennee Personnel L. J. Burke, Site Project Superintendent C. E. Quaka, Site QA Supervisor s
v. Reidy, QA i.ngineer T. R. Sommerfield, QA Engineer R. T. Rose, Project Structural Engineer D. J. Skoza, QA Engineer K. W. Steele, Station Construction J. W. Gieseker, Station Construction G. E. Groth, Station Construction
- L. Tapella, QA Engineer Contractor and Other Personnel M. R. Dougherty, QA Supervisor, Walsh Construction Company R. Ouzts, QA Manager, H. P. Foley Company W. S. Marini, Quality Assurance, H. P. Foley Company
- Denotes those who did not attend exit interview.
Licensee Action on Previously Reported Items (0 pen) Finding by NRR-DSE/HMB that rip-rap on the cooling lake spillway was improperly placed and that gradation of stones used to con:truct the rip-rap incorrect.
Licensee is in process of correcting the finding by breaking larger stones and hauling stone in to meet gradation requirements.
The inspector was informed by licensee representative that the spillway would be ready for inspection by mid October.
NRR-DSE/HMB personnel are scheduled to inspect the spillway on October 23, 1919.
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Section I Prepared by J. H. Neisler Reviewed by C. C. Williams, Chief Projects Section 2 s
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Review of Residual Feat Removal System Radiographs 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.R. system.
The caller mentioned the B-2 heat exchanger as having pipe cracks which do not show up because of "very bad" radiographic work, and the film results.
During this inspection, the following radiographs of welds in the R.H.R. system were screened by RIII.
a.
Weld #RH486, ISI #1RH1077-1 line IRH03-18 Film Position 0-10R1, density 2.02-2.25, Penetrameter #12, 4T, meets code 10-2-R1, density 3.72-3.89, Penetrameter #12, 4T, meets code 20-30R1, density 2.36-3.14, Penetrameter #12, 4T, meets code 30-20R1, density 2.50-3.46, Penetrameter #12, 4T, meets code 40-50R1, density 2.25-3.23, Penetrameter #12, 4T, meets code 50-0R1, density 2.40-3.55, Penetraneter #12, 4T meets code For this weld, the inspector also reviewed the following ISI baseline data reports; ISI liquid penetrant report #EDS 0005A Line 9, dated May 9, 1979. No relevant indications identified.
Accepted by code inspector.
ISI ult rasonic examination reports 72003, beam angle 0 and report 72005 beam angle 45. No relevant indications were identified. Accepted by code inspector.
b.
Weld #RH474, ISI #1RH1007-67, line #1RH02AB-18 Film Position 0-12R1, density 2.11-3.60, Penetrameter #12, 4T, meets code 12-24P1, density 2.19-3.32, Penetrameter #12, 4T, meets code 1523 008-3-
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24-36R1, density 2.18-3.08, Penetrameter #12, 4T, meets code 36-48R1, density 2.06-3.13, Penetrameter #12, 4T, meets code 48-0R1, density 2.30-3.31, Penetrameter #12, 4T, meets code For this weld, the inspector also reviewed the f ollowing ISI baseline data reports:
ISI liquid penetrant report EDS 20190 line 1.
No relevant indi-s cations were identified.
Results accepted by code inspector.
ISI ultrasonic examination report #EDS 20196 beam angle 0 and 72005 beam angle 45 No relevant indications were identified en either report.
Both reports were accepted by code inspector.
Welds 474 and 436 are pipe to nozzle welds on Unit 1 R.ll.R.
heat exchanger B-2.
The inspector also performed a visual inspection on these welds and the inlet and outlet nozzle to pipe welds on the identical heat exchanger in Unit 2.
No relevant indications were noted.
No items of noncompliance or deviations were identified in this area.
2.
Reactor Recirculation System Safe End Assembly Modification, Unit 2 The inspector observed cutting being performed to remove the old thermal sleeve from the recirculation system nozzle safe end assembly at the 30 location and the machining of the weld prep on the nozzle at the 120 location.
Procedures, checklists and quality control activities are the same as those used for removal of the original safe ends assemblies in Unit 1.
No items of noncompliance or deviations were identified in this area.
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Section II
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Prepared by P. A. Barrett Reviewed by D. W. Hayes, Chief Engineering Support Section 1
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1.
Observation of Second Shift Activities On October 2, 1979 during the second shift, the RIII inspector a.
took an extensive tour of the Unit I reactor and auxiliary buildings. The CECO Site Construction Superintendent stated that, except for a skeleton maintainance crew, no second shift construction activities were being performed.
During the RIII inspector's tour, two craftsmen were observed installing 0* rings on conduits identified on Corrective Action Reports 1762 and 1763. There were no other apparent work activities.
b.
The RIII inspector observed that the 250 volt battery charger IDC03E had been put into the equalize mode. The shift engineer provided a 250 VDC Battery Data Sheet (LOC-M1 Revision 1) dated September 30, 1979 which indicated that the equalizing activities were being controlled in accordance with procedure LOP-DC-07 Revision 2.
No items of noncompliance were identified.
2.
Control of Cable Raceway Fill The RIII inspector selected two cable trays, one conduit and an a.
intersection of four trays to verify that appropriate design measures have been taken to control the thermal (ampacity) and dead-weight loading of the enclosed cables.
The raceways were selected on the basis of visible potential overfills.
The RIII inspector and the licensee's representative physically counted the cables enclosed in the two cable trays and the one conduit.
(1) One of the trays was scheduled to contain 173 cables.
173 cables were actually installed.
169 of the 173 scheduled cables were documented as being installed to date.
Thus, there was an apparent discrepancy of four cables.
(2) The other tray was scheduled to contain 208 cables.
212 cables wcre actually installed.
204 of the 208 scheduled cables were documented as being installed to date.
Thus, there was an apparent discrepancy of eight cables.
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(3) The conduit was scheduled to contain 15 cables.
14 cables
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were actually installed. All 15 of the scheduled cables were documented as being installed to date. One of the scheduled cables was actually installed in an adjacent conduit.
The totals for the above scheduled cables were obtained from the Cable Pan Loading Report dated August 24, 1979 and s
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September 6, 1979, which was an uncontrolled document.
This document was the only available document at the site which would readily indicate the raceway loading (fill) conditions.
Therefore, the RIII inspector could not readily determine if the above conditiens were acceptable or not.
This matter is unresolved pending review of the pertinent control documents.
(373/79-34-01)
The review will include the design measures to control the fill in the aforementioned tray intersection.
b.
The RIII inspector observed a conduit which intersected junction box #1JB113A at el vation 786 feet and column lines 9-15 in the auxiliary building.
Cables #1VC 151, IVC 192 and IVC 136 were installed in the above conduit. The installed routing did not correspond to the governing drawing #1E-1-3474 Revision T.
The licensee provided paperwork which indicated that the entire area (El. 786 ft., Column 9-15) was in process of being redesigned and reworked. However, the above situations had not yet been identified on a control document. Therefore, the licensce initiated CECO Nonconformance Report No. 358 on October 3, 1979 during this inspection.
No items of noncompliance were identified.
3.
NSSS Supplied Class IE Components The RIII inspector reviewed site procurement documentation for various components which were supplied by General Electric Company.
All of the reviewed components were certified to be in accordante with the purchase specifications by Produ:t Quality Certifications (certificates of conformance).
The RIII inspector verified that the documented components were actually installed in the plant.
Documen-tation, which substantiates the validity of the PQC's, will be reviewed during a subsequent inspection.
(373/79-34-02)
Unresolved Matters Unresolved matters are matters about which more information is requited to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Unresolved items disclosed during the inspection are discussed in Section II, paragraph 2.a.
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Exit Interview
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The inspectors met with licensee representatives (denoted under Persons Contacted) on October 4, 1979.
The inspectors summarized the scope and findings of the inspection. The licensee acknowledged the findings as reported.
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