IR 05000424/1986103
| ML20214K422 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/17/1986 |
| From: | Conlon T, Gibbons T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20214K407 | List: |
| References | |
| 50-424-86-103, 50-425-86-47, NUDOCS 8612020295 | |
| Download: ML20214K422 (6) | |
Text
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. NUCLEAR REGULATORY COMMISSION
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j 101 MARIETTA STREET,N.W.
ATLANTA. GEORGI A 30323
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Report Nos.: 50-424/86-103 and 50-425/86-47 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos'.: 50-424 and 50-425 -
License Nos.:
CPPR-108 and CPPR-109
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Facility Name: Vogtle 1 and 2 Inspection Conducted: October 20-24, 1986
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Inspector:
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A thA T. D. Gibbo Da~te Signed Approved b pc
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T. E. Conlon, Section Chief Date Signed Engineering Branch
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Division of Reactor Safety
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SUMMARY.
Scope:
This routine, unannounced inspection involved the areas of electrical cables and termination work and work activities and licensee identified items.
Results: No violations or deviations were identified.
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8612020295 861119 PDR ADOCK 05000424 G
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1 REPORT DETAILS
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1.
Persor.s Contacted Licensee Employees
- P. D. Rice, Vice President, Project Engineering
- E. D. Groover, QA Site Manager - Construction
- G. S. McCarley, Project Compliance Coordinator
- R. E. Hollands, Compliance Superintendent Other licensee employees contacted included construction craftsmen, engineers, technicians, inspectors and office personnel.
NRC Resident Inspectors
- H. Livermore, Senior Resident Inspector R. Schepens, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 24, 1986, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Unresolved Items Unresolved items were not identified during the inspection.
Electrical (Cables and Terminations II) Observation of Work and Work 5..
Activities (Unit 1) (51064B)
The inspector selected twenty six cables for examination to assure that the SAR and QC procedures were being followed.
The cables selected are listed below:
l 1AA0206EA, 1BA0322EA, 1AB0402HA, 1AB0405HA, 1AB0408HA, 1AB0409HA, 1AB04104HA, 1AB0412HA, 1AB0413HA, IAB0417HA, 1AB0416HA, 1AB0402HB, 1AB0505HA, 1BBE2750, IBBE26SD 1BBC07SB, IBBC08SD, IBBB38LB, IBB0612SA, IBB0609SG, ICD 1M03SN, IBBB15SA, 1BBB16SA, IBBB14SA, IBBB24SA and IBBE13SA.
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.The above list of cables included ten power. cables and sixteen control cables. Two of the power cables were ~4160 volt Motor feeders and two of the-control cables were for motor operated valves.
The inspector examined installed cables to verify that the cable was pulled on the proper raceway.
The cable was identified on the outer jacket and the cable pulling card
' identified the reel number which can be traced back to the manufacture's
. test reports.
The licensee has.a system for the handling of nonconforming material by segregation or by tagging. The cable pull card is the document
- which controls the cable installation.
The cable pull card contains a letter code which identifies the. cable to be used.
The QC inspector verifies the cable type and the reel number. The back of the pull card has an inspection check-list which identifies the procedures and signature blocks for the QC inspectors verification..The NRC inspector verified the size and type of cable, the terminations at the terminal boards, sealed splices, raceways and fire seals.
The cable routing was examined to assure that they were. in the proper tray, physical separation and protection was-completed as specified on the pull card.
The raceway installation was examined to assure that the supports, identifications and loading was acceptable.
The 4160 volt cables high potential tests records were-acceptable.
The inspector reviewed the procedures for nonconformance control and during discussions with engineers and QC inspectors, the inspector confirmed that the licensee nonconformance program is operational.
Within the areas examined, there were no violations or deviations identi-fied.
6.
Licensee Identified Items a.
(Closed) Item 424/CDR 86-109 Diesel Generator (DG) Jacket Water Heat Exchanger (10 CFR 50.55)(e)).
The final report was submitted on September 17, 1986.
The report has been reviewed and determined to be acceptable.
The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the enrrective actions identified in the report have been completed. The licensee identified that during flushing of the Unit. A DG Jacket Water Heat Exchanger that the required design flow rate of 1800 gpm could not be achieved. This was caused by restrictions within the heat exchanger.
The licensee's evaluation indicated that the restriction was caused by bent tubes which were probably caused by a pressure surge.
The heat exchanger from a unit 2 DG was used for a replacement and the flush was completed and accepted.
The defective heat exchanger has been repaired and returned to the site for installation on the Unit 2 DG. The replace-ment was completed and documented on Nuclear Plant Maintenance Work Orders (NPMW0) 18511956 and Deficiency report T-1-85-14444.
The item remains for Unit ~*
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b.
(Closed) Item 424/CDR-85-39 "Transamerica Delaval (TDI) Diesel-Generator Cylinder Head Weld Repair" (10 CFR 50.55(e)).
The final report was submitted on January 13, 1986.
The report has been reviewed and determined. to be acceptable.
The' inspector held-discussions ' with responsible licensee representatives and reviewed
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supporting documentation to verify that the corrective actions-identified in the report have been completed.
The TDI owners group-identified that a potential problem involving the cylinder weld' head repair using unauthorized procedures.
The owners group finding was evaluated by Bechtel design.
Bechtel calculations identify that it is possible to have a total loss of jacket water causing an engine trip.
Five heads were found to have weld repairs made to the unapproved procedure and one_ cylinder head damaged during maintenance were returned to TDI for rework.
The six heads were reworked, accepted and returned
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to the site.
The heads were reinstalled using NPMWO 18504439 and
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18513068.
The NPMWO have been completed and inspected.
This item remains open for Unit 2.
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(Closed) Item 424/CDR-82-30LimitorquePinionGearKeys (10 CFR 50.55(e)).
l The final report was submitted on June 1,1983, and reviewed June 16, 1986.
The report has been reviewed and determined to be acceptable.
The inspector held discussions with responsible licensee representa-tives and reviewed supporting documentation to verify that the corrective actions identified in the report have been completed.
Westinghouse Electric Corporation (WEC) notified the NRC by letter, dated August 6,1982, that six sheared pinion gear keys had been found in Limitorque Model SB-0-25 motor operators at another utility.
The pinion gear problem had been previously identified in IE Notice 81-08 which discussed the shearing of pinion gear keys on SMB-4 motor operators.
The licensee does not use any of the above operators. WEC and the licensee have decided to replace the pinion keys on the Model SMB-0-15 motor operators.
There are six motor operators used on Unit 1.
WEC has performed the work and inspection has accepted the work field equipment change order N-58-BF. This item remains open for Unit 2.
d.
(Closed) Item 424/CDR 84-59 "TDI Diesel Generator Thrust Bearings" (10CFR50.55(e)).
The final report was submitted on November 12, 1984.
The report has been reviewed and determined to be acceptable.
The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the corrective actions identi-fied in the report have been completed.
TDI notified the NRC by letter, dated February 15, 1984, that a problem existed with the lubrication of the turbocharger thrust bearing.
The problem is insufficient lubrication which occurs on a quick start after a long standby period.
TDI recommended a drip system to minimize the thrust L
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bearing wear.
The flow through the turbo charger should be at least 0.1 gph and may be as high as 0.35 gph. The change required modifica-tion to the piping and increasing the orifice size.
The work was performed and documented on Maintenance Work Orders 1-86-03409, l
1-86-03410, 1-86-03482, 1-86-03483 and 1-86-01577.
The licensee has verified adequate flow. This item remains open for Unit 2.
e.
(Closed) Item 424/CDR 85-85 and 425/CDR 85-85, Containment Tubing and Instrument Support (10 CFR 50.55(e)).
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The final report was submitted on January 23, 1986.
The report has been reviewed and determined to be acceptable.
The inspector held discussions with responsible licensee representatives and reviewed supporting documentation.
The licensee designer identified that there was a possibility of some tubing and instrument supports installations that failed to meet the seismic qualification.
An engineering evaluation of a field change identified that it was possible for tubing or instrument supports to have a natural frequency of less than 33 cycles.
The designers performed a field walkdown which identified 50 support installations with the potential of exceeding ceismic qualifi-cation by having a natural frequency less than 33 cycles.
The evaluation concluded that the existing installations are acceptable and no modifications are required. The licensee has evaluated this item as not reportable. The inspector concurs with the licensees evaluation.
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(Closed) Item 424/CDR-86-94 "TDI Diesel Generator Valve Springs" (10 CFR 50.55(e)).
The final report was submitted on March 6, 1986.
The report has been
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reviewed and determined to be acceptable.
The inspector held discus-
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sions with responsible licensee representatives and reviewed supporting l
documentation to verify that the corrective actions identified in the report have been completed.
TDI by letter, dated November 6,1985, notified the NRC of potential defect in the valve springs on the diesel engines supplied to the site.
TDI reported that there were valve spring failures on two non nuclear engines used for ship propulsion.
The evaluation of the failed springs revealed impurities in the wire, draw marks and incomplete shot peening.
TDI considers the spring failures to be an isolated case and therefore not generic.
However, the licensee decided to replace all springs. Nuclear Plant Maintenance Work Order 1816538 and 18616539 were issued to control and document the installation and inspection for the Unit 1 DGs.
424/CDR 85-83 arid Westinghouse Flux Mapping System (10 CFR 50.55(e)).
The final report was submitted on January 29, 1986.
The report has been reviewed and determined to be acceptable.
The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the corrective actions identi-fied in the report have been completed.
The licensee identified this item during review of IEN 85-45, " Potential Seismic Interaction
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Involving the Moveable Incore Flux Mapping Systems Used in Westinghouse Designed Plants."
The 10 Path transfer assembly is mounted directly above the seal tube. The incore thimble tubes which are mounted to the seal table are a reactor pressure boundary.
The corrective actions identified by a seismic analysis was the addition of a stiffener and adding four anchor assembles to four wheel assemblies.
Work was documented on Process Control Sheet number 360-6.
The work was inspected and accepted.
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