IR 05000321/1982001
| ML20041C557 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/04/1982 |
| From: | Herdt A, York J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20041C556 | List: |
| References | |
| 50-321-82-01, 50-321-82-1, 50-366-82-01, 50-366-82-1, IEB-79-14, NUDOCS 8203020305 | |
| Download: ML20041C557 (5) | |
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UNITED STATES E
't, NUCLEAR REGULATORY COMMISSION g
a REGION 11 101 MARIETTA ST., N.W., SulTE 3100 o,
s ATLANTA, GEORGIA 30303 s
Report Nos. 50-321/82-01, 50-366/82-01 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302 Facility Name: Hatch Docket Nos. 50-321, 50-366 License Nos. DPR-57, NFP-5 Inspection at Hatch near Baxely, Georgia Inspector:
W,To /L 2/4/S]2 J. W.
rk
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Da'te Signed
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djp Approved by:
A. R. Herdt, Section Chief D e Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on January 12-15, 1982 Areas Inspected This special, unannounced inspection involved 22 inspector-hours on site in the l
areas of ultrasonic inspection of Low Pressure Turbine Discs, fuel cladding j
corrosion, and seismic analysis for as-built safety-related piping systems (IE
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Results l
Of the three areas inspected, no violations or deviations were identified.
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PDR ADOCK 05000321
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s REPORT DETAILS 1.
Persons Contacted Licensee Employees
- C. Jones, Assistant Plant Manager
- T. V. Greene, Assistant Plant Manager
- C. E. Belflower, QA Site Supervisor
- J. M. Watson, Sr. QA Field Representative P. Fornel, Jr., Assistant QA Site Supervisor S. Curtis, Sr. Reactor Engineer
- R. Nix, Maintenance Superintendent W. 8. Thigpen, Sr. QA Field Representative R. Glisson, Engineering Supervisor
- D. A. McCusker, QC Supervisor Other licensee employees contacted included technicians and office personnel.
Other Organizations T. Dunkin, Field Engineer, General Electric M. Tetlak, Ultrasonic Technician, General Electric
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 15, 1982 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings l
Not inspected.
4.
Unresolved Items I
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Unresolved items were not identified during this inspection.
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5.
Ultrasonic Inspection of General Electric Low Pressure Turbine Discs (Unit 1)
In a meeting at NRC Headquarters in Bethesda, Maryland on January 6, 1982, General Electric (GE) stated that some stress corrosion cracking eminating from keyways on Low Pressure Turbine Discs had been detected.
GE recom-mended that six nuclear plants in this country that have been operating for approximately six years have their Low Pressure (LP) Turbines inspected within the next six months. One of the units was Hatch Unit 1.
Since this unit was currently in an outage, it was decided to inspect the LP Rotors.
Hatch Unit I has two Low Pressure Rotors. Each rotor has seven stages and therefore fourteen turbine discs. Each disc has one keyway. The LP units have preheaters and are therefore less likely to have a significant ultrasonic indication.
The inspector reviewed the ultrasonic test procedure, " Procedure for Wheelbore Testing," Revision 2 dated November 18, 1981 and witnessed part of the ultrasonic inspection of one of the LP Rotors. GE has a specially designed system for automatically ultrasonic testing of the LP Turbine Disc Bores. Not only is the keyway inspected, but the entire area of the bore.
Within the areas inspected no violation or deviations were identified.
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6.
Inspection of Fuel Cladding Corrosion (Unit 1)
l Hatch Unit I had an unplanned outage on October 9, 1981 to locate and replace leaking fuel assemblies. The licensee considered this event to be caused by abnormal fuel degradation as a result of accelerated fuel cladding corrosion. Eleven (11) of the 168 fuel assemblies in Reload 2 were found to be leaking.
This reload was in the middle of its third and final usage cycle. A full core load consists of 560 fuel assemblies and all of these were tested for leakage in Hatch 1.
After determining which of the fuel assemblies were leaking, the individual assemblies were disassembled by GE and visually, ultrasonically and eddy
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current inspected. It was found that the fuel cladding (Zircalloy 2 tubing)
had been penetrated by accelerated corrosion only on some of the gadolinia rods, and in the highest power area of the rod. All of the gadolinia rods examined had some degree of accelerated corrosion. There is a small number of these rods in each fuel assembly at Hatch Unit 1, and they contain fuel pellets that have a mixture of uranium dioxide and gadolinum oxide. These rods aid in excessive reactivity control and in reducing local power peaking. Corrosion or crud samples were removed from some of these leaking fuel rods and sent to GE in San Jose, Califonia for analysis.
The licensee and GE decided to inspect Reload 1 which had completed its usage period and was stored, and a similar condition was found i.e.,
accelerated corrosion on the gadolinia rods.
Sipping inspection of these fuel assemblies revealed seventeen leakers.
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As a result of this condition, GE has' recommended tighter controls of water chemistry.- Specifically, a limit of two' parts per billion (ppb) maximum copper (Cu) in the feedwater and 1 ppb Cu maximum (filterable metal) in the Reactor Vessel were recommended. The licensee will now use a more elaborate start up procedure, in that, feedwater flushing will be utilized and chemi-cal analysis of the water will be performed hourly. Once full power opera-tion has been achieved, a daily chemical analysis of the water will be performed. Even with this stricter chemistry control GE does not guarantee that further fuel cladding corrosion will not occur.
Within the areas inspected no violations or deviations were identified.
7.
(0 pen) IE Bulletin 79-14:
Seismic Analysis For As-Built Safety-Related Piping Systems (Units 'l and 2)
Walkdown inspections were conducted by Bechtel and are complete for both units. Georgia Power QA performed approximately 15 walkdowns and Georgia Power QC monitored approximately 10 percent of these inspections in order to evaluate the Bechtel inspection efforts. A Bechtel Site Engineer reviewed the inspection packages and efforts as they were completed.
The Site Engineer made some evaluations and the remaining evaluations were performed by the Bechtel Design Group in Gaithersburg, Maryland.
All identified operability -(safety) problems that were identified in the inspection of both units have been corrected. Other modifications have been identified as being necessary before the requirements of IEB 79-14 are satisfied.
Unit 1 is in an unscheduled outage that should be completed by mid or late February. Unit 2 will start an outage of 11-13 weeks duration when Unit 1 is back on line. The licensee stated that the modifications on Unit 2 necessitated by IEB 79-14 will be made during this outage. Unit 1 is-scheduled for a 22-week outage in the fall of 1982 for torus modification and during this period of time the IEB 79-14 modifications will be per-formed.
The inspector reviewed the following procedures:
a.
Procedure No. HNP1-10124 Rev. 4, " Surveillance Procedure for Safety Related Seismic Class-I Systems" b.
Procedure No. 2-11021 Rev.
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" Surveillance Procedure for Safety Related Seismic Class-I Systams"
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Four hangers, two from each unit were inspected and are as follows:
Unit 1 f
a.
Hanger No. SDGH-41 in the Diesel Generator Bldg. Service Water System
b.
Hanger No. RHRH-388 in the Residual Heat Removal System
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Unit 2 a.
Hanger No. P41-SDGH-41 in the Plant Service Water System b.
Hanger No. 2G41-FPC-R114 in the Fuel Pool Cooling System Within the areas inspected no violations or deviations were identified.