IR 05000382/1993015
| ML20036A872 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/05/1993 |
| From: | Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20036A871 | List: |
| References | |
| 50-382-93-15, NUDOCS 9305170121 | |
| Download: ML20036A872 (8) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Inspection Report: 50-382/93-15 Operating License:
HPF-38 Licensee:
Entergy Operations, Inc.
P.O. Box B Killona, Louisiana 70066 facility Name: Waterford Steam Electric Station, Unit 3 Inspection At: Taft, Louisiana Inspection Conducted: April 19-23, 1993 Inspector:
L. D. Gilbert, Reactor Inspector, Maintenance Section Division of Reactor Safety Approved:
Dr. Dale A. Powers, Chief, Maintenance Section Date
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Division of Reactor Safety
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Inspection Summary Areas Inspected:
Routine, announced inspection of erosion / corrosion monitoring program, and followup.
Results:
The administrative procedure clearly defined responsibilities for the
erosion / corrosion program (Section 2.1).
The licensee has developed a good program for the detection of component
degradation in high-energy piping resulting from erosion / corrosion (Section 2.1).
Summary of Inspection Findinas:
No inspection findings were opened.
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r Inspection followup Item 382/9008-01 was closed (Section 3).
- 9305170121 930510 PDR ADOCK 05000382 O
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Attachments:
i Attachment 1 - Persons Contacted and Exit Meeting
Attachment 2 - Documents Reviewed
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DETAILS
1 PLANT STATUS
During this inspection period, the plant was operating at power.
2 INSPECTION OF EROSION / CORROSION MONITORING PROGRAMS (49001)
The objectives of this inspection were to ascertain whether licensee
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commitments and procedures that were developed and implemented to address the long-term erosion / corrosion monitoring program were in accordance with NRC requirements and Generic Letter 89-08, " Erosion / Corrosion-Induced Pipe Wall
Thinning." This portion of the inspection primarily addressed programmatic aspects of the licensee's erosion / corrosion monitoring program. The inspection of the licensee's implementation of the erosion / corrosion
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monitoring program will take place at a later time.
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2.1 Discussion The inspector reviewed the licensee's response to Generic Letter 89-08. The
response was documented in two letters dated July 21 and November 17, 1989.
The licensee notified the NRC in these letters that a formalized long-term
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erosion / corrosion program, equivalent to the Nuclear Utility Management and
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Resources Council guidelines referenced in Generic Letter 89-08, had been i
implemented. The program was to provide assurance of the structural integrity
of carbon-steel piping systems designed to carry high-energy water in
single-phase flow and steam in two-phase flow.
In late 1991, the licensee l
upgraded the erosion / corrosion program to include the Electric Power Research
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Institute, Inc. (EPRI) CHECMATE computer program for predicting component wall
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thinning in carbon-steel high-energy piping systems. The erosion / corrosion l
computer models for Waterford 3 were developed by ABB Impell Corporation using the computer analysis program in the CHECMATE Computer Program User's Manual.
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The inspector verified that a formalized program was in place regarding (
erosion / corrosion monitoring of piping system components.
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i responsibilities, interfaces, and requirements for administration of the erosion / corrosion program at the Waterford Steam Electric Station, Unit 3, were defined in Nuclear Operations Engineering and Construction Procedure N0ECP-254, " Control-of Erosion / Corrosion," Revision 2.
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procedure specified that the Design Engineering Director had overall responsibility for the control of erosion / corrosion. The procedure also i'
assigned responsibilities for:
Coordinating the erosion / corrosion program to the inspection program j
supervisor,
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t Implementing and maintaining the erosion / corrosion program to the
responsible engineer, Performing nondestructive examination activities in support of the
erosion / corrosion program to the operations quality assurance manager, and i
Evaluating the acceptability of measured component wall thicknesses that
are below the acceptable minimum thickness to the design engineering manager.
In addition, the procedure specified requirements for selection and identification of examination locations, grid pattern layout, performance of examinations, examination acceptance criteria and disposition of results, program expansion, records, and outage summary reports. The procedure specified the following criteria for the selection of components for examination during a specific refueling outage.
Results from previous examinations,
Requests by plant personnel,
Industry events, and
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Priority selection based on CHECMATE predictive analysis.
- The inspector reviewed the engineering evaluation that identified the following piping systems as being potentially susceptible to erosion / corrosion:
steam generator feedwater; steam generator blowdown, feedwater heater drains, extraction steam from high-pressure turbine to feedwater heaters, extraction steam scavenging, condensate, and main steam.
The inspector verified that the carbon-steel piping systems, which would be susceptible to erosion / corrosion that were specified in Section 3 of the Waterford Steam Electric Station, Unit 3, Final Safety Analysis Report as high-energy lines, were included in the erosion / corrosion program. The inspector selected four of the above piping systems for detailed review. The review concentrated on the database in the erosion / corrosion models used for the computer analyses of the systems. The systems selected for review were the feedwater, extraction steam to heaters, heater drains, and blowdown systems. For each of the systems, the inspector compared the engineering input data and plant conditions to the database in the computer program for a
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segment of piping. The documentation provided by the engineering consultant
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stated that input data was checked by a second person. The database parameters reviewed included the pipe size, schedule and length, component material and geometry factors, and operating conditions regarding flow rate,
water chemistry, temperature, pressure, and hours of operation.
For the
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components selected and parameters reviewed, the database in the computer programs was consistent with the parameters specified by engineering, operations, and chemistry. The basis for the engineering input parameters was derived from, and in agreement with, the piping isometric drawings, the heat balance diagram, the piping line list, and the CHECMATE User's Manual.
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-5-The licensee's refueling erosion / corrosion summary reports for the last three refueling outages documented that:
183 component examinations were performed i
in Refuel 3, 280 component examinations were performed in Refuel 4, and 249 component examinations were performed in Refuel 5.
Of those examinations performed in Refuel 5, approximately 60 component examinations were selected by the licensee based on the result of the CHECMATE program predictions. This selection was a conservative sample using the criteria provided in the Nuclear Utility Management and Resources Council guidelines referenced in Generic
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Letter 89-08.
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The inspector was informed that the licensee was a member of CHECMATE Users'
Group and the responsible engineer attended their meetings. The responsible engineer had also received training on the CHECMATE User's Manual. The training was provided by EPRI.
In addition to the EPRI training, instructions
on use of the erosion / corrosion computer prograw were given by the engineering contractor. The inspector concluded that the training was appropriate.
The inspection of the implementation of the licensee's erosion / corrosion
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monitoring proy 'm will be performed at a later dated.
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2.2 ConclurdRBI
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The administrative procedure clearly defined respcnsibilities for developing, maintaining, and implementing the erosion / corrosion program. The licensee had i
developed a good program, for the detection of component degradai. ion in high-energy piping resulting from erosion / corrosion, that addressed the concerns identified in Generic Letter 89-08.
3 FOLLOWUP (92701)
i (Closed) Insoection Follewuo Item 382/9003-01: The Enhancement of Procedures for Handlino Out-of-Tolerance Conditions identified Durina Calibration of
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instrumentation During closure of Unresolved Item 382/8901-07, an inspection followup item was identified which related to completion of an ongoing program to upgrade calibration procedures.
In particular, the program would be upgraded to
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improve:
(1) procedural requirements for the notification of the shift i
supervisor of as-found, out-of-tolerance conditions identified during calibration activities; (2) records for documenting the acceptability of calibrations more clearly; and (3) timeliness of the reviews for potential i
generic trends pertaining to calibration of similar components.
The inspector was informed that a change was made to calibration procedures to m1uire imediate notification to thu shift supervisor and control room r.jpervisor of maintenance or calibration problems identified during
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calibration of safety-related or Technical Specifications related
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instrumentation. The inspector reviewed two calibration procedures and verified that the changes had been made. The procedures reviewed were:
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'I-6-MI-005-202, " Calibration of Pressure Instruments," Revision 5, and MI-005-203, l
" Calibration of Differential Pressure Instruments," Revision 7.
The inspector
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also verified that the form used to record the calibration of instrumentation had been modified to clearly document satisfactory or out-of-tolerance conditions.
In addition, two programs were in place for trending calibrations and instrumentation failures. The trending was performed on a daily and i
periodic basis to identify any potential generic problems.
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ATTACHMENT 1
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1 PERSONS CONTACTED 1.1 Licensee Personnel
- J. Abisamra, Supervisor, Mechanical / Design Engineering
- J. Azzarello, Director, Design Engineering H. Benford, Authorized Nuclear Inservice Inspector
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- T. Gaudet, Supervisor, Operational Licensing
- J. Hologa, Manager, Mechanical / Civil Design
- J. Howard, Manager, Procurement Programs, Engineering
- T. Leonard, Acting General Manager, Plant Operations
- A. Lockhart, Manager, Quality Assurance
- B. Loetzerich, Licensing Engineer D. Packard, General Manager, Plant Operations
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- J. Rhodes, Erosion / Corrosion Program Engineer
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- J. Roberts, Supervisor, Nondestructive Examination, Quality Assurance
- G. Robiri, Inservice Inspection Lead Design Engineer 1.2 NRC Personnel S. Campbell, Acting Resident Inspector In addition to the personnel listed above, the inspector contacted other personnel during this inspection period.
- Denotes personnel that attended the exit meeting.
2. EXIT MEETING An exit meeting was conducted on April 23, 1993.
During this meeting, the inspector reviewed the scope and findings of the report. The licensee did not.
identify as proprietary any information provided to, or reviewed by, the inspector.
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DOCUMENTS REVIEWED
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Procedure N0ECP-254, " Control of Erosion / Corrosion," Revision 2
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Drawing LOU-1554 G-072,'" Heat Balance," Sheet 8, Revision 3
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Drawing LOV-1564 G-IS1, " Flow Diagram Main & Extraction Steam Systems,"
.t Sheet 3, Revision 28 Drawing LOV-1564 G-164, " Flow Diagram Miscellaneous Reactor Auxiliary Systems," Sheet 3, Revision 28 j
f Drawing LOV-1564 G-153, " Flow Diagram Feedwater, Condensate & Air Evacuation Systems," Sheet 3, Revision 32 and Sheet 4, Revision 31 i
Drawing 4305-1315, " Extraction Steam System," Revision 11 Drawing 4305-3262, "Feedwater System," Revision 7 I
Drawing 4305-32'i3, "Feedwater System," Revision 5 Drawing 4305-7345, " Heater Drain System," Revision 1 Drawing 4305-7346, " Heater Drain System," Revision 4
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Drawing 8469-697, " Blow Down System," Revision 3 Drawing LOV 5817.0758, " Balance of Plant Piping Line List," Revision 23 Impell Report No. 11-0490-0022, " Erosion / Corrosion Intpection Program Assessment and Recommendations for Waterford S.E.S. Unit No.
3," Revision 0
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Calculation 0490-115-001, "Waterford 3 Extraction Steam CHECMATE Model,"
Revision 0 Calculation 0490-115-002, "Waterford 3 Heater Drains CHECMATE Model,"
Revision 0 Entergy Inter-Office Correspondence W3FI-92-0472, "NRC Information
Notice 92-07 Rapid Flow-Induced Erosion / Corrosion of Feedwater Piping," dated
December 22, 1992 Waterford 3 Third Refueling Erosion Corrosion Summary Report Waterford 3 Fourth Refueling Erosion Corrosion Summary Report Waterford 3 Fifth Refueling Erosion Corrosion Summary Report
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