IR 05000482/1993006
| ML20035B434 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/23/1993 |
| From: | Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20035B432 | List: |
| References | |
| 50-482-93-06, 50-482-93-6, NUDOCS 9304010355 | |
| Download: ML20035B434 (7) | |
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APPENDIX
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,D U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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Inspection Report: 50-482/93-06
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Operating License: NPF-42 Licensee: Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839
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Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At:
Burlington, Kansas Inspection Conducted: March 1-5, 1993
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Inspector: R. C. Stewart, Reactor Inspector, Maintenance Section, Division of Reactor Safety l
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Dr. Dale A. Powers, Chief, Maintenance Section Date '
Division of Reactor Safety Insoection Summary Areas Insoected: Routine, announced inspection of surveillance testing and calibration control programs and followup of an unresolved item.
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Results:
The administrative procedures clearly defined responsibilities for the
surveillance testing, calibration control, and inservice inspection and inservice testing of pumps and valve programs (Section 2.1).
The administrative controls in place for scheduling and tracking
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surveillance and calibration testing activities appeared to be good.
Surveillance test procedures contained the aporopriate elements and appeared to correlate with the Technical Specification requirements
(Section 2.1).
Personnel effectively implemented the surveillance testing and
calibration control programs (Section 2.1).
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Sumary of Inspection Findinos:
Unresolved Item 482/9209-03 was closed (Section 3.1).
9304010355 930329 PDR ADOCK 05000482
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Attachments:
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Attachment 1 - Persons Contacted and Exit Meeting l
Attachment 2 - Administrative Procedures Reviewed
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DETAILS
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1 PLANT STATUS
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During this inspection period, the plant was in Mode 1 at 100 percent power.
l On Wednesday, at 2 p.m., a power reduction was initiated for the scheduled
refueling outage.
l 2 SURVEILLANCE TESTING AND CALIBRATION CONTROL PROGRAMS (61725)
The purpose of this portion of the inspection was to ascertain whether the
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licensee had developed a program for the control and evaluation of Technical
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Specification required surveillance testing and calibration.
Also included in the inspection was the licensee's control of safety-related instrumentation
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not specifically controlled by Technical Specifications.
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2.1 Discussion
The inspectar reviewed the licensee procedures (Attachment 2), which were applicable to the control of the surveillance testing and calibration i
programs. The inspector also discussed the surveillance testing and calibration programs with the cognizant test and calibration personnel.
i The administrative requirements and responsibilities of the surveillance
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program were detailed in the Wolf Creek Nuclear Operating Corporation Procedure ADM 02-300, " Surveillance Testing," Revision 18. The procedure assigned the responsibility for scheduling surveillance activities and maintaining the status of surveillance tests to the surveillance coordinator.
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The responsibility to coordinate with other shift activities and to authorize the actual performance of the tests was assigned to the control room shift supervisor.
The licensee's administrative procedures for implementing the Technical-
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Specification surveillance testing requirements were found to be sufficiently i
detailed to provide positive control of plant surveillance activities. The l
procedures addressed areas such as test frequency, group responsibility, test status, and scheduling. Additional instructions were included for reviewing, evaluating, and reporting failures, and for taking corrective actions.
Surveillance scheduling, tracking, and completion status were accomplished with computer assistance.
There were no recent license amendments that related to Technical Specification surveillance test requirements, j
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A master schedule for surveillarce testing, calibration, and inservice testing had been established which included frequency for each test, calibration, j
inspection, and plant group responsible for performing each test and
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calibration.
The surveillance coordinator verified the responsibilities had
been assigned and maintained the master surveillance schedule.
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During the inspection, the inspectar witnessed three surveillance activities required by Section 4 of the Technical Specifications, and one calibration of safety-related instrumentation not specifically controlled by Technical Specifications.
The activities witnessed were performed using the following procedures:
STS-IC-507F, " Channel Calibration Steamline Pressure Transmitter
Protection Set 111," Revision 0; STS EF-100B, "ESW Inservice Pump B Test and ESW B/ Service Water Cross
Connect Valve Test," Revision 11; STS-EF-2108, "ESW System Inservice Check Valve Test," Revision 3; and f
STf! 203A RCP-B, " Seal Water Injection Flow," Revision 2.
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The personnel performing the surveillance and calibration activities were knowledgeable of the procedural requirements and kept c.
ations personnel
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informed of surveillance test status. The surveillance procedures clearly identified the Technical Specification requirements and acceptance criteria.
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The inspector verified that the instrumentation and control technicians
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perform:ng the test and calibrstion activities were qualified and used calibrated instruments.
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2.2 Conclusions
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The administrative procedures clearly defined responsibilities for the surveillance testing, calibration control, and inservice inspection and
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inservice testing of. pumps and valves programs,
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The administrative controls in place for scheduling and tracking surveillance j
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and calibration testing activities appeared to be good. Surveillance test
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procedures contained the appropriate elements and appeared to correlate with the Technical Specification requirements.
Personnel effectively implemented the surveillance testing and calibration j
control programs.
3 FOLLOWUP (92701)
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3.1 1 Closed) Unresolved Item (482/9209-03): Main Steam Safety Valve j
Testing-Vendor Test Supervisor Did Not Meet Qualifications Per ASME PTC 25.3 - 1976 During a previous inspection, the inspectors observed that a vendor's test
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supervisor did not_have the qualifications to meet ASME Code PTC 25.3 - 1976, paragraph 3.02, requirements (trevitest).
The available documentation did not
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-5-indicate that the qualification requirement had been recognized as being applicable. The licensee took the position that the assigned licensee maintenance engineer met the qualification requirements and was the " test supervisor."
During this inspection in a meeting with the onsite authorized nuclear inservice inspector representative and the cognizant licensee personnel, the inspector was provided a copy of an ASME code committee letter of response to the issue.
The letter, dated August 27, 1992, stated that the provisions provided by PTC 25.3 - 1976, paragraph 3.02, were permissive for the vendor's employee under the effective supervision of the qualifier. licensee employee.
Nevertheless, the licensee has, for future ap)lications, incorporated the code qualification requirements into the applicable vendor contract documents.
The inspector reviewed the trevitest, Procedure STS Mi-008, " Main Steam Safety Valve Settings," Revision 5, containing the test results of four valves tested on March 3, 1993.
Those valves were as follows:
ABV 0046
ABV 0055
ABV 0068
ABV 0076
There were no discrepancies noted.
This matter is closed.
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ATTACHMENT 1
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1. PERSONS CONTACTED 1.1 Licensee Personnel
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S. Austin, Shift Supervisor
- D. Gerrelts, Manager, Instrumentation and Control
- R. Hagan, Vice President, Nuclear Assurance
- W. Lindsay, Manager, Quality Assurance
- J. Lutz, Licensing Engineer
- 0. Maynard, Director, Plant Operations
- K. Moles, Manager, Regulatory Services
- T. Morrill, Manager, Radiation Protection W. Norton, Manager, Technical Support
- G. Pendergrass, Supervisor, Results Engineering
- F. Rhodes, Vice President, Engineering
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- R. Schmidt, Surveillance Coordinator W. Sheldon, Shift Supervisor
- J. Weeks, Manager, Operations
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- M. Williams, Manager, Plant Support
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J. Winkel, Authorized Nuclear Inservice Inspector 1.2 NRC Personnel
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- B. Nicholas, Senior Radiation Specialist
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- G. Pick, Senior Resident Inspector
In addition to the personnel listed above, the inspector contacted other personnel during this inspection period.
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- Denotes personnel that attended the exit meeting.
2 EXIT MEETING
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An exit meeting was conducted on March 5, 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 r
inspector.
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ATTACHMENT 2 ADMINISTRATIVE PROCEDU2ES REVIEWED ADM 02-300, " Surveillance Testing," Revision 18 ADM 08-807, "I&C Group Surveillance Testing," Revision 8 ADM 02-311, " Surveillance Test Master Cross-Reference and Review Requirements," Revision 6 ACM 02-312, " Mode Change Checklist and Surveillance Tracking Program,"
Revision 6 ADM 01-200, "TS Change Review," Revision 2 ADM 08-806, "I&C Group Calibration of Process Instrumentation and Special Maintenance," Revision 10 ADM 05-119, "lSI Program Plan Document," Revision 1 i
ADM 05-200, "ASME Code Testing on Pumps and Valves," Revision 1
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ADM 01-027, " Maintenance and Test Scheduling During Power Operations,"
Revision 7
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