IR 05000482/1986029
| ML20205R659 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/31/1987 |
| From: | Hunnicutt D, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20205R629 | List: |
| References | |
| 50-482-86-29, NUDOCS 8704060406 | |
| Download: ML20205R659 (4) | |
Text
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.o APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-482/86-29 License: NPF-42 Docket: 50-482 Licensee: Wolf Creek Nuclear Operating Corporation (WCNOC)
P. O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: WCGS site in Coffey County, Kansas Inspection Conducted: October 20-24, December 9-12, 1986; and February 23-24, 1987 l,
7 Inspector:
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R.'C. Stewart, Reactor Inspector, Operations Date /
Section, Reactor Safety Branch Approved:
N 3/3//D y
./ g D. M. Hunnicutt, Chief, Operations Section Date '
F Reactor Safety Branch Inspection Summary Inspection Conducted October 20-24, December 9-12, 1986; and February 23-24, 1987 (Report 50-482/86-29)
Areas Inspected: Routine, unannounced. inspection of the licensee's calibration program relating _to plant instrumentation specified by Technical Specifications.
Results: Within the area inspected, no violations or deviations were identified.
8704060406 870401 DR ADOCK 0500
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-2-DETAILS 1.
Persons Contacted Kansas Gas & Electric (KG&E)
- W. M. Lindsay, Supervisor, Quality Systems
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- G. D. Boyer, Plant Manager F. T. Rhodes, Vice President, Nuclear Operations C. M. Estes, Superintendent of Operations'
- K. R. Petersen, Lead Engineer, Licensing
- G. J. Pendergrass, Licensing Engineer
- C. J. Hoch, QA Tech Other
- R.
F. Rowe, Jr., I&C Coordinator D. Gerrelts, Senior Engineer, Specialist The NRC inspector also contracted other licensee personnel _during the inspection.
- Denotes those attending the exit interview conducted December 12, 1986.
2.
Calibration This inspection was to ascertain whether the licensee had developed and i
implemented a program for the control and evaluation of instrument calibrations and channel functional tests-specified by Technical Specifications (TS) for the following systems:
Reactor Protection Emergency Core Cooling Activation Reactivity Control Plant Auxiliary Reactor Coolant Electrical Distribution The inspection included the determination that procedures had been established for the calibration program administrative controls and implementation as prescribed by the WCGS FSAR, Section 7.0 and related
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commitments to Regulatory Guides and Standards. The NRC inspector's review included the following principal procedures:
ADM 02-104 Surveillance Testing ADM 01-012 I&C Supervisor Duties and Responsibilities
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.o-3-ADM'01-210 Calibration and Control of Maintenance, Measuring-and Testing ADM 08-806 I&C Group Calibration of Process Instruments and Special Maintenance ADM 08-807-I&C Group Surveillance Testing ADM 08-850 Protective' Relay Maintenance and Recalibration ADM 05-103 WCGS Total-Plant Setpoint Document ADM 08-805 I&C Personnel Training
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In conjunction with th'e above review, the NRC inspector verified;that instrument calibration, channel calibration, and channel functional testing were performed at the TS required frequency by reviewing the licensee's " Surveillance Scheduling and Tracking" procedure data base computer printout dated October 23, 1986, for approximately 50 percent of each of the systems noted above.
No discrepancies were identified.
In addition, the NRC. inspector examined seven completed. test and calibration procedures for surveillances performed during the prior 18 months. The objective was to verify that approved procedures were utilized, acceptance criteria were met, performance was in accordance with the procedure, and the procedure contained "as found" conditions.
Specific procedures reviewed were as follows:
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STS-1C-901 Analog Channel Operation Test RCS Cold Over Pressure
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Protective Instrumentation
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STS-1C-725A 7300 Process and N.I. Respo'nses Time' Test (NOTE:
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Nuclear Instruments (N.I.))?
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STS-1C-908A Channel Calibration Accumulator Level: Transmitter
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STS-1C-431 Channel Calibration NIS Source = Range N31
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- .t STS-1C-500F Channel Calibration Dt/T Avg.JInstrumeiltation Loop 3
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STS-1C-505B ChannelCalibrationSteamGeneratorNarrow;RangeLevel_
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L STS-1C-782 Loss of Power - ESF Response Time. Test _ Separation,,
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GR-1 & 2 Channel II
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In addition, the NRC inspector conducted a walkthrough with a licensee test engineer during the performance of a slave relay test, K634 Train B (STS-1C-6348, Revision 1) Steam Line/Feedwater isolation. _
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No violations or deviations were identified.
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Exit Interview-
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l The inspection scope and findings'were summarized on December 12; 1986,.
with the resident inspectors'and licensee personnel indicated in paragraph 1--
above.
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