IR 05000482/1990011
| ML20033G981 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/05/1990 |
| From: | Stetka T, Wagner P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20033G979 | List: |
| References | |
| 50-482-90-11, NUDOCS 9004130257 | |
| Download: ML20033G981 (8) | |
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APPENDIX
U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
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NRC Inspection Report:
50-482/90-11 Operating License: NPF-42 Docket: 50-482 Licensee: Wolf Creek Nuclear Operating Corporation (WCN00)
P.O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: WCG3, Burlington, Kansas
Inspection Conducted: March 26-30, 1990
Inspector:
Q C. Wo4A f/5/90
P. C. Wagner, Regetor Inspector, Plant Systems Date Section, Division of Reactor Safety i
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Approved:
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etka, 011ef, Plant Systems Section Data isi{nofReactorSafety g
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Inspection Sunnary j
l Inspection Conducted March 26-30, 1990 (Report 50-482/90-11)
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Areas Inspected: Routine, uniannounced inspection of the licensee's instrument
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calibration program and followup on previous reportable events.
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Results: While no violations or deviations were identified, some
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instrumentation calibration program shortcomings were noted. The inspector
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observed that while some of the calibration procedures contained detailed, step-by-step instructions, others did not.
In particular, the inspector found the lack of guidance on actions to be taken for discovered out-of-tolerance
conditions to be a program shortcoming. The inspector also found the lack of a formal, broad, trending program to be a shortcoming of the instrumentation calibration program at the WCGS.
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9004130257 900406 s
PDR ADOCK 05000482 O
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DETAILS
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PERSONS CONTACTED
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WCGS Personnel
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- J. Bailey, Vice President, Nuclear Operations
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- H. Chernoff, Supervisor, Licensing
- R. Flannigan, Manager, Nuclear Systems Engineering
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- C Fowler, Manager Instrumentation and Controls (I&C)
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D. Gerrelts I&C Engineer i
- R. Holloway, Manager, Maintenance and Modifications
- W. Lindsay, Manager. Quality Assurance (QA)
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- C. Parry, Manager, Site QA
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- F. Rhodes, Vice President, Engineering and Technical Services
- S. Wideman, Licensing Specialist III
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- M. Williams, Manager, Plant Support l
NRC Personnel
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- D. Garrison, Reactor Inspector, Region IV
- M. Skow, Senior Resident Inspector, WCGS
- R. Stewart, Reactor Inspu ' r, Region'lV
The inspector also contac 9d other members of the licensee's staff during the
inspection.
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- Denotes those personnel in attendance at the exit meeting held on March 30,
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1990.
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2.
FOLLOWUP (92701)
j (Closed)Part21 Report 87-03:
Foxboro Corporation Capacitor Degradation.
By letter dated June 4,1986, Foxboro Corporation informed the NRC and affected i
licensees-that the aluminum electrolytic capacitors utilized in some Foxboro equipment could slowly degrade. The report was submitted in accordance with
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the provisions of 10 CFR Part 21 and provided licensees recommended corrective
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actions. The report stated that "H-Line" and " SPEC 200" power supplies, older than 10 years, should be refurbished or replaced.
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The inspector reviewed the Industry Technical Information Review and Evaluation Form (ITIP-0008) implemented by the licensee in response to this issue. The licensee's ITIP evaluation determined that "H-Line" equipment was not utilized at the WCGS in critical applications and that " SPEC 200" power supplies were used. The recommended corrective actions at the WCGS consisted of' verifying the calibration of the " SPEC 200" and oth r large power supplies on an 18-month t
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frequency.
In addition, the inspector verified that the instrument and control (INC) preventative maintenance data base had been revised to include provisions
for the replacement of the electrolytic capacitors (or the replacement of the
entirepowersupply)ona10-yearinterval.
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This item, which was tracked by the licensee under Log No.87-011, is closed.
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INSTRUMENTATION CALIBRATION (56700)
The inspector evaluated the instrument calibration program being implemented by
the licensee through procedure reviews, record reviews, and design documentation evaluations. The inspector selected nine parameters listed in
the Technical Specifications (TSs) for detailed review. The selected
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parameters were-t Reactorcoolantpump(RCP)underfrequency
Turbine trip on low oil pressure
. Low power trip block
Pressurizer low pressure
Auxiliary feedwater (AFW) auto start
l AFW flow indication
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l AFW suction pressure indication
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Automatic switchover from refueling water storage tank l
The inspector also reviewed various abnormal conditions operating procedures to I
select additional instrument samples. The inspector selected the following instrumentation, which was utilized in the performance of plant operations, but
not specifically listed in the TSs:
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Essential service water strainer differential pressure
Volume control tank level l
Boric acid flow
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RCP seal water flow
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l The inspector reviewed the technical content of the procedures for calibrating
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the instrumentation that measured the above parameters. The inspector evaluated if the procedures provided the following provisions:
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Prompt reporting of out-of-tolerance conditions
Prerequisites
Record of as-found and as-left values
Sign-off or initial for completion of steps
Review of test results I
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Independent verification of valve lineups
1, A listing of the calibration and operating pro::edures that were reviewed is
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included in the Attachment to this report.
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-4-During the process of reviewing the completed calibration records for trends, the inspector noted a problem with the calibrations of some seismic instruments. The calibrations that were performed in 1985 and early 1986, documented as-found conditions that were outside of the required tolerances for i
these instruments. The out-of-tolerance conditions were not, however, j
documented as having been evaluated. The inspector discussed this problem with
licensee personnel and was informed that similar problems had been identified
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by earlier NRC inspections and had been corrected. The inspector found Violation 482/8632-01 to document the type of problem discussed; the licensee's corrective actions were found acceptable in NRC Inspection Report 50-482/88-21, and the violation was closed.
The impector did not identify any recent occurrences in which out-of-tolerance conditions had not been evaluated. However, the inspector did note that the instructions to report out-of-tolerance conditions to the shift supervisor for a Technical Specification determination were not included in all applicable proceduras.
In particular, the recent revision of the above Seismic Instrument Calibration Procedure STS 1C-895, " Analog Channel Operational Test Triax Time History and Response Spectrum Recording System," Revision 4, dated February 28, i
1990, contained no instructions on what should be done if an out-of-tolerance i
condition was detected. The inspector recommended that the licensee consider being more consistent in providing procedural guidance to those implementing test procedures.
The inspector also verified that the instrumentation response times were bein0 verified to be within the TS required limits by evaluating the testing performed on the RCP UF instruments. The instrument calibration procedure verified that the instrument responded within prescribed limits, and other test procedures verified that the response times of the electronics loop, logic relays, and reactor trip breakers were within their limits. The inspector verified that the additive time limits were within the TS requirement.
In order to assess the appropriateness of the inputs being used for component calibrations and actuation setpoints, the inspector evaluated the scaling information for two of the instrument loops inspected. The inspector reviewed the flow orifice manufacturer's data for the AFW flow instruments to verify I
that the test differential pressures, being used to simulate the flow j
conditions, corresponded to the manufacturer's recommendations. The inspector i
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also reviewed the basic Westinghouse Corporation scaling information, and
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substituted WCGS plant-specific data collected during initial startup testing, to verify turbine impulse pressure settings. The inspector verified that the trip voltages corresponded to appropriate turbine first stage shell pressures that were, in turn, equivalent to the percentages of rated thermai power requirca by the TS.
The inspector discussed the advantages of an aggressive tracking and trending l
program with involved licensee personnel. The licensee had recently
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-5-implemented an informal program which included plotting the results of various transmitter surveillance data. The inspector recommended that the trending program be continued and expanded.
No violations or deviations were identified.
EXIT INTERVIEW (30703)
An exit interview was conducted on March 30, 1990, with the licensee representatives identified in paragraph 1.
During this interview, the inspector reviewed the scope and findings of t!.e inspection as detailed in this report. Although some proprietary documents wera reviewed by the inspector, no
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proprietary documents were removed f rom the facility, and no proprietary information is contained in this report.
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ATTACHMENT'
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List of Documents Reviewed Instrument Surveillance Test Procedures / Records-TS:
(AllnumbersprefixedwithSTSIC-)
201 Analog Channel Operational Test 7300 Process Instrumentation Protection Set 1 211A Actuntion Logic Test Train A Solid State Protection System 218 RCP Underfrequency Trip Actuating Device Operational Test 219 RX Trip on Turbine Auto Stop TADOT 502A Calibration of Pressurizer Pressure Transmitters 502B Channel Calibration of 7300 Process-Pressurizer Pressure Instrumentation 50EA Calibration of Steam Generator Narrow Range Level Transmitter 505B Channel Calibration Steam Generator Necrow Range Level 506A Channel Calibration-Impulse Chanber Pressure 506B Calibration of 7300 Process-Turbine Impulse Pressure 508A Refueling Water Storage Tank Level Transmitter Calibration 508B Channel Calibration of 7300 Process-Refueling Water Storage Tank 540B Channel Calibration AFW System Flow
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to Steam Generator B
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565 Channel Calibra^, ion AP. Pump Suction
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Pressure Indication for Remote
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Shutdown Panel
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680 Channel Calibration for Turbine Trip on Low Hydraulic Fluid Pressure 72SC 7300 Process and N.I. Response Time Test (2/4 Logic) Protection Set 111 727A Solid State Protection System Train A Response Time i
746A Reactor Protection System-Reactor Trip Breaker "A" Time Response Testing 801TI RCP B Underfrequency Channel Calibration 892 Channel Calibration Triaxial Peak Recording Accelerographs
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894 Channel Calibration Triaxial Time History and Response Spectrum Recording System 895 Analog Channel Operational Test
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Triax Time History and Reponse Spectrum Recording System Surveillance Test Procedures - Non-Technical Specification:
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205A Calibration of RCP C Seal Water
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l Injection Flow Transmitters l
234 Channel Calibration - Boric Acid Transfer Pump to Charging Pump Suction Flow Transmitter
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l 4198 Channel Calibration of the Volume Control l
Tank Level Instrumentation 455 Channel Calibration ESW Self-Cleaning a
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Strainer Differential Pressure Other Facility Procedures:
SV7-SF07.a Startup Adjustments of Reactor
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Control System
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-3-0FN 00-014 Hot Standby. to Cold Shutdown from Outside the Control Room 0FN 00-017 Control Room Evacuation 0FN 00-022 Plant Cooldown Concurrent with an Instrument Bus failure OFN 00-027 Loss of Vital 480 VAC Bus Drawings:
435-005-12 PERMUTIT Outline Drawing -
Concentric Orifice Plates M-716-083-04 SNUPPS Process Control Block Diagram Turbine Impulse Chamber Pressure l
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