IR 05000267/1983010
| ML20023D893 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/19/1983 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20023D892 | List: |
| References | |
| 50-267-83-10, IEB-80-11, NUDOCS 8306060126 | |
| Download: ML20023D893 (7) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/83-10 License:
DPR-34 Docket:
50-267 Category:
Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name:
Fort St. Vrain Nuclear Generating Station Inspection at:
Fort St. Vrain Site, flatteville, Colorado Inspection Conducted: April 1-30, 1983 Inspectors:
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W2JJ M. W. Dickerson, Senior Resident Reactor Inspector Date
$< U-13 G. L. Plumlee III, Resident Reactor Inspector Date Approved:
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.Pe# -U T. F. Westerman, Chief Date Reactor Project Section A Inspection Summary Inspection Conducted April 1-30, 1983 (Report:
50-267/83-10)
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Areas Inspected: Routine, announced inspection of Operational Safety Verification; Surveillance; Maintenance; Bulletin Followup; Follow Up of Previous Inspection Findings: and Review of Periodic and Special Reports. The inspection involved 189 inspector-hours onsite by two NRC inspectors.
Resul ts: Within the six areas inspected, no violoations or deviations were identified.
8306060126 830520 PDR ADOCK 05000267 G
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DETAILS 1.
Persons Contacted T. Borst, Radiation Protection Manager R. Burchfield, Results Engineering Supervisor W. Craine, Superintendent of Maintenance R. Craun, Nuclear Site Engineering Supervisor M. Denniston, Shift Supervisor D. Evans, Shift Supervisor W. Franek, Superintendent Operations W. Franklin, Shift Supervisor C. Fuller, Technical / Administrative Services Manager J. Gahm, QA Manager B. Gunnerson, Structural Supervisor Nuclear Projects J. Jackson, QA/QC Supervisor M. McBride, Operations Manager H. O'Hagen, Shift Supervisor T. Orlin, Superintendent QA Services G. Redmond, Maintenance QC Superviosr G. Reigel, Shift Supervisor T. Schleiger, Health Physics Supervisor L. Singleton, Superintendent Operations QA J. Van Dyke, Shift Supervisor
D. Warembourg, Manager Nuclear Production R. Webb, Maintenance Supervisor W. Woodard, Health Physicist The NRC inspectors also contacted other plant personnel including reactor operators, maintenance men, electricians, technicians, and administrative personnel.
2.
Licensee Action on Previous Inspection Findings (Closed) Violation (50-267/8231-02): Isolation Valve Shut for Radiation Transmitters RT 6314-1 and RT 6314-2. The valve was opened immediately and all supervisory personnel charged with the day-to-day administration of Procedure P-1 were instructed to ensure that all valve operations were completed in accordance with procedural requirements.
(Closed) Violation (50-267/8231-03): Surveillance $R 5.4.10-SA/BiA Was Not Performed in Accordance with the Procedural Requirements.
Personnel involved in the test were reminded of the correct method to add test equipment and that surveillances are to be performed as written unless modified by an approved deviation. The test was also modified in Issue 1, dated April 28, 1983, to include the proper test equipment.
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(Closed) Violation (50-267/8231-06): Failure to Utilize a Procedure During Removal and Replacement of a Section of Safety-Related Piping.
A training class for all maintenance personnel has been conducted which reviewed the procedural process for handling situations of this type as they occur. Additionally, the individuals directly involved were instructed by their supervisors as to the correct method for handling repairs of *.his type.
(Closed)
Ope.. : tem (8231-04): Corrections to EMP 43 (CAAR-592).
The problems previously identified have been corrected by Issue 3 of EMP 43 dated March 25, 1983.
3.
Operational Safety Verification The NRC inspector reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements, and the licensee's management control system is effec-tively discharging its responsibilities for continued safe operation.
The review was conducted by direct observation of activities, tours of the facility, interviews and discussions with licensee personnel, independent verification of safety system status and limiting conditions for operations, and review of facility records.
Logs and records reviewed included:
Shift Supervisor Logs
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Reactor Operator Logs
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Equipment Operator Logs
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Auxiliary Operator Logs
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Technical Specification Compliance Logs
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Operations Order Book
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Operations Deviations Reports
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Clearance Log
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Temporary Configuation Reports
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Plant Trouble Reports
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During tours of accessible areas, particular attention was directed to the following:
Monitoring Instrumentation
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Radiation Controls
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Housekeeping
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Fluid Leaks
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Piping Vibrations
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Hanger / Seismic Restraints
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Clearance Tags
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Fire Hazards
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Control Room Manning
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During a review of EMP 40, " Discharging and Testing Battery Cells,"
Issue 3, dated March 25, 1983, the NRC inspector determined that Step 3.7.1 references an Attachment EMP 40A - Storage Battery Record,
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that was not attached to the procedure. This was discussed with the licensee whose followup review indicated that their master copy also did not contain the required attachment. The licensee was informed that this is considered an open item (8310-01) pending incorporation of the required attachment.
During a tour of the reactor building on April 20, 1983, the NRC inspector identified test equipment in use for load testing
'n'all Number 87 that appeared to be out-of-calibration due to an attached calibration sticker that indicated that calibration of the instrument was over due. Discussions with the licensee and contractor performing the load test indicated that the test equipment, compression gages, had been calibrated prior to the contractor coming to the site and that the calibration records would be included with the contractor's test report. The licensee was performing a test of the bond between the boundary and the masonary block mortar joint in conformance with his reply of January 11, 1983, P-83022, in response to Bulletin 80-11. The licensee was informed that this is an open item (8310-02) pending the NRC inspector's review of the appropriate calibration record.
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The NRC inspector reviewed Clearance 5459 for C-2104 "D" circulator for proper preparation and verification of handswitch and valve position and tagging as required. The critical valves were also identified as required to comply with the licensee's commitment on independent verification of sealed / critical valves.
During a review of the Temporary Configuration Report Log (TCR),
the NRC inspector determined that TCR 82-10-11 addressing the installation of a blind flange on the Purge Vacuum Pump C-1302 mechanical safety to prevent leakage was still logged as being in effect. However, the NRC inspector was aware that this blind flange had been removed previously. This was discussed with the licensee and verified to be the case. The licensee has closed this TCR.
No ' violations or deviations were identified.
4.
Surveillance (Monthly)
The NRC inspector reviewed aspects of surveillance testing involving safety-related systems. The review included observation and review relative to Technical Specification requirements. The surveillance tests reviewed and observed were:
SR 5.4.13-A 480 Volt Switchgear Room Temperature Indicator and-Alarm Calibration SR 5.3.2-W Main and Reheat Valve Partial Stroke Test SR 5.2.16b-M PCRV Closure Leakage Instrumentation Functional Test During a review of SR 5.4.13-A on April 5,1983, the NRC inspector determined that the calibration acceptance criteria for the calibration of TI-75191 was not in accordance with RP 168,
"Foxboro Model 693A EMF-To-Current Converter Operation, Maintenance and Calibration." This was brought to the licensee's attention whose followup review indicated a change to the acceptance criteria at which TS-75191 trips was also necessary. These problems were corrected in Issue 7 of SR 5.4.13-A dated April 20, 1983.
No violations or deviations were identifie.
S.
Maintenance (Monthly)
The NRC inspector reviewed records and observed work in progress to ascertain that the following maintenance activities were being conducted in accordance with approved procedures, Technical Specifications, and appropriate Codes and Standards. The following maintenance activities were reviewed and observed:
PTR 3-516 Repair C2104 "D" Circulator Steam Outlet to Stem Inlet Pipe Flange Leak in Accordance With MP 21-15, " Helium Circulator Change Out Procedure" as Modified by Procedure Deviation Report 83-102 and MP 100, " General Welding Procedure" PTR 4-96 MT-1119 Low Light Level Problem Repair in Accordance With RP-385, " Moisture Monitor Flow Verification," and RP-488,
" Pulling Moisture Monitor Penetration Covers" Ci4 1565/CWP 83-24 Install one Cryogenic Chiller Unit for Testing.
Provide Cold Refrigerant to Two Moisture Monitors MT-1116 and MT-1122.
PTR 2-24 HV-2224, Loop 2 Main Steam Stop-Check Valve, Repair in Accordance with MP-22, " Maintenance and Repair of Rockwell-Edwards Valves, Pressure Seal Type," MP-100, " General Welding Procedure," and MP 91-15, " Maintenance and Repair of System 91 Hydraulic Valve Actuators" No violations or deviations were identified.
6.
Report Reviews The NRC inspector reviewed the following reports for content, reporting requirements, and adequacy:
Monthly Operations Report, March 1983 Report of Changes, Tests, and Experiments, January 1,1982 through December 31, 1982 (Revised Copy)
Revised Copy of 26th Startup Report, November 23, 1982, through February 22, 1983.
7.
Exit Interview Exit interviews were conducted at the end of various segments of this inspection with Mr. D. Warembourg, Manager, Nuclear Production, and/or other members of the Public Service Company staff. At the interviews, the NRC inspectors discussed the findings indicated in the previous l
paragraphs. The licensee acknowledged these findings.
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