IR 05000267/1979007
| ML19261E113 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/20/1979 |
| From: | Dickerson M, Verduzco G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19261E111 | List: |
| References | |
| 50-267-79-07, 50-267-79-7, NUDOCS 7907050146 | |
| Download: ML19261E113 (8) | |
Text
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF Ii15PECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/79-07 Docket No. 50-267 License No. DPR-34 Licensee: Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name: Fort St. Vrain Nuclear Generating Scation Inspection At: Fort St. Vrain Site, Platteville, Colorado Inspection Conducted: April 2-6, 1979 Inspector: 7, [ M
- /2.o/;v M. W. Dickerson, Reactor Inspector Date dim d.be-A/m
- Ti. H. Verduzco, Reactor'4hspector Date ' Approved By: 7- [ F/' */77 T. F. Westerman, Chief, Reactor Projects Date Section Irspection Summary Insp 'ction on April 2-6, 1979 (Report No. 50-267/79-07) A-eas Inspected: Routine, unannounced inspection of calibration technical ~specification (T/S) specified; calibration non-T/S specified; plant operations and follow-up on inspector identified and unresolved problems.
The inspection involved sixty-four (64) inspector-hours on-site by two (2) NRC inspectors.
Results: f, ] items of noncompliance or deviations were identified.
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-2-Details 1.
Persons Contacted Public Service Company of Colorado
- L. Brey, QA Panager
- W. Franek, Results Supervisor W. Franklin, Shift Supervisor, Operations
- J. Gaba, Supervisor Technical Services
- W. Hillyard, Administrative Services Manager
- T. Howard, Superintendent Operations QA
- F. Mathie, Operations Manager G. Riegel, Reactor Operator L. Singleton, Shift Suptrvisor, Operations J. Solakiewicz, QA Engineer
- D. Warembourg, Manager Nuclear Production R. Weber, Instrument Technician G. Wiltschack, Results Engineer R. Wolium, Instrument Technician P. ~.immerman, Senior Results Technician
- Actended Exit Interview.
2.
Licensee Action on Previcus Inspection Findings (Closed) Inspector Follow-up Item (IR 50-267/76-09) Conditional Quali-fication of ASME Vendors. ASME Vendors will be considered qualified for those items covered by the ASME certification.
(0 pen) Unresolved Item (IR 50-267/76-13) Records of Plant Operating Cycles.
Formal administrative controls have not been established.
Moreaver, the engineering analysis required to establish the basis for these controls has not been completed.
During this inspection, the licensee was requesteo to add this item to their commitment list and to establish a formal completion date.
(Closed) Unresolved Item (IR 50-267/78-13) Determination of compliance with LCO's.
Procedure PM-30W " Technical Specification Compliance Log," Revision 5, was issued on March 12, 1979, to document the status cf compliance with limiting conditions for operation on a daily basis.
(Closed) Inspector follow-up item (IR E7-267/79-03) Surveillance Procedure 5.G.2a-W " Station & PPS Battery Check" was changed in Revi-sion 9 dated February 13, 1979, to provide for temperature corrections for specific gravity and for the use of a calibrated thermometer.
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-3-3.
Review of Plant Operations - A review of plant operations was conducted to ascertain whether facility operation was in conformance with the requirements estab-lished in Technical Specifications, 10 CFR, and administrative proce-dures, or licensee comnitments discussed in correspondence to the commission.
included in the inspection were observation of control room activities, review of operational logs and records, and a tour of accessible areas.
Logs and records reviewed included: Shift Supervisor Log (February 5-April 4,1979) Reactor Operators Log (February 5-April 4,1979) Turbine Building Logs (February 5-April 1,1979) Electric Plant Log (February 5-February 28, 1979) Surveillance Logs 1-3 (February 5-February 24, 1979) Operating Order Book Form 1 Log (je '" log) Plant Trouble Report During the tour of accessible areas, particular attention was directed to the following: Monitoring Instrumentation Radiation Controls Housekeeping Fluid Leaks Piping Vibrations Hanger / Seismic Restraints Clearance Tags Annonciators Control Room Manning During this tour, the inspector noted several items requiring remedial action: Water from check valve 46722 (PCRV cooling system) was observed to be leaking into a cable tray.
Inspection by plant electrical department personnel revealed minimal accumulation of water within the cable tray.
A plant trouble report was initiated April 4,1979, for repair of check valve 46722.
The oil reservoir level in seismic restraint MSS-149 was noted to be excessively low.
A licensee representative 286 357 .
-4-indicated that all seismic restraints would be inspected prior to startup. This is an open item.
Houseleeping in various areas of the reactor and auxiliary buildings was in need of attention.
A licenses representative has indicated that housekeeping deficiencies have been corrected.
Both emergency diesel generators had a greater than normal accumula-tion of oil beneath them.
Licensee representatives indicated that a cleaning schedule will be developed to preclude recurrence of this problem. This is an open item.
The inspector witnessed performance of the weekly functional test of the radioactive gaseous effluent vent monitor system (5.8.1d-W).
No items of noncompliance or deviations were identified.
4.
Calibration - T/S Specified The inspector reviewed surveillance records, procedures, qualifications of individuals perfoming calibration, and held discussions with representatives of the licensee to detennine whether calibration of components and equipment were in conformance with the requirements of the Technical Specifications.
However, since no T/S required calibrations were scheduled during the inspection, no calibraticr.s were witnessed.
Records of the following calibrations were revieved: SR 5.2.7.d-A Water Turbine Instrument Calibration, Revision 11.
Calibration completed January 19, 1979.
T/S 5.2.7.d.
Instruments and contrc's associated with both turbine water removal pumps and the turbine water removal tank, calibrated annually.
SR 5.3.1-R Steam Water Dump Tank Level Indicator Calibration, Revision 8.
Calibration completed January 27,1978(scheduled for completion during the current refueling out-age).
T/S 5.3.1.
The steam water dump tank level indi-cators calibrated at each refueling.
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-5-SR 5.4.1.1.3c-R Startup Channel Scram Calibration, Revision 13.
Calibration completed December 1, 1978.
T/S 5.4.1.1.3.c.
Internal test signals and trip set points, calibrated at each refueling.
SR 5.4.1.1.9c.-R Primary Coolant Pressure Scram Cali .on, Revi-sian 10.
Calibration completed March 1,1979.
T/S 5.4.1.1.9.c.
Internal test signals and trip set points, calibrated at each refueling.
SR 5.4.1.2.1h-R Steam Pipe Rupture (Pipe Cavity) Calibrai. ion, Revi - sion 12.
Calibration completed March 10, 1979.
T/S 5.4.1.2.1.h.
Pressure sensors, calibrated at each refueling.
SR 5.4.4.A2 PCRV Cooling Water System Temperature Calibration, Revision 9.
Calibration completed February 7,1979.
T/S SR.5.4.4.
Thirty-six outlet subheader temperature indicators and ninety-seven liner cooling tube outlet thermocouples, calibrated annually.
SR 5.4.13-A 480 Volt Switchgear Room Temperature Indicator and Alann Calibration, Revision 1.
Calibration completed January 8, 1979.
- T/S 5.4.13 Temperature indicator and aldria, calibrated annually.
SR 5.5.2.Al Reactor Building Pressure Relief, Revision 7.
Calibration completed March 27, 1979.
T/S 5.5.2 Overpressure relief system differential precsure switches, calibrated annually.
SR 5.8.2c-Q Radioactive Liquid Effluent Activity, Revision 13.
Calibration completed December 18, 1978.
T/S 5.8.2c.
Activity monitors, calibrated quarterly.
Primary Standards: Oscilloscope M-3197, calibrated January 31, 1978 Frequency Counter M-3178, calibrated March 2, 1978 Thermocouple Indicator M-3161, calibrated June 12, 1978 fio items of nonconfonnance or deviations were identified.
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-6-5.
Calibration - System 21 Instruments The status of the system 21 instruments required to be calibrated and/or functionally tested prior to resumption of operation following the first refuel'ng cutage (I&E letter dated November 1,1978) was determined to be as follows: Instrument No.
Date Calibrated PDS-2152 3/6/79 PC-21105 3/9/79 PT-21105 3/9/79 XEP-21105 3/9/79 XPS-21105 3/9/79 PIC-21106 3/6/79 LS-21130 3/30/79 LS-21288 2/17/79 LIS-21474 3/4/79 LIS-21475 3/4/79 LIS-21476 3/4/79 LIS-21477 3/3/79 LSL-21116 Remain to be calibrated during refueling PS-21120 " XSL-21185 " XSL-21187 " . XPS-21183 " LS-21385 " LSH-21451 " LSH-21452 " LSH-21453 " LS-21502 " LS-21287 " PI-21358 Require change notica completion prior to calibration PI-21359 " No items of nonconformance or deviatior.s were identified.
6.
Calibration (non-T/S) The inspector reviewed calibration procedure _ scords to ascertain whether components and equipments associated. safety related sys-tems, and/or functions not identified in the Technical Specifications as requiring calibration at a specific frequency, are calibrated in accordance with specific requirements established by the licensee.
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. . -7-Calibration procedures and records of the following instruments were reviewed.
SM-2105 Circulator 1A Steam Turbine Speed Modifier, calibrated May 17, 1978 Results Procedure (RP) 17, Spee1 and Wobble Measurement System Master and Slave Module Calibration, Revision 2, April 25, 1978.
SM-21161 Circulator 1A Speed Modifier, calibrated May 24, 1978.
RP-17, Speed and Wobole Measurement System Master and Slave Module Calibration, Revision 2, April 25,1978.
PDIS-21191 Circulator 1A Seal System, calibrated July 1,1978.
RP-89A, Calibration of Barton Differential Pressure Switch, Revision 4, May 10, 1978.
LT-21124 Circulator ID HP Separater, calibrated June 11, 1977.
RP-153, Calibration of Foxboro Differential Pressure Transmitter, Revision 2, March 20, 1978.
LC-2135 Bearing Water Surge Tank 1A, calibrated February 8,1978.
RP-181, Masoneilan Pressure and Temperature Controller Calibration, February 5,1976.
PDIS-2155 Loop 1 Bearing Water Filters, calibrated March 11, 1978.
RP-89A, Calibration of Barton Differential Pressure Switch, Revision 4, May 10, 1978.
FSL-21298 Bearing Water Cooler IC-ID Outlet, calibrated September 18, 1978.
RP-89A, Calibration of Barton Differential Pressure Switch, Revision 4, May 10, 1978.
FV-21333 Bearing Water Make-up to LP Separater, calibrated tiovember 15.
1978.
RP-89A, Calibration of Barton Differential Pressure Switch, Revision 4, May 10,1978.
ZI-2205 Loop 1 Feedwater, calibrated September 13, 1978.
RP-91, Moog DC Servocontroller Calibration, Revision 2, April 4, 1978.
F:' '?06-/ Loop 2 Feedwater Servo Amplifier, calibrated September 18, 1978.
RP-91, Moog DC Servocontroller Calibration, Revision 2, April 4, 1978.
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. . -8-Procedures examined in conjunction with the foregoing calibrations had been reviewed and approved as required by facility Technical Specifi-cations.
The calibrations and procedures contained no apparent incon-sistencies wit Technical Specification.
The inspector witnessed calibration of Buffer Helium Recirculator C 2106 S (LIS 21476). Trip settings of 12 and 21 inches of water were verified pursuant to Results Procedure 89A, using instruments M3149 (Wallace and Tierman Pressure Gage) and M3140 (Simpson Electronic VOM).
Both M3149 and M3140 were certified by Electric Standardizing Laboratory of Denver, Colorado, to be within manufacturers specifications, as indicated by test instruments traceable to the National Bureau of Standards.
Certification dates for these instru-ments are February 23, and February 28, 1979, respectively.
The inspector also witnessed partial calibration of Buffer Helium Recirculator C2105 (LIS 21475).
No items of noncompliance or deviation were identified.
7.
Report Review The inspector reviewed the Fort St. Vrain Juclear Generating Station r Annual Report #8, January-December 1978, and Report of Changes, Tests, and Experimcnts Not Requiring Prior Conmission Approval Pursuant to 10 CFR 50.59(A), January 1,1978-December 31, 1978.
No items of nonconfomance or deviation were identified.
8.
Exit Interview An exit interview was conducted with representatives of the licensee on April 6,1979, at the conclusion of the inspection.
At the inter-view, the inspectors discussed the findings indicated in the previous paragraphs. The licensee acknowledged t'ese findings.
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