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| {{Adams
| | #REDIRECT [[IR 05000395/1989013]] |
| | number = ML20246A534
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| | issue date = 08/04/1989
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| | title = Insp Rept 50-395/89-13 on 890701-31.Violation Noted.Major Areas Inspected:Monthly Surveillance Observations,Monthly Maint Observation,Operational Safety Verification,Action on Previous Insp Findings & Other Areas
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| | author name = Cantrell F, Hopkins P, Prevatte R
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| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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| | addressee name =
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| | addressee affiliation =
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| | docket = 05000395
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| | license number =
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| | contact person =
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| | document report number = 50-395-89-13, NUDOCS 8908230003
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| | package number = ML20246A526
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| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
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| | page count = 8
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| }}
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| See also: [[see also::IR 05000395/1989013]]
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| =Text=
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| 101 MARIETTA STREET,N.W.
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| ATLANTA, GEORGIA 30323
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| > Report No.':: 50-395/89-13: A
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| Licensee:. South Carolina Electric & Gas Company ^
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| Columbia, SC 29218
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| G
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| Docket No.:":50-395 License No.: NPF-12.
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| . .
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| Facility Name': V. C. Summer
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| Inspection Conducted:.-July;1 .31,<1989
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| Inspectors:
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| ~
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| b
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| R. 'L.- Prevatte
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| M Yh f 9 f
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| Date' Signed
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| l @h,idd A 7A//89
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| P. C'. Hopkins Date Signed. -
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| Approved by: Ms
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| F.1 .~ Cantrell, Secti ef
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| Da,te Signed
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| * '
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| ' Division of Reactor Pr ects
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| SUMMARY
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| Scope:
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| This routine inspection was conducted.by the resident inspectors onsite in the
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| areas of' monthly surveillance, observations, monthly maintenance observation,
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| operational: safety verification, action' on previous inspection findings,' and:
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| other areas.' Certain tours were conducted'on backshifttor weekends. Backshift
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| or weekend tours were conducted on July 11, 12, 13, 18, 19. 23,'24, 25 .and 26,
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| 1989.-
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| Results:
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| The unit began the month at 100 percent power. A trip from 100 percent power
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| occurred.on July 11, 1989, as the result.of a maintenance technician shorting.
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| + ' out a power supply- for the generator stator water cooling system. The unit
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| trip and SCE&G grid heavy loading resulted in a loss of offsite power with a
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| transfer. of the. safety related buses to the emergency diesel generators,
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| paragraph 4.b. The unit was restarted and returned to power on July 13, 1989.=
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| l , It ' operated at full ' power for the remainder of the' month.- The areas of
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| maintenance and: surveillance continue to' perform satisfactorily. A violation
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| for failure to control the temporary installation of portable demineralizers
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| was identified, paragraph 4.c. The licensee's evaluation 'of this event
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| determined that' although a seismic event could effect the operation of safety
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| equipment, the affected systems would still continue to operate satisfactorily.
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| 8908230003 890804
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| FDR ADOCK 05000395
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| REPORT DETAILS
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| 1.- Persons Contacted
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| Licensee Employees
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| W. Baehr, Manager, Chemistry and Health Physics
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| C. Bowman, Manager, Scheduling and Modifications !
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| *0. Bradham, Vice President, Nuclear Operations
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| M. Browne, Manager, Systems Engineering & Performance
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| W. Higgins, Supervisor, Regulatory Compliance
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| S. Hunt, Manager, Quality Systems
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| *A. Koon, Manager, Nuclear Licensing
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| G. Moffatt, Manager, Maintenance Servic2s
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| D. Moore, General Manager, Engineering Services
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| *K. Nettles, General Manager, Nuclear Safety
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| C. Price, Manager, Technical Oversite '
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| M. Quinton, General Manager, Station Support
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| J. Shepp, Associate Manager, Operations
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| J. Skolds, General Manager, Nuclear Plant Operations
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| *G. Soult, General Manager, Operations and Maintenance
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| .
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| G. Taylor, Manager, Operations
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| D. Warner, Manager, Core Engineering and Nuclear Computer Services
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| *M. Williams, General Manager, Nuclear Services
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| K. Woodward, Manager, Nuclear Operations Education and Training
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| Other licensee employees . contacted included engineers, technicians,
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| operators, mechanics, security force members, and office personnel.
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| * Attended exit interview
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| Acronyms and initialisms used throughout this report are listed in the
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| last paragraph.
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| 2. Monthly Surveillance Observation (61726)
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| The inspectors observed surveillance activities of safety related systems
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| and components to ascertain that these activities were conducted in
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| accordance with license requirements. The inspectors observed portions of
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| 35 selected surveillance tests including all aspects of Reactor Building !
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| Closecut Inspection, STP 109.001. The inspectors verified that required
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| administrative approvals were obtained prior to initiating the test,
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| testing was accomplished by qualified personnel, required test instruments-
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| tion was properly calibrated, data met TS requirements, test discrepancies
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| were rectified, and the systems were properly returned to service. The
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| licensee demonstrated good communication between test technicians and i
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| control room personnel during performance of test procedures. The
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| materials, parts, components and test equipment used were found to be l
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| correct and documented properly. Technicians had procedures available at
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| all times and utilized them properly.
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| No violations or deviations were identified.
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| 3. . Menthly Maintenance Observation (62703)
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| The inspectors observed maintenance activities of safety related systems
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| and components to ascertain that these activities were conducted in
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| accordance with approved procedures, TS, industry codes and standards.
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| The inspectors determined that the procedures used were ' adequate to
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| control the activity, and that these activities were accomplished by
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| qualified personnel. The inspectors independently verified that the
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| equipment was properly tested before being returned to service.
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| Additionally, the inspectors reviewed several outstanding job orders to
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| determine that the licensee was giving priority to safety related
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| l: maintenance and not developing a backlog which might affect a given
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| system's performance. The operational maintenance activities observed by
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| '
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| the inspectors during this report were judged.to be satisfactory. It
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| appears that with the installation of control room barriers and a new
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| tagging desk in the control room, the traffic in the critical areas of the
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| -control room has been reduced. This has also resulted in ' smoother
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| processing of MWR's, STP's and other maintenance activities through. the
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| control room. The following specific maintenance activities were
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| observed:
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| MWR 87C00it Replace regulator for demineralized instrument air
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| supply
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| MWR 8901080 Repair controller on hydrogen analyzer
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| MWR 8901211 Calibrate pressurizer control channels 444C & 444D
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| PMTS 115543 Repair air intake transmitter for SW building
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| MWR 89G0095 Repair smoke detectors
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| PMTS 112043 Repair discharge flow transmitter on C FW booster pump
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| PMTS 116745 Calibrate heater coil temperature controller in
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| auxiliary building supply plenum
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| PMTS 118844 Calibrate temperature element on SW building pump room
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| MWR 88E0125 Repair flexible conduit to smoke analyzer
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| MWR 88E0108 Test and replace smoke analyzer
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| PMTS 117045 Calibrate temperature alarm on SW booster pump
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| MWR 8956808 Remove necessary parts and reinstall torque motor j
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| PMTS 122056 Perform inspection on open cycle cooling water booster
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| pump A 1
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| PMTS 122063 Rotate turbine on closed cycle cooling water pump A
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| PMTS 121916 Verify alignment of 480V breakers
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| PMTS 121917 Electrical adjustment on 7.2kV switchgear treaker
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| PMTS 119740 Inspection of FW pump turbine
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| MWR 8901221 Repair posit.an indication circuitry on pressurizer
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| sample header isolation valve
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| MWR 87G0095 Repair sample detection line
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| PMTS 122395 Vibration analysis check on RHR pump A
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| PMTS 121729 Vibration analysis check on EFW pump A
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| PMTS P122139 Audit misalignment log
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| PMTS P122104 Inspect 7.2kV switchgear breakers
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| No violations or deviations were identified.
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| 4. Operational Safety Verification (71707)
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| a. The inspectors toured the control room, reviewed plant logs and
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| records and held discussions with plant staff personnel to verify
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| that the plant was being operated safely and in conformance with
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| applicable requirements. Specific items inspected in the control
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| room included: adequacy of staffing and attentiveness of control room
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| personnel, TS and procedural adherence, operability of equipment and
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| indicated control room status, control room' logs, tagout books,
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| operating orders, jumper / bypass controls, computer printouts and
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| annunciators. Tours of other plant areas were conducted to verify
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| equipment operability, control of ignition sources and co,mbustible
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| materials, the condition of fire detection and extinguishing
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| equipment, the control of maintenance and surveillance cctivities in
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| progress, the implementation of radiation protective controls and the i
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| physical security plan. Tours were conducted during normal and
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| random off-hour periods.
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| b. On July 11,1989, at 2:35 p.m., the unit tripped from 100 percent
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| power. The trip resulted from an I&C technician shorting a wire
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| while reconnecting a thermocouple inside the stator water cooling
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| control cabinet. The short circuit blew the power supply fuses and
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| resulted in a low flow signal on stator water cooling. The normal
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| l protective action would have resulted in a turbine run back. This
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| ! circuit did not function correctly and resulted in a turbine trip and
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| reactor trip.
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| At the time of.the' reactor trip the utility. grid was' experiencing.a
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| high load of approximately 3100.MW's. This loss of-the 900 MW's
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| being generated by Summer resulted in allarge voltage oscillation
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| which actuated protective relays that 'also ' tripped 4 pumped storage
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| units at the Fairfield Pumped Storage Facility (approximately 250MW) -
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| 3 units'~ at the. Saluda Hydro (approximately 135MW), and both fossil
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| generating ' units at~ McMeekin Station (approximately 250MW). '.These
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| losses resulted in the 230kV offsite power source to Summer dropping
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| -to approximately 203kV and the 115kV source dropping to approximately-
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| 100kV. .This . low voltage condition actuated the undervoltage' relays -
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| l which automatically separated the 7200 volt ESF buses from offsite
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| power. This started the emergency diesel' generators and placed the
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| safety related buses on the' diesel generator. The non-safety service
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| buses remained connected to the degraded offsite power source and
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| continued to operate throughout the event. at reduced voltages, . An
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| unusual event was declared at 3:10 p.m. due to the loss of both
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| offsite power sources. The system voltage was returned to normal and.
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| thel safety related buses were reconnected to offsite power at
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| approximately 5:00 p.m. The DG's'were' secured and the unusual event
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| was terminated at 5:11 p.m.
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| Further investigation by the licensee revealed that the MVAR loading
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| of Summer, the, grid MVAR distribution at the time of the unit trip
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| and lower.than normal setpoints on some generator back-up protection.
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| relays: may have led to this event. The licensee has developed
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| administrative - guidelines to . provide for - improved system MVAR
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| distribution that should reduce the probability of future similar
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| occurrences. After completing all necessary repairs and implementing
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| the'above step, the unit was restarted.on July 12, 1989, and returned
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| to power operation on July 13,1989. The licensee is currently
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| preparing a LER on this event.- The event will also be discussed.
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| during a meeting scheduled for August 1, 1989. at NRC headquarters.
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| c. While. conducting a routine walkdown of the plant on July 6, 1989 -the
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| inspectors discovered two temporary demineralizers on the 412
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| elevation of the intermediate building. These units are 24 inches in
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| diameter and approximately six feet high and are configured to stand 'l
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| in an upright position. The weight of each of the components is
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| approximately 1750 lbs. The support for.these units was a 1/2-inch
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| sisal' rope which attached these units to two EFW line supports and a
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| SW line support. A concern with the effects of this installation on
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| the operability of the SW and EFW system and nearby safety-related
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| components during a seismic event was immediately discussed with the
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| operations shift supervisor. The shift supervisor immediately had
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| these units removed from the area and documented this in off-normal
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| occurrence 89-058 and NCN 3386.
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| Further investigation into this item revealed that these units had
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| been installed on June 1, 1989, to permit draining of the SG while the
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| plant was in Mode 5. This installation was accomplished without a
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| MWR as required by the Station Housekeeping and plant Inspection
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| Program Procedure SAP 142, and Conduct of Maintenance Procedure
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| SAP-300. The unit was restarted on June 11,-1989 with the units
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| still in place. This installation had been noted by plant management
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| and directions had been given to remove the units on or around June 20,
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| 1989.
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| In this instance personnel were deficient in not performing this work
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| under the licensee MWR program. No documentation to require
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| engineering review of this temporary installation was performed as
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| required by SAP 142. The above procedure was also inadequate in that
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| it did not insure that a seismic evaluation of the installation be
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| performed and that time limits were established to insure removal of
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| this hazard prior to plant start-up. This is contrary to the
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| requirement of TS 6.8.1.a which requires that procedures be
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| established, implemented and maintained for activities referenced in
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| Appendix A of Regulatory Guide 1.33, Revision 2 February 1972.
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| This is 'a violation, " Failure to Control Temporary Installations,"
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| 89-13-01.
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| The licensee has performed an evaluation which determined that a
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| seismic event could have resulted in the portable demineralized
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| becoming mobile and possibly damaging two FW line supports and
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| shearing off a test connection on a CCW line and a drain line'in the
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| SW system. The failure of the EFW supports would not have resulted in
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| the system becoming inoperable and the loss of flow in the SW and CCW
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| system would not have degraded system flow below the worst case
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| analyzed values. The potential flooding from the lines were well
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| within the capacity of space dewatering equipment. This analysis
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| determined that all systems would remain operable.
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| This event is similar to a licensee identified violation that was
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| documented in inspection report 89-03. In that event temporary
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| scaffolding had been erected for shielding of RHR piping to reduce
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| personnel radiation exposure while the plant was in a refueling
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| outage. Due to procedural deficiencies and personnel errors the
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| scaffolding was not removed prior to plant start-up. That
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| installation had the potential to impact on system operability.
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| The licensee, in their response to this violation, should address
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| procedural changes made to insure that temporary installations are
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| controlled and that dates or mode restraints are established to
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| insure that temporary installations which are required while the
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| plant is shutdown are removed prior to unit start-up.
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| Violations cr deviations were identified.
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| - _ _ _ _ - - _ _ - - _ - _ _ - _ - _ _ _ _ - - _ _ _ _ _ _ . ._- i
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| 6
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| 5. Action on Prev ous Inspection Findings (92701, 92702)
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| (Closed) TI2513/94, Inspection for verification of licensee changes made
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| to comply with PWR moderator dilution requirements, multi-plant action
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| item 13-03. The inspector reviewed inspection requirements specified.in
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| this instruction and reviewed the V. C. Summer Safety Evaluation Report and
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| supplements to determine what requirements had been established. This
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| review identified that dilution events and- preventive measures were
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| discussed and resolved in section 15 of the SER and in supplements 1 and 3
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| to the SER. However, multi-plant action item B-03 was not specifically
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| discussed. Discussion with Mr. L. Kopp, the NRR lead contact for.this
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| item, indicates thut this item is not applicable for V. C. Summer. The
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| SIMS open item list for V. C. Summer also does not list this item. Further
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| discussion with Mr. Kopp revealed that since V.C. Summer was licensed in
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| 1982, this issue would have been resolved in the normal licensing process
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| for V. C. Summer and all other plants licensed after 1979. Based on the
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| above, this item is administratively closed.
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| 6. Other Areas
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| The inspectors-toured the licensee's lead dispatch center in Columbia, SC
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| on July 25, 1989. Computer control and indication systems and procedures
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| that are used to operate' and control SCE&G's grid was discussed in detail.
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| This tour was very beneficial and provided the inspectors with a better
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| understanding of this tystem.
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| 7. ExitInterview(30703)
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| The inspection scope and findings were summarized on July 31, 1989, with
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| those persons indicated in paragraph 1. The inspectors described the
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| areas inspected and discussed the inspection findings. The plant trip and
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| the resulting offsite power loss event which occurred on July 11, 1989, was
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| discussed in detail. This included the short term corrective measures and
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| the current investigation into root cause and long term corrective action.
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| The violation which resulted from the failure to control the temporary
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| installation of portable demineralizers in the intermediate building was
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| attributed to procedural inadequacies and a failure to follow procedures.
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| It was also noted that the violation was similar to LIV 89-03-01 when the
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| plant was restarted without removing scaffolding that contained temporary
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| shielding. No dissenting comments were received from the licensee. The
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| licensee did not identify as proprietary any of the materials provided to
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| or reviewed by the inspectors during the inspection.
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| 8. Acronyms and Initialisms
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| CCW Component Cooling Water
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| l DG Diesel Generator ,
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| EFW Emergency Feedwater
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| FW Feedwater
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| L- _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ - _ - _ _ _
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| 7
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| I&C Instrumentation and Control
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| MW Megawatt.
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| - MWR Maintenance Work Request
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| MVAR Million Volt Amps Reactive
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| NCN Non-Conformance Notice
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| i NRC Nuclear Regulatory Commission
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| NRR Nuclear Reactor Regulation
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| PMTS Preventive Maintenance Task Sheet
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| - QC Quality Control
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| RHR Residual Heat Removal
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| SAP Station Administrative Procedure
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| SCE&G South Carloina Electric & Gas Company
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| SER Safety Evaluation Report
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| SG Steam Generator
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| SIMS Safety Issues Management Systems
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| STP Surveillance Test Procedures
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| SW Service Water
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| TS Technical Specifications
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| ,
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| ----________-______m_______m____
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| }}
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