IR 05000341/1987003

Safety Insp Rept 50-341/87-03 on 870112-15.No Violations or Deviations Noted.Major Areas Inspected:Actions Taken on Previously Identified Items & Followup on Licensee Program for Determining Temp Sensor Operability

ML20210S168
Person / Time
Site:	Fermi
Issue date:	02/06/1987
From:	Darrin Butler, Huber M, Phillips M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20210S112	List: IR 05000341/1987003 ML20210S107
References
50-341-87-03, 50-341-87-3, NUDOCS 8702170574
Download: ML20210S168 (7)

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V. S. NUCLEAR REGULATORY COMMISSION-

REGION III

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Report No. 50-341/87003(DRS)

Docket No. 50-341 . License No. NPF-43 Licensee: Detroit Edison Company 2000 Second Avenue Detroit, MI 48224 Facility Name: Enrico Fermi Nuclear Power Plant, Unit 2 Inspection A&: Enrico Fermi 2 Site, Monroe, Michigan Inspection Conducted: January 12-15, 1987 Inspectors: [B 1 R /3 /F7

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pu' 4 M. P. Hu er 2!3 Date Approved By: o e d 111ps, ef Operational Programs Section Date Inspection Summary Inspection cn January 12-15,1987(ReportNo. 50-341/87003(DRS))

Areas Inspected: Unannounced, special safety inspection on actions taken on previously-identified items and followup on the licensee's program for temperature sensor operability determininhfthetwoareasinspected,noviolationsordeviationswere Results:

identifie DR 870206 ADOCK 05000341 PDR

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DETAILS Persons Contacted

• F. E. Agosti, Vice President, Nuclear Operations

• S. Orser, Vice President, Nuclear Engineering

• B. R. Sylvia, Group Vice President

• S. G. Catola, Chairman, Nuclear Safety Review Board

• M.May, R. Trahey,intenance Ma EngineerDirector, Quality Assurance

• Assistant Maintenance Engineer

• D. Tucker, Ohlemacher,ing Act Su)erintendent, Operations

• Preston, Operations Engineer F. H. Sondgeroth, Licensing S. Frost Licensing

• Filipek, Instrument and Control Engineer NRC Personnel W. Rogers, Senior Resident Inspector

• Parker, Resident Inspector

• Denotes those who attended the exit meeting on January 15, 1987.

The inspectors also contacted other licensee personnel during the course of the inspectio . Followup on Previously Identified Items (0 pen)UnresolvedItem 341/86032-01(DRP)): Calibration of safety-related temperaturesensingdev(ice It has been industry )ractice to calibrate temperature channels by disconnecting the sensor. Either a millivolt source (forthermocouples)orresistancedecadebox(forresistance temperature devices) were used to calibrate the channel. The calibration was determined from standard calibration curves. The temperature sensors were not removed from their thermowell. Operability could be determined following channel restoration by either comparing similar channels, verifying computer display readouts, or using current / voltage output checks on non-indicating channels. The licensee has been following this practic Thelicensee'sTechnicalSpecification(TS) definition (Section1.4)for Channel Calibration states, n part, that the Channel Calibration shall encompass the entire channel, including the sensor and alarm and/or trip functions. Hence, it appears that the TS recuirements for sensor calibration were not being met. Rection III FRC has requested assistance from the Office of Nuclear Reactor legulation (NRR) to determine how the TS definition for Channel Calibration a) plies to temperature sensor This item will remain open pending furtler evaluation by NRR. Temperature sensors are further discussed in Paragraphs 3 and 4.

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3. Safety-Related Technical Specification Temperature Sensor Operability Determination The inspectors reviewed the licensee's operability determination methods and three month survey of channel checks on TS related temperature sensors as described in Letter GP-86-0004, dated October 10, 1986 (Mr. Sylvia (DECO) to Mr. Keppler (NRC)). The licensee was using three methods to assess temperature channel integrit (1) Comparison Checks of Redundant Sensors The licensee used shiftly and monthly comparisons of redundant sensors to verify the temperature channel was responding correctly to plant conditions. Acceptance criteria was provided on the checklists to verify that redundant sensors were agreeing within a nominal valu (2) Operator Qualitative Assessment The licensee used shiftly and monthly channel checks, and the operators' familiarity with structures, systems and componentstodeterminewhetherthetemperatureindIcationwas representative of plant conditions. The acceptance criteria provided on the checklist was typically a maximum value with no minimum value designated. Discussions with licensee personnel indicated the criteria selected was reasonable for expected plant condition The inspectors noted there was no minimum acceptance criteria s)ecified for ^T temperature channels. There exists the potential t1at ^T temperature channels may read at or near zero. The licensee needs to develop minimum acceptance criteria for 'T temperature channels and instructions for the operators on plant conditions where the assessment of ^T occurs in Sur-veillance Procedure No. 24.000.02. This is considered x. open item (341/87003-01(DRS)).

(3) Pre and Post Connection Comparisons The licensee plans to compare the reading prior to calibrating the temperature channel with the channel reading after calibratio At the time of this inspection, this technique was used only with the Electric Hydrogen Recombiner temperature channel calibration The inspector determined that Surveillance Procedures No. 44.220.001, " Electric Hydrogen Recombiner Channel Calibration Division I," and No. 44.220.002,"" Electric Hydrogen Recombiner Channel Calibration Division II, had adequate steps in the procedures to ensure the pre and post connection comparisons were performe _ _ _ _ _ _ _ _ _ _ _

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The licensee conducted a sampling of channel checks performed over a three month period to assess the reasonableness of the reading Five sets of base line data were collected. Three sets were collected during power operation, one set during HPCI testing, and one set during RCIC testing. The data collection was carried out by Nuclear Plant Operators in performing Channel Checks during operation and Surveillance-Tests on TS temperature sensors. The data were analyzed for the following groups of temperature sensors

Torus Water Temperature Main Steam Line Leak Detection Drywell and Torus Temperature Thermal Recombiner Reactor Water Cleanu) Steam Leak Detection HPCI E uipment Room Leak Detection RCIC E uipment Room Leak Detection The inspectors reviewed the licensee's data and determined the licensee had collected adequate information and that their conclusions were reasonable. The data followed predictable trends and should be reliable for use by the operators in making qualitative assessment The inspector determined the licensee had adequate steps in Surveillance

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Procedure N Surveillances,"24.000.02,6.4(ChannelChecks"Shiftly, Section to provide Daily, Weekly and Situatio the operator withguidanceinmakingaqualitativeassess)m,entofchanneloperatio In addition, the Night Order, dated October 4,1986, affirmed the importance of assessing channel behavior and a determination that continued operability of the instrument channel was warranted. Operators that were interviewed indicated the acceptance criteria to make a qualitative assessment was adequat August 27, 1986, SpetemberA review ofanddataSeptember collected21, on 1986 August 21,ined1986, determ 12, 1986,iscrepancies that the operators were picking up d in temperature channel behavior and that they were addressing the items in the " Remarks" section of the Surveillance Tes The inspection effort has determined the licensee was implementing the program committed to in Letter GP-86-000 . Safety-Related Non-Technical Specification Temperature Channel Operability The test procedures for the calibration of safety-related non-Technical Specification (TS) temperature devices employed by the licensee were similar to the procedures used for the testing of TS devices. These procedures were also used to assess the temperature channel operabilit The following devices were calibrated and verified operable in the Licensee'sPreventiveMaintenance(PM) program: Drywell Average Air Temperature The following temperature recorders were calibrated in accordance withInstrumentandControlCalibration(IC)ProceduresNo. 46.000.04 snd No. 46.000.06 at an 18 month interval:

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Device Event Type T47-R803A PM-T247 T47-R803B PM-T254 The operability of the following temperatures elements was also assessed in accordance with Surveillance Procedure No. 24.000.02:

Device Device Device T47-N014A T47-N016D T47-N019A T47-N014B T47-N017A T47-N019B T47-N014C T47-N017B T47-N019C T47-N014D T47-N017C T47-N019D T47-N015A T47-N017D T47-N020A T47-N015B T47-N018A T47-N020B T47-N016A T47-N018B T47-N020C T47-N016B T47-N018C T47-N020D T47-N016C T47-N0180 b. Recirculation and Emergency Make-up Air Filters, Charcoal and Inlet Air Heaters The following temperature elements were calibrated in accordance with IC Procedure No. 46.000.06 at an 18 month interval:

Device Event Type Device Event Type T41-N227A PM-A314 T41-230 PM-A320 T41-N227B PM-A315 T41-231 PM-A321 T41-N228A PM-A316 T41-232 PM-A322 T41-N228B PM-A317 T41-233 PM-A323 T41-N229A PM-A318 T41-N229B PM-A319 c. Standby Gas Treatment Thefollowingtemperatureelements(TE)andtemperaturecontrollers (TC) were calibrated in accordance with IC Procedure No. 46.000.06 at an 18 month interval:

Device (TE) Event Type Device (TC) Event Type T46-N007A PM-A888 T46-K001A PM-A888 T46-N007B PM-A889 T46-K001B PM-A889 d. Standby Liquid Control System The following temperature switches (TS) and tem)erature recorder (TR)werecalibratedbyprocedureatan18montiinterval:

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l Device (TS) Event Type Procedure C41-N003 PM-C771 46.000.06 C41-N006 PM-C773 46.000.03 Device (TR) Event Type Procedure C41-R002 PM-C792 46.000.09 The operability of these devices was also assessed in Surveillance Procedure No. 24.000.0 e. Safety Relief Valve Tailpipe Temperature The calibration and o)erability checks of temperature elements B21-N004A through H, 321-N004 J through P, 821-004R, and tem)erature indicator 821-R614 were performed in accordance with IC )rocedure No. 46.000.04, as event PM-B148, and at an 18 month interva f. Idle Reactor Coolant Recirculation loop Start-Up The calibration and operability checks of temperature element G33-N042 and temperature indicator G33-R607 were performed in accordance with IC Procedure No. 46.000.04, as event PM-G071, and at an 18 month interval, g. Reactor Vessel Flange and Head Flange Temperature The following temperature elements (TE) and temperature indicators (TI) were calibrated in accordance with IC Procedure No. 46.000.04 at an 18 month interval:

Device (TE) Event Type Device (TI) Event Type B21-N050B PM-8676 B21-R007 PM-8676 B21-N028C PM-8675 B21-R006 PM-B675 The operability of these devices was also assessed in accordance with Surveillance Procedure No. 24.000.0 h. RHR Reservoirs Thefollowingtemperatureelements(TE)andtemperatureindicators (TI)werecalibratedinaccordancewithMaintenanceProcedure No. MI-IC-0811 at an 18 month interval:

Device (TE) Event Type Device (TI) Event Type E11-N558A PM-E147 E11-R800A PM-E147 E11-N558B PM-E148 E11-R800B PM-E148

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Procedures

! 46.000.03 Temperature Sensing Instruments Calibration 46.000.04 Calibration of Indicators and Recorders l

l 46.000.06 ' Analog and Pressure Sensing Switches l 46.000.09 Controllers and M/A Stations 24.000.02 l

Shiftly,11ancesDaily, Surve1 Weekly, and Situation Required MI-IC-0811 Leeds and Northrup Speedomax Mark III Recorder l The above listed devices were caiibrated at the same interval as TS required devices. It appears that these devices were adequately entered in the preventive maintenance progra . Unresolved Items

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An unresolved item is a matter about which more information is required

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in order to ascertain whether it is an acceptable item, an open item, a deviation, or a violation. A previously identified unresolved item is discussed in Paragraph 2. . Open Item l

Open items are matters which have been discussed with the licensee, which

will be reviewed further by the inspector, and which involve some action i An o on the part of the NRC or licensee or both.theinspectionisdiscussedinParagr Exit Interview

! The inspectors met with licensee representatives (denoted in Paragraph 1)

on January 15, 1987 to discuss the scope and findings of the inspectio Thelicenseeacknowledgedthestatementsmadebytheinspectorwithrespect to items discussed in the report. The inspectors also discussed the li(ely informational content of the inspection report with regard to docu.nents or processes reviewed by the inspector during the inspection. The licensee did not identify any such document / processes as proprietary.

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