Information Notice 1985-74, Station Battery Problems

Station Battery Problems

ML031180629
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill
Issue date:	08/29/1985
From:	Jordan E L NRC/IE
To:
References
IN-85-074, NUDOCS 8508270031
Download: ML031180629 (4)

SSINS No.: 6835IN 85-74UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, DC 20555August 29, 1985IE INFORMATION NOTICE NO. 85-74: STATION BATTERY PROBLEMS

Addressees

All nuclear power reactor facilities holding an operating license (OL) or aconstruction permit (CP).

Purpose

This notice describes problems that have occurred with lead-acid stationbatteries at several nuclear power plants. These problems were discovered as aresult of inspections by the NRC Performance Appraisal Team (PAT). It isexpected that recipients will review the information for applicability to theirfacilities and consider actions, if appropriate, to preclude a similar problemoccurring at their facilities. However, suggestions contained in this informationnotice do not constitute NRC requirements; therefore, no specific action orwritten response is required.

Description of Circumstances

All four recent inspections by the PAT identified problems with lead-acidstation batteries. Although all of the problems are not listed here, a summaryof a few of the more significant problems with lead-acid station batteries thatwere identified as a result of these inspections is provided below:Cooper PAT Inspection (November 1984):The battery rated-load discharge test was performed at a discharge ratesignificantly less than the manufacturer's recommended rated-load dischargerate for the 8-hour period of the test. The licensee had no records of batterycharging following the completion of battery discharge test and consequentlythe time and date the batteries were returned to service could not be determined.The licensee failed to correct specific gravity measurements for electrolytetemperature and level. The licensee had no written procedures for conductingcharges of the station batteries.McGuire PAT Inspection (February 1985):Three cells were placed on single-cell chargers for about 2 years, thus raisingquestions regarding the operability of the battery and electrical independenceand separation of the Class 1E dc power systems. The cells on single cell8508270031 JIN 85-74August 29, 1985 charge were at voltages higher than specified in the vendor manual. Althoughone cell in the battery was jumpered out, the float voltage for the entirebattery was not reduced; consequently each cell was floated at a voltage higherthan specified in the battery vendor manual. The battery performance dischargetest was performed improperly because the test was stopped before reaching theminimum specified voltage.Susquehanna PAT Inspection (February 1985):There were no station procedures for maintaining station batteries in accordancewith the battery vendor's manual or IEEE Std 450-1975, "IEEE RecommendedPractice for Maintenance, Testing and Replacement of Large Lead Storage Batteriesfor Generating Stations and Substations" (which is endorsed by Regulatory Guide1.129, "Maintenance, Testing and Replacement of Large Lead Storage Batteriesfor Nuclear Power Plants"). Intercell resistance values were not compared withprevious values to determine when corrective action was required. The licenseedid not always conduct equalizing charges when required; nor did the licenseehave procedures for monitoring the progress of an equalizing charge or determiningwhen the charge should be terminated. Surveillance procedures for the 60-monthrated-capacity discharge test did not conform to IEEE Std 450-1975 because thetest was terminated at the end of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, instead of when the terminal voltagefell to the minimum specified value (usually 1.75 volts per cell). The licensee'sprocedures did not require that the average specific gravity be calculated andcompared to the technical-specification acceptance criteria.San Onofre PAT Inspection (March 1985):During the first 2 years of operation, the battery capacity tests required bythe Final Safety Analysis Report (FSAR) and IEEE Std 450-1980 were not performedon Units 2 and 3. The total battery float voltage was not adjusted to accountfor two jumpered out cells. The two jumpered out cells did not receive themanufacturer's specified surveillances, maintenance, or charges. The pilotcells were not being changed on a yearly basis, as recommended by the vendor'stechnical instructions. The station engineer responsible for the technicalaspects of battery operation, maintenance, and surveillance did not receivesurveillance results and data sheets on a routine basis.Discussion:Recent IE inspections of operating facilities indicate that several widespreaddeficiencies may exist in the operation and maintenance of station batteries.These deficiencies are attributable to a variety of causes, including licenseeerror, inadequate knowledge of batteries by maintenance technicians andsupervisors, and inadequate procedural guidance. The results of theseinspections suggest a general lack of appreciation amongst licensee personnelfor proper maintenance and surveillance of station batteries. Although batteriescontain no moving parts, considerable care and attention to detail is requiredto maintain them operable. Too often, licensees may be treating these vitalengineered safety features (ESF) power supplies as "passive" components and notproviding them the necessary management and technical attentio IN 85-74August 29, 1985 The following reference materials provide guidance as to the individualrequirements for a facility's station batteries.1. IEEE 450-1975, and 19802. Regulatory Guide 1.129, Rev. 1, "Maintenance, Testing and Replacementof Large Lead Storage Batteries for Nuclear Power Plants" (Thisregulatory guide endorses IEEE Std 450-1975 with certain exceptions.)3. Facility Technical Specifications4. Final Safety Analysis Report (FSAR)5. Station Battery Vendor Technical Manual (The vendors of stationbatteries periodically update their manuals to include revisedguidance.)Other recent problems with station batteries were described in IE InformationNotice 84-83: VARIOUS BATTERY PROBLEMS, November 14, 1984.No specific action or written response is required by this information notice.If you have questions about this matter, please contact the Regional Adminis-trator of the appropriate NRC regional office or this office.war Joran, DirectorDivisi of Emergency Preparednessand Engineering ResponseOffice of Inspection and Enforcement

CONTACT

S: E. W. Weiss, IE(301) 492-9005L. J. Callan, IE(301) 492-9497

Attachment:

List of Recently Issued IE Information Notices Attachment 1IN 85-74August 29, 1985LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation Date ofNotice No. Subject Issue Issued to84-70Sup. 185-7385-7285-7185-70Reliance On Water Level 8/26/85Instrumentation With ACommon Reference LegEmergency Diesel Generator 8/23/85Control Circuit Logic DesignErrorUncontrolled Leakage Of 8/22/85Reactor Coolant OutsideContainmentContainment Integrated Leak 8/22/85Rate TestsTeletherapy Unit Full 8/15/85Calibration And QualifiedExpert Requirements (10 CFR35.23 And 10 CFR 35.24)Recent Felony Conviction For 8/15/85Cheating On Reactor OperatorRequalification TestsDiesel Generator Failure At 8/14/85Calvert Cliffs NuclearStation Unit 1Loose Phosphor In Panasonic 8/12/85800 Series Badge Thermo-luminescent Dosimeter (TLD)ElementsValve-Shaft-To-Actuator Key 8/8/85May Fall Out Of Place WhenMounted Below Horizontal AxisAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll materiallicenseesAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPMaterials and fuelcycle licenseesAll power reactorfacilities holdingan OL or CP85-6985-6885-42Rev. 185-67OL = Operating LicenseCP = Construction Permit