Index | Site       Map | FAQ | Facility       Info | Reading       Rm | New | Help | Glossary | Contact UsProtecting People and the EnvironmentUNITED STATES NUCLEAR REGULATORY COMMISSION -   About NRC    - The     Commission 
  - Statutory Authority 
  - Strategic Plan 
  - Budget &      Performance 
  - Organization & Functions 
  - Locations 
  - History 
  - Values 
  - Policymaking 
  - Radiation Protection 
  - Fire Protection 
  - How We Regulate 
  - Grants 
  - Civil Rights 
  - 
- NuclearReactors    - Operating Reactor Locations 
  - Reactor Quick Links 
  - Power Reactors 
  - Research and Test     Reactors 
  - Operating Reactors 
  - Operator Licensing 
  - New Reactors 
  - Operator     Licensing for New Reactors 
  - Reactor Safety Research 
  - Advisory Comm (ACRS) 
  - Decommissioning     of Nuclear Facilities 
  - 
- NuclearMaterials    - Fuel Cycle Facility Locations 
  - Uranium     Recovery Locations 
  - Materials Quick Links 
  - Special Nuclear Material 
  - Source Material 
  - Byproduct Material 
  - Med, Academic & Ind Uses 
  - Source Materials Facilities 
  - Uranium Recovery 
  - Fuel Cycle Facilities 
  - Materials     Transportation 
  - Materials Research 
  - Advisory Comm (ACMUI) 
  - Decommissioning     of Nuclear Facilities 
  - Materials     Environmental Reviews 
  - 
- RadioactiveWaste    - Waste Quick Links 
  - Low-Level Waste 
  - Waste Incidental to     Reprocessing 
  - Incidental Waste Criteria 
  - High-Level Waste 
  - Uranium Mill Tailings 
  - LLW Disposal 
  - HLW Disposal 
  - Spent Fuel Storage 
  - Spent Fuel Transport 
  - Waste Research 
  - 
- NuclearSecurity    - Security     Spotlight 
  - NRC     Responsibilities 
  - Domestic Safeguards 
  - Radioactive Material Security 
  - Facility Protection 
  - Nuclear Material Control 
  - International Safeguards 
  - Information Security 
  - Emergency     Preparedness 
  - &; 
- Public Meetings&   Involvement    - Public Meeting Schedule 
  - Commission     Schedule 
  - Conferences & Symposia 
  - Documents for Comment 
  - Brochures & Fact Sheets 
  - Involving Stakeholders 
  - Info Quality Guidelines 
  - Rulemaking Process 
  - Licensing 
  - Enforcement 
  - Hearing Process 
  - Hearing Applications 
  - 

Home       > Electronic Reading       Room       > Document       Collections       > General       Communications       > Information       Notices       > 1999       > IN 99-13

UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001

April 29, 1999
NRC INFORMATION NOTICE 99-13:INSIGHTS FROM NRC INSPECTIONS OF LOW- AND MEDIUM-VOLTAGE CIRCUIT       BREAKER MAINTENANCE PROGRAMS - Addressees 
- Purpose 
- Description   of Circumstances 
- Discussion    - I.     General Programmatic Issues 
  - II.     Preventive Maintenance 
  - III.     Licensee/Vendor Interface 
  - IV.     Control Voltage Calculations 
  - V.     Operating Experience Review 
- Related   Generic Communications 
- Conclusion 
Addressees
All holders of operating licenses for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to summarize observations made and insights gained during inspections of licensee circuit breaker maintenance programs. It is expected that recipients will review the information for applicability to their facilities and consider actions, as appropriate. However, suggestions contained in this information notice are not NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances
Because of concerns about the reliability of safety-related medium-voltage (4-kV to 15-kV) and low-voltage (600-V and below) power circuit breakers, the NRC inspected the circuit breaker maintenance programs at eight nuclear power plant sites in 1998, using Temporary Instruction (TI) 2515/137, Revision 1, "Inspection of Medium-Voltage and Low-Voltage Power Circuit Breakers," issued on March 9, 1998. For more detailed information, the individual inspection reports are available through the NRC Public Document Room. Attachment 1 lists the inspection reports and their accession numbers.

The TI inspections confirmed that the programs were generally adequate. However, observations made at several of the plants inspected indicate that licensee programs have several areas in common in which improvement may be desirable. In addition, in a few instances certain aspects of programs did not meet NRC requirements, and violations were cited. Licensees for the inspected plants have already taken steps to address many of the areas of concern identified by the inspections. This notice was developed so that all licensees may take advantage of insights gained from the inspections when considering circuit breaker maintenance program improvements.
Discussion
Significant observations from the TI inspections are described below and have been categorized as follow: (1) general programmatic issues, (2) preventive maintenance, (3) licensee/vendor interface, (4) control voltage calculations, and (5) operating experience review. However, licensees are encouraged to review the inspection reports for detailed findings and their resolutions.
I.  General Programmatic Issues
Licensee preventive maintenance procedures and practices did not always reflect all of the applicable vendor recommendations or industry operating experience, and when licensees deviated from such recommendations and operating experience there was often no documented basis or rationale given. Adherence to vendor recommendations is not a regulatory requirement, but a sound engineering basis for such deviations is important, and should be performed in consultation with the vendor when possible, to ensure that valuable vendor information is not overlooked.

Storage, shelf life, environment, segregation, and issuance of lubricants and cleaning materials were not well controlled. Some licensees had not identified shelf lives for circuit breaker lubricants and cleaning agents or solvents.

Individual breakers at some plants either did not come with or were not given unique identifiers. Some licensees were not aware that group or series identifiers, such as shop order numbers, were not unique. Some licensees did not record both the breaker serial number, when present, or the cubicle number in maintenance records to allow for tracking of breaker location, performance, and maintenance history.

At most plants, the racking of breakers in and out of the cubicle (and local operation when required) was the job of operations department personnel rather than circuit breaker maintenance personnel. However, operations department training and/or procedures did not always cover breaker position verification or functional testing in the connected position (closing the breaker and running load equipment, when permitted by plant conditions). Training operations department personnel to verify proper indications, closing spring recharging, and restoration of all electrical and mechanical interfaces and interlocks, and cycling the breaker after it is racked in, could result in fewer failures to close on demand.
II.  Preventive Maintenance
Preventive maintenance was not always performed with the frequency recommended by the original equipment manufacturer (OEM), and licensees had no documented justification for deviating from that frequency.

Maintenance procedures sometimes did not cover inspection for specific problems identified in industry operating experience. Some licensees stated that they covered such items in training, but specific items in question were seldom explicitly addressed in lesson plans.
III.  Licensee/Vendor Interface
The TI inspections revealed that circuit breaker and switchgear vendor manuals were often not kept current, and the programs for periodic recontact provided for in Generic Letter (GL) 90-03 were ineffective in obtaining revisions or updates to vendor manuals, or other pertinent technical information.

Some licensees identified areas in which improvements could be made to vendor interface programs, including (1) periodic review of plant equipment to ensure that lists of key safety-related equipment are current, (2) establishing organizational and procedural interfaces and links to ensure that vendor interface personnel are kept informed of equipment changes or modifications, (3) establishing personal contact with the appropriate vendor personnel, (4) substantial involvement in the process by technically knowledgeable personnel, and (5) periodic comprehensive reconciliation with the vendor of lists of equipment and related technical publications or documentation.
IV.  Control Voltage Calculations
The TI inspections revealed that a few licensees had not performed the circuit breaker control voltage calculations based on as-built systems. In some cases where calculations were performed several discrepancies were identified, including (1) not starting with the minimum battery voltage; (2) using an incorrect minimum battery voltage that did not take into account loading, state of discharge, and/or aging factors; (3) using incorrect current paths, cable lengths, conductor sizes, and/or ohms/foot values to determine overall cable resistance; (4) calculation of cable conductor resistance using ambient temperature values, but neglecting temperature rise caused by heat from surrounding cables in a raceway or without having data to justify the non-conservative lower temperature assumption; and (5) using incorrect loading values in the final determinations of voltage drops. One licensee, had not translated this design basis information into test procedures to demonstrate breaker operability (NRC Inspection Report 50-266/98-13).
V.  Operating Experience Review
At most of the plants inspected, weaknesses were observed in the review of operational experience documents related to low- and medium-voltage circuit breakers. These documents included NRC information notices (INs); INPO SEE-IN documents or Nuclear Network reports; and vendor information, such as service information letters, technical bulletins, or service advisory letters.

The TI inspections revealed instances of industry operating experience information erroneously determined to be not applicable because of narrowly focused and/or superficial reviews, and insufficient involvement by technically knowledgeable personnel. Problems generically applicable to several types of breakers were often not recognized because the plant's breakers did not have exactly the same model designation as the one used as an example in the information notice or the vendor technical bulletin.

TI 2515/137, Revision 1, lists 62 NRC information notices and bulletins that deal with problems with low- and medium-voltage power circuit breakers. As many as one-third of these were erroneously determined to be not applicable at one or more plants.
Related Generic Communications
IN 98-38, "Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections," issued on October 15, 1998, alerted licensees to issues identified by reactive NRC inspections at plants that experienced problems concerning circuit breaker reliability in 1997. The events discussed in that information notice were the catalyst that prompted the TI inspections of licensee maintenance programs in 1998.
Conclusion
This information notice requires no specific action or written response. However, recipients are reminded that they are required to consider industry-wide operating experience (including NRC information notices) where practical when setting goals and performing periodic evaluations under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear power plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions about the information in this notice, please contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
/s/'d byLedyard B. Marsh, ChiefEvents Assessment, Generic       Communications, and Non-Power Reactors BranchDivision of Regulatory       Improvement ProgramsOffice of Nuclear Reactor RegulationTechnical contacts:Stephen Alexander, NRR301- 415-2995E-mail: sda@nrc.govAmar Pal, NRR301- 415-2760E-mail: anp@nrc.govDavid Skeen, NRR301- 415-1174E-mail: dls@nrc.govS.K. Mitra, NRR301- 415-2783E-mail: skm1@nrc.govAttachments:1. Table       of NRC TI Inspection Reports2. List of Recently Issued NRC       Information Notices(NUDOCS Accession Number 9904280024)
ATTACHMENT 1

IN 99-13April 29, 1999Page 1 of 1
TABLE 1 - Temporary Instruction 2515/137 Inspection ReportsPLANTREPORT NUMBERISSUE DATEACCESSION NUMBERCallaway50-483/98-1510/26/989810290263Hatch 1 & 250-326/98-0804/30/989805110181Nine Mile Point 250-410/98-1811/13/989811240071Perry50-440/98-1107/16/989807220299Point Beach 1 & 250-266/98-1309/11/989809180178Seabrook50-443/98-0709/28/989810050116Sequoyah 1 & 250-327/98-0506/12/989807070138Waterford 350-382/98-1311/17/989811240126