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| {{#Wiki_filter:I IUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555April 23, 1992NRC INFORMATION NOTICE 92-30: FALSIFICATION OF PLANT RECORDS | | {{#Wiki_filter:I I UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555 April 23, 1992 NRC INFORMATION |
| | |
| | NOTICE 92-30: FALSIFICATION |
| | |
| | OF PLANT RECORDS |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors and all licensed operators and senior operators. | | All holders of operating |
| | |
| | licenses or construction |
| | |
| | permits for nuclear power reactors and all licensed operators |
| | |
| | and senior operators. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the NRC's concern that plant mechanics,technicians, and operators may have falsified plant logs at several nuclearpower plants. The NRC is reminding plant mechanics, technicians, and operators(both licensed and non-licensed) of the penalties that could result fromintentionally violating Federal regulatory requirements and criminal statutes.The NRC is also reminding addressees that all personnel are subject to therequirements of 10 CFR 50.9(a) which states that information required bystatute or by the Commission's regulations be complete and accurate in allmaterial aspects. It is expected that recipients will review the informationfor applicability to their facilities and consider actions, as appropriate, toavoid similar problems. However, suggestions contained in this informationnotice are not NRC requirements; therefore, no specific action or writtenresponse is required. | | The U.S. Nuclear Regulatory |
| | |
| | Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees |
| | |
| | to the NRC's concern that plant mechanics, technicians, and operators |
| | |
| | may have falsified |
| | |
| | plant logs at several nuclear power plants. The NRC is reminding |
| | |
| | plant mechanics, technicians, and operators (both licensed and non-licensed) |
| | of the penalties |
| | |
| | that could result from intentionally |
| | |
| | violating |
| | |
| | Federal regulatory |
| | |
| | requirements |
| | |
| | and criminal statutes.The NRC is also reminding |
| | |
| | addressees |
| | |
| | that all personnel |
| | |
| | are subject to the requirements |
| | |
| | of 10 CFR 50.9(a) which states that information |
| | |
| | required by statute or by the Commission's |
| | |
| | regulations |
| | |
| | be complete and accurate in all material aspects. It is expected that recipients |
| | |
| | will review the information |
| | |
| | for applicability |
| | |
| | to their facilities |
| | |
| | and consider actions, as appropriate, to avoid similar problems. |
| | |
| | However, suggestions |
| | |
| | contained |
| | |
| | in this information |
| | |
| | notice are not NRC requirements; |
| | therefore, no specific action or written response is required.Description |
| | |
| | of Circumstances |
| | |
| | On March 1, 1992, the shift superintendent |
| | |
| | for the Public Service Company of New Hampshire's |
| | |
| | Seabrook Nuclear Station was conducting |
| | |
| | a surveillance, in accordance |
| | |
| | with a personnel |
| | |
| | performance |
| | |
| | monitoring |
| | |
| | program, to verify that operations |
| | |
| | department |
| | |
| | personnel |
| | |
| | were properly performing |
| | |
| | their assigned duties.On this occasion, the shift superintendent |
| | |
| | reviewed the security department's |
| | |
| | computerized |
| | |
| | card key entry records against locations |
| | |
| | in which an auxiliary operator's (AO's) log entries had indicated |
| | |
| | that he had performed |
| | |
| | inspections. |
| | |
| | The shift superintendent |
| | |
| | found that the AO had logged "SAT" (satisfactory) |
| | for some plant areas, indicating |
| | |
| | that he had performed |
| | |
| | the required periodic inspections, although the computerized |
| | |
| | security data indicated |
| | |
| | that some of these areas had not been entered.The shift superintendent's |
| | |
| | findings prompted the licensee to establish |
| | |
| | an independent |
| | |
| | review team (IRT) to performi a comprehensive |
| | |
| | analysis of the root cause(s) and the generic implications |
| | |
| | of this occurrence. |
| | |
| | The IRT interviewed |
| | |
| | the individuals |
| | |
| | involved and the management |
| | |
| | and supervisory |
| | |
| | staff and examined a wide range of historical |
| | |
| | records created or used since the issuance of the full power operating |
|
| |
|
| ==Description of Circumstances==
| | license, including |
| On March 1, 1992, the shift superintendent for the Public Service Company ofNew Hampshire's Seabrook Nuclear Station was conducting a surveillance, inaccordance with a personnel performance monitoring program, to verify thatoperations department personnel were properly performing their assigned duties.On this occasion, the shift superintendent reviewed the security department'scomputerized card key entry records against locations in which an auxiliaryoperator's (AO's) log entries had indicated that he had performed inspections.The shift superintendent found that the AO had logged "SAT" (satisfactory) forsome plant areas, indicating that he had performed the required periodicinspections, although the computerized security data indicated that some ofthese areas had not been entered.The shift superintendent's findings prompted the licensee to establish anindependent review team (IRT) to performi a comprehensive analysis of theroot cause(s) and the generic implications of this occurrence. The IRTinterviewed the individuals involved and the management and supervisorystaff and examined a wide range of historical records created or used sincethe issuance of the full power operating license, including security logs,92041701135/!
| |
| IN 92-30April 23, 1992 operations logs and procedures, administrative program manuals, and traininglesson plans. Discrepancies were found by the IRT, and some involved violationsof technical specifications and some involved licensed operators.In response to the findings at Seabrook, random checks were conducted at theHaddam Neck Plant and Millstone Nuclear Power Station. To date, no dis-crepancies have been identified at Haddam Neck. At Millstone, the NortheastNuclear Energy Company (the licensee) determined that several non-licensedplant equipment operators (PEOs) had not completed certain inspection roundsas represented in their logs. The Millstone licensee has since expanded itsevaluation to verifying the accuracy of log entries recorded by all PEOs.The management at Millstone informed plant personnel of its findings andexpectations for recording log entries. The Millstone licensee alsoestablished an IRT (with a representative from the Seabrook IRT acting inan advisory status) to investigate its findings, to determine the extent ofthe problem, and to determine corrective actions that should be taken.At Oyster Creek, several non-licensed PEOs were involved with falsification ofrecords associated with routine plant log taking rounds. None of the recordsinvolved were related to technical specifications. The discovery of thefalsified log entries was from an ongoing random investigation comparingsecurity door entry records with operator rounds.As a result of discrepancies found at Seabrook, Oyster Creek, and Millstone,at least one indivie-a-yn his e-pT tte-rmnn iniated,-s-everaltudiv-tduals- -resigned, and several other individuals were suspended.On January 28, 1992, two Instrumentation and Control technicians at the VogtleElectric Generating Plant, Unit 1, performed a surveillance on a portion ofthe reactor trip system instrumentation. The Georgia Power Company (thelicensee) informed the NRC that the technicians failed to properly follow thesurveillance procedure and subsequently created the data that was entered onthe calibration data sheet.NRC evaluation of each of these matters is continuing.Discussion of Safety SignificanceMaintenance of shift records, log sheets, and surveillance records, attentionto detail, and work ethics are important factors which contribute to the safeoperation of nuclear power plants. Complacency, by mechanics, technicians, orlicensed or non-licensed operators, cannot be tolerated. Similarly, manage-ment expectations and supervisory overview of rounds need to be clearlycommunicated and monitored. All personnel involved in NRC-regulated activitiesare responsible for complying with applicable NRC regulatory requirements andother Federal laws. Log keeping activities as well as surveillancesperformed by licensed or non-licensed personnel are subject to therequirements of 10 CFR 50.9(a) regarding completeness and accuracy of information.
| |
|
| |
|
| IN 92-30April 23, 1992 In addition, the administrative section of plant technical specificationsrequires that written procedures be implemented covering the applicable proce-dures in Appendix A of Regulatory Guide 1.33, Quality Assurance ProgramRequirements (Operation). Among the safety-related activities which Appendix Astates should be covered by written procedures are surveillances and logentries.Willful violations, committed by personnel at any level of a licensee'sorganization, are of regulatory concern because the NRC must have reasonableassurance that licensed activities will be conducted in a manner that willprotect the public health and safety. Such reasonable assurance is providedin large part by the integrity and conscientiousness of each individualperforming licensed activities. Deliberate violations concerning matterswithin the scope of an individual's responsibilities, including falsificationof records, will be considered for enforcement action against the individualas well as the facility licensee. As provided in 10 CFR 50.5, "DeliberateMisconduct by Unlicensed Persons," 56 Federal Register 40684, August 15, 1991,the NRC may take direct enforcement action against unlicensed personnel whodeliberately cause a licensee to be in violation of the Commission's regulationsor who provide false information to the licensee concerning licensed activities. | | security logs, 9204170113 |
| | 5/! |
| | IN 92-30 April 23, 1992 operations |
| | |
| | logs and procedures, administrative |
| | |
| | program manuals, and training lesson plans. Discrepancies |
| | |
| | were found by the IRT, and some involved violations |
| | |
| | of technical |
| | |
| | specifications |
| | |
| | and some involved licensed operators. |
| | |
| | In response to the findings at Seabrook, random checks were conducted |
| | |
| | at the Haddam Neck Plant and Millstone |
| | |
| | Nuclear Power Station. To date, no dis-crepancies |
| | |
| | have been identified |
| | |
| | at Haddam Neck. At Millstone, the Northeast Nuclear Energy Company (the licensee) |
| | determined |
| | |
| | that several non-licensed |
| | |
| | plant equipment |
| | |
| | operators (PEOs) had not completed |
| | |
| | certain inspection |
| | |
| | rounds as represented |
| | |
| | in their logs. The Millstone |
| | |
| | licensee has since expanded its evaluation |
| | |
| | to verifying |
| | |
| | the accuracy of log entries recorded by all PEOs.The management |
| | |
| | at Millstone |
| | |
| | informed plant personnel |
| | |
| | of its findings and expectations |
| | |
| | for recording |
| | |
| | log entries. The Millstone |
| | |
| | licensee also established |
| | |
| | an IRT (with a representative |
| | |
| | from the Seabrook IRT acting in an advisory status) to investigate |
| | |
| | its findings, to determine |
| | |
| | the extent of the problem, and to determine |
| | |
| | corrective |
| | |
| | actions that should be taken.At Oyster Creek, several non-licensed |
| | |
| | PEOs were involved with falsification |
| | |
| | of records associated |
| | |
| | with routine plant log taking rounds. None of the records involved were related to technical |
| | |
| | specifications. |
| | |
| | The discovery |
| | |
| | of the falsified |
| | |
| | log entries was from an ongoing random investigation |
| | |
| | comparing security door entry records with operator rounds.As a result of discrepancies |
| | |
| | found at Seabrook, Oyster Creek, and Millstone, at least one indivie-a-yn |
| | |
| | his e-pT tte-rmnn iniated,-s-everaltudiv-tduals- |
| | -resigned, and several other individuals |
| | |
| | were suspended. |
| | |
| | On January 28, 1992, two Instrumentation |
| | |
| | and Control technicians |
| | |
| | at the Vogtle Electric Generating |
| | |
| | Plant, Unit 1, performed |
| | |
| | a surveillance |
| | |
| | on a portion of the reactor trip system instrumentation. |
| | |
| | The Georgia Power Company (the licensee) |
| | informed the NRC that the technicians |
| | |
| | failed to properly follow the surveillance |
| | |
| | procedure |
| | |
| | and subsequently |
| | |
| | created the data that was entered on the calibration |
| | |
| | data sheet.NRC evaluation |
| | |
| | of each of these matters is continuing. |
| | |
| | Discussion |
| | |
| | of Safety Significance |
| | |
| | Maintenance |
| | |
| | of shift records, log sheets, and surveillance |
| | |
| | records, attention to detail, and work ethics are important |
| | |
| | factors which contribute |
| | |
| | to the safe operation |
| | |
| | of nuclear power plants. Complacency, by mechanics, technicians, or licensed or non-licensed |
| | |
| | operators, cannot be tolerated. |
| | |
| | Similarly, manage-ment expectations |
| | |
| | and supervisory |
| | |
| | overview of rounds need to be clearly communicated |
| | |
| | and monitored. |
| | |
| | All personnel |
| | |
| | involved in NRC-regulated |
| | |
| | activities |
| | |
| | are responsible |
| | |
| | for complying |
| | |
| | with applicable |
| | |
| | NRC regulatory |
| | |
| | requirements |
| | |
| | and other Federal laws. Log keeping activities |
| | |
| | as well as surveillances |
| | |
| | performed |
| | |
| | by licensed or non-licensed |
| | |
| | personnel |
| | |
| | are subject to the requirements |
| | |
| | of 10 CFR 50.9(a) regarding |
| | |
| | completeness |
| | |
| | and accuracy of information. |
| | |
| | IN 92-30 April 23, 1992 In addition, the administrative |
| | |
| | section of plant technical |
| | |
| | specifications |
| | |
| | requires that written procedures |
| | |
| | be implemented |
| | |
| | covering the applicable |
| | |
| | proce-dures in Appendix A of Regulatory |
| | |
| | Guide 1.33, Quality Assurance |
| | |
| | Program Requirements (Operation). |
| | |
| | Among the safety-related |
| | |
| | activities |
| | |
| | which Appendix A states should be covered by written procedures |
| | |
| | are surveillances |
| | |
| | and log entries.Willful violations, committed |
| | |
| | by personnel |
| | |
| | at any level of a licensee's |
| | |
| | organization, are of regulatory |
| | |
| | concern because the NRC must have reasonable |
| | |
| | assurance |
| | |
| | that licensed activities |
| | |
| | will be conducted |
| | |
| | in a manner that will protect the public health and safety. Such reasonable |
| | |
| | assurance |
| | |
| | is provided in large part by the integrity |
| | |
| | and conscientiousness |
| | |
| | of each individual |
| | |
| | performing |
| | |
| | licensed activities. |
| | |
| | Deliberate |
| | |
| | violations |
| | |
| | concerning |
| | |
| | matters within the scope of an individual's |
| | |
| | responsibilities, including |
| | |
| | falsification |
| | |
| | of records, will be considered |
| | |
| | for enforcement |
| | |
| | action against the individual |
| | |
| | as well as the facility licensee. |
| | |
| | As provided in 10 CFR 50.5, "Deliberate |
| | |
| | Misconduct |
| | |
| | by Unlicensed |
| | |
| | Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement |
| | |
| | action against unlicensed |
| | |
| | personnel |
| | |
| | who deliberately |
| | |
| | cause a licensee to be in violation |
| | |
| | of the Commission's |
| | |
| | regulations |
| | |
| | or who provide false information |
| | |
| | to the licensee concerning |
| | |
| | licensed activities. |
|
| |
|
| ==Addressees== | | ==Addressees== |
| may wish to take actions as appropriate to ensure that plantpersonnel are properly performing their assigned duties. | | may wish to take actions as appropriate |
| | |
| | to ensure that plant personnel |
| | |
| | are properly performing |
| | |
| | their assigned duties. |
|
| |
|
| ==Addressees== | | ==Addressees== |
| may alsowish to distribute copies of this information notice to all their employees.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contact(s) listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contact(s): David C. Fischer, NRR(301) 504-1154Eugene M. Kelly, RI(215) 337-5183James A. Prell, RI(215) 337-5108Attachment: List of gecently I sued NRC Information Notices | | may also wish to distribute |
| | |
| | copies of this information |
| | |
| | notice to all their employees. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contact(s) |
| | listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational |
| | |
| | ===Events Assessment=== |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contact(s): |
| | David C. Fischer, NRR (301) 504-1154 Eugene M. Kelly, RI (215) 337-5183 James A. Prell, RI (215) 337-5108 Attachment: |
| | List of gecently I sued NRC Information |
| | |
| | Notices |
| | |
| | m z ,-0190 rn Z 0 FQ)m 0>0 CD C e I D mC C,0 cn"3 an 0 2*oi G)C)z0=i CJ > 0 O = a U)0 nU)G) m'ii >~s r s Attachment |
| | |
| | IN 92-30 April 23, 1992 Page I of 1 I I I I I LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 92-21, Spent Fuel Pool Re- 04/22/92 All holders of OLs or CPs Supp. 1 activity Calculations |
| | |
| | for-nuclear |
| | |
| | power reactors.92-29 Potential |
| | |
| | Breaker Mis- 04/17/92 All holders of OLs or CPs coordination |
| | |
| | Caused by for nuclear power reactors.Instantaneous |
| | |
| | Trip Circuitry 92-28 Inadequate |
| | |
| | Fire Suppres- 04/08/92 All holders of OLs or CPs sion System Testing for nuclear power reactors.92-27 Thermally |
| | |
| | Induced Acceler- 04/03/92 All holders of OLs or CPs ated Aging and Failure of for nuclear power reactors.ITE/GOULD |
| | |
| | A.C. Relays Used in Safety-Related |
| | |
| | Applic-ations 92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPs Operated Flexible Wedge for nuclear power reactors.Gate Valves 92-25 Potential |
| | |
| | Weakness in 03/31/92 All holders of OLs or CPs Licensee Procedures |
| | |
| | for A for nuclear power reactor Loss of the Refueling Cavity Water 92-24 Distributor |
| | |
| | Modification |
| | |
| | to 03/30/92 All holders of OLs or CPs Certain Commercial-Grade |
| | |
| | for nuclear power reactors.Agastat Electrical |
| | |
| | Relays 92-23 Results of Validation |
| | |
| | Test- 03/27/92 All holders of OLs or CPs ing of Motor-Operated |
| | |
| | Valve for nuclear power reactors Diagnostic |
| | |
| | Equipment |
| | |
| | and all vendors of motor-operated valve (MOV) diag-nostic equipment. |
| | |
| | OL -Operating |
| | |
| | License CP |
| | |
| | * Construction |
| | |
| | Permit |
| | |
| | IN 92-30 April 23, 1992 In addition, the administrative |
| | |
| | section of plant technical |
| | |
| | specifications |
| | |
| | requires that written procedures |
| | |
| | be implemented |
| | |
| | covering the applicable |
| | |
| | proce-dures in Appendix A of Regulatory |
| | |
| | Guide 1.33, Quality Assurance |
| | |
| | Program Requirements (Operation). |
| | |
| | Among the safety-related |
| | |
| | activities |
| | |
| | which Appendix A states should be covered by written procedures |
| | |
| | are surveillances |
| | |
| | and log entries.Willful violations, committed |
| | |
| | by personnel |
| | |
| | at any level of a licensee's |
| | |
| | organization, are of regulatory |
| | |
| | concern because the NRC must have reasonable |
| | |
| | assurance |
| | |
| | that licensed activities |
| | |
| | will be conducted |
| | |
| | in a manner that will protect the public health and safety. Such reasonable |
| | |
| | assurance |
| | |
| | is provided in large part by the integrity |
| | |
| | and conscientiousness |
| | |
| | of each individual |
| | |
| | performing |
| | |
| | licensed activities. |
| | |
| | Deliberate |
| | |
| | violations |
| | |
| | concerning |
| | |
| | matters within the scope of an individual's |
| | |
| | responsibilities, including |
| | |
| | falsification |
| | |
| | of records, will be considered |
| | |
| | for enforcement |
| | |
| | action against the individual |
| | |
| | as well as the facility licensee. |
| | |
| | As provided in 10 CFR 50.5, "Deliberate |
| | |
| | Misconduct |
| | |
| | by Unlicensed |
| | |
| | Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement |
| | |
| | action against unlicensed |
| | |
| | personnel |
| | |
| | who deliberately |
| | |
| | cause a licensee to be in violation |
| | |
| | of the Commission's |
|
| |
|
| mz,-0190rn Z0 FQ)m0>0CDCeI DmCC,0cn"3an02*oiG)C)z0=i CJ > 0O = a U)0 nU)G) m'ii >~s rsAttachmentIN 92-30April 23, 1992Page I of 1IIIIILIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-21, Spent Fuel Pool Re- 04/22/92 All holders of OLs or CPsSupp. 1 activity Calculations for-nuclear power reactors.92-29 Potential Breaker Mis- 04/17/92 All holders of OLs or CPscoordination Caused by for nuclear power reactors.Instantaneous TripCircuitry92-28 Inadequate Fire Suppres- 04/08/92 All holders of OLs or CPssion System Testing for nuclear power reactors.92-27 Thermally Induced Acceler- 04/03/92 All holders of OLs or CPsated Aging and Failure of for nuclear power reactors.ITE/GOULD A.C. Relays Usedin Safety-Related Applic-ations92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPsOperated Flexible Wedge for nuclear power reactors.Gate Valves92-25 Potential Weakness in 03/31/92 All holders of OLs or CPsLicensee Procedures for A for nuclear power reactorLoss of the RefuelingCavity Water92-24 Distributor Modification to 03/30/92 All holders of OLs or CPsCertain Commercial-Grade for nuclear power reactors.Agastat Electrical Relays92-23 Results of Validation Test- 03/27/92 All holders of OLs or CPsing of Motor-Operated Valve for nuclear power reactorsDiagnostic Equipment and all vendors of motor-operated valve (MOV) diag-nostic equipment.OL -Operating LicenseCP
| | regulations |
|
| |
|
| * Construction Permit
| | or who provide false information |
|
| |
|
| IN 92-30April 23, 1992 In addition, the administrative section of plant technical specificationsrequires that written procedures be implemented covering the applicable proce-dures in Appendix A of Regulatory Guide 1.33, Quality Assurance ProgramRequirements (Operation). Among the safety-related activities which Appendix Astates should be covered by written procedures are surveillances and logentries.Willful violations, committed by personnel at any level of a licensee'sorganization, are of regulatory concern because the NRC must have reasonableassurance that licensed activities will be conducted in a manner that willprotect the public health and safety. Such reasonable assurance is providedin large part by the integrity and conscientiousness of each individualperforming licensed activities. Deliberate violations concerning matterswithin the scope of an individual's responsibilities, including falsificationof records, will be considered for enforcement action against the individualas well as the facility licensee. As provided in 10 CFR 50.5, "DeliberateMisconduct by Unlicensed Persons," 56 Federal Register 40684, August 15, 1991,the NRC may take direct enforcement action against unlicensed personnel whodeliberately cause a licensee to be in violation of the Commission's regulationsor who provide false information to the licensee concerning licensed activities.
| | to the licensee concerning |
| | |
| | licensed activities. |
|
| |
|
| ==Addressees== | | ==Addressees== |
| may wish to take actions as appropriate to ensure that plantpersonnel are properly performing their assigned duties. | | may wish to take actions as appropriate |
| | |
| | to ensure that plant personnel |
| | |
| | are properly performing |
| | |
| | their assigned duties. |
|
| |
|
| ==Addressees== | | ==Addressees== |
| may alsowish to distribute copies of this information notice to all their employees.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contact(s) listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contact(s): David C. Fischer, NRR(301) 504-1154Eugene M. Kelly, RI(215) 337-5183James A. Prell, RI(215) 337-5108Attachment: List of Recently Issued NRC Information NoticesDocument Name: IN/GUNDECK LOGCONCURRENCES --- SEE NEXT PAGE | | may also wish to distribute |
| | |
| | copies of this information |
| | |
| | notice to all their employees. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contact(s) |
| | listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational |
| | |
| | ===Events Assessment=== |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contact(s): |
| | David C. Fischer, NRR (301) 504-1154 Eugene M. Kelly, RI (215) 337-5183 James A. Prell, RI (215) 337-5108 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices Document Name: IN/GUNDECK |
| | |
| | LOG CONCURRENCES |
| | |
| | --- SEE NEXT PAGE |
| | |
| | *SEE PREVIOUS CONCURRENCE |
| | |
| | OEAB:DOEA:NRR |
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| | DCFischer* |
| | 04/07/92 ADM:RPB JMain*04/08/92 C:OEAB:DOEA:NRR |
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| | AEChaffee* |
| | 04/07/92 C:LOLB:DLPQ:NRR |
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| | RMGallo*04/08/92 C:LHFB:DLPQ:NRR |
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| | JSWenmiel* |
| | 04/09/92 RI LBettenhausen* |
| | 04/14/92 D:DRP:RII LAReyes*04/15/92 D: OE JLieberman* |
| | 04/15/92 C:OGCB:DOEA:NRR |
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| | CHBerlinger* |
| | 04/15/92 D:D : CE 04/ 9v |
| | |
| | *SEE PREVIOUS CONCURRENCE |
| | |
| | OEAB:DOEA:NRR |
| | |
| | DCFischer* |
| | 04/07/92 C:LHFB:DLPQ:NRR |
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| | JSWermiel* |
| | 04/09/92 C:OGC CHBerjinger |
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| | 04/15 /92 ADM:RPB JMa i n*04/08/92 RI ter st'LBettenhausen |
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| | 04/14/92 C:OEAB:DOEA:NRR |
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| | C:LOLB:DLPQ:NRR |
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| | AEChaffee* |
| | RMGallo*04/07/92 04/08/92 D:DRP:RII |
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| | ';*" M. I.LAReyes i rman 04/15/92 04 /92 D:DOEA:NRR |
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| | CERossi ,3 04/ /92- IN 92-XX April xx, 1992 This information |
| | |
| | notice requires no specific action or Written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this n ptice, please contact one of the technical |
| | |
| | contact(s) |
| | listed below or the propriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. ossi, Director Division f Operational |
| | |
| | ===Events Assessment=== |
| | Office o Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contact(s): |
| | Davi C. Fischer, RR (301) 4-1154 Eugene M. 1 , RI (215) 337-51 Attachment: |
| | List of Recently Issue NR Information |
| | |
| | Notices Document Name: IN/GUNDECK |
| | |
| | OG*SEE PREVIOUS CONCURRENCY |
| | |
| | p i\OEAB:DOEA:NRR |
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| | ADM:RPB X C:OEAB:DOEA:NRR |
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| | C:LOLB:DLPQ:NRR |
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| | DCFischer* |
| | JMain AEChaffee* |
| | MGallo 04/07/92) |
| | ¢p 04/.3/92 04/07/92 0 \ /92 CA CILHFB:DLPQ:NRR |
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| | DRP:RI C:OGCB:DOEA:NRR |
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| | D:D A:NRR JSWermiel |
| | |
| | EMKell CHBerlinger |
| | |
| | CERos 04/ '/92 04/ / 2 04/ /92 04/ /92 Document Name: OEAB:DOEA:NRR |
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| | DCFischer 04/7 /92 C:LHFB:DLPQ:NRR |
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| | JSWermiel 04/ /92 IN/GUNDECK |
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| | LOG NRR C:LOLB:DLPQ:NRR |
| | |
| | RMGallo 04/ /92 04/ /':DOEA:NRR.Rossi 4/ /92 04/ |
| | IN 92-XX April xx, 1992 This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contact(s) |
| | listed below or th appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Charl E. Rossi, Director Divis on of Operational |
| | |
| | ===Events Assessment=== |
| | Offi e of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contact(s): |
| | D id C. Fisch , NRR (301 504-1154 Eugene Kel y, RI (215) 337 1 3 Attachment: |
| | List of Recently Iss e RC Information |
| | |
| | Notices Document Name: IN/GUNDECK |
| | |
| | LOG OEAB:DOEA:NRR |
| | |
| | ADM:RPB C:OEAB:DO |
| | |
| | :NRR C:LOLB:DLPQ:NRR |
| | |
| | DCFischer |
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| | JMain Q AEChaffee |
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| | RMGallo 04/ /92 04/8 /9'2 04/ /92 04/ /92 C:LHFB:DLPQ:NRR |
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| | C:OGCB:DOE |
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| | :NRR D/DOEA:NRR |
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| *SEE PREVIOUS CONCURRENCEOEAB:DOEA:NRRDCFischer*04/07/92ADM:RPBJMain*04/08/92C:OEAB:DOEA:NRRAEChaffee*04/07/92C:LOLB:DLPQ:NRRRMGallo*04/08/92C:LHFB:DLPQ:NRRJSWenmiel*04/09/92RILBettenhausen*04/14/92D:DRP:RIILAReyes*04/15/92D: OEJLieberman*04/15/92C:OGCB:DOEA:NRRCHBerlinger*04/15/92D:D :CE04/ 9v
| | JSWermiel |
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| |
|
| *SEE PREVIOUS CONCURRENCEOEAB:DOEA:NRRDCFischer*04/07/92C:LHFB:DLPQ:NRRJSWermiel*04/09/92C:OGCCHBerjinger04/15 /92ADM:RPBJMa i n*04/08/92RI ter st'LBettenhausen04/14/92C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRRAEChaffee* RMGallo*04/07/92 04/08/92D:DRP:RII ';*" M. I.LAReyes i rman04/15/92 04 /92D:DOEA:NRRCERossi ,304/ /92- IN 92-XXApril xx, 1992 This information notice requires no specific action or Written response. Ifyou have any questions about the information in this n ptice, please contactone of the technical contact(s) listed below or the propriate Office ofNuclear Reactor Regulation (NRR) project manager.Charles E. ossi, DirectorDivision f Operational Events AssessmentOffice o Nuclear Reactor RegulationTechnical contact(s): Davi C. Fischer, RR(301) 4-1154Eugene M. 1 , RI(215) 337-51Attachment: List of Recently Issue NR Information NoticesDocument Name: IN/GUNDECK OG*SEE PREVIOUS CONCURRENCY p i\OEAB:DOEA:NRR ADM:RPB X C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRRDCFischer* JMain AEChaffee* MGallo04/07/92) ¢p 04/.3/92 04/07/92 0 \ /92 CACILHFB:DLPQ:NRR DRP:RI C:OGCB:DOEA:NRR D:D A:NRRJSWermiel EMKell CHBerlinger CERos04/ '/92 04/ / 2 04/ /92 04/ /92 Document Name:OEAB:DOEA:NRRDCFischer04/7 /92C:LHFB:DLPQ:NRRJSWermiel04/ /92IN/GUNDECK LOGNRRC:LOLB:DLPQ:NRRRMGallo04/ /9204/ /':DOEA:NRR.Rossi4/ /9204/
| | CBerlingej |
| IN 92-XXApril xx, 1992 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contact(s) listed below or th appropriate Office of NuclearReactor Regulation (NRR) project manager.Charl E. Rossi, DirectorDivis on of Operational Events AssessmentOffi e of Nuclear Reactor RegulationTechnical contact(s): D id C. Fisch , NRR(301 504-1154Eugene Kel y, RI(215) 337 1 3Attachment: List of Recently Iss e RC Information NoticesDocument Name: IN/GUNDECK LOGOEAB:DOEA:NRR ADM:RPB C:OEAB:DO :NRR C:LOLB:DLPQ:NRRDCFischer JMain Q AEChaffee RMGallo04/ /92 04/8 /9'2 04/ /92 04/ /92C:LHFB:DLPQ:NRR C:OGCB:DOE :NRR D/DOEA:NRRJSWermiel CBerlingej CERossi04/ /92 04/ /92 / 04/ /92I
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| }} | | CERossi 04/ /92 04/ /92 / 04/ /92 I}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Falsification of Plant RecordsML031200393 |
Person / Time |
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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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
04/23/1992 |
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From: |
Rossi C E Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-92-030, NUDOCS 9204170113 |
Download: ML031200393 (10) |
|
Similar Documents at 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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. 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Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - 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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
I I UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 23, 1992 NRC INFORMATION
NOTICE 92-30: FALSIFICATION
OF PLANT RECORDS
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors and all licensed operators
and senior operators.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to the NRC's concern that plant mechanics, technicians, and operators
may have falsified
plant logs at several nuclear power plants. The NRC is reminding
plant mechanics, technicians, and operators (both licensed and non-licensed)
of the penalties
that could result from intentionally
violating
Federal regulatory
requirements
and criminal statutes.The NRC is also reminding
addressees
that all personnel
are subject to the requirements
of 10 CFR 50.9(a) which states that information
required by statute or by the Commission's
regulations
be complete and accurate in all material aspects. It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
On March 1, 1992, the shift superintendent
for the Public Service Company of New Hampshire's
Seabrook Nuclear Station was conducting
a surveillance, in accordance
with a personnel
performance
monitoring
program, to verify that operations
department
personnel
were properly performing
their assigned duties.On this occasion, the shift superintendent
reviewed the security department's
computerized
card key entry records against locations
in which an auxiliary operator's (AO's) log entries had indicated
that he had performed
inspections.
The shift superintendent
found that the AO had logged "SAT" (satisfactory)
for some plant areas, indicating
that he had performed
the required periodic inspections, although the computerized
security data indicated
that some of these areas had not been entered.The shift superintendent's
findings prompted the licensee to establish
an independent
review team (IRT) to performi a comprehensive
analysis of the root cause(s) and the generic implications
of this occurrence.
The IRT interviewed
the individuals
involved and the management
and supervisory
staff and examined a wide range of historical
records created or used since the issuance of the full power operating
license, including
security logs, 9204170113
5/!
IN 92-30 April 23, 1992 operations
logs and procedures, administrative
program manuals, and training lesson plans. Discrepancies
were found by the IRT, and some involved violations
of technical
specifications
and some involved licensed operators.
In response to the findings at Seabrook, random checks were conducted
at the Haddam Neck Plant and Millstone
Nuclear Power Station. To date, no dis-crepancies
have been identified
at Haddam Neck. At Millstone, the Northeast Nuclear Energy Company (the licensee)
determined
that several non-licensed
plant equipment
operators (PEOs) had not completed
certain inspection
rounds as represented
in their logs. The Millstone
licensee has since expanded its evaluation
to verifying
the accuracy of log entries recorded by all PEOs.The management
at Millstone
informed plant personnel
of its findings and expectations
for recording
log entries. The Millstone
licensee also established
an IRT (with a representative
from the Seabrook IRT acting in an advisory status) to investigate
its findings, to determine
the extent of the problem, and to determine
corrective
actions that should be taken.At Oyster Creek, several non-licensed
PEOs were involved with falsification
of records associated
with routine plant log taking rounds. None of the records involved were related to technical
specifications.
The discovery
of the falsified
log entries was from an ongoing random investigation
comparing security door entry records with operator rounds.As a result of discrepancies
found at Seabrook, Oyster Creek, and Millstone, at least one indivie-a-yn
his e-pT tte-rmnn iniated,-s-everaltudiv-tduals-
-resigned, and several other individuals
were suspended.
On January 28, 1992, two Instrumentation
and Control technicians
at the Vogtle Electric Generating
Plant, Unit 1, performed
a surveillance
on a portion of the reactor trip system instrumentation.
The Georgia Power Company (the licensee)
informed the NRC that the technicians
failed to properly follow the surveillance
procedure
and subsequently
created the data that was entered on the calibration
data sheet.NRC evaluation
of each of these matters is continuing.
Discussion
of Safety Significance
Maintenance
of shift records, log sheets, and surveillance
records, attention to detail, and work ethics are important
factors which contribute
to the safe operation
of nuclear power plants. Complacency, by mechanics, technicians, or licensed or non-licensed
operators, cannot be tolerated.
Similarly, manage-ment expectations
and supervisory
overview of rounds need to be clearly communicated
and monitored.
All personnel
involved in NRC-regulated
activities
are responsible
for complying
with applicable
NRC regulatory
requirements
and other Federal laws. Log keeping activities
as well as surveillances
performed
by licensed or non-licensed
personnel
are subject to the requirements
of 10 CFR 50.9(a) regarding
completeness
and accuracy of information.
IN 92-30 April 23, 1992 In addition, the administrative
section of plant technical
specifications
requires that written procedures
be implemented
covering the applicable
proce-dures in Appendix A of Regulatory
Guide 1.33, Quality Assurance
Program Requirements (Operation).
Among the safety-related
activities
which Appendix A states should be covered by written procedures
are surveillances
and log entries.Willful violations, committed
by personnel
at any level of a licensee's
organization, are of regulatory
concern because the NRC must have reasonable
assurance
that licensed activities
will be conducted
in a manner that will protect the public health and safety. Such reasonable
assurance
is provided in large part by the integrity
and conscientiousness
of each individual
performing
licensed activities.
Deliberate
violations
concerning
matters within the scope of an individual's
responsibilities, including
falsification
of records, will be considered
for enforcement
action against the individual
as well as the facility licensee.
As provided in 10 CFR 50.5, "Deliberate
Misconduct
by Unlicensed
Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement
action against unlicensed
personnel
who deliberately
cause a licensee to be in violation
of the Commission's
regulations
or who provide false information
to the licensee concerning
licensed activities.
Addressees
may wish to take actions as appropriate
to ensure that plant personnel
are properly performing
their assigned duties.
Addressees
may also wish to distribute
copies of this information
notice to all their employees.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contact(s)
listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact(s):
David C. Fischer, NRR (301) 504-1154 Eugene M. Kelly, RI (215) 337-5183 James A. Prell, RI (215) 337-5108 Attachment:
List of gecently I sued NRC Information
Notices
m z ,-0190 rn Z 0 FQ)m 0>0 CD C e I D mC C,0 cn"3 an 0 2*oi G)C)z0=i CJ > 0 O = a U)0 nU)G) m'ii >~s r s Attachment
IN 92-30 April 23, 1992 Page I of 1 I I I I I LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 92-21, Spent Fuel Pool Re- 04/22/92 All holders of OLs or CPs Supp. 1 activity Calculations
for-nuclear
power reactors.92-29 Potential
Breaker Mis- 04/17/92 All holders of OLs or CPs coordination
Caused by for nuclear power reactors.Instantaneous
Trip Circuitry 92-28 Inadequate
Fire Suppres- 04/08/92 All holders of OLs or CPs sion System Testing for nuclear power reactors.92-27 Thermally
Induced Acceler- 04/03/92 All holders of OLs or CPs ated Aging and Failure of for nuclear power reactors.ITE/GOULD
A.C. Relays Used in Safety-Related
Applic-ations 92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPs Operated Flexible Wedge for nuclear power reactors.Gate Valves 92-25 Potential
Weakness in 03/31/92 All holders of OLs or CPs Licensee Procedures
for A for nuclear power reactor Loss of the Refueling Cavity Water 92-24 Distributor
Modification
to 03/30/92 All holders of OLs or CPs Certain Commercial-Grade
for nuclear power reactors.Agastat Electrical
Relays 92-23 Results of Validation
Test- 03/27/92 All holders of OLs or CPs ing of Motor-Operated
Valve for nuclear power reactors Diagnostic
Equipment
and all vendors of motor-operated valve (MOV) diag-nostic equipment.
OL -Operating
License CP
Permit
IN 92-30 April 23, 1992 In addition, the administrative
section of plant technical
specifications
requires that written procedures
be implemented
covering the applicable
proce-dures in Appendix A of Regulatory
Guide 1.33, Quality Assurance
Program Requirements (Operation).
Among the safety-related
activities
which Appendix A states should be covered by written procedures
are surveillances
and log entries.Willful violations, committed
by personnel
at any level of a licensee's
organization, are of regulatory
concern because the NRC must have reasonable
assurance
that licensed activities
will be conducted
in a manner that will protect the public health and safety. Such reasonable
assurance
is provided in large part by the integrity
and conscientiousness
of each individual
performing
licensed activities.
Deliberate
violations
concerning
matters within the scope of an individual's
responsibilities, including
falsification
of records, will be considered
for enforcement
action against the individual
as well as the facility licensee.
As provided in 10 CFR 50.5, "Deliberate
Misconduct
by Unlicensed
Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement
action against unlicensed
personnel
who deliberately
cause a licensee to be in violation
of the Commission's
regulations
or who provide false information
to the licensee concerning
licensed activities.
Addressees
may wish to take actions as appropriate
to ensure that plant personnel
are properly performing
their assigned duties.
Addressees
may also wish to distribute
copies of this information
notice to all their employees.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contact(s)
listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact(s):
David C. Fischer, NRR (301) 504-1154 Eugene M. Kelly, RI (215) 337-5183 James A. Prell, RI (215) 337-5108 Attachment:
List of Recently Issued NRC Information
Notices Document Name: IN/GUNDECK
LOG CONCURRENCES
--- SEE NEXT PAGE
OEAB:DOEA:NRR
DCFischer*
04/07/92 ADM:RPB JMain*04/08/92 C:OEAB:DOEA:NRR
AEChaffee*
04/07/92 C:LOLB:DLPQ:NRR
RMGallo*04/08/92 C:LHFB:DLPQ:NRR
JSWenmiel*
04/09/92 RI LBettenhausen*
04/14/92 D:DRP:RII LAReyes*04/15/92 D: OE JLieberman*
04/15/92 C:OGCB:DOEA:NRR
CHBerlinger*
04/15/92 D:D : CE 04/ 9v
OEAB:DOEA:NRR
DCFischer*
04/07/92 C:LHFB:DLPQ:NRR
JSWermiel*
04/09/92 C:OGC CHBerjinger
04/15 /92 ADM:RPB JMa i n*04/08/92 RI ter st'LBettenhausen
04/14/92 C:OEAB:DOEA:NRR
C:LOLB:DLPQ:NRR
AEChaffee*
RMGallo*04/07/92 04/08/92 D:DRP:RII
';*" M. I.LAReyes i rman 04/15/92 04 /92 D:DOEA:NRR
CERossi ,3 04/ /92- IN 92-XX April xx, 1992 This information
notice requires no specific action or Written response.
If you have any questions
about the information
in this n ptice, please contact one of the technical
contact(s)
listed below or the propriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. ossi, Director Division f Operational
Events Assessment
Office o Nuclear Reactor Regulation
Technical
contact(s):
Davi C. Fischer, RR (301) 4-1154 Eugene M. 1 , RI (215) 337-51 Attachment:
List of Recently Issue NR Information
Notices Document Name: IN/GUNDECK
OG*SEE PREVIOUS CONCURRENCY
p i\OEAB:DOEA:NRR
ADM:RPB X C:OEAB:DOEA:NRR
C:LOLB:DLPQ:NRR
DCFischer*
JMain AEChaffee*
MGallo 04/07/92)
¢p 04/.3/92 04/07/92 0 \ /92 CA CILHFB:DLPQ:NRR
DRP:RI C:OGCB:DOEA:NRR
D:D A:NRR JSWermiel
EMKell CHBerlinger
CERos 04/ '/92 04/ / 2 04/ /92 04/ /92 Document Name: OEAB:DOEA:NRR
DCFischer 04/7 /92 C:LHFB:DLPQ:NRR
JSWermiel 04/ /92 IN/GUNDECK
LOG NRR C:LOLB:DLPQ:NRR
RMGallo 04/ /92 04/ /':DOEA:NRR.Rossi 4/ /92 04/
IN 92-XX April xx, 1992 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contact(s)
listed below or th appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charl E. Rossi, Director Divis on of Operational
Events Assessment
Offi e of Nuclear Reactor Regulation
Technical
contact(s):
D id C. Fisch , NRR (301 504-1154 Eugene Kel y, RI (215) 337 1 3 Attachment:
List of Recently Iss e RC Information
Notices Document Name: IN/GUNDECK
LOG OEAB:DOEA:NRR
ADM:RPB C:OEAB:DO
- NRR C:LOLB:DLPQ:NRR
DCFischer
JMain Q AEChaffee
RMGallo 04/ /92 04/8 /9'2 04/ /92 04/ /92 C:LHFB:DLPQ:NRR
C:OGCB:DOE
- NRR D/DOEA:NRR
JSWermiel
CBerlingej
CERossi 04/ /92 04/ /92 / 04/ /92 I
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list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992, Topic: Overspeed trip)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992, Topic: Overspeed trip)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992, Topic: Overspeed trip)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade, Overspeed trip)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992, Topic: Unidentified leakage)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992, Topic: Local Leak Rate Testing)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
... further results |
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