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| | issue date = 04/23/1992 | | | issue date = 04/23/1992 |
| | title = Falsification of Plant Records | | | title = Falsification of Plant Records |
| | author name = Rossi C E | | | author name = Rossi C |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 10 | | | page count = 10 |
| }} | | }} |
| {{#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 |
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| | UNITED STATES |
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| | NUCLEAR REGULATORY COMMISSION |
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| | OFFICE OF NUCLEAR REACTOR REGULATION |
| | |
| | WASHINGTON, D.C. 20555 April 23, 1992 NRC INFORMATION NOTICE 92-30: FALSIFICATION OF PLANT RECORDS |
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|
| ==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. |
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| |
|
| ==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== | | ==Description of Circumstances== |
| 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/! | | On March 1, 1992, the shift superintendent for the Public Service Company of |
| 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.
| | |
| | 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 |
|
| |
|
| 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. | | 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== | | ==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. |
|
| |
|
| 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
| | 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 |
| | |
| | e |
| | |
| | m mC |
| | |
| | z |
| | |
| | ,- |
| | Attachment |
| | |
| | 0190 IN 92-30 |
| | C,0 |
| | ID April 23, 1992 Page I of 1 LIST OF RECENTLY ISSUED |
| | |
| | rnZ NRC INFORMATION NOTICES |
| | |
| | cn |
| | |
| | CD |
| | |
| | 0 FQ) |
| | m C "3 I |
| | |
| | Information Date of |
| | |
| | 0> I Notice No. Subject Issuance Issued to |
| | |
| | 0 I |
| | |
| | an I 04/22/92 All holders of OLs or CPs |
| | |
| | 92-21, Spent Fuel Pool Re- I 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. |
| | |
| | *oi ITE/GOULD A.C. Relays Used |
| | |
| | in Safety-Related Applic- ations |
| | |
| | 0G)C) 92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPs |
| | |
| | Operated Flexible Wedge for nuclear power reactors. |
| | |
| | 2 z0 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. |
| | |
| | 0 nU) |
| | =i CJ > 0 |
| | 'ii >~ |
| | sO = a rU) OL - Operating License |
| | |
| | sm CP |
|
| |
|
| * Construction Permit | | * Construction Permit |
|
| |
|
| 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. | | G) |
| | |
| | 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 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 ADM:RPB C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR |
| | |
| | DCFischer* JMain* AEChaffee* RMGallo* |
| | 04/07/92 04/08/92 04/07/92 04/08/92 C:LHFB:DLPQ:NRR RI D:DRP:RII D: OE |
| | |
| | JSWenmiel* LBettenhausen* LAReyes* JLieberman* |
| | 04/09/92 04/14/92 04/15/92 04/15/92 C:OGCB:DOEA:NRR D:D : |
| | CHBerlinger* CE |
| | |
| | 04/15/92 04/ 9v |
| | |
| | *SEE PREVIOUS CONCURRENCE |
| | |
| | OEAB:DOEA:NRR ADM:RPB C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR |
| | |
| | DCFischer* JMa in* AEChaffee* RMGallo* |
| | 04/07/92 04/08/92 04/07/92 04/08/92 C:LHFB:DLPQ:NRR RI ter st' D:DRP:RII ';*" M. I. |
| | |
| | JSWermiel* LBettenhausen LAReyes i rman |
| | |
| | 04/09/92 04/14/92 04/15/92 04 /92 C:OGC D:DOEA:NRR |
| | |
| | ===CHBerjinger CERossi ,3=== |
| | 04/15 /92 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 nptice, 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: IN/GUNDECK LOG |
| | |
| | OEAB:DOEA:NRR NRR C:LOLB:DLPQ: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
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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/
| | 04/7 /92 04/ /' 04/ /92 C:LHFB:DLPQ:NRR :DOEA:NRR |
| 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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| }} | | ===JSWermiel .Rossi=== |
| | 04/ /92 04/ 4/ /92 |
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| | IN 92-XX |
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| | April xx, 1992 This information notice requires no specific action or written response. If |
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| | you have any questions about the information in this notice, please contact one |
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| | of the technical contact(s) listed below or th appropriate Office of Nuclear |
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| | Reactor Regulation (NRR) project manager. |
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| | Charl E. Rossi, Director |
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| | Divis on of Operational Events Assessment |
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| | Offi e of Nuclear Reactor Regulation |
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| | Technical contact(s): D id C. Fisch , NRR |
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| | (301 504-1154 Eugene Kel y, RI |
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| | (215) 337 1 3 Attachment: List of Recently Iss e RC Information Notices |
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| | Document Name: IN/GUNDECK LOG |
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| | OEAB:DOEA:NRR ADM:RPB C:OEAB:DO :NRR C:LOLB:DLPQ:NRR |
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| | ===JSWermiel CBerlingej 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 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) |
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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
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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
e
m mC
z
,-
Attachment
0190 IN 92-30
C,0
ID April 23, 1992 Page I of 1 LIST OF RECENTLY ISSUED
rnZ NRC INFORMATION NOTICES
cn
CD
0 FQ)
m C "3 I
Information Date of
0> I Notice No. Subject Issuance Issued to
0 I
an I 04/22/92 All holders of OLs or CPs
92-21, Spent Fuel Pool Re- I 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.
- oi ITE/GOULD A.C. Relays Used
in Safety-Related Applic- ations
0G)C) 92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPs
Operated Flexible Wedge for nuclear power reactors.
2 z0 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.
0 nU)
=i CJ > 0
'ii >~
sO = a rU) OL - Operating License
sm CP
G)
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 ADM:RPB C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR
DCFischer* JMain* AEChaffee* RMGallo*
04/07/92 04/08/92 04/07/92 04/08/92 C:LHFB:DLPQ:NRR RI D:DRP:RII D: OE
JSWenmiel* LBettenhausen* LAReyes* JLieberman*
04/09/92 04/14/92 04/15/92 04/15/92 C:OGCB:DOEA:NRR D:D :
CHBerlinger* CE
04/15/92 04/ 9v
OEAB:DOEA:NRR ADM:RPB C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR
DCFischer* JMa in* AEChaffee* RMGallo*
04/07/92 04/08/92 04/07/92 04/08/92 C:LHFB:DLPQ:NRR RI ter st' D:DRP:RII ';*" M. I.
JSWermiel* LBettenhausen LAReyes i rman
04/09/92 04/14/92 04/15/92 04 /92 C:OGC D:DOEA:NRR
CHBerjinger CERossi ,3
04/15 /92 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 nptice, 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
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: IN/GUNDECK LOG
OEAB:DOEA:NRR NRR C:LOLB:DLPQ:NRR
DCFischer RMGallo
04/7 /92 04/ /' 04/ /92 C:LHFB:DLPQ:NRR :DOEA:NRR
JSWermiel .Rossi
04/ /92 04/ 4/ /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 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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