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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 I UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:I I |
|
| |
|
| COMMISSION
| | UNITED STATES |
|
| |
|
| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | NUCLEAR REGULATORY COMMISSION |
| WASHINGTON, D.C. 20555 April 23, 1992 NRC INFORMATION
| |
|
| |
|
| NOTICE 92-30: FALSIFICATION
| | OFFICE OF NUCLEAR REACTOR REGULATION |
|
| |
|
| OF PLANT RECORDS | | WASHINGTON, D.C. 20555 April 23, 1992 NRC INFORMATION NOTICE 92-30: FALSIFICATION OF PLANT RECORDS |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating | | All holders of operating licenses or construction permits for nuclear power |
|
| |
|
| licenses or construction
| | reactors and all licensed operators and senior operators. |
| | |
| permits for nuclear power reactors and all licensed operators
| |
| | |
| and senior operators. | |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information |
| | |
| 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) | | notice to alert addressees to the NRC's concern that plant mechanics, technicians, and operators may have falsified plant logs at several nuclear |
| determined
| |
|
| |
|
| that several non-licensed
| | power plants. The NRC is reminding plant mechanics, technicians, and operators |
|
| |
|
| plant equipment
| | (both licensed and non-licensed) of the penalties that could result from |
|
| |
|
| operators (PEOs) had not completed
| | intentionally violating Federal regulatory requirements and criminal statutes. |
|
| |
|
| certain inspection
| | The NRC is also reminding addressees that all personnel are subject to the |
|
| |
|
| rounds as represented
| | requirements of 10 CFR 50.9(a) which states that information required by |
|
| |
|
| in their logs. The Millstone | | statute or by the Commission's regulations be complete and accurate in all |
|
| |
|
| licensee has since expanded its evaluation
| | material aspects. It is expected that recipients will review the information |
|
| |
|
| to verifying | | for applicability to their facilities and consider actions, as appropriate, to |
|
| |
|
| the accuracy of log entries recorded by all PEOs.The management
| | avoid similar problems. However, suggestions contained in this information |
|
| |
|
| at Millstone
| | notice are not NRC requirements; therefore, no specific action or written |
|
| |
|
| informed plant personnel
| | response is required. |
|
| |
|
| of its findings and expectations | | ==Description of Circumstances== |
| | On March 1, 1992, the shift superintendent for the Public Service Company of |
|
| |
|
| for recording
| | New Hampshire's Seabrook Nuclear Station was conducting a surveillance, in |
|
| |
|
| log entries. The Millstone
| | accordance with a personnel performance monitoring program, to verify that |
|
| |
|
| licensee also established
| | operations department personnel were properly performing their assigned duties. |
|
| |
|
| an IRT (with a representative
| | On this occasion, the shift superintendent reviewed the security department's |
|
| |
|
| from the Seabrook IRT acting in an advisory status) to investigate
| | computerized card key entry records against locations in which an auxiliary |
|
| |
|
| its findings, to determine
| | operator's (AO's) log entries had indicated that he had performed inspections. |
|
| |
|
| the extent of the problem, and to determine | | The shift superintendent found that the AO had logged "SAT" (satisfactory) for |
|
| |
|
| corrective
| | some plant areas, indicating that he had performed the required periodic |
|
| |
|
| actions that should be taken.At Oyster Creek, several non-licensed
| | inspections, although the computerized security data indicated that some of |
|
| |
|
| PEOs were involved with falsification
| | these areas had not been entered. |
|
| |
|
| of records associated
| | The shift superintendent's findings prompted the licensee to establish an |
|
| |
|
| with routine plant log taking rounds. None of the records involved were related to technical
| | independent review team (IRT) to performi a comprehensive analysis of the |
|
| |
|
| specifications.
| | root cause(s) and the generic implications of this occurrence. The IRT |
|
| |
|
| The discovery
| | interviewed the individuals involved and the management and supervisory |
|
| |
|
| of the falsified | | staff and examined a wide range of historical records created or used since |
|
| |
|
| log entries was from an ongoing random investigation
| | the issuance of the full power operating license, including security logs, |
| | 9204170113 |
| | 5/! |
|
| |
|
| comparing security door entry records with operator rounds.As a result of discrepancies
| | IN 92-30 |
| | April 23, 1992 operations logs and procedures, administrative program manuals, and training |
|
| |
|
| found at Seabrook, Oyster Creek, and Millstone, at least one indivie-a-yn | | lesson plans. Discrepancies were found by the IRT, and some involved violations |
|
| |
|
| his e-pT tte-rmnn iniated,-s-everaltudiv-tduals-
| | of technical specifications and some involved licensed operators. |
| -resigned, and several other individuals
| |
|
| |
|
| were suspended. | | In response to the findings at Seabrook, random checks were conducted at the |
|
| |
|
| On January 28, 1992, two Instrumentation
| | Haddam Neck Plant and Millstone Nuclear Power Station. To date, no dis- crepancies have been identified at Haddam Neck. At Millstone, the Northeast |
|
| |
|
| and Control technicians
| | Nuclear Energy Company (the licensee) determined that several non-licensed |
|
| |
|
| at the Vogtle Electric Generating
| | plant equipment operators (PEOs) had not completed certain inspection rounds |
|
| |
|
| Plant, Unit 1, performed
| | as represented in their logs. The Millstone licensee has since expanded its |
|
| |
|
| a surveillance
| | evaluation to verifying the accuracy of log entries recorded by all PEOs. |
|
| |
|
| on a portion of the reactor trip system instrumentation.
| | The management at Millstone informed plant personnel of its findings and |
|
| |
|
| The Georgia Power Company (the licensee) | | expectations for recording log entries. The Millstone licensee also |
| informed the NRC that the technicians
| |
|
| |
|
| failed to properly follow the surveillance
| | established an IRT (with a representative from the Seabrook IRT acting in |
|
| |
|
| procedure
| | an advisory status) to investigate its findings, to determine the extent of |
|
| |
|
| and subsequently | | the problem, and to determine corrective actions that should be taken. |
|
| |
|
| created the data that was entered on the calibration
| | At Oyster Creek, several non-licensed PEOs were involved with falsification of |
|
| |
|
| data sheet.NRC evaluation
| | records associated with routine plant log taking rounds. None of the records |
|
| |
|
| of each of these matters is continuing. | | involved were related to technical specifications. The discovery of the |
|
| |
|
| Discussion
| | falsified log entries was from an ongoing random investigation comparing |
|
| |
|
| of Safety Significance
| | security door entry records with operator rounds. |
|
| |
|
| Maintenance
| | As a result of discrepancies found at Seabrook, Oyster Creek, and Millstone, at least one indivie-a-yn his e-pT tte-rmnn |
|
| |
|
| of shift records, log sheets, and surveillance
| | iniated,-s-everaltudiv-tduals- - |
| | resigned, and several other individuals were suspended. |
|
| |
|
| records, attention to detail, and work ethics are important
| | On January 28, 1992, two Instrumentation and Control technicians at the Vogtle |
|
| |
|
| factors which contribute
| | Electric Generating Plant, Unit 1, performed a surveillance on a portion of |
|
| |
|
| to the safe operation
| | the reactor trip system instrumentation. The Georgia Power Company (the |
|
| |
|
| of nuclear power plants. Complacency, by mechanics, technicians, or licensed or non-licensed
| | licensee) informed the NRC that the technicians failed to properly follow the |
|
| |
|
| operators, cannot be tolerated.
| | surveillance procedure and subsequently created the data that was entered on |
|
| |
|
| Similarly, manage-ment expectations
| | the calibration data sheet. |
|
| |
|
| and supervisory
| | NRC evaluation of each of these matters is continuing. |
|
| |
|
| overview of rounds need to be clearly communicated
| | ===Discussion of Safety Significance=== |
| | Maintenance of shift records, log sheets, and surveillance records, attention |
|
| |
|
| and monitored. | | to detail, and work ethics are important factors which contribute to the safe |
|
| |
|
| All personnel
| | operation of nuclear power plants. Complacency, by mechanics, technicians, or |
|
| |
|
| involved in NRC-regulated
| | licensed or non-licensed operators, cannot be tolerated. Similarly, manage- ment expectations and supervisory overview of rounds need to be clearly |
|
| |
|
| activities | | communicated and monitored. All personnel involved in NRC-regulated activities |
|
| |
|
| are responsible | | are responsible for complying with applicable NRC regulatory requirements and |
|
| |
|
| for complying
| | other Federal laws. Log keeping activities as well as surveillances |
|
| |
|
| with applicable
| | performed by licensed or non-licensed personnel are subject to the |
|
| |
|
| NRC regulatory
| | requirements of 10 CFR 50.9(a) regarding completeness and accuracy of information. |
|
| |
|
| requirements
| | IN 92-30 |
| | April 23, 1992 In addition, the administrative section of plant technical specifications |
|
| |
|
| and other Federal laws. Log keeping activities
| | requires that written procedures be implemented covering the applicable proce- dures in Appendix A of Regulatory Guide 1.33, Quality Assurance Program |
|
| |
|
| as well as surveillances
| | Requirements (Operation). Among the safety-related activities which Appendix A |
|
| |
|
| performed
| | states should be covered by written procedures are surveillances and log |
|
| |
|
| by licensed or non-licensed
| | entries. |
|
| |
|
| personnel | | Willful violations, committed by personnel at any level of a licensee's |
|
| |
|
| are subject to the requirements | | organization, are of regulatory concern because the NRC must have reasonable |
|
| |
|
| of 10 CFR 50.9(a) regarding
| | assurance that licensed activities will be conducted in a manner that will |
|
| |
|
| completeness
| | protect the public health and safety. Such reasonable assurance is provided |
|
| |
|
| and accuracy of information. | | in large part by the integrity and conscientiousness of each individual |
|
| |
|
| IN 92-30 April 23, 1992 In addition, the administrative
| | performing licensed activities. Deliberate violations concerning matters |
|
| |
|
| section of plant technical
| | within the scope of an individual's responsibilities, including falsification |
|
| |
|
| specifications
| | of records, will be considered for enforcement action against the individual |
|
| |
|
| requires that written procedures
| | as well as the facility licensee. As provided in 10 CFR 50.5, "Deliberate |
|
| |
|
| be implemented
| | Misconduct by Unlicensed Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement action against unlicensed personnel who |
|
| |
|
| covering the applicable
| | deliberately cause a licensee to be in violation of the Commission's regulations |
|
| |
|
| proce-dures in Appendix A of Regulatory
| | or who provide false information to the licensee concerning licensed activities. |
| | |
| 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 | | may wish to take actions as appropriate to ensure that plant |
|
| |
|
| to ensure that plant personnel
| | personnel are properly performing their assigned duties. |
| | |
| are properly performing | |
| | |
| their assigned duties. | |
|
| |
|
| ==Addressees== | | ==Addressees== |
| may also wish to distribute | | may also |
|
| |
|
| copies of this information | | wish to distribute copies of this information notice to all their employees. |
|
| |
|
| notice to all their employees. | | This information notice requires no specific action or written response. If |
|
| |
|
| This information
| | you have any questions about the information in this notice, please contact |
|
| |
|
| notice requires no specific action or written response.
| | one of the technical contact(s) listed below or the appropriate Office of |
|
| |
|
| If you have any questions
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| about the information
| | Charles E. Rossi, Director |
|
| |
|
| in this notice, please contact one of the technical
| | Division of Operational Events Assessment |
|
| |
|
| 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 | | Office of Nuclear Reactor Regulation |
|
| |
|
| Technical | | Technical contact(s): David C. Fischer, NRR |
| | |
| 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
| | (301) 504-1154 Eugene M. Kelly, RI |
|
| |
|
| A.C. Relays Used in Safety-Related | | (215) 337-5183 James A. Prell, RI |
|
| |
|
| 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
| | (215) 337-5108 Attachment: List of gecently I sued NRC Information Notices |
|
| |
|
| Weakness in 03/31/92 All holders of OLs or CPs Licensee Procedures
| | e |
|
| |
|
| for A for nuclear power reactor Loss of the Refueling Cavity Water 92-24 Distributor
| | m mC |
|
| |
|
| Modification
| | z |
|
| |
|
| to 03/30/92 All holders of OLs or CPs Certain Commercial-Grade
| | ,- |
| | Attachment |
|
| |
|
| for nuclear power reactors.Agastat Electrical
| | 0190 IN 92-30 |
| | C,0 |
| | ID April 23, 1992 Page I of 1 LIST OF RECENTLY ISSUED |
|
| |
|
| Relays 92-23 Results of Validation
| | rnZ NRC INFORMATION NOTICES |
|
| |
|
| Test- 03/27/92 All holders of OLs or CPs ing of Motor-Operated
| | cn |
|
| |
|
| Valve for nuclear power reactors Diagnostic
| | CD |
|
| |
|
| Equipment
| | 0 FQ) |
| | m C "3 I |
|
| |
|
| and all vendors of motor-operated valve (MOV) diag-nostic equipment.
| | Information Date of |
|
| |
|
| OL -Operating
| | 0> I Notice No. Subject Issuance Issued to |
|
| |
|
| License CP
| | 0 I |
|
| |
|
| * Construction
| | an I 04/22/92 All holders of OLs or CPs |
|
| |
|
| Permit
| | 92-21, Spent Fuel Pool Re- I Supp. 1 activity Calculations for-nuclear power reactors. |
|
| |
|
| IN 92-30 April 23, 1992 In addition, the administrative
| | 92-29 Potential Breaker Mis- 04/17/92 All holders of OLs or CPs |
|
| |
|
| section of plant technical
| | coordination Caused by for nuclear power reactors. |
|
| |
|
| specifications
| | Instantaneous Trip |
|
| |
|
| requires that written procedures
| | Circuitry |
|
| |
|
| be implemented
| | 92-28 Inadequate Fire Suppres- 04/08/92 All holders of OLs or CPs |
|
| |
|
| covering the applicable
| | sion System Testing for nuclear power reactors. |
|
| |
|
| proce-dures in Appendix A of Regulatory
| | 92-27 Thermally Induced Acceler- 04/03/92 All holders of OLs or CPs |
|
| |
|
| Guide 1.33, Quality Assurance
| | ated Aging and Failure of for nuclear power reactors. |
|
| |
|
| Program Requirements (Operation).
| | *oi ITE/GOULD A.C. Relays Used |
|
| |
|
| Among the safety-related
| | in Safety-Related Applic- ations |
|
| |
|
| activities
| | 0G)C) 92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPs |
|
| |
|
| which Appendix A states should be covered by written procedures
| | Operated Flexible Wedge for nuclear power reactors. |
|
| |
|
| are surveillances
| | 2 z0 Gate Valves |
|
| |
|
| and log entries.Willful violations, committed
| | 92-25 Potential Weakness in 03/31/92 All holders of OLs or CPs |
|
| |
|
| by personnel
| | Licensee Procedures for A for nuclear power reactor |
|
| |
|
| at any level of a licensee's
| | Loss of the Refueling |
|
| |
|
| organization, are of regulatory
| | Cavity Water |
|
| |
|
| concern because the NRC must have reasonable
| | 92-24 Distributor Modification to 03/30/92 All holders of OLs or CPs |
|
| |
|
| assurance
| | Certain Commercial-Grade for nuclear power reactors. |
|
| |
|
| that licensed activities
| | Agastat Electrical Relays |
|
| |
|
| will be conducted
| | 92-23 Results of Validation Test- 03/27/92 All holders of OLs or CPs |
|
| |
|
| in a manner that will protect the public health and safety. Such reasonable
| | ing of Motor-Operated Valve for nuclear power reactors |
|
| |
|
| assurance
| | Diagnostic Equipment and all vendors of motor- operated valve (MOV) diag- nostic equipment. |
|
| |
|
| is provided in large part by the integrity
| | 0 nU) |
| | =i CJ > 0 |
| | 'ii >~ |
| | sO = a rU) OL - Operating License |
|
| |
|
| and conscientiousness
| | sm CP |
|
| |
|
| of each individual
| | * Construction Permit |
|
| |
|
| performing
| | G) |
|
| |
|
| licensed activities.
| | IN 92-30 |
| | April 23, 1992 In addition, the administrative section of plant technical specifications |
|
| |
|
| Deliberate
| | requires that written procedures be implemented covering the applicable proce- dures in Appendix A of Regulatory Guide 1.33, Quality Assurance Program |
|
| |
|
| violations
| | Requirements (Operation). Among the safety-related activities which Appendix A |
|
| |
|
| concerning
| | states should be covered by written procedures are surveillances and log |
|
| |
|
| matters within the scope of an individual's
| | entries. |
|
| |
|
| responsibilities, including
| | Willful violations, committed by personnel at any level of a licensee's |
|
| |
|
| falsification
| | organization, are of regulatory concern because the NRC must have reasonable |
|
| |
|
| of records, will be considered
| | assurance that licensed activities will be conducted in a manner that will |
|
| |
|
| for enforcement
| | protect the public health and safety. Such reasonable assurance is provided |
|
| |
|
| action against the individual
| | in large part by the integrity and conscientiousness of each individual |
|
| |
|
| as well as the facility licensee.
| | performing licensed activities. Deliberate violations concerning matters |
|
| |
|
| As provided in 10 CFR 50.5, "Deliberate
| | within the scope of an individual's responsibilities, including falsification |
|
| |
|
| Misconduct
| | of records, will be considered for enforcement action against the individual |
|
| |
|
| by Unlicensed
| | as well as the facility licensee. As provided in 10 CFR 50.5, "Deliberate |
|
| |
|
| Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement | | Misconduct by Unlicensed Persons," 56 Federal Register 40684, August 15, 1991, the NRC may take direct enforcement action against unlicensed personnel who |
|
| |
|
| action against unlicensed
| | deliberately cause a licensee to be in violation of the Commission's regulations |
|
| |
|
| personnel
| | or who provide false information to the licensee concerning licensed activities. |
| | |
| 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 | | may wish to take actions as appropriate to ensure that plant |
| | |
| to ensure that plant personnel | |
| | |
| are properly performing
| |
|
| |
|
| their assigned duties. | | personnel are properly performing their assigned duties. |
|
| |
|
| ==Addressees== | | ==Addressees== |
| may also wish to distribute | | may also |
|
| |
|
| copies of this information | | wish to distribute copies of this information notice to all their employees. |
|
| |
|
| notice to all their employees. | | This information notice requires no specific action or written response. If |
|
| |
|
| This information
| | you have any questions about the information in this notice, please contact |
|
| |
|
| notice requires no specific action or written response.
| | one of the technical contact(s) listed below or the appropriate Office of |
|
| |
|
| If you have any questions
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| about the information
| | Charles E. Rossi, Director |
|
| |
|
| in this notice, please contact one of the technical
| | Division of Operational Events Assessment |
|
| |
|
| contact(s)
| | Office of Nuclear Reactor Regulation |
| listed below or the appropriate
| |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
| | Technical contact(s): David C. Fischer, NRR |
|
| |
|
| ===Events Assessment===
| | (301) 504-1154 Eugene M. Kelly, RI |
| Office of Nuclear Reactor Regulation
| |
|
| |
|
| Technical
| | (215) 337-5183 James A. Prell, RI |
|
| |
|
| contact(s):
| | (215) 337-5108 Attachment: List of Recently Issued NRC Information Notices |
| 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
| | Document Name: IN/GUNDECK LOG |
|
| |
|
| LOG CONCURRENCES
| | CONCURRENCES --- SEE NEXT PAGE |
| | |
| --- SEE NEXT PAGE | |
|
| |
|
| *SEE PREVIOUS CONCURRENCE | | *SEE PREVIOUS CONCURRENCE |
|
| |
|
| OEAB:DOEA:NRR | | OEAB:DOEA:NRR ADM:RPB C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR |
|
| |
|
| DCFischer* | | DCFischer* JMain* AEChaffee* RMGallo* |
| 04/07/92 ADM:RPB JMain*04/08/92 C:OEAB:DOEA:NRR | | 04/07/92 04/08/92 04/07/92 04/08/92 C:LHFB:DLPQ:NRR RI D:DRP:RII D: OE |
|
| |
|
| AEChaffee*
| | JSWenmiel* LBettenhausen* LAReyes* JLieberman* |
| 04/07/92 C:LOLB:DLPQ:NRR | | 04/09/92 04/14/92 04/15/92 04/15/92 C:OGCB:DOEA:NRR D:D : |
| | CHBerlinger* CE |
|
| |
|
| RMGallo*04/08/92 C:LHFB:DLPQ:NRR
| | 04/15/92 04/ 9v |
| | |
| 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 | |
|
| |
|
| *SEE PREVIOUS CONCURRENCE | | *SEE PREVIOUS CONCURRENCE |
|
| |
|
| OEAB:DOEA:NRR | | OEAB:DOEA:NRR ADM:RPB C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR |
|
| |
|
| DCFischer* | | DCFischer* JMa in* AEChaffee* RMGallo* |
| 04/07/92 C:LHFB:DLPQ:NRR | | 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* | | JSWermiel* LBettenhausen LAReyes i rman |
| 04/09/92 C:OGC CHBerjinger
| |
|
| |
|
| 04/15 /92 ADM:RPB JMa i n*04/08/92 RI ter st'LBettenhausen | | 04/09/92 04/14/92 04/15/92 04 /92 C:OGC D:DOEA:NRR |
|
| |
|
| 04/14/92 C:OEAB:DOEA:NRR | | ===CHBerjinger CERossi ,3=== |
| | 04/15 /92 04/ /92- |
|
| |
|
| C:LOLB:DLPQ:NRR
| | IN 92-XX |
|
| |
|
| AEChaffee*
| | April xx, 1992 This information notice requires no specific action or Written response. If |
| RMGallo*04/07/92 04/08/92 D:DRP:RII
| |
|
| |
|
| ';*" M. I.LAReyes i rman 04/15/92 04 /92 D:DOEA:NRR
| | you have any questions about the information in this nptice, please contact |
|
| |
|
| CERossi ,3 04/ /92- IN 92-XX April xx, 1992 This information
| | one of the technical contact(s) listed below or the propriate Office of |
|
| |
|
| notice requires no specific action or Written response.
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| If you have any questions
| | Charles E. ossi, Director |
|
| |
|
| about the information
| | Division f Operational Events Assessment |
|
| |
|
| 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 | | Office o Nuclear Reactor Regulation |
|
| |
|
| Technical | | Technical contact(s): Davi C. Fischer, RR |
|
| |
|
| contact(s):
| | (301) 4-1154 Eugene M. 1 , RI |
| 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 | | (215) 337-51 Attachment: List of Recently Issue NR Information Notices |
|
| |
|
| OG*SEE PREVIOUS CONCURRENCY | | Document Name: IN/GUNDECK OG |
|
| |
|
| p i\OEAB:DOEA:NRR | | *SEE PREVIOUS CONCURRENCY p i\ |
| | OEAB:DOEA:NRR ADM:RPB X C:OEAB:DOEA:NRR C:LOLB:DLPQ:NRR |
|
| |
|
| ADM:RPB X C:OEAB:DOEA:NRR
| | DCFischer* JMain AEChaffee* MGallo |
|
| |
|
| C:LOLB:DLPQ:NRR
| | 04/07/92) ¢p 04/.3/92 04/07/92 0 \ /92 |
| | * CA |
|
| |
|
| DCFischer*
| | CILHFB:DLPQ:NRR DRP:RI C:OGCB:DOEA:NRR D:D A:NRR |
| 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
| | JSWermiel EMKell CHBerlinger CERos |
|
| |
|
| D:D A:NRR JSWermiel
| | 04/ '/92 04/ / 2 04/ /92 04/ /92 |
|
| |
|
| EMKell CHBerlinger
| | Document Name: IN/GUNDECK LOG |
|
| |
|
| CERos 04/ '/92 04/ / 2 04/ /92 04/ /92 Document Name: OEAB:DOEA:NRR
| | OEAB:DOEA:NRR NRR C:LOLB:DLPQ:NRR |
|
| |
|
| DCFischer 04/7 /92 C:LHFB:DLPQ:NRR | | DCFischer RMGallo |
|
| |
|
| JSWermiel 04/ /92 IN/GUNDECK
| | 04/7 /92 04/ /' 04/ /92 C:LHFB:DLPQ:NRR :DOEA:NRR |
|
| |
|
| LOG NRR C:LOLB:DLPQ:NRR
| | ===JSWermiel .Rossi=== |
| | 04/ /92 04/ 4/ /92 |
|
| |
|
| RMGallo 04/ /92 04/ /':DOEA:NRR.Rossi 4/ /92 04/
| | IN 92-XX |
| IN 92-XX April xx, 1992 This information | |
|
| |
|
| notice requires no specific action or written response. | | April xx, 1992 This information notice requires no specific action or written response. If |
|
| |
|
| If you have any questions
| | you have any questions about the information in this notice, please contact one |
|
| |
|
| about the information
| | of the technical contact(s) listed below or th appropriate Office of Nuclear |
|
| |
|
| in this notice, please contact one of the technical
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| contact(s)
| | Charl E. Rossi, Director |
| listed below or th appropriate
| |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Charl E. Rossi, Director Divis on of Operational
| | Divis on of Operational Events Assessment |
|
| |
|
| ===Events Assessment===
| |
| Offi e of Nuclear Reactor Regulation | | Offi e of Nuclear Reactor Regulation |
|
| |
|
| Technical | | Technical contact(s): D id C. Fisch , NRR |
| | |
| 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
| | (301 504-1154 Eugene Kel y, RI |
|
| |
|
| RMGallo 04/ /92 04/8 /9'2 04/ /92 04/ /92 C:LHFB:DLPQ:NRR
| | (215) 337 1 3 Attachment: List of Recently Iss e RC Information Notices |
|
| |
|
| C:OGCB:DOE
| | Document Name: IN/GUNDECK LOG |
|
| |
|
| :NRR D/DOEA:NRR | | OEAB:DOEA:NRR ADM:RPB C:OEAB:DO :NRR C:LOLB:DLPQ:NRR |
|
| |
|
| JSWermiel
| | DCFischer JMain Q AEChaffee RMGallo |
|
| |
|
| CBerlingej
| | 04/ /92 04/8 /9'2 04/ /92 04/ /92 C:LHFB:DLPQ:NRR C:OGCB:DOE :NRR D/DOEA:NRR |
|
| |
|
| CERossi 04/ /92 04/ /92 / 04/ /92 I}} | | ===JSWermiel CBerlingej CERossi=== |
| | 04/ /92 04/ /92 / 04/ /92 I}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Falsification of Plant RecordsML031200393 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
04/23/1992 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
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
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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 - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. 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
|
---|
|
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)
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