ML062220633
| ML062220633 | |
| Person / Time | |
|---|---|
| Issue date: | 09/01/2006 |
| From: | NRC/NRR/ADRA/DNRL/NGDB |
| To: | |
| Oesterle, E,ADRA/DNRL/NRBA, 301-415-1365 | |
| Shared Package | |
| ML061800499 | List: |
| References | |
| DG-1145 | |
| Download: ML062220633 (25) | |
Text
C.IV.8 Generic Issues The requirements of proposed 10 CFR 52.79(a)(20) specify that the contents of a combined license (COL) application must include the proposed technical resolutions of those unresolved safety issues (USIs) and medium-and high-priority generic safety issues (GSIs) that are identified in the version of NUREG-0933 current on the date 6 months before the docket date of the application and that are technically relevant to the design. Applicants for design certification have a similar requirement in proposed 10 CFR 52.47(a)(18) for addressing USIs and GSIs. This requirement specifies that an applicant for design certification must provide the information necessary to demonstrate technical resolution of those USIs and medium-and high-priority GSIs identified in the NUREG-0933 version that is current on the date 6 months before the docket date of the application. In addition, the USIs and GSIs must be technically relevant to the standard plant design.
Since the inception of the generic issues program in 1976, the NRC has identified and categorized reactor safety issues. These safety issues were grouped into TMI Action Plan Items, Task Action Plan Items, New Generic Items, Human Factors Issues, and Chernobyl Issues and are collectively called Generic Safety Issues (GSIs). A listing of generic issues that are applicable to future reactor plants is provided Appendix B to NUREG-0933. Applicants for design certification and combined licenses should refer to this appendix for the list of generic issues that need to be addressed in their applications. In addition, applicants should address those generic issues for which there is either no entry or TBD in the Future Plants Effective Date column.
At the time DG-1145 was developed, the benchmark for Appendix B was Supplement 29 to NUREG-0933. Applicants for design certification and combined licenses should review the version of NUREG-0933 and its supplements in effect 6 months prior to the docket date of the application for the generic issues that should be addressed for their specific application. NUREG-0933 and its Supplements may be accessed through the NRCs web page (www.nrc.gov).
C.IV.8.2 Operational Experience (Generic Letters and Bulletins)
The requirements of proposed 10 CFR 52.79(a)(37) specify that the contents of COL application must include information which demonstrates how operating experience insights from generic letters and bulletins issued up to 6 months before the docket date of the application, or comparable international operating experience, has been incorporated into the plant design. Applicants for design certification have a similar requirement in proposed 10 CFR 52.47(a)(19).
The staff has reviewed the generic letters and bulletins dating back to 1980 and made a preliminary assessment of each document to determine whether it needs to be addressed by COL applicants and/or design certification applicants. The attached table provides the results of the staffs preliminary review. This review will be finalized for the final issuance of this guide. The screening criteria used by the staff for this review is provided as follows:
DG-1145, Page C.IV.8-1
Screening Criteria:
Exclusion Code Interpretation N
N/A to commercial nuclear power plants P
Procurement issue A
Administrative issue M
Maintenance/Installation/Surveillance issue PR Procedural/Verification S
Superceded X
Not applicable DG-1145, Page C.IV.8-2
Generic Letter Title Exclusion Code Notes80-001 NUREG-0630, "Cladding, Swelling and Rupture Models..."80-002 Quality Assurance Requirements Regarding DG Fuel Oil A
80-003 BWR Control Rod Failures BWR only 80-004 IEB 80-01 Operability of ADS Valve Pneumatic Supply see BL 80-01 80-005 IEB 79-01B Environmental Qualification of Class 1E Equipment 80-006 Issuance of NUREG-0313, Rev 1, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure BWR only 80-007 Information Regarding the Program for Environmental Qualification of Safety-Related Electrical Equipment (Not Issued)
X Not issued 80-008 IEB 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment A
BWR only 80-009 Low Level Radioactive Waste Disposal 80-010 Issuance of NUREG-0588, "Interim Staff Position on Equipment Qualifications of Safety-Related Electrical Equipment 80-011 IEB 80-03 Loss of Charcoal from Standard Type II, 2 Inch, Tray Absorber Cells P
See BL 80-03 80-012 IEB 80-04 Analysis of A PWR Main Steam Line Break With Continued Feedwater Addition See BL 80-04 80-013 Qualification of Safety-Related Equipment Note 6 80-014 LWR Primary Coolant System Pressure Isolation Valves USI B-63 80-015 Request for Additional Management and Technical Resources Information A
80-016 IEB 79-01b, Environmental Qualification of Class 1E Equipment X
Note 3 (A-24)80-017 Modifications to Boiling Water Reactor Control Rod Drive Systems BWR only 80-018 Crystal River 3 Reactor Trip from Approximately 100% Full Power B&W facilities only 80-019 Resolution of Enhanced Fission Gas Release Concerns80-020 Actions Req. from OL Applicants of NSSS Designs By W and CE Resulting from NRC B&O Task force Review of TMI-2 Accident 80-021 IEB 80-05 Vacuum Condition Resulting in Damage to CVCS Holdup Tanks See BL 80-05 80-022 Transmittal of NUREG-0654 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Prepared A
80-023 Change of Submittal Date for Evaluation Time Estimates A
80-024 Transmittal of Information on NRC "Nuclear Data Link Specifications" A
80-025 IEB 80-06, Engineering Safety Features Reset Controls See BL 80-06; Note 2 80-026 Qualifications of Reactor Operators80-027 IEB 80-07 BWR Jet Pump Assembly Failure BWR only DG-1145, Page C.IV.8-3
Generic Letter Title Exclusion Code Notes80-028 IEB 80-08 Examination of Containment Liner Penetration Welds M
See BL 80-08; AP1000 has no containment liner 80-029 Modifications to Boiling Water Reactor Control Rod Drive Systems BWR only 80-030 Clarification of the Term "Operable" as it applies to Single-Failure Criterion for Safety Systems Required by the TSs Note 5 80-031 IEB 80-09 Hydramotor Actuator Deficiencies P
See BL 80-09 80-032 Information Request on Category I Masonry Walls Employed By Plants Under CP and OL Review 80-033 Actions Req. from OL Applicants of B&W Designed NSSS Resulting from NRC B&O Task force Review of TMI-2 Accident X
B&W facilities only 80-034 Clarification of NRC Requirements for Emergency REsponse Facilities X
Note 3 (A-24)80-035 Effect of a DC Power Supply Failure on ECCS Performance 80-036 IEB 80-10 Contamination of Non-Rad. System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment A, M See BL 80-10 80-037 Five Additional TMI-2 Related Requirements to Operating Reactors80-038 Summary of Certain Non-Power Reactor Physical Protection Requirements N
80-039 IEB 80-11 Masonry Wall Design See BL 80-11 80-040 Transmit NUREG-0654, Report of the B&O Task force; and Appropriate NUREG-0626, Generic Eval. of FW Transient and SBLOCA GE facilities only 80-041 Summary of Meetings Held on April 22 &23, 1980 With Representatives of the Mark I Owners Group A
Mark I containment facilities only 80-042 IEB 80-12, Decay Heat Removal System Operability See BL 80-12; Note 2 80-043 IEB 80-13 Cracking in Core Spray Spargers BWR only 80-044 Reorganization of Functions and Assignments Within ONRR/SSPB N
80-045 Fire Protection Rule Notes 6 and 7 80-046 Generic Technical Activity A-12 Fracture toughness USI A-12 80-047 Additional Guidance on "Potential for Low Fracture toughness and Lamellar Tearing on PWR SG and Reactor Coolant Pump Supports" USI A-12 80-048 Revision to May 19, 1980, Letter on Fire Protection (80-045)
See GL 80-45; Note 7 80-049 Nuclear Safeguards Problems A
80-050 Generic Activity A-10 BWR Cracks (USI A-10)
BWR only 80-051 On-Site Storage of Low-Level Waste A
80-052 Five Additional TMI-2 Related Requirements - Errata Sheets to 5/7/80 Letter A
DG-1145, Page C.IV.8-4
Generic Letter Title Exclusion Code Notes80-053 Decay Heat Removal Capability 80-054 IEB 80-14 Degradation of Scram Discharge Volume Capability BWR only 80-055 IEB 80-15 Possible Loss of Hotline With Loss of off-Site Power A
Cover letter for BL 80-15 80-056 Commission Memo and Order on Equipment Qualification X
Note 4 80-057 Further Commission Guidance for Power Reactor Operating Licenses NUREG-0660 and NUREG-0694 80-058 IEB 80-16 Potential Misapplication of Rosemount Inc. Models 1151/1152 Pressure Transmitters With "A" Or "D" Output Codes P; M See BL 80-16 80-059 Transmittal of Federal Register Notice RE Regional Meetings to Discuss Environmental Qualification of Elec. Equipment N
80-060 Request for Information Regarding Evacuation Times A
80-061 TMI-2 Lessons Learned 80-062 TMI-2 Lessons Learned BWR only 80-063 IEB 80-17 Failure of Control Rods to Insert During A Scram at A BWR A
BWR only; cover letter for BL 80-17 80-064 Scram Discharge Volume Designs BWR only 80-065 Request for Estimated Construction Completion and Fuel Load Schedules A
80-066 IEB 80-17 Supplement 1 Failure of Control Rods to Insert During A Scram at A BWR BWR only; see BL 80-17 80-067 Scram Discharge Volume BWR only 80-068 IEB 80-17 Supplement 2 Failures Revealed By Testing Subsequent to Failure of Control Rods to Insert During A Scram at A A
BWR only; cover letter for BL 80-17 80-069 IEB 80-18 Maintenance of Adequate Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side HELB A
Cover letter for BL 80-18 80-070 IEB 80-19 Failures of Mercury-Wetted Matrix Relays in RPS of Operating Nuclear Power Plants Designed By GE A
Cover letter for BL 80-19 80-071 IEB 80-20 Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches A
Westinghouse only; cover letter for BL 80-20 80-072 Interim Criteria for Shift Staffing 80-073 Functional Criteria for Emergency Response Facilities, NUREG-0696 A
80-074 Notice of forthcoming Meeting With Representatives of EPRI to Discuss Program for Resolution of USI A-12, Fracture toughness A
DG-1145, Page C.IV.8-5
Generic Letter Title Exclusion Code Notes80-075 Lessons Learned Tech Specs A
80-076 Notice of forthcoming Meeting With GE to Discussed Proposed BWR Feedwater Nozzle Leakage Detection System A
BWR only; see A-10 80-077 Refueling Water Level 80-078 Mark I Containment Long-Term Program BWR Mark I containment only 80-079 IEB 80-17 Supplement 3 Failures Revealed By Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR BWR only 80-080 Preliminary Clarification of TMI Action Plan Requirements80-081 Preliminary Clarification of TMI Action Plan Requirements - Addendum to 9/5/80 Letter 80-082 IEB 90-01b, Supplement 2, EQ of Class 1E Equipment X
Note 3 (A-24)80-083 Environmental Qualification of Safety-Related Equipment 80-084 BWR Scram System BWR only 80-085 Implementation of Guidance from USI A-12, Potential for Low Fracture toughness and Lamellar Tearing on Component Supports USI A-12 80-086 Notice of Meeting to Discuss Final Resolution of USI A-12 A
80-087 Notice of Meeting to Discuss Status of EPRI-Proposed Resolution of the USI A-12 Fracture toughness Issue A
80-088 Seismic Qualification of AFW Systems80-089 IEB 79-01B Supplement 3 Environmental Qualification of Class 1E Equipment 80-090 Post TMI Requirements, NUREG-0737 80-091 ODYN Code Calculation BWR only 80-092 IEB 80-21 Valve Yokes Supplied By Malcolm Foundry Company, Inc.
P 80-093 Emergency Preparedness80-094 Emergency Plan A
80-095 Generic Activity A-10 BWR only 80-096 Fire Protection 80-097 IEB 80-23 Failures of Solenoid Valves Manufactured By Valcor Engineering Corporation A
Cover letter for BL 80-23 80-098 IEB 80-24, Prevention of Damage Due to Water Leakage Inside Containment A
Cover letter for BL 80-24; Note 2 80-099 TS Revision for Snubber Surveillance 80-100 Appendix R to 10 CFR Part 50 Regarding Fire Protection Note 6 80-101 Inservice Inspection Programs A
DG-1145, Page C.IV.8-6
Generic Letter Title Exclusion Code Notes80-102 Commission Memo and Order of May 23, 1980 (Referencing IEB 79-01b, Supp. 2)
X Note 3 (A-24)80-103 Fire Protection - Revised Federal Register Notice A
80-104 Orders on Environmental Qualification of Safety Related Electrical Equipment A
80-105 Implementation of Guidance for USI A-12, Potential for Low Fracture toughness and Lamellar Tearing on Component Supports USI A-12 80-106 Report on ECCS Cladding Models, NUREG-0630 A
Note 9 80-107 BWR Scram Discharge System BWR only 80-108 Emergency Planning A
80-109 Guidelines for SEP and Soil Structure Interaction Reviews80-110 Periodic Updating of FSARs A
80-111 IEB 80-17 Supplement 4, Failure of Control Rods to Insert During A Scram at a BWR A
Cover letter for BL 80-17; BWR only 80-112 IEB 80-25 Operating Problems With Target Rock Safety Relief Valves A
Cover letter for BL 80-25 80-113 Control of Heavy Loads USI A-36 81-001 Qualification of Inspection, Examination, Testing and Audit Personnel (Reg. Guide 1.58)
RG 1.58 was withdrawn 81-002 Analysis, Conclusions and Recommendations Concerning Operator Licensing A
81-003 Implementation of NUREG-0313, Rev. 1, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping BWR only 81-004 Emergency Procedures and Training for Station Blackout Events USI A-44 81-005 Information Regarding the Program for Environmental Qualification of Safety-Related Electrical Equipment USI A-24 81-006 Periodic Updating of Final Safety Analysis Reports (FSARs)
A 81-007 Control of Heavy Loads USI A-36 81-008 ODYN Code GE BWR only 81-009 BWR Scram Discharge System BWR only 81-010 Post-TMI Requirements for the Emergency Operations Facility A
81-011 BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619)
BWR only 81-012 Fire Protection Rule (45 FR 76602, 11/19/80)81-013 SER for GEXL Correlation for 8X8R Fuel Reload Applications for Appendix D Submittals of the GE Topical Report BWR only DG-1145, Page C.IV.8-7
Generic Letter Title Exclusion Code Notes81-014 Seismic Qualification of AFW Systems81-015 Environmental Qualification of Class 1E Electrical Equipment-Clarification of Staff's Handling of Proprietary Information A
81-016 NUREG-0737 Item I.C.1 SER on Abnormal Transient Operating Guidelines (ATOG)
B&W facilities only 81-017 Functional Criteria for Emergency Response Facilities X
Note 3 81-018 BWR Scram Discharge System-Clarification of Diverse Instrumentation Requirements BWR only 81-019 Thermal Shock to Reactor Pressure Vessels USI A-49 81-020 Safety Concerns Associated with Pipe Breaks in the BWR Scram System BWR only 81-021 Natural Circulation Cooldown A
81-022 Engineering Evaluation of the H.B. Robinson Reactor Coolant System Leak on 1/29/81 A
No action defined 81-023 INPO Plant Specific Evaluation Reports A
81-024 Multi-Plant Issue B-56 Control Rods Fail to Fully Insert BWR only 81-025 Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans A
81-026 Licensing Requirements for Pending Construction Permit and Manufacturing License Applications81-027 Privacy and Proprietary Material in Emergency Plans A
81-028 Steam Generator Overfill USI A-47; PWR only 81-029 Simulator Examinations A
81-030 Safety Concerns Associated With Pipe Breaks in the BWR Scram System BWR only 81-031 Small Break LOCA Confirmatory Integral Systems Experiments for B&W Designed Plants (Never issued)
X Not issued 81-032 NUREG-0737, Item II.K.3.44-Evaluation of Anticipated Transients Combined With Single Failure BWR only 81-033 Technical Specification for Station Batteries Multiplant Action (Never issued)
X Not issued 81-034 Safety Concerns Associated With Pipe Breaks in the BWR Scram System BWR only 81-035 Safety Concerns Associated With Pipe Breaks in the BWR Scram System BWR only 81-036 Revised Schedule for Completion of TMI Action Plan Item II.D.1, Relief and Safety Valve Testing A
81-037 ODYN Code Reanalysis Requirements BWR only 81-038 Storage of Low-Level Radioactive Wastes at Power Reactor Sites A
81-039 NRC Volume Reduction Policy 81-040 Qualifications of Reactor Operators A
DG-1145, Page C.IV.8-8
Generic Letter Title Exclusion Code Notes82-001 New Applications Survey A
82-002 Commission Policy on Overtime A
82-003 High Burnup MAPLHGR Limits GE BWR only 82-004 Use of INPO SEE-IN Program A
See TMI action plan item I.C.5 82-005 Post-TMI Requirements A
82-006 RTD Response Time Determination [never issued]
X Not issued 82-007 Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture A
BWR only 82-008 Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture A
Note 1 82-009 EQ of Safety-Related Electrical Equipment X
Note 3 (A-24)82-010 Post-TMI Requirements A
82-011 Transmittal of NUREG-0916 Relative to the Restart of R.E. Ginna Nuclear Power Plant A
82-012 Nuclear Power Plant Staff Working Hours A
82-013 Reactor Operator and Senior Reactor Operator Examinations A
82-014 Submittal of Documents to the NRC A
82-015 Nuclear Plant Staff Working Hours (Not issued)
X Not issued 82-016 NUREG-0737 Technical Specifications82-017 Inconsistency of Requirments Between 50.54(T) and 50.15 X
Note 4 82-018 Reactor Operator and Senior Reactor Operator Requalification Examinations A
82-019 Submittal of Copies of Documentation to NRC-Copy Requirements for Emergency Plans and Physical Security Plans N
82-020 Guidance for Implementation of the SRP X
Note 4 82-021 Technical Specifications for Fire Protection Audits82-022 Congressional Request for Information Concerning Steam Generator Tube Integrity USI A-3 82-023 Inconsistency Between Requirements of 10 CFR 73.40(D) and Standard TSs82-024 Safety Relief Valve Quencher Loads: BWR MARK II and III Containments BWR only 82-025 Integrated IAEA Exercise for Physical Inventory at LWRs A
82-026 NUREG-0744, Rev. 1 - Pressure Vessel Material Fracture Toughness USI A-11 82-027 Transmittal of NUREG-0763, Guidelines for Confirmatory In-Plant Tests of Safety-Relief Valve Discharges for BWR Plants, and NUREG-0783 BWR only 82-028 Inadequate Core Colling Instrumentation System X
Note 3 82-029 NUREG/CR-2980 X
Not issued 82-030 Filings Related to 10 CFR 50 Production and Utilization Facilities A
82-031 NUREG-0737 Technical Specifications X
Not issued DG-1145, Page C.IV.8-9
Generic Letter Title Exclusion Code Notes82-032 Draft Steam Generator Report [SAIC]
USI A-3 82-033 Supplement 1 to NUREG-0737-Emergency Response Capabilities X
Note 3 82-034 Secy 82-111 Modification of Vacuum Breakers & Mark I Containments X
Not issued 82-035 Never issued X
Not issued 82-036 Assignment of Authority to Regions for Nonpower Reactors Amendments and Licensing Activities (Not issued)
X Not issued 82-037 NUREG-0737 Tech Specs X
Not issued 82-038 Meeting to Discuss Developments for Operator Licensing Examinations A
82-039 Problems with Submittals of 10 CFR 73.21 Safeguards Info A
83-001 Operator Licensing Examination Site Visit A
83-002 NUREG-0737 Technical Specifications BWR only 83-003 Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Pre-Service and Inservice Examinations" (Not issued)
X Not issued 83-004 Regional Workshops Regarding Supplement 1 to NUREG-0737, Requirements for Emergency Response Capability A
83-005 Safety Evaluation of Emergency Procedure Guidelines, Revision 2, NEDO-24934, June 1982 BWR only 83-006 Certificates and Revised Format for Reactor Operator and Senior Reactor Operator Licenses A
83-007 The Nuclear Waste Policy Act of 1982 A
Note 6 83-008 Modification of Vacuum Breakers on Mark I Containments GE BWR only 83-009 Review of Combustion Engineering Owners' Group Emergency Procedures Guideline Program CE facilities only 83-010 Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps" CE facilities only 83-011 Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions83-012 Issuance of NRC Form 398 - Personal Qualifications Statement - Licensee A
83-013 Clarification of SRs for HEPA filters and Charcoal Adsorber Units in STS and ESF Cleanup Systems83-014 Definition of "Key Maintenance Personnel" (Clarification of GL 82-12)
A See GL 82-12 83-015 Implementation of RG 1.150 83-016 Transmittal of NUREG-0977 Relative to the ATWS Events at Salem Generating Station, Unit No. 1 (GL 83-028)
A See GL 83-28 DG-1145, Page C.IV.8-10
Generic Letter Title Exclusion Code Notes83-017 Integrity of Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses A
83-018 NRC Staff Review of the BWR Owners' Group (BWROG) Control Room Survey Program BWR only 83-019 New Procedures for Providing Public Notice Concerning Issuance of Amendments to Operating Licenses A
83-020 Integrated Scheduling for Implementation of Plant Modifications A
83-021 Clarification of Access Control Procedures for Law Enforcement Visits A
83-022 Safety Evaluation of "Emergency Response Guidelines" A
83-023 Safety Evaluation of "Emergency Procedure Guidelines" CE facilities only 83-024 TMI Task Action Plan Item I.G.1, "Special Low Power Testing and Training,"
Recommendations for BWRs BWR only; see TMI Action Plan Item I.G.1 83-025 Issuance of NRC form 398 Personal Qualifications Statement - Licensee (not issued)
X Not issued 83-026 Clarification of SRs for Diesel Fuel Impurity Level Tests RG 1.137 83-027 Surveillance Intervals in Standard TSs83-028 Required Actions Based on Generic Implications of Salem ATWS Event A, M Note 3 83-029 This Generic Communication was not issued X
Not issued 83-030 Deletion of STS SR 4.8.1.1.2.d.6 for DG testing RG 1.108 83-031 Safety Evaluation of "Abnormal Transient Operating Guidelines" B&W facilities only 83-032 NRC Staff Recommendations Regarding Operator Actions for Reactor Trip and ATWS A
83-033 NRC Positions of Certain Requirements of Appendix R 83-034 Important to Safety (not issued)
X Not issued 83-035 Clarification of TMI Action Plan Item II.K.3.31 83-036 NUREG-0737 Technical Specifications BWR only 83-037 NUREG-0737 Technical Specifications83-038 NUREG-0965, "NRC Inventory of Dams" A
83-039 Voluntary Survey of Licensed Operators A
83-040 Operator Licensing Examination A
83-041 Fast Cold Start of Diesel Generator 83-042 Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" USI A-36 83-043 Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications A
83-044 Availability of NUREG-1021, "Operator Licensing Examiner Standards" A
DG-1145, Page C.IV.8-11
Generic Letter Title Exclusion Code Notes84-001 NRC Use of the Terms "Important to Safety" and "Safety-Related" A
Note 4 84-002 Notice of Meeting Regarding Facility Staffing A
84-003 Availability of NUREG-0933, "A Prioritization of Generic Safety Issues" A
84-004 Safety Evaluation of W Topical Reports on Elimination of Postulated Pipe Breaks in PWRs Task Action Plan Item A-2 (USI A-2)84-005 Copy of change to NUREG-1021, "Operator Licensing Examiner Standards" A
84-006 Operator and Senior Operator License Examination Criteria for Passing Grade A
84-007 Procedural Guidance for Pipe Replacement at BWRs BWR only 84-008 Interim Procedures for NRC Management of Plant-Specific Backfitting A
84-009 Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii)
X Note 6 84-010 Administration of Operating Tests Prior to Initial Criticality 84-011 Inspections of BWR Stainless Steel Piping BWR only 84-012 Compliance with 10CFR Part 61 and Implementation of the RETS and Attendant PCP 84-013 TSs for Snubbers84-014 Replacement and Requalification Training Program A
84-015 Proposed Staff Actions to Improve and Maintain DG Reliability 84-016 Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants A
Note 7 84-017 Annual Meeting to Discuss Recent Developments Regarding Operator Training, Qualifications, and Examinations A
84-018 Filing of Applications for Licenses and Amendments A
84-019 Availability of Supplement 1 to NUREG-0933, "A Prioritization of Generic Safety Issues" A
84-020 Scheduling Guidance for Licensee Submittals of Reloads That Involve Unreviewed Safety Questions84-021 Long Term Low Power Operation in PWRs PWR only 84-022 10 CFR 20.408 Termination Reports (not issued)
X Not issued 84-023 Reactor Vessel Water Level Instrumentation in BWRs BWR only 84-024 Certificate of Compliance to 10CFR50.49, EQ of Electrical Equipment Important to Safety X
Note 8 85-001 Fire Protection Policy Steering Committee Report A
85-002 Staff Recommended Actions Regarding Steam Generator Tube Integrity USI A-3 DG-1145, Page C.IV.8-12
Generic Letter Title Exclusion Code Notes85-003 Clarification of Equivalent Control Capacity for Standby Liquid Control Systems BWR only 85-004 Operating Licensing Examinations A
85-005 Inadvertent Boron Dilution Event 85-006 Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related USI A-9 85-007 Implementation of Integrated Schedules for Plant Modifications A
85-008 10 CFR 20.408 Termination Reports - format A
85-009 Technical Specifications for Generic Letter 83-28, Item 4.3 85-010 Technical Specification for Generic Letter 83-28, Items 4.3 and 4.4 B&W facilities only 85-011 Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 USI A-36 85-012 Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps85-013 Transmittal of NUREG-1154 Regarding the David-Besse Loss of Main and Aux. Feedwater Event PR 85-014 Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated By the Utility 85-015 Information on Deadlines for 10 CFR 50.49, "EQ of Electric Equipment Important to Safety at NPPs" A
85-016 High Boron Concentrations85-017 Availability of Supplements 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues" A
85-018 Operator Licensing Examinations A
85-019 Reporting Requirements on Primary Coolant Iodine Spikes A
85-020 Resolution of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking in Babcock and Wilcox Plants B&W facilities only 85-021 Not Issued X
Not issued 85-022 Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage USI A-43 86-001 Safety Concerns Associated With Pipe Breaks in the BWR Scram System BWR only 86-002 Technical Resolution of Generic Issue B Thermal Hydraulic Stability BWR only 86-003 Applications for License Amendments A
86-004 Policy Statement on Engineering Expertise on Shift DG-1145, Page C.IV.8-13
Generic Letter Title Exclusion Code Notes86-005 Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" X
B&W facilities only; Note 3 (see TMI Action Item II.K.3.5)86-006 Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" X
CE facilities only; Note 3 (see TMI Action Item II.K.3.5)86-007 Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event USI A-1 86-008 Availability of Supplement 4 to NUREG-0933, A Prioritization of Generic Safety Issues" A
86-009 Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs86-010 Implementation of Fire Protection Requirements86-011 Distribution of Products Irradiated in Research Reactors N
86-012 Criteria for Unique Purpose Exemption from Conversion from the use of HEU Fuel N
86-013 Potential Inconsistency Between Plan Safety Analyses and TSs86-014 Operator Licensing Examinations A
86-015 Information relating to Compliance with 10CFR50.49 X
Note 8 86-016 Westinghouse ECCS Evaluation Models86-017 Availability of NUREG-1169, "Technical Findings Related to Generic Issue C-8, BWR Misc.
Leakage and Treatment Methods" BWR only; see Task Action Item C-8 87-001 Public Availability of the NRC Operator Licensing Examination Question Bank A
87-002 Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46)
USI A-46 87-003 Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46)
USI A-46 87-004 Temporary Exemption from Provisions of the FBI Criminal History Rule for Temporary Workers A
87-005 Request for Additional Info (RFI) on Assessment... Degradation of Mark I Drywells BWR only 87-006 Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves87-007 Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Confirming Amendments A
87-008 Implementation of 10 CFR 73.55 Miscellaneous Amendments and Search Requirements A
87-009 Section 3.0 and 4/0 of STS on LCOs and SRs DG-1145, Page C.IV.8-14
Generic Letter Title Exclusion Code Notes87-010 Implementation of 10 CFR 73.57, Requirements for FBI Criminal History Checks A
87-011 Relaxation in Arbitrary Intermediate Pipe Rupture Requirements87-012 Loss of Residual Heat Removal While the RCS is Partially Filled 87-013 Integrity of Requalification Examinations at Non-Power Reactors N
87-014 Operator Licensing Examinations A
87-015 Policy Statement on Deferred Plants X
Deferred facilities only 87-016 Transmittal of NUREG-1262, "Answers to Questions on Implementation of 10 CFR 55 on Operators' Licenses" A
88-001 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping BWR only 88-002 Integrated Safety Assessment Program II A
88-003 Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" GSI 93 88-004 Distribution of Gems Irradiated in Research Reactors N
88-005 Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWRs88-006 Removal of Organization Charts from Technical Specification Administrative Control Requirements A
88-007 Modified Enforcement Policy...10CFR50.49 X
Note 8 88-008 Mail Sent or Delivered to the office of Nuclear Reactor Regulation A
88-009 Pilot Testing of Fundamentals Examination A
BWR only 88-010 Purchase of GSA Approved Security Containers P
88-011 NRC Position on Radiation Embrittlement of RV Materials and its Impacts on Operations USI A-47; RG 1.99 88-012 Removal of Fire Protection Requirements for TSs A
88-013 Operator Licensing Examinations A
88-014 Instrument Air Supply System Problems Affecting Safety-Related Equipment 88-015 Electric Power Systems - Inadequate Control Over Design Process88-016 Removal of Cycle-Specific Parameter Limits from TSs A
88-017 Loss of Decay Heat Removal - 10 CFR 50.54(f) 88-018 Plant Record Storage on Optical Disks X
Note 4 88-019 Use of Deadly Force by Licensee Guards to Prevent Theft of Special Nuclear Material A; PR 88-020 Individual Plant Examination for Severe Addicent Vulnerabilities89-001 Implementation of Programmatic Control for RETS...
A DG-1145, Page C.IV.8-15
Generic Letter Title Exclusion Code Notes89-002 Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products P
89-003 Operator Licensing National Examination Schedule A
89-004 Guidance on Developing Acceptable IST Programs89-005 Pilot Testing of the Fundamentals Examination A
89-006 Task Action Plan Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54(f) 89-007 Power Reactors Safetguards Contingency Planning for Surface Vehicle Bombs A; PR 89-008 Erosion/Corrosion Induced Pipe Wall Thinning M
89-009 ASME Section III Component Replacements P
89-010 Safety-Related MOV Testing and Surveillance M
89-011 Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy" BWR only 89-012 Operator Licensing Examination A
89-013 Service Water System Problems Affecting Safety-Related Equipment 89-014 Line-Item Improvements in TSs...
A 89-015 Emergency Response Data System A
89-016 Installation of a Hardened Wetwell Vent BWR only 89-017 Planned Administrative Changes to the NRC Operator Licensing Written Examination Process A
89-018 Resolution of Unresolved Safety Issue A-17, Systems Interactions in Nuclear Power Plants USI A-47; USI A-17 89-019 Request for Action Related to Resolution of Unresolved Safety Issue A-47, Safety Implication of Control Systems in LWR Nuclear Power Plants, Pursuant to 10 CFR 50.54(f)
USI A-47, A-27 89-020 Protected Area Long-Term Housekeeping N
89-021 Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements A
89-022 Potential for Increased Roof Loads and Plant Area Flood Runoff Depth at Licensed Nuclear Power Plants Due to Recent Change in Probable Maximum Precipitation Criteria Developed By the National Weather Service 89-023 NRC Staff Responses to Questions Pertaining to Implementation of 10 CFR Part 26 A
90-001 Request for Voluntary Participation in NRC Regulatory Impact Survey A
90-002 Alternative Requirements for Fuel Assemblies in the Design Features of TSs90-003 Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 "Vendor Interface for Safety-Related Components" P
DG-1145, Page C.IV.8-16
Generic Letter Title Exclusion Code Notes90-004 Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs A
90-005 Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping M
90-006 Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional LTOP Protection for PWRs" USI A-26 90-007 Operator Licensing National Examination Schedule A
90-008 Simulation Facility Exemptions A
90-009 Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions91-001 Removal of the Schedule for the Withdrawal of RV Material Surveillance Specimens from the TSs A
91-002 Reporting Mishaps Involving LLW Forms Prepared for Disposal A
91-003 Reporting of Safeguards Events A
91-004 Changes in TS Surveillance Intervals to Accomodate a 24-month Fuel Cycle A
91-005 Licensee Commercial-Grade Procurement and Dedication Programs P
91-006 Resolution of Generic Issue A-30, Adequacy of Safety-Related DC Power Supplies, Pursuant to 10 CFR 50.54(f)
USI A-30 91-007 GI-23, RCP Seal Failure and Its Possible Effect on SBO USI 23 91-008 Removal of Component Lists from the TSs A
91-009 Modification of Surveillance Interval, Electrical Protection Assemblies in Power Supplies, RPS BWR only 91-010 Explosives Searches at Protected Area Portals N
91-011 Resolution of Generic Issues 48, LCOs for Class 1E Vital Instrument Buses, and 49, Interlocks and LCOs for Class 1E Tie Breakers Pursuant to 10 CFR 50.54(f)
USI 48 & 49 91-012 Operator Licensing National Examination Schedule A
91-013 Request for Info Related to the Resolution of GI 130, "Essential Service Water System Failures at Multi-Unit Sites" USI 130 91-014 Emergency Telecommunications A
91-015 Operating Experience Feedback Report, Solenoid-Operated Valve Problems P, M 91-016 Licensed Operators' and Other Nuclear Facility Personnel Fitness for Duty A
91-017 Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants P; M DG-1145, Page C.IV.8-17
Generic Letter Title Exclusion Code Notes91-018 Information... Regarding Two NRC... [IPs] on Resolution of Degraded and Nonconforming Conditions and on Operability A
91-019 Information to Addressees Regarding New Telephone Numbers for NRC offices Located in one White Flint North A
92-001 Reactor Vessel Structural Integrity 92-002 Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown" PR USI 79 92-003 Compilation of the Current Licensing Basis: Request for Voluntary Participation in Pilot Program A
92-004 Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f)
BWR only 92-005 NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program A
92-006 Operator Licensing National Examination Schedule A
92-007 Office of Nuclear Reactor Regulation Reorganization A
92-008 Thermo-Lag 330-1 Fire Barriers (BL-92-001)
P Note 2 92-009 Limited Participation By NRC in the IAEA International Nuclear Event Scale A
93-001 Emergency Response Data System Test Program A
93-002 NRC Public Workshop on Commercial Grade Procurement and Dedication A
93-003 Verification of Plant Records A
93-004 Rod Control System Failure and Withdrawal of RCCAs93-005 Line-Item TS Improvements to Reduce SRs for Testing During Power Ops A
93-006 Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" GSI 106 93-007 Modification of the TS Admin Control Requirements for Emergency and Security Plans A
93-008 Relocation of TS Tables of Instrument Response Time Tables A
94-001 Removal of Accelerated Testing and Special Reporting Requirements for Emergency DGs M
GSI B-56 94-002 Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs BWR only 94-003 Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs BWR only DG-1145, Page C.IV.8-18
Generic Letter Title Exclusion Code Notes94-004 Voluntary Reporting of Additional Occupational Radiation Exposure Data A
95-001 NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities N
95-002 Use of NUMARC/EPRI Report TR-102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements Under 10 CFR 50.59 A
95-003 Circumferential Cracking of SG Tubes USI A-3 95-004 Final Disposition of the Systematic Evaluation Program Lessons-Learned Issues A
95-005 Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking 95-006 Changes in the Operator Licensing Program A
95-007 Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves P
95-008 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval PR 95-009 Monitoring and Training of Shippers and Carriers of Radioactive Materials PR 95-010 Relocation of Selected TS Requirements Related to Instrumentation A
96-001 Testing of Safety-Related Logic Circuits96-002 Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat A
96-003 Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits A
96-004 Boraflex Degradation in Spent Fuel Pool Storage Racks P
96-005 Periodic Verification of Design-Basis Capability of Safety-Related MOVs96-006 Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions96-007 Interim Guidance on Transportation of Steam Generators PR PWR only 97-001 Degradation of CRDM Nozzle and Other VHPs See BL 2001-01 and 2002-02 97-002 Revised Contents of the Monthly Operating Report, May 15, 1997 A
97-003 Annual Financial Surety Update Requirements for Uranium Recovery Licensees, July 9, 1997 N
97-004 Assurance of Sufficient NPSH for ECCS and Containment Heat Removal Pumps97-005 SG Tube Inspection Techniques M; PR PWR only DG-1145, Page C.IV.8-19
Generic Letter Title Exclusion Code Notes97-006 Degradation of SG Internals PR PWR only 98-001 Year 2000 Readiness of Computer Systems at Nuclear Power Plants, Issued May 11, 1998.
A 98-002 Loss of Reactor Coolant Inventory and Associated Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition 98-003 NMSS Licensees' and Certificate Holders' Year 2000 Readiness Programs, 6/22/98 N
98-004 Potential for Degradation of the ECCS and CSS after a LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material 98-005 Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds, November 10, 1998 BWR only 99-001 Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities, 5/3/1999 [Materials]
N 99-002 Laboratory Testing of Nuclear-Grade Activated Charcoal PR 03-001 Control Room Habitability 04-001 Requirements for steam generator tube inspections PWR only 04-002 Potential impact of debris blockage on Emergency Recirculation during design basis accidents at PWRs PWR only 06-001 Steam generator tube integrity and associated technical specifications PWR only 06-002 Grid reliability and the impact on plant risk and the operability of offsite power 06-003 Potentially nonconforming Hemyc and MT fire barrier configurations 1
The issues involved in this GL were incorporated into Issues A-3 through A-5 2
The issues involved in this GL are covered in the review of the associated BL 3
The issues involved in this GL are covered in the review of a USI or GSI issue, for example a TMI Action Plan issue NOTES DG-1145, Page C.IV.8-20
Generic Letter Title Exclusion Code Notes 4
The GL is not involved with operational experience 5
Not used 6
The GL involved with requirements stated in the CFR or in an SRP Section 7
The GL concerns were addressed in another GL; therefore does not need to be reviewed again (e.g.,86-004) 8 The GL involved enforcement of 10CFR 50.49 (EQ) reg; therefore does not need to be reviewed 9
The GL does not involve requirements: therefore does not need to be reviewed DG-1145, Page C.IV.8-21
Bulletin Title Exclusion Code Notes 80-01 Operability of ADS Valve Pneumatic Supply BWR only 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment P
BWR only 80-03 Loss of Charcoal from Standard Type II, 2 Inch, Tray Adsorber Cells P
80-04 Analysis of a PWR Main Steam Line Break with Contiued FW Addition 80-05 Vacuum Condition Resulting in Damage to the CVCS Holdup Tanks 80-06 Engineered Safety Feature Reset Controls PR 80-07 BWR Jet Pump Assembly Failure BWR only 80-08 Examination of Containment Liner Penetration Welds 80-09 Hydramotor Actuator Deficiencies P
80-10 Contamination of Nonradioactive System and Resulting Potential for..
A; M 80-11 Masonry Wall Design 80-12 Decay Heat Removal System Operability 80-13 Cracking in Core Spray Spargers BWR only 80-14 Degradation of Scram Discharge Volume Capability BWR only 80-15 Possible Loss of Emergency Notification System with LOOP A
80-16 Potential Misapplication of Rosemount...Models 1151 and 1152 Pressure Transmitters with Either "A" or "D" Output Codes P; M 80-17 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR BWR only 80-18 Maintenance of Adequate Min Flow Centrifugal Charging Pump....
80-19 Failures of Mercury-Wetted Matrix Relays in Reactor Protective Systems of...Plants Designed by Combustion Engineering P
80-20 Failure of Westinghouse Type W-2 Spring Return to Neutral Control Switches P
80-21 Valve Yokes Supplied by Malcolm Foundry Company, Inc.
P 80-22 Automation Industries, Model 200-520-008 Sealed-Source Connectors N
80-23 Failures of Solenoid Valves Manufactured by Valcor Engineering Corporation P
80-24 Prevention of Damage Due to Water Leakage Inside Containment 80-25 Operating Problems with Target Rock Safety-Relief Valves at BWRs BWR only 81-01 Failure and Surveillance of Mechanical Snubbers 81-02 Failure of Gate Type Valves to Close Against Differential Pressure P; A; S 81-03 Flow Blockage of Cooling Water to Safety System Components...
M 82-01 Alteration of Radiographs of Welds in Piping Subassemblies A
82-02 Degradation of Threaded Fasteners in the RC Pressure Boundary of PWR Plants P; M 82-03 Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless Steel, Recirculation System Piping at BWR Plants BWR only 82-04 Deficiencies in Primary Containment Electrical Penetration Assemblies P
DG-1145, Page C.IV.8-22
Bulletin Title Exclusion Code Notes 83-01 Failure of Trip Breakers (Westinghouse DB-50) to Open on Automatic Trip Signal M
83-02 Stress Corrosion Cracking in Large-Diameter Stainless Steel Recirculation System Piping at BWR Plants BWR only 83-03 Check Valve Failures in Raw Water Cooling Systems of DGs 83-04 Failure of the Undervoltage Trip Function of Reactor Trip Breakers P
83-05 ASME Nuclear Code Pumps and Spare Parts Manufactured by the Hayward Tyler Pump Company P
83-06 Nonconforming Materials Supplied by Tube-Line Facilities at Long Island City, NY, Houston,TX, &
Carol Stream,IL P
83-07 Apparently Fraudulent Products Sold by Ray Miller, Inc.
P 83-08 Elect. Circuit Breakers With Undervoltage Trip...in Safety-Related Applications other than the Reactor Trip System M
84-01 Cracks in BWR Mark I Containment Vent Headers BWR only 84-02 Failure of GE Type HFA Relays In Use In Class 1E Safety Systems P
84-03 Refueling Water Cavity Water Seal 85-01 Steam Binding of Auxiliary Feedwater Pumps GSI 93 85-02 Undervoltage Trip Attachments of Westinghouse DB-50 Reactor Trip Bkrs.
P; M 85-03 MOV Common Mode Failures During Plant Transients...
A; M; P See GL 89-10 86-01 Min. Flow Logic Problems that Could Disable RHR Pumps 86-02 Static "O" Ring Differential Pressure Switches P
86-03 Potential Failure of Multiple ECCS Pumps Due to Single Failure...
86-04 Defective Teletherapy Timer That May Not Terminate Treatment Dose N
87-01 Thinning of Pipe Walls A; S 87-02 Fastener Testing to Determine Conformance w Applicable Material Specs.
P 88-01 Defects in Westinghouse Circuit Breakers P
88-02 Rapidly Propagating Fatigue Cracks in SG Tubes 88-03 Inadequate Latch Engagement in HFA Type Latching Relays Manufactured by General Electric (GE) Company P
88-04 Potential Safety-related Pump Loss 88-05 Nonconforming Materials Supplied by Piping Supplies, Inc.... and West Jersey Manufacturing Company...
P 88-06 Actions To Be Taken for the Transportation of Model No. SPEC 2-T Radiographic Exposure Device N
88-07 Power Oscillations in BWRs BWR only 88-08 Thermal Stress in Piping Connected to RCS DG-1145, Page C.IV.8-23
Bulletin Title Exclusion Code Notes 88-09 Thimble Tube Thinning in Westinghouse Reactors 88-10 Nonconforming Molded-Case Circuit Breakers P
88-11 Pressurizer Surge Line Thermal Stratification 89-01 Failure of Westinghouse SG Tube Mechanical Plugs P
PWR only 89-02 Stress Corrosion Cracking of High-Hardness Type 410.. Bolting.. Anchor Darling S350W.. Swing Check Valves.. Similar P
89-03 Potential Loss of Required Shutdown Margin During Refueling Ops PR 90-01 Loss of Fill-Oil in Transmitters Manufactured by Rosemount P
90-02 Loss of Thermal Margin Caused by Channel Box Bow BWR only 91-01 Reporting Loss of Criticality Safety Controls N
92-01 Failure of Thermo-Lag 330 Fire Barrier System...
P 92-02 Safety Concerns Related to "End of Life" of Aging Theratronics Teletherapy Units N
92-03 Release of Patients after Brachytherapy N
93-01 Release of Patients After Brachytherapy Treatment With Remote Afterloading Devices N
93-02 Debris Plugging of ECCS Suction Strainers PR USI A-43.
93-03 Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs BWR only 94-01 Potential Fuel Pool Draindown Caused by Inadequate Maintenance Practices at Dresden Unit 1 Plant specific 94-02 Corrosion Problems in Certain Stainless Steel Packagings Used to Transport Uranium Hexafluoride P
95-01 Quality Assurance Program for Transportation of Radioactive Material P
95-02 Unexpected Clogging of a RHR Pump Strainer...
PR 96-01 Control Rod Insertion Problem P
96-02 Movement of Heavy Loads over Spent Fuel in the Reactor Core...
PR USI A-36 96-03 Potential Plugging of ECCS Suction Strainers by Debris PR See GSI 191; USI A-43 96-04 Chemical, Galvanic, or Other Reactions in Spent Fuel Storage and Transportation Casks PR 97-01 Potential for Erroneous Calibration, Dose Rate, or Radiation Exposure Measurements with Certain Victoreen Model 530 and 530SI Electrometer/Dosemeters P; A 97-02 Puncture Testing of Shipping Packages under 10 CFR Part 71 A
- no BLs between 1998 and 2000***
01-01 Circumferential Cracking of RPV Head Penetration Nozzles DG-1145, Page C.IV.8-24
Bulletin Title Exclusion Code Notes 02-01 Reactor Pressure Vessel Head Degradation...
02-02 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs 03-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors USI A-43; See GSI-191 03-02 Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity 03-03 Potentially Defective 1-inch Valves for Uranium Hexafluoride Cylinders N
03-04 Rebaselining of Data in the Nuclear Materials Management and Safeguards System PR 04-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors PWR only 05-01 Material Control and Accounting at Reactors and Wet Spent Fuel Storage Facilities 05-02 Emergency Preparedness and Response Actions for Security-Based Events DG-1145, Page C.IV.8-25