Resolution of Generic Safety Issues: Appendix B: Generic Issues requiring licensees review in applications for design certification and combined licenses ( NUREG-0933, Main Report with Supplements 1–35 )

The table below identifies those generic issues (GIs) that have resulted in a regulatory product: hence, they may be applicable to operating and future nuclear power plants.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 52.47(a)(21), applications for design certification must contain, “Proposed technical resolutions of those unresolved safety issues (USIs) and medium- and high-priority generic safety issues which are identified in the version of NUREG-0933 current on the date up to 6 months before the docket date of the application and which are technically relevant to the design.”

Similarly, in accordance with 10 CFR 52.79(a)(20), applications for combined licenses must contain, “Proposed technical resolutions of those USIs and medium- and high-priority generic safety issues which are identified in the version of NUREG-0933 current on the date up to 6 months before the docket date of the application and which are technically relevant to the design.”

The priority designations for these issues are consistent with Appendix C. However, the process for prioritization of GIs (high, medium, low, drop) was replaced in 1999 by a screening and assessment process described in Management Directive (MD) 6.4, "Generic Issues." Upon the completion of the screening and assessment process, the staff will have determined whether the proposed issue requires new or revised regulatory actions, or should it exit the program. For the purposes of 10 CFR 52.47(a)(21) and 10 CFR 52.79(a)(20), any proposed issue successfully passing the screening and assessment stages will be considered equivalent to a high-priority GI.

The following table identifies those issues that fall within these requirements:

Issue Number	Issue Title	Resolution
Section 1. TMI Action Plan Items
I.A.1	Operating Personnel: Operating Personnel and Staffing Shift Technical Advisor	Resolved TMI Action Plan item by NUREG-0737
I.A.2	Operating Personnel: Training and Qualifications of Operating Personnel Immediate Upgrading of Operator and Senior Operator Training and Qualifications: Qualifications - Experience	Resolved TMI Action Plan item by NUREG-0737
I.A.3	Operating Personnel: Licensing and Requalification of Operating Personnel Revise Scope of Criteria for Licensing Examinations	Resolved TMI Action Plan item by NUREG-0737
I.A.4	Operating Personnel: Simulator Use and Development	Resulted in new regulatory product (Footnote 299 and 439)
I.B.1	Support Personnel: Management for Operations: Organization and Management Long-Term Improvements	Resolved TMI Action Plan item by NUREG-0737
I.B.2.1	Support Personnel: Inspection of Operating Reactors	Resolved TMI Action Plan item by NUREG-0737
I.B.2.2	Support Personnel: Inspection of Operating Reactors: Resident Inspector at Operating Reactors	Resolved TMI Action Plan item by NUREG-0737
I.B.2.3	Support Personnel: Inspection of Operating Reactors: Regional Evaluations	Resolved TMI Action Plan item by NUREG-0737
I.B.2.4	Support Personnel: Inspection of Operating Reactors: Overview of Licensee Performance	Resolved TMI Action Plan item by NUREG-0737
I.C.1	Operating Procedures: Short-Term Accident Analysis and Procedures Revision	Resolved TMI Action Plan item by NUREG-0737
I.C.2	Operating Procedures: Shift and Relief Turnover Procedures	Resolved TMI Action Plan item by NUREG-0737
I.C.3	Operating Procedures: Shift Supervisor Responsibilities	Resolved TMI Action Plan item by NUREG-0737
I.C.4	Operating Procedures: Control Room Access	Resolved TMI Action Plan item by NUREG-0737
I.C.5	Operating Procedures: Procedures for Feedback of Operating Experience to Plant Staff	Resolved TMI Action Plan item by NUREG-0737
I.C.6	Operating Procedures: Procedures for Verification of Correct Performance of Operating Activities	Resolved TMI Action Plan item by NUREG-0737
I.C.7	Operating Procedures: NSSS Vendor Review of Procedures	Resolved TMI Action Plan item by NUREG-0737
I.C.8	Operating Procedures: Pilot Monitoring of Selected Emergency Procedures for Near-Term Operating License Applicants	Resolved TMI Action Plan item by NUREG-0737
I.C.9	Operating Procedures: Long-Term Program Plan for Upgrading of Procedures	Resolved TMI Action Plan item by NUREG-0737
I.D.1	Control Room Design: Control Room Design Reviews	Resolved TMI Action Plan item by NUREG-0737
I.D.2	Control Room Design: Plant Safety Parameter Display Console	Resolved TMI Action Plan item by NUREG-0737
I.D.3	Control Room Design: Safety System Status Monitoring	Resolved TMI Action Plan item by NUREG-0737
I.D.4	Control Room Design: Control Room Design Standard	Resolved TMI Action Plan item by NUREG-0737
I.D.5	Control Room Design: Improved Control Room Instrumentation Research	Resulted in new regulatory product (Footnote 1205)
I.D.6	Control Room Design: Technology Transfer Conference	Resolved TMI Action Plan item by NUREG-0737
I.E.1	Analysis and Dissemination of Operating Experience: Office for Analysis and Evaluation of Operational Data	Resolved TMI Action Plan item by NUREG-0737
I.E.2	Analysis and Dissemination of Operating Experience: Program Office Operational Data Evaluation	Resolved TMI Action Plan item by NUREG-0737
I.E.3	Analysis and Dissemination of Operating Experience: Operational Safety Data Analysis	Resolved TMI Action Plan item by NUREG-0737
I.E.4	Analysis and Dissemination of Operating Experience: Coordination of Licensee, Industry, and Regulatory Programs	Resolved TMI Action Plan item by NUREG-0737
I.E.5	Analysis and Dissemination of Operating Experience: Nuclear Plant Reliability Data System	Resolved TMI Action Plan item by NUREG-0737
I.E.6	Analysis and Dissemination of Operating Experience: Reporting Requirements	Resolved TMI Action Plan item by NUREG-0737
I.E.7	Analysis and Dissemination of Operating Experience: Foreign Sources	Resolved TMI Action Plan item by NUREG-0737
I.E.8	Analysis and Dissemination of Operating Experience: Human Error Rate Analysis	Resolved TMI Action Plan item by NUREG-0737
I.F.1	Quality Assurance: Expand QA List	Resolved TMI Action Plan item by NUREG-0737
I.F.2	Quality Assurance: Develop More Detailed QA Criteria	Resulted in new regulatory product (Footnote 48)
I.G.1	Preoperational and Low Power Testing: Training Requirements	Resolved TMI Action Plan item by NUREG-0737
I.G.2	Preoperational and Low Power Testing: Scope of Test Program	Resulted in new regulatory product (Footnote 654)
II.B.1	Consideration of Degraded or Melted Cores in Safety Review: Reactor Coolant System Vents	Resolved TMI Action Plan item by NUREG-0737
II.B.2	Consideration of Degraded or Melted Cores in Safety Review: Plant Shielding to Provide Access to Vital Areas and Protect Safety Equipment for Post-Accident Operation	Resolved TMI Action Plan item by NUREG-0737
II.B.3	Consideration of Degraded or Melted Cores in Safety Review: Post-Accident Sampling	Resolved TMI Action Plan item by NUREG-0737
II.B.4	Consideration of Degraded or Melted Cores in Safety Review: Training for Mitigating Core Damage	Resolved TMI Action Plan item by NUREG-0737
II.B.6	Consideration of Degraded or Melted Cores in Safety Review: Risk Reduction for Operating Reactors at Sites with High Population Densities	Resulted in new regulatory product (Footnote 806)
II.B.8	Consideration of Degraded or Melted Cores in Safety Review: Rulemaking Proceeding on Degraded Core Accidents	Resulted in new regulatory product (Footnote 807)
II.D.1	Reactor Coolant System Relief and Safety Valves: Testing Requirements	Resolved TMI Action Plan item by NUREG-0737
II.D.3	Reactor Coolant System Relief and Safety Valves: Relief and Safety Valve Position Indication	Resolved TMI Action Plan item by NUREG-0737
II.E.1	System Design: Auxiliary Feedwater System	Resolved TMI Action Plan item by NUREG-0737
II.E.3	System Design: Decay Heat Removal	Resolved TMI Action Plan item by NUREG-0737
II.E.4	System Design: Containment Design	Resolved TMI Action Plan item by NUREG-0737
II.E.5	System Design: Design Sensitivity of B&W Reactors	Resulted in new regulatory product (Footnote 98, 159, 160, and 443)
II.E.6	System Design: In Situ Testing of Valves	Resulted in new regulatory product (Footnote 1217)
II.F.1	Instrumentation and Controls: Additional Accident Monitoring Instrumentation	Resolved TMI Action Plan item by NUREG-0737
II.F.2	Instrumentation and Controls: Identification of and Recovery from Conditions Leading to Inadequate Core Cooling	Resolved TMI Action Plan item by NUREG-0737
II.F.3	Instrumentation and Controls: Instruments for Monitoring Accident Conditions	Resulted in new regulatory product (Footnote 55, 151, and 376)
II.G.1	Electrical Power: Power Supplies for Pressurizer Relief Valves, Block Valves, and Level Indicators	Resolved TMI Action Plan item by NUREG-0737
II.J.4.1	General Implications of TMI for Design and Construction Activities Revise Deficiency Reporting Requirements	Resulted in new regulatory product (Footnote 1396)
II.K.1	Measures to Mitigate Small Break Loss of Coolant Accidents and Loss of Feedwater Accidents: IE Bulletins	Resulted in new regulatory product (Footnote 48)
III.A.1	Emergency Preparedness and Radiation Effects: Improve Licensee Emergency Preparedness - Short-Term	Resolved TMI Action Plan item by NUREG-0737
III.A.2	Emergency Preparedness and Radiation Effects: Improving Licensee Emergency Preparedness—Long-Term	Resolved TMI Action Plan item by NUREG-0737
III.A.3	Emergency Preparedness and Radiation Effects: Improving NRC Emergency Preparedness	Resulted in new regulatory product (Footnote 779)
III.D.1	Radiation Protection: Radiation Source Control	Resolved TMI Action Plan item by NUREG-0737
III.D.3	Radiation Protection: Worker Radiation Protection Improvement	Resulted in new regulatory product (Footnote 48, 98 and 912)
Section 2. Task Action Plan Items
A-1	Water Hammer	Resulted in new regulatory product (Footnote 698)
A-2	Asymmetric Blowdown Loads on Reactor Primary Coolant Systems	Resulted in new regulatory product (Footnote 700)
A-3	Westinghouse Steam Generator Tube Integrity	Resulted in new regulatory product (Footnote 1136 and 1138)
A-4	CE Steam Generator Tube Integrity	Resulted in new regulatory product (Footnote 1136 and 1138)
A-5	B&W Steam Generator Tube Integrity	Resulted in new regulatory product (Footnote 1136 and 1138)
A-6	Mark I Short-Term Program	Resulted in new regulatory product (Footnote 701)
A-7	Mark I Long-Term Program	Resulted in new regulatory product (Footnote 702
A-8	Mark II Containment Pool Dynamic Loads Long-Term Program	Resulted in new regulatory product (Footnote 703)
A-9	ATWS	Resulted in new regulatory product (Footnote 704 and 725)
A-10	BWR Feedwater Nozzle Cracking	Resulted in new regulatory product (Footnote 742)
A-11	Reactor Vessel Materials Toughness	Resulted in new regulatory product (Footnote 744)
A-12	Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports	Resulted in new regulatory product (Footnote 388)
A-13	Snubber Operability Assurance	Resulted in new regulatory product (Footnote 11, NUREG 0800, Section 3.9.3)
A-23	Containment Leak Testing	Resulted in new regulatory product (Footnote 122 and 123)
A-24	Qualification of Class 1E Safety-Related Equipment (former USI)	Resulted in new regulatory product (Footnote 19)
A-25	Non-Safety Loads on Class 1E Power Sources	Resulted in new regulatory product (Footnote 144)
A-26	Reactor Vessel Pressure Transient Protection (former USI)	Resulted in new regulatory product (Footnote 746)
A-28	Increase in Spent Fuel Pool Storage Capacity	Resulted in new regulatory product (Footnote 11, NUREG 0800, Section 5.4.7)
A-31	RHR Shutdown Requirements	Resulted in new regulatory product (Footnote Section 5.4.7 of NUREG 0800)
A-35	Adequacy of Offsite Power Systems	Resulted in new regulatory product (Footnote 117)
A-36	Control of Heavy Loads Near Spent Fuel	Resulted in new regulatory product (Footnote 1842, 1843, and 1844)
A-39	Determination of Safety Relief Valve Pool Dynamic Loads and Temperature Limits	Resulted in new regulatory product (Footnote 60, 734, 748, and 749)
A-40	Seismic Design Criteria	Resulted in new regulatory product (Footnote 1245 and 1246)
A-42	Pipe Cracks in Boiling Water Reactors	Resulted in new regulatory product (Footnote 750)
A-43	Containment Emergency Sump Performance	Resulted in new regulatory product (Footnote 1059)
A-44	Station Blackout	Resulted in new regulatory product (Footnote 1109)
A-46	Seismic Qualification of Equipment in Operating Plants	Resulted in new regulatory product (Footnote 1069)
A-47	Safety Implications of Control Systems	Resulted in new regulatory product (Footnote 1250)
A-48	Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment	Resulted in new regulatory product (Footnote 1227)
A-49	Pressurized Thermal Shock (former USI)	Resulted in new regulatory product (Footnote 1074)
B-10	Behavior of BWR Mark III Containments	Resulted in new regulatory product (Footnote 600)
B-36	Develop Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineer Safety Feature Systems and for Normal Ventilation Systems	Resulted in new regulatory product (Footnote 208 and 209)
B-53	Load Break Switch	Resulted in new regulatory product (Footnote 59)
B-56	Diesel Reliability	Resulted in new regulatory product (Footnote 1487)
B-59	(N-1) Loop Operation in BWRs and PWRs	Resulted in new regulatory product (Footnote 774)
B-63	Isolation of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary	Resulted in new regulatory product (Footnote 168)
B-64	Decommissioning of Reactors	Resulted in new regulatory product (Footnote 1364, 1570, 1571, and 1572
B-66	Control Room Infiltration Measurements	Resulted in new regulatory product (Footnote 3 and 98)
C-1	Assurance of Continuous Long-Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment	Resulted in new regulatory product (Footnote 19 and 46)
C-4	Statistical Methods for ECCS Analysis	Resulted in new regulatory product (Footnote 908)
C-5	Decay Heat Update	Resulted in new regulatory product (Footnote 920)
C-6	LOCA Heat Sources	Resulted in new regulatory product (Footnote 0908)
C-10	Effective Operation of Containment Sprays in a LOCA	Resulted in new regulatory product (ANSI/ANS 56.5-1979, "PWR and BWR Containment Spray System Design Criteria")
C-17	Interim Acceptance Criteria for Solidification Agents for Radioactive Solid Wastes	Resulted in new regulatory product (Section 61.56 of 10 CFR Part 61,Federal Register on December 27, 1982, 47 FR 57446)
Section 3. New Generic Issues
25	Automatic Air Header Dump on BWR Scram System	Resulted in new regulatory product (Footnote 125)
40	Safety Concerns Associated with Pipe Breaks in the BWR Scram System	Resulted in new regulatory product (Footnote 328
41	BWR Scram Discharge Volume Systems	Resulted in new regulatory product (Footnote 201, 420, 421 and 422)
43	Reliability of Air Systems	Resulted in new regulatory product (Footnote 1140 and 1141)
45	Inoperability of Instrumentation Due to Extreme Cold Weather	Resulted in new regulatory product (Footnote 501)
51	Proposed Requirements for Improving the Reliability of Open Cycle Service Water Systems	Resulted in new regulatory product (Footnote 1259)
59	Technical Specification Requirements for Plant Shutdown when Equipment for Safe Shutdown is Degraded or Inoperable	Resulted in new regulatory product (Footnote 767)
67.3.3	Steam Generator Staff Actions: Improved Accident Monitoring	Resulted in new regulatory product (Footnote 376)
70	PORV and Block Valve Reliability	Resulted in new regulatory product (Footnote 1290)
73	Detached Thermal Sleeves	Resulted in new regulatory product (Footnote 742, 1316 and 1445)
75	Generic Implications of ATWS Events at the Salem Nuclear Plant	Resulted in new regulatory product (Footnote 520, 1297, and 1298)
86	Long-Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping	Resulted in new regulatory product (Footnote 1111)
87	Failure of HPCI Steam Line Without Isolation	Resulted in new regulatory product (Footnote 1217)
89	Stiff Pipe Clamps	Resulted in new regulatory product (Footnote 1448)
93	Steam Binding of Auxiliary Feedwater Pumps	Resulted in new regulatory product (Footnote 1112 and 1113)
94	Additional Low Temperature Overpressure Protection for Light-Water Reactors	Resulted in new regulatory product (Footnote 1290)
99	RCS/RHR Suction Line Valve Interlock on PWRs	Resulted in new regulatory product (Footnote 1145)
103	Design for Probable Maximum Precipitation	Resulted in new regulatory product (Footnote 1262)
108	BWR Suppression Pool Temperature Limits	Resulted in new regulatory product (Footnote 702 and 733, and 734)
112	Westinghouse RPS Surveillance Frequencies and Out-of-Service Times	Resulted in new regulatory product (Footnote 0823)
118	Tendon Anchorage Failure	Resulted in new regulatory product (Footnote 481, 1360, and 1361)
119	Piping Review Committee Recommendations: Piping Rupture Requirements and Decoupling of Seismic and LOCA Loads	Resulted in new regulatory product (Footnote 1345)
124	Auxiliary Feedwater System Reliability	Resulted in new regulatory product (Footnote 1203)
128	Electrical Power Reliability	Resulted in new regulatory product (Footnote 1399, 1400, 1401, and 1402)
130	Essential Service Water Pump Failures at Multi-plant Sites	Resulted in new regulatory product (Footnote 1368, 1408, 1409, and 1410)
139	Thinning of Carbon Steel Piping in LWRs	Resulted in new regulatory product (Footnote 1093, 1095 and 1132)
155.1	Generic Concerns Arising from Three Mile Island (TMI)-2 Cleanup More Realistic Source Term Assumptions	Resulted in new regulatory product (Footnote 1465, 1530, and 1564)
177	Vehicle Intrusion at Three Mile Island (TMI)	Resulted in new regulatory product (final Rule was published on August 1, 1994)
182	General Electric Extended Power Uprate	Resulted in new regulatory product
183	Cycle-Specific Parameter Limits in Technical Specifications	Resulted in new regulatory product (Footnote 1637)
186	Potential Risk and Consequences of Heavy Load Drops	Resulted in new regulatory product (Footnote 2000 and 2187)
189	Susceptibility of Ice Condenser Containments to Early Failure from Hydrogen Combustion During A Severe Accident	Resulted in new regulatory product (10 CFR 50.44)
191	Assessment of Debris Accumulation on PWR Sump Performance	Resulted in new regulatory product (Footnote 1912 and 1913)
199	Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States	Resulted in new regulatory product, NRC Order EA-12-049 Currently open in Regulatory Office Implementation
204	Flooding of Nuclear Power Plant Sites following upstream Dam Failures	Resulted in new regulatory product, NRC Order EA-12-049 Currently open in Regulatory Office Implementation
Section 4. Human Factors Issues
HF1.1	Staffing and Qualifications: Shift Staffing	Resulted in new regulatory product. (Footnote 994)
Section 5. Chernobyl Issues:
None
Section 6. Nuclear Material Safety and Safeguards Issues:
NMSS-0007	Criticality Benchmarks Greater Than 5% Enrichment	Resulted in new regulatory product. (Footnote 1925)
NMSS-0010	Troxler Gauge Source Rod Weld Failures	Resulted in new regulatory product. (Footnote 1713 and 1808)
NMSS-0014	Surety Estimates for Groundwater Restoration at In-Situ Leach Fields	Resulted in new regulatory product. (Footnote 1892)
NMSS-0016	Adequacy of 0.05 Weight Percent Limit in 10 CFR 40	Resulted in new regulatory product. (footnote 1894)
NMSS-0017	Misleading Marketing Information to General Licensees	Resulted in new regulatory product. (footnote 1781)

Parent topic: Appendices