ML081490118

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NRC Review: Generic Communications Status for TVA Watts Bar Unit 2
ML081490118
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 05/28/2008
From:
NRC/NRR/ADRO/DORL/WBSPB
To:
Tennessee Valley Authority
Milano P, NRR/DORL , 415-1457
Shared Package
ML081490093 List:
References
TAC MD8314
Download: ML081490118 (35)
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Text

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 71-01 Involves Main Steam isolation valves NA NA IEB 71-02 PWR Reactor Trip Circuit Breakers NA NA IEB 71-03 Catastrophic failure of Main steam line Relief valve Headers NA NA IEB 72-01 Failed hangers for Emergency Core Cooling System Suction header NA NA Simultaneous Actuation of a Safety Injection Signal on Both units of IEB 72-02 NA NA a Dual unit Facility IEB 72-03 Limitorque Valve Operator Failures NA NA Faulty Overcurrent Trip Delay Device in Circuit Breakers for IEB 73-01 C C TVA letter dated 04/04/1973 - IR390/391 75-5 Engineered Safety Systems IEB 73-02 Malfunction of Containment Purge Supply Valve Switch C C TVA letter dated 08/22/1973 - IR390/391 75-5 IEB 73-03 Defective Hydraulic Snubbers and Restraints C C IR 390/391 85-08 IEB 73-04 Defective Bergen-Patterson Hydraulic Shock Absorbers C C IR 390/391 85-08 IEB 73-05 Manufacturing Defect in BWR Control Rods NA NA IEB 73-06 Inadvertent Criticality in a BWR NA NA IEB 74-01 Valve Deficiencies C C TVA letter dated 04/15/1974 - IR390/391 75-5 IEB 74-01a Abnormal Occurrences in Piping Systems C C TVA letter dated 04/15/1974 - IR390/391 75-5 IEB 74-02 Truck Strike Possibility NA NA Failure of Structural or Seismic Support Bolts on Class I Implement NUREG-0577 on Unit 2 similar as IEB 74-03 CI CI Components Unit 1 Failure of Structural or Seismic Support Bolts on Class I IEB 74-03a C C Components IEB 74-04 Malfunction of Target Rock Safety Relief Valves NA NA IEB 74-04a Malfunction of Target Rock Safety Relief Valves NA NA IEB 74-05 Shipment of an Improperly Shielded Source NA NA IEB 74-06 Defective Westinghouse (W) Type W-2 Control Switch Component C C TVA letter dated 10/18/1974 - IR390/391 75-6 IEB 74-07 Personnel Exposure - Irradiation Facility NA NA IEB 74-08 Deficiency in the ITE Molded Case Circuit Breakers, Type HE-3 C C TVA letter dated 08/21/1974 - IR390/391 75-5 IEB 74-09 Deficiencies in GE Model 4KV Magne-Blast Circuit Breakers C C TVA letter dated 09/20/1974 - IR390/391 76-6 IEB 74-10 Failures in 4 inch Bypass Pipe at Dresden 2 NA NA IEB 74-10a Failures in 4 inch Bypass Pipe at Dresden 2 NA NA IEB 74-10b Failures in 4 inch Bypass Pipe at Dresden 2 NA NA IEB 74-11 Improper Wiring of Safety Injection Logic at Zion 1 & 2 C C IR 390/391 75-6 Page 1 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 74-12 Incorrect Coils in W Type SG Relays at Trojan C C TVA letter dated 12/12/1974 - IR390/391 75-5 Improper Factory Wiring on GE Motor Control Centers at Fort IEB 74-13 C C TVA letter dated 12/24/1974 - IR390/391 75-5 Calhoun IEB 74-14 BWR Relief Valve Discharge to Suppression Pool NA NA Misapplication of Cutler-Hammer Three Position Maintained Switch Install modified A3 Cutler-Hammer 10250T IEB 74-15 CI CI Model No. 10250T switches Improper Machining of Pistons in Colt Industries (Fairbanks-Morse)

IEB 74-16 C C TVA letter dated 01/02/1975 - IR390/391 75-3 Diesel Generators IEB 75-01 Through-Wall Cracks in Core Spray Piping at Dresden-2 NA NA Defective Radionics Radiograph Exposure Devices and Source IEB 75-02 NA NA Changes Incorrect Lower Disc Spring and Clearance Dimension in Series IEB 75-03 CI CI Modify valves not modified at factory 8300 and 8302 ASCO Solenoid Valves IEB 75-04 Cable Fire at BFNPP CI CI Part of fire protection CAP IEB 75-05 Operability of Category I Hydraulic Shock and Sway Suppressors CI CI Unit 2 action: Install proper suppressors IEB 75-06 Defective W Type OT-2 Control Switches CI CI IEB 75-07 Exothermic Reaction in Radwaste Shipment NA NA IEB 75-08 PWR Pressure Instrumentation CT CT NRC IR 390/391 85-08 IEB 76-01 BWR Isolation Condenser Tube Failure NA NA Repair or Replace relays before preoperational IEB 76-02 Relay Coil Failures CI CI tests IEB 76-03 Relay Malfunctions - GE Type STD Relays C C TVA letter dated 05/17/1976 - IR390/391 76-6 IEB 76-04 Cracks in Cold Water Piping at BWRs NA NA IEB 76-05 Relay Failures C C TVA letter dated 06/07/1976-IR 390/391 85-08 Diaphragm Failures in Air Operated Auxiliary Actuators for TVA memo dated 01/25/1985- IR 390/391 85-IEB 76-06 C C Safety/Relief Valves 05 IEB 76-07 Crane Hoist Control Circuit Modifications C C TVA letter dated 10/29/1976 - IR 390/391 85-08 IEB 76-08 Teletherapy Units NA NA IEB 77-01 Pneumatic Time Delay Relay Setpoint Drift C C TVA letter dated 07/01/1977-IR 390/391 85-08 Potential Failure Mechanism in Certain W AR Relays with Latch IEB 77-02 C C TVA letter dated 11/11/1977-IR 390/391 85-08 Attachments Include necessary periodic testing in test IEB 77-03 On-Line Testing of the W Solid State Protection System CI CI procedures Page 2 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Calculation Error Affecting Performance of a System for Controlling IEB 77-04 CT CT NRC IR 391/78-09 pH of Containment Sump Water Following a LOCA IEB 77-05 Electrical Connector Assemblies C C TVA letter dated 01/17/1978 - IR391 78-9 IEB 77-05A Electrical Connector Assemblies C C TVA letter dated 01/17/1978 - IR391 78-9 Potential Problems with Containment Electrical Penetration IEB 77-06 C C IR 390/391 85-08 Assemblies Containment Electrical Penetration Assemblies at Nuclear Power IEB 77-07 C C TVA letter dated 01/20/1978 - IR391 78-9 Plants under Construction Assurance of Safety and Safeguards During an Emergency -

IEB 77-08 C C TVA letter dated 03/01/1978 - IR391 78-9 Locking Systems IEB 78-01 Flammable Contact - Arm Retainers in GE CR120A Relays C C TVA letter dated 03/20/1978 - IR391 78-9 IEB 78-02 Terminal Block Qualification C C TVA letter dated 03/01/1978 - IR391 78-9 Potential Gas Mixture Accumulations Associated with BWR Offgas IEB 78-03 NA NA System Operations Environmental Qualification of Certain Stem Mounted Limit Ensure NAMCO switches have been approved-IEB 78-04 CI CI Switches Inside Reactor Containment IR50-391/82-10 IEB 78-05 Malfunctioning of Circuit Breaker Auxiliary Contact Mechanism C C TVA letter dated 06/12/1978 - IR391 78-15 IEB 78-06 Defective Cutler-Hammer Type M Relays and DC Coils C C IR 391/78-19 ML072530128 IEB 78-07 Protection Afforded by Air-Line Respirators and Supplied-Air Hoods NA NA ML072610768 IEB 78-08 Radiation Levels from Fuel Element Transfer Tubes NA NA BWR Drywell Leakage Paths Associated with Inadequate Drywell IEB 78-09 NA NA Closures Bergen-Patterson Hydraulic Shock Suppressor Accumulator Spring IEB 78-10 C C TVA letter dated 08/14/1978 IR 391/ 78-19 Coils ML072530128 IEB 78-11 Examination of Mark I Containment Torus Welds NA NA TVA Westinghouse letter dated 10/29/1979 -

IEB 78-12 Atypical Weld Material in Reactor Pressure Vessel Welds C C IR390/391 81-04 TVA Westinghouse letter dated 10/29/1979 -

IEB 78-12a Atypical Weld Material in Reactor Pressure Vessel Welds C C IR390/391 81-04 TVA Westinghouse letter dated 10/29/1979 -

IEB 78-12b Atypical Weld Material in Reactor Pressure Vessel Welds C C IR390/391 81-04 Failures in Source Heads Kay Ray Gauge Models 7050, 7050B, IEB 78-13 NA NA 7051, 7051B, 7060, 7060B, 7061 and 7061B IEB 78-14 Deterioration of Buna-N Components in ASCO Solenoids NA NA IEB 79-01 Environmental Qualification of Class 1E Equipment C C IR 391/80-05 IEB 79-01r1 Environmental Qualification of Class 1E Equipment C C IR 391/80-05 IEB 79-01a Environmental Qualification of Class 1E Equipment C C IR 391/80-05 Page 3 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 79-01b Environmental Qualification of Class 1E Equipment C C IR 391/80-05 IEB 79-01bs1 Environmental Qualification of Class 1E Equipment C C IR 391/80-05 IEB 79-01bs2 Environmental Qualification of Class 1E Equipment C C IR 391/80-05 IEB 79-01bs3 Environmental Qualification of Class 1E Equipment C C IR 391/80-05 Pipe Support Base Plate Designs Using Concrete Expansion NRC review of HAAUP program in NUREG-IEB 79-02 CI CI Anchor Bolts 1232, SSER6 & SSER8 Pipe Support Base Plate Designs Using Concrete Expansion NRC review of HAAUP program in NUREG-IEB 79-02r1 CI CI Anchor Bolts 1232, SSER6 & SSER8 Pipe Support Base Plate Designs Using Concrete Expansion NRC review of HAAUP program in NUREG-IEB 79-02r1s1 CI CI Anchor Bolts 1232, SSER6 & SSER8 Pipe Support Base Plate Designs Using Concrete Expansion NRC review of HAAUP program in NUREG-IEB 79-02r2 CI CI Anchor Bolts 1232, SSER6 & SSER8 Longitudinal Weld Defects in ASME SA-312 Type 304 SS Pipe TVA letter dated 07/16/1981-IR391/82-17 and IEB 79-03 C C Spools Fabricated by Youngstown Welding & Engineering IR391/84-33 Longitudinal Weld Defects in ASME SA-312 Type 304 SS Pipe TVA letter dated 07/16/1981-IR391/82-17 and IEB 79-03a C C Spools Fabricated by Youngstown Welding & Engineering IR391/84-33 Incorrect Weights for Swing Check Valves Manufactured by Velan IEB 79-04 C C TVA letter dated 10/20/1980- IR391/83-11 Engineering IEB 79-05 Nuclear Incident at TMI NA NA IEB 79-05a Nuclear Incident at TMI NA NA IEB 79-05b Nuclear Incident at TMI NA NA IEB 79-05c Nuclear Incident at TMI NA NA Review of Operational Errors and System Misalignments Identified IEB 79-06 C C IR 391/80-05 During the Three Mile Island Incident Review of Operational Errors and System Misalignments Identified IEB 79-06a C C IR 391/80-05 During the Three Mile Island Incident Review of Operational Errors and System Misalignments Identified IEB 79-06aR1 C C IR 391/80-05 During the Three Mile Island Incident Review of Operational Errors and System Misalignments Identified IEB 79-06b C C IR 391/80-05 During the Three Mile Island Incident Review of Operational Errors and System Misalignments Identified IEB 79-06c C C IR 391/80-05 During the Three Mile Island Incident IEB 79-07 Seismic Stress Analysis of Safety-Related Piping C C TVA letter dated 05/31/1979 - IR391/79-25 IEB 79-08 Events Relevant to BWRs Identified During TMI Incident NA NA Complete preservice preventive maintenance IEB 79-09 Failure of GE Type AK-2 Circuit Breaker in Safety Related Systems CI CI on AK-2 Circuit Breakers IEB 79-10 Requalification Training Program Statistics C C IR states that IEB is NA & requires no action ML072560606.

Faulty Overcurrent Trip Device in Circuit Breakers for Engineering IEB 79-11 C C TVA letter dated 07/20/1979- IR391/79-25 Safety Systems Page 4 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 79-12 Short Period Scrams at BWR Facilities NA NA IEB 79-13 Cracking in Feedwater Piping C C TVA letter dated 12/01/1983-IR 390/391 85-08 IEB 79-13r1 Cracking in Feedwater Piping C C TVA letter dated 12/01/1983-IR 390/391 85-08 IEB 79-13r2 Cracking in Feedwater Piping C C TVA letter dated 12/01/1983-IR 390/391 85-08 NRC review of HAAUP Program in NUREG-IEB 79-14 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI 1232, SSER6 & SSER8 NRC review of HAAUP Program in NUREG-IEB 79-14r1 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI 1232, SSER6 & SSER8 NRC review of HAAUP Program in NUREG-IEB 79-14r1s1 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI 1232, SSER6 & SSER8 NRC review of HAAUP Program in NUREG-IEB 79-14r1s2 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI 1232, SSER6 & SSER8 IEB 79-15 Deep Draft Pump Deficiencies C C TVA letter dated 01/24/1992-IR 390/391 95-70 ML072610753 IEB 79-15s1 Deep Draft Pump Deficiencies C C TVA letter dated 01/24/1992-IR 390/391 95-70 ML072610753 IEB 79-16 Vital Area Access Controls C C IR states that IEB is NA & requires no action ML072560606 IEB 79-17 Pipe Cracks in Stagnant Borated Water Systems at PWR Plants NA NA IEB 79-17r1 Pipe Cracks in Stagnant Borated Water Systems at PWR Plants NA NA Audibility Problems Encountered on Evacuation of Personnel from IEB 79-18 NA NA High-Noise Areas Page 5 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 79-19 Packaging of Low-Level Radioactive Waste for Transport and Burial NA NA IEB 79-20 Packaging, Transport and Burial of Low-Level Radioactive Waste NA NA Reviewed in 7.2.5 of both original 1982 SER IEB 79-21 Temperature Effects on Level Measurements CI CI and SSER14 Possible Leakage of Tubes of Tritium Gas Used in Time Pieces for IEB 79-22 NA NA Luminosity Potential Failure of Emergency Diesel Generator Field Exciter IEB 79-23 C C TVA letter dated 10/29/1979- IR391/80-05 Transformer Insulate section of piping in containment spray IEB 79-24 Frozen Lines CI CI full flow test line IEB 79-25 Failures of W BFD Relays in Safety Related Systems C C IR 391/80-02 IEB 79-26 Boron Loss from BWR Control Blades NA NA IEB 79-26r1 Boron Loss from BWR Control Blades NA NA IEB 79-27 Loss of Non-Class 1E I & C Power System Bus During Operation CI CI Reviewed in 7.5.3 of original 1982 SER Possible Malfunction of NAMCO Model EA180 Limit Switches at IEB 79-28 C C TVA letter dated 04/01/1993-IR 390/391 93-32 Elevated Temperatures ML072680504 IEB 80-01 Operability of ADS Valve Pneumatic Supply NA NA IEB 80-02 Inadequate QA for Nuclear Supplied Equipment NA NA IEB 80-03 Loss of Charcoal from Standard Type II, 2 Inch Tray Adsorber Cells C C TVA letter dated 30/21/1980- IR 391/80-12 ML072560654 Analysis of a PWR Main Steam Line Rupture with Continued IEB 80-04 CI CI IR 50-391/85-49-Complete analysis for Unit 2 Feedwater Addition ML072500505 Vacuum Condition Resulting in Damage to Chemical Volume Closed in IR50-391/84-45-Complete IEB 80-05 CI CI Control System Holdup Tanks surveillance procedures for Unit 2 Reviewed in 7.3.5 of 1982 SER. Perform IEB 80-06 Engineered Safety Features Reset Control CI CI verification during preoperational testing IEB 80-07 BWR Jet Pump Assembly Failure NA NA IEB 80-07s1 BWR Jet Pump Assembly Failure NA NA IEB 80-08 Examination of Containment Liner Penetration Welds C C TVA letter dated 07/08/1980- IR 391/80-12 TVA letter dated 01/15/1981- NUREG/CR 5291, IEB 80-09 Hydramotor Actuator Deficiencies C C IR390/391 85-08 & IR 391/85-49 Contamination of Non-radioactive System and Resulting Potential 1. Correct deficiencies involving monitoring of IEB 80-10 for Unmonitored, Uncontrolled Release of Radioactivity to CI CI systems. 2. Include proper monitoring of non-Environment radioactive systems in procedures.

Page 6 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 80-11 Masonry Wall Design CI CI Complete corrective actions in 50-391/93-01 Implement operating instructions & abnormal IEB 80-12 Decay Heat Removal System Operability CI CI operating instructions for RHR IEB 80-13 Cracking in Core Spray Spargers NA NA IEB 80-14 Degradation of Scram Discharge Volume Capability CT CT NRC reviewed in SSER6 1.14.2 Possible Loss of Emergency Notification System with Loss of IEB 80-15 C C IR 390/391 85-08 Offsite Power Potential Misapplication of Rosemount Models 1151 and 1152 IEB 80-16 C C TVA letter dated 08/29/1980- IR390/391 81-17 Pressure Transmitters With Either "A" or "D" Output Codes ML072570467 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at IEB 80-17 NA NA a BWR Failure of 76 of 185 Control Rods to Fully Insert During a Scram at IEB 80-17s1 NA NA a BWR Failure of 76 of 185 Control Rods to Fully Insert During a Scram at IEB 80-17s2 NA NA a BWR Failure of 76 of 185 Control Rods to Fully Insert During a Scram at IEB 80-17s3 NA NA a BWR Failure of 76 of 185 Control Rods to Fully Insert During a Scram at IEB 80-17s4 NA NA a BWR Failure of 76 of 185 Control Rods to Fully Insert During a Scram at IEB 80-17s5 NA NA a BWR Maintenance of Adequate Minimum Flow Thru Centrifugal Charging IR 50-391/85-49-Implement design and IEB 80-18 CI CI Pumps Following procedure changes.

a Secondary Side High Energy Rupture TVA letter dated 09/04/1980- NUREG/CR 4933, IEB 80-19 Mercury-Wetted Matrix Relay in Reactor Protective Systems C C IR390/391 81-17 TVA letter dated 09/04/1980- NUREG/CR 4933, IEB 80-19r1 Mercury-Wetted Matrix Relay in Reactor Protective Systems C C IR390/391 81-17 IEB 80-20 Failure of W Type W-2 Spring Return to Neutral Control Switches CI CI Modify switches IEB 80-21 Valve Yokes Supplied by Malcolm Foundry Co. C C TVA letter dated 05/06/1981-IR390/391 85-08 Automation Industries, Model 200-520-008 Sealed-Source IEB 80-22 NA NA Connectors TVA letter dated 03/31/1981- NUREG/CR 5292, IEB 80-23 Failures of Solenoid Valves Manufactured by Valcor Eng. Corp C C IR390/391 81-17 ML072570467 Confirm reactor cavity cannot be flooded, IEB 80-24 Prevention of Damage Due to Water Leakage Inside Containment CI CI resulting in partial/total submergence Page 7 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 80-25 Operating Problems with Target Rock SR Valves at BWRs NA NA NRC: IR 390/391 81-17. Report states bulletin IEB 81-01 Surveillance of Mechanical Snubbers NA NA is NA NRC: IR 390/391 81-17. Report states bulletin IEB 81-01r1 Surveillance of Mechanical Snubbers NA NA is NA IEB 81-02 Failure of Gate Type Valves to Close Against Differential Pressure C C TVA letter dated 09/30/1983-IR390/391 84-03 IEB 81-02s1 Failure of Gate Type Valves to Close Against Differential Pressure C C TVA letter dated 09/30/1983-IR390/391 84-03 IEB 81-03 Flow Blockage to Cooling Water by Asiatic Clams and Mussels C C TVA letter dated 07/21/1981- IR390/391 81-17 ML072570467 IEB 82-01 Alteration of Radiographs of Welds in Piping Subassemblies C C IR 390/391 85-08 IEB 82-01r1 Alteration of Radiographs of Welds in Piping Subassemblies C C IR 390/391 85-08 IEB 82-01r1s1 Alteration of Radiographs of Welds in Piping Subassemblies C C IR 390/391 85-08 Degradation of Threaded Fasteners in the Reactor Coolant IEB 82-02 CI CI Approach accepted in IR50-391/85-08 Pressure Boundary of PWR Plants Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless IEB 82-03 NA NA Applies only to BWR's Steel, Recirculation System Piping at BWR Plants ML031210724 Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless IEB 82-03r1 NA NA Applies only to BWR's Steel, Recirculation System Piping at BWR Plants ML031210724 Deficiencies in Primary Containment Electrical Penetration IEB 82-04 C C TVA letter dated 01/24/1983- IR391/83-08 Assemblies Failure of Trip Breakers (Westinghouse DB-50) to Open on IEB 83-01 C C IR 390/391 85-08 and 391/92-13 Automatic Trip Signal Stress Corrosion Cracking in Large-Diameter Stainless Steel IEB 83-02 NA NA Recirculation System Piping at BWR Plants Check Valve Failures in Raw Water Cooling Systems of Diesel IEB 83-03 NA NA Generators Install new undervoltage attachment with wider IEB 83-04 Failure of the Undervoltage Trip Function of Reactor Trip Breakers CI CI grooves on reactor trip breakers ASME Nuclear Code Pumps and Spare Parts Manufactured by TVA letter dated 09/07/1983-IR 391/85-04 and IEB 83-05 C C Hayward Tyler Pump Co NUREG/CR 5297 IEB 83-06 Nonconforming Material Supplied by Tube-Line CI CI IR 390/391 84-03; NUREG/CR 4934 IEB 83-07 Apparently Fraudulent Products Sold by Ray Miller, Inc C C TVA letter dated 03/22/1984-IR391/85-04 IEB 83-07s1 Apparently Fraudulent Products Sold by Ray Miller, Inc C C TVA letter dated 03/22/1984-IR391/85-04 IEB 83-07s2 Apparently Fraudulent Products Sold by Ray Miller, Inc C C TVA letter dated 03/22/1984-IR391/85-04 Electrical Circuit Breakers With Undervoltage Trip in Safety Related IEB 83-08 C C TVA letter dated 03/29/1984-IR391/84-33 Applications other than the Reactor Trip System IEB 84-01 Cracks in BWR Mark 1 Containment Vent Headers NA NA Page 8 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number TVA letter dated 07/10/1984-IR390/391 84-42 IEB 84-02 Failure of GE Type HFA Relays In Use In Class 1E Safety Systems C C and IR391/84-54 ML072570623 IEB 84-03 Refueling Cavity Water Seal CI CI Reviewed in IR390/391/93-11 IEB 85-01 Steam Binding of Auxiliary Feedwater Pumps CI CI IR 390/391 90-20. See App EE of SSER 16 Undervoltage Trip Attachment of W DB-50 Type Reactor Trip Install automatic shut trip on Westinghouse DS-IEB 85-02 CI CI Breakers 416 reactor trip breakers appear as C & CI Motor Operated Valve Common Mode Failures During Plant IEB 85-03 C C Superseded by GL89-10 Transients due to Improper Switch Settings ML072690589 Motor Operated Valve Common Mode Failures During Plant IEB 85-03s1 C C Superseded by GL89-10 Transients due to Improper Switch Settings ML072690589 IEB 86-01 Minimum Flow Logic Problems That Could Disable RHR Pumps NA NA IEB 86-02 Static "O" Ring Differential Pressure Switches C C TVA letter dated 11/20/1986-IR390/391 90-24 ML072610318 Potential Failure of Multiple ECCS Pumps Due to Single Failure of IEB 86-03 C C TVA letter dated 11/14/1986-IR390/391 87-03 Air-Operated Valve in Minimum Flow Recirculation Line ML072530767 Defective Teletherapy Timer That May Not Terminate Treatment IEB 86-04 NA NA Dose IEB 87-01 Thinning of Pipe Walls in Nuclear Power Plants C C Fastener Testing to Determine Conformance with Applicable IEB 87-02 CI CI NRC letter dated 08/18/1989 Material Specifications Fastener Testing to Determine Conformance with Applicable IEB 87-02s1 CI CI NRC letter dated 08/18/1989 Material Specifications Fastener Testing to Determine Conformance with Applicable IEB 87-02s2 CI CI NRC letter dated 08/18/1989 Material Specifications IEB 88-01 Defects in W Circuit Breakers C C TVA letter dated 11/15/1991-IR 390/391 93-01 ML072680775 NRC letter 06/07/1990-Evaluate E/C data to IEB 88-02 Rapidly Propagating Fatigue Cracks in Steam Generator Tubes CI CI determine anti vibration bar depth Inadequate Latch Engagement in HFA Type Latching Relays IEB 88-03 C C TVA letter dated 04/13/1992-IR 390/391 92-13 Manufactured by General Electric (GE) Company ML072680594 NRC letter 05/24/1990-Perform calculations &

IEB 88-04 Potential Safety-Related Pump Loss CI CI install check valves Nonconforming Materials Supplied by Piping Supplies, Inc. and IEB 88-05 CI CI NRC reviewed in App. EE of SSER16 West Jersey Manufacturing Company Nonconforming Materials Supplied by Piping Supplies, Inc. and IEB 88-05s1 CI CI West Jersey Manufacturing Company Page 9 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Nonconforming Materials Supplied by Piping Supplies, Inc. and IEB 88-05s2 CI CI West Jersey Manufacturing Company Actions to be Taken for the Transfer of Model No. SPEC 2-T IEB 88-06 NA NA Radiographic Exposure Device IEB 88-07 Power Oscillations in BWRs NA NA IEB 88-07s1 Power Oscillations in BWRs NA NA Implement program to prevent thermal IEB 88-08 Thermal Stresses in Piping Connected to Reactor Cooling Systems CI CI stratification Implement program to prevent thermal IEB 88-08s1 Thermal Stresses in Piping Connected to Reactor Cooling Systems CI CI stratification Implement program to prevent thermal IEB 88-08s2 Thermal Stresses in Piping Connected to Reactor Cooling Systems CI CI stratification Implement program to prevent thermal IEB 88-08s3 Thermal Stresses in Piping Connected to Reactor Cooling Systems CI CI stratification TVA letter 03/11/1994 commitment to establish IEB 88-09 Thimble Tube Thinning in Westinghouse Reactors CI CI program and inspect thimble tubes Replace circuits not traceable to a circuit IEB 88-10 Nonconforming Molded-Case Circuit Breakers CI CI breaker manufacturer Replace circuits not traceable to a circuit IEB 88-10s1 Nonconforming Molded-Case Circuit Breakers CI CI breaker manufacturer NRC reviewed in SSER16 App EE. Complete IEB 88-11 Pressurizer Surge Line Thermal Stratification CI CI mods to accommodate surge line IEB 89-01 Failure of Westinghouse Steam Generator Tube Mechanical Plugs CI CI NRC letter 09/26/1991-Remove SG tube plugs IEB 89-01s1 Failure of Westinghouse Steam Generator Tube Mechanical Plugs CI CI NRC letter 09/26/1991-Remove SG tube plugs IEB 89-01s2 Failure of Westinghouse Steam Generator Tube Mechanical Plugs CI CI NRC letter 09/26/1991-Remove SG tube plugs Stress Corrosion Cracking of High-Hardness Type 410 Stainless IEB 89-02 CI CI NRC reviewed in App EE of SSER16 Steel Preloaded Bolting ML073371330 in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Nature Potential Loss of Required Shutdown Margin During Refueling IEB 89-03 CI CI IR 390/391 94-04. NRC letter dated 06/22/1990 Operations Implement & Id. Potentially defective IEB 90-01 Loss of Fill-Oil in Transmitters Manufactured by Rosemount CI CI transmitters & enhanced surveillance program Page 10 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Implement & Id. Potentially defective IEB 90-01s1 Loss of Fill-Oil in Transmitters Manufactured by Rosemount CI CI transmitters & enhanced surveillance program IEB 90-02 Loss of Thermal Margin Caused by Channel Box Bow NA NA IEB 91-01 Reporting Loss of Criticality Safety Controls NA NA IEB 91-01s1 Reporting Loss of Criticality Safety Controls NA NA Failure of Thermo-Lag 330 Fire Barrier System to Perform its IEB 92-01 OV OV Specified Fire Endurance Function Failure of Thermo-Lag 330 Fire Barrier System to Perform its IEB 92-01s1 OV OV Specified Fire Endurance Function Safety Concerns Related to "End of Life" of Aging Theratronics IEB 92-02 NA NA Teletherapy Units IEB 92-03 Release of Patients After Brachytherapy NA NA Release of Patients After Brachytherapy Treatment with Remote IEB 93-01 NA NA Afterloading Devices IEB 93-02 Debris Plugging of Emergency Core Cooling Suction Strainers NA NA ML072690589 IEB 93-02s1 Debris Plugging of Emergency Core Cooling Suction Strainers NA NA Resolution of Issues Related to Reactor Vessel Water Level IEB 93-03 NA NA Instrumentation in BWRs Potential Fuel Pool Draindown Caused by Inadequate Maintenance IEB 94-01 NA NA Practices at Dresden Corrosion Problems in Certain Stainless Steel Packaging's Used to IEB 94-02 NA NA Transport Uranium Hexaflouride Quality Assurance Program for Transportation of Radioactive IEB 95-01 NA NA Material Unexpected Clogging of a Residual Heat Removal Pump Strainer IEB 95-02 NA NA While Operating in Suppression Pool Cooling Mode IEB 96-01 Control Rod Insertion Problems (PWR) OV OV Movement of Heavy Loads over Spent Fuel, over Fuel in the IEB 96-02 CI CI NRC letter 05/20/1998 Reactor, or over Safety-Related Equipment IEB 96-03 Potential Plugging of ECCS Suction Strainers by Debris in BWRs NA NA Chemical, Galvanic, or Other Reactions in Spent Fuel Storage and IEB 96-04 NA NA Transportation Casks Potential for Erroneous Calibration, Dose Rate, or Radiation IEB 97-01 NA NA Exposure Measurements with Certain Victoreen Model 530 and 531SI Electrometers, Dose Meters IEB 97-02 Puncture Testing of Shipping Packages Under 10 CFR Part 71 NA NA Page 11 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Circumferential Cracking of Reactor Pressure Vessel (RPV) Head IEB 01-01 OV OV Penetration Nozzles RPV Head Degradation and Reactor Coolant Pressure Boundary IEB 02-01 OV OV Integrity RPV Head and Vessel Head Penetration Nozzle Inspection IEB 02-02 OV OV Program Potential Impact of Debris Blockage on Emergency Sump IEB 03-01 NA NA TVA: Letter dated September 7, 2007 Recirculation ML0725706761 Leakage from RPV Lower Head Penetrations and Reactor Coolant IEB 03-02 OV OV Pressure Boundary Integrity Potentially Deficient 1-inch Valves for Uranium Hexaflouride IEB 03-03 NA NA Cylinders Rebaselining of Data in the Nuclear Management and Safeguards IEB 03-04 C C NRC letter dated 12/18/2003 System Inspection of Alloy 82/182/600 Materials Used in the Fabrication of IEB 04-01 OV OV Pressurizer Penetrations and Steam Space Piping Connections at PWRs Material Control and Accounting of Reactors and Spent Fuel TVA letter dated 03/21/2005 and 05/11/2005.

IEB 05-01 C C Storage Facilities NRC letter dated 11/30/2005 ML052560158 Emergency Preparedness and Response Actions for Security IEB 05-02 C C TVA letters dated 01/20/2006 & 08/16/2006 Based Events IEB 07-01 Security Officer Attentiveness OV OV cr76001 Crane Hoist Control Circuit Modifications C C Compliance achieved 12/12/1976- IR 50/391/76-cr76002 Relay Failures - Westinghouse BF (ac) and BFD (dc) Relays C C 11 ML071760483 cr76003 Radiation Exposures in Reactor Cavities NA NA cr76004 Neutron Monitor and Flow Bypass Switch Malfunctions NA NA Hydraulic Shock and Sway Suppressors - Maintenance of Bleed cr76005 C C TVA letter 01/07/1977 and Lock-up Velocities on ITT Grinnell Models...

Stress Corrosion Cracks in Stagnant, Low Pressure Stainless cr76006 NA NA Piping Containing Boric Acid Solution at PWRs Inadequate Performance by Reactor Operating and Support Staff cr76007 NA NA Members cr77001 Malfunctions of Limitorque Valve Operators NA NA cr77002 Potential Heavy Spring Flooding (OL) NA NA cr77002a Potential Heavy Spring Flooding (CP) NA NA cr77003 Fire Inside a Motor Control Center NA NA cr77004 Inadequate Lock Assemblies NA NA cr77005 Fluid Entrapment in Valve Bonnets NA NA Page 12 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number cr77006 Effects of Hydraulic Fluid on Electrical Cables NA NA cr77007 Short Period During Reactor Startup NA NA cr77008 Failure of Feedwater Sample Probe NA NA Improper Fuse Coordination in BWR Standby Liquid Control System cr77009 NA NA Control Circuits cr77010 Vacuum Conditions Resulting in Damage to Liquid Process Tanks NA NA cr77011 Leakage of Containment Isolation Valves with Resilient Seats NA NA cr77012 Dropped Fuel Assemblies at BWR Facilities NA NA cr77013 Reactor Safety Signals Negated During Testing NA NA Separation of Contaminated Water Systems from Noncontaminated cr77014 NA NA Plant Systems cr77015 Degradation of Fuel Oil Flow to the Emergency Diesel Generator NA NA cr77016 Emergency Diesel Generator Electrical Trip Lock-Out Features NA NA cr78001 Loss of Well Logging Source NA NA cr78002 Proper Lubricating Oil for Terry Turbines NA NA Packaging Greater than Type A Quantities of Low Specific Activity cr78003 NA NA Radioactive Material for Transport cr78004 Installation Errors That Could Prevent Closing of Fire Doors NA NA cr78005 Inadvertent Safety Injection During Cooldown NA NA Potential Common Mode Flooding of ECCS Equipment Rooms at cr78006 NA NA BWR Facilities Damaged Components of a Bergen-Paterson Series 25000 cr78007 NA NA Hydraulic Test Stand Environmental Qualification of Safety-Related Electrical Equipment cr78008 NA NA at Nuclear Power Plants cr78009 Arcing of General Electric Company Size 2 Contactors NA NA cr78010 Control of Sealed Sources in Radiation Therapy NA NA cr78011 Recirculation MG Set Overspeed Stops NA NA cr78012 HPCI Turbine Control Valve Lift Rod Bending NA NA cr78013 Inoperability of Service Water Pumps NA NA cr78014 HPCI Turbine Reversing Chamber Hold Down Bolting NA NA Tilting Disc Check Valves Fail to Close with Gravity in Vertical cr78015 NA NA Position cr78016 Limitorque Valve Actuators NA NA Inadequate Guard Training/Qualification and Falsified Training cr78017 NA NA Records cr78018 UL Fire Test NA NA Page 13 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number cr78019 Manual Override (Bypass) of Safety System Actuation Signals NA NA cr79001 Administration of Unauthorized Byproduct Material to Humans NA NA cr79002 Failure of 120 Volt Vital AC Power Supplies NA NA Inadequate Guard Training-Qualification and Falsified Training cr79003 NA NA Records cr79004 Loose Locking Nut on Limitorque Valve Operators NA NA cr79005 Moisture Leakage in Stranded Wire Conductors NA NA cr79006 Failure to Use Syringe and Bottle Shields in Nuclear Medicine NA NA Unexpected Speed Increase of Reactor Recirculation MG Set cr79007 NA NA Resulted in Reactor Power Increase cr79008 Attempted Extortion - Low Enriched Uranium NA NA Occurrences of Split or Punctured Regulator Diaphragms in Certain cr79009 NA NA Self Contained Breathing Apparatus cr79010 Pipefittings Manufactured from Unacceptable Material NA NA cr79011 Design/Construction Interface Problem NA NA cr79012 Potential Diesel Generator Turbocharger Problem NA NA cr79013 Replacement of Diesel Fire Pump Starting Contactors NA NA cr79014 Unauthorized Procurement and Distribution of XE-133 NA NA Bursting of High Pressure Hose and Malfunction of Relief Valve O-cr79015 NA NA Ring in Certain Self-Contained Breathing Apparatus Excessive Radiation Exposures to Members of the General Public cr79016 NA NA and a Radiographer Contact Problem in SB-12 Switches on General Electric Company cr79017 NA NA Metalclad Circuit Breakers cr79018 Proper Installation of Target Rock Safety-Relief Valves NA NA cr79019 Loose Locking Devices on Ingersoll-Rand Pumps NA NA Failure of GTE Sylvania Relay Type PM Bulletin 7305 Catalog 5U12 cr79020 NA NA 11-AC with a 120V AC Coil cr79021 Prevention of Unplanned Releases of Radioactivity NA NA cr79022 Stroke Times for Power Operated Relief Valves NA NA N.R.R But defective shipment was received and cr79023 Motor Starters and Contactors Failed to Operate NA A-O should be addressed Proper Installation and Calibration of Core Spray Pipe Break cr79024 NA NA Detection Equipment on BWRs N.R.R but inspections & C.A expected on behalf cr79025 Shock Arrestor Strut Assembly Interference NA A-O of WBN 2 cr80001 Service Advice for GE Induction Disc Relays NA NA cr80002 Nuclear Power Plant Staff Work Hours NA NA cr80003 Protection from Toxic Gas Hazards NA NA Page 14 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Securing of Threaded Locking Devices on Safety-Related cr80004 NA NA Equipment Emergency Diesel-Generator Lubricating Oil Addition and Onsite cr80005 NA NA Supply cr80006 Control and Accountability Systems for Implant Therapy Sources NA NA cr80007 Problems with HPCI Turbine Oil System NA NA cr80008 BWR Technical Specification Inconsistency - RPS Response Time NA NA cr80009 Problems with Plant Internal Communications Systems NA NA cr80010 Failure to Maintain Environmental Qualification of Equipment NA NA cr80011 Emergency Diesel Generator Lube Oil Cooler Failures NA NA Valve-Shaft-to-Actuator Key May Fall Out of Place when Mounted cr80012 NA NA Below Horizontal Axis cr80013 Grid Strap Damage in Westinghouse Fuel Assemblies NA NA Radioactive Contamination of Plant Demineralized Water System cr80014 NA NA and Resultant Internal Contamination of Personnel Loss of Reactor Coolant Pump Cooling and Natural Circulation cr80015 NA NA Cooldown Operational Deficiencies in Rosemount Model 510DU Trip Units and cr80016 NA NA Model 1152 Pressure Transmitters cr80017 Fuel Pin Damage Due to Water Jet from Baffle Plate Corner NA NA 10 CFR 50.59 Safety Evaluations for Changes to Radioactive cr80018 NA NA Waste Treatment Systems cr80019 Noncompliance with License Requirements for Medical Licensees NA NA cr80020 Changes in Safe-Slab Tank Dimensions NA NA cr80021 Regulation of Refueling Crews - NA NA cr80022 Confirmation of Employee Qualifications NA NA cr80023 Potential Defects in Beloit Power Systems Emergency Generators NA NA cr80024 AECL Teletherapy Unit Malfunction NA NA cr80025 Case Histories of Radiography Events NA NA Design Problems Involving Indicating Pushbutton Switches cr81001 NA NA Manufactured by Honeywell Incorporated cr81002 Performance of NRC-Licensed Individuals while on Duty NA NA cr81003 Inoperable Seismic Monitoring Instrumentation NA NA The Role of Shift Technical Advisors and Importance of Reporting cr81004 NA NA Operational Events Page 15 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number cr81005 Self-Aligning Rod End Bushings for Pipe Supports NA NA Potential Deficiency Affecting Certain Foxboro 10 to 50 Milliampere cr81006 NA NA Transmitters cr81007 Control of Radioactively Contaminated Material NA NA cr81008 Foundation Materials NA NA cr81009 Containment Effluent Water that Bypasses Radioactivity Monitor NA NA Steam Voiding in the Reactor Coolant System During Decay Heat cr81010 NA NA Removal Cooldown cr81011 Inadequate Decay Heat Removal During Reactor Shutdown NA NA Inadequate Periodic Test Procedure of PWR Reactor Protection cr81012 NA NA System Torque Switch Electrical Bypass Circuit for Safeguard Service Valve Report required if discrepancies found. Clarify if cr81013 NA A-O Motors discrepancies were found.

cr81014 Main Steam Isolation Valve Failures to Close NA NA Unnecessary Radiation Exposures to the Public and Workers cr81015 NA NA During Events Involving Thickness and Level Measuring Devices GL 77-01 Intrusion Detection Systems Handbook NA NA GL 77-02 Fire Protection Functional Responsibilities NA NA Transmittal of NUREG-0321, "A Study of the Nuclear Regulatory GL 77-03 NA NA GL states no copies of NUREG found Commission Quality Assurance Program" Shipments of Contaminated Components From NRC Licensed GL 77-04 NA NA Nuclear Power Facilities to Vendors and Service Companies Nonconformity of Addresses of Items Directed to the Office of GL 77-05 NA NA Nuclear Reactor Regulation GL 77-06 Questionnaire Related to Steam Generators NA NA GL 77-07 Reliability of Standby Diesel Generator Units NA NA Revised Intrusion detection handbook and Entry Control Systems GL 77-08 NA NA Handbook GL 78-01 Correction To Letter Of 12/15/77 NA NA Asymmetric Loads Background and Revised Request for Additional Reviewed in SSER15-App C. Resolved by GL 78-02 C C Information approval of leak-before-break analysis GL 78-03 Request for Information on Cavity Annulus Seal Ring NA NA GL 78-04 Steam Generator Operating History NA NA Internal Distribution Of Correspondence - Asking For Comments On GL 78-05 NA NA Mass Mailing System GL 78-06 This Generic Letter Was Never Issued NA NA GL 78-07 This Generic Letter Was Never Issued NA NA Page 16 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Enclosing NUREG-0408 RE Mark I Containments, And Granting GL 78-08 NA NA Exemption From GDC 50 And Enclosing Sample Notice Multiple Subsequent Actuations of Safety Relief Valves Following GL 78-09 NA NA an Isolated Event GL 78-10 Guidance On Radiological Environmental Monitoring NA NA GL 78-11 Guidance on Spent Fuel Pool Modifications NA NA Notice Of Meeting Regarding "Implementation of 10 CFR 73.55 GL 78-12 NA NA Requirements And Status Of Research..."

GL 78-13 Forwarding of NUREG-0219 NA NA GL 78-14 Transmittal Of Draft NUREG-0219 For Comment NA NA GL 78-15 Request for Information on Control of Heavy Loads Near Spent Fuel NA NA Request For Information On Control Of Heavy Loads Near Spent GL 78-16 NA NA Fuel Pools GL 78-17 Corrected Letter On Heavy Loads Over Spent Fuel NA NA GL 78-18 Corrected Letter On Heavy Loads Over Spent Fuel NA NA Enclosing Sandia Report SAND 77-0777, "Barrier Technology GL 78-19 NA NA Handbook" Enclosing - "A Systematic Approach To The Conceptual Design Of GL 78-20 NA NA Physical Protection Systems For Nuclear Facilities" Transmitting NUREG/CR-0181 Concerning Barrier & Penetration GL 78-21 NA NA Data Needed For Physical Security System Assessment Revision To Intrusion Detection Systems And Entry Control GL 78-22 NA NA Handbooks And Nuclear Safeguards Technology Handbook GL 78-23 Manpower Requirements For Operating Reactors NA NA Model Appendix I Technical Specifications And Submittal Schedule GL 78-24 NA NA For BWRs GL 78-25 This Generic Letter Was Never Issued NA NA GL 78-26 Excessive Control Rod Guide Tube Wear NA NA GL 78-27 Forwarding of NUREG-0181 NA NA GL 78-28 Forwarding pages omitted from 07/11/78 letter NA NA GL 78-29 Notice of PWR steam generator conference NA NA GL 78-30 Forwarding of NUREG-0219 NA NA GL 78-31 Notice of Steam Generator Conference Agenda NA NA GL 78-32 Reactor Protection System Power Supplies NA NA GL 78-33 Meeting Schedule And Locations For Upgraded Guard Qualification NA NA Page 17 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number TVA Westinghouse letter dated 10/29/1979-IR GL 78-34 Reactor Vessel Atypical Weld Material C C 390/391 81-04 GL 78-35 Regional Meetings To Discuss Upgraded Guard Qualifications NA NA Cessation of Plutonium Shipments By Air Except In NRC Approved GL 78-36 NA NA Containers Revised Meeting Schedule & Locations For Upgraded Guard GL 78-37 NA NA Qualifications Forwarding Of 2 Tables Of Appendix I, Draft Radiological Effluent GL 78-38 NA NA Technical Specifications, PWR, and NUREG-0133 Forwarding of 2 Tables of Appendix I, Draft Radiological Effluent GL 78-39 NA NA Technical Specifications, BWR, And NUREG-0133 GL 78-40 Training & Qualification Program Workshops NA NA GL 78-41 Mark II Generic Acceptance Criteria For Lead Plants NA NA GL 78-42 Training and Qualification Program Workshops NA NA Interservice Procedures for Instructional Systems Development -

GL 79-01 NA NA TRADOC Transmitting Rev. to Entry Control Systems Handbook (SAND 77-GL 79-02 NA NA 1033), Intrusion Detection Handbook (SAND 76-0554),

and Barrier Penetration Database GL 79-03 Offsite Dose Calculation Manual NA NA Referencing 4/14/78 Letter - Modifications to NRC Guidance GL 79-04 NA NA "Review and Acceptance of Spent Fuel Pool Storage and Handling" Information Relating to Categorization of Recent Regulatory Guides GL 79-05 NA NA by the Regulatory Requirements Review Committee GL 79-06 Contents of the Offsite Dose Calculation Manual NA NA GL 79-07 Seismic (SSE) and LOCA Responses (NUREG-0484) NA NA No copies of GL are available GL 79-08 Amendment to 10 CFR 73.55 NA NA Staff Evaluation of Interim Multiple-Consecutive Safety-Relief Valve GL 79-09 NA NA Actuations GL 79-10 Transmitting Regulatory Guide 2.6 for Comment NA NA Transmitting "Summary of Operating Experience with Recalculating GL 79-11 NA NA Steam Generators, January 1979" NUREG-0523 GL 79-12 ATWS - Enclosing Letter to GE, with NUREG-0460, Vol. 3 NA NA Schedule for Implementation and Resolution of Mark I Containment GL 79-13 NA NA Long Term Program GL 79-14 Pipe Crack Study Group - Enclosing NUREG-0531 and Notice NA NA Page 18 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Steam Generators-Enclosing Summary of Operating Experience GL 79-15 NA NA with Recirculating Steam Generators, NUREG-0523 GL 79-16 Meeting Re Implementation Of Physical Security Requirements NA NA GL 79-17 Reliability of Onsite Diesel Generators at Light Water Reactors NA NA GL 79-18 Westinghouse Two-Loop NSSS NA NA GL 79-19 NRC Staff Review of Responses to I&E Bulletins 79-06 and 79-06a NA NA GL 79-20 Cracking in Feedwater Lines C C Enclosing NUREG/CR 0660, "Enhancement of on Site Emergency GL 79-21 NA NA Diesel Generator Reliability" Enclosing NUREG-0560, "Staff Report on the Generic Assessment GL 79-22 NA NA of Feedwater Transients in PWRs Designed by B&W GL 79-23 NRC Staff Review of Responses to I&E Bulletin 79-08 NA NA Applies to ALL PWR's. Requests submittal of GL 79-24 Multiple Equipment Failures in Safety-Related Systems NA A-O reports GL 79-25 Information Required to Review Corporate Capabilities NA NA GL 79-26 Upgraded Standard Technical Specification Bases Program NA NA GL 79-27 Operability Testing of Relief and Safety Relief Valves NA NA GL 79-28 Evaluation of Semi-Scale Small Break Experiment NA NA Transmitting NUREG-0473, Revision 2, Draft Radiological Effluent GL 79-29 NA NA Technical Specifications Transmitting NUREG-0472, Revision 2, Draft Radiological Technical GL 79-30 NA NA Specifications GL 79-31 Submittal of Copies of Response to 6/29/79 NRC Request NA NA GL 79-32 Transmitting NUREG-0578, "TMI-2 Lessons Learned" NA NA Transmitting NUREG-0576 - Security Training and Qualification GL 79-33 NA NA Plans GL 79-34 New Physical Security Plans (FR 43280-285) NA NA GL 79-35 Regional Meetings to Discuss Impacts on Emergency Planning NA NA GL compliance w/ BTP PSB-1, "Adequacy of GL 79-36 Adequacy of Station Electric Distribution Systems Voltages CI CI Station Electric Distribution System GL 79-37 Amendment to 10 CFR 73.55 Deferral from 8/1/79 to 11/1/79 NA NA GL 79-38 BWR Off-Gas Systems - Enclosing NUREG/CR-0727 NA NA Transmitting Division 5 Draft Regulatory Guide and Value Impact GL 79-39 NA NA Statement Follow-up Actions Resulting from the NRC Staff Reviews Regarding GL 79-40 NA NA the TMI-2 Accident Page 19 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number GL 79-41 Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard NA NA Potentially Unreviewed Safety Question on Interaction Between GL 79-42 NA NA Non-Safety Grade Systems and Safety Grade Systems GL 79-43 Reactor Cavity Seal Ring Generic Issue NA NA GL 79-44 Referencing 6/29/79 Letter Re Multiple Equipment Failures NA NA Transmittal of Reports Regarding Foreign Reactor Operating GL 79-45 NA NA Experiences GL 79-46 Containment Purge and Venting During Normal Operation NA NA GL 79-47 Radiation Training NA NA Confirmatory Requirements Relating to Condensation Oscillation GL 79-48 NA NA Loads for the Mark I Containment Long Term Program Summary of Meetings Held on 9/18-20/79 to Discuss Potential GL 79-49 NA NA Unreviewed Safety Question on Systems Interaction for B&W Pl GL 79-50 Emergency Plans Submittal Dates NA NA Follow-up Actions Resulting from the NRC Staff Reviews Regarding Applies to all C.P holders and requires GL 79-51 NA A-O the TMI-2 Accident implementation of actions GL 79-52 Radioactive Release at No. Anna Unit 1 and Lessons Learned NA NA GL 79-53 ATWS NA NA GL 79-54 Containment Purging and Venting During Normal Operation NA NA Summary of Meeting Held on October 12, 1979 to Discuss GL 79-55 NA NA Responses to IE Bulletins79-05C and 79-06C and HPI Termination Criteria GL 79-56 Discussion of Lessons Learned Short Term Requirements NA NA GL 79-57 Acceptance Criteria for Mark I Long Term Program NA NA GL 79-58 ECCS Calculations on Fuel Cladding NA NA GL 79-59 GL was never issued. NA NA GL 79-60 Discussion of Lessons Learned Short Term Requirements NA NA GL 79-61 Discussion of Lessons Learned Short Term Requirements NA NA GL 79-62 ECCS Calculations on Fuel Cladding NA NA Check Applicability. Header (yes) content (No).

GL 79-63 Upgraded Emergency Plans NA A-O Request add. Info.

GL 79-64 Suspension of All Operating Licenses NA NA Radiological Environmental Monitoring Program Requirements -

GL 79-65 NA NA Enclosing Branch Technical Position, Revision 1 GL 79-66 Additional Information Re 11/09/79 Letter on ECCS Calculations NA NA Page 20 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Estimates for Evacuation of Various Areas Around Nuclear Power GL 79-67 NA NA Reactors GL 79-68 Audit of Small Break LOCA Guidelines NA NA Cladding Rupture, Swelling, and Coolant Blockage as a Result of a GL 79-69 NA NA Reactor Accident GL 79-70 Environmental Monitoring for Direct Radiation NA NA NUREG-0630, "Cladding, swelling and Rupture-Models for LOCA GL 80-01 NA NA Analysis" GL 80-02 QA Requirements Regarding Diesel Generator Fuel Oil C C FSAR Section 9.5.4.2. Verified through review.

GL 80-03 BWR Control Rod Failures NA NA GL 80-04 IEB 80-01 Operability Of ADS Valve Pneumatic Supply NA NA GL 80-05 IEB 79-01b Environmental Qualification Of Class 1E Equipment NA NA Issuance Of NUREG-0313, Rev 1, "Technical Report On Material GL 80-06 NA NA Selection And Processing Guidelines For BWR Coolant Pressure Information Regarding The Program For Environmental GL 80-07 NA NA Qualification Of Safety-Related Electrical Equipment IEB 80-02 Inadequate Quality Assurance For Nuclear Supplied GL 80-08 NA NA Equipment GL 80-09 Low Level Radioactive Waste Disposal NA NA Issuance Of NUREG-0588, "Interim Staff Position On Equipment GL 80-10 NA NA Qualifications Of Safety-Related Electrical Equipment IEB 80-03 Loss Of Charcoal From Standard Type II, 2 Inch, Tray GL 80-11 NA A-O Requires action on behalf of C.P holder Absorber Cells IEB 80-04 Analysis Of A PWR Main Steam Sine Break With GL 80-12 NA NA Continued Feedwater Addition GL 80-13 Qualification Of Safety Related Electrical Equipment NA NA GL 80-14 LWR Primary Coolant System Pressure Isolation Valves CT CT NRC reviewed in 1.14.2 of SSER 6 Request For Additional Management And Technical Resources GL 80-15 NA NA Information GL 80-16 IEB 79-01b Environmental Qualification Of Class 1E Equipment NA NA GL 80-17 Modifications To Boiling Water Reactor Control Rod Drive Systems NA NA GL 80-18 Crystal River 3 Reactor Trip From Approximately 100% Full Power NA NA GL 80-19 Resolution Of Enhanced Fission Gas Release Concern NA NA Page 21 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Actions Req.. From OL Applicants Of NSSS Designs By W and CE GL 80-20 NA NA Resulting From NRC B&O Task Force Review Of TMI2 Accident Vacuum Condition Resulting in Damage to Chemical Volume Complete surveillance procedures for Unit 2. IR GL 80-21 CI CI Control System Holdup Tanks 50/391/84-45 Transmittal Of NUREG-0654 "Criteria For Preparation And GL 80-22 NA NA Evaluation Of Radiological Emergency Response Plans And GL 80-23 Change Of Submittal Date For Evaluation Time Estimates NA NA Transmittal Of Information On NRC "Nuclear Data Link GL 80-24 NA NA Specifications" GL 80-25 IEB 80-06 Engineering Safety Feature (ESF) Reset Controls NA NA GL 80-26 Qualifications Of Reactor Operators NA NA GL 80-27 IEB 80-07 BWR Jet Pump Assembly Failure NA NA Info expected to be submitted 90 days after GL 80-28 IEB 80-08 Examination Of Containment Liner Penetration Welds NA A-O issuance GL 80-29 Modifications To Boiling Water Reactor Control Rod Drive Systems NA NA Clarification Of The Term "Operable" As It Applies To Single Failure GL 80-30 NA NA Criterion For Safety Systems Required By TS GL 80-31 IEB 80-09 Hydramotor Actuator Deficiencies NA NA Information Request on Category I Masonry Walls Employed by GL 80-32 NA A-O B80-11 requests actions from all C.P facilities Plants Under CP and OL Review Actions Req. From OL Applicants Of B&W Designed NSSS GL 80-33 NA NA Resulting From NRC B&O Task Force Review Of TMI2 Accident Clarification of NRC Requirements for Emergency Response GL 80-34 NA NA Facilities at Each Site GL 80-35 Effect Of A DC Power Supply Failure On ECCS Performances NA NA IEB 80-10 Contamination Of Non-Radioactive System And GL 80-36 Resulting Potential For Unmonitored, Uncontrolled Release To NA NA Envir GL 80-37 Five Additional TMI-2 Related Requirements To Operating Reactors NA NA Summary of Certain Non-Power Reactor Physical Protection GL 80-38 NA NA Requirements GL 80-39 IEB 80-11 Masonry Wall Design NA NA Page 22 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Transmittal Of NUREG-0654 "Report Of The B&O Task Force "

GL 80-40 NA NA Appropriate NUREG-0626 "Generic Eval Of FW Transient And Sbl Summary Of Meetings Held On April 22 &23, 1980 With GL 80-41 NA NA Representatives Of The Mark I Owners Group GL 80-42 IEB 80-12 Decay Heat Removal System Operability NA NA GL 80-43 IEB 80-13 Cracking In Core Spray Spargers NA NA GL 80-44 Reorganization Of Functions And Assignments Within ONRR/SSPB NA NA GL 80-45 Fire Protection Rule NA NA A-12, Fracture Toughness and Additional Guidance on Potential for N.R.R.-NUREG-0577 states laminar issue was GL 80-46 C C Low Fracture Toughness and Laminar Tearing on resolved.

PWR Steam Generator Coolant Pump Supports Additional Guidance On "Potential For Low Fracture Toughness N.R.R.-NUREG-0577 states laminar issue was GL 80-47 C C And Laminar Tearing On PWR SG Reactor Coolant Pump Suprts resolved.

GL 80-48 Revision To 5/19/80 Letter On Fire Protection NA NA GL 80-49 Nuclear Safeguards Problems NA NA GL 80-50 Generic Activity A-10 BWR Cracks NA NA GL 80-51 On-Site Storage Of Low-Level Waste NA NA Five Additional TMI-2 Related Requirements - Erata Sheets To GL 80-52 NA NA 5/7/80 Letter GL 80-53 Decay Heat Removal Capability NA NA GL 80-54 IEB 80-14 Degradation Of Scram Discharge Volume Capability NA NA GL 80-55 IEB 80-15 Possible Loss Of Hotline With Loss Of Off-Site Power NA NA GL 80-56 Commission Memorandum And Order On Equipment Qualification NA NA Further Commission Guidance For Power Reactor Operating GL 80-57 NA NA Licenses NUREG-0660 And NUREG-0694 IEB 80-16 Potential Misapplication Of Rosemount Inc. Models GL 80-58 NA NA 1151/1152 Pressure Transmitters With "A" Or "D" Output Codes Transmittal Of Federal Register Notice RE Regional Meetings To GL 80-59 NA NA Discuss Environmental Qualification Of Elec. Equipment GL 80-60 Request for Information Regarding Evaluation Times NA NA GL 80-61 TMI-2 Lessons Learned NA NA GL 80-62 TMI-2 Lessons Learned NA NA Page 23 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number IEB 80-17 Failure Of Control Rods To Insert During A Scram At A GL 80-63 NA NA BWR GL 80-64 Scram Discharge Volume Designs NA NA Request For Estimated Construction Completion And Fuel Load GL 80-65 NA NA Schedules IEB 80-17 Supplement 1 Failure Of Control Rods To Insert During A GL 80-66 NA NA Scram At A BWR GL 80-67 Scram Discharge Volume NA NA IEB 80-17 Supplement 2 Failures Revealed By Testing Subsequent GL 80-68 NA NA To Failure Of Control Rods To Insert During A Scram At A IEB 80-18 Maintenance Of Adequate Minimum Flow Through GL 80-69 NA NA Centrifugal Charging Pumps Following Secondary Side Helb IEB 80-19 Failures Of Mercury-Wetted Matrix Relays In RPS Of GL 80-70 NA NA Operating Nuclear Power Plants Designed By GE IEB 80-20 Failures Of Westinghouse Type W-2 Spring Return To GL 80-71 NA NA Neutral Control Switches GL 80-72 Interim Criteria For Shift Staffing NA NA Functional Criteria For Emergency Response Facilities", NUREG-GL 80-73 NA NA 0696 Notice Of Forthcoming Meeting With Representatives Of EPRI To GL 80-74 NA NA Discuss Program For Resolution Of USI A-12, Fracture Tough GL 80-75 Lessons Learned Tech Specs NA NA Notice Of Forthcoming Meeting With GE To Discussed Proposed GL 80-76 NA NA BWR Feedwater Nozzle Leakage Detection System GL 80-77 Refueling Water Level - Technical Specifications Changes CT CT Address in Tech Specs as appropriate.

GL 80-78 Mark I Containment Long-Term Program NA NA IEB 80-17 Supplement 3 Failures Revealed By Testing Subsequent GL 80-79 NA NA To Failure Of Control Rods To Insert During A Scram At A GL 80-80 Preliminary Clarification Of TMI Action Plan Requirements NA NA Preliminary Clarification Of TMI Action Plan Requirements -

GL 80-81 NA NA Addendum To 9/5/80 Letter IEB 79-01b Supplement 2 Environmental Qualification Of Class 1E GL 80-82 NA NA Equipment GL 80-83 Environmental Qualification Of Safety-Related Equipment NA NA GL 80-84 BWR Scram System NA NA Page 24 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Implementation Of Guidance From USI A-12 "Potential For LOW GL 80-85 NA NA Fracture Toughness And Lamellar Tearing On Component Support GL 80-86 Notice Of Meeting To Discuss Final Resolution Of USI A-12 NA NA Notice Of Meeting To Discuss Status Of EPRI-Proposed Resolution GL 80-87 NA NA Of The USI A-12 Fracture Toughness Issue GL 80-88 Seismic Qualification Of Auxiliary Feedwater Systems NA NA IEB 79-01b Supplement 3 Environmental Qualification Of Class 1E GL 80-89 NA NA Equipment NUREG-0737, TMI (Prior and future GLs, with the exception of GL 80-90 CI CI certain discrete scopes, have been screened into NUREG list for those applicable to Watts Bar 2)

GL 80-91 Odyn Code Calculation NA NA IEB 80-21 Valve Yokes Supplied By Malcolm Foundry Company, GL 80-92 NA A-O Report was to be submitted within 60 days Inc.

GL 80-93 Emergency Preparedness NA NA GL 80-94 Emergency Plan NA NA A-10, NUREG-0619, "BWR Feedwater Nozzle and Control Rod GL 80-95 NA NA Drive Return Line Cracking" GL 80-96 Fire Protection NA NA IEB 80-23 Failures Of Solenoid Valves Manufactured By Valcor GL 80-97 NA NA Engineering Corporation IEB 80-24 Prevention Of Damage Due To Water Leakage Inside GL 80-98 NA NA Containment GL 80-99 Technical Specification Revisions For Snubber Surveillance NA NA Appendix R to 10 CFR 50 Regarding Fire Protection-Federal GL 80-100 NA NA Register Notice GL 80-101 Inservice Inspection Programs NA NA Commission Memorandum And Order Of May 23, 1980 GL 80-102 NA NA (Referencing IEB 79-01b Supplement 2 - q.2 & 3 - Sept 30, 1980)

GL 80-103 Fire Protection - Revised Federal Register Notice NA NA Orders On Environmental Qualification Of Safety Related Electrical GL 80-104 NA NA Equipment Implementation Of Guidance For USI A-12, Potential For Low GL 80-105 NA NA Fracture Toughness And Lamellar Tearing On Component Supports GL 80-106 Report On ECCS Cladding Models, NUREG-0630 NA NA GL 80-107 BWR Scram Discharge System NA NA Page 25 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number GL 80-108 Emergency Planning NA NA Guidelines For Systematic Evaluation Program Soil Structure GL 80-109 NA NA Interaction Reviews GL 80-110 Periodic Updating Of FSARS NA NA IEB 80-17 Supplement 4, Failure Of Control Rods To Insert During GL 80-111 NA NA A Scram At A BWR IEB 80-25 Operating Problems With Target Rock Safety Relief GL 80-112 NA NA Valves GL 80-113 Control of Heavy Loads C C Superseded by GL 81-007 Qualification of Inspection, Examination, Testing and Audit GL 81-01 NA NA Personnel Analysis, Conclusions and Recommendations Concerning Operator GL 81-02 NA NA Licensing NUREG-0313, Technical Report on Material Selection and GL 81-03 NA NA Processing Guidelines for BWR Coolant Pressure Boundary Piping GL 81-04 Emergency Procedures and Training for Station Blackout C C Superseded by Station Blackout Rule Information Regarding The Program For Environmental GL 81-05 NA NA Qualification Of Safety-Related Electrical Equipment GL 81-06 Periodic Updating of Final Safety Analysis Reports (FSARS) NA NA Unit 2 Heavy Loads program will be in GL 81-07 Control of Heavy Loads CI CI compliance with NUREG-0612 GL 81-08 Odyn Code NA NA GL 81-09 BWR Scram Discharge System NA NA GL 81-10 Post-TMI Requirements For The Emergency Operations Facility NA NA BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle GL 81-11 NA NA Cracking (NUREG-0619)

GL 81-12 Fire Protection Rule (and prior related GLs) NA NA SER For GEXL Correlation For 8X8R Fuel Reload Applications For GL 81-13 NA NA Appendix D Submittals of The GE Topical Report GL 81-14 Seismic Qualification of Auxiliary Feedwater Systems CI CI TVA: FSAR 10.4.9 Environmental Qualification of Class 1E Electrical Equipment-GL 81-15 NA NA Clarification of Staffs Handling of Proprietary Information NUREG-0737 Item I.C.1 SER on Abnormal Transient Operating GL 81-16 NA NA Guidelines (ATOG)

GL 81-17 Functional Criteria for Emergency Response Facilities NA NA BWR Scram Discharge System-Clarification of Diverse GL 81-18 NA NA Instrumentation Requirements Page 26 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number GL 81-19 Thermal Shock to Reactor Pressure Vessels NA NA Safety Concerns Associated With Pipe Breaks in the BWR Scram GL 81-20 NA NA System TVA responded 12/03/1981- Unit 2 action: Issue GL 81-21 Natural Circulation Cooldown CI CI operating procedures Engineering Evaluation of The H.B. Robinson Reactor Coolant GL 81-22 NA NA System Leak on 1/29/81 GL 81-23 INPO Plant Specific Evaluation Reports NA NA GL 81-24 Multi-Plant Issue B-56 Control Rods Fail To Fully Insert NA NA Change in Implementing Schedule For Submission and Evaluation GL 81-25 NA NA of Upgraded Emergency Plans Licensing Requirements for Pending Construction Permit and GL 81-26 NA NA Manufacturing License Applications GL 81-27 Privacy and Proprietary Material in Emergency Plans NA NA GL 81-28 Steam Generator Overfill NA NA GL 81-29 Simulator Examinations NA NA Safety Concerns Associated With Pipe Breaks in the BWR Scram GL 81-30 NA NA System Small Break LOCA Confirmatory Integral Systems Experiments for GL 81-31 NA NA B&W Designed Plants NUREG-0737, Item II.K.3.44-Evaluation of Anticipated Transients GL 81-32 NA NA Combined With Single Failure GL 81-33 Technical Specification for Station Batteries Multiplant Action NA NA Safety Concerns Associated With Pipe Breaks in the BWR Scram GL 81-34 NA NA System Safety Concerns Associated With Pipe Breaks in the BWR Scram GL 81-35 NA NA System Revised Schedule for Completion of TMI Action Plan Item II.D.1, GL 81-36 NA NA Relief and Safety Valve Testing GL 81-37 ODYN Code Reanalysis Requirements NA NA GL 81-38 Storage of Low Level Radioactive Wastes at Power Reactor Sites NA NA GL 81-39 NRC Volume Reduction Policy NA NA GL 81-40 Qualifications of Reactor Operators NA NA GL 82-01 New Applications Survey NA NA GL 82-02 Commission Policy on Overtime NA NA GL 82-03 High Burnup MAPLHGR Limits NA NA GL 82-04 Use of INPO See-in Program NA NA GL 82-05 Post-TMI Requirements NA NA Page 27 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number GL 82-06 NEVER ISSUED NA NA GL 82-07 Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture NA NA GL 82-08 Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture NA NA GL 82-09 Environmental Qualification of Safety Related Electrical Equipment NA NA GL 82-10 Post-TMI Requirements NA NA Transmittal of NUREG-0916 Relative to the Restart of R.E. Ginna GL 82-11 NA NA Nuclear Power Plant GL 82-12 Nuclear Power Plant Staff Working Hours NA NA GL 82-13 Reactor Operator and Senior Reactor Operator Examinations NA NA GL 82-14 Submittal of Documents to the NRC NA NA GL 82-15 NEVER ISSUED NA NA GL 82-16 NUREG-0737 Technical Specifications NA NA GL 82-17 Inconsistency of Requirements Between 50.54(T) and 50.15 NA NA Reactor Operator and Senior Reactor Operator Requalification GL 82-18 NA NA Examinations Submittal of Copies of Documentation to NRC-Copy Requirements GL 82-19 NA NA for Emergency Plans and Physical Security Plans GL 82-20 Guidance for Implementing the Standard Review Plan Rule NA NA GL 82-21 Fire Protection Audits NA NA Congressional Request for Information Concerning Steam GL 82-22 NA NA Generator Tube Integrity Inconsistency Between Requirements of 10CFR 73.40(D) and GL 82-23 Standard Tech Specs For Performing Audits of Safeguards NA NA Contingency Safety Relief Valve Quencher Loads: BWR MARK II and III GL 82-24 NA NA Containments GL 82-25 Integrated IAEA Exercise for Physical Inventory at LWRS NA NA NUREG-0744, REV. 1 - Pressure Vessel Material Fracture GL 82-26 NA NA Toughness Transmittal of NUREG-0763 - Guidelines For Confirmatory In-Plant GL 82-27 NA NA Tests of Safety-Relief Valve Discharge for BWR Plants GL 82-28 Inadequate Core Cooling Instrumentation System O O GL 82-29 This Generic Letter Was Never Issued NA NA GL 82-30 Filings Related to 10 CFR 50 Production and Utilization Facilities NA NA GL 82-31 NEVER ISSUED NA NA GL 82-32 Draft Steam Generator Report (SAI) NA NA Page 28 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Supplement to NUREG-0737, Requirements for Emergency NRC reviewed in SSER5,SSER6 & 18.2.2 of GL 82-33 CI CI Response Capability SSER15. Install SPDS prior start up GL 82-34 NEVER ISSUED NA NA GL 82-35 NEVER ISSUED NA NA GL 82-36 NEVER ISSUED NA NA GL 82-37 NEVER ISSUED NA NA Meeting to Discuss Developments for Operator Licensing GL 82-38 NA NA Examinations Problems With Submittals of Subsequent Information of CURT GL 82-39 NA NA 73.21 For Licensing Reviews GL 83-01 Operator Licensing Examination Site Visit NA NA GL 83-02 NUREG-0737 Technical Specifications NA NA Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel GL 83-03 NA NA Welds During Pre-Service and Inservice Examinations" Regional Workshops Regarding Supplement 1 to NUREG-0737, GL 83-04 NA NA Requirements For Emergency Response Capability Safety Evaluation of "Emergency Procedure Guidelines, Revision GL 83-05 NA NA 2," June 1982 Certificates and Revised Format For Reactor Operator and Senior GL 83-06 NA NA Reactor Operator Licenses GL 83-07 The Nuclear Waste Policy Act of 1982 NA NA GL 83-08 Modification of Vacuum Breakers on Mark I Containments NA NA Review of Combustion Engineering Owners' Group Emergency GL 83-09 NA NA Procedures Guideline Program GL 83-10a Resolution of TMI Action items II.K.3.5 NA NA GL 83-10b Resolution of TMI Action items II.K.3.5 NA NA Automatic Trip of Reactor Coolant Pumps (GL 83-10 a & b: CE, GL NRC letter 06/08/1990-Incorporate emergency GL 83-10c CI CI 83-10 d: W licensees, GL 83-10 e & f: B&W) response guidelines GL 83-10d Resolution of TMI Action items II.K.3.5 NA NA GL 83-10e Resolution of TMI Action items II.K.3.5 NA NA GL 83-10f Resolution of TMI Action items II.K.3.5 NA NA Licensee Qualification for Performing Safety Analyses in Support of GL 83-11 NA NA Licensing Actions Issuance of NRC FORM 398 - Personal Qualifications Statement -

GL 83-12 NA NA Licensee Clarification of Survell. Req's for HEPA Filters and Charcoal GL 83-13 NA NA Absorber Units In STD. Tech Specs on ESF Cleanup Systems Definition of "Key Maintenance Personnel," (Clarification of Generic GL 83-14 NA NA Letter 82-12)

Page 29 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Implement. of Reg. Guide 1.150, "Ultrasonic Testing of RX Vessel GL 83-15 NA NA Welds During Preservice & Inservice Examinations, REV.1 Transmittal of NUREG-0977 Relative to the ATWS Events at Salem GL 83-16 NA NA Generating Station, Unit NO. 1 Transmittal of NUREG-0977 Relative to the ATWS Events at Salem GL 83-16a NA NA Generating Station, Unit NO. 1 Integrity of Requalification Examinations for Renewal of Reactor GL 83-17 NA NA Operator and Senior Reactor Operator Licenses NRC Staff Review of the BWR Owners' Group (BWROG) Control GL 83-18 NA NA Room Survey Program New Procedures for Providing Public Notice Concerning Issuance GL 83-19 NA NA of Amendments To Operating Licenses GL 83-20 Integrated Scheduling for Implementation of Plant Modifications NA NA Clarification of Access Control Procedures for Law Enforcement GL 83-21 NA NA Visits GL 83-22 Safety Evaluation of "Emergency Response Guidelines" NA NA GL 83-23 Safety Evaluation of "Emergency Procedure Guidelines" NA NA TMI Task Action Plan Item I.G.1, "Special Low Power Testing and GL 83-24 NA NA Training," Recommendations for BWRS Issuance of NRC Form 398 Personal Qualifications Statement -

GL 83-25 NA NA Licensee Clarification Of Surveillance Requirements For Diesel Fuel Impurity GL 83-26 NA NA Level Tests GL 83-27 Surveillance Intervals in Standard Technical Specifications NA NA Required Actions Based on Generic Implications of Salem ATWS GL 83-28 Events (Prior and future GLs, with the exception of GL 83-28 certain discrete scopes, have been screened into the following list):

TVA letters dated 11/07/1983 & 12/04/1987. IR ML072500568-GL 83-28 1.2 - Post Trip Review Data and Information Capability C C 391/86-04 ML072750564 2.1 - Equipment Classification and Vendor Interface (Reactor Trip GL 83-28 CI CI NRC letter 10/20/1986 & 06/18/1990 System Components) ML072500568 2.2 - Equipment Classification and Vendor Interface (All SR GL 83-28 CI CI Components)

NRC letter 12/10/1985; 10/27/1986 &

GL 83-28 3.1 - Post-Maintenance Testing (Reactor Trip System Components) CT CT 07/02/1990. IR 391/86-04 ML072610753 NRC letter 12/10/1985; 10/27/1986 &

GL 83-28 3.2 - Post-Maintenance Testing (All SR Components) CT CT 07/02/1990. IR 391/86-04 ML072610753 Page 30 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number GL 83-28 4.1 - Reactor Trip System Reliability (Vendor Related Modifications) CI CI 4.2 - Reactor Trip System Reliability (Preventive Maintenance and GL 83-28 CT CT NRC letters 07/26/1985 and 06/18/1992 Surveillance Program for Reactor Trip Breakers) ML072750564 4.3 - Reactor Trip System Reliability (Automatic Actuation of Shunt TVA letters dated11/07/1983 & 03/22/1985. IR GL 83-28 C C Trip Attachment) 50-391/86-04 ML072750564 4.5 - Reactor Trip System Reliability (Automatic Actuation of Shunt GL 83-28 CT CT NRC letters 06/28/1990 and 10/09/1990 Trip Attachment) ML072610753 GL 83-29 This Generic Communication was not issued NA NA Deletion of STD. Tech Spec Surveillance Requirement 4.8.1.1.2.d.6 GL 83-30 NA NA For Diesel Generator Testing GL 83-31 Safety Evaluation of "Abnormal Transient Operating Guidelines" NA NA NRC Staff Recommendations Regarding Operator Action for GL 83-32 NA NA Reactor Trip and ATWS NRC Positions on Certain Requirements of Appendix R to 10 CFR GL 83-33 NA NA 50 GL 83-34 Important to Safety NA NA GL 83-35 Clarification of TMI Action Plan Item II.K.3.31 NA NA GL 83-36 NUREG-0737 Technical Specifications NA NA GL 83-37 NUREG-0737 Technical Specifications NA NA GL 83-38 NUREG-0965, "NRC Inventory of Dams" NA NA GL 83-39 Voluntary Survey of Licensed Operators NA NA GL 83-40 Operator Licensing Examination NA NA GL 83-41 Fast Cold Starts of Diesel Generators NA NA Clarification to GL 81-07 Regarding Response to NUREG-0612, GL 83-42 NA NA "Control of Heavy Loads at Nuclear Power Plants" Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, GL 83-43 NA NA and Standard Technical Specifications Availability of NUREG-1021, "Operator Licensing Examiner GL 83-44 NA NA Standards" GL 84-01 NRC Use Of The Terms "Important To Safety" and "Safety Related" NA NA GL 84-02 Notice of Meeting Regarding Facility Staffing NA NA Availability of NUREG-0933, "A Prioritization of Generic Safety GL 84-03 NA NA Issues" Safety Evaluation of Westinghouse Topical Reports Dealing with GL 84-04 NA NA Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)

Page 31 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number GL 84-05 Change to NUREG-1021, "Operator Licensing Examiner Standards" NA NA Operator and Senior Operator License Examination Criteria For GL 84-06 NA NA Passing Grade GL 84-07 Procedural Guidance for Pipe Replacement at BWRs NA NA Interim Procedures for NRC Management of Plant-Specific GL 84-08 NA NA Backfitting GL 84-09 Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) NA NA GL 84-10 Administration of Operating Tests Prior to Initial Criticality NA NA GL 84-11 Inspections of BWR Stainless Steel Piping NA NA Compliance W 10CFR61 and Implementation of Rad Effluent Tech GL 84-12 NA NA Specs, Attendant Process Control Program GL 84-13 Technical Specification for Snubbers NA NA GL 84-14 Replacement and Requalification Training Program NA NA Proposed Staff Actions to Improve and Maintain Diesel Generator GL 84-15 NA NA Reliability Adequacy of On-Shift Operating Experience for Near Term GL 84-16 NA NA Operating License Applicants Annual Meeting to Discuss Recent Developments Regarding GL 84-17 NA NA Operator Training, Qualifications, and Examinations GL 84-18 Filing of Applications for Licenses and Amendments NA NA Availability of Supplement 1 to NUREG-0933, "A Prioritization of GL 84-19 NA NA Generic Safety Issues" Scheduling Guidance for Licensee Submittals of Reloads That GL 84-20 NA NA Involve Unreviewed Safety Questions GL 84-21 Long Term Low Power Operation in Pressurized Water Reactors NA NA GL 84-22 10 CFR 20.408 Termination Reports - Format NA NA GL 84-23 Reactor Vessel Water Level Instrumentation in BWRs NA NA Cert of Compliance to 10CFR50.49, Eq of Electric Equipment See Special Program for Environmental GL 84-24 CI CI Important to Safety for Npps Qualification GL 85-01 Fire Protection Policy Steering Committee Report NA NA Staff Recommended Actions Regarding Steam Generator Tube GL 85-02 CI CI TVA letter 06/17/1985-Perform SG inspection Integrity Clarification of Equivalent Control Capacity for Standby Liquid GL 85-03 NA NA Control Systems GL 85-04 Operating Licensing Examinations NA NA GL 85-05 Inadvertent Boron Dilution Events NA NA Page 32 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Quality Assurance Guidance for ATWS Equipment That Is Not GL 85-06 NA NA Safety-Related GL 85-07 Implementation of Integrated Schedules for Plant Modifications NA NA GL 85-08 10 CFR 20.408 Termination Reports - Format NA NA GL 85-09 Technical Specifications For Generic Letter 83-28, Item 4.3 NA NA GL 85-10 Technical Specification For Generic Letter 83-28, Items 4.3 and 4.4 NA NA Completion of Phase II of "Control Of Heavy Loads At Nuclear GL 85-11 C C Verified. No response required.

Power Plants" NUREG-0612 Implementation Of TMI Action Item II.K.3.5, "Automatic Trip Of Reviewed in 15.5.4 of 1982 SER; became GL 85-12 CI CI Reactor Coolant Pumps license condition #35.Resolved SSER4 Transmittal Of NUREG-1154 Regarding The Davis-Besse Loss Of GL 85-13 NA NA Main And Auxiliary Feedwater Event Commercial Storage At Power Reactor Sites Of Low Level GL 85-14 NA NA Radioactive Waste Not Generated By The Utility Information On Deadlines For 10CFR50.49, "EQ Of Electric GL 85-15 NA NA Equipment Important To Safety At Npps" GL 85-16 High Boron Concentrations NA NA Availability Of Supplements 2 and 3 To NUREG-0933, "A GL 85-17 NA NA Prioritization Of Generic Safety Issues" GL 85-18 Operator Licensing Examinations NA NA GL 85-19 Reporting Requirements On Primary Coolant Iodine Spikes NA NA Resolution Of Generic Issue 69: High Pressure Injection/Make-up GL 85-20 NA NA Nozzle Cracking In Babcock And Wilcox Plants GL 85-21 This Generic Communication was not issued NA NA Potential For Loss Of Post-LOCA Recirculation Capability Due To GL 85-22 NA NA Insulation Debris Blockage Safety Concerns Associated With Pipe Breaks In The BWR Scram GL 86-01 NA NA System Technical Resolution of Generic Issue B Thermal Hydraulic GL 86-02 NA NA Stability GL 86-03 Applications For License Amendments NA NA Applies to O.L.A and requires actions.

GL 86-04 Policy Statement On Engineering Expertise On Shift NA A-O Additional info needed.

Implementation Of TMI Action Item II.K.3.5, "Automatic Trip Of GL 86-05 NA NA Reactor Coolant Pumps" Implementation Of TMI Action Item II.K.3.5, "Automatic Trip of GL 86-06 NA NA Reactor Coolant Pumps" Page 33 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Transmittal of NUREG-1190 Regarding The San Onofre Unit 1 Loss GL 86-07 NA NA of Power And Water Hammer Event Availability of Supplement 4 to NUREG-0933, "A Prioritization of GL 86-08 NA NA Generic Safety Issues" Technical Resolution of Generic Issue B-59, (n-1) Loop Operation in Confirm Tech Specs prohibit (N-1) Loop GL 86-09 CT CT BWRs and PWRs Operation GL 86-10 Implementation of Fire Protection Requirements NA NA Fire Endurance Test Acceptance Criteria for Fire Barrier Systems GL 86-10S1 Used to Separate Redundant Safe shutdown Trains within same fire NA NA area.

GL 86-11 Distribution of Products Irradiated in Research Reactors NA NA Criteria for Unique Purpose Exemption From Conversion From The GL 86-12 NA NA Use of Heu Fuel Potential Inconsistency Between Plant Safety Analyses and GL 86-13 NA NA Technical Specifications GL 86-14 Operator Licensing Examinations NA NA Info ... Compliance W 10CFR50.49 "Eq of Electric Equipment GL 86-15 NA NA Important to Safety For Nuclear Power Plants" GL 86-16 Westinghouse ECCS Evaluation Models NA NA Availability of NUREG-1169, "Technical Findings Related to Generic GL 86-17 NA NA Issue C-8, BWR MSIC Leakage And Treatment Methods" Public Availability Of The NRC Operator Licensing Examination GL 87-01 NA NA Question Bank Verification of Seismic Adequacy of Mechanical and Electrical GL 87-02 NA NA Equipment in Operating Reactors, USI A-46 Transmits SSER No. 2 on SQUG Generic Implementation GL 87-02s1 NA NA Procedure, Revision 2, as Corrected February 14, 1992 (GIP-2)

Verification of Seismic Adequacy of Mechanical and Electrical GL 87-03 NA NA Equipment in Operating Reactors, USI A-46 Temporary Exemption From Provisions Of The FBI Criminal History GL 87-04 NA NA Rule For Temporary Workers Request for Additional Information on Assessment of License GL 87-05 NA NA Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells Periodic Verification of Leak Tight Integrity of Pressure Isolation GL 87-06 NA NA Valves Page 34 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Information Transmittal of Final Rulemaking For Revisions To GL 87-07 NA NA Operator Licensing - 10 CFR 55 And Confirming Amendments Implementation of 10 CFR 73.55 Miscellaneous Amendments and GL 87-08 NA NA Search Requirements Sections 3.0 And 4.0 of Standard Tech Specs on Limiting GL 87-09 NA NA Conditions For Operation And Surveillance Requirements Implementation of 10 CFR 73.57, Requirements For FBI Criminal GL 87-10 NA NA History Checks GL 87-11 Relaxation in Arbitrary Intermediate Pipe Rupture Requirements NA NA Loss of Residual Heat Removal While The Reactor Coolant System GL 87-12 C C Superseded by GL88-17 is Partially Filled GL 87-13 Integrity requalification Examinations at Non-Power Reactors NA NA GL 87-14 Operator Licensing Exams NA NA GL 87-15 Policy Statement on deferred plants NA NA Transmittal of NUREG-1262, "Answers to Questions On GL 87-16 NA NA Implementation of 10CFR 55 on Operator's Licenses" GL 88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping NA NA GL 88-02 Integrated Safety Assessment Program II (ISAP II) NA NA GL 88-03 Resolution of GSI 93, Steam Binding of Auxiliary Feedwater Pumps CI CI See App EE of SSER 16 GL 88-04 Distribution of Gems Irradiated in Research Reactors NA NA Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary GL 88-05 CI CI NRC Acceptance letter 08/08/1990 Components in PWR plants Removal of Organization Charts from Technical Specification GL 88-06 NA NA Administrative Control Requirements Modified Enforcement Policy Relating to 10 CFR 50.49, EQ of See Special Program for Environmental GL 88-07 CI CI Electrical Equipment Important to Safety for Nuclear Power Plants Qualification GL 88-08 Mail Sent or Delivered to the Office of Nuclear Reactor Regulation NA NA GL 88-09 Pilot Testing of Fundamentals Examination NA NA GL 88-10 Purchase of GSA Approved Security Containers NA NA NRC Position on Radiation Embrittlement of Reactor Vessel NRC Acceptance letter 06/29/1989 for both GL 88-11 CI CI Material and its Impact on Plant Operations Units.

Removal of Fire Protection Requirements from Technical GL 88-12 NA NA Specification GL 88-13 Operator Licensing Examinations NA NA Page 35 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Instrument Air Supply System Problems Affecting Safety-Related NRC letter 07/26/1990. Unit 2 action: Complete GL 88-14 CI CI Equipment implementation.

GL 88-15 Electric Power Systems - Inadequate Control Over Design Process NA NA Removal of Cycle-Specific Parameter Limits from Technical GL 88-16 NA NA Specifications Implement mods to provide RCS temp, RV level GL 88-17 Loss of Decay Heat Removal CI CI and RHR system performance. ML073230823 GL 88-18 Plant Record Storage on Optical Disks NA NA Use of Deadly Force by Licensee Guards to Prevent Theft of GL 88-19 NA NA Special Nuclear Material GL 88-20 Individual Plant Examination for Severe Accident Vulnerability O O Initiation of the Individual Plant Examination for Severe Accident GL 88-20s1 O O Vulnerabilities - 10 CFR 50.54 Accident Management Stratagies for Consideration in the Individual GL 88-20s2 O O Plant Examination Process Completion of Containment Performance Improvement Program GL 88-20s3 O O and Forwarding of Insights for Use in the IPE for SAV Individual Plant Examination of External Events (IPEEE) for Severe GL 88-20s4 O O Accident Vulnerabilities Individual Plant Examination of External Events (IPEEE) for Severe GL 88-20s5 O O Accident Vulnerabilities - 10 CFR 50.54(f)

Implementation of Programmatic and Procedural Controls for GL 89-01 NA NA Radiological Effluent Technical Specifications Actions to Improve the Detection of Counterfeit and Fraudulently N.R.R but actions should be taken. Applies to GL 89-02 NA A-O Marketed Products all C.P holders GL 89-03 Operator Licensing Examination Schedule NA NA GL 89-04 Guidelines on Developing Acceptable Inservice Testing Programs OV OV GL 89-05 Pilot testing of the Fundamentals Examination NA NA NRC reviewed in SSER5,SSER6 &

GL 89-06 TMI Action Plan Item I.D.2 - Safety Parameter Display System CI CI SSER15(18.2.2)-Install SPDS prior start up Power Reactor Safeguards Contingency Planning for Surface TVA letter dated 10/31/1989 & NRC memo GL 89-07 C C Vehicle Bombs 06/26/1990. IR50-391/95-70 ML072610753 Prepare procedure & perform baseline GL 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning CI CI inspections GL 89-09 ASME Section III Component Replacements NA NA NRC accepted review 09/14/1990 and reviewed GL 89-10 Safety-Related Motor-Operated Valve Testing and Surveillance CI CI App. SSER16.

Page 36 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number NRC accepted review 09/14/1990 and reviewed GL 89-10s1 Results of the Public Workshops CI CI App. SSER16.

NRC accepted review 09/14/1990 and reviewed GL 89-10s2 Availability of Program Descriptions CI CI App. SSER16.

Consideration of the Results of NRC-Sponsored Tests of Motor- NRC accepted review 09/14/1990 and reviewed GL 89-10s3 CI CI Operated Valves App. SSER16.

NRC accepted review 09/14/1990 and reviewed GL 89-10s4 Consideration of Valve Mispositioning in Boiling Water Reactors CI CI App. SSER16.

NRC accepted review 09/14/1990 and reviewed GL 89-10s5 Inaccuracy of Motor-Operated Valve Diagnostic Equipment CI CI App. SSER16.

Information on Schedule and Grouping, and Staff Responses to NRC accepted review 09/14/1990 and reviewed GL 89-10s6 CI CI Additional Public Questions App. SSER16.

Consideration of Valve Mispositioning in Pressurized-Water NRC accepted review 09/14/1990 and reviewed GL 89-10s7 CI CI Reactors App. SSER16.

Resolution of Generic Issue 101 "Boiling Water Reactor Water GL 89-11 NA NA Level Redundancy" GL 89-12 Operator Licensing Examination NA NA Service Water System Problems Affecting Safety Related GL 89-13 CI CI NRC letters 07/09/1990 & 06/13/1997 Equipment Line-Item Improvements in Technical Specifications - Removal of GL 89-14 NA NA 3.25 Limit on Extending Surveillance Intervals GL 89-15 Emergency Response Data System NA C ML072610803 GL 89-16 Installation of a Hardened Wetwell Vent NA NA Planned Administrative Changes to the NRC Operator Licensing GL 89-17 NA NA Written Examination Process Resolution of Unresolved Safety Issues A-17, "Systems Interactions GL 89-18 NA NA in Nuclear Power Plants" Request for Actions Related to Resolution of Unresolved Safety GL 89-19 CI CI NRC acceptance letter 10/24/1990 Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 Perform evaluation of common mode failures CFR 50.54(f) due to fire GL 89-20 Protected Area Long Term Housekeeping NA NA Request for Information Concerning Status of Implementation of GL 89-21 NA A-O NRC requests review and subsequent report Unresolved Safety Issue (USI) Requirements Potential For Increased Roof Load Due to Changes in Maximum GL 89-22 C C TVA letter dated 12/16/1981 Precipitation NRC Staff Responses to Questions Pertaining to Implementation of GL 89-23 NA NA 10 CFR Part 26 Page 37 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Request for Voluntary Participation in NRC Regulatory Impact GL 90-01 NA NA Survey Alternative Requirements for Fuel Assemblies in the Design GL 90-02 NA NA Features Section of Technical Specifications Alternative Requirements for Fuel Assemblies in the Design GL 90-02s1 NA NA Features Section of Technical Specifications Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 GL 90-03 NA NA "Vendor Interface for Safety-Related Components" Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, GL 90-03s1 NA NA "Vendor Interface for Safety-Related Components" Request for Information on the Status of Licensee Implementation NRC letter 12/09/1994. Actions: Implement GL 90-04 CI CI of GSIs Resolved with Imposition of Requirements or CAs modification and testing.

Guidance for Performing Temporary Non-Code Repair of ASME GL 90-05 NA NA Code Class 1, 2, and 3 Piping Resolution of Generic Issues 70, "PORV and Block Valve NRC letter 01/09/1991 accepted TVA's GL 90-06 CT CT Reliability," and 94, "Additional LTOP Protection for PWRs" response for both units.

GL 90-07 Operator Licensing National Examination Schedule NA NA GL 90-08 Simulation Facility Exemptions NA NA Alternative Requirements for Snubber Visual Inspection Intervals GL 90-09 NA NA and Corrective Actions Removal of the Schedule for the Withdrawal of Reactor Vessel GL 91-01 NA NA Material Specimens from Technical Specifications GL 91-02 Reporting Mishaps Involving LLW Forms Prepared for Disposal NA NA GL 91-03 Reporting of Safeguards Events NA NA Changes in Technical Specification Surveillance Intervals to GL 91-04 NA NA Accommodate a 24-Month Fuel Cycle Licensee Commercial-Grade Procurement and Dedication GL 91-05 NA NA Programs Resolution of Generic Issue A-30, "Adequacy of Safety Related DC GL 91-06 NA NA Power Supplies" GI-23, "Reactor Coolant Pump Seal Failures" and Its Possible GL 91-07 NA NA Effect on Station Blackout GL 91-08 Removal of Component Lists from Technical Specifications NA NA Modification of Surveillance Interval for the Electrical Protective GL 91-09 NA NA Assemblies in Power Supplies for the Reactor Protection System GL 91-10 Explosives Searches at Protected Area Portals NA NA Page 38 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Resolution of Generic Issues A-48, "LCOs for Class 1E Vital GL 91-11 Instrument Buses", and 49, "Interlocks and LCOs for 1E Tie NA NA Breakers" GL 91-12 Operator Licensing National Examination Schedule NA NA Request for Information Related to Resolution of Generic Issue 130, GL 91-13 NA NA "Essential Service Water System Failures @ Multi-Unit Sites" GL 91-14 Emergency Telecommunications NA NA Operating Experience Feedback Report, Solenoid-Operated Valve GL 91-15 NA NA Problems at U.S. Reactors Licensed Operators' and Other Nuclear Facility Personnel Fitness GL 91-16 NA NA for Duty Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear GL 91-17 NA NA Power Plants" Information to Licensees Regarding Two NRC Inspection Manual GL 91-18 NA NA Superseded by RIS 2005-20 Sections on Resolution of Degraded and Nonconforming Conditions and on Operability [GL 91-18 has been superseded RIS 2005-20]

NRC Generic Letter 91-18, Revision 1: Information to Licensees GL 91-18r1 NA NA Superseded by RIS 2005-20 Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions [GL 91-18 R1 has been superseded RIS 2005-20]

Information to Addressees Regarding New Telephone Numbers for GL 91-19 NA NA NRC Offices Located in One White Flint North GL 92-01 Reactor Vessel Structural Integrity NA NA GL 92-01r1 NA NA GL 92-01r1s1 NA NA Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel GL 92-02 NA NA (PWR) Thermal Stress During Natural Convection Cooldown" Compilation of the Current Licensing Basis: Request for Voluntary GL 92-03 NA NA Participation in Pilot Program Resolution of the Issues Related to Reactor Vessel Water Level GL 92-04 NA NA Instrumention in BWRs Pursuant to 10 CFR 50.54(f)

NRC Workshop on the Systematic Assessment of Licensee GL 92-05 NA NA Performance (SALP) Program GL 92-06 Operator Licensing National Examination Schedule NA NA GL 92-07 Office of Nuclear Reactor Regulation Reorganization NA NA GL 92-08 Thermo-Lag 330-1 Fire Barriers OV OV Page 39 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Limited Participation by NRC in the IAEA International Nuclear GL 92-09 NA NA Event Scale GL 93-01 Emergency Response Data System Test Program NA C IR 390/391-95-78 ML072610803 NRC Public Workshop on Commercial Grade Procurement and GL 93-02 NA NA Dedication GL 93-03 Verification of Plant Records NA NA Rod Control System Failure and Withdrawal of Rod Control Cluster GL 93-04 CI CI NRC letter dated 12/09/1994 Assemblies, 10 CFR 50.54(f)

Line-Item Technical Specifications Improvements to Reduce GL 93-05 NA NA Surveillance Requirements for Testing During Power Operation Research Results on Generic Safety Issue 106, "Piping and the Use GL 93-06 NA NA of Highly Combustible Gases in Vital Areas" Modification of the Technical Specification Administrative Control GL 93-07 NA NA Requirements for Emergency and Security Plans Relocation of Technical Specification Tables of Instrument GL 93-08 NA NA Response Time Limits Removal of Accelerated Testing and Special Reporting GL 94-01 NA NA Requirements for Emergency Diesel Generators Long Term Solutions and Upgrade of Interim Operating GL 94-02 NA NA Recommendations for Thermal/Hydraulic Instabilities in BWRs GL 94-03 IGSCC of Core Shrouds in BWRs NA NA Voluntary Reporting of Additional Occupational Radiation Exposure GL 94-04 NA NA Data NRC Staff Technical Position on Fire Protection for Fuel Cycle GL 95-01 NA NA Facilities Use of Numarc/epri Report TR-102348, "Guideline on Licensing GL 95-02 NA NA Digital Upgrades,"

in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 GL 95-03 Circumferential cracking of Steam Generator (SG) Tubes OV OV Final Disposition of the Systematic Evaluation Program Lessons-GL 95-04 NA NA Learned Issues Voltage Based Repair Criteria for W SG Tubes Affected by Outside GL 95-05 C C N.R.R. TVA letter 09/07/2007 Diameter Stress Corrosion Cracking GL 95-06 Changes in the Operator Licensing Program NA NA Pressure Locking and Thermal Binding of Safety-Related Power- Evil. pressure locking & thermal binding of GL 95-07 CI CI Operated Gate Valves safety related power gate valves 10 CFR 50.54(p) Process for Changes to Security Plans Without GL 95-08 NA NA Prior NRC Approval Page 40 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Monitoring and Training of Shippers and Carriers of Radioactive GL 95-09 NA NA Materials Relocation of Selected Technical Specifications Requirements GL 95-10 NA NA Related to Instrumentation TVA responded 04/18/1996. Implement GL 96-01 Testing of Safety-Related Circuits CI CI recommendations Reconsideration of Nuclear Power Plant Security Requirements GL 96-02 NA NA Associated with an Internal Threat Relocation of the Pressure Temperature Limit Curves and Low N.R.R.-Submit temp. pressure limits &

GL 96-03 CI CI Temperature Overpressure Protection System Limits incorporate into licensee-controlled doc.

GL 96-04 Boraflex Degradation in Spent Fuel Pool Storage Racks NA NA Periodic Verification of Design-Basis Capability of Safety-Related TVA response on 07/21/1999-Implement joint GL 96-05 CI CI Motor-Operated Valves owner's group MOV PV program Assurance of Equipment Operability and Containment Integrity NRC letter 04/06/1999-Implement & provide GL 96-06 OV OV During Design-Basis Accident Conditions containment penetration relief.

NRC Generic Letter 96-06, Supplement 1: Assurance of Equipment NRC letter 04/06/1999-Implement & provide GL 96-06s1 OV OV Operability and Containment containment penetration relief.

Integrity During Design-Basis Accident Conditions GL 96-07 Interim Guidance on Transportation of Steam Generators NA NA Degradation of Control Rod Drive Mechanism Nozzle and Other GL 97-01 OV OV Vessel Closure Head Penetrations GL 97-02 Revised Contents of the Monthly Operating Report NA NA Annual Financial Update of Surety Requirements for Uranium GL 97-03 NA NA Recovery Licensees Assurance of Sufficient Net Positive Suction Head for Emergency GL 97-04 OV OV Core Cooling and Containment Heat Removal Pumps GL 97-05 SG Tube Inspection Techniques OV OV GL 97-06 Degradation of SG Internals OV OV Year 2000 Readiness of Computer Systems at Nuclear Power GL 98-01 NA NA IR 50-390/391 99-09 Plants ML993620597 Loss of Reactor Coolant Inventory and Associated Potential for GL 98-02 Loss of Emergency Mitigation Functions While in a Shutdown OV OV Condition NRC Generic Letter 98-03: NMSS Licensees' and Certificate GL 98-03 NA NA Holders' Year 2000 Readiness Programs Potential for Degradation of the ECCS and the Containment Spray GL 98-04 OV OV System After a Page 41 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment NRC Generic Letter 98-05: Boiling Water Reactor Licensees Use of GL 98-05 NA NA the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds NRC Generic Letter 99-01: Recent Nuclear Material Safety and GL 99-01 NA NA Safeguards Decision on Bundling Exempt Quantities GL 99-02 Laboratory Testing of Nuclear Grade Activated Charcoal NA NA WB closeout letter ML003681388 GL 03-01 Control Room Habitability OT OT GL 04-01 Requirements for SG Tube Inspection OV OV Potential Impact of Debris Blockage on Emergency Recirculation GL 04-02 OV OV during Design Basis Accidents at PWRs GL 06-01 SG Tube Integrity and Associated Technical Specifications OT OT Grid Reliability and the Impact on Plant Risk and the Operability of GL 06-02 OV OV Offsite Power Potentially Nonconforming Hemyc and MT Fire Barrier GL 06-03 OV OV Configurations GL 07-01 Independent Safety Engineering Group OV OV Complete testing of four additional cables.

Managing Gas Accumulation in Emergency Core Cooling, Decay GL 07-02 O O Heat Removal, and Containment Spray systems Inaccessible or Underground Power Cable Failures that Disable GL 08-01 O O Accident Mitigation Systems or Cause Plant Transients NUREG 0737 TMI Items (TVA letter dated September 14, 1981 applies to all):

NUREG 0737 I.A.1.3 Shift Manning C C Closed in SSER 16.

I.A.2.1 Immediate upgrade of RO and SRO Training and NUREG 0737 C C Closed in SSER 16.

qualifications NUREG 0737 I.A.2.3 Administration of Training programs C C Closed in SSER 16.

NUREG 0737 I.A.3.1 Revise scope and criteria for licensing exams C C Closed in SSER 16.

NUREG 0737 I.B.1.2 Independent Safety Engineering Group OV OV NRC reviewed App. EE of SSER16. Implement NUREG 0737 I.C.1 Short term accident and procedure review CI CI Emergency Operating Procedures NUREG 0737 I.C.2 Shift and relief turnover procedures C C Closed in SSER 16.

NUREG 0737 I.C.3 Shift supervisor responsibility C C Closed in SSER 16.

NUREG 0737 I.C.4 Control Room Access C C Closed in SSER 16.

NUREG 0737 I.C.5 Feedback of Operating experience C C Closed in SSER 16.

NUREG 0737 I.C.6 Verify correct performance of operating activities C C Closed in SSER 16.

Page 42 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number Unit 2: Revise power ascension and emergency NUREG 0737 I.C.7 NSSS vendor revision of procedures CI CI procedures I.C.8 Pilot monitoring of selected emergency procedures for Pilot monitor selected emergency procedures NUREG 0737 CI CI NTOLs for NTOL NUREG 0737 I.D.1 CRDR OV OV NRC reviewed in SSER5,SSER6 & 18.2.2 of NUREG 0737 I.D.2 Plant-safety-parameter-display console CI CI SSER15 NUREG 0737 I.G.1 Training during low power testing C C Closed in SSER 16.

NUREG 0737 II.B.1 Reactor-coolant-vent-system CI CI Verify installation of reactor coolant vents Complete design review of EQ of equipment for NUREG 0737 II.B.2 Plant shielding CI CI spaces/systems of post accident NUREG 0737 II.B.3 Post-accident sampling CT CT NRC reviewed in 9.3.2 of SSER16.

NUREG 0737 II.B.4 Training for mitigating core damage C C Closed in SSER 16.

NRC reviewed in Tech. Eval. Report attached to NUREG 0737 II.D.1 Relief and safety valve test requirements CI CI App. EE of SSER15 Verify installation of the acoustic monitoring NUREG 0737 II.D.3 Valve position indication CI CI system to PORV to indicate position Perform auxiliary feedwater system analysis. It NUREG 0737 II.E.1.1 Auxiliary feedwater system evaluation, modifications CI CI pertains to syst. failure & flow rate IR 50-391/84-16 & letters dated 03/29/1985 &

NUREG 0737 II.E.1.2 Auxiliary feedwater system initiation and flow CI CI 10/31/1995 NRC letters 03/29/1985 & 10/31/1995-NUREG 0737 II.E.3.1 Emergency power for pressurizer heaters CI CI Implement procedures & testing NUREG 0737 II.E.4.1 Dedicated Hydrogen Penetrations C C IR 50-391/83-19 NRC letters 03/29/1985; 07/12/1990 &

NUREG 0737 II.E.4.2 Containment isolation dependability CT CT 10/31/1995 NUREG 0737 II.F.1.2. Accident-monitoring instrumentation :

Install noble gas, iodine/particulate sampling &

NUREG 0737 A. - Noble gas CI CI containment High Range monitors Install noble gas, iodine/particulate sampling &

NUREG 0737 B. - Iodine/particulate sampling CI CI containment High Range monitors Install noble gas, iodine/particulate sampling &

NUREG 0737 C. - Containment high range monitoring CI CI containment High Range monitors Verify installation of containment water level NUREG 0737 D. - Containment pressure CI CI monitors Verify installation of containment water level NUREG 0737 E. - Containment water level CI CI monitors Verify installation of containment hydrogen NUREG 0737 F. - Containment hydrogen CI CI accident monitoring instrumentation Page 43 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments Accession TVA NRC Number NUREG 0737 II.F.2 Instrumentation for detection of inadequate core-cooling O O II.G.1 Power supplies for pressurizer relief valves, block valves Implement mods. So PORV & block valves NUREG 0737 CI CI and level indicators powered same train but different bus NUREG 0737 II.K.1.5 Review ESF valves C C NRC letter dated 03/29/1985 Confirm multi unit operation will have no impact NUREG 0737 II.K.1.10 Operability status CI CI on administrative procedures NUREG 0737 II.K.1.17 Trip per low-level B/S C C NRC letter dated 03/29/1985 II.K.2.13 Effect of High Pressure Injection for small Break LOCA In SSER4 staff concluded vessel integrity would NUREG 0737 C C with no Auxiliary Feedwater be maintained for small breaks.

LICENSE CONDITION-Voiding the reactor NUREG 0737 II.K.2.17 Voiding in the reactor Coolant System C C coolant system.

Reviewed in SSER5 and NRC letter NUREG 0737 II.K.3.1 Auto PORV isolation C C 06/129/1990 Reviewed on SSER5 & NRC letter dated NUREG 0737 II.K.3.2 Report on PORV failures C C 06/29/1990 NUREG 0737 II.K.3.3 Reporting SV/RV failures/challenges CT CT NRC reviewed in App EE of SSER16 License condition #35. Item reviewed in App.

NUREG 0737 II.K.3.5 Auto trip of RCPs CI CI EE of SSER 16.

Reviewed in original 1982 SER. Set derivative NUREG 0737 II.K.3.9 PID controller CI CI time constant to zero.

NUREG 0737 II.K.3.10 Anticipatory trip at high power CT CT NRC letter 10/31/1995; SSER 16 II.K.3.12 Confirm existence of anticipatory reactor trip upon NUREG 0737 C C Closed in SSER16 turbine trip In SSER3 NRC accepted commitment from NUREG 0737 II.K.3.17 ECCS outages C C 10/28/1983 letter.

Ensure DG power is provided to pump sealing NUREG 0737 II.K.3.25 Power on pump seals CI CI cooling system NUREG 0737 II.K.3.30 SB LOCA methods CI CI NRC letters dated 03/29/1985 & 07/24/1986 NUREG 0737 II.K.3.31 Plant specific analysis CI CI Complete analysis for unit 2.

NUREG 0737 III.A.1.1 Emergency Preparedness, Short term C C NRC completed review of REP in SSER20 NUREG 0737 III.A.1.2 Upgrade Emergency Support facilities C C NRC completed review of REP in SSER20 NUREG 0737 III.A.2 Emergency Preparedness C C NRC completed review of REP in SSER20 NUREG 0737 III.D.1.1 Primary coolant outside containment OT OT NUREG 0737 III.D.3.3 In-plant I2 radiation monitoring CI CI NRC reviewed in App. EE of SSER16 NUREG 0737 III.D.3.4 Control-room habitability OV OV Page 44 of 45

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 2. Generic Communications Status-Open (A-O & OT also Included)

Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments TVA NRC Accession Number N.R.R But defective shipment was received cr79023 Motor Starters and Contactors Failed to Operate NA A-O and should be addressed N.R.R but inspections & C.A expected on cr79025 Shock Arrestor Strut Assembly Interference NA A-O behalf of WBN 2 Torque Switch Electrical Bypass Circuit for Safeguard Service Valve Report required if discrepancies found.

cr81013 NA A-O Motors Clarify if discrepancies were found.

Applies to ALL PWR's. Requests submittal GL 79-24 Multiple Equipment Failures in Safety-Related Systems NA A-O of reports Follow-up Actions Resulting from the NRC Staff Reviews Regarding Applies to all C.P holders and requires GL 79-51 NA A-O the TMI-2 Accident implementation of actions Check Applicability. Header (yes) content GL 79-63 Upgraded Emergency Plans NA A-O (No). Request add. Info.

IEB 80-03 Loss Of Charcoal From Standard Type II, 2 Inch, Tray GL 80-11 NA A-O Requires action on behalf of C.P holder Absorber Cells Info expected to be submitted 90 days after GL 80-28 IEB 80-08 Examination Of Containment Liner Penetration Welds NA A-O issuance Information Request on Category I Masonry Walls Employed by Plants B80-11 requests actions from all C.P GL 80-32 NA A-O Under CP and OL Review facilities GL 80-92 IEB 80-21 Valve Yokes Supplied By Malcolm Foundry Company, Inc. NA A-O Report was to be submitted within 60 days Applies to O.L.A and requires actions.

GL 86-04 Policy Statement On Engineering Expertise On Shift NA A-O Additional info needed.

Actions to Improve the Detection of Counterfeit and Fraudulently N.R.R but actions should be taken. Applies GL 89-02 NA A-O Marketed Products to all C.P holders Request for Information Concerning Status of Implementation of NRC requests review and subsequent GL 89-21 NA A-O Unresolved Safety Issue (USI) Requirements report GL 82-28 Inadequate Core Cooling Instrumentation System O O GL 88-20 Individual Plant Examination for Severe Accident Vulnerability O O Initiation of the Individual Plant Examination for Severe Accident GL 88-20s1 O O Vulnerabilities - 10 CFR 50.54 Page 45 of 49

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 2. Generic Communications Status-Open (A-O & OT also Included)

Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments TVA NRC Accession Number Accident Management Stratagies for Consideration in the Individual GL 88-20s2 O O Plant Examination Process Completion of Containment Performance Improvement Program and GL 88-20s3 O O Forwarding of Insights for Use in the IPE for SAV Individual Plant Examination of External Events (IPEEE) for Severe GL 88-20s4 O O Accident Vulnerabilities Individual Plant Examination of External Events (IPEEE) for Severe GL 88-20s5 O O Accident Vulnerabilities - 10 CFR 50.54(f)

Managing Gas Accumulation in Emergency Core Cooling, Decay Heat GL 07-02 O O Removal, and Containment Spray systems Inaccessible or Underground Power Cable Failures that Disable GL 08-01 O O Accident Mitigation Systems or Cause Plant Transients NUREG 0737 II.F.2 Instrumentation for detection of inadequate core-cooling O O GL 03-01 Control Room Habitability OT OT GL 06-01 SG Tube Integrity and Associated Technical Specifications OT OT NUREG 0737 III.D.1.1 Primary coolant outside containment OT OT Page 46 of 49

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 3. Generic Communication Status-Open for Validation Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Rev.1 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments TVA NRC Accession Number Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire IEB 92-01 OV OV Endurance Function Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire IEB 92-01s1 OV OV Endurance Function IEB 96-01 Control Rod Insertion Problems (PWR) OV OV Circumferential Cracking of Reactor Pressure Vessel (RPV) Head IEB 01-01 OV OV Penetration Nozzles IEB 02-01 RPV Head Degradation and Reactor Coolant Pressure Boundary Integrity OV OV IEB 02-02 RPV Head and Vessel Head Penetration Nozzle Inspection Program OV OV Leakage from RPV Lower Head Penetrations and Reactor Coolant Pressure IEB 03-02 OV OV Boundary Integrity Inspection of Alloy 82/182/600 Materials Used in the Fabrication of IEB 04-01 OV OV Pressurizer Penetrations and Steam Space Piping Connections at PWRs IEB 07-01 Security Officer Attentiveness OV OV GL 89-04 Guidelines on Developing Acceptable Inservice Testing Programs OV OV GL 92-08 Thermo-Lag 330-1 Fire Barriers OV OV GL 95-03 Circumferential cracking of Steam Generator (SG) Tubes OV OV NRC letter 04/06/1999-Implement &

Assurance of Equipment Operability and Containment Integrity During GL 96-06 OV OV provide containment penetration Design-Basis Accident Conditions relief.

NRC Generic Letter 96-06, Supplement 1: Assurance of Equipment NRC letter 04/06/1999-Implement &

GL 96-06s1 Operability and Containment Integrity During Design-Basis Accident OV OV provide containment penetration Conditions relief.

Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel GL 97-01 OV OV Closure Head Penetrations Assurance of Sufficient Net Positive Suction Head for Emergency Core GL 97-04 OV OV Cooling and Containment Heat Removal Pumps GL 97-05 SG Tube Inspection Techniques OV OV GL 97-06 Degradation of SG Internals OV OV Loss of Reactor Coolant Inventory and Associated Potential for Loss of GL 98-02 OV OV Emergency Mitigation Functions While in a Shutdown Condition Page 47 of 49

Potential for Degradation of the ECCS and the Containment Spray System GL 98-04 After a LOCA Because of Construction and Protective Coating Deficiencies OV OV and Foreign Material in Containment GL 04-01 Requirements for SG Tube Inspection OV OV Potential Impact of Debris Blockage on Emergency Recirculation during GL 04-02 OV OV Design Basis Accidents at PWRs Grid Reliability and the Impact on Plant Risk and the Operability of Offsite GL 06-02 OV OV Power GL 06-03 Potentially Nonconforming Hemyc and MT Fire Barrier Configurations OV OV Complete testing of four additional GL 07-01 Independent Safety Engineering Group OV OV cables.

NUREG 0737 I.B.1.2 Independent Safety Engineering Group OV OV NUREG 0737 I.D.1 CRDR OV OV NUREG 0737 III.D.3.4 Control-room habitability OV OV Page 48 of 49

NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 4. Generic Communication Status-Applicable therefore Open Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; Ver.1 CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Position ADAMS Item Title Additional Comments TVA NRC Accession Number N.R.R But defective shipment was received and should cr79023 Motor Starters and Contactors Failed to Operate NA A-O be addressed N.R.R but inspections & C.A expected on behalf of cr79025 Shock Arrestor Strut Assembly Interference NA A-O WBN 2 Torque Switch Electrical Bypass Circuit for Safeguard Report required if discrepancies found. Clarify if cr81013 NA A-O Service Valve Motors discrepancies were found.

GL 79-24 Multiple Equipment Failures in Safety-Related Systems NA A-O Applies to ALL PWR's. Requests submittal of reports Follow-up Actions Resulting from the NRC Staff Reviews Applies to all C.P holders and requires implementation GL 79-51 NA A-O Regarding the TMI-2 Accident of actions Check Applicability. Header (yes) content (No). Request GL 79-63 Upgraded Emergency Plans NA A-O add. Info.

IEB 80-03 Loss Of Charcoal From Standard Type II, 2 GL 80-11 NA A-O Requires action on behalf of C.P holder Inch, Tray Absorber Cells IEB 80-08 Examination Of Containment Liner GL 80-28 NA A-O Info expected to be submitted 90 days after issuance Penetration Welds Information Request on Category I Masonry Walls GL 80-32 NA A-O B80-11 requests actions from all C.P facilities Employed by Plants Under CP and OL Review IEB 80-21 Valve Yokes Supplied By Malcolm Foundry GL 80-92 NA A-O Report was to be submitted within 60 days Company, Inc.

Applies to O.L.A and requires actions. Additional info GL 86-04 Policy Statement On Engineering Expertise On Shift NA A-O needed.

Actions to Improve the Detection of Counterfeit and N.R.R but actions should be taken. Applies to all C.P GL 89-02 NA A-O Fraudulently Marketed Products holders Request for Information Concerning Status of GL 89-21 Implementation of Unresolved Safety Issue (USI) NA A-O NRC requests review and subsequent report Requirements

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