ML081490118

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

ML081490118
Person / Time
Site:	Watts Bar
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: ML081490118
References
TAC MD8314
Download: ML081490118 (35)

Text

Rev.1 ADAMS TVA NRC Accession 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 IEB 72-02 Simultaneous Actuation of a Safety Injection Signal on Both units of a Dual unit Facility NA NA IEB 72-03 Limitorque Valve Operator Failures NA NA IEB 73-01 Faulty Overcurrent Trip Delay Device in Circuit Breakers for Engineered Safety Systems C

C TVA letter dated 04/04/1973 - IR390/391 75-5 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 IEB 74-03 Failure of Structural or Seismic Support Bolts on Class I Components CI CI Implement NUREG-0577 on Unit 2 similar as Unit 1 IEB 74-03a Failure of Structural or Seismic Support Bolts on Class I Components C

C 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 Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments Page 1 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 74-12 Incorrect Coils in W Type SG Relays at Trojan C

C TVA letter dated 12/12/1974 - IR390/391 75-5 IEB 74-13 Improper Factory Wiring on GE Motor Control Centers at Fort Calhoun C

C TVA letter dated 12/24/1974 - IR390/391 75-5 IEB 74-14 BWR Relief Valve Discharge to Suppression Pool NA NA IEB 74-15 Misapplication of Cutler-Hammer Three Position Maintained Switch Model No. 10250T CI CI Install modified A3 Cutler-Hammer 10250T switches IEB 74-16 Improper Machining of Pistons in Colt Industries (Fairbanks-Morse)

Diesel Generators C

C TVA letter dated 01/02/1975 - IR390/391 75-3 IEB 75-01 Through-Wall Cracks in Core Spray Piping at Dresden-2 NA NA IEB 75-02 Defective Radionics Radiograph Exposure Devices and Source Changes NA NA IEB 75-03 Incorrect Lower Disc Spring and Clearance Dimension in Series 8300 and 8302 ASCO Solenoid Valves CI CI Modify valves not modified at factory 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 IEB 76-02 Relay Coil Failures CI CI Repair or Replace relays before preoperational 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 IEB 76-06 Diaphragm Failures in Air Operated Auxiliary Actuators for Safety/Relief Valves C

C TVA memo dated 01/25/1985-IR 390/391 85-05 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 IEB 77-02 Potential Failure Mechanism in Certain W AR Relays with Latch Attachments C

C TVA letter dated 11/11/1977-IR 390/391 85-08 IEB 77-03 On-Line Testing of the W Solid State Protection System CI CI Include necessary periodic testing in test procedures Page 2 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 77-04 Calculation Error Affecting Performance of a System for Controlling pH of CT CT NRC IR 391/78-09 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 IEB 77-06 Potential Problems with Containment Electrical Penetration Assemblies C

C IR 390/391 85-08 IEB 77-07 Containment Electrical Penetration Assemblies at Nuclear Power Plants under Construction C

C TVA letter dated 01/20/1978 - IR391 78-9 IEB 77-08 Assurance of Safety and Safeguards During an Emergency -

Locking Systems C

C TVA letter dated 03/01/1978 - IR391 78-9 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 IEB 78-03 Potential Gas Mixture Accumulations Associated with BWR Offgas System Operations NA NA IEB 78-04 Environmental Qualification of Certain Stem Mounted Limit Switches Inside Reactor Containment CI CI Ensure NAMCO switches have been approved-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 IEB 78-09 BWR Drywell Leakage Paths Associated with Inadequate Drywell Closures NA NA IEB 78-10 Bergen-Patterson Hydraulic Shock Suppressor Accumulator Spring Coils C

C TVA letter dated 08/14/1978 IR 391/ 78-19 ML072530128 IEB 78-11 Examination of Mark I Containment Torus Welds NA NA IEB 78-12 Atypical Weld Material in Reactor Pressure Vessel Welds C

C TVA Westinghouse letter dated 10/29/1979 -

IR390/391 81-04 IEB 78-12a Atypical Weld Material in Reactor Pressure Vessel Welds C

C TVA Westinghouse letter dated 10/29/1979 -

IR390/391 81-04 IEB 78-12b Atypical Weld Material in Reactor Pressure Vessel Welds C

C TVA Westinghouse letter dated 10/29/1979 -

IR390/391 81-04 IEB 78-13 Failures in Source Heads Kay Ray Gauge Models 7050, 7050B, 7051, 7051B, 7060, 7060B, 7061 and 7061B NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments 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 IEB 79-02 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts CI CI NRC review of HAAUP program in NUREG-1232, SSER6 & SSER8 IEB 79-02r1 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts CI CI NRC review of HAAUP program in NUREG-1232, SSER6 & SSER8 IEB 79-02r1s1 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts CI CI NRC review of HAAUP program in NUREG-1232, SSER6 & SSER8 IEB 79-02r2 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts CI CI NRC review of HAAUP program in NUREG-1232, SSER6 & SSER8 IEB 79-03 Longitudinal Weld Defects in ASME SA-312 Type 304 SS Pipe Spools Fabricated by Youngstown Welding & Engineering C

C TVA letter dated 07/16/1981-IR391/82-17 and IR391/84-33 IEB 79-03a Longitudinal Weld Defects in ASME SA-312 Type 304 SS Pipe Spools Fabricated by Youngstown Welding & Engineering C

C TVA letter dated 07/16/1981-IR391/82-17 and IR391/84-33 IEB 79-04 Incorrect Weights for Swing Check Valves Manufactured by Velan Engineering C

C TVA letter dated 10/20/1980- IR391/83-11 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 IEB 79-06 Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident C

C IR 391/80-05 IEB 79-06a Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident C

C IR 391/80-05 IEB 79-06aR1 Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident C

C IR 391/80-05 IEB 79-06b Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident C

C IR 391/80-05 IEB 79-06c Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident C

C IR 391/80-05 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 IEB 79-09 Failure of GE Type AK-2 Circuit Breaker in Safety Related Systems CI CI Complete preservice preventive maintenance on AK-2 Circuit Breakers IEB 79-10 Requalification Training Program Statistics C

C IR states that IEB is NA & requires no action ML072560606.

IEB 79-11 Faulty Overcurrent Trip Device in Circuit Breakers for Engineering Safety Systems C

C TVA letter dated 07/20/1979-IR391/79-25 Page 4 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments 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 IEB 79-14 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI NRC review of HAAUP Program in NUREG-1232, SSER6 & SSER8 IEB 79-14r1 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI NRC review of HAAUP Program in NUREG-1232, SSER6 & SSER8 IEB 79-14r1s1 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI NRC review of HAAUP Program in NUREG-1232, SSER6 & SSER8 IEB 79-14r1s2 Seismic Analysis for As-Built Safety-Related Piping Systems CI CI NRC review of HAAUP Program in NUREG-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 IEB 79-18 Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas NA NA Page 5 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments 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 IEB 79-21 Temperature Effects on Level Measurements CI CI Reviewed in 7.2.5 of both original 1982 SER and SSER14 IEB 79-22 Possible Leakage of Tubes of Tritium Gas Used in Time Pieces for Luminosity NA NA IEB 79-23 Potential Failure of Emergency Diesel Generator Field Exciter Transformer C

C TVA letter dated 10/29/1979-IR391/80-05 IEB 79-24 Frozen Lines CI CI Insulate section of piping in containment spray 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 IEB 79-28 Possible Malfunction of NAMCO Model EA180 Limit Switches at Elevated Temperatures C

C TVA letter dated 04/01/1993-IR 390/391 93-32 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 IEB 80-04 Analysis of a PWR Main Steam Line Rupture with Continued Feedwater Addition CI CI IR 50-391/85-49-Complete analysis for Unit 2 ML072500505 IEB 80-05 Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks CI CI Closed in IR50-391/84-45-Complete surveillance procedures for Unit 2 IEB 80-06 Engineered Safety Features Reset Control CI CI Reviewed in 7.3.5 of 1982 SER. Perform 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 IEB 80-09 Hydramotor Actuator Deficiencies C

C TVA letter dated 01/15/1981-NUREG/CR 5291, IR390/391 85-08 & IR 391/85-49 IEB 80-10 Contamination of Non-radioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment CI CI

1. Correct deficiencies involving monitoring of systems. 2. Include proper monitoring of non-radioactive systems in procedures.

Page 6 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 80-11 Masonry Wall Design CI CI Complete corrective actions in 50-391/93-01 IEB 80-12 Decay Heat Removal System Operability CI CI Implement operating instructions & abnormal 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 IEB 80-15 Possible Loss of Emergency Notification System with Loss of Offsite Power C

C IR 390/391 85-08 IEB 80-16 Potential Misapplication of Rosemount Models 1151 and 1152 Pressure Transmitters With Either "A" or "D" Output Codes C

C TVA letter dated 08/29/1980- IR390/391 81-17 ML072570467 IEB 80-17 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR NA NA IEB 80-17s1 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR NA NA IEB 80-17s2 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR NA NA IEB 80-17s3 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR NA NA IEB 80-17s4 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR NA NA IEB 80-17s5 Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR NA NA IEB 80-18 Maintenance of Adequate Minimum Flow Thru Centrifugal Charging Pumps Following CI CI IR 50-391/85-49-Implement design and procedure changes.

a Secondary Side High Energy Rupture IEB 80-19 Mercury-Wetted Matrix Relay in Reactor Protective Systems C

C TVA letter dated 09/04/1980- NUREG/CR 4933, IR390/391 81-17 IEB 80-19r1 Mercury-Wetted Matrix Relay in Reactor Protective Systems C

C TVA letter dated 09/04/1980- NUREG/CR 4933, 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 IEB 80-22 Automation Industries, Model 200-520-008 Sealed-Source Connectors NA NA IEB 80-23 Failures of Solenoid Valves Manufactured by Valcor Eng. Corp C

C TVA letter dated 03/31/1981-NUREG/CR 5292, IR390/391 81-17 ML072570467 IEB 80-24 Prevention of Damage Due to Water Leakage Inside Containment CI CI Confirm reactor cavity cannot be flooded, resulting in partial/total submergence Page 7 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 80-25 Operating Problems with Target Rock SR Valves at BWRs NA NA IEB 81-01 Surveillance of Mechanical Snubbers NA NA NRC: IR 390/391 81-17. Report states bulletin is NA IEB 81-01r1 Surveillance of Mechanical Snubbers NA NA NRC: IR 390/391 81-17. Report states bulletin 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 IEB 82-02 Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants CI CI Approach accepted in IR50-391/85-08 IEB 82-03 Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless Steel, Recirculation System Piping at BWR Plants NA NA Applies only to BWR's ML031210724 IEB 82-03r1 Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless Steel, Recirculation System Piping at BWR Plants NA NA Applies only to BWR's ML031210724 IEB 82-04 Deficiencies in Primary Containment Electrical Penetration Assemblies C

C TVA letter dated 01/24/1983-IR391/83-08 IEB 83-01 Failure of Trip Breakers (Westinghouse DB-50) to Open on Automatic Trip Signal C

C IR 390/391 85-08 and 391/92-13 IEB 83-02 Stress Corrosion Cracking in Large-Diameter Stainless Steel Recirculation System Piping at BWR Plants NA NA IEB 83-03 Check Valve Failures in Raw Water Cooling Systems of Diesel Generators NA NA IEB 83-04 Failure of the Undervoltage Trip Function of Reactor Trip Breakers CI CI Install new undervoltage attachment with wider grooves on reactor trip breakers IEB 83-05 ASME Nuclear Code Pumps and Spare Parts Manufactured by Hayward Tyler Pump Co C

C TVA letter dated 09/07/1983-IR 391/85-04 and 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 IEB 83-08 Electrical Circuit Breakers With Undervoltage Trip in Safety Related Applications other than the Reactor Trip System C

C TVA letter dated 03/29/1984-IR391/84-33 IEB 84-01 Cracks in BWR Mark 1 Containment Vent Headers NA NA Page 8 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 84-02 Failure of GE Type HFA Relays In Use In Class 1E Safety Systems C

C TVA letter dated 07/10/1984-IR390/391 84-42 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 IEB 85-02 Undervoltage Trip Attachment of W DB-50 Type Reactor Trip Breakers CI CI Install automatic shut trip on Westinghouse DS-416 reactor trip breakers appear as C & CI IEB 85-03 Motor Operated Valve Common Mode Failures During Plant Transients due to Improper Switch Settings C

C Superseded by GL89-10 ML072690589 IEB 85-03s1 Motor Operated Valve Common Mode Failures During Plant Transients due to Improper Switch Settings C

C Superseded by GL89-10 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 IEB 86-03 Potential Failure of Multiple ECCS Pumps Due to Single Failure of Air-Operated Valve in Minimum Flow Recirculation Line C

C TVA letter dated 11/14/1986-IR390/391 87-03 ML072530767 IEB 86-04 Defective Teletherapy Timer That May Not Terminate Treatment Dose NA NA IEB 87-01 Thinning of Pipe Walls in Nuclear Power Plants C

C IEB 87-02 Fastener Testing to Determine Conformance with Applicable Material Specifications CI CI NRC letter dated 08/18/1989 IEB 87-02s1 Fastener Testing to Determine Conformance with Applicable Material Specifications CI CI NRC letter dated 08/18/1989 IEB 87-02s2 Fastener Testing to Determine Conformance with Applicable Material Specifications CI CI NRC letter dated 08/18/1989 IEB 88-01 Defects in W Circuit Breakers C

C TVA letter dated 11/15/1991-IR 390/391 93-01 ML072680775 IEB 88-02 Rapidly Propagating Fatigue Cracks in Steam Generator Tubes CI CI NRC letter 06/07/1990-Evaluate E/C data to determine anti vibration bar depth IEB 88-03 Inadequate Latch Engagement in HFA Type Latching Relays Manufactured by General Electric (GE) Company C

C TVA letter dated 04/13/1992-IR 390/391 92-13 ML072680594 IEB 88-04 Potential Safety-Related Pump Loss CI CI NRC letter 05/24/1990-Perform calculations &

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 90-01s1 Loss of Fill-Oil in Transmitters Manufactured by Rosemount CI CI Implement & Id. Potentially defective 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 IEB 92-01 Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function OV OV IEB 92-01s1 Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function OV OV IEB 92-02 Safety Concerns Related to "End of Life" of Aging Theratronics Teletherapy Units NA NA IEB 92-03 Release of Patients After Brachytherapy NA NA IEB 93-01 Release of Patients After Brachytherapy Treatment with Remote Afterloading Devices NA NA 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 IEB 93-03 Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs NA NA IEB 94-01 Potential Fuel Pool Draindown Caused by Inadequate Maintenance Practices at Dresden NA NA IEB 94-02 Corrosion Problems in Certain Stainless Steel Packaging's Used to Transport Uranium Hexaflouride NA NA IEB 95-01 Quality Assurance Program for Transportation of Radioactive Material NA NA IEB 95-02 Unexpected Clogging of a Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NA NA IEB 96-01 Control Rod Insertion Problems (PWR)

OV OV IEB 96-02 Movement of Heavy Loads over Spent Fuel, over Fuel in the Reactor, or over Safety-Related Equipment CI CI NRC letter 05/20/1998 IEB 96-03 Potential Plugging of ECCS Suction Strainers by Debris in BWRs NA NA IEB 96-04 Chemical, Galvanic, or Other Reactions in Spent Fuel Storage and Transportation Casks NA NA IEB 97-01 Potential for Erroneous Calibration, Dose Rate, or Radiation Exposure Measurements with Certain Victoreen NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments IEB 01-01 Circumferential Cracking of Reactor Pressure Vessel (RPV) Head Penetration Nozzles OV OV 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 IEB 03-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation NA NA TVA: Letter dated September 7, 2007 ML0725706761 IEB 03-02 Leakage from RPV Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity OV OV IEB 03-03 Potentially Deficient 1-inch Valves for Uranium Hexaflouride Cylinders NA NA IEB 03-04 Rebaselining of Data in the Nuclear Management and Safeguards System C

C NRC letter dated 12/18/2003 IEB 04-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations OV OV and Steam Space Piping Connections at PWRs IEB 05-01 Material Control and Accounting of Reactors and Spent Fuel Storage Facilities C

C TVA letter dated 03/21/2005 and 05/11/2005.

NRC letter dated 11/30/2005 ML052560158 IEB 05-02 Emergency Preparedness and Response Actions for Security Based Events C

C TVA letters dated 01/20/2006 & 08/16/2006 IEB 07-01 Security Officer Attentiveness OV OV cr76001 Crane Hoist Control Circuit Modifications C

C cr76002 Relay Failures - Westinghouse BF (ac) and BFD (dc) Relays C

C Compliance achieved 12/12/1976-IR 50/391/76-11 ML071760483 cr76003 Radiation Exposures in Reactor Cavities NA NA cr76004 Neutron Monitor and Flow Bypass Switch Malfunctions NA NA cr76005 Hydraulic Shock and Sway Suppressors - Maintenance of Bleed and Lock-up Velocities on ITT Grinnell Models...

C C

TVA letter 01/07/1977 cr76006 Stress Corrosion Cracks in Stagnant, Low Pressure Stainless Piping Containing Boric Acid Solution at PWRs NA NA cr76007 Inadequate Performance by Reactor Operating and Support Staff Members NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments 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 cr77009 Improper Fuse Coordination in BWR Standby Liquid Control System Control Circuits NA NA 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 cr77014 Separation of Contaminated Water Systems from Noncontaminated Plant Systems NA NA 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 cr78003 Packaging Greater than Type A Quantities of Low Specific Activity Radioactive Material for Transport NA NA cr78004 Installation Errors That Could Prevent Closing of Fire Doors NA NA cr78005 Inadvertent Safety Injection During Cooldown NA NA cr78006 Potential Common Mode Flooding of ECCS Equipment Rooms at BWR Facilities NA NA cr78007 Damaged Components of a Bergen-Paterson Series 25000 Hydraulic Test Stand NA NA cr78008 Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants NA NA 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 cr78015 Tilting Disc Check Valves Fail to Close with Gravity in Vertical Position NA NA cr78016 Limitorque Valve Actuators NA NA cr78017 Inadequate Guard Training/Qualification and Falsified Training Records NA NA cr78018 UL Fire Test NA NA Page 13 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments 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 cr79003 Inadequate Guard Training-Qualification and Falsified Training Records NA NA 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 cr79007 Unexpected Speed Increase of Reactor Recirculation MG Set Resulted in Reactor Power Increase NA NA cr79008 Attempted Extortion - Low Enriched Uranium NA NA cr79009 Occurrences of Split or Punctured Regulator Diaphragms in Certain Self Contained Breathing Apparatus NA NA 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 cr79015 Bursting of High Pressure Hose and Malfunction of Relief Valve O-Ring in Certain Self-Contained Breathing Apparatus NA NA cr79016 Excessive Radiation Exposures to Members of the General Public and a Radiographer NA NA cr79017 Contact Problem in SB-12 Switches on General Electric Company Metalclad Circuit Breakers NA NA cr79018 Proper Installation of Target Rock Safety-Relief Valves NA NA cr79019 Loose Locking Devices on Ingersoll-Rand Pumps NA NA cr79020 Failure of GTE Sylvania Relay Type PM Bulletin 7305 Catalog 5U12 11-AC with a 120V AC Coil NA NA cr79021 Prevention of Unplanned Releases of Radioactivity NA NA cr79022 Stroke Times for Power Operated Relief Valves NA NA cr79023 Motor Starters and Contactors Failed to Operate NA A-O N.R.R But defective shipment was received and should be addressed cr79024 Proper Installation and Calibration of Core Spray Pipe Break Detection Equipment on BWRs NA NA cr79025 Shock Arrestor Strut Assembly Interference NA A-O N.R.R but inspections & C.A expected on behalf 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments cr80004 Securing of Threaded Locking Devices on Safety-Related Equipment NA NA cr80005 Emergency Diesel-Generator Lubricating Oil Addition and Onsite Supply NA NA 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 cr80012 Valve-Shaft-to-Actuator Key May Fall Out of Place when Mounted Below Horizontal Axis NA NA cr80013 Grid Strap Damage in Westinghouse Fuel Assemblies NA NA cr80014 Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel NA NA cr80015 Loss of Reactor Coolant Pump Cooling and Natural Circulation Cooldown NA NA cr80016 Operational Deficiencies in Rosemount Model 510DU Trip Units and Model 1152 Pressure Transmitters NA NA cr80017 Fuel Pin Damage Due to Water Jet from Baffle Plate Corner NA NA cr80018 10 CFR 50.59 Safety Evaluations for Changes to Radioactive Waste Treatment Systems NA NA 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 cr81001 Design Problems Involving Indicating Pushbutton Switches Manufactured by Honeywell Incorporated NA NA cr81002 Performance of NRC-Licensed Individuals while on Duty NA NA cr81003 Inoperable Seismic Monitoring Instrumentation NA NA cr81004 The Role of Shift Technical Advisors and Importance of Reporting Operational Events NA NA Page 15 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments cr81005 Self-Aligning Rod End Bushings for Pipe Supports NA NA cr81006 Potential Deficiency Affecting Certain Foxboro 10 to 50 Milliampere Transmitters NA NA cr81007 Control of Radioactively Contaminated Material NA NA cr81008 Foundation Materials NA NA cr81009 Containment Effluent Water that Bypasses Radioactivity Monitor NA NA cr81010 Steam Voiding in the Reactor Coolant System During Decay Heat Removal Cooldown NA NA cr81011 Inadequate Decay Heat Removal During Reactor Shutdown NA NA cr81012 Inadequate Periodic Test Procedure of PWR Reactor Protection System NA NA cr81013 Torque Switch Electrical Bypass Circuit for Safeguard Service Valve Motors NA A-O Report required if discrepancies found. Clarify if discrepancies were found.

cr81014 Main Steam Isolation Valve Failures to Close NA NA cr81015 Unnecessary Radiation Exposures to the Public and Workers During Events Involving Thickness and Level Measuring Devices NA NA GL 77-01 Intrusion Detection Systems Handbook NA NA GL 77-02 Fire Protection Functional Responsibilities NA NA GL 77-03 Transmittal of NUREG-0321, "A Study of the Nuclear Regulatory Commission Quality Assurance Program" NA NA GL states no copies of NUREG found GL 77-04 Shipments of Contaminated Components From NRC Licensed Nuclear Power Facilities to Vendors and Service Companies NA NA GL 77-05 Nonconformity of Addresses of Items Directed to the Office of Nuclear Reactor Regulation NA NA GL 77-06 Questionnaire Related to Steam Generators NA NA GL 77-07 Reliability of Standby Diesel Generator Units NA NA GL 77-08 Revised Intrusion detection handbook and Entry Control Systems Handbook NA NA GL 78-01 Correction To Letter Of 12/15/77 NA NA GL 78-02 Asymmetric Loads Background and Revised Request for Additional Information C

C Reviewed in SSER15-App C. Resolved by 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 GL 78-05 Internal Distribution Of Correspondence - Asking For Comments On Mass Mailing System NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 78-08 Enclosing NUREG-0408 RE Mark I Containments, And Granting Exemption From GDC 50 And Enclosing Sample Notice NA NA GL 78-09 Multiple Subsequent Actuations of Safety Relief Valves Following an Isolated Event NA NA GL 78-10 Guidance On Radiological Environmental Monitoring NA NA GL 78-11 Guidance on Spent Fuel Pool Modifications NA NA GL 78-12 Notice Of Meeting Regarding "Implementation of 10 CFR 73.55 Requirements And Status Of Research..."

NA NA 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 GL 78-16 Request For Information On Control Of Heavy Loads Near Spent Fuel Pools NA NA 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 GL 78-19 Enclosing Sandia Report SAND 77-0777, "Barrier Technology Handbook" NA NA GL 78-20 Enclosing - "A Systematic Approach To The Conceptual Design Of Physical Protection Systems For Nuclear Facilities" NA NA GL 78-21 Transmitting NUREG/CR-0181 Concerning Barrier & Penetration Data Needed For Physical Security System Assessment NA NA GL 78-22 Revision To Intrusion Detection Systems And Entry Control Handbooks And Nuclear Safeguards Technology Handbook NA NA GL 78-23 Manpower Requirements For Operating Reactors NA NA GL 78-24 Model Appendix I Technical Specifications And Submittal Schedule For BWRs NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 78-34 Reactor Vessel Atypical Weld Material C

C TVA Westinghouse letter dated 10/29/1979-IR 390/391 81-04 GL 78-35 Regional Meetings To Discuss Upgraded Guard Qualifications NA NA GL 78-36 Cessation of Plutonium Shipments By Air Except In NRC Approved Containers NA NA GL 78-37 Revised Meeting Schedule & Locations For Upgraded Guard Qualifications NA NA GL 78-38 Forwarding Of 2 Tables Of Appendix I, Draft Radiological Effluent Technical Specifications, PWR, and NUREG-0133 NA NA GL 78-39 Forwarding of 2 Tables of Appendix I, Draft Radiological Effluent Technical Specifications, BWR, And NUREG-0133 NA NA 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 GL 79-01 Interservice Procedures for Instructional Systems Development -

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

NA NA and Barrier Penetration Database GL 79-03 Offsite Dose Calculation Manual NA NA GL 79-04 Referencing 4/14/78 Letter - Modifications to NRC Guidance "Review and Acceptance of Spent Fuel Pool Storage and Handling" NA NA GL 79-05 Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee NA NA 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 GL 79-09 Staff Evaluation of Interim Multiple-Consecutive Safety-Relief Valve Actuations NA NA GL 79-10 Transmitting Regulatory Guide 2.6 for Comment NA NA GL 79-11 Transmitting "Summary of Operating Experience with Recalculating Steam Generators, January 1979" NUREG-0523 NA NA GL 79-12 ATWS - Enclosing Letter to GE, with NUREG-0460, Vol. 3 NA NA GL 79-13 Schedule for Implementation and Resolution of Mark I Containment Long Term Program NA NA GL 79-14 Pipe Crack Study Group - Enclosing NUREG-0531 and Notice NA NA Page 18 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 79-15 Steam Generators-Enclosing Summary of Operating Experience with Recirculating Steam Generators, NUREG-0523 NA NA 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 GL 79-21 Enclosing NUREG/CR 0660, "Enhancement of on Site Emergency Diesel Generator Reliability" NA NA GL 79-22 Enclosing NUREG-0560, "Staff Report on the Generic Assessment of Feedwater Transients in PWRs Designed by B&W NA NA GL 79-23 NRC Staff Review of Responses to I&E Bulletin 79-08 NA NA GL 79-24 Multiple Equipment Failures in Safety-Related Systems NA A-O Applies to ALL PWR's. Requests submittal of 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 GL 79-29 Transmitting NUREG-0473, Revision 2, Draft Radiological Effluent Technical Specifications NA NA GL 79-30 Transmitting NUREG-0472, Revision 2, Draft Radiological Technical Specifications NA NA 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 GL 79-33 Transmitting NUREG-0576 - Security Training and Qualification Plans NA NA 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 79-36 Adequacy of Station Electric Distribution Systems Voltages CI CI GL compliance w/ BTP PSB-1, "Adequacy of 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 GL 79-39 Transmitting Division 5 Draft Regulatory Guide and Value Impact Statement NA NA GL 79-40 Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident NA NA Page 19 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 79-41 Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard NA NA GL 79-42 Potentially Unreviewed Safety Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems NA NA 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 GL 79-45 Transmittal of Reports Regarding Foreign Reactor Operating Experiences NA NA GL 79-46 Containment Purge and Venting During Normal Operation NA NA GL 79-47 Radiation Training NA NA GL 79-48 Confirmatory Requirements Relating to Condensation Oscillation Loads for the Mark I Containment Long Term Program NA NA GL 79-49 Summary of Meetings Held on 9/18-20/79 to Discuss Potential Unreviewed Safety Question on Systems Interaction for B&W Pl NA NA GL 79-50 Emergency Plans Submittal Dates NA NA GL 79-51 Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident NA A-O Applies to all C.P holders and requires 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 GL 79-55 Summary of Meeting Held on October 12, 1979 to Discuss Responses to IE Bulletins79-05C and NA NA 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 GL 79-63 Upgraded Emergency Plans NA A-O Check Applicability. Header (yes) content (No).

Request add. Info.

GL 79-64 Suspension of All Operating Licenses NA NA GL 79-65 Radiological Environmental Monitoring Program Requirements -

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 79-67 Estimates for Evacuation of Various Areas Around Nuclear Power Reactors NA NA GL 79-68 Audit of Small Break LOCA Guidelines NA NA GL 79-69 Cladding Rupture, Swelling, and Coolant Blockage as a Result of a Reactor Accident NA NA GL 79-70 Environmental Monitoring for Direct Radiation NA NA GL 80-01 NUREG-0630, "Cladding, swelling and Rupture-Models for LOCA Analysis" NA NA 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 GL 80-06 Issuance Of NUREG-0313, Rev 1, "Technical Report On Material Selection And Processing Guidelines For BWR Coolant Pressure NA NA GL 80-07 Information Regarding The Program For Environmental Qualification Of Safety-Related Electrical Equipment NA NA GL 80-08 IEB 80-02 Inadequate Quality Assurance For Nuclear Supplied Equipment NA NA GL 80-09 Low Level Radioactive Waste Disposal NA NA GL 80-10 Issuance Of NUREG-0588, "Interim Staff Position On Equipment Qualifications Of Safety-Related Electrical Equipment NA NA GL 80-11 IEB 80-03 Loss Of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells NA A-O Requires action on behalf of C.P holder GL 80-12 IEB 80-04 Analysis Of A PWR Main Steam Sine Break With Continued Feedwater Addition NA NA 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 GL 80-15 Request For Additional Management And Technical Resources Information NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 80-20 Actions Req.. From OL Applicants Of NSSS Designs By W and CE Resulting From NA NA NRC B&O Task Force Review Of TMI2 Accident GL 80-21 Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks CI CI Complete surveillance procedures for Unit 2. IR 50/391/84-45 GL 80-22 Transmittal Of NUREG-0654 "Criteria For Preparation And Evaluation Of Radiological Emergency Response Plans And NA NA GL 80-23 Change Of Submittal Date For Evaluation Time Estimates NA NA GL 80-24 Transmittal Of Information On NRC "Nuclear Data Link Specifications" NA NA 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 GL 80-28 IEB 80-08 Examination Of Containment Liner Penetration Welds NA A-O Info expected to be submitted 90 days after issuance GL 80-29 Modifications To Boiling Water Reactor Control Rod Drive Systems NA NA GL 80-30 Clarification Of The Term "Operable" As It Applies To Single Failure Criterion For Safety Systems Required By TS NA NA GL 80-31 IEB 80-09 Hydramotor Actuator Deficiencies NA NA GL 80-32 Information Request on Category I Masonry Walls Employed by Plants Under CP and OL Review NA A-O B80-11 requests actions from all C.P facilities GL 80-33 Actions Req. From OL Applicants Of B&W Designed NSSS Resulting From NRC B&O Task Force Review Of TMI2 Accident NA NA GL 80-34 Clarification of NRC Requirements for Emergency Response Facilities at Each Site NA NA GL 80-35 Effect Of A DC Power Supply Failure On ECCS Performances NA NA GL 80-36 IEB 80-10 Contamination Of Non-Radioactive System And Resulting Potential For Unmonitored, Uncontrolled Release To Envir NA NA GL 80-37 Five Additional TMI-2 Related Requirements To Operating Reactors NA NA GL 80-38 Summary of Certain Non-Power Reactor Physical Protection Requirements NA NA GL 80-39 IEB 80-11 Masonry Wall Design NA NA Page 22 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 80-40 Transmittal Of NUREG-0654 "Report Of The B&O Task Force "

Appropriate NUREG-0626 "Generic Eval Of FW Transient And Sbl NA NA GL 80-41 Summary Of Meetings Held On April 22 &23, 1980 With Representatives Of The Mark I Owners Group NA NA 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 GL 80-46 A-12, Fracture Toughness and Additional Guidance on Potential for Low Fracture Toughness and Laminar Tearing on C

C N.R.R.-NUREG-0577 states laminar issue was resolved.

PWR Steam Generator Coolant Pump Supports GL 80-47 Additional Guidance On "Potential For Low Fracture Toughness And Laminar Tearing On PWR SG Reactor Coolant Pump Suprts C

C N.R.R.-NUREG-0577 states laminar issue was 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 GL 80-52 Five Additional TMI-2 Related Requirements - Erata Sheets To 5/7/80 Letter NA NA 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 GL 80-57 Further Commission Guidance For Power Reactor Operating Licenses NUREG-0660 And NUREG-0694 NA NA GL 80-58 IEB 80-16 Potential Misapplication Of Rosemount Inc. Models 1151/1152 Pressure Transmitters With "A" Or "D" Output Codes NA NA GL 80-59 Transmittal Of Federal Register Notice RE Regional Meetings To Discuss Environmental Qualification Of Elec. Equipment NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 80-63 IEB 80-17 Failure Of Control Rods To Insert During A Scram At A BWR NA NA GL 80-64 Scram Discharge Volume Designs NA NA GL 80-65 Request For Estimated Construction Completion And Fuel Load Schedules NA NA GL 80-66 IEB 80-17 Supplement 1 Failure Of Control Rods To Insert During A Scram At A BWR NA NA GL 80-67 Scram Discharge Volume NA NA GL 80-68 IEB 80-17 Supplement 2 Failures Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A NA NA GL 80-69 IEB 80-18 Maintenance Of Adequate Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side Helb NA NA GL 80-70 IEB 80-19 Failures Of Mercury-Wetted Matrix Relays In RPS Of Operating Nuclear Power Plants Designed By GE NA NA GL 80-71 IEB 80-20 Failures Of Westinghouse Type W-2 Spring Return To Neutral Control Switches NA NA GL 80-72 Interim Criteria For Shift Staffing NA NA GL 80-73 Functional Criteria For Emergency Response Facilities", NUREG-0696 NA NA GL 80-74 Notice Of Forthcoming Meeting With Representatives Of EPRI To Discuss Program For Resolution Of USI A-12, Fracture Tough NA NA GL 80-75 Lessons Learned Tech Specs NA NA GL 80-76 Notice Of Forthcoming Meeting With GE To Discussed Proposed BWR Feedwater Nozzle Leakage Detection System NA NA 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 GL 80-79 IEB 80-17 Supplement 3 Failures Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A NA NA GL 80-80 Preliminary Clarification Of TMI Action Plan Requirements NA NA GL 80-81 Preliminary Clarification Of TMI Action Plan Requirements -

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 80-85 Implementation Of Guidance From USI A-12 "Potential For LOW Fracture Toughness And NA NA Lamellar Tearing On Component Support GL 80-86 Notice Of Meeting To Discuss Final Resolution Of USI A-12 NA NA GL 80-87 Notice Of Meeting To Discuss Status Of EPRI-Proposed Resolution Of The USI A-12 Fracture Toughness Issue NA NA GL 80-88 Seismic Qualification Of Auxiliary Feedwater Systems NA NA GL 80-89 IEB 79-01b Supplement 3 Environmental Qualification Of Class 1E Equipment NA NA GL 80-90 NUREG-0737, TMI (Prior and future GLs, with the exception of certain discrete scopes, have been screened CI CI into NUREG list for those applicable to Watts Bar 2)

GL 80-91 Odyn Code Calculation NA NA 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 GL 80-93 Emergency Preparedness NA NA GL 80-94 Emergency Plan NA NA GL 80-95 A-10, NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Cracking" NA NA GL 80-96 Fire Protection NA NA GL 80-97 IEB 80-23 Failures Of Solenoid Valves Manufactured By Valcor Engineering Corporation NA NA GL 80-98 IEB 80-24 Prevention Of Damage Due To Water Leakage Inside Containment NA NA GL 80-99 Technical Specification Revisions For Snubber Surveillance NA NA GL 80-100 Appendix R to 10 CFR 50 Regarding Fire Protection-Federal Register Notice NA NA GL 80-101 Inservice Inspection Programs NA NA GL 80-102 Commission Memorandum And Order Of May 23, 1980 (Referencing IEB 79-01b Supplement 2 - q.2 & 3 - Sept 30, 1980)

NA NA GL 80-103 Fire Protection - Revised Federal Register Notice NA NA GL 80-104 Orders On Environmental Qualification Of Safety Related Electrical Equipment NA NA GL 80-105 Implementation Of Guidance For USI A-12, Potential For Low Fracture Toughness And Lamellar Tearing On Component Supports NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 80-108 Emergency Planning NA NA GL 80-109 Guidelines For Systematic Evaluation Program Soil Structure Interaction Reviews NA NA GL 80-110 Periodic Updating Of FSARS NA NA GL 80-111 IEB 80-17 Supplement 4, Failure Of Control Rods To Insert During A Scram At A BWR NA NA GL 80-112 IEB 80-25 Operating Problems With Target Rock Safety Relief Valves NA NA GL 80-113 Control of Heavy Loads C

C Superseded by GL 81-007 GL 81-01 Qualification of Inspection, Examination, Testing and Audit Personnel NA NA GL 81-02 Analysis, Conclusions and Recommendations Concerning Operator Licensing NA NA GL 81-03 NUREG-0313, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping NA NA GL 81-04 Emergency Procedures and Training for Station Blackout C

C Superseded by Station Blackout Rule GL 81-05 Information Regarding The Program For Environmental Qualification Of Safety-Related Electrical Equipment NA NA GL 81-06 Periodic Updating of Final Safety Analysis Reports (FSARS)

NA NA GL 81-07 Control of Heavy Loads CI CI Unit 2 Heavy Loads program will be in 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 GL 81-11 BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619)

NA NA GL 81-12 Fire Protection Rule (and prior related GLs)

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

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 81-19 Thermal Shock to Reactor Pressure Vessels NA NA GL 81-20 Safety Concerns Associated With Pipe Breaks in the BWR Scram System NA NA GL 81-21 Natural Circulation Cooldown CI CI TVA responded 12/03/1981-Unit 2 action: Issue operating procedures GL 81-22 Engineering Evaluation of The H.B. Robinson Reactor Coolant System Leak on 1/29/81 NA NA 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 GL 81-25 Change in Implementing Schedule For Submission and Evaluation of Upgraded Emergency Plans NA NA GL 81-26 Licensing Requirements for Pending Construction Permit and Manufacturing License Applications NA NA 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 GL 81-30 Safety Concerns Associated With Pipe Breaks in the BWR Scram System NA NA GL 81-31 Small Break LOCA Confirmatory Integral Systems Experiments for B&W Designed Plants NA NA GL 81-32 NUREG-0737, Item II.K.3.44-Evaluation of Anticipated Transients Combined With Single Failure NA NA GL 81-33 Technical Specification for Station Batteries Multiplant Action NA NA GL 81-34 Safety Concerns Associated With Pipe Breaks in the BWR Scram System NA NA GL 81-35 Safety Concerns Associated With Pipe Breaks in the BWR Scram System NA NA GL 81-36 Revised Schedule for Completion of TMI Action Plan Item II.D.1, Relief and Safety Valve Testing NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments 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 GL 82-11 Transmittal of NUREG-0916 Relative to the Restart of R.E. Ginna Nuclear Power Plant NA NA 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 GL 82-18 Reactor Operator and Senior Reactor Operator Requalification Examinations NA NA GL 82-19 Submittal of Copies of Documentation to NRC-Copy Requirements for Emergency Plans and Physical Security Plans NA NA GL 82-20 Guidance for Implementing the Standard Review Plan Rule NA NA GL 82-21 Fire Protection Audits NA NA GL 82-22 Congressional Request for Information Concerning Steam Generator Tube Integrity NA NA GL 82-23 Inconsistency Between Requirements of 10CFR 73.40(D) and Standard Tech Specs For Performing Audits of Safeguards Contingency NA NA GL 82-24 Safety Relief Valve Quencher Loads: BWR MARK II and III Containments NA NA GL 82-25 Integrated IAEA Exercise for Physical Inventory at LWRS NA NA GL 82-26 NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness NA NA GL 82-27 Transmittal of NUREG-0763 - Guidelines For Confirmatory In-Plant Tests of Safety-Relief Valve Discharge for BWR Plants NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 82-33 Supplement to NUREG-0737, Requirements for Emergency Response Capability CI CI NRC reviewed in SSER5,SSER6 & 18.2.2 of 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 GL 82-38 Meeting to Discuss Developments for Operator Licensing Examinations NA NA GL 82-39 Problems With Submittals of Subsequent Information of CURT 73.21 For Licensing Reviews NA NA GL 83-01 Operator Licensing Examination Site Visit NA NA GL 83-02 NUREG-0737 Technical Specifications NA NA GL 83-03 Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Pre-Service and Inservice Examinations" NA NA GL 83-04 Regional Workshops Regarding Supplement 1 to NUREG-0737, Requirements For Emergency Response Capability NA NA GL 83-05 Safety Evaluation of "Emergency Procedure Guidelines, Revision 2," June 1982 NA NA GL 83-06 Certificates and Revised Format For Reactor Operator and Senior Reactor Operator Licenses NA NA 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 GL 83-09 Review of Combustion Engineering Owners' Group Emergency Procedures Guideline Program NA NA 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 GL 83-10c Automatic Trip of Reactor Coolant Pumps (GL 83-10 a & b: CE, GL 83-10 d: W licensees, GL 83-10 e & f: B&W)

CI CI NRC letter 06/08/1990-Incorporate emergency 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 GL 83-11 Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions NA NA GL 83-12 Issuance of NRC FORM 398 - Personal Qualifications Statement -

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

NA NA Page 29 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 83-15 Implement. of Reg. Guide 1.150, "Ultrasonic Testing of RX Vessel Welds During Preservice & Inservice Examinations, REV.1 NA NA GL 83-16 Transmittal of NUREG-0977 Relative to the ATWS Events at Salem Generating Station, Unit NO. 1 NA NA GL 83-16a Transmittal of NUREG-0977 Relative to the ATWS Events at Salem Generating Station, Unit NO. 1 NA NA GL 83-17 Integrity of Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses NA NA GL 83-18 NRC Staff Review of the BWR Owners' Group (BWROG) Control Room Survey Program NA NA GL 83-19 New Procedures for Providing Public Notice Concerning Issuance of Amendments To Operating Licenses NA NA GL 83-20 Integrated Scheduling for Implementation of Plant Modifications NA NA GL 83-21 Clarification of Access Control Procedures for Law Enforcement Visits NA NA GL 83-22 Safety Evaluation of "Emergency Response Guidelines" NA NA GL 83-23 Safety Evaluation of "Emergency Procedure Guidelines" NA NA GL 83-24 TMI Task Action Plan Item I.G.1, "Special Low Power Testing and Training," Recommendations for BWRS NA NA GL 83-25 Issuance of NRC Form 398 Personal Qualifications Statement -

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

GL 83-28 1.2 - Post Trip Review Data and Information Capability C

C TVA letters dated 11/07/1983 & 12/04/1987. IR 391/86-04 ML072500568-ML072750564 GL 83-28 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components)

CI CI NRC letter 10/20/1986 & 06/18/1990 ML072500568 GL 83-28 2.2 - Equipment Classification and Vendor Interface (All SR Components)

CI CI GL 83-28 3.1 - Post-Maintenance Testing (Reactor Trip System Components)

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

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

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

07/02/1990. IR 391/86-04 ML072610753 Page 30 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 83-28 4.1 - Reactor Trip System Reliability (Vendor Related Modifications)

CI CI GL 83-28 4.2 - Reactor Trip System Reliability (Preventive Maintenance and Surveillance Program for Reactor Trip Breakers)

CT CT NRC letters 07/26/1985 and 06/18/1992 ML072750564 GL 83-28 4.3 - Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment)

C C

TVA letters dated11/07/1983 & 03/22/1985. IR 50-391/86-04 ML072750564 GL 83-28 4.5 - Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment)

CT CT NRC letters 06/28/1990 and 10/09/1990 ML072610753 GL 83-29 This Generic Communication was not issued NA NA GL 83-30 Deletion of STD. Tech Spec Surveillance Requirement 4.8.1.1.2.d.6 For Diesel Generator Testing NA NA GL 83-31 Safety Evaluation of "Abnormal Transient Operating Guidelines" NA NA GL 83-32 NRC Staff Recommendations Regarding Operator Action for Reactor Trip and ATWS NA NA GL 83-33 NRC Positions on Certain Requirements of Appendix R to 10 CFR 50 NA NA 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 GL 83-42 Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" NA NA GL 83-43 Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications NA NA GL 83-44 Availability of NUREG-1021, "Operator Licensing Examiner Standards" NA NA 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 GL 84-03 Availability of NUREG-0933, "A Prioritization of Generic Safety Issues" NA NA GL 84-04 Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in NA NA PWR Primary Main Loops (Generic Letter 84-04)

Page 31 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 84-05 Change to NUREG-1021, "Operator Licensing Examiner Standards" NA NA GL 84-06 Operator and Senior Operator License Examination Criteria For Passing Grade NA NA GL 84-07 Procedural Guidance for Pipe Replacement at BWRs NA NA GL 84-08 Interim Procedures for NRC Management of Plant-Specific Backfitting NA NA 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 GL 84-12 Compliance W 10CFR61 and Implementation of Rad Effluent Tech Specs, Attendant Process Control Program NA NA GL 84-13 Technical Specification for Snubbers NA NA GL 84-14 Replacement and Requalification Training Program NA NA GL 84-15 Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability NA NA GL 84-16 Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants NA NA GL 84-17 Annual Meeting to Discuss Recent Developments Regarding Operator Training, Qualifications, and Examinations NA NA GL 84-18 Filing of Applications for Licenses and Amendments NA NA GL 84-19 Availability of Supplement 1 to NUREG-0933, "A Prioritization of Generic Safety Issues" NA NA GL 84-20 Scheduling Guidance for Licensee Submittals of Reloads That Involve Unreviewed Safety Questions NA NA 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 GL 84-24 Cert of Compliance to 10CFR50.49, Eq of Electric Equipment Important to Safety for Npps CI CI See Special Program for Environmental Qualification GL 85-01 Fire Protection Policy Steering Committee Report NA NA GL 85-02 Staff Recommended Actions Regarding Steam Generator Tube Integrity CI CI TVA letter 06/17/1985-Perform SG inspection GL 85-03 Clarification of Equivalent Control Capacity for Standby Liquid Control Systems NA NA GL 85-04 Operating Licensing Examinations NA NA GL 85-05 Inadvertent Boron Dilution Events NA NA Page 32 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 85-06 Quality Assurance Guidance for ATWS Equipment That Is Not Safety-Related NA NA 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 GL 85-11 Completion of Phase II of "Control Of Heavy Loads At Nuclear Power Plants" NUREG-0612 C

C Verified. No response required.

GL 85-12 Implementation Of TMI Action Item II.K.3.5, "Automatic Trip Of Reactor Coolant Pumps CI CI Reviewed in 15.5.4 of 1982 SER; became license condition #35.Resolved SSER4 GL 85-13 Transmittal Of NUREG-1154 Regarding The Davis-Besse Loss Of Main And Auxiliary Feedwater Event NA NA GL 85-14 Commercial Storage At Power Reactor Sites Of Low Level Radioactive Waste Not Generated By The Utility NA NA GL 85-15 Information On Deadlines For 10CFR50.49, "EQ Of Electric Equipment Important To Safety At Npps" NA NA GL 85-16 High Boron Concentrations NA NA GL 85-17 Availability Of Supplements 2 and 3 To NUREG-0933, "A Prioritization Of Generic Safety Issues" NA NA GL 85-18 Operator Licensing Examinations NA NA GL 85-19 Reporting Requirements On Primary Coolant Iodine Spikes NA NA GL 85-20 Resolution Of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking In Babcock And Wilcox Plants NA NA GL 85-21 This Generic Communication was not issued NA NA GL 85-22 Potential For Loss Of Post-LOCA Recirculation Capability Due To Insulation Debris Blockage NA NA GL 86-01 Safety Concerns Associated With Pipe Breaks In The BWR Scram System NA NA GL 86-02 Technical Resolution of Generic Issue B Thermal Hydraulic Stability NA NA GL 86-03 Applications For License Amendments NA NA GL 86-04 Policy Statement On Engineering Expertise On Shift NA A-O Applies to O.L.A and requires actions.

Additional info needed.

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 86-07 Transmittal of NUREG-1190 Regarding The San Onofre Unit 1 Loss of Power And Water Hammer Event NA NA GL 86-08 Availability of Supplement 4 to NUREG-0933, "A Prioritization of Generic Safety Issues" NA NA GL 86-09 Technical Resolution of Generic Issue B-59, (n-1) Loop Operation in BWRs and PWRs CT CT Confirm Tech Specs prohibit (N-1) Loop Operation GL 86-10 Implementation of Fire Protection Requirements NA NA GL 86-10S1 Fire Endurance Test Acceptance Criteria for Fire Barrier Systems Used to Separate Redundant Safe shutdown Trains within same fire area.

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

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 87-07 Information Transmittal of Final Rulemaking For Revisions To Operator Licensing - 10 CFR 55 And Confirming Amendments NA NA GL 87-08 Implementation of 10 CFR 73.55 Miscellaneous Amendments and Search Requirements NA NA GL 87-09 Sections 3.0 And 4.0 of Standard Tech Specs on Limiting Conditions For Operation And Surveillance Requirements NA NA GL 87-10 Implementation of 10 CFR 73.57, Requirements For FBI Criminal History Checks NA NA GL 87-11 Relaxation in Arbitrary Intermediate Pipe Rupture Requirements NA NA GL 87-12 Loss of Residual Heat Removal While The Reactor Coolant System is Partially Filled C

C Superseded by GL88-17 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 GL 87-16 Transmittal of NUREG-1262, "Answers to Questions On Implementation of 10CFR 55 on Operator's Licenses" NA NA 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 GL 88-05 Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants CI CI NRC Acceptance letter 08/08/1990 GL 88-06 Removal of Organization Charts from Technical Specification Administrative Control Requirements NA NA GL 88-07 Modified Enforcement Policy Relating to 10 CFR 50.49, EQ of Electrical Equipment Important to Safety for Nuclear Power Plants CI CI See Special Program for Environmental 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 GL 88-11 NRC Position on Radiation Embrittlement of Reactor Vessel Material and its Impact on Plant Operations CI CI NRC Acceptance letter 06/29/1989 for both Units.

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 88-14 Instrument Air Supply System Problems Affecting Safety-Related Equipment CI CI NRC letter 07/26/1990. Unit 2 action: Complete implementation.

GL 88-15 Electric Power Systems - Inadequate Control Over Design Process NA NA GL 88-16 Removal of Cycle-Specific Parameter Limits from Technical Specifications NA NA GL 88-17 Loss of Decay Heat Removal CI CI Implement mods to provide RCS temp, RV level and RHR system performance.

ML073230823 GL 88-18 Plant Record Storage on Optical Disks NA NA GL 88-19 Use of Deadly Force by Licensee Guards to Prevent Theft of Special Nuclear Material NA NA GL 88-20 Individual Plant Examination for Severe Accident Vulnerability O

O GL 88-20s1 Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54 O

O GL 88-20s2 Accident Management Stratagies for Consideration in the Individual Plant Examination Process O

O GL 88-20s3 Completion of Containment Performance Improvement Program and Forwarding of Insights for Use in the IPE for SAV O

O GL 88-20s4 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities O

O GL 88-20s5 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - 10 CFR 50.54(f)

O O

GL 89-01 Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications NA NA GL 89-02 Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products NA A-O N.R.R but actions should be taken. Applies to 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 GL 89-06 TMI Action Plan Item I.D.2 - Safety Parameter Display System CI CI NRC reviewed in SSER5,SSER6 &

SSER15(18.2.2)-Install SPDS prior start up GL 89-07 Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs C

C TVA letter dated 10/31/1989 & NRC memo 06/26/1990. IR50-391/95-70 ML072610753 GL 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning CI CI Prepare procedure & perform baseline inspections GL 89-09 ASME Section III Component Replacements NA NA GL 89-10 Safety-Related Motor-Operated Valve Testing and Surveillance CI CI NRC accepted review 09/14/1990 and reviewed App. SSER16.

Page 36 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 89-10s1 Results of the Public Workshops CI CI NRC accepted review 09/14/1990 and reviewed App. SSER16.

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

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

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

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

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

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

GL 89-11 Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy" NA NA GL 89-12 Operator Licensing Examination NA NA GL 89-13 Service Water System Problems Affecting Safety Related Equipment CI CI NRC letters 07/09/1990 & 06/13/1997 GL 89-14 Line-Item Improvements in Technical Specifications - Removal of 3.25 Limit on Extending Surveillance Intervals NA NA GL 89-15 Emergency Response Data System NA C

ML072610803 GL 89-16 Installation of a Hardened Wetwell Vent NA NA GL 89-17 Planned Administrative Changes to the NRC Operator Licensing Written Examination Process NA NA GL 89-18 Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" NA NA GL 89-19 Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication CI CI NRC acceptance letter 10/24/1990 of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)

Perform evaluation of common mode failures due to fire GL 89-20 Protected Area Long Term Housekeeping NA NA GL 89-21 Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements NA A-O NRC requests review and subsequent report GL 89-22 Potential For Increased Roof Load Due to Changes in Maximum Precipitation C

C TVA letter dated 12/16/1981 GL 89-23 NRC Staff Responses to Questions Pertaining to Implementation of 10 CFR Part 26 NA NA Page 37 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 90-01 Request for Voluntary Participation in NRC Regulatory Impact Survey NA NA GL 90-02 Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications NA NA GL 90-02s1 Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications NA NA GL 90-03 Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 "Vendor Interface for Safety-Related Components" NA NA GL 90-03s1 Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components" NA NA GL 90-04 Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs CI CI NRC letter 12/09/1994. Actions: Implement modification and testing.

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

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 91-11 Resolution of Generic Issues A-48, "LCOs for Class 1E Vital Instrument Buses", and 49, "Interlocks and LCOs for 1E Tie Breakers" NA NA GL 91-12 Operator Licensing National Examination Schedule NA NA GL 91-13 Request for Information Related to Resolution of Generic Issue 130, "Essential Service Water System Failures @ Multi-Unit Sites" NA NA GL 91-14 Emergency Telecommunications NA NA GL 91-15 Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors NA NA GL 91-16 Licensed Operators' and Other Nuclear Facility Personnel Fitness for Duty NA NA GL 91-17 Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" NA NA GL 91-18 Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of NA NA Superseded by RIS 2005-20 Degraded and Nonconforming Conditions and on Operability [GL 91-18 has been superseded RIS 2005-20]

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

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

NA NA GL 92-05 NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program NA NA 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 92-09 Limited Participation by NRC in the IAEA International Nuclear Event Scale NA NA GL 93-01 Emergency Response Data System Test Program NA C

IR 390/391-95-78 ML072610803 GL 93-02 NRC Public Workshop on Commercial Grade Procurement and Dedication NA NA GL 93-03 Verification of Plant Records NA NA GL 93-04 Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f)

CI CI NRC letter dated 12/09/1994 GL 93-05 Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation NA NA GL 93-06 Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" NA NA GL 93-07 Modification of the Technical Specification Administrative Control Requirements for Emergency and Security Plans NA NA GL 93-08 Relocation of Technical Specification Tables of Instrument Response Time Limits NA NA GL 94-01 Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators NA NA GL 94-02 Long Term Solutions and Upgrade of Interim Operating Recommendations for Thermal/Hydraulic Instabilities in BWRs NA NA GL 94-03 IGSCC of Core Shrouds in BWRs NA NA GL 94-04 Voluntary Reporting of Additional Occupational Radiation Exposure Data NA NA GL 95-01 NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities NA NA GL 95-02 Use of Numarc/epri Report TR-102348, "Guideline on Licensing Digital Upgrades,"

NA NA 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 GL 95-04 Final Disposition of the Systematic Evaluation Program Lessons-Learned Issues NA NA GL 95-05 Voltage Based Repair Criteria for W SG Tubes Affected by Outside Diameter Stress Corrosion Cracking C

C N.R.R. TVA letter 09/07/2007 GL 95-06 Changes in the Operator Licensing Program NA NA GL 95-07 Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves CI CI Evil. pressure locking & thermal binding of safety related power gate valves GL 95-08 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval NA NA Page 40 of 45

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments GL 95-09 Monitoring and Training of Shippers and Carriers of Radioactive Materials NA NA GL 95-10 Relocation of Selected Technical Specifications Requirements Related to Instrumentation NA NA GL 96-01 Testing of Safety-Related Circuits CI CI TVA responded 04/18/1996. Implement recommendations GL 96-02 Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat NA NA GL 96-03 Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits CI CI N.R.R.-Submit temp. pressure limits &

incorporate into licensee-controlled doc.

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

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

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment GL 98-05 NRC Generic Letter 98-05: Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from NA NA Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds GL 99-01 NRC Generic Letter 99-01: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities NA NA 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 GL 04-02 Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at PWRs OV OV GL 06-01 SG Tube Integrity and Associated Technical Specifications OT OT GL 06-02 Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power OV OV GL 06-03 Potentially Nonconforming Hemyc and MT Fire Barrier Configurations OV OV GL 07-01 Independent Safety Engineering Group OV OV Complete testing of four additional cables.

GL 07-02 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray systems O

O GL 08-01 Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients O

O 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.

NUREG 0737 I.A.2.1 Immediate upgrade of RO and SRO Training and qualifications C

C Closed in SSER 16.

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 NUREG 0737 I.C.1 Short term accident and procedure review CI CI NRC reviewed App. EE of SSER16. Implement 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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments NUREG 0737 I.C.7 NSSS vendor revision of procedures CI CI Unit 2: Revise power ascension and emergency procedures NUREG 0737 I.C.8 Pilot monitoring of selected emergency procedures for NTOLs CI CI Pilot monitor selected emergency procedures for NTOL NUREG 0737 I.D.1 CRDR OV OV NUREG 0737 I.D.2 Plant-safety-parameter-display console CI CI NRC reviewed in SSER5,SSER6 & 18.2.2 of 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 NUREG 0737 II.B.2 Plant shielding CI CI Complete design review of EQ of equipment for 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.

NUREG 0737 II.D.1 Relief and safety valve test requirements CI CI NRC reviewed in Tech. Eval. Report attached to App. EE of SSER15 NUREG 0737 II.D.3 Valve position indication CI CI Verify installation of the acoustic monitoring system to PORV to indicate position NUREG 0737 II.E.1.1 Auxiliary feedwater system evaluation, modifications CI CI Perform auxiliary feedwater system analysis. It pertains to syst. failure & flow rate NUREG 0737 II.E.1.2 Auxiliary feedwater system initiation and flow CI CI IR 50-391/84-16 & letters dated 03/29/1985 &

10/31/1995 NUREG 0737 II.E.3.1 Emergency power for pressurizer heaters CI CI NRC letters 03/29/1985 & 10/31/1995-Implement procedures & testing NUREG 0737 II.E.4.1 Dedicated Hydrogen Penetrations C

C IR 50-391/83-19 NUREG 0737 II.E.4.2 Containment isolation dependability CT CT NRC letters 03/29/1985; 07/12/1990 &

10/31/1995 NUREG 0737 II.F.1.2. Accident-monitoring instrumentation :

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

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

containment High Range monitors NUREG 0737 C. - Containment high range monitoring CI CI Install noble gas, iodine/particulate sampling &

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

Rev.1 ADAMS TVA NRC Accession Number Key: NA= Not Applicable; A-O=Applicable, therefore Open; C= Closed; CI=Closed/Implementation; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open NRC Review: Generic Communications Status for TVA Watts Bar Unit 2.

Table 1. Generic Communications Matrix Master Table Item Title Position Additional Comments NUREG 0737 II.F.2 Instrumentation for detection of inadequate core-cooling O

O NUREG 0737 II.G.1 Power supplies for pressurizer relief valves, block valves and level indicators CI CI Implement mods. So PORV & block valves powered same train but different bus NUREG 0737 II.K.1.5 Review ESF valves C

C NRC letter dated 03/29/1985 NUREG 0737 II.K.1.10 Operability status CI CI Confirm multi unit operation will have no impact on administrative procedures NUREG 0737 II.K.1.17 Trip per low-level B/S C

C NRC letter dated 03/29/1985 NUREG 0737 II.K.2.13 Effect of High Pressure Injection for small Break LOCA with no Auxiliary Feedwater C

C In SSER4 staff concluded vessel integrity would be maintained for small breaks.

NUREG 0737 II.K.2.17 Voiding in the reactor Coolant System C

C LICENSE CONDITION-Voiding the reactor coolant system.

NUREG 0737 II.K.3.1 Auto PORV isolation C

C Reviewed in SSER5 and NRC letter 06/129/1990 NUREG 0737 II.K.3.2 Report on PORV failures C

C Reviewed on SSER5 & NRC letter dated 06/29/1990 NUREG 0737 II.K.3.3 Reporting SV/RV failures/challenges CT CT NRC reviewed in App EE of SSER16 NUREG 0737 II.K.3.5 Auto trip of RCPs CI CI License condition #35. Item reviewed in App.

EE of SSER 16.

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

NUREG 0737 II.K.3.10 Anticipatory trip at high power CT CT NRC letter 10/31/1995; SSER 16 NUREG 0737 II.K.3.12 Confirm existence of anticipatory reactor trip upon turbine trip C

C Closed in SSER16 NUREG 0737 II.K.3.17 ECCS outages C

C In SSER3 NRC accepted commitment from 10/28/1983 letter.

NUREG 0737 II.K.3.25 Power on pump seals CI CI Ensure DG power is provided to pump sealing 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

Rev.1 ADAMS TVA NRC Accession Number cr79023 Motor Starters and Contactors Failed to Operate NA A-O N.R.R But defective shipment was received and should be addressed cr79025 Shock Arrestor Strut Assembly Interference NA A-O N.R.R but inspections & C.A expected on behalf of WBN 2 cr81013 Torque Switch Electrical Bypass Circuit for Safeguard Service Valve Motors NA A-O Report required if discrepancies found.

Clarify if 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 GL 79-51 Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident NA A-O Applies to all C.P holders and requires implementation of actions GL 79-63 Upgraded Emergency Plans NA A-O Check Applicability. Header (yes) content (No). Request add. Info.

GL 80-11 IEB 80-03 Loss Of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells NA A-O Requires action on behalf of C.P holder GL 80-28 IEB 80-08 Examination Of Containment Liner Penetration Welds NA A-O Info expected to be submitted 90 days after issuance GL 80-32 Information Request on Category I Masonry Walls Employed by Plants Under CP and OL Review NA A-O B80-11 requests actions from all C.P 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 GL 86-04 Policy Statement On Engineering Expertise On Shift NA A-O Applies to O.L.A and requires actions.

Additional info needed.

GL 89-02 Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products NA A-O N.R.R but actions should be taken. Applies to all C.P holders GL 89-21 Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements NA A-O NRC requests review and subsequent report GL 82-28 Inadequate Core Cooling Instrumentation System O

O GL 88-20 Individual Plant Examination for Severe Accident Vulnerability O

O GL 88-20s1 Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54 O

O 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 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Item Title Position Additional Comments Page 45 of 49

Rev.1 ADAMS TVA NRC Accession Number 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 Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Item Title Position Additional Comments GL 88-20s2 Accident Management Stratagies for Consideration in the Individual Plant Examination Process O

O GL 88-20s3 Completion of Containment Performance Improvement Program and Forwarding of Insights for Use in the IPE for SAV O

O GL 88-20s4 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities O

O GL 88-20s5 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - 10 CFR 50.54(f)

O O

GL 07-02 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray systems O

O GL 08-01 Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients O

O 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

Rev.1 ADAMS TVA NRC Accession Number IEB 92-01 Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function OV OV IEB 92-01s1 Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function OV OV IEB 96-01 Control Rod Insertion Problems (PWR)

OV OV IEB 01-01 Circumferential Cracking of Reactor Pressure Vessel (RPV) Head Penetration Nozzles OV OV 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 IEB 03-02 Leakage from RPV Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity OV OV IEB 04-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at PWRs OV OV 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 GL 96-06 Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions OV OV NRC letter 04/06/1999-Implement &

provide containment penetration relief.

GL 96-06s1 NRC Generic Letter 96-06, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions OV OV NRC letter 04/06/1999-Implement &

provide containment penetration relief.

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

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

Ver.1 ADAMS TVA NRC Accession Number cr79023 Motor Starters and Contactors Failed to Operate NA A-O N.R.R But defective shipment was received and should be addressed cr79025 Shock Arrestor Strut Assembly Interference NA A-O N.R.R but inspections & C.A expected on behalf of WBN 2 cr81013 Torque Switch Electrical Bypass Circuit for Safeguard Service Valve Motors NA A-O Report required if discrepancies found. Clarify if 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 GL 79-51 Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident NA A-O Applies to all C.P holders and requires implementation of actions GL 79-63 Upgraded Emergency Plans NA A-O Check Applicability. Header (yes) content (No). Request add. Info.

GL 80-11 IEB 80-03 Loss Of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells NA A-O Requires action on behalf of C.P holder GL 80-28 IEB 80-08 Examination Of Containment Liner Penetration Welds NA A-O Info expected to be submitted 90 days after issuance GL 80-32 Information Request on Category I Masonry Walls Employed by Plants Under CP and OL Review NA A-O B80-11 requests actions from all C.P 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 GL 86-04 Policy Statement On Engineering Expertise On Shift NA A-O Applies to O.L.A and requires actions. Additional info needed.

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

Requirements NA A-O NRC requests review and subsequent report 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; CT= Closed/Technical Specifications; OT=Open/Technical Specifications; OV=Open/Validation; O= Open Item Title Position Additional Comments