ML072570678

Generic Communications Issued Prior to 1995

ML072570678
Person / Time
Site:	Watts Bar
Issue date:	09/07/2007
From:	Bajestani M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML072570678 (47)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 September 7, 2007 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN Pl-35 Washington, D.C. 20555-0001 In the Matter of ) Docket No. 50-391 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) - UNIT 2 - GENERIC COMMUNUCATIONS ISSUED PRIOR TO 1995 The purpose of this letter is to respond to a request made by the Nuclear Regulatory Commission Staff regarding WBN Unit 2 construction completion.

Specifically, the Staff requested that the summary of generic communications, included as part of Attachment 1 to the WBN Unit 2 Construction Reactivation letter (Reference 1) be supplemented with references to closure documentation where applicable. TVA performed a search of docketed material for each Generic Letter and Bulletin. Enclosure 1 to this letter contains the revised attachment. The closure documentation referenced in the Enclosure is available for review at the WBN site.

Some of the WBN Unit 2 related Bulletins and Generic Letters were closed based on a review of the Unit 1 implementing procedures, technical specifications or other activities. As part of the completion of the WBN Unit 2 actions of the Generic Letter or Bulletin, TVA will track and validate that the Unit 2 implementing C-1

U.S. Nuclear Regulatory Commission Page 2 September 7, 2007 procedures, technical specifications and other activities include the same requirements.

In addition, TVA will validate the remaining closed Bulletins and Generic Letters issued prior to 1995 as part of the Watts Bar Unit 2 licensing process. TVA will continue to review generic communications as the WBN Unit 2 Regulatory Framework is developed. TVA will provide a separate submittal to address the initial responses to the new Bulletins and Generic Letters. TVA will address both the open Bulletins and Generic Letters issued prior to 1995 and the new generic communications in the WBN Unit 2 Regulatory Framework submittal.

If you have any questions, please contact me at (423) 365-2351.

Sincerely, Masoud ajestani Watts ar Unit 2 Vice President

References:

1. TVA letter dated August 3, 2007, William R.

McCollum, Jr. to NRC, "Watts Bar Unit 2 -

Reactivation of Construction Activities".

U.S. Nuclear Regulatory Commission Page 3 September 7, 2007 Enclosure (cc w/Enclosure):

Catherine Haney, Director U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Loren R. Plisco, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center, Suite 23T85 61 Forsyth Street, SW, Atlanta, Georgia 30303-8931 U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

U.S. Nuclear Regulatory Commission Page 4 September 7, 2007 JEM:

Enclosure cc (w/Enclosure):

G. Arent, EQB IB-WBN M. Bajestani, EQB IB-WBN R. R. Baron, EQB IB-WBN A. S. Bhatnagar, LP 6A-C R. H. Bryan, BR 4X-C J. C. Fornicola, LP 6A-C M. D. Skaggs, ADM-IV-WBN J. Valente, EQB lB-WBN E. J. Vigluicci, ET llA-K EDMS, WT 3B-K

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document Enclosure 1 Generic Communications IEB 73-01 Faulty Overcurrent Trip Delay Device in Circuit Closed IR 390/391 75-5 IR 390/391 75-5 Breakers for Engineered Safety Systems TVA letter dated TVA letter dated April 4, 1973 April 4, 1973 IEB 73-02 Malfunction of Containment Purge Supply Valve 6.2.4 Closed IR 390/391 75-5 IR 390/391 75-5 Switch TVA letter dated TVA letter dated August 22, 1973 August 22, 1973 IEB 73-03 Defective Hydraulic Snubbers and Restraints 3.9.3 Closed OL @ time NA NA IEB 73-04 Defective Bergen-Patterson Hydraulic Shock 3.9.3 Closed IR 390/391 85-08 IR 390/391 85-08 Absorbers references TVA references TVA memo February 7, memo February 7, 1985 1985 IEB 73-05 Manufacturing Defect in BWR Control Rods NA BWR NA NA IEB 73-06 Inadvertent Criticality in a BWR NA BWR NA NA IEB 74-01 Valve Deficiencies 3.9.3, 3.9.6 Closed IR 390/391 75-5 IR 390/391 75-5 TVA letter dated TVA letter dated April 15, 1974 April 15, 1974 IEB 74-02 Truck Strike Possibility NA Dated issue NA NA IEB 74-03 Failure of Structural or Seismic Support Bolts on 3.9.3 Closed Note 3 IR 390/391 85-08 IR 390/391 85-08 Class I Components references TVA references TVA memo January 22, memo January 22, 1985 1985 IEB 74-04 Malfunction of Target Rock Safety Relief Valves NA BWR NA NA IEB 74-05 Shipment of an Improperly Shielded Source NA Not generation NA NA IEB 74-06 Defective Westinghouse (W) Type W-2 Control Closed IR 390/391 75-6 IR 390/391 75-6 Switch Component TVA letter dated TVA letter dated October 18, 1974 October 18, 1974 IEB 74-07 Personnel Exposure - Irradiation Facility NA Not generation NA NA I

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 74-08 Deficiency in the ITE Molded Case Circuit Breakers, Closed IR 390/391 75-5 IR 390/391 75-5 Type HE-3 TVA letter dated TVA letter dated August 21, 1974 August 21, 1974 IEB 74-09 Deficiencies in GE Model 4KV Magne-Blast Circuit Closed IR 390/391 76-6 IR 390/391 76-6 Breakers TVA letter dated TVA letter dated September 20, September 20, 1974 1974 IEB 74-10 Failures in 4 inch Bypass Pipe at Dresden NA BWR NA NA IEB 74-11 Improper Wiring of Safety Injection Logic at Zion 1 Closed IR 390/391 75-6 IR 390/391 75-6

&2 IEB 74-12 Incorrect Coils in W Type SG Relays at Trojan Closed IR 390/391 75-5 IR 390/391 75-5 IEB 74-13 Improper Factory Wiring on GE Motor Control Closed IR 390/391 75-5 IR 390/391 75-5 Centers at Fort Calhoun TVA letter dated TVA letter dated December 24, 1974 December 24, 1974 IEB 74-14 BWR Relief Valve Discharge to Suppression Pool NA BWR NA NA IEB 74-15 Misapplication of Cutler-Hammer Three Position Closed Note 3 IR 390/391 75-5 IR 390/391 75-5 Maintained Switch Model No. 10250T TVA letter dated TVA letter dated May 5, 1975 May 5, 1975 IEB 74-16 Improper Machining of Pistons in Colt Industries Closed IR 390/391 75-3 IR 390/391 75-3 (Fairbanks-Morse) Diesel Generators TVA letter dated TVA letter dated January 2, 1975 January 2, 1975 IEB 75-01 Through-Wall Cracks in Core Spray Piping at NA BWR NA NA Dresden-2 IEB 75-02 Defective Radionics Radiograph Exposure Devices NA Not generation NA NA and Source Changes IEB 75-03 Incorrect Lower Disc Spring and Clearance 3.9.6 Closed Note 3 IR 390/391 75-6 IR 390/391 75-6 Dimension in Series 8300 and 8302 ASCO TVA letter dated TVA letter dated Solenoid Valves May 16, 1975 May 16, 1975 2

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 75-04 Cable Fire at BFNPP 9.5.1 Closed Note 3 IR 390/391 85-08 IR 390/391 85-08 Closed to Fire Closed to Fire Protection CAP Protection CAP IEB 75-05 Operability of Category I Hydraulic Shock and Sway 3.9.3 Closed Note 3 IR 390/391 75-6 IR 390/391 75-6 Suppressors TVA letter dated TVA letter dated June 16, 1975 June 16, 1975 IEB 75-06 Defective W Type OT-2 Control Switches Closed Note 3 IR 390/ 85-25 391/ IR 390/ 85-25 391/

85-20 TVA letter 85-20 TVA letter dated July 31, 1975 dated July 31, 1975 IEB 75-07 Exothermic Reaction in Radwaste Shipment NA Not generation NA NA IEB 75-08 PWR Pressure Instrumentation Closed Note 3 IR 390/391 85-08 IR 390/391 85-08 IEB 76-01 BWR Isolation Condenser Tube Failure NA BWR NA NA IEB 76-02 Relay Coil Failures Open TVA letter dated May 17, 1976 IEB 76-03 Relay Malfunctions - GE Type STD Relays Closed IR 390/391 76-6 IR 390/391 76-6 TVA letter dated TVA letter dated May 17, 1976 May 17,1976 IEB 76-04 Cracks in Cold Water Piping at BWRs NA BWR NA NA IEB 76-05 Relay Failures Closed IR 390/391 85-08 IR 390/391 85-08 TVA letter dated TVA letter dated June 7, 1976 June 7, 1976 IEB 76-06 Diaphragm Failures in Air Operated Auxiliary 3.9.3, 3.9.6 Closed IR 390/391 85-08 IR 390/391 85-08 Actuators for Safety/Relief Valves References TVA References TVA memo January 25, memo January 25, 1985 1985 3

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 76-07 Crane Hoist Control Circuit Modifications Closed IR 390/391 85-08 IR 390/391 85-08 TVA letter dated TVA letter dated October 29, 1976 October 29, 1976 IEB 76-08 Teletherapy Units NA Not generation NA NA IEB 77-01 Pneumatic Time Delay Relay Setpoint Drift Closed IR 390/391 85-08 IR 390/391 85-08 TVA letter dated TVA letter dated July 1, 1977 July 1, 1977 IEB 77-02 Potential Failure Mechanism in Certain W AR Closed IR 390/391 85-08 IR 390/391 85-08 Relays with Latch Attachments TVA letter date TVA letter date November 11, 1977 November 11, 1977 IEB 77-03 On-Line Testing of the W Solid State Protection Open IR 390/ 78-11 System IEB 77-04 Calculation Error Affecting Performance of a 6.2 Closed Note 3 IR 390/ 78-11 and IR 390/ 78-11 and System for Controlling pH of Containment Sump 391/ 78-09 TVA 391/ 78-09 TVA Water Following a LOCA letter dated January letter dated January 23, 1978 23, 1978 IEB 77-05 Electrical Connector Assemblies Closed IR 390/ 78-11 and IR 390/ 78-11 and

& 77-05 A 391/ 78-09 TVA 391/ 78-09 TVA letter dated January letter dated January 17, 1978 17, 1978 IEB 77-06 Potential Problems with Containment Electrical 3.10, 3.11 Closed OL @ time IR 390 391/ 85-08 IR 390/ 391/ 85-08 Penetration Assemblies IEB 77-07 Containment Electrical Penetration Assemblies at 3.10, 3.11 Closed IR 390/ 78-11 and IR 390/78-11 and Nuclear Power Plants under Construction 391/ 78-09 TVA 391/ 78-09 TVA letter dated January letter dated January 20,1978 20,1978 4

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 77-08 Assurance of Safety and Safeguards During an Closed Site IR 390/ 78-11 and IR 390/ 78-11 and Emergency - Locking Systems 391/ 78-09 IVA 391/ 78-09 TVA letter dated March letter dated March 1, 1, 1978 1978 IEB 78-01 Flammable Contact - Arm Retainers in GE CR120A Closed IR 390/ 78-11 and IR 390/78-11 and Relays 391/ 78-09 TVA 391/ 78-09 TVA letter dated March letter dated March 20, 1978 20, 1978 IEB 78-02 Terminal Block Qualification Closed IR 390/ 78-11 and IR 390/ 78-11 and 391/ 78-09 TVA 391/ 78-09 TVA letter dated March letter dated March 1, 1, 1978 1978 IEB 78-03 Potential Gas Mixture Accumulations Associated NA BWR NA NA with BWR Offgas System Operations IEB 78-04 Environmental Qualification of Certain Stem 3.11 Closed Note 3 IR 390/ 82-13 and IR 390/ 82-13 and Mounted Limit Switches Inside Reactor 391/82-10 Closed 391/82-10 Closed Containment to EQ Program to EQ Program TVA TVA letter dated letter dated December 19, 1978 December 19, 1978 IEB 78-05 Malfunctioning of Circuit Breaker Auxiliary Contact Closed IR 390/ 78-17 and IR 390/ 78-17 and Mechanism 391/ 78-15 TVA 391/ 78-15 TVA letter dated June letter dated June 12, 12, 1978 1978 IEB 78-06 Defective Cutler-Hammer Type M Relays and DC Closed IR 390/ 78-22 and IR 390/ 78-22 and Coils 391/78-19 391/78-19 IEB 78-07 Protection Afforded by Air-Line Respirators and NA Site NA NA Supplied-Air Hoods EB 78-08 Radiation Levels from Fuel Element Transfer Tubes NA Site IR 390/391 85-08 IR 390/391 85-08 5

Item t Title Applicable FSAR Section Status Comments (see notes)

WBN Unit I Closure Document WBN Unit 2 Closure Document IEB 78-09 BWR Drywell Leakage Paths Associated with NA BWR NA NA Inadequate Drywell Closures IEB 78-10 Bergen-Patterson Hydraulic Shock Suppressor 3.9.3 Closed IR 390/ 78-22 and IR 390/ 78-22 and Accumulator Spring Coils 391/ 78-19 TVA 391/ 78-19 TVA letter dated August letter dated August 14,1978 14, 1978 IEB 78-11 Examination of Mark I Containment Torus Welds NA BWR NA NA IEB 78-12 Atypical Weld Material in Reactor Pressure Vessel 5.4 Closed IR 390/391 81-04 IR 390/391 81-04 Welds Westinghouse letter Westinghouse letter dated October 29, dated October 29, 1979 1979 IEB 78-13 Failures in Source Heads Kay Ray Gauge Models NA Not generation NA NA 7050, 7050B, 7051, 7051B, 7060, 7060B, 7061 and 7061B IEB 78-14 Deterioration of Buna-N Components in ASCO NA BWR NA NA Solenoids IEB 79-01 Environmental Qualification of Class 1E Equipment 3.11 Closed IR 390/ 80-06 and IR 390/ 80-06 and 391/80-05 391/80-05 IEB 79-02 Pipe Support Base Plate Designs Using Concrete 3.9.3 Open TVA letter dated Expansion Anchor Bolts August 21, 1995 IEB 79-03 Longitudinal Weld Defects in ASME SA-312 Type 3.9.3, 6.1.1 Closed IR 390/ 82-21 and IR 390/ 82-21 and 304 SS Pipe Spools Fabricated by Youngstown 391/ 82-17, 390/ 391/ 82-17, 390/ 84-Welding & Engineering 84-35 and 391/ 84- 35 and 391/ 84-33, 33, TVA letter TVA letter dated dated July 16, 1981 July 16, 1981 IEB 79-04 Incorrect Weights for Swing Check Valves 3.7, 3.9 Closed IR 390/ 83-15 and IR 390/83-15 and Manufactured by Velan Engineering 391/83-11 TVA 391/83-11 TVA letter dated October letter dated October 20,1980 20, 1980 6

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 79-05 Nuclear Incident at TMI NA B&W NA NA IEB 79-06 Review of Operational Errors and System Closed IR 390/ 80-06 and IR 390/ 80-06 and Misalignments Identified During the Three Mile 391/80-05 391/80-05 Island Incident IEB 79-07 Seismic Stress Analysis of Safety-Related Piping 3.9.3 Closed IR 390/ 79-30 and IR 390/ 79-30 and 391/ 79-25 TVA 391/ 79-25 TVA letter dated May 31, letter dated May 31, 1979 1979 IEB 79-08 Events Relevant to BWRs Identified During TMI NA BWR NA NA Incident IEB 79-09 Failure of GE Type AK-2 Circuit Breaker in Safety Closed Note 3 TVA letter June 20, TVA letter June 20, Related Systems 1979 1979 IEB 79-10 Requalification Training Program Statistics NA Site IR 390/ 80-06 and NA 391/80-05 IEB 79-11 Faulty Overcurrent Trip Device in Circuit Breakers Closed IR 390/ 79-30 and IR 390/ 79-30 and for Engineering Safety Systems 391/ 79-25 TVA 391/ 79-25 TVA letter dated July 20, letter dated July 20, 1979 1979 IEB 79-12 Short Period Scrams at BWR Facilities NA BWR NA NA IEB 79-13 Cracking in Feedwater Piping 3.9.3, 6.1.1 Closed OL @ time IR 390/ 391 85-08 IR 390/ 391 85-08 TVA letter TVA letter December 1, 1983 December 1, 1983 IEB 79-14 Seismic Analysis for As-Built Safety-Related Piping 3.9.3 Open TVA letter August Systems 21,1995 IEB 79-15 Deep Draft Pump Deficiencies 3.9.3, 3.9.6 Closed IR 390/391 95-70 IR 390/391 95-70 TVA letter dated TVA letter dated January 24, 1992 January 24, 1992 7

Item T Title Applicable FSAR Section Status lComments (see notes) WBN ClosureUnit I Document WBN UnitDocument Closure 2 IEB 79-16 Vital Area Access Controls NA Site IR 390/ 80-06 and IR 390/ 80-06 and 391/80-05 391/80-05 IEB 79-17 Pipe Cracks in Stagnant Borated Water Systems at 3.9 NA IR 390/ 80-06 and IR 390/ 80-06 and PWR Plants 391/80-05 391/80-05 NUREG/ CR 5286 NUREG/ CR 5286 IEB 79-18 Audibility Problems Encountered on Evacuation of NA Site IR 390/ 80-06 and IR 390/ 80-06 and Personnel from High-Noise Areas 391/80-05 391/80-05 IEB 79-19 Packaging of Low-Level Radioactive Waste for NA Site IR 390/ 80-06 and IR 390/ 80-06 and Transport and Burial 391/80-05 391/80-05 IEB 79-20 Packaging, Transport and Burial of Low-Level NA Site IR 390/ 80-06 and IR 390/ 80-06 and Radioactive Waste 391/80-05 391/80-05 IEB 79-21 Temperature Effects on Level Measurements Open IR 390/391 95-45 IEB 79-22 Possible Leakage of Tubes of Tritium Gas Used in NA Site IR 390/ 80-06 and IR 390/ 80-06 and Time Pieces for Luminosity 391/80-05 391/80-05 IEB 79-23 Potential Failure of Emergency Diesel Generator Closed IR 390/ 80-06 and IR 390/ 80-06 and Field Exciter Transformer 391/ 80-05 TVA 391/ 80-05 TVA letter dated October letter dated October 29,1979 29, 1979 IEB 79-24 Frozen Lines 6.3 Open IR 390/ 84-59 and 391/84-45 IEB 79-25 Failures of W BFD Relays in Safety Related Closed IR 390/ 80-03 and IR 390/ 80-03 and Systems 391/ 80-02 TVA 391/ 80-02 TVA letter dated January letter dated January 4,1980 4,1980 IEB 79-26 Boron Loss from BWR Control Blades NA BWR NA NA 8

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 79-27 Loss of Non-Class 1E I & C Power System Bus Open IR 390/ 80-12 TVA During Operation letter dated February 5, 1990 and NCO closure IEB 79-28 Possible Malfunction of NAMCO Model EA180 Limit Closed IR 390/391 93-32 IR 390/391 93-32 Switches at Elevated Temperatures TVA letter April 1, TVA letter April 1, 1993 1993 IEB 80-01 Operability of ADS Valve Pneumatic Supply NA BWR NA NA IEB 80-02 Inadequate QA for Nuclear Supplied Equipment NA BWR NA NA IEB 80-03 Loss of Charcoal from Standard Type II, 2 Inch Tray 6.5 Closed IR 390/ 80-15 and IR 390/ 80-15 and Adsorber Cells 391/ 80-12 TVA 391/ 80-12 TVA letter dated March letter dated March 21,1980 21, 1980 IEB 80-04 Analysis of a PWR Main Steam Line Rupture with 3.6, 5.5.9, Open IR 390/ 80-12 and Continued Feedwater Addition 6.2,10.3, 391/ 80-09 390/

10.4 85-60 and 391/ 85-49 IEB 80-05 Vacuum Condition Resulting in Damage to 9.3.4 Open IR 390/ 84-59 and Chemical Volume Control System Holdup Tanks 391/ 84-45 TVA letter dated June 9, 1980 IEB 80-06 Engineered Safety Features Reset Control 6.2.2, 6.3, Open SSER 3 390/ 85-6.5 60 and 391/ 85-49 IEB 80-07 BWR Jet Pump Assembly Failure NA BWR NA NA IEB 80-08 Examination of Containment Liner Penetration 3.8 Closed IR 390/391 81-19 IR 390/391 81-19 Welds TVA letter July 8, TVA letter July 8, 1980 1980 9

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 80-09 Hydramotor Actuator Deficiencies Closed NUREG/ CR 5291 NUREG/ CR 5291 IR 390/391/ 85-08 IR 390/391/ 85-08 IR 390/ 85-60 and IR 390/ 85-60 and 391/ 85-49 TVA 391/ 85-49 TVA letter January 15, letter January 15, 1981 1981 IEB 80-10 Contamination of Non-radioactive System and Open IR 390/391 81-17 Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment IEB 80-11 Masonry Wall Design 3.8.4 Open IR 390/391/ 95-46 IR 390/391/ 93-01 IEB 80-12 Decay Heat Removal System Operability 10.4.7, Closed Note 3 IR 390/391 85-08 IR 390/391 85-08 10.4.8 NUREG/CR 4005 NUREG/CR 4005 IEB 80-13 Cracking in Core Spray Spargers NA BWR NA NA IEB 80-14 Degradation of Scram Discharge Volume Capability NA BWR NA NA IEB 80-15 Possible Loss of Emergency Notification System Closed Site IR 390/391/ 85-08 IR 390/391/ 85-08 with Loss of Offsite Power IEB 80-16 Potential Misapplication of Rosemount Models 1151 Closed IR 390/391/ 81-17 IR 390/391/ 81-17 and 1152 Pressure Transmitters With Either "A" or TVA letter dated TVA letter dated "D" Output Codes August 29, 1980 August 29, 1980 IEB 80-17 Failure of 76 of 185 Control Rods to Fully Insert NA BWR NA NA During a Scram at a BWR IEB 80-18 Maintenance of Adequate Minimum Flow Thru 6.3 Open 390/ 85-60 and Centrifugal Charging Pumps Following a Secondary 391/85-49 Side High Energy Rupture I I 10

Item Title Applicable FSAR Status Comments (see notes) WBN ClosureUnit 1 WBN ClosureUnitDocument 2

Section Document IEB 80-19 Mercury-Wetted Matrix Relay in Reactor Protective Closed NUREG/CR 4933 NUREG/CR 4933 Systems IR 390/391/ 81-17 IR 390/391/ 81-17 TVA letter dated TVA letter dated September4, 1980 September4, 1980 IEB 80-20 Failure of W Type W-2 Spring Return to Neutral Open 390/ 85-60 and Control Switches 391/85-49 390/391/ 94-35 TVA letter dated July 31, 1991 IEB 80-21 Valve Yokes Supplied by Malcolm Foundry Co. 3.9.3, 3.9.6 Closed 390/391/ 85-08 390/391/ 85-08 TVA TVA letter dated letter dated May 6, May 6, 1981 1981 IEB 80-22 Automation Industries, Model 200-520-008 Sealed- NA Not generation NA NA Source Connectors IEB 80-23 Failures of Solenoid Valves Manufactured by Valcor 3.9.3, 3.9.6 Closed IR 390/391/ 81-17 IR 390/391/ 81-17 Eng. Corp NUREG/CR 5292 NUREG/CR 5292 TVA letter dated TVA letter dated March 31, 1981 March 31, 1981 IEB 80-24 Prevention of Damage Due to Water Leakage Open IR 390/391/ 85-08 Inside Containment IR 390/ 85-60 and 391/85-49 IEB 80-25 Operating Problems with Target Rock SR Valves at NA BWR NA NA BWRs IEB 81-01 Surveillance of Mechanical Snubbers 3.9.3 NA IR 390/391/ 81-17 IR 390/391/ 81-17 IEB 81-02 Failure of Gate Type Valves to Close Against 3.9.6 Closed IR 390/391/ 84-03 IR 390/391/ 84-03 Differential Pressure TVA letter dated TVA letter dated September 30, September 30, 1983 1983 II

Item Title FSAR Section J

Applicable] Status Comments (see notes)

WBN Unit 1 ClosureJ Document WBN Unit 2 Closure Document IEB 81-03 Flow Blockage to Cooling Water by Asiatic Clams 9.2.1 Closed IR 390/391 81-17 IR 390/391 81-17 and Mussels TVA letters dated TVA letters dated July 21, 1981, July 21, 1981, March 21, 1983 March 21, 1983 IEB 82-01 Alteration of Radiographs of Welds in Piping 3.9.3 Closed IR 390/391/ 85-08 IR 390/391/ 85-08 Subassemblies IEB 82-02 Degradation of Threaded Fasteners in the Reactor 3.9.3 Closed Note 3 IR 390/391/ 85-08 IR 390/391/ 85-08 Coolant Pressure Boundary of PWR Plants references a references a February 6, 1985 February 6, 1985 TVA memo TVA memo IEB 82-03 Stress Corrosion Cracking in Thick-Wall, Large NA BWR NA NA Diameter, Stainless Steel, Recirculation System Piping at BWR Plants IEB 82-04 Deficiencies in Primary Containment Electrical 3.10, 3.11 Closed IR 390/83-10 and IR 390/83-10 and Penetration Assemblies 391/ 83-08 TVA 391/ 83-08 TVA letter dated January letter dated January 24,1983 24, 1983 IEB 83-01 Failure of Trip Breakers (Westinghouse DB-50) to Closed IR 390/391/ 85-08, IR 390/391/ 85-08, Open on Automatic Trip Signal 390/391/ 92-13 390/391/ 92-13 IEB 83-02 Stress Corrosion Cracking in Large-Diameter NA BWR NA NA Stainless Steel Recirculation System Piping at BWR Plants IEB 83-03 Check Valve Failures in Raw Water Cooling NA Addressed by NA NA Systems of Diesel Generators IST for CP holders IEB 83-04 Failure of the Undervoltage Trip Function of Reactor Closed Note 3 IR 390/391/ 85-08 IR 390/391/ 85-08 Trip Breakers 12

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 83-05 ASME Nuclear Code Pumps and Spare Parts 3.9.3, Closed IR 390/ 85-03 and IR 390/ 85-03 and Manufactured by Hayward Tyler Pump Co 3.9.6,17.1 391/85-04 391/85-04 NUREG/CR 5297 NUREG/CR 5297 TVA letter dated TVA letter dated September 7, 1983 September 7, 1983 IEB 83-06 Nonconforming Material Supplied by Tube-Line 3.9.3, Closed Note 3 IR 390/391 84-03 IR 390/391 84-03 5.2.1, NUREG/CR 4934 NUREG/CR 4934 6.1.1, 17.1 TVA letter dated TVA letter dated February 2, 1984 February 2, 1984 IEB 83-07 Apparently Fraudulent Products Sold by Ray Miller, 17.1 Closed IR 390/ 85-03 and IR 390/ 85-03 and Inc 391/ 85-04 TVA 391/ 85-04 TVA letter dated March letter dated March 22, 1984 22, 1984 IEB 83-08 Electrical Circuit Breakers With Undervoltage Trip in Closed IR 390/ 84-35 and IR 390/ 84-35 and Safety Related Applications other than the Reactor 391/ 84-33 TVA 391/ 84-33 TVA Trip System letter March 29, letter March 29, 1984 1984 IEB 84-01 Cracks in BWR Mark 1 Containment Vent Headers NA BWR NA NA IEB 84-02 Failure of GE Type HFA Relays In Use In Class 1 E Closed IR 390/391/ 84-42 IR 390/391/ 84-42 Safety Systems IR 390/ 84-77 and IR 390/ 84-77 and 391/ 84-54 TVA 391/ 84-54 TVA letter dated July 10, letter dated July 10, 1984 1984 IEB 84-03 Refueling Cavity Water Seal 9.1.1, 9.1.2 Open IR 390/391/ 93-11 TVA letter dated December 6, 1984 13

Item Title lApplicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 85-01 Steam Binding of Auxiliary Feedwater Pumps 10.4.9 Closed Note 3 IR 390/391 90-20 IR 390/391 90-20 TVA letter dated TVA letter dated January 27, 1986 January 27, 1986 IEB 85-02 Undervoltage Trip Attachment of W DB-50 Type Open IR 390/391/ 93-56 Reactor Trip Breakers TVA letter dated December 3, 1985 IEB 85-03 Motor Operated Valve Common Mode Failures 3.9.3, 3.9.6 Closed Superseded During Plant Transients due to Improper Switch by GL 89-10 Settings IEB 86-01 Minimum Flow Logic Problems That Could Disable NA BWR NA NA RHR Pumps IEB 86-02 Static "0"Ring Differential Pressure Switches Closed IR 390/391/ 90-24 IR 390/391/ 90-24 TVA letter dated TVA letter dated November 20, 1986 November 20, 1986 IEB 86-03 Potential Failure of Multiple ECCS Pumps Due to 6.3 Closed IR 390/391/ 87-03 IR 390/391/ 87-03 Single Failure of Air-Operated Valve in Minimum TVA letter dated TVA letter dated Flow Recirculation Line November 14, 1986 November 14, 1986 IEB 86-04 Defective Teletherapy Timer That May Not NA Not generation NA NA Terminate Treatment Dose IEB 87-01 Thinning .of Pipe Walls in Nuclear Power Plants 3.9.3, 6.1 Closed Closed to GL NUREG/CR 5287 NUREG/CR 5287 89-08 TVA letter dated TVA letter dated September 18, September 18, 1987 1987 14

WBN Unit 2 Unit I1 WBN Unit I

Item Title Applicable Status Comments WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 87-02 Fastener Testing to Determine Conformance with 17.1 Closed Note 3 NRC letter dated NRC letter dated Applicable Material Specifications August 18, 1989 August 18, 1989 TVA letters dated TVA letters dated April 15, 1988, July April 15, 1988, July 6, 1988, September 6, 1988, September 12, 1988 and 12, 1988 and January 27, 1989 January 27, 1989 IEB 88-01 Defects in W Circuit Breakers Closed IR 390/391/ 93-01 IR 390/391/ 93-01 TVA letter dated TVA letter dated November 15, 1991 November 15, 1991 IEB 88-02 Rapidly Propagating Fatigue Cracks in Steam 5.5.2 Open IR 390/391/ 90-24 Generator Tubes NRC letter dated June 7, 1990, SSER 6, TVA letters dated March 31, 1998, March 1, 1989 and April 16, 1990 IEB 88-03 Inadequate Latch Engagement in HFA Type Closed IR 390/391/ 92-13 IR 390/391/ 92-13 Latching Relays Manufactured by General Electric TVA letter dated TVA letter dated (GE) Company April 13, 1992 April 13, 1992 IEB 88-04 Potential Safety-Related Pump Loss 5.5.7, 6.3 Open IR 390/391/ 94-10 IR 390/391/ 95-70 TVA letters dated June 29, 1989 and December 20, 1990 15

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 88-05 Nonconforming Materials Supplied by Piping 3.9.3, 6.1, Open IR 390/ 391/ 92-26 Supplies, Inc. and West Jersey Manufacturing 17.1 NRC SE June 11, Company 1992, TVA letters August 1, 1991, January 14, 1992 and April 21, 1992 IEB 88-06 Actions to be Taken for the Transfer of Model No. NA Not generation NA NA SPEC 2-T Radiographic Exposure Device IEB 88-07 Power Oscillations in BWRs NA .BWR NA NA IEB 88-08 Thermal Stresses in Piping Connected to Reactor 3.9.3, Open IR 390/391/ 94-55 Cooling Systems 5.5.7, 6.3 Partial SE October 21, 1994, SSE June 26, 1995, TVA letters August 6, 1990, March 29, 1994, January 10, 1995 and April 24, 1995 IEB 88-09 Thimble Tube Thinning in Westinghouse Reactors 5.2 Open TVA letters March 11, 1994 and November 4, 1997 IEB 88-10 Nonconforming Molded-Case Circuit Breakers Open IR 390/391/ 93-11 TVA letter November 8, 1989 16

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 88-11 Pressurizer Surge Line Thermal Stratification 3.9.3 Open IR 390/391/ 94-55 NRC SEs dated October 30, 1992 and April 28, 1993, TVA letters March 30, 1992 and June 22, 1992 IEB 89-01 Failure of Westinghouse Steam Generator Tube 5.5.2 Open IR 390/391/ 90-33, Mechanical Plugs NRC letters June 22, 1990 and September 26, 1991, TVA letters June 16, 1989, November 13, 1990 and August 6, 1991 IEB 89-02 Stress Corrosion Cracking of High-Hardness Type 3.9.3, Open IR 390/391 90-20 410 Stainless Steel Preloaded Bolting in Anchor 3.9.6, 6.1 NRC letter dated Darling Model S350W Swing Check Valves or June 22, 1990, TVA Valves of Similar Nature letters June 1, 1988 and April 25, 1990 IEB 89-03 Potential Loss of Required Shutdown Margin During 9.1 Closed Note 3 IR 390/391/ 94-04 IR 390/391/ 94-04 Refueling Operations NRC letter dated NRC letter dated June 22, 1990, June 22, 1990, TVA TVA letter dated letter dated June 19, June 19, 1990 1990 17

Item Title Applicable Status Comments WBN Unit 1 lWBN Unit 2 FSAR (see notes) Closure Closure Document Section Document IEB 90-01 Loss of Fill-Oil in Transmitters Manufactured by Open IR 390/391/ 94-04 Rosemount NRC letter dated October 20, 1994, TVA letters dated January 31, 1992 and January 19, 1994 B 90-02 Loss of Thermal Margin Caused by Channel Box NA BWR NA NA Bow B 91-01 Reporting Loss of Criticality Safety Controls NA Not generation NA NA B 92-01 Failure of Thermo-Lag 330 Fire Barrier System to Open IR 390/391/ 93-29 Perform its Specified Fire Endurance Function SSER 18, TVA letter dated October 16,1992 B 93-01 Release of Patients After Brachytherapy Treatment NA Not generation NA NA with Remote Afterloading Devices B 92-02 Safety Concerns Related to "End of Life" of Aging NA Not generation NA NA Theratronics Teletherapy Units B 93-02 Debris Plugging of Emergency Core Cooling NA BWR NA NA Suction Strainers B 93-03 Resolution of Issues Related to Reactor Vessel NA BWR NA NA Water Level Instrumentation in BWRs B 94-01 Potential Fuel Pool Draindown Caused by NA Permanently NA NA Inadequate Maintenance Practices at Dresden Shutdown plants B 95-01 Quality Assurance Program for Transportation of NA Not generation NA NA Radioactive Material 18

Item Title Applicable TStatus Comments WBN Unit I TWBN Unit 2 FSAR (see notes) Closure Closure Document Section Document B 95-02 Unexpected Clogging of a Residual Heat Removal NA BWR NA NA Pump Strainer While Operating in Suppression Pool Cooling Mode B 96-01 Control Rod Insertion Problems (PWR) 4.2 Open NRC letter dated July 22, 1996 TVA letter dated April 5, 1996 B 96-02 Movement of Heavy Loads over Spent Fuel, over 3.8.6, 9.1 Open NRC letter dated Fuel in the Reactor, or over Safety-Related May 20, 1998, Equipment SSER 13, TVA letter dated May 13, 1996 B 96-03 Potential Plugging of ECCS Suction Strainers by NA BWR NA NA Debris in BWRs B 97-01 Potential for Erroneous Calibration, Dose Rate, or NA Not generation NA NA Radiation Exposure Measurements with Certain Victoreen Model 530 and 531 SI Electrometers, Dose Meters B 97-02 Puncture Testing of Shipping Packages Under 10 NA Not generation NA NA CFR Part 71 B 01-01 Circumferential Cracking of Reactor Pressure 5.2.3, Open NRC letter dated Vessel (RPV) Head Penetration Nozzles 5.2.4, November 20, 2001 5.2.5, 5.4 TVA letters dated August 31, 2001 and April 22, 2002 19

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document B 02-01 RPV Head Degradation and Reactor Coolant 5.2.3, Open NRC letter dated Pressure Boundary Integrity 5.2.4, May 20, 200 TVA 5.2.5, 5.4 letters dated April 2, 2002, May 17, 2002, January 24, 2003 and February 27, 2003 B 02-02 RPV Head and Vessel Head Penetration Nozzle 5.4 Open NRC letter dated Inspection Program December 20, 2002 TVA letters dated September 11, 2002 and February 27, 2003 B 03-01 Potential Impact of Debris Blockage on Emergency 6.2 Open NRC letter dated Sump Recirculation September 20, 2005 TVA letters dated August 8, 2003, April 6, 2004, November 19, 2004 and August 5, 2005 B 03-02 Leakage from RPV Lower Head Penetrations and 5.2.3 - Open NRC letter dated Reactor Coolant Pressure Boundary Integrity 5.2.5, 5.4 October 6, 2004 TVA letters dated September 22, 2003 and December 10, 2003 B 03-03 Potentially Deficient 1-inch Valves for Uranium NA Not generation NA NA Hexaflouride Cylinders 20

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document B 03-04 Rebaselining of Data in the Nuclear Management Closed Site TVA letter dated TVA letter dated and Safeguards System December 18, 2003 December 18, 2003 B 04-01 Inspection of Alloy 82/182/600 Materials Used in the 3.9.3, 6.1 Open TVA letters dated Fabrication of Pressurizer Penetrations and Steam July 27, 2004, Space Piping Connections at PWRs February 11, 2005 and May 24, 2005 B 05-01 Material Control and Accounting of Reactors and Closed Site TVA letters dated TVA letters dated Spent Fuel Storage Facilities March 21,2005 March 21, 2005 and and May 11, 2005 May 11, 2005 B 05-02 Emergency Preparedness and Response Actions Closed Site TVA letters dated TVA letters dated for Security Based Events January 20, 2006 January 20, 2006 and August 16, and August 16, 2006. 2006.

GL 77-06 Questionnaire Related to Steam Generators NA OL @ time NA NA GL 77-07 Reliability of Standby Diesel Generator Units NA OL @ time NA NA GL 78-02 Asymmetric Loads Background and Revised 3.1, 3.9.3, Open Request for Additional Information 3.9.5 GL 78-03 Request for Information on Cavity Annulus Seal 9.1.1, 9.1.2 Open See IEB 84-03 SSER 6, Section Ring 1.4.2 GL 78-04 Steam Generator Operating History NA OL @ time NA NA GL 78-09 Multiple Subsequent Actuations of Safety Relief NA BWR NA NA Valves Following an Isolated Event GL 78-15 Request for Information on Control of Heavy Loads NA Addressed by NA NA Near Spent Fuel later BU/GLs 21

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 78-34 Reactor Vessel Atypical Weld Material 5.4.2, 6.1 Open See IEB 78-12 NA NA GL 79-20 Cracking in Feedwater Lines 3.9.3, 6.1 Open See IEB 79-13 NA NA GL 79-24 Multiple Equipment Failures in Safety Related NA OL @ time NA NA Systems GL 79-36 Adequacy of Station Electric Distribution Systems 8.2, 8.3.1 Open TVA letter dated Voltages October 9, 1981, SSERs, Section 8.3.1.2, IR 50-390, 391/84-90, Confirmatory Issue 28 GL 79-42 Potentially Unreviewed Safety Question on NA OL @ time NA NA Interaction Between Non-Safety Grade Systems and Safety Grade Systems GL 79-46 Containment Purge and Venting During Normal NA OL @ time NA NA Operation GL 79-52 Radioactive Release at No. Anna Unit 1 and NA OL @ time NA NA Lessons Learned GL 79-57 Acceptance Criteria for Mark I Long Term Program NA BWR NA NA GL 79-58 ECCS Calculations on Fuel Cladding NA OL @ time NA NA GL 80-02 QA Requirements Regarding Diesel Generator Fuel Closed FSAR Section FSAR Section Oil 9.5.4.2 9.5.4.2 GL 80-13 Qualification of Safety Related Electrical Equipment NA OL @ time NA NA GL 80-14 LWR Primary Coolant System Pressure Isolation 3.9.3, Closed Note 3 SSER 6, Section SSER 6, Section Valves 3.9.6, 5.5 1.14.2, FSAR 1.14.2, FSAR 22

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document Section 5.2.7.4 Section 5.2.7.4 GL 80-18 Crystal River 3 Reactor Trip From Approximately NA B &W NA NA 100% Full Power GL 80-21 Vacuum Condition Resulting in Damage to 9.3.4 Open Chemical Volume Control System Holdup Tanks GL 80-32 Information Request on Category I Masonry Walls NA Addressed by NA NA Employed by Plants Under CP and OL Review IEB 80-11 GL 80-34 Clarification of NRC Requirements for Emergency NA Site Response Facilities at Each Site GL 80-38 Summary of Certain Non-Power Reactor Physical NA Not generation NA NA Protection Requirements GL 80- A-12, Fracture Toughness and Additional Guidance 3.1, 3.9.3 Open TVA letters dated 46/47 on Potential for Low Fracture Toughness and September 11, Laminar Tearing on PWR Steam Generator Coolant 1981 and October Pump Supports 23,1981. NRC letter dated August 10,1981 GL 80-53 Decay Heat Removal Capability NA OL @ time NA NA GL 80-60 Request for Information Regarding Evaluation NA Site Times GL 80-77 Refueling Water Level - Technical Specifications Closed Note 3 Technical Changes Specification GL 80-84 BWR Scram System NA BWR NA NA GL 80-90 NUREG-0737, TMI (Prior and future GLs, with the Open See NUREG NA NA exception of certain discrete scopes, have been list screened into NUREG list for those applicable to Watts Bar 2)

GL 80-95 A-10, NUREG-0619, "BWR Feedwater Nozzle and NA BWR NA NA 23

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document Control Rod Drive Return Line Cracking" GL 80-113 Control of Heavy Loads Closed See later GLs, NA NA IEBs GL 81-03 NUREG-0313, Technical Report on Material NA BWR NA NA Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping GL 81-04 Emergency Procedures and Training for Station Closed Subsumed by NA NA Blackout SB GL 81-07 Control of Heavy Loads 9.1.4 Open TVA letters dated October 28, 1981, August 25, 1982, February 6, 1984, March 20, 1984, September 24, 1984, January 24, 1986, July 28, 1993, SSER, 9.1.4, License Condition 39 GL 81-12 Fire Protection Rule (and prior related GLs) Closed OL @ time SSER 18 and 19 Corrective Action Note 3 9.5.1 Program GL 81-14 Seismic Qualification of Auxiliary Feedwater Closed OL @ time FSAR, Section FSAR, Section Systems Note 3 10.4.9 10.4.9 GL 81-20, Safety Concerns Associated With Pipe Breaks in NA BWR NA NA

-30, -34, - the BWR Scram System 35 24

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 81-21 Natural Circulation Cooldown 5.5 Open TVA letter dated December 3, 1981 and July 11, 1991 and SSER 16, Confirmatory Issue 15, SSER 10 GL 82-28 Inadequate Core Cooling Instrumentation System 4.4 Open TVA letter dated June 29, 1983 and SSER 10, License Condition 3 GL 82-33 Supplement to NUREG-0737, Requirements for 7.5.2 Open TVA letters dated Emergency Response Capability January 13, 1981, August 20, 1981, April 15, 1983, July 27, 1983, October 31, 1983, January 4, 1984, March 7, 1995. NRC letter dated March 27, 1992 GL 83-08 Modification of Vacuum Breakers on Mark I NA BWR NA NA Containments GL 83-10c Automatic Trip of Reactor Coolant Pumps 5.5 Closed Note 3 TVA letters dated TVA letters dated January 5, 1984 January 5, 1984 and and June 25, 1984. June 25, 1984. NRC NRC letter dated letter dated June 8, June 8, 1990. 1990.

25

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 83-28 Required Actions Based on Generic Implications of 15.2 Salem ATWS Events (Prior and future GLs, with the exception of certain discrete scopes, have been screened into the following list):

1.2 - Post Trip Review Data and Information Closed TVA letters dated TVA letters dated Capability November 7, 1983 November 7, 1983 and December 4, and December 4, 1987, IR 50-390, 1987, IR 50-390, 391/86-04 391/86-04 2.1 - Equipment Classification and Vendor Interface Closed Note 3 TVA letters dated TVA letters dated (Reactor Trip System Components) November 7, 1983 November 7, 1983 and August 24, and August 24, 1990, NRC letters 1990, NRC letters dated October 20, dated October 20, 1986 and June 18, 1986 and June 18, 1990 1990 2.2 - Equipment Classification and Vendor Interface Open TVA letters dated (All SR Components) November 7, 1983, June 4, 1984, September 7, 1984, March 22, 1985, May 31, 1985, December 4, 1987, February 7, 1990.

NRC letters dated June 1, 1989 and September 7, 1990 3.1 - Post-Maintenance Testing (Reactor Trip Closed Note 3 TVA letters dated TVA letters dated System Components) November 7, 1983, November 7, 1983, January 17, 1986 January 17, 1986 26

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document and November 1, and November 1, 1993. NRC letters 1993. NRC letters dated December dated December 10, 10, 1985, October 1985, October 27, 27, 1986 and July 1986 and July 2, 2, 1990; IR 390, 1990; IR 390, 391/86-04 391/86-04 3.2 - Post-Maintenance Testing (All SR Closed Note 3 TVA letters dated TVA letters dated Components) November 7, 1983, November 7, 1983, January 17, 1986 January 17, 1986 and November 1, and November 1, 1993. NRC letters 1993. NRC letters dated December dated December 10, 10, 1985, October 1985, October 27, 27, 1986 and July 1986 and July 2, 2, 1990; IR 390, 1990; IR 390,

_ 391/86-04 391/86-04 4.1 - Reactor Trip System Reliability (Vendor Open TVA letters dated Related Modifications) November 7, 1983, May 19, 1985, January 17, 1986, November 1, 1993.

NRC letters dated July 26, 1985 and May 28, 1986 (IR 50-390/86-04 and 50-391/86-04) 27

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 t FSAR Section (see notes) Closure Document Closure Document J

4.2 - Reactor Trip System Reliability (Preventive Closed Note 3 TVA letters dated TVA letters dated Maintenance and Surveillance Program for Reactor November 7, 1983, November 7, 1983, Trip Breakers) February 10, 1986 February 10, 1986 and May 19, 1986. and May 19, 1986.

NRC letters dated NRC letters dated July 26, 1985 and July 26, 1985 and June 18, 1992, June 18, 1992, SSER 16 SSER 16 4.3 - Reactor Trip System Reliability (Automatic Closed TVA letters dated TVA letters dated Actuation of Shunt Trip Attachment) November 7, 1983, November 7, 1983, March 22, 1985. IR March 22, 1985. IR 50-390/86-04 and 50-390/86-04 and 50-391/86-04, NRC 50-391/86-04, NRC letter dated June letter dated June 18, 18, 1990, License 1990, License Condition 40 Condition 40 4.5 - Reactor Trip System Reliability (Automatic Closed Note 3 TVA letters dated TVA letters dated Actuation of Shunt Trip Attachment) November 7, 1983 November 7, 1983 and July 26, 1985. and July 26, 1985.

NRC letters dated NRC letters dated June 28, 1990 and June 28, 1990 and October 9, 1990, October 9, 1990, SSERs 6 and 16 SSERs 5 and 16 GL 84-09 Recombiner Capability Requirements of 10 CFR NA BWR NA NA 50.44(c)(3)(ii)

GL 84-11 Inspection of BWR Stainless Steel Piping NA BWR NA NA GL 84-23 Reactor Vessel Water Level Instrumentation in NA BWR NA NA BWRs 28

Title Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 84-24 Certification of Compliance to 10 CFR 50.49 3.11 Closed Incorporated NA NA into license review GL 85-02 Recommended Actions Stemming From NRC 5.5.2 Open TVA letter dated Integrated Program for the Resolution of June 17, 1985 Unresolved Safety Issues Regarding Steam Generator Tube Integrity GL 85-11 Completion of Phase II of "Control of Heavy Loads Closed See GL 81-07 NA NA at Nuclear Power Plants" GL 85-12 Implementation of TMI Item II.K.3.5 15.5.4 Open TVA letter dated October 29, 1981, IR 50-390/95-70 and 50-391/95-70 GL 86-05 Implementation of TMI Item II.K.3.5 NA B &W NA NA GL 86-06 Implementation of TMI Item II.K.3.5 NA CE NA NA GL 87-02 Verification of Seismic Adequacy of Mechanical and NA Previously NA NA

& 03 Electrical Equipment in Operating Reactors, USI A- operated 46 plants GL 87-05 Request for Additional Information on Assessment NA BWR NA NA of License Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells GL 87-06 Periodic Verification of Leak Tight Integrity of NA OL @ time NA NA Pressure Isolation Valves GL 87-12 Loss of Residual Heat Removal While The Reactor 5.4.7 Closed Note 3 TVA letter October TVA letter October Coolant System is Partially Filled 2,1987, SSER 16 2,1987, SSER 16 GL 88-01 NRC Position on IGSCC in BWR Austenitic NA BWR NA NA Stainless Steel Piping 29

Item Title Applicable FSAR Status ]Comments (see notes)

WBN Unit 1 Closure

[WBN Unit 2 Closure Document Section Document GL 88-03 Resolution of GSI 93, Steam Binding of Auxiliary 10.4.9 Closed Note 3 TVA letter June 3, TVA letter June 3, Feedwater Pumps 1988. NRC letters 1988. NRC letters dated February 17, dated February 17, 1988 and July 20, 1988 and July 20, 1988, SSER 16 1988, SSER 16 GL 88-05 Boric Acid Corrosion of Carbon Steel Reactor 5.2 Open TVA letter dated Pressure Boundary Components in PWR plants June 1, 1988, NRC letter dated August 8, 1990 GL 88-07 Modified Enforcement Policy Relating to 10 CFR 3.11 Closed To Special NA NA 50.49, EQ of Electrical Equipment Important to Program Safety for Nuclear Power Plants GL 88-11 NRC Position on Radiation Embrittlement of 5.2.3, Open TVA letter dated Reactor Vessel Material and its Impact on Plant 5.2.4, December 9, 1988, Operations 5.2.5, 5.4 NRC letter dated June 29, 1989 GL 88-14 Instrument Air Supply System Problems Affecting 9.3.1 Open TVA letters dated Safety-Related Equipment February 23, 1989, May 12, 1989, July 12, 1990, August 23, 1994, July 14, 1995. NRC letters dated July 26, 1990 and July 27, 1995, IR 390 and 391/93-

_43 30

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 88-17 Loss of Decay Heat Removal 4.4, 6.2,6.3 Open TVA letters dated February 2, 1989, May 31, 1989, February 7, 1995, October 10, 1995.

NRC letters dated June 19, 1990, October 2, 1990, March 8, 1995 GL 88-20 Individual Plant Examination for Severe Accident Open TVA letters dated Vulnerability October 30, 1989, May 25, 1990, December 20, 1991, February 11, 1993, December 27,1993, May 2, 1994. NRC letters dated November 9, 1989, January 12, 1990, October 5, 1994 GL 89-04 Guidelines on Developing Acceptable Inservice 3.9.3, 3.9.6 Open TVA letters dated Testing Programs August 21, 1989, July 22, 1994, Outstanding Issue 3

GL 89-06 TMI Action Plan Item I.D.2 - Safety Parameter 7.5.2 Open TVA letters dated Display System July 11, 1989 and November 7, 1997 31

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 89-07 Power Reactor Safeguards Contingency Planning Closed TVA letter dated IVA letter dated for Surface Vehicle Bombs October 31, 1989, October 31, 1989 NRC memo dated and NRC memo June 26, 1990 and dated June 26, 1990 IR 50-390/95-70 and 50-391/95-70 GL 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning 6.6, 10.3, Open TVA letter dated 10.4.7 July 19, 1989 and NRC memo dated June 26, 1990 GL 89-10 Safety-Related Motor-Operated Valve Testing and 6.9 Open TVA letters dated Surveillance December 21, 1989, August 9, 1995, September 15,1995. NRC letter dated September 14, 1990 GL 89-13 Service Water System Problems Affecting Safety 9.2.1 Open TVA letters dated Related Equipment January 26, 1990 and November 5, 1997. NRC letters dated September 9, 1990 and June 13, 1994 GL 89-15 Emergency Response Data System NA Site GL 89-16 Installation of a Hardened Wetwell Vent NA BWR NA NA 32

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 I FSAR (see notes) Closure Closure Document Section Document GL 89-19 Request for Actions Related to Resolution of 7.7, 10.3 Open TVA letter dated Unresolved Safety Issue A-47 "Safety Implication of March 22, 1990.

Control Systems in LWR Nuclear Power Plants" NRC letter dated Pursuant to 10 CFR 50.54(f) October 29, 1990 GL 89-20 Protected Area Long Term Housekeeping NA Site GL 89-22 Potential For Increased Roof Load Due to Changes 2.3 Open in Maximum Precipitation GL 90-06 Resolution of Generic Issues 70, "PORV and Block 5.2.2, 5.5.7 Open TVA letter dated Valve Reliability," and 94, "Additional LTOP December 21, Protection for PWRs" 1990. NRC letter dated January 9, 1991.

GL 91-06 Resolution of Generic Issue A-30, "Adequacy of NA OL @ time NA NA Safety Related DC Power Supplies" GL 91-11 Resolution of Generic Issues A-48, "LCOs for Class NA OL @ time NA NA 1E Vital Instrument Buses", and 49, "Interlocks and LCOs for 1E Tie Breakers" GL 91-13 Request for Information Related to Resolution of NA Selected NA NA Generic Issue 130, "Essential Service Water plants System Failures @ Multi-Unit Sites" GL 92-01 Reactor Vessel Structural Integrity 5.2.3, Open TVA letters dated 5.2.4, July 7, 1993, 5.2.5, 5.4 October 15, 1993 and June 13, 1994.

NRC letters dated May 11, 1994 and July 14,1999 33

Item Title Applicable Status Comments WBN Unit I WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 92-04 Resolution of Issues Related to Reactor Vessel NA BWR NA NA Water Level Instrumentation in BWRs GL 92-08 Thermo-Lag 330-1 Fire Barriers 9.5.1 Open TVA letters dated April 16,1993, June 30, 1993, March 22, 1995 and June 15, 1995.

NRC letter dated January 6, 1998 GL 93-01 Emergency Response Data System Test Program NA Site GL 93-04 Rod Control System Failure and Withdrawal of Rod 4.4 Open TVA letters dated Control Cluster Assemblies, 10 CFR 50.54(f) August 5, 1993, September 20, 1993, December 28,1995, SSER 16 GL 94-02 Long Term Solutions and Upgrade of Interim NA BWR NA NA Operating Recommendations for Thermal/Hydraulic Instabilities in BWRs GL 94-03 IGSCC of Core Shrouds in BWRs NA BWR NA NA GL 95-01 NRC Staff Technical Position on Fire Protection for NA Not generation NA NA Fuel Cycle Facilities GL 95-03 Circumferential cracking of Steam Generator (SG) 5.5.2 Open TVA letter dated Tubes June 27, 1995.

NRC letter dated May 16,1997 34

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 95-05 Voltage Based Repair Criteria for W SG Tubes 5.5.2 Open No specific TVA letter dated Affected by Outside Diameter Stress Corrosion action or June 14, 2002.

Cracking response NRC letters dated required July 24, 2000 and February 26, 2002.

GL 95-07 Pressure Locking and Thermal Binding of Safety- 6.9 Open TVA letters dated Related Power-Operated Gate Valves February 13, 1996, March 15, 1996 and July 26, 1996.

NRC letters dated June 28, 1996, May 28, 1999 and September 15, 1999 (SE)

GL 96-01 Testing of Safety-Related Circuits Open TVA letter dated April 18, 1996 GL 96-03 Relocation of the Pressure Temperature Limit 5.2.2, 5.2.4 Open TVA letters dated Curves and Low Temperature Overpressure July 31, 1995, Protection System Limits September 8, 1995 and June 20, 1997.

NRC letter dated September 22, 1995.

35

TStatus Item Title

[Applicable FSAR Section Comments (see notes)

WBN Unit 1 Closure Document WBN Unit 2 Closure Document GL 96-05 Periodic Verification of Design-Basis Capability of 6.9 Open TVA letters dated Safety-Related Motor-Operated Valves November 18, 1996, March 17, 1997, April 28, 1998 and April 26, 1999. NRC letters dated January 27, 1999, July 21, 1999 GL 96-06 Assurance of Equipment Operability and 9.2.1, 9.2.2 Open TVA letters dated Containment Integrity During Design-Basis Accident October 30, 1996, Conditions January 28, 1997, August 31, 1998 and December 21, 1998. NRC letters dated May 27, 1998, July 9, 1998 and April 6, 1999 GL 97-01 Degradation of Control Rod Drive Mechanism 5.2.3, Open TVA letters dated Nozzle and Other Vessel Closure Head 5.2.4, 5.2.5 April 30, 1997, July Penetrations 30, 1997 and February 11, 1999.

NRC letters dated September 25, 1998 and November 4, 1999 36

Item Title Applicable TStatus Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document GL 97-04 Assurance of Sufficient Net Positive Suction Head 6.2.2, 6.3 Open TVA letters dated for Emergency Core Cooling and Containment Heat November 4, 1997 Removal Pumps and December 22, 1997. NRC letter dated June 17, 1998 GL 97-05 SG Tube Inspection Techniques 5.5.2 Open TVA letter dated March 16, 1998.

NRC letter dated September 22, 1998 GL 97-06 Degradation of SG Internals 5.5.2 Open TVA letter dated March 30, 1998.

NRC letter dated October 19, 1999 GL 98-01 Year 2000 Readiness of Computer Systems at NA Site NA NA Nuclear Power Plants GL 98-02 Loss of Reactor Coolant Inventory and Associated 5.5.7, 6.3 Open TVA letter dated Potential for Loss of Emergency Mitigation November 24, Functions While in a Shutdown Condition 1998, IR 50-390/99-11 and 50-391/99-11 GL 98-04 Potential for Degradation of the ECCS and the 6.1.2, Open TVA letter dated Containment Spray System After a LOCA Because 6.2.2, 6.3 November 10, of Construction and Protective Coating Deficiencies 1998. NRC letter and Foreign Material in Containment dated November 24, 1999 GL 99-02 Laboratory Testing of Nuclear Grade Activated NA Site Charcoal 37

Item Title lApplicable Status Comments WBN Unit 1 WBN Unit 2

_FSAR (see notes) Closure Closure Document Section Document GL 03-01 Control Room Habitability 6.4 Open TVA letters dated August 3, 2003 and August 4, 2004.

GL 04-01 Requirements for SG Tube Inspection 5.5.2 Open TVA letter dated October 29, 2004.

NRC letter dated April 8, 2005 GL 04-02 Potential Impact of Debris Blockage on Emergency 6.2.2 Open TVA letters dated Recirculation during Design Basis Accidents at March 7, 2005, July PWRs 21, 2005, September 1, 2005 and April 11, 2006.

NRC letters dated June 3, 2005, February 10, 2006 and May 10, 2006 GL 06-01 SG Tube Integrity and Associated Technical 5.5.2 Open TVA letter dated Specifications February 21, 2006.

GL 06-02 Grid Reliability and the Impact on Plant Risk and 8.0, 8.1, Open NRC letter dated the Operability of Offsite Power 8.2, 8.3 May 3, 2007 TVA letters dated April 3, 2006 and January 31, 2007 GL 06-03 Potentially Nonconforming Hemyc and MT Fire 9.5.1 Open TVA letter dated Barrier Configurations June 7, 2006 and NRC letter dated January 31, 2007 GL 07-01 Inaccessible or Underground Power Cable Failures 8.3.1 Open TVA letter dated that Disable Accident Mitigation Systems or Cause May 4, 2007 Plant Transients I I I 38

Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document NUREG Control of Heavy Loads 9.1.4 Open Due to GL 81- See GL 81-07 0612 07 commitment NUREG TMI Items (TVA letter dated September 14, 1981 0737 applies to all)

I.C.1 Short term accident and procedure review 13.5 Open SSER 16 I.C.7 NSSS vendor revision of procedures 13.5 Open NRC letter dated March 29, 1985, SSER 16.

I.C.8 Pilot monitoring of selected emergency NRC letter dated procedures for NTOLs 13.5 Open March 29, 1985, SSER 16.

I.D.1 CRDR 6.4 Open TVA letters dated October 2, 1987 and February 23, 1990. NRC letters dated March 29, 1985, December 23,1993, SSER 16.

I.D.2 Plant-safety-parameter-display console 7.5.2 Open TVA letter dated November 1, 1990.

NRC letter dated March 29, 1985, SSER 16.

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Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document II.E.1.1 Auxiliary feedwater system evaluation, 10.4.9 Open NRC letters dated modifications March 29, 1985 and October 31, 1995, SSER 16.

II.E.1.2 Auxiliary feedwater system initiation and 7.3, 7.5 Closed Note 3 IR 50-390/84-20 IR 50-390/84-20 and flow and 50-391/84-16, 50-391/84-16, NRC NRC letters dated letters dated March March 29, 1985 29, 1985 and and October 31, October 31, 1995, 1995, SSER 16. SSER 16.

II.E.3.1 Emergency power for pressurizer heaters 8.3.1 Closed Note 3 NRC letters dated NRC letters dated March 29, 1985 March 29, 1985 and and October 31, October 31, 1995, 1995, SSER 16. SSER 16 I1.E.4.1 Dedicated Hydrogen Penetrations Closed IR 50-390/83-27 IR 50-390/83-27 and and 50-391/83-19, 50-391/83-19, SER SER (NUREG- (NUREG-0847) 0847)

I1.E.4.2 Containment isolation dependability 6.2.4,7.3 Closed Note 3 TVA letters dated TVA letters dated October 29, 1981 October 29, 1981 and February 25, and February 25, 1985. NRC letters 1985. NRC letters dated March 29, dated March 29, 1985, July 12, 1990 1985, July 12, 1990 and October 31, and October 31, 1995, SSER 16. 1995, SSER 16.

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Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document I Section - Document TVA letters dated October 29, 1981 I.F.1.2. Accident-monitoring instrumentation and August 12, 1982, and NRC letter dated March 29, 1985, apply to A-F.

A. - Noble gas 7.5 Open B. - Iodine/particulate sampling 7.5 Open TVA letter dated April 26, 1985 C. - Containment high range monitoring 7.5 Open D. - Containment pressure 7.5 Open E. - Containment water level 7.5 Open F. - Containment hydrogen 7.5 Open II.F.2 Instrumentation for detection of 4.4, 6.3, Open TVA letters dated inadequate core-cooling 7.5 October 29, 1981, August 12, 1982, February 25, 1985, September 19, 1985 and January 24,1992. NRC letter dated March 29, 1985, SSER 16 II.G.1 Power supplies for pressurizer relief 7.4, 7.5, Open NRC letter dated valves, block valves and level indicators 8.3.1 March 29, 1985, SSER 16.

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Item Title 1Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document ll.K.1.5 Review ESF valves Closed See IEB 79-06 NRC letter dated NRC letter dated and 80-06 March 29, 1985, March 29, 1985, SSER 16. SSER 16.

ll.K.1.10 Operability status Open NRC letter dated March 29, 1985, SSER 16.

ll.K.1.17 Trip per low-level B/S Closed See IEB 79- NRC letter dated NRC letter dated 06A March 29, 1985, March 29, 1985, SSER 16. SSER 16.

ll.K.3.1 Auto PORV isolation 15.5.3 Open NRC letter dated March 29, 1985, SSER 16.

ll.K.3.3 Reporting SV/RV failures/challenges 5.2.2 Open NRC letter dated March 29, 1985, SSER 16.

ll.K.3.5 Auto trip of RCPs 15.5.4 Open TVA letter dated October 29, 1981.

NRC letter dated March 29, 1985, SSER 16.

ll.K.3.9 PID controller Open NRC letter dated March 29, 1985, SSER 16.

1I.K.3.10 Anticipatory trip at high power Closed Note 3 NRC letter dated NRC letter dated October 31, 1995, October 31, 1995, SSER 16 SSER 16 ll.K.3.17 ECCS outages 6.3 Open TVA letter dated October 28, 1983.

NRC letter dated March 29. 1985.

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Item Title Applicable Status Comments WBN Unit 1 WBN Unit 2 FSAR (see notes) Closure Closure Document Section Document SSER 16.

II.K.3.25 Power on pump seals 9.2.2 Open SSER 16 I1.K.3.30 SB LOCA methods 15.5.5 Closed TVA letter dated TVA letter dated October 29, 1981. October 29, 1981.

NRC letters dated NRC letters dated March 29, 1985, March 29, 1985, July 24, 1986, July 24, 1986, SSER SSER 16. 16.

I1.K.3.31 Plant specific analysis 15.5.5 Open TVA letters dated October 29, 1981 and October 17, 1986. NRC letter dated March 29, 1985, SSER 16.

II1.D.1.1 Primary coolant outside containment 5.5.7, 6.3, Open SSER 16 9.2 II1.D.3.3 In-plant 12 radiation monitoring Open SSER 16 1l1.D.3.4 Control-room habitability 6.4 Closed Note 3 TVA letter dated TVA letter dated October 29, 1981, October 29, 1981.

SSER 16 SSER 16 Notes:

1. OL @ time indicates this generic communication was applicable to units with an operating license at the time they were issued.

2. Site indicates a multiunit issue that was completed for both units with the closure for Watts Bar Unit 1.

3. Additional WBN Unit 2 implementing procedure, technical specification requirement and/or other activity required for completion.

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