ML030700581
| ML030700581 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/28/2003 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML030700581 (5) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 28, 2003 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Stop OWFN, P1-35 Washington, D.C.
20555-0001 Gentlemen:
In the Matter of
)
Docket No.
50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN)--
UNIT 1 -
REGULATORY FRAMEWORK FOR THE RESTART OF UNIT 1
Reference:
TVA letter dated December 13, 2002, Regulatory Framework for the Restart of Unit 1.
Table 1 of the referenced letter listed NRC generic communications for which TVA has outstanding actions.
In the generation of that table, TVA inadvertently omitted Bulletin 79-12, Short Period Scrams At BWR Facilities.
This discrepancy was discovered during a review of outstanding commitments on Unit 1.
Actions for Bulletin 79-12 have been completed on Units 2 and 3, and TVA's commitment management program still contains the commitment to implement those actions on Unit 1.
The commitment was appropriately included in the Unit 1 restart scope.
TVA has reviewed Table 1 in the December 13, 2002, letter, and no other omissions were identified.
TVA has also reviewed all NRC generic letters and bulletins issued since the original Unit 1 framework letter was issued on July 10, 1991.
No additional NRC generic letters or bulletins were identified for which TVA has open commitments.
Enclosed is a revision to Table 1 of the referenced letter which includesBulletin 79-12 as a generic communication action requiring implementation.
TVA regrets any confusion this oversight may have caused.
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U.S. Nuclear Regulatory Commission Page 2 February 28, 2003 If you have questions regarding this issue, please call me at (729) 256-2636.
Si cerel T. E. Abney Manager of Li nsin and Industr Affai s Enclosure cc (Enclosur ATTN:
Do ent Control Desk Mail Stop OWFN, Pl-35 Washington, D.C. 20555-0001 (Via NRC Electronic Distribution)
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE
Table 1: Regulatory Issues Open Commitments to Implement Actions Bulletins:
79-02 79-12 79-14 80-06 84-02 86-02 88-07 88-10 93-03 96-03 82-33 83-08 83-28 88-11 88-14 89-06 89-08 89-10 89-16 96-01 96-05 98-01 I.D.1 I.D.2 II.B.3 II.E.4.2.1 -4 II.F.1.2.C II.F.1.2.D II.F.I.2.E II.F.2.4 II.K.3.13 II.K.3.18 II.K.3.28 Control Room Design Review Safety Parameter Display Console Post-Accident Sampling System Containment Isolation Dependability - Implement Diverse Isolation Accident -
Monitoring -
Containment High Range Radiation Accident -
Monitoring -
Containment Pressure Accident -
Monitoring -
Containment Water Level (Generic Letter 84-23) - Instrumentation for Detection of Inadequate Core Cooling HPCI/RCIC Initiation Levels ADS Actuation Modifications Qualification of ADS Accumulators Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts Short Period Scrams At BWR Facilities Seismic Analysis for As-Built Safety Related Piping Systems Engineered Safety Feature Reset Controls Failure of GE Type HFA Relays in Use in Class 1E Safety Systems Static "0" Ring Differential Pressure Switches Power Oscillation in Boiling Water Reactors Nonconforming Molded-Case Circuit Breakers Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors Generic Letters:
Instrumentation to Follow the Course of an Accident -
R.G. 1.97 Modification of Vacuum Breakers on Mark 1 Containments Salem ATWS Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations Instrument Air Supply System Problems Affecting Safety Related Equipment Safety Parameter Display System Erosion/Corrosion-Induced Pipe Wall Thinning Safety-Related Motor-Operated Valve Testing and Surveillance Installation of a Hardened Wetwell Vent Testing of Safety-Related Logic Circuits Periodic Verification of Design Basis Capability of Motor Operated Valves Readiness of Computer Systems at Nuclear Power Plants NUREG-0737 (TMI Action Plan) Action Items
Commitment to Provide Submittal Bulletins:
Loss of Fill Oil in Rosemount Transmitters Debris Plugging of Emergency Core Cooling Suction Strainers Generic Letters:
87-02 88-20, S 4 92-04 95-07 96-06 97-04 98-04 Verification of Seismic Adequacy of Mechanical and Electrical Equipment In Operating Reactors Individual Plant Examination of External Events for Severe Accident Vulnerabilities Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pressure Locking and Thermal Binding of Safety-Related and Power Operated Gate Valves Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions Assurance of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss of Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment Requirement for Submittal Within a Specified Period After Actions are Complete Bulletins:
88-03 88-04 95-02 Generic 88-01 89-13 92-01 94-02 94-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE Potential Safety Related Pump Loss Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool Cooling Mode Letters:
NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping Service Water System Problems Affecting Safety Related Equipment Reactor Vessel Structural Integrity Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs 90-01 93-02