L-79-012, Regulatory Framework for Restart
| ML030620692 | |
| 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 | |
| BL-79-012 | |
| Download: ML030620692 (6) | |
Text
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 TVAs 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 includes Bulletin 79-12 as a generic communication action requiring implementation. TVA regrets any confusion this oversight may have caused.
U.S. Nuclear Regulatory Commission Page 2 February 28, 2003 If you have questions regarding this issue, please call me at (729) 256-2636.
Sincerely, original signed by:
T. E. Abney Manager of Licensing and Industry Affairs Enclosure cc (Enclosure):
ATTN: Document Control Desk Mail Stop OWFN, P1-35 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
U.S. Nuclear Regulatory Commission Page 2 February 28, 2003 Enclosure cc (Enclosure):
A. S. Bhatnagar, PAB 1E-BFN M. J. Burzynski, BR 4X-C R. G. Jones, POB 2C-BFN J. E. Maddox, LP 6A-C D. C. Olcsvary, LP 6A-C C. M. Root, PAB 1G-BFN J. R. Rupert, LP 6A-C K. W. Singer, LP 6A-C E. J. Vigluicci, ET 11A-K R. E. Wiggall, PEC 2A-BFN NSRB Support, LP 5M-C EDMS-K s:lic/submit/subs/Unit 1 Regulatory Framework
ENCLOSURE Table 1: Regulatory Issues Open Commitments to Implement Actions Bulletins:
79-02 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts 79-12 Short Period Scrams At BWR Facilities 79-14 Seismic Analysis for As-Built Safety Related Piping Systems 80-06 Engineered Safety Feature Reset Controls 84-02 Failure of GE Type HFA Relays in Use in Class 1E Safety Systems 86-02 Static O Ring Differential Pressure Switches 88-07 Power Oscillation in Boiling Water Reactors 88-10 Nonconforming Molded-Case Circuit Breakers 93-03 Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs 96-03 Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors Generic Letters:
82-33 Instrumentation to Follow the Course of an Accident - R.G. 1.97 83-08 Modification of Vacuum Breakers on Mark 1 Containments 83-28 Salem ATWS 88-11 Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations 88-14 Instrument Air Supply System Problems Affecting Safety Related Equipment 89-06 Safety Parameter Display System 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning 89-10 Safety-Related Motor-Operated Valve Testing and Surveillance 89-16 Installation of a Hardened Wetwell Vent 96-01 Testing of Safety-Related Logic Circuits 96-05 Periodic Verification of Design Basis Capability of Motor Operated Valves 98-01 Readiness of Computer Systems at Nuclear Power Plants NUREG-0737 (TMI Action Plan) Action Items I.D.1 Control Room Design Review I.D.2 Safety Parameter Display Console II.B.3 Post-Accident Sampling System II.E.4.2.1 -4 Containment Isolation Dependability - Implement Diverse Isolation II.F.1.2.C Accident - Monitoring - Containment High Range Radiation II.F.1.2.D Accident - Monitoring - Containment Pressure II.F.1.2.E Accident - Monitoring - Containment Water Level II.F.2.4 (Generic Letter 84-23) - Instrumentation for Detection of Inadequate Core Cooling II.K.3.13 HPCI/RCIC Initiation Levels II.K.3.18 ADS Actuation Modifications II.K.3.28 Qualification of ADS Accumulators
Commitment to Provide Submittal Bulletins:
90-01 Loss of Fill Oil in Rosemount Transmitters 93-02 Debris Plugging of Emergency Core Cooling Suction Strainers Generic Letters:
87-02 Verification of Seismic Adequacy of Mechanical and Electrical Equipment In Operating Reactors 88-20, S 4 Individual Plant Examination of External Events for Severe Accident Vulnerabilities 92-04 Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs 95-07 Pressure Locking and Thermal Binding of Safety-Related and Power-Operated Gate Valves 96-06 Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions 97-04 Assurance of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps 98-04 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 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE 88-04 Potential Safety Related Pump Loss 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool Cooling Mode Generic Letters:
88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping 89-13 Service Water System Problems Affecting Safety Related Equipment 92-01 Reactor Vessel Structural Integrity 94-02 Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs 94-03 Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs