ML21286A262

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Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.11, Id Resolution of Construction Permit Concern - Summary
ML21286A262
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/04/2021
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
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ML21286A574 List: ... further results
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Download: ML21286A262 (11)
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BFN-16 TABLE 1.11-1 (Sheet 1)

BROWNS FERRY NUCLEAR PLANT TOPICAL REPORTS SUBMITTED TO THE AEC IN SUPPORT OF DOCKET GE Report No. Title

1. APED 5286 Design Basis for Critical Heat Flux in Boiling Water Reactors (September 1966)
2. APED 5446 Control Rod Velocity Limiter (March 1967)
3. APED 5449 Control Rod Worth Minimizer (March 1967)
4. APED 5450 Design Provisions for In Service Inspection (April 1967)
5. APED 5453 Vibration Analysis and Testing of Reactor Internals (April 1967)
6. APED 5555 Impact Testing on Collet Assembly for Control Rod Drive Mechanism 7RDB144A (November 1967)
7. TR67SL211 An Analysis of Turbine Missiles Resulting from Last Stage Wheel Failure (October 1967)
8. APED 5608 General Electric Company Analytical and Experimental Program for Resolution of ACRS Safety Concerns (April 1968) (Not Class I)
9. APED 5455 The Mechanical Effects of Reactivity Transients (January 1968)
10. APED 5528 Nuclear Excursion Technology (August 1967)
11. APED 5448 Analysis Methods of Hypothetical Super Prompt Critical Reactivity Transients in Large Power Reactors (April 1968)
12. APED 5458 Effectiveness of Core Standby Cooling Systems for General Electric Boiling Water Reactors (March 1968)
13. APED 5640 Xenon Considerations in Design of Large Boiling Water Reactors (June 1968)
14. APED 5454 Metal Water Reactions Effects on Core Cooling and Containment (March 1968)
15. APED 5460 Design and Performance of General Electric Boiling Water Reactor Jet Pumps (September 1968)
16. APED 5654 Considerations Pertaining to Containment Inerting (August 1968)
17. APED 5696 Tornado Protection for the Spent Fuel Storage Pool (November 1968)
18. APED 5706 In Core Neutron Monitoring System for General Electric Boiling Water Reactors, Rev. 1 (April 1969)
19. APED 5703 Design and Analysis of Control Rod Drive Reactor Vessel Penetrations (November 1968)
20. SPED 5698 Summary of Results Obtained From a Typical Startup and Power Test Program for a General Electric Boiling Water Reactor (February 1969)
21. APED 5750 Design and Performance of General Electric Boiling Water Reactor Main Steam Line Isolation Valves (March 1969)
22. APED 5756 Analytical Methods for Evaluating the Radiological Aspects of the General Electric Boiling Water Reactor (March 1969)
23. APED 5652 Stability and Dynamic Performance of the General Electric Boiling Water Reactor (April 1969)

BFN-16 TABLE 1.11-1 (Cont'd)

(Sheet 2)

BROWNS FERRY NUCLEAR PLANT TOPICAL REPORTS SUBMITTED TO THE AEC IN SUPPORT OF DOCKET GE Report No. Title

24. APED 5736 Guidelines for Determining Safe Test Intervals and Repair Times for Engineered Safeguards (April 1969)
25. APED 5447 Depressurization Performance of the General Electric Boiling Water Reactor High Pressure Coolant Injection System (June 1969)
26. NEDO 10017 Field Testing Requirements for Fuel, Curtains and Control Rods (June 1969)
27. NEDO 10029 An Analytical Study on Battle Fracture of GE-BWR Vessel Subject to the Design Basis Accident (July 1969)
28. NEDO 10045 Consequences of a Steam Line Break for a General Electric Boiling Water Reactor (October 1969)
29. NEDO 10173 Current State of Knowledge High Performance BWR Zircaloy-Clad UO Fuel (May 2

1970)

30. NEDO 10139 Compliance of Protection Systems to Industry Criteria: General Electric BWR Nuclear Steam Supply System (June 1970)
31. NEDO 10179 Effects of Cladding Temperature and Material on ECCS Performance (June 1970)
32. NEDO 10174 Consequences of a Postulated Flow Blockage Incident in a Boiling Water Reactor (May 1970)
33. NEDO 10189 An Analysis of Functional Common-Mode Failures in GE BWR Protection and Control Instrumentation (July 1970)
34. NEDO 10208 Effects of Fuel Rod Failure on ECCS Performance (August 1970)
35. NEDO 10320 The General Electric Pressure Suppression Containment Analytical Model (April 1971)
36. NEDO 10320 The General Electric Pressure Suppression Containment Analytical Supplement 1 Model(May 1971)
37. NEDO 10329 Loss-of-Coolant Accident and Emergency Core Cooling Models for General Electric Boiling Water Reactors (April 1971)
38. NEDO 10329 Loss-of-Coolant Accident and Emergency Core Cooling Models for Supplement 1 General Electric Boiling Water Reactors (April 1971)
39. NEDO 10349 Analysis of Anticipated Transients Without Scram (March 1971)

BFN-16 TABLE 1.11-2 (Sheet 1)

BROWNS FERRY NUCLEAR PLANT AEC-ACRS CONCERNS - RESOLUTIONS Identification Section No. AEC-ACRS Concern Browns Ferry Resolutions 1.2.2 Effects of Fuel Failure on CSCS Topical Report (GE-APED-5608)

Performance Topical Report (NEDO-10208 August 1970) 1.2.3 Effects of Fuel Bundle Flow Blockage Topical Report (GE-APED-5608)

Topical Report (NEDO-10174 July 1970) 1.2.4 Verification of Fuel Damage Limit Topical Report (GE-APED-5608)

Dresden 2/3 - Amendment 14/15 Topical Report (NEDO-10173 May 1970) 1.2.6 Effects of Cladding Temperature and Topical Report (GE-APED-5608)

Materials on CSCS Performance Topical Report (GE-APED-5458)

Topical Report (NEDO-10179 June 1970) 1.2.5 Quality Assurance and Inspection of FSAR (Incorporated in Design -

the Reactor Primary System Section 4 and Appendix D) 1.2.7 Control Rod Block Monitor Design FSAR (Incorporated in Design -

Sections 1, 7 and Appendix G)

Dresden 2/3 - Amendments 17/18 and 19/20 Brunswick 1/2 - Supplement 5 1.2.8 Station Startup Program Topical Report (GE-APED-5698)

FSAR (Incorporated in Design -

Section 13) 1.2.9 Main Steam Line Isolation Valve FSAR (Incorporated in Design -

Testing Under Simulated Accident Section 4)

Conditions Topical Report (GE-APED-5750)

Topical Report (GE-NEDO-10045)

Topical Report (GE-APED-5608) 1.2.10 Performance Testing of the Plant FSAR (Incorporated in Design -

Standby Diesel Generator System Section 8)

General Motors Report 1.2.11 Formulation of an In-Service FSAR (Incorporated in Design -

Inspection Program Section 4)

Technical Specifications -

Sections 3/4) 1.2.12 Diversification of CSCS Initiation FSAR (Incorporated in Design -

Signals Sections 6 and 7) 1.2.13 Control Systems for Emergency Power FSAR (Incorporated in Design -

Section 8) 1.2.14 Misorientation of Fuel Assemblies FSAR (Incorporated in Design -

Section 3) 1.2.15 Concern of Dr. Stephen H. Hanauer - FSAR (Incorporated in Design -

emergency power and Core Standby Sections 6, 8 and 14, Appendix I)

Cooling Systems

BFN-16 TABLE 1.11-2 (Cont'd)

(Sheet 2)

BROWNS FERRY NUCLEAR PLANT AEC-ACRS CONCERNS - RESOLUTIONS Identification Section No. AEC-ACRS Concern Browns Ferry Resolutions 1.2.16 Fuel Clad Disintegration Limitations FSAR (Incorporated in Design -

Section 6)

Topical Report (GE-APED-5608)

Dresden 2/3 - Amendment 7/8 1.2.17 General concerns with regard to reactors FSAR (Incorporated in Design -

of high power density and all large Appendix I) water-cooled power reactors

BFN-16 TABLE 1.11-3 (Sheet 1)

BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 AEC-STAFF CONCERNS - RESOLUTIONS Identification Section No. AEC-Staff Concern Resolutions 1.3.2.1 Units 1 and 2 ACRS concerns FSAR Appendix I, subsection 1.2 1.3.2.2 Core Spray Cooling Effectiveness FSAR (Incorporated in Design Section 6)

Topical Report (GE-APED-5458) 1.3.2.3a Reliability of CSCS Injection Valves FSAR (Incorporated in Design -

Section 4, 6 and 7) 1.3.2.3b Diversification of the CSCS Initiation FSAR (Incorporated in Design -

Signals Sections 6 and 7) 1.3.2.3c Sequencing of CSCS FSAR (Incorporated in Design -

Sections 6 and 8) 1.3.2.3d Core Spray Cooling Effectiveness (See 1.3.2.2 above) 1.3.2.3e Performance Testing of the Standby FSAR (Incorporated in Design -

Diesel Generator System Section 8)

General Motors Report 1.3.2.3f Fuel Failure Modes FSAR (Incorporated in Design -

Sections 6, 7, 14 and Appendix A)

Topical Report (GE-APED-5652)

Topical Report (GE-APED-5756)

Topical Report (GE-APED-5448)

Topical Report (GE-APED-5528)

Topical Report (GE-APED-5455)

Topical Report (GE-APED-5608)

Topical Report (GE-APED-5458)

Topical Report (NEDO 10208 August 1970)

Topical Report (NEDO 10174 July 1970)

Topical Report (NEDO 10173 May 1970)

Topical Report (NEDO 10179 June 1970)

Dresden 2/3 Amendment 7/8 1.3.2.4 Control Rod Block Monitor Design FSAR (Incorporated in Design -

Sections 1, 7 and Appendix G)

Dresden 2/3 Amendments 17/18 and 19/20 Brunswick 1/2 Supplement 5 1.3.2.5 Core Cooling FSAR (Incorporated in Design -

Section 6)

Topical Report (GE-APED-5458) 1.3.2.6 Control Rod Worth Minimizer Topical Report (GE-APED-5449)

FSAR (Incorporated in Design -

Section 7) 1.3.2.7 Control Rod Velocity Limiter Topical Report (GE-APED-5446)

FSAR (Incorporated in Design -

Section 3)

BFN-16 TABLE 1.11-3 (Cont'd)

(Sheet 2)

BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 AEC-STAFF CONCERNS - RESOLUTIONS Identification Section No. AEC-Staff Concern Resolutions 1.3.2.8 In-Core Nuclear Instrumentation Topical Report (GE-APED-5456)

Topical Report (GE-APED-5706)

FSAR (Incorporated in Design -

Section 7) 1.3.2.9 Jet Pump Development Topical Report (GE-APED-5460) 1.3.2.10.1 Core Analytical Models FSAR (Incorporated in Design -

Sections 6, 7 and 14)

Topical Report (GE-APED-5652)

Topical Report (GE-APED-5756)

Topical Report (GE-APED-5448)

Topical Report (GE-APED-5528)

Topical Report (GE-APED-5455)

Dresden 2/3 Amendment 10/11 1.3.2.10.2 Fuel Failure Modes (See 1.3.2.3f above) 1.3.2.10.3 Electrical Load Control Using FSAR (Incorporated in Design -

Variable Speed Reactor Coolant Section 7)

Recirculation System Pumps Startup Test Results Oyster Creek No. 1 Nine Mile Point No. 1 Dresden No. 2 Millstone No. 1 1.3.2.10.4 Diversification of the CSCS Initiation (See 1.3.2.3b above)

Signals 1.3.2.10.5 Main Steam Line Isolation Valve FSAR (Incorporated in Design -

Testing Under Simulated Accident Section 4)

Conditions Topical Report (GE-APED-5750)

Topical Report (GE-NEDO-10045)

Topical Report (GE-APED-5608) 1.3.2.10.6 Performance Testing of the Station (See 1.3.2.3e above)

Standby Diesel Generator System

BFN-16 TABLE 1.11-4 BROWNS FERRY NUCLEAR PLANT UNIT 3 AEC-STAFF CONCERNS - RESOLUTIONS Identification Section No. AEC-Staff Concern Resolutions 1.3.3.1 Performance Testing of the Standby (See 1.3.2.3e above, Table 1.11-3)

Diesel Generator System 1.3.3.2 Reactor Building Basement Corner FSAR (Incorporated in Design -

Room Flooding Section 4) 1.3.3.3 Automatic Pressure Relief System FSAR (Incorporated in Design -

Initiation Interlock Sections 6 and 7) 1.3.3.4 Criterion 35 Intent FSAR (Incorporated in Design -

Section 4 Appendix A) 1.3.3.5 RPV-Stub Tube Design FSAR (Incorporated in Design -

Section 4)

Topical Report (GE-APED-5703) 1.3.3.6 Requirements for Further Technical (See Table 1.11-3)

Information from Unit 1 and 2 C.P.

1.3.3.7 CSCS Thermal Effects on The Reactor Topical Report (GE-NEDO-10029)

Vessel and Internals FSAR (Incorporated in Design -

Sections 3 and 4) 1.3.3.8 Depressurization Performance of HPCIS FSAR (Incorporated in Design -

Section 6)

Topical Report (GE-APED-5608)

Topical Report (GE-APED-5447) 1.3.3.9 Electrical Equipment Inside FSAR (Incorporated in Design -

Containment Section 7) 1.3.3.10 Primary System Leakage Detection FSAR (Incorporated in Design -

Sections 4 and 10)

BFN-16 TABLE 1.11-5 (Sheet 1)

AEC ACRS CONCERNS ON OTHER DOCKETS - RESOLUTIONS Identification Section No. AEC-ACRS Concern _ Resolutions_

1.4.2 Ring Header Leakage Design FSAR (Incorporated in Design -

Sections 4, 5 and 6) 1.4.3 CSCS Thermal Effects on The Reactor Topical Report (GE-NEDO-10029)

Vessel and Internals FSAR (Incorporated in Design -

Sections 3 and 4) 1.4.4 Effects of Blowdown Forces on Reactor FSAR (Incorporated in Design -

Primary System Components Sections 3, 4 and Appendix C) 1.4.5 Separation of Control and Protection FSAR (Incorporated in Design -

System Functions Sections 6, 7 and Appendix A) 1.4.6 Instrumentation For Prompt Detection FSAR (Incorporated in Design -

of Gross Fuel Failures Section 7)

Brunswick 1/2 - Supplements 3 and 4 1.4.7 Design of Piping Systems to Withstand FSAR (Incorporated in Design -

Earthquake Forces Section 12 and Appendix C)

Dresden 2/3 - Amendment 13/14 1.4.8 LPCIS - Logic Control System Design FSAR (Incorporated in Design -

Section 6) 1.4.9 Reevaluation of Main Steam Line Break Topical Report (GE-APED-5608)

Accident Topical Report (NEDO-10045)

FSAR (Incorporated in Design -

Section 14) 1.4.10 Depressurization Performance of HPCIS FSAR (Incorporated in Design -

Section 6)

Topical Report (GE-APED-5608)

Topical Report (GE-APED-5447) 1.4.11 AEC General Design Criteria No. 35 FSAR (Incorporated in Design -

Intent Design Conformance Section 4) 1.4.12 Automatic Pressure Relief System FSAR (Incorporated in Design -

Initiation Interlock Sections 6 and 7) 1.4.13 Scram Reliability Study FSAR (Incorporated in Design -

Sections 3 and 7)

Study Results (To be Available Early 1970)

Brunswick 1/2, Supplement 6 1.4.14 Design Basis of Engineered Safety Topical Report (GE-APED-5756)

Features FSAR (Examined Capability of Design -

Section 14)

BFN-16 TABLE 1.11-5 (Cont')

(Sheet 2)

AEC ACRS CONCERNS ON OTHER DOCKETS - RESOLUTIONS Identification Section No. AEC-ACRS Concern _ Resolutions 1.4.15 Hydrogen Generation Study Topical Report (GE-APED-5454)

Topical Report (GE-APED-5654)

Brunswick 1/2, Supplement 4 Study Results (To be Available Middle 1970) 1.4.16 Primary Containment Inerting Topical Report (GE-APED-5454)

Topical Report (GE-APED-5654)

FSAR (Incorporate in Design -

Sections 5 and 6)

Dresden 2 - ACRS Letter, 9/10/69) 1.4.17 Seismic Design and Analysis Models FSAR (Re-Confirmation of Design -

Section 12 and Appendix C)

Dresden 2 - Re-Confirmation Information (submitted October 1969) 1.4.18 Automatic Pressure Relief System FSAR (Incorporated in Design -

Single Component Failure Capability Sections 6 and 8)

Manual Operation 1.4.19 Matters of Current Regulatory Staff Applicant Discussion (a) Standby Gas Treatment System FSAR (Incorporated in Design -

Electrical and Physical Separation Sections 5, 7, and 8)

(b) Official, Issued Technical Specifi- Proposed Technical Specifications cations - License Appendix A Appendix B 1.4.20 Flow Reference Scram FSAR (Incorporated in Design -

Section 7) 1.4.21 Future Items of Consideration for Incorporation ....

(a) Radiolytic Decomposition of Topical Report (GE-APED-5454)

Cooling Water Topical Report (GE-APED-5654)

Brunswick 1/2, Supplement 4 Study Results (To be Available Middle 1970)

(b) Development of Instrumentation FSAR (Justified Design - Sections Vibration and Loose Parts 3, 4 and Appendix C)

Detection (c) Consequences of Water Contamination FSAR (Incorporated in Design -

Structural Material - LOCA Section 14) 1.4.22 Diesel Generator Synchronization FSAR (Incorporated in Design -

Considerations Sections 6, 7, and 8)

BFN-16 TABLE 1.11-5 (Cont'd)

(Sheet 3)

AEC ACRS CONCERNS ON OTHER DOCKETS - RESOLUTIONS Identification Section No. AEC-ACRS Concern _ Resolutions 1.4.23 Development of Instrumentation FSAR (Justified Design - Section 4)

Primary Containment Leakage Technication Specification -

Detection System Increased Appendix B Sections 3 and 4)

Sensitivity Studies 1.4.24 Development of Instrumentation - FSAR (Justified Design - Sections 3, Vibration and Loose Parts 4, and Appendix C)

Detection Studies 1.4.25 CSCS - Leakage Detection, Protection, FSAR (Justified in Design - Sections and Isolation Capability 4, 10 and Appendix A)

Brunswick 1/2 - Supplement 4, C/R 6.4 1.4.26 Main Steam Lines - Standards For FSAR paragraph 1.4.2.6 Fabrication, Q/C and Inspection

BFN-16 TABLE 1.11-6 AEC ACRS CONCERNS ON OTHER DOCKETS - CAPABILITY FOR RESOLUTION Identification Section No. AEC-Staff Concern Capability for Resolution 1.5.2 Tornado and Missile Protection FSAR (Incorporated in Design -

GE BWR-Spent Fuel Storage Pool Sections 2, 10, and 12)

Topical Report (GE-APED-5696) 1.5.3 BWR System Stability Analysis FSAR (Incorporated in Design -

Section 7)

Topical Report (GE-APED-5652)

Topical Report (GE-APED-5640)

Peach Bottom 2/3 - Amendment 2

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