ML20155F909

Forwards Master Table of Contents to Rev 16 of Usar.Info Was Inadvertantly Omitted at Time of 981023 Submittal

ML20155F909
Person / Time
Site:	Monticello
Issue date:	10/27/1998
From:	Hammer M NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9811060149
Download: ML20155F909 (10)

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Northern States Power Company Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362 l

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October 27,1998 10CFR 50.71(e) i 10CFR 50.59(b)(2) l U S Nuclear Regulatory Commission l Attn: Document Control Desk l Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT l Docket No. 50-263 License No. DPR-22 Submittal of Master Table of Contents to Revision No.16 to the Updated Safety Analysis Roport j On October 23,1998, Revision No.16 to the Updated Safety Analysis Report (USAR) for the Monticello Nuclear Generating Plant was submitted to the NRC. At that time, the Master Table of Contents (TOC) was inadvertantly omitted. Therefore, attached to this letter are 10 copies of the TOC .

Please contact Sam Shirey. Sr. Licensino Engineer at (612) 295-1449 if you require additional information related to this suomittal.

Michael F. Hammer

$Q1Q Plant Manager Monticello Nuclear Generating Plant cc: Regional Administrator-lli, NRC NRR Project Manager, NRC Resident inspector, NRC

Enclosures:

TABLE OF CONTENTS j)f>6 b 9811060149 981027

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27-OCT-1998 Northern States Power Company Page 1 Monticello Nuclear Generating Plant Document Control Distribution System ,

Document Distribution Manifest Controlled Documents - Current OCT 271998 -

Name: . . US NRC Manifest Number: 98-0416 Date Mailed:

Title:

ATTN: DOCUMENT CONTROL DESK Distribution Type: I Company: MONTI LICENSING Manual Number:

Location: ATTN: MARC VOTH ID Number: YYYYO9 MNGP-SAB/2ND FLOOR

% COPIES OF USAR Document Type Document Number Revision Title NOTE: The following issues are new or revised 9703 USAR-TOC 16 USAR TABLE OF CONTENTS

MONTICELLO UPDATED SAFETY ANALYSIS REPORT UsAR TOC TABLE OF CONTENTS

• Rf,y,l7 q

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. TABLE OF CONTENTS VOLUME 1 SECTION 1 INTRODUCTION AND

SUMMARY

I 1.1 Purpose, Scope and Organization 1.2 Principal Design Criteria 1.3 Summary Design Description and Safety Analysis 1.4 Identification and Qualification of Contractors I 1.5 References

1. FIGURES SECTION 2 SITE AND ENVIRONS 2.1 Introduction 2.2 Site Description 2.3 Meteorology 2.4 Hydrology 2.5 Geology and SoilInvestigation 1 2.6 Seismology 2.7 Radiation Environmental Monitoring Program (REMP) 2.8 Ecological and Biological Studies 2.9 Consequences of Hypothetical Local Catastrophes 2.10 References i

2. FIGURES SECTION 3 REACTOR 3.1 General Summary 3.2 Thermal and Hydraulic Characteristics i FOR ADMINISTRATIVE USE ONLY Resp supv: LlO l Assoc Ref: USAR-MAN bMSR: N Frea: 2 lyrs on ARMS: USAR-TOC l Doc Type: 9703 l Admin Initials: 1-(J Date:ll)Z i Qf 1/akr

MONTICELLO UPDATED sAFErY ANALYSTS REPORT usAR TOC

• Rivision 16 Page 2 of 7 TABLE OF CONTENTS (CONT'D) . .

3.3 Nuclear Characteristics 3.4 Fuel Mechanical Characteristics 3.5 Reactivity Control Mechanical Characteristics 3.6 Other Reactor Vessel Internals 3.7 References

3. FIGURES SECTION 4 REACTOR COOLANT SYSTEM 4.1 Summary Description 4.2 Reactor Vessel 4.3 Recirculation System 4.4 Reactor Pressure Relief System 4.5 Reactor Coolant System Vents 4.6 Hydrogen Water Chemistry 4.7 Zinc Water Chemistry (GEZIP) 4.8 References

4. FIGURES VOLUME 2 SECTION 5 CONTAINMENT SYSTEM 5.1 Summary Description 5.2 Primary Containment System 5.3 Secondary Containment System 5.4 References h

5. FIGURES 1/akr

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' hoNTICELLo UPDATED SAFETY AN'ALYsts REPORT usAR toc

. Revision 16

' Page 3 of 7 f

. TABLE OF CONTENTS (CONT'D)-

SECTION 6 - PLANT ENGINEERED SAFEGUARDS 6.1 Summary Description

, 6.2. Emergency Core Cooling System (ECCS)-

6.3 Main Steam Line Flow Restrictions 6.4 Control Rod Velocity Limiters d ,

6.5 Control Rod Drive Housing Supports 6.6 Standby Liquid Control System 6.7 - Main Control Room, Emergency Filtration Train Building and 1 Technical Support Center Habitability .

v 6.8 References

6. FIGURES SECTION 7 PLANT INSTRUMENTATION AND CONTROL SYSTEMS 7.1 Summary Description 7.2 Reactor Control Systems 7.3 Nuclear instrumentation System 1

7.4 Reactor Vessel Instrumentation 7.5 Plant Radiation Monitoring Systems-t 7.6 Plant Protection System 7.7 Turbine-Generator System Instrumentation and Control 7.8' NUMAC Rod Worth Minimizer and Plant Process On-Line Computer

[.

7.9 Other Systems Control and Instrumentation

- 7.10 Seismic and Transient Performance Instrumentation Systems 7.11 Reactor Shutdown Capability

.7.12 Detailed Control Room Design Review

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• j MONTICELLO UPDATED SAFETY ANALYSIS REPORT usAR TOC l Revision 16 Page 4 of 7 )

TABLE OF CONTENTS (CONT'D) - -

7.13 Safety Parameter Display System 7.14 References

7. FIGURES VOLUME 3 SECTION 8 PLANT ELECTRICAL SYSTEMS 8.1 Summary 8.2 Transmission System 8.3 Auxiliary Power System 8.4 Plant Standby Diesel Generator Systems 8.5 DC Power Supply Systems 8.6 Reactor Protection System Power Supplies 8.7 Instrumentation and Control AC Power Supply Systems 8.8 Electrical Design Considerations 8.9 Environmental Qualification of Safety-Related Electrical Equipment 8.10 Adequacy of Station Electrical Distribution System Voltages 8.11 Power Operated Valves 8.12 Station Blackout 8.13 References

8. FIGURES SECTION 9 PLANT RADIOACTIVE WASTE CONTROL SYSTEMS 9.1 Summary Description 9.2 Liquid Radwaste System h 9.3 Gaseous Radwaste System I/akr

^ '*h0f4TICELLO UPDATED SAFETY ANALYSTS REPORT . usAR TOC Rtvision 16 Page 5 of 7 J

V .. .

TABLE OF CONTENTS (CONT'D) 9.4 Solid Radwaste System 9.5 References

9. FIGURES

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SECTION 10 PLANT AUXILIARY SYSTEMS 10.1 Summary Description 10.2 Reactor Auxiliary Systems

-10.3 Plant Service Systems 4

10.4 Plant Cooling System 10.5 References I

'10. FIGURES q SECTION 11 PLANT POWER CONVERSION SYSTEMS v~ ~

11.1 Summary Description 11.2 Turbine-Generator System i 11.3 Main Condenser System 11.4  : Main Turbine Bypass System 11.5 Circulating Water System i

11.6 Cooling Tower System J 11.7 Condensate Demineralizer System 11.8 Condensate and Reactor Feedwater Systems

11. FIGURES  :

VOLUME 4 -  !

SECTION 12 ' PLANT STRUCTURES AND SHIELDING r Summary Description

-Q 12.1 12.2 Plant Principal Structures and Foundations I/akr

MoNTICELLO UPDATED SAFETY ANALYSTS REPORT USARToC . . .

Rinision 16 Page 6 of 7 TABLE OF CONTENTS (CONT'D) - -

12.3 Shielding and Radiation Protection 12.4 Radioactive Materials Safety 12.5 References

12. FIGURES SECTION 13 PLANT OPERATIONS 13.1 Summary Description 13.2 Organization, Responsibilities, and Qualifications 13.3 Personnel Experience and Training 13.4 Operational Procedures 13.5 Operational Records and Reporting Requirements 13.6 Operational Review and Audits 13.7 Emergency Procedures 13.8 References

13. FIGURES l

l l SECTION 14 PLANT SAFETY ANALYSIS l 14.1 Summary Description 14.2 Fuel Cladding Integrity Safety Limit l .

14.3 Operating Limits 14.4 Transient Events Analyzed for Core Reload 14.5 Special Events 14.6 Plant Stability Analysis 14.7 Accident Evaluation Methodology 14.8 Anticipated Transients Without Scram (ATWS) 14.9 Post-Accident Plant Systems Shielding Design Review 1/akr

. .~ - - .. . . ... - - . . . - - - - . . - - . . . - . . . . . . . . . .

• MONTICELLO

• • UPDATED SAFETY ANALYSIS REPORT usAR TOC P.svision 16 Page 7 of 7 TABLE OF CONTENTS (CONT'D) 14.10 Other Analyses '

14.11 References

14. FIGURES l

14.A Current Cycle's Supplemental Reload Licensing Submittal L 1

VOLUME 5 '

l SECTION 15 USAR DRAWINGS VOLUME 6 APPENDIX A Seismic Design Criteria f APPENDIX B Deleted l 1

VOLUME 7 APPENDIX C Operational Quality Assurance Plan APPENDIX D Pre-Operational and Startup Tests APPENDIX E Plant Comparative Evaluation APPENDIX F Containment Vessel Design Summary Report VOLUME 8 APPENDIX G Probable Maximum Flodd APPENDIX H Reactor Pressure Vessel Design Summary Report 4

APPENDIX l Postulated Pipe Failures Outside Containment O

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