ML19319D692

Chapter 15 to Crystal River 3 & 4 PSAR, Tech Specs. Tech Specs to Be Submitted at Later Date

ML19319D692
Person / Time
Site:	Crystal River, 05000303
Issue date:	08/10/1967
From:	FLORIDA POWER CORP.
To:
References
NUDOCS 8003240677
Download: ML19319D692 (3)

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TABLE OF CONTENTS Section M

15 TECHNICAL SPECIFICATIONS 15-1 O

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~15 TECHNICAL SPECIFICATI0!iS

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Proposed technical specifications for the Crystal River Plant baits 3 and la

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vill be submitted by Florida Power. "orporation to include those teuhnical operating limits,~ conditions and : :quirements to be met'in the ir.terest of M

public health and safety. These' technical specifications vill be submitted in time to permit their orderly review and.the timely issuance of an

..l operating license.

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Crystal River Units 3' & 4 Nuclear Generating Plant Pae'iui"^av A

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APPENDICES

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-M AMENDMENT NO. 2 FLORIDA POWER CORPORATION Crystal River Plant Units 3 & 4 taendment No. 2 to the Florida Power Corporation's Preliminary Safety Analysis Report includes both insert pages, as listed below, and Supplement No.1.

Supplement Nc.1 censists of the response to the letter dated January 19, 1968 from Dr. Peter A. Morris, Director, Division of Reactor Licensing. The supple-ment also contains answers to the " Requested Additional Information" by D.R.L.

en January 19, 1968 (1.0 through 9.15).

NOTE Incicsed herewith, immediately following the instruction sheets, you will find a title sheet enti'. led " Appendices" and a complete Table of Contents (pages "i" through "vii").

These sheets are to be inserted in the binder entitled " APPENDICES, which accotapanies this amendment.

Remove the contents in existing Volume h--from the tab entitled " APPENDIX" to the end of the valume ( Appendix 12A)--and incert all anpendices in the binder entitled "APPEUDICES. " (The title sheet and table of contents in existing Volume 4 should remain in place. )

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The fol10 wing sheets of the Florida Power Corporation's Preliminary Safety Analysis Report are to be deleted and, where appropriate, revised sheets dated 2-7-68 should.

be inserted.

Remove the fellowing sheets:

Insert the following sheets :

Pages: Table of centents - vii Pares: Table of contents - vii (cne each in Volumes 1, 2, 3, and h)

(one each in Volumes 1, 2, 3, and h)

Pages:

1-27, 1-28, 1-29, 1-30, 1-35, Paces:

1-27, 1-28, 1-29, 1-30, 1-35, and 1-36.

and 1-36.

Fici.r e s :

1-2, 1-3, 1 h, 1-5, 1-6, 1-7, Figures:

1-2, 1-3, 1-h, 1-5, 1-6, 1-7, 1-9, and 1-12.

1-9, and 1-12.

Pages:

5-17, 5-18, and 5-19.

Pages:

5-17, 5-18, and 5-19.

Figure:

5-6.

Figure:

5-6.

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Docket 303. 50-YJP 50-y>3 Fetsrurtr / 7,1968 j.'

Pc:r.ove the fellowind sheets:

Insert the followinr' cheete :

Paces:

0-1, 6-2, 6-3, 6 4, 6-5, 6-6, Pares:

6-1, 6-2, 6-3, 6 h, 6-5, 6 6, 6-7, 6-3, 9-9, 6-10, 6-11, 6-12, 6-17, 6-7, 6-8, 6-9, 6-10, 6-11, 6-12, 6-17, 6-18, 6-21, and 6-22.

6-18, 6-21, and 6-22.

F1 cures:

6-1, 6-2, 6 h, and 6-5 Figures:

6-1, 6-2, 6-h, and 6-5.

Pages: 7-9 and 7-10.

Pares :

7-9 and 7-10.

Figure:

7-2.

Figure:

7-2.

Pages:

8-1, 8-2, 8-5, 8-6, 8-7, 8-8, Pages:

8-1, 8-2, 8-5, 8-6, 8-7, 8-8, 6-9, 8-10, 8-11, and 8-12, 8-9, 8-10, 8-11, and 8-12.

Figures: 8-1 and 8-2.

Figures: 8-1 and 8-2.

Pares: 9-3, 9 L, 9-5, 9-6, 9-7, 9-8, Pages: 9-?, 9 '., 9-5, 9-6, 9-7, 9-8, 9-17, 9-18, 9-19, 9-20, 9-21, 9-22, 9-17, 9-18, 9-19, 9-19a, 9-20, 9-21, 9-22 9-23, 9-24, 9-27, 9-28, 9-29, and 9-22a, 9-23, 9-24, 9-27, 9-28, 9-29, 9-30.

and 9-30.

Figures :

9-2, 9 h, 9-5, 9-6, 9-8, Fieures:

9-2, 9 h, 9 hu, 9-5, 9-6, 9-8, 9-9, and 9-12.

9-9, and 9-12.

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Pages:

11-11,11-11a, 11-17, and 11-18.

Pages:

11-11, ll-lla, 11-17, and 11-18.

U Pages:

16-7, lh-8, 14-29, lb-30, Pages:

1h-7, 1h-8. 1h-29, lk-30, 14-37,1h-38, ih hld, lh-42,14 h5, 14-37, 14-38, 14 '

1, 14 h2, 1h h5, and 14-46.

and 1L 46.

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Figures: 14-37 and 1h-38.

Figures: 1h-37 and lh-38.

Pagel: 1A-9 and 1A-10.

Pages: 1A-9 and 1A-10.

Pages: 5A-1 and 5A-2.

Pages:

SA-1 and 5A-2.

Suuplement 1 Insert entire Supplement 1 in Volume k.

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014.8

TABLE OF CONTENTS

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Section P_ age, 1

INTRODUCTION AND SIM4ARY Volume 1 Tab 1 1-1

1.1 INTRODUCTION

1-1 1.2 DESIGN HIGHLIGHTS.

1-2 1.2.1 SITE CEARACTERISTICS 1-2 1.2.2 POWER LEVEL 1-2 1.2.3 PEAK SPECIFIC POWER LEVEL 1-2 1.2.h REACTOR BUILDING SYSTEM 1-2 1.2.5 ENGINEERED SAFEGUARDS.

1-3 1.2.6 ELECTRICAL SYSTDiS AND EMERGENCY POWER 1-3 1.2.7 ONCE-THROUGH STEAM GENERATORS 1-h 1.3 TABULAR CHARACTERISTICS.

1-k 1.h PRINCIPAL DESIGN CRITERIA 1-7 1.k.1 CRITERION 1 1-7 1.h.2 CRITERION 2 1-9 1.4.3 CRITERION 3 1-10 1.4.h CRITERION h 1-10 1.h.5 CRITERION 5 1-11 1.4.6 CRITERION 6 1-11 1.h.7 CRITERION 7 1-12 1.h.8 CRITERION 8 1-13 1.h.9 CRITERION 9 1-13 7x 1.h.10 CRITERION 10.

1-14

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1.h.11 CRITERION 11.

1-15 1.k.12 CRITERION 12.

1-15 1.h.13 CRITERION 13 1-16 1.4.14 CRITERION 1h.

1-17 1.4.15 CRITERION 15 1-17 1.h.16 CRITERION 16.

1-18 1.h.17 CRITERION 17 1-19 1.h.18 CRITE'. ION 18.

1-20 1.h.19 CRIT'.iION 19 1-21 1.h.20 CRITIRION 20.

1-22 1.h.21 CRII CRION 21.

1-22 1.h.22 CRIT RION 22.

1-22 1.4.23 CRIT RION 23.

1-23 1.h.24 CRITlRION 24.

1-2h 1.4.25 CRITEIION 25 1-2k 1.h.26 CRITH TON 26.

1-25 1.4.27.

CRITERIL." 27.

1-26 15 RESEARCH AND DEVELOPMENT REQUIREMENTS 1-26 1 5.1 ONCE-THROUGH STEAM GENERATOR TEST.

1-26 1 5.2 CONTROL ROD DRIVE LINE TEST.

1-26 1 5.3 SELF-POWERED DEIECTOR TESTS.

1-27 1 5.4 THERMAL AND HYDRAULIC PROGRAMS.

1-27 1.6 IDENTIFICATION OF AGENTS AND CONTRACTORS 1-27

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17 CONCLUSIONS.

1-28 sU 0149 i

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Section Pggg s

v) 2 SITE AND ENVIRONMENT Volume 1.

Tab 2.

2-1 2.1 SUM!4ARY 2-1 2.2 SITE AND ADJACENT AREAS.

2-1 2.2.1 SITE LOCATION AND TOPOGRAPHY 2-1 2.2.2 SITE OWNERSHIP 2-2 2.2.3 SITE ACTIVITIES.

2-2 2.2.4 POPULATION 2-3 2 2.5 LAND USE 2-3 2.2.6 DAIRY ANIMALS 2-3 2.3 METEOROLOGY AND CLIMATOLOGY 2-3 2.3.1

SUMMARY

2-3 2.3.2 DESCRIPTIVE METEOROLOGY 2-4 2.3.3 ATMOSPHERIC DIFFUSION.

2-7 2.3.h SITE METEOROLOGICAL PROGRAM.

2-9 2.h HYDROLOGY 2-10 2.h.1 CHARACTERISTICS OF STREAMS IN VICINITY 2-10 2.h.2 FLOOD STUDIES AND HURRICANE EFFECTS 2-11 2.h.3 DESIGN OF CIRCULATING WATER SYSTEM 2-11 2.h.h LIQUID WASTE DISCHARGES 2-12 2.h.5 GROUNDWATER 2-12 2.5 GEOLOGY 2-12 2.6 SEISMOLOGY 2-13 2.6.1 SEISMICITY STUDY 2-13 2.6.2 RESPONSE SPECTRA 2-13

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2.7 SITE ENVIRONMENTAL RADIOACTIVITY PROGFAM 2-13 (m-)

2.8 REFERENCES

2-lh 3

REACTOR,

Volume 1.

. Tab 3 3-1 3.1 DESIGN BASES 3-1 3.1.1 PERFORMANCE OBJECTIVES 3-1 3.1.2 LIMITS.

3-1 3.2 REACTOR DESIGN.

3-6 3.2.1 GENERAL

SUMMARY

3-6 3.2.2 NUCLEAR DESIGN AND EVALUATION 3-7

3. 2. 3 THERMAL AND HYDRAULIC DESIGN AND EVALUATION 3-32 3.2.4 MECHANICAL DESIGN LAYOUT.

3-68 3.3 TESTS AND INSPECTIONS 3-95 3.3.1 NUCLEAR TESTS AND INSPECTION 3-95 3.3.2 THERMAL AND HYDRAULIC TESTS AND INSh~.. N.

3-95 3.3.3 FUEL ASSEMBLY, C0FIROL ROD ASSEMBLY, AND CONTROL ROD DRIVE MECHANICAL TESTS AND INSPECTION.

3-98 3.3.h INTERNALS TESTS AND INSPECTIONS 3-103 3.h REFERENCES 3-10h h

REACTOR COOLANT SYSTD4.

Volume 1.

. Tab h h-1 4.1 PERFORMANCE OBJECTIVES 4-1 4.1.2 DESIGN CHARACTERISTICS 4-1 l

h l.3 EXPECTED OPERATING CONDITIONS 4-2

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h REACTOR COOLANT SYSTE4 (CONTINUED). Volume 1.

Tab k k.1.h SERVICE LIFE.

k-3 h.1.5 CODES AND CLASSIFICATIONS 4-6 h.2 SYSTEM DESCRIPTION AND OPERATION.

h-6 k.2.1 GENERAL DESCRIPTION 4-6 h.2.2 MAJOR COMPONENTS 4-6 h.2.3 PRESSURE-RELIEVING DEVICES h-12 4.2.h ENVIRONMENTAL PROTECTION.

h-12 4.2.5 MATERIALS OF CONSTRUCTION h-12 4.2.6 MAXIMU;4 HEATING AND COOLING RATES.

h-lh h.2.7 LEAK DETECTION h-lk h.3 SYSTB4 DESIGN EVALUATION k-16 4.3.1 SAFETY FACTORS 4-16 4.3.2 RELIANCE ON INTERCONNECTED SYSTEMS h-23 4.3.3 SYSTEM INTEGRITY h-23 4.3.h PRESSURE RELIEF.

4-23 h.3.5 REDUNDANCY h-2h b.3.6 SAFETY ANALYSIS.

4-24 4.3.7 OPERATIONAL LIMITS.

h-2h b.h TESTG AND INSPECTIONS 4-25 h.h.1 COMPONENT In-SERVICE INSPECTION h-25 h.h.2

' REACTOR COOLANT SYSTEM TESTS AND INSPECTIONS h-27 h.h.3 MATERIAL IRRADIATION SURVEILLANCE.

h-28 h.5 REFERENCES h.30

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CONTAIntE!E SYSTB4 Volume 2.

Tab 5.

5-1 (d

5.1 REACTOR BUILDING 5-1 5.1.1 DESIGN BASES.

5-1 5.1.2 STRUCTURE DESIGN 5-2 5.2 ISOLATION SYSTEM

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5-9 i

5.2.1 DESIGN BASES.

5-9 5.2.2 SYSTEM DESIGN 5-10 5.3 VENTILATION SYSTE4 5-11 5.3.1 DESIGN BASES.

5-11 5.3.2 SYSTE4 DESIGN 5-12 5.h LEAKAGE MONITORING SYSTEM 5-13 5.5 SYSTEM DESIGN EVALUATION 5-15 s.6 TESTS AND INSPECTION.

5-15 5.6.1 PREOPERATIONAL TESTING AND INSPECTION 5-15 5.6.2 POSTOPERATIONAL LEAK MONITORING 5-16 6

ENGINEERED SAFEGUARDS Volume 2.

Tab 6.

6-1 6.1 EMERGENCY INJECTION 6-1 6.1.1 DESIGN BASES.

6-1 6.

1.2 DESCRIPTION

6-2 6.1.3 DESIGN EVALUATION 6-3 6.1.4 TESTS AND INSPECTIONS.

6-6

'6.2 REACTOR BUILDING ATMOSPHERE COOLING AND WASHING.

6-13 6.2.1 DESIGN BASES.

6-13 r~'p N.J iii f

Section Page 6

ENGINEERED SAFEGUARDS (CONTINUED). Volume 2.

Tab 6 6.

2.2 DESCRIPTION

6-13 6.2.3 DESIGN EVALUATION 6-lk 6.2.h TESTS AND INSPECTIONS.

6-19 6.3 ENGINEERED SAFEGUARDS LEAKAGE AND RADIATION CONSIDEPATIONS 6-20 6.

3.1 INTRODUCTION

6-20 6.3.2 SUl' MARY OF POSTACCIDENT RECIRC'ULATION AND LEAKAGE CONSIDERATIONS 6-20 6.3.3 LEAKAGE ASSUMPTIONS 6-21 6.3.h DESIGN BASIS LEAKAGE 6-22 6.3.5 LEAKAGE ANALYSIS CONCLUSIONS 6-22 7

INSTRUMENTATION _AND CONTROL Volume 2.

Tab 7.

7-1 71 PROTECTION SYSTEMS 7-1 7.1.1 DESIGN BASES.

7-1 7.1.2 SYSTEM DESIGN 7-5 7.1 3 SYSTEMS EVALUATION.

7-11 7.2 REGULATING _ SYSTEMS 7-15 7 2.1 DESIGN BASES.

7-15 7.2.2 SYSTEM DESIGN 7-17 7.2.3 SYSTEM EVALUATION 7-22 73 INSTRUMENTATION 7-25 7.3.1 NUCLEAR INSTRUMENTATION 7-25 (3

7 3.2 NONNUCLEAR PROCESS INSTRUMENTATION 7-27

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7.3.3 INCORE MONITORING SYSTEM.

7-28 7.4 OPERATING CONTROL STATIONS 7-31 7.h.1 GENERAL LAYOUT 7-31 7.h.2 INFORMATION DISPLAY AND CONTROL FUNCTION 7-31 7.h.3

SUMMARY

OF ALARMS 7-31 7.h.h COMMUNICATION 7-32 7.h.5 OCCUPANCY.

7-32 7.h.6 AUXILIARY CONTROL STATIONS T-33 7.h.7 SAFETY FEATURES.

7-33 8

ELECTRICAL SY _ STEMS Volume 2.

Tab 8.

8-1 8.1 DESIGN BASES 8-1 8.2 ELECTRICA5~5YSTEM DESIGN 8-1 8.2.1 NETWORK INTERCONNECTIONS.

8-1 8.2.2 PLANT DISTRIBUTION SYSTEM B-2 8.2.3 SOURCES OF AUXILIARY POWER.

8-9l1 8-6 8.3.

TESTS AND INSPECTIONS 9

AUXILIARY AND ENERGENCY SYSTEMS.

Volume 2.

Tab 9.

9-1 9.1 MAKEUP _AND PURIFICATION SYSTEM 9-2

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iv (Revised 1-15-68).

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Section Page 9

AUXILIARY AND D4ERGENCY SYSTE4S (CONTINUED). Volume 2.

. Tab 9 9.1.1 DESIGN BASES

. 9-2 9.1.2 SYSTEM DESCRIPTION AND EVALUATION 9-3 9.'2 CHEMICAL ADDITION AND SAMFLING SYSTE!

9-9 9.2.1 DESIGN BASES 9-9 9.2.2 SYSTE4 DESCRIPTION AND EVALUATION 9-10 93 COOLING WATER SYSTEMS.

9-18 9.3.1 DESIGN BASES 9-18 9.3.2 SYSTE4 DESCRIPTION AND EVALUATION

. 9-19 9.h SPENT FUEL COOLING SYSTEM 9-24 9.h.1 DESIGN BASES 9-24 9.h.2 SYSTEM DESCRIPTION AND EVALUATION 9-24 9.5 DECAY HEAT REMOVAL SYSTEM 9-27 951 DESIGN BASES 9-27 9.5.2 SYSTEM DESCRIPTION AND EVALUATION 9-27 9.6 FUEL HANDLING SYSTE4

. 9-31 9.6.1 DESIGN BASES

. 9-31 9.6.2 SYSTEM DESCRIPTION AND EVALUATION

. 9-32 9.7 PLANT VENTILATION SYSTEMS 9-37 9.7.1 DESIGN BASES 9-37 9.7.2 SYSTE4 DESCRIPTION AND EVALUATION 9-37 10 STEAM AND POWER CONVERSION SYSTEM Volume 2.

Tab 10.

. 10-1 fi 10.1 DESIGN BASES

. 10-1 10.1.1 OPERATING AND PERFORMANCE REQUIRE 4ENTS

. 10-1 10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS.

. 10-1 10.1.3 FUNCTIONAL LIMITATIONS

. 10-1 10.1.h SECONDARY FUNCTIONS

. 10-1 10.2 SYSTEM DESIGN AND OPERATION

. 10-2 10.2.1 SCHEMATIC FLOW DIAGRAM

. 10-2 10.2.2 CODES AND STANDARDS

. 10-2 10.2.3 DESIGN FEATURES.

. 10-3 10.2.h SHIELDING.

. 10-3 10.2.5 CORROSION PROTECTION

. 10-3 10.2.6 IMPURITIES CONTROL,

. 10-3 10.2.7 RADIOACTIVITY

. 10-3 10.3 SYSTEM ANALYSIS

. 10-3 10 3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS

. 10-3 10.3.2 TRANSIENT CONDITIONS

. 10-4 10.3.3 MALFUNCTIONS

. 10-5 10.3.4 OVERPRESSURE PROTECTION

. 10-5 10.3.5 INTERACTIONS.

. 10-5 10.3.6 OPERATIONAL LIMITS.

. 10-5 10.h TESTS AND INSPECTIONS 10-5 v

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Section Page g-]

11 R_ADI0 ACTIVE WASTES AND RADIATION

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Volune 3 Tab 11.

. 11-1 11.1 RADIOACTIVE WASTES

. 11-1 11.1.1 DESIGN BASES.

. 11-1 11.1.2 SYSTEM DESIGN

. 11-3 11.1.3 TESTS AND INSPECTIONS.

. 11-12 11.2 RADIATION SHIELDING

. 11-12 11.2.1 PRI!!ARY. SECONDARY, REACTOR BUILDING, AND AUXILIAPY Sl!IELDING.

. 11-12 11.2.2 AREA RADIATION MONITORING SYSTEM

. 11-17 11.2.3 HEALTH PilYSICS

. 11-18 11.3 RE_FE.RENCES

. 11-22 I?

CONCUCT OF OPEPATIONS Volume 3.

Tab 12.

. 12-1 12.1 ORGANIZATION AND RESPONSIBILITY

. 12-1 12.1.1 FUNCTIONAL DESCRIPTION

. 12-1 12.1.2 QUALIFICATIONS

. 12-2 12.1.3 ORGANIZATION DIAGRAM

. 12-2 12.2 TRAINING

. 12-2 12.2.1 STATION STAFF

. 12-2 12.2.2 REPLACEMENT PERSONNEL.

. 12-5 12.2.3 ON-THE-JOB TRAINING

. 12-6 12.2.4 EMERGENCY PLANS 12-6l 12.2 5 PROCEDURES APPLICABLE TO ACCIDENTS INVOLVING O'

RADIOACTIVE MATERIALS

. 12-6 12.3 WRITTEN PPOCEDURES

. 12-7 12.h RECORDS

. 12-7 12 5 ALMINISTRATIVE CONTROL

. 12-7 13 INITIAL TESTS AND OPERATION Volume 3.

Tab 13.

. 13-1 13.1 TESTS PRIOR TO reactor PUELING

. 13-1 13.2 INITIAL CRITICALITY

. 13-1 13 3 POSTCRITICALITY TESTS

. 13-1 1h SAFETY ANALYSIS Volume 3 Tab 14.

. 14-1 14.1 CORE AND COOLANT BOUNDARY PPOTECTION ANALYSIS

. 1k-1 1k.1.1 ABNORMALITIES

. Ik-1 14.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES.

. 1h-3 14.2 STANDBY SAFEGUARDS ANALYSIS

. Ik-20 14.2.1 SITUATIONS ANALYZED AND CAUSES.

. 1h-20 lb.2.2 ACCIDENT ANALYSES

. Ih-21

-14.3 REFEFENCES

. 1h-57 15 TECHNICAL SPECIFICATIONS Volume 3.

Tab 15.

. 15-1 A

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vi (Revised 1-15-68)

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,i-TABLE OF APPENDICES

\\~-l Appendix 1A TECHlICAL QUALIFICATICUS.

. Appendices

. Tab 1A 2A POPULATIO:1 A:lD LA!!D USE

. Appendices

. Tab 2A 2B METEOROLOGY

. Appendices.

. Tab 2B 2C FLOOD STUDIES A!!D HURRICANE EFFECTS

. Appendices.

. Tab 2C 2D RADI0 ACTIVE LIQUID WASTE DISCRARGE LIMITS.

. Appendices.

. Tab 2D 2E GROUNDWATER

. Appendices.

. Tab 2E 2F GENERAL GEOLOGY--REGIONAL TECTONICS

. Appendices.

. Tab 2F 2G E:lGI:iEERING GEOLOGY AND FOUNDATION STUDIES.

. Appendices.

. Tab 2G 2H BEDROCK SOLUTION STUDIES.

. Appendices.

. Tab 2H 2I SEISMOLOGY..

. Appendices.

. Tab 2I SA STRUCTURAL..

..... Appendices.

. Tab SA SB DESIGN PROGRAM FOR REACTOR BUILDING

. Appendices..... Tab 5B SC DESIGN CRITERIA FOR REACTOR BUILDING.. Appendices.

. Tab SC SD QUALITY CONTROL

. Appendices.

. Tab SD SE LINER PLATE SPECIFICATION

. Appendices

. Tab 5E 5F REACTOR BUILDING INSTRUMENTATION.

. Appendices

. Tab 5F SG TURBINE-GENERATOR MISSILES.

. Appendices.

. Tab 5G

's 12A FLORIDA PUBLIC SAFETY E ERGENCY

\\2 PROCEDURES.

. Appendices.

. Tab 12A Supplement 1

Response to DRL letter,1-19-68..... Volume h.. Supplement No.1 2

Voluntary Response to AEC Cral Inquiry. Volume h.. Supplement No. 2 3

Voluntary Response to AEC Oral Inquiry. Volume h.. Supplement No. 3 4

Response to DRL letter, 3-13-69..... Volume h.. Supplement No. h 5

Reeponse to DRL letter, 11-8-69..... Volume 5.. Supplement No. 5 6

Response to DRL letter,11-8-69..... Volume 5.. Supplement No. 6

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