ST-HL-AE-1108, Forwards Characterization of FSAR Changes Since Dec 1981,per 840612 Commitment.Documents That Have Been or Will Be Submitted for NRC Review Listed

Forwards Characterization of FSAR Changes Since Dec 1981,per 840612 Commitment.Documents That Have Been or Will Be Submitted for NRC Review Listed

ML20092N799
Person / Time
Site:	South Texas
Issue date:	07/02/1984
From:	Goldberg J HOUSTON LIGHTING & POWER CO.
To:	Novak T Office of Nuclear Reactor Regulation
References
ST-HL-AE-1108, NUDOCS 8407050064
Download: ML20092N799 (17)

Text

,

The Light m m P u y ii""s'e"iisi"i"a & re-<< ito.n"xivoo >1eese".1<x s77"oi <7is>228-92ii July 2, 1984 ST-HL-AE-1108 File No: G5/G9.2 Mr. Thomas M. Novak U. S. Nuclear Regulatory Commission Assistant Director for Licensing Division of Licensing 7920 Norfolk Avenue Bethesda, MD 20016

Dear Mr. Novak:

South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Characterization of FSAR Changes In accordance with our commitment to you on June 12, 1984, we are forwarding with this letter the characterization of changes in the FSAR since December 1981.

We reviewed the FSAR to determine the nature of changes, without regard to the technical content, and assessed the nature of chan3es by section as major, minor, or none. The "none" category includes minor word changes, section title changes, and editorial changes. Although the review was necessarily subjective, it will aid an NRC reviewer in determining the amount of time necessary to read the information that has changed.

The Standard Review Plan Table of Contents was used as a guideline for FSAR section breakdown. Sections that are not addressed in the SRP were include / in the characterization down to the subsection level (i.e.,

xx.xx.xx).

The amendment with the most impact on each section has also been noted.

For those sections currently in the review process and those scheduled for future update, the amendment in which those sections are scheduled for publication is noted. Amendment 39 is in final management review now and should be submitted to the NRC within two weeks.

Please note that the NRC questions and responses were not listed individually on the attachments. We consider all of " Responses to NRC Questions, Volume II" and the responses to the 211 series questions in Volume I to be major review items.

B407050064 840702 PDR ADOCK 05000498 A

PDR

[j W2/NRC2/q l

I

C flouston Lighting se Power company ST-HL-AE-1108 File No: G5/G9.2 Page 2 In_ addition to the FSAR, the following documents have been or will be submitted for NRC review:

o Final Control Room Design Review o

Final Heavy Loads Report o

Security Plan o

Fire Hazards Analysis Report July 84 o

Emergency Plan Sept 84 o

-Tech Specs Jan 85 If you should have any questions concerning this matter, please contact Mr. ' Michael E. Powell at (713) 993-1320.

Very truly yours, J. H. Goldberg Vice President Nuclear Engineering and Construction JHG/JTC/mg_

Attachment:

Characterization of FSAR Changes 1

W2/NRC2/q

F Ilouston Lighting & Power Company ST-HL-AE-1108 File Number: G5/G9.2 Page 3 cc:

Darrell G. Eisenhut, Director Brian E. Berwick, Esquire Division of Licensing Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P. O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 John T. Collins Lanny Sinkin Regional Administrator, Region IV Citizens Concerned About Nuclear Power Nuclear Regulatory Commission 114 W. 7th, Suite 220 611 Ryan Plaza Drive, Suite 1000 Austin, TX 78701 Arlington, TX 76012 Robert G. Perlis, Esquire Victor Nerses, Project Manager Hearing Attorney U.S. Nuclear Regulatory Commission Office of the Executive Legal Director 7920 Norfolk Avenue U.S. Nuclear Regulatory Commission Bethesda, MD 20016 Washington, DC 20555 D. P. Tomlinson Charles Bechhoefer, Esquire Resident Inspector / South Texas Project Chairman, Atomic Safety & Licensing Board c/o U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission P. 0. Box 910 Washington, DC 20555 Bay City, TX 77414 Dr. James C. Lamb, III M. D. Schwarz, Jr., Esquire 313 Woodhaven Road Raker & Botts Chapel Hill, NC 27514 One Shell Plaza Houston, TX 77002 Judge Ernest E. Hill Hill Associates J. R. Newman, Esquire 210 Montego Drive Newman & Holtzinger, P.C.

Danville, CA 94526 1025 Connecticut Avenue, N.W.

Washington, DC 20036 William S. Jordan, III, Esquire Director, Office of Inspection Harmon & Weiss and Enforcement 1725 I Street, N.W.

U.S. Nuclear Regulatory Commission Suite SOS Washington, DC 20555 Washington, DC 20006 E. R. Brooks /R. L. Range Citizens for Equitable Utilities, Inc.

Central Power & Light Company c/o Ms. Peggy Buchorn P. O. Box 2121 Route 1, Box 1684 Corpus Christi, TX 78403 Brazoria, Texas 77422 H. L. Peterson/G. Pokorny City of Austin P. O. Box 1088 Austin, TX 78767 J. B. Poston/A. vonRosenberg City Public Service Board P. O. Box 1771 San Antonio, TX 78296 Revised 04/03/84 W2/NRC2/q

'PAGE NO. OCC01 SECTIONSWITHfAJOR)(CHANGESSINCEAMENDMENT22 (DEC 1981)

C6/29/84

1. ~"

SECTION TITLE AMENDMENT 01.2 GENERAL PLANT DESCRIPTION 36 01.5.1 VERIFICATION TESTS (17x17 XLR FUEL 33 ASSEMBLY) 01.7 ELECTRICAL, INSTRUMENTATION, AND CONTROL 36 DRAWINGS C2.1.2 EXCLUSION AREA AUTHORITY AND CONTROL 30 02.1.3 POPULATION DISTRIBUTION 30 02.2 NEARBY INDUSTRIAL, TRANSPORTATION AND 35 MILITARY FACILITIES C2.4.11 LOW WATER CONSIDERATION 40+

C2.4.12 DISPERSION, DILUTION, AND TRAVEL TIMES 40+

OF ACCIDENTAL RELEASES OF LIQUID EFFLUENTS IN SURFACE WATER C2.4.13 GROUNDWATER 40+

O2.4.2 FLOODS 40+

G2.4.3 PROBABLE MAXIMUM FLOOD OF STREAMS AND 40+

RIVERS 02.4.4 POTENTIAL DAM FAILURES (SEISMICALLY 40+

INDUCED) i C2.4.5 PROBABLE MAXIMUM SURGE AND SEICHE 40+

FLOODING

-C2.4.8 COOLING WATER CANALS AND RESERVOIRS 40+

C3.10 SEISMIC QUALIFICATION OF CATEGORY I 38 INSTRUMENTATION AND ELECTRICAL EQUIPMENT

'C3.10N SEISMIC QUALIFICATION OF CATEGORY I 40+

INSTRUMENTATION AND ELECTRICAL EQUIPMENT: NSSS

-C3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND 38 ELECTRICAL EQUIPMENT lC3.11N ENVIORNMENTAL DESIGN OF MECHANICAL AND 40+

ELECTRICAL EQUIPMENT: NSSS C3.12 CONFORMANCE WITH NRC REGULATORY GUIDES 38 NOTE: 40+ indicates' subsequent to Amendment 40

PAGE NO. CCCO2 SECTIONS ~WITH MAJORjCHANGES SINCE AMENDMENT 22 (DEC 1981)

" ^ ~ '

C6/29/84 SECTION TITLE AMENDMENT 03.2 CLASSIFICATION.0F STRUCTURES, 33 COMPONENTS, AND SYSTEMS 03.3.2 TORNADO LOADINGS 33 03.4.1 FLOOD PROTECTION 40+

03.5.1 MISSILE SELECTION AND DESCRIPTION 36 C3.5.1.1 INTERNALLY GENERATED MISSILES OUTSIDE 36 THE CONTAINMENT C3.5.1.3 TURBINE MISSIL ES 36

-03.3.3 BARRIER DESIGN PROCEDURES 36

.03.6 PROTECTION AGAINST DYNAMIC EFFECTS 40 ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 03.6.1 POSTULATED pit'ING ANALYSIS IN FLUID 40 SYSTEMS-C3.6.2 DETERMINATION OF BREAK LOCATIONS AND 40 DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING C3.7.3A SEISMIC SUBSYSTEM ANALYSIS, BALANCE OF 34 PLANT (BOP, EXCLUSIVE OF NSSS)

C3.7.38 SEISMIC SUBSYSTEM ANALYSIS, NSSS SCOPE 34 03.7.4 SEISMIC INSTRUMENTATION 34 C3.8 DESIGN OF CATEGORY I STRUCTURES 40 03.8.4 OTHER SEISMIC CATEGORY I STRUCTURES 40 C3.8.A COMPUTER PROGRAMS USED IN STRUCTURAL 40 ANALYSIS 03.8.B VISUAL INSPECTION ACCEPTANCE CRITERIA 32 FOR STRUCTURAL STEEL AND MISCELLANEOUS STEEL WELDING TO MEET DESIGN REQUIREMENTS C3.9.2 DYNAMIC TESTING AND ANALYSIS 40+

C3.9.3 ASME CODE CLASS 1,

2, AND 3 COMPONENTS, 40+

COMPONENT SUPPORTS, AND CORE SUPPORT STRUCTURES

n PAGE NO. C0023 SECTIONS WITH MAJORlCHANGES SINCE AMENDMENT 22 (DEC 1981)

.C6/29/84 SECTION TITLE AMENDMENT C3.9.6 INSERVICE TESTING OF PUMPS AND VALVES 40+

04.3 NUCLEAR DESIGN 30

.04.4.6 INSTRUMENTATION REQUIREMENTS 30 05.4.15 REACTOR HEAD VENT SYSTEM 38 C5.4.A COLD SHUTDOWN CAPABILITY - RESPONSE TO 38 BRANCH TECHNICAL POSITION RSB 5-1 C6.1.2 ORGANIC MATERIALS 33 06.1.3 POSTACCIDENT CHEMISTRY 33 C6.2.1 CONTAINMENT FUNCTIONAL DESIGN 40+

06.2.1.1 CONTAINMENT 40+

C6.2.1.2 CONTAINMENT SUBCOMPARTMENT ANALYSIS 40+

C6.2.1.3

~ MASS AND ENERGY RELEASE ANALYSIS.FOR 40+

POSTULATED LOSS-OF-COOLANT ACCIDENTS C6.2.1.4 MASS AND ENERGY RELEASE ANALYSIS FOR 40+

POSTULATED SECONDARY SYSTEM PIPE RUPTURES INSIDE CONTAINMENT C6.2.1.5 MINIMUM CONTAINMENT PRESSURE ANALYSIS 40+

FOR PERFORMANCE CAPABILITY FTUDIES OF EMERGENCY CORE COOLING SYSTEM C6.2.4 CONTAINMENT ISOLATION SYSTEM 39 C6.2.5 COMBUSTIBLE GAS CONTROL IN CONTAINMENT 38 C6.2.6 CONTAINMENT LEAKAGE TESTING 39 C6.4 HABITABILITY SYSTEMS 38 C6.5.2 CONTAINMENT SPRAY SYSTEM - IODINE 38 REMOVAL G

7.1 INTRODUCTION

40+

G7.3 ENGINEERED SAFETY FEATURES SYSTEMS 40+

G7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 40+

G7.5 SAFETY RELATED DISPLAY INSTRUCTIONS 40

$ddDE CHANGES SINCE AMENDMENT 22 (DEC 1981)

PAGE NO. 00004 SECTIONS WITHi 3

C6/29/84 SECTION TITLE AMENDMENT

-07.6 ALL OTHER SYSTEMS REQUIRED'FOR SAFETY 40+

G7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 40+

C7A POST-TMI REQUIREMENTS - RESPONSE TO 40+

NUREG-0737 CLARIFICATION OF TMI ACTION PLAN REQUIREMENTS C7B-COMPLIANCE WITH REGULATORY GUIDE 1.97, 40+

REV. 2 C

3.1 INTRODUCTION

36

'08.2 OFFSITE POWER SYSTEM 36 C8.3.1 AC POWER SYSTEMS 36 C8.3.2 DC. POWER SYSTEMS 36 09.1.4 FUEL HANDLING SYSTEM 40+

E9.2.1 SERVICE WATER SYSTEMS 39 C9.2.2 COMPONENT COOLING WATER SYSTEM 39 C9.2.3 MAKEUP DEMINERALIZED WATER SYSTEh 39 C9.2.4 POTABLE AND SANITARY WATER SYSTEM 39 C9.2.5 ULTIMATE HEAT SINK 39 C9.2.6 CONDENSATE STORAGE FACILITIES 39 C9.2.7 REACTOR MAKEUP WATER SYSTEM 39 C9.2.8 FRESH WATER AND SERVICE WATER SYSTEh3 39 C9.3.1 COMPRESSED AIR SYSTEM 40 C9.3.2 PROCESS SAMPLING SYSTEMS 40 C9.3.3 EQUIPMENT AND FLOOR DRAIN SYSTEM 40 C9.3.6 FAILED FUEL DETECTION 40

.09.4.1 ELECTRICAL SUXILIARY BUILDING HVAC 40+

SYSTEM C9.4.2 FUEL HANDLING BUILDING HVAC SYSTEM 40+

y SECTIONSWITH!MAJON)CHANGESSINCEAMENDMENT22

~PAGE NO. 02:05 06/29/84

~

(DEC 1981)

SECTION TITLE AMENDMENT 09.4.3 MECHANICAL BUILDING HVAC SYSTEM 40+

E9.4.4 TGB HVAC 40+

C9.4.5 RCB HVAC 40+

C9.4.6 DGB HVAC SYSTEM 40+

09.4.7 MISCELLANEOUS BUILDING HVAC SYSTEM 40+

C9.4.8 MAIN STEAM ISOLATION BUILDING 40+

VENTILATION SYSTEM C9.5.1 FIRE PROTECTION SYSTEM 40 09.5.10

' AUXILIARY FUEL OIL STORAGE AND TRANSFER 40 SYSTEM C9.5.2 COMMUNICATIONS SYSTEMS 40 C9.5.3 Pl. ANT LIGHTING SYSTEMS 40+

09.5.4 DIESEL GENERATOR FUEL OIL STORAGE AND 40 TRANSFER SYSTEM C9.5.5 DIESEL GENERATOR COOLING WATER SYSTEM 40 C9.5.6 DIESEL GENERATOR STARTING SYSTEM 40 C9.5.7 DIESEL GENERATOR' LUBRICATION SYSTEM 40 C9.5.8 DIESEL GENERATOR COMBUSTION f,IR INTAKE 40 AND EXHAUST SYSTEM 09.5.9 AUXILIARY STEAM SYSTEM 40 10.3 MAIN STEAM SUPPLY SYSTEM 39 10.3.6 STEAM AND FEEDWATER SYSTEM MATERIALS 39 10.4.1 CONDENSER 39 10.~4.2 MAIN CONDENSER EVACUATION SYSTEM 39 10.4.3 TURBINE GLAND SEALING SYSTEM 39 10.4.6 CONDENSATE POLISHING DEMINERALIZER 39 SYSTEM 10.4.8

-STEAM GENERATOR BLOWDOWN SYSTEM 39

[

~ P A G E' N O. ' 0 0 _T 0 6~

SECTIONS WITH MAJOR. CHANGES SINCE AMENDMENT 22 (DEC 1981)

~~#

C6/29/84 SECTION TITLE AMENDMENT

'10.4.9 AUXILIARY FEEDWATER SYSTEM 39 1EA AUXILIARY FEEDWATER SYSTEM RELIABILITY 40+

EVALUATION 11.3 GASEOUS WASTE MANAGEMENT SYSTEM 39 11.4 SOLID WASTE MANAGEMENT SYSTEM 39 11.5 PROCESS AND EFFLUENT RADIOLOGICAL 40+

MONITORING AND SAMPLING SYSTEMS 11.A OFFSITE RADIOLOGICAL IMPACT DUE TO 40+

EFFLUENTS RESULTING FROM OPERATION OF THE SOUTH TEXAS PROJECT 12.1 ASSURING THAT. OCCUPATIONAL RADIATION 37 EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE 12.2 RADIATION SOURCES 37 12.3-12.4 RADIATION PROTECTION DESIGN FEATURES 39 13.1.1 MANAGEMENT AND TECHNICAL SUPPORT 30 ORGANIZATION 13.1.2-13.1.3 OPERATING ORGANIZATION 30 13.5.1 ADMINISTRATION PROCEDURES 24 13.'5.2 OPERATING AND MAINTENANCE PROCEDURES 24 13.6 PHYSICAL SECURITY 30 15.1.5 SPECTRUM OF STEAM SYSTEM PIPING FAILURE 40+

INSIDE AND OUTSIDE CONTAINMENT 15.5.1-15.5.2 INADVERTENT OPERATION OF ECCS AND 40+

i CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION THAT INCREASES REACTOR COOLANT INVENTORY 15.6.2 FAILURE OF SMALL LINES CARRYING PRIMARY 40+

COOLANT OUTSIDE CONTAINMENT l

15.6.3 STEAM GENERATOR TUBE RUPTURE 40+

15.7.1 WASTE GAS SYSTEM FAILURE 40+

l

'PAGE NO 00007 SECTIONS WITH.HAJOR'3 CHANGES SINCE AMENDMENT 22 (DEC 1981)

• " ~ ~ ~

C6/29/84 SECTION TITLE AMENDMENT 15.7.2 RADIOACTIVE LIQUID WASTE SYSTEM LEAK OR 40+

FAILURE (RELEASE TO ATMOSPHERE) 15.7.3 POSTULATED RADIOACTIVE RELEASE DUE TO 40+

LIQUID-CONTAINING TANK FAILURES

. 15.7.4 DESIGN BASIS FUEL HANDLING ACCIDENTS 40+

15.7.5 SPENT FUEL CASK DROP ACCIDENT 40+

i

. 15.A FISSION PRODUCT-INVENTORIES 40+

i 15.B DOSE MODELS 40+

I I

i

+

P l

I

~.

PAGE NO. 00001 SECTIONS WITH MI'NOR) CHANGES SINCE AMENDMENT 22 (DEC 1981) w SECTION TITLE AMENDMENT C1.1.1 GENERAL INFORMATION 27 C1.2.1 SITE CHARACTERISTICS 36

.C1.3 COMPARISON TABLE 36 01.4.3 ENGINEER / CONSTRUCTION MANAGER AND 35 CONSTRUCTOR C1.5.5 RAPID REFUELING HARDWARE TESTS 33

'01.5.7 PROTOTYPE CONTROL ROD DRIVE MECHANISM 33 WITH ROD HOLD-OUT DEVICE SYSTEM TEST C155.8 WESTINGHOUSE TEST ENGINEERING LABORATORY 33 FACILITY G1.6 MATERIAL. INCORPORATED BY REFERENCE 33 C2.2.1-02.2.2 IDENTIFICATION OF POTENTIAL HAZARDS IN 35 SITE VICINITY C2.

2.2 DESCRIPTION

S 35 C2.2.3 EVALUATION OF POTENTIAL ACCIDENTS 35 C2.3.1 REGIONAL CLIMATOLOGY 39 C2.4.~1 HYDROLOGIC DESCRIPTION 40+

C2.4.10 FLOODING PROTECTION REQUIREMENT 40+

O2.4.6 PROBABLE MAXIMUM TSUNAMI FLOODING 40+

C2.5.1 BASIC GEOLOGIC AND SEISMIC INFORMATION 35

-C2.5.2 VIBRATORY GROUND MOTION 25 C:2. 5. 4 STABILITY OF SUBSURFACE MATERIALS 36 02.5.5 STABILITY OF SLOPES 35 C2.5.6 EMBANKMENT AND DAMS 36 C2.5.A FOUNDATION VERIFICATION 35 C2.5.B GEOLOGIC MAPPING INDEX 35 C2.5.C GEOTECHNICAL MONITORING 36

F.

PAGE NO. CC002 SECTIONS WITH MI,NORiCHANGES SINCE AMENDMENT 22 (DEC 1981)

C6/29/84 SECTION TITLE AMENDMENT 03.1.2 CRITERIA CONFORMANCE 33 03.3.1 WIND LOADING 33 C3.4.2 ANALYSIS PROCEDURES 40+

C3.5.1.2 INTERNALLY GENERATED MISSILES INSIDE THE 36 CONTAINMENT

.C3.5.1.4 MISSILES GENERATED BY NATURAL PHENOMENA 36 03.5.1.6 AIRCRAFT HAZARDS 36 03.7.1 SEISMIC INPUT 34 C3.7.2 SEISMIC SYSTEM ANALYSIS 34 03.8.1 CONCRETE CONTAINMENT 40 C3.8.2 STEEL CONTAINMENT SYSTEM (ASME CLASS MC 40 COMPONENTS)

C3.8.3 CONCRETE AND STRUCTURAL STEEL INTERNAL 40 STRUCTURES OF CONCRETE CONTAINMENTS C3.9.1 SPECIAL TOPICS FOR MECHANICAL COMPONENTS 40+

C3.9.4 CONTROL ROD DRIVE SYSTEMS 40+

C3.9.5 REACTOR PRESSURE VESSEL INTERNALS 40+

C4.1

SUMMARY

DESCRIPTION 30 C4.2 FUEL SYSTEM DESIGN 30 C4.4 THERMAL AND HYDRAULIC DESIGN 30

'C4.5.2 REACTOR INTERNALS MATERIALS 27

..C4. 6 FUtlCTIONAL DESIGN OF CONTROL ROD DRIVE 27 SYSTEM C5.1.1 SCHEMATIC FLOW DIAGRAM 30

C5.2.1 COMPLIANCE WITH CODES AND CODE CASES 33 C5.2.2~

OVERPRESSURE PROTECTION 33 85.2.3 REACTOR COOLANT PRESSURE BOUNDARY 33 MATERIALS i

7 PAGE:NO. 20003 SECTIONS WITH MINOR, CHANGES SINCE AMENDMENT 22 iDEC 1981)

C6/29/84 SECTION TITLE AMENDMENT 05.2.4 INSERVICE INSPECTION AND TESTING OF THE 33 REACTOR COOLANT PRESSURE BOUNDARY C5.2.5 REACTOR COOLANT PRESSURE BOUNDARY 33 LEAKAGE DETECTION SYSTEM C5.3.2-PRESSURE-TEMPERATURE LIMITS 27 C5.4.10 PRESSURIZER 38 C5.4.11 PRESSURIZER RELIEF DISCHARGE SYSTEM 38 C5.4.12-VALVES 38 C5.4.'13 SAFETY AND RELIEF VALVES 38 C5.4.14 COMPONENT SUPPORTS 38 C5.4.2 STEAM GENERATOR 38 C5.4.2.1 STEAM GENERATOR MATERIALS 38 05.4.2.2 STEAM GENERATOR TUBE INSERVICE 38 INSPECTION C5.4.3 REACTOR COOLANT PIPING 38 "C5.4.7 RESIDUAL HEAT REMOVAL SYSTEM 38

'E6.2.2 CONTAINMENT HEAT REMOVAL SYSTEMS 38 06.3.

EMERGENCY CORE COOLING SYSTEM 36 06.6 INSERVICE INSPECTION OF ASME CODE CLASS 31 2 AND CLASS 3 COMPONENTS G7.2 REACTOR TRIP SYSTEM 40+

09.1.2 SPENT FUEL STORAGE 36 C9.1.3

-SPENT FUEL POOL COOLING AND CLEANUP 36 SYSTEM C9.3.4 CHEMICAL AND VOLUME CONTROL SYSTEM / BORON 39 RECYCLE SYSTEM C9.5.1.A.

STP COMPLIANCE WITH BRANCH TECHNICAL 40 POSITION APSCB 9.5-1, APPENDIX A (REPLACED BY FHAR)

PAGE NO. 00004 SECTIONS WITH MI,NOR? CHANGES SINCE AMENDMENT 22 (DEC 1981) 06/29/84 SECTION TITLE AMENDMENT 10.1

SUMMARY

DESCRIPTION 39 10.2 TURBINE GENERATOR 39 10.2.3 TURBINE MISSILES 39 10.4.4 TURBINE BYPASS SYSTEM 39 10.4.5 CIRCULATING WATER SYSTEM 39 10.4.7 CONDENSATE AND FEEDWATER SYSTEMS 39 11.1 SquRCE TERMS 39 11.2 LIQUID WASTE MANAGEMENT SYSTEMS 39 12.5 HEALTH PHYSICS 37 13.2.1 PLANT STAFF TRAINING PROGRAM 24 13.3 EMERGENCY PLANNING 28 13.4 REVIEW AND AUDIT 28 14.1 SPECIFIC INFORMATION TO BE INCLUDED IN 40 PRELIMINARY SAFETY ANALYSIS REPORTS (SECTION DELETED) 14.2 INITIAL PLANT TEST PROGRAM 40

15.0 INTRODUCTION

(ACCIDENT ANALYSIS) 40+

15.1.1-15.1.4 DECREASE IN FEEDWATER TEMPERATURE, 40+

INCREASE IN FEEDWAER FLOW, INCREASE IN STEAM FLOW, AND INADVERTENT OPENING OF A STEAM GENERATOR RELIEF OR SAFETY VALVE 15.2.1-15.2.5 LOSS OF EXTERNAL LOAD, TURBINE TRIP, 40+

LOSS OF CONDENSER VACUUM, CLOSURE OF MAIN STEAM ISOLATION VALVE AND STEAM PRESSURE REGULATORY FAILURE (CLOSED)

=15.2.6 LOSS OF NONEMERGENCY AC POWER TO THE 40+

STATION AUXILIARIES (LOSS OF OFFSITE POWER) 15.2.7 LOSS OF NORMAL FEEDWATER FLOW 40+

15.2.8 FEEDWATER SYSTEM PIPE BREAK 40+

- PAGE NO. 0:0 5 SECTIONS WITH MINORiCHANGES SINCE AMENDMENT 22 (DEC 1981)

C6/29/84 SECTION TITLE AMENDMENT 15.3.1-15.3.2 LOSS OF FORCED REACTOR COOLANT FLOW 40+

INCLUDING TRIP OF PUMP AND FLOW CONTROLLER MALFUNCTIONS 15.3.3-15.3.4 REACTOR COOLANT PUMP ROTOR SEIZURE AND 40+

REACTOR COOLANT PUMP SHAFT BREAK 15.4.1 UNCONTROLLED ROD CLUSTER CONTROL 40+

ASSEMBLY BANX WITHDRAWAL FROM A SUBCRITICAL OR LOW POWER STARTUP CONDITION 15.4.2 UNCONTROLLED ROD CLUSTER CONTROL 40+

ASSEMBLY BANK WITHDRAWAL AT POWER 15.'4.3 ROD CLUSTER CONTROL ASSEMBLY 40+

MISOPERATION 15.4.4 STARTUP OF AN INACTIVE REACTOR COOLANT 40+

LOOP AT AN INCORRECT TEMPERATURE 15.4.6 CHEMICAL AND VOLUME CONTROL SYSTEM 40+

MALFUNCTION THAT RESULTS IN A DECREASE IN THE BORON CONCENTRATION IN THE REACTOR COOLANT 15.4.7 INADVERTENT LOADING OF A FUEL ASSEMBLY 40+

INTO AN IMPROPER POSITION 15.4.8 SPECTRUM OF ROD CLUSTER CONTROL ASSEMBLY 40+

EJECTION ACCIDENTS 15.6.5 LOSS OF-COOLANT ACCIDENTS 40+

15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM 40+

17.2 QUALITY ASSURANCE DURING THE OPERATIONS 27 PHASE 6

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01.1.2 J;, ORGANIZATION OF CONTENTS

' OWNERS

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01.4.1-01.4.'2 APPLICANT

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N, 01.4.4 hUCLEAR STEAM SUPRLY SYSTEM SUPPLIER 01.4.5 CONSULTANTS 01.5.2 LOWER INTERNALS.1/7 SCALE MODEL INTERNALS TEST 0,

01.5.3 LOWER INTERNALS VIBRATION TEST N

-01.5.4 LOCA HEAT TRANSFER (17x17 XLR)l

\\

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01.5.'6 PROTOTYPE ROTO-LOK CLO JRE SYSTEii. TEST 02.1.1-..

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SITE LOCATION AND DESCRIPTIONN 302.2.B GHS WELL ACCIDCNT ANALYSIS

.02.2.D CELANESE PIPELI'hES

\\'

s 102.3.2 LOCAL METEOROLOGY 02.3.3 ONSITE METEOROLOGICAL MEASUREMENT PROGRAM oO2.3.4 SHORT-TERM (ACCIDENT) DIFFUSION ESTIMATES O2.3.5 LONG-TERM (ROUTINE) DIFFUSION ESTIMATES O2.4.14 TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTS 0 2. 4. 7-ICE EFFECTS O2.4.9 CHANNEL DIVERSIONS O2.5.3 SURFACE FAULTING

-03.1.1

SUMMARY

DESCRIPTION 03.5.1.5 MISSILES GENERATED BY EVENTS NEAR THE SITE.

03.5.2-SYSTEMS TO BE PROTECTED

PAGE~NO..OOOO2 SECTIONS WITH.NOLCHANGES SINCE AMENDMENT 22 (DEC 1981) 06/27/84 SECTION-TITLE 03.7.A DYNAMId LATERAL EARTH PRESSURES 03.8.5 FOUNDATIONS AND CONCRETE SUPPORTS 04.5.1 CONTROL ROD SYSTEM STRUCTURAL MATERIALS 05i1.2 PIPING AND INSTRUMENTATION DIAGRAM 05.1.3:

ELEVATION DRAWINGS 05.2.1.1-COMPLIANCE WITH 10CFR50.55a 05.3.1 REACTOR VESSEL MATERIALS 05.3.3 REACTOR VESSEL INTEGRITY 05.4.1.1 DESIGN BASES 05.4.4.

MAIN STEAM LINE FLOW RESTRICTOR 05.4.5 MAIN STEAM ISOLATION SYSTEM 05.4.9 MAIN STEAM AND FEEDWATER PIPING 06.'1.1 METALLIC MATERIALS 0>6r. 5. 3 FISSIOtt PRODUCT CONTROL SYSTEMS 09.1.1 NEW FUEL STORAGE 13.2.2 REPLACEMENT AND RETRAINING 13.2.3 FIRE BRIGADE TRAINING 13.2.4 APPLICABLE NRC DOCUMENTS 15.0.2 OPTIMIZATION OF CONTROL SYSTEMS 15.6.1 INADVERTENT OPENING OF A PRESSURIZER SAFETY OR RELIEF VALVE