CY-98-005, Forwards Volumes 1-3 to Decommissioning UFSAR, Which Accurately Presents Changes Completed Since Previous Submittal.Ufsar Will Be Updated IAW 10CFR50.71(e)(4),as Plant Continues to Recategorize Structures,Sys & Components

Forwards Volumes 1-3 to Decommissioning UFSAR, Which Accurately Presents Changes Completed Since Previous Submittal.Ufsar Will Be Updated IAW 10CFR50.71(e)(4),as Plant Continues to Recategorize Structures,Sys & Components

ML20199F943
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/26/1998
From:	Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20199F950	List: CY-98-005, Forwards Volumes 1-3 to Decommissioning UFSAR, Which Accurately Presents Changes Completed Since Previous Submittal.Ufsar Will Be Updated IAW 10CFR50.71(e)(4),as Plant Continues to Recategorize Structures,Sys & Components
References
CY-98-005, CY-98-5, NUDOCS 9802040177
Download: ML20199F943 (3)

Text

_ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - - .

ONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT '[

362 INJUN HOLLOW ROAD e EAST HAMPToN. CT 06424-3099 January 26,1998 i

Docket No. 50-213 CY-98-005 Re: 10CFR50.71(e)

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Decommissioning Uodated Final Safety Analvsis Report The purpose of this letter is for Connecticut Yankee Atomic Power Company (CYAPCO) to provide the initial publication of the Decommissioning Updated Final Safety Analysis Report (UFSAR). This document is provided in Attachment 1 and is a complete revision of the Haddam Neck Plant (HNP) UFSAR.

Revision 10 has been prepared to resolve previously identified discrepancies and to reflect changes that have occurred since the previous submittalW as a result of the defueled status of the Haddam Neck Plant. In a letter dated December 5,1996,(2)

CYAPCO informed the NRC that the Board of Directors of CYAPCO had decided to permanently cease operations at the HNP and that the fuel had been permanently removed from the reactor. Since that time, many of the systems and components have been recategorized to reflect the permanently defueled status. The recategorization effort is ongoing and coincides with decommissioning needs. In addition, the design basis accidents were revised and updated to reflect the permanently defueled status.

Pursuant to 10CFR50.71(e)(2)(i), I certify that this revision accurately presents changes completed since our previous submittal that are necessary to reflect information and analyses associated with changing the plant from power operations to the current (1) CYAPCO Letter 815762, from T. C. Feigenbaum, to the U. S. Nuclear Regulatory Commission," Revision 9 to the Updated Final Safety Analysis Report," dated July 1,1996.

(2) CYAPCO Letter B16066, from T. C. Feigenbaum, to the U. S. Nuclear Regulatory Commission," Certifications Of Permanent Cessation Of Power Operation And That Fuel Has Been Removed From The Reactor," dated December 5,1996. 63 i g mo3 En*28aLi8"8a86 "l -- )

, U. S. Nuctur Regulatory Commission

- CY-98-005/Page 2

, defueled condition. As the plant continues to recategorize . structures, systems, and  !

component's, the UFSAR will be updated in accordance with 10CFR50.71(e)(4). l Pursuant to 10CFR50.71(e) and 10CFR50.4(b)(6), this transmittal consists of one original and ten copies. As stipulated in 10CFR50.71(e)(2)(ii): "This submittal.shall 4

include an identification of changes made under the provisions of Section 50.59, but not previously submitted to the Commission." Pursuant to Section 50.59(b) and Technical Specification Section 6.9.1.4, such information is routinely submitted to the NRC as part of our annual reports, and is not included in this submittal. The most recent annual report was submitted on February 28,1997,W for the period January 1,1996, through i December 31,1996.

If the NRC should have any questions, please contact Mr. G. P. van Noordennen at (860) 267-3938.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY N- /

Russell %_Mellor \

Vice President - Operations and Decommissioning Subscribed and sworn to before me this&iday of January,1998 h& h.w Date Commission Expires: IAbido0'A Attachment cc: H. J. Miller, NRC Region l Administrator T. L. Fredrichs, NRC Project Manager, Haddam Neck Plant W. J. Raymond, NRC Senior Resident inspector, Haddam Neck Plant D. Galloway, Acting Director, CT DEP Monitoring and Radiation Division (3) CYAPCO Letter B16240, from J. J. LaPlatney to the U. S. Nuclear Regulatory Commission, " Annual Reports," dated February 28,1997.

l

ONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN Hollow ROAD e EAST HAMPToN. CT 06424-30J9 January 26,1998 NL/CY-98-011 To: HNP UFSAR Controlled Copyholders From: S. J. SarverM #

Nuclear Licen g Extension 3936 S u F -t: Distribution of Change No. 30 to the Haddam Neck Plant (HNP)

Updated Final Safety Analysis Report (UFSAR)

Attached, please find the subject change, dated January 26,1998, to the Haddam Neck Plant UFSAR. This change is a total rewrite of the HNP UFSAR that replaces the existing copy in its entirety. The old UFSAR, through change 29, should be returned to HNP Licensing.

Nuclear Document Services (NDS) will send you a form acknowledging that you have received this change to your controlled copy of the UFSAR and have turned in the old UFSAR. Please complete the form and return it to NDS.

SJS/jmc ATTACHMENT cc: (w/o attachments)

R. B. Lundin f!

G. P. van Noordennen Nuclear Records NL Memo File 1026-3 REV F-91

HADDAM NECK PLANT UFSAR ES Chne Nor Date Received Date Entered - Initials- Remarks -

Total Rewrito issued 1/98 M

O O

REC-CHG DOC a

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i HADDAM NECK PLANT UFSAR UFSAR Figures to Drawings Matrix Figure Number Title Drawing Number Sheets 1.2-1 Legend 16103- 26000 4-6 10.2-1 Hydrogen Gas System 16103 - 26055 2 10.3-1 Main Steam System 16103- 26012 1-11 10.3-2 Hydrazine Feed and ETA System 16103- 26068 1 10.4-1 Circulating Water and Vacuum 16103- 26017 1 Priming System 10.4-2 Arrangement Screenwell- Sh.1 16103 - 27058 1 10.4-3 Arrangement Screenwell- Sh. 2 16103- 27058 2

. .. . . .. ... ... . . . . . ..g..;.. .g...

.;. . .g. .;.;.. . .. . .. ..... . .. . .. .g. . . . .. . ...g. .g . . .. ... . . . ....... .. .. . .. . .

. . .. 7.g . . . . .. .. . . ..g .... .. . . . . . . .;. . ... .;. ...g. . . .. . . . . .. .. .. .. ... . .... ... .g ..g. .. ...g. . . . . . .. ... . . .. .... ...... .

c

Systems

\-

10.4-6 Feedwater and Condensate 16103- 26016 1 Sample System 11.2-1 Liquid Waste System 16103- 26030 1-5 11.3-1 Gaseous Waste System 16103- 26031 1-3 2.1-1 Location Map N/A N/A 2.1-2 Topographic Map N/A N/A 2.1-3 General Site Plan N/A N/A 2.1 -4 Connecticut Yankee Site Plan 16103 - 10000 1 2.1-5 Restricted Area N/A N/A 2.1-6 Population Sectors Within 50 Miles N/A N/n 2.3-1 MeteorologicalInstrument and Data N/A N/A Quality Assurance Flow Diagram 2.4-1 Dam Failure Flood Hydrograph N/A N/A m\

t,d ..................................................................................................................................

Page 1 of 5 January 1998

s HADDAM NECK PLANT UFSAR  !

' 1 UFSAR Figures to Drawings Matrix Figure Number Title Drawing Number Sheets l 2.5-1 Borings and Seismic Survey Plan 16103- 11004 1

....g........................;.........;.....................................g..g...........g...............................

2.5-3 Boring Record Sheet 2 16103- 11003 2 2.5-4 Boring Record Sheet 3 16103- 11003 3 3.7-1 Average Acceleration Spectrum for N/A N/A Use at Haddam, CT 3.7-2 Horizonta! Seismic Design- N/A N/A Response Spectra 3.7-3 Seismic Design Ground Spectrum N/A N/A Currently in Use 3.7-4 Free-Field Horizontal Acceleration N/A N/A l q Design Response Spectra l

Q ......................................................................................................................................

3.7-5 Site Specific Spectrum N/A N/A 3.7-6 Modified Free-Field Horizontal N/A N/A Acceleration Time History 3.7-7 Comparison of the Response N/A N/A Spectrum of the Modified Free-Field Horizontal Acceleration Time History and the Design Response Spectrum With 5% Critical Damping 3.8-1 Arrangement-Primary Plant 16103 - 27002 1

. 6. 'a'a's'a~ 'isJ' d' "" '"' " " i'15" "'i"6~""""""" "' i " ~"

Penetrations 3.8-2 Arrangement-Primary Plant 16103- 27003 1 3.8-3 Arrangement-Primary Plant 16103- 27004 1 3.8-4 Arrangement. Primary Plant 16103- 27005 1 O

\.J Page 2 of 5 January 1998

C s HADDAM NECK PLANT UFSAR UFSAR Figu es to Drawings Matrix Figure Number Title Drawing Number Sheets 3.8-5 Arrangement-Primary Plant 16103- 27006 1 3.8-6 Arrangement-Primary Plant 16103- 27007 1 3.8-7 Arrangement - Primary Auxiliary 16103- 27042 1 Building 3.8-8 Arrangement - Primary Auxiliary 16103- 27042 2 Building 3.8-9 General Arrangement - New & 16103- 27036 1 Spent Fuel Building 4.2-1 Fuel Rod Assembly N/A 1-2 4.2-2 Bottom Nozzle 16103- 29696 44

/ ,\ 4.2-3 Top Nozzle Assembly 16103- 29696 47

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4.2-4 Thimble Assembly N/A N/A 4.2-5 Skeleton Structure 16103- 29696 27 i 4.5-1 Control Rod Drive Mechanism Coil N/A N/A l Stack

}

4.5-2 HJTC Probe Holder Support Tube N/A N/A 4.5-3 HJTC Probe Pressure Boundary N/A N/A Installation 4.5-4 incore Instrumentation Arrangement N/A N/A 4.5-5 Connecticut Yankee Reactor 16103- 29305 1 General Assembly 5.1-1 Reactor Coolant System 16103- 26007 1-3 5.1-2 Arrangement Primary Plant 16103 - 27002-27007 1-6 5.3-1 Reactor Vessel and Intemals N/A N/A 5.4-1 Reactor Coolant Pump N/A N/A s

v ..................................................................................................................................

Page 3 of 5 January 1998 1

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l

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,A

. HADDAM NECK PLANT UFSAR

\

UFSAR Figures to Drawings Matrix Figure Number Title Drawing Number Sheets 5.4-2 Steam Generator N/A N/A 6.2-1 Containment Air Recirculation N/A N/A System 6.3 1 Residual Heat Removal System 16103 - 26028 1 6.3 2 Safety injection System 16103- 26010 1-2 6.4-1 Control Room Plan Showing Air N/A N/A Conditioners and Ductwork 8.1-1 Main One-Line Diagram 16103 - 30002 1 8.2-1 Equipment Arrangement - 115kV 16103 - 33004 1 Swyd.

8.3-1 4160V One-Line Diagram - Bus 1 A, 16103 - 33003 1 P

1 B, 2, 3

" " " ~ " " " ' " " " " " " " '

..;.g. ............. ........;..g. g. .b'A';'s';'B'is'gri's"' " ~' ' "'6'5' ~5"' '1 1 i Emergency Bus 8 and 9 8.3-3 Arrangement - Switchgear Room i 16103 - 33002/27084 1-2 I

l 8.3-4 Arrangement - New Diese: 16103 - 27075 1 Generator Building 8.3-5 Fuel Oil Supply to Diesel Generator 16103 - 26020 1 and Auxiliary Steam Boiler 8.3-6 Diesel Generator Systems - 16103- 26020 2 Ccmpressed Air 8.3-7 125V DC One-Line Diagram - Bus 16103- 30008 1-2 A, B and C Dist. Swbd. Swgr. Rm.

9.1-1 Spent Fuel Pool Cooling System 16103- 26049 1 9.1-2 Spent Fuel Pool Decay Heat Loads N/A N/A 9.2-1 Service Water System 16103 - 26014 1-9 Page 4 of 5 January 1998

.. ___J

(' HADDAM NECK PLANT UFSAR i

UFSAR Figures to Drawings Matrix Figure Number Title Drawing Number Sheets 9.2-2 Component Cooling System 16103 - 26008 3-7 9.2-3 Closed Cooling Water System 16103- 26027 12 9.2-4 Well Water and Water Treatment 16103- 26003 1-2 System 9.2-5 Domestic Water System 16103- 26067 1-6 9.2-6 Turbine Building Waste Water 16103- 26047 1 Treatment System 9.2-7 Nitrogen System 16103- 26055 1 9.2-8 Primary Water System 16103- 26046 1-3 l 9.3-1 Service Air System 16103 - 26051 1-4

[,

s 9.3-2 Control Air System 16103- 26052 1-9 s

9.3-3 Containment Control Air System 16103- 26054 1 9.3-4 Primary Sampling System 16103 - 26009 1-2 9.3-5 Post Accident Sampling System 16103- 26057 1 9.3-6 Miscellaneous Bottled Gas System 16103- 26055 3 9.3-7 Chemical and Volume Control 16103- 26018 1-6 System 9.3-8 Boron Recovery System 16103- 26004 1-4 9.4-1 Primary Ventilation System 16103 - 26024 1-5 9.4-2 Switchgear Building HVAC 16103- 26063 1-2 9.5-1 Fire Protection System 16103- 26056 1-16 Page 5 of 5 January 1998 1

l l

T (G HADDAM NECK PLANT UFSAR Drawings to UFSAR Figures Matrix Drawing Number Sheets Figure Number Title 16103- 10000 1 2.1-4 Connecticut Yankee Site Plan 16103- 10008 1 10.4-4 CXJ Discharge Canal 16103- 11003 1 2.5-2 Boring Record Sheet 1 16103- 11003 2 2.5-3 Boring Record Sheet 2 16103- 11003 3 2.5-4 Boring Record Sheet 3 16103- 11004 1 2.5-1 Borings and Seismic Surve

..................................................................................................................................yPlan 16103- 22027 2 3.8-10 Reactor Containment Pipinn.

Penetrations 16103- 26000 4-6 1.2-1 Legend 1 16103- 26003 1-2 9.2-4 Well Water and Water Treatment

' ,O S

( .........................................................................................ystem 16103- 26004 1-4 9.3-8 Boron Recovery S l

................................................................................................................ystem 16103- 26007 1-3 5.1-1 Reactor Coolant S

....................................................................................................................ystem 16103- 26008 3-7 9.2-2 Component Coolin 7 ................................................................................................................gSystem 16103- 26009 1-2 9.3-4 Primary Samplin

..........................................................................................................gSystem.................................

16103- 26010 1-2 6.3-2 Safety injection S

............................................................................................................ystem ..............................

16103- 26012 1-11 10.3-1 Main Steam System 16103- 26013 1-13 10.4-5 Feedwater and Condensate S

....................................................................................................................................ystems 16103- 26014 1-9 9.2-1 Service Water S

...............................................................................................................ystem 16103- 26016 1 10.4-6 Feedwater and Condensate Sample S

....................................................................................ystem 16103- 26017 1 10.4-1 Circulating Water and Vacuum Primin

.............................................................................................gSystem O

k Page 1 of 5 January 1998

3 HADDAM NECK PLANT UFSAR

)

Drawings to UFSAR Figures Matrix Drawing Number Sheets Figure Number Title 16103- 26018 1-6 9.3-7 Chemical and Volume Control System 16103- 26020 1 8.3-5 Fuel Oil Supply to Diesel Generator and Auxiliary Steam Boiler 16103- 26020 2 8.3-6 Diesel Generator Systems -

Compressed Air 16103- 26024 1-5 9.4-1 Prim ry Ventilation Gystem 16103- 26027 1-2 9.2-3 Closed Cooling Water System 16103- 26028 1 6.3-1 Residual Haat Removal System 16103- 26030 1-5 11.2-1 Liquid Waste System 16103 - 26031 1-3 11.3-1 Gaseous Waste System h x 16103 - 26046 1-3 9.2-8 Primary Water System 16103- 26047 1 9.2-6 Turbine Building Waste Water Treatment System 16103 - 26049 1 9.1-1 Spent Fuel Pool Cooling System 16103 - 26051 1-4 9.3-1 Service Air System 16103- 26052 1-9 9.3-2 Control Air System 16103- 26054 1 9.3-3 Containment Control Air System 16103- 26055 1 9.2-7 Nitrogen System 16103- 26055 2 10.2-1 Hydrogen Gas System 16103 - 26055 3 9.3-6 Miscellaneous Bottled Gas System 16103 - 26056 1-16 9.5-1 Fire Protection System 16103- 26057 1 9.3-5 Post Accident Sampling System 16103- 26063 1-2 9.4-2 Switchgear Building HVAC g .....................................................................................................................................

(_.) Page 2 of 5 January 1998 s

______s

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m HADDAM NECK PLANT UFSAR Drawings to UFSAR Figures Matrix Drawing Number Sheets Figure Number Title 16103 - 26067 1-6 9.2-5 Domestic Water System 16103- 26068 1 10.3-2 Hydrazine Feed and ETA System 16103- 27002 1 3.8-1 Arrangement. Primary Plant 16103 - 27002-27007 1-6 5.1-2 Arrangement Primary Plant 10103- 27003 1 3.8-2 Arrangement. Primary Plant 16103- 27004 1 3.8-3 Arrangement. Primary Plant 16103- 27005 1 3.8-4 Arrangement-Primary Plant 16103- 27006 1 3.8-5 Arrangement-Primary Plant 16103 - 27007 1 3.8-6 Arrangement-Primary Plant p 16103 - 27036 1 3.8-9 General Arrangement - New &

- V l Spent Fuel Building l 16103- 27042 1 3.8-7 Arrangement - Primary Auxiliary Building 16103- 27042 2 3.8-8 Arrangement - Primary Auxiliary Building 16103 - 27058 1 10.4-2 Arrangement Scremwell - Sh.1 16103- 27058 2 10.4-3 Arrangement Screenwell - Sh. 2 16103- 27075 1 8.3-4 Arrangement - New Diesel Generator Building 16103- 29305 1 4.5-5 Connecticut Yankee Reactor General Assembly 16103- 29696 27 4.2-5 Skeleton Structure 16103- 29696 44 4.2-2 Bottom Nozzle 16103- 29696 47 4.2-3 Top Nozzle Assembly (G

L Page 3 of 5 January 1998

,~'

\

w HADDAM NECK PLANT UFSAR Drawings to UFSAR Figures Matrix Drawing Number Sheets Figure Number Title 16103- 30002 1 8.1-1 Main One-Line Diagram 16103- 30008 12 8.3-7 125V DC One-Line Diagram - Bus A, B and C Dist. Swbd. Swgr. Rm.

16103- 30011 1 8.3-2 4160V One-Line Diagram -

Emergency Bus 8 and 9 16103- 33002/27084 1-2 8.3-3 Arrangement - Switchgear Room 16103- 3300? 1 8.3-1 4160V One-Line Diagram - Bus 1 A, 18,2,3 16103 - 33004 1 8.2-1 Equipment Arrangement - 115kV Swyd.

N/A 12 4.2-1 Fuel Rod Assembly O N/A N/A 2.1-1 Location Map (s ........................

N/A N/A 2.1-2 Topographic Map N/A N/A 2.1-3 Genersi Site Plan N/A N/A 2.1-5 Restricted Area N/A N/A 2.1-6 Population Sectors Within 50 Miles N/A N/A 2.3-1 Meteorological Instrument and Data

... ................................................. .................... ............ Qualit ............y As s ura n ce Flow Dia g ra m N/A N/A 2.4-1 Dam Failure Flood Hydrogra

.................................................................................................................................ph ..............

N/A N/A 3.7-1 Average Acceleration Spectrum for Use at Haddam, CT N/A N/A 3.7-2 Horizontal Seismic Design-Response Spectra N/A N/A 3.7-3 Seismic Design Ground Spectrum

.. ........................................................................................yinUse Currentl k Page 4 of 5 January 1998

_ _ _ _ _ _ _ _ _ _ _ o

p

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HADDAM NECK PLANT UFSAR Drawings to UFSAR Figu es Matrix Drawing Number Sheets Figure Number Title N/A N/A 3.7-4 Free-Field Horizontal Acceleration Design Response S

...................................................................................................................pecra t N/A N/A 3.7-5 Site Specific Spectrum N/A N/A 3.7-6 Modified Free-Field Horizontal Acceleration Time Histor

..............................................................................................................................y N/A N/A 3.7-7 Comparison of the Response Spectrum of the Modified Free-Field Horizontal Acceleration Time History and the Design Response Spectrum With 5% Critical Dam ping N/A N/A 4.2-4 Thimble Assembly N/A N/A 4.5-1 Control Rod Drive Mechar, ism Coil Stack l(x .......................................................................................................................................

N/A N/A 4.5-2 HJTC Probe Holder Support Tube N/A N/A 4.5-3 HJTC Probe Pressure Boundary Installation I N/A N/A 4.5-4 Incore Instrumentation Arrangement N/A N/A 5.3-1 Reactor Vessel and Intemals N/A N/A 5.4-1 Ructor Coolant Pump N/A N/A 5.4-2 Steam Generator N/A N/A 6.2-1 Containment Air Recirculation System N/A N/A 6.4-1 Control Room Plan Showing Air Conditioners and Ductwork N/A N/A 9.1-2 Spent Fuel Pool Decay Heat Loads c

O t

Page 5 of 5 January 1998 ,

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HADDAM NECK PLANT UFSAR

SUMMARY

TABLE OF CONTENTS' Section Tjilm VOLUME 1 i 4

1.0 INTRODUCTION

AND GENtiRAL DESCRIPTION OF PLANT

1.1 INTRODUCTION

1.2 GENERAL PLANT DESCRIPTION 1.3 COMPARISON TABLES ,

1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.6 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.6 MATERIAL INCORPORATED BY REFERENCE 1.7 DRAWINGS AND OTHER DETAILED INFORMATION 1.8 - CONFORMANCE TO NRC REGULATORY GUIDES

~ 2.0 SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.2 NEARBY INDUSTRIAL, TRAN3PORTATION, AND MILITARY FACILITIES 2.3 METEOROLOGY 2.4 HYDROLOGIC ENGINEERING 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING 3.0 ' DESIGN OF STRUCTURES, CGMPONENTS, EQUIPMENT AND SYSTEMS l

3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS 3.3 WIND AND TORNADO LOADINGS 3.4 ' WATER LEVEL DESIGN 3.5 MISSILE PROTECTION 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PlPING '

b 3.7 SEISMIC DESIGN

' 3.8 DESIGN OF CLASS I AND CLASS ll STRUCTURES 3.9 MECHANICAL SYSTEM AND COMPONENTS 3.10- SEISMIC QUALIFICATION OF SEISMIC CATEGORY I INSTRUMENTATION AND ELECTRIC EQUIPMENT 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIP-MENT 4.0 REACTOR 4.1

SUMMARY

DESCRIPTION 4.2 FUEL' SYSTEM DESIGN

?4.3 NUCLEAR DESIGN 4.4 THERMAL AND HYDRAULIC DESIGN O 4.5 -

4.6 REACTOR MATERIALS FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS i January 1998 TOCVOL1.CY Updated 01/20/96 5.48 PM

HADDAM NECK PLANT UFSAR

SUMMARY

TABLE OF CONTENTS O Section Ijt!g 5.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.1

SUMMARY

DESCRIPTION 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.3 REACTOR VESSEL 5.4 - COMPONENT AND SUBSYSTEM DESIGN VOLUME 2 6.0 ENGINEERED SAFETY FEATURES 6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.2 CONTAINMENT SYSTEM 6.3 EMERGENCY CORE COOLING SYSTEM 6.4 HABITABILITY SYSTEMS 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.6 IN-SERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 4

7.0 INSTRUMENTATION AND CONTROLS

'/ 7,1 INTRODUCTION

'\ 7.2 REACTOR TRIP SYSTEM 7.3 ENGINEERED SAFETY FEATURE SYSTEMS 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.5 SAFETY-RELATEC DISPLAY INSTRUMENTATION 7.6 ALL OTH5ft INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 8.0 ELECTRIC POWER

8.1 INTRODUCTION

! 8.2. OFF-SITE POWER SYSTEM a3 ON SITE POWER 9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.2 WATER SYSTEMS 9.3 PROCESS AUXILIARIES 9.4 AIR CONDITIONING, HEATING, COOLING AND VENTILATION Sif.,TEMS 9.5 OTHER AUXILIARY SYSTEMS O

li January 1998 TOCVOL1.CY Updated 01/20/98 S.48 PM

HADDAM NECK PLANT UFSAR iq

SUMMARY

TABLE OF CONTENTS Section Title VOLUME 3 10.0 STEAM AND POWER CONVERSION SYSTEM 10.1

SUMMARY

DESCRIPTION 10.2 TURBINE-GENERATOR SYSTEM 10.3 MAIN STEAM SYSTEM 10.4 OTHER FEATURES OF THE STEAM AND POWER CONVERSION SYSTEM 11.0 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS 11.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.3 GASEOUS WASTE MANAGEMENT SYSTEM 11.4 SOLID WASTE MANAGEMENT SYSTEM 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING 12.0 RADIATION PROTECTION 7s 12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW

(}

' AS IS REASONABLY ACHIEVABLE (ALARA) 12.2 RADIATION SOURCES 12.3 RADIATION PROTECTICd DESIGN FEATURES 12.4 DOSE ASSESSMENT 12.5 HEALTH PHYSICS PROGRAM 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE 13.2 TRAINING PROGRAMS 13.3 EMERGENCY PLANNING 13A REVIEW AND AUDIT 13.5 PLANT PROCEDURES 13.6 PHYSICAL SECURITY PLANS <

14.0 INITIAL TEST PROGRAM 15.0 ACCIDENT ANALYSES 15.1

SUMMARY

15.2 NON LOCA TPANSIENT ANALYSES i5.3 LOSS OF COOLANT ACCIDENT TRANSIENT ANALYSES 15.4 ANTICIPATED TRANSIENTS WITHOUT SCRAM 15.5 RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT

'v ill January 1998 TOCVOL1.CY Updated 01/20/98 5 48 PM

HADDAM NECK PLANT UFSAR l

SUMMARY

TABLE OF CONTENTS 10.0 TECHNICAL SPECIFICATIONS 17.0 QUALITY ASSURANCE 17.1 CONNECTICUT YANKEE QUALITY ASSURANCE PROGRAM l l

l I

O iv Januay 1998 TOCVOL1.CY Updated 01/20/98 5 48 PM

O Connecticut Yankee DECOMMISSIONING UPDATED FINAL SAFETY ANALYSIS REPORT O