ML13004A043

Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 1.0 - Introduction and General Description of Plant

ML13004A043
Person / Time
Site:	Byron, Braidwood
Issue date:	12/14/2012
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
References
RS-12-221
Download: ML13004A043 (63)

Text

B/B-UFSAR 1.0-i REVISION 5 - DECEMBER 1994 CHAPTER 1.0 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS

PAGE

1.0 INTRODUCTION

AND GENERAL DESCRIPTION OF PLANT 1.1-1

1.1 INTRODUCTION

1.1-1

1.2 GENERAL

PLANT DESCRIPTION 1.2-1 1.2.1 Site and Environment 1.2-1

1.2.2 Nuclear

Steam Supply System 1.2-1

1.2.3 Engineered

Safety Features 1.2-2

1.2.4 Emergency

Core Cooling System 1.2-3

1.2.5 Control

and Instrumentation 1.2-3

1.2.6 Electrical

System 1.2-4

1.2.7 Turbine

and Auxiliaries 1.2-4 1.2.8 Fuel Handling System 1.2-5

1.2.9 Radioactive

Waste Management System 1.2-5 1.2.10 Features of Special Interest 1.2-5 1.2.11 Structures 1.2-6

1.3 COMPARISON

TABLES 1.3-1

1.3.1 Comparisons

with Similar Facility Designs 1.3-1

1.3.2 Comparison

of Final and Preliminary Information 1.3-2 1.3.3 References 1.3-2

1.4 IDENTIFICATION

OF AGENTS AND CONTRACTORS 1.4-1

1.4.1 Licensee

1.4-1 1.4.2 Architect-Engineer 1.4-1

1.4.3 Reactor

Designer 1.4-1

1.4.4 Constructor

1.4-2

1.4.5 Consultants

and Service Organization 1.4-2 1.4.5.1 Security Systems - ETA 1.4-2 1.4.5.2 Dames & Moore 1.4-3 1.4.5.3 HARZA Engineering 1.4-3 1.4.5.4 Murray and Trettel, Inc. 1.4-3 1.4.5.5 Shirmer Engineering Corporation 1.4-3 1.4.5.6 Hyla S. Napadensky 1.4-4 1.4.5.7 NALCO Chemical Company 1.4-4 1.4.5.8 Westinghouse Environmental Systems Department (WESD) 1.4-4 1.4.5.9 Illinois Natural History Survey (INHS) 1.4-5 1.4.5.10 NUS Corporation 1.4-5 1.4.5.11 Eberline Instrument Corporation (EIC) 1.4-5

B/B-UFSAR 1.0-ii REVISION 9 - DECEMBER 2002 TABLE OF CONTENTS (Cont'd)

PAGE 1.4.5.12 Meteorology Research, Inc. (MRI) 1.4-5 1.4.5.13 Illinois State Museum (ISM) 1.4-6 1.4.5.14 Equitable Environmental Health, Inc. (EEH) 1.4-6 1.4.5.15 Espey, Huston & Associates, Inc. (EH & A) 1.4-6 1.4.5.16 University of Wisconsin-Milwaukee (UWM) 1.4-7 1.4.5.17 Aero-Metric Engineering, Inc. (AME) 1.4-7 1.4.5.18 Iowa Institute of Hydraulic Research 1.4-7 1.4.5.19 Babcock and Wilcox International (B&W) 1.4-8 1.4.5.20 Framatome Technologies, Incorporated (FTI) 1.4-8 1.4.5.21 Stone & Webster Engineers and Constructors, Inc, (S&W) 1.4-8

1.5 REQUIREMENTS

FOR FURTHER TECHNICAL INFORMATION 1.5-1

1.5.1 Programs

Required For Plant Operation 1.5-1 1.5.1.1 Core Stability Evaluation 1.5-1

1.5.2 Other

Programs Not Required For Plant Operation 1.5-1 1.5.2.1 Fuel Development Program For Operation at High Power Densities 1.5-2 1.5.2.2 Blowdown Forces Program 1.5-2 1.5.2.3 Blowdown Heat Transfer Testing 1.5-2

1.5.3 References

1.5-4

1.6 MATERIAL

INCORPORATED BY REFERENCES 1.6-1

1.7 DRAWINGS

1.7-1 1.7.1 Electrical, Instrumentation, and Control Drawings 1.7-1

1.7.2 Drawings

for Independent Structural Review 1.7-1

B/B-UFSAR 1.0-iii REVISION 9 - DECEMBER 2002 CHAPTER 1.0 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT LIST OF TABLES

NUMBER TITLE PAGE 1.3-1 Plants Using Three-Buttress Containment Design 1.3-3 1.4-1 Exelon Generation Company's Nuclear Power Plants in Service or Under Construction 1.4-9 1.4-2 Nuclear Power Plants Completed or Currently Under Design by Sargent & Lundy 1.4-10 1.4-3 Westinghouse Pressurized Water Reactor Nuclear Power Plants 1.4-11 1.5-1 Blowdown Heat Transfer Phase I Test Parameters 1.5-5 1.5-2 Blowdown Heat Transfer Phase II Test Parameters 1.5-6 1.6-1 Topical Reports Incorporated by Reference 1.6-2 1.7-1 Deleted 1.7-2

B/B-UFSAR 1.0-iv REVISION 9 - DECEMBER 2002 CHAPTER 1.0 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT DRAWINGS CITED IN THIS CHAPTER*

• The listed drawings are included as "General References" only; i.e., refer to the drawings to obtain additional detail or to obtain background information. These drawings are not part of the UFSAR. They are controlled by the Controlled Documents Program.

DRAWINGS* SUBJECT M-1 General Site Plan Units 1 & 2 M-2 Property Development Units 1 & 2 M-5 General Arrangement Roof Plan Units 1 & 2 M-6 General Arrangement Main Floor At El. 451'-0" Units 1

& 2 M-7 General Arrangement Mezzanine Floor At El. 426'-0" Units 1 & 2 M-8 General Arrangement Grade Floor At El. 401'-0" Units 1 & 2 M-9 General Arrangement Floor Plan At El. 383'-0" Units 1

& 2 M-10 General Arrangement Basement Floor At El. 364'-0" Units 1 & 2 M-11 General Arrangement Floor Plan At El. 346'-0" Units 1

& 2 M-12 General Arrangement Radwaste/Service Building Units 1

& 2 M-13 General Arrangement Fuel Handling Building Units 1 &

2 M-14 General Arrangement Section "A-A" Units 1 & 2 M-15 General Arrangement Section "B-B" Units 1 & 2 M-16 General Arrangement Section "C-C" and "D-D" Units 1 &

2 M-17 General Arrangement Section "E-E" Units 1 & 2 M-18 General Arrangement Section "F-F" Units 1 & 2 M-19 General Arrangement Lake Screen House Units 1 & 2 (Braidwood)

M-20 General Arrangement River Screen House Units 1 & 2 M-22 General Arrangement Miscellaneous Plans Units 1 & 2 M-34 P&ID Index and Symbols Units 1 & 2

B/B-UFSAR 1.1-1 REVISION 10 - DECEMBER 2004 CHAPTER 1.0 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

1.1 INTRODUCTION

The Nuclear Regulatory Commission approved the transfer of the

facility licenses from Commonwealth Edison (ComEd) Company to

Exelon Generation Company, LLC (EGC) on August 3, 2000 (Reference

1). References in the Updated Final Safety Analysis Report (UFSAR) to ComEd, CECo, and Commonwealth Edison have been

retained, as appropriate, instead of being changed to EGC to

properly preserve the historical context.

This UFSAR is submitted by Exelon Generation Company for nuclear

power plants at Byron, Illinois and at Braidwood, Illinois (Drawings M-1 and M-2) in accordance with the requirements of 10

CFR 50.71(e). Each power plant consists of two units having

nearly identical nuclear steam supply systems (NSSS) and turbine

generators. The main exception is that the original Unit 1 steam

generators were replaced by steam generators of a different

design. The power plants at the two sites are as nearly

identical as site characteristics permit. The bulk of this UFSAR

applies to the standardized, non-site-related aspects of the

power plants. Sections which describe features specific to the

sites are repeated for each site and the applicable station name appears at the top of these pages. Every effort has been made in the preparation of this document to conform to the Nuclear

Regulatory Commission (NRC) Regulatory Guide 1.70, "Standard

Format and Content of Safety Analysis Reports for Nuclear Power

Plants", Revision 2, September 1975. The guidance provided in Nuclear Energy Institute (NEI) 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, June 1999, as endorsed by NRC Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10CFR50.71(e)," Revision 0, September 1999, is used to comply with the provisions of 10CFR50.71(e).

Each nuclear power plant consists of two nearly identical

generating units, and two pressurized water reactor (PWR) (NSSS)

and turbine-generator furnished by Westinghouse Electric

Corporation (Westinghouse) similar in design concept to several

projects recently licensed or currently under review by the NRC (see Section 1.3). Unit 1 contains steam generators supplied by

B&W and Unit 2 contains steam generators supplied by

Westinghouse. Westinghouse Electric Corporation, Sargent &

Lundy, and the Commonwealth Edison Company jointly participated

in the original design and construction of each unit. The plant

is operated by Exelon Generation Company. Sargent & Lundy (S&L)

is the architect-engineer for both stations.

Each nuclear steam supply system is designed for a power output

of 3600.6 MWt which is the license application rating. The

equivalent warranted gross and approximate net electrical outputs

of each unit are 1242 MWe and 1210 MWe, respectively. The

nuclear steam supply system is evaluated for safety analyses at

3658 MWt.

B/B-UFSAR 1.1-1a REVISION 9 - DECEMBER 2002 Specifically, the containment and engineered safety features (ESF) are designed and evaluated for operation at the power

rating of 3658 MWt. Accidents (such as loss-of-coolant, steamline break, and other postulated accidents having offsite

dose consequences) are also analyzed at a power rating of 3658 MWt.

B/B-UFSAR 1.1-2 REVISION 9 - DECEMBER 2002 The reactor containments are of post-tensioned concrete construction with a carbon steel liner. Sufficient free volume

is provided to contain the energy released in a major accident

without need for "pressure suppression" devices. Sargent & Lundy

is responsible for containment design.

Byron Station is located in north central Illinois, near the town

of Byron and near the Rock River (Drawing M-1). Cooling for the plant is provided by two natural draft cooling towers for non-

essential service cooling, and by mechanical draft cooling towers

for essential cooling. The fuel loading dates for the two units

were November 1984 and November 1986 for Units 1 and 2, respectively. The corresponding dates for commercia1 operation

were September 1985 and August 1987.

The Braidwood Station is located in northeastern Illinois, near

the town of Braidwood and near the Kankakee River (Drawing M-1).

Cooling for the plant is provided by a large man-made cooling pond

of approximately 2500 acres constructed over a previously

strip-mined area. Essential service cooling is provided by a

99-acre auxiliary cooling pond which is integral with the main

pond. The fuel loading dates for the two units were October 1986

and December 1987 for Units 1 and 2, respectively. The

corresponding dates for commercial operation were July 1988 and

October 1988.

The standard symbols used on piping and instrument diagrams and

other figures in this UFSAR are shown in Drawing M-34.

1.2 REFERENCES

1. NRC letter, "Braidwood, Byron, Dresden, LaSalle, Quad Cities, and Zion - Orders Approving Transfer of Licenses

From Commonwealth Edison Company To Exelon Generation

Company, LLC, and Approving Conforming Amendments," dated

August 3, 2000

B/B-UFSAR 1.3-1 REVISION 8 - DECEMBER 2000 1.3 COMPARISON TABLES

1.3.1 Comparisons

with Similar Facility Designs

The design is conceptual ly similar to Exelon Generation Company's Zion Station. D ifferences in the design of the two plants have been allowed only (1) when dic tated by the site characteristics, (2) when the change would result in significant safety improvement, simplif ication of constru ction or operation procedures, or cost savi ngs; or (3) as required to comply with appropriate codes and st andards, NRC criteria, regulatory guides, and regulations.

The nuclear steam supply system is similar to that of the Zion Station but has a slight ly higher power rati ng. The reactor containments are of the same materials and s ize as those at the Zion Station, but each has only three buttresses, rather than six as used at Zion.

The number of post-t ensioning tendons is reduced, and the number of wires per tendon incr eased, from that used at Zion. The r educed number of buttresses allows for greater separation of penetration ar eas for redundant safety-related systems.

Several plants on which this buttress design has been used are listed in Table 1.3-1.

The polar cranes in the reactor containment are mounted on the containment wall, rather than on the missile barrier as at Zion.

This allows use of a g reater area for co mponent laydown in the containment.

Two 100%-capacity cont ainment spray systems are used, rather than the three systems used at Zion.

Four containment fan coolers are used, rather than the five u sed at Zion.

The emergency diesel-generator systems for each unit are entir ely independent and use two 5500-kW diesel generators per unit.

The arrangement of equipment in the co mmon auxiliary bui lding allows greater physical separation of r edundant systems and their piping and

cables than was possible at Zion.

The Byron Station uses natural draft cooling towers for heat rejection. Zion utilizes once-t hrough cooling.

Mechanical draft cooling towers are provided for essential service cooling at Byron.

The Braidwood Statio n uses a large man-made cooling pond for heat rejection. An auxiliary cooling pond, integral with the main pond, is provided for es sential service cooling.

Table 1.3-2 of the FSAR provided the des ign comparison of the Byron/Braidwood nuclear steam supply system wi th Comanche Peak, Indian Point 2, South Texas, Sun Deser t, W. B. McGuire Nuclear Station, Trojan Nuclear Power Plant, SNUPPS, and the Watts Bar Application. This inf ormation was current at the time the Byron Unit 1 operating license was granted and has not been included in the UFSAR.

B/B-UFSAR 1.3-2 REVISION 8 - DECEMBER 2000 1.3.2 Comparison of Final and Preliminary Information The Byron/Braidwood Power Plant design was s ubject to continuing review throughout the construction of the stations. The experience gained at Zion Stat ion and other PWRs was used to enhance equipment reli ability and perfor mance. Current design technology was used to upgrade earlier p lant design methods.

No significant design ch anges have been made to the Byron Station or the Braidwood Stati on which have not been previously reported by amendment to the PS AR, except for the inclusion of 17 x 17

optimized fuel. Table 1.3-3 of the FSAR lis ted those significant changes reported since t he issuance of the B yron and Braidwood Stations Construction Pe rmits. This informati on was current at the time the Byron U nit 1 operating lice nse was granted and has not been included in the UFSAR.

Other changes included t he removal of the part length control rods (they are not n eeded to control X enon induced axial instabilities), the enla rgement of spent fue l capacity, the use of more corrosion-resist ant materials in the s team generators and moisture steam separator s, improved equipment packaging to do a reactor refueling in a shorter time peri od, an upgraded design for the reactor coolant pump seals, and replacement steam generators for Unit 1. These concepts are described in later chapters.

1.3.3 References

1. Exelon Generatio n Company, "Byron/Br aidwood Stations Fire Protection Report in Response to Appendix A of BTP APCSB 9.5-1," (current amendment).

B/B-UFSAR 1.3-3 TABLE 1.3-1 PLANTS USING T HREE-BUTTRESS CO NTAINMENT DESIGN

PLANT/UTILITY DATE OF OPERATION Arkansas Nuclear One

Arkansas Power & Light Co.

5-21-74 Millstone-2

Northeast Utilities 8-1-75 Rancho Seco Sacramento Municipal Utility District 8-16-74 Trojan Portland General Electric Co.

11-21-75 J.M. Farley-1

Alabama Power Co.

6-25-77 B/B-UFSAR 1.4-1 REVISION 8 - DECEMBER 2000 1.4 IDENTIFICATION OF AG ENTS AND CONTRACTORS

1.4.1 Licensee

Exelon Generation Company is the Licensee for the Byron Station, Units 1 and 2, which is located in Roc kvale Township, Ogle County, approximately 4 miles south of Byron , Illinois, and for Units 1 and 2 of the B raidwood Station, whic h is located in Reed Township, Will County, approximately 6 m iles southwest of Wilmington, Illinois.

The Licensee is r esponsible for the design, construction, and operation of the n uclear power plants.

Commonwealth Edison su pplies electrical serv ice to an area of 13,000 square miles with a population of app roximately 8 million persons, located primarily in the northern thi rd of Illinois.

Dresden 1, Commonwea lth Edison's first n uclear generating station, went into comme rcial service during A ugust 1960, and has produced more than 10 billion kWh.

Additional nucle ar units in service or under con struction are listed in Table 1.4-1.

1.4.2 Architect-Enqineer

For the work covered by this application, Sa rgent & Lundy (S&L) has been retained as the design consultants. The Licensee has employed Sargent & Lundy for pow er plant design work for over 80 years. Sargent & Lundy is an independent cons ulting engineering organization founded in Chicago, in 1891.

For over three-quarters of a century, the firm has spec ialized exclusively in the design of generation, tr ansmission, dist ribution, and utilization of steam a nd electric power and related facilities.

The firm has provided the comple te engineering s ervices for more than 600 turbine-generator u nits with a total capacity of 53,000,000 kW. Of t his total, some 9,80 0,000 kW is in nuclear generating capacity.

Table 1.4-2 lists the nuclear plants completed by or curr ently under design by Sargent & Lundy.

1.4.3 Reactor

Designer

Westinghouse has designed, dev eloped, and manu factured nuclear power facilities since t he 1950s, beginning with the world's first large central stat ion nuclear power pl ant (Shippingport), which started producing power in 1957. Comple ted or contracted

B/B-UFSAR 1.4-2 REVISION 5 - DECEMBER 1994 commercial nuclear cap acity totals were in excess of 98,000 MWe. Westinghouse p ioneered new nuclear design concepts, such as chemical shim control of reac tivity and the rod cluster control concept, through out the last two decad es. Westinghouse manufacturing facilities include the largest com mercial nuclear fuel fabrication facility in the world and t he world's most modern heat transfer e quipment production facility, as well as other facilities producing nucle ar steam supply system (NSSS) components. Table 1

.4-3 lists all Wes tinghouse pressurized water reactor (PWR) pl ants to date, incl uding those plants under construction or on ord er at the time of the Byron/Braidwood application.

The U.S. Nuclear Regulatory Commissi on (NRC) and the Electric Power Research I nstitute have contracted with Westinghouse for research into NSSS-related activ ities. Westinghouse experience was also utilized by the NRC and Metropolitan Edison immediately following the Three Mile Island Unit 2 accident and the corporation continues to participate wit h the Westinghouse Owner's Group of utilities in ad dressing the NRC action plan and other operations improvements.

1.4.4 Constructor

Construction coordination of all activities at the site was under the supervision of the C ommonwealth Edison's Station Construction Department. Th e department exercises site managerial functions as discussed in Chapter 1 7.0 of the UFSAR.

The Station Construction Departm ent was the constructor for Zion Station. This departm ent has coordinated the construction activities for almost all of Commonwealth Ed ison's existing power plants. It was also the construction coordi nator for La Salle County Station.

1.4.5 Consultants

and Service Organization 1.4.5.1 Security System - ETA

The design of the physical secur ity system and the administrative controls was perform ed by ETA, Inc.

ETA personnel have had varied and in-depth experience in the design, safety analysis, and environmental r eview of nuclear power plants and related facilit ies as well as in the management and organization of security sys tems. They are very familiar with the details of the current generation of light water reactors and, in particular, those critical areas and components of the plants wh ich might be the most vulnerable to sabotage.

They are also famili ar with the current regulations and guidelines of the NRC that define the required performance and objectives of a security system for licensed activities.

B/B-UFSAR 1.4-3 1.4.5.2 Dames & Moore The independent consulti ng firm of Dames &

Moore was employed to conduct studies relating to the geo logy, seismology, and groundwater hydrology at both sites. The firm also conducted preconstruction baseline studies, including wi ldlife surveys as well as soil and vegetation analyses.

Having performed envir onmental studies for approximately 30 nuclear power plant si tes, Dames & Moore is a recognized authority in the field of en vironmental engine ering of nuclear power plants.

1.4.5.3 HARZA Engineering

HARZA was employed in the design of the water treatment facilities at both stations.

HARZA has been involved with a variety of technical studies for at least ten nuclear power sta tions. Among these studies have been facility design, review of design and structure, hydrology, and groundwater. In addition, HARZA Eng ineering has designed some of the largest hy droelectric projects in the world, including major concrete struc tures and earthfilled dams.

1.4.5.4 Murray and Trettel, Inc.

Murray and Trettel (M&T) is an environmental consulting firm which, since 1960, has provided signif icant meteorological input to both preoperational and operational phases of meteorological progr ams for nuclear power stat ions. M&T has also provided meteorological input to a wide variety of air pollution and environmental prob lems as well as allied control technique programs.

Murray & Trettel provided meteor ological data for both stations by implementation of an onsite measurement p rogram incorporating a tower for elev ation measurements.

1.4.5.5 Shirmer Engi neering Corporation

Shirmer Engineering is a firm of consulting fire protection engineers. The firm has done work on 17 Department of Energy nuclear fuel production and laboratory facilit ies, as well as for numerous nuclear power stations for Sargent & Lundy.

Shirmer Engineering has also performed servi ces for many fossil units. Shirmer Engineering prov ided evaluation of the fire protection systems at both stations and assisted in the preparation of the Byron/Braidwood Fire Protection Report.

B/B-UFSAR 1.4-4 1.4.5.6 Hyla S. Napadensky Ms. Napadensky was ret ained to help evaluate the probability of an accidental explosion occurring on a train carrying explosives in the vicinity of t he Braidwood Station.

Ms. Napadensky is the Manager of Fire Safety Research at the IIT Research Institute of the Illinois Insti tute of Technology.

Ms. Napadensky has dir ected analytical and e xperimental research in the areas of explosion effects, haz ards and r isk analysis, safety of chemical systems, explosives and propellant sensitivity, and initiat ion mechanisms during her 17 years with IIT Research Institute.

1.4.5.7 NALCO Ch emical Company

The NALCO Chemical Com pany (formerly Industr ial Bio-Test, Inc.)

consisted of two divisions, Indu strial Bio-Test Labo ratories, and NALCO Environmental Scie nces, which conduct st udies relating to toxicology and ecolo gical sciences, re spectively. The Environmental Science Di vision includes seven subdivisions: (1) aquatic biology, (2) fis heries and field opera tions, (3) water and wastewater chemistry, (4) radiochemistry, (5) air sciences and data processing, (6) land and plant sciences, and (7) environmental physiology.

As a technical consult ant on the Braidwo od project, the NALCO Chemical Company provided a clam bed mapping sur vey in the area of the station's intake and discharge struct ures located on the Kankakee River.

1.4.5.8 Westinghouse E nvironmental Syste ms Department (WESD)

WESD, established as a department of t he Westinghouse Power Systems Company in 1969, consisted of environmental scientists and engineers experienced in the areas of aqua tic and terrestrial biology and ecology; g eology; limnology; env ironmental chemistry and physics; physical oceanography, meteorol ogy and climatology, radiology, public health aspec ts of pollutant emissions, and systems engineering and integration.

WESD conducts broad en vironmental surveys, environmental program planning and data interpretation, and provides recom mended action programs for meeting federal, state, and local environmental quality regulations. As a technical consult ant on the Braidwood project, WESD staff biol ogists conducted a 2-y ear baseline study of the Braidwood Stati on site. Distribution s of phytoplankton, zooplankton, periphyton, benthos, fi sh, fish eggs and larvae, and water chemistry in the Kankakee Rive r in the vicinity of the site were determined, and quantitative data on terr estrial flora and fauna were collected.

The impacts of plant construction and operation in the biotic communit ies of the site were predicted.

B/B-UFSAR 1.4-5 1.4.5.9 Illinois Natural History Survey (INHS)

The Illinois Natural History Survey (INH S), which has its beginnings almost 12 0 years ago, is a di vision of the State Department of Registra tion and Education and provides services to farmers, homeowners, sportsmen, and all other citizens of Illinois as well as to industries.

INHS cooperates in biological research with the Illinois Department of Agriculture, Conservation, and Public Health; the University of Illinois, Southern Illinois University, and other educational institutions; various research branches of t he federal government; and other agricultural, conservati on, municipal, and bus iness organizations throughout t he state.

INHS aquatic biologists were involved in a 4-year study of the Kankakee River and Hor se Creek near Custer P ark, Illinois. The purpose of the s tudy is to obtain bi ological, physical, and chemical data which will be used to evaluate any effects of the construction and operation of the Braidwood Station and its associated cooling lake on the biota and water quality of the Kankakee River and Hor se Creek. The sta tion's cooling pond will

use the Kankakee River as a source of water for both intake and discharge purposes.

1.4.5.10 NUS Corporation

NUS Corporation is a consulting engineer ing, research, and testing firm specializ ing in environment al and energ y systems engineering, systems analysis, design engine ering, management consulting, and training pro grams related to these areas. NUS has provided advice and professional g uidance to utility, industrial, and governme nt clients throughou t the United States and in a number of f oreign countries.

As a technical consult ant on the Braidwo od project, NUS was involved in a study to determine the adequacy of the station's ultimate heat sink.

1.4.5.11 Eberline Instrum ent Corporation (EIC)

Eberline Instrument Corp oration (EIC) has pr ovided radiation measurement equipment, comprehensive rad iation protection services, and analytical labor atory services to the nuclear industry since 1953.

As a technical consult ant on the Byron/Braidwood projects EIC performed preoperational envir onmental radiolo gical baseline studies on and a round the site.

1.4.5.12 Meteorology Re search, Inc. (MRI)

Meteorology Research, In

c. (MRI) is an environ mental consulting firm which, since 19 51, has provided m eteorological and air

B/B-UFSAR 1.4-6 REVISION 1 - DECEMBER 1989 quality instruments and services to all aspects of industry in the solution of weathe r-related problems.

These range from environmental impact a ssessments of existing or proposed airports and other major deve lopments to proble ms of warehousing and marketing seasonal con sumer goods. Of particu lar interest is the influence the local to pography has on temper atures and winds.

MRI provided meteorolo gical data from 1973 t hrough mid-1975 for Byron and Braidwood St ations by implementati on of an onsite meteorological measu rement program.

1.4.5.13 Illinois Sta te Museum (ISM)

The Illinois State Mus eum conducts archaeolo gical investigations throughout the s tate of Illinois. As a member of the Illinois Archaeological Survey, t hey have the experti se and services to perform contract archaeo logical work. Their studies included a pedestrian reconnaissance surv ey, subsurface testing and excavating, and laborato ry analyses of datifac ts, pollen, and soils.

As a technical consult ant on the Braid wood project, ISM identified and made re commendations which Commonwealth Edison acted upon to aid in preserv ing the archaeolog ical sites on Braidwood Station and pi peline corridor property.

1.4.5.14 Equitable Environmen tal Health, Inc. (EEH)

Equitable Environmen tal Health, Inc. (EEH), successor to Environmental Analysts, Inc./Tabershaw-Cooper Associated, Inc., is a multidisciplinary firm that offers the consulting services of medical professionals, sc ientists, engineer s, economists, and technical support pe rsonnel in all areas of environmental health and e conomics.

EEH staff biologists conducted a 2-year base line study of the Byron Station site. Dis tributions of phytopla nkton, zooplankton, periphyton, benthos, f ish, fish eggs and larvae, and water chemistry in the Rock River in t he vicinity of t he site were determined and q uantitative data on terrestr ial flora and fauna were collected. The impacts of plant constr uction and operation on the biotic communities of the site were predicted, and data were provided for a benefit-cost analysis of the project.

1.4.5.15 Espey, Huston & Asso ciates, Inc. (EH & A)

Espey, Huston & Associat es, Inc. (EH & A) is a consulting firm addressing the e nvironmental problems as sociated with industrial and urban development.

EH & A professionals c over a broad range of expertise includi ng civil engineeri ng, environmental engineering, mathematics and com puter science, and all phases of aquatic, estuarine, and terrestrial ecology.

B/B-UFSAR 1.4-7 REVISION 1 - DECEMBER 1989 As a technical consultant on the Byron project, EH & A conducted the construction p hase terrestrial and aquatic monitoring programs.

1.4.5.16 University of Wi sconsin-Milwaukee (UWM)

The University of Wi sconsin-Milwaukee un der Dr. Elizabeth Benchley of the Dept. of Anthrop ology, conducts archaeological investigations throughout Wisconsin and nort hern Illinois. As a member of the Illinois Archaeo logical Survey, they have the expertise and services to perform contract archaeological work. Their studies included a pedestri an reconnaissance survey, subsurface t esting, and lab anal ysis of datifacts, pollen, and soils.

As a technical consult ant on the Byron p roject, UWM identified and made recommendations which C ommonwealth Edison acted upon to aid in preserving the arc haeological sites on Byron Station and pipeline corrido r property. Also, UWM conducted archaeological investiga tions on the Byron transmission line right-of-ways.

1.4.5.17 Aero-Metric En gineering, Inc. (AME)

Aero-Metric Engineering, Inc., f ounded in 1969, is based in Sheboygan, Wisconsin.

The staff was made up of over 50 technical photogrammetric person nel, many having professional engineer and/or survey registration. AM E's capabilities allow for a complete range of precision phot ogrammetric services, including aerial photography, mapping, and m ultiple survey skills.

As a technical consult ant on the Byron project, AME will be providing annual aerial infra-red photographs.

1.4.5.18 Iowa Institute of Hydraulic Research The Iowa Institute of Hy draulic Research, form ally organized in 1931, is a Division of the University of Iowa's College of Engineering. The Institute staff exceeded 80 in number and was comprised of a profess ional staff with Ph.Ds in the areas of Civil Engineering, Mec hanical Engineering, P hysics, Mechanics and Hydraulics, and Aero nautical Engineering, with most of these personnel holding joint academic a ppointments in the College of Engineering

's Division of Ene rgy Engineering. The Institute of Hydraul ic Research conducts programs of fundamental research and advanced design and analysis in the areas of environmental pollution, bioeng ineering, naval hydrodynamics, river mechanics, ice hydraulics, hydrology, water resources, hydraulic struc tures, fluid m echanics, advanced instrumentation and dat a-handling techniques for fluids research, and m athematical modeling of watersheds and hydrology.

B/B-UFSAR 1.4-8 REVISION 9 - DECEMBER 2002 As a technical consult ant on the Braid wood project, the Institute conducted a thermal evaluation to determine the adequacy of the ulti mate heat sink.

1.4.5.19 Babcock and Wilc ox International (B&W)

B&W is located in Cambri dge, Ontario, Canada.

B&W has fabricated fossil-fueled boiler c omponents for over 100 years and has fabricated nuclear system compon ents since the l ate 1950's. B&W has supplied replaceme nt steam generators fo r Byron Unit 1 and Braidwood Unit 1.

1.4.5.20 Framatome Technologi es, Incorporated (FTI)

FTI is located in Lync hburg, Virginia and has been providing services to the electric power i ndustry for over four decades.

FTI engineering services include the necessary expertise, experience, and NRC-appr oved computer codes and methodologies to support the transient analysis of the Un it steam generators.

1.4.5.21 Stone & Webster Engineers and Construc tors, Inc. (S&W)

S&W is located in Bost on, Massachusetts and has been providing services to the electric power industry for over 100 years. S&W has provided balance-o f-plant design-engineeri ng support services in support of the po wer uprate of the Byron and Braidwood units.

B/B-UFSAR

1.4-9 REVISION 8

- DECEMBER 2000 TABLE 1.4-1 EXELON GENERATION COMPAN Y'S NUCLEAR POWER PLANTS IN SERVICE OR UNDER CONSTRUCTION UNIT NOMINAL GROSS 1 RATING (MWe)

SCHEDULED COMMERCIAL SERVICE DATE Dresden 1 210 1960 Dresden 2 850 1972 Dresden 3 850 1972 Quad-Cities 1 850 1972 Quad-Cities 2 850 1972 Zion 1 1085 1973 Zion 2 1085 1973 La Salle 1 1122 1978 La Salle 2 1122 1979 Byron 1 1175 1985 Byron 2 1175 1987 Braidwood 1 1175 1988 Braidwood 2 1175 1988 1 Note that this is a gross rating, not a net rating.

B/B-UFSAR 1.4-10 REVISION 1 - DECEMBER 1989 TABLE 1.4-2 NUCLEAR POWER PLANTS COMPLETED OR CURRENTLY UNDER DESIGN BY SARGENT & LUNDY UNIT NOMINAL GROSS 2 RATING (MWe)

YEAR OF POWER OPERATION EBWR 5 1956 Elk River 22 1962 La Crosse 60 1967 SEFOR 20 (MWt) 1969 Dresden 2 850 1969 Dresden 3 850 1971 Quad-Cities 1 850 1971 Quad-Cities 2 850 1972 Zion 1 1085 1973 Zion 2 1085 1973 Fort St. Vrain, Unit 1 330 1973 Enrico Fermi, Unit 2 1200 1988 La Salle County Station, Unit 1 1122 1979 La Salle County Station, Unit 2 1122 1980 Byron Station, Unit 1 1175 1985 Byron Station, Unit 2 1175 1987 Braidwood Statio n, Unit 1 1175 1988 Braidwood Statio n, Unit 2 1175 1988 Clinton Power Station, Unit 1 992 1981 Kaiseraugst 992 1982 2 Note that this is a gross rating, not a net rating.

B/B-UFSAR 1.4-11 TABLE 1.4-3 WESTINGHOUSE PRESSURIZED WATER REACTOR NUCLEAR POWER PLANTS PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Shippingport Duquesne Light Company; Energy Research & Development Administration Pennsylvania 1957 90 4 Yankee-Rowe Yankee Atomic Electric Company Massachusetts 1961 175 4 Trio Vercellese (Enrico Fermi)

Ente Nazionale per L'Energia Elettrica (ENEL) Italy 1965 260 4 Chooz (Ardennes)

Societe d'Energie Nucleaire Franco-Belge des Ardennes (SENA) France 1967 305 4 San Onofre Unit 1 Southern California Edison Co.; San Diego Gas and Electric Co. California 1968 450 3 Haddam Neck (Connecticut Yankee)

Connecticut Yankee Atomic Power Company Connecticut 1968 575 4 Jose Cabrera-Zorita Union Electrica, S.A. Spain 1969 153 1 Beznau Unit 1 Nordostschweizerische Krafwerke AG (NOK) Switzerland 1969 350 2 Robert Emmett Ginna Rochester Gas and Electric Corporation New York 1970 490 2 Mihama Unit 1 The Kansai Electric Power Company, Inc. Japan 1970 320 2 Point Beach Unit 1 Wisconsin Electric Power Co.; Wisconsin Michigan Power Co. Wisconsin 1970 497 2 H. B. Robinson Unit 2 Carolina Power and Light Co. South Carolina 1971 707 3 B/B-UFSAR 1.4-12 REVISION 8 - DECEMBER 2000 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Beznau Unit 2 Nordostschweizerische Kraftwerke AG (NOK) Switzerland 1972 350 2 Point Beach Unit 2 Wisconsin Electric Power Co.; Wisconsin Michigan Power Co. Wisconsin 1972 497 2 Surry Unit 1 Virginia Electric and Power Co. Virginia 1972 822 3 Turkey Point Unit 3 Florida Power and Light Co. Florida 1972 745 3 Indian Point Unit 2 Consolidated Edison Company of New York, Inc. New York 1973 873 4 Prairie Island Unit 1 Northern States Power Company Minnesota 1973 530 2 Turkey Point Unit 4 Florida Power and Light Co. Florida 1973 745 3 Surry Unit 2 Virginia Electric and Power Co. Virginia 1973 822 3 Zion Unit 1 Exelon Generation Company Illinois 1973 1050 4 Kewaunee Wisconsin Public Service Corp.; Wisconsin Power and Light Co.;

Madison Gas and Electric Co. Wisconsin 1974 560 2 Prairie Island Unit 2 Northern States Power Company Minnesota 1974 530 2 Takahama Unit 1 The Kansai Electric Power Company, Inc. Japan 1974 781 3 Zion Unit 2 Exelon Generation Company Illinois 1974 1050 4

B/B-UFSAR 1.4-13 REVISION 8 - DECEMBER 2000 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Doel Unit 1 Indivision Doel Belgium 1975 390 2 Doel Unit 2 Indivision Doel Belgium 1975 390 2 Donald C. Cook Unit 1 Indiana and Michigan Electric Company (AEP) Michigan 1975 1060 4 Ringhals Unit 2 Statens Vattenfallsverk (SSPB) Sweden 1975 822 3 Almaraz Unit 1 Unit Electrica, S.A.; Compania Sevillana de Electricidad, S.A.;

Hidroelectrica Espanola, S.A. Spain 1976 902 3 Beaver Valley Unit 1 Duquesne Light Company; Ohio Edison Company; Pennsylvania Power Company Pennsylvania 1976 852 3 Diablo Canyon Unit 1 Pacific Gas and Electric Co. California 1976 1084 4 Indian Point Unit 3 Consolidated Edison Company of New York, Inc. New York 1976 965 4 Lemoniz Unit 1 Iberduero, S.A. Spain 1976 902 3 Salem Unit 1 Public Service Electric and Gas Company; Exelon Generation Company; Atlantic City Electric Co.;

Delmarva Power and Light Co. New Jersey 1976 1090 4 B/B-UFSAR 1.4-14 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Trojan Portland General Electric Co.; Eugene Water and Electric Board; Pacific Power and Light Company Oregon 1976 1130 4 Almaraz Unit 2 Union Electrica, S.A.; Compania Sevillana de Electricidad, S.A.;

Hidroelectrica Espanola, S.A. Spain 1977 902 3 Asco Unit 1 Fuerzas Electricas de Cataluna, S.A. (FESCA) Spain 1977 902 3 Diablo Canyon Unit 2 Pacific Gas and Electric Co. California 1977 1106 4 Joseph M. Farley Unit 1 Alabama Power Company Alabama 1977 829 3 Ko-Ri Unit 1 Korea Electric Power Co., Ltd. Korea 1977 564 2 North Anna Unit 1 Virginia Electric and Power Co. Virginia 1977 898 3 North Anna Unit 2 Virginia Electric and Power Co. Virginia 1977 898 3 Ohi Unit 1 The Kansai Electric Power Co., Inc. Japan 1977 1122 4 Ohi Unit 2 The Kansai Electric Power Co., Inc. Japan 1977 1122 4 Ringhals Unit 3 Statens Vattenfallsvert (SSPB) Sweden 1977 900 3 Sequoyah Unit 1 Tennessee Valley Authority Tennessee 1977 1148 4 Angra dos Reis Unit 1 Furnas-Centrais Electricas, S.A. Brazil 1978 626 2

B/B-UFSAR 1.4-15 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Asco Unit 2 Fuerzas Electricas de Cataluna, S.A. (FESCA);

Empresa Nacional Hidroelectrica del Ribagorzana, S.A. (ENHER); Fuerzas Hidroelectricas del Segre, S.A.;

Hidroelectrica de Cataluna, S.A. Spain 1978 902 3 Donald C. Cook Unit 2 Indiana and Michigan Electric Company (AEP) Michigan 1978 1060 4 Lemoniz Unit 2 Iberduero, S.A. Spain 1978 902 3 Sequoyah Unit 2 Tennessee Valley Authority Tennessee 1978 1148 4 Watts Bar Unit 1 Tennessee Valley Authority Tennessee 1978 1177 4 William B. McGuire Unit 1 Duke Power Company North Carolina 1978 1180 4 Joseph M. Farley Unit 2 Alabama Power Company Alabama 1979 829 3 Krsko Savske Elektrarne, Ljubljana, Slovenia, Elektroprivreda, Zagreb, Croatia Yugoslavia 1979 615 2 Ringhals Unit 4 Statens Vattenfallsvert (SSPD) Sweden 1979 900 3

B/B-UFSAR 1.4-16 REVISION 8 - DECEMBER 2000 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Salem Unit 2 Public Service Electric and Gas Company; Exelon Generation Company Atlantic City Electric Co.; Delmarva Power and Light Co. New Jersey 1979 1115 4 Virgil C. Summer South Carolina Electric and Gas Company South Carolina 1979 900 3 Watts Bar Unit 2 Tennessee Valley Authority Tennessee 1979 1177 4 William B. McGuire Unit 2 Duke Power Company North Carolina 1979 1180 4 Byron Unit 1 Exelon Generation Company Illinois 1981 1120 4 Comanche Peak Unit 1 Texas Utilities Generating Co. Texas 1980 1150 4 Seabrook Unit 1 Public Service Company of New Hampshire; United Illuminating Company New Hampshire 1980 1200 4 South Texas Project Unit 1 Houston Lighting and Power Co.;

Central Power and Light Co.;

City Public Service of San Antonio; City of Austin, Texas Texas 1980 1250 4 B/B-UFSAR 1.4-17 REVISION 8 - DECEMBER 2000 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Beaver Valley Unit 2 Duquesne Light Company; Ohio Edison Company; Pennsylvania Power Co.;

Cleveland Electric Illuminating Company; Toledo Edison Company Pennsylvania 1981 852 3 Braidwood Unit 1 Exelon Generation Company Illinois 1981 1120 4 Callaway Unit 1 SNUPPS - Union Electric Co. Missouri 1981 1150 4 Catawba Unit 1 Duke Power Company South Carolina 1981 1153 4 Jamesport Unit 1 Long Island Lighting Company New York 1981 1150 4 Ko-Ri Unit 2 Korea Electric Power Co., Ltd. Korea 1981 605 2 NORCO Puerto Rico Water Resources Authority Puerto Rico - 583 2 Braidwood Unit 2 Exelon Generation Company Illinois 1982 1120 4 Byron Unit 2 Exelon Generation Company Illinois 1982 1120 4 Catawba Unit 2 Duke Power Company South Carolina 1982 1153 4 Comanche Peak Unit 2 Texas Utilities Generating Co. Texas 1982 1150 4 Marble Hill Unit 1 Public Service Company of Indiana, Inc.;

Northern Indiana Public Service Company Indiana 1982 1150 4 B/B-UFSAR 1.4-18 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Millstone Unit 3 Northeast Nuclear Energy Co. Connecticut 1982 1156 4 Seabrook Unit 3 Public Service Company of New Hampshire; United Illuminating Company New Hampshire 1982 1200 4 South Texas Project Unit 2 Houston Lighting and Power Co.; Central Power and Light Co.; City Public Service of San Antonio; City of Austin, Texas Texas 1982 1250 4 Taiwan Unit 5 Taiwan Power Company Taiwan 1982 950 3 Wolf Creek Unit 1 SNUPPS - Kansas Gas and Electric Company; Kansas City Power and Light Company Kansas 1982 1150 4 Alvin W. Vogtle Unit 1 Georgia Power Company Georgia 1983 1113 4 Callaway Unit 2 SNUPPS - Union Electric Company Missouri 1983 1150 4 NEP-1 New England Power Company - 1983 1150 4 Fort Calhoun Unit 2 Omaha Public Power District; Nebraska Public Power District Nebraska 1983 1150 4 Jamesport Unit 2 Long Island Lighting Company New York 1983 1150 4 Sears Island Central Maine Power Company Maine - 1200 4 B/B-UFSAR 1.4-19 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Taiwan Unit 6 Taiwan Power Company Taiwan 1983 950 3 Alvin W. Vogtle Unit 2 Georgia Power Company Georgia 1984 1113 4 Marble Hill Unit 2 Public Service Company of Indiana, Inc.;

Northern Indiana Public Service Company Indiana 1984 1150 4 Shearon Harris Unit 1 Carolina Power and Light Co. North Carolina 1984 900 3 Sterling SNUPPS - Rochester Gas and Electric Corporation; Central Hudson Gas and Electric Corporation; Niagara Mohawk Power Corporation; Orange and Rockland Utilities, Inc. New York 1984 1150 4 Atlantic Unit 1 (O.P.S.) Public Service Electric and Gas Company; Atlantic City Electric Co.;

Jersey Central Power and Light Company New Jersey 1985 1150 4 NEP-2 New England Power Company - 1985 1150 4 South Dade Unit 1 Florida Power and Light Co. Florida 1985 1150 4 Sundesert Unit 1 San Diego Gas and Electric Co. California 1985 950 3

B/B-UFSAR 1.4-20 TABLE 1.4-3 (Cont'd)

PLANT OWNER UTILITY LOCATION SCHEDULED COMMERCIAL OPERATION MWe NET NUMBER OF LOOPS Tyrone Unit 1 SNUPPS - Northern States Power Company Wisconsin 1985 1150 4 Shearon Harris Unit 2 Carolina Power and Light Co. North Carolina 1986 900 3 South Dade Unit 2 Florida Power and Light Co. Florida 1986 1150 4 Atlantic No. (O.P.S.) Public Service Electric and Gas Company; Atlantic City Electric Co.;

Jersey Central Power and Light Company New Jersey 1987 1150 4 Shearon Harris Unit 4 Carolina Power and Light Co. North Carolina 1988 900 3 Sundesert Unit 2 San Diego Gas and Electric Co. California 1988 950 3 Sayago Unit 1 Iberduero, S.A. Spain 1980's 1000 3 Sayago Unit 4 Iberduero, S.A. Spain 1980's 1000 3 Shearon Harris Unit 3 Carolina Power and Light Co. North Carolina 1990 900 3 Unassigned Unit 1 (O.P.S.) Public Service Electric and Gas Company; Atlantic City Electric Company New Jersey 1990 1150 4 Unassigned Unit 2 (O.P.S.) Public Service Electric and Gas Company; Atlantic City Electric Company New Jersey 1992 1150 4

B/B-UFSAR 1.5-1 1.5 REQUIREMENTS FOR FURTH ER TECHNICAL INFORMATION The design of the Byron/Braidwood units is bas ed upon proven concepts which have been develop ed and success fully applied to the design of pressurized water reactor system

s. There are currently no areas of resear ch and developme nt which are required for operati on of this plant.

At the time of issuance of construction permits for the Byron/

Braidwood units, the Prelimina ry Safety Analys is Report (PSAR) and the standard design report which it referenced, RESAR-3, identified certain res earch and development pr ograms which were incomplete. These p rograms, which have been successfully completed, have provid ed technical informati on which has been used either to demonst rate the safety of design, more sharply define margins of conser vatism, or lead to design improvements.

Reference 1 presents descriptions of those safety-related research and development programs which have been carried out for, by, or in conjunc tion with Westinghouse Nuclear Energy Systems, and which are applicable to Wes tinghouse pressurized water reactors. The discussion which follows documents the completion of the construction permit stage rese arch programs.

1.5.1 Programs

Required for Plant Operation Two programs were iden tified as required for plant design and operation in the PSAR:

a. core stability evaluation and

b. fuel rod burst program.

Both programs are co mplete. The fuel rod burst program was completed at the time of the PSA R. The core sta bility evaluation program was not. A disc ussion of the core s tability evaluation program follows.

1.5.1.1 Core Sta bility Evaluation

The program to establish means for the detection and control of potential xenon oscill ations and for the shaping of the axial power distribution for improved core per formance has been satisfactorily completed.

See item 1, Referen ce 2, for a further discussion of the tests and results.

1.5.2 Other

Programs N ot Required for Plant Operation

The following programs w ere not complete at the time of the PSAR but are now satisfac torily complete.

B/B-UFSAR 1.5-2 1.5.2.1 Fuel Development Program for Operation at High Power Densities The program to demonst rate the satisfact ory operation of fuel at high burnup and p ower densities has been satisfactorily completed. See item 8, Reference 2, for a further discussion of the program a nd its results.

1.5.2.2 Blowdown Forces Program Westinghouse has completed B LODWN-2, an improved digital computer program for the calcula tion of local fluid pressures, flows and density transients in the primary coolant systems during a LOCA.

BLODWN-2 is used to evaluate the effects of blowdown forces in this application. Refer to it em 15 in Reference 4 for a further discussion of the tests and results.

1.5.2.3 Blowdown Heat Transfer Testing (Form erly Titled Delayed Departure From N ucleate Boiling)

The NRC Acceptance Cri teria for Emergency Core Cooling Systems for Light-Water Powe r Reactors was issued in Section 50.46 of 10 CFR 50 on December 28, 19

73. It defines the basis and conservative assumptio ns to be used in the evaluation of the performance of emergency core cooling systems (ECCS).

Westinghouse believes that some of the conservatism of the criteria is associated w ith the manner in wh ich transient DNB phenomena are treated in the e valuation models.

Transient critical heat flux data presented at the 1972 specialists meeting of the Committee on Reactor Safe ty Technology (C REST) indicated that the time to DNB can be dela yed under transi ent conditions.

To demonstrate the c onservatism of the E CCS evaluation models, Westinghouse initiated a program to experiment ally simulate the blowdown phase of a LOCA. This testing is part of the Electric Power Research Institute (EPRI) sponsored Blow down Heat Transfer Program, which was start ed early in 1976. T esting was completed in 1979. A DNB corr elation developed by Wes tinghouse from these test results is used in the ECCS analyses for Byron/Braidwood.

Objective The objective of the blo wdown heat transfer te st was to determine the time that DNB occurs under LOCA conditions. Thi s information was used to confirm a new Westinghou se transient DNB correlation.

The steady-state DNB data obtain ed from 15x15 and 17x17 test programs was used to assure th at the geometrical differences between the two fuel a rrays is correctly treat ed in the transient correlations.

B/B-UFSAR 1.5-3 Program The program was divided into two phases.

The Phase I tests started from steady-st ate conditions, with sufficient power to maintain nucleate boiling throughout the bundle, and progressed

through controlled ram ps of decreasing test se ction pressure or flow initiated DNB.

By applying a series of controlled conditions, investigation of the DNB was studied over a range of qualities and flows, and at pres sures relevant to a PWR blowdown.

Phase I provided separate-effects data for h eat transfer correlation development.

Typical parameters used for Phase I test ing are shown in Table 1.5-1.

Phase II simulated P WR behavior during a LOCA to permit definition of the time d elay associated with onset of DNB. Tests in this phase covered the large double-ended guillotine cold leg break. All tests in Phase II were also started after establishment of typical steady-stat e operating cond itions. The fluid transient was th en initiated, and the rod power decay was programmed in such a m anner as to simulate t he actual heat input of fuel rods. The test was terminated when the heater rod temperatures reached a predetermined limit.

Typical parameters u sed for Phase II testing are shown in Table 1.5-2.

Test Description

The experimental program was con ducted in the J-Loop at the Westinghouse Forest Hills Facili ty with a full length 5x5 rod bundle simulating a se ction of a 15x15 fuel as sembly to determine DNB occurrence under LOCA conditions.

The heater rod bundl es used in this prog ram were internally-heated rods, cap able of a maximum line ar power of 18.8 kW/ft, with a total power of 135 kW (for exte nded periods) over the 12-foot heated length of the rod. Heat was generated internally by means of a varying cross-sectional resistor which approximates a chopped cosine power distribut ion. Each rod was adequately instrumented with a total of 12 clad thermocouples.

Results The experiments in t he DNB facility re sulted in cladding temperature and fluid pr operties measured as a function of time throughout the blowd own range from 0 to 20 seconds.

Facility modifications and installation of the initial test bundle were completed.

A series of shak edown tests in the

B/B-UFSAR 1.5-4 REVISION 1 - DECEMBER 1989 J-Loop were performed. These tests provided data for instrumentation calibr ation and check-ou t, and provided information regarding fa cility control a nd performance. Initial program tests were performed during the first half of 1975.

Under the sponsorship of EPRI, t esting was rei nitiated during 1976 on the same test bu ndle. The testing was terminated in November 1976 and plans were m ade for a new test bundle and further testing during 1 978-1979. These tes ts were completed in December of 1979.

1.5.3 References

1. F. T. Eggleston, "Safety-Rel ated Research and Development for Westinghouse Pressurized W ater Reactors, Program

Summaries," WCAP-876 8, October 1978.

2. F. T. Eggleston, "Safety-Relat ed Research and Development for Westinghouse PWRs Program Summaries," WCAP-8768.

Spring 1976 Edition.

3. "Safety-Related Rese arch and Development for Westinghouse PWRs Program Summaries," WCA P-8458. Fall 1977 Edition.

4. "Safety-Related Rese arch and Development for Westinghouse PWRs Program Summaries," WCA P-8004. Fall 1972 Edition.

B/B-UFSAR 1.5-5 TABLE 1.5-1 BLOWDOWN HEAT TRANSFER P HASE I TEST PARAMETERS

PARAMETERS NOMINAL VALUE INITIAL STEADY-S TATE CONDITIONS Pressure 1250 to 2250 psia

Test section mass velocity 1.12 to 2.5x10 6 lb/hr-ft 2 Core inlet temperature 550° F to 600° F Maximum heat flux 306,000 to 531,000 Btu/hr-ft 2

TRANSIENT RAMP CONDITIONS

Pressure decrease 0 to 350 psia/sec and subcooled depressurization

from 2250 psia

Flow decrease 0 to 100%/sec

Inlet enthalpy constant

B/B-UFSAR 1.5-6 TABLE 1.5-2 BLOWDOWN HEAT TRANSF ER PHASE II TEST PARAMETERS

PARAMETERS NOMINAL VALUE INITIAL STEADY-S TATE CONDITIONS Pressure 2250 psia

Test section mass velocity 2.5x10 6 lb/hr-ft 2 Inlet coolant temperature 545° F Maximum heat flux 531,000 Btu/hr-ft 2

TRANSIENT CONDITIONS Simulated break

Double-ended cold leg

guillotine breaks

B/B-UFSAR 1.6-1 1.6 MATERIAL INCORPO RATED BY REFERENCES Table 1.6-1 lists topical repo rts which prov ide information additional to that p rovided in this UFSAR and which have been filed separately with the Nuclear Regulatory Com mission (NRC) in support of this and si milar applications.

A legend to the revi ew status code l etters follows:

A - NRC review complete; NRC acceptance letter issued.

AE - NRC accepted as part of the Westinghouse Emergency Core Cooli ng System (ECCS) evaluation model only; does not constitute acceptance for any purpo se other than for ECCS analyses. B - Submitted to t he NRC as background information; not undergo ing formal NRC review. O - On file with NRC; ol der generation report with current validity; not actively under formal

NRC review. U - Actively under f ormal NRC review.

B/B-UFSAR 1.6-2 TABLE 1.6-1 TOPICAL REPORTS INCORP ORATED BY REFERENCE REPORT REFERENCE SECTION(S)

REVIEW STATUS "The Doppler Effect for a Non-Uniform Temperature Distributi on in Reactor Fuel Elements," WCAP-2048, July 1962 4.3 0 "Single Phase Local Boil ing and Bulk Boiling Pressure Drop Correlations," WCAP-2850 (Proprietary), A pril 1966 and WCAP-7916 (Non-Proprietary

), June 1972 4.4 0 "In-Pile Measurement of UO 2 Thermal Conductivity," W CAP-2923, 1966 4.4 0 "Hydraulic Tests of the San Onofre Reactor Model," WCAP-3269-8, June 1964 4.4 0 "LEOPARD - A Spectrum Dependent Non-Spatial Depletion Code for the IBM - 7094," WCAP-3269-26, September 1963 4.3, 4.4 15.0, 15.4 0

"Saxton Core II Fuel Performance Evaluation," WCAP-3385-56, Part II, "Evaluation of Mass Spectrometric and Radi ochemical Analyses of Irradiated Saxton Plut onium Fuel," July 1970 4.3, 4.4 0 "Xenon-Induced Spatial Instabilities in Large PWRs," WCAP-3680

-20, (EURAEC-1974)

March 1968 4.3 0 "Control Procedures for Xenon-Induced X-Y Instabilities in Large PWR's," WCAP-3680-21, (EURAEC-21

11) February 1969 4.3 0 "Xenon-Induced Spatial Instabilities in Three-Dimensions," WCAP-3680-22, (EURAEC-2116)

September 1969 4.3 0 "Pressurized Water Rea ctor pH - Reactivity Effect Final Rep ort," WCAP-3698-8, (EURAEC-2074) October 1968 4.3 0 "PUO 2 - UO 2 Fueled Critical Experiments," WCAP-3726-I, July 1967 4.3 0 B/B-UFSAR 1.6-3 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Melting Point of Irradiated UO 2 ," WCAP-6065, February 1965 4.2, 4.4 0 "Burnup Physics of H eterogeneous Reactor Lattices," WCAP-6069, June 1965 4.4 0 "LASER - A Depletion Program for Lattice

Calculations Based on MUFT and THERMOS," WCAP-6073, April 1966 4.3 0 "Supplementary Repor t on Evaluation of Mass Spectrometric and Radiochemical Analyses of Yankee C ore I Spent Fuel, Including Isotopes of Elements Thori um Through Curium," WCAP-60 86, August 1969 4.3 0 "Subchannel Thermal Anal ysis of Rod Bundle Cores," WCAP-7015, Rev ision 1, January 1969 4.4 0 "The PANDA Code," WC AP-7048 (Proprietary) and WCAP-7757 (Non-Propr ietary), January 1975 4.3 A "Evaluation of Protective Coatings for Use in Reactor Containment," WCAP-7198-L (Proprietary), April 1969 and WCAP-7825 (Non-Proprietary), December 1971 4.3 0 "Power Distribution Co ntrol of Westinghouse Pressurized Water Re actors," WCAP-7208 (Proprietary), September 1968 and WCAP-7811, (Non-Proprietary), December 1971 4.3 - "The TURTLE 24.0 Diffusi on Depletion Code," WCAP-7213 (Proprieta ry) and WCAP-7758 (Non-Proprietary), January 1975 4.3, 15.0 15.4 A "Core Power Capability in Westinghou se PWRs," WCAP-7267-L (Proprietary

), October 1969 and WCAP-7809 (Non-Proprie tary), December 1971 4.3 - "Reactor Protection Syst em Diversity in Westinghouse Pressuriz ed Water Reactors," WCAP-7306, April 1969 15.4 - "Evaluation of Nuclear H ot Channel Factor Uncertainties," WCAP-7 308, December 1971 4.3 A B/B-UFSAR 1.6-4 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Application of the THINC Program to PWR Design," WCAP-7359-L (Proprietary), August 1969 and WCAP-7838 (Non-Proprietary), January 1972 4.4 O "Seismic Testing of Elec trical and Control Equipment," WCAP-7397-L (Proprietary) and WCAP-7817 (Non-Proprie tary), December 1971 3.10 O "Seismic Testing of Elec trical and Control Equipment (WCID Process Control Equipment)," WCAP-7397-L, Supplement 1 (Proprietary) and WCAP-7817, Supplement 1 (Non-Proprietary), December 1971 3.10 O "Sensitized Stainless Steel in Westinghouse

PWR Nuclear Steam Supply Systems," WCAP-7477-L (Proprietary), M arch 1970 and WCAP-7735 (Non-Proprietary), August 1971 5.2 A "Radiological Consequences of a Fuel Handling Accident," WCAP-7518-L (Proprietary) and WCAP-7828 (Non-Proprietar y), June 1970 15.7 O "Seismic Vibration Testi ng with Sine Beats," WCAP-7558, October 1972 3.10 O "An Evaluation of the Rod Ejection Accident in Westinghouse Pressu rized Water Reactors Using Spatial Kinetics Methods," WCAP-7588, Revision 1-A, January 1975 15.4 A "Dynamic Fracture Toug hness Properties of Heavy Section A533 Grade B Class 1 Steel

Plate," WCAP-7623, December 1970 5.4 O "Interchannel Thermal Mi xing with Mixing Vane Grids," WCAP-76 67-L (Proprietary) and WCAP-7755 (Non-Proprieta ry), January 1975 4.4 A "DNB Tests Results f or New Mixing Vane Grids (R)," WCAP-7695-L (Proprietary) and WCAP-7958 (Non-Proprie tary) and Addendum, January 1975 4.4 A B/B-UFSAR 1.6-5 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "An Evaluation of Solid State Logic Reactor Protection in Antici pated Transients," WCAP-7706, February 1973 4.6, 7.1 O "Electric Hydrogen Recombiner for PWR Containments," WCAP-77 09-L, Supplements 1 through 7 (Proprieta ry) and WCAP-7820, Supplements 1 through 7 (Non-Proprietary), 1971 through 1977 3.11, 6.2 A "A Comprehensive Space-Time Dependent Analysis of Loss of Coola nt (SATAN-IV D igital Code)," WCAP-7750, August 1971 3.6 O "Overpressure Protection for Westinghouse Pressurized Water Reac tors," WCAP-7769, October 1971 15.2 O "Overpressure Protection for Westinghouse Pressurized Water Reac tors," WCAP-7769, Revision 1, June 1972 5.2 O "Behavior of Austenitic Stainless Steel in Post Hypothetical Loss of Coolant Accident Environment," WCAP-7798-L (Proprietary) and WCAP-7803 (Non-Proprieta ry), January 1972 6.1 O "Nuclear Fuel Division Quality Assurance Program Plan," WCAP-78 00, Revision 4-A, April 1975 4.2, 17 A "Nuclear Design of Wes tinghouse Pressurized Water Reactors with Burn able Poison Rods," WCAP-7806, December 1971 4.3 B "Power Distribution Co ntrol of Westinghouse Pressurized Water Reac tors," WCAP-7811, December 1971 4.3 O "Seismic Testing of Elec trical and Control Equipment (Low Seismic Plants)," WCAP-7817, Supplements 1-8, December 1971-March 1974 3.10 O B/B-UFSAR 1.6-6 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Evaluation of Steam Generator Tube, Tubesheet and Divider Plate Under Combined LOCA Plus SSE Condit ions," WCAP-7832, December 1973 5.4 A "Inlet Orificing of Op en PWR Cores," WCAP-7836, January 1972 4.4 B "Neutron Shielding Pads," WCAP-7870, May 1972 3.9 A "LOFTRAN Code Descri ption," WCAP-7907, June 1972 5.2, 15.0 15.1, 15.2, 15.3, 15.4, 15.5, 15.6 A "FACTRAN - A FORTRAN-IV Code for Thermal Transients in a UO 2 Fuel Rod," WCAP-7908, June 1972 15.0, 15.2 15.3, 15.4 A "MARVEL, A Digital C omputer Code for Transient Analysis of a Multiloop PWR System," WCAP-7909, June 1972 6.3 O "Power Peaking Facto rs," WCAP-7912-L (Proprietary) and WCAP-7912 (Non-Proprietary), January 19 75 and Supplement 4.3, 4.4 A "Damping Values of N uclear Power Plant Components," WCA P-7921, May 1974 lA, 3.7 A "Basis for Heatup and Cooldown Limit Curves," WCAP-7924, April 1975 5.3 A "Effect of Axial Spa cing on Interchannel Thermal Mixing with the R Mixing Vane Grid," WCAP-7941-L (Proprietary) and WCAP-7959 (Non-Proprietary), January 1975 4.4 A "Fuel Assembly Safety An alysis for Combined Seismic and Loss of Cool ant Accident, 15x15," WCAP-7950, July 1972 3.7 A "THINC-IV An Improved Program for Thermal and Hydraulic Analysis of Rod Bundle Cores," WCAP-7956, June 1973 4.4 A B/B-UFSAR 1.6-7 REVISION 9 - DECEMBER 2002 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Axial Xenon Tra nsient Tests at the Rochester Gas and Electric Reactor

," WCAP-7964, June 1971 4.3 O "TWINKLE - A Multi-D imensional Neutron Kinetics Computer Code," WCAP-7979 (Proprietary) and WCAP-8028 (Non-

Proprietary), January 1975 15.0, 15.4 A "WIT-6 Reactor Transient Analysis Computer Program Description," WCAP-7980, November 1972 15.0, 15.4 A "Application of Modifi ed Spacer Factor to "L" Grid Typical and C old Wall Cell DNB," WCAP-7988 (Proprieta ry) and WCAP-8030 (Non-Proprietary), October 1972 4.4 A "Application of the THIN C-IV Program to PWR

Design," WCAP-8054 (Prop rietary) and WCAP-8195 (Non-Proprietary), October 1973 4.4 A "Pipe Breaks for the LOCA Analysis of the Westinghouse Primary Coolant Loop,"

WCAP-8082 (Proprieta ry) and WCAP-8172 (Non-Proprietary), January 1975 3.6 A "Reactor Coolant Pump In tegrity in LOCA," WCAP-8163, September 1973 lA, 5.4 O "Calculational M odel for Core Reflooding After a Loss of Coolant Accident (WREFLOOD Code)," WCAP-8170 (P roprietary) and WCAP-8171 (Non-Proprie tary), June 1974 15.6 A "Effect of Local Heat Fl ux Spikes on DNB in Non-Uniform Heated Rod Bundles," WCAP-8174 (Proprietary) and WCAP-8202, (Non-Proprietary), August 1973 4.4 A "WFLASH, A FORTRAN-I V Computer Program for Simulation of Transi ents in a Multi-Loop PWR," WCAP-8200, Revision 2 (Proprietary) and WCAP-8261, Revision 1 (Non-Proprietary), July 1974 15.6 A B/B-UFSAR 1.6-8 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Fuel Densification Ex perimental Results and Model for Re actor Application," WCAP-8218 (Proprietary) and WCAP-8219 (Non-Proprietary), March 1975 4.1, 4.2, 4.3, 4.4 A "Safety Analysis of the 17x17 Fuel Assembly for Combined Seismic and Loss of Coolant Accident," WCAP-8236 (Proprietary), December 1973 and WCAP-8288 (No n-Proprietary), January 1974 and Addenda 3.7, 4.2 A "Safety Analysis of the 8-Grid 17x17 Fuel Assembly for Combined Seismic and Loss of Coolant Accident," W CAP-8236, Addendum 1 (Proprietary), M arch 1974 and WCAP-8288, Addendum 1 (Non-Prop rietary), April 1974 3.7 A "Documentation of Sele cted Westinghouse Structural Analysis Computer Codes," WCAP-8252, Revis ion 1, July 1977 3.6, 3.9 O "Hydraulic Flow Test of the 17x17 Fuel Assembly," WCAP-8278 (Proprietary) and

WCAP-8279 (Non-Proprie tary), February 1974 4.2, 4.4 O "Effect of 17x17 Fuel Assembly Geometry on DNB," WCAP-8296 (Westi nghouse Proprietary) and WCAP-8927 (Non-Pro prietary), February 1975 4.4 A "The Effect of 1 7x17 Fuel Assembly Geometry on Interchannel Thermal Mixing," WCAP-8298 (Proprietary) and WCAP

-8299 (Non-Proprietary), January 1975 4.4 A "LOCTA-IV Program: Lo ss of Coolant Transient Analysis," WCAP-8301 (Proprietary) and

WCAP-8305 (Non-Proprie tary), June 1974 15.0, 15.6 AE SATAN-IV Program: C omprehensive Space-Time Dependent Analysis of Loss of Coolant,"

WCAP-8302 (Proprieta ry) and WCAP-8306 (Non-Proprietary

), June 1974 15.0, 15.6 AE B/B-UFSAR 1.6-9 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Prediction of the Flow-Induced Vibration of Reactor Internals by Scale Model Tests," WCAP-8303 (Proprieta ry) and WCAP-8317 (Non-Proprietary

), July 1975 3.9 A "Control of Delta Ferr ite in Austenitic

Stainless Steel Weld ments," WCAP-8324-A, June 1974 lA, 5.2 A "Containment Pressure Analysis Code (COCO)," WCAP-8327 (Proprietary) and WCAP-8326 (Non-Proprietary), June 1974 15.6 AE "Westinghouse Anticipated Transients Without Trip Analysis," WCAP-8 330, August 1974 4.3, 4.6, 15.1, 15.2, 15.4, 15.8 O "Westinghouse ECCS E valuation Model -

Summary," WCAP-8339, July 1974 6.2, 15.6 AE "Westinghouse ECCS -

Plant Sensitivity Studies," WCAP-8340 (Proprietary) and WCAP-8356 (Non-Proprie tary), July 1974 15.6 AE "Westinghouse ECCS Evaluation Model Sensitivity Studies," WC AP -8341 (Proprietary) and WCAP-8342 (Non-Pro prietary), July 1974 lA(N), 17 A "Effects of Fuel Densifi cation Power Spikes on Clad Thermal Transien ts," WCAP-8359, July 1974 4.3 AE "Westinghouse Nuclea r Energy Systems Division Quality Assurance Plan," WCAP-8370, Revision 9A, S eptember 1977 1A, 17 A "Qualification of Westinghouse Seismic

Testing Procedure for Electrical Equipment Tested Prior to May 1974

," WCAP-8373, August

1974 3.10 O "Revised Clad Flatteni ng Model," WCAP-8377 (Proprietary) and WCAP

-8381 (Non-Proprietary), July 1974 4.2 A B/B-UFSAR 1.6-10 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Power Distribution Control and Load

Following Proced ures," WCAP-8385 (Proprietary) and WCAP-8403 (Non-

Proprietary), September 1974 4.3, 4.4 A "An Evaluation of Loss of Flow Accidents Caused by Power System Frequency Transients in Westinghouse PWRs," W CAP-8424, Revision 1, June 1975 15.3 O "17x17 Drive Line Comp onents Tests - Phase IB, II, III, D-Loop Dr op and Deflection," WCAP-8446 (Proprietary) and WCAP-8449 (Non-Proprietary), December 1974 3.9, 15.0 A "Analysis of Data fr om the Zion (Unit 1) THINC Verification Test," WCAP-8453-A (Proprietary), May 1 976 and WCAP-8454 (Non-Proprietary), January 1975 4.4 A "Westinghouse ECCS E valuation Model -

Supplementary Inform ation," WCAP-8471 (Proprietary) and WCAP-8472 (Non-Proprietary), April 1974 15.6 AE "Incore Power Distributi on Determination in Westinghouse Pressuriz ed Water Reactors," WCAP-8498, July 1975 4.3 O "UHI Plant Internals Vibration Measurement Program and Pre and Po st Hot Functional Examinations," WCAP-8516-P (Proprietary) and WCAP-8517 (Non-Proprie tary), April 1975 3.9 A "Critical Heat Flux Te sting of 17x17 Fuel Assembly Geometry with 22 Inch Spacing," WCAP-8536 (Proprieta ry) and WCAP-8537 (Non-Proprietary

), May 1975 4.4 A "Westinghouse ECCS - Four Loop Plant (17x17) Sensitivity Studies," WC AP-8565 (Proprietary) and WCAP-8566 (Non-Pro prietary), July 1975 15.6 A B/B-UFSAR 1.6-11 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Improved Thermal Design Procedure,"

WCAP-8567-P, July 19 75 (Proprietary) and WCAP-8568, July 1975 (Non-Proprietary) 4.4, 15.0 A "Augmented Startup a nd Cycle 1 Physics Program Supplement 1," WCAP-8575, June 1976 (Proprietary) and WCAP

-8576, June 1976 (Non-Proprietary) and Supplements.

4.3 O "The Application of Pr eheat Temperatures

After Welding Pressu re Vessel Steels," WCAP-8577, February 1976 lA A "Failure Mode and Effects Analysis (FMEA) of the Engineered Safe guard Features Actuation System," WCAP-8584 (Prop rietary) and WCAP-8760 (Non-Proprietary), April 1976 4.6 O "Environmental Qualifica tion of Westinghouse NSSS Class lE Equipm ent," WCAP-8587, September 1975 lA, 3.1O, 3.11 A "Westinghouse ECCS Eva luation Model - October 1975 Version," WCAP-8622 (Prop rietary) and WCAP-8623 (Non-Proprie tary), November 1975 15.6 A "Experimental Verificati on of Wet Fuel Storage Criticality An alyses," WCAP-8682 (Proprietary) and WCAP-8683 (Non-Proprietary), December 1975 4.3 B "Fuel Rod Bowing," WCA P-8691 (Proprietary) and WCAP-8692 (N on-Proprietary), December 1975 4.2 O "Delta Ferrite in Prod uction Austenitic Stainless Steel Weld ments," WCAP-8693, January 1976 lA, 5.2 B "MULTIFLEX - A FORTRAN-IV Computer Program for Analyzing Thermal-Hydraulic-Structure System Dynamics," WCAP-8 708 (Proprietary) and WCAP-8709 (Non-Proprie tary), February 1976 3.9 A B/B-UFSAR 1.6-12 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Improved Analytical Models Used in Westinghouse Fuel Rod Design Computations," WCAP-8720 (Proprietary) and WCAP-8785 (Non-Proprietary), October 1976 4.2 A "New Westinghouse Co rrelation WRB-1 for Predicting Critical Heat Flux in Rod Bundles with Mixing Vane Grids

," WCAP-8762, July 1976 (Proprietary) and WCAP

-8763, July 1976 (Non-Proprietary) 4.4 A "Safety-Related Research and Development for Westinghouse Pressur ized Water Reactors, Program Summaries," WC AP-8768, Revision 2, October 1978 1.5, 4.2, 4.3 B "Verification of Neutron Pad and 17x17 Guide Tube Designs by Preoperational Tests on the Trojan 1 Power Plant," W CAP-8780, May 1976 3.9 B "Improved Analytical Models Used in Westinghouse Fuel Rod Design Computations," WCAP-8785, October 1976 4.2 - "Hybrid B 4C Absorber Control Rod Evaluation Report," WC AP-8846, October 1977 4.2, 15.0 15.3 A "Westinghouse ECCS - Four Loop Plant (17x17) Sensitivity Studies wi th Upper Head Fluid Temperature at T hot ," WCAP-8865, May 1977 15.6 A "7300 Series Process C ontrol System Noise Tests," WCAP-8892-A, April 1977 7.1 A "Safety Analysis for t he Revised Fuel Rod Internal Pressure Design Basis," WCAP-8963 (Proprietary), November 1976 and WCAP-8964 (Non-Proprietary), August 1977 4.2 A "Westinghouse Emergency Core Cooling System Small Break October 19 75 Model," WCAP-8970 (Proprietary) and WCAP

-8971 (Non-Proprietary), April 1977 15.6 A B/B-UFSAR 1.6-13 REVISION 1 - DECEMBER 1989 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Failure Mode and Effects Analysis of the

Solid State Full Length Rod Control System," WCAP-8976, September 1977 4.6 O "Nuclear Design of Wes tinghouse Pressurized Water Reactors with Burn able Poison Rods," WCAP-9000-L, Revision 1 (Proprietary), July 1969 and WCAP-7806 (Non-Proprietary), December

1971. 4.3 "Axial Power Distribution Monitoring Using Four-Section Ex-Core Detectors," WCAP-9105 (Proprietary) and WCAP

-9106 (Non-Proprietary), July 1977 4.3 A "Westinghouse Emergency Core Cooling System Evaluation Model for A nalyzing Large LOCAs During Operation with One Loop Out of Service for Plants Without Loop Isolation Valves," WCAP-9166 (Proprietary) and WCAP-9167 (Non-Proprietary), February 1978 15.6 O "Westinghouse Emergency Core Cooling System Evaluation Model - M odified October 1975 Version," WCAP-9168 (Proprietary) and WCAP-9150 (Non-Proprie tary), September 1977 15.6 O "Properties of Fuel and Core Component Materials," WCAP-9179 (P roprietary), September 1977 and WCAP-9224 (Non-Proprietary) 4.2 O "Westinghouse ECCS Evaluation Model, February 1978 Versio n," WCAP-9220 (Proprietary Ver sion), WCAP-9221 (Non-Proprietary Versi on), February 1978 15.6 A "Verification Testing and Analyses of the 17x17 Optimized Fuel Assembly," WCAP-9401 (Proprietary) and WCAP-9402 (Non-

Proprietary), March 1979 4.1, 4.2, 4.4 A "PALADON - Westinghouse Nodal Comput er Code," WCAP-9485 (Proprieta ry) and WCAP-9486 (Non-Proprietary)

December 1978 4.3 A B/B-UFSAR 1.6-14 REVISION 10 - DECEMBER 2004 TABLE 1.6-1 (Cont'd)

REPORT REFERENCE SECTION(S)

REVIEW STATUS "Reference Core Report 17x17 Opt imized Fuel Assembly," WCAP-9500 (Non Proprietary), July 1979 4, 15 A "RELAP5/MOD2-B&W - An Advanced Computer Code for Light Water Reactor LOCA and non-LOCA Transient Analysis" BA W-10164, Revision 3 (non-proprietary), October 1996 15 A "CONTEMPT - Computer P rogram for Predicting Containment Pressure-Tempera ture Response to a Loss-of-Coolant Ac cident,", BAW-10095A, Revision 1, April 1978 6 O "Beacon Core Monitoring and Operations Support System," WCAP-12472 (P roprietary Class 2), August 1994 4.3, 4.4, 7.7 A "Relaxation of Constant Axial Offset Control, FQ Surveillance Techni cal Specification,"

WCAP-10216-P-A , Revision 1A (Proprietary Class 2), February 1994 4.3, 4.4 A B/B-UFSAR 1.7-1 REVISION 9 - DECEMBER 2002

1.7 DRAWINGS

The drawings cited in each UFSAR Chapter are included as "General References" only; i.

e., refer to the d rawings to obtain additional detail or to obtain background information. These drawings are not part of the UFS AR. They are controlled by the Controlled Documents Program. References on the figures contained in the UFSAR to ComE d, CECo, and Com monwealth Edison will be revised to r eflect the change in facility ownership to Exelon Generation Company when other c hanges to that figure are needed. 1.7.1 Electrical, Instrumentat ion, and Control Drawings

Subsection 1.7.1 of the FSAR provides a list of electrical, instrumentation, and control dra wings that were provided to the NRC during the initi al licensing phase.

1.7.2 Drawings

for Indepen dent Structural Review

Subsection 1.7.2 of the FSAR provides a list of the structural, architectural, mechanical loading and electrical loading drawings that were provided to the NR C to enable them to perform the Project Structural Rev iew and the Indepe ndent Structural Review during the lic ensing phase.

B/B-UFSAR 1.7-2 REVISION 9 - DECEMBER 2002 TABLE 1.7-1 This Table has been intentionally deleted.

B/B-UFSAR REVISION 9 - DECEMBER 2002

Pages 1.7-3 through 1.7-17 have been int entionally deleted.

B/B-UFSAR REVISION 9 - DECEMBER 2002

Figures 1.1-1 through 1.1-3 have been de leted intentionally.

B/B-UFSAR REVISION 9 - DECEMBER 2002

Figures 1.2-1 through 1.

2-17 have been d eleted intentionally.