ML17298A843
| ML17298A843 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/25/2017 |
| From: | Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17298A847 | List: |
| References | |
| RNP-RA/17-0063 | |
| Download: ML17298A843 (72) | |
Text
HBR 2 UPDATED FSAR CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
HBR 2 UPDATED FSAR 1-i Amendment No. 11 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS
SECTION TITLE PAGE
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT 1.1.0-1
1.1 INTRODUCTION
1.1.0-1
1.2 GENERAL
PLANT DESCRIPTION 1.2.1-1 1.2.1 SITE AND ENVIRONMENT 1.2.1-1 1.2.2
SUMMARY
PLANT DESCRIPTION 1.2.2-1 1.2.2.1 STRUCTURES 1.2.2-1 1.2.2.2 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 1.2.2-1a 1.2.2.3 REACTOR AND PLANT CONTROL 1.2.2-2 1.2.2.4 WASTE DISPOSAL SYSTEM 1.2.2-2 1.2.2.5 FUEL HANDLING SYSTEM 1.2.2-3 1.2.2.6 TURBINE AND AUXILIARIES 1.2.2-3 1.2.2.7 ELECTRICAL SYSTEM 1.2.2-3 1.2.2.8 ENGINEERED SAFETY FEATURES PROTECTION SYSTEMS 1.2.2-3
1.2.2.9 INDEPENDENT SPENT FUEL STORAGE INSTALLATION 1.2.2-4
HBR 2 UPDATED FSAR 1-ii Revision No. 20 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS (continued)
SECTION TITLE PAGE
1.3 COMPARISON
TABLES 1.3.1-1 This Section was deleted in Revision 20.
1.4 IDENTIFICATION
OF CONTRACTORS 1.4.0-1
1.5 REQUIREMENTS
FOR FURTHER TECHNICAL INFORMATION 1.5.1-1
1.5.1 DELETED
BY AMENDMENT NO. 11
1.5.2 SAFETY
INJECTION SYSTEM DESIGN 1.5.2-1
1.5.3 SYSTEMS
FOR REACTOR CONTROL DURING XENON INSTABILITIES 1.5.3-1
1.5.4 CONTAINMENT
SPRAY ADDITIVE FOR IODINE REMOVAL 1.5.4-1
1.5.5 BLOWDOWN
CAPABILITY OF REACTOR INTERNALS 1.5.5-1
1.5.6 PROGRAMS
CONDUCTED DURING OPERATION 1.5.6-1
1.6 MATERIAL
INCORPORATED BY REFERENCE 1.6.0-1
1.7 DRAWINGS
AND OTHER DETAILED INFORMATION 1.7.0-1
1.8 CONFORMANCE
TO NRC REGULATORY GUIDES 1.8.0-1
HBR 2 UPDATED FSAR 1-iii Revision No. 20 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT LIST OF TABLES
TABLE TITLE PAGE 1.1.0-1 ACRONYMS 1.1.0-2 1.1.0-2 UNITS 1.1.0-10
HBR 2 UPDATED FSAR 1-iv Revision No. 20 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT LIST OF FIGURES
FIGURE TITLE 1.2.2-1 PLOT PLAN 1.2.2-2 GENERAL ARRANGEMENT REACTOR BUILDING PLANS - SHEET 1
1.2.2-3 GENERAL ARRANGEMENT REACTOR BUILDING PLANS - SHEET 2
1.2.2-4 GENERAL ARRANGEMENT REACTOR BUILDING - SECTIONS
1.2.2-5 GENERAL ARRANGEMENT REACTOR AUXILIARY BUILDING PLANS
1.2.2-6 GENERAL ARRANGEMENT REACTOR AUXILIARY BUILDING -
SECTIONS
1.2.2-7 GENERAL ARRANGEMENT FUEL HANDLING BUILDING AND MACHINE SHOP PLANS
1.2.2-8 GENERAL ARRANGEMENT FUEL HANDLING BUILDING AND MACHINE SHOP SECTIONS
1.2.2-9 GENERAL ARRANGEMENT TURBINE BUILDING GROUND FLOOR PLAN
1.2.2-10 GENERAL ARRANGEMENT TURBINE BUILDING MEZZANINE FLOOR
PLAN
1.2.2-11 GENERAL ARRANGEMENT TURBINE BUILDING OPERATING FLOOR
PLAN
1.2.2-12 GENERAL ARRANGEMENT TURBINE BUILDING SECTIONS
HBR 2 UPDATED FSAR 1.1.0-1 Revision No. 27
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
This updated Final Safety Analysis Report (FSAR) is for the H. B. Robinson Steam Electric
Plant Unit 2 (HBR 2). It is submitted to fulfill the requirements of 10CFR 50.71(e), as published
in the Federal Register on May 9, 1980. The Atomic Energy Commission (AEC) issued Facility
Operating License No. DPR-23 for HBR 2, dated July 31, 1970, specifying maximum power
level of 2200 MWt upon completion of preliminary testing and certain other prerequisites. These
prerequisites were satisfactorily met in the following months. The Docket No. is 50-261, and the
Construction Permit for the unit was No. CPPR-26. The Nuclear Regulatory Commission (NRC)
issued a license amendment on June 29, 1979, which authorized operation at a maximum
power level of 2300 MWt. A subsequent license amendment was issued on November 5, 2002, authorizing operation at a maximum power level of 2339 MWt. The FSAR for the unit was
submitted in November, 1968, and was amended a number of times prior to the issuance of the
licenses. This updated FSAR has been organized in accordance with the guidelines contained
in Regulatory Guide 1.70, Revision 3.
Table 1.1.0-1 lists the acronyms and Table 1.1.0-2 gives the abbreviations used throughout this
updated FSAR.
HBR 2 is situated on Lake Robinson, a man-made 2250 acre lake, about 4.5 miles from
Hartsville, South Carolina.
The HBR 2 reactor is a pressurized light water moderated and cooled system. The unit is
designed to produce 2339 MWt. All steam and power conversion equipment, including the
turbine generator, was designed to permit generation of 787 MWe (gross).
The nuclear power plant incorporates a closed-cycle pressurized water Nuclear Steam Supply
System (NSSS) and a Turbine-Generator System utilizing dry and saturated steam. Equipment
includes systems for the processing of radioactive wastes, handling of fuel, electrical
distribution, cooling, power generation structures, and all other onsite facilities required to
provide a complete and operable nuclear power plant.
HBR 2 UPDATED FSAR 1.1.0-2 Revision No. 18 TABLE 1.1.0-1 ACRONYMS AC air conditioning; also, alternating current
ACI American Concrete Institute
ACS Auxiliary Coolant System
AEC Atomic Energy Commission
AISC American Institute of Steel Construction
AISI American Iron and Steel Institute
ALARA as low as is reasonably achievable
AMSAC ATWS Mitigation System Actuation Circuitry
ANS American Nuclear Society
ANSI American National Standards Institute
APCSB Auxiliary and Power Conversion Systems Branch
API American Petroleum Institute
ARC Automatic Rod Control
ASA American Standards Association
ASCE American Society of Civil Engineers
ASME American Society of Mechanical Engineers
ASTM American Society for Testing and Materials
ATWS Anticipated Transient Without Scram
AVT All Volatile Treatment
AWS American Welding Society
AWWA American Water Works Association
BAT boron acid tank
B&PV boiler and pressure vessel
BIT boron injection tank HBR 2 UPDATED FSAR 1.1.0-3 Amendment No.3 TABLE 1.1.0-1 (Cont'd)
BOC beginning of cycle
BOL beginning of life
BTP branch technical position
BWR boiling water reactor
CCW component cooling water
CES Critical Experiment Station
CFPP Containment Fire Protection Status Panel
CFR Code of Federal Regulations
CIS Containment Isolation System
CMAA Crane Manufacturers Association of America, Inc.
CNS Corporate Nuclear Safety
CP&L Carolina Power & Light Company
CRD control rod drive
CRDM control rod drive mechanism
CRDS Control Rod Drive System
CS carbon steel CSS Containment Spray System
CV containment vessel CVCS Chemical and Volume Control System
CVTR Carolina-Virginia Tube Reactor
DBA design basis accident
DC direct current DECLG double-ended, cold leg guillotine
DF decontamination factor HBR 2 UPDATED FSAR 1.1.0-4 Amendment No.7 TABLE 1.1.0-1 (Cont'd)
DG diesel generator
DMIMS Digital Metal Impact Monitoring System
DNB departure from nucleate boiling
DNBR departure from nucleate boiling ratio
DOT Department of Transportation
DS dedicated shutdown DTT Design Transition Temperature
Ebasco Electric Bond and Share Company
ECCS Emergency Core Cooling System
EFPH effective full-power hours
EFPY effective full-power years
ENC Exxon Nuclear Corporation
EOC end of cycle
EOL end of life
EPRI Electric Power Research Institute
ESF Engineered Safety Features
FAP Fire Alarm Status Panel
FDAP Fire Detection Actuation Panel
FDAS Fire Detection Actuation System
FHB Fuel Handling Building
FI Fully Integral Ruggedized Rotor
FIRL Franklin Institute Research Laboratory
FM Factory Mutual Research; also, frequency modulated
FSAR Final Safety Analysis Report
GDC General Design Criteria
HBR 2 UPDATED FSAR 1.1.0-5 Amendment No.3 TABLE 1.1.0-1 (Cont'd)
GM Geiger - Mueller
GWPS Gaseous Waste Processing System
HBR H. B. Robinson
HEPA high-efficiency particulate air filters
HIS Hydraulic Institute Standards
HP high pressure HPSI high pressure safety injection
HVAC heating, ventilating, and air conditioning
IAEA International Atomic Energy Agency
I&C instrumentation and control
IC internal combustion
ID inside diameter IEEE Institute of Electrical and Electronic Engineers
INPO Institute of Nuclear Power Operations
IPBS Integrated Planning, Budgeting, and Scheduling
IPCEA Insulated Power Cable Engineers Association
ISI in-service inspection
IVSW isolation valve seal water
IVSWS Isolation Valve Seal Water System
LED light emitting device; also, light-emitting diode
LHGR linear heat generation rate
LMFBR liquid metal fast breeder reactor
LOCA loss-of-coolant accident LP low pressure LPSI low pressure safety injection
LVDT linear variable differential transducers HBR 2 UPDATED FSAR 1.1.0-6 Amendment No.3 TABLE 1.1.0-1 (Cont'd)
LWR light water reactor
MCA maximum credible accident
MCC motor control center
MDNBR minimum departure from nucleate boiling ratio
MG motor generator
MM Modified Mercalli MOV motor operated valve
MPC maximum permissible concentration
MSIV main steam isolation valve
MSL mean sea level
MTC moderator temperature coefficient
MWT makup water tank
NBS National Bureau of Standards
NDE nondestructive examination
NDTT nil-ductility transition temperature
NEMA National Electrical Manufacturer's Association
NFPA National Fire Protection Association
NIS Nuclear Instrumentation System
NML Nuclear Mutual Limited
NPSH net positive suction head
NRC Nuclear Regulatory Commission
NSAC Nuclear Safety Analysis Center (EPRI)
NSSS Nuclear Steam Supply System
NWRC National Weather Records Center
OBE operational basis earthquake
OD outside diameter HBR 2 UPDATED FSAR 1.1.0-7 Amendment No.3 TABLE 1.1.0-1 (Cont'd)
ORNL Oak Ridge National Laboratory
OSHA Occupational Safety and Health Administration
PA Public Address PACV Post-Accident Containment Venting
PBX private branch exchange
PCI pellet-cladding interaction
PCT peak clad temperature
PDC II power distribution control II
PF power factor PFI Pipe Fabrication Institute
pH Concentration of Hydrogen ions
PLA Pickard, Lowe & Associates
PLSA Part Length Shield Assembly
PMF probable maximum flood
PORV power-operated relief valve(s)
PPS Penetration Pressurization System
PRCF Plutonium Recycle Facility
PRT pressurizer relief tank
PSAR Preliminary Safety Analysis Report
PTS Pressurized Thermal Shock
PVC polyvinyl chloride PWR pressurized water reactor
QA quality assurance
QAC Quality Assurance Committee
QC Quality Control QCS Quality Control Systems HBR 2 UPDATED FSAR 1.1.0-8 Amendment No.3 TABLE 1.1.0-1 (Cont'd)
RAB Reactor Auxiliary Building
RC radiation control RCC rod cluster control
RCCA rod cluster control assembly
RCDT reactor coolant drain tank
RCGVS Reactor Coolant Gas Vent System
RCP reactor coolant pump
RCPB reactor coolant pressure boundary
RCPS Reactor Coolant Pump System
RG Regulatory Guide RG&E Rochester Gas and Electric
RH relative humidity RHR residual heat removal
RHRS Residual Heat Removal System
RMS Radiation Monitoring System
RTD resistance temperature detectors
RTG reactor and turbine-generator
RTGB reactor and turbine-generator board
RT NDT Reference Temperature, Nil-Ductility Transition
RTS Reactor Trip System
RWP radiation work permits
RWST refueling water storage tank
SAFDL specified acceptable fuel design limit
HBR 2 UPDATED FSAR 1.1.0-8a Revision No. 15 TABLE 1.1.0-1 (Continued)
SAR Safety Analysis Report SBOStation Blackout
SFP Spent Fuel Pit
SHNPP Shearon Harris Nuclear Power Plant
SI Safety Injection
SIS Safety Injection System
SOR Senior Operator License
SPCSiemens Power Corporation
SRO Senior Reactor Operator
SRWP Standing Radiation Work Permit
SS Stainless Steel SSE Safe Shutdown Earthquake
SSPC Steel Structure Painting Council
STP Standard Temperature and Pressure
SWP Service Water Pump
SWPS Solid Waste Processing System
HBR 2 UPDATED FSAR 1.1.0-9 Amendment No.10 TABLE 1.1.0-1 (Cont'd)
SWRI Southwest Research Institute
SWS Service Water System
TD theoretical density TDH total developed head
TEMA Tubular Exchanger Manufacturers' Association
TLD thermoluminescent dosimeters
USAEC United States Atomic Energy Commission
USAS United States of America Standards
USGS United States Geological Survey
UHF ultra high frequency
UL Underwriter's Laboratories, Inc.
UPS uninterruptible power supply
UT ultrasonic test UTM Universal Transverse Mercator
VCT volume control tank
VHF very high frequency
WAPD Westinghouse Atomic Power Division
WDS Waste Disposal System
Westinghouse Westinghouse Electric Corporation
WOL wedge opening loading
WREC Westinghouse Reactor Evaluation Center
HBR2UPDATEDFSAR 1.1.0-10TABLE1.1.0-2 UNITS acre ac acre-foot ac-ft ampere amp atmosphere per cubic centimeter atm/cc average temperature T avg brake horsepower bhp British thermal units per hour Btu/hr British thermal units per hour/foot Btu/hr/ft British thermal units per hour/square foot Btu/hr-ft 2 calorie cal centimeter cm centipoise cp Chi/Q /Q cubic centimeter cm 3 or cc cubic centimeters per hour cc/hr cubic centimeters per minute cc/min cubic feet per minute cfm or ft 3/min cubic feet per second ft 3/sec or cfs cubic foot ft 3 cubic meter m 3 cubic yard yd 3 curie Ci curie per cubic centimeter Ci/cc curie per second Ci/sec HBR2UPDATEDFSAR 1.1.0-11 TABLE 1.1.0-2 (Cont'd) curie per year Ci/yr cycles per second cps or Hz degrees centigrade
°C degrees Farenheit
°F degrees Kelvin
°K direct current DC disintegrations per second per milligram DPS/mg electron volt ev feet (foot) ft feet per second fps foot-inch ft-in.foot-pound ft-lb gallon gal gallons per day gal/day or gpd gallons per hour gal/hr gallons per minute gal/min or gpm gram g gram mole per degree Rankine g mole/°R gram per cubic centimeter g/cc or g/cm 3 Hertz hz horsepower HP hour hr inch (inches) in. inch water gage in. wg or wg inside diameter ID kiloelectron volt Kev HBR2UPDATEDFSAR 1.1.0-12 TABLE 1.1.0-2 (Cont'd) kilogram kg kilovolt kV kilovolt-ampere kVa kilowatt kW kilowatt per foot kW/ft megawatt MW megawatt days per metric ton of uranium MWD/MTU megawatt (electric)
Mwe megawatt (thermal)
Mwt mercury Hg meter m micro curie per cubic centimeter Ci/cc micro mho per centimeter (conductivity) mho/cm micron, micro mile per hour mph mile per second mps millicurie mCi milligram per square decimeter mg/dm 2 milliliter ml million electron volts Mev millirem per hour mrem/hr milliroentgen per hour mR/hr millivolt mv minute or minimum min HBR 2 UPDATED FSAR
1.1.0-13 TABLE 1.1.0-2 (Cont'd)
neutron multiplication factor, effective K eff neutron multiplication factor, infinity K neutrons per square centimeter-second (nv) n/cm 2-sec ohm-centimeter (Resistivity) ohm-cm
parts per billion ppb
parts per million ppm
per second sec
-1 pound lb
pound mass lbm
pounds per cubic foot lb/ft 3 or pcf pounds per hour lb/hr
pounds per square foot lb/ft 2 or psf pounds per square inch psi
pounds per square inch (absolute) psia
pounds per square inch (differential) psid
pounds per square inch (gage) psig
radiation absorption dose rad
radius r
reactivity k/k reactivity change rate k/sec revolutions per minute rpm
revolutions per second rps
roentgen R
roentgen equivalent man rem
roentgens per hour R/hr
root mean square rms HBR 2 UPDATED FSAR 1.1.0-14 TABLE 1.1.0-2 (Cont'd) second sec
specific gravity sp gr square ( )2 or sq square centimeter cm 2 square foot ft 2 or sq ft
square inch in.2 or sq in.
square mile mi 2 or sq mi
standard cubic feet scf or stdft
standard cubic feet per minute scfm or stdft 3/min standard cubic feet per second scfs temperature of the cold leg T cold temperature of the hot leg T hot thickness T
thousand pounds kip thousand pounds per linear foot k/lf thousand pounds per square inch ksi thousandth of an inch mil ton (short ton) ton, st tonne (metric ton, 2,204.62 lb) te, mt volt V
volt alternating current V AC volt ampere Va volt direct current V DC volume percent vol %
water column wc watt W HBR 2 UPDATED FSAR 1.1.0-15 TABLE 1.1.0-2 (Cont'd) watt per cubic centimeter W/cc week wk
weight percent wt %
yard yd
year yr
HBR 2 UPDATED FSAR 1.3.1-1 Revision No. 20
1.3 COMPARISON
TABLES Section 1.3 information was deleted in Revision 20.
HBR 2 UPDATED FSAR 1.4.0-1 1.4 IDENTIFICATION OF CONTRACTORS The Carolina Power & Light Company (CP&L), as owner, engaged or approved the engagement
of, the contractors and consultants identified below in connection with the design and
construction of HBR Unit 2. However, irrespective of the explanation of contractual
arrangements offered below, CP&L was the sole applicant for the construction permit and is the
operating licensee, and as owner and licensee is responsible for the design, construction, and
operation of the Unit.
HBR 2 was designed and built by the Westinghouse Electric Corporation as prime contractor for
CP&L. Westinghouse undertook to provide a complete, safe, and operable nuclear power plant
ready for commercial service. The project was directed by Westinghouse from the offices of its
Atomic Power Division in Pittsburgh, Pennsylvania, and by Westinghouse representatives at the
plant site during construction and plant startup. Westinghouse engaged the engineering firm of
Electric Bond and Share Company (Ebasco) Services Incorporated of New York City, New York, to provide the design of the structures and non-nuclear portions of the plant to prepare
specifications for the purchase and construction thereof. CP&L reviewed the designs and
specifications prepared by Westinghouse and Ebasco Services to assure that the general plant arrangements, equipment, and operating provisions were satisfactory to them. CP&L inspected
the construction work to assure that the plant was built in accordance with the approved plans
and specifications.
The plant was constructed under the general direction of Westinghouse through a general
contractor who was responsible for the management of all site construction activities and who
either performed or subcontracted the work of construction and equipment erection.
Preoperational testing of equipment and systems and initial plant operation was performed by
CP&L personnel under the technical direction of Westinghouse.
As consultants on studies of plant site geology, hydrology, and seismology, the firm of Dames
and Moore of New York, New York, was engaged by CP&L to work in conjunction with Ebasco
Services.
As additional consultants on seismology and geology, Dr. G. W. Housner of the California
Institute of Technology; Dr. J. L. Stuckey and Dr. L. L. Smith, Consultants, Raleigh, North
Carolina; and Dr. P. Byerly, Consultant, Oakland, California, were engaged by CP&L.
As consultants on reactor and plant engineering, site meteorology, and general site studies, the
firm of Pickard, Lowe, and Associates of Washington, D. C. was engaged by CP&L.
HBR 2 UPDATED FSAR 1.5.1-1 Amendment No. 11 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION Research and development (as defined in Section 50.2 of the commission's regulations) was
conducted regarding final core design details and parameters (no longer applicable due to
refueling changes), analytical methods for kinetics calculation, safety injection (emergency core
cooling) system, xenon stability and related control systems, containment spray additive
effectiveness, and capability of reactor internals to resist blowdown forces. The information
submitted in Supplement No. 1, Tab 11 Item 1 of the original FSAR clarified the status of
Westinghouse safety-related research and development programs as they related to the HBR 2.
That information is now obsolete and not included in the updated FSAR.
1.5.1 DELETED
BY AMENDMENT NO. 11.
1.5.2-1 1.5.2 SAFETY INJECTION SYSTEM DESIGN
The design of the safety injection system is essentially that proposed at the time the
construction permit was issued; that is, it includesnitrogen-pressurized accumulators to inject
borated water into the RCS to rapidly and reliably reflood the core following a loss-of-coolant
accident (LOCA). Additional analyses have been performed to demonstrate that the
accumulators in conjunction with other components of the emergency core cooling system can
adequately cool the core for any pipe rupture.
Research and development work has also been performed on the integrity of Zircaloy-clad fuel
under conditions simulating those during a LOCA. Under the conservatively evaluated
temperature predicted for the fuel rods during LOCA, the clad may burst due to a combination of
fuel rod internal gas pressure and the reduction of clad strength with temperature. Burst
cladding could block flow channels in the core, so that core cooling by the safety injection
system would be insufficient to prevent fuel rod melting.
Rod burst experiments have therefore been conducted on Zircaloy rods to evaluate the
mechanism and effects of this potential channel blockage. Single rod tests are presented in
detail in Reference 1.5.2-1.
1.5.3-1 Revision No. 18 1.5.3 SYSTEMS FOR REACTOR CONTROL DURING XENON INSTABILITIES
In the transition to large Zircaloy-clad-fuel cores, the potential of power spatial redistribution
caused by instabilities in local xenon concentration was created.
Extensive analytical work has been performed on reactor core stability (References 1.5.3-1, 1.5.3-2, and 1.5.3-3). These references indicate that a core of this size may be unstable against axial power redistribution, but is nominally stable against transverse (denoted X-Y)
power oscillations. The plant is therefore provided with instrumentation which will allow the
operator to detect the axial power oscillations, and procedures exist for suppressing these
oscillations (Section 7.7.1).
Control information for suppression of power oscillation is obtained from four long ion chambers, each divided into an upper and lower section, mounted vertically outside the core. Both
calculation and experimental measurements at SENA, San Onofre and Haddam Neck have
shown that this out-of-core instrumentation represents in core power distribution, which is
adequate for power distribution control (Reference 1.5.3-3).
The control strategy is based on the difference in output between the top and bottom sections of
the long ion chambers. If the operator allows axial power imbalance to exceed operating limits, various levels of protection are invoked automatically. These include generation of alarms, turbine power cutback and blocking of control rod withdrawal.
1.5.5-1 Revision No. 15 1.5.5 BLOWDOWN CAPABILITY OF REACTOR INTERNALS
As documented in the response to AEC Questions dated 3/24/69, the computer code BLODWN-
2 was used to evaluate the blowdown capability of the reactor internals. In the response to AEC
Questions dated 8/22/69, it was indicated that the BLODWN-2 analysis performed for Indian
Point was applicable to Robinson. Detailed data from that evaluation was included in the
response to AEC Questions which indicates that the "Blowdown Capability of Reactor Internals" was evaluated with BLODWN-2.
Furthermore, in June 1980, the response of the reactor vessel (including the internals) to a
guillotine break at the reactor vessel inlet nozzle was evaluated by a different set of computer
codes in WCAP-9748 (Westinghouse Owners Group Asymmetric LOCA Loads Evaluation).
Subsequent review by the NRC determined that the probability of failure in the primary system
is low enough that a double ended guillotine break need not be postulated as a design basis
event for defining structural loads (reference Generic Letter 84-04).
The response of Siemens fuel assemblies to LOCA blowdown forces was evaluated in XN-NF-
76-47 (Combined Seismic-LOCA Mechanical Evaluation for Exxon Nuclear 15x15 Reload Fuel).
This evaluation is cited in UFSAR Section 4.0.
1.5.6-1 1.5.6 PROGRAMS CONDUCTED DURING OPERATION
There are no ongoing programs specific to HBR 2 to demonstrate the acceptability of
contemplated future changes in design or modes of operation.
1.5R-1 Amendment No. 11 HBR 2 UPDATED FSAR
REFERENCES:
SECTION 1.5
1.5.2-1 WCAP-7379-L, Performance of Zircaloy Clad Fuel Rods During a Single Rod Test, October 6, 1969. (Westinghouse Proprietary).
1.5.3-1 Poncelet, C. G. and Christie, A. M., "Xenon Induced Spatial Instabilities in Large Pressurized Water Reactors," WCAP-3680-20, March 1968.
1.5.3-2 McGough, J. D., "The Effect of Xenon Spatial Variations and the Moderator Coefficient Core Stability," WCAP-2983, August 1966.
1.5.3-3 Westinghouse Proprietary Report, "Power Distribution Control in Westinghouse PWR," WCAP-720. OCTOBER 1968.
1.5.4-1 Westinghouse Confidential Report, "Investigation of Chemical Additives for Reactor Containment Sprays," WCAP-7153, March 1968.
HBR 2 UPDATED FSAR 1.6.0-1 1.6 MATERIAL INCORPORATED BY REFERENCE Topical Reports and other material incorporated by reference are called out in individual
subsections and listed in the section reference lists.
HBR 2 UPDATED FSAR 1.7.0-1 1.7 DRAWINGS AND OTHER DETAILED INFORMATION The "drawing package" is not part of the original FSAR. This section is not applicable to the
Updated FSAR.
HBR 2 UPDATED FSAR 1.8.0-1 Revision No. 27 1.8 CONFORMANCE TO NRC REGULATORY GUIDES Regulatory Guides (originally called Safety Guides) have been published beginning in late 1970.
Since H. B. Robinson (HBR) was licensed for operation prior to that time, they were not
addressed. Those Regulatory Guides which have been addressed during the operating phase
are discussed below.
HBR 2 UPDATED FSAR 1.8.0-2 Revision No. 27 Regulatory Guide 1.8 PERSONNEL SELECTION AND TRAINING (SEPTEMBER 1975)
ANSI Standard N18.1-1971 PERSONNEL SELECTION AND TRAINING
The criteria for selection and training of personnel for operation of Robinson 2 are addressed in
the Robinson Technical Specifications.
HBR 2 UPDATED FSAR 1.8.0-3 Revision No. 27 Regulatory Guide 1.13 FUEL STORAGE FACILITY DESIGN BASIS Conform to Regulatory Guide 1.13 only as it relates to the new high-density spent fuel storage
racks design for preventing damage resulting from the safe shutdown earthquake (SSE), and
protecting the fuel from mechanical damage.
HBR 2 UPDATED FSAR 1.8.0-4 Revision No. 27 Regulatory Guide 1.28 QUALITY ASSURANCE PROGRAM REQUIREMENTS (DESIGN AND CONSTRUCTION)
Conformance with Regulatory Guide 1.28 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-5 Revision No. 27 Regulatory Guide 1.29 SEISMIC DESIGN CLASSIFICATION Comply with Regulatory Guide 1.29, Revision 3, only as it relates to the new high-density spent
fuel storage racks designated Seismic Category I as defined and outlined in the regulatory
guide.
HBR 2 UPDATED FSAR 1.8.0-6 Revision No. 27 Regulatory Guide 1.30 QUALITY ASSURANCE REQUIREMENTS FOR THE INSTALLATION, INSPECTION, AND TESTING OF INSTRUMENTATION AND ELECTRICAL
EQUIPMENT
Conformance with Regulatory Guide 1.30 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-7 Revision No. 27 Regulatory Guide 1.33 QUALITY ASSURANCE PROGRAM REQUIREMENTS (OPERATION)
Conformance with Regulatory Guide 1.33 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-8 Revision No. 27 Regulatory Guide 1.37 QUALITY ASSURANCE REQUIREMENTS FOR CLEANING OF FLUID SYSTEMS AND ASSOCIATED COMPONENTS OF WATER-COOLED NUCLEAR POWER PLANTS
Conformance with Regulatory Guide 1.37 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-9 Revision No. 27 Regulatory Guide 1.38 QUALITY ASSURANCE REQUIREMENTS FOR PACKAGING, SHIPPING, RECEIVING, STORAGE, AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR
POWER PLANTS
Conformance with Regulatory Guide 1.38 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17
HBR 2 UPDATED FSAR 1.8.0-10 Revision No. 27 Regulatory Guide 1.39 HOUSEKEEPING REQUIREMENTS FOR WATER-COOLED NUCLEAR POWER PLANTS Conformance with Regulatory Guide 1.39 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-11 Revision No. 27 Regulatory Guide 1.52 DESIGN, TESTING, AND MAINTENANCE CRITERIA FOR POST ACCIDENT ENGINEERED SAFETY - FEATURE ATMOSHPERE CLEANUP
SYSTEM AIR FILTRATION AND ADSORPTION
UNITS OF LIGHT-WATER-COOLED NUCLEAR
POWER PLANTS (MARCH 1978)
ANSI Standard N510-1975/1980 TESTING OF NUCLEAR AIR-CLEANING SYSTEMS The RNP Ventilation Filter Testing Program, as described in Section 5.5.11 of the Improved
Technical Specification, shall comply with the frequencies specified in Positions C.5 and C.6 of
Regulatory Guide 1.52 (March 1978) and conducted in general conformance with ANSI
Standard N510-1975 or N510-1980. Applicable portions of the Fuel Handling Building Ventilation System and Containment Purge System shall be tested in accordance with ANSI
Standard N510-1975. Applicable portions of the Control Room Emergency Filtration System
shall be tested in accordance with ANSI Standard N510-1980.
HBR 2 UPDATED FSAR 1.8.0-12 Revision No.27 Regulatory Guide 1.54 QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS (JUNE
1973)
ANSI Standard N101.4-1972 QUALITY ASSURANCE FOR PROTECTIVE COATINGS APPLIED TO NUCLEAR FACILITIES
HBR2 is not committed to compliance with RG 1.54 and ANSI 101.4.
The applicable surfaces at Robinson 2 are recoated with original type coating or approved equal
in accordance with original specification requirements, or equivalent engineering requirements
established for touch-up and repair.
HBR 2 UPDATED FSAR 1.8.0-13 Revision No.27 Regulatory Guide 1.58 QUALIFICATION OF NUCLEAR POWER PLANT INSPECTION, EXAMINATION, AND TESTING PERSONNEL
Conformance with Regulatory Guide 1.58 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-14 Revision No. 27 Regulatory Guide 1.60 DESIGN RESPONSE SPECTRA FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS Comply with Regulatory Guide 1.60 only as it relates to design spectra for the new high-density
spent fuel storage racks.
HBR 2 UPDATED FSAR 1.8.0-15 Revision No. 27 Regulatory Guide 1.61 DAMPING VALUES FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS Comply with Regulatory Guide 1.61 only as related to damping factors for the new high-density
spent fuel storage racks.
HBR 2 UPDATED FSAR 1.8.0-16 Revision No. 27 Regulatory Guide 1.64 QUALITY ASSURANCE REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS Conformance with Regulatory Guide 1.64 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-17 Revision No. 27 Regulatory Guide 1.74 QUALITY ASSURANCE TERMS AND DEFINITIONS Conformance with Regulatory Guide 1.74 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-18 Revision No. 27 Regulatory Guide 1.75 PHYSICAL INDEPENDENCE OF ELECTRICAL SYSTEMS. See Section 7.4.2.1 for application of Regulatory Guide 1.75.
HBR 2 UPDATED FSAR 1.8.0-19 Revision No. 27 Regulatory Guide 1.88 REQUIREMENTS FOR COLLECTION, STORAGE, AND MAINTENANCE OF QUALITY ASSURANCE RECORDS FOR NUCLEAR POWER PLANTS Conformance with Regulatory Guide 1.88 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-20 Revision No. 27 Regulatory Guide 1.92 COMBINING MODAL RESPONSES AND SPATIAL COMPONENTS IN SEISMIC RESPONSE ANALYSIS Guidelines set forth in Regulatory Guide 1.92 were used only as they related to the new high-
density fuel storage rack seismic analysis.
HBR 2 UPDATED FSAR 1.8.0-21 Revision No. 27 Regulatory Guide 1.94 QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION, INSPECTION, AND TESTING OF STRUCTURAL CONCRETE AND STRUCTURAL
STEEL DURING THE CONSTRUCTION PHASE
OF NUCLEAR POWER PLANTS
Conformance with Regulatory Guide 1.94 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-22 Revision no. 27 Regulatory Guide 1.97 INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS TO ASSESS PLANT CONDITIONS
DURING AND FOLLOWING AN ACCIDENT (REV 3)
The guidelines for selecting variables to be monitored were established in accordance with
Regulatory Guide 1.97 (Revision 3) and NUREG 0737
Supplement 1.
The compliance with these documents is detailed in the following correspondence:
CP&L Letter NLS-84-509, E. E. Utley (CP&L) to S. A. Varga (NRC), "Response to
Order Confirming Commitments on Emergency Response Facility," dated December
31, 1984.
CP&L Letter NLS-85-198, S. R. Zimmerman (CP&L) to S. A. Varga (NRC), "Revision
to Compliance Report for Regulatory Guide 1.97, Revision 3," dated July 18, 1985.
CP&L Letter NLS-86-267, A. B. Cutter (CP&L) to S. A. Varga (NRC), "Revision 2 to
Regulatory Guide 1.97 Submittal," dated July 28, 1986.
CP&L Letter NLS-87-093, A. B. Cutter (CP&L) to S. A. Varga (NRC), "Change
Reactor Coolant Pump Seal Return Flow to Type D3 Variable," dated May 1, 1987.
CP&L Letter NLS-87-136, S. R. Zimmerman (CP&L) to S. A. Varga (NRC), "Revision
4 to Regulatory Guide 1.97 Submittal," dated October 9, 1987.
CP&L Letter NLS-87-065, A. B. Cutter to NRC, "CCW Temperature Instrumentation -
R.G. 1.97," dated March 27, 1987.
NRC Letter, G. Requa (NRC) to E. E. Utley (CP&L) "Request for Information - R.G.
1.97," March 5, 1987.
NRC Letter, K. T. Eccleston (NRC) to E. E. Utley (CP&L), "Regulatory Guide 1.97,"
April 29, 1987.
CP&L Letter RNP-RA/01-0164, B. L. Fletcher III to NRC, "Request for Technical
Specification Change to Eliminate Requirements for the Post-Accident Sampling
System," dated October 31, 2001.
NRC Letter, A. G. Hansen (NRC) to J. W. Moyer (CP&L), "H. B. Robinson Steam
Electric Plant, Unit No. 2 - Issuance of an Amendment RE: Elimination of
Requirements for the Post-Accident Sampling System (TAC No. MB3380)," dated
January 14, 2002
HBR 2 UPDATED FSAR 1.8.0-23 Revision No. 27 Regulatory Guide 1.116 QA REQUIREMENTS FOR INSTALLATION, INSPECTION, AND TESTING OF MECHANICAL EQUIPMENT AND SYSTEMS
Conformance with Regulatory Guide 1.116 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-24 Revision No. 27 Regulatory Guide 1.123 QUALITY ASSURANCE REQUIREMENTS FOR CONTROL OR PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR POWER PLANTS
Conformance with Regulatory Guide 1.123 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-25 Revision No. 27 Regulatory Guide 1.124 DESIGN LIMITS AND LOADING COMBINATIONS FOR CLASS I LINEAR-TYPE COMPONENT SUPPORTS DEP complied with Regulatory Guide 1.124 only as it related to the design of the rack
component supports for the new high-density fuel storage racks.
HBR 2 UPDATED FSAR 1.8.0-26 Revision No. 27 Regulatory Guide 1.133 LOOSE PARTS DETECTION PROGRAM FOR THE PRIMARY SYSTEM OF LIGHT-WATER-COOLED REACTORS (REVISION 1)
RG 1.133 Revision 1 Section D states "In cases where licensees of operating reactors (licensed
prior to January 1, 1978) have not previously committed to install a loose-part detection system
or where the design of an existing system precludes upgrading to an effective functional
capability, the licensee should install a system in conformance with the programmatic aspects of
the guide, specifically Sections C.2 and C.3, or propose an acceptable alternative. In cases
where a loose part is known to be present or there exists a high probability that a part may
become loose based on experience with other reactors of similar design, a loose-part detection
system conforming to this guide should be installed."
The Loose Parts Detection System at HBR 2 is in compliance with the regulatory position C.2
and C.3 with the following exceptions:
Portions of the functional tests are performed every quarter instead of the recommended
monthly frequency of Section C.3.a.(2).(d). Portions of the background checks are performed
every six months instead of the recommended quarterly frequency of Section C.3.a.(2).(e).
Special reports to the NRC are not submitted to setpoint changes as recommended in Section
C.3.a.(2).(a).
HBR 2 UPDATED FSAR 1.8.0-27 Revision No. 27 Regulatory Guide 1.137 FUEL OIL SYSTEMS FOR STANDBY DIESEL GENERATORS (REVISION 1)
HBR 2 will comply with Regulatory Guide 1.137 with the following exceptions:
Regulatory Position C.1 is not applicable to HBR 2 per NRC's letter dated January 13, 1978 which
distributed Regulatory Guide 1.137 and provided additional guidance regarding NRC's implementation of this guide for all nuclear power plants. Position C.1 was to be evaluated on a
case by case basis for application to all construction permit cases under review whose Safety Evaluation Report had not been issued as of November 1, 1979. Since HBR 2 had an operating license as of this date, Position C.1 is not applicable.
Regulatory Position C.2 is applicable to HBR 2 per NRC's letter dated January 13, 1978 except as
follows:
A. The analyses performed will be limited to API or specific gravity, water and sediment, viscosity and cloud point. The specifications that will be met will be in accordance with the
Diesel Fuel Oil Testing Program (Improved Standard Technical Specifications Bases) which
also are in accordance with the emergency diesel generator manufacturer's
recommendations.
B. The Unit No. 2 diesel fuel oil storage tank is filled from site storage tanks, the sampling frequency will be as described below:
- 1. New fuel oil received for storage in the fuel oil storage tanks and subsequently transferred to the Unit 2 DG fuel oil storage tank is verified to meet the analysis limits of the Diesel Fuel Oil Testing Program prior to adding to the storage tanks. This is
accomplished either by verifying the integrity of the seal(s) on the tank truck against
the certificate of compliance or by testing of the fuel oil prior to transfer from the tank
truck.
- 2. Stored fuel in the storage tanks and in the Unit 2 DG fuel oil storage tank is sampled every 31 days in accordance with the Diesel Fuel Oil Testing Program.
Diesel Generator (DG) fuel oil is controlled under the QA Program by virtue of the procedures for
testing of DG fuel oil being incorporated in the Plant Operating Manual which is part of the approved
QA Program.
Fuel Oil sampling from the discharge of the transfer pump was compared to the methodology in
ASTM D270-1975 and verified to be an equivalent sampling methodology.
The above position is based on the following references:
(1) NRC letter, Robert B. Minogue (NRC) to Regulatory Guide Distribution List (Division 1), regarding Regulatory Guide 1.137 dated January 13, 1978.
(2) NRC letter, D. G. Eisenhut (NRC) to All Power Reactor Licenses, January 7, 1980, Incoming Document No. NLU-80-48.
(3) CP&L letter, NO-80-725, M. A. McDuffie (CP&L) to D. A. Eisenhut (NRC), "Quality Assurance Requirements for Diesel Generator Fuel Oil", May 14, 1980.
HBR 2 UPDATED FSAR 1.8.0-28 Revision No. 27 Regulatory Guide 1.137 FUEL OIL SYSTEMS FOR STANDBY DIESEL GENERATORS (REVISION 1)
(4) NRC letter, Steven A. Varga (NRC) to J. A. Jones (CP&L), September 30, 1981, Incoming Document No. NLU-81-482.
(5) CP&L letter, NO-81-1914, November 20, 1981, S. R. Zimmerman (CP&L) to S. A.
Varga (NRC), "Quality Assurance Requirements Regarding Diesel Generator
Fuel Oil" (6) NRC letter, S. A. Varga (NRC) to J. A. Jones (CP&L), December 10, 1981, Incoming Document No. NLU-81-607.
(7) CP&L Letter, NO-92-1404, Charles R. Dietz (CP&L) to NRC, regarding Fuel Oil Sampling methodologies, May 15, 1992.
(8) NRC Inspection Report No. 50-261/92-32, December 28, 1992.
HBR 2 UPDATED FSAR 1.8.0-29 Revision No. 27 Regulatory Guide 1.144 AUDITING OF QUALITY ASSURANCE PROGRAMS FOR NUCLEAR POWER PLANTS Conformance with Regulatory Guide 1.144 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-30 Revision No. 27 Regulatory Guide 1.145 ATMOSPHERIC DISPERSION MODELS FOR POTENTIAL ACCIDENT CONSEQUENCE ASSESSMENTS OF NUCLEAR POWER PLANTS, (RE-ISSUE FEBRUARY, 1983 TO CORRECT
PAGE 1.145-7 IN REVISION 1, NOVEMBER 1982)
HBR-2 complies with the provisions of Regulatory Guide 1.145, February 1983, for the analysis of offsite meteorology conditions that support the Updated FSAR Chapter 15
Accident Analyses performed using the Alternative Source Term (AST) dose methodology
described in Regulatory Guide 1.183. Compliance with the specific details contained within this
Regulatory Guide is limited to the analyses as described in the applicable DEP licensing
submittals for AST implementation.
HBR 2 UPDATED FSAR 1.8.0-31 Revision No. 27 Regulatory Guide 1.146 QUALIFICATION OF QA PROGRAM AUDIT PERSONNEL FOR NUCLEAR POWER PLANTS Conformance with Regulatory Guide 1.146 is addressed in the description of the Quality
Assurance Program incorporated by reference in Chapter 17.
HBR 2 UPDATED FSAR 1.8.0-32 Revision No. 27 Regulatory Guide 1.155 STATION BLACKOUT
HBR2 complies with the intent of NRC Regulatory Guide 1.155. In developing the Station
Blackout (SBO) Coping Analysis (Document 8S19-P-101), the guidance of NUMARC 87-00
has been applied. The NUMARC 87-00 methodology has been utilized, with specific
exceptions in areas including: (1) evaluation of the effects of loss of ventilation, and (2)
evaluation of the containment isolation capability. The analytical method applied and the
results of these analyses are documented in SBO Coping Analysis 8S19-P-101.
HBR 2 UPDATED FSAR 1.8.0-33 Revision No. 27 Regulatory Guide 1.183 ALTERNATIVE RADIOLOGICAL SO URCE TERMS FOR EVALUATING DESIGN BASIS ACCIDENTS AT NUCLEAR POWER REACTORS, JULY 2000
HBR-2 complies with the provisions of Regulatory Guide 1.183, July 2000, for selected Updated
FSAR Chapter 15 Accident Analyses. Compliance with the specific details contained within this
Regulatory Guide is limited to the following bounding design basis accidents, as described in
the applicable DEP licensing submittals.
FSAR Section
References:
- 1. Common Dose Consequence Inputs for Alternative Source Term (AST) Analyses (UFSAR Section 15.0.12) 2. Main Steamline Break Event (UFSAR Section 15.1.5)
- 3. Reactor Coolant Pump Shaft Seizure (Locked Rotor) (UFSAR Section 15.3.2)
- 4. Withdrawal of a Single Full-Length RCCA (UFSAR Section 15.4.3.1)
- 5. Steam Generator Tube Rupture (UFSAR Section 15.6.3)
- 6. Design Basis Fuel Handling Accidents (UFSAR Section 15.7.4)
HBR 2 UPDATED FSAR 1.8.0-34 Revision No. 27 Regulatory Guide 4.15 QUALITY ASSURANCE FOR RADIOLOGICAL MONITORING PROGRAMS - EFFLUENT STREAMS AND THE ENVIRONMENT HBR 2 is not committed to Regulatory Guide 4.15. The guidance within Reg. Guide 4.15 was
used as a source of information to aid in developing and maintaining quality assurance for the
Radiological Environmental Monitoring Program. This program is implemented by procedures
as required by the Robinson Technical Specifications.