ML093641094
| ML093641094 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/30/2009 |
| From: | Ebasco Services |
| To: | Office of Nuclear Reactor Regulation, Power Authority of the State of New York |
| References | |
| Download: ML093641094 (298) | |
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S. POWER AUTHORITY- OF THE STATE' ' OF NEW YOIRK INDIAY POINT NO. 3' NUCLEAR: POWER PLANT, SYSTEMS tNTWERACTION; STUDY VOLUME Il Prepared for the PowerfAuthority of the State of New York by EBASCOV SERVICES, INCORPORATED, 1010.
POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT No. 3,NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY VOLUME II CONTENTS SECTION TITLE PAGE APPENDIX A AUXILIARY FEEDWATER SYSTEM (AFS) SYSTEMS INTERACTION STUDY. A-1.1I IntroductionA A- 1.2 Systems Interaction Study AES.-Boundary A-2 A-2. 1 Results on AFS of Interconnected A-3 Systems Interactions A-2.2 Results on AFS of Non-connected A- 9 Systems Interactions A-3.1I AFS Functional Description A-22 A-3 .2 AFS Operating Description A-26 A-4. .0 AFS Interaction Matrix/Documentation Sheets A-5. 0 AFS Non-connected Systems Interactions Study Photographs,
SYSTEMS INTERACTION STUDY APPENDIX A -AUXILIARY FEEDWATER SYSTEM (AFS) APPENDIX A-
1.1 INTRODUCTION
This chapter describes the work performed by Ebasco on the Indian Point No. I Nuclear Power Plant Auxiliary Feedwater System for systems interactions consistent with the criteria, methodology and guidelines presented in the Chapters 3 thru 6 of Volume I. Interconnected process coupled, and nonconnected spatially coupled systems interactions were investigated-and the results presented inSections A-2.1 and A-2.2 respectively.-
APPENDIX A APPENIX AAUXILIARY FEEDWATER SYSTEM - .(AFS) (Cont'd) APPENDIX A-1.2 SYSTEM BOUNDARY CONDITIONS The Indian Point No. 3 Nuclear Power Plant Auxiliary Feedwater System was reviewed for systems interactions based on current unit installations with credit taken for specific commitments to the NRC regarding hardware and procedural modifications. The boundary of tne systems interaction study for the Indian Point No.. 3 Nuclear Power Plant, Auxiliary Feedwater System is shown in Figure A-6.- The turbine steam supply from the steam generators and all of. the Auxiliary Feedwater System components (see Table A-I) are included in the-study. -The water supplies to the extent of the piping-systems and valves that deliver water to-the Auxiliary Feedwater System are included. Electrical, power'and control supplies are included to the extent presented in Figure A-l for three electrical states, full1 power, -loss of one bus, and no AC electric power (onsite or offaite). This evaluation is conducted assuming the presence of an AFS, actuation signal, therefore the AFS actuation signal is outside the boundary of this study. As discussed in Chapter 5, latent and dynamic operator (Human) induced failures are also outside the boundary of this study. Consistent with this, the effects of control system failures on operator actions, i.e., those failures which deprive the operator of required information for normally controlling plant conditions,, or which provide confusing or incorrect information to the operator, have been specifically omitted from this study. The effects of non-safety-grade control system failures on plant safety is excluded from this study. Justification for this exclusion is provided in the Authiority's response to IE Information Notice .79-22, via iPN-79-74, dated October 9, 1979.
POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT
SUMMARY
OF COMPONENT TYPES TO BE REVIEWED FOR SYSTEMS INTERACTIONS TABLE A-I INSTRUMENTAT ION HETN, VENTIALTING ALL MECHANICAL ELECTRICAL &CONTROL & AIR CONDITIONING OTHERS PUMP MOTORS TRANSMITTERS FA NS
- 1) CENTRIFUGAL CABLES SWITCHES (PROCESS VARIABLE) COOLERS
- 2) RECIPROCATING CONDUITS & TRAYS POSITION OR LIMIT SWITCHES DUCTWORK VALVE BATTERIES & CHARGERS PNEUMATIC CONTROLERS LO UVERS
- 1) Air Operated DIESEL GENERATOR PNEUMATIC CONTROL VALVES CHILLERS
- 2) Motor Operated MOTOR CONTROL CENTER & SWITCHGEAR PNEUMATIC SOLENOIDS
- 3) Hydraulic Operator CIRCUIT BREAKERS & CONTACTS PNEUMATIC/ELECTRICAL CONVERTERS
- 4) Check SWITCHES LOCAL INDICATORS
- 5) Manual INVERTERS LOCAL CONTROL SWITCHES
- 6) Safety/Relief MOTOR OPERATORS FOR VALVES INSTRUMENT RACKS
- 7) Solenoid INSTRUMENT SENSING LINES FLOW ORIFICE INSTRUMENT AIR LINES & SPECIALTIES RESTRICTION ORIFICE STEAM TURBINE COMPRESSORS PIPING GAS STORAGE TANKS TANKS (FLUID)
SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM COM4PONENT POWER SUPPLY
SUMMARY
(REF 1 TABLE A-3 Primary Backup Component Power'Supply, source Source( 5 ) Function A. STEAM SUPPLY TRAIN PCV-1139 (20-1/ABFP2) (1) 125 Volt DC Pnl. 31 Battery 31 Bus Stm. Supply to Aux. Blr. Fd. Pump 32 Turbine (N.C.) PCV-1139 (20-2/ABFP2) (2) 125 Volt DC Pnl. 31 Battery 31 Bus Stm. Supply to Aux. Blr. Fd. Pump 32 Turbine (N.C.) PCV-1310A (SOV-1310)( 1 ) 125 Volt DC Pnl. 33 Battery 31 Bus Stm. Supply Isolation Valve to Aux. BFP 32 Turbine (N.O.) PCV-1310B (SOV-1311) (1) 125 Volt DC Pnl. 34 Battery 32 Bus Stm. Supply Isolation Valve to Aux. BFP 32 Turbine (N.O.) B. TURBINE PUMP 32 TRAIN Aux. Bir. Fd. Pump 32 Steam Driven Residual Heat Generated Steam CT-1O Hand Operated Valve on pump 32 Suction Heater from Condensate Storage Tank (L.O.) PCV-1188 (SOV-1288) (3) 120 Volt AC Instrument Bus 31 Battery 31 Bus 3A Valve on alt. path from City Wtr. Sys. for Aux. Fdwtr. Pump 32 Suction (N.C.) PCV-405A (1) 120 Volt AC Instrument Battery Bus Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 31 (N.C.) PCV-405B (1) 120 Volt AC Instrument Battery Bus Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 32 (N.C.) PCV-4050 (1) 120 Volt AC Instrument Battery Bus Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 23 (N.C.) PCV-4050 (1) 120 Volt AC Instrument Battery Bus Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 24 (N.C.) C. MOTOR-DRIVEN PUMP 31 TRAIN Aux. Blr. Fd. Pump 31 480 Bolt Bus-3A Bus 3A Dsl. 31 CT-27 Hand Operated Valve on Pump 31 Suction Header from Condensate Storage Tank (L.O.) PCV-1087 (SOV -1287) (3) 120 Volt AC Instrument Bus 33 Battery 33 Dsl1. 31 Valve on Alt. Path from City Wtr Sys. for Aux. Fd. Pump 31 Suction (N.C.) PCV-406A (1) 120 Volt AC Instrument Bus 33 Battery 33 Dsl. 31 Aux. Blr. Fd. Pump 31 Discharge to Stm. Gen. 31 (N.O.) PCV-4068 (1) 120 Volt AC Instrument Bus 33 Battery 33 Del. 31 Aux. Blr. Fd. Pump 31 Discharge to Stm. Gen. 32 (N.O.) (1) Valve Fails Open on Loss of Air or Electric Power. (N.C.) Normally Closed (2) Valve Fails Open on Loss of Air and cannot be Closed Without Electric Power. (N.0.) Normall'y Open (3) Valve Fails Closed on Loss of Air or Electric Power (L.O.) Locked Open ()AC Instrument Buses are powered off of corresponding DC panel. (5) Transfer from Batteries to Bus 3A is manual. Backup to.Bus 3A'Diesel 31..
SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM COMPONENT POWER SUPPLY
SUMMARY
(REF 1) TABLE A-3 (Cont'd) Primary Backup Component Power Supply Source'4 Source~~ Function D. MOTOR-DRIVEN PUMP 33 TRAIN Aux! Bir. Fd. Pump 33 480 Volt Bus 6A Bus 6A Dsel. CT-33 Hand Operated Valve on Pump 33 Suction Header from Condensate Storage Tank (L.O.) PCV-1189 (SQV-1289) 1(3) 120 Volt AC Instrument Bus 32 Battery 32 Dsl. 32 Valve on Alt. path from City Water Sys. for Aux. Fd. Pump 33 Suction (NIC.) PCV-406C(1 120 Volt AC Instrument Bus 32 Battery 32 Dsl. 32 Aux. Blr. Fd. Pump 33 Discharge to Stm. Gen. 33 (N.O.) PCV-406D(1 120 Volt AC instrument Bus 32 Battery 32 Dal. 32 Aux. Blr. Fd. Pump 33 Discharge to Stm. Gen. 34 (N..O.) E. MISCELLANEOUS LCV-1158 (SOV-1258) :(3) 125 Volt DC Dist. Pnl. 31 Battery 31 Dsl. 32 Condensate Storae Tan low-level shutoff valve (N.O.) Storage Tank CT-6(4 Hand Operated Condensate discharge valve (L.0.) Storage Tani discharge valve (L..O.) CT-64 (4) Hand Operated Condensate Valve Fails Open on Loss of Air or Electric Power. (N.C.) Normally Closed Valve Fails Open on Loss of Air and cannot be Closed Without Electric Power. (N.o.) Normally Open Valve Fails Closed on Loss of Air or Electric Power (L.0. ) Locked Open, AC Instrument Buses are powered off of corresponding DC panel. Transfer from Batteries to Bus 3A is manual. Backup to Bus 3A Diesel 31.
APPENDIX A APPENIX AUXILIARY A FEEDWATER SYSTEM (Cont'd) APPENDIX A-2.1 Results on AFS of Interconnected Systems Interactions (Cont'd) Vent and drain lines and valves, and connected lines which are small in size were not evaluated since it was assessed that failure of these co mponents would not significantly affect the system performance. Other events that require operation of the Auxiliary Feedwater System are:
- Loss of main feedwater transient
- Loss of main feedwater with offsite power available
- Station b~lackout (loss of main feedwater without offsite power available)
- Rupture of a main steam line
- Loss of all AG Power
- Loss of coolant accident
APPENDIX A APPENIX AUXILIARY A FEEDWATER SYSTEM (Cont'd) APPENDIX A-2.1.1
SUMMARY
AND CONCLUSIONS For the case presented, the acceptance criteria for evaluating component failures of the Auxiliary Feedwater System were as follows: I - A flow rate of 400 gpm be delivered to at least two (2) steam generators (200 gpm to each) 2 -The flow is delivered within 30 minutes of the initial demand.' Random component failures are categorized as recoverable or nonrecoverable. A recoverable random failure is defined as a failure that does not cause a system failure since the operator is assumed to have sufficient time to take successful action to recover from the failure. Recoverable failures are those that can be corrected before a specified time criteria is exceeded.. Nonrecoverable random failures are failures that cause a sy stem failure due to the inability of the operator to recover from the failure because of a time criteria. The results presented in this section as described in Table A-2.1 show that the Auxiliary Feedwater System emergency operating mode for the loss of normal feedwater event resulting from a feedline break outside containment coincident with a loss of all offsite power is reliable. Component redundancy and recoverability of component failures made the system sound. These results are consistent with the PRA findings of the Pickard, Lowe and Garrick, Inc. Study.
SYSTEMS INTERACTION STUDY APPENDIX A -AUXILIARY FEEDWATER SYSTEM APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions APPENDIX A-2.2.1 Systems Interactions Induced by the Effects of a Safe Shutdown Earthquake (SSE) GENERAL DISCUSSION General Design Criterior 2, "Design Bases for Protection Against Natural Phenomena", of Appendix A to 10CFR Part 50, "General Design Criteria for Nuclear.Power Plants", require that structures, systems, and components important to safety be desi gned to withstand the effects of earthquakes without loss of capability to perform their intended safety functions. NRC Regulatory Guide 1.29, "Seismic Design Classification",'(formerly Safety Guide 29) describes an acceptable method of identifying and classifying those plant features that should be designed to withstand the effects of the SSE. Regulatory position C.1.g. of NRC 1.29 states that the Auxilary Feedwater System including components, supports and foundations shall be designated as Seismic Category I and should be designed to withstand the effects of the SSE and remain functional. In addition, regulatory position C.2 of NR.C RG 1.29 states tnat those portions of structures, systems, or components whose continued function is not required but those failure could reduce the functioning of any plant feature designated Seismic Category I, to an unacceptable safety level should be designed and constructed so that the SSE would not cause such failure. Based upon the above, a review of the seismic design classification of the structures, systems and components associated with the-safe operation of the Auxiliary Feedwater System was conducted. In addition a plant walkdown of the auxiliary feed pump building and associated structures was conducted to review the effects of nonseismic structures,'systems and components whose failure during an SSE could reduce the functionability of any plant features important to safety to an unacceptable level.
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cont 'd) APPENDIX A-2.2..1 Systems Interactions Induced by the Effects of a Safe Shutdown Earthquake (SSE) (Cont'd) GENERAL DISCUSSION (Cont'd) The plant walkdown activities were consistent with the methodology guidelines and evaluatioon criteria described in Chapters 5 and 6.
SUMMARY
AND CONCLUSION In general due to the lack of documentation, it was impossible to complete a comprehensive review of the seismic design classification. In those instances where documentation existed an appropriate reference was included. Structures, systems and components that were not substantiated by seismic documentation consistent with the quality assurance requirements of Appendix B to IOCFR Part 50 were assumed to be nonseismic and were evaluated with respect to their effects on other Seismic Category I items. Acceptable and unacceptable system interactions resulting from the failure of nonseismic structures, systems or components are presented in Appendix A-4. From a review of the results of the seismic system interactions, the following items are considered to be the major contributors to the identification of adverse systems interactions3 I - Crane/monorail structure located directly above the two (2) motor driven and the turbine driven auxiliary feedwater pumps. 2 - 4' nonseismic floor drain pipe directly above the electrical cable trays containing-essential safety rela ted equipment. A- 10
APPENDIX A-2.2 .Results on the AFS of Nonconnected Systems Interactions (Cont'd) APPENDIX A-2..2.1 Systems Interactions Induced by the Effects of a Safe Shutdown Earthquake (SSE) (Cont'd)
SUMMARY
AND CONCLUSION (Cont'd) 3 -Space heaters and electrical lighting fixtures located directly above essential safety related equipment and structures. 4 -Nonseismic electrical cable trays and conduit routed directly above essential safety related equipmenmt and structures. 5 -Large nonseismic instrument rocks located within close proximity to essential safety related equipment and structures. 6 -Large roll-up door located in the shieldwall whose structural failure could affect the flow control stations of the turbine driven auxiliary feedwater pumps. Modifications including the possible use of guard structures, protective covers, and restraining devices are expected to prevent impairment of function due to the above concerns. A-i 1
SYSTEMS INTERACTION STUDY APPENDIX A AUXILIARY FEEDWATER SYSTEM APPENDIX A-2.2 Results on the APS of Nonconnected Systems Interactions. (Cant 'd) APPENDIX A-2.2.2 Pipe Failure Induced Systems Interactions The Auxiliary Feedwater System was reviewed for potential systems interactions resulting from high energy line breaks. The Indian Point No. 3, Nuclear Power Plant, Safety Evaluation Report, Docket No. 50-286,*dated September 21, 1973, Chapter.6 entitled Engineered Safety Features was used as the base document for pipe failure induced systems interactions*. Several modifications have been made to this system in order to give it additional protection in the unlikely event of high energy line breaks outside the containment. The auxiliary feedwater lines are directly connected into the feedwater system and experience the same pressure as the feedwater system. The Staff had a concern that a break in an auxiliary feedwater line within the room that houses the motor-driven and the steam turbine-driven auxiliary feedwater pumps might result in back flow from the feedwater system and could possibly flood these three pumps. Because of this concern, check valves were installed in the piping that connects the discharge side of these pumps with the normal feedwater system. These check valves are located outside of the auxiliary feedwater pump room and prevent backf low from the feedwater system into the Auxiliary Feedwater System. Another modification made was additional protection of the electric motor-driven auxiliary feedwater pumps from a high temperature-high humidity environment. A postulated high-energy pipe break in the steam supply to the steam turbine-driven auxiliary feedwater pump might result in temperature and humidity conditions in the pump room for which the electric motor-driven pumps A- 12
APPENDIX A-2.2 Results on th~e AFS of Nonconnected Systems Interactions (Cont 'd) APPENDIX A-2.2.2 Pipe Failure Induced Systems Interactions (Cont'd) were untested. These motor-driven pumps are "drip-proof," but their operability at elevated temperatures and in a steam environment was not demonstrated. Consequently, two redundant valves in the steam supply line to the auxiliary feedwater turbine-d'ven pump were installed. These valves are outside of the room that houses the auxiliary feedwater pumps. Each valve is signaled to close automatically on high temperature in the pump room. Each valve has its own separate temperature sensor. There is control room indication of each valve's position, and an alarm will-sound upon closure. operation of these valves would limit the temperature and humidity rise in th pump room due to a break in the steam supply to the steam turbine auxiliary feedwater pump. The consequences of pipe ruptures in the vicinity of the auxiliary feedwater pumps which might cause flooding in the pump room were also examined. The drainage capabilities of the pump room were modified to prevent water levels from reaching a depth of 14 in. off the floor from such postulated break. At the 14 in. level, water would begin to touch the bottom of the electric motor-driven auxiliary feedwater pumps. Pipe restraints on feedwater lines-in the room above the auxiliary-feedwater room were also installed. This was done to eliminate any concrete from the pump room roof falling onto the pumps as a result of whipping of the pipes after a postulated pipe rupture. The Staff reviewed these modifications and found them acceptable. In view of thie design modifications that have been made to limit the consequences of pipe whip, flooding, and temperature and pressure transien ts in the pump room, and in view of the design criteria that were in effect at the time of the construction permit, it was concluded that the design of the Auxiliary Feedwater System, as modified, does not lead to any unacceptable systems interactions. A- 13
SYSTEMS INTERACTION STUDY APPENDIX A AUXILIARY FEEDWATER SYSTEM APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cant 'd) APPENDIX A-2.2.3 Systems Interactions Induced by the Effects of Internally and Externally Generated Missiles General Design Criterion 4, "Environmental and Missile Design Bases", requires that all structures, systems and components that are necessary for attaining and maintaining a safe shutdown of the reactor facility and whose failure could result in a significant release of radioactivity, be designed to withstand the effects of internally and externally generated missiles. Internally generated missiles are components of pressurized systems such as .valve bonnets and hardware retaining bolts, relief valve parts, and instrument wells: high speed rotati g machinery, such as impellers and fan blades i-esulting from component overspeed or failure (resulting from seisure) which are within a structure protecting systems and components necessary for safe shutdown. Externally generated missiles are missiles generated by natural phenomena such as tornado and those components of pressurized systems and high speed rotating machinery located outside structures protecting systems and components necessary for safe plant shutdown.. A- 14
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cont 'd) APPENDIX A-2.2.3 Systems Interactions Induced by the Effects of Internally and Externally Generated Missiles (Cont'd) A-2.2.3.1 Internally Generated Missile System Interactions During the walkdown phase of the system interaction study, an observation was made relative to the potential for the generation of-internal missiles-from pressurized systems and high speed rotating machinery and the effects on safe shutdown capabilities. It was observed that adequate separation and system redundancy existed so as to preclude damaging effects from internally generated missiles such as valve bonnents and nardware retaining bolts, relief valve parts and instrument wells. In addition it was observed that high energy lines were provided with pipe whip restraints so as to prevent impact on safety related systems and components. The auxiliary feedwater pumps located within the auxiliary feedpump building were evaluated for missiles assoicated with overspeed failure. The motor driven auxiliary feedwater pumps maximum no-load speed was assumed to be the synchronus speed of the motor which is no more than 2 percent above the rated operating speed. Consequently, no pipe break or single failure in the suction or discharge lines of the pump would increase the pump speed over that of the no-load condition. Therefore, the generation of missiles associated with the motor driven ,pumps is not a credible occurance. However, an evaluation of the turbine driven auxiliary feedwater pump showed that missiles could be generated due to turbine overspeed protection failure, and that several safety related systems and components in the auxiliary feed pump building were potential targets. A- 15
APPENDIX A-2.2 Results on the APS of Nonconnected Systems Interactions (Cont 'd) APPENDIX A-2.2.3 Systems Interactions Induced by the Effects of Internally and Externally Generated Missiles (Cont'd) A-2.2.3.1 Internally Generated Missile System Interactions (Cont'd) In November 1971, the NRC informed the Power Authority of the State of New York (PASNY) of the NRC's requirements for the Auxiliary Feedwater system at the Indian Point No. 3 Nuclear Power Plant. Among the long-term recommendations was the requirment to evaluate the potential for the generation of internal missiles in the Auxiliary Feedwater Pump Room and its effect on vital equipment and systems. On July 15, 1980 the NRC issued, Interim Safety Evaluations of the auxiliary feedwater system. One of the open items in these reports was the stipulation that the "Licensee provide a description of the results of the (missile generation) evaluation prior to, August 11, 1980 and prior to implementation of any corrective measures."1 PASNY contracted EDS Nuclear Inc to evaluate the capability of the auxiliary feedwater system to withstand internally generated missiles. The evaluation has determined that the auxiliary feedwater pump turbine could be a source of a destructive missile and therefore, an analysis of auxiliary feedwater pump turbine missiles was undertaken. The evaluation showed that missiles could be generated and that several safety related systems at different locations in the auxiliary feed pump building were potential targets. Because of these results, it was decided that protection at the missile source was the best approach. A-1 6
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cant 'd) APPENDIX A-2.2'.3 Systems Interactions Induced by the Effects of Internally and Externally Generated Missiles (Cont'd) A-2.2.3.1 Internally Generated Missile System Interactions (Cont'd) From a systems interaction point of view, protection at the source designed for destructive overspeed missiles is an acceptable solution. This ensures that safe shutdown equipment will not interact with a missile source as a result of disk failure at any possible speed. Although the missile shield has not yet been installed it was assumed that near term modifications will be made. Therefore, based upon the commitment to install a missile shield system no credible interaction of a missile source with safety related targe' equipment located in the auxiliary feed pump building were found. A-2.2.3.2 Externally Generated Missile System Interactions A review of the Indian Point 3 Facility Safety Analysis Report, Chapter 3.5 and the NRC (then AEC) Safety Evaluation Report, dated September 21, 1973 was conducted to determine if the structures systems and components associated with the auxiliary feedwater system were protected against the effects of externally generated missiles. A review of this type was conducted in order to preclude the evaluation of systems interactions resulting from externally generated missiles. Our review concluded that various structures at the Indian Point 3 site have been designed and constructed to withstand the effects of tornado generated missiles. Among these structures are the primary auxiliary building, the control room, the containment building, the diesel generator building, the cable tunnels, and the waste hold-up tank pit. The shield wall of the auxiliary feedwater pump building has been designed considering the effects of externally generated missiles. A-17
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cant 'd) APPENDIX A-2.2.4 Systems Interactions Induced by the Effects of Flooding Design Criterion 2, 'Design Bases for Protection Against Natural Phenomena"1 require that all systems and components whose failure could prevent safe shutdown of the plant or result in uncontrolled release of si gnificant radioactivity, be designed to withstand the effects of flooding due to natural phenomena. A review of the Indian Point 3 Facility Safety Analysis Report, and the NRC (then AEC) Safety Evaluation Report, was conducted to determine to what extent the structures, systems and components associated with-the Auxiliary Feedwater System were protected against the effects of flooding due to natural phenomena. Our review concluded that it was established that the most severe flooding condition at the site, corresponds to a water elevat ion of 15,ft above mean sea level (MSL). As stated in the Facility SER, this elevation is lower by three inches than the critical elevation at which water would start seeping into the lowest of the plant buildings. The staff concluded in their report that under the most extreme conditions the flood level could reach a level of 15.0 ft MSL, exclusive of wind-generated wave action. Wind-generated wave action could raise the flooding level above plant grade in the vicinity of the service water pumps. In the event of wind-generated wave action in conjunction with extreme flooding conditions, the plant will still be protected. In this unlikely event, the plant will be shutdown in accordance with the Techincal Specifications, and the service water pump areas will be protected. Other areas, such as the diesel generator area, will not require additional protection from the wind-generated waves in that these waves rapidly dissipate once they strike land. A- 18
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cont'd) APPENDIX A-2.2.4 Systems Interactions Induced by the Effects of Flooding (Cont'd) Consequently, the combination of the elevation of thie plant structures, and the Technical Specification requirements on plant operation and service water pump protection, result in accetable conditions to protect the plant against flooding. Based upon our review and the findings above, we concluded that no credible flooding conditions caused by natural phenomena will exist and therefore, no adverse system interactions were identified for the structures, systems and components of the Auxiliary Feedwater System. A- 19
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems-Interactions (Cont 'd) APPENDIX A-2..2.5 System Interactions Induced by Severe Environment (Other Than Flooding) Resulting From Natural Phenomena. General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena", require that all systems, components and structures whose failure could prevent safe shutdovwn of the plant or result in uncontrolled release of significant radioactivity, be designed to withstand the resulting effects of severe environment due to natural phenomena. A review of the Indian Point 3 Facility Safety Analysis Report, and the NRC (then AEC) Safety Evaluation Report, was conducted to determine to what extent the structures, systems and components associated with the Auxiliary Feedwater System were protected against the effects of severe environment due to natural phenomena. Our review concluded that the effects of tornado wind loadings and depressurization was considered in the design of all Category I structures. The auxiliary feed pump building is designated as a Category I structure. Therefore, no adverse system interactions were identified for the structures, systems and components of the Auxiliary Feedwater System contained within the auxiliary feed pump building. A-20
APPENDIX A-2.2 Results on the AFS of Nonconnected Systems Interactions (Cant 'd) APPENDIX A-2.2.6 Systems Interactions Induced by Fires The Commission's basis criterion for fire protection is setforth in General Design Criterion 3, Appendix A to 1OCRF Part 50, which states: I - "Structures, systems, and componets importan-t to safety shall be designed and located to minimize, consistent with other safety requirements, the probability and effect of fires and explosions." 2 -"Noncombustible and heat resistant materials shall be used wherever pratical throughout the unit, particularly in locations such as the containment and the control room." 3 -"Fire detection and protection systems of appropriate capacity and capability shall be provided and designed to minimize the adverse effects of fires on structures, systems, and components important to safety." 4 -"Fire fighting systems shall be designed to assure that their rupture or inadvertent operation does not significantly impair the safety capability of these structures, systems, and components." The Indian Point No. 3 Fire Protection Program Report, Revision 1, dated AD-'.1 1977 was reviewed to determine to what extent the structures, systems and components associated with the Auxiliary Feedwater System were protected against the effects of fires. It was concluded in the report that the results of the fire hazards evaluation had shown that there are no areas in the plant where a design basis fire would cause the loss of the primary as well as the redundant shutdown system. Therefore, no adverse system interactions were identified due to fire induced failures of systems, components and structures of the Auxiliary Feedwater System. A-21
SYSTEMS INTERACTION STUDY APPENDIX A - AUXILIARY FEEDWATER SYSTEM APPENDIX A-3.0 Auxiliary Feedwater System Description APPENDIX A-3.1 System Functional Description (1) Tne Auxiliary Feedwater System serves as a backup system for supplying feedwater to the secondary side of the steam generators at times when the feedwater system is not available, thereby maintaining the heat sink capabilities of the steam generator. The Auxiliary Feedwater System is an Engineered Safeguards System, and is directly relied upon to prevent core damage and primary system overpressurization in the event of transients such as a loss of normal feedwater or a secondary system pipe rupture, and to provide a means for plant cooldown following any plant transient. Following a reactor trip, decay heat is dissipated by evaporating water in the steam generators and venting the generated steam either to the condensers through the steam dump or to the atmosphere through the steam generator safety valves or the power-operated relief valves. Steam generator water inventory must be maintained at a level sufficient to ensure adequate heat transfer and continuation of the decay heat removal process. The water level is maintained under these circumstances by the Auxiliary Feedwater System which delivers an emergency water supply to the steam generators. The Auxiliary Feedwater System is capable of functioning for extended periods, allowing time either to restore normal feedwater flow or to proceed with an orderly cooldown of the plant to the reactor coolant temperature where the Residual Heat Removal System can assume the burden of decay heat removal. The Auxiliary Feedwater System flow and the emergency water supply capacity must be sufficient to remove core decay heat, reactor coolant pump heat, and sensible heat during the plant cooldown. A-22
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.1 System Functional Description (Cont'd) DESIGN CONDITIONS The reactor plant conditions which impose safety-r 1 ted performance requirements on the design of the Auxiliary Feedwater System are as follows for Indian Point Unit No. 3 Nuclear Power Plant.
- Loss of main feedwater transient
- Station blackout (i.e., loss of main feedwater without offsite power available)
- Rupture of a Main Steam Line
- Loss of all AC Power
- Loss of Coolant Accident (LOCA)*
- Cooldown Loss of Main Feedwater Transients The design loss of main feedwater transients are those caused by:
- Interruptions of the Main Feedwater System flow due to malfunction in the feedwater or condensate system
- Loss of offsite power or blackout with the consequential shutdown of the main feedwater system pumps, auxiliaries, and controls Loss of main feedwater transients are characterized by a rapid reduction in steam generator water levels which results in a reactor trip, a turbine trip, and auxiliary feedwater actuation by the protection system logic.. Following reactor trip from high power, the power quickly falls to decay heat levels.
A-23
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.1 System Functional Description (Cont'd) DESIGN CONDITIONS (Cont'd)' Loss of Main Feedwater Transients (Cont'd) The water levels continue to decrease, progressively uncovering the steam generator tubes as decay beat is transferred and discharged in the form of steam either through the steam dump valves to the condenser or through the steam generator safety or power-o era ed relief valves to the atmosphere. The .reactor coolant temperature increases as the residual heat in excess of that dissipated tnrough the steam generators is absorbed. With increased temperature, the volume of reactor coolant expands and begins filling the pressurizer. Without the addition of sufficient auxiliary feedwater, further expansion will result in water being discharged through the pressurizer safety and relief valves. If the temperature rise and the resulting volumetric expansion of the primary coolant are permitted to continue, then (1) pressurizer safety valve capacities may be exceeded causing over-pressurization of the Reactor Coolant System and/or (2) the continuing loss of fluid from the primary coolant system may result in bulk boiling in the Reactor Coolant System and eventually in core uncovering, loss of natural circulation, and core damage. If such a situation were ever to occur, the Emergency Core Cooling System would be ineffectual because the primary coolant system pressure exceeds the shutoff head of the safety injection pumps, the nitrogen over-pressure in the accumulator tanks, and the design pressure of the Residual Heat Removal Loop. Hence, the timely introduction of sufficient auxil iary feedwater is necessary to arrest the decrease in the steam generator water levels, to reverse the rise in reactor coolant temperature, to prev'it the pressurizer from filling to a water solid condition, and eventually to establish stable hot standby con ditions. Subsequently, a decision may be made A-24
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.l System Functional Description (Cont'd) DESIGN CONDITIONS (Cont'd) Loss of Main Feedwater Transients (Cont'd) to proceed with plant cooldown if the problem cannot be satisfactorily corrected. The blacKout transient differs from a simple loss of main feedwater in-that emergency power sources must be relied upon to operate vital equipment. The loss of power to the electric driven condenser circulating water pumps results in a loss of condenser vacuum and condenser dump valves. Hence, steam formed by decay heat is relieved through the steam generator safety valves or the power-operated relief valves. The calculated transient is similar for both the loss of main feedwater and the blackout, except that reactor coolant pump heat input is not a consideration in the blackout transient following loss of power to the reactor coolant pump bus. The station blackout transient serves as the basis for the minimum flow (400 gpm) required for Indian Point No. 3 Nuclear Power Plant. The system is designed so. that a minimum of 400 gpm is provided against the steam generator safety valve set pressure (with 3% accumulation) to prevent water relief from the pressurizer. This is accomplished, even considering the effect of the turbine driven pump throttling with an assumed single failure. A-2 5
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Op erating Description (2) Auxiliary Feedwater Flow Path The Auxiliary Feedwater System consists of two subsystems. One system utilizes a steam turbine-driven pump, with the steam capable of being supplied from No. 32 and No. 33 steam generators upstream of the isolation valves. A pressure reducing control valve reduces the pressure to the 600 psi design value of the turbine. This system is capable of supplying a total of 800 gpm to all four steam generators. The other system utilizes two motor-driven pumps each with a capacity of 400 gpm. -Tne discharge piping is arranged so that each pump supplies two steam generators (see Figure A-2). Water Supplies Water-supplies to the Auxiliary Feedwater System is redundant. The normal source is by gravity feed from the condensate storage .tank which is sized to meet the normal operating and maintenance needs of the turbine cycle. Each auxiliary feedwater pump takes suction on the header through a check and, normally open stop valve. Individual flow .elements are provided on the suction to each of the two motor driven pum s (No. 31 and No. 33). Pump suction pressure is indicated in the control room by PI-1263-R, PI-1264-R and PI-1265-R for each pump. Availability of water from this source is guaranteed by LCV-1158 which closes when the quantity of water in the condensate storage tank drops to 360,000 gallons. When LCV-1158 closes, make-up to the main condensers is prevented and a sufficient quantity of water is assured to be available to remove the residual heat generated by the reactor for 24 hours at hot shutdown condition. A-26
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Water Supplies (Cont'd) An alternate supply of water for the pumps is provided for emergency backup and long-term cooling from-the city water system. Each pump is supplied from a header tftrough a check and control valve which is normally closed. This valve is controlled by a switch located in the control room which will operate the solenoid, applying or removing air from the valve. Valve position is indicated in the control-room. Discharge Routing Discharge from the pumps is routed to the steam generators. Steam.generators No. 31 and No. 32 are supplied by No. 31 and No. 32 auxiliary boiler feed pumps. Steam generators No. 33 and No. 34 are supplied by No..32 and No. 33 feed pumps. Each feedwater line is provided with a flow control valve for feedwater regulation. A common flow transmitter for each steam generator is used to indicate flow in the control room from the motor driven or turbine driven flow. paths. Pump discharge pressure is provided both locally and in the control room. Recirculation lines, which are provided for pump protection are routed back to the condensate storage tank. Motor Driven Auxiliary Feedwater Pumps The motor driven pumps are Ingersoll-Rand Company No. 3HMTA, nine stage, horizontal split case centrifugal units, each of which supplies 400 gpm of water at a head of 1350 psi. The motor drives are furnished by Westinghouse Electric Corporation. A-2 7
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Motor Driven Auxiliary Feedwater Pumps (Cont'd)
- a. Motor Driven Pump Control Auxiliary feed pumps No. 31 and No. 33 are driven by motors supplied from 480V buses 3A and 6A respectively. Control switches exist both locally and in the"control room on the Condensate and Feedwater Supervisory Panel. The local switches allow "Start and Stop" pushbutton operation of the pumps. The switches in the control room have three positions "On-Auto-Trip". Thie following conditions will automatically start the pumps as described.
- Automatic loss of either main boiler feed pump will start both No. -31 and No. 33.
- Low-Low steam generator level in any steam generator will start both No. 31 and No. 33.
- In the event of a unit trip which is initiated by a safety injection signal the following Auxiliary Feedwater System events will occur:
- 1) Actuates the turbine driven AFW pump.
- 2) The pumps will be provided with a start signal as the safeguards buses are reloaded.
A-28
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Motor Driven Auxiliary Feedwater PumDs (Cont'd)
- a. Motor Driven Pump Control (Cont'd)
- Loss of outside power without safety injection will provide both pumps with a start signal after the diesels have tied into the 480V buses. A time delay is associated with starting the pumps to allow for loading of the diesels.
Undervoltage on either bus 3A or 6A will trip the pump fed by the bus. The following indication and alarms are provided in the COR to monitor the pumps.
- Pump on-off-auto trip lights.
- Pump lock off alarm
- Pump auto trip alarm
- Pump on local control alarm Each motor driven pump is provided with a pressure sustaining control system to prevent the pump from "running out" on its curve. As the discharge presq re of the pump decreases below the set point of 1355, PT-406A for No. 31 pump and PT-406B f No. 33 pump will generate a signal that will override the signal from-tho flow controllers on the Condensate and Feedwater Supervisory Panel. -The signal will operate to close the valves until the pressure is restored in the discharge line hav :ng low pressure.
A-2 9
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Motor Driven Auxiliary Feedwater Pumns (Cont'd)
- b. Turbine Driven Auxiliary Feedwater Pump The full size turbine driven pump is a Worthington Corporation No. 4-WT-127, horizontal, multi-stage, centrifugal pump with a capacity of 800 gpm at 1350 psi.
Auxiliary Feedwater Turbine
- a. Turbine Description The turbine drive is a Worthington Corporation horizontal axial flow, non-condensing unit rated at 970 HP at 3570 RPM.
- b. Auxiliary Turbine SteamSupply Steam to drive the turbine is supplied from the main steam shut ff will close whenever the temperature in th Pump Room reaches 120 0 preset valve. These valves have' been added to protect motor driven pumps from being rendered inoperable in the unlikely event of the steam line rupturing within the building.
A-30
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Auxiliary Feedwater Turbine (Cont'd)
- b. Auxiliary Turbine Steam Supply (Cont'd)
During turbine operation the steam supply pressure is regulated by PCV-1139. This pressure control valve maintains a 600 psig steam pressure to the turbine. Pressure' controller 1176-S senses the downstream pressure and generates a signal for use by the positioner. The control signal generated by the positioner is then applied to the diaphragm of PCV-1139 through the start solenoids-(3 and 4). Pressure controller 1176-S will also alarm low pressure at 550 psig in the control room. once the pressure has been reduced the steam enters the, turbine steam chest which contains the governor and turbine trip valves. To remove moisture in the main steam supply, traps have been provided where necessary. The discharge from the traps have been routed to the main steam trap system which is directed to the drains provided on the turbine casing, steam chest and exhaust piping. The exhaust from the turbine is directed to the atmosphere.
- c. Auxiliary Turbine Cooling System The thrust bearing and turbine inboard and outboard bearings are cooled by water from the discharge of the pump.
A- 31
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Auxiliary Feedwater Turbine (Cont'd)
- c. Auxiliary Turbine Cooling System (Cont'd)
A pressure control valve PCV-1213 maintains the water supply to the bearing at 65 psig. The pressure control valve, receives its signal from PC-1213 downstream of the control valve. The return water from each bearing is tied-together and returned to the condensate storage tank. Flow through each bearing and the combined return temperature are indicated locally.
- d. Turbine Driven Pump Control The turbine driven pump is a variable speed device, and the two motor driven pumps are constant speed devices. The speed of thie turbine driven pump is governed by a remote pneumatic speed changer (HC-1118) that is located on the Condensate and Feedwater Supervisory Panel in the control room. The speed changeris designed to operate over an entire speed range of 0 to 100%.
Pressure Reducing Valve PCV-1113 4s used as the steam shutoff and start valve for the Auxiliary Feed Pump Turbine. The mode of operation of this valve is controlled by "Trip-Auto-On" switches; one located in the control room, and one in the Auxiliary Boiler Feed Pump Building. These switches control the position of f ur solenoid valves mounted on the air inlet A-3 2
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Auxiliary Feedwater Turbine (Cont'd)
- d. Turbine Driven Pump Control (Cont'd) to the valve actuator. These solenoid valves are in their de-energized state, which allows the positioner output to open the valve. Normally the valve is maintained in stand-by with the control switches in "Auto". In this position SOV's 1 and 3 are energized, this will cut off the positioner output (SOV-3 closed) and apply full instrument air pressure to the valve actuator (SOy-I open) holding the valve closed. The SOy's will be de-energized and the pump started by any of the following:
-7 Low-Low water level in any two of the four steam generators (15% of span).
- Loss of outside power (provided a S..I. signal DOES NOT exist).
- Positioning the control switch to "START".
The turbine governor valve is controlled by a governor and speed changer. The speed changer can be operated locally or
*from the control room by HC-1118 as shown. A trip valve has been provided to immediately shutdown the turbine on an overspeed of approximately 4516 R.P.M. Turbine speed is indicated in the control room.
A-3 3
APPENDIX A-3.0 AUXILIARY F1EEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Recirculation Flow Path and Control An automatic pump recirculation control system is provided on each motor driven pump to recirculate the pump discharge back to the condensate storage tank at low flow. A maintained contact "Close-Auto-Open" control switch and valve position indicating lights are located in the control room on the Condensate and Feedwater Supervisory Panel for each recirculation valve. A manual operator is provided on each valve for local operation.*.Suction flow is measured by flow switchs FC-1135-S, FC-1-135SA-S and FC-1136-S, FC-1135SB-S for pumps No. 31 and No. 32 respectively. "These swtiches are provided with contacts which are interlocked as follows:
- A decrease in flow to 100 gpm actuates a low flow annunciato in the CCR.
- A further decrease in flow to 50 gpm will de-energize solenoid valve SOV 1321 S0V1323 on control valves FCV 1121 and FCV 1123 in the recirculation lines to initiate recirculation flow back to the condensate storage tank and also energize a time-delay relay.
- The time delay interlock functions to trip the pump in the event that the flow does not increase to 100 gpm in a preset amount of time. If the flow returns to above 100 gpm in less than the preset time, the recirculation valve will close, and the trip timer is reset.
If the pump is tripped by the low flow timer, the timer circuit must be reset by selecting the pump to the trip position prior to restarting. This will A-34
APPE~NDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Recirculation Flow Path and Control (Cont'd) clear the trip circuit of the auxiliary feed pump circuit breaker and reset the common pump low flow alarm so that a low flow condition on the second. pump, if operating, will still be alarmed. Pump control switch manual trip action, or automatic electrical stripping action will automatically perform the above trip timer and low flow alarm reset function. Selecting the recirculation valve control switch to the "Open" or "Close" position will' defeat all automatic features (except the low flow alarm) and hold the valve in that position regardless of flow through the pump. If during the winter a prolonged shutdown of the turbine generator-is experienced a means has been provided to heat the condensate storage tank. Toe recirculation lines back to the condensate storage tank from the two motor driven pumps provides a source of both heat and flow in sufficient quantities. to protect the tank from freezing. When using the pumps in this manner the recirculation flow must be adjusted to provide a flow of 125 gpm for each pump, using the special high pressure drop valves BFD-77 and 78. The flow to the tank is extremely important in order to provide the maximum BTU input to the tank with the minimum hazard to the pumps. Only one pump is required to protect the tank from temperatures above 15 0F The turbine driven pump is provided with a continuous recirculation system back to the condensate storage tank. An additional feature provided on the turbine driven pump is that-part of recirculated water is used to cool the thrust bearing and turbine bearings. A-35
APPENDIX A-3.0 AUXILIARY FEEDWATER SYSTEM DESCRIPTION (Cont'd) APPENDIX A-3.2 System Operating Description (Cont'd) Auxiliary Feedpump Flow Con' 'ol As previously described, two auxiliary feed systems exist which are independent of each other. Flow control to the steam generators is provided by eight controllers located on the Condensate and Feedwater Supervisory Panel in the control room. There are two controllers associated with each-steam generator, one each for the feedwater supplies from the motor and turbine driven pumps. Which controller is used will be dependent..on the operating conditions of the unit. Flow indication is provided for each auxiliary 'feedwater line to each steam generator. The flow nozzle is located in the common terminal line from the steam driven and the motor driven pumps. The output from each of these transmitters is connected to flow indicators located on the Condensate and Feedwater Supervisory Panel and in the auxiliary feedwater-pump building. The steam generator wide range level recorders have also been located on this panel. Level in the steam-generator is maintained by positioning the flow controller. All pneumatic instruments associated with the auxiliar y pump flow controls are provided with nitrogen back-up. Three nitrogen bottles are located inside the auxiliary feed pump room which connect into the instrument air supply down stream of a check valve. A pressure regulator set at 50 psig will feed nitrogen into the instrument air supply system whenever the normal air supply pressure decreases below this setting. A pres sure switch (PC-1355-S) located at the bottles will annunciate in the control room to warn the operator whenever the bottles require changing. A-36
SYSTEMS INTERACTION STUDY APPENDIX A NOTES TO TABLE A-2.1 NOTE: (1) Failure mode(s) for each type of component listed on Table 6-1.are summarized as follows: A - Complete loss of function due to instantaneous loss of electrical power
- 1) Loss of one redundant electrical division comcident with loss of all offsite power
- 2) Loss of all AC power (onsite and offsite)
- 3) Loss of DC power
- 4) Other B -Complete loss of function due to instantaneous loss of power (other than electrical)
- 1) Loss of pneumatic power (plant air, compressed gas, etc)
- 2) Loss of hydraulic power
- 3) Other (explain where necessary)
C Partial loss of function due to instantaneous lbss of electrical power
- 1) Loss of one redundant electrical division comcident with loss of all offsite power
- 2) Loss of all AC power (onsiteand offsite)
- 3) r
- 4) Other D -Partial loss of function due to instantaneous loss of power (other than electrical)
- 1) Partial loss of pneumatic power (eg crimped air supply line)
- 2) Partial loss of hydraulic power
- 3) .Other (explain Where necessary)
E -Complete loss of function due to instantaneous mechanical failure(s)
- 1) plugged component
- 2) component normally open and does not close
- 3) component normally closed and does not open
- 4) component does not start, due to mechancial interference
- 5) other (explain where necessary)
A-3 7
SYSTEMS INTERACTION STUDY APPENDIX A NOTES TO TABLE A-2.1 (Cont'd) NOTE: (1) Failure mode(s) for each type of component listed on Table 6-1 are summarized as follows: (Cont'd) F -Partial loss of function due to instantaneous mechanical failure(s)
- 1) plugged component, partial
- 2) component normally open and does not close completely,
- 3) component normally closed and does not open completely
- 4) component does not reach full speed due to mechanical interference
- 5) other (explain were necessary)
G -Other failures not covered by A thru F. (describe where necessary) (2) It hias been assumed that the loss of function, either completely or partially of pressure transmitters, pressure controllers, pneumatic/electrical converters, etc associated with the instrumentation and control components of the auxiliary feedwater, system is less limiting than complete or partial -loss of controlled component, eg pressure or flow control valves. A-3 8
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.-k0, RA4;24 Ry-IIaz Soy- I z I 5z '-(2 KoIAFE F41WP toC APVIiVUJ M-71 E Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES & EFFECTS ANALYSIS SHEET 7 OF 9 FIGURE A-2.1
r I. I.
~oo~e~T FAILUR.E ooe(s') Me-kovOF.,
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~Ac- A0ou Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES & EFFECTS ANALYSIS SHEET 8 OF 9 FIGURE A-2.1
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A 15 C b'E 'F IQ Koo ID O PT- IZGO - OIT TO0- l~oL)C
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- TI-v-to-1-23 PC - 117(o - 4 K.- 55 KI O'E Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES & EFFECTS ANALYSIS SHEET 9 OF 9 FIGURE A-2.1
SYSTEMS INTERACTION STUDY APPENDIX A NOTES TO TABLE A-2.l NOTE: Jl) Failure mode~s) for each type of component listed on Table 6-1 are summarized as follows: A -Complete loss of function due to instantaneous loss of electrical power
- 1) Loss of one redundant'electrical division comcident with loss of all offsite power
- 2) Loss of all AC power '(onsite and offsite)
- 3) Loss of DC power
- 4) Other B -Complete loss of function due to instantaneous loss of power (other than electrical)
- 1) Loss of pneumatic power (.plant air, compressed gas, etc)
- 2) Loss of hydraulic power
- 3) Other (explain where 'necessary)
C -Partial loss of function due to instantaneous loss of electrical power
- 1) Loss of one redundant electrical division~comcident with loss of all offsite power
- 2) Loss of all AC power (onsite and offsite)
- 3) Loss of DC power
- 4) Other D -Partial loss of function due to instantaneous loss of power (other than electrical)
- 1) Partial loss of pneumatic power (eg crimped air supply line)
- 2) Partial loss of hydraulic power
- 3) Other (explain where necessary)
E -Complete loss of-function due to instantaneous mechanical failure',s)
- 1) plugged component
- 2) component normally open and does not close
- 3) component normally closed and does not open
- 4) component does not start due to mechancial interference
- 5) other (explain where necessary)
SYSTEMS INTERACTION STUDY APPENDIX A NOTES TO TABLE-A-2.l '(Cont'd) NOTE: (1) Failure mode(s) for each type of component listed on.Table 6-1 are summarized as follows: (,Cont'd) F -Partial loss of function due to instantaneous mechanical failure~s)
- 1) plugged component, partial
- 2) component normally dpen and does not close completely 3). component normally closed and does not open completely
- 4) component does not reach full speed due to mechanical interference
- 5) other ',explain were necessary)
G-Other failures not covered by A thru F. ',describe where necessary)
'2) It has been assumed that the loss of function, either completely or partially of pressure transmitters, pressure controllers, pneumatic/electrical converters, etc associated with the instrumentation and control components of the auxiliary feedwater system is less limiting than complete or partial loss of controlled component, eg pressure or flow control-valves.
FAILtIRE TO AFVVS DF.LIVnRAT 1.ASV 20 1OrM TO *AC" orrvWo s UAM OEEEATOPS loo cF SFAULTM TREE IG UREPAT2 .t
S0 9 P 7
-A 31 0 1 001 8 "32 1 2 002 C ~3 3 3 00 o 342 4 04 MAIN FERYWATEF1 LINE.CHECK VALVE.
e FAILS OPEN AND LEAKS TO MAIN FIFFOWATEII SHEET 2,OF 9 Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWER PLANT SYSTMIS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEMl
- FAULT TREES FIGURE A-2.2
FE RACIGSCTION SErDSHRG TO 1 AFW34 6- 6 5 46 ISLAIOCVLEC SOLATIO VALEA O CHECK VAVEVAVE0CT ~~FDPUqPLUGSARR R rFAFTELUS BRANHIN FAILS TOTANFR Otis 01100oo ISOLATIONSYTEM AVEARPRAE INTALCIO STUDYN
,4~ FAULT TALSTEESNSER FI UR AE6
S1V7ET 4 OF3 Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM FAULT TREES FIGURE A-2.2
3, 32 29 II2 cv "02 WATER NOT SUCTION to AFWPUMP* CONDENSATE WATE UNAVIJA~E tCITY WATER r A vPm#UNAVAILAL OABLEM Sr UINT UAVAILAMPL# SUJCTION CONDENSATE Nail WAER PRO CHECK VALVE CT.0 AIOPAE0 STORAGEIAN TANKYSAOEGE UANK FAILSIO OPEN AVFAL IC 10AW AVAIlABLE A t4 UAALBESrECIF $?OF VALVE STOP VALVE CT SPrLIEGSl C164 PIIGSI CIECK VALVE CF.4 p SOIATION VALVE TR44ESTRAINMERS PAILIS TO OPEN Cl. TTRANSF ENS ClA' COSE ' CLOSED PrtY Prt P 0006 1364 P13T G SHEET 5 OF 9 Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWAER PLA14T SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM
-FAULT TREES FIGURE A-2.2
I' a I Pcv.1187 1187 2 Pcv-l 189 1189 3 PCV-1188 me8 SHEET 6 OF ' Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWTER PLANT SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM
- FAULT TREES FIGURE A-2.2
NOWF FROM 717 0 TURBINE DRIVEN - - 4- 4-0 AFW PUMP 38 4- 481 4- 0A 5 SECTION TO SG a 2 32 48-2 48-3 47.1 401,8 6 Dy3 J3 48-4 48-5 47-2 405C 7 4 ~ 86 48-7 47-3 4050 9 CHECK VALVE BF]D-31 FW PTH FROM WATER NOT FAILUJREOF AT AFW PUMP .31 TO SG aAFTER AVAILA13LE AT AFWP 3Z. DISCHARGE FAILS BRANCHING IS AFWP 32 TO START TO OPEN UNAVAILABLE SUCTION PCV 11 0031 ISOLATION VALVE ISOLATION VALVE CHECK VALVE AIR OPERATED BF041 1 PLUGS OR OFO-112 PLUGS oR BFO-9FAILS VALVE FCV-e TRANSFERS CLOSED TRANSFERS CLOSED TO OPEN FAILS TO OPEN rxv PxV PCV DPAV Oil 0g M1il T 7 OF9 Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATERSYSTEM
-FAULT TREES FIGURE A-2.
01 0 Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWETR PLANT SYSTEMS INTERACTION STUDY, AUXILIARY FEEDWATER SYSTEM
- FAULT TREES FIGURE A-2.2 FAILURE OF DOT" HI0" TEMPERATUlRE SO. 3L. AND SHUT OFF VALVE 23 3) TO PROVIDE TRANSFERS CLOSED SttAMTO, COMMON HEADER SHEET 8 OF 9
a I I 2 41 SHEET 9 OF 9 Power Authority of the State of New Yorl INDIAN POINT NO. 3 NUCLEAR POW4ER PLANT SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM FAULT TREES FIGURE A-2.2
Am An IRW 'Row FROM GAS TURBINE/ FROM 138 Ky 13.8 KV SWITCHYAiD' SWITCHiYARD FROMI MCC 39 IFROM MCC 37 I BUS A [ANL 1 CPOWER DPOWER PANE L 32 F-- OCIRCUIT
~~~~1 BREAKER A BATTERY SCHIARGER I %.J6.9KV/480 V
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Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWER PTANT 480 V ESSENTIAL POWER SUPPLY BLOCK DIAGRAM SYSTEMS INTERACTION STUDY FIGURE A-2.3 a
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~IT0OROOMDETEMN IT cR swis AWN PLAUT PROTECT .m 0 'o, J
P 7 PltoTv C Sr "NAL ST'1111L 110 STUIATION 515 INITIATIO RODS PROPPED RACTR TRIP FISSIOIN STEPPED SNty GAaG D SEE OERATO BEE OERATO COAMLNTRLATRTI CTENIARAN ANN 53 S 5 p I~iPA55 LOOPS InRYA MIPo IN RY4 ATONACIONP RIMAIN CO. TMO4 STOP TURBINe VALVES SAOLE.=SOLENOID q I - 1 TERMINATES TRIP MAIN MAI IM8I9L PR TORMINEDRWAER FLOW TURBINE Il RLS SO 35E535A NCONTOLPVLME STOP VALVES LWO SYSTEMS 3555 4I r 0 PUMPS SIPPI.ES MTOR RIVE A -FE TIqboIP PIS TURINE DRIVEN 4.7 A~OMETD APRPUMP SUPPLY P01R TO DIESEL ESSENTIAL 50STEMS GENRTR Co O WATER SEE O1APRAPUMP TERMINATE PR PFLOWTO MAP EED WATER SG 3.,3z,3.304 BYWSCONTROL51.05 4 i.e i I PUMP aSUIPPUIES CO RTR TO SG31.5Z MTRDIE P UP PUMPal5 SUPPLIES CO WTRTO SSVV3'-S4 SI 3 0 HEAT TRANSFPER - NT- OPTEMINTN 7WPUP TERMINATE MAIN PEED WAER OR ESP FEU SERI ATER
'W PLWTO RIMI CONTROL PLOTS SYSTEMS SG. !1.5235.34 P55 P" FCV ECU 4IT 427 41$7 4A?
TEIMATNEO- ETA PM SSUPPLESIEE TERMINATE FEED WATER M70 UM E O SP SAL ERC AT e EIN PLOWA TO BYPASSCONROL I.VALVES REMOVEHNEAT PROM CONTAINMENT SMAIN1,T2,35P3 ISOLATI O VLVS SYSTIEMvS MS SOG.5302.534 34 CONTAINMENT IGFM PE ICV FCY PCV I1L1.II. H43L44TL _____AUTOTEZIP SECOND ONE. PLTOPLO. SrSs FOM OTINET3Z LN PN SEEODO=MEAN PROVIDECOTIMN OP TERMNN. P04 PIMP MOETVALETS FIN FLO To SAS CONTA'INMENTSPAPUS SPRAY WATER Pro-Z-SI BED?.SE TEONDUPPEAS OTIMN HEA TR%3Fi~tESSNATL OTARINATENTG SPRA PUMVS me u.F OR IS S RCE N AET SECOND MEANS READY TO COOL REACTOR ---- AFCTYMJ SVPRAYIATER PAM P OP PRW TeRMINATING PLOW TOS555 71W PUMPS COREPUS RESSURES IF M~ATEAM REAOVEYT OL ASSURE PROPER SIINETO OL ELIMINATING MON-ESSENTIAL OPERATINGOWTON ESP AUXILIADY REAmCTR COe" POTENTIAL RA NC PROCESS LINE OF RADIOACTIVE FOR ESP SYSTEMS SYTEMS AINMENTISc VI.OS RELEASES Os ISD TRAIN A TRAIN-j - WATERE ISOLATE SGS MAIN STEA PROM COMMON isOAINVVE FIPR AUTHORITYOF THE STATEOF NEW YORK INDIAN POINT NO 3 NUCLEAR POWER PLANT ASSURe PROPER eSF AUXILIARY OPEATING O -- e- SYSTEMS SPRAYWATER COD To CONTAINMENT SRYVLE SYSTEMS INTERACTION STUDY PON ZSP SYSTEMS TRAIN TRAIN - SHUTDOWN LOGIC DIAGRAMV P A, PRESSURE EBASCO SERVICES INCORPORATED
-oN *P-0OTE 20-81 I I tc FIGUIGRE I-I-WI 15 ITILI 17-A 15 I' U 13 14 is1 is 17 -18 I I
9 1 ib 11 12 is 14 1 ta isIA 17 1 2 S 14 5 B I to ii 12 13 14 I 15 17 j.~) ,,,,P OOT ClOSE EASE: 5LOAtE ArVEC!CO SJEAN, ZENERATOR CLOSE ALL AFW COWTAO'- VAL<t VALVEINLINE FROM WIVE LINE FRO. MMOR DRIVE. AF. QESPONrE ArW PUUP N, 3Z Pimp MOTCLOSED NOT CLOSED AL.L. VERIFYAFW PUMP CLOVALVE! w 32 OPERATION SED STOP Pu.;; &RUNNING QP TURBINE VERIFYAFW 31 3Z b, OPERATION F PUMPS NOT U.N.
, PS ST. PUMPS VERIFY w R AFVJ PUM-Z PERArso IF NOT UWIN-MG
;T-&QT-pMuNn- MPS START TM MOTORMIVEW PUMPSPuh.WG cot OPEQ&T." TURBINE DRIVE.
TSTATUS PUMP RUNNING ALL VALVE G CLOSED FIRM AFW PUMP'TE2:..AT::l 3231a10 STEAM WIE Ost 4 H VER.F, 0 AUK rEEDWATER VER.FYWN.Rim CONTROLOF INO.CATORI-PUM' STEPMTO GENE AFW PU.9 M..3Z TO GOOD IF T:V-E STEAM ZP.M.R.. _j GENERATORS A'r LZAS rwo STUAMGENERATOK5 ARE WeEDED, L TEAM NorM_ _..ERA Ga"e prRS
'W "ALY 4.
4" TEAM SL "ST EVELGENERATORLVE O INDICATORS A W C FW ISV COWT LIR5 To MJUNrMVE ACWUST CONTROLLERS STEM GEN. LAVE, 3TEM ISOLATION STEAMLINEPRESSURE VALVES POS.TION INDICATOR DUMP VALve OUMP OR COWO'NSER _OMTROLLERS A04UST CO-TROLLE i TO DECREASE S TISAM PRESSURE r:Qlly REACTOR COOLANT C DOWN RATE
.0 5TFAMPRESSURE AT PSA?
POWERAUTHORITYOF THE STAT NEWY( yes INDIAN I',iNT NC) SHUTDOWN LOGIC UiA\:RAM 1.0 To QRR SYSTEMS INTERACTION STUDY SYSTEM EBASCO SERVE.. INCORPORATED L7-NONE 0...3-20-81
=:AIIU T-71 -.. T- 10
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77.7I--
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FEED LNE BEAKOIII CONTANMEN~TWflN4U55bOF q( OFF SiTPOWER. 0. Pd S jq. N o,~a
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EBASCO SERVICES iINC. r POWER Xj40OFATHS STATE OF NEW YORK( INDIAN PINT No.3 WUCLEAR POWER PLANT SYSTEMS ImTERAcT ON STU DV I. IFIGURE A-5
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INCES 1' -m;_ cm.pwq","v I - I
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- DIV.MtAS-DR. a[ APPROVED' 1ADMoTO UCERFVE
-DATE310-8 ck&J 1 YTEEACIO T1 (rAtV9 rIobJE kr AF5 S5TUD'C WUIL)C&RY,
Power Authority of the State of New York INDIAN POINT NO. 3 Reprinted From Figure 9-3-25 IP-3 Fire Hazards Analysis SYSTEMS INTERACTITON STUDY
.Revision 1, April 19.77 AUXILIARY FEEDWATER SYSTEMv FIRE ZONES
ILI>_ ill K i
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.1 Power Authority of the -State of:NewYork INDIAN POINT NOl. 3.
Reprinted-*From Figure 9-3-26 IP-3'.:Fire Hazards Analysis SYSTEMS INTERACTION STUDY Revision 1, April 197.7 AUXILIARY FEEDWATER SYSTEM FIRE ZONES
PlCrU*RE NUMBER
§d" PIC.TURE UBR JJSPACE HEATER OL POER AMHI-ORITY OF T14E 5ThMO(*NEW YOP INDIAN PINT Mo35 NUCLEAR POWER PLANT PLAN EL' 18'-6 SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER BUILDING EBASCO SERVICES INCORPORATE)) I Cm.
INCHES 141
IS PICTURE NUMBER mN*. 1 LIGNTINQ FixTuRE fSPACE HEATER Ia } PLAN EL 32-6 NER AUTHO~RITY Or TVAF STA.TE OF NEW YORK~ INDIAN POINT No 5 NUCLEA~R POW' PLANT SYSTEMS INTERACTION STUDY IXILIARY FEEDWATER BUILDING EBASCO SERVICES INCORPORATED
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G"CT10-14 39 CT- B6 2 O0. 40 Cr-31
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441 CT- 25 (a4EC) 45 PCV- I IT 8OCT - 107C 471CT-82zM. 481 CTOZB uI* I ptWp
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SHEET _LOF POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: XF~W ?UNABILP4 FIRE ZONE:2 LOCATION WITHIN FIRE ZONE: 4 INTERACTION NO.: INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS:
- 6) ~71c CS~4 DESCRIPTION OF POSTULATED INTERACTION:
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SHEET OF 23 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4F', d79 4 FIRE ZONE: LOCATION WITHIN FIRE ZONE: AJ 4 INTEACTIN N .3'-08-c,-o.~ -&~-~..3 -~ ~ -c INTERACTION SKECH. O. IDENTIFICATION OF INTERACTION COMPONENTS: n~ DESCRIPTION OF POSTULATED INTERACTION: Cc~ Y jl- -741'e;r sv?)Po ', EVALUATION & DISPOSITION OF INTERACTION: J6', ae A ey 9P Interaction gngineer/Date Ebasco Services Incorporated
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SHEET 1/OF1Jf POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: .4F&) 9'a m? 4u, FIRE ZONE: 2 LOCATION WITHIN FIRE ZONE: AJA INTERACTION NO.: 5--' /C. 4 ~3//.s 3 ' INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION:
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SHEET 2OF( POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4f-pi ,cfC4 p FIRE ZONE: 213 LOCATION WITHIN FIRE ZONE: INTERACTION NO.: 3 /4/-/0- 104) 3-61 INTERACTION SKETCH NO. :F . / A IDENTIFICATION OF INTERACTION COMPONENTS: Z~Oc~r(OS 2" /7~7G~7 4;r/ e
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SHEET __ OF 2 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4~u -Pw~ fain I, /. FIRE ZONE: 2 3 LOCATION WITHIN FIRE ZONE: /A INTERACTION NO.: 33- 102-1-105-,"- ~o, 3i-' 0 3 3 /: 3-18-12/OS>, 3'5 3./,'/O INTERACTION SKETCH NO.:
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SHEET /4 OF.2 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4 =a 7a M a /u FIRE ZONE: 23% LOCATION WITHIN FIRE ZONE: IA INTERACTION NO.: 3.3 -/q-/l--/0(0 INTERACTION SKETCH NO.: -4/.,
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SHEETI/ 0F Ay POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4ct 7~W~If~ &~UU 27 FIRE ZONE: 1? 3 LOCATION WITHIN FIRE ZONE: AJA 3 3-ze)-11-106 33-2b-/~-/O5 INTERACTION NO.: 53-ZO-/3-/O INTERACTION SKETCH NO.: r-rT-l Phcy/o /o, ~ IDENTIFICATION OF INTERACTION COM*2ONE]
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SHEET .OF~4~ POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: AFW' ,'RarnoP 3wL4',n FIRE ZONE: 2 LOCATION WITHIN FIRE ZONE: IA INTERACTION NO.: 33 Zs- 0 /~Z/ 33-Z 7- 02 )~ 32-Z-/,~ 33-zoo- cz -//3/7cq0 3 6-/-/~) INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: ccd<4 '4' 6,1 10) EVALUATION & DISPOSITION OF INTERACTION: 41 -001 L. Interaction'Engineer/Date eviwer/Date Ebasco Services Incorporated
SHEET L?2OF 2y POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: ,4,c44j fdrnf 4AX,'Id_' 'I FIRE ZONE-: LOCATION WITHIN FIRE ZONE: ,J/4 INTERACTION NO.: zZ 3-3 -2I INTERACTION SKETCH NO.: pe/o1s IDENTIFICATION OF INTERACTION COMPONENTS: n
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SHEET ZOOF4 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: .44a) 0,Jm FIRE ZONE: !1 LOCATION WITHIN FIRE ZONE: /AJ/4 INTERACTION NO.: 330- / 1) 3 2~~ INTERACTION SKETCH NO.: s- o 41/ IDENTIFICATION OF INTERACTION COMPONENTS: powe'. ~qI~~cnch&,'# fe ~A~(e k/e~d.ei. A'8 ~ 4 ( 7-c-e~t) ~77Z', DESCRIPTION OF POSTULATED INTERACTION: LA C1stt4t J ~Es*I ~C~-4~e~ ?~PPh ~ .'-7r r74/ EVALUATION & DISPOSITION OF INTERACTION: v~~j 0 VeOny 4 Y1e cetb/e tcm Interaction Engineer/Date / Rev wer/Date/ / Ebasco Services Incorporated
SHEET Z/1 OF POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4F1-L iiMR ; Ilt7 FIRE ZONE:Z$ LOCATION WITHIN FIRE ZONE: AIA INTERACTION NO.: 433 - .3 3'3-- 3
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PICTURE 6 PICTURE 7 PICTURE 8 PICTURE 9
PICTURE 10 PCUE1 PICTURE 11 PICTURE 12 PICTUE 12PICTURE 13
PICTURE 14 PICTURE 15 PICTURE 16 PCUE1 PICTURE 17
PICTURE 18 PICTURE 19 PICTURE 20 PCUE2 PICTURE 21
PICTURE 22 PICTURE 23 PICTURE 24 PCUE2 PICTURE 25
PICTURE 26 PICTURE 27 PICTURE 28 PICTURE 29
PICTURE 30 PICTURE 31 PICTURE 32 PCUE3 PICTURE 33
PICTURE 34 PICTURE 35 PICTURE 36 PICTURE 37
PICTURE 38 PICTURE 39 PICTURE 40 PICTURE 41 PCUE4
PICTURE 42 PICTURE 43 PICTURE 44 PICTURE 45 PCUE4
PICTURE 46 PCUE447 PICTURE PICTURE 48 PCUE449 PICTURE
PICTURE 50 PICTURE 51 PICTURE 52 53 PICTUE 52PICTURE
PICTURE 54 PCUE555 PICTURE PICTURE 57 PICTUE 57PICTURE 58
PICTURE 59 PICTURE 61 PICTURE 62 PCUE6 PICTURE 63
PICTURE 64 PICTURE 65 PICTURE 66 PICTUE 66PICTURE 67
PICTURE 68 69 PICTUE 68PICTURE PICTURE 70 PCUE771 PICTURE
PICTURE 72 PICTURE 73 PICTURE 74 PCUE775 PICTURE
PICTURE 76 PICTURE 77 PICTURE 78 PCUE7 PICTURE 79
PICTURE 80 PICTURE 81 PICTURE 82 83 PICTUE 82PICTURE
PICTURE 84 PCUE885 PICTURE PICTURE 100PITR10 PICTURE 101
PICTURE 102PITR10 PICTURE 103 PICTURE 104PITR10 PICTURE 105
PICTURE 106PIUR10 PICTURE 107 PICTURE 108PITR10 PICTURE 109
PICTURE 110PITR11 PICTURE 111 PICTURE 112PITR13 PICTURE 113
PICTURE 114 PICTURE 115 PICTURE 116PITR17 PICTURE 117
PICTURE 118 PICTURE 201 PICTURE 202PCTR20 PICTURE 203
INSTRUMENT RACK NO. 5 INSTUMET RAK N.5INSTRUMENT RACK NO. 8 INSTRUMENT RACK NO. 9 INSTUMET RAK N.9INSTRUMENT RACK NO. 28
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