ML093641094

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Preliminary Power Authority of the State of New York, Indian Point No. 3, Nuclear Power Plant, Systems Interaction Study. Volume Ii
ML093641094
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Site: Indian Point Entergy icon.png
Issue date: 12/30/2009
From:
Ebasco Services
To:
Office of Nuclear Reactor Regulation, Power Authority of the State of New York
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{{#Wiki_filter:a IPJi ~In" rL.7 T'bXLU mw*2- mnSLtlL -3_ ~3 on "' 9E ' 04" 0 t awl b S.POWER AUTHORITY-OF THE STATE' ' OF NEW YOIRK INDIAY POINT NO. 3' NUCLEAR: POWER PLANT, SYSTEMS tNTWERACTION; STUDY VOLUME Il Prepared for the Power fAuthority 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 APPENDIX A A-1.1I A- 1.2 A-2. 1 A-2.2 A-3.1I A-3 .2 A-4. .0 A-5. 0 AUXILIARY FEEDWATER SYSTEM (AFS) SYSTEMS INTERACTION STUDY.IntroductionA Systems Interaction Study AES.-Boundary A-2 Results on AFS of Interconnected A-3 Systems Interactions Results on AFS of Non-connected A- 9 Systems Interactions AFS Functional Description A-22 AFS Operating Description A-26 AFS Interaction Matrix/Documentation Sheets AFS Non-connected Systems Interactions Study Photographs, SECTION TITLE PAGE 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.- 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.APPENDIX A 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 MECHANICAL ELECTRICAL INSTRUMENTAT ION &CONTROL HETN, VENTIALTING & AIR CONDITIONING PUMP 1) CENTRIFUGAL

2) RECIPROCATING VALVE 1) Air Operated 2) Motor Operated 3) Hydraulic Operator 4) Check 5) Manual 6) Safety/Relief
7) Solenoid FLOW ORIFICE RESTRICTION ORIFICE STEAM TURBINE COMPRESSORS PIPING GAS STORAGE TANKS TANKS (FLUID)MOTORS CABLES CONDUITS & TRAYS BATTERIES

& CHARGERS DIESEL GENERATOR MOTOR CONTROL CENTER & SWITCHGEAR CIRCUIT BREAKERS & CONTACTS SWITCHES INVERTERS MOTOR OPERATORS FOR VALVES TRANSMITTERS SWITCHES (PROCESS VARIABLE) POSITION OR LIMIT SWITCHES PNEUMATIC CONTROLERS PNEUMATIC CONTROL VALVES PNEUMATIC SOLENOIDS PNEUMATIC/ELECTRICAL CONVERTERS LOCAL INDICATORS LOCAL CONTROL SWITCHES INSTRUMENT RACKS INSTRUMENT SENSING LINES INSTRUMENT AIR LINES & SPECIALTIES ALL OTHERS FA NS COOLERS DUCTWORK LO UVERS CHILLERS SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM COM4PONENT POWER SUPPLY

SUMMARY

(REF 1 TABLE A-3 Power'Supply, Primary source Backup Source(5) Function A. STEAM SUPPLY TRAIN PCV-1139 (20-1/ABFP2)

(1) PCV-1139 (20-2/ABFP2) (2) PCV-1310A (SOV-1310)(1) PCV-1310B (SOV-1311) (1) B. TURBINE PUMP 32 TRAIN Aux. Bir. Fd. Pump 32 CT-1O PCV-1188 (SOV-1288) (3) PCV-405A (1) PCV-405B (1) PCV-4050 (1) PCV-4050 (1)125 Volt DC Pnl. 31 125 Volt DC Pnl. 31 125 Volt DC Pnl. 33 125 Volt DC Pnl. 34 Steam Driven Hand Operated 120 Volt AC Instrument Bus 31 120 Volt AC Instrument 120 Volt AC Instrument 120 Volt AC Instrument 120 Volt AC Instrument Battery 31 Battery 31 Battery 31 Battery 32 Bus Bus Bus Bus Stm. Supply to Aux. Blr. Fd. Pump 32 Turbine (N.C.) Stm. Supply to Aux. Blr. Fd. Pump 32 Turbine (N.C.) Stm. Supply Isolation Valve to Aux. BFP 32 Turbine (N.O.) Stm. Supply Isolation Valve to Aux. BFP 32 Turbine (N.O.)Residual Heat Generated Steam Battery 31 Battery Battery Battery Battery Bus 3A Bus Bus Bus Bus Valve on pump 32 Suction Heater from Condensate Storage Tank (L.O.) Valve on alt. path from City Wtr. Sys. for Aux. Fdwtr. Pump 32 Suction (N.C.) Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 31 (N.C.) Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 32 (N.C.) Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 23 (N.C.) Aux. Blr. Fd. Pump 32 Discharge to Stm. Gen. 24 (N.C.)C. MOTOR-DRIVEN PUMP 31 TRAIN Aux. Blr. Fd. Pump 31 CT-27 PCV-1087 (SOV -1287) (3) PCV-406A (1) PCV-4068 (1)480 Bolt Bus-3A Hand Operated 120 Volt AC Instrument Bus 33 120 Volt AC Instrument Bus 33 120 Volt AC Instrument Bus 33 Bus 3A Battery 33 Battery 33 Battery 33 Dsl. 31 Dsl1. 31 Dsl. 31 Del. 31 Valve on Pump 31 Suction Header from Condensate Storage Tank (L.O.) Valve on Alt. Path from City Wtr Sys. for Aux. Fd. Pump 31 Suction (N.C.) Aux. Blr. Fd. Pump 31 Discharge to Stm. Gen. 31 (N.O.) Aux. Blr. Fd. Pump 31 Discharge to Stm. Gen. 32 (N.O.)(1) Valve Fails Open on Loss of Air or Electric Power. (2) Valve Fails Open on Loss of Air and cannot be Closed Without Electric Power. (3) Valve Fails Closed on Loss of Air or Electric Power ()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..(N.C.) (N .0.) (L.O.)Normally Closed Normall'y Open Locked Open Component SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM COMPONENT POWER SUPPLY

SUMMARY

(REF 1) TABLE A-3 (Cont'd)Power Supply Primary Source'4 Backup Source~~D. MOTOR-DRIVEN PUMP 33 TRAIN Aux! Bir. Fd. Pump 33 CT-33 PCV-1189 (SQV-1289) 1(3) PCV-406C(1 PCV-406D(1 480 Volt Bus 6A Hand Operated 120 Volt AC Instrument Bus 32 120 Volt AC Instrument Bus 32 120 Volt AC instrument Bus 32 Bus 6A Battery 32 Battery 32 Battery 32 Dsel.Dsl. 32 Dsl. 32 Dal. 32 Valve on Pump 33 Suction Header from Condensate Storage Tank (L.O.) Valve on Alt. path from City Water Sys. for Aux. Fd. Pump 33 Suction (NIC.) Aux. Blr. Fd. Pump 33 Discharge to Stm. Gen. 33 (N.O.) Aux. Blr. Fd. Pump 33 Discharge to Stm. Gen. 34 (N..O.)E. MISCELLANEOUS LCV-1158 (SOV-1258)
(3) CT-6(4 CT-64 (4)125 Volt DC Dist. Pnl. 31 Hand Operated Hand Operated Battery 31 Dsl. 32 Condensate Condensate Condensate Storae Tan Storage Tank Storage Tani low-level shutoff valve (N.O.) discharge valve (L.0.) discharge valve (L..O.)Valve Fails Open on Loss of Air or Electric Power. Valve Fails Open on Loss of Air and cannot be Closed Without Electric Power. Valve Fails Closed on Loss of Air or Electric Power AC Instrument Buses are powered off of corresponding DC panel. Transfer from Batteries to Bus 3A is manual. Backup to Bus 3A Diesel 31.(N.C.) (N.o.) (L.0. )Normally Closed Normally Open Locked Open, Component Function APPENIX A AUXILIARY 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 A AUXILIARY 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.APPENDIX A 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 th at 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 interactions 3 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 APPENDIX A-2..2.1.Results on the AFS of Nonconnected Systems Interactions (Cont'd) 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 sys tems 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. E xternally 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 f or 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 APPENDIX A-2.2.4 Results on the AFS of Nonconnected Systems Interactions (Cont'd) 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 suct ion 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 f low 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 Desc ription (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 I I I r YOIAPo~.4~UT T)E~CeIPTI 0 FAWLURE Aooe(1 V:FFELT -rOt4,N )TE-ME--kODOF. D~ eFCr10 J EvYtuA&-'io" 0F 7-iuLw--~ ~ -= ________________________________________________ a -- t -___-(ou&cfr To ,Oe_ J Rig A~ um 31 1 0 u s (0 A t)C fEAKhEZR Fo BeeKu?- O AI C 0E 'F C Lcvrs 4 azvxd., -t -ow frj L5 f-xvm OHe2 w aiu.Lk fj ?oo.i ~n~e4~4I9tir Loss 4 34. t~A~.3 ms4 ~ ?114*f ::S a vo 4 oes ooAvo yom 4 6 o w~or cow~e o-s ~o E -2 D5Wa~s in 4 sc4oi LV% wtv a AM COf{o~ct -L;Ia w\uv'~O.eIV SC -1 or -62, rV-to( 4ock 'eceA SA4- N'. -0?tOOVy E~t 405 Aoe Fr\' 405OS. 14 O tey4ld1 c<,-35or 34, 4 ur6m {4ou 40 c4ecteA s -AL, r Cossin Fc/ 4o S,5.c oa r> T-tO IW~I LI 1-- C- 64t r ,- c TA isL Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES & EFFECTS ANALYSIS SHEET 1 OF 9 FIGURE A-2.1 Qo ,E - _______ ________________ r T efo"ot4EI.)T TOeO, reip-iik FAILUIFE AooeI£.FF~ro" 5N $->Tc-M Me-, hOF c DeEEerLoQkJ ~V~LU41~I~t'4 OF V'~A.4r~S I ~ --. -. ______________________________ NI-i NI-2 IE F AFVW PUNAP 51 iuV0 CDR16LO 1 u 5 lem coz:vj -Pumr PVY13 L 0 4 4 kLt sJ .b 2U~ ~rn~j~j~ +0e-ilecis O' &w 'A L-05e c u,.JO W o~4i 4co ow Vnrn ---C2.- to2eeO.TO(S. Z, ve, cive5 o.O 1"C sAla lln \Ob 4 1va ro -ue o'vd VecevM a4A~ow4L 64Con rdp Yoi Vle51+a-b 055 a,21 iA Io o+6.)Wndto Q 0 v ~4obtei o-1) iOuWUMP dJsU1uJe rlI .xto A 4 eM- "-I r43UAL 'VI V YOV'I o4ZJP WA ICiui1 c4s~cfttA' yLO (?,I -w1-7 eo_________________________ £ _________________________________________ J Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM F FAILURE MODES & EFFECTS ANALYSIS SHEET 2 OF 9 FIGURE A-2.1-\cc epo£c o-- e&~o~~~eA~tLIOA thJo 4~e&A eos M -, <4~~ -I r t I I I I I I I -1 I 7eCOIPT-4O gC T&W -; \-oss OF MtAu/i.IF( Supi.-FAILUR~E Aooecs I--FF c-T CM S-TC-M ME--PAOVoF tD A% r i ID to4 ovtvs aTI proifi -s~w e\c N To4I O 6A 9 c ad C,)j tt S4-5a 1 nJ -2. OV 1 cSdm s m '40vc~e +~v C1rk WA9-17am\ fuuv-r)O wc w~ 5te ince ?lwcAI sPte d*itv ncoflfroI VOOMv, locoll Oservez Ic cait'vol Vk C01(.0un -L) losOFsuIrQC k VOOwl (P1- IIl 1fl6;) Cti woctet" VMS!6 mI w eC xl cks e M~otoy v t.ie4QmJps-alO4'VI(J 7c1e8' 1.10u ow 4(Lec.4W~ c~u~oe us+ vec4jc ~ ~c o.V~yealwvc.Qves vo~ve Pc_ ove8 PC P'-118 9 CT- 4 7.1 2NCCEPIF-Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES & EFFECTS ANALYSIS SHEET 3 OF 9 FIGURE A-2.1 KIC m-7 m -5 EV&Wwrto" O;r FAtWaG rD -5i4iPTI (& L vcaQe~ C.. 27) CT T- 4 C~iecr c kerE. Cc~c vo.Q~,e v/~4e. VaQvc V(0QVEC C1 -32 c{- 25, Cw ce vo-Qem s -40 CI,e4 vcake.L1feK. vaokve Ckecv. vdve Ci ecv vo.ve.VFD-3:M 5FD- 3S BFOT~Ci-~cx va.ve b-o- 40 C~ec~&',C~Fp42 6661C vatye PFJD -1311 O 6 ex(r ViOQvC e) L- -32 FAILUR.E Aoo>eo. (smg qoerq~p('4 IEFFF C OW !~q!-:TeM METP4 V O EVALUA1rio" 4OfrF &ItLUV iF~~~T~F=t -. _______________ _________________________ I OLoP$ 1,31or 5 3 -k u u" &OO'vw ' ..4%% 5 1 4. c i654 S " P OcW 0 6ou AVO w32 Y oXI j ej jerCt 4 ? I-Wf AUM6 055\ uka t 4 1o~sc Ow'~A~uJ~ o 4s loss~~~~~~ s 6o.o~~eut~ 4.~M-6 dvo P .T- 12 ie Ivl-4.'OYoo PmC418w A Y'mto Yopm, %IAIUM CA~jLe v -IC0Y io% &e ts o \l4Aov sko u < mjlayto 4e Ge/ok~Jo... 1 ko4 pe& oyvhcJ e 5 Ms )S. I Yeviotel i! kba )?wt '-u V.C.C) cl ~ IS OLSs0U p j40 I 4 4CI0564A) 'ac 4 WIA- Sff140 9510,5 M 4&ce e 4-Acce o-W Accepozx, a Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES & EFFECTS ANALYSIS SHEET 4 OF 9 FIGURE A-2.1 z7TeN Ace?M- 12 M-I17 M-A is.M-20 M'- 'Z) NM-ZI Mv- 25 I Y a CO~APO i-i FALUE ooeCw (%e vJomoi)- I MF-7 00 O EvAI I A-rtn'06r FiILI1IO V i C l- sI n I I 1 I .~

  • S ~ '~ -, -S I 1 I I~r~ -~ b '~ -, ~ I I M-Z9 t-32 M'-33 IM-32 M~A-365 N4- -3to ea(vo D 3t Ckc 1 r- vo~vc ~P 47- 341 rvOciud vaC Pir-Q2.3 moa~aA \OQVC FT- -6*ffiid ou J53D -bi-zl ftiu.Va~ve

~o 41 Maa,1wk /'ve- BFD 3 r~oavokieVc ,~-4) mom~a kvck vc "s- 564 M. 40 4ALvovcI4 NM- 41 rM-44 M-43 MA- 46I M -48)-mamaa avipF- 4s-3i %I-T .31 ul-flo -32 I'TTo -33 irr -3 Drri o -34 15 Ic 0~loss 4 Lw,4o.A, ALtAWOr iAO~SG-161 %VT-TO loss o aAbAL 4 v.L49t9 V ;SG -34 4OS COe~v t rOV.yI{o iAD QV6LI4e. &VIe Y %A ios~(v(wQ~"d. 4~ {sI (o.LA c,,owfrol Voowi 0 1 oQ1roy vu4%CA'r VoA/Cvo onro om n 6ie~ch~o S'wi am 4' 0 PrV tlQ~v M-2av~4 o\/.qe2ve4l s-26.1 4 o 4 4 c Xs- oz. 4o5-. c;ir 1 1w# 4&4 e vaP~~ I~A-2A-Z4 IZ. 1, §\Lw~-Yo -~ e vii ~ tLA4 M -Z7 M Z-) N4 2-5)Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAI LURE MODES & EFFECTS ANALYSIS SHEET 5 OF 9 FIGURE A-2.1 A~ccfAa~Ln. ~co ~ccc~ptaJ~6o Z-TEN, On I-1 F7-FFE4= n" S,4c-,TC-M D eF-AP-O e& LI M~- 49 M-5o MA- 5-4 M-515 M-51 M. o e Y -~FALURE Aoo(s c E 061 ,D E-=FFCT Ot, Z-4STE-m-Me-IDAkoD OF D ETC( 0 C-v.LUA1Srot4 0O:FA-11LUVRE --- I ~___1_%-0______W__-A_ ___ _ %AaI?rC- -.'57 .50\/ -it's ,O v-6 5 061 A\w otci FC.446Aobr i41'~r O4c FCV 4 b'vcAes wil11M V~A 4e___ 10lf biU ov r )w 4 4c.~~er~ o 1 -LW~vo CWV VOOW1 peAose 61f AVom r 0 IOle cio cl~ ')Os ' 06, It. Vol "OmK 4O maJ4:0 A V(v re~u a ".I "* ov U4Z0AL. e?~u Lrs L'4 ot 0s.vrec f aI G.Y ,ecf4v ae Lo c L c Yofv .-a bR * $61Al 4, Teaum aaeee rc44 Power Authority of the State of New York INDIAN POINT NO. 3 AUXILIARY FEEDWATER SYSTEM FAILURE MODES& EFFECTS ANALYSIS SHEET 6 OF 9 FIGURE A-2.1 Klo ws4o* ~'cowv- .e-r r KlJo M-60 (cow 'D)M-71 CoIAPao,~eoyT ]DelcempTa O L FAILURE oo~s flmeg-if I# OF S~JAI a IA9'nP~L.~ (~~C ~h (f-n ,i ea i-r. na, i i --I .1 1 1 -T -1 q&&4eAFr-W -4o Fkcv- v3-1O P c- A. .-k0, RA4;24 Ry -I Iaz Soy- I z I 5z '-(2 C410 E a Ao IA auip~to( tcli4 z~o e, mZ. aVvl 1W ~u4, eu0 KoIAFE F41WP toC APVIiVUJ E r5&~ivo vi 0 1 011'AD Um I 0,10i 40 S.- 4oA l C ID, n4f/OymA bcxxp oVi~e4 r VA~C Alp-1 e4a~ tL% MMIscc A -7 ,CC~-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.GFFEc-r 0" S,-41STC-M I r I. I.~oo~e~T D~e~iPTI 0 eJ FAILUR.E ooe(s')C-FFE:CT Ot- N Tttd Me-kovOF., -e-TEC.T 0"K EV&LLU6.-ro" OgF \ILu~e I I ____________T__T-___F-= Vcdve con, Ol+von vave. PC-- l1toA voav Pcv- r 10 e>vole PC'1' -i~~O A ,FC- 12.t3( ; Fo c 11 5G .16 vlaw C"iVlovei Flow con,~mkio(. Ft -(3 5 4 P--1242l PI -4O( e) NtA- 4o'4g ~Ac- A0ou do ,mdi rny 4o mc mOQryleV4 Qh13 tNA-(a4I COW f0ve41f b NTo-VIOIU E' To KQoue.1-1 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 I\A -(,o 0 LI rrn~ca ;-;-4kgeva c jvl 7;i6 Paw~ 1 TTIO'-g2 TO~ cfo".Po.4eoY -De-5ceIpTI co ~i FAILuF~e Ao~eo')ri-=FEFCT Ot-4 'NTek4 t r Me-, hov OF.-., ______________ I __________________________________.If-5 A 15 C b'E 'F IQ PT- IZGO PT I(o s T-4o~ A~ Pvk- 4o F iA.- 406 ( PT- 161G PC -117(o K.- 55 TDE ~o~Ko o l~oL)C kioo t;;vio&oc-OIT TO0--TI-v-to-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: K~O-iTTO-"a- 17 T-?Zo 1-23 -4 ID O C:V&LUAIIO " O;r FAIL.URE C-10 1AC.Lusloki cl SYSTEMS INTERACTION STUDY APPENDIX A NOTES TO TABLE A-2.l NOTE: Jl) Failure mode~s) for e ach 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. AFVVS FAILtIRE TO DF.LIVnRAT 1.ASV 20 1 OrM TO *AC" orrvWo s UAM OEEEATOPS SFAULTM TREE loo cF IG U REPAT2 .t 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 S0 SErDSHRG FE RACIGSCTION TO AFW 1 34 6- 6 5 46 ISLAIOCVLEC SOLATIO VALEA O CHECK VAVEVAVE0CT ~~FDPUqPLUGSARR rFAFTELUS R BRANHIN FAILS TOTANFR Otis 01100oo ISOLATIONSYTEM INTALCIO STUDYN AVEARPRAE ,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 WATER NOT 3, 32 29 II2 cv "02 SUCTION to AFWPUMP* CONDENSATE WATE UNAVIJA~E tCITY WATER A vPm#UNAVAILAL r OABLEM Sr UINT UAVAILAMPL# SUJCT ION CONDENSATE Nail WAER PRO CHECK VALVE CT.0 AIOPAE0 STORAGEIAN TANKYSAOEGE UANK FAILSIO OPEN AVFAL UAALBESrECIF IC 10AW AVAIlABLE A t4 $?OF VALVE STOP VALVE CT SPrLIEGSl C164 PIIGSI CIECK VALVE CF.4 p SOIATION VALVE TR44ESTRAINMERS PAILIS TO OPEN Cl. T TRANSF ENS CLOSED ClA' COSE ' 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 - 4-0 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. 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 HI0" TEMPERATUlRE SHUT OFF VALVE TRANSFERS CLOSED FAILURE OF DOT" SO. 3L. AND 23 3) TO PROVIDE SttAMTO, COMMON HEADER SHEET 8 OF 9 01 0 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 FROM 138 Ky SWITCHiYARD FROMI MCC 39 CPOWER [ANL 1 F--FROM GAS TURBINE/ 13.8 KV SWITCHYAiD' IFROM MCC 37 I BUS A DPOWER PANE L 32~~~~1 I ~~~1 FROM MCC 34 IB US 2A)480 V ESSENTIAL POWER SUPPLY BLOCK DIAGRAM OCIRCUIT BREAKER A BATTERY SCHIARGER %.J6.9 KV/480 V (Y- TRANSFORMER DC CONTROL POWER Power Authority of the State of New York INDIAN POINT NO. 3 NUCLEAR POWER PTANT SYSTEMS INTERACTION STUDY FIGURE A-2.3 a IRW'Row 'S 0ol ones K1G.0.i totetb4 so OSFINIOW S tAt 458 TI t toJ.V 4M94 Ott~~~f~flinA NtottR IO UNI O ...Is Powe Auhoit of, the State ofNesYr SYSEM INEATO STUDY, ELETRI POWE SYTE DIARA 36^FIUR A-2.4ACCv to -- 12"11NZ13 14 1is is 17 is 19I TO STEAM GEN. P40 31 I 466 0loo TO STEAM Gem. %. 32 .'60-004 TO STEAM 0GEN. No5o 4 '6FO .0 TO STE.AM GEN No64032 6.0 O~rO-olt 60-? ~ 666 002 I 60 6604 660A t aro -40" ZW , F 4 3 4 I woMae o Co C 4 2 IBOD 0.5J t6~.~~1 323 COEN5ATE =TRAGE CloCK 2*0C0 lola AuxlLIARY CEEOWATER .i5-1 4160 1270 CONDEMSE0 NOTWELL CT'4 4 S .4.4 ' O hol ~~I4; 766064b38 6 3w0oS 1~~ 664WD s660661 k.70DR.AA-CARY CEEOWATER 600 u l6 CT TL CT35 CILL*1 3BOO5.56-41 ~ MtPA0, 'PI '12r2 8 .06 C-7.CV 54

  • ro 6441 I "1p *ll 00 CT3G CP3 A. CT3 sP? 20 0 LIE I .1665'CT 35 CT 29 CT-SO30O ,.V4.I__ L 0 m NI 140-6 8WO-47 %5 (06 S-I4 40SF 105 641UTOWl PANEL u F PiW NIROE BOTTLE POWER AUTHORITY OF THE STATE OF NEW YORK? INDIAN POINT NO 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY FLOW DIAGRAM AUXILIARY FEWA TR SYSTEM EBASCO SERVICES INCORPORATED -NONE 32 MF ORIGINAL~00 dM41 h~~1FIGU1 I a 90 0 11 10 INST AR.A R.. 10 FCY-417 I ? D-Iooq I I T 0 1 th I.IM5TR. AIR-I k7-r-_r--r I I a I -b 14 7-1a 16 17 .'is I a a 4 a0 I to i InIs 4 I1I7 IVI LARGE MAIN STEMP USE BRAAIE ACCIDENT INSIDE CONTAINMENT VITTO LOSS OFESITE POWER A U 0 C D p 0 4 i.e 0 STUIATION SEE OERATO CTENIARAN SYSTEMS r 4I 35 55 PUMPS SIPPI.ES MTOR RIVE A -FE Co WATER O SEE O1APRAPUMP PM SSUPPLESIEE M70 UM O E SP SAL ERC AT e SYSTIEMvS MS FOM OTINET3Z LN PN HEA TR%3Fi~tESSNATL me u.F OR IS S RCE N AET SVPRAY IATER PAM P REAOVEY T OL SIINETO REAmCTR COe" OL WATERE ASSURe PROPER eSF AUXILIARY OPEATING O --e- SYSTEMS PON ZSP SYSTEMS TRAIN TRAIN P A,~IT0OROOMDETEMN IT BEE OERATO ATONACIONP q I -1 TRIP MAIN MAI IM8I9L TURBINE Il RLS STOP VALVES LWO TIqboIP PIS TURINE DRIVEN 4.7 A~OMETD APRPUMP TERMINATE MAIN PEED WAER 'W PLWTO RIMI CONTROL PLOTS SG. !1.5235.34 P55 P" FCV ECU 4IT 427 41$7 4A? TERMINATE FEED WATER EIN PLOWA TO BYPASS CONROL I.VALVES SO G.5302.534 34 PE ICV FCY PCV I1L1.II. H43L 44TL _____AUTO TEZIP SEEODO=MEAN OP TERMNN. P04 PIMP MOET VALETS FIN FLO To SAS Pro-Z-SI BED?.SE SECOND MEANS OP TeRMINATING 71W PUMPS PRW PLOW TO S555 ELIMINATING MON-ESSENTIAL POTENTIAL RA NC PROCESS LINE OF RADIOACTIVE AINMENT ISc VI.OS RELEASE S Os ISD ISOLATE SGS MAIN STEA PROM COMMON isOAINVVE COD WATER CONTAINMENT SPRAY To SRYVLE PRESSURE -SUPPLY P01R TO DIESEL ESSENTIAL 50STEMS GENRTR PUMP aSUIPPUIES MTRDIE CO RTR TO SG 31.5Z P UP PUMP al5 SUPPLIES CO WTRTO SSVV3'-S4 SI 3 HEAT TRANSFPER - NT-FEU OR ESP SERI ATER SYSTEMS REMOVE HNEAT PROM CONTAINMENT CONTAINMENT IGFM PROVIDECOTIMN CONTA'INMENTSPAPUS SPRAY WATER READY TO COOL ----AFCTYMJ REACTOR COREPUS ASSURE PROPER OPERATING OWTON ESP AUXILIADY FOR ESP SYSTEMS SYTEMS TRAIN A TRAIN-j -CONTAIMMENT I I I-I-WI 13 14 is1 ITILI -A FIPR AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY SHUTDOWN LOGIC DIAGRAMV EBASCO SERVICES INCORPORATED -oN *P-0OTE 20-81 tc FIGUIGRE I' 15 17 15 U I I ST'1111L 110 515 INITIATIO COAMLNTRLATRTI 53 I~iPA55 S 5 MIPo IN LOOPS InRYA RY4 WIT i I I a a .1 lb 11 14 1 1 is 12 13 is .17 .is is 17-18 PLAUT PROTECT .m wis AWN s cR 'o, S r P 7 PltoTv J "NAL RODS PROPPED RACTR TRIP FISSIOIN STEPPED SNty GAaG ANN RIMAIN CO. TMO4 TURBINe STOP VALVES SAOLE.=SOLENOID TERMINATES PR FLOW TORMINEDRWAER SO 35E535A NCONTOLPVLM E TERMINATE PR PFLOWTO MAP EED WATER SG 3.,3z,3.304 BYWSCONTROL 51.05 OPTEMINTN 7WPUP TEIMATNEO-ETA SMAIN1,T2,35P3 ISOLATI O VLVS SECOND ONE. PL PLO. TO SrSs TEONDUPPEAS OTIMN OTARINATENTG SPRA PUMVS RESSURES IF M~ATEAM 1 2 S 14 5 B I to ii 12 13 14 I 15 IA 17 j.~),,,,P OOT 5LOAtE ClOSE EASE: ArVEC!CO SJEAN, ZENERATOR CLOSE ALL AFW COWTAO'- VAL<t VALVE IN LINE FROM WIVE LINE FRO. MMOR DRIVE. AF. QESPONrE ArW PUUP N, 3Z Pimp MOT CLOSED NOT CLOSED AL.L. VERIFY AFW PUMP CLOVALVE!

w 32 OPERATION SED STOP Pu.;; &RUNNING Q P TURBINE VERIFY AFW 31 3Z b, OPERATION F PUMPS NOT U.N. , PS ST. PUMPS VERIFY w R AFVJ PUM-Z PERArso ;T-&QT -pMuNn- IF NOT UWIN-MG START MPS TM MOTOR MIVEW PUMPS Puh.WG cot OPEQ&T." TURBINE DRIVE. TSTATUS PUMP RUNNING ALL VALVE CLOSED FIRM AFW PUMP 3231a10 STEAM WIE Ost GENE VER.F, 'TE2:..AT::l AUK rEEDWATER VER.FY WN.Rim INO.CATORI-CONTROL OF AFW PU.9 M..3Z PUM' STEPMTO TO GOOD IF T:V STEAM ZP.M.R.. -E GENERATORS _j A'r LZAS rwo STUAM GENERATOK5 ARE WeEDED, L L TEAM _..ERA 4. 'W "ALY prRS NorM_ A W LVE S Ga"e 4" "ST O TEAM GENERATOR EVEL INDICATORS C FW ISV COWT LIR5 To MJUNrM VE ACWUST CONTROLLERS STEM GEN. LAVE, 3TEM STEAM LINE PRESSURE ISOLATION INDICATOR VALVES POS.TION DUMP OR COWO'NSER OUMP VALve _OMTROLLERS A04UST CO-TROLLE i TO DECREASE S TISAM PRESSURE r:Qlly REACTOR COOLANT C DOWN RATE .0 5TFAM PRESSURE AT PSA? yes 1.0 To QRR SYSTEM POWER AUTHORITY OF THE STAT NEW Y(I NDIAN I',iNT NC) SHUTDOWN LOGIC UiA\:RAM SYSTEMS INTERACTION STUDY EBASCO SERVE.. INCORPORATED L7-NONE 0...3-20-81 =:AIIU 77.7I----~--. -, r~~0 -3 14 10 17 U MI I I £999 14 11 G 4 H 0 9 1 ib 11 12 is 14 1 ta is 17-j T-71 -..T-16 17 F 4

0. Pd S jq. N o,~a -g FEED LNE BEAKOIII CONTANMEN~TWflN4U55 bOF OFF SiTPOWER.EBASCO SERVICES 1 NC. DIV. Mwf DR. DATELMQCH-al SCALE 2loKAL INDIAN PIkNT* No B NUCLEAR POWER PLANT SSTEMAS INTERACTION STUDY s!5HUTflOWI4 IOGIC_________________________________________________________________________

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  • I ~* N Reprinted-*From Figure 9-3-26 IP-3'.:Fire Hazards Analysis Revision 1, April 197.7 Power Authority of the -State of:NewYork INDIAN POINT NOl. 3. SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER SYSTEM FIRE ZONES Wi Wk H.-4.1

§d" PIC.TURE UBR JJSPACE HEATER PLAN EL' 18'-6 POER AMHI-ORITY OF T14E 5ThMO(*NEW YOP INDIAN PINT Mo35 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY AUXILIARY FEEDWATER BUILDING EBASCO SERVICES INCORPORATE)) I 141 PlCrU*RE OL INCHES Cm.NUMBER IS PICTURE NUMBER mN*.1 LIGNTINQ FixTuRE fSPACE HEATER 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 .EAPMVDDATE __~if"zjA-7M.2 I I U I... I * ~Ud I 41 V Ia}ImcmI5I -~ flea VALvES 381 CT-83 (I"VIENT)G"CT10-14 39 CT- B6 2 O0. 40 Cr-31 .41 PCV- 1189 42 soV- isl GCT -%07S 43 Cr-B (191 DR.) 441 CT- 25 (a4EC) 45 PCV- I IT 8OCT -107C 471CT-82 zM.481 CTOZB k 15_1 BUILDING Fl RE, ZONE: LOCAe ON WITHIN FFEZN ptWp ? k.e, EBASCO SERVICES INCORPORATED ~ ~DIV4. ADPR R V E i ,--L AR-.)vN =-R .P L ANT DATE L~CH 5'ANTE-RNT 10NW5T.U.Dy SCALE i X N-Tq hA WA I

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XF~W ?UNABILP4 FIRE ZONE:2 LOCATION WITHIN FIRE ZONE: 4 INTERACTION NO.: INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: CS~4 6) ~71c DESCRIPTION OF POSTULATED INTERACTION: 7Va4: CF-2v/EVALUATION & DISPOSITION OF INTERACTION: ~~94~;& --74ec ,nerE6tion Engineer/Date eview r Ebasco ~ervices Incorporated SHEET 3O POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCU1MENTATION SHEET BUILDING: 4Fr W PuL V FIRE ZONE: LOCATION WITHIN FIRE ZONE: Q INTERACTION NO.: COc $d/ INTERACTION SKETCH NO.: 19.~q. 7 9.o-~~ 7 IDENTIFICATION OF INTERACTION COMPONENTS: (5l 7-- 2~ 6i' ~eir& ~- ,EE7ao 2f2)/~DESCRIPTION OF POSTULATED INTERACTION: EVALUATION &DISPOSITION OF INTERACTION: 74 4a",A 210 Interact on Engineer/Date Ebasco Services Incorporated Re e eIDate 0 ?- 0 V fl --17 SHEET %OE 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: 4lP) POA lt FIRE ZONE: ) LOCATION WITHIN FIRE ZONE: INTERACTION NO.: o -c. -tt INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF PO STULATED INTERACTION: ~/'L~eZ /e, EVALUATION & DISPOSITION OF INTERACTION: ~~r/Dafl~Ebasco Services Incorporated hibtera ion Engineer/Date SHEET fFC 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: AFk PMp P 3 FIRE ZONE:-23!LOCATION WITHIN FIRE ZONE: INTERACTION NO.: 0 INTERACTION SKETCH NO.: 06 o-~-e IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: '/01 EVALUATION & DISPOSITION OF INTERACTION: Interact onEnierDt ((1 4e~h~,r Re ew / ate_ Ebasco Services Incorporated SHEET O~ 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: AV= ::L4 POM.P jL~C~ FIRE ZONE:23 LOCATION WITHIN FIRE ZONE:p l INTERACTION NO.: ~i)?4~(~ 9 ,~1/-4 ~C7 2 2 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: 1 ea Initerac ybn Engineer/Date Rv Dt Ebasco Services Incorporated SHEET O POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: AFOJ PUPP i5Lr-tc( FIRE ZONE: LOCATION WITHIN FIRE ZONE: INTERACTION NO.: 09- lc-0 O 0 -q-coj 0Lz INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION:/ EVALUATION & DISPOSITION OF INTERACTION: Int6ractip Engineer/Date Rv Date it : Ebasco Services Incorporated SHEET OF1, POWERl AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 'NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYST24S INTERACTION INTERACT ION DOCIJ}IENTATION SHEET BUILDING: 1 4FTOW UW FIRE ZONE: LOCATION WITHIN FIRE ZONE: INTERACTION NO.: INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION CO' ONENTS:/ / / /DESCRIPTION OF POSTULATED INT. EVIJAIN& ~POIIN/F!'ION:~TERACTION: R~~2/ e /K~rDae Ebasco Services Incorporated Interaction Engineer/Date VALVES GCT. 1075 01 0 No 11oz 103 J041 It

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feracti Engineer/Date SHEET O 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

1 4FW~ T)'j Mi' 5Lt:(x FIRE ZONE: LOCATION WITHIN FIRE ZONE: O INTERACTION NO.: INTERACTION SKETCH NO.: A5 IDENTIFICATION OF INTERACTION COMPONENTS: A 4' ,~1 A /DESCRIPTION OF POSTULATED INTERACTION:. A EVALUATION & DISPOSITION OF INTERACTION: A, Reviewer/Date Ebasco Services Incorporated Interaction Engineer/Date POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: ~ P~(L G FIRE ZONE: LOCATION WITHIN FIRE ZONE: JA INTERACTION NO.: 0.3 / 6 o 3 517 ~ INTERACTION SKETCH N. IDENTIFICATION OF INTERACTION COMPONENTS:/ p I I / / //DESCRIPTION OF POSTULATED INTERACTION~ / / / /EVALUATION &OF INTERACTION: Reviewer/Date Ebasco Services Incorporated SHEET O 5 I 'eraction 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: AFVP 1-(>3 Lb(c FIRE ZONE: LOCAT ION WITHIN FIRE ZONE: INTERACTION NO.: 0L.3~4j~O -~ -y INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: 4'9, 9,* *99 Inter7action Engineer/Date Reviewer/Date Ebasco Services Incorporated SHEET,_O <./ y r I, / SHEET 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: A(PW f?/J/3LW7 FIRE ZONE: ;L LOCATION WITHIN FIRE ZONE: INTERACTION NO.: 3 /.V' INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSI ON OF INTERACTION:-f / *9? / ~ / /Reviewer/Date Ebasco Services Incorporated teraction Engineer/Date VA~LVES ot OZ 03 04 05 -~~ ~- K 1 InI ___-I107 z -- -T-3313 cT-94 454s 5 __ LOCATIO:- IDV.1DR FITRIE.: ZONE D 4-EAC E RVCSINOPRAE I-OrAT 10 N: DIMicDJ APPROVED--7-S:A' TER:%Z-710 F-0 'U T-1 LN Z. r Li"A -T 7 SHEET OF4 POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: AF-W Pum~fp '3112 FIRE ZONE: c23 LOCATION WITHIN FIRE ZONE:t4 INTERACTION NO.:07 O// //-3 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: r~ / I DESCRIPTION OFPOSTULATED INTERACTION: a 4 ,tX C6~EVALUATION & DISPOSITION OF INTERACTION: )/x e I erac -on Engineer/Date A~ CT-32 C~4/4 4 AA20 ~Revioe 4Da t 1 Ebasco Services Incorporated SHEET ZOF 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:4jw U P Lb. FIRE ZONE: LOCATION WITHIN FIRE ZONE: A -INTERACTION NO.: 0 7-02-2i-q-ojlz- !i~ 07)- -?"-' INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACT N:/ EVALUATION & DISP ITION OF INTERACTION: Interaction Engineer/Date Reviewer/Date Ebasco Services Incorporated SHEET POWER AUTHORITY OF THE STATE OF NEW YORK SET O INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY, EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: AFL~J P'mp Balt>C-4 FIRE ZONE: C LOCATION WITHIN FIRE ZONE: N A INTERACTION NO.: 07-o 3-zj -LW Ol7-O03-7-/ 07-o -z-INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS:/ DESCRIPTION OF POSTUL.ATED INTERACT ON: EVALUATION & DISP ITION OF INTERACTION: Interaction-Engineer/Date Reviewer/Date Ebasco Services Incorporated SHEET OF4 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTER ACTION DOCUMENTATION SHEET BUILDING: A4FA) PUMYP i3Lttt 4f FIRE ZONE: 3 LOCATION WITHIN FIRE ZONE: DA INTERACTION NO.: 0o q.. / 7C4Z 4 7 4 2 7-0421-57 0 -04?Z-4 .) 7-q4-25-4t INTERACTION SKETCH NO.:Il IDENTIFICATION OF INTERACTION COMPONENTS:/ DECIPIN FPOTLAE ITRATON* EVAUATON DIPO ONOF NTEACTON terationEngneerDateRevewerDat EbsoSriesIcroae H~G~m4~em QOZ Y-0 9D 3: 031 90 011 0405 SOG. () .Y DD U 01. CTG ~4. ~ I I I I I.4 OZICT-G4 ~3i9 j___ 03ICT ______ --~04 CT ' -2'III I _ _ 5CT-35 _- ~ 0CT-35 8 L4)--' _ ~ -T--84 (tST --______ --* -4 01 C~a4 -4G '615I- vea.)[ I__ __ !i-)T 4 1 4C~4 4 I _ 12 _____CT____8_ -03/4.- -VPLVES5____ __ __ _____ __ __ _ ___ __ __ __ __ ___ _ _ __ __BUILDING : XF~L4OPUMP ~L)-A Z~'L77 'NT ~FI RE ZONE: LOCATION: WITHI N Fl RE ZONE[EASCO SERVICES INCORPORATE% it '-p Is-I-7~ K7T 08 t: 2 0--. F-I I I I ~ _______ I _________________ ________ ____ i********~~**~****** -i _____ ____ 1 .4.......... I -_____ _____ -~ --___ I. _____ I ______ F7i __ _ ---- -4[Tj SHEET _ FA 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: AF\AJ > NUA P -t1 = FIRE ZONE: z 3 LOCATION WITHIN FIRE ZONE: INTERACTION NO.: o -c)*1 ./5O(.O/0511 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: /C-r-2/.) c§7-3o EVALUATION & DISPOSITION OF INTERACTION: eviewerlDat / fg Ebasco Services Incorporated Initeralion Engineer/Date %-I SHEET 2-. OF POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: AFv.) Puti"P 'e FIRE ZONE: 2--3 LOCATION WITHIN FIRE ZONE: INTERACTION NO. C)tb-07. -0q- 131 0(6 02-05" (5 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: ~~t~cC) 3 O DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF Intera ion Engineer/Date INTERACTION: iie/Dat(Ebasco Services Incorporated SHEET )_j OFJe 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: A~yUv -UP'L?1 E3-L-b FIRE ZONE: LOCATION WITHIN FIRE ZONE: INTERACTION NO.: O~0 ' 3 O ~ 3 O 1 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: 2?7- 7 'DESCRIPTION OF POSTULATED INTERACTION: A4 Cyr 5 EVALUATION & DISPOSITION OF INTERACTION: '/4C LU c 42?,r inl Engineer/Date Ebasco Services Incorporated (7~24~ 7') SHEET _ F 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: WO r-iPAk4T-L9=C. FIRE ZONE: 2 3 LOCATION WITHIN FIRE ZONE,: INTERACTION NO.:c( oqoz02-39 INTERACTION SKETCH NO.:, IDENTIFICATION OF INTERACTION COMPONENTS: (7a4~i/ 4, /t(C I DESCRIPTION OF POSTULATED INTERACTION: 7 C~tt444/d CT~4$1 EVALUATION & DISPOSITION OF INTERACTION: Ebasco Services Incorporated Izi'terac ion Engineer/Date i 5 -wl -/: , 6a4l 49 _10' -SHEET $ 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: AR),d /3(e FIRE ZONE: .0;3 LOCATION WITHIN FIRE ZONE:A/ INTERACTION NO.: 05- 37 INTERACTION SKETCH NO.: I IDENTIFICATION OF INTERACTION COMPONENTS: (:.1) cc) -(0x -2,7 7a)C7f- ?J4e .W WJ7eU DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION:. ,..,*Inercon Engineer/Date R ci iwfer/Dat Ebasco Services Incorporated 'v-) SHEET (, 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: 41=Wi- PUM*P 5L0C6j FIRE ZONE: ep-3 LOCATION WITHIN FIRE ZONE: ,J INTERACTION NO. : 00,-/ -4 0(0 0 / 64 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: I ....) ~4cc) 2'A ~T-~ 7A' (/ / DESCRIPTION OF POSTUlATED INTERACTION: / *1 / 'I / 4~f / / I I EVALUATION & DISPOS~ION OF INTERACTION: .5, / / / / I /basco Services Incorporated Interaction Engineer/Date SHEET O 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: F(JK)PdifPTL) FIRE ZONE: LOCATION WITHIN FIRE ZONE: 7' INTERACTION NO.: ~4.7/ ),O -/-6 INTERACTION-SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: 7 DESCRIPTION OF POSTULATED INTERACTION: EVALUATION &. DISPOSITION OF INTERACTION: X,/Ebasco Services Incorporated Interaction Engineer/Date SHEET gOF -, 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: AFI'J PB~t/ FIRE ZONE: g.~/ LOCATION WITHIN FIRE ZONE: A INTERACTION NO.: N -7 1 -60o0 -140 I INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS:/ DESCRIPTION OF POSTULATED I/I p -I I 5' EVALUATION & DISPOSI'rION OF / .7 / I / A' -I. Interaction Engineer/nate INTERACTION: INTERACTION: Ebasco Services Incorporated LdNE 101 14'BFO.- 10o1 o 02j03I 9 FP CD 0 amp, 80~ Az!8l 93J .7 I 1V + 1 84 1 050-O 0 8 3 -S, 07108104)110 "0j I I L *10214:BFD' 10% 81 'jj5f5 _ ..___Zs_ _KI_ _ 10 ds- 10 gelii 107 __em____toll ~so 2181 __________ BUILDING:O XL~FIRE ZONE: 52Ab LOCATION: Lt WITHIN FIRE ZONE EBASCO SERVICES INCORPORATED APPiRO ED 4 1 UtL CR F C) "NE RJ LAT VSI~5 NTER-Tf:>,N15TUDY VT -S.-------fI (f) F w (-5 0 F-I-'-, ntf DO-77__j SHEET._O 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 //t";Sh) FIRE ZONE: .5 LOCATION WITHIN FIRE ZONE: A/A INTERACTION NO. INTERACTION SKETCH NO. 05O./01/- eo/ez).,5 011C p 20 11& ,1 mA 2 050/107- 60/1 P IDENTIFICATION OF INTERACTION COMPONENTS: 4",3FL /cA9,100 6x3 i'co--l .C "-1211A15- /0/7' DESCRIPTION OF POSTULATED INTERACTION"A~~/i 4 45 p EVALUATION & DISPOSITION OF INTERACTION: Intera ,on Engineer/Date Ebasco Services Incorporated R viewer/a C)Jojjj SHEET2 O0F 7 POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: A e P(Jt Po DL47 FIRE ZONE: £T A LOCATION WITHIN FIRE ZONE:/4 INTERACTION NO.: 10O ~.-'~ / 5O (3)/ / INTERACTION SKETCH NO.:C 0Z / 7 6 IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Interac tibn Engineer/Date ierDt Ebasco Services Incorporated SHEET OF 7 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: AFAJPR41^0 IPG$ FIRE ZONE: 6~ LOCATION WITHIN FIRE ZONE:1V/A .INTERACTION.NO.: 95~- /o-z, 0-3 -/0 '-eZ S, 03 -/ Aa$ , O1O3 r INTERACTION SKETCH NO.: IDENTIFICATION.OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: (111*1.5 /O) W0-0 EVALUATION & DISPOSITION OF INTERACTION: 61AL~T~' lee*k/Ebasco Services Incorporated Ifiteraction Engineer/Date , le / SHEET 4OF 7 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT,3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUME~NTATION SHEET BUILDING: A~ d' ~~ FIRE ZONE: 5 4 LOCATION WITHIN FIRE ZONE: INTRATIN N.:/~.&A /C6O //o INTERACTION SNEC.: O. IDENTIFICATION OF INTERACTION COMPONENTS: 7)) {~gi L/-I -DESCRIPTION OF POSTULATED INTERACTION:-el"voc' D EVALUATION &DISPOSITION OF INTERACTION: / ~ _1/v i1hterac Aon Engineer/Date Ebasco Services Incorporated SHEET S:OF 7 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUNMEN TATION SHEET BUILDING: Aj'f PUa1w 3LD*FIRE ZONE: 52A LOCATION WITHIN FIRE ZONE: ^-1A INTERACTION NO.: 57O-O/3 O ~ 9-o-~ INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMdPONENTS: 'VJCI)DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: / 6V41 e~eAV Interactiq6 Engineer/Date Ebasco Services Incorporated SHEET OF7 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILD ING: ,P/2/t Ic FIRE ZONE: 52A7'LOCATION WITHIN FIRE ZONE: INTERACTION NO.: 0p5-C( O4 /0-061-04 INTERACTION SKETCH NO.: IDENTFCTOe FITRCTO OPNNS DESCRIPTION OF POSTULATED INTERACTION: 7Z ,,4'EVALUATION & DISPOSITION OF INTERACTION: VqA' Interaction Engineer/Date Ebasco Services Incorporated z 5 , ' " , el 769 -, 7.V. 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LX>C FIRE ZONE: b LOCATION WITHIN FIRE ZONE: U INTERACTION NO.: INTERACTION SKETCH NO.: L-(k) ueeP IDENTIFICATION OF INTERACTION COMPONENTS: 00 e C,5e 4 T oA/ Ale bO DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Interaftion Engineer/Date Ebasco Services Incorporated SHEET /6:OF Y 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-L)//i'.P , FIRE ZONE: 3 LOCATION WITHIN FIRE ZONE: 1A/A INTERACTION NO.: 01-/ 0 / INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: eP" ~M7e&,411a &sAe 4;75 4?"C7-10.71£/4L EVALUATION & DISPOSITION OF INTERACTION: aeP7A6c C!Z)7A7C 4 Interafftion Engineer/Date RepeiD Ebasco Services Incorporated L-i SHEET/f OF POWER AUTHORITY OF THE STATE OF NEW YOrRK INDI.AN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 1 4F,41 ?41'1,oo 13D FIRE ZONE: 93 LOCATION WITHIN FIRE ZONE:,jM INTERACTION NO.: Q. r./5-5 INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: '/~t~4~(5 ~A;"40i~5l ac s-, DESCRIPTION OF POSTULATED INTERACTION: NQ3/,3/7, EVALUATION & DISPOSITION OF INTERACTION: 7 ~/e447 44 Intra(kin Engineer/Date Ebasco Services Incorporated R(ywler / ate t--" V) 10 )91 SHEET /3OF POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: ,4?J/($AL) FIRE ZONE: 9.13 LOCATION WITHIN FIRE ZONE: AJ4 INTERACTION NO.: 0/- UP? z INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: (7~yf)4" 1 FD -/Cw /~e'~~ flow ~~i0 DESCRIPTION OF POSTULATED INTERACTION: ~~O44{y4 $&" 43{A'3 EVALUATION & DISPOSITION OF INTERACTION: Ao~t /.)d 14cp o o Interact ion Engineer/Date Re /Dte Ebasco Services Incorporated SH{EET&Z 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 BUILD INGY4/~ , FIRE ZONE: A~23 LOCATION WITHIN FIRE-ZONE: AIA INTERACTION NO.: 6)/- 09 ~ INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: 7/A 6Q~E ~'~; 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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: 19Z m Y 3Lj~ & C r FIRE ZONE:6; LOCATION WITHIN FIRE ZONE:I A INTERACTION NO.: f- 08-0.3 -/3 INTERACTION SKETCH NO.: F-I6L/Pe 5:-l 19#07'0 3 IDENTIFICATION OF INTERACTION COMPONENTS: a4ce 12u5j7eCM 6Vr7'&e ,aw. 0 6r-1.71APri ?41..je /o v 4m -,0 i4 A -DESCRIPTION OF POSTULATED INTERACTION: Rau~~ Swle RowrA 41 /Tof* 1r.35 4AO 1f AdD #/j-5 EVALUATION & DISPOSITION OF INTERACTION: .A 0-oi 4 0e o eS 7A F-~?Trteractdon Engineer/Date Ebasco Services Incorporated ie'(der/Da-te V) to h SHEETQ& 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: 4 FAU 1,?tlwpo $Zoc FIRE ZONE:C2 LOCATION WITHIN FIRE ZONE: I INTERACTION NO.: co/ 07-0c3 -/3 INTERACTION SKETCH NO.: Fi-l&ae -~~' IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: ' ewe 4A<Li~-01'De -9!Ebasco Services Incorporated Interaction Engineeiifate ." 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If FIRE ZONE: 0, LOCATION WITHIN FIRE ZONE: NA/A INTERACTION NO.: 0- C)7- 07-0/ INTERACTION SKETCH NO.:. -7uE~ -P~a7#0 IDENTIFICATION OF INTERACTION COMPONENTS: (7e6) 0'A0V)Pu'nP S,~ ~ * ~J&'A DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Iner/ion Enginei r/Oate~e Ebasco Services Incorporated SHEETO 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 .,lu/ /~ ~~ i4 FIRE ZONE: 3 LOCATION WITHIN FIRE ZONE: IV INTERACTION NO.: oI- ol-C03 -13 INTERACTION SKETCH NO.: /6 5 P , 4io 0 / IDENTIFICATION OF INTERACTION COMPONENTS: (f t-i&. ; '2 ISu','L 7,-, ra, Dw i , 4 rnpm !932, DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Inter& tion Engine~r ate RE e/ate Ebasco Services Incorporated SHEET Or OF POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: c ?u q/l &&r FIRE ZONE: LOCATION WITHIN FIRE ZONE: ~1 INTERACTION NO.: 't INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: ( 'P cec C) 6,44j i7We' DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Interaction Engineef/V'ate Re eker/Dt Ebasco Services Incorporated SHEETOV OF4Q 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: Aox FEDpuvmW' Ltoc FIRE ZONE: LOCATION WITHIN FIRE ZONE: JA INTERACTION NO.. c o4-&)e -lo INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: 5PAC E /A,--/4 z# A41, 5 6py' /745i 4'1~ 7 AA)O)EVALUATION & DISPOSITION OF INTERACTION: Mt 6AL)AR01 Interaction Engineer/Date Ebasco Services Incorporated wer/D t SHEET 01OF POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 40Qf FIRE ZONE: 23) LOCATION WITHIN FIRE ZONE: N INTERACTION NO.: 0/-C -I C 0. 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Afrvj Pump aumcinJ FIRE ZONE: 2 LOCATION WITHIN FIRE ZONE: INTERACTION NO.: 335-0/ /00) )INTERACTION SKETCH NO.J5-4/.IDENTIFICATION OF INTERACTION COMPONENTS: (- ar-re ) 4 1 00 nd u ly'7 55 -25 5/ /rl, ,4FW Pm~n- y3 conciatl 66 .SCe-,5 DESCRIPTION OF POSTULATED INTERACTION: r-ltfec 16 r 9 clperv~*co i Cv'-s EVALUATION & DISPOSITION OF INTERACTION: 4: -C~e9r' -F64ev2-16 Interaction Engineer/Date Ebasco Services Incorporated 02-05 -/00 (/O7e 7) %--etKf5x5 CWhilci af7(-p))e4o /00 viewer/rate SHEET 2OF4 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: Acu pmp a /,. FIRE ZONE: 3 LOCATION WITHIN FIRE ZONE: N INTERACTION NO.: 30 ~//7 3 -~ 5 ~ ' INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: (.5cuLrce) 2~evds r CleI' 6-oc AFWP ~f m4y# DESCRIPTION OF POSTULATED INTERACTION: 7v EVALUATION & DISPOSITION OF INTERACTION: A4cre 7~ b/e -bi -A CotI,<4 S1e41io , v 704rVer~ Interacti-on tngineer/Date aevewrDtel Ebasco Services Incorporated SHEET 3 OF 2 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUM~ENTATION SHEET BUILDING: FIRE ZONE: 2 3 LOCATION WITHIN FIRE ZONE: , INTERACTION NO.: 33- 0,3 9-c 0j 0e3/ -,o INTERACTION SKETCH Nl _1, phoata /05)1 04/IDENTIFICATION OF INTERACTION COMPONENTS: n -2" d ur4ed60 Cev~~u1 crC-G.4 Ctrldc*. 60 SKX-a F01r Pcv-//87 DESCRIPTION OF POSTULATED INTERACTION: %ai'/J L%~, c?~~d h ~4 /aC1e~~,.5L, Ip~EVALUATION & DISPOSITION OF INTERACTION:

4 C<Ce P~cob/-2 1e&0 1., '7 0(044 r C;e m 's It e 7 po, 2-le& Interaction Engineer/Date Ebasco Services Incorporated 2 e 04ju1" Neieer/at4 AFaj Pump meldol ,f okovi 0 P SHEET 40 F POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET 4Fa -Poe,? Rael.rl FIRE ZONE
i; 3. LOCATION WITHIN FIRE ZONE: AJ A< INTERACTION NO.: 33-0~4-06-10../

3O '-C7/INTERACTION SKETCH NO.4 $ --e., P040 9 A/ C)/IDENTIFICATION OF INTERACTION COMPONENTS: 'y~*ce)~AFWPupP #n4'.#3 Fee/et~,,c~'s~9 7 DESCRIPTION OF POSTULATED INTERACTION: 471nd 14 6 9h EVALUATION & DISPOSITION OF INTERACTION: 4 Ccep'/ab4 2e~cJ~ -/,F 11-1-01 7flx /a-ttS4 4 ,, t'vedu ,A Interaction' Engineer/Date

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FIRE ZONE: 2 3 LOCATION WITHIN FIRE ZONE: /A INTERACTION NO.: 33- 102-1-105-,"- ~o, 3i-' 0 3 3 /: 3'5 3-18-12/OS>, 3./,'/O INTERACTION SKETCH NO.: -41, pho /6S IDENTIFICATION OF INTERACTION COMPONENTS: 7~ceriob0 CCc-4 Si2L3Z DESCRIPTION OF POSTULATED INT ERACTION: EVALUATION & DISPOSITION OF INTERACTION: ,4C ce#~ b)C Ac~I-~2~csi~j /'elle z ~ flc4P Ac, eca r7~Rev, wer/Date Ebasco Services Incorporated Interaction tngaineerlDate 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 7 a M a /u FIRE ZONE: 23%LOCATION WITHIN FIRE ZONE: IA INTERACTION NO.: INTERACTION SKETCH NO.: .ClS -4/., 04~4 0 T IDENTIFICATION OF INTERACTION COMPONENTS: gx #S x-,oc- -/& ' e-- I1e DESCRIPTION OF POSTULATED INTERACTION: 6' ~-ni/sA& ;k sv)O0 "Ih'?C 6 S~EVALUATION & DISPOSITION OF INTERACTION: V~e- er/ate Ebasco Services Incorporated 14/J- CeIb /e Soa~o n~)7 1 Bay.Interaction Engineer/Date 3.3 -/q-/l--/0(0 n ls oc(rre : ro , 'j (.- h .-r4-A4mdtd,-m --SAOS-,3 box ,-4t c4tf4t arol 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 FIRE ZONE: 7~W~If~ &~UU 2 7 1? 3 LOCATION WITHIN FIRE ZONE: AJA INTERACTION NO.: 3 3-ze)-11-106 INTERACTION SKETCH NO.: r-rT-l IDENTIFICATION OF INTERACTION COM*2ONE] ~urce pa~ce /ee er: Roc)e ~X 2aZ ra ec(n 00Oil Z l' -/j 0=33-2b-/~-/O5 53-ZO-/3-/O Phcy/o /o, ~A f1v-1136sA DESCRIPTION OF POSTULATED INTERACTION: ,%Ap)Pt e'-4 rl EVALUATION & DISPOSITION OF INTERACTION: 61n c4 Fp-Ob/Ebasco Services Incorporated H~ kC7e7~Interactibn Engineer/Date 4a'JIk AeviyerDate T,94*Aad-l" tS ox I& )( 2 3 Z G?,ld CO-rdat'7 eJ;// c;l;,5,etbk .41v y FC- 113,C' Cn4 jc-c-llesA 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 -//3/7cq 0 3 6-/-/~) INTERACTION SKETCH NO.: IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: ccd<4 '4' 6,1 10) EVALUATION & DISPOSITION OF INTERACTION: L. 41 -001 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: FIRE ZONE-: LOCATION WITHIN FIRE ZONE: ,J/4 INTERACTION NO.: z Z 3-3 -2I INT ERACTION SKETCH NO.: pe/o1s IDENTIFICATION OF INTERACTION COMPONENTS: G~1& 0 DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Vz'4 C, fP I 6/4 ere 4'C-V*4/A Ab 4- w)' exws*V4 4~"L A40n ;I/6s-o "c "CAJ//y)ct hove sLvA C,#t v-nass Z cLLLsa- a,,,/-$ 7 C ::R 2- y Interaction Engineer/Dat a1/ :e Revwe/ai Ebasco Services Incorporated ran">~ nost~, ,4,c44j fdrnf 4AX,'Id_' ' I n : S'w u rre e4 Ue+.s feam appr.6 K. 8 .o " "m SHEET /8OF 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: 4FAJfJI4?w'. FIRE ZONE: 2)3 LOCATION WITHIN FIRE ZONE:/V INTERACTION NO. : 3.3 f.~y ,6. 3 -,96 -0, 2/I,3-O INTERACTION SKETCH NO.:-3 30 4 9 A-~~ ~-4<, ph o~to / 46 IDENTIFICATION OF INTERACTION COMPONENTS: n-w~ // ,% jconcdartJ- ~ S)-DESCRIPTION OF POSTULATED INTERACI]Ceo d) C , k-9)Zi3 I/ Ycm~ION: ,Ys\t 0 ,f O /54, EVALUATION & DISPOSITION OF INTERACTION: -~~~Ye jAC%~ -I t5S~ i Cfl 11a~ qec ( c -/: -fF Interaction ~ngineer/Date de4 Ov ~ G~v7 L na &7C eg/'Re /ewer/Datej/ Ebasco Services Incorporated -,ray S SHEET / ?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: ,4FWA -pupO aeu '/0 4 cJ FIRE ZONE: 23 LOCATION WITHIN FIRE ZONE: AJA INTERACTION NO. : 33 -.3/02/4// 3.3- 3 i INTERACTION SKETCH NO.: ~IDENTIFICATION OF INTERACTION COMPONENTS: ,2~Ce- i~pe X -32 ra~y DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: Interaction' Engineer/Date 06Lpcd tlnci Rev ewer/Date Ebasco Services Incorporated pxx o // =-L4 r ei Ue. 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~77Z', DESCRIPTION OF POSTULATED INTERACTION: LA C 1 stt4t J ~ Es*I ~C~-4~e~?~PPh ~ .'-7r r74/EVALUATION & DISPOSITION OF INTERACTION: 0 VeOny v~~j 4 Y1e cetb/e tcm Rev wer/Date/ /Ebasco Services Incorporated ( 7-c-e~t)~A~(e k/e~d.ei. 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Tt(,PC%:fS 4 it Diro;o anc( /7,-/ Cokb/e Wa a I Is ELECT RICAL I L C Of Ii.NO-en. 'U I 1' T P V I -06G1071 IL ('j tS d; to Lo [ Z LO 104 -1 5 I 08 w I :3 a U. U.I0 IW 4(1-SOUF\~I ~d (4 I -~ L IG ox 21AABE -___ -t 1 9 Ccu -at -q08)7__H_ ___ 1 ~-20 YelTmLATI ON-FARS 11 21LOCAL Dar_ __s4o P"3__2 ____ ___ ___ ____ ___ _ -I -I K 7 7 j --' I _ _ _ _ _ _ _ _ _ _I _ _ _ _ _ _ _ _ _ _ 1 BUOLDING : FI RE ZONE: LO CATIO01': WITHIN FIRE~ --. -.. -.. -- --.--~. ---EBASCO SERVICESINCORORAOrDD.~ji DIV DR.fi.% APPROVED ~ CE~~~~ DATE3~~H~L~~ftr~!Tc. -~ SCAL~J~. 4~~ZIN!" T.t~ P'I ~ 4 No E~ ~@~--f6 ZONE 1091 0 SHEET [ OF 9;--POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET Ap-iA./ yotumpaufly FIRE ZONE: 5 LOCATION WITHIN FIRE ZONE: A/A INTERACTION NO.: <-// /c')/2,o7 INTERACTION SKETCH NO.: F~ 54(,ph IDENTIFICATION OF INTERACTION COMPONENTS: DESCRIPTION OF POSTULATED INTERACTION: 107 , Ix -3 2 z(4 4BF-)" IS f~ppbYt e?,~Cf 2" /~Ti~C"l-*he L~EVALUATION & DISPOSITION OF INTERACTION: +/k care +n~lp1Iec/4-CCep4~k <: C : 2n z- R Interaction Engineer/Date e~~na,O lce7~b/e c.doge .O dleemedA 4v 4vie we r/ D t Ebasco Services Incorporated BUILDING: ke 4,-Is dllr" SHEET aor9 POWER AUTHORITY OF THE STATE OF NEW4 YORK INDIAN POINT 3 NUCLEAR POWER PLANT SYSTEMS INTERACTION STUDY EXTERNALLY INDUCED SYSTEMS INTERACTION INTERACTION DOCUMENTATION SHEET BUILDING: 4&W Fu mp 4uQ.FIRE ZONE: 9 a LOCATION WITHIN FIRE ZONE: A/A INTERACTION NO.: 4-O // % 3 ~ -? 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C 4~;2/-/ Interaction tngin-eer/Date PR ewer/Dao Ebasco Services Incorporated SHEET OF~. e 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: A FtAJ 4Punf)J ,~'J FIRE ZONE: 2 3 LOCATION WITHIN FIRE ZONE: A/A INTERACTION NO. : 341 4? -/0 INTERACTION SKETCH NO.: s-~ photo /tl IDENTIFICATION OF INTERACTION COMPONENTS: 50ureeC : Su4 box ;CA4 -1 DESCRIPTION OF POSTULATED INTERACTION: EVALUATION & DISPOSITION OF INTERACTION: dee0.o7e CC -66'yl ~~4 ~ o n 1/Cf dcicx~ Cjher7 'Trockh 'by ho F I~nteraction Eikgineer/Date R eeDa Ebasco Services Incorporated SHEET, 0 OF F 62 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: 4FA L i LiW~FIRE ZONE: 23 LOCATION WITHIN FIRE ZONE: AJA INTERACTION NO.: .341~ -0 /'INTERACTION SKETCH NO.: pb~ 4. pdc o(5 IDENTIFICATION OF INTERACTION COMPONENTS: S u L4(ee : e

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