ML18038A334

Forwards Rev 2 to Updated FSAR for Nine Mile Point Unit 2 & Annual Safety Evaluation Summary Rept

ML18038A334
Person / Time
Site:	Nine Mile Point
Issue date:	10/31/1990
From:	Wilczek S NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18038A335	List: ML18038A334
References
NMP2L-1258, NUDOCS 9011090077
Download: ML18038A334 (597)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM t1czek, Jr.Vice President Nuclear Support Subscribed and sworn to before me thr sun day of~C, 1990.Notary Pu lic DlANE R.NlMBALL pub"c5rno Srarsof Nrrrr Yore daga Cotrmy t3o.493@@Qtrardlod In Onondaga My Commlsslon Explros Enclosure to NMP2L 1258 NINE NILE POINT-UNIT 2 SAFETY EVALUATION SUNNARY REPORT Docket No.50-410 License No.NPF-69 0

Safety Evaluation Summary Report Page 1 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 87-063, Rev.1 Mod.PN2Y86MX162 Fig.11.4-1a Solid Waste Management System (WSS)Title of Change: Seal Water to Waste Sludge Pumps Description of Change: An existing waste sludge transfer pump was replaced with two new centrifugal slurry pumps (2WSS-P50A 6 B).Additional pump seal water supply and return lines were connected from the existing lines for the second pump;one new manual isolation valve was provided on each of four lines.This change was previously reported in letter NMP2L 1177, dated October 26, 1988.An additional change was made, based on Revision 1 of the safety evaluation, to minimize wiring changes.Flow element 2WSS-FE103 was relocated to upstream of valve 2WSS-V308 (from downstream) on the same line.Safety Evaluation Summary: The solid waste management system is not safety-related and is not required for safe shutdown of the plant.Relocation of the flow element does not affect its operation as it is still located on the common pump discharge piping.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.NOTE: This safety evaluation revision is being reported at this time in support of the changes to USAR Figure 11.4-1a, which was revised in USAR Revision 1.

Safety Evaluation Summary Report Page 2 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 87-118, Rev.1 Mod.PN2Y87MZ132 Figures 6.2-38 (Sh.5), 6.2-71a, 6.2-71b System Containment Atmosphere Monitoring System (CMS)Title of Change: Add PSIA Pressure Monitor for Drywell and Suppression Chamber Pressure Indication Description of Change: 0 Technical Specification 3/4.6.1.5 requires drywell and suppression chamber internal pressure to be maintained between 14.2 and 15.45 psia.Previous pressure monitors only read out in psig.This modification added two (2)transmitters and two (2)control room indicators with psia scales.This now enables pressure monitoring in the Technical Specifications identified scale.The new monitors are identified as 2CMS*PT178 and 2CMS-PT179.Safety Evaluation Summary: The added equipment of this modification only performs a monitoring function and does not impact the safe operation of other operating equipment.

No safety-related functions are affected.Although it does not perform a safety function, 2CMS*PT178 is designed and installed as safety-related since it shares"a common sensing line with 2CMS*PT1A, which is safety-related.2CMS-PT179 is installed as nonsafety-related.

It shares a sensing line with 2CMS-PT168.

This sensing line utilizes a safety-related excess flow check valve to protect the integrity of the primary containment in accordance with Regulatory Guide 1.11.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

0 I 4 p4'(!qt.I-l~'~Saf valuation ,Sum;;y Report"Page, 3 of.112 j7 v af Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 87-148, Rev.1 Mod.PN2Y86MX184 Figures 9.3-5j, 11.2-1f, 11.2-1h System: Title of Change: Liquid Radwaste System (LWS)Waste and Regenerator Evaporation Reboiler Cleanout Description of Change: The piping from the waste evaporator reboiler bottoms was 3/4" and connected to valves V516, V517, V574 and V575.During startup, these lines became plugged due to sodium sulfate (NA,SO,)crystallization.

In order to correct this situation, the piping size was increased to 1-1/2" and the current valves were replaced with pairs of valves.Flush connections were located between them.A warm water flush line and hose were also added.Existing heat tracing was removed and new heat tracing installed.

Safety Evaluation Summary: This modification has no effect on safe shutdown or safe plant operation.

All modification work was performed in accordance with the requirements of Regulatory Guide 1.143.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.I ce>~>S Safety Evaluation Summary Report Page 4 of 112 Safety Evaluation No.: Xmplementation Document No.: 87-151 Mod.PN2Y87MZ187 (Partial)USAR Affected Pages: 9.4-45, 9.4-6, (sh.4)19 (Sh.9.4-2c, 32, 9A.1 2~3 1 3 9.4-46, 9.4-47;Tables 9.5-1 (Sh.8), 9.5-2 Figures 1.2-2, 1.2-1), 8.3-3 (Sh.2), 9.4-14 (Sh.1), 9.5-3 5g 11 3 2g 12'1 12.3-34, 12.3-46 System: Title of Change: N/A Relocation of Z&C Shop Description of Change: This modification is one of a series designed for Control Room enhancements.

This modification converted the service room, elev.261'-0" of the service building, to an I&C shop, and proposed additional work to the existing Z&C Shop at elev.288'-6" in the control building.Work completed on the new ZGC Shop included room finishing (drop ceiling, tile floor, drywall and paint), replacement of existing heating and ventilation equipment with new HVAC system, revision to existing fire protection water sprinkler system and associated electrical work.Proposed work on the existing ZaC Shop includes room finishing and electrical work.This work is still in process;therefore, this USAR revision only reflects work completed on elev.261'-0" as of April 30, 1990.Safety Evaluation Summary: This modification converted the service room, elev.261'-0", to an ZaC shop and allows completion of work on another.This modification does not affect any safety-related systems and has, no effect on the safe shutdown of the, plant.Components added to the existing I&C shop in the control building (elev.288'-6")are not seismically supported (i.e., drop ceiling and lighting).

A failure of such components will have no impact since no safety-related components are located in this area.

Safety Evaluation Summary Report Page 5 of 112 Safety Evaluation No.87-151 (Continued)

Safety Evaluation Summary: (Continued)

Fire load increases have been calculated.

This modification does not affect the Appendix R safe shutdown analysis.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 6 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 87-175, Rev.2 Mod.PN2Y87MX259 (Partial)Figure 10.1-6a Feedwater System (FWS)Replacement of Paul Monroe Hydraulic Actuators with Limitorque Motor-Operated Actuators, 2FWS-LV10A, 2FWS-LV10B, and 2FWS-LV10C Description of Change:Due to high failure rate and maintenance frequency, the existing Paul Monroe electrohydraulic actuators for feedwater control valves 2FWS-LV10A, B, C are in the process of being replaced with Limitorque electrically-operated actuators.

The modification of each valve includes the following:

1)removal of existing actuator and installation of new actuator, control panel and transformers; 2)rework existing conduits and cables and install new conduits and cables into local control panel, transformers and valve actuator;3)revisions to the position indication loop which requires change-out of transmitter card for current/voltage converter in panel P825 (Foxboro cabinet);4)minor rewiring in P825;5)the existing control circuit, contactor, and overloads in the affected MCCs are to be removed, as the MCCs have only a thermal/hydraulic magnetic breaker for these loads.The feedwater control system gain change logic is removed and is set at a fixed value for all valve operations.

The cavitation interlock and the feedwater runback loss of signal bypass are maintained in the control circuits.USAR Revision 2 reflects the installation of the motor actuator on 2FWS-LV10B, which was completed prior to April 30, 1990.The balance of the modification is ongoing.

Safety Evaluation Summary Report Page 7 of 112 Safety Evaluation No.Safety Evaluation Summary: 87-175, Rev.2 (Continued)

This modification is not safety-related.

The m'odified valves are located in the turbine building, and no safety-related equipment will be impacted.No new transients will occur as a result of this modification.

System response was tested both with and without the gain change logic during power ascension and was satisfactory in both configurations.

This fixed gain is standard GE BWR design.The new design does not change the response of the valves to an ATWS event.Based on the evaluations performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 8 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 88-039, Rev.2 Temporary Mod.88-138 N j'A Breathing Air System (AAS)Temporary Capping of Safety Valve 2AAS-SV126 Discharge Line Description of Change: Frequent lifting of safety valve 2AAS-SV126 was causing breathing air system compressor 2AAS-Cl to run excessively to maintain acceptable system pressure.The operating pressure of the compressor was originally changed to 90 psig to provide greater margin over the safety valve setpoint.This change was previously reported in letter NMP2L 1239, dated June 11, 1990.Due to insufficient air volume availability with the compressor operating at 90 psig, the operating pressure has been raised to 9S psig, and safety valve 2AAS-SV126 has been disabled by capping its discharge line.Safety Evaluation Summary: Disabling safety valve 2AAS-SV126 allows system pressurization without unduly deteriorating compressor 2AAS-C1.System protection from over-pressurization with safety valve 2AAS-SV126 capped is provided by safety valves 2AAS-SV127 and 2AAS-SV128, which have the same setpoint and are located just downstream.

There, are no valves between 2AAS-SV126 and 2AAS-SV127 to prevent protection of the affected portion of the system.This temporary modification is expected to remain in effect until final implementation of a permanent modification which is currently scheduled for October 1990.

0 Safety Evaluation Summary Report Page 9 of 112 Safety Evaluation No.88-039, Rev.2 (Continued)

Safety Evaluation Summary: (Continued)

The breathing air system (AAS)is not safety-related.

Zt is designed to provide air suitable for breathing at breathing air stations for use by unit personnel during potential or actual airborne contamination situations.

The temporary modification will have no impact on the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 10 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 88-046 DRF L12-00766 N//A Fuel Extended Load Line Limit Analysis (ELLLA)for Cycle 1 (100%Rated Thermal Power to 96%Rated Core Flow)Description of Change: The configuration of the power flow map was modified to allow operation at 100%power at core flows less than 100%of rated (108.5 million lb//hr).Specifically, operation down to a minimum of 96%rated core flow at 100%rated power is allowed, as well as operation above the 100%rod line (as defined within the safety evaluation).

Safety Evaluation Summary: The limiting USAR Chapter 15 transients (Feedwater Controller Failure and Load Rejection with Bypass Failure)at the ELLLA 100%power intercept point (100%Rated Thermal Power, 96%of Rated Core Flow)are bounded by the license basis point (104.3%Rated Thermal Power, 100%Rated Core Flow).For equipment out-of-service previously identified, the MCPR limit is not affected by ELLLA operation.

The analyses results also show that operation in the ELLLA region is within allowable design limits for overpressure protection, stability, LOCA, containment, reactor internals and ATWS events.Operation of NNP2 within the ELLLA window concurrent with single recirculation loop operation or 2 SRVs out-of-service is an unanalyzed condition and is, therefore, not allowed.Based on the evaluation and analyses performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 11 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 88-059, Rev.1 Mod.PN2Y87MX134 9.5-6;Tables 9A.3-1 (Sh.4), 9A.3-6 (Sh.5);Figures 9.5-3c, 9.5-3b, 9.5-3a, 9A.3-7 System: Title of Change: Fire Protection CO~System Provide Cross Zone Auto Actuation to CO, Zone 757SL Description of Change: Fire zone 757SL, as previously designed, required only one detector to activate to initiate CO~suppression in the turbine alternator exciter enclosure.

This modification provided cross zone actuation to fire zone 757SL (changed to 757XL).This prevents unwanted CO, actuation by requiring two detectors (one smoke and one thermal)to be actuated.This modification is consistent with other total flooding CO~systems.Safety Evaluation Summary: This modification prevents a single spurious actuation of a detection loop from initiating unwanted CO~flooding.The installation of the cross zone actuation complies with NFPA Standards 12, 72D, and 72E.This change to the fire detection system does not affect the safe operation or safe shutdown of the plant.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 12 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 88-077 Mod.PN2Y87MX233 11.3-5;Figures 11.3-1a, 11.3-1b System: Title of Change: Offgas System (OFG)Add Sample Pumps to Offgas H, Analyzer Description of Change: This modification modifies the H~analyzer portion of the offgas system to correct identified problems with the operation of the instruments.

The following changes are included: 1)Installation of a sample gas conditioning system, upstream of the hydrogen analyzers 20FG-AT16A/'B and upstream of 20FG-AT115, to control moisture content of the sample.2)Installation of an air eductor in the common discharge line of the subject H, analyzers to maintain a positive flow to the analyzers, thus assuring sample capability.

Three flow switches and annunciation are added to provide indication when flow and sample capability is lost.A manual pressure control valve and a local pressure indicator are installed on the air supply line to the eductor.A check valve is also installed on the air supply line to prevent cross contamination from the offgas to the instrument air system.3)Relocating the H2 sample discharge line connection, including a new root valve, further downstream of the freeze-out dryers to alleviate problems with freezing of the root connection.

The existing root valve (V25)is capped in-place.

Safety Evaluation Summary Report Page 13 of 112 Safety Evaluation No.88-077 (Continued)

Safety Evaluation Summary: This modification to the nonsafety-related offgas system enables it to properly monitor hydrogen concentration as required.This does not affect the operation of any safety systems and does not affect the safe operation or shutdown of the plant.The release rates of the offgas system are not affected.The new instrument air supply to the H, analyzer discharge line does not impact the capabilities of the instrument air system, and provisions, have been made to prevent cross-contamination from the offgas to the instrument air system.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 14 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 88U-110 EE-80 Series Drawings Figures 9.5-5 through 9.5-39 Communications Systems Plant Communications Plans Description of Change: This change revises the USAR communication plan figures based on the reissuance of the associated source engineering drawings.The reissued drawings incorporate changes to resolve comments resulting from the independent verification review conducted by Niagara Mohawk's internal Nuclear Compliance and Verification group (partially satisfies the commitment made in Item 1 of NMPC letter NMP2L 1217, dated November 29, 1989).These changes affect only the background detail shown on the drawings, and do not involve any actual changes to communication systems devices.Safety Evaluation Summary: The revised USAR communication plan figures depict an increased level of background detail, but do not involve any actual changes to communications equipment such as handsets, speakers, amplifiers, strobe lights, jacks, or telephones.

Since the effectiveness and reliability of the communications systems is not diminished, these drawing changes do not involve an unreviewed safety question.NOTE: Safety Evaluation 88U-110 is being reported again at this time to address the reissuance of the source engineering drawings.All additions/relocations of communications systems equipment have been addressed in Safety Evaluation 88U-110 and were previously reported in NMPC letter NMP2L 1198, dated April 28, 1989.

Safety Evaluation Summary Report Page 15 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 88U-121, Rev.1 LDCNs U-1295, U-1296 Listed Below Suppression Pool Hydrodynamic Analysis, High Energy Line Break Whip/Jet Impingement Evaluations, Spent Fuel Pool Storage Racks Title of Change: Miscellaneous Figures-Updating Due to Source Verification Description of Change:This modification describes changes to FSAR figures resulting from source document verification.

Where source documents (drawings, calculations, etc.)have been revised or superseded, the figures have been updated to reflect the changes.This safety evaluation was previously reported in letter NMP2L 1198 dated April 28, 1989.Additional corrections/updates have been made for the following:

Page 6A.2-9 Figures 3.6A-56,-57,-58,-60 Figure 6A.1-3 Figure 6A.2-6,-7 Figure 6A.4-39 Figure 9.1-3 Safety Evaluation Summary: The identified USAR changes are due to revisions/superseding of drawings or calculations.

These changes do not involve any actual plant changes, do not affect plant performance or reliability, and have no impact on station procedures.

Based on the evaluation performed, it is concluded that these USAR changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 16 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 88U-323 LDCN U-1081 12'9g 12'10'2 3 13'2.3-15; Figures 12.3-1 through 12.3-66 System: Title of Change: N/A Editorial Changes to USAR Section 12.3 Description of Change: Various editorial changes are made in USAR Section 12.3.These changes are made for clarity and to maintain consistency between the text and figures of Section 12.3.Safety Evaluation Summary: The identified USAR changes are editorial in nature and do not alter the plant design basis.Based on the evaluation performed, it is concluded that these changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 17 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-004 EDC 2E00130 Figure 6.2-38, Sheet 10 Containment Monitoring System (CMS)Title of Change: Setpoint Change to Suppression Pool High Temperature Alarm Description of Change: The setpoint for the suppression pool high temperature alarm has been increased from 82.5'F to 85'F.This provides additional margin above current operationally experienced summer suppression pool water temperatures, which have caused constant alarming conditions.

Safety Evaluation Summary: This setpoint change will reduce the suppression pool water high temperature alarms, received during normal operation, without affecting the safe operation or shutdown of the plant.Sufficient margin is still maintained to allow initiation of RHR suppression pool cooling prior to exceeding the Technical Specifications limit of<904F;thus, the initial suppression pool temperature of 90'F used in the accident analysis is maintained.

Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 18 of 112 Safety Evaluation No.: Implementation Document No.: 89-007 Calculations MS-1722, Rev.1;MS-1126, Rev.2;MS-168S, Rev.1;MS-1424, Rev.4;PZ-002AK, Rev.1 USAR Affected Pages: System: Title of Change: 3 6A 15'6A 16'0 3 3 Exclusion Area Piping FSAR Section 3.6A Revision Description of Change: In the process of resolving problems with main steam line flooding (LER 88-01), a discrepancy between the FSAR text in Section 3.6A and Question a Response F210.17A was found.The response to the Q&R stated that the design of pipe in the exclusion area met Branch Technical Position (BTP)MEB 3-1 requirements.

MEB 3-1 specifies the requirements for all piping in the"exclusion area" between containment and the inboard or outboard isolation valves.However, Section 3.6A described exceptions taken to requirements of MEB 3-1 for certain evaluations in that it did not address non-nuclear piping.In response to this discrepancy, calculations were revised to demonstrate compliance with MEB 3-1 for Class 3 and non-nuclear piping in the"exclusion area." This results in the revised Section 3.6A becoming consistent with the QSR response.Safety Evaluation Summary: The revised calculations indicate that the piping in question meets higher standards than indicated in the FSAR.Therefore, the changes to the FSAR indicate that the design is meeting more stringent requirements, thereby enhancing safety, and contains additional conservatism in the design.Thus, this change does not have any affect on the safe operation of any system or safe shutdown of the plant and does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 19 of 112 Safety Evaluation No.89-007 (Continued)

Safety Evaluation Summary: (Continued)

NOTE: This safety evaluation is being reported at this time in support of the changes to USAR Sections 3.6A and 10.3, which were incorporated in USAR Revision 0.

Safety Evaluation Summary Report Page 20 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-009 Temporary Modification N/A Liquid Radioactive Waste System (LWS)Title of Change: Temporary Filtering System at 2LWS-PI88B Description of Change: An acid spill occurred in the condenser area of the turbine building.The acid reacting with concrete, paint, metal, etc., introduced a waste solution of approximately 30%solids and organic materials, into the floor drain system.Effluent from the floor drain system is processed by the liquid radioactive waste system (LWS).The floor drain filtering system in the radwaste building is designed to process a waste effluent of 2%solids and organic materials.

Collected drainage is pumped from the floor drain collector surge tank (2LWS-TK17), to be processed by the LWS system through surge pump 2LWS-P17A/B.

This temporary modification provides for the temporary removal of pressure indicator 2LWS-PI88B to allow the installation of a 3" flex hose from the discharge side of pump 2LWS-P17B to a London Nuclear Filtering System.The London Filtering System provides an additional filtering process into this system which removes the majority of the solids and organic materials prior to returning the effluent into the designed regenerant waste tank/evaporator system and further filtering if/as required.Safety Evaluation Summary: This temporary modification provides an additional filtering system to prevent damage to LWS equipment following the unexpected acid spill and allow the nonsafety-related LWS system to perform its design function.This does not affect the

Safety Evaluation Summary Report Page 21 of 112 Safety Evaluation No.: 89-009 (Continued)

Safety Evaluation Summary: (Continued) operation of any safety systems or components.

The pressure indicator (PI88B)that is temporarily removed is for local pump discharge pressure indication and does not perform any control or protective functions for the LWS system or pump 2LWS-P17B.

Based on the evaluation performed, it is concluded that this temporary change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 22 of 112 Safety Evaluation No.: " Implementation Document No.: USAR Affected Pages: 89-014, Rev.1 Mod.PN2Y88MX093 (Partial)Figures 9.2-1q, 9.2-6a, 9.2-17b, 9.3-1h System: Title of Change: N/A Unit 2 Chemistry Lab/Counting Room Description of Change:This modification converts the existing contaminated tool storage room (elevation 261'econtamination area, radwaste building, Unit 2)into both a chemistry laboratory and a counting room.The changes include installation of counting room/chemistry lab equipment in support of routine water chemistry surveillance at Unit 2, and the addition of an air conditioning unit to the room to maintain desired environmental conditions.

USAR Revision 2 reflects portions of the modification completed prior to April 30, 1990.Safety Evaluation Summary: This modification adds a new chemistry lab and counting room to relieve personnel congestion and improve availability and convenience of facilities for Unit 2 Chemistry personnel.

This facility does not perform a safety function.Post accident sampling and analysis will not be performed in this facility.The installation of this laboratory will not affect any safety systems or components and will not affect the safe operation or shutdown of the plant.The installation of this facility complies with existing design and construction specifications and codes.Potentially contaminated and chemical waste will be processed through the existing drain systems and radioactive waste processing facilities.

Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 23 of 112, Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-016, Rev.1 N//A N/A Diesel Generator Ventilation System (HVP)Title of Change: Remove Power from 2HVP*MOD1B and 2HVP*MOD6B; 2HVP*MOD1B to be Opened and 2HVP*MOD6B to be Closed Description of Change: This temporary modification de-energizes motor-operated dampers 2HVP*MOD1B and 2HVP*MOD6B by the removal of power.2HVP*MOD1B damper will be in the open position while 2HVP*MOD6B damper will be in the closed position, which will maintain compliance with the diesel generator emergency cooling criteria by ensuring a cooling rate consistent with the requirements for emergency cooling while the emergency diesels are operating.

Safety Evaluation Summary: The removal of power from 2HVP*MOD1B, with the positioning of the damper in the open position, and the removal of power from 2HVP*MOD6B with its damper positioned in the closed position, will prevent actuation of these dampers.Upon an automatic start signal to the emergency diesel generator (2EGS*EG3), fans 2HVP*FN1B a 2HVP*FN1D exhaust is modulated between the exhaust damper (2HVP*MOD1D) and the recirculation damper (2HVP*MOD6D).

The modulation of the dampers associated with 2HVP*FN1D will maintain a cooling rate consistent with the thermal load to maintain the diesel generator (EG3)room temperature within prescribed limits during operation of diesel generator 2EGS*EG3 (Div.II).There are no trip functions associated with this temporary modification.

Safety Evaluation Summary Report Page 24 of 112 Safety Evaluation No.: 89-016 Rev.1 (Continued)

Safety Evaluation Summary: (Continued)

This temporary modification will remove safety-related components from service but will not affect the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 25 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-017 Temporary Mod.89-059 N/A Circulating Water Acid Treatment System Title of Change: Manual, Direct Acid Injection to Circulating Water Description of Change: Due to maintenance and repairs, the circulating water acid system is inoperative, thus requiring an alternate method of supplying acid to the circulating water system.Acid injection will be performed at the cooling tower through the use of a commercial tank truck and a temporary header installed across the discharge flumes.The normal injection portion of the acid system will remain inoperative during the time this temporary modification is in place.However, monitoring instrumentation will be available to check and record water pH.Safety Evaluation Summary: Acid treatment of the circulating water is utilized to maintain clean heat exchanger surfaces and to prevent biological growth within the circulating water systems condenser.

This temporary modification provides an alternate method of performing a nonsafety-related function that will not impact the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 26 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-019, Rev.1 Temporary Mods89-061, 89-062 N/A Miscellaneous Equipment and Floor Drains System Title of Change: Temporary Mod.to Steam Line Drain Valves 2DTM-AOV128 and 2DTM-AOV144 Description of Change: This temporary modification removes the electrical interlocks between valves 2ASS-STV112 and 2DTM-AOV144, and between valves 2ASS-STV143 and 2DTM-AOV128, by lifting or jumpering leads in the control room.Removal of these interlocks allows isolation of drain paths that had allowed extraction steam to flow through drain lines to the main condenser, resulting in a loss of plant efficiency.

Safety Evaluation Summary: Steam supply line drains remove any condensate build-up from the lines.Drain line valves 2DTM-AOV128 and 2DTM-AOV144 open to provide additional drainage capacity required during low pressure operations and shutdown conditions.

The normal drain line path will still provide for the removal of low point condensate from the steam supply lines during full power operations.

Additional automatic valve controls to open the valves at turbine low pressure will be functional, and manual control is available through control switches in the control room.The drain valves and their associated electrical interlocks are part of the turbine building miscellaneous drains system.This is a nonsafety-related system and is not required for safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 27 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-020 Temporary Mod.89-063 N/A Reactor Recirculation System Reactor Recirculation Pumps Vibration Monitoring Personal Computer Description of Change: This temporary modification consists of the installation of a computer work station, adjacent and connected to vibration monitoring panel 2RCS-PNL100, to provide continuous, remote, on-line monitoring of the NMP2 reactor coolant recirculation pumps 2RCS*P1A and 2RCS*P1B.The system will receive power from a local 120V convenience outlet.A temporary telephone line hook-up will be installed to provide remote access to this information to site personnel and General Electric-San Jose, eliminating the need for frequent access to restricted areas of the plant.Safety Evaluation Summary: The reactor coolant recirculation pump vibration monitoring program is used for detecting loss of wear ring bolting integrity, performing short-and long-term trending, and will serve as a basis for scheduling maintenance and repair in a timely manner.The vibration monitoring system is not required for the safe operation or shutdown of the plant.Failure of equipment installed under this temporary modification would not jeopardize or challenge plant safety systems.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 28 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-021, Rev.1 Temporary Mod.89-066 N/A Service Water System Control Room Chiller Inlet Temperature Control-Temporary Setpoint Change to 2SWP*TSL91A(B)

Description of Change: Service water to each control building chilled water condenser contains a recirculation loop with a pump (2SWP*P2A and 2SWP*P2B).

These pumps work in conjunction with the temperature control valves located in the chiller return lines to maintain the service water inlet temperature to the chillers above 60'F.Currently, the logic associated with the service water system provides for a start signal for 2SWP*P2A(B) when service water temperature decreases to an upper limit of 63'F and a lower limit of 60'F.This temporary modification will allow increasing the setpoint range for the condenser water pumps 2SWP*P2A(B) to an upper range of 754F and lower range of 724F.Safety Evaluation Summary: This temporary change to the setpoint for 2SWP*TSL91A(B) will add additional cooling capability to help maintain Control Room environment.

As long as the service water temperature entering the chiller is less than 82'F, there is no impact on station operation.

In addition, the service water outlet temperature of the chillers will be monitored on a shift basis when service water temperature is greater than 70'F.If the outlet temperature reaches 82'F, and the 2SWP*P2A(B) are still in service, then the operator shall secure the pumps.Operator action thus ensures the chiller inlet temperature does not exceed 824F.

Safety Evaluation Summary Report Page 29 of 112 Safety Evaluation No.: 89-021 Rev.1 (Continued)

Safety Evaluation Summary: (Continued)

Based on the evaluation performed,'t is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 30 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 89-022 RMU No.052578 N/A System: Title of Change: Control Building HVAC System Temporary Change to Allow Optional Operation of Control Room Return Duct Heaters 2HVC*CH11A/B and 2HVC*CH12A/B Description'f Change: Duct heaters 2HVC*CH11A/B, CH12A/B heat the return air to the air conditioning units when the temperature in the Control Room decreases to 40 degrees Fahrenheit.

This temporary change eliminates the need for the automatic controlling of heaters 2HVC*CH11A/B, CH12A/B when climatic conditions exist such that supplemental heating of the return air to the Control Room HVAC system is not required.This is desirable to (1)perform maintenance on the heaters and (2)eliminate unnecessary cycling of the air conditioning units.Safety Evaluation Summary: As indicated in the FSAR, the purpose of the Control Room air return duct heaters is to maintain air returning from the Control Room above 40 degrees Fahrenheit.

Therefore, as long as the Control Room temperature can be maintained above 40 degrees Fahrenheit, there is no impact on station operation.

Based on the evaluation performed, it is concluded that, this temporary modification does not involve an unreviewed safety question.

4 5 V Safety Evaluation Summary Report Page 31 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-024, Rev.1 N/A 9.4-40, 9.4-42 Turbine Building Ventilation System/Effluent Monitoring Operating with the Turbine Building Roof Vents Open Description of Change: This change allows the turbine building roof vents to be opened for intermittent periods during normal plant operation to provide additional cooling of the main steam tunnel and turbine building.This modification is being implemented to prevent inadvertent or spurious MSIV isolation as a result of high outside air temperature.

During mid-July 1989, high outside air temperatures caused the temperatures in the main steam tunnel to reach the high alarm setpoint on several occasions.

The trip setpoint (Technical Specifications limit)was reached on one occasion, causing a half isolation.

Because the turbine building is maintained at subatmospheric pressures, as discussed in FSAR Section 9.4, by opening the turbine building roof vents, cooler outside air will be drawn in and through the building, eventually being exhausted through the main stack via the normal turbine building ventilation system.Cooling the turbine building will result in cooling the main steam tunnel.Safety Evaluation Summary: The turbine building HVAC system has no safety-related function.Failure or malfunction of the system will not compromise any safety-related system or component or prevent safe reactor shutdown.The turbine building is not classified as a

Safety Evaluation Summary Report Page 32 of 112 Safety Evaluation No.89-024, Rev.1 (Continued)

Safety Evaluation Summary: (Continued) containment structure.

However, the turbine building ventilation system is designed to exhaust more air from the building than is being supplied, thereby maintaining a subatmospheric pressure to inhibit the exfiltration of contaminants.

The open turbine building roof vents are not considered as additional radioactive release points.Provisions are made to ensure that the open turbine building roof vents do not provide a potential for unmonitored effluent releases during normal operation, and to ensure that the releases of activity to the environment will not differ from those analyzed in FSAR Section 11.3.3 and Appendix 11A.The design basis main steam line break and offgas system failure analyses in FSAR Chapter 15 envelope the consequences of a design basis accident occurring while the turbine building roof vents are open.Lowering the main steam tunnel and turbine building temperatures will not adversely affect the ability of the main steam tunnel temperature monitors to detect a main steam line break.Based on the evaluations performed, it is concluded that this change does not involve an unreviewed safety question.

1 Safety Evaluation Summary Report Page 33 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-025 Mod.PN2Y88MZ093 N/A Essential Lighting System Temporary Markup of Two Essential Lighting Circuits in Panel 2LAN-PNLU01 Description of Change: This temporary change disabled two essential lighting circuits in order to facilitate installation of two new essential lighting circuits and to avoid working in a high radiation area when installing the new circuits.The egress/essential lighting was disabled in the following areas: condensate storage building, radwaste switchgear room, dirty workshop, sample room, large tool and equipment decontamination area, and radwaste control room.Safety Evaluation Summary: The disabling of the essential lighting circuits 138 and 540 will not affect the safe shutdown of the plant since there are no safety-related components located in the condensate storage building, the radwaste switchgear room, the dirty workshop, the sample room, the large tool and equipment decontamination area and the radwaste control room.In the event of a loss of normal power (LOP)while these two essential lighting circuits are de-energized, the referenced areas would be completely in the dark;however, since the outages are brief in duration, the likelihood of experiencing a coincident LOP is remote.Based on the evaluation performed, it is concluded that this temporary change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 34 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-026 Temporary Mod.88-74 N//A Circulating Water System (CWS)Remove Temperature Element 2CWS-TE10B Description of Change: This temporary modification removes one of four temperature elements (2CWS-TE10B) located on the tube-side discharge of the main condenser, in the 72 inch circulating water line 2CWS-072-405-4.This change was necessary due to temperature element failure and lack of availability of a replacement.

Safety Evaluation Summary: The circulating water system is nonsafety-related and is not required for safe operation or shutdown of the plant.The three remaining temperature elements will still provide their individual computer point signals.There are no alarms, controls, or isolation functions associated with the condenser tube side discharge temperature elements.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 35 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-028, Rev.1 Temporary Mod.89-71 N/A Containment Monitoring System (CMS)Title of Change: Sample Temperature for Containment Radiation Monitor Description of Change: This temporary modification installed three thermocouples to record process temperatures on one of the containment atmosphere radiation monitors (2CMS*CAB10B).

The thermocouples were installed in place of two sample valves and one calibration test valve.Data collected from the thermocouples is to be used to design modifications to eliminate condensation of moisture in the monitor process stream.Safety Evaluation Summary: This installation of thermocouples in place of the two sample valves and the one calibration test valve will not affect the operation of the radiation monitor.The radiation monitor remains operational for the following reasons: 1)Removal of the valves does not affect the function of the radiation monitor to monitor the primary containment for airborne particulate radioactivity and airborne gaseous radioactivity.

2)Chemistry procedure N2-CSP-7V can be temporarily revised so that grab samples of the primary containment atmosphere can be taken at the radiation monitor, if required.3)The function to calibrate the gas radiation detector is not changed when one of the calibration test valves is removed, since calibration is actually accomplished by removing the detector from the skid.

Safety Evaluation Summary Report Page 36 of 112 Safety Evaluation No.89-028, Rev.1 (Continued)

Safety Evaluation Summary: (Continued) 4)The integrity of the pressure boundary will be maintained by the use of seismically-qualified components.

The primary containment atmosphere radiation monitors 2CMS*CAB10AJ'B provide only indication and alarm functions.

In the event of an accident, these monitors are isolated from primary containment and would not affect the safe shutdown of the reactor.These monitors are not used for post-accident monitoring.

Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 37 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-030 Temporary Mod.89-050 N/A Offgas System (OFG)Offgas H, Sampling Discharge Line Revision Description of Change: To enable proper operation of the Offgas H, Sampling system, this temporary modification revises the H~sampling common discharge line connection to the offgas process stream since the present line connection (20FG-V290) is too restrictive.

Stainless steel tubing (1/2")is run from a threaded connection upstream of valve 20FG-V290 to an existing 3/4" globe vent valve (20FG-V188), which is located approximately six feet further downstream from the present discharge line connection.

Additional heat tracing and insulation are also provided to prevent freezing.Safety Evaluation Summary: This temporary modification will modify the nonsafety-related offgas system to enable it to properly monitor the hydrogen concentration.

The installation of this temporary modification will not compromise the integrity of the offgas system and is consistent with the design intent of the H~sampling system, as described in USAR Sections 11.3.1, 11.3.2 and Figures 11.3-1a and 11.3-16 (which have been modified by Modification PN2YMX233 and Safety Evaluation 88-077).Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 38 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-042 Temporary Mod.89-078 N/A Service Water System/Process and Effluent Radiological Monitoring and Sampling Title of Change: Service Water Sampling Tap Description of Change: During repairs to radiation monitor 2SWP*CAB146A, this change installed a temporary sample tap from service water effluent line 2-SWP-002-405-4.

An abandoned conductivity element, 2SWP-CE144A, was removed and a sampling line run from its location.The line consisted of approximately 30 feet of Tygon tubing and a shutoff valve.The installation of a service water sample line provided a convenient and accessible location from which to take grab samples required by the Technical Specifications for continued operation with a channel of service water effluent radiological monitoring out of service.Accessing the usual location for taking grab samples was considered to be a hazard to personal safety.Safety Evaluation Summary: This temporary modification will support the verification that service water radioactive levels are within Technical Specifications limits.It will not impact the safe operation or shutdown of the plant.The sample line installation is non-safety related.Effects of a break in the sample line or failure of the shutoff valve have been considered.

Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 39 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-043 Temporary Mod.2087 N//A Solid Radioactive Waste Management System (WSS)Title of Change: Temporary Sample Point for Evaporator Bottoms Description of Change: This modification provides a temporary sample point in the solid radioactive waste management system (WSS)at the valve (2WSS-V714)provided for system flushing.The blind flange downstream of 2WSS-V714 has been removed and a sampling valve added in its place.The temporary sample point off valve 2WSS-V714 is needed because it is felt that non-representative samples are being obtained at the designed location due to clogging of the sample line.Safety Evaluation Summary: This temporary modification is to a nonsafety-related system.This change will permit sampling of evaporator bottoms at a location other than the designed shielded location (2WSS-SA119).

Although ALARA long-term concerns exist at the temporary non-shielded location, it is deemed acceptable for a short duration since, at this early stage of plant operation, the radiation levels have not yet risen to the levels expected as the plant ages.System operating procedures have been revised to require evaluation of radiation levels prior to utilizing the temporary sample point.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 40 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-045 Temporary Nod.89-76 N/A Radwaste Building HVAC System (HVW)Title of Change: Record Air Flow at 2HVW-CAB196 and 2HVW-FI115 Description of Change: This temporary modification records the air flow for continuous airborne radiation monitor 2HVW-CAB196.

Also, a flow transmitter has been installed in parallel with flow indicator 2HVW-FI115, via the instrument line drain valves at 2HVW-FI115, for the purpose of recording air flow in the equipment exhaust duct.The purpose of this temporary modification is to gather data to determine the root cause of the numerous flow alarms that have been experienced for radiation monitors which have gas flow controls.Safety Evaluation Summary: The continuous air monitor 2HVW-CAB196 and flow indicator 2HVW-FI115 are nonsafety-related.

2HVW-CAB196 is a continuous airborne monitor which monitors the air in the radwaste equipment exhaust system duct.It is used for trending only and has no Technical Specifications basis.The flow element for 2HVW-FI115 is located downstream of the filters and fans for the equipment exhaust system.2HVW-FI115 is a local indicator only.It provides no control nor does it provide any alarms.

Safety Evaluation Summary Report Page 41 of 112 Safety Evaluation No.89-045 (Continued)

Safety Evaluation Summary: (Continued)

The temporary recording of air flows will not affect the operation of the equipment exhaust system.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 42 of 112 Safety Evaluation No.: Implementation Document No.: 89-048 Technical Specification Table 4.8.1.1.2-1 USAR Affected Pages: System: Table 1.8-1, page 122 of 169 Division I, II, and III Diesel Generators Title of Change: Diesel Generator Testing, Regulatory Guide 1.108 Description of Change: This change corrects an inconsistency between Technical Specifications Table 4.8.1.1.2-1 and USAR Table 1.8-1, page 122 of 169, regarding the diesel generator test schedule.The USAR commitment to Regulatory Guide 1.108 Rev.1, regulatory position C.2.d, is inconsistent with the referenced Technical Specifications table and does not reflect recent industry concerns over fast starts for diesel generators.

Safety Evaluation Summary: This change to the USAR makes the USAR consistent with the Technical Specifications and'eflects testing requirements which minimize diesel engine mechanical stress and wear.This USAR change is administrative in nature and does not affect the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 43 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-054 EDC 2M00287 Figures 9.3-1c, 9.3-1j, 9.3-1k, 9.5-lc, 9.5-1e, 9.5-if, 9.5-1g,'9.5-1h Fire Protection Water System (FPW), Service Air System (SAS)Title of Change: Assign New Equipment Numbers for Fire Protection Air Regulators Description of Change: Air pressure regulator units 2FPW-REG 1 through 8 were previously shown in the fire protection water (FPW)system on P&IDs 43C, E, F, and H.These regulator units were provided by the installing sprinkler contractor.

The single component (regulator) shown on the P&IDs was actually several individual components (isolation valves, bypass valves, check valves)in addition to the regulator.

The unidentified valves have been assigned new equipment part numbers in order to provide positive identification in procedures, valve alignments and maintenance requests.This requires that these components be added to system P&IDs.The air pressure regulators have been re-identified as part of the SAS system and are removed from FPW system P&IDs for consistency.

Safety Evaluation Summary: This change does not add or modify existing plant systems or operation, but merely adds additional detail'o existing design documents.

It does not affect the design or operation of the SAS or FPW system and does not affect safe shutdown of the plant.

I Safety Evaluation Summary Report Page 44 of 112 Safety Evaluation No.89-054 ,(Continued)

Safety Evaluation Summary: (Continued)

Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 45 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-059 EDC 2E10072 Fig.5.1-2a Nuclear Boiler Instrumentation System Title of Change: Nuclear Boiler Instrumentation System Modifications Description of Change: This modification revises USAR Figure 5.1-2a to correct the alarm annunciator window number for reactor vessel high pressure, and to add the component identification number for the steam dome pressure indicator 2ISC-PI1108.

These changes correct inconsistencies between the USAR figure and as-built parent documents.

Safety Evaluation Summary: The changes to USAR Figure 5.1-2a are editorial corrections/

clarifications, and do not involve any physical changes to the plant.These changes do not adversely affect the ability of any safety-related systems or components to perform their safety functions.

Based on the evaluation performed, it is concluded that these changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 46 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-060, Rev.2 N/A N/A Miscellaneous Buildings Floor Drains System (DFM)Operation of NMP2 Water Treatment Building Sumps as a Contaminated System to Support System Decontamination Description of Change: This safety evaluation addresses the use of the sump system in the water treatment building (north annex to the screenwell building)as contaminated.

This evaluation includes all decontamination efforts related to the present contamination, but does not include its long term routine operation to satisfy original design considerations.

The extent of contamination includes sumps 5, 6, and 7, sump pump I7, associated lines and trenches, and part of the floor of the waste neutralizer tank cubicle.No equipment is being added, deleted or modified in conjunction with this evaluation.

Safety Evaluation Summary: This evaluation was performed in accordance with Z.E.Bulletin No.80-10,"Contamination of Non-Radioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment." The water treatment sumps and associated piping are part of a normally non-contaminated system.However, due to the timing in the sump pump start up sequence, the connection of the sump pump discharge into the bottom of the floor drain collector tank inlet header, and leakage of a check valve, contaminated water from the

,

Safety Evaluation Summary Report Page 47 of 112 Safety Evaluation No.89-060, Rev.2 (Continued)

Safety Evaluation Summary: (Continued) floor drain collector tank inlet header was able to backflow into the waste neutralizer tank cubicle sump.The amount of radioactive contamination present does not reduce the ability of the sumps to perform their intended function.Although the sump system is not designed to the same criteria as a radioactive system, the integrity of the system does assure the short term containment of liquids and precludes an inadvertent release to an unrestricted area.Administrative and radiation protection measures have been taken to secure the contaminated area and restrict its use.The pump discharge line has been isolated and marked up.The area is properly posted and controlled as a restricted area in accordance with plant procedures.

A survey of the accessible portion of the pump discharge line has confirmed that dose rates from the line do not present a radiological concern and that there is no impact on personnel or equipment in the unrestricted area.Operation of sump pump 57 will be controlled to prevent further contamination of the system during any decontamination efforts.During operation of sump pump N7, the system will be monitored, including, as a minimum, isotopic analysis of the sump contents before and after system operation, and physical surveillance of the system piping in the unrestricted area during sump system operation.

Based on the evaluation performed, it is concluded that operation of the sump system, until system decontamination efforts are completed, does not involve an unreviewed safety question.

0 Safety Evaluation Summary Report Page 48 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-061 Procedure N2-OP-101D Table 13.5-6 (Sh.4)Reactor Recirculation System Procedure N2-0P-101D,"Power Changes" Description of Change: A new operating procedure, N2-OP-101D,"Power Changes," has been created.Safety Evaluation Summary: The subject procedure is developed to consolidate all concerns related to power changes, including rapid power reductions.

Development and approval of this procedure satisfies unresolved item no.89-12-02 from NRC Inspection Report 50-410/89-12, and does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 49 of 112 Safety Evaluation No.: Implementation Document No.: 89-066 Drawings 12187-SK-032483-.25; 12177-BY-002Ag Bg Cg E 45065-C thru E-45069C USAR Affected Pages: System: Title of Change: Figure 1.2-1 Various Minor Construction Activities at the Nine Mile Point SiteDescription of Change: These changes involve various minor site construction activities such as removal or addition of fences;additions, relocation, or removal of site access and service roads;and regrading and seeding of site areas outside the protected area.Safety Evaluation Summary: Evaluation of these minor construction activities and site changes has determined that: 1.Site attributes that relate to the probable maximum flood (PMF)analysis are not adversely affected.2.The ability of the revetment ditch system to protect safety-related facilities from the maximum postulated lake level as a result of the probable maximum wind storm is not adversely affected.3.Atmospheric dispersion factors used in calculating the radiological consequences of accidents are not affected.Based on the evaluation performed, it is concluded that these changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 50 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 89-068 Temporary Mod.88-151 N/A 1 Turbine Building HVAC System Temporary Installation of Air Conditioning Units in the Turbine Building East Switchgear Room Description of Change: Temporary additional cooling for personnel comfort is required in the turbine building east switchgear room to supplement the existing cooling supplied by 2HVT-UC225.

Two air conditioning units and a condensate pump unit moved from the radwaste control room were located in the east switchgear room.The existing condensing unit positioned at grade outside of the radwaste building was relocated west to an outside position, at grade, adjacent to the switchgear room.These units are not connected to the turbine building HVAC system and provide air recirculation within the switchgear room only.Safety Evaluation Summary: As indicated in USAR Section 9.4.4.3, the turbine building HVAC system has no safety-related function.Failure or malfunction of the system or subsystems will not compromise any safety-related system or component, nor will it prevent safe reactor shutdown.There are no safety-related components in the turbine building east switchgear room.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 51 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-069, Rev.4 Temporary Mod.89-092 N/A Circulating Water System-Units 1 and 2 Title of Change: Circulating Water System Discharge Path Description of Change: A recent pH imbalance in the circulating water chemistry has resulted in elevated levels of copper concentration from condenser tubing corrosion.

This change allows discharge of Unit 2 circulating water blowdown to the Unit 1 circulating water system where it will be diluted, then returned to the lake with Unit 1 water effluent having sufficient flow to dilute the copper concentrations to acceptable levels, as determined by the New~York State Department of Environmental Conservation.

This temporary modification provides the means to draw circulating water directly from the cooling tower basin initially and from CWS later, as necessary.

Temporary discharge lines consisting of flexible hose, rigid pipe, and pumps have been run overland to the Unit 1 intake canal.Unit 2 circulating water will be discharged to the Unit 1 circulating water influent downstream of the service water influent.The Unit 1 circulating water system will be operated continuously, providing a minimum flow to be determined by the calculated need for dilution of Unit 2 discharge.

The addition of a scale inhibitor, Betz 3450, to the Unit 2 circulating water system is required to control the increased scaling due to copper concentration and a rise in pH.The addition of a corrosion inhibitor, Betz Copper-Trol Cu-l, will further reduce the leaching of copper into the circulating water at Unit 2.

Safety Evaluation Summary Report Page 52 of 112 Safety Evaluation No.Safety Evaluation Summary: 89-069, Rev.4 (Continued)

The current level of copper concentration in the Unit 2 circulating water jeopardizes system equipment due to increased corrosion rates induced by accelerated corrosion rates beyond those already existing.Operation of the Unit 2 circulating water system does not jeopardize nuclear safety, as the system is not required for safe shutdown of the plant and failures associated with the system have already been analyzed in the USAR.The Unit 2 circulating water copper concentration controls blowdown to Lake Ontario.The greater circulating water influent and effluent flow at Unit 1 will provide the means by which to sufficiently dilute Unit 2 circulating water system discharge prior to its return to the lake.As there is adequate Unit 1 intake flow to accommodate the Unit 2 discharge, and the copper concentration will not affect the reliability of equipment, there is no impact on the operation of Unit 1.The remainder of the Unit 2 circulating water system will continue to function as designed.The Unit 2 CWS copper concentration will not affect the reliability or the Unit 2 service water system relative to corrosion.

Operation of the Unit 2 tempering water system will have no negative impact on the service water system and will maintain the intake water temperature.

The addition of a scale inhibitor to the Unit 2 circulating water will have no negative impact on system and equipment operation or reliability, and will help to extend service life by controlling the corrosive effects of scaling..The addition of a corrosion inhibitor will reduce copper leaching from the condenser tubes and reduce the level of soluble copper in the circulating water.ln the event of a condenser tube leak, the addition of these compounds will not have a negative impact on the chemistry of condensate water, feedwater, or reactor water.An increase in the level of chlorides in the Unit 2 circulating water is within the ability of the demineralizers to maintain the quality of feedwater/reactor water.

Safety Evaluation Summary Report Page 53 of 112 Safety Evaluation No.Safety Evaluation Summary: 89-069, Rev.4 (Continued)(Continued)

Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 54 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-070 E&DCR C46950C, ECN SFC-612 Figure 9.1-6 (Sheets 3, 6)Spent Fuel Pool Cooling System (SFC)Title of Change: Spent Fuel Pool Cooling Relay Changes Description of Change: The SFC circulating pump flow time delay relays were resetting as soon as the pumps were tripped on low flow or low discharge pressure.These alarm conditions were not"seen" by the PMS computer due to the alarm contact reset time being much faster than the computer scan time.This change replaced the subject Agastat relays with Agastat relays capable of performing two time delay functions (four pole, double throw).The original time delay function for tripping the pump remains as originally designed.The second time delay function is only for holding the alarm contacts in long enough for the computer to sense the condition.

Safety Evaluation Summary: The second time delay function of the replacement relays in no way affects the operation of the SFC pumps.The new Agastat relays are the same size as the old relays and are installed in the existing safety-related switchgear, 2ENS*SWG101 and 2ENS*SWG103.

The new relays are safety-related and meet the same design and qualification requirements as the old relays.Based on the evaluation performed,'it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 55 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-071 Temporary Mod.89-94 N/A Condenser Air Removal System, Offgas System Title of Change: Use of Helium Leak Detection System Description of Change: This temporary modification is for the installation and use of a helium leak detection system in an effort to locate points of air inleakage to the condenser.

The general test method is to spray helium around potential points of air inleakage at components

~~subject to condenser vacuum (packings, flanged joints, fittings, etc.)and to observe the test monitor for indications of helium detection.

The helium leak detector test station will be installed at, the air removal pump 2ARC-P1A during startup (steam line pressure (200 psig)and in the offgas charcoal adsorber room when the steam jet air ejectors are operating.

Both locations will utilize the same test equipment:

helium leak test station (Veeco Model MS-170), 3/8" copper tubing with fittings, shut off valves, and a vacuum pump.Safety Evaluation Summary: This change has no effect on the operation or function of the condenser air removal system, the offgas system, or the main condenser.

None of these systems is required for safe shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 56 of 112 Safety Evaluation No.: Implementation Document No.: 89-072 LDCNs U-782, U-1405, and U-1401 USAR Affected Pages: 3 7A 20 g 3~7A 25 g 3~7A 26 g 3.7A-27, 3.9A-3a, 3.9A-4, 3 9A 5g 3'A 23'A~15 1g 3A 15 2g 3A 15A 1g 3A~15A 2g 6A.3-6, 6A.3-11, 6A.9-3 (Non-Proprietary), and 6A.3-11, 6A.3-27 (Proprietary)

System: Title of Change: N/A Permit Use of the SUPERPIPE Computer Program for Piping Analysis Description of Change: This change permits design engineers to use the computer program SUPERPIPE as an alternative to NUPIPE-SW for piping analysis.Safety Evaluation Summary: NUPIPE-SW and SUPERPIPE are similar programs.Both require piping to be idealized using discrete mass points whose connecting members are assigned representative physical properties.

Both programs'develop stiffness matrices and solve for resultant deflections, loads, and stresses when subjected to external loads.The analytical methods used to solve complex equations are also simi'lar.All analysis methodologies and commitments described in USAR Sections 3.7, 3.9, and Appendix 6A that are implemented by routines in a computer program remain unchanged.

Either program can be used without affecting any piping analysis procedure or criteria.The main difference between the programs is that SUPERPIPE provides automatic options for modelling, analyzing, and combining load cases that are not provided in NUPIPE-SW.

The SUPERPIPE program has been benchmarked in accordance with the NRC acceptance criteria outlined in Standard Review Plan Section 0

Safety Evaluation Summary Report Page 57 of 112 Safety Evaluation No.89-072 (Continued)

Safety Evaluation Summary: (Continued) 3.9.The SUPERPIPE vendor has a working quality assurance program and software control program which has been audited by NMPC for compliance with the intent of 10CFR50 Appendix B.Based on-the evaluation performed, it is concluded that this change does not involve an unreviewed safety question

Safety Evaluation Summary Report Page 58 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 89-073 EDC 2M00308I EDC 2M10080 Figures 5.4-16a, 5.4-17 (Sheet 1)System: Reactor Water Cleanup System (WCS)Title of Change: Change Position Indication for 2WCS*MOV101 and 2WCS*V41 to Show Normal Position Description of Change: This drawing change revises the normal position designation on the system PaID and the corresponding USAR figures for valves 2WCS*MOV101 (from normally closed to normally open)and 2WCS*V41 (from normally open to normally closed).This change reflects the manner in which the reactor water cleanup system is normally operated.Safety Evaluation Summary: There is one RPV bottom drain line that is a supply to the WCS system.This 4" line has a normally closed motor operated valve, 2WCS*MOV101, that is used to control thermal stratification when the RCS pumps are unavailable.

A 2" bypass line around 2WCS*MOV101 has a manually operated valve, 2WCS*V41, that is normally left open to provide a constant flow back to the WCS system to remove crud and debris from the bottom head area.Both valves are located in the drywell.Industry operating experience indicates that during normal operation, the 2" bypass line builds up crud blockage over time.This blockage significantly reduces flow through the 2" bypass line necessitating the opening of the 2WCS*MOV101 valve to maintain the flow.

Safety Evaluation Summary Report Page 59 of 112 Safety Evaluation No.89-073 (Continued)

Safety Evaluation Summary: (Continued)

To simplify operations of these two valves, the WCS system will be operated with the 2WCS*MOV101 valve normally open and the 2WCS*V41 valve normally closed.This valve lineup will maintain the design function of the line, while providing the benefit of remote operating capability for valve 2WCS*MOV101 from the Control Room to isolate the WCS system from the RPV, if required.This change in normal operations will not require any physical changes to the plant, and will not have any effect on system interaction or safe operation.

Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 60 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 89-074 EDC 2S10095 9A.2-2, 9B.2-1;Figures 9A.3-5, 9A.3-6, 9A.3-7 System: Title of Change: Fire Protection Fire Zone Corrections Description of Change: Various changes are made to the fire protection arrangement drawings (EB-22 series)and the associated USAR figures in Appendix 9A.These changes are needed to correctly represent fire protection equipment locations and fire zone boundaries.

The affected areas are the auxiliary service building south and the turbine building (Fire Area 50, Zone 762NZ and Fire Area 80, Zones 246NW, 611NW, and 761NZ).Corresponding revisions are made to the combustible loading tabulations for the affected fire zones, and to Procedure N2-FDP-11, Fire Protection Preplans.Lastly, the definition of a fire area in USAR Sections 9A.2.4 and 9B.2 is clarified to indicate that separation of fire areas by 2-hour fire barriers is acceptable in certain circumstances.

Safety Evaluation Summary: The changes to USAR Figures 9A.3.5 through 9A.3.7, Procedure N2-FDP-11 and the USAR fire area definition, Sections 9A.2.4 and 9B.2, will ensure the plant as-built orientation is correctly represented.

These are documentation changes only, and no physical plant modifications are involved.These changes will not alter any safety function described in the USAR and are not required for safe shutdown, as Fire Areas 50 and 80 do not contain safe shutdown equipment or cabling.Changing the decontamination room, el.306 ft., from Zone 761NZ to 762NZ will separate Fire Areas 50 and 80 by a 2-hour rated fire wall.This arrangement satisfies the circumstances under which separation of fire areas by a 2-hour fire barrier is acceptable per BTP CMEB 9.5-1.

0 Safety Evaluation Summary Report Page 61 of 112 Safety Evaluation No.89-074 (Continued)

Safety Evaluation Summary: (Continued)

Based on the evaluation performed, it is concluded that these changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 62 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 89-077, Rev.1 WR 169489'and 169457 N//A Liquid Radioactive Waste System (LWS)Title of Change: Retubing of Regenerant Evaporator Reboiler (2LWS-E7)and Retubing of Waste Evaporator Reboiler (2LWS-E4)Description of Change: This change involves the retubing of the regenerant evaporation reboiler and the waste evaporator reboiler.The tubes of both components were damaged by corrosion pitting.The regenerant evaporator reboiler had been temporarily repaired by lining the deteriorated tubes with thin-walled tubing.The damaged tubing and the sleeving used as a temporary repair are removed and replacement tubing, equivalent to the original, installed.

Safety Evaluation Summary: Retubing of the regenerant evaporator reboiler and the waste evaporator reboiler restores these components to their original design conditions and will have a positive impact on the effective operation of the liquid radwaste system.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 63 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-001 Mod.PN2Y89MX158 Figure 10.1-5d Condensate System (CNM)Rework of 2CNM-RV71A/B/C Piping and Reconfiguration of Vent Lines Description of Change: Relief Valves 2CNM-RV71A/B/C were previously located above condensate vent valves 2CNM-V212A/B/C and their associated piping high point, thereby not allowing complete air removal.The modification relocated the vent lines such that they tap off the relief valve inlet lines, rise above the elevation of the valves (2CNM-RV71A/B/C) seats, then route down into the existing vent lines to their associated drain.Valves 2CNM-V212A/B/C were removed and re-installed within reach of the floor elevation in the current vent line piping.New valves (2CNM-V370A/B/C) have been placed in each of the new high point vent pipe sections.This change also reconfigures inlet piping to 2CNM-RV71A/B slightly to preclude failure caused by cyclic vibration.

Safety Evaluation Summary: The condensate system is not safety-related and is not required for safe operation or shutdown of the plant.This modification ensures proper venting of air thus precluding the effects of water hammer, improves access to the vent valves, facilitates repairs to the vent line, and enhances vibration handling capability.

Based on the evaluations performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 64 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-003 Calc.A-10.1-AA-26, Rev.1 2.2-2, 2.2-9 N//A NMP2 Helicopter Operations Description of Change: NMPC helicopter services provide local transportation between the site and surrounding areas including Syracuse Hancock Airport.This safety evaluation reviews the acceptability of this type of operation in the context of aircraft hazards as discussed in USAR Sections 2.2.3.1.7 and 3.5.1.6.NMP2 helicopter operations involve approximately 45 to 60 flights per year between the Syracuse Airport and the site.The flight path does not encroach on the air space above the site security fence.Safety Evaluation Summary: There are currently three helicopter landing areas in the vicinity of NMP2, all within approximately 0.5 miles of the site: 1.In the parking area, approximately 1200 ft southeast of the NMP2 reactor building.2.In the parking area adjacent to the training center.3.In the lawn area adjacent to the training center.Based on the NRC Standard Review Plan 3.5.1.6 methodology, the conservatively calculated probability of a helicopter accident leading to radiological consequences in excess of 10CFR100 limits has been estimated to be 1 x 10.Based on the conservatisms included in calculating this value, it can be reasonably concluded, that the actual probability would be less than about 10 per reactor year.In accordance with NRC Standard Review

Safety Evaluation Summary Report Page 65 of 112 Safety Evaluation No.90-003 (Continued)

Safety Evaluation Summary: (Continued)

Plans 2.2.3 and 3.5.1.6, this ensures that helicopter operations do not represent a credible hazard to the plant and need not be considered in the plant design basis.Based on the analyses and evaluations performed, it is concluded that NMPC helicopter operations do not constitute an unreviewed safety question.

Safety Evaluation Summary Report Page 66 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-004 Mod.PN2Y89MX155 Figure 10.1-6c Feedwater Pump Seal and Leakoff System (FWP)Feed Pump Seal Cooling Line Isolation Description of Change:This modification relocates isolation valves 2FWP-V12A/B/C and adds break flanges in the seal water cooling lines to the feedwater pumps (2FWS-P1A/B/C).

The previous arrangement did not provide sufficient flexibility for maintenance of the feedwater pumps during plant operation or shutdown conditions.

Safety Evaluation Summary: This modification facilitates the" performance of maintenance on the feedwater pumps.The function and original design requirements of the feedwater pump seal and leakoff system are not changed.The system is not safety-related, and the changes will not have any adverse effect on the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 67 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-005 QATR-1, Rev.5 1 7~2 1 N/A Revision 5 to Quality Assurance Topical Report (QATR-1)Description of Change: Revision 5 to the Quality Assurance Topical Report (QATR-1)has been issued.Revision 5 is a general update and clarification, including changes in the Nuclear Division organization since the issue of Revision 4.~~Safety Evaluation Summary: QATR-1 Revision 5 was transmitted to the NRC in letter NMP1L 0475 dated February 5, 1990, to satisfy the requirement of 10CFR50.54 for an annual update to the QA Program.As noted in NMP1L 0475, the changes included in QATR-1 Revision 5 do not reduce the effectiveness of the QA Program.Thus, these changes will not adversely affect the safe operation or shutdown of the plant and do not involve an unreviewed safety question.

t Safety Evaluation Summary Report Page 68'of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 90-007 Mod'.PN2Y89MX157 Figure 10.1-6a Turbine Building Equipment Drains System Title of Change: Relocation of Feedwater Pump Drain Line Description of Change:The feedwater pump drains provide the means by which to drain water from the pumps and nearby piping when maintenance and/or repair is required.Previously, the water was directed to the turbine building floor drain system with discharge to the LWS drain collector"subsystem.

However, the drain collector system did not have the capacity to adequately process the feedwater.

This modification directs the pump drain water to the equipment drain system with discharge to the LWS waste collector subsystem.

Safety Evaluation Summary: Feedwater is non-oily, low conductivity water compatible with the equipment drain and LWS waste collector systems, and these systems have the capacity to handle the additional water.The installation will be made with materials and specifications equal to those of the original installation, and the ability to drain the feedwater pumps will not be impacted.Failures associated with this change will not exceed flooding conditions already analyzed in the USAR, reference Section 3.4.1.These changes will not adversely affect the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 69 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-009 Mod.PN2Y90MZ003 Figure 10.1-5d Condensate System (CNM)Feedwater Pump Suction Valve, Bypass Valve, 2CNM-HV59A, B, C Description of Change: This modification added a manual valve in the bypass loop downstream of bypass globe valves 2CNM-HV59A, B, C.The manual valve provides a means of gradually increasing the flow of warmer water and also provides a positive isolation capability for feedwater pump repairs.Safety Evaluation Summary: The changes implemented by this modification will not alter the.intended design function of the condensate system.The modification will, however, improve overall performance of the system.None of the safety-related structures, systems, or components will be impacted by this modification.

This modification will not adversely impact the capability to shutdown the plant safely and to maintain the plant in a safe shutdown condition.

Therefore, it is concluded that this modification does not involve an unreviewed safety question.

S afety Evaluation Summary Report Page 70 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-010 Mod.PN2Y90MZ005 Figures 9.3-12j, 10.1-5d Condensate System (CNM)2CNM-HV119 Description of Change: The condensate system was vented through high point vent feedwater pump suction valve 2CNM-HV119.

This vent drains into an equi:pment drain located in the vicinity of the valve.Due to personnel safety concerns raised due to high temperature and splashing of hot fluids in the area at the time of venting, line 2-CNM-750-308-4 has been re-routed and tied into an existing drain line.An isolation valve has also been added in line 2-CNM-750-308-4 downstream of valve 2CNM-HV119.

Safety Evaluation Summary: This modification alleviates the concerns regarding high temperature and splashing of hot fluids in the area at the time of venting, allows for the system to be vented directly to the main condenser during normal operation, and eliminates the release of contaminated steam to the atmosphere.

The changes are non-safety related and do not adversely affect the ability of any safety-related structures, systems, or components to perform their safety function.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 71 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-012 EDC 2F00030 N/A Turbine Building Floor Drain System (DET/DFT)Reroute Effluent of 2SST-TK1 Flow Path from the Floor Drain (DFT)to the Equipment Drain (DET)Description of Change: This temporary modification reroutes the effluent of 2SST-TK1 (turbine building sample panel recovery tank)from the floor~~drain system (DFT)to the equipment drain (DET)system.Safety Evaluation Summary: The water from tank 2SST-TK1 is normally of permissible for influx to the equipment drain (DET)system.Should conductivity water enter the equipment drain system via TKl, a high conductivity alarm would be received in the control room, alerting the operator to take appropriate required by existing procedures.

quality high 2SST-radwaste action as The temporary changes are non-safety-related and do not adversely affect the ability of any safety-related structures, systems, or components to perform their safety functions.

The flood analysis as described in USAR Appendix 3C is also not affected.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 72 of 112 Safety Evaluation No.: Implementation Document No.: 90-013 Temporary Mods90-003 thru 90-011 USAR Affected Pages: System: N//A Equipment and Floor Drain Systems (Various)Title of Change: Temporary Modification for Defeating Nine (9)Equipment and//or Floor Drain Nuisance Alarms in the Main Control Room Panel 2CEC*PNL851 Description of Change: This temporary modification is to defeat the following equipment and//or floor drain nuisance alarms at Control Room panel 2CEC*PNL851, and allow Operations to maintain these system trouble alarms through direct response to the specific radwaste control room annunciator in alarm at panel 2CES-PNL513.

1.2.3.5.6.7.8.9.Reactor Building Equipment Drain System Trouble Reactor Building Floor Drain System Trouble Turbine Building Floor Drain System Trouble Turbine Building Equipment Drain System Trouble Main Stack Floor Drain Sump Tank 3 System Trouble Auxiliary Boiler Buil'ding Floor Drain System Trouble Radwaste Building Floor/'Equipment Drain System Trouble Condensate Storage Tank Floor Drain System Trouble Main Stack Floor Drain Tank 2 System Trouble Safety Evaluation Summary: Currently, annunciators on the radwaste control panel 2CES-PNL513 supply a common annunciator system trouble alarm to the Main Control Room panel 2CEC*PNL851.

This trouble alarm is a general non-specific indication that requires operators to access radwaste control room panel 2CES-PNL513 for the specific problem indication to be corrected.

Safety Evaluation Summary Report Page 73 of 112 Safety Evaluation No.90-013 (Continued)

Safety Evaluation Summary: (Continued)

The defeating of control room panel 2CEC*PNL851 nuisance trouble alarms will eliminate the distraction and time-consuming efforts of the Main Control Room operators to correct these alarms.The specific radwaste control room annunciator trouble condition will be corrected at the radwaste control room which is manned on a continuous basis.These changes are non-safety-related and will not affect the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 74 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 90-015, Rev.1 Temporary Mod.90-012 N/A Radwaste Building Floor and Equipment Drain System (DFW)Title of Change: Temporary Replacement of Radwaste Floor Drain Sump Pump Description of Change: Due to the unavailability of spare pumps or parts, a temporary sump pump is installed in the sump served by pump 2DFW-P1A/B.

This involves the removal of a 2" flanged spool piece and associated sump cover plate from the sump pump discharge piping, allowing the temporary sump pump to be tied in.Additionally, an~~~alternate means of processing drain water through the radwaste floor drain collector surge pumps 2LWS-P17A/B is accomplished by means of a temporary hose installed between a drain valve in the 2DFW-P1A discharge pipe and a suction strainer drain valve off the inlet piping to the floor drain collector surge pumps.Safety Evaluation Summary: The change implemented by this temporary modification will not change the function of the existing floor drain system or affect the safe operation or shutdown of the plant.The removed spool piece does not perform any protective function for the DFW system.This tie-in will allow for the use of existing discharge piping check and isolation valves to control discharge flow.The temporary hose installation allows alternate processing of drain water, if required, and is not detrimental to normal system operation.

The temporary sump pump operation can also be monitored by installed sump tank level switches.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 75 of 112 Safety Evaluation No.: Implementation Document=No.:

UFSAR Affected Pages: System: 90-020 Temporary Mod.90-025 N/A Fire Protection Water System (FPW)Title of Change: Temporary Sprinkler System/Turbine Building El.250'-0" Description of Change: A temporary sprinkler system is installed to provide additional fire protection to the area at el.250'-0" underneath the turbine track bay.The area is frequently used as a work area for repair~~~~~and maintenance of equipment which, on some occasions, results in storage of combustibles.

The temporary sprinkler system is charged from the water supply to fire hose reel no.5 and is attached with a manual valve between valve FPW-V203 and the hose reel.The attachment is such that the hose and sprinkler may be operated independently of one another.The sprinkler piping is attached to the bottom of the el.261'-0" turbine track bay steel and incorporates 21 sprinkler heads and provides approximately 900 sq.ft.of coverage.Safety Evaluation Summary: This temporary modification is located in a non-safety-related area and will not affect any safety-related equipment or safe shutdown of the plant.The temporary sprinkler system is installed beneath the turbine track bay using hangers to suspend the piping from the structural steel.The additional loading induced into the structural steel by the hangers is minimal and will not impact the structural integrity of the track bay slab.If a sprinkler pipe rupture would occur, no safety-related equipment would sustain damage from flooding.

0 Safety Evaluation Summary Report Page 76 of 112 Safety Evaluation No.90-020 (Continued)

Safety Evaluation Summary: (Continued)

Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 77 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-022 FPEE-2-89-011, EDC 2S10168 Figure 9A.3-5 Fire Protection Incorporation of Fire Protection Engineering Evaluations Into Fire Protection Arrangement Drawing Description of Change: USAR Figure 9A.3-5 depicts a non-safe shutdown, non-BTP, balance of plant fire barrier which has an unsealed acid trench running beneath the barrier.A Fire Protection Engineering Evaluation

~~~~~~~~(FPEE)has been written analyzing and justifying the opening.This change references the FPEE on the fire protection arrangement drawing and associated USAR Figure 9A.3-5 to provide clarification and traceability for the fire protection program.Safety Evaluation Summary: This revision has no adverse impact on the Fire Protection Program, does not adversely affect the Appendix R Safe Shutdown Analysis, and is consistent with the guidance provided by Standard Review Plan CMEB 9.5.1.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 78 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 90-023 N/A N/A Liquid Waste/Process and Effluent Radiological Monitoring and Sampling Title of Change: Temporary Modification for 2LWS-CAB206 and its Electrical Interlock to Valve 2LWS-AOV142 Description of Change: This temporary change removes the electrical interlock between radiation monitor 2LWS-CAB206 and valve 2LWS-AOV142 to allow the operation of the valve if, per Technical Specifications, independent samples are within specification limits to discharge liquid waste effluents into the service water system discharge bay.Radiation monitor 2LWS-CAB206 is currently inoperative, and its repair requires its de-energization, which causes valve 2LWS-V142 to cycle automatically closed preventing the only discharge path for liquid waste effluents into the service water system discharge bay.Safety Evaluation Summary: With radiation monitor 2LWS-CAB206 inoperative, Technical Specifications requirements (L.C.O.3.3.7.9, Action Statement"b," and Item 1, Table 3.3.7.9-1) allow effluent releases to continue provided that, before initiating a release, at least two independent samples are analyzed in accordance with Specification 4.11.1.1.1 (Table 4.11.1-1, Item 1), and at least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.These Technical Specifications requirements are being fulfilled.

The loss of liquid waste effluent monitoring for a period in excess of thirty days will be addressed in the Semiannual Radioactive Effluent Release Report as required by Section 3.3.7.9, Action B of the Technical Specifications.

Safety Evaluation Summary Report Page 79 of 112 Safety Evaluation No.90-023 (Continued)

Safety Evaluation Summary: (Continued)

Based on the evaluation performed, it is concluded that this temporary modification will not impact the safe operation or shutdown of the plant and does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 80 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 90-024 EDC 2E00437 Figures 6.2-71a, 9.3-1d, 9.3-1f System: Instrument Air System, Containment Atmosphere Monitoring System Title of Change: PID-19D, 19F, and 82A Typographical Errors Description of Change: Typographical errors were found and corrected on PID-19D, 19F, and 82A relating to ERF computer identification numbers~~~~~~~~~~(duplication and omissions).

The associated USAR figures are revised accordingly.

Safety Evaluation Summary: This is a documentation change only and does not involve any physical changes.USAR figure changes (ERF computer identification numbers)are made to bring the figures to an as-built configuration, and no logic functions are affected.These document corrections do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 81 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 90-029 EDC 2M00340 Figures 9.4-8a, 9.4-10a, 9.4-12b System: Reactor, Turbine, and Radwaste Buildings HVAC Systems Title of Change: Removal of Pre-filters from the Reactor, Turbine, and Radwaste Buildings Supply Air Ventilation Units Description of Change: This modification provides for the annual removal of intake pre-~~~~~~~~filters from the reactor building normal ventilation system, the turbine building HVAC system, and the radwaste building HVAC system for the duration of the winter snow'season.The equipment identification numbers for these pre-filters are 2HVR-FLT4 through FLT9 (reactor building), 2HVW-FLT1 (radwaste building), and 2HVT-FLT3 and FLT4 (turbine building).

During severe weather conditions, (high winds with lake-effect snow), operation of these systems has resulted in the accumulation of snow and ice on the pre-filters causing a high pressure differential across the filters.Safety Evaluation Summary: Operation of the affected HVAC systems without the pre-filters in place is acceptable since downstream filters are in place and provide the required degree of filtration.

The outside air is generally cleaner during the winter months because the ground is snow-covered, frozen, or wet, and the air is free of flying insects, in contrast to conditions in summer months.Also, the existing systems provide a low temperature alarm in the event that the heating coil were to become inefficient, and a trouble alarm will be present if a high differential pressure exists across the downstream filters.In addition, the outside surfaces and fins of the heating coils are inspected for cleanliness at

Safety Evaluation Summary Report Page 82 of 112 Safety Evaluation No.90-029 (Continued)

Safety Evaluation Summary: (Continued) least once a year and cleaned if necessary.

This modification affects the non-safety related portions of the reactor building ventilation system and the non-safety related radwaste and turbine building ventilation systems.These changes do not adversely affect the ability of any safety-related systems or components to perform their safety function.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 83 of 112 Safety Evaluation No.: Implementation Document No.: 90-035 Drawings EV-4M-1, EM-021M;GEN-930, EV 4K 3g EV 4L 3 EV 198AQ Og EM 002Gg Procedures N2-MMP-931 USAR Affected Pages: 9.1-32;Table 3.2-1 (Sh.16, 26h);Figures 1.2-10 (Sh.2), 9.1-25, 12.3-12, 12.3-45;Appendix 9C, Figure 5-2 System: Title of Change: Refueling Equipment Reactor Internals Storage Pool Gate Description of Change:~~~~~This change involves the purchase and installation of the reactor internals storage pool gate to support refueling outage activities.

Though this activity was deferred until after commercial operation, the gate details are already shown on plant design drawings, and the gate storage location is currently shown in the FSAR.In order to facilitate refueling outage operations and maintenance activities, the laydown location for the reactor internals storage pool gate, and also for the reactor vessel insulation, reactor vessel service platform, and the stud tensioner and stand have been revised.Operating and maintenance procedures have also been revised to address restrictions on the use of the reactor internals storage pool gate.Safety Evaluation Summary: The reactor internals storage pool is designed to facilitate storage of the reactor dryer and separator during refueling.

The sealing mechanism associated with the gate is comprised of redundant inflatable seals.The gate's seals have been designed with a pressure gauge that can be readily checked by operators at any time during the use of the reactor internals storage pool gate to confirm seal integrity.

Additionally, each gate seal has a dedicated check valve which is designed to minimize the rate at

Safety Evaluation Summary Report Page 84 of 112 Safety Evaluation No.90-035 (Continued)

Safety Evaluation Summary: (Continued) which seal air pressure decreases in the event of a loss of the non-safety-related instrument air system.The internals storage pool is required to be flooded while removing the separator and remains flooded during the entire refueling process until the steam dryer and separator are re-installed.

Therefore, any time that the reactor cavity is flooded and the spent fuel pool gates are removed, the reactor internals storage pool will be flooded.Consequently, at no time could a failure of the reactor internals storage pool gate or seal result in lowering water level to unacceptable levels in the spent fuel pool.The internals storage pool gate is fabricated so that a failure of the structural aspects of the gate will not occur during a SSE.This design/fabrication prevents portions of the gate from falling into the RPV or onto the refueling seal between the RPV and drywell wall during a SSE when the gate is in either the installed or stored position.The gate has also been designed to withstand concurrent hydrostatic and seismic loads when in the installed position between the storage pool and the reactor cavity.The change to the laydown areas for the internals storage pool gate, reactor vessel insulation, the reactor service platform, and the stud tensioner do not increase the possibility or consequence of an accident or malfunction since the entire refuel floor elevation is safety-related and has been designed to support heavy loads regardless of location.Heavy load handling considerations, as defined in NUREG-0612, have been evaluated.

Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

0 Safety Evaluation Summary Report Page 85 of 112 Safety Evaluation No.: Implementation Document No.: 90-036 Temporary Mods.90-028,90-029, 90-030 USAR Affected Pages: System: N/A Turbine Building Equipment Drains (DET), Condensate System (CNM)Title of Change: Divert Pumps 2CNM-P2A, B, C Pedestal Drain Line Flow Description of Change: The condensate booster pumps (2CNM-P2A, B, C)are seeping oil onto the pump pedestal which eventually flows to the attached drain lines and the DET drain system.This temporary change involves the diversion of flow of the condensate booster pumps (2CNM-P2A, B, C)pedestal'rain lines from the turbine building equipment drain system (DET)to a collection apparatus.

Safety Evaluation Summary: The turbine building equipment drain system (DET)is for the collection and processing of low conductivity, non-oily radioactive, potentially radioactive, or non-radioactive water.The temporary modification will prevent the oil from entering the DET system and allow Operations to monitor the rate of leakage from the condensate booster pumps.Should a water leak develop around the condensate pumps (2CNM-P2A, B, C)that produces flow normally directed to the equipment drain system (DET)through the affected drain lines, and said flow were sufficient to overflow the collector apparatus, the floor drain system (DFT)is capable of handling the added volume.The flood analysis previously evaluated in Section 3.4.1 of the USAR is not affected.

0 Safety Evaluation Summary Report Page 86 of 112 Safety Evaluation No.90-036 (Continued)

Safety Evaluation Summary: (Continued)

Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 87 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 90-040 Temporary Mod.90-032 N/A Reactor Plant Sampling System (SSR)Title of Change: 2SSR-IPNL145 Hydrolasing Description of Change: Hydrolasing was performed on the drain header for the reactor water sample panel, 2SSR-IPNL145, to reduce contamination and the resulting exposures to Chemistry personnel using the sample panel.Seven tubing lines are serviced by the header.To accomplish the hydrolasing, the header was isolated by closing isolation valves in five of the tubing lines (which places them in an inoperable state), and by modifying two lines by adding Tygon tubing of sufficient length (less than 10'-0")to bypass the header and access equipment drain 2DER-ED4404 directly.Safety Evaluation Summary: Although five tub'ing lines which utilize the drain header to route water to the equipment drain (2DER-ED4404) will be marked-up and inoperable, the two lines which are required to meet Technical Specifications requirements in Section 3/4.4.4 regarding continuous monitoring of reactor water conductivity (influent to RWCU filter-demineralizers and RCS system loop A pump discharge), will remain in service.Hydrolasing of the header will only require the header to be isolated temporarily.

The sample panel design still provides a means for obtaining grab samples from the five sample lines which are inoperable, if needed.This temporary modification is expected to be in place less than one week and will have no impact on the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this temporary modification does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 88 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-041 EDC 2F0069 Figure 9.2-2 (Sheet 19)Service Water System USAR Figure 9.2-2, Drawing Error Description of Change: This change corrects an error that was found on the service water system logic diagram, USAR Figure 9.2-2, Sheet 19.The annunciator window identified as 851225 should actually be 851255 (RHR heat exchanger service water discharge radiation high).Safety Evaluation Summary: This is a documentation change only and does not involve any changes to the actual system logic.This document correction reflects the as-built plant condition and does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 89 of 112 Safety Evaluation No.: Xmplementation Document No.: USAR Affected Pages: System: Title of Change: 90-042 FPQAP-l, Rev.2 9A.3-32 Fire Protection Quality Assurance Program Revision 2 to Fire Protection Quality Assurance Program (FPQAP-1)Description of Change: Revision 2 to the Fire Protection Quality Assurance Program (FPQAP-1)has been issued.Revision 2 is a general update and clarification, including changes in the Nuclear Division Organization since the issue of Revision 1.Safety Evaluation Summary: 4 FPQAP-1 Revision 2 was transmitted to the NRC in letter JP90-228, dated May 25, 1990, to satisfy the requirement of 10CFR50.54 for an annual update to the QA program.As noted in the May 25, 1990 letter, the changes included in FPQAP-1 Revision 2 do not reduce the effectiveness of the Fire Protection QA program.Thus, these changes will not adversely affect the safe operation or shutdown of the plant and do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 90 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 90-044 Temporary Modification N/A Moisture Separators 6 Reheaters Title of Change: Temperature Monitoring of Reheate'r Drain Receiver Tanks (2DSR-TK6A/6B)

Level Instrumentation Description of Change: This temporary modification involves externally attaching temperature sensors to the standpipes, instrument lines, level~~~~~~~switches, and associated reference legs of the reheater drain receiver tanks.Temperature data will be collected to determine if the calibration of the tank level instrumentation contains errors resulting from incorrect density values.The temperature sensors are powered from non-safety-related sources.Safety Evaluation Summary: This temporary modification adds temperature sensors to non-safety-related piping, standpipes, and instrument lines to collect temperature data, and will not affect the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 91 of 112 Safety Evaluation No.: 90-050 Implementation Document No.: N/A USAR Affected Pages: System.Title of Change: N/A Control Building Chilled Water System (HVK)Operation of 2HVK*CHL1A with Worn Oil Seal Description of Change: Control building chiller 2HVK*CHL1A compressor seal has become worn allowing the oil in the upper sump to seep down to the lower sump when the unit is not operating.

This leakage with the chiller shut down over a long duration would make automatic starts uncertain.

Thxs evaluate.on analyzes the operation of the chiller (2HVK*CHL1A) with the worn seal utilizing a trending program to determine the rate of degradation.

This will assure reliable operation of the chiller until repairs can be facilitated.

Acceptance criteria are developed which are used to determine chiller operability.

Safety Evaluation Summary: To assure that chiller 2HVK*CHL1A will be capable of an auto start, it will be operated full time, thereby not allowing the oil to seep out of its upper oil sump, as is possible while the chiller unit is shut down.The weekly surveillance procedure will check to determine if the idle leakage rate for the equipment (2HVK*CHL1A) is acceptable to assure automatic restart for a DBA with interruption of power to the chiller.A special surveillance program will trend the compressor seal's condition using two methods;one method trends bearing pressure once each shift and the other method trends seal leakage on a weekly basis.

Safety Evaluation Summary Report Page 92 of 112 Safety Evaluation No.90-050 (Continued)

Safety Evaluation Summary: (Continued)

The trending program provides sufficient confidence that unacceptable seal deterioration will be detected in a timely manner.Therefore, this special surveillance program allows operation of NMP2 without declaring chiller 2HVK*CHL1A inoperable since reasonable assurance is provided that the chiller will start and perform its intended function for at least thirty days consistent with the requirements of control room habitability after a LOCA.If a LOCA event occurs with a total loss of offsite power to both chiller trains and a single active failure of the Division II chiller (2HVK*CHL1B) to restart, adequate assurance exists that chiller 2HVK*CHL1A will perform its safety function.The duration of the down time associated with the weekly surveillance test is sufficiently long to demonstrate that the chiller unit would automatically restart during DBA.Based on the evaluation performed, it is concluded that operation of the chiller (2HVK*CHL1A) is acceptable and does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 93 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 90-066, Rev.1 EAS-34-0688B, NEDC-31538P 15.0-9, 15.0-12, 15.1-8;Table 15.0-3 (Sheets 1, 2, 3)System Title of Change: Various NMP2 Increased Core Flow Analysis (ICFA)Description of Change: The purpose of this safety evaluation is to allow operations up to 105%of rated core flow (113.9 MLB/HR)and revise the cycle 1 Core Operating Limit Report (COLR).This safety evaluation applies to the cycle 1 COLR only.Safety Evaluation Summary: The results of this safety evaluation show that the MCPR operating limits for the limiting transients (Feedwater controller failure and load rejection with bypass failure)operating in the ICFA region are bounded by the license (100%rated core flow), except when EOC-RPT is out of service.A correction is made to the MCPR limit in the Core Operating Limit Report (COLR)for EOC-RPT out of service.For other equipment out of service previously identified in the Technical Specifications, the operating MCPR limit is not affected by increased core flow operation.

The analysis results also show that operation in the ICFA region is within allowable design limits for overpressure protection, LOCA, containment, reactor internals and flow induced vibration.

Increased core flow is allowed under the constraints of NMP2 Technical Specifications and Core Operating Limit Report.To ensure the current rod withdrawal error analysis remains valid, the RMB setpoint will be clipped to 106%.Based on the evaluation and analyses performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 94 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 90-085 EDC 2M10159 Figures 1.2-7 (Sheet 1), 12.3-28, 12.3-61 System: Title of Change: Radwaste Building Radwaste Building Truck Bay Radiation Zone Description of Change: USAR Figures 12.3-28 and 12.3-61 are revised to add a missing radiation zone symbol (/I)to the truck bay area.Figure 1.2-7 is revised to incorporate a missing equipment identifier.

These are drawing changes only.Safety Evaluation Summary: Depending on the operations occurring, the dose rates in the truck bay area will vary from (1 MR/HR when the radwaste truck bay area is empty to>100 MR/HR when a cask is being filled for shipment.These dose rates were assumed in the original analysis or calculations but were inadvertently left off the drawings.No changes are required to any other documents.

Based on the evaluation performed, it is concluded that these drawing changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 95 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: 90-107 NMPC Letters NMP2L 0653, NMP2L 0665 7~1 7a Instrumentation and Controls (General)Title of Change: FSAR Section 7.1.2.3 Revision Description of Change: Section 7.1.2.3 of the FSAR is revised as follows: The commitment to perform an analysis with respect to the use of lifted leads or jumpers is deleted, as the commitment was satisfied by NMPC's submittal of letter NMP2L 0653, dated March 6, 1986.2.Supplemental information is added with respect to procedural requirements governing the use of lifted leads and jumpers.This information was previously submitted by NMPC in letter NMP2L 0665, dated March 21, 1986.Safety Evaluation Summary: The NRC Safety Evaluation Report, Supplement 3, Section 7.3.2.5, concludes that, based on NMPC's commitments, the necessary steps and precautions are taken to permit testing of safety-related systems without degrading system functions.

These FSAR revisions reflect the NRC-approved position regarding the use of lifted leads and jumpers during testing and, therefore, do not constitute any unreviewed safety questions.

Safety Evaluation Summary Report Page 96 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-108 Procedures NTP-11, NTP-16 1.10-16 N/A FSAR Table 1.10-1 Revision to Administration of Training Programs Description of Change: This change to the NMPC position regarding NUREG-0737 Item I.A.2.3 deletes reference to NMP Unit 1 SRO license holders since NMP Unit 2 now has its own instructor qualification program.This revised FSAR position clarifies the qualification requirement for NMP instructors and meets the requi rements of NUREG-0737, and is consistent with FSAR Section 13.2.1.2 in that all instructors teaching the licensed training and retraining programs shall demonstrate SRO qualifications and participate in appropriate requalification programs.Safety Evaluation Summary: The change to the NMPC position regarding NUREG-0737 Item I.A.2.3 enhances the clarity of the current FSAR position with regard to administration of training programs consistent with NRC requirements and FSAR Chapter 13.2 commitments and, therefore, does not constitute an unreviewed safety question.

Safety Evaluation Summary Report'Q Page 97 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-109 N/A Table 1.8-1, Sht.149 of 169 N/A NMP2 FSAR Table 1.8-1 Revision to Licensed Personnel Medical Evaluation Requirements Description of Change: This change to FSAR Table 1.8-1 Regulatory Guide 1.134, Rev.1, 1976, endorsed by this revision Regulatory Guide 1.134, Rev.2, revises the NMPC commitment from and the associated ANSI N546-to the current requirements of and ANSI/ANS-3.4-1983.

Additionally, reference to FSAR Chapter 13 is deleted since Chapter 13 does not discuss medical examination or certification requirements for licensed operators.

Safety Evaluation Summary: This change upgrades the FSAR commitment for medical evaluation of licensed operators and senior operators to the latest NRC approved standards.

This revised commitment was contained in NMPC's letter NMP 62510, dated February 21, 1990.Thus, this FSAR change is administrative in nature and does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 98 of 112 Safety Evaluation No.: Implementation Document No.: 90-113 Procedure N2-RTP-129, Spec.P281F USAR Affected Pages: System: Table 5.2-8 Drywell Atmosphere Monitoring System Title of Change: Clarification of Leak Detection Details Description of Change: setpoints:

~~1.Foot notes 1 and 2 to Table 5.2-8 are revised and combined into a single footnote to clarify that the leak detection sensitivity presented in the table is a Minimum Detectable Concentration based on a 10 minute Minimum Detectable Level (MDL)for I-131 (particulate) and Xe-133 (gaseous)radioactivity.

The following FSAR changes are made to provide clarification of the leak detection equipment sensitivity and additional explanation of the method for determining leak detection 2.A second footnote is added to Table 5.2-8, clarifying the method used to detect reactor coolant pressure boundary leakage using airborne particulate and gaseous radioactivity readings.Safety Evaluation Summary: The changes to FSAR Table 5.2-8 make the FSAR discussion of RCPB leakage detection sensitivities and methods consistent with the plant as-built condition and working procedures, and with Technical Specification Interpretation 539, which addresses the limitations of particulate and gaseous radioactivity monitors to detect RCPB leakage.

Safety Evaluation Summary Report Page 99 of 112 Safety Evaluation No.90-113 (Continued)

Safety Evaluation Summary: (Continued)

These changes do not reflect a deterioration in the RCPB leakage detection capabilities of NMP2', nor do they affect any system or effluent releases in such a way that the radiological consequences of postulated accidents could be increased.

Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 100 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: System: Title of Change: 90-114 Calc.WH(C)-001 Table 2.4-15 N/'A Correct Inconsistencies Between Source Document and the USAR Description of Change: USAR Table 2.4-15 is revised to correct inconsistencies between the table and its source document, calculation WH(C)-001 and Disposition No.OA.The changes include revisions to assumed building depths, flow through doors, and addition of a new door for consideration in the flooding analysis.Several editorial corrections are also incorporated.

Safety Evaluation Summary: These changes revise the flooding calculation and the USAR table (which summarizes the flooding analysis results)to properly reflect the plant as-built condition.

The revised calculations demonstrate that the conclusions of the probable maximum precipitation (PMP)flood study are not affected;i.e., the plant can be safely shut down.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 101 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 90-115 Drawings 945E400, 945E493 Figure 9.5-41 (Sheets 1 thru 12)System: Title of Change: High-Pressure Core Spray System Division III Diesel Generator USAR Figure 9.5-41 Update Description of Change: USAR Figure 9.5-41 is updated to correct editorial mistakes and add missing information to agree with the source documents as follows:~~~~1.Sheet 8: "Low Cooling Water Exp.Tank Level" alarm is indicated as input to common alarm.2.Sheet 10: Missing elements are added and corrections are made to the logic of the D.C.circulating oil pump.3.Sheet 11: Fuel oil system flow diagram, legend table and notes are corrected for clarification purposes and to reflect"as-built" condition.

4.Sheet 12: This sheet is added for missing fuel oil prime pump logic and fuel oil system alarms.5.6.Sheets 6 through 11: Legend for'!local" indication is revised for consistency.

Sheets 1 through 11: The total number of sheets is ,corrected from 11 to 12.

Safety Evaluation Summary Report Page 102 of 112 Safety Evaluation No.Safety Evaluation Summary: 90-115 (Continued)

This change updates USAR Figure 9.5-41 to agree with the source documents.

The design function and method of performance of the HPCS system and its components is not altered, and no field work is required.As such, this change has no impact on the safe operation or shutdown of the plant.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 103 of 112 Safety Evaluation No.: Implementation Document No.: 90-116 Appendix R Safe Shutdown Analysis USAR Affected Pages: System: Title of Change: 9B~2 1 g 9B 2 2I 9B~2 3g 9B~4-3, 9B.6-1, 9B.6-2, 9B.6-3, 9B.8-7, 9B.9-1;Tables 9B.8-1, 9B.8-2;Figure 9B.4-2 Various Update of Appendix R Safe Shutdown Analysis-Appendix 9B of USAR Description of Change: I This change revises USAR Appendix 9B, Appendix R Safe Shutdown Analysis, to incorporate resolutions to comments resulting from the independent verification review conducted by Niagara Mohawk's internal Nuclear Compliance and Verification group.The changes include the following:

2.Correction of inconsistencies between Section 9B.4 and Table 9B.8-1 regarding the RCIC system.Section 9B.4 correctly designates the RCIC system as part of safe shutdown trains 3 and 4, whereas Table 9B.8-1 erroneously listed the RCIC system as part of safe shutdown trains 1 and 3.In Section 9B.2, the definitions for the terms"general fire area" and"divisional fire area" are deleted, as these terms are not used in the safe shutdown analysis.The definitions of fire area and fire subarea are clarified.

These USAR changes do not involve any physical modifications to the plant.Safety Evaluation Summary: There are no design or hardware changes as a result of these revisions to USAR Appendix 9B.The safe shutdown analysis

Safety Evaluation Summary Report Page 104 of 112 Safety Evaluation No.90-116 (Continued)

Safety Evaluation Summary: (Continued) continues to show that at least one train of safe shutdown systems is available to safely shut the plant down in case of fire in any fire area.Therefore, safe shutdown capability exists as required by Appendix R in the event of a fire.Based on the evaluation performed, it is concluded that this change does not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 105 of 112 Safety Evaluation No.: Implementation Document No.: USAR Affected Pages: 90-117 Calc.12177-WM(B)-27, Rev.2 1.10-133, 2.2-6;Tables 2'3g 2'5 (Sh 1)I 2 2 7 2.2-8 System: Title of Change: Environmental Program Update USAR Text and Tables Description of Change: effect of acc habitability.

This change identifies revisions to USAR text and tables to correct inconsistencies between the USAR and source documentation.

The USAR revisions relate to calculations of the idental release of toxic chemicals on control room Safety Evaluation Summary: The identified USAR changes correct inconsistencies between the USAR and source documentation.

These corrections do not involve any actual plant changes, do not alter the plant design basis, and in no way alter the habitability conditions in the control room.Based on the evaluation performed, it is concluded that these USAR changes do not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 106 of 112 Safety Evaluation No.: Implementation Document No.: 90-122 Fire Hazards Analysis USAR Affected Pages: 9.5-5, 9.5-6, 9.5-6a, 9A.2-2, 9A.2-3, 9A.3-7, 9A.3-7a, 9A.3-12, 9A.3-49, 9A.3-56;Tables 9A.3-1 (Sh.3), 9A.3-6 (Sh.2, 4)I 9A~3-8 (Sh.2)System: Title of Change: Fire Protection Fire Protection 1990 USAR Update Description of Change: ThAn is change documents and evaluates revisions to the Fire Hazards alysis.The following summarizes the USAR changes made: Sections 9.5.1.2.8 and 9A.3-Clarified to indicate that charcoal filters 2HVC-FLT1A, B and 2HVR-FLT3 are not protected with sprinklers.

2.Section 9.5.1.2.10

-The commitment to NFPA 12A (halon systems)is clarified to indicate use of the 1980 edition.3.Sections 9.5.1.2.13 and 9A.3.6.1.2

-The text is clarified to indicate that Unit 2 does not entirely comply with NFPA 72D and 72E.These deviations are already identified in USAR Table 9.5-3.4~Section 9A.2-The definitions for the terms"general fire area" and"divisional fire area" are deleted, as these terms are not used in the Fire Hazards Analysis.The definitions of fire area and fire subarea are clarified.

5.Section 9A.3 and Tables 9A.3-1, 9A.3-6, and 9A.3-8-, These are updated to reflect changes in fire loading that have occurred.6.Section 9A.3-Updated to account for the designated storage area (turbine building track bay)for combustible liquids and Class A combustibles.

Safety Evaluation Summary Report Page 107 of 112 Safety Evaluation No.Description of Change: 90-122 (Continued)(Continued) 7.Section 9A.3.7.4-Corrected to properly state that the walls of the plant computer room are partially rated.Safety Evaluation Summary: The revisions described herein a provided in NRC Standard Review Position CMEB 9.5-1 for the impl Protection Program, and provide safety to that already provided changes have any adverse impact shut down in the event of a fire performed, it is concluded that unreviewed safety question.re consistent with the guidance Plan 9.5.1 and Branch Technical ementation and control of a Fire an equivalent or greater level of in the plant.None of the on the plant's ability to safely Based on the evaluation these changes do not involve an

Safety Evaluation Summary Report Page 108 of 112 USAR TEXTt TABLE AND FIGURE CHANGES (BASED ON PREVIOUSLY REPORTED SAFETY EVALUATIONS)

A number of text and figure revisions were made to the USAR to include additional changes that are based on previously reported safety evaluations.

These changes are identified below.Safety Evaluation No.: 87-059, Revision 2 Previously Reported: 10/25/89 USAR Table 3B-5 Sheets 1, 3, 4, 5, Table 3B-6 Sheets 1, 3, 4, 5, 6 and Figure 3B-2 Sheet 3, have been revised to include additional footnotes regarding plant operation with the removal of secondary containment hatches.Safety Evaluation No.: 87-155 Previously Reported: 10/25/89~~~USAR Figure 10.1-6c has been updated to delete instruments 2FWP-PDK5A/B/C, per ECN FWP-604 and Safety Evaluation 87-155.Safety Evaluation No.: 88-032 Previously Reported: 10/26/88 USAR Figure 10.4-11 Sheets 1, 2, 3 and 9 have been further updated to include changes per ECN FWS-612 and EDC 2E10099, as described in Safety Evaluation 88-032.Safety Evaluation No.: 88-061 Previously Reported: 06/11/90 USAR Page 6.2-86a has been updated, per EDC 2M00085, to be consistent with changes made to Figure 6.2-73a (USAR Revision 0), as described in Safety Evaluation 88-061.

0 Safety Evaluation Summary Report Page 109 of 112 Safety Evaluation No.: 88-064 Revision 2 Previously Reported: 10/25/89 USAR Figure 9.3-1b has been revised to correct an editorial error on LDCN U-549, Revision 3.Safety Evaluation No.: 88-085 Previously Reported: 06/11/90 USAR Figure 9.3-6 Sheet 1 has been updated to reflect the revised setpoint for 2SSR-CSL106 per EDC 2E00078, as described in Safety Evaluation 88-085.Safety Evaluation No.: 88U-014 Previously Reported: 04/28/89 USAR Figure 9.2-2 Sheet 19 has been updated to reflect additional

~~~changes per ECN SWP-649, as described in Safety Evaluation 88U-014.Safety Evaluation No.: 88U-019 Previously Reported: 04/28/89 USAR Figure 9.5-40a has been revised to reflect the as-built condition of*PI322A/B and*AOV323A/B per ECN EGA-607, as described in Safety Evaluation 88U-019.Safety Evaluat'ion No.: 88U-029 Previously Reported: 04-28/89 USAR Figure 10.4-10 Sheet 11 has been revised to correct a drafting error.Page 10.4-32 has been updated to include the addition of alarms to the condensate pumps and condensate booster pumps as described in Safety Evaluation 88U-029.

0 Safety Evaluation Summary Report Page 110 of 112 Safety Evaluation No.: 88U-068 Previously Reported: 04/28/89 USAR Figures 12.3-5, 12.3-8, 12.3-38, 1.2-19 Sheet 2 and 12.3-47 have been updated to reflect'he as-built configuration.

These changes involve equipment locations and radiation zones described in Safety Evaluation 88U-068.Safety Evaluation No.: 88U-069 Previously Reported: 04/28/89 USAR Figures 1.2-19 Sheet 1, 12.3-13, 12.3-46, 1.2-19 Sheet 2, 12.3-14 and 12.3-47 have been updated to reflect the as-built configuration per EDC 2M10129 and 2M10161, as described in Safety Evaluation 88U-069.Safety Evaluation No.: 88U-071~~~~~~~~~~~Previously Reported: 04/28/89 USAR Figures 1.2-26, 1.2-27, 1.2-28, 12.3-22, 12.3-23, 12.3-55, 12.3-56, and 10.4-7d have been updated to reflect the as-built configuration per EDC 2M10151, as described in Safety Evaluation 88U-071.Safety Evaluation No.: 88U-072 Previously Reported: 04/28/89 USAR Figures 12.3-24, 12.3-27, 12.3-57, 12.3-58, and 12.3-60 have been updated to reflect the as-built configuration per EDC 2M10151, as described in Safety Evaluation 88U-072.

Safety Evaluation Summary Report Page 111 of 112 Safety Evaluation No.: 88U-120 Previously Reported: 04/28/89 USAR Figures 6A.2-13 and 6A.2-25 have been updated to include previously approved changes, identified in LDCN U-447, that were inadvertently omitted from the update.This omission was identified during the verification of LDCN U-447.Safety Evaluation No.: 88U-129 Previously Reported: 04/28/89 USAR Figure 9.4-4 (Sheet 9)has been updated per EDC 2E10125, as described in Safety Evaluation 88U-129.Safety Evaluation No.: 88U-238 Previously Reported: 04/28/89 USAR Figure 9.3-11e has been updated per EDC 2M10043A, as~~~described in Safety Evaluation 88U-238.Safety Evaluation No.: 88U-255 Previously Reported: 04/28/89 USAR Table 1.8-1 Sheets 65, 66, and 67 have been revised to delete information which was previously relocated to USAR Section 14.2, per LDCN U-1145, as described in Safety Evaluation 88U-255.Safety Evaluation No.: 88U-262 Previously Reported: 04/28/89 USAR Page 1.12-32 has been revised to correct an editorial error regarding the date of a NRC letter.

Safety Evaluation Summary Report Page 112 of 112 Safety Evaluation No.: 88U-276 Previously Reported: 04/28/89 USAR Table 7.1-3 Sheet 4 has been revised to reflect Revision 3 of Regulatory Guide 1.97 to be consistent with LDCN U-361 Revision 1, and Safety Evaluation 88U-276.Safety Evaluation No.: 88U-282 Previously Reported: 04/28/89 USAR Figure 6.2-70 Sheet 21 has been updated to be consistent with PaIDs 13A-10, 13D-9 and Safety Evaluation 88U-282.USAR Figure 6.2-70 Sheet 30 has been updated to be consistent with PGIDs 19D-10, 19F-7 and Safety Evaluation 88U-282.Safety Evaluation No.: 89-056 Previously Reported: 10/25/89~~~~~~~~USAR Tables 9A.3-2 Sheet 2, 9A.3-9 Sheet 2, 9A.3-1 Sheet 2, and 9A.3-6 Sheet 5 have been revised to reflect calculation FPW-28 Revision 8, as described in Safety Evaluation 89-056.These changes resolve verification comments regarding LDCNs U-883, U-1117 and U-1200, which were incorporated into USAR Revision 1.END OF SAFETY EVALUATION

SUMMARY

REPORT

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES GENERAL TABLE OF CONTENTS Page T=Table~F=Fi ure 1 11 111 1V Amendme Number RO RO RO RO'6 Page Page T=Table Amendment T=T le Amendment~F=Fi ure Number F=F ure Number$i D Xi 0 I.9 USAR Rev'sion 0 EP-i April 1989 t r 1 J Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 1 Page T=Table~P=Pi uee 1-i 1-ii 1-iii 1-iv 1-v 1-vi 1-vii 1-viii 1-ix 1-x 1.1-1 1.1-2 1.1-3 F 1.1-1 1.2-1 1.2-2 1.2-3 1.2-4 1.2-5 1.2-6 1.2-7 1.2-8 1.2-9 1.2-10 1.2-11 1.2-12 1.2-13 1.2"14 1.2"15 1.2-16 1.2"17 1.2-18 1.2-19 1~2-20 1.2-21 1.2-22 1.2-23 1.2-24 1.2-25 1.2-26 1.2-27 1.2"28 1.2-29 Amendment Number 24 24 24 24 RO'26 24 24 RO 19 0 24 21 0 0 21 0 0 0 0 0 0 0 21 19 0 0 21 21 0 18 0 RO 0 19 0 21 0 0 18 0 0 Page T=Table~F=Fi uee 1.2-30 1.2-31 1.2-32 1.2-33 1.2-33a 1.2-33b 1.2-34 1.2-35 1.2-36 1.2-37 1.2-38 1.2-39 1.2-40 1.2-41 F 1~2-1 F 1.2-2 F 1.2-3 F 1.2-4 F 1~2-5 F 1.2-6 S}l 1 Sh 2 F 1.2-7 S}1 1 S}1 2 F 1.2-8 S}1 1 Sjl 2 F 1.2-9 S}1 1 S}l 2 F 1.2-10 Sh 1 S}l 2 F 1~2-11 S}1 1 S}l 2 Sjl 3 S}1 4 F 1.2-12 F 1.2-13 S}l 1 S}1 2 S}1 3 F 1.2-14 Amendment Number 28 28 0 23 18 18 0 0 0 0 0 23 0 21 RO 23 26 26 26 RO Rl Rl Rl Rl 26 Rl Rl Rl Rl'O RO RO RO RO RO 26 RO RO Page T=Table~F=Fi uee 1.2-15 S}1 1 S}l 2 S}1 3 1.2-16 1.2-17 S}l 1'}l 2 S}l 3 S}1 4 Sjl 5 S}1 6 1.2-18 1.2-19 S}1 1 S}1 2 1.2-20 S}l 1 S}1 2 1.2-21 S}1 1 S}1 2 1.2-22 S}1 1 S}1 2 1.2-23 Sjl 1 Sh 2 1.2-24 1.2-25 1.2-26 S}1 1 S}1 2 1.2-27 S}1 1 Sh 2 1.2-28 1.2-29 S}1 1 S}l 2 Sh 3 1.2-30 1.2-31 1.2-32 S}1 1 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO Rl 26 RO 26 RO 26 26 26 26 RO 26 RO RO 0 RO RO 0 0 23 0 RO RO USAR Revision EP 1-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sh 2 Sh 3 1.2-33 1.2-34 1.2-35 1.2-36 1.2-37 Sh 1 Sh 2 1.2-38 1.2-39 1.2"40 1.3-1 T 1.3-1 S}1 1 Sh 2 Sh 3 sh 4 T 1.3-2 Sh 1 Sh 2 T 1.3-3 Sh 1 Sh 2 Sh 3 T 1.3-4 T 1.3"5 Sh 1 Sh 2 T 1.3-6 T 1.3-7 T 1.3"8 Sh 1 Sh 2 T 1.3-9 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Amendment Number RO RO RO RO 26 26 26 26~0 0 23 RO 21 21 0 21 0 RO 21 28 0 0 20 0 28 4 21 23 4 18 28 18 18 18 0 23 0 Page T=Table~F=Fi ure Sh 10 Sh 10a 1.4-1 1.4-2 1.4-3 1.4"4 1.4-5'.4-6 1.4-7 1.4"8 T 1.4-1 Sh 1 Sh 2 1.5-1 1.5"2 1.5-3 1.5-4 1.5-5 1.6"1 T 1.6-1 Sh 1 Sh la Sh 2 Sh 3 sh 4 Sh 5 Sh 6 Sh 6a Sh 7 Sh 8 1.7-1 T 1.7"1 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Amendment Number 23 23 21 23 28 28 10 19 10 10 19 19 Rl 10 RO 23 23 23 1 1 1 1 1 1 Page T=Table~F=Fi ure Sh 10 Sh 11 S}1 12 Sh 13 Sh 14 Sh 15 S}1 16 Sh 17 Sh 18 Sh 19 Sh 19a Sh 20 Sh 21 Sh 22 Sh 23 Sh 23a Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 S}1 29 Sh 30 Sh 31 Sh 32 S}1 33 Sh 34 Sh 35 S}1 36 Sh 37 Sh 38 Sh 39 Sh 40 Sh 41 S}1 42 S}1 43 Sh 44 Sh 44a Sh 45 Sh 46 Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 Amendment Number 1 1 1 1 1 1 1 1 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 USAR Revision EP 1-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sh 52 S}1 53 Sh 53a Sh.54 Sh 55 Sh 55a Sh 55b Sh 55c Sh 55d Sh 55e S}L 5'5K S}1 55g Sh 56 Sh 56a Sh 57 Sh 57a Sh 58 Sh 58a Sh 59 Sh 59a Sh 60 Sh 60a Sh 60b Sh 60c T 1.7-2 Sh 1 Sh 2 S}1 3 S}1 4 F 1.7-1a F 1.7-lb F 1.7-lc F 1.7-1d'1.7-le F 1.7-2 F 1.7-3 S}1 l Sh 2 F 1.7-4 1.8-1 T 1.8-1 Sh l Sh 2 Sh 3 Amendment Number 23 23 23 23 9 9 9 9 9 9 9 9 9 9 23 23 23 23 23 23 23 23 24 23 RO RO RO RO RO RO RO RO RO 0 RO RO RO 0 0 4 Page T=Table~F=Fi ure Sh 4 S}1 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Sh l3 Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 Sh 20 Sh 20a Sh 21 Sh 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 S}L 28 Sh 29 S}1 30 S}1 31 Sh 31a Sh 32 S}1 33 S}L 34 S}1 35 Sh 36 Sh 37'Sh 38 Sh 38a Sh 39 Sh 40 S}1 41 Sh 42 Sh 43 Sh 44 S}1 45 Amendment Number 0 23 0 12 0 0 5 3 0 0 0 0 0 Rl 0 3 18 19 0 0 0 0 0 0 0 0 RO 0 RO RO 0 23 0 0 0 18 RO RO RO RO 0 0 0 28 0 Page T=Table~F=Fi ure Sh 46 Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 Sh 52 Sh 53 Sh 54 Sh 55 Sh 55a Sh 56 Sh 56a Sh 56b Sh 57 Sh 57a Sh 58 Sh 59 Sh 60 Sh 60a Sh 61 Sh 62 Sh 63 Sh 64 Sh 65 Sh 66 S}1 67 Sh 68 Sh 69 Sh 70 Sh 71 Sh 72 Sh 73 Sh 74 Sh 75 Sh 76 Sh 77 Sh 78 Sh 79 Sh 80 Sh 81 S}1 82 Sh 83 Sh 84 Sh 85 Amendment Number 0 0 0 0 21 0 0 0 0 7 7 24 24 RO RO 18 26 0 8 28 0 Rl 0 Rl 0 0 0 0 0 0 0 8 0 0 0 0 0 0 0 0 0 5 0 22 13 USAR Revision EP 1-3 October 1989 Ate~y~y.

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee S}1 86 S}1 87 S}1 88 S}1 89 Sh 89a S}1 89b S}1 90 S}1 91 S}l 92 S}1 93 S}1 94 Sh 95 S}1 96 S}l 97 Sh 98 S}1 99 S}1 100 S}1 101 S}l 102 Sh 102a S}1 103 Sh 104 S}l 105 S}1 106 S}1 107 S}1 108 Sh 108a S}1 109 Sh 110 S}1 111 S}1 112 Sh 113 S}1 114 S}1 115 S}1 116 S}1 117 Sh 118 S}1 119 Sh 120 Sh 121 S}1 122 S}L 123 S}1 124 Sh 125 S}l 126 Amendment Number 0 0 0 RO RO RO 0 0 0 0 0 0 0 0 18 RO 0 0 RO RO 0 0 0 0 Rl RO RO 11 28 RO 0 0 4 0 0 0 8 27 20 0 26 0 0 0 0 Page T=Table~F=Fi uee Sh 127 S}1 128 S}1 129 Sh 130 S}1 131 S}1 132 S}1 133 S}1 134 S}1 135 S}1 136 S}1 137 S}1 138 S}l 139 S}1 140 Sh 141 S}1 142 S}1 143 Sh 144 S}1 145 S}1 146 S}1 147 S}1 148 S}1 149 Sh 150 Sh 151 Sh 152 Sh 153 S}1 154 S}1 155 Sh 155a S}1 156 Sh 157 Sh 158 S}1 159 S}l 160 Sh 160a S}l 161 S}l 162 S}1 163 S}1 164 S}1 165 S}l 166 S}1 167 S}1 168 S}1 169 Amendment Number 0 0 0 RO 0 7 0 0 0 0 RO 3 3 0 0 0 0 0 3 0 0 21 0 0 0 15 0'17 17 7 7 0 0 RO RO Rl RO 0 RO RO 28 28 0 RO Page T=Table~F=Fi uee Sh 169a T 1.8-1a S}1 1 S}l 2 S}1 3 Sh 4 S}1 5 S}1 6 Sh 7 S}1 8 S}1 9 S}1 10 Sh 11 S}1 12 S}1 13 Sh 14 S}1 15 S}1 16 S}1 17 T 1.8-2 S}1 1 S}1 2 Sh 3 S}1 4 S}1 5 Sh 5a Sh 6 S}1 7 Sh 7a S}1 8 S}1 9 Sh 10 S}1 1 oa Sh lob Sh 10c S}1 11 Sh 1 la Sh 12 S}1 13 Sh 13a S}1 14 F 1.8-1 1.9"1 T 1.9-1 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 0 0 0 0 0 7 11 28 14 0 14 0 7 7 7 0 7 0 0 Rl 0 RO USAR Revision EP 1-4 October 1989 I

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sjl 1 S}1 2 Sh 3 Sjl 4 Sh 5 Sjl 6 Sjl 7 Sjl 8 Sjl 9 S}1 10 Sjl 11 Att 1.9-1 Att 1.9-2 Att 1.9-3 Att 1.9-4 Att 1.9-5 Att 1.9-6 Att 1.9-7 Att 1.9-8 Att 1.9-9 Att 1.9-10 Att 1.9"11 Att 1.9-12 Att 1.9-13 S}l 1 S}l 2 Sjl 3 Att 1.9-14 S}1 1 Sjl 2 Sh 2a Sjl 2b Sjl 3 Sh 4 Att F 9-15 Att 1.9-16 Att 1.9-17 Att 1.9-18 Att 1~9-19 Att 1.9-20 Att 1.9-21 Att 1.9-22 Att 1.9-23 Att 1.9-24 Att 1.9-25 Amendment Number 7 1 1 18 RO 23 Rl 26 1 1 1 7 1 1 1 1 1 1 1 1 1 1 5 1 12 12 12 1 RO 27 1 1 25 1 1 1 1 1 1 1 Page T=Table~F=Fi ure Att 1.9-26 Att 1.9-27 Att 1.9-28 Att 1.9-29 Att 1.9-30 S}1 1 S}1 2 Att 1.9-31 Att 1.9-32 Att 1.9-33 Att 1.9-34 Att 1.9-35 Att 1.9-36 Att 1.9-37 Sjl 1 S}1 2 Att 1.9-38 Att 1.9-39 Att 1.9-40 Att 1.9-41 Att 1.9-42 Sjl 1 S}1 2 Att 1.9-43 Att 1.9-44 Att 1.9-45 Att 1~9-46 Att 1.9-47 Att 1.9-48 Att 1.9"49 Att 1.9-50 Att 1.9"51 Att 1.9-52 Att 1.9-52a Att 1.9-53 Att 1.9-54 Att 1~9-55 Att 1~9-56 Att 1~9-57 Att 1.9-58 Att 1.9-59 Att 1.9-60 Att 1.9-61 Sh 1 Sh la Amendment Number 1 1 1 RO 1 1 1 1 1 1 18 1 27 1 1 1 Rl 22 5 26 1 1 1 5 23 1 1 1 23 23 5 1 18 1 18 1 1 1 1 RO RO Page T=Table~F=Fi ure Sh 1b Sjl 2 S}l 3 Sjl 4 Att 1.9-62 Att 1.9-63 Att 1.9-64 Att 1.9-65 Att 1.9-66 Att 1.9-67 Att 1.9-68 S}1 1 Sh 2 Att 1.9-69 Att 1.9-70 Att 1.9-71 S}1 1 S11 2 Att 1.9-72 Att 1.9"73 Att 1.9-74 Att F 9-75 Att 1~9"76 Att 1~9-77 Att 1~9-78 Att 1.9-79 Att 1.9-80 Att 1.9-81 Att 1.9-82 Att 1.9-83 1.10-1 1.10-2 1.10"3 1.10-3a 1.10-3b 1.10"4 1.10-5 1.10-6 1.10-6a 1.10-6b 1~10-7 1.10-8 1.10-9 1.10-9a Amendment Number 27 27 27 RO 21 1 1 1 1 1 1 1 26 25 1 1 1 1 1 1 1 1 27 1 RO 1 1 1 0 9 23 23 9 9 0 25 25 25 23 0 RO 17 USAR Revision EP 1-5 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 1.10-9b 1.10-10 1.10-11 1.10-12 1.10-13 1.10-13a 1.10-13b 1.10-14 1.10-15 1.10-16 1.10-17 1.10"18 1.10"19 1.10-19a 1.10-19b 1.10-20 1.10-21 1.10-22 1.10-23 1.10-24 1.10-25 1.10-26 1.10-27 1.10-27a 1.10-27b 1.10"28 1.10-29 1.10-30 1.10-30a 1.10-30b 1.10"31 1.10-32 1.10"33 1.10-33a 1.10-33b 1.10-34 1.10-35 1.10-35a F 10-35b 1.10-36 1.10-37 1.10-38 1.10-39 1.10-40 1.10"41 14 17 23 0 9 9 9 0 0 RO 0 RO RO RO 9 0 0 0 0 0 23 17 23 23 23 0 0 23 23 14 0 0 RO RO 14 23 14 14'4 23 23 0 RO 0 0 1.10-42 1.10"43 1.10-44 1.10-45 1.10-46 1.10-46a 1.10-46b 1.10-47 1.10-47a 1.10-47b 1.10-48 1.10"49 1.10-50 1.10-51 1.10-51a 1.10-51b 1.10-52 1.10-53 1.10-54 1.10-55 1.10-56 1.10-57 1.10-57a 1.10-57b 1.10-58 1.10-58a 1.10-58b 1.10-59 1.10-60 1~10-61 1.10-62 1.10-63 1.10-64 1.10-64a 1.10-64b 1.10-64c 1.10-64d 1.10-64e 1.10-64f le10-64fa 1.10-64fb 1.10-64g 1.10-64ga 1.10-64gb 1elo-64}1 0 0 0 0 3 RO 3 23 23 14 23 0 0 5 5 5 0 0 0 0 23 13 13 13 13 13 13.25 7 Rl 23 7 26 7 20 23 23 10 RO 10 10 10 10 10 27 1.10-64i 1.10-64ia 1.10-64ib 1.10-64j 1 e 10-641%1.10-641 1.10-64m 1.10-64n 1.10-64o le10-64p T IIeB.3-1 Sh 1 S11 2 T II.B.3-2 F II.B.3-1a F II.B.3-2 F II.B.3-3 F II.B.3-4 F II.B.3-5 F II.B.3-6 1.10-65 1.10-66 1.10-67 1.10-68 1.10-69 1.10-69a 1.10-69b 1.10-69b.1 1.10-69b.2 1.10-69c 1.10-69d 1.10-69e 1.10-69f 1.10-69g 1elo-6911 1.10-69i 1.10-69j 1elo-69k 1.10-691 1.10-69m 1.10-69n 1.10-70 1.10-70a 1.10-70b 1.10-71'28 10 10 7 10 10 23 23 7 7 RO RO RO RO 7 20 20 20 20 23 23 0 13 RO 23 23 23 23 15 15 15 15 15 15 15 15 15 26 15 15 10 10 10 0 USAR Revision EP 1-6 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 1.10-72 1.10-73 1.10-73a 1.10-73al 1.10-73a2 1.10-73b 1.10"73c 1.10-73ca 1.10"73cb 1.10-73d 1.10-73e lelo-73K 1.10-73g 1elo-73}1 1.10-73i 1.10-73j 1.10-73ja 1.10-73jb 1.10-73k 1.10-731 1.10-73m T II.E.4.2-1 S}1 1 Sh la S}1 2 S}1 3 1.10-73n 1.10-74 1.10-75 1.10-76 1.10-77 1.10-78 1.10-79 1.10-80 1.10-80a 1.10-80b 1.10-81 1.10-82 1.10-83 1.10"84 1.10-84a 1.10-84b 1.10-84c 1.10-84d 1.10"85 0 4 23 23 23 23 28 8 8 24 23 22 23 22 22 22 23 8 23 22 22 24 24 8 8 4 23 0 23 0 0 0 Rl 13 13 23 0 0 14 RO RO Rl Rl 23 1.10-85.1 1.10-85.2 1.10-85a 1.10-85al 1.10-85a2 1.10-85b 1.10"85c 1.10-85d 1.10-85e 1elo-85'.10-85g 1.10-85}1 1.10-86 1.10-87 1.10-88 1.10-89 1.10-90 1~10-90a 1.10-90b 1.10-91 1.10-92 1.10-92a 1.10-92b 1.10"93 1.10-94 1.10-95 1.10-96 1.10-97 1.10-98 1.10-99 1.10-99a 1.10-99b 1.10-99c 1.10-99d 1.10-100 1.10-101 1.10"102 1.10"103 1.10"104 1.10"105 1.10-106 1.10-107 1.10-108 1.10-109 1.10-110 23 23 23 23 23 15 15 15 15 Rl 23 15 27 0 23 0 RO RO 9 27 10 10 10 RO 0 27 27 RO 23 19 19 19 28 19 0 27 0 0 13 0 0 Rl Rl 23'23 1.10-111 1.10-112 1.10-113 1.10-114 1.10-115 1.10-116 1.10-'17 1.10-118 1.10-119 1.10-120 1.10-121 1.10-122 1.10-123 1.10-124 le10-125 1.10-126 1.10-127 1.10-128 1.10-129 1.10-130 1.10-131 1.10-132 1.10-133 1~11-1 T 1.11-1 Sh 1 S}1 2 Sh 3 S}1 4 S}l 5 S}l 6 1.12-1 1.12-2 1.12-3 1.12-4 1.12-5 1.12-6 1.12-6a 1.12-6b 1.12-7 1.12-8 1.12-9 1.12-10 23 23 23 23 23 23 23 23 23 23 Rl 0 Rl 23 18 15 0 0 0 0 0 0 RO 0 0 Rl 0 0 0 3 3 3 3 3 18 18 18 3 3 3 3 USAR Revision EP 1-7 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 1.12-11 1.12-12 1.12-13 1.12-14 1.12-15 1.12-16 1.12-17 1.12-18 1.12-19 1.12-20 1.12-21 1.12-22 1.12-23 1.12"24 1.12-25 1.12-26 1.12-27 1.12-28 1.12-29 1.12-30 1.12-31 1.12-32 1.12-32a 1.12-32b 1.12-33 1.12-34 1.12-35 1.12-36 1.12-37 1.12-38 1.12-39 1.12-40 1.12-41 1.12-42 Amendment Number 27 3 18 23 23 3 28 3 3 3 28 3 3 3 3 3 3 3 3 3 3 RO RO RO 4 4 4 4 27 4 4 4 4 4 Page T=Table~F=Fi ure 1.13-11 1.13-12 1.13-13 1.13-14 1.13-15 1.13-16 1.13-17 1.13-18 1.13-19 1.13-20 1.13-21 1.13-22 1~13-23 1.13-24 Amendment Number RO 9 9 Rl 9 9 Rl 9 19 9 9 19 9 9 Page T=Table Amendment~F=Fi ure'umber 1.13-1 1.13-2 1.13-3 1.13-4 1.13-5 1.13-6 1.13-7 1.13-8 1.13-9 1.13-10 USAR Revision EP 1-8 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 2 Page T=Table~FFi uee 2 1 2 11 2 ll a 2-iib 2 ill 2"iiia 2-iiib 2-lv 2-v 2-vl 2-Vl 1 2 vila 2-viib 2 V111 2-vl.l la 2-viiib 2-lx 2-x 2-Xl 2-xia 2-xib 2 Xll 2-xl la 2-xiib 2 Xlll 2-xllla 2"xiiib 2-xlv 2-xv 2-xvl 2-Xvl 1 2 xvlll 2 Xvl1 la 2-xviiib 2-xlx 2-xixa 2-xixb 2 xx 2-xxl 2-xxia 2"xxib 2 Xxl1 2 XX11 1 2"xxlv 2-xxv 2-xxvl 2-xxvl,a Amendment Number 24 24 24 24 RO 24 24 RO 24 0 24 24 24 24 RO 14 7 24 24 RO 3 24 24 24 24 24 15 RO 0 0 0 5 RO 5 26 26 3 24 13 13 13 0 24 24 24 24 26 Page T=Table~F=Pi uee 2-xxvib 2-xxvl 1 2-XXV111 2 xxvllla 2-xxviiib 2-xxlx 2-xxx 2-xxxl 2-xxx1 1 2.1-1 2.1-2 2.1-3 2.1-3a 2.1-3b 2.1-4 2.1-5 2.1-6 2.1-6a 2.1-6b 2.1-7 2.1-7a 2.1-7b 2'-8 2.1-9 T 2.1-1 T 2'-2 T 2.1-3 T 2.1-4 T 2.1-5 T 2.1-6 T 2.1-7 T 2.1-8 T 2.1-9 T 2.1-10 T 2'-ll T 2'-12 T 2.1-13 T 2.1-14 T 2.1-15 T 2.1-16 T 2.1-17 T 2.1-18 T 2.1-19 T 2.1-20 T 2.1-21 T 2'-22 Amendment Number 11 24 24 14 14 24 24 24 24 RO RO RO 4 4 RO 7 7 7 7 RO RO 11 11 7 23 28 28 7 7 7 7 7 7 7 7 7 7 7 7 7 7 0 7 7 7 7 Page T=Table~F=Fi uee F 2.1-1 F 2.1-2 F 2.1-3 F 2.1-4 F 2.1-5 F 2.1-6 F 2.1-7 F 2.1-8 F 2.1-9 F 2.1-10 F 2.1-11 F 2.1-12 F 2'-13 F 2.1-14 F 2.1-15 F 2'-16 F 2'-17 F 2.1-18 F 2.1-19 F 2.1-20 2.2-1 2'-2 2'-3 2.2-4 2.2-5 2.2-5a 2'-5b 2,2-6 2~2 7 2.2-8 2.2-9 2.2-10 2.2-11 T 2.2-1 T 2.2-2 T 2.2-3 T 2.2-4 S11 1 S11 2 S11 3 T 2.2-5 Sh 1 Sh 2 T 2.2-6 T 2'-7 T 2".2-8 Amendment Number 13 RO RO 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 0 ll 19 RO RO 26 3 3 RO RO 8 0 26 3 RO 25 0 RO 25 25 0 RO RO 0 RO RO USAR Revision EP 2-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 2.2-9 F 2.2-1 2.3-1 2~3 2 2~3 3 2.3-4 2'-5 2,3-5a 2.3-5b 2.3-6 2~3 7 2.3-8 2.3-8a 2.3-8b 2.3-8c 2.3-8d 2.3-9 2.3-10 2.3-10a 2.3-10b 2.3-11 2.3-11a 2.3-lib 2.3-12 2.3-13 2.3-14 2.3-15 2.3-16 2.3-17 2.3-18 2.3-19 2.3-19a 2.3-19b 2.3-20 2.3-21 2.3-22 2~3 23 2.3-24 2.3-25 2.3-26 2.3-26a 2.3-26b 2'-27 2.3-28 2.3-29 2.3-30 Amendment Number 28 9 0 0 0 0 5 5 5 23 0 22 22 19 22 19 10 10 5 5 5 5 5 0 0 0 0 0 26 0 5 5 5 3 0 0 0 26 19 3 3 3 26 26 0 0 Page T=Table~F=Fi ure 2.3-31 2~3 32 2'32a 2.3-32b 2e3-33 2'33a 2.3-33b 2.3-34 2.3-34a 2.3-34b 2.3-35 2.3-35a 2.3-35b 2.3"36 2'-37 2.3-38 2.3-39 2.3-40 2.3-41 2.3-42 2.3-43 2.3"44 2.3-45 2.3-46 2.3-47 2.3-48 2.3-49 2.3-50 2.3-51 2.3-51a 2.3-51b 2.3-52 2.3-53 2.3-54 2.3-55 2.3-56 2.3-57 2.3-58 2.3-59 2.3-60 2.3-61 2.3-62 2.3-62a 2.3-62b T 2.3-1 T 2e3-2 T 2'-3 Amendment Number 3 RO RO RO 23 23 23 RO 13 13 13 13 13 13 0 26 23 23 26 13 23 13 13 23 RO 3 0 0 23 23 23 0 0 RO 0 0 0 0 10 13 13 19 19 19 0 0 0 Page T=Table~F=Fi ure T 2.3-4 S}1 1 S}1 2 T 2.3-4A T 2~3 5 Sh 1 S}1 2 T 2.3-5A Sh 1 S}1 2 T 2.3-6 T 2.3-7 F 2.3-1 F 2.3-2 F 2'-3 F 2.3-4 F 2.3-5 F 2.3-6 F 2.3-7 F 2.3-8 F 2.3-9 F 2.3-10 F 2.3-11 F 2.3-12 F 2.3-13 F 2.3-14 F 2.3-15 F 2.3-16 F 2.3-17 F 2.3-18 F 2.3-19 F 2.3-20 F 2.3-21 F 2.3-22 F 2.3-23 F 2.3-24 F 2'-25 F 2.3-26 F 2e3-27 F 2'-28 F 2.3-29 F 2.3-30 F 2.3-31 F 2.3-32 F 2'-33 F 2.3-34 F 2.3-35 Amendment Number 0 0 Rl RO RO 5 19 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 USAR Revision EP 2-2 October 1989

Nine Mile Point Unxt 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee F 2.3-36 F 2.3"37 F 2.3-38 F 2.3-39 F 2.3-40 F 2.3-40a F 2.3-41 F 2.3-42 F 2.3-43 F-2.3-44 F 2.3-45 F 2.3"46 2.4-1 2.4-2 2,4-3 2.4-3a 2.4-3b 2.4-4 2.4-4a 2.4-4b 2.4-5 2.4-5a 2.4-5b 2.4-6 2.4-7 2.4-8 2.4-9 2.4-10 2.4-11 2.4"12 2.4-12a 2.4-12b 2.4-13 2.4-13a 2.4-13b 2.4-14 2.4-14a 2.4-14b 2.4-15 2.4-15a 2.4-15b 2.4-16 2.4-16a 2.4"16b 2.4-17 2.4-18 Amendment Number 0 0 3 3 3 RO RO RO 26 26 26 25 0 0 0 26 0 RO RO RO RO 26 26 26 26 26 RO RO RO RO RO 23 19 RO Page T=Table~F=Pi uee 2.4-19 2.4-20 2.4-21 2.4-22 2.4-23 2.4-24 2.4-25 2.4-26 2.4-27 2.4-28 2.4-29 2.4-30 2.4-31 2.4-32 2.4-33 2.4-34 2.4-35 2.4-36 2.4-36a 2.4-36b 2.4-37 2.4-38 2.4-39 2.4-40 2.4-41 2.4"42 2.4-43 2.4-44 T 2.4-1 T 2.4-2 T 2.4-3 T 2.4-4 T 2'-5 T 2.4-6 T 2.4-7 T 2.4-8 T 2.4-9 T 2.4-10 S}1 1 Sh 2 S}1 3 T 2.4-11 S}1 1 Sh 2 S}1 3 Sh 4 T 2.4-12 Amendment Number 3 0 26 Rl 25 0 0 0 0 27 0 0 0 0 0 0 0 19 19 19 26 0 0 5 26 0 0 25 0 0 26 0 0 0 0 0 4 Page T=Table~F=Fi uee T 2.4-13 T 2.4-14 T 2.4-15 S}1 1 Sh 2 F 2.4-1 F 2.4-2 F 2.4-3 F 2.4-4 F 2.4-5 F 2.4-6 F 2.4-7 F 2.4-8a F 2.4-8b F 2.4-9 F 2.4-10 F 2.4-11 F 2.4-12 F 2.4-13 F 2.4-14 F 2.4-15 F 2.4-16 F 2.4-17 F 2.4-18 2.5-1 2.5-la 2.5-1b 2.5-2 2.5-3 2.5-4 2.5-5 2.5-5a 2.5-5b 2.5"6 2~5 7 2.5-8 2.5-9 2.5-10 2.5-11 2.5-12 2.5-13 2.5-14 2.5-15 2.5-16 2.5-17 2.5-18 Amendment Number RO RO RO 8 0 26 0 26 0 RO RO 0 8 0 0 0 0 0 3 3 26 4 25 4 0 0 0 28 28 28 0 0 0 0 0 0 0 0 0 0 0 0 0 USAR Revision 1 EP 2-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 2.5-19 2.5-20 2.5-21 2e5-22 2.5-22a 2.5"22b 2.5-23 2.5-24 2.5"25 2.5-26 2e5"27 2.5"28 2.5-29 2.5-30 2.5-31 2.5-32 2e5-33 2.5-34 2.5-35 2.5"36 2'-37 2.5-38 2.5-39 2.5-40 2.5-41 2.5-42 2.5-43 2.5"44 2.5-45 2.5-46 2.5-47 2.5-48 2.5"49 2.5"50 2.5-51 2.5-52 2'-53 2~5-54 2'-55 2.5"56 2.5-57 2.5"58 2.5-59 2.5-60 2.5-61 2.5-62 2.5-63 0 0 0 RO RO RO 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 26 0 0 0 0 0 RO 0 0 0 0 RO RO RO RO RO 0 0 RO 0 4 RO 2.5-64 2.5-65 2.5-66 2.5-67 2.5"68 2.5-69 2.5-70 2.5-71 2~5 72 2~5 73 2.5-74 2~5 75 2.5-76 2.5-77 2.5-78 2.5-79 2.5-80 2.5-81 2.5-82 2.5-83 2.5-84 2.5-85 2.5-86 2.5-87 2.5-88 2.5-89 2.5"90 2.5-91 2.5-92 2.5-93 2.5-94 2.5-95 2.5-96 2.5-97 2.5-98 2.5-99 2.5-100 2.5-101 2.5-102 2.5-103 2.5-104 2.5-105 2.5-106 2.5-107 2.5-108 2.5-109 2.5-110 RO RO 0 0 0 0 0 0 RO 0 0 0 0 0 0 0 0 0 0 RO RO 0 RO 0 0 0 0 RO 0 0 0 0 0 0 26 0 0 0 0 0 0 0 0 0 0 0 0 2.5-111 2.5-112 2.5-113 2.5-114 2.5-115 2.5-116 2.5-117 2.5-118 2.5-119 2.5-120 2.5-121 2.5-122 2.5-123 2.5-124 2.5-125 2.5-126 2.5-127 2.5-128 2.5-129 2.5-130 2.5-131 2.5-132 2.5-133 2.5"134 2.5-135 2.5-136 2.5-137 2.5-138 2.5-139 2.5-140 2.5-141 2.5-142 2.5-143 2.5-144 2.5"145 2.5-146 2.5-147 2.5"148 2.5-149 2.5-150 2.5-151 2.5-152 2.5-153 2.5-154 2.5-155 2.5-156 2.5-157 0 0 0 0 0 0 0 0 0 RO RO RO 0 RO 0 0 RO 28 0 0 0 0 4 0 0 0 0 0 0 0 0 0 0 0 26 USAR Revision EP 2-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Fi're 2.5-158 2.5-159 2.5-160 2.5"161 2.5-162 2.5-163 2.5-164 2.5-165 2.5-166 2.5-167 2.5-167a 2.5-167b 2.5-167c 2.5-167d 2.5-168 2.5-168a 2.5-168b 2.5-168c 2.5-168d 2.5-169 2.5-170 2.5"171 2.5-171a 2.5-171b'.5-172 2.5-173 2.5-173a 2.5-173b 2.5-174 2.5-174a 2.5-174b 2.5-174c 2.5-174d 2.5-175 2.5-176 2.5-176a 2.5"176b 2.5-177 2.5"177a 2.5-177b 2.5-177c 2.5-177d 2.5-178 2.5-178a 2.5"178b 2.5-178c 2.5'-178d Amendment Number 0 0 0 0 0 0 0 0 0 27 5 RO 5 5 18 5 5 5 5 0 0 Rl RO 5 0 RO RO RO RO 15 15 15 15 11 ll 5 5 5 18 RO RO RO 18 12 12 RO 12 Page T=Table~i'=Fi ure 2.5-179 2.5-180 2.5"181 2.5-182 2.5-183 2.5-184 2.5-185 2.5-186 2.5-187 2.5-188 2.5-189 2.5-190 2.5-191 2.5-192 2.5-192a 2.5-192b 2.5-193 2.5"194 2.5-194.1 2.5-194.2 2.5"194a 2.5-194b 2.5-194c 2.5-194d 2.5-194e 2'-1948 2.5-194g 2.5-194}l 2.5-194i 2.5-194j 2'-194k 2.5-1941 2.5-195 2'-196 2.5-197 2'-198 2.5-199 2'-200 2.5-201 2.5-202 2'-203 2.5-204 2'-205 2'-206 2.5-207 2.5-208 2.5-209 Amendment Number 12 RO 0 0 0 0 0 0 0 0 0 0 0 15 RO 11 0 RO 24 24 14 27 26 26 19 14 14 14 14 14 26 26 14 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page T=Table~P=Fi ure 2.5-210 2.5-211 2.5-212 2.5-213 2.5-214 2.5-215 2.5-216 2'-217 2.5-218 2.5-219 2.5-220 T 2.5-1 T 2.5-2 S}1 1 Sjl 2 Sh 3 Sh 4 Sh 5 S}1 6 T 2.5-3 S}1 1 Sjl 2 Sjl 3 T 2.5-4 T 2.5-5 S}1 1 S}1 2 Sjl 3 T 2.5-6 T 2.5-7 T 2.5-8 T 2.5-9 Sjl 1 Sh 2 T 2.5-10 T 2.5-11 T 2.5-12 S}1 1 S}1 2 T 2.5-13 T 2.5-14 T 2'-15 T 2'-16 S}1 1 Sjl 2 T 2~5-17 T 2.5-18 Amendment Number 0 0 0 0 0 0 0 0 0 13 RO 0 USAR Revision 1 EP 2-5 October 1989,

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Pi ure S}l 1 S}1 2 S}1 3 sh 4 T 2.5-19 T 2.5-20 T 2.5-21 S}1 1 S}1 2 S}1 3 S}1 4 S}1 5 T 2.5-22 S}1 1 S}1 2 T 2e5-23 S}l 1 S}1 2 T 2.5-24 T 2.5-25 T 2.5-26 T 2.5-27 T 2.5-28 T 2.5-28A T 2.5-29 S}1 1 Sh 2 S}1 3 S}1 4 S}1 5 S}1 6 Sh 7 T 2.5-30 T 2.5-31 T 2'-32 T 2e5-33 S}1 1 S}1 2 S}1 3 S}1 4 S}1 5 T 2.5-34 T 2.5-35 T 2.5-36 T 2.5"37 T 2.5-38 T 2.5-39 Amendment Number 0 0 0 0 0 0 0 0 0 0 0 0 21 0 0 0 0 0 22 0 5 5 5 5 Page T=Table~P=Fi ure 2.5-40 2.5"41 2.5-42 2.5-43 S}1 1 S}l 2 2.5-44 2.5-45 2.5-45A 2.5-46 2.5-46A 2.5-46B 2.5-46C 2.5-47 2.5-48A 2.5-48B 2.5-48C 2.5"49 2'-50 2.5-1 2'-2 2.5-3 2.5"4 2.5-5 2.5-6 2.5-7 2.5-8 2.5-9 2.5-10 2.5-11 2.5"12 2.5-13 2.5-14 2.5-15 2.5"16 2.5-17 2.5-18 2.5-19 2.5-20 2.5-21 2'-22 2e5-23 2.5-24 2.5-25 2.5-26 2.5-27 2.5-28 Amendment Number 18 9 ll 18 19 18 14 17 17 14 14 14 17 17 22 0 0 0 0 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 Page T=Table~P=Fi ure 2.5-28A 2.5-29 2.5-30 2.5-31 2e5-32 2~5 33 2.5-34 2~5 35 2.5-36 2.5-37 2.5-38 2.5-39 2.5-40 2.5-41 2.5-42 2.5-43 2'-44 2.5-45 2.5-47 2.5-48 2.5-49 2.5-50 2.5-51 2.5-52 2.5-53 2.5-54 2.5-55 2.5-56 2.5-57 2.5-58 2'-59 2.5-60 2.5-61 2.5"62 2.5-63 2.5-64 2.5-65 2.5-66 2.5-67 2.5-68 2.5-69 2'-70 2.5-71 2.5-72 2~5 73 2.5-74 2~5 75 Amendment Number 13 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 0 0 0 USAR Revision EP 2-6 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Pi ure Amendment Number Page T=Table~P=Pi ure Amendment Number Page T=Table~P=Pi ure Amendment Number 2.5-76 2~5 77 2.5-78 2'-79 2.5-80 2.5-81 2.5-82 2.5-83 2.5-84 2.5-85 2.5-86 2.5-87 2.5-88 2.5-89 2.5-90 2.5-91 2.5-92 2.5-93 2.5-94 2.5-95 2.5-96 2.5-96A 2.5-96B 2.5-96C 2.5-96D 2.5-96E 2.5-96F 2.5"97'.5-98 2.5-99 2.5-100 2.5"101 2.5-102 2.5-102A 2.5-102B 2.5-103 2.5-104 2.5-105 2.5"105A 2.5-105B 2.5"105C 2.5-105D 2.5-105E 2.S-105F 2.5-105G 2.5-105H 2.5-105I 0 0 0 0 0 0 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 5 5 5 5 27 27 0 0 0 0 0 0 5 5 0 0 0 5 5 5 5 5 5 5 5 5 F 2.5-105J 2.5-106 2.5-107 2.5-108 2.5-109 2.5-110 2.5-111 2.5-112 2.5-113 2.5-114 2.5-115 Sjl 1 S11 2 2.5-116 2.5-117 Sh 1 Sjl 2 2.5-118 2.5-119 S11 1 S11 2 Sjl 3 Sjl 4 2.5-120 Sjl 1 S11 2 S11 3 S11 4 2.5-121 Sjl 1 Sjl 2 S11 3 2.5-122 2.5-123 2.5-124 2.5-125 2.5-126 2.5-127 2.5-127a 2.5-127b 2.5-128 2.5-129 2.5-130 2.5-131 2.5-132 2.5-133 2.5-134 ll 0 0 0 0 5 5 0 5 0 0 0 0 0 0 0 0 0 22 9 9 23 5 5 5 5 5 5 2.5-135 2.5-136 2.5-137 2.5-138 2.5-139 2.5-140 2.5-141 2.5-142 2.5-143 2.5-144 2.5-145 2.5-146 2.5-147 2.5-148 2.5-149 2.5-150 2.5-151 2.5-152 2.5-153 2.5-154 2.5-155 2.5-156 2.5-157 2.5-158 2.5-159 2.5-160 2.5-161 2.5-162 2.5-163 2.5-164 2.5-165 2.5-166 2.5-167 2.5-168 2.5-169 2.5-170 2.5-171 2.5-172 2.5-173 2.5-174 2.5-175 2.5-176 2.5-177 2.5-178 2.5-179 2.5-180 2.5-181 11 12 12 12 12 12 12 12 12 12 12 12 12 12 12 28 13 13 13 22 22 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 USAR Revision EP 2-7 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Fi ure 2.5-182 2.5-183 2.5"184 2.5-185 2.5-186 2.5"187 2.5-188 2.5-189 2.5-190 2.5-191 2.5"192 S}1 1 S}1 2 2.5-193 Sh 1 S}l 2 2.5-194 2.5-195 2.5"196 2.5"197 S}1 1 S}l 2 Sh 3 2.5-198 Sh 1 S}1 2 S}l 3 Sh 4 S}1 5 S}1 6 2.5-199 Sh 1 Sh 2 S}1 3 S}1 4 S}1 5 2e5-200 S}l 1 S}1 2 2.5"201 S}1 1 S}1 2 S}1 3 2.5-202 2.5-203 2'-204 2.5-205 Amendment Number 14 14 14 14 14 14 27 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 Page T=Table~F=Fi ure F 2.5-206 F 2.5-207 F 2.5-208 S}1 1 Sh 2 Sh 3 S}1 4 Sh 5 S}1 6 Sh 7 Sh 8 S}i 9 S}1 10 F 2.5-209 F 2.5-210 S}1 1 S}1 2 S}1 3 Sh 4 F 2.5"211 S}1 1 Sh 2 F 2.5-212 Sh 1 Sh 2 S}1 3 App 2A 2A-1 2A-2 2A-3 2A-4 2A-5 T 2A-1, S}1 1 S}l 2 S}1 3 sh 4 F 2A-1 App 2B 2B-i 2B-ii 2B-iii 2B-iv T 2B-1 T 2B-2 Amendment Number 14 14 14 14 14 14 14 14 14 14 14 14 23 26 26 26 26 26 26 26 26 26 Page T=Table~F=Fi ure T 2B-2A T 2B-2B T 2B-3 S}1 1 S}1 2 S}1 3 S}1 4 S}l 5 S}l 6 S}1 7 S}1 8 S}1 9 T 28-4 Sh 1 S}1 2 Sh 3 Sh 4 S}1 5 S}1 6 Sh 7 S}1 8 S}1 9 T 2B-5 S}l 1 S}1 2 S}1 3 Sh 4 S}1 5 S}1 6 S}1 7 Sh 8 S}1 9 T 2B-6 Sh 1 S}1 2 S}1 3 S}1 4 Sh 5 S}1 6 Sh 7 Sh 8 S}1 9 Sh 10 Sh 11 Sh 12 Sh 13 Sh 14 Amendment Number 0 0 0 0 0 0 0 0 0 USAR Revision 1 EP 2"8 October 1989 0

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure S}1 15 S}i 16 Sh 17 Sh 18 S}1 19 Sh 20 S}1 21 Sh 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sh 30 Sh 31 Sh 32 S}1 33 Sh 34 S}1 35 Sh 36 Sh 37 Sh 38 Sh 39 Sh 40 S}1 41 S}1 42 Sh 43 Sh 44 Sh 45 Sh, 46 Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 Sh 52 Sh 53 S}i 54 Sh 55 Sh 56 Sh 57 Sh 58 Sh 59 Sh 60 Sh 61 Amendment Number Page T=Table~F=Fi ure Sh 62 Sh 63 Sh 64 S}1 65 Sh 66 Sh 67 Sh 68 Sh 69 Sh 70 Sh 71 Sh 72 Sh 73 Sh 74 Sh 75 Sh 76 Sh 77 Sh 78 Sh 79 Sh 80 Sjl 81 Sh 82 Sh 83 Sh 84 Sh 85 Sh 86 Sh 87 Sh 88 Sh 89 Sh 90 Sh 91 Sh 92 Sh 93 Sh 94 Sh 95 Sh 96 Sh 97 Sh 98 Sh 99 Sh 100 Sh 101 Sh 102 Sh 103 Sh 104 Sh 105 Sh 106 Sh 107 Sh 108 Amendment Number Page T=Table~F=Fi ure T 2B-7 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Sh 13 Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 S}1 20 Sh 21 S}1 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sjl 30 Sh 31 Sh 32 Sh 33 Sjl 34 Sh 35 S}1 36 Sh 37 Sh 38 Sh 39 Sh 40 Sh 41 Sh 42 Sh 43 Sh 44 Sh 45 Sh 46 Amendment Number USAR Revision EP 2-9 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 S}1 52 S}1 53 S}1 54 Sh 55 Sh 56 Sh 57 S}1 58 Sh 59 Sh 60 Sh 61 Sh 62 Sh 63 Sh 64 Sh 65 Sh 66 S}1 67 S}1 68 Sh 69 Sh 70 Sh 71 Sh 72 Sh 73 S}1 74 S}1 75 Sh 76 Sh 77 Sh 78 Sh 79 Sh 80 Sh 81 Sh 82 S}1 83 Sh 84 S}1 85 Sh 86 Sh 87 Sb.88 Sh 89 Sh 90 Sh 91 Sh 92 Sh 93 Amendment Number Page T=Table~F=Fi ure Sh 94 Sh 95 Sh, 96 Sh 97 Sh 98 Sh 99 Sh 100 Sh 101 Sh 102 Sh 103 Sh 104 Sh 105 Sh 106 Sh 107 Sh 108 T 2B-8 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Sh 13 Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 Sh 20 Sh 21 Sh 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sh 30 Sh 31 Amendment Number Page T=Table Amendment~F=Fi ure'umber Sh 32 Sh 33 Sh 34 Sh 35 Sh 36 S}1 37 Sh 38 Sh 39 Sh 40 S}1 41 Sh 42 Sh 43 Sh 44 Sh 45 Sh 46 Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 Sh 52 Sh 53 S}1 54 Sh 55 Sh 56 Sh 57 S}1 58 Sh 59 Sh 60 Sh 61 Sh 62 Sh 63 Sh 64 Sh 65 Sh 66 Sh 67 Sh 68 Sh 69 Sh 70 Sh 71 Sh 72 Sh 73 Sh 74 Sh 75 S}1 76 Sh 77 Sh 78 USAR Revision EP 2-10 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Fi ure Sh 79 S}1 80 Sh 81 Sh 82 Sh 83 Sh 84 Sh 85 Sh 86 Sh 87 Sh 88 Sh 89 Sh 90 Sh 91 Sh 92 Sh 93 Sh 94 Sh 95 Sh 96 Sh 97 Sh 98 Sh 99 Sh 100 Sh 101 Sh 102 Sh 103 Sh 104 Sh 105 Sh 106 Sh 107 S}1 108 T 2B-9 T 2B-10 Sh 1 S}1 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 T 2B-ll T 2B-12 T 2B-13 T 2B-14 Sh 1 Sh 2 Sh 3 Amendment Number Page T=Table~F=Fi ure T 2B-15 Sh 1 S}1 2 Sh 3 T 2B-16 Sh 1 Sh 2 Sh 3 T 2B-17 S}1 1 S}1 2 Sh 3 S}1 4 Sh 5 Sh 6 Sh 7 S}1 8 Sh 9 Sh 10 Sh 11 S}1 12 T 2B-18 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 S}1 10 Sh 11 Sh 12 T 2B-19 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Amendment Number Page T=Table~P=Pi ure T 2B-20 T 2B-21 T 2B-22 T 2B-23 T 2B-24 T 2B-25 Sh 1 Sh 2 T 2B-26 T 2B-27 T 2B-28 T 2B-29 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 T 2B-30 T 2B-31 T 2B-32 T 2B-33 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 T 2B-34 Sh 1.Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 T 2B-35 Sh 1 Sh 2 Amendment Number USAR Revision EP 2-11 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee Sh 3 sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 T 2B-36 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 sh 6 Sh 7 Sh 8 Sh 9 T 28-37 Sh l Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 S}1 12 Sh 13 Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 Sh 20 Sh 21 Sh 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Amendment Number 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0 0 0 0 Page T=Table~FFi uue Sh 30 Sh 31 Sh 32 sh 33 Sh 34 Sh 35 Sh 36 Sh 37 Sh 38 Sh 39 Sh 40 S}1 41 Sh 42 Sh 43 Sh 44 Sh 45 sh 46 Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 Sh 52 Sh 53 Sh 54 Sh 55 Sh 56 Sh 57 Sh 58 Sh 59 Sh 60 Sh 61 Sh 62 Sh 63 Sh 64 Sh 65 Sh 66 Sh 67 Sh 68 Sh 69 S}1 70 Sh 71 Sh 72 Sh 73 Sh 74 Sh 75 Sh 76 Amendment Number Sh Sh 107 108 2B-38 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Sh 13 Sh 14 Page T=Table~F=Fi uee Sh 77 Sh 78 Sh 79 Sh 80 Sh 81 Sh 82 Sh 83 Sh 84 Sh 85 Sh 86 Sh 87 Sh 88 Sh 89 Sh 90 Sh 91 Sh 92 Sh 93 Sh 94 Sh 95 Sh 96 Sh 97 Sh 98 Sh 99 Sh 100 Sh 101 Sh 102 Sh 103 Sh l04 Sh 105 Sh 106 Amendment Number USAR Revision EP 2-12 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sh 15 Sh 16 Sh 17 Sh 18 S}1 19 Sh 20 Sh 21 Sh 22 S}1 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sh 30 Sh 31 Sh 32 S}1 33 Sh 34 Sh 35 Sh 36 Sh 37 Sh 38 Sh 39 Sh 40 Sh 41 Sh 42 Sh 43 Sh 44 Sh 45 Sh 46 Sh 47 Sh 48 S}1 49 Sh 50 Sh 51 Sh 52 Sh 53 Sh 54 Sh 55 Sh 56 Sh 57 Sh 58 Sh 59 Sh 60 Sh 61 Amendment Number Page T=Table~F=Fi ure Sh 62 S}1 63 S}i 64 Sh 65 Sh 66 S}1 67'Sh 68 Sh 69 Sh 70 Sh 71 Sh 72 Sh 73 Sh 74 Sh 75 Sh 76 Sh 77 Sh 78 Sh 79 S}1 80 Sh 81 S}1 82 Sh 83 Sh 84 Sh 85 Sh 86 Sh 87 Sh 88 Sh 89 Sh 90 Sh 91 Sh 92 Sh 93 Sh 94 Sh 95 Sh 96 Sh 97 Sh 98 Sh 99 Sh 100 S}1 101 Sh 102 Sh 103 Sh 104 Sh 105 Sh 106 Sh 107 Sh 108 Amendment Number Page T=Table~F=Fi ure 28-39 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Sh 13 S}1 14 S}1 15 Sh 16 Sh 17 Sh 18 Sh 19 S}1 20 Sh 21 Sh 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sh 30 Sh 31 Sh 32 Sh 33 Sh 34 Sh 35 Sh 36 Sh 37 Sh 38 Sh 39 Sh 40 Sh 41 Sh 42 Sh 43 Sh 44 S}1 45 Sh 46 Amendment Number USAR Revision EP 2-13 October 1989 f~

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uue Sjl 47 Sjl 48 Sjl 49 Sh 50 Sjl 51 Sjl 52 Sh 53 Sh 54 Sjl 55 S}i 56 Sjl 57 Sh 58 Sjl 59 Sjl 60 Sh 61 Sjl 62 Sh 63 Sjl 64 Sjl 65 Sjl 66 S}i 67 Sh 68 Sh 69 Sh 70 Sjl 71 Sh 72 Sjl 73 Sh 74 Sh 75 Sh 76 Sh 77 Sh 78 Sjl 79 Sh 80 Sh 81 Sh 82 Sjl 83 Sjl 84 Sjl 85 Sjl 86 Sjl 87 Sjl 88 Sh 89 Sh 90 Sjl 91 Sjl 92 Sjl 93 Amendment Number Page T=Table~F=Fi uue Sh 94 Sjl 95 Sjl 96 Sh 97 Sjl 98 Sh 99 S}i 100 S}1 101 Sh 102 Sh 103 S}1 104 Sh 105 Sh 106 Sh 107 Sh 108 T 2B-40 T 2B-41 T 2B-42 T 2B-42A T 2B-43 T 2B-44 Sh 1 Sjl 2 T 2B-45 T 2B-46 T 2B-47 T 2B-48 Sjl 1 S}1 2 T 2B-49 T 2B-50 T 2B-51 Sh 1 Sh 2 T 2B-52 T 2B-52A T 2B-53 T 2B-54 S}1 1 Sjl 2 App 2C 2C-1 2C-2 2C-3 2C-4 T 2C-1 Amendment Number Page T=Table~FFi uue F 2C-1 F 2C"2 F'C-3 App 2D 2D-i 2D-1 2D-2 2D-3 2D-4 2D-5 2D-6 2D-7 2D-8 2D-9 F 2D-1 F 2D-2 F 2D-3 App 2E 2E-1 2E-2 2E-3 App 2F 2F-i 2F-ia 2F-ib 2F-ii T 2F-1 S}1 1 Sjl 2 Sjl 3 T 2F-2 S}1 1 Sh 2 T 2F-2a Sh 1 Sjl 2 T 2F-2b T 2F-2c Sh 1 Sh 2 T 2F-3 T 2F-4 T 2F-5 T 2F-6 Amendment Number 0 23 23 23 0 23 23 23 13 13 23 23 23 23 23 23 23 0 13 USAR Revision EP 2-14 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee Sh 1 Sh 2 Sh 3 Sh 4 S}1 5 Sh 6 Sh 7 Sh 8 S}1 9 Sh 10 Sh 11 Sh 12 T 2F-7 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 T 2F-8 T 2F-9 T 2F-10 T 2F-ll Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 App 2G 2G-i T 2G-1 T 2G-2 T 2G-3 T 2G-4 T 2G"5 T 2G-6 T 2G-7 T2G-7a T 2G-8 Amendment Number 0 0 0 23 0 23 23 23 23 23 23 23 24 0 0 0 0 0 0 0 0 23 0 0 0 0 23 23 23 23 23 23 23 0 23 0 0 0 0 0 23 23 23 23 Page T=Table~F=Fi uee T 2G-9 App 2H 2H-i 2H-ia 2H-ib 2H-ii 2H-iii 2H-iv 2H-v 2H-vi 2H-vii 2H-1 Notes Sh 1 Sh 2 Sh 3 F 2H-1 F 2H-lA F 2H-2 F 2H-3 F 2H-4 F 2H-5 F 2H-6 F 2H-7 F 2H-8 F 2H-9 F 2H-10 F 2H-11 F 2H-12 F 2H-13 F 2H-14 F 2H-15 F 2H-16 F 2H-17 F 2H-18 F 2H-19 F 2H-20 F 2H-21 F 2H-22 F 2H-23 F 2H-24 F 2H-25 F 2H-26 F 2H-27 F 2H-28 F 2H"29 Amendment Number Page T=Table~F=Fi uee 2H"30 2H-31 Sh 1 Sh 2 2H-32 2H-33 2H-34 2H-35 2H-36 2H-37 2H-38 2H-39 2H-40 2H-41 2H-42 2H-43 2H-44 2H-45 2H-46 2H-47 2H-48 2H-49 2H-50 2H-51 2H-52 2H-53 2H-54 S}1 1 Sh 2 2H-55 2H-56 2H-57 2H-58 2H-59 2H-60 2H-61 2H-62 2H-63 2H-64 2H-65 2H-66 2H-67 2H-68 2H-69 2H-70 2H-71 2H-72 Amendment Number USAR Revision EP 2-15 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table Amendment~F=Fi ure Number F 2H-73 F 2H-74 F 2H-75 F 2H-76 S4 1 S4 2 F 2H-77 F 2H-78 F 2H-79 F 2H-80 F 2H-81 F 2H-82 F 2H-83 F 2H-84 F 2H-85 F 2H-86 F 2H-87 Sh 1 Sh 2 F 2H-88 F 2H-89 F 2H-90 F 2H-91 F 2H-92 F 2H-93 F 2H-94 F 2H-95 F 2H-96 F 2H-97 F 2H-98 F 2H-99 F 2H-100 F 2H-101 App 2I DSZ 2I-i 2I-ii 2I"iii 2I-iv 2I-v 2I-1 2I-2 2I-3 2I-4 2I-5 2I-6 0 0 0 0 0 0 0 0 0 0 0, 0 2I-7 2I-8 2I-9 2I-10 2I-11 2I-12 2I-13 2I-14 2I-15 2I-16 2I-17 2I-18 2I-19 2I-20 2I-21 2I-22 2I-23 2I-24 2I-25 2I-26 2I-27 2I-28 2I-29 2I-30 2I-31 2I-32 2I-33 2I-34 2I-35 2I-36 2I-37 2I-38 2I-39 2I-40 2I-41 2I-42 2I-43 2I-44 2I-45 2I-46 2I-47 2I-48 2I-49 2I-50 2I-51 2I-52 2I-53 2I-54 2I-55 2I-56 2I-57 2I-58 2I-59 2I-60 2I-61 2I-62 2I-63 2I-64 2I-65 2I-66 2I-67 2I-68 2I-69 2I-70 2I-71 2I-72 2I-73 2I-74 2I-75 2I-76 2I-77 2I-78 2I-79 2I-80 2I-81 2I-82 2I-83 2I-84 2I-85 2I-86 2I-87 2I-88 2I-89 2I-90 2I-91 2I-92 2I-93 2I-94 2I-95 2I-96 2I-97 2I-98 2I-99 2I-100 0 0 0 0 0 0 0 19 USAR Revision EP 2-16 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~FFi ure 2I-101 2I-102 21-103 2I-104 2I-105 2I-106 2I-107 2I-108 2I-109 2I-110 2I-111 2I-112 2I-113 2I-114 2I-115 2I-116 2I-117 2I"118 2I-119 2I-120 2I-121 2I-122 2I-123 2I-124 2I"125 2I-126 2I-127 2I-128 2I-129 2I-130 2I-131 2I-132 2I"133 2I-134 2I-135 2I-136 2I-137 2I"138 2I-139 2I-140 2I-141 2I-142 2I-143 2I"144 App 2J 2J-i Amendment Number Page T=Table~FFi ure 2J-1 2J-2 2J-3 2J-4 2J-5 2J-6 2J-7 2J-8 2J-9 2J-10 2J-11 2J-12 App 2K 2K-i 2K-ii 2K-iii 2K-iv 2K-v 2K-vi 2K-vii 2K-viii F 2K-1 F 2K-2 F 2K-3 F 2K-4A F 2K-4B F 2K-5A F 2K-5B F 2K-6A F 2K-6B F 2K-6C F 2K-7A F 2K-7B F 2K-7C F 2K-8A F 2K-8B F 2K-8C F 2K-9A F 2K-9B F 2K-9C F 2K-10A F 2K-10B F 2K"llA F 2K-11B F 2K-12A F 2K-12B Amendment Number Page T=Table~F=Fi ure 2K-12C 2K-12D 2K-12E 2K-12F 2K-13A 2K-13B 2K-13C 2K-13D 2K-13E 2K-13F 2K-14A 2K-14B 2K-14C 2K-15 2K-16A 2K-16B 2K-17A 2K-17B 2K-17C 2K-18A 2K-18B 2K-18C 2K-19A 2K-19B 2K-19C 2K-20A 2K-20B 2K-20C 2K-21A 2K-21B 2K-21C 2K-22A 2K-22B 2K-22C 2K-23A 2K-23B 2K-23C 2K-24A 2K-24B 2K-24C 2K-24D 2K-24E 2K-24F 2K-25A 2K-25B 2K-25C 2K-25D Amendment Number USAR Revision EP 2"17 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Pi uue F 2K-25E F 2K-25F F 2K-26A F 2K-26B F 2K-26C F 2K-26D F 2K-26E F 2K-26F F 2K-27A F 2K-27B F 2K-27C F 2K-27D F 2K-27E F 2K-27F F 2K-28A F 2K-28B F 2K-28C F 2K-28D F 2K-28E F 2K-28F F 2K-29A F 2K-29B F 2K-29C F 2K-29D F 2K-29E F 2K-29F F 2K-30A F 2K-30B F 2K-30C F 2K-30D F 2K-30E F 2K-30F F 2K-31A F 2K-31B F 2K-31C F 2K-31D F 2K-31E F 2K-31F F 2K-32A F 2K-32B F 2K-32C F 2K-32D F 2K-32E F 2K-32F F 2K-33A F 2K-33B F 2K-33C Amendment Number 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0 0 0 0 0 0 0 0 0 0 Page T=Table~P=Pi uue F 2K-34A F 2K-34B F 2K-34C F 2K-35A F 2K-35B F 2K-35C F 2K-36A F 2K-36B F 2K-36C F 2K-37A F 2K-37B F 2K-37C F 2K-37D F 2K-37E F 2K-37F F 2K-38A F 2K-38B F 2K-38C F 2K-38D F 2K-38E F 2K-38F F 2K-39A F 2K-39B F 2K-39C F 2K-39D F 2K-39E F 2K-39F F 2K-40A F 2K-40B F 2K-40C F 2K-41A F 2K-41B F 2K-42A F 2K-42B F 2K-43A F 2K-43B F 2K-44A F 2K-44B F 2K-45A F 2K-45B F 2K-45C F 2K-45D F 2K-46A F 2K-46B F 2K-46C F 2K-46D F 2K-47A Amendment Number Page T=Table~P=Fi uue F 2K-47B F 2K-47C F 2K-47D App 2L 2L-i 2L-ii 2L-iii 2L-1 2L-2 T 2L-1 Sh 1 S}1 2 T 2L-2 Sh 1 Sh 2 T 2L-3 Sh 1 Sb 2 T 2L-4 Sh 1 S11 2 T 2L-5 S11 1 S11 2 T 2L-6 S11 1 S11 2 T 2L-7 Sh 1 Sh 2 T 2L-8 Sjl 1 Sh 2 T 2L-9 S11 1 S11 2 T 2L-10 T 2L-11 T 2L-12 T 2L-13 T 2L-14 T 2L-15 T 2L-16 T 2L-17 T 2L-18 T 2L-19 Amendment Number USAR Revision EP 2-18 October 1989

'l Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure'2L-20 T 2L-21 T 2L-22 T 2L-23 T 2L-24 T 2L"25 T 2L-26 T 2L-27 T 2L-28 F 2L"1 F 2L-2 Amendment Number 7 7 7 7 7 7 7 7 7 7 13 Page T=Table Amendment~F=Fi ure Number Page T=Table Amendment~F=Fi ure Number USAR Revision 1 EP 2-19 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES 2N-1 2N-2 2N-3/4 2N-5/6 (F 2N-7 2N-8 2N-9 2N"10 2N-11 2N-12 2N-13" 2N-14 2N-15 2N-16 2N-17 2N-18 2N-19 2N-20 2N"21 2N-22 230.3-1)2N"23/24 (F 231.10-1)2N-25/26 2N-27/28 2N-29/30 (F 231.11-1)2N-31 2N-32 2N-33 2N-34 2N"35 2N-36 Page T=Table~ii=Fi uee App 2M Table of Contents NRC Site Visit (7 pg)NRC Meeting Field Notebook 76-2 (2 pg)Meeting at Site (4 pg)Affidavit-Douglas E.Isler Affidavit-John J.Markham Affidavit-John H.Peck (2 pg)Figure 1 Figure 2 Figure 3 Figure 4 App 2N Amendment Number 16 16 16 16 16 16 16 16 16 16 16 16 16 RO RO RO-RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 2"20 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ere 2N-37 2N-38 2N-39 2N-40 2N-41 2N-42 2N-43 2N-44 2N-45/46 2N-47/48 (T 2N-49 2N-50 2N-51 2N-52 2N-53 2N-54 2N-55 2N-56 2N-57/58 (T 2N-59/60 (T 2N"61/62 (T 2N-63/64 (T F 241.16-1 F 241.16-2 F 241.16-3 F 241.16-4 F 241.16-5 F 241.16"6 F 241.16-7 F 241.16-8 F 241.16-9 F 241.16-10 F 241.16-11 F 241.16"12 F 241.16-13 F 241.16-14 F 241.16-15 F 241.16-16 F 241.16-17 F 241.16-18 F 241'6-19 F 241.16-20 F 241.16-21 F 241.16-22 F 241.16-23 F 241.16-24 F 241.16-25 241.2"1)241.16-1)241.16-2, Sh 1)241.16-2, Sh 2)241.16-2, Sh 3)Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 2-21 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi use F 241.16-26a F 241.16-26b F 241.16-27a F 241.16-27b F 241.16-27c F 241.16-28a F 241.16-28b F 241.16-29 F 241.16-30 F 241.16-31a F 241.16-31b F 241.16-32a F 241.16-32b F 241.16-32c F 241.16-33 F 241.16-34 F 241.16-35 F 241.16-36 F 241.16-37 F 241.16-38 F 241.16-39 F 241.16-40 F 241.16"41 F 241.16-42 F 241.16-43 F 241.16-44 F 241.16-45 F 241.16-46'mendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO App 2P 2P-1 2P-2 2P-3 2P"4 2P-5 2P-6 2P-7/8 (T 451.13-1)2P-9/10 (T 451.13-2)2P-11/12 (T 451.13-3)2P-13/14 (T 451.13-4)2P-15 2P-16 2P-17/18 2P-19/20 (F 451'4-1)2P-21/22 (F 451'4-2)2P-23/24 (F 451.14-3)2P-25 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 2-22 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 2P"26 2P"27 2P-28 2P-29 2P-30 2P"31 2P-32 2P-33/34 2P-35/36 2P-37/38 2P-39/40 2P"41/42 2P-43/44 2P-45/46 2P-47/48 2P-49/50 2P-51/52 2P-53/54 2P"55/56 2P-57/58 2P-59/60 2P-61/62 2P-63/64 2P-65/66 (T 451.15-1)(T 451.15-2)(T 451.15-3)(T 4S1.1S-4)(T 451.15-5, Sh 1)(T 451.15-5, Sh 2)(T 4S1.15-5, Sh 3)(T 451.15-5, Sh 4)(T 451.15-6, Sh 1)(T 451.1S-6, Sh 2)(T 451.15-6, Sh 3)(T 451.15-6, Sh 4)(T 451.1S-7, Sh 1)(T 451.15-7, Sh 2)(T 451.15-7, Sh 3)(T 451.15-7, Sh 4)Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure App 2Q 2Q"1 2Q-2 2Q-3 2Q-4 2Q-5 2Q-6 2Q-7 2Q-8 2Q-9 2Q-10 2Q-ll 2Q-12 2Q-13 2Q-14 2Q-15 2Q-16 2Q-17 2Q-18 2Q-19 2Q-20 2Q-21 2Q-22 T GI-1 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO.RO RO RO RO RO RO USAR Revision 1 EP 2-23 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 3 Page T=Table Amendment~F=Fi ur'e Number Page T=Table~F=Pi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 3 1 3 11 3 111 3-lv 3-U 3-Ul 3 Vll 3-Vl 1 1 3 lX 3-x 3-xl 3-Xl 1 3 xlla 3-xiib 3 Xlll 3-xlv 3-XU 3-xvl 3-Xvl 1 3-xvlll 3-xlx 3-xx 3-xxl 3 xxll 3 XX111 3 xxlv 3-xxlva 3-xxivb 3-xxv 3-xxvl 3-xxvll 3 xxvlll 3-xxlx 3 xxx 3-xxxl 3-xxxl 1 3 xxxl la 3-xxxiib 3-xxxl l l 3 xxxllla 3-xxxiiib 3-xxxlv 3 xxxlva 3"xxxivb 3-xxxv 0 0 0 9 25 RO 0 0 RO RO 19 24 24 24 23 8 RO RO RO 28 28 26 24 24 RO 7 7 7 0 24 12 12 12 12 12 12 21 12 RO 24 5 24 23 5 RO 3-xxxvl 3-xxxvll 3 xxxvlll 3-xxxlx 3-xl 3-xla 3-xlb 3-xli 3-xlil 3-xli2 3-xiii 3-xliii 3-xliv 3"xliva 3-xlivb 3-xlv 3-xlvi 3-xlvii 3-xlviii 3-xlix 3.1-1 3.1-2 3.1-3 3.1"4 3.1-5 3.1-6 3.1-7 3.1-8 3.1-9 3.1-10 3.1-11 3.1-12 3.1-13 3.1-13a 3.1-13b 3.1-14 3.1-15 3.1-16 3.1-17 3.1-18 3.1-19 3.1-20 3.1-21 3.1-22 28 24 24 24 24 12 12 27 21 21 0 24 RO RO 18 0 RO RO RO RO 0 0 0 0 18 12 0 0 0 0 0 0 28 19 19 0 0 0 0 0 0 0 0 0 3.1-23 3.1-24 3.1-25 3.1-26 3.1-27 3.1-28 3.1-29 3.1-30 3.1-31 3.1-32 3.1-33 3.1-34 3.1-35 3.1-36 3.1-37 3.1-38 3.1-39 3.1-40 3.1-41 3.1"42 3.1-43 3.1"44 3.1-45 3.1-46 3.1-47 3.1-48 3.1-49 3.1-50 3.1-51 3.1-52 3.1"53 3.1-54 3'"55 3.1-56 3.1-57 3.1-58 3.1-59 3.1-60 3.1-61 3.1"62 3.1-63 3.1-64 3.1"65 3.1-66 3.1"67 0 28 0 0 0 0 0 0 0 0 0 27 0 0 0 0 0 0 0 0 19 0 19 0 27 0 0 0 0 28 0 0 0 0 0 0 RO 0 0 0 0 0 0 0 0 USAR Revision 1 EP 3"1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 3.1-68 3.1-69 3.1-70 3.1-71 3.2-1 3~2 2 3e2-3 T 3.2-1 Sh 1 S}1 2 S}l 3 Sh 3a S}1 4 Sh 5 Sh 5a Sh 6 Sjl 7 Sjl 8 Sh 9 S}1 9a Sjl 10 Sh 10a Sh 11 Sh lla Sjl 12 Sh 12a Sh 13 Sh 13a S}1 14 Sh 14a Sh 15 Sh 15a S}1 16 Sh 16a Sh 17 Sh 17a S}1 18 Sjl 19 S}1 20 S}1 21 Sjl 22 S11 23 Sh 24 Sh 25 Amendment Number 26 15 9 28 Rl 27 19 RO 19 26 26 26 23 27 26 RO 19 26 19 RO RO 25 RO 27 26 27 Rl Rl RO RO RO 0 20 7 0 RO 7 RO 12 Page T=Table~F=Fi ure S}l 26 Sh 26a Sjl 26b Sh 26c Sjl 26d Sh 26e Sjl 26K Sh 26g Sjl 26}1 T 3~2 2 Sh 1 Sh 2 T 3~2 3 T 3.2-4 Sh 1 S}l 2 F 3.2-1 3.3-1 3~3 2 3~3 3 3.3-4 3.3-5 3.3-6 T 3.3-1 3.4-1 3.4-1a 3.4-1b 3.4-2 3.4-2a 3.4-2b 3.4-3 3.4-3a 3.4-3b 3.4-4 3.4-5 3.4-6 T 3.4-1 S}l 1 S}1 2 T 3.4-2 Sh 1 Sjl 2 Sh 3 Amendment Number 13 Rl RO Rl RO RO RO RO RO RO RO 23 28 28 21 26 13 0 5 5 0 0 RO 5 5 RO RO RO RO RO 5 RO 0 0 RO RO RO 25 RO Page T=Table~F=Fi ure T 3.4-3 T 3.4-4 T 3.4-5 S}l 1 S}1 2 T 3.4-6 T 3.4-7 3.5-1 3~5 2 3.5-3 3.5-4 3.5-4a 3.5-4b 3.5-4c 3.5-4d 3.5-5 3.5-5a 3.5-5b 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 3.5-13 3.5-14 3.5-15 3.5-15a 3.5-15b 3.5-16 3.5-17 3.5-18 3.5-19 3.5-19a 3.5-19b 3.5-20 3.5-21 3.5-22 T 3.5-1 S}1 1 Sh 2 T 3.5-2 T 3.5-3 Amendment Number RO RO RO RO RO 28 4 9 5 27 27 27 27 26 27 27 27 0 8 0 0 0 0 1 0 0 24 14 14 0 0 21 RO RO RO 0 0 0 RO 0 26 0 USAR Revision EP 3-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 3.5-4 T 3.5-5 T 3.5-6 T 3~5 7 T 3.5-8 T 3.5-9 T 3.5-10 T 3.5-11 T 3.5-12 T 3.5-13 T 3.5"14 T 3.5-15 T 3.5-16 T 3.5-17 Sh 1 Sh 2 Sh 3 T 3.5-18 S}1 1 Sh 2 Sh,3 T 3.5-19 T 3.5-20 Sh 1 Sh 2 Sh 3 T 3.5-21 T 3.5-22 Sh 1 S}1 2 F 3.5-1 F 3.5-2 F 3.5-3 F 3.5-4 F 3.5-5 3.6A-l 3.6A"2 3.6A-3 3.6A-4 3.6A-5 3.6A-6 3.6A-7 3.6A-8 3.6A-9 Amendment Number 0 28 0 0 0 0 0 28 0 0 28 0 0 26 24 24 25 24 24 4 0 0 0 0 0 0 0 0 27 0 RO RO 0 Page T=Table~F=Fi u're 3.6A-10 3'A-10a 3.6A-10b 3.6A-ll 3'A-12 3.6A-12a 3~6A-12b 3.6A-13 3.6A-14 3.6A-14a 3.6A-14b 3.6A-15 3.6A-15a 3.6A-15b 3.6A-16 3.6A-17 3.6A-17a 3.6A-17b 3.6A-18 3.6A-19 3.6A-20 3.6A-21 3.6A-22 3.6A-23 3.6A-24 3.6A"25 3.6A-26 3.6A-27 3.6A-28 3.6A-28a 3.6A-28b 3.6A-29 3.6A-30 3.6A-31 3.6A-32 3.6A-33 3.6A-34 3.6A-35 3.6A-35a 3.6A-35b 3.6A-36 3.6A-37 3.6A-38 T 3.6A-1 S}1 1 Amendment Number RO RO RO 0 RO RO RO 0 12 12 12 RO RO RO RO 12 12 12 0 0 0 0 0 0 0 0 0 0 RO RO RO 0 0 21 0 0 0 12 12 12 5 27 RO 28 Page T=Table~F=Fi ure Sh 2 Sh 3 Sh 4 Sh 5 T 3.6A-2 T 3.6A-3 T 3.6A-4 T 3'A-5 T 3'A"6 T 3.6A-7 T 3.6A-8 T 3.6A-9 T 3.6A-10 T 3.6A-ll T 3.6A-12 T 3.6A-13 T 3.6A-14 T 3.6A-15 T 3.6A-16 T 3.6A-17 T 3.6A-18 T 3.6A-19 T 3.6A-20 T 3.6A-21 T 3.6A-22 T 3.6A-23 T 3.6A-24 T 3.6A-25 T 3.6A-26 T 3.6A-27 T 3.6A-28 T 3.6A-29 T 3.6A-30 T 3.6A-31 T 3.6A-32 T 3.6A-33 T 3.6A-34 T 3.6A-35 T 3.6A-36 T 3.6A-37 T 3.6A-38 T 3.6A-39 T 3.6A-40 T 3'A-41 T 3'A-42 Amendment Number 28 28 23 28 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 USAR Revision EP 3-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 3.6A-43 T 3.6A-44 T 3.6A-45 T 3.6A-46 T 3.6A-47 T 3.6A-48 T 3.6A-49 T 3.6A-50 T 3.6A-51 T 3.6A-52 T 3.6A-53 T 3.6A-54 T 3.6A-55 T 3.6A-56 T 3.6A-57 T 3.6A-58 T 3.6A"59 T 3.6A-60 T 3.6A-61 T 3.6A-62 T 3.6A-63 T 3.6A-64 T 3'A-65 T 3'A-66 T 3.6A-67 T 3.6A-68 T 3'A-69 T 3.6A"70 T 3.6A-71 T 3.6A-72 Sh 1 S}L 2 S}L 3 S}L 4 T 3.6A-73 S}L 1 S}1 2 F 3.6A-l F 3.6A-2 F 3'A-3 F 3.6A-4 F 3.6A-5 F 3'A-6 F 3'A-7 F 3.6A-8 Amendment Number 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 21 21 21 21 21 21 0 0 0 0 0 0 0 0 Page T=Table~F=Fi ure 3.6A-9 3.6A-10 3.6A-ll 3.6A-12 3.6A-13 3.6A-14 3.6A-15 3.6A-16 3.6A-17 3.6A-18 3.6A-19 3.6A-20 3.6A-21 3.6A-22 3.6A-23 3.6A-24 3.6A-25 3.6A-26 3.6A-27 3.6A-28 3.6A-29 3.6A-30 3.6A-31 3.6A-32 3.6A-33 3.6A-34 3.6A-35 3.6A-36 3.6A-37 3.6A-38 3.6A-39 3.6A-40 3.6A-41 3.6A-42 3.6A"43 3.6A-44 3.6A-45 3.6A-46 3.6A-47 3.6A-48 3.6A-49 3.6A-50 3.6A-51 3.6A-52 3.6A-53 Amendment Number 0 0 0 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 27 27 RO RO Page T=Table~F=Fi ure F 3.6A-54 F 3'A-55 F 3.6A-56 F 3.6A-57 F 3.6A-58 F 3.6A-59 F 3.6A-60 3.6B-1 3.6B-2 3.6B-3 3.6B-4 3.6B-5 3.6B-6 3.68-7 3.68-8 3.6B-9 3.68-9a 3.6B-9b 3.6B-10 3.6B-11 3.6B-12 3.6B-13 3.6B-14 3.6B-15 3.6B-16 3.68-17 3.6B-18 3.6B-19 3.6B-20 3.68-21 T 3.6B-1 T 3.6B-2 F 3.6B-1 F 3'B-2 F 3.6B-3 3.7A-1 3'A-2 3.7A-3 3.7A-3a 3.7A-3b 3.7A-4 3'A-5 3.7A-5a Amendment Number 27 RO RO RO RO RO RO 0 0 23 0 RO 12 0 12 12 27 12 12 0 0 0 0 0 0 0 0 0 0 23 0 27 24 0 0 24 26 23 18 18 0 23 5 USAR Revision EP 3-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 3.7A-5b 3.7A-6 3.7A"7 3.7A-7a 3.7A-7b 3.7A-8 3.7A-9 3.7A-10 3.7A"11 3.7A-12 3.7A-13 3.7A"13a 3.7A-13b 3.7A-14 3.7A-15 3.7A-16 3.7A-17 3.7A-18 3.7A-19 3.7A-20 3.7A-20a 3.7A"20b 3.7A-21 3.7A-22 3.7A-22a 3.7A"22b 3'A-23 3.7A-23a 3.7A-23b 3.7A-24 3.7A-25 3.7A-26 3.7A-27 3.7A-27a 3.7A-27b 3.7A-28 3'A-28a 3.7A-28b 3.7A-29 3.7A-30 3.7A-31 3.7A-32 3.7A-33 3.7A-34 T 3.7A-1 5 23 27 23 5 23 24 0 RO 0 20 20 20 0 0 0 0 0 23 3 RO 3 18 RO RO RO 25 26 25 3 26 0 RO RO RO 5 RO 5 26 26 26 27 26 12 0 T T T T T T T T T T T T F F F F F F F F F F F F F F F F F F F F F F F F F F F F F 3'A-2 Sjl 1 Sh 2 3.7A-3 3.7A-4 3.7A-5 Sjl 1 Sh 2 3.7A-6 3.7A-7 3.7A-8 3.7A-9 3.7A-10 3.7A-11 3'A-12 3.7A-13 3.7A-l 3'A-2 3.7A-3 3.7A-4 3.7A-5 3.7A-6 3'A-7 3.7A-8 3.7A-9 3.7A-10 3.7A-ll 3.7A-12 3.7A-13 3.7A-14 3.7A-15 3.7A-16 3.7A-17 3.7A-18 3.7A-19 3.7A-20 3.7A-21 3.7A-22 3.7A-23 3.7A-24 3.7A-25 3e7A-26 3.7A-27 3.7A-28 3.7A-29 0 RO 22 22 22 22 22 22 22 22 RO 25 25 RO 0 0 26 26 22 22 22 22 22 22 22 22 22 22 22 22 22 23 0 20 23 23 23 23 23 23 20 20 20 F 3.7A-30 F 3.7A-31 F 3.7A-32 F 3.7A-33 F 3.7A-34 F 3.7A"35 F 3.7A-36 S11 1 Sh 2 3.78-1 3.78-2 3'8-3 3.78-4 3'8-5 3.78-6 3'8-7 3.78-8 3.78-9 3.78-10 3.78-11 3.78-12 3.78-13 3.78-14 3.78-15 3.78-16 3.78-17 3.78-17a 3.78-17b 3.78-18 3.78-19 3.78-20 3.78-21 3.78-21a 3.78-2lb 3.78-22 3.78-23 3.78-24 3.78-25 3'8-26 3.78-27 T 3.78-1 T 3.78-2 F 3.78-1 F 3'8-2 20 20 23 5 18 RO RO RO 0 0 23 0 0 0 23 23 0 0 0 0 23 23 23 0 20 20 20 19 0 0 RO RO RO 23 23 0 25 0 0 23 0 0 0 USAR Revision EP 3-5 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 3'B-3 3.8-1 3.8-2 3.8-3 3.8-4 3.8-5 3.8-6 3.8-7 3.8-8 3.8-9 3.8-10 3.8"loa 3.8-10b 3.8-11 3.8-12 3.8-13 3.8"14 3.8"15 3.8-16 3.8"17 3.8-17a 3.8-17b 3.8-18 3.8-19 3.8-19a 3.8-19b 3.8-20 3.8-21 3.8-22 3.8-23 3.8-24 3.8-25 3.8-25.1 3.8-25.2 3.8-25a 3.8-25b 3.8-25ba 3.8-25bb 3.8-25c 3.8-25d 3.8"26 3.8-26a 3.8-26b 3.8-27 Amendment Number 19 23 18 18 0 0 18 0 0 0 19 3 3 0 20 20 26 0 20 3 3 3 22 18 3 3 RO 19 0 0 26 24 24 24 13 25 22 22 13 13 23 23 23 22 Page T=Table~F=Fi ure 3.8-27a 3.8-27b 3.8-28 3.8-29 3.8-30 3.8-31 3.8-32 3.8-33 3.8-34 3.8-35 3.8-36 3.8-37 3.8-38 3.8-39 3.8-40 3.8-41 3.8-42 3.8"43 3.8-43a 3.8-43b 3.8-44 3.8-45 3.8-45a 3.8-45b 3.8"46 3.8"47 3.8-47a 3.8-47b 3.8-48 3.8-49 3.8-50 3.8-51 3.8-51a 3.8-51b 3.8-52 3.8-53 3.8-54 3.8"55 3.8-56 3.8"57 3.8-58 3.8-59 3.8-60 3.8-61 3.8-62 Amendment Number 22 22 0 0 0 0 0 0 0 0 0 27 23 Rl 0 0 26 26 21 21 0 5 5 5 0 21 3 3 0 26 23 22 22 3 0 0 26 21 0 3 0 0 0 0 0 Page T=Table~F=Fi ure 3.8-63 3.8-63a 3.8-63b 3.8-64 3.8-65 3.8-65a 3.8-65b 3.8-66 3.8-67 3.8-68 3.8-69 3.8-69a 3.8-69b 3.8-70 3.8-71 3.8-71a 3.8-7lb 3.8-72 3.8-73 3.8-73a 3.8-73b 3.8-74 3.8-75 3.8"76 3.8-77 3.8-78 T 3.8"1 S}l 1 S}1 2 S}1 3 S}l 4 S}1 5 S}L 6 T 3.8-2 S}1 1 S}L 2 T 3.8-3 S}L 1 S}L 2 S}1 3 S}1 4 S}1 5 T 3.8-4 S}1 1 S}1 2 Amendment Number 21 21 21 26 23 23 21 Rl 23 0 5 5 5 0 RO 26 5 21 23 23 23 0 0 27 26 0 25 23 0 0 26 26 19 26 26 0 0 0 26 25 28 USAR Revision 1 EP 3-6 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure S}1 3 Sh 4 T 3.8-5 Sh 1 Sh 2 T 3.8-6 Sh 1 Sh 2 T 3.8"7 Sh 1 Sh 2 T 3.8-8 T 3.8-9 Sh 1 S}1 2 T 3.8"10 Sh 1 S}1 2 Sh 3 T 3.8-11 Sh 1 Sh 2 S}1 3 T 3.8-12 Sh 1 Sh 2 S}1 3 Sh 3a Sh 4 T 3.8"13 T 3.8-14 T 3.8"15 Sh 1 Sh 2 F 3.8"1 3.8-2 3.8-3 3.8"4 3.8-5 3.8-6 3.8-7 3.8"8 3.8"9 3.8-10 3.8-11 Amendment Number 26 25 27 27 27 27 27 27 26 26 0 26 26 26 19 23 23 0 19 26 26 26 26 26 27 23 0 0 0 0 0 0 0 26 0 0 0 Page T=Table~F=Fi ure F 3.8-12 F 3.8-13 F 3.8-14 F 3.8-15 F 3.8-16 F 3.8-17 F 3.8-18 Sh 1 Sh 2 F 3~8-19 Sh 1 Sh 2 F 3.8-20 F 3.8-21 3.9A-1 3.9A-la 3.9A"lb 3.9A"2 3.9A-2a 3.9A"2b 3.9A-3 3.9A-3a 3.9A-3b 3.9A-4 3.9A-4a 3.9A-4b 3.9A-5 3.9A-5a 3.9A-5b 3.9A-6 3.9A-6a 3'A-6b 3.9A-7 3.9A"la 3.9A-lb 3.9A-8 3.9A-8a 3'A-8b 3.9A-9 3.9A-9a 3.9A-9b 3.9A"10 3.9A-11 3.9A-lla Amendment Number 16 0 0 0 26 26 26 23 RO RO RO RO RO RO RO RO 23 19 19 RO RO RO RO RO 28 RO RO RO 27 20 20 0 27 27 Page T=Table~F=Fi ure 3.9A-lib 3'A-12 3.9A-13 3.9A-13a 3.9A-13b 3.9A-14 3.9A-14a 3.9A-14b 3.9A-15 3.9A-15a 3.9A"15b 3.9A-16 3.9A-17 3'A-17a 3.9A-17b 3'A-18 3.9A-19 3.9A-19a 3'A-19b 3'A-20 3.9A-20a 3.9A-20b 3.9A-21 3.9A-21a 3.9A-21b 3.9A-22 3.9A-23 3.9A-23a 3.9A-23b 3.9A-24 3.9A-24a 3.9A-24b 3.9A-24c 3.9A-24d 3.9A-25 3.9A-26 3.9A-26a 3'A-26b 3.9A-26c 3.9A-26d 3'A-27 3.9A-27a 3.9A-27b 3.9A-28 T 3.9A-1 Amendment Number 27 12 RO RO RO Rl RO RO RO RO RO RO RO 21 20 23 20 20 20 23 20 20 27 20 23 28 RO RO 12 RO RO RO RO RO 23 RO 12 27 25 12 RO RO RO Rl USAR Revision EP 3-7 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure S}1 1 Sh 2 T 3.9A-2 S}1 1 S}l 2S}1 3 S}1 4 S}i 5 S}1 6 Sh 7 S}1 8 T 3.9A-3 T 3.9A-4 S}1 1 S}1 2 S}1 3 Sh 4 S}1 5 S}1 6 Sh 6a S}i 6b Sh 6c T 3.9A-5 S}1 1 S}1 2 S}1 3 T 3.9A-6 T 3.9A-7 T 3.9A-8 Sh 1 S}1 2 T 3.9A-9 T 3.9A-10 S}1 1 S}1 2 S}1 3 Sh 3a T 3.9A-ll T 3.9A-12 Sh 1 S}1 2 S}l 3 Sh 4 S}i 5 Sh 6 Amendment Number RO RO 20 20 RO RO RO RO 20 20 0 27 27 27 18 27 27 28 28 28 0 27 0 0 0 0 12 0 RO RO RO RO 18 RO RO RO Rl RO RO Page T=Table~F=Fi ure S}1 7 S}1 8 Sh 9 S}1 10 Sh 11 S}1 12 Sh 13 S}l 14 S}1 15 S}1 16 S}1 17 S}1 18 S}1 19 S}1 20 S}1 21 T 3.9A-13 Sh 1 S}l 2 S}l 3 T 3.9A-14 T 3.9A-15 S}l 1 S}1 2 Sh 2a T 3.9A-16 S}1 1 Sh 2 F 3'A-1 F 3'A-2 F 3'A-3 F 3.9A-4 F 3.9A-5 F 3'A-6 F 3.9A-7 F 3.9A-8 F 3.9A-9 F 3.9A"10 F 3.9A-11 F 3.9A"12 F 3~9A-13 F 3.9A-14 F 3.9A"15 F 3.9A-16 F 3.9A-17 F 3.9A-18 Amendment Number RO RO RO RO RO RO RO RO RO RO Rl RO 28 26 RO 12 12 12 RO 26 26 26 RO RO 8 12 12 12 RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure F 3'A-19 F 3.9A-20 F 3.9A-21 F 3.9A-22 F 3.9A-23 F 3.9A-24 F 3.9A-25 F 3.9A-26 F 3.9A-27 F 3.9A-28 F 3.9A-29 F 3.9A-30 F 3.9A-31 F 3.9A-32 F 3.9A-33 F 3'A-34 F 3e9A-35 F 3.9A-36 F 3.9A-37 F 3.9A-38 F 3.9A-39 F 3.9A-40 F 3.9A-41 F 3.9A-42 F 3'A-43 F 3'A-44 F 3.9A-45 F 3.9A-46 F 3'A-47 F 3.9A-48 F 3.9A-49 F 3.9A-50 F 3'A-51 F 3'A-52 F 3.9A-53 F 3.9A-54 F 3'A-55 F 3.9A-56 F 3'A-57 F 3.9A-58 F 3.9A-59 F 3'A-60 F 3.9A-61 F 3'A-62 F 3.9A-63 Amendment Number RO RO RO"RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision EP 3-8 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 3.9A-64 F 3.9A-65 F 3.9A-66 F 3.9A-67 3.9B"1 3.9B-2 3.9B-3 3.9B-4 3.9B-4a 3.9B-4b 3.9B"5 3.9B-6 3.9B"7 3.9B-8 3.9B-9 3.9B-10 3.9B-ll 3.9B-12 3.9B"13 3.9B-14 3.9B-15 3.9B"16 3.9B-16a 3.9B"16b 3.9B-17 3.9B"18 3.9B-19 3.9B"20 3'B-21 3.9B-21a 3.9B-21b 3.9B"22 3.9B-23 3.9B-24 3.9B-25 3.9B-26 3.9B-26a 3.9B-26b 3.9B-27 3.9B-28 3.9B"29 3.9B-30 3.9B-31 3.9B-32 Amendment Number RO RO RO RO 0 0 0 28 28 28 0 0 0 RO RO RO 0 0 Rl 0 23 27 27 27 0 24 26 26 12 28 12 20 0 13 0 13 RO 13 13 0 0 0 26 7 Page T=Table~F=Fi ure 3.9B-32a 3'B-32b 3.9B-33 3.9B-34 3.9B-34a 3.9B-34b 3.9B-35 3.9B-36 3.9B-37 3.9B-38 3.9B-39 3.9B-40 3.9B"41 3.9B-42 3.9B-43 3.9B-44 3.9B-45 3.9B-46 3.9B-47 3.9B-47a 3.9B-47b 3.9B-48 3.9B-49 3.9B-49a 3.9B"49b 3'B-50 3.9B-50a 3.9B-50b 3'B-51 3.9B-52 3.9B-52a 3.9B-52b 3'B-53 3.9B-54 3.9B-55 3.9B-56 3.9B-56a 3.9B-56b 3'B-57 3.9B-58 3'B-59 3'B-60 3.9B-61 3.9B-62 3.9B-63 Amendment Number 7 7 RO 28 28 28 0 20 20 0 0 0 0 0 0 0 28 0 20 20 20 0 20 28 20 28 28 28 0 RO RO RO 0 0 RO 12 12 12 0 26 0 26 0 26 12 Page T=Table~F=Fi ure 3.9B-63a 3.9B"63b 3.9B-64 3.9B-65 3.9B-66 3.9B"67 3.9B-68 3.9B-69 3.9B-70 3.9B-71 3.9B-72 3.9B-73 T 3.9B-l S}1 1 S}1 2 T 3.9B-2 Sh 1 S}1 2 S}1 3 S}1 4 S}1 5 T 3.9B-2a S}1 1 S}1 2 S}1 3 T 3.9B-2b T 3.9B-2c T 3.9B-2d T 3.9B-2e T 3.9B-2f Sh 1 S}1 2 S}1 3 Sh 4 T 3.9B-2g T 3.9B-2h S}1 1 Sh 2 S}1 3 S}1 4 T 3.9B-2i S}1 1 S}1 2 S}1 3 S}1 4 Amendment Number 12 12 0 0 26 0 0 0 0 0 0 28 28 19 28 28 0 0 12 22 22 22 28 22 22 22 22 22 26 24 22 22 22 26 22 22 22 22 22 USAR Revision 1 EP 3"9 October 1989 0

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 3.9B-2j Sh 1 Sh 2 Sh 3 Sh 4 S}1 5 Sh 6 T 3.9B-2k Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 T 3.9B-21 Sh 1 Sh 2 T 3.9B-2m Sh 1 S}1 2 T 3.9B-2n Sh 1 Sh 2 Sh 3 T 3.9B-2o T 3.9B-2p T 3.9B-2q T 3.9B-2r S}1 1 Sh 2 Sh 3 S}1 4 T 3.9B-2s Sh 1 Sh 2 T 3.9B"2t Sh 1 Sh 2 S}1 3 T 3.9B-2u S}L 1 S}1 2 Sh 3 Amendment Number RO 0 0 RO 0 0 28 28 28 26 RO 20 0 28 20 26 20 26 26 27 26 26 26 23 23 23 Page T=Table~F=Fi ure T 3.9B-2v S}1 1 Sh 2 Sh 3 Sh 4 T 3.9B-2w Sh 1 Sh 2 T 3.9B-2x ,S}1 1 Sh 2 Sh 3 Sh 4 T 3.9B-2y Sh 1 S}1 2 T 3.9B-2z Sh 1 Sh 2 Sh 3 T 3'B-3 Sh 1 S}1 2 Sh 3 Sh 4 T 3.98-4 S}1 1 Sh la Sh 2 T 3'B-5 T 3.9B"6 Sh 1 Sh 2 Sh 3 T 3.9B"7 T 3.9B-8 T 3.9B-9 Sh 1 S}1 2 Sh 3 S}1 4 T 3.9B-10 S}1 1 S}1 2 Sh 3 Amendment Number 0 28 24 24 0 28 26 24 26 24 20 20 28 28 28 28 28 25 0 Page T=Table~F=Fi ure T 3.9B"11 Sh 1 Sh 2 Sh 3 F 3.9B-1 F 3.9B-2 F 3.9B-3 F 3.9B-4 F 3'B-5 3.10A-1 3.10A-la 3.10A-lb 3.10A-2 3.10A-3 3.10A-3a 3.10A-3b 3.10A-4 3.10A-5 T 3.10A-1 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 S}1 9 Sh 10 Sh 11 Sh 12 Sh 13 Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 S}1 19 Sh 20 Sh 21 3.10B-1 3'0B-2 3.10B-2a Amendment Number 0 0 0 0 26 0 0 0 20 20 20 0 20 20 20 0 27 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 22 22 22 USAR Revision 1 EP 3"10 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 3.10B-2b 3.10B"3 3.10B-3a 3.10B-3b 3.10B-4 3.10B-5 3.10B-5a 3.10B-5b 3.10B-6 3.10B-7 T 3.10B-1 S11 1 Sh 2 S11 3 S}1 4 Sh 5 T 3.10B-2 F 3.10B-1 F 3elOB-2 F 3.10B-3 F 3.10B-4 3.11-1 3.11"la 3.1l-lb 3.11-2 3.11-3 3.11-3a 3.11-3b 3.11-4 3.11-5 3.11"6 3.11-7 App 3A 3A-i 3A-ii 3A-iii 3A-iv 3A-v 3A-vi 3A"vii 3A-viii 3A-ix 3A-x Amendment Number 22 22 22 22 22 22 22 22 22 22 20 20 20 20 20 22 22 22 22 22 RO RO 19 RO 19 19 7 Rl 19 RO Rl 0 27 19 0 23 27 19 23 27 5 27 Page T=Table~F=Fi ure 3A-1 3A-2 3A.1-1 3A.1-2 3A.1-3 T 3A.1-1 F 3A.1-1 3A.2-1 3A.2-2 3A.2-3 3A.2-4 F 3A.2-1 F 3A.2-2 3A.3-1 3A.3-2 3A.3-3 3A.3-4 3A.3-5 T 3A.3-1 F 3A.3-1 F 3A.3-2 3A.4-1 3A.4-2 F 3A.4-1 F 3A.4-2 F 3A.4-3 F 3A.4-4 3A.5-1 3A.5-2 3A.6-1 3A.6-2 F 3A.6-1 F 3A.6-2 3A.7-1 T 3A.7-1 F 3A.7-1 F 3A.7-2 3A.8-1 3A.8-2 3A.8-3 3A.9-1 3A.9-2 3A.9-3 3A.9-4 3A.9-5 Amendment Number 9 23 0 0 0 23 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 25 25 25 25 0 0 0 27 27 27 27 0 Page T=Table~F=Fi ure 3A.9"6 F 3A.9-1 F 3A.9-2 F 3A.9-3 F 3A.9-4 F 3A.9-5 F 3A.9-6 F 3A.9-7 3A.10-1 3A.10"2 3A.10-3 T 3A.10-1 F 3A.10"1 F 3A.10-2 F 3A.10-3 F 3A.10"4 3A.ll-l 3A.12-1 3A.12-2 T 3A.12-1 Sh 1 S}1 2 F 3A.12-1 3A.13-1 3A.13-2 T 3A.13-1 T 3A.13-2 F 3A.13-1 F 3A.13"2 3A.14-1 3A.14-2 3A.14-3 T 3A.14"1 F 3A.14"1 F 3A.14-2 3A.15-1 3A.15-2 T 3A.15-1 T 3A.15-2 T 3A.15-3 T 3A.15-4 T 3A.15-5 T 3A.15-6 T 3A.15"7 T 3A.15-8 Amendment Number 27 0 0 0 0 0 0 0 27 27 27 27 0 0 0 27 0 0 0 26 26 RO 3 0 3 3 RO 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 USAR Revision EP 3-11 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number T 3A.15-9 T 3A.15-10 F 3A.15-1 F 3A.15-2 F 3A.15-3 3A.16-1 3A.16-2 T 3A.16-1 T 3A.16-2 T 3A.16-3 T 3A.16-4 T 3A.16-5 3A.17-1 3A.17-2 3A.17-3 T 3A.17-1 T 3A.17-2 T 3A.17-3 T 3A.17-4 T 3A.17-5 3A.18-1 3A.18-la 3A.18-1b 3A.18-2 T 3A.18-1 F 3A.18-1 F 3A.18-2 3A.19-1 F 3A.19-1 F 3A.19-2 3A.20-1 3A.20-2 T 3A.20-1 F 3A.20-1 F 3A.20-2 F 3A.20-3 F 3A.20-4 F 3A.20-5 3A.21-1 3A.21-2 T 3A.21-1 T 3A.21-2 F 3A.21-1 F 3A.21-2 F 3A.21-3 0 0 0 0 0 19 19 19 19 19 19 19 0 0 0 0 0 0 0 0 23 25 5 5 5 5 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 F 3A.21-4 3A.22-1 3A.22-2 T 3A.22-1 T 3A.22-2 F 3A.22-1 3A.23-1 3A.23-2 T 3A.23-1 Sh 1 Sh 2 3A.24-1 3A.24-2 T 3A.24-1 T 3A.24-2 F 3A.24-1 F 3A.24-2 F 3A.24-3 3A.25-1 3A.26-1 3A.26-2 T 3A.26-1 F 3A.26-1 F 3A.26-2 3A.27-1 3A.27-2 T 3A.27-1 3A.28-1 3A.28-2 3A.28-3 3A.29-1 3A.30-1 3A.30-2 3A.31-1 3A.31-2 3A.32-1 3A.33-1 3A.33-2 T3A.33-1 T3A.33-2 App 3B 3B-i 3B-ii 3B-iii 0 5 0 0 0 27 0 0 0 0 0 0 0 0 0 0 0 4 0 0 0 3 3 0 0 0 0 0 0 4 9 9 9 9 23 23 23 23 23 0 RO 0 0 3B-iv 3B-v 3B-vi 3B-1 3B-2 3B-3 3B-4 3B-5 3B-6 3B-7 3B-8 3B-9 3B-10 3B-ll 3B-12 T 3B-1 Sh 1 Sh 2 Sh 3 T 3B-2 T 3B-3 Sh 1 Sh 2 Sh 3 Sh 4 S}1 5 Sh 6 Sh 7 T 3B-4 Sh 1 Sh 2 T 3B-5 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 T 3B-6 Sh 1 Sh 2 Sh 3 S}1 4 Sh 5 S}1 6 T 3B-7 RO RO RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl USAR Revision EP 3-12 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 3B-8 T 3B"9 T 3B-10 T 3B-11 T 3B"12 T 3B-13 T 38-14 T 3B-15 T 3B-16 T 3B-17 T 3B-18 F 3B-1 S}1 1 S}1 2 S}1 3 S}1 4 S}1 5 F 3B-2 Sh 1 S}1 2 S}1 3 sh 4 Sh 5 F 3B-3 F 3B-4 F 3B-5 F 3B-6 F 3B-7 F 3B-8 F 3B-9 F 3B-10 F 3B-11 F 3B-12 F 38-13 F 3B-14 F 3B-15 F 3B-16 F 3B-17 F 3B-18 F 3B"19 F 3B-20 F 3B-21 F 3B"22 F 3B-23 F 3B-24 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure F 3B-25 F 3B-26 F 3B-27 F 3B-28 F 3B-29 F 3B-30 F 3B-31 F 3B-32 F 3B-33 F 3B-34 F 3B-35 F 3B-36 F 3B-37 F 3B-38 F 3B-39 F 3B-40 F 3B-41 F 3B-42 F 3B-43 F 3B-44 F 3B-45 F 3B-46 F 3B-47 F 3B-48 F 3B-49 F 3B-50 F 3B-51 F 3B-52 F 3B-53 F 3B-54 F 3B"55 F 3B-56 App 3C 3C-i 3C-ii 3C-1 3C-2 3C-3 3C-4 3C-5 3C-6 3C-7 3C-8 3C-9 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 0 26 26 0 28 RO 28 28 28 28 28 28 Page T=Table~F=Fi ure 3C-10 3C-11 3C-11a 3C-lib 3C-12 3C-13 3C-14 3C-15 3C-16 3C-17 3C-18 3C-19 3C-20 3C-21 3C-22 3C-23 3C-24 3C-25 3C-26 3C-26a 3C-26b 3C-27 3C-27a 3C-27b 3C-28 3C"29 3C-30 3C-30a 3C-30b 3C-31 3C-32 3C-33 3C-34 F 3C.3-1 F 3C.3-2 F 3C.3-3 T 3C.4-1 T 3C.4-2 T 3C.4-3 T 3C.4-4 T 3C.4-5 T 3C.4-6 T 3C.5"1 T 3C.5-2 S}1 1 Amendment Number 28 28 RO 18 28 28 28 12 12 12 12 12 28 12 RO 13 27 RO 27 27 27 27 RO 27 27 13 27 27 27 13 27 RO 27 12 12 12 27 27 27 27 18 13 27 26 USAR Revision EP 3-13 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sjl 2 F 3C.3-1 F 3C~3-2 F 3C.3-3 Amendment Number 13 12 12 12 Page T=Table~F=Fi ure Amendment Number Page T=Table Amendment~F=Fi ure Number App 3D 3D-1 3D-2 3D-3 3D-4 3D-5 3D-6 3D-7 3D-8 3D-9 3D-10 3D-ll 3D-12 3D-13 3D"14 3D-15 3D-16 3D-17 3D-18 3D-19 T 3D-1 S}1 1 S}1 2 S}l 3 S}l 4 S}l 5 S}1 6 S}1 7 S}1 8 S}1 9 S}1 10 S}1 11 S}1 12 S}1 13 S}1 14 RO.RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO App 3E 3E-1 3E-2 3E"3 3E-4 RO RO RO RO RO USAR Revision EP 3-14 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 4 Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table Amendment~F=Fi ure Number 4"i 4-ii 4-iii 4-iiia 4"iiib 4-iv 4-v 4-vi 4-vii 4-viii 4.1-1 4.1-2 4.1-3 4.1-4 4.1"5 4.1-6 4.1-7 4.1-8 4.1-9 4.1"10 4'"11 4.1-12 4.1-13 4.1"14 4.1-15 4.1-16 4.2-1 4.2-2 4.3-1 4.3-2 4.3-3 4.3-4 T 4.3-1 T 4.3-2 T 4.3-3 F 4.3-1 F 4.3-2 4.4-1 4.4-2 4.4-2a 4.4-2b 7 24 16 16 16 0 RO 24 24 9 0 0 0 0 27 19 19 0 19 19 19 19 0 19 19 0 19 14 19 0 19 0 0 0 0 0 19 0 7 Rl 7 4.4-3 4'-4 4.4-5 4.4-6 4'-7 4.4-8 4.4"9 4.4-9a 4.4-9b 4.4-9c 4.4"9d 4.4-10 4.4-11 T 4.4-1 Sh 1 Sh 2 T 4.4-2 T 4.4-3 T 4.4-4 T 4.4-5 T 4.4-6 T 4.4-7 T 4.4-8 T 4.4-9 F 4.4-1 F 4.4-2 F 4.4-3 F 4.4-4 F 4.4-5 F 4.4-6 F 4.4-7 F 4.4-8 F 4.4-9 F 4.4-10 4.5-1 4.5-2 4.5-3 4.5-4 4.5-5 4.5-6 4.5-6a 4.5-6b 4.5-7 4.5-8 19 0 0 19 0 19 16 16 16 17 17 9 7 19 19 19 19 0 19 24 19 23 9 0 0 0 0 0 16 9 9 9 16 19 0 27 0 27 19 19 19 0 27 4.5-9 4.5-10 4.6-1 4.6-2 4.6-3 4.6-4 4.6-5 4.6-6 4.6-7 4.6-8 4.6-8a 4.6-8b 4.6-9 4.6-10 4.6"11 4.6-12 4.6-12a 4.6-12b 4.6-12c 4.6-12d 4.6-12e 4.6-12f 4.6-12g 4.6-12h 4.6-12i 4.6-12j 4.6-13 4.6-14 4.6-15 4.6-16 4.6-17 4.6-18 4.6-19 4.6-20 4.6-21 4.6-22 4.6-23 4.6-24 4.6-25 4.6-26 4.6-27 4.6-28 4.6-29 4.6-30 0 0 27 0 0 0 0 5 23 5 19 0, 0 5 5 5 5 5 5 5 25 7 7 7 0 0 0 26 0 26 19 0 0 0 0 0 0 0 0 19 0 0 USAR Revision EP 4-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 4.6-31 4.6-32 4.6"33 4.6-34 4.6-35 4.6"36 4.6-37 4.6-38 F 4.6"1 F 4.6-2 F 4.6-3 F 4.6-4 F 4.6"5a F 4.6-5b F 4.6-5c F 4.6-6 F 4.6-7 Sh 1 S}L 2 Sb 3 F 4.6-8 F 4.6-9 Amendment Number 0 0 0 19 25 0 0 5 0 0 19 0 Rl RO Rl 0 23 23 23 0 0 Page T=Table Amendment~F=Fi ure Number Page T=Table Amendment~F=Fi ure Number App 4A 4A-1 4A-2 RO Rl RO USAR Revision 1 EP 4-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 5 Page T=Table~F=Fi ure 5-i 5-ii 5-iii 5-iv 5-v 5 v1 5"vii 5 v111 5 1x 5-x 5-xa 5-xb 5 x1 5.1-1 5.1-2 5.1-3 5.1"4 F 5.l-la F 5'-lb F 5.1-2a F 5.1-2b F 5.1-2c 5.2-1 5.2-2 5'-3 5.2-4 5.2-4a 5.2-4b 5.2-5 5.2-5a 5.2-5b 5.2"6 5.2-7 5.2"8 5.2"8a 5.2"8b 5.2-9 5.2"9a 5.2-9b 5.2-10 5.2-10a 5.2-10b 5.2-11 Amendment Number 7 24 24 0 24 24 24 RO RO RO RO 7 24 0 0 19 0 24 19 RO RO RO-15 0 28 24 24 7 RO RO RO RO 0 7 19 7 13 6 6 23 7 7 RO Page T=Table~F=Fi ure 5.2"12 5.2"12a 5.2-12b 5.2-12c 5.2-12d 5.2-13 5.2-14 5.'2-15 5.2-16 5.2"17 5.2-18 5.2-19 5'-20 5.2-21 5.2-21a 5.2"21b 5.2-22 5.2-23 5.2-24 5.2-25 5.2-26 5.2-27 5.2-28 5.2-28a 5.2-28b 5.2-29 5.2-30 5.2-31 5.2-32 5.2-32a 5.2-32b 5~2 33 5.2-33a 5.2-33b 5.2-34 5.2-35 5.2-36 5.2-37 5.2"37a 5.2-37b 5.2-38 5.2-39 5'-40 5.2-41 5.2"42 Amendment Number 7 24 24 24 7 0 0 0 0 Rl 0 RO 5 19 Rl 5 0 0 0 0 0 0 Rl 22 11 26 RO RO 23 23 5 RO 19 5 RO RO RO 23 RO 23 10 RO Rl 0 0 Page T=Table~F=Fi ure 5.2-43 5.2-44 5.2-45 S.2-45a 5.2"45b 5.2-46 T 5.2-1 S}1 1 Sh 2 Sh 3 Sh 3a Sh 3b Sh 4 Sh 5 Sh 5a Sh 6 Sh 6a S}1 6b Sh 6bl Sh 6ba Sh 7 Sh 8 Sh 8a Sh 8al Sh 8b Sh 8c Sh 8d T 5'-2 T 5.2-3 T 5.2-4 T 5.2-5 Sh 1 Sh 2 Sh 3 Sh 3a Sh 4 Sh 5 Sh 6 T 5.2-6 T 5.2-7 Sh 1 S}1 2 T 5.2-8 T 5'-9 T 5.2-10 Amendment Number 0 5 5 5 5 RO RO 23 RO 23 24 21 25 RO 28 23 28 21 19 ll 19 21 RO 26 28 28 0 24 RO 24 23 28 28 Rl 24 23 23 0 0 19 RO RO USAR Revision EP 5-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 5.2"1 F 5.2-2 F 5.2-3 F 5.2-4 S11 1 S11 2 F 5~2-5 F 5.2-5a F 5'-6 F 5.2-7 F 5.2-8 F 5.2-9 5.3-1 5~3 2 5.3-3 5.3-4 5.3"5 5.3-6 5~3 7 5.3-7a 5.3"7b 5.3-8 5.3"9 5.3-10 5.3-11 5.3-12 5.3-13 5.3-14 5.3-15 5.3-16 5.3-17 5.3-18 5.3-19 5.3-20 5.3-21 5~3 22 T 5.3"1 Sjl 1 Sjl 2 T 5~3 2 F 5.3-1 F 5'-2 F 5.3-3 F 5.3-4 Amendment Number 23 23 0 7 0 0 0 0 24 23 24 11 24 RO 27 24 24 0 ll Rl Rl ll 0 ll 24 0 RO 24 Rl 24 27 0 0 0 0 0 24 0 0-Page T=Table~F=Fi ure F 5.3-5 5.4-1 5.4-2 5.4-3 5.4-4 5.4-4a 5.4-4b 5.4-5 5.4-5a 5.4-5b 5.4-6 5.4-7 5.4-8 5.4-9 5.4-9a 5.4-9b 5.4-10 5.4-11 5.4-12 5.4-13 5.4-14 5.4-15 5.4-16 5.4-17 5.4-17a 5.4-17b 5.4-18 5.4-19 5.4-20 5.4-21 5.4-21a 5.4-21b 5.4-22 5.4-23 5.4-23a 5.4-23b 5.4-24 5.4-25 5.4-26 5.4-27 5.4-28 5.4-28a 5.4-28b 5.4-29 Amendment Number 24 RO 24 24 23 23 23 24 24 24 24 24 24 28 28 28 28 RO 28 RO 28 28 RO RO RO RO 0 0 0 5 24 7 24 RO RO RO 9 24 24 27 5 24 5 24 Page T=Table~F=Fi ure 5.4"30 5.4-31 5'-32 5.4-33 5.4-34 5.4-34a 5.4"34b 5.4"34c 5.4-34d 5.4-35 5.4"36 5.4-37 5.4-37a 5.4-37b 5.4-38 5.4-38a 5.4"38b 5.4-39 5.4-40 5.4-41 5.4-42 5.4-42a 5.4-42b 5.4-43 5.4-43a 5.4-43b 5.4-44 5.4-45 5.4-45a 5.4-45b 5.4-46 5.4-47 5.4"48 5.4-49 5.4-50 5.4-50a 5.4-50b 5.4-51 5.4-5la 5.4-5lb 5.4-52 5.4-53 5.4-54 T 5.4-1 S11 1 Amendment Number 24 24 24 24 13 28 28 8 8 0 RO RO RO 13 26 23 13 RO 5 27 5 RO 5 Rl 10 5 0 RO 5 5 RO RO RO 24 RO RO RO Rl 13 13 0 0 28 24 USAR Revision EP 5-2 October 1989 i

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Pi ure Sh 2 Sjl 3 5.4-2 5.4-3 5.4-1 5.4-2a 5.4-2b 5.4-2c 5.4-2d 5.4-3 5.4-4 5.4-5 5.4-6 5.4-7 5.4-8 5.'4-9a 5.4-9b 5.4"9c 5.4-9d 5.4-'10 S}1 1 Sh 2 5.4-10a 5.4-10b 5.4-11 5.4-12 5.4-13a 5.4"13b 5.4-13c 5.4-13d 5.4-13e 5.4-13f 5.4-13g 5.4-14 Sh 1 S11 2 Sh 3 5.4-15 5.4-16a 5.4-16b'.4-16c 5.4-16d 5.4-16e 5.4-16f 5.4-17 Amendment Number 24 0 28 0 0 RO Rl Rl RO 0 0 0 0 28 28 RO Rl RO Rl 23 23 24 7 0 0 RO RO RO Rl RO RO RO 23 23 Rl 0 RO RO RO RO RO RO Page T=Table~P=Pi ure Sh 1 S11 2 S11 3 F 5.4"18 F 5.4-19 App 5A 5A-i 5A-1 5A-2 5A-2a 5A-2b 5A-3 T 5A-1 S11 1 S}1 2 T 5A-2 Sh 1 S}1 2 T 5A-3 T 5A-4 F 5.A-1 F 5.A-2 Att 5A-1 App 5B 5B-1 5B-2 5B"3 Amendment Number 0 23 0 RO 23 0 24 24 28 28 28 0 RO RO RO RO Page T=Table~P=Pi ure Amendment Number USAR Revision EP 5-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 6 Page T=Table~F=Fi uee 6-i 6-ii 6-iii 6-iv 6-v 6-vi 6-vii 6-viii 6-ix 6-x 6-xa 6-xb 6-xi 6-xii 6-xiii 6-xiv 6-xiva 6-xivb 6"xv 6-xvi 6-xvii 6-xviii 6"xix 6-xixa 6-xixb 6-xx 6-xxi 6-xxii 6-xxiia 6-xxiib 6"xxiii 6.1-1 6.1-2 6.1-3 6.1-4 6.1-4a 6.1-4b 6.1-5 6.1"6 T 6.1-1~S}1 1 S}1 2 T 6.1-2 Sh 1 Amendment Number RO RO 24 24 24 RO RO 24 24 RO RO 11 RO 24 24 24 24 17 15 27 24 27 RO RO 27 24 24 24 24 24 24 27 27 RO 3 3 3 28 28 27 28 RO Page T=Table~F-Fi uee Sh 2 T 6.1-3 6.2-1 6.2-2 6.2-2a 6.2-2b 6.2-3 6.2-4 6.2-5 6.2-6 6.2-6a 6.2-6b 6.2-7 6.2-8 6.2-9 6.2-10 6.2-11 6.2-12 6.2-13 6.2-14 6.2-15 6.2-15a 6.2-15b 6.2-16 6.2-17 6.2-18 6.2-19 6.2-20 6.2-21 6.2-22 6.2-23 6.2-24 6.2-24a 6.2-24b 6.2-24c 6.2-24d 6.2-25 6.2-25a 6.2-25b 6'-26 6.2-27 6.2-28 6.2-29 6'-30 Amendment Number RO 28 0 7 RO 7 0 0 23 RO 23 RO 0 RO 23 0 RO 0 0 0 RO RO RO RO 0 RO 0 0 0 0 RO 20 18 RO RO 17 RO RO RO RO 5 5 0 0 Page T=Table~F=Fi uee 6'-30a 6.2-30b 6.2-31 6.2-32 6.2-33 6.2-33a 6.2-33b 6.2-34 6.2-35 6.2-35a 6.2-35b 6.2-36 6.2-37 6.2-37a 6.2-37b 6.2"38 6.2-39 6'-40 6.2-41 6.2-42 6.2-43 6.2-43a 6.2-43b 6.2-44 6.2"45 6.2-46 6.2-46a 6.2-46b 6.2-47 6.2-47a 6.2-47b 6.2"48 6.2-49 6.2-50 6'-51 6.2-51a 6.2-5lb 6.2-52 6.2-53 6.2-53a 6'-53b 6.2-54 6.2-54a 6.2-54b 6.2-55 Amendment Number ll 11 0 0 RO RO RO 11 23 5 5 RO 23 RO RO RO 0 0 0 18 RO Rl RO 15 RO RO RO RO 23 5 5 15 RO RO 27 25 13 27 Rl 8 8 RO RO 27 21 USAR Revision 1 EP 6-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 6.2-5Sa 6.2-55b 6.2-55c 6.2-55d 6.2-56 6.2"57 6.2-57a 6.2-57b 6.2-57c 6.2-S7d 6.2-57e 6.2-57K 6.2-58 6.2-59 6.2-59a 6.2-59b 6.2-60 6.2-60a 6.2-60b 6.2-61 6.2-61a 6'-61b 6.2-62 6.2-62a 6.2-62b 6.2"63 6.2-63a 6.2"63b 6.2-64 6'-65 6.2-65a 6.2-65b 6.2-66 6.2"67 6.2-67a 6.2"67b 6.2"68 6.2"68a 6.2-68b 6.2"69 6.2-69a 6.2-69b 6,2-70 6.2-71 6.2-71a Amendment Number 27 Rl RO RO 18 RO RO RO RO Rl RO 26 0 RO RO RO 28 28 5 26 RO RO 7 23 7 RO RO RO 18 17 17 17 0 26 21 21 26 25 5 ll 5.5 RO 5 5 Page T=Table~F-Fi ure 6.2-71b 6.2-72 6.2-72a 6.2-72b 6.2-73 6.2-74 6.2"75 6.2-75a 6.2"75b 6.2-76 6.2-76a 6.2-76b 6.2-77 6.2-77a 6.2-77b 6.2-78 6.2-79 6.2-79a 6.2-79b 6.2-80 6.2-80a 6.2-80b 6.2-81 6.2-82 6.2-83 6.2-83a 6.2-83b 6.2"84 6.2-84a 6.2-84b 6.2-85 6.2-85a 6.2-85b 6.2-86 6.2-86a 6'-86b 6.2-87 6.2-87a 6.2-87b 6.2-88 6.2-88a 6.2-88b 6.2-89 T 6.2-1 T 6'-2 Amendment Number 5 Rl RO RO 28 27 RO 27 5 15 28 5 27 RO 15 8 15 15 15 RO 15 15 RO 15 Rl 27 23 27 23 23 27 17 17 27 19 17 26 Rl 17 Rl Rl RO 15 0 Page T=Table~F=Fi ure Sh 1 S11 2 T 6.2-3 S11 1 Sh 2 Sh 3 T 6.2-4 T 6.2-4a T 6.2-5 T 6'-6 S11 1 S11 2 T 6.2-7 T 6.2-8 T 6.2-9 T 6.2-10 T 6.2-11 T 6.2-12 T 6.2-13 T 6.2-14 T 6.2-15 S11 1 S11 2 T 6.2-16 T 6.2-17 T 6.2-18 T 6.2-19 T 6.2-20 T 6.2-20a T 6'-21 T 6.2-22 T 6'-23 T 6'-24 T 6.2-25 T 6.2-26 T 6'-27 T 6.2-27A T 6.2-28 T 6'-29 T 6.2-30 T 6.2-31 T 6.2-32 T 6.2-33 T 6.2-34 T 6.2-35 Amendment Number RO RO RO 0 RO 0 RO RO 0 0 RO 0 0 0 0 0 26 0 0 0 0 0 0 21 0 0 0 0 0 0 0 RO ll RO RO RO RO RO RO 11 USAR Revision 1 EP 6-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 6.2-36 T 6.2-37 T 6.2-38 S}1 1.S}1 2 T 6.2-39 S}1 1 Sjl 2 S}1 3 S}1 4 Sjl 5 S}1 6 T 6.2-40 T 6.2-41 T 6.2-42 T 6.2-43 T 6.2-43A T 6'-43B T 6.2-44 T 6.2-44A T 6.2-44B T 6.2-45 T 6.2"45A T 6.2-45B T 6'-46 T 6.2-47 T 6.2-48 T 6.2"49 T 6.2-50 T 6.2-51 T 6.2-52 T 6.2"53 T 6.2-54 T 6'-55 T 6.2-55a S}l 1 S}1 2 S}1 3 T 6.2"55b S}1 1 Sjl 2 Sjl 3 T 6'-55c S}1 1 S}1 2 Amendment Number ll 27 ll 11 11 11 ll ll ll ll 11 ll 11 RO 11 11 11 ll 11 28 11 11 28 28 0 RO RO RO Rl 21 RO RO RO RO RO RO Rl RO Page T=Table~F-Fi ure S}1 3 T 6.2-55d Sh 1 S}1 2 Sjl 3 T 6.2-56 S}1 1 Sjl 2 Sh 2a Sh 3 S}L 4 S}1 5 S}1 6 Sh 7 S}1 8 S}1 9 S}1 10 Sh 11 Sh 12 Sh 13 S}1 14 Sh 15 S}L 16 S}1 17 Sh 17a S}1 18 Sh 19 Sh 19a S}l 20 Sh 20a S}1 21 Sh 22 Sh 22a S}1 23 Sh 23a Sh 24 S}1 24a Sh 24b T 6.2-57 T 6.2-58 T 6.2"59 Sjl 1 Sh 2 T 6.2-59A Sh 1 Amendment Number RO RO RO RO RO Rl 28 28 28 21 28 RO RO 27 27 28 26 28 27 28 28 28 28 RO 17 17 RO RO 26 27 26 28 RO 28 27 26 28 0 RO RO 18 Page T=Table~F=Fi ure Sh 2 6.2-59B 6.2"59C 6.2-59D 6.2-60 6.2-61 6.2-62 6.2-63 S}1 1 S}1 2 6.2-64 6.2"65 S}1 1 S}1 2 6.2-1 6.2-2 6.2-3 6.2-4 6.2-5 6.2-6 6.2-7 6.2-8 6.2-9 6'-10 6.2-11 6.2-12 6.2-13 6.2"14 6.2-15 6.2-16 6.2-17 6.2-18 6.2-19 6.2-20 6.2-21 6'-22 6.2-23 6.2-24 6'-25 6.2-26 6.2-27 6.2-28 6.2-28A 6.2-28B 6.2-28C Amendment Number 18 18 15 RO 27 27 25 24 24 RO RO RO RO 0 0 0 0 0 0 0 0 27 0 0 0 0 0 0 0 0 0 18 18 0 18 0 0 0 0 RO RO RO RO USAR Revision 1'EP 6-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 6.2-29 F 6.2"29A F 6.2-29B F 6.2-29C F 6.2-29D F 6.2-29E F 6'-29F F 6.2-29G F 6.2-29H F 6.2-29I F 6.2"29J F 6.2-30 F 6.2-30A F 6'-31 F 6.2-31A F 6.2-31B F 6.2-32 F 6.2-33 Sjl 1 Sh 2 Sh 3 sh 4 S}1 5 S}1 6 S}1 7 Sh 8 F 6.2-33A F 6.2-33B F 6.2-34 F 6.2-35 F 6.2"36 F 6.2-37 F 6.2"38 S}1 1 S}1 2 S}1 3 Sh 4 S}l 5 S}1 6 S}1 7 Sh 8 S}1 9 Sh 10 S}1 11 S}1 12 Amendment Number 0 ll ll 11 ll ll 11 11 ll 11 ll 11 ll 11 RO RO 11 23 23 23 23 23 23 23 23 RO RO 0 0 0 0 RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F-Fi ure F 6.2-39 F 6.2-39A F 6.2-40 F 6.2-41 F 6.2-42 F 6.2-43 F 6.2"44 F 6.2"45 F 6.2-46 F 6'-46A F 6.2-47 F 6.2-48 F 6.2-49 F 6.2-50 F 6.2-51 F 6.2-52 F 6.2-53 S}1 1 Sjl 2 S}1 3 S}1 4 S}1 5 Sjl 6 F 6.2-54 F 6.2-55 F 6.2-56 S}1 1 S}l 2 S11 3 S}1 4 Sh 5 S}1 6 S}1 7 S}1 8 S}1 9 Sjl 10 F 6.2-57 F 6.2-58 F 6.2-59 Sh 1 S}1 2 S}1 3 Sjl 4 S}1 5 F 6.2"60 Amendment Number" 0 9 27 27 28 27 RO RO RO RO 0 0 0 27 RO 11 11 ll ll 11 11 11 23 11 ll 23 23 23 23 23 23 23 23 23 ll ll ll ll ll ll 11 23 Page T=Table~F=Fi ure F 6.2-61 F 6'-62 Sjl 1 Sh 2 S}1 3 Sh 4 Sjl 5 F 6.2-62A F 6.2-63 F 6.2-64 S}1 1 S}1 2 S}1 3 S}1 4 Sh 5 F 6.2-64A F 6.2-65 F 6'-66 S}l 1 S}l 2 S}1 3 Sh 4 S}1 5 Sh 6 F 6'-66A F 6'-67 F 6.2-68 F 6.2-68A F 6.2-69 F 6'-69A F 6.2-70 Sh 1 Sh 2 Sh 3 S}1 4 S}1 5 Sh 6 S}1 7 S}1 8 Sjl 9 Sjl 10 S}1 11 S}1 12 S}1 13 S}1 14 Amendment Number 11 11 11 ll ll ll ll 11 ll ll 11 ll 11 11 11 ll ll ll 11 ll ll ll 11 27 11 27 Rl RO RO RO RO.RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 6-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure S}1 15 Sh 16 S}1 17 S}1 18 S}1 19 S}1 20 S}1 21 S}1 22 S}1 23 S}1 24 S}1 25 S}1 26 S}1 27 Sh 28 S}1 29 S}1 30 S}1 31 S}1 31A S}1 32 S}1 33 S}1 34 S}1 35 S}1 36 Sh 37 S}1 38 Sh 39 S}1 40 S}1 41 S}1 42 S}1 43 Sh 43a S}1 43b F 6.2-71A F 6'-71B F 6.2-72A F 6.2"72B F 6'-72C F 6'-72D F 6.2-72E F 6'-72F F 6'-72G F 6.2-72H F 6'-72I F 6.2-72J F 6.2-72K Amendment Number Rl RO RO RO RO RO Rl RO RO RO RO RO Rl RO Rl RO RO RO RO RO Rl RO RO Rl RO RO RO Rl RO RO RO RO RO RO RO RO 7 RO 28 15 15 RO RO 15 Page T=Table~FF-i ure S}1 1 S}1 2 S}1 3 Sh 4 Sh 5 F 6.2-73A F 6.2-74 F 6.2-75 F 6.2-76 F 6'-76A F 6.2-77 F 6'-77A F 6.2-78 F 6.2-79 F 6'-80 F 6.2-81 F 6.2"82 F 6.2-83 F 6'-84 F 6.2-85 F 6.2-86 F 6.2-87 F 6.2-88 F 6.2-89 F 6.2-90 6.3-1 6.3-2 6.3-3 6.3-4 6.3-5 6.3-6 6.3-6a 6.3"6b 6.3-7 6.3-8 6.3"8a 6.3-8aa 6.3-8ab 6.3-8b 6.3-8c 6.3"Sd 6.3-9 6.3-10 6.3-10a Amendment Number Rl RO RO RO RO RO 10 24 RO RO RO RO 4 18 25 18 25 Rl RO 18 28 13 27 27 27 0 RO 28 0 23 23 6 6 19 26 26 20 20 25 24 19 0 5 27 Page T=Table~F=Fi ure 6.3-10b 6.3-11 6.3-12 6.3"13 6.3-14 6.3-14a 6.3-14b 6.3-15 6.3-16 6.3-16a 6.3-16b 6.3-17 6.3-18 6.3"19 6.3"20 6.3-20a 6.3"20b 6.3-21 6.3"22 6.3-23 6.3-23a 6.3-23b 6.3-24 6.3-24a 6.3-24b 6.3-24c 6.3-24d 6.3-25 6.3-26 6.3-27 6.3-28 6.3-29 6.3-30 6.3-31 6.3-32 6.3-33 T 6.3-1 Sh 1 S}1 2 S}1 3 T 6.3-2 S}1 1 S}1 2 T 6.3-3 T 6.3-4 Amendment Number 5 27 23 5 5 23 5 RO 27 23 23 23 0 0 5 23 5 26 0 20 20 20 20 7 7 7 7 20 0 20 20 0 Rl 27 26 0 20 20 20 20 20 20 USAR Revision 1 EP 6-5 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure S}1 1 S}1 2 T 6.3-5 T 6.3-6 S}1 1 S}1 2 F 6.3-1 S}1 1 S}1 2 F 6..3"2 F 6.3-3A F 6.3-3B F 6'.3-4A F 6.3"4B F 6.3-5A F 6'-5B F 6.3-5C F 6.3-6a F 6.3"6b F 6.3-7a F 6.3-8 F 6.3-9 F 6.3-10 F 6.3-11 F 6.3"12 F 6.3-13 F 6.3-14 F 6.3-15 F 6.3-16 F 6.3-17 F 6.3-18 F 6.3-19 F 6.3-20 F 6.3-21 F 6.3-22 F 6.3-23 F 6.3-24 F 6.3-25 F 6.3-26 F 6.3-27 F 6.3-28 F 6.3-29 F 6.3-30 F 6.3-31 F 6.3-32 Amendment Number 22 20 20 20 20 27 23 RO 20 5 20 5 20 7 7 RO RO RO 20 0 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 Page T=Table~P-Fi ure F 6.3"33 F 6.3-34 F 6.3-35 F 6.3-36 F 6.3"37 F 6.3-38 F 6.3-39 F 6.3-40 F 6.3-41 F 6.3"42 F 6.3-43 F 6.3-44 F 6.3-45 F 6.3-46 F 6.3-47 F 6.3"48 F 6.3-49 F 6.3-50 F 6.3-51 F 6.3-52 F 6.3-53 F 6.3-54 F 6.3-55 F 6.3-56 6.4-1 6.4-2 6.4-3 6.4-4 6.4-5 6.4-6 6.4-7 F 6.4-1 6.5-1 6.5-2 6.5-2a 6.5-2b 6.5-3 6.5-4 6.5-4a 6.5-4b 6.5-5 6.5-6 6.5"7 Amendment Number 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 0 0 26 0 26 0 Rl 0 0 28 25 25 RO 28 25 25 RO 28 24 Page T=Table~F=Fi ure 6.5-7a 6.5-7b 6.5"8 6.5-8a 6.5-8b 6.5-9 6.5-10 6.5-11 T 6.5-1 F 6.5-1 S}1 1 S}1 2 S}1 3 Sh 4 S}1 5 S}1 6 S}1 7 S}1 8 F 6.5-2 F 6.5-3 F 6.5-4 F 6'-5 6.6-1 6.6-1a 6.6-1b 6.6-2 6.6-3 App 6A 6A-1 App 6B 6B-i 6B-1 6B-2 6B-3 6B"4 6B-5 6B-6 6B-7 6B-8 6B-9 F 6B-1 F 6B-2 Amendment Number 23 23 26 20 20 28 0 0 0 RO Rl RO RO Rl RO RO Rl 0 RO RO RO RO ll 11 0 0 0 0 0 0 23 23 0 23 23 0 0 0 0 USAR Revision 1 EP 6-6 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure App 6C 6C-1 6C-2 6C-3 6C-4 6C-5 6C-6 6C-7 6C-8 6C-9 6C-10 6C-11 6C-12 6C-13 6c-14 6C-15 6C-16 6C-17 6C"18 6C-19 6C-20 6C-21 6C-22 6C-23/24(6C-25/26(6C-27/28(T HC-1 T HC-2)F HC-1)Page Amendment T=Table Number~F-Fi ure RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page Amendment T=Table Number~F=Fi ure Amendment Number USAR Revision 1 EP 6-7 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 7 Page T=Table~F=Fi ure 7 l 7 ll 7 ill 7-lv 7"v 7-vl 7-vl1 7-viia 7-viib 7 vill 7 lx 7-x 7 Xl 7-xii 7.1-1 7.1-1a 7.l-lb 7.1-2 7.1-3 7.1-4 7'-5 7.1-5a 7'-5b 7.1-6 7.1-6a 7.1-6b 7.1-6c 7.1-6d 7.1-7 7.1-7a 7.1-7b 7.1-8 T 7.1-1 S}1 1 Sh 2 Sh 3 T 7.1-2 Sh 1 Sh 2 Sh 3 T 7'-3 S}1 1 Sh 2 S}1 3 S}1 4 S}1 5 Amendment Number RO 24 RO RO RO RO 24 RO 24 RO RO 24 24 24 RO RO RO RO 18 0 RO RO RO RO RO RO RO RO Rl Rl 28 0 0 9 18 28 18 28 24 24 RO RO RO Page T=Table~F=Fi ure T 7.1-4 S}1 1 S}1 2 7.2-1 7~2 2 7'-3 7'3a 7.2-3b 7.2"4 7'-5 7.2-6 7~2 7 7.2-8 7.2-9 7'-10 7.2-11 7.2-12 7.2-13 7.2-13a 7.2-13b 7.2-13c 7.2-13d 7.2-14 7.2-15 7.2-16 7.2-17 7.2-18 7.2"19 7.2-20 7.2-21 7'-22 T 7.2-1 T 7'-2 S}1 1 S}l 2 S}1 3 Sh 4 S}1 5 sh 6 S}1 7 S}1 8 S}1 9 S}1 10 S}1 11 S}1 12 S}1 13 Amendment Number RO RO 23 RO RO RO 26 9 0 0 0 9 0 Rl 0 Rl Rl RO RO RO RO Rl 0 0 0 9 9 0 RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure S}1 14 S}l 15 S}1 16 S}l 17 S}l 18 F 7.2-1 S}l 1 Sh 2 S}l 3 S}1 4 S}1 5 7.3-1 7~3 2 7~3 3 7.3-4 7.3-5 7.3-6 7.3-7 7.3-7a 7.3-7b 7.3-8 7.3"9 7.3-9a 7.3-9b 7.3-10 7.3-11 7.3-12 7.3-13 7.3-13a 7.3-13b 7.3-14 7.3-15 7'-16 7.3-16a 7.3-16b 7.3-17 7.3-18 7.3-19 7.3-19a 7.3-19b 7.3-20 7.3-21 7~3 22 7.3-22a 7.3-22b 7.3-23 Amendment Number RO RO RO RO RO 23 23 RO Rl 23 0 23 Rl 23.Rl 26 25 25 9 Rl 23 13 13 0 RO 23 9 9 9 RO 9 28 18 18 28 28 RO RO 9 Rl Rl Rl RO RO Rl USAR Revision 1 EP 7-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table~P=Pi ure Amendment Number Page T=Table~F=Pi ure Amendment Number 7.3-24 7'-25 7.3-26 7.3-26a 7.3-26b 7~3 27 7.3-28 7.3-29 7.3-30 7.3-31 7.3-31a 7.3-31b 7~3 32 7~3 33 7.3-33a 7.3-33b 7.3-34 7'-35 T 7.3"1 T 7'-2 T 7'-3 T 7.3-4 T 7~3 5 Sjl 1 S}l 2 T 7.3-6 T 7e3-7 T 7.3-8 T 7.3-9 T 7.3-10 T 7.3-11, Sh 1 Sh 2 T 7'-12 T 7.3-13 T 7.3"14 T 7.3-15 T 7.3-16 Sjl 1 Sjl 2 T 7.3"17 S}1 1 S}1 2 S}1 3 S}1'4 S}1 5 sh 6 Rl 26 RO Rl RO 0 Rl 23 10 23 10 10 0 RO Rl Rl RO RO Rl Rl Rl Rl 23 Rl Rl Rl Rl Rl Rl RO Rl Rl Rl Rl Rl RO Rl RO RO RO RO RO RO Sh 7 Sh 8 Sjl 9 Sjl 10 S}1 11 Sjl 12 Sjl 13 S}1 14 Sjl 15 S}1 16 F 7.3-1 F 7.3-2 S}1 1 S}1 2 S}1 3 F 7.3-3 S}1 1 Sjl 2 Sjl 3 F 7.3-4 S}1 1 Sjl 2 Sh 3 Sh 4 Sjl 5 F 7'-5 S}1 1 Sjl 2 F 7'-6 Sh 1 S}1 2 S}1 3 S}1 4 Sh 5 F 7.3-7 F 7.3-8 F 7.3-9 F 7.3-10 S}1 1 S}1 2 7.4-1 7.4-2 7.4-3 7.4-3a 7.4-3b 7'-4 RO RO RO RO RO RO RO RO Rl Rl 9 RO 23.,23 RO RO RO RO 23 RO RO 23 RO 23 RO 23 RO RO RO RO 9 9 Rl RO 21 0 RO RO RO RO 7.4-4a 7.4-4b 7.4-5 7.4-6 7.4-6a 7.4-6b 7.4-7 7.4"8 7.4-8a 7.4-8b 7.4-9 7.4-10 7.4-11 7.4-11a 7.4-11b 7.4-12 7.4-12a 7.4-12b 7.4-13 7.4-13a 7.4-13b 7.4"14 7.4-15 7'-16 7.4-17 7.4-18 7.4"19 7.4-19a 7.4"19b 7.4-20 7.4"21 7'-22 7.4-22a 7.4"22b 7.4-23 7.4-23a 7.4-23b 7'-23c 7.4-23d 7.4-24 T 7.4-1 F 7.4-1 Sh 1 Sh 2 S}1 3 Sh 4 Sjl 5 RO 18 20 24 24 24 RO RO RO RO RO RO RO RO 23 RO RO RO RO 18 18 Rl Rl 0 0 0 RO RO RO 18 23 18 23 23 Rl RO RO RO RO 0 RO RO 23 23 RO RO USAR Revision 1 EP 7-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Sjl 6 F 7.4-2 7.5-1 7.5-1a 7.5"lb 7.5-2 7.5-3 7.5-4 7.5-5 7.5-6 7~5 7 T 7.5-1 S}1 1 S}1 2 Sjl 3 S}1 4 S}1 5 S}1 6 Sjl 7 Sh 8 S}1 9~S}1 10 Sh 11 Sh 12 S}1 13 S}1 14 T 7.5"2 Sh 1 Sh 2 S}1 3 Sh 4 Sh 5 Sh 6 S}1 7 S}1 8 Sh 9 S}1 10 S}1 11 S}1 12 Sjl 13 S}1 14 S}1 15 S}1 16 S}1 17 Sjl 18 S}1 19 Amendment Number'O RO RO RO RO 27 0 RO 27 23 RO Rl RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure S}l 20 Sh 21 S}1 22 7.6-1 7.6-2 7.6-2a 7.6.2b 7.6-3 7.6-3a 7.6-3b 7.6-4 7.6-4a 7.6-4b 7.6-5 7.6-6 7.6"6a 7.6-6b 7.6"7 7.6"8 7.6-8a 7.6-8b 7.6-8c 7.6-8d 7.6"9 7.6-9a 7.6-9b 7.6-10 7.6-10a 7,.6-10b 7.6"11 7.6-12 7.6"13 7.6-14 7.6-15 7.6-16 7.6-17 7.6-18 7.6"19 7.6-20 7.6-21 7.6-22 7.6-22a 7.6"22b 7.6-23 7.6-23a 7.6"23b Amendment Number RO RO RO 18 Rl RO 10 RO 10 10 Rl 10 10 26 Rl 18 10 27 24 Rl RO RO'O RO 10 10 Rl Rl 18 Rl Rl Rl 10 0 0 27 27 0 27 0 Rl RO RO 13 10 10 Page T=Table~F=Fi ure 7.6-24 7.6-25 7.6-26 7.6-26a 7.6-26b 7.6-26c 7.6-26d 7.6-26e 7.6-26K 7.6-26g 7.6-26h 7.6-27 T 7.6-1 T 7'-2 T 7.6-3 S}1 1 S}1 2 T 7.6"4 T 7.6-5 T 7.6-6 F 7.6-1 Sh 1 Sh 2 F 7.6-2 F 7.6-3 S}l 1 Sh 2 F 7.6-4, F 7'-5 F 7.6-6 S}1 1 S}1 2 S}1 3 S}1 4 Sh 5 Sjl 6 Sjl 7 F 7.6-7 F 7'-8 F 7.6-9 S}l 1 S}l 2 S}l 3 S}l 4 S}1 5 Sjl 6 Sh 7 Amendment Number 10 10 18 18 24 18 18 18 Rl Rl 18 0 Rl 10 RO Rl 10 27 27 RO RO 0 23 23 0 0 23 23 23 23 23 23 23 27 27 23 23 23 23 23 Rl 23 USAR Revision 1 EP 7"3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure S}1 8 S11 9 Sh 10 7.7-1 7.7-1a 7.7"1b 7~7 2 7~7 3 7'"4 7~7 5 7.7-6 7~7 7 7.7-8 7.7-9 7.7-10 7.7-11 7.7-12 7.7-13 7.7"14 7.7-15 7.7-16 7'-17 7.7-18 7.7-19 7.7"20 7.7-21 7.7-21a 7.7-2lb 7'-22 7'22a 7'-22b 7~7 23 7'-24 7.7-24a 7.7-24b 7'-25 7.7-26 7~7 27 7.7-27a 7.7-27b 7'-28 7.7-29 7.7-30 7.7-31 7'-32 7~7 33 Amendment Number 23 23 RO 26 10 10 0 10'0 27 0 0 27 Rl 0 0 0 27 0 0 Rl 0 0 RO RO RO 18 18 18 27 10 RO Rl Rl 14 10 RO 23 23 23 0 23 RO RO 14 0 Page T=Table~F=Fi ure 7.7-34 7.7-35 7.7-36 7~7 37 7.7-38 7.7-39 7.7-39a 7.7-39b 7.7-40 7.7-41 7.7-42 T 7.7-1 T 7~7 2 T 7.7-3 S}1 1, Sjl 2 F 7.7-1 S}1 1 S}1 2 S}1 3 sh 4 S}1 5 Sjl 6 S}1 7 F 7'-2 S}1 1 Sh 2 Sjl 3 Sjl 4 S}l 5 sh 6 S}1 7 S}1 8 S}1 9 Sjl 10 S}1 11 Sh 12 S}1 13 S}1 14 S}l 15 S}l 16 Sjl 17 S}1 18 Sjl 19 Sjl 20 S}1 21 S}1 22 Amendment Number 0 9 9 9 10 26 26 26 10 10 10 10 10 10 0 RO 23 23 RO 23 RO RO 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 Page T=Table~F=Fi ure S}1 23 Sh 24 S}1 25 Sh,26 Sjl 27 S}1 28 Sjl 29 S}l 30 S}1 31 Sh 32 S}1 33 Sh 34 S}1 35 F 7.7-3 F 7.7-4 F 7.7-5 F 7.7-6 S11 1 S}1 2 S}l 3 S}1 4 S}1 5 S}1 6 Sh 7 F 7.7-7 F 7.7-8 F 7.7-9 F 7'-10 App 7A 7A.1-1 7A.1-2 7A.1-3 7A.1-4 7A.1-5 7A.1-6 7A.1-7 7A.1-8 7A.1-9 7A.1-10 7A.1-11 7A.1-12 7A.1-13 7A.1-14 7A.1-15 7A.1-16 T 7A.1-1 Amendment Number 23 23 23 RO 23 23 23 23 23 23 23 23 23 0 10 0 23 23 RO RO 23 RO RO RO RO 0 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 7-4 October 1989 0

Nineile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 7A.1-2 F 7A.1-3 F 7A.1-4 F 7A.1-5 F 7A.1-6 F 7A.1-7 F 7A.1-8 F 7A..1-9 7A.2-1 7A.2-2 7A.2-3 7A.3-1 7A.3-2 7A.3-3 7A.4-1 7A.4-2 7A.4-3 7A.5<<1 7A.5-2 7A.5-3 7A.5-4 7A.5-5 7A.6-1 7A.6-2 7A.6 3 7A.6-4 F7A.6-1 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure Sh 17 Sh 18 Amendment Number RO RO Page T=Table Amendment~F=Fi ure Number App 7B 7B-1 T 7B"1 S}1 1 S}1 2 Sh 3 S}1 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 S}1 10 Sh 11 Sh 12 S}1 13 S}1 14 Sh 15 Sh 16 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 7<<5 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 8 Page T=Table~F=Fi ure 8-i 8-ii 8-iii 8-iiia 8-iiib 8-iv 8-v 8-va 8"vb 8-vi 8.1-1 8.1-2 8.1-3 8.1-3a 8.1-3b 8.1"4 8.1-5 8.1-6 8.1-7 8.1-8 F 8'-1 8.2"1 8.2-1a 8.2-lb 8.2-2 8.2"2a 8.2-2b 8.2-3 8.2-4 8.2-5 8.2-5a 8.2"5b 8.2-6 8.2-6a 8,2-6b 8.2-7 8.2-7a 8.2-7b 8.2-8 8.2-9 8.2"10 8.2-11 8.2-12 8.2"13 8.2-14 Amendment Number RO RO RO 24 24 0 RO RO 26 RO 7 27 27 27 27 0 0 RO 0 0 27 14 RO 7 RO RO RO 0 21 26 14 14 23 14 7 13 13 13 0 4 23 RO 23 21 RO Page T=Table~F=Fi ure 8.2-15 8.2-15a 8.2"15b 8.2-16 8.2-16a 8.2"16b 8.2-17 8.2-18 8.2-19 8.2-20 8.2-21 8'-22 8.2-23 8.2-23a 8.2-23b 8.2-24 8.2-24a 8.2-24b 8.2-24c 8.2-24d 8.2-25 8.2-26 T 8'-1 Sh 1 Sh 2 Sh 3 sh 4 F 8.2-1a F 8.2-1b F 8.2-lc F 8.2-2 F 8.2-3 F 8.2-4 F 8.2-4a'F 8.2-5 F 8.2-5a F 8.2-6 F 8.2-6a F 8.2-6b F 8.2-6c F 8.2-7 F 8.2-8 F 8.2-9 8.3-1 8.3-2 8.3-3 Amendment Number 26 26 26 26 26 26 7 RO RO 23 RO Rl 23 7 7 15 23 RO 28 28 RO RO RO RO 16 28 RO RO RO 26 7 0 26 26 26 26 26 26 26 RO RO 26 Page T=Table~F=Fi ure 8.3-4 8.3-4a 8.3-4b 8.3-5 8.3-6 8.3-7 8.3-7a 8.3-7b 8.3-8 8.3-8a 8.3-8b 8.3-9 8.3-9a 8.3-9b 8.3-10 8.3-11 8.3-1la 8.3-11b 8.3-12 8.3-12a 8.3-12b 8.3-13 8.3-14 8.3-15 8.3-16 8.3"17 8.3-18 8.3-18a 8.3-18b 8.3-18c 8.3-18d 8.3-19 8.3-19a 8.3-19b 8.3-20 8.3-20a 8.3-20b 8.3-21 8.3-22 8.3-23 8.3-24 8.3-24a 8.3-24b 8.3-25 8.3-25a 8.3-25b 8.3-26 Amendment Number 23 24 6 RO 23 RO 7 7 Rl 7 7 Rl 23 13 23 RO 19 7 RO 23 23 27 20 RO 19 RO RO RO 28 RO 7 RO RO RO 25 RO 23 RO RO 26 RO 27 27 RO RO 20 RO USAR Revision EP 8-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES~i=ii ure Number Page T=Table Amendment Page T=Table~F=Fi ure Amendment Number Page T=Table~F=ii ure Amendment Number 8.3-26a 8.3-26b 8.3-27 8.3-27a 8.3"27b 8.3-27c 8.3-27d 8.3-28 8.3-29 8.3-30 8.3"31 8.3-32 8.3"33 8.3-34 8.3-35 8.3"36 8.3-37 8.3-37a 8.3-37b 8.3-38 8.3"39 8.3-40 8.3-40a 8.3-40b 8.3-41 8.3-42 8.3-42a 8.3-42b 8.3"43 8.3"44 8.3-45 8.3-45a 8.3-45b 8.3-46 8.3-46a 8.3-46b 8.3-47 8.3-48 8.3-48a 8.3-48b 8.3-49 8.3-49a 8.3-49b 8.3-50 8.3-50a 8.3-50b 8.3-51 RO 7 7 RO RO RO RO RO'3 23 2'3 RO RO RO RO RO RO RO 21 RO 0 RO 15 15 RO RO RO~7 RO 0 19 19 19 RO 13 13 0 RO 7 7 23 RO 20 RO 23 15 26 8.3-5la 8.3-51b 8.3-52 8.3-52a 8.3-52b 8.3"53 8.3-53a.8.3-53b 8.3-54 8.3-54a 8.3-54b 8.3-55 8.3-56 8.3-57 8.3-57a 8.3-57b 8.3-58 8.3-58a 8.3-58b 8.3-59 8.3"60 8.3-61 8.3"62 8.3-62a 8.3"62b 8.3-63 8.3-64 8.3-64a 8.3-64b 8.3-65 8.3-66 8.3"67 8.3-68 8.3-69 8.3-70 8.3"71 8.3-72 T 8.3-1 S}1 1 Sh la S}1 2 S}1 3 Sh 4 Sh 5 S}l 6 S}l 7 S}l 8 25 23 RO RO 23 7 7 7 28 28 7 23 19 RO RO 7 23 19 7 27 RO 14 Rl Rl 18 23 23 19 19 RO 19 0 0 RO Rl 0 RO RO RO RO Rl RO RO RO RO RO S}l 9 S}1 10 S}1 11 S}1 12 S}1 13 T 8.3-2 S}l 1 S}l 2 S}l 3 S}1 4 S}1 5 S}1 6 S}1 7 Sh 8 Sh 9 S}l 10 S}1 11 T 8.3-3 S}1 1 S}1 2 T 8.3-3A T 8.3-4 S}1 1 S}1 2 Sh 3 Sh 4 Sh 5 S}l 6 S}l 7 S}l 8 S}1 9 S}1 10 S}1 11 S}1 12 S}1 13 S}1 14 S}1 15 S}1 16 S}l 17 S}1 18 S}1 19 S}1 20 Sh 21 S}1 22 Sh 23 Sh 24 S}1 25 RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO 27 27 Rl RO RO 28 28 Rl RO 28 RO RO RO RO 28 RO 28 28 28 Rl RO RO 28 RO 28 28 RO USAR Revision EP 8"2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table Amendment~F=Pi ure Number Page T=Table~F=Fi ure Amendment Number S}1 26 Sh 27 S}1 28 S}1 29 S}1 30 S}1 31 S}1 32 S}1'33 S}1 34 S}1 35 S}1 36 S}1 37 S}1 38 S}1 39 Sh 40 T 8.3-5 T 8'-6 T 8.3-6a Sh 1 Sh 2 T 8.3-7 T 8.3"8 T 8.3-9 T 8.3-10 T 8.3-11 T 8.3-12 T 8.3-13 T 8.3-14 T 8.3-15 F 8.3"1 F 8.3"2 F 8.3-3 Sh 1 S}1 2 F 8.3-4 F 8.3"5 F 8.3"6 S}1 1 Sh 2 S}1 3 S}1 4 S}1 5 Sh 6 S}1 7 Sh 8 S}1 9 S}1 10 RO RO RO RO Rl 28 RO RO 28 RO RO RO RO 28 RO RO RO RO RO RO RO RO RO RO RO 23 0 0 RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO S}1 11 S}1 12 S}1 13 S}1 14 Sh 15 S}l 16 S}l 17 S}1 18 S}1 19 S}1 20 Sh 21 Sh 22 Sh 23 S}1 24 S}1 25 Sh 26 Sh 27 S}1 28 S}l 29 S}1 30 S}1 31 F 8.3-7 F 8.3-8 S}1 1 S}1 2 F 8.3-8A F 8.3-8B S}1 1 S}1 2 S}l 3 sh 4 S}1 5 S}1 6 S}1 7 S}l 8 S}1 9 S}1 10 S}1 11 S}1 12 Sh 13 Sh 13a S}1 13b Sh 13c S}l 13d Sh 13e Sh 13el S}1 13K RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO 15 15 15 15 15 15 15 15 15 15 15 RO 23 28 28 28 28 28 28 28 F 8.3"9 S}1 1 S}1 2 F 8.3-10 F 8.3-11 App 8A 8A-1 8A-2 8A-3 8A-4 23 0 RO Rl RO RO RO RO RO USAR Revision 1 EP 8-3 October 1989

Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 9 Page T=Table~F=Fi ure 9-i 9-ii 9-iii 9-iv 9-iva 9-ivb 9-v 9"vi 9-vii 9-viia 9-viib 9-viii 9-ix 9-x 9-xi 9-xii 9-xiii 9-xiiia 9"xiiib 9-xiv 9"xv 9-xvi 9"xvii 9-xviii 9-xix 9-xx 9-xxi 9"xxii 9.1-1 9.1-2 9.1-2a 9.1-2b 9.1-3 9.1-3a 9.1-3b 9.1-4 9.1-5 9.1"6 9.1-6a 9'-6b 9.1-7 9.1-7a 9.1-7b 9.1-8 Amendment Number 5 RO 24 12 12 12 RO 24 24 24 23 0 RO RO RO RO 24 26 26 24 Rl RO RO RO RO 24 RO Rl 0 5 20 5 5 22 5 0 5 20 20 20 28 5 5 RO Page T=Table~F=Fi ure 9.1-8a 9.1-8b 9.1-9 9.1-9a 9.1-9b 9.1-10 9.1-10a 9.1-10b 9.1-11 9.1-11a 9.1-11b 9.1-12 9.1-13 9.1-14 9.1-14a 9.1-14b 9.1-15 9.1-15a 9.1-15b 9.1-16 9.1-17 9.1-18 9'-19 9.1-20 9.1-21 9.1-22 9.1-23 9'-24 9'-25 9.1-26 9.1-27 9.1-28 9.1-29 9.1-29a 9'-29b 9.1-30 9.1-31 9.1-32 9.1-33 9.1-34 9.1-35 9.1-36 9.1-37 9.1-38 9.1-39 Amendment Number 23 20 14 14 14 RO 14 14 23 23 23 26 19 26 19 5 28 28 5 0 0 24 21 0 9 0 21 0 0 21 0 0 RO RO 28 0 27 21 0 0 0 0 0 0 0 Page T=Table~F=Fi ure 9.1-40 9.1-41 9.1-42 9.1-42a 9.1-42b 9.1-43 9.1-44 9.1-45 9.1-46 T 9.1-1 T 9.1-2 T 9.1-3 T 9.1-4 S}1 1 S}1 2 T 9.1-5 T 9.1-6 F 9'-1 F 9'-1A F 9.1-2 F 9.1-3 F 9'-3A F 9'-4 F 9'-5a F 9'-5b F 9.1-5c F 9.1-5d F 9.1-6 S}1 1 S}1 2 S}1 3 S}1 4 S}1 5 Sh 6 S}1 7 Sh 8 F 9.1-7 F 9.1-8 F 9.1-9 F 9.1-10 F 9.1-11 F 9.1-12 F 9.1-13 F 9.1-14 F 9'-15 Amendment Number ,0 27 27 9 9 23 20 20 20 0 0 0 0 0 5 19 0 5 4 RO 5 23 RO RO RO RO RO RO RO RO RO RO RO RO 27 0 0 0 0 0 0 0 0 USAR Revision 1 EP 9-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 9.1-16 F 9.1-17 F 9.1-18 F 9.1-19a F 9.1-20a F 9'-21 F 9.1-22 F 9'-23 F 9.1-24 F 9.1-25 F 9.1-26a 9.2-1 9.2-2 9.2-2a 9.2-2b 9.2-3 9.2-4 9.2-4a 9.2-4b 9.2"5 9.2-5a 9.2"5b 9.2"6 9.2-7 9.2-7a 9.2-7b 9.2-8 9.2-9 9.2-10 9.2-10a 9.2-10b 9.2-11 9.2-1la 9.2<<lib 9.2-12 9.2-13 9.2-14 9.2-15 9'-16 9.2-17 9.2-18 9.2-18a 9.2-18b 9.2-19 Amendment Number 0 0 0 RO RO 0 0 0 0 RO RO 0 RO 5 5 25 25 25 5 ll 25 5 24 Rl 25 23 25 28 27 22 22 27 23 23 27 27 RO 0 27 RO RO RO 25 25 Page T=Table~F=Fi ure 9.2-20 9.2-21 9.2"22 9.2-22a 9.2-22b 9.2-23 9.2-23a 9.2-23b 9.2-24 9.2-25 9.2-25a 9.2-25b 9.2-26 9.2-26a 9.2-26b 9.2-27 9.2-28 9.2-28a 9.2"28b 9.2-29 9.2-30 9.2-31 9.2-32 9.2"33 9.2-34 9'-35 9.2-36 9.2-37 9.2-38 9.2-39 9.2-39a 9.2-39b 9.2-40 9.2"41 9.2-42 9.2-43 9.2-44 9'-45 9.2"46 9.2-46a 9.2-46b 9.2-47 9.2-48 9.2-48a 9.2"48b Amendment Number 25 RO RO RO RO 23 23 23 23 23 23 18 23 23 18 RO 25 25 25 0 0 0 0 0 0 0 0 0 0 26 26 26 0 Rl 22 RO RO 23 5 24 5 24 RO 20 20 Page T=Table~F=Fi ure 9.2-49 9.2-50 9.2-51 T 9.2"lA S}1 1 S}1 2 Sh 3 S}1 4 Sh 5 Sh 6 T 9'-1B S}1 1 Sh 2 S}1 3 S}1 4 S}1 5 T 9.2-2 S}1 1 S}1 2 S}1 3 Sh 4 S}1 5 S}1 6 S}1 7 S}1 8 S}1 9 T 9.2-3 Sh 1 S}1 2 T 9.2-4 S}1 1 S}1 2 S}1 3 T 9.2-5 T 9.2"6 T 9.2-7 T 9'-8 T 9.2-9 F 9.2-la 9.2-1b 9.2-1c 9.2-1d 9.2-le 9.2-1j 9.2-lg Amendment Number RO 23 0 Rl 28 28 28 Rl Rl Rl 28 28 28 Rl Rl 28 28 28 Rl 28 28 28 Rl RO 23 23 23 23 0 0 0 0 0 RO RO RO RO RO RO RO USAR Revision EP 9"2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 9.2-1h F 9.2-1j F 9.2-1k F 9.2-11 F 9.2-1m F 9.2-1n F 9.2-1p F 9.2-1q, F 9.2-2 S}1 1 S}1 2 Sh 3 Sh 4 S}1 5 Sh 6 S}1 7 S}1 8 S}1 9 S}L 10 S}1 11 S}1 12 S}L 13 S}1 14 S}1 15 Sh 16 S}1 17 S}1 18 S}1 19 Sh 20 S}L 21 S}1 22 Sh 23 S}1 24 S}1 25 Sh 26 S}1 27 F 9.2-3a F 9'-3b F 9'-3c F 9'-3d F 9.2-3e F 9.2-3f F 9'-3g F 9.2-4 S}1 1 Amendment Number Rl RO RO RO RO RO RO RO Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl Rl RO RO RO RO RO RO RO Rl Page T=Table~F=Fi ure S}1 2 S}1 3 S}L 4 S}1 5 S}1 6 Sh 7 S}1 8 Sh 9 S}l 10 S}1 11 S}l 12 9.2-5a 9.2-5b 9.2-5c 9.2-5d 9.2-5e 9.2-6a 9.2-7 S}1 1 S}1 2 S}1 3 S}1 4 S}1 5 S}1 6 S}1 7 Sh 8 S}1 9 S}1 10 S}1 11 S}1 12 9.2-8a 9.2-8b 9.2-9a 9.2-9b 9'-10 9.2"11 9'-12 9.2"13 9.2-14 9.2-15 9.2-16 9.2-17a 9.2-17b 9'-17c 9.2-18 Amendment Number RO Rl RO RO Rl RO RO RO RO RO RO Rl RO RO RO Rl RO RO RO RO RO RO RO RO RO Rl RO RO RO Rl Rl RO RO 0 23 23 0 0 0 0 RO RO RO Page T=Table~F=Fi ure Sh 1 S}l 2 S}1 3 sh 4 F 9.2-19a F 9.2-19b F 9.2-19c F 9.2-19d F 9.2-19e F 9.2-19f F 9.2-20 S}1 1 S}1 2 Sh 3 S}l 4 S}1 5 F 9.2-21 9.3-1 9.3-1a 9.3"lb 9.3-2 9.3"3 9.3-4 9.3-4a 9.3-4b 9.3-5 9.3-6 9.3"7 9.3-8 9.3-9 9.3-10 9.3-11 9.3-11a 9.3-lib 9.3-11c 9.3-lid 9.3-11e 9.3-1lf 9.3-1lg 9.3-llh 9.3-1li 9.3-1lj 9.3-12 9.3-13 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 18 RO RO 28 25 RO RO RO RO 12 12 RO 23 23 24 RO RO 12 26 24 RO RO 28 RO RO 12 25 23 ,USAR Revision EP 9-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee 9.3-14 9.3-15 9.3-16 9.3-17 9.3-17a 9.3-17b 9.3-18 9.3-19 9.3-20 9.3-21 9.3-22 9.3-22a 9.3-22b 9.3-23 9.3-23a 9.3-23b 9.3-24 9.3-25 9.3-26 9.3-26a 9.3-26b 9.3"27 9.3-28 9.3-28a 9.3-28b 9.3-29 9.3-29a 9.3-29b 9.3-30 9.3-31 9.3-32 9.3-33 9.3-33a 9.3-33b 9.3-34 9.3-35 9.3-35a 9.3-35b 9.3-36 T 9.3-1 S}1 1'S}1 2 Sh 3 S}1 4 S}1 5 Amendment Number 0 RO 23 24 24 24 0 0 0 0 22 22 22 27 22 22 27 27 22 27 22 RO RO 24 22 24 18 18 18 27 RO 26 26 18 RO 28 28 28 Rl 0 0 0 0 23 Page T=Table~F=Fi uee Sh Sa Sh 6 S}1 7 S}1 8 S}1 9 Sh 9a Sh 10 T 9.3"2 Sh 1 S}1 2 T 9.3-3 F 9.3-la F 9.3-lb F 9.3-1c F 9.3-1d F 9.3-1e F 9.3-1f F 9.3-1g F 9.3-1h F 9.3-lj F 9.3-1k F 9.3-1L F 9.3-lm F 9.3"2 S}1 1 S}1 2 S}1 3 Sh 4 Sh 5 Sh 6 Sjl 7 Sjl 8 Sh 9 S}1 10 Sh 11 F 9.3"3a F 9.3-3b F 9.3-3c F 9.3-3d F 9.3-3e F 9.3"4 S}1 1 S}1 2 F 9'-5a F 9.3-5b Amendment Number 23 0 0 23 23 23 23 21 23 RO RO Rl RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi uue F 9.3"5c F 9.3-5d F 9.3-5e F 9.3-5f F 9.3-5g F 9.3-5}1 F 9.3"5j F 9'-5k F 9'-6 Sh 1 S}1 2 Sjl 3 Sjl 4 F 9.3-7 S}1 1 Sjl 2 S}l 3 Sh 4 S}1 5 sh 6 S}l 7 S}1 8 F 9.3-8 S}1 1 S}l 2 Sjl 3 F 9.3-9a F 9.3-9b F 9.3-9c F 9.3-9d F 9.3-9e F 9.3-9f F 9.3-10a F 9'-lob F 9.3-10c F 9.3-10d F 9.3-10e F 9.3"lof F 9.3-10g F 9.3-10h F 9.3-10j F 9.3-1la F 9.3-11b F 9.3"llc F 9.3-11d Amendment Number RO RO Rl Rl RO RO Rl RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO USAR Revision EP 9-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uue F 9.3-lie F 9.3-12a F 9.3-12b F 9.3-12c F 9.3-12d F 9.3-12e F 9.3"12f F 9.3"12g F 9.3-12h F 9.3"12j F 9.3-12k F 9.3-12L F 9.3-13 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 F 9.3-14 Sh 1 Sh 2 Sh 3 Sh 4 F 9.3-15 F 9.3-16 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 F 9.3-17a F 9.3-18 F 9.3-19 F 9.3-20a F 9'-20b 9.4-1 Amendment Number Rl RO Rl RO Rl RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 26 0 RO RO 26 Page T=Table~F=Fi uue 9.4-2 9.4-2a 9.4-2b 9.4-3 9.4"4 9.4-5 9.4-6 9.4-7 9.4-8 9.4-9 9.4-10 9.4-11 9.4-12 9.4-13 9.4-14 9.4-15 9.4-16 9.4-17 9.4-18 9.4-19 9.4-20 9.4-21 9.4-21a 9.4-21b 9.4-22 9.4-23 9.4-23a 9.4-23b 9.4-24 9.4-25 9.4-26 9.4-26a 9.4"26b 9.4-27 9.4-28 9.4-29 9.4-30 9.4-31 9.4-32 9.4-32a 9.4-32b 9.4"33 9.4-33a 9.4-33b 9.4-34 Amendment Number 26 26 5 23 RO 26 26 23 25 22 26 25 25 RO RO 25 0 RO 25 25 25 25 25 15 RO RO 25 15 5 RO 15 15 5 RO 28 24 25 25 Rl Rl Rl RO 25 22 22 Page T=Table~F=Fi uue 9.4-34a 9.4-34b 9.4-35 9.4-36 9.4-37 9.4-37a 9.4-37b 9.4-37c 9.4-37d 9.4-38 9.4-39 9.4-40 9.4"41 9.4-42 9.4"43 9.4-44 9.4-44a 9.4-44b 9.4-45 9.4-46 9.4-47 9.4-48 9.4-49 9.4-50 9.4-51 9.4-52 9.4-53 9.4-54 9.4-54a 9.4-54b 9.4-55 9.4-56 9.4-56a 9.4-56b 9.4"57 9.4-57a 9.4-57b 9.4-58 9.4-58a 9.4-58b 9.4-59 9.4-59a 9.4-59b 9.4-60 9.4-61 Amendment Number 22 22 22 26 Rl Rl 22 22 22 25 23 23 23 23 0 Rl Rl Rl 28 24 25 0 Rl 25 23 23 23 23 23 23 RO RO 24 23 RO 23 23 9 24 RO 25 23 23 24 26 USAR Revision 1 EP 9-5 October 1989 0 Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 9.4-62 9.4-63 9.4-64 9.4-65 9.4-66 9.4-67 9.4-67a 9.4-67b 9.4-68 9.4-69 9.4-70 9.4-71 9.4-72 9.4-72a 9.4-72b 9.4-73 T 9.4-1 Sh 1 S}1 2 S}1 3 T 9.4-2 S}1 1 Sjl 2 S}l 3 Sjl 4 S}1 5 S}1 6 S}1 7 Sjl 8 S}1 9 S}1 10 Sjl 11 S}1 12 Sjl 13 Sh 14 T 9.4-3 S}1 1 Sh 2 S}1 3 S}1 4 S}1 5 S}1 6 S}1 7 S}1 8 S}1 9 25 23 5 23, Rl 24 20 20 0 23 25 0 23 23 23 24 Rl RO Rl 26 RO 26 26 26 26 26 RO 26 26 26 26 26 26 RO RO RO 26 RO RO RO RO RO Sjl 10 Sh 11 Sh 12 T 9.4"4 S}1 1 Sjl 2 Sjl 3 Sh 4 Sjl 5 Sh 5a Sh 6 S}1 7 T 9.4"5 S}1 1 Sh 2 Sh 3 S}1 4 Sh 5 S}l 6 S}1 7 S}1 8 Sjl 9 S}1 10 Sh 11 S}1 12 Sjl 13 S}1 14 Sh 15 S}1 16 S}1 17 S}1 18 S}1 19 S}1 20 S}1 21 T 9.4-6 T 9.4-7 S}1 1 S}1 2 T 9.4-8 S}1 1 S}1 2 S}1 3" sh 4 Sh 5 S}1 6 RO RO 26 26 26 26 Rl Rl Rl 26 26 26 26 RO 26 RO 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 RO 26 26 T T T T F F F F F F F F F F F F F F F F F F F 9.4-9 9.4-10 Sjl 1 Sjl 2 9.4-11 S}1 1 S}1 2 9.4-12 S}1 1 S}1 2 Sjl 3 Sh 4 S}1 5 9.4-1a 9.4-1b 9.4-1c 9.4-1d 9.4-1e 9.4-1f 9.4-2a 9.4-2b 9'-2c 9.4-2d 9.4-2e 9.4-3a 9.4-3b 9.4-3c 9.4-3d 9.4-3e 9.4-3f 9'-4 S}l 1 S}1 2 S}1 3 S}1 4 S}1 5 S}1 6 Sjl 7 S}1 8 S}1 9 9.4-5 Sh 1 S}1 2 S}1 3 Sjl 4 26 26 26 28 28 28 28 28 28 28 Rl RO Rl RO RO RO RO Rl RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision EP 9-6 October 1989 , Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uue Sjl 5 Sh 6 S}1 7 S}1 8 F 9.4-6 Sh 1 Sjl 2 Sji 3 S}1 4 Sjl 5 S}1 6 S}1 7 F 9'-7 Sh 1 Sh 2 Sjl 3 Sh 4 S}1 5 S}1 6 S}1 7 Sjl 8 Sjl 9 S}1 10 S}1 11 S}1 12 S}1 13 Sjl 14 F 9.4-8a F 9.4-8b F 9.4-8c F 9.4-8d F 9.4-8e F 9.4-8f F 9.4-8g F 9.4-8}1 F 9.4-8j F 9.4-8k F 9.4-8L F 9.4-9 S}1 1 S}1 2 S}1 3 Sh 4 S}1 5 Sjl 6 Amendment Number RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl Rl Rl Rl RO Rl RO Page T=Table~F=Fi uue Sjl 7 Sjl 8 Sh 9 Sjl 10 S}1 11 Sjl 12 Sjl 13 S}1 14 Sh 15 S}1 16 S}1 17 Sjl 18 Sjl 19 Sjl 20 Sjl 21 S}1 22 Sjl 23 Sh 24 S}1 25 F 9.4"loa F 9.4-10b F 9.4-10c F 9.4-10d F 9.4-10e F 9.4-11 S}1 1 Sjl 2 Sh 3 Sh 4 Sh 5 S}1 6 S}1 7 S}1 8 S}1 9 S}1 10 S}1 11 S}1 12 S}1 13 Sjl 14 Sjl 15 S}1 16 S}1 17 F 9.4-12a F 9.4-12b F 9.4-12c Amendment Number RO Rl RO Rl RO RO RO RO RO RO Rl RO Rl Rl RO RO RO RO RO RO RO RO RO Rl RO RO RO RO Rl RO RO RO RO RO RO Rl RO RO Rl RO RO RO RO RO Page T=Table~P=Fi uee F 9'-12d F 9.4-13 S}1 1 Sjl 2 S}1 3 Sh 4 Sjl 5 S}1 6 Sh 7 Sh 8 S}1 9 Sjl 10 Sjl 11 Sjl 12 F 9.4-14 S}1 1 S}1 2 Sjl 3 F 9.4-15a F 9.4-16 S}1 1 S}1 2 S}1 3 Sh 4 S}1 5 S}1 6 Sh 7 S}1 8 S}1 9 F 9.4-17 Sh 1 Sjl 2 Sh 3 Sh 4 S}1 5 S}1 6 Sh 7 S}1 8 Sjl 9 S}1 10 S}1 11 Sjl 12 S}1 13 F 9.4-18 S}1 1 Amendment Number RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl Rl Rl RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 9-7 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table Amendment~F=Fi ure Number Sh 2 S11 3 S11 4 F 9.4-19 S11 1 S}L 2 Sh 3 F 9.4-20 Sh 1 Sh 2 Sh 3 Sjl 4 Sjl 5 F 9.4-21 Sh 1 Sh 2 Sb 3 Sh 4 F 9.4-22a F 9.4-22b F 9.4-22c F 9.4"22d F 9.4-22e F 9.4-23 S}1 1 SL 2 Sh 3 SK 4 Sh 5 Sh 6 Sh 7 9.5-1 9.5-1a 9.5-1b 9.5"2 9.5-3 9.5"4 9.5-4a 9.5-4b 9.5"5 9.5-6 9.5"6a 9.5"6b 9.5-7 RO RO RO RO RO RO RO Rl RO RO RO RO Rl RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 9 RO RO 27 26 Rl 9.5"8 9.5-9 9.5-10 9.5-11 9.5-12 9.5-12a 9.5-12b 9.5-13 9.5-14 9.5-15 9.5-16 9.5-17 9.5"17a 9.5-17b 9.5-18 9.5-18a 9.5-18b 9.5"19 9.5-19a 9.5-19b 9.5-20 9.5-20a 9.5-20b 9.5-21 9.5-22 9.5"22a 9.5-22al 9.5-22a2 9.5-22b 9.5-22c 9.5"22d 9.5-22e 9.5-228 9.5-23 9.5-23a 9.5-23b 9.5-24 9.5-24.1 9.5-24.2 9.5-24a 9.5-24b 9.5-24c 9.5-24d 9.5-25 9.5-25a Rl RO 28 0 Rl 23 23 0 RO 0 RO 24 13 7 RO 23 23 RO RO RO RO RO 15 RO 25 23 21 21 22 26 26 18 17 RO RO RO 28 28 25 13 13 13 13 RO RO 9.5-25b 9.5-26 9'-26a 9.5-26b 9.5-27 9.5-27a 9.5-27b 9.5-28 9.5-29 9.5-30 9.5-31 9.5-3la 9.5-31b 9'-32 9'-33 9.5-33a 9.5-33b 9.5-34 9.5-35 9.5-35a 9.5-35b 9.5-36 9.5-36a 9.5-36b 9.5-37 9.5-37a 9.5-37b 9.5-38 9.5-38a 9.5-38b 9.5"39 9.5-40 9.5-40a 9'-40b 9.5-41 9.5-41a, 9.5-41b 9'-42 9.5-42a 9.5"42b 9.5-43 9.5-43a 9.5-43b 9.5-44 9.5-44a RO 20 20 20 Rl RO 20 RO 21 RO RO 26 13 0 RO RO 7 24 9 9 9 9 9 9 RO RO, RO Rl RO 20 28 23 17 7 26 9 9 RO RO RO Rl RO RO RO 21 USAR Revision EP 9-8 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 9.5-44b 9.5"45 9.5-45a 9.5-45b 9.5-46 9.5-47 9.5-47a 9.5-47b 9.5-48 9.5-49 9.5-49a 9.5-49b 9.5"50 9.5-50a 9.5-50b 9.5-51 9.5"51a 9.5-51b 9.5<<51c 9.5-51d 9.5"52 9.5-52a 9.5-52b 9.5-53 9.5-54~9.5-55 9.5-55a 9.5-55b 9.5"56 9.5"57 9.5-57a 9.5-57b 9.5-58 9.S-58a 9.5-58b 9.5-59 9.5-60 9.5-61 9.5-6la 9.5-61b 9.5-62 9.5-63 9.5-64 9.5"65 9.5-66 8 RO Rl 7 0 RO 7 7 0 7 19 7 13 RO 7 RO RO RO RO RO 20 14 11 23 20 23 20 7 0 RO RO 7 RO RO 7 RO RO RO RO RO RO, 18 26 27 RO 9.5-67 9.5-67a 9.5"67b 9.5-68 T 9.5-1 S}L 1 Sh 2 Sh 3 Sh 4 S}1 5 S}1 6 S}1 7 Sh 8 Sjl 9 T 9.5-2 S}L 1 S}1 2 Sh 3 S}1 4 S}1 5 S}1 6 S}1 7 S}1 8 T 9.5-3 S}1 1 S}1 2 Sh 3 Sh 4 S}1 5 S}1 6 S}1 7 S}1 8 S}1 9 Sh 9a Sh 10 S}1 11 T 9.5-3a F 9.5-1a F 9.5-1b F 9.5-1c F 9.5-1d F 9.5-le F 9.5-1f F 9.5-1g F 9.5-1}1 RO RO RO RO 8 8 8 26 23 26 26 RO RO 0 0 23 26 26 26 0 0 26 26 26 26 26 26 26 26 RO 27 26 26 26 RO RO RO RO RO RO RO RO F F F F F F F F F F F F F F F F F F F F P P F F F F F P F F F P F F F 9.5-2a 9.5-2b 9.5-3a 9.5-3b 9.5-3c 9.5-4a 9.5-5 9.5-6 9.5-7 9.5"8 S}L 1 S}1 2 9.5-9 S}1 1 S}L 2 9.5-10 S}1 1 S}1 2 9.5-11 9.5-12 9.5-13 9.5"14 9.5-15 9.5-16 9.5-17 9.5-18 9.5-19 9.5-20 S}1 1 S}1 2 9.5-21 9.5-22 9'-23 9.5-24 9.5-25 9.5-26 S}1'S}1 2 9.5"27 9.5-28 9.5-29 9.5-30 9.5-31 9.5-32 9.5-33 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision EP 9-9 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 9.5-34 F 9.5-35 F 9.5-36 F 9.5-37 F 9.5-38 F 9.5-39 F 9.5-40a F 9.5"40b F 9.5-40c F 9.5-41 S}1 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 S}1 7 Sh 8 S}1 9 S}1 10 S}1 11 F 9.5-42 F 9.5-43 F 9.5-44 F 9.5-45 F 9.5-46 F 9.5-47 F 9.5-48 S}1 1 S}1 2 F 9.5-49 F 9'-50 F 9.5-51 F 9.5-52a F 9.5-52b F 9'-52c F 9.5-53 S}1 1 Sh 2 S}1 3 S}1 4 Sh 5 S}1 6 S}1 7 Amendment Number RO RO RO RO RO 26 RO RO RO RO RO RO RO RO RO RO Rl RO RO RO 23 7 28 8 28 7 Rl Rl RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure App 9A 9A-i 9A-ii 9A-iii 9A-iv 9A-v 9A-vi 9A-vii 9A-viii 9A.1-1 9A.2-1 9A.2-la 9A.2-1b 9A.2-2 9A.2-3 9A.2-4 9A.2-5 9A.2-6 9A.3-1 9A.3-la 9A.3-1b 9A.3-2 9A.3-3 9A.3-4 9A.3-5 9A.3-6 9A.3-7 9A.3-7a 9A.3-7b 9A.3-8 9A.3-9 9A.3-10 9A.3-10a 9A.3-10b 9A.3-11 9A.3-12 9A.3-12a 9A.3-12b 9A.3-13 9A.3-14 9A.3-14a 9A.3-14b 9A.3-15 9A.3-16 9A.3-16a Amendment Number 6 RO RO Rl RO RO Rl RO RO 6 RO 24 24 26 RO 6 25 RO 28 Rl 28 Rl Rl Rl RO RO RO Rl 26 Rl RO Rl 24 24 RO RO 10 10 RO RO RO RO RO Rl 24 Page T=Table~F=Fi ure 9A.3-16b 9A.3"17 9A.3-17a 9A.3-17b 9A.3-18 9A.3-19 9A.3-20 9A.3-20a 9A.3-20b 9A.3-21 9A.3-22 9A.3-23 9A.3-24 9A.3-25 9A.3-26 9A.3-27 9A.3-28 9A.3"29 9A.3-29a'A.3-29b 9A.3-30 9A.3-30a 9A.3-30b 9A.3-31 9A.3-31a 9A.3-31b 9A.3-32 9A.3"33 9A.3-34 9A.3-35 9A.3-36 9A.3-37 9A.3-38 9A.3-39 9A.3-40 9A.3-40a 9A.3-40b 9A.3-41 9A.3-41a 9A.3-41b 9A.3-42 9A.3-42a 9A.3"42b 9A.3-43 9A.3-44'mendment Number 24 Rl RO 23 RO RO 23 23 23 RO 6 RO RO RO 26 RO 23 RO 26 26 26 RO 13 RO RO 14 RO RO RO RO RO RO RO RO Rl RO RO Rl Rl Rl Rl Rl 13 RO RO USAR Revision EP 9-10 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee 9A.3"44a 9A.3"44b 9A.3-45 9A.3-45a 9A.3-45b 9A.3"46 9A.3-47 9A.3-48 9A.3-48a 9A.3-48b 9A.3-49 9A.3-49a 9A.3-49b 9A.3"50 9A.3-50a 9A.3-50b 9A.3-50c 9A.3-50d 9A.3-50e 9A.3-50K 9A.3-51 9A.3-5la 9A.3-51b 9A.3-52 9A.3-52a 9A.3-52b 9A.3-52c 9A.3-52d 9A.3-53 9A.3"53a 9A.3-53b 9A.3-53c 9A.3-53d 9A.3"54 9A.3"55 9A.3-55a 9A.3-55b 9A.3-56 9A.3-57 9A.3-57a 9A.3"57b 9A.3-58 9A.3-59 9A.3"60 T 9A.3-1 Amendment Number RO 13 9 9 9 RO RO 28 RO 28 RO 28 13 28 28 28 RO 28 RO 28 RO 10 10 Rl RO RO RO RO 28 RO RO RO 28 26 23 RO 18 RO RO 17 13 RO RO RO Page T=Table~F=Fi uee Sh 1 Sjl 2 S}l 3 Sjl 4 T 9A.3-2 S}L 1 S}L 2 Sh 3 T 9A.3-3 T 9A.3-4 Sh 1 Sjl 2 S}1 3 Sjl 4 Sjl 5 S}1 6 T 9A.3-5 T 9A.3-6 S}1 1 S}1 2 Sjl 3 S}l 4 Sjl 5 T 9A.3-7 S}1 1 S}l 2 T 9A.3-8 Sjl 1 S}L 2 T 9A.3-9 Sjl 1 S}1 2 Sh 3 T 9A.3-10 S}1 1 S}1 2 T 9A.3-11 T 9A.3-12 T 9A.3-13 ,T 9A.3-14 T 9A.3-15 S}1 1 Sjl 2 Sjl 3 S}1 4 Amendment Number RO Rl Rl RO RO Rl RO Rl RO Rl Rl Rl Rl Rl Rl RO Rl Rl Rl RO RO RO RO Rl Rl Rl Rl Rl RO RO Rl RO 6 26-12 26 26 Page T=Table~F=Fi uee S}L 5 Sjl 6 T 9A.3-16 T 9A.3-17 S}L 1 S}1 2 Sjl 3 T 9A.3-18 Sh 1 Sjl 2 Sjl 3 Sjl 4 Sjl 5 Sjl 6 S}L 7 T 9A.3-19 T 9A.3-20 Sjl 1 Sh 2 T 9A.3-21 F 9A.3-1 F 9A.3-2 F 9A.3-3 F 9A.3-4 F 9A.3-5 F 9A.3-6 F 9A.3"7 F 9A.3"8 F 9A.3-9 F 9A.3-10 F 9A.3-11 F 9A.3-12 F 9A.3-13 F 9A.3-14 Sjl 1 Sjl 2 F 9A.3-15 S}i 1 Sjl 2 F 9A.3-16 Sjl 1 Sjl 2 F 9A.3-17 Sjl 1 S}1 2 Amendment Number 26 26 RO 28 28 28 28 RO 28 28 28 28 28 Rl 28 28 RO Rl RO Rl Rl Rl Rl Rl RO 23 23 23 RO RO RO 28 28 28 28 28 28 28 USAR Revision EP 9-11 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure F 9A.3-18 F 9A.3-19 F 9A.3-20 F 9A.3-21 F 9A.3-22 9B-1 App 9C 9C-i 9C-ii 9C-iii 9C.1-1 9C.2-1 9C.3-1 9C.3-2 9C.3-3 9C.3"4 9C.3-5 9C.3-6 9C.3-7 9C.3-8 9C.3"9 9C.3-10 9Ce3-11 9C.3-12 T 3"1 S}1 1 S}1 2 T 3-2 Sh 1 Sh 2 S}1 3 S}1 4 T 3-3 Sh 1 Sh 2 Sh 3 T 3-4 T 3-5 9C.4-1 T 4-1 Sh 1 Sh 2 Sh 3 Amendment Number RO 28 28 28 28 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure S}1 4 Sh 5 Sh 6 Sh 7 Sh 8 Sh 9 Sh 10 9C.5-1 F 5-1 F 5-2 F 5-3 F 5-4 S}1 1 Sh 2 9C.6-1 9C.7-1 9C.8-1 9C.8-2 9C.8-3 9C.8-4 9C.8-5 9C.9-1 9C.10-1 9C.10-2 9C.10-3 9C.10-4 9C.10"5.Amendment Number RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table Amendment~F=Fi ure Number.USAR Revision EP 9-12 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 10 10-i 10-ii 10-iii 10"iv 10-v 10-va 10-vb 10"vi 24 24 24 0 RO RO 24 RO 10.1-1 10.1-2 10.1-3 T 10'"1 F 10.1"1 F 10.1-2 F 10.1-3a F 10.1-3b F 10.1-3c F 10.1"3d 1 0 0 21 0 21 RO RO RO RO F 10.1-3e.RO F 10.1"3E F 10.1-3g F 10.1-34 F 10.1"3j F 10.1-31@F 10.1-4a F 10.1"4b F 10.1-4c F 10.1-4d F 10.1-5a F 10.1-5b F 10.1-5c F 10.1-5d F 10.1-5e F 10.1"6a F 10.1-6b F 10.1-6c F 10.1-6d F 10.1-6e F 10.1-7a F 10.1-7b RO Rl Rl RO Rl RO RO RO RO Rl Rl RO Rl RO RO RO RO RO RO Rl Rl F 10.1-7c Rl F 10.1-7d F 10.1-7e F 10.1-7K F 10.1-7g F 10.1-711 F 10.1-7j RO RO RO RO RO RO Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure F 10.1-7k F 10.1-71 F 10.1-7m F 10.1-7n F 10.1-7p F 10.1-7q F 10.1-7r F 10.1-7s F 10.1-7t F 10'-7u F 10.1-7w F 10.1-8a F 10.1-8b F 10.1-8c F 10.1-8d F 10.1-8e F 10.1-8K F 10.1-8g F 10.1-9a F 10.1-9b F 10.1-9c F 10.1"9d F 10.1-9e F 10 1-9E F 10.1-9g F 10.1-94 10.2-1 10'-2 10.2-3 10.2-3a 10.2-3b 10.2-4 10.2-5 10.2-5a 10.2"5b 10.2-6 10.2-7 10.2-8 10.2-9 10.2-10 10.2-11 10'-12 F 10.2-1 F 10.2-2 F 10.2-3 Sh 1 Sh 2 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 21 0 13 28 7 RO RO RO RO 0 0 23 0 0 0 0 0 0 Rl'Page T=Table~F=Fi ure Sh 3 10.3"1 10.3-la 10.3-1b 10.3-2 10.3-3 10.3-3a 10.3-3b 10.3-4 10.3"5 10.4-1 10.4-2 10.4-3 10.4-3a 10.4-3b 10.4"4 10.4-4a 10.4-4b 10.4-5 10.4-6 10.4-7 10.4-7a 10.4-7b 10.4-8 10.4-9 10.4-10 10.4-11 10'-12 10.4"13 10.4-14 10.4-15 10.4-16 10.4-17 10.4-17a 10.4-17b 10.4"18 10'-19 10.4-19a 10.4-19b 10'-20 10.4-21 10'-22 10.4-23 10.4-23a 10.4-23b 10.4-24 Amendment Number 5 5 5 27 RO RO 5 0 23 0 RO 21 6 6 28 6 6 0 0 Rl 21 21 RO 27 21 21 0 0 RO RO 0 RO RO RO 18 28 28 18 0 0 0 26 5 5 Rl USAR Revision 1 EP 10-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number 10.4-25 10.4-25a 10.4-25b 10.4-26 10.4-26a 10.4"26b 10.4"27 10.4-28 10.4-28a 10.4"28b 10.4"29 10.4"30 10.4-31 10.4-32 10.4-33 10.4-33a 10.4-33b 10.4-34 10.4-34a 10.4-34b 10.4-35 10.4-36 10.4-37 10.4-38 10.4-39 T 10.4"1 T 10'-2 F 10.4>>1 S}1 1 Sh 2 S}1 3 S}1 4 Sh 5 F 10.4-2a F 10.4-3 S}1 1 Sh 2 S}1 3 S}1 4 Sh 5 F 10.4-4 F 10.4-5 F 10.4-6 F 10.4-7a F 10.4-7b F 10.4"7c F 10.4-7d F 10.4-7e 10 5 5 21 5 5 RO 24 14 7 RO 0 0 RO 25 25 20 RO 20 20 0 0 0 24 0 RO 27 RO RO RO RO Rl Rl RO RO RO RO RO 0 0 0 RO RO RO Rl RO F 10.4-7Z F 10.4-7g F 10.4-7}1 F 10.4-8 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 S}1 9 Sh 10 F 10.4-9 S}1 1 Sh 2 Sh 3 sh 4 Sh 5 Sh 6 S}1 7 Sh 8 Sh 9 Sh 10 F 10.4-10 Sh 1 Sh 2 Sh 3 Sh 4 S}1 5 Sh 6 S}1 7 Sh 8 Sh 9 Sh 10 S}1 11 S}1 12 S}1 13 S}1 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 Sh 20 S}1 21 S}1 22 RO RO RO RO RO RO RO RO RO RO Rl Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO S}1 23 F 10.4-11 S}1 1 Sh 2 Sh 3 Sh 4 S}1 5 Sh 6 Sh 7 S}i 8 Sh 9 F 10'-12 Sh 1 Sh 2 S}1 3 S}1 4 Sh 5 Sh 6 Sh 7 F 10.4-13 S}1 1 S}1 2 Sh 3 Sh 4 S}1 5 Sh 6 S}1 7 Sh 8 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO USAR Revision 1 EP 10-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 11 Page T=Table~F=Fi ure 11-i 11-ii 11-iia 11-iib ll-iii 11-iv 11-v 11-vi 11.1-1 11.1-2 11.1-3 11.1-4 11.1-5 llew 1-6 11.1-7 11.1"8 11.1-9 11.1"10 11.1-11 11.1"12 11.1"13 11.1"14 11.1-15 T 11.1-1 S}1 1 Sh 2 S}1 3 T 11'-2'11.1-3 T 11.1-4 T 11'-5 T 11.1-6 T 11.1-7 T 11.1-8 F 11.1-1 F 11.1-2 F 11.1-3 11.2-1 11.2-2 11.2-3 11.2-3a 11.2-3b 11.2"4 11.2"4a 11.2-4b Amendment Number 24 24 23 23 RO 0 8 RO 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RO 0 0 0 23 19 19 Rl 0 0 0 0 0 0 23 RO 23 23 23 RO 5 5 Page T=Table~F=Fi ure 11.2-5 11.2-5a 11.2-5b 11.2-6 11.2-6a 11.2-6b 11.2-7 11.2-8 11.2-9 11.2-10 11.2-11 11.2-12 11.2-13 11.2-14 11.2-14a 11.2-14b 11.2-15 11.2"16 11.2"17 11.2-18 T 11.2-1 S}1 1 S}1 2 S}1 3 S}1 4 S}1 5 T 11.2-2 T 11'-3 T 11'-4 T 11.2-5 S}1 1 Sh 2 T 11.2-6 S}1 1 Sh 2 F 11.2-la F 11.2-lb F 11.2-lc F 11.2-1d F 11.2-1e F 11.2-lf F 11.2-1g F 11.2-1h F 11.2-1j F 11.2-1k F 11'-1L F 11.2-1m Amendment Number 5 RO 5 RO 5 5 RO RO RO RO 23 RO RO RO RO 23 23 0 RO RO RO RO RO 25 25 RO RO 0 27 27 27 27 RO RO RO RO RO RO RO RO Rl RO RO RO Page T=Table~F=Fi ure 11.3-1 11.3-1a 11.3-1b 11.3-2 11.3-2a 11.3-2b 11.3-3 11.3-4 11.3-5 11.3-5a'11.3-5b 11.3"6 11.3-7 11.3-7a 11.3-7b 11.3".8 11.3-9 T 11'-1 S}1 1 S}1 2 T 11.3"2 Sh 1S}1 2 T 11.3-3 S}1 1 S}1 2 F 11.3-1a F 11.3"lb F 11.3-lc F 11.3-2 11.4-1 11.4-1a 11.4-1b 11.4-2 11.4-2a 11.4-2b 11.4-3 11.4-3a 11.4-3b 11.4-4 11.4-4a 11.4-4b 11.4-5 11.4-6 T 11.4"1 Amendment Number 3 3 3 RO 23 5 23 23 RO RO 5 24 9 9 9 12 12 12 0 RO RO 12 12 Rl Rl RO 0 3 3 3'O RO 8 RO Rl RO RO Rl 23 Rl RO Rl USAR Revision 1 EP 11-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 11.4-2 T 11.4-3 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 T 11.4-4 Sh 1 Sh 2 T 11.4-5 T 11.4-6 T 11.4"7 F 11.4-la F 11.4-lb F 11.4-1c F 11.4-1d F 11.4-1e F 11.4-1f F 11.4"lg F 11.4-1h 11.5-1 11.5-2 11.5-2a 11.5-2b 11.5-3 11.5-3a 11.5-3b 11.5-4 11.5-5 11.5-5a 11.5"5b 11.5-6 11.5-7 11.5"8 11.5-9 11.5-10 11.5-10a 11.5-10b 11.5"11 11.5-lla 11.5-11b 11.5-12 11.5-12a 11.5"12b 11'-13 Amendment Number RO 28 26 0 26 26 RO RO 8 8 8 Rl RO RO RO RO RO RO RO 23 23 RO 23 23 23 23 23 23 23 23 23 23 23 23 28 23 23 Rl 25 23 23 7 7 28 Page T=Table~F=Fi ure 11.5-14 T 11.5-1 S}1 1 Sh 2 Sh 2a T 11'-2 Sh 1 Sh 2 Sh 3 Sh 4 F 11.5-1 F 11.5-2 F 11.5-3a F 11.5-3b F 11.5-3c F 11.5-4 F 11.5-5 F 11'-6 F 11.5-7 F 11.5-8 Sh 1 Sh 2 App 11A llA-i 11A-ii 11A.l-l llA.1-2 T 11A.1-1 T 11A.l"2 AT 11A.1-3 T llA.1-4 T llA.1-5 T llA.1-6 T 11A.1-7 T 11A.1-8 T llA.1-9 T 11A.1-10 T 11A.1-11 T 11A.1-12 T llA.1-13 T llA.1-14 T llA.1-15 T 11A.1-16 T 11A.1-17 T 11A.1-18 T llA.1-19 Amendment Number 23 RO RO RO 0 0 RO 0 RO RO RO RO RO 23 0 RO RO 0 0 0 0 RO RO RO RO RO 0 0 RO 0 0 0 0 0 25 25 25 0 RO RO RO Page T=Table~FFi ure llA.2-1 llA.2-2 T 11A.2-1 T 11A.2-2 Amendment Number RO 0 RO RO USAR Revision 1 EP 11-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 12 Page T=Table~F=Fi ure 12-i 12-ii 12-iii 12"iv 12-iva 12-ivb 12-v 12-vi 12-vii 12-viia 12-viib 12-viii 12-ix 12-x 12-xi 12-xii 12,1-1 12.1-2 12.1-3 12.1-4 12.1-5 12.1-6 12.1-7 12.1-8 12.1-9 12.1-9a 12.1-9b 12.1-10 12.1-11 12.1-12 12.1-13 12.1-13a 12.1-13b 12.1-14 12.1-14a 12.1-14b 12.1-15 12.2-1 12.2-1a 12.2-1b 12.2-2 12.2-3 12.2-4 12.2-5 12.2-6 Amendment Number RO 24 RO 24 24 12 24 Rl 24 24 , 24 0 RO RO RO RO 0 RO 0 0 RO RO 9 Rl 26 9 9 0 0 0 7 7 7 7 7 7 0 ll 11 11 0 11 ll RO 0 Page T=Table~F=Fi ure 12'-7 12.2-8 12.2-8a 12.2-8b 12.2-9 12.2-10 12.2-11 12.2-12 12.2-13 12.2-14 12.2-15 12.2-16 T 12.2-1 T 12.2-2 T 12.2-3 T 12.2-4 S}1 1 S}1 2 S}1 3 T 12'-5 S}1 1 S}1 2 T 12~2-6 S}1 1 S}l 2 Sh 3 T 12.2-7 S}1 1 S}1 2 T 12.2"8 S}1 1 S}l 2 T 12.2-9 T 12'-10 S}1 1 S}1 2 S}1 3 T 12.2-11 T 12.2-12 S}1 1 S}1 2 S}1 3 T 12.2-13 S}1 1 S}1 2 S}1 3 T 12.2-14 Amendment Number 0 9 9 9 RO 25 0 7 7 9 9 ll RO RO RO RO RO Rl Rl RO 0 RO Rl 0 0 Rl Rl Rl Rl 0 Rl Rl Rl Rl Rl RO 7 Page T=Table~F=Fi ure T 12.2-15a T 12.2-15b T 12.2"16 12.3"1 12.3"2 12.3-3 12.3-4 12.3"5 12.3-6 12.3-7 12.3-7a 12.3-7b 12.3-8 12.3"9 12.3-10 12.3"ll 12.3-11al 12.3-1lbl 12.3-11a 12.3-11b 12.3-11c 12.3-11d 12.3-lie 12.3-llf 12.3-12 12.3-13 12.3-14 12.3-15 12.3-15a 12.3-15b 12.3-16 12.3-17 12.3-18 12.3-19 12.3-20 12.3-21 12.3-22 12.3-23 12.3-23a 12'-23b 12.3-24 12.3-25 12.3-26 12.3-27 12.3-28 12.3-29 Amendment Number RO RO ll 0 0 0 RO'0 RO RO RO 0 7 RO RO 20 20 13 13 RO RO RO 13 RO 0 0 5 5 5 0 0 1 0 Rl 0 10 10 10 10 RO 10 0 0 10 RO USAR Revision EP 12-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee Amendment Number Page T=Table'~F=Fi uee Amendment Number Page T=Table~F=Fi use Amendment Number 12.3-30 12.3"30a 12.3-30b 12.3-31 12.3-3la 12.3-3lb 12.3-32 12.3-33 T 12.3-1 Sh 1 Sh 2 S}1 3 S}l 4 T 12.3-2 S}1 1 S}1 2 S}1 3 T 12.3-3 S}1 1 Sh 2 T 12.3-4 S}1 1 S}1 2 S}1 3 Sh 4 F 12.3"1 F 12.3-2 F 12.3-3 F 12.3-4 F 12'-5 F 12'-6 F 12.3"7 F 12.3-8 F 12.3-9 F 12.3-10 F 12.3-11 F 12.3-12 F 12.3-13 F 12.3-14 F 12.3-15 F 12.3-16 F 12.3-17 F 12.3-18 F 12'-19 F 12'-20 F 12.3-21 F 12.3-22 RO RO RO RO RO RO RO 0 RO RO 24 Rl RO RO RO RO RO Rl Rl RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO RO RO RO RO RO RO RO RO RO F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F"F F F F 12.3-23 12.3-24 12.3-25 12.3"'26 12.3-27 12.3-28 12.3-29 12.3-30 12.3-30a 12.3-31 12.3-32 12.3-33 12.3-34 12.3"35 12.3-36 12.3-37 12.3-38 12.3"39 12.3-40 12.3-41 12.3-42 12.3-43 12.3-44 12.3-45 12.3-46 12.3-47 12.3"48 12.3-49 12.3-50 12.3-51 12.3-52 12.3-53 12.3-54 12.3-55 12'-56 12.3-57 12.3-58 12.3-59 12.3-60 12.3-61 12.3"62 12.3"63 12.3-63a 12.3-64 12.3-65 12.3-66 12.3-67 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO RO'O RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO F 12.3-68 F 12.3-69 S}1 1 S}1 2 S}l 3 S}1 4 12.4-1 12.4-1a 12.4-1b 12.4-1c 12.4-1d 12.4-2 12.4-2a 12.4-2b 12.4-3 T 12.4-1 T 12'-2 T 12.4-3 T 12.4-4 T 12.4-5 T 12.4-6 T 12.4-7 Sh 1 S}1 2 T 12.4-8 T 12.4-9 T 12.4-10 T 12.4-11 T 12.4-12 T 12.4-13 12.5-1 12.5-2 12.5-3 12.5-4 12.5-5 12.5-6 12.5-7 12.5-7a 12.5-7b 12.5"8 12.5-9 12.5-10 12.5-11 12.5-12 12.5-13 RO RO RO RO RO 15 RO 24 15 12 12 12 RO RO RO RO RO RO 20 20 20 20 20 RO'0 15 15 Rl RO 26 Rl RO 0 1 27 1 0 27 1 0 0 RO USAR Revision EP 12-2 October 1989

Nine Mile Point'Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 12.5-14 12.5-14a 12.5-14b 12.5-15 12.5-16 12.5-17 12.5-18 12.5-19 12.5-20 T 12'-1 T 12.5"2 T 12.5-3 T 12.5-4 Amendment Number 5 5 5 28 RO RO RO 26 26 Rl RO 5 1 Page T=Table Amendment~F=Fi ure Number Page T=Table Amendment~F=Fi ure Number USAR Revision 1 EP 12-3 October 1989 3 Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 13 Page T=Table~F=Fi ure 13"i 13-ii 13-iii 13-iv 13-iva 13-ivb 13-v 13-vi 13-vii 13-viii 13.1-1 13.1-2 13.1-2a 13.1-2b 13.1-3 13.1-3a 13.1-3b 13.1-4 13.1-4a 13.1"4b 13.1-5 13.1-5a 13.1-5b 13.1-6 T 13.1-1 T 13.1-2 T 13.1"3 Sh 1 Sh la Sh 2 Sh 2a S}1 2b Sh 2c Sh 3 Sh 3a Sh 4 Sh 5 Sh 6 S}1 7 T 13.1"4 Sh 1 S}L 2 S}1 3 Sh 4 Amendment Number RO RO RO RO RO 9 RO RO RO RO 28 Rl RO 9 RO 9 9 RO RO 1 RO 9 9 28 RO 28 RO RO RO RO RO RO RO RO 28 23 0 28 28 28 28 16 Page T=Table~F=Fi ure Sh 5 T 13.1"5 F 13.1-1 F 13.1-1a F 13.1-2 F 13.1-3 F 13.1-3a F 13.1"4 F 13.1-4a F 13.1-5 F 13'-5a F 13.1-5b F'3.1"6 F 13'-7 F 13.1"8 F 13'"9 F 13.1-10 13.2-1 13.2-2 13.2-3 13.2-4 13.2-5 13.2-6 13'-7 13.2-8 13.2-9 13.2-10 13.2-11 13.2-12 13.2-13 13.2-14 13.2-15 13.2-16 13.2-17 13.2-18 13.2-19 13.2-20 13.2-21 13.2-22 13.2-23 13.2-24 13.2-25 13.2-26 13.2-27 Amendment Number 28 28 Rl Rl Rl RO RO RO RO RO 13 9 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Rl RO RO RO RO Page T=Table~F=Fi ure 13.2-28 13.2-29 13.2-30 13.2-31 13.2-32 13.2-33 13.2"34 13.2"35 13.2-36 13.2-37 13.2-38 13.2-39 13.2-40 T 13.2-1 F 13.2-1 13.3"1 13.3-2 13.4-1 13.4"2 13.4-2a 13.4-2b 13.4-3 13.4-4 T 13.4"1 T 13.4-2 Sh 1 S}1 2 S}L 3 T 13.4-3 Sh 1 Sh 2 Sh 3 F 13.4-1 13.5-1 13.5-2 13.5-3 13.5-3a 13.5-3b 13.5"4 13.5-4a 13.5"4b 13.5-5 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO 28 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 6 RO 6 6 RO USAR Revision EP 13-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 13.5-6 13.5-7 T 13.5-1 S}1 1 S}1 2 T 13.5-2 T 13'-3 S}1 1 S}1 2 S}1 3 T 13.5"4 T 13.5-5 T 13.5-6 Sh 1 Sh 2 S}1 3 S}1 4 S}1 5 T 13~5-7 F 13.5-1 13.6-1 App 13A 13A-1 13A-2 13A-3 13A-4 13A-5 13A-6 13A-7 13A-8 13A-9 13A-10 13A-ll 13A-12 13A-13 13A-14 13A-14a 13A-14b 13A-14c 13A-14d 13A-14e 13A-14f 13A-14g Amendment Number RO RO RO 0 23 RO RO RO 28 22 23 RO RO RO 23 23 0 0 0 16 16 16 0 0 0 0 0 0 0 0 16 16 16 17 17 17 17 17 17 Page T=Table~F=Fi ure 13A"14h 13A-14i 13A-14j 13A-14k 13A-141 13A-14m 13A-14n 13A-14o 13A-14p 13A-14q 13A-14r 13A"14s 13A-14t 13A-14u 13A-14v 13A-15 13A"16 13A-17 13A-18 13A-19 13A-19a 13A-19b 13A-20 13A-21 13A-22 13A-23 13A"24 13A-25 13A-26 13A"27 13A-28 13A-29 13A-30 13A-31 13A-32 13A-33 13A-34 13A-35 13A-36 13A-37 13A-38 13A-39 13A"40 13A-41 13A-4la Amendment Number 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 16 16 16 16 16 16 16 0 0 0 0 0 0 16 16 0 0 0 0 0 0 0 16 16 16 16 16 16 16 16 Page T=Table~F=Fi ure 13A"41b 13A-42 13A-43 13A-43a 13A-43b 13A-43c 13A-43d 13A-44 13A-45 13A-46 13A-47 13A"48 13A-49 13A-50 13A"51 13A-52 13A-53 13A-54 13A-55 13A-56 13A-57 13A-58 13A-59 13A-60 13A-61 13A-62 13A-63 13A"64 13A-65 13A"66 13A-67 13A"68 13A-68a 13A-68b 13A"68c 13A"68d 13A-69 13A-70 13A-71 13A-72 13A-72a 13A-72b 13A-72c 13A-72d 13A-72e Amendment Number 16 16 16 16 16 16 16 0 0 16 16 16 16 0 0 0 0 0 0 16 16 16 16 16 16 16 16 16 16 16 16 16 9 9 17 17 0 16 16 0 17 17 17 17 17 USAR Revision EP 13-2 October 1989 l Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 13A-72f 13A-72g 13A-72h 13A-72i 13A-72j 13A-721%13A-721 13A-72m 13A"72n 13A-72o 13A-72p 13A-73 13A-74 13A-74a 13A-74b 13A-75 13A-76 13A-77 13A-78 13A-79 13A-80 13A"81 13A-82 13A-83 13A-83a 13A"83b 13A-84 13A-85 13A-86 13A-87 13A-88 13A-89 13A-90 13A-91 13A-92 13A-93 13A-94 13A-95 13A-96 13A-97 13A"98 13A-99 13A-100 13A-101 13A-102 Amendment Number 17 17 17 17 17 17 17 17 17 17 17 16 16 16 16 16 16 16 0 16 16 16 16 16 16 16 16 16 16 16 16 16 16 16 16 16 16 16 0 0 0 0 0 0 0 Page T=Table~F=Fi ure 13A-103 13A-104 13A-105 13A-106 13A-107 13A-108 13A-109 13A-110 13A-ill 13A"112 13A-112a 13A-112b 13A-113 13A-114 13A-115 13A-116 13A-117 13A-118 13A-119 13A-120 13A-121 13A-122 13A"123 13A-124 13A-124a 13A-124b 13A-124c 13A-124d 13A-125 13A-126 13A-127 13A-128 13A-129 13A-129a 13A-129b 13A-129c 13A-129d 13A-129e 13A-129f 13A-129g 13A-129h 13A-129i 13A-129j 13A-129k 13A-1291 Amendment Number 0 0 0 0 0 0 0 16 16 16 16 16 0 0 0 0 0 16 16 16 16 16 16 16 16 16 16 16 0 0 0 0 0 17 17 17 17 17 17 17 17 17 17 17 17 Page T=Table~F=Fi ure 13A-130 13A-130a 13A-130b 13A-131 13A-132 13A"133 13A-134 13A"135 13A-136 13A"137 App 13B 13B-1 Amendment Number 16 16 16 0 0 0 16 16 16 16 USAR Revision EP 13-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 14 Page T=Table~F=Fi uue 14-i 14-ii 14-iia 14-iib 14-iii 14-iv 14-v 14-vi 14-vii 14-viii 14-ix 14-x 14-xi 14-xia 14-xib 14-xii 14.1-1 14.2-1 14.2-2 14.2-3 14.2-4 14.2-5 14.2-6 14.2-7 14.2-8 14.2-9 14'-10 14.2-11 14.2-12 14.2"13 14.2-14 14.2"15 14.2-16 14.2"17 14.2"18 14.2-19 14.2-20 14.2"21 14.2-22 14.2-23 14.2-24 14.2-25 14.2"26 Amendment Number 28 22 28 22 RO RO RO RO RO RO RO 28 RO 28 16 RO 22 22 22 22 28 25 RO RO 25 RO 28 RO 22 RO 22 RO 22 22 22 RO 22 22 RO 22 RO RO Page T=Table~F=Fi uue 14.2-27 14.2-28 14.2-29 14.2-30 14.2-31 14.2-31a 14.2-31b 14.2-32 14.2-33 14.2-34 14.2-35 14.2-36 14.2-37 T 14.2-1 S}1 1 S}1 2 S}l 3 S}1 4 Sh 5 Sjl 6 T 14.2-1a Sh 1 S}1 2 Sh 3 S}1 4 T 14'-lb Sjl 1 S}1 2 S}1 3 Sh 4 F 14.2-lb-l T 14.2-2 S}L 1 S}1 2 T 14.2-3 Sh 1 S}l 2 T 14.2-4 T 14.2-5 S}1 1 Sh 2 T 14'-6 T 14.2-7 S}1 1 S}1 2 Amendment Number 22 22 Rl RO 28 28 28 Rl 28 28 RO RO 28 RO RO RO RO RO 22 RO RO RO RO RO RO RO RO RO 22 22 22 22 22 22 22 22 22 22 Page T=Table~F=Fi uee T 14.2-8 Sh 1 Sjl 2 T 14.2-9 S}1 1 Sjl 2 T 14.2-10 S}l 1 Sh 2 T 14'-11 S}1 1 S}1 2 T 14.2-12 S}1 1 Sjl 2 T 14.2-13 S}1 1 S}L 2 T 14.2-14 T 14.2-15 S}1 1 S}1 2 T 14.2-16 S}1 1 Sh 2 T 14.2-17 S}1 1 S}1 2 T 14.2-18 T 14.2-19 Sh 1 Sh 2 T 14.2-20 S}1 1 Sjl 2 T 14'-21 S}L 1 Sh 2 T 14.2-22 S}L 1 Sjl 2 T 14.2-23 Sh 1 S}1 2 T 14'-24 Amendment Number 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 USAR Revision EP 14-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~FFi ure T 14.2-25 S}1 1 S}i 2 T 14'-26 S}1 1 S11 2 T 14'-27 Sjl 1 S11 2 T 14.2-28 S}1 1 S}i 2 T 14.2-29 S}i 1 S}i 2 T 14.2-30 S}i 1 S}1 2 T 14.2-31 Sh 1 Sh 2 T 14.2-32 S}i 1 S}1 2 T 14.2-33 S}i 1 S}i 2 T 14.2-34 S}1 1 S}1 2 T 14.2-35 S}1 1 S}1 2 T 14.2-36 Sjl 1 Sh 2 T 14.2-37 S}1 1 S}1.2 T 14.2-38 S}i 1 S}1 2 T 14.2-39 Sh 1 S}i 2 Amendment Number 24 22 22 22 24 22 24 22 24 22 24 22 24 22 24 24 25 25 24 22 22 22 24 22 22 22 24 22 24 22 Page T=Table~F=Fi ure T 14'-40 S}1 1 S}1 2 T 14.2-41 S}i 1 S}1 2 T 14'-42'}i 1 S}i 2 T 14.2-43 S}1 1 S}1 2 T 14.2"43A S}i 1 S}i 2 T 14.2-44 Sh 1 S}i 2 T 14.2-45 Sh 1 Sh 2 T 14.2-46 S}1 1 S}1 2 T 14.2-47 S}1 1 S}i 2 T 14.2-48 S}1 1 S}i 2 T 14.2"49 S}i 1 S}1 2 T 14.2-50 S}i 1 S}1 2 T 14.2-51 S}1 1 S}i 2 T 14.2-52 S}i 1 S}1 2 T 14.2-53 Sjl 1 S}1 2 Amendment Number 24 22 28 28 24 22 24 22 RO 26 24 22 22 22 24 22 24 26 24 22 24 22 24 22 24 22 24 22 24 22 Page T=Table~F=Fi use T 14.2-54 S}1 1 Sh 2 T 14.2-55 S}1 1 S}i 2 T 14.2-56 S}i 1 S11 2 T 14.2-57 S}i 1 S}i 2 T 14.2-58 S}i 1 S}i 2 T 14.2-59 S}i 1 S}i 2 T 14.2-60 Sh 1 S}i 2 T 14.2-61 S}i 1 S}1 2 T 14.2-62 S11 1 S}i 2 T 14.2-63 S}i 1 S}i 2 T 14.2-64 Sh 1 S}1 2 T 14.2-65 Sh 1 S11 2 T 14.2-66 S}i 1 S11 2 T 14.2-67 S}1 1 S}1 2 T 14.2-68 Sh 1 S}i 2 Amendment Number 24 22 24 22 24 22 24 22 24 22 24 22 24 22 24 22 24 22 28 28 24 22 24 22 22 22 24 22 24 22 USAR Revisi,on 1 EP 14-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table Amendment~F=Fi ure Number T 14.2-69 S}l 1 Sjl 2 T 14.2-70 Sh 1 Sjl 2 T 14.2-71 Sjl 1 Sjl 2 T 14.2-72 S}1 1 S}l 2 T 14.2-73 Sjl 1 S}1 2 T 14.2"74 S}1 1 S}l 2 T 14.2-75 Sjl 1 S}l 2 T 14.2-76 S}l 1 Sjl 2 T 14'-77 S}1 1 S}l 2 T 14.2-78 S}1 1 S}1 2 T 14'-79 Sjl 1 S}l 2 T 14.2-80 S}1 1 S}l 2 T 14.2-81 S}1 1 Sjl 2 T 14.2-82 Sh 1 Sjl 2 T 14.2-83 Sjl 1 S}1 2 24 22 22 22 24 22 24 22 25 25 26 26 24 22 26 22 24 28 24 22 24 22 24 22 24 22 24 22 22 22 T 14.2-84 S}1 1 Sjl 2 T 14.2-85 S}1 1 Sjl 2 T 14.2-86 S}1 1 S}l 2 T 14'-87 Sjl 1 S}1 2 T 14.2-88 S}l 1 Sh 2 T 14.2-89 S}l 1 S}1 2 T 14.2-90 S}1 1 S}1 2 T 14.2"91 S}l 1 S}l 2 T 14.2-92 S}1 1 S}1 2 T 14'-93 S}1 1 S}1 2 T 14.2-94 S}l 1 S}l 2 T 14.2-95 S}1 1 S}1 2 T 14.2-96 Sh 1 S}1 2 T 14.2-97 Sh 1 Sh 2 T 14'-98 S}l 1 S}l 2 22 22 22 22 24 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 24 22 22 22 22 22 22 22 T 14.2-99 S}1 1 Sjl 2 T 14.2-100 Sh 1 Sh 2 T 14.2-101 S}1 1 S}1 2 T 14.2-102 Sh 1 S}l 2 T 14.2-103 S11 1 Sh 2 T 14.2-104 S}1 1 S}1 2 T 14.2-105 Sh 1 Sh 2 T 14.2-106 S}l 1 S}1 2 T 14'-107 S}1 1 Sjl 2 T 14.2-108 S}1 1 Sjl 2 T 14'-109 S}1 1 Sjl 2 T 14.2-110 Sjl 1 S}1 2 T 14.2-111 S}1 1 Sjl 2 T 14.2-112 S}1 1 S}l 2 T 14.2-113 S}1 1 Sh 2 22 22 24 22 24 24 24 26 24 22 24 22 25 22 24 22 24 22 24 22 26 22 24 22 17 17 25 25 24 22 USAR Revision 1 EP 14-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P~Pi ure Amendment Number Page T=Table~P=Pi use Amendment Number Page T=Table~P=Pi ure Amendment Number T 14.2-114 Sh 1 Sh 2 T 14'-115 S}1 1 S}1 2 T 14.2-116 T 14.2-117 S}1 1 S}1 2 T 14.2-118 S}1 1 Sh 2 T 14.2-119 S}1 1 Sh 2 T 14.2-120 Sh 1 Sh 2 T 14.2-121 Sh 1 S}1 2 T 14'-122 Sh 1.S}i 2 T 14'-123 S}1 1 S}1 2 T 14'-124 S}1 1 Sh 2 T 14'-125 S}1 1 Sh'Sh 3 T 14.2-126 S}1 1 Sh 2 Sh 2a T 14.2-127 Sh 1 Sh 2 T 14~2-128 Sh 1 Sh 2 24 22 24 22 24 24 22 24 22 24 22 24 22 24 22 24 22 24 22 22 22 24 22 22 24 22 22 22 22 22 22 T 14.2-129 S}1 1 Sh 2 Sh 2a T 14.2-130 S}1 1 S}1 2 T 14.2-131 T 14.2-132 T 14.2-201 S}1 1 S}1 2 T 14'-202 Sh 1 S}1 2 T 14.2-203 S}1 1 Sh 2 T 14.2-204 Sh 1 Sh 2 T 14.2-205 T 14'-206 Sh 1 S}1 2 Sh 3 Sh 3a S}1 3b Sh 4 T 14.2-207 Sh 1 Sh 2 T 14.2-208 S}1 1 S}1 2 T 14'-209 Sh 1 S}1 2 T 14.2-210 Sh 1 S}1 2 T 14'-211 S}1 1 S}1 2 T 14'-212 22 24 28 22 22 24 26 RO 22 RO 28 8 28 e 22 RO 12 12 RO RO 28 28 16 28 28 28 28 28 RO RO 8 28 28 Sh 1 Sh 2 S}1 3 T 14.2-213 S}1 1 S}1 2 S}1 3 Sh 4 F 14.2-213-1 T 14.2-214 Sh 1 S}1 2 T 14'-215 Sh 1 S}1 2 T 14.2-216 Sh 1 Sh 2 T 14.2-216A T 14'-217 Sh 1 S}1 2 T 14.2-218 S}1 1 Sh 2 T 14.2-219 Sh 1 Sh 2 T 14'-220 Sh 1 S}1 2 T 14.2-221 Sh 1 S}1 2 S}1 3 T 14.2-222 Sh 1 S}1 2 S}1 3 T 14.2-223 S}1 1 S}1 2 T 14.2-224 S}1 1 Sh 2 22 RO 12 RO RO RO RO 12 22 28 28 28 Rl 16 RO RO 22 28 8 28 28 28 28 RO 22 RO RO 16 RO 22 22 12 USAR Revision 1 EP 14-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment~F=Fi ure Number Page T=Table Amendment~F=Fi ure Number Page T=Table~F=Fi ure Amendment Number T 14.2-225 Sh 1 S}1 2 S}1 3 T 14.2-226 S}1 1 S}1 2 T 14.2-227 Sh 1 Sh 2 S}1 3 T 14'-228 S}L 1 Sh 2 T 14.2-229 T 14.2-230 S}1 1 S}1 2 S}1 3 T 14.2-231 S}1 1 S}1 2 Sh 3 Sh 4 T 14.2-232 S}1 1 S}i 2 T 14.2-233 S}1 1 Sh 2 Sh 3 F 14.2-233-1 T 14.2-234 S}1 1 S}1 2 Sh 3 S}1 4 S}1 5 F 14'-234-1 T 14.2-235 S}1 1 S}1 2 Sh 3 T 14.2-236 Sh 1~'8 28 28 RO RO RO RO RO 28 RO 12 28 28 28 28 RO 28 RO 28 28 22 RO 16 RO RO RO RO 28 22 8 12 22 22 RO Sh 2 F 14.2-236-1 T 14.2-237 Sh 1 Sh 2 T 14.2-238 T 14.2-239 Sh 1 Sh 2 F 14.2-239-1 T 14.2-240 Sh 1 Sh 2 T 14.2-241 S}1 1 S}1 2 Sh 3 S}1 4 T 14.2-241a T 14.2-24lb T 14.2-242 Sh 1 Sh 2 T 14.2-243 Sh 1 S}1 2 T 14.2-244 Sh 1 S}i 2 S}1 3 T 14.2-245 Sh 1 Sh 2 Sh 3 T 14.2-301 Sh 1 Sh 2 T 14'-302 T 14.2-303 S}1 1 S}1 2 Sh 2a Sh 2b S}1 3 T 14'-304 28 22 28 28 22 28 28 8 28 RO 28 RO RO 22 22 22 8 28 RO RO 28 28 22 22 28 22 RO Rl 28 28 RO RO 28 Rl S}1 1 Sh 2 Sh 2a Sh 2b Sh 2c Sh 2d Sh 3 T 14.2-305 Sh 1 Sh 2 T 14.2-306 T 14.2-307 T 14'-401 T 14.2-402 S}1 1 S}1 2 Sh 3 S}1 4 T 14.2-403 F 14.2-1 F 14'-2 F 14.2-3 F 14.2-4 F 14.2-5 F 14.2-6 F'4.2-7 RO RO 28 28 28 28 28 22 22 28 28 22 16 16 16 16 28 24 28 24 28 RO 22 16 USAR Revision EP 14-5 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 15 Page T=Table~F=Fi ure 15-i 15-ii 15-iii 15-iv 15-v 15-vi 15-vii 15-viii 15-ix 15-x 15-xi 15-xii 15-xiii 15-xiv 15-xv 15-xvi 15-xvii 15-xviii 15-xix 15-xx 15-xxi 15-xxii 15-xxiia 15-xxiib 1S-xxiii 15-xxiv 15-xxv 15-xxvi 15-xxvii 15.0-1 15.0-2 15.0-3 15.0-4 15.0-5 15.0-6 15.0"7 15.0-7a 15.0-7b 15.0-8 15.0-9 15.0"10 15.0-11 15.0-lla 15.0-11b 15.0-11c Amendment Number RO 0 0 0 0 RO 24 24 0 RO 6 24 12 RO 0 18 RO RO 24 0 24 RO 18 18 0 0 22 24 0 0 0 0 0 0 0 6 6 6 Rl 0 0 7 7 28 28 Page T=Table~F=Fi ure 15.0"lid 15.0-12 T 15'-1 S11 1 Sjl 2 S11 3 T 15.0-2 T 15.0-3 Sh 1 Sh 2 S11 3 T 15.0-4 T 15.0-5 S}1 1 Sjl 2 F 15.0-1 F 15.0-2 F 15.0-3 15.1-1 15'-2 15.1-2a 15'-2b 15.1-3 15'-4 15.1-5 15'-6 15.1-7 15.1-8 15.1-9 15.1-10 15.1-11 15.1-12 15.1-13 15.1-14 15.1-15 15.1-16 15.1-17 T 15'-1 T 15.1-2 T 15'-3 T 15.1-4 T 15'-5 T 15.1-6 F 15.1-1 F 15.1-2 Amendment Number RO RO Rl Rl Rl 0 0 22 0 0 RO RO 0 0 0 0 22 6 6 0 27 22 0 0 27 0 0 22 27 0 0 0 0 0 22 RO 22 26 0 0 0 0 Page T=Table~F=Fi ure F 15.1-3 F 15'"4 15.2-1 15.2-2 15.2-3 15.2-4 15.2-5 15;2-6 15.2-7 15.2-8 15.2-8a 15'-8b 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 15.2-15 15.2-16 15.2-17 15.2-18 15.2-19 15.2-20 15.2-21 15.2-21a 15.2-21b 15.2-22 15.2-23 15.2-24 15'-25 15.2-25a 15.2-25b 15.2-26 15'-27 15.2-28 15.2-29 15.2-30 15.2-31 15'-32 15.2-32a 15.2-32b 15.2-33 15.2"34'15'-1 Amendment Number 0 0 0 6 22 22 0 Rl Rl Rl 0 22 0 28 RO RO 22 23 0 0 0 0 RO RO RO 22 0 0 10 10 10 0 0 22 22 0 0 22 22 22 0 0 0 USAR Revision EP 15-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure T 15.2-2 T 15.2-3 T 15.2-4 T 15.2-5 T 15.2-6 T 15.2-7 Sh 1 S}l 2 T 15.2-8 T 15.2-9 T 15.2-10 S}1 1 S}1 2 T 15.2-11 T 15.2-12 T 15.2-13 F 15.2-1 F 15.2-2 F 15.2-3 F 15.2-4 F 15.2-5 F 15.2-6 F 15.2-7 F 15.2-8 F 15'-9 F 15.2-10 F 15.2-11 Notes S}1 1 S}1 2 F 15.2-12 F 15.2-13 F 15.2-14 F 15.2"15 F 15.2-16 F 15.2-17 15.3-1 15.3-2 15.3-3 15.3-4 15.3-5 15.3-6 15.3-7 15.3-8 15.3"9 Amendment Number 0 0 0 28 0 0 0 0 22 0 0 22 27 22 0 0 22 22 0 0 0 0 10 22 22 22 22 0 0 0 0 0 0 0 0 0 22 0 0 22 27 0 Page T=Table~F=Fi ure 15.3-10 15.3-11 15.3-12 15.3-13 15.3-14 T 15'-1 T 15'-2 T 15.3-3 T 15.3-4 T 15.3-5 F 15.3-1 F 15.3-2 F 15.3-3 F 15.3-4 F 15.3-5 15.4-1 15.4-2 15.4-3 15.4-4 15.4-4a 15.4-4b 15.4-5 15.4-6 15'-7 15.4-8 15.4-9 15.4-10 15.4-11 15.4-12 15.4-13 15'-14 15'-15 15.4-15a 15.4-15b 15.4-16 15.4-17 15.4-18 15.4-18a 15.4-18b 15.4-19 15.4-20 15.4-21 T 15.4-1 T 15.4-2 T 15'-3 Amendment Number 22 0 0 0 0 22 10 10 22 10 0 0 0 0 0 0 22 28 28 RO 28 0 0 22 0 0 0 0 22 22 0 22 6 27 22 12 RO RO 12 12 0 28 0 0 22 Page T=Table~F=Fi ure T 15.4-4 T 15.4-5 T 15.4-6 T 15.4-7 T 15.4-8 T 15.4-9 T 15.4-10 S}1 1 S}l 2 T 15.4-11 T 15.4-12 T 15.4-13 T 15.4-14 T 15.4-15 T 15.4-16 F 15.4-1 F 15.4-2 F 15.4-3 F 15.4-4 F 15.4-5 F 15.4-6 F 15.4-7 F 15.4-8 15.5-1 15.5-2 15.5-3 T 15.5-1 F 15.5"1 15.6-1 15.6-2 15.6-3 15.6"4 15.6-5 15.6-6 15.6"7 15.6-8 15.6-8a 15.6-8b 15.6-9 15.6-10 15.6-11 15.6-12 15.6-12a 15.6-12a.l Amendment Number 22 0 0 0 27 22 12 12 12 12 12 12 12 12 22 22 0 0 0 0.0 0 12 12 RO 12 0 0 12 RO 12 12 25 0 RO RO RO RO USAR Revision 1 EP 15"2 October 1989 ' Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi uee 15.6-12a.2 15'-12b 15.6"12c 15.6-12d 15.6-13 15.6-13a 15.6-13b 15.6-14 15.6-14a 15.6-14b 15.6-15 15.6-16 15.6-17 15.6-18 T 15.6-1 S}1 1 Sh 2 T 15.6-2 T 15.6-3 T 15.6-4 T 15.6-5 T 15.6"6 Sb 1 Sh 2 T 15.6-7 T 15.6"8 T 15.6-9 T 15.6"10 T 15.6-11 T 15,6"12 T 15.6-13 Sh 1 S}1 2 Sjl 3 S11 4 S4 5 Sh 6 Sb 7 Sh 8 Sb 9 S11 10 S11 11 S11 12 Sh 13 T 15.6-14 T 15.6-15a Amendment Number 25 RO RO 18 Rl 13 13 23 10 10 0 25 0 18 RO Rl 0 12 Rl 28 RO RO 12 RO RO 12 12 12 RO RO RO RO RO RO RO RO Rl RO RO RO RO RO 23 Page T=Table~F=Fi uee T 15.6-15b T 15.6-16a T 15.6-16b T 15.6-17 T 15.6-18 T 15.6-19 T 15.6-20 T 15.6-21 15.7-1 15.7-2 15.7-3 15.7-4 15.7-5 15.7-6 15.7-7 15.7-8 15.7-9 15.7-10 15.7-11 15.7-12 15.7-13 15.7-13a 15.7-13b 15.7-14 15.7-15 15.7-16 15.7-17 15.7-18 T 15.7-1 T 15.7-2 T 15.7-3 T 15.7-4 T 15.7-5 T 15.7-6 T 15.7-7 Sh 1 Sh 2 T 15.7-8 S11 1 Sb 2 T 15.7-9 S}1 1 Sb 2 T 15.7-10 T 15.7-11 Amendment Number RO 23 RO 13 13 13 13 22 0 25 23 19 0 RO 0 0 0 0 0 0 RO RO RO 12 18 12 RO Rl 25 13 0 0 Rl 0 23 0 RO RO Rl RO Page T=Table~F=Fi uee T 15.7-12 T 15.7-13 T 15.7-14 T 15.7-15 T 15.7-16 Sb 1 S11 2 T 15.7-17 15.8-1 15.8-2 15.8-3 15.8-4 App 15A 15A-i 15A"ii 15A-iii 15A-iv 15A-v 15A-vi 15A-vii 15A-viii 15A-1 15A-2 15A-3 15A-4 15A-5 15A-6 15A-7 15A-8 15A-9 15A-10 15A"11 15A-12 15A-13 15A-14 15A-15 15A-16 15A-17 15A-18 15A-19 15A-20 15A-21 15A-22 15A-23 Amendment Number RO 12 12 12 Rl Rl Rl 18 18 18 18 USAR Revision EP 15-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 15A"24 15A-25 15A-26 15A"27 15A-28 15A-29 15A-30 15A"31 15A-32 15A-33 15A-34 15A"35 15A-36 15A-37 15A-38 15A-39 15A"40 15A"41 15A"42 15A-43 15 A-44 15A-45 15A-46 15A-47 15A"48 15A-49 15A-50 15A-51 15A-52 15A-53 15A-54 15A-55 15A-56 15A"57 15A-58 15A-59 T 15A"1 T 15A-2 S11 1 S}1 2 T 15A-3 T 15A-4 T 15A-5 T 15A"6 T 15A-7 T 15A-8 Amendment Number Page T=Table~F=Fi ure T 15A-9 T 15A-10 T 15A-11 F 15A-1 F 15A-2 F 15A-3 F 15A-4 F 15A-5 F 15A-6 F 15A-7 F 15A-8 F 15A-9 F 15A-10 F 15A-ll F 15A-12 F 15A-13 F 15A-14 F 15A-15 F 15A-16 F 15A-17 F 15A-18 F 15A-19 F 15A-20 F 15A-21 F 15A-22 F 15A-23 F 15A-24 F 15A-25 F 15A-26 F 15A-27 F 15A-28 F 15A-29 F 15A-30 F 15A-31 F 15A-32 F 15A-33 F 15A-34 F 15A-35 F 15A-36 F 15A-37 F 15A-38 F 15A-39 F 15A-40 F 15A-41 F 15A-42 F 15A-43 Amendment Number 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 28 0 0 0 0 0 28 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page T=Table~F=Fi ure F 15A-44 F 15A-45 F 15A-46 F 15A-47 F 15A-48 F 15A-49 F 15A-50 F 15A-51 F 15A-52 F 15A-53 App 15B 15.B-i 15.B-ii 15.B-iii 15'-iv 15.B.1-1 15.B.1-2 15.B.2-1 15.B.2-2 15.B.2-3 15.B.2-4 15'.2-5 15.B.2-6 15'.3-1 15'.3-2 15.B.3-3 15.B.3-4 15.BE 3-5 15.BE 3-6 15.B.3-7 15.B.3-8 15.B.3-9 15.B.3-10 15.B.3-11 15.B.3-12 15.B.3-13 15.B.3-14 15.B.3-15 15.B.3-16 15'.3-17 15.B.3-18 15.B.3-19 15'E 3-20 15.B.3-21 15.B.3-22 Amendment Number 26 26 26 26 26 Rl 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 USAR Revision EP 15-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 15.B.4-1 15.8.4-2 15.B.4-3 15.B.5-1 15.BE 5-2 15.B.5-3 15.BE 5-4 15.B.6-1 15.B.6-2 15.B.6-3 15.B.6-4 15.B.6-5 15.B.7-1 15.B.7-2 15.B.8-1 15.B.8-2 App 15C 15C-i 15C-.ii 15C-iii 15C"1 15C-2 15C"3 15C-4 15C-5 15C-6 15C-7 15C-8 15C-9 15C-10 15C-11 15C-12 15C-13 15C-14 15C-15 15C-16 15C-17 15C-18 15C"19 15C-20 App 15D App 15E 15E-i Amendment Number 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 RO Page T=Table~F=Fi ure 15E-ii 15E-iii 15E.1-1 15E.1-2 15E.2-1 15E.2-2 15E.3-1 15E.3-2 15E.3-3 15E.3-4 15E.3-5 15E.3-6 15E.3-7 15E.3-8 15E.3-9 15E.3-10 15E.3-11 15E.3-12 15E.3-13 15E.3-14 15E.3-15 15E.3-16 15E.3-17 15E.3"18 15E.4-1 15E.4-2 15E.4-3 15E.4"4 15E.4-5>15E.4-6 15E.5-1 App 15F App 15G App 15H 15H-1 15H-2 158-3 158-4 15H-5 15H-6 15H-7 15H-8 15H-9 Amendment Number RO 26 26 RO RO RO RO 26 RO Rl RO Rl 26 RO 26 RO RO 26 26 26 28 26 26 26 26 26 RO RO 26 26 RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure 15H-10 15H-ll 15H-12 15H-13 15H-14 Amendment Number RO RO RO RO RO USAR Revision 1 EP 15-5 October 1989

Nine Mile Point Unit 2 FSAR~LIST OF EFFECTIVE PAGES CHAPTER 16 I Page Page T=Table Amendment T=Table Amendment~F=Fi ure Number'F=Fi ure Number Page T=Table Amendment~F=Fi ure Number 16"1 RO USAR Revision 0 EP 16-1 April 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 17 Page T=Table~F=Fi ure 17-i 17"ii 17-iii 17-iv 17-v 17.0"1 17.0-2 17.0-3 T 17.0-1 17.1-1 17.1-1a 17.1-1b 17.1-2 17.1-2a 17.1-2b 17.1-3 17.1-4 17.1-4a 17.1-4b 17.1-5 17.1-5a 17.1-5b 17.1-6 17.1-7 17'-8 17.1-9 17.1-10 17'-108 17.1-10b 17.1-11 17.1-12 17.1-13 17.1-13a 17.1-13b 17.1-14 17.1-15 17.1-15a 17.1-15b 17.1-16 17.1-16a 17.1-16b 17.1-17 17.1-17a Amendment Number'3 9 15 RO 24 7 0 15 7 RO 26 20 28 RO 9 28 28 28 28 28 RO 5 28 RO 28 0 28 13 13 RO 0 9 28 5 28 9 9 5 5 5 5 5 5 Page T=Table~F=Fi ure 17.1-17b 17.1-18 17.1-19 17.1-20 17.1-21 17.1-22 17.1-22a 17'-22b 17.1-23 17.1-23a 17.1-23b 17.1-24 17.1-248 17.1-24b 17.1-25 17.1-26 17.1-27 17.1-27a 17.1-27b 17.1-28 17.1-29 17.1-30 17.1-308 17.1-30b 17.1-31 17.1-32 17.1-32a 17.1-32b 17.1"33 17.1-33a 17.1-33b 17.1-34 17.1-346 17.1-34b 17.1-35 17.1-35a 17.1-35b 17.1-36 17.1-368 17.1-36b 17.1"37 17.1-38 17.1-38a 17.1-38b 17.1-39 Amendment Number 5 0 0 0 0 28 28 9 RO 5 5 5 5 1 0 5 9 9 9 0 0 5 5 1 9 9 9 9 5 5 5'9 Rl 9 28 15 15 9 28 5 0 15 28 28 5 Page T=Table~F=Fi ure 17.1-39a 17.1-39b 17.1-40 17.1-40a 17.1-40b 17.1-41 17.1-42 17.1-43 17.1-438 17.1-43b 17.1-44 17.1-44a 17.1-44b 17.1-45 17.1-46 17.1-47 17.1-48 17.1-49 17.1-50 17.1-50a 17.1-50b 17.1-51 17.1-52 17.1-53 T 17.1-1 S11 1 Sh 2 S11 3 Sh 4 Sh 5 F 17.1-1 F 17.1-2 17.2-1 Amendment Number 9 5 9 22 5 9 0 5 5 5 5 5 5 9 0 28 28 5 1 1 1 0 13 18 0 0 0 0 0 28 RO RO USAR Revision EP 17-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 18 Page T=Table~F=Fi ure 18.1-1 18.1-1a 18.1-1b 18.1-2 18.1-2a 18.1-2b T 18.2-1 Sh 1 Sh 2 Sh 3 Sh 4 T 18.2-2 T 18.2-3 T 18.2-4 T 18.2-5 S}1 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 T 18.2-6 S}1 1 S}1 2 F 18.2-1 F 18.2-2 F 18.2-3 F 18.2-4 F 18.2-5 F 18.2-6 F 18.2-7 F 18.2-8 F 18.2-9 F 18.2-10 F 18.2-11 F 18.2-12 F 18.2-13 F 18.2-14 F 18.2-15 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table~F=Fi ure 18.2-16 18.2-17 18.2-18 18.2-19 18.2-20 18.2-21 18.2"22 18.2-23 18.2-24 18.2-25 18.2-26 18.2-27 18.2-28 18.2-29 18.2"30 18.2"31 18.2-32 18.2-33 18.2-34 18.2-35 18.2-36 18.2-37 18.2"38 18.2-39 18.2-40 18,2-41 18.2-42 Amendment Number RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO Page T=Table Amendment~F=Fi ure Number USAR Revision 18-1 April 1989

Nine Mile Point Unit 2 DAR LIST OF EFFECTIVE PAGES DESIGN ASSESSMENT REPORT APPENDIX 6A Page T=Table~F=Fi uee 6A-i 6A-ii 6A-iii 6A-iiia 6A-iiib 6A-iv 6A-v 6A-vi 6A-vii 6A-viia 6A-viib 6A-viii 6A-viiia 6A-viiib 6A-ix 6A-ixa 6A-ixb 6A-x 6A-xi 6A-xii 6A-xiii 6A-xiv 6A-xv 6A"xvi 6A-xvii 6A-xviii 6A-xviiia 6A-xviiib 6A-xix 6A-xx 6A-xxi 6A-xxii 6A-xxiia 6A-xxiib 6A-xxiii 6A-xxiv 6A-xxv 6A-xxvi 6A-xxvii 6A-xxviii 6A.l-l 6A.1-2 6A.1-2a 6A.1-2b 6A.1-3 Amendment Number 24 0 24 24 24 24 24 7 24 24 9 27 9 9 21 24 17 RO 24 RO 27 24 25 24 RO 24 22 22 24 24 RO RO 24 24 0 24 24 24 24 24 26 9 9 9 9 Page T=Table~F=Fi uee 6A.1-4 6A.1-5 T 6A.1-1 S}L 1 S}1 2 Sh 3 F 6A.l-l F 6A.1-2 F 6A.1-3 6A.2-1 6A.2-2 6A.2-3 6A.2-4 6A.2-5 6A.2-6 6A.2-7 6A.2-8 6A.2-8a 6A.2-8b 6A.2-9 6A.2-10 6A.2-11 6A.2-12 6A.2-13 6A.2-14 T 6A.2-1 Sh 1 S}1 2 T 6A.2-1a Sh 1 Sh 2 T 6A.2-1b Sh 1 S}L 2 T 6A.2-2 S}L 1 S}1 2 Sh 3 T 6A.2-3 S}1 1 S}1 2 S}1 3 F 6A.2-1 F 6Ae2-2 F 6A.2-3'mendment Number 0 23 0 0 0 17 0 RO 0 0 0 0 0 0 27 5 5 5 RO 0 23 23 0 27 27 27 23 23 23 0 23 0 0 0 Page T=Table~F=Fi uee F 6A.2-4 F 6A.2"5 F 6A.2-6 F 6A.2-7 F 6A.2-8 F 6A.2-9 F 6A.2-10 F 6A.2-11 F 6A.2-12 F 6A.2-13 F 6A.2-14 F 6A.2-15 F 6A.2-16 F 6A.2-17 F 6A.2-18 F 6A.2-19 F 6A.2-20 F 6A.2-21 F 6A.2-22 F 6A.2-23 F 6A.2-24 F 6A.2-25 F 6A.2-26 F 6A.2-27 6A.3-1 6A.3-2 6A.3-3 6A.3-4 6A.3-5 6A.3-6 6A.3-7 6A.3-8 6A.3-9 6A.3-9a 6A.3-9b 6A.3-9c 6A.3-9d 6A.3-9e 6A.3-9Z 6A.3-9g 6A.3-9h 6A.3-9i 6A.3-9j 6A.3-9k 6A.3-91 Amendment Number 0 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 0 23 0 0 0 0 26 0 26 0'22 22 22 22 22 22 22 22 22 22 22 22 22 USAR Revision 1 DAR-1 October 1989

Nine Mile Point Unit 2 DAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure 6A.3-10 6A.3-11 6A.3"12 T 6A.3-1 T 6A.3-2 T 6A.3-3 T 6A.3"4 T 6A.3"5 T 6A.3-6 T 6A.3-7 T 6A.3-8 T 6A.3"9 T 6A.3"10 T 6A.3-11 T 6A.3-12 T 6A.3"13 T 6A.3-14 T 6A.3-15 F 6A.3-1 F 6A.3-2 F 6A.3-3 F 6A.3-4 F 6A.3-5 F 6A.3"6 F 6A.3-7 F 6A.3"8 F 6A.3-9 F 6A.3-10 F 6A.3-11 F 6A.3-12 F 6A.3-13 F 6A.3"14 F 6A.3-15 F 6A.3-16 F 6A.3-17 F 6A.3-18 F 6A.3-19 F 6A.3"20 F 6A.3-21 F 6A.3"22 F 6A.3-23 F 6A.3"24 F 6A.3"25 F 6A.3-26 F 6A.3"27 F 6A.3-28 Amendment Number 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RO RO 0 0 RO RO RO 0 0 0 0 RO RO RO RO RO 0 RO RO RO RO RO 0 0 0 0 0 0 Page T=Table~F=Fi ure F 6A.3-29 F 6A.3-30 F 6A.3-,31 F 6A.3-32 F 6A.3-33 F 6A.3-34 F 6A.3-35 F 6A.3-36 F 6A.3-37 F 6A.3-38 F 6A.3-39 F 6Ae3-40 F 6A.3-41 F 6A.3-42 F 6A.3-43 F 6A.3-44 6A.4-1 6A.4-2 6A.4-2a 6A.4-2b 6A.4-3 6A.4-4 6A.4-4a 6A.4-4b 6A.4-5 6A.4-5a 6A.4-5b 6A.4-6 6A.4-7 6A.4-8 6A.4-8a 6A.4-8b 6A.4-9 6A.4-10 6A.4-11 6A.4-12 6A.4-12a 6A.4-12b 6A.4-13 6A.4-14 6A.4-15 6A.4-16 6A.4-16a 6A.4-16b 6A.4-17 Amendment Number 0 0 RO 0 RO RO RO RO 0 RO 0 0 0 RO 23 23 0 RO RO RO 0 23 21 21 23 23 21 RO 0 23 23 21 0 0 0 23 23 6 0 23 26 26 6 6 0 Page T=Table~F=Fi ure 6A.4-18 6A,4-19 6A.4-19a 6A.4-19b 6A.4-20 6A.4-21 6A.4-22 6A.4-23 6A,.4-24 6A.4-24a 6A.4-24b 6A.4-25 6A.4-25a 6A.4-25b 6A.4-26 6A.4-27 6A.4-28 6A.4"29 6A.4-30 6A.4"31 6A.4-32 6A.4-33 6A.4-34 6A.4-35 6A.4-36 6A.4-37 6A.4-37a 6A.4-37b 6A.4-38 6A.4-39 6A.4-40 6A.4-41 T 6A.4-1 sh 1 Sh 2 T 6A.4-2 T 6A.4-3 T 6A.4-3a T 6A.4-4 T 6A.4-5 T 6Ae4-6 T 6A.4-7 S}1 1 Sh 2 T 6A.4-8 T 6A.4-9 Amendment Number 0 6 21 21 23 0 28 27 23 23 19 22 22 22 23 23 23 23 26 26 0 26 0 0 0 23 21 21 RO RO 0 21 RO RO 0 RO 21 28 0 0 0 23 0 0 USAR Revision 1 DAR-2 October 1989

Nine Mile Point Unit 2 DAR LIST OF EFFECTIVE PAGES Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number Page T=Table~F=Fi ure Amendment Number T T T T T T T T F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F F 6A.4-10 Sh 1 S}1 2 S}1 3 6A.4-11 6A.4-12 6A.4-13 6A.4-14 6A.4-15 S}1 1 S}1 2 6A.4-16 6A.4-17 6A.4-1 6A.4-2 6A.4-3 6A.4-4 6A.4-5 6A.4-6 6A.4-7 6A.4-8 6A.4-9 6A.'4-10 6A.4-11 6A.4-12 6A.4-13 6A.4-14 6A.4-15 6A.4-16 6A.4-17 6A.4"18 6A.4-19 6A.4-20 6A.4-21 6A.4-22 6A.4"23 6A.4-24 6A.4-25 6A.4-26 6A.4-27 6A.4-28 6A.4-29 6A.4-30 6A.4-31 6A.4-32 6A.4-33 17 27 17 0 0 0 17 17 17 17 0 RO RO 0 17 0 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO F 6A.4-34 F 6A.4-35 F 6A.4-36 F 6A.4"37 F 6A.4-38 F 6A.4-39 F 6A.4-40 F 6A.4-41 F 6A.4-42 F 6A.4-43 F 6A.4-44 F 6A.4-45 F 6A.4-46 F 6A.4-47 F 6A.4-48 F 6A.4-49 F 6A.4-50 F 6A.4-51 F 6A.4-52 F 6A.4"53 F 6A.4-54 F 6A.4-55 F 6A.4-56 F 6A.4-57 6A.5-1 6A.5-2 6A.5-2a 6A.5-2b 6A.5-3 6A.S-3a 6A.5-3b 6A.5-4 6A.5-4a 6a.5-4b 6A.5-5 6A.5-6 T 6A.5-1 T 6A.5-2 S}1 1 S}1 2 T 6A.5-3 T 6A.S-4 Sh 1 S}l 2 T 6A.5-5 RO RO RO RO 0 RO , RO RO RO 0 0 0 RO RO Rl RO 21 25 21 21 21 21 21 21 0 5 7 5 7 7 7 7 7 7 7 0 26 26 26 23 24 7 7 T 6A.5-6 S}1 1 S}l 2 T 6A.5-7 T 6A.5-8 S}l 1 S}l 2 F 6A.5-1 F 6A.5-2 F 6A.5-3 F 6A.5-4 F 6A.5-5 F 6A.5-6 F 6A.5-7 F 6A.5-8 F 6A.5-9 F 6A.5-10 F 6A.5-11 F 6A.5-12 F 6A.5-13 F 6A.5-14 F 6A.5-15 F 6A.5-16 F 6A.5-17 F 6A.5-18 F 6A.5-19 F 6A.5-20 F 6A.5-21 F 6A.5-22 F 6A.5-23 F 6A.5-24 F 6A.5-25 F 6A.5-26 F 6A.5-27 F 6A.5-28 F 6A.5-29 F 6A.5-30 F 6A.5<<31 F 6A.5-32 F 6A.5-33 F 6A.5-34 F 6A.5-35 F 6A.5-36 F 6A.5-37 F 6A.5-38 F 6A.5-39 24 7 7 7 7 0 0 0 0 0 0 0 0 0 0 0 23 0 0 0 0 0 0 0 16 0 0 0 0 0 23 23 23 23 23 23 0 23 23 0 0 23 23 23 USAR Revision 1 DAR-3 October 1989

Nine Mile Point Vnit 2 DAR LIST OF EFFECTIVE PAGES Page T=Table~F=Pi ure F 6A.5-40 F 6A.5-41 F 6A.5-42 F 6A.5-43 6A.6-1 6A.6-2 6A.6-3 6A.6"4 T 6A.6-1 T 6A.6-2 Sb 1 Sh 2 F 6A.6-1 F 6A.6-2 F 6A.6-3 F 6A.6-4 Sh 1 S}1 2 F 6A.6-5 F 6A.6-6 F 6A.6-7 6A.7-1 6A.7-2 6A.7-3 6A.7-4 6A.7-5 6A.7-5a 6A.7-5b 6A.7-6 6A.7-7 T 6A.7-1 T 6A.7-2 F 6A.7-1 6A.8"1 6A.8-2 6A.9-1 6A.9-2 6A.9-3 6A.9-4 6A.9-4a 6A.9-4b 6A.9-5 Amendment Number 23 23 23 23 0 0 26 0 23 23 23 RO 0 0 0 7 0 0 23 7 7 23 23 0 23 0 0 0 0 RO RO RO 27 Page T=Table~P=Fi ure 6A.9"6 6A 9-7 6A.9-8 6A.9-9 6A.9-9a 6A.9"9b 6A.9-10 6A.9-11 6A.9-11al 6A.9-llbl 6A.9-lla 6A.9-11b 6A.9-11c 6A.9-11d 6A.9-11e 6A.9-1lf 6A.9-12 T 6A.9"1 T 6A.9-2 T 6A.9-2a T 6A.9-2b T 6A.9-3 T 6A.9-4 T 6A.9-5 T 6Ae9-6 T 6A.9-7 F 6A.9-1 F 6A.9-2 F 6A.9-3 6A.10-1 6A.10-2 6A.10-3 6A.10"4 6A.10-5 6A.10-6 6A..10-7 6A.10-8 6A.10-9 6A.10-9a 6A.10-9b 6A.10-10 T 6A.10-1 T 6A.10-2 S11 1 Sjl 2 Amendment Number RO RO 20 20 20 20 20 20 20 20 9 9 9 9 9 9 23 Rl RO RO RO RO RO RO RO RO 23 23 23 Rl RO 21 22 21 21 21 21 RO 24 24 RO RO RO RO Page T=Table~FPi ure T 6A.10-3 T 6Ae10-4 T 6A.10-5 T 6A.10"6 T 6A.10-7 T 6A.10-8 T 6A.10-9 F 6A.10-1 F 6A.10-2 F 6A.10"3 F 6A.10-4 F 6A.10-5 F 6A.10-6 F 6A.10-7 F 6A.10-8 F 6A.10-9 F 6A.10-10 F 6A.10-11 F 6A.10-12 F 6A.10-13 F 6A.10-14 F 6A.10-15 F 6A.10-16 F 6A.10-17 F 6A.10-18 F 6A.10-19 F 6A.10-20 Amendment Number 21 21 21 21 Rl 21 21 21 RO RO RO RO RO RO RO RO RO Rl Rl Rl 22 22 22 22 22 22 22 USAR Revision 1 DAR-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES APPENDIX R REVIEW SAFE SHUTDOWN ANALYSIS APPENDIX 98 Page T=Table~F=Fi ure 98-i 98-ia 98-ib 98-ii 98-iii 98-iv 98.1-1 98.2-1 98'-2 98.2-3 98.3-1 98'-1 98.4-2 98.4-3 98.4-4 98.4-5 98.4-6 98.4-7 98.4-8 F 98.4-1 F 98.4-2 98.5"1 98.5-2 98.5-3 98.5-4 98'-5 T 98.5-1 98.6-1 98.6-2 98.6-3 98.6-4 T 98.6-1 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 T 98.6-2 Amendment Number 24 24 23 RO 244 23 RO 4 4 23 4 22 4 4 22 4 4 4 22 22 RO 4 4 21 23 RO 22 11 25 11 28 28 RO RO RO RO 11 Page" T=Table~F=Fi ure T 98'-3 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 sh 6 Sh 7 Sh 7a S}1 8 Sh 9 F 98.6-1 F 98'-2 F 98.6-3 F 98.6-4 F 98.6-5 F 98'-6 98.7-1 98.8-1 98.8-2 98.8-3 98.8-4 98.8-5 98.8-5a 98.8-5b 98.8-6 98.8-7 T 98'-1 Sh 1 Sh la Sh 2 S}1 3 sh 4 Sh 5 Sh 5a Sh 6 S}1 7 Sh 8 Sh 9 Sh 10 Sh 11 Sh 12 Sh 13 Amendment Number 23 ll RO 11 RO 11 23 RO 28 11 4 ll ll ll ll ll 23 RO 23 Rl 23 Rl Rl RO 25 RO RO 28 11 RO 28 28 28 11 28 28 28 RO 11 RO 11 Page T=Table~F=Fi ure Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 Sh 20 Sh 21 Sh 22 Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sh 30 Sh 30a Sh 31 Sh 32 Sh 33 Sh 34 S}1 35 Sh 36 Sh 37 Sh 38 Sh 39 Sh 40 Sh 41 Sh 42 Sh 43 Sh 44 Sh 45 Sh 46 Sh 47 Sh 48 Sh 49 Sh 50 Sh 51 Sh 52 Sh 53 Sh 54 Sh 55 Sh 56 Sh 57 Amendment Number ll RO 11 11 RO 11 28 28 28 28 28 28 RO RO RO RO RO RO ll RO RO 28 28 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 ll RO RO 23 RO 19 19 USAR Revision SSA-1 October.1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table~P=Pi ure S}1 58 Sh 59 Sh 60 Sh 60a Sh 61 Sh 62 Sh 63 Sh 64 Sh 65 Sh 66 Sh 66a Sh 67 Sh 68 Sh 69 Sh 70 Sh 71 Sh 72 Sh 73 Sh 73a Sh 74 Sh 75 Sh 75a T 9B.8-2 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 6 Sh 7 Sh 8 S}1 9 Sh 10 Sh 11 Sh 12 S}1 13 Sh 14 Sh 15 Sh 16 Sh 17 Sh 18 Sh 19 Sh 20 Sh 21 Sh 22 Amendment Number RO ll RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO 28 11 28 ll 28 28 28 11 11 ll 11 ll 28 28 28 28 28 28 RO RO RO RO Page T=Table~F=Fi ure Sh 23 Sh 24 Sh 25 Sh 26 Sh 27 Sh 28 Sh 29 Sh 29a Sh 29b Sh 29c Sh 29d Sh 29e Sh 29'h 30 Sh 31 Sh 32 Sh 33 Sh 33a Sh 34 Sh 34a Sh 35 Sh 36 Sh 37 Sh 38 Sh 38a Sh 38b T 9B.8-3 Sh 1 Sh 2 Sh 3 Sh 4 Sh 5 Sh 5a S}1 6 Sh 7 Sh 8 Sh 9 Sh 10 S}1 11 Sh 12 Sh 13 Sh 14 9B.9-1 Amendment Number RO RO 28 28 28 23 23 23 23 23 23 23 23 ll ll RO 23 23 RO RO 11'3 28 RO 23 Rl 23 RO RO RO RO RO RO RO RO RO RO 23 RO Rl RO RO Page T=Table~F=Fi ure 9B.10-1 9B.ll-l 9B.12-1 9B.12-2 9B.12-3 9B.12-4 9B.12-5 9B.12-6 9B.12-7 9B.12-8 9B.12-9 9B.12-10 9B.12-11 Amendment Number RO 21 RO RO RO RO RO RO RO RO RO RO RO USAR Revision SSA-2 October 1989 f 0 I>' Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume 5.3 Reactor Vessel 5.4 Component and Subsystem Design Appendixes 5A, 5B 13 13 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 6.2 6,3 6.4 6.5 6.6 Appendixes 6A through 6C Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 13 14 15 15 15 15 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 7.2 7'7.4 7.5 7.6 7~7 Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls.Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS 16 16 16 16 i 17 17 17 9.1 9.2 9.3 9'9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 18 19 20,21 21,22 23 USAR Revision 0 April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 23 10.1 10.2 10.3 10.4 Summary, Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System 23'23 24 11.1 11.2 11.3 11.4 11.5 Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems Appendix 11A CHAPTER 12 RADIATION PROTECTION CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 24 24 25 25 25 25 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26, 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR CHAPTER 1 LIST OF FIGURES Figure Number 1.1-1 1.2-1 1.2-2 1.2-3 1.2-4 1.2-5 Title HEAT BALANCE AT RATED POWER PLOT PLAN STATION ARRANGEMENT DELETED DELETED DELETED 26 1.2-6 Sjl.1 l.2-6 S}1.2 1.2-7 1.2-7 SI1.2 1.2-8 S11.1 1.2-8 Sjl.2 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EK 175'-0" AND 188.'-6" GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EK 196'-0" GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EL 215'-0~~GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EK 240'-0" GENERAL ARRANGEMENT, REACTOR BUILDING PLAN-EL 261'-0" AND MISCELLANEOUS GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EL 215'-0" AND MISCELLANEOUS 1.2-9 S11.1 GENERAL ARRANGEMENT, REACTOR BUIKDING PLAN EL 289'-0" 1.2-9 Sh.2 1.2-10 Sh.1 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EL 306'-0" GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EL 328'-10" 1.2-10 Sh.2 GENERAL ARRANGEMENT, REACTOR BUILDING PEAN EL 353'-10" Amendment 26 1-vii May 1986 Nine Mile Point Unit 2 FSAR CHAPTER 1 LIST OF FIGURES (Cont)Figure Number Title 1.2-11 1.2-12 1.2-13 1.2-14 1.2-15 1.2-16 1.2-17 1.2-18 GENERAL ARRANGEMENT, REACTOR BUILDING SECTIONS (SHEETS 1 THROUGH 4)GENERAL ARRANGEMENT, REACTOR BUILDING SECTION 2-2 1 GENERAL ARRANGEMENT, RADWASTE BUILDING PLAN EL 261'0", 270'9 I'ND 309'0" (SHEETS 1 THROUGH 3)GENERAL ARRANGEMENT, RADWASTE BUILDING SECTIONS GENERAL ARRANGEMENT, CONTROL ROOM PLAN EL 360'-0" I 288'-6" I 261'-0" (SHEETS 1 THROUGH 3)GENERAL ARRANGEMENT, CONTROL BUILDING GENERAL ARRANGEMENT, EMERNGECY DIESEI GENERATOR BUILDING PLAN (SHEETS 1 THROUGH 6)GENERAL ARRANGEMENT, EMERGENCY DIESEL GENERATOR BUILDING SECTIONS 1.2-19 1.2-20 1.2-22'" I 1.2-23 1.2-24 GENERAL ARRANGEMENT, TURBINE BUILDING PLAN EL 250'-0" (SHEETS 1 AND 2)GENERAL ARRANGEMENT, TURBINE BUILDING PLAN EL 277'-6" (SHEETS 1 AND 2)GENERAL ARRANGEMENT, TURBINE BUILDING PLAN EL 306'-6" (SHEETS 1 AND 2)GENERAL ARRANGEMENT, TURBINE BUILDING SECTION 1-1 (SHEETS 1 AND 2)GENERAL ARRANGEMENT, TURBINE BUILDING PLAN SECTION 2-2 AND 4-4.(SHEETS 1 AND 2)GENERAL ARRANGEMENT, TURBINE BUiLDING PLAN SECTION 3-3 Amendment 24 1 Viii February 1986 .Nine Mile Point Unit 2 FSAR CHAPTER 1 LIST OF FIGURES (Cont)Figure Number Title 1.2-25 GENERAL ARRANGEMENT, TURBINE BUILDING PLAN SECTION 5-5 1.2-26 1.2-27 1.2-28 1.2-29 1.2-30 1~2-31 1.2-32 1~2 3 3 1.2-34 1.2-35 1.2>>36 1~2 3 7 1.2-38 GENERAL ARRANGEMENT, SCREENWELL BUILDING WATER TREATMENT AND SERVICE WATER PUMPS PLAN (SHEETS 1 AND 2)GENERAL ARRANGEMENT, SCREENWELL BUILDING WATER TREATMENT AND SERVICE WATER PUMPS PLAN SECTION (SHEETS 1 AND 2)GENERAL ARRANGEMENT, SCREENWELL BUILDING WATER TREATMENT AND,SERVICE WATER PUMPS PLAN SECTION GENERAL ARRANGEMENT AND DETAILS, INTAKE AND DISCHARGE TUNNELS (SHEETS 1 THROUGH 3)GENERAL ARRANGEMENT AND DETAILS, INTAKE STRUCTURE GENERAL ARRANGEMENT AND DETAILS, MAIN STACK GENERAL ARRANGEMENT, NORMAL SWITCHGEAR BUILDING PLANS (SHEETS 1 THROUGH 3)GENERAL ARRANGEMENT, NORMAL SWITCHGEAR BUILDING GENERAL ARRANGEMENT, AUXILIARY BOILER HOUSE GENERAL ARRANGEMENT, STANDBY GAS TREATMENT BUILDING EL 261'-0" GENERAL ARRANGEMENT, STANDBY GAS TREATMENT BUILDING AND RAILROAD ACCESS IOCK SECTION GENERAL ARRANGEMENT, CONDENSATE STORAGE TANK BUILDING (SHEETS 1 AND 2)COOLING TOWER FILL LEVEL PLAN AND SECTION Amendment 24 1-ix February 1986 Nine Mile Point Unit.2 FSAR CHAPTER 1 LIST OF FIGURES (Cont)Figure Number 1.2-39 1.2-40 1.7-1 1.7-2 1.7-3 1.7-4 1.8-1~Title COOLING TOWER SECTION BELOW THE FILL LEVEL GENERAL ARRANGEMENTi HYDROGEN STORAGE AREA PIPING AND INSTRUMENTATION DIAGRAM (SWEC)(SHEETS 1 THROUGH 5)PIPING AND INSTRUMENT SYMBOLS (GE)LOGIC DIAGRAMS SYMBOLS (SWEC)(SHEETS 1 AND 2)ELECTRICAL'NE-LINE DIAGRAMS SYMBOLS (SWEC)ENGINEERED SAFETY-FEATURE FILTER DRAIN ARRANGEMENT 1.10-1 1.10-2 1.10,-3 1.10-4 DELETED DELETED DELETED DELETED USAR Revision 0 1-x April 1989 Nine Mile Point Unit 2 FSAR TABLE 1.8-1 (Cont)Re ulator Guide 1.23 Revision 0 Februar 1972 Onsite Meteorological Program FSAR Section 2.3.3 Position Niagara Mohawk Power Corporation complies with Regulatory Guide 1.23 (Safety Guide 23)(February, 1972).However, the wind speed sensor in use at the 200-ft level until July 1982 did not meet the requirements of the guide.The new sensor installed after July 1982 has the starting speed and ac-curacy specified by the Regulatory Guide.The severe weather conditions encountered at Nine Mile Point lead to the choice of the very rugged wind speed sensor in-stalled in November 1972.It had a starting speed of about 2.6 mph and would continue to operate with speeds of 1 to 1.5 mph.The wind speed accuracy is+1.0 mph above 10 mph as opposed to,the Regulatory Guide 1.23 Criterion I 0.5 mph for all)wind speeds.More sensitive wind speed sensors available at that time were prone to icing and physical damage from high wind speeds.24 of 169

Nine Nile Point Unit 2 FSAR TABLE 1.8-1 (Cont)Re lator Guide 1.58 Revision 1 Se tember 1980 Cont 3.5.2 Level II One year of satisfactory performance as Level I or 5 years related experience in the corresponding inspection, examination, or test category or class, or 2.High school graduation/GED equivalent plus 3 years of related experience in equivalent inspection, examination, or testing activities, or 3.Completion of college-level work leading to an as-sociate degree in a related discipline plus 1 year related experience in equivalent inspection, examination, or testing activities, or 4.-Four-year college graduate plus 6 months of related experience in equivalent inspection, examination, or testing activities. 3.5.3 Level III Six years of satisfactory performance as a Level II or 15 years of related experience in the cor-responding inspection, examination, or test category or class, or 2.High school graduate/GED equivalent plus 10 years of related experience in equivalent inspection, examination, or testing activities; or high school graduation plus 8 years experience in equivalent inspection, examination, or testing activities, with at least 2 years as Level II, and with at'least 2 years associated with nuclear facilities or if not, at least sufficient training to be ac-quainted with the relevant quality assurance aspects of a nuclear facility, or 3.Completion of college level work leading to an as-sociate degree and 7 years of related experience in equivalent inspection, examination, or testing activities, with at least 2 years of this ex-perience associated with nuclear facilities, or if not, at least sufficient training to be acquainted 65 of 169 0-Nine Mile Point Unit 2 FSAR TABLE 1.8-1 (Cont)Re ulator Guide 1.58 Revision 1 Se tember 1980 Cont with the relevant quality assurance aspects of a nuclear facility, or Four-year college graduate plus 5 years of related experience in equivalent inspection, examination, or testing activities, with at least 2 years of this experience associated with nuclear facilities -or if not, at least sufficient, training to be acquainted with the relevant quality assurance aspects of a nuclear facility.5.Graduate degree plus 3 years of related experience in equivalent inspection, examination, or testing activities, with at least 2 years of experience as-sociated with nuclear facilities or, if not, at least sufficient training to be acquainted with the relevant quality assurance aspects of a nuclear facility.NMPC The NMPC quality assurance program for Unit 2 is currently in compliance with Regulatory Positions C.5, 6, 7, 8, and 10 of Regulatory Guide 1.58, Revision 1.NSSS General Electric startup operations personnel qualifications meet the requirements of this guide as described below: 1.Personnel are selected and trained according to the criteria of ANSI N18.1-1971 (NRC.Regulatory Guide 1.8), with the exception of NRC Licensing. 2.The Operations Manager meets the equivalent of ANSI N18.1, Paragraph 4.2.2, Operations Manager.The Operations Manager is normally present for preoperational testing, and will therefore be qualified at the time that preoperational testing is begun.3.The Operations Superintendent meets the equivalent of ANSI N18.1, Paragraph 4.3.1, Supervisors Requiring NRC Licenses.The Operating Superinten-66 of 169

Nine Mile Point Unit 2 FSAR TABLE 1.8-1 (Cont)Re lator Guide 1.58 Revision 1 Se tember 1980 Cont dent will normally be present for preoperational testing and therefore will be qualified at the time preoperational testing is begun.The Shift Superintendents meet the qualification of ANSI N18.1, Paragraph 4'.1, Supervisors Requiring NRC Licenses.5.The Lead Startup Test Design and Analysis Engineer meets the qualifications of ANSI.N18.1, Paragraph 4.4.1, Reactor Engineering and Physics.He will be qualified at the time of initial core loading or appointment, to the position.His onsite responsibilities begin just prior to fuel loading.6.The Startup Test Design and Analysis Engineers meet the qualifications of ANSI N18.1, Paragraph 3.3, Reactor Technical support personnel. Their onsite responsibilities begin just prior to fuel loading.7.The Startup Control and Instrumentation Engineer meets the qualifications of ANSI N18.1, Paragraph 4.4.2, Instrumentation and Control.He will be qualified at the time preoperational test-ing is begun.8.The Startup Chemist meets the qualifications of ANSI N18.1, Paragraph 4.4.3,.Radiochemistry, utilizing cumulative experience from several reac-tor startup programs.He will be qualified at the time of the initial core loading.67 of 169

Nine Mile Point Unit 2 FSAR TABLE 1.8-1 (Cont)Re lator Guide 1.108 Revision 1 Au ust 1977 Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at, Nuclear Power Plants FSAR Sections 8.3.1.2, 14.2 Position The Unit 2 project complies with'the Regulatoxy Position (Paragraph C)of this guide.The IEEE 387-1977 (Section 3.7)definitions of Continuous Rating and Short-Time Rating are applied to the diesel generator continuous rating and 2-hour rating referred to in Section C.2.a.3 of the Regulatory Guide.Section 3/4.8 of the Technical Specifications details the periodic testing requirements of the diesel generator units.26 Amendment 26 122 of 169 May 1986

Nine Mile Point Unit 2 CESAR TABLE 1.8-1 (Cont)Re lator Guide 1.134 Revision 1 March 1979 Medical Evaluation of Nuclear Power Plant Personnel Requiring Operating Licenses FSAR Section Chapter 13 Position The Unit 2 project complies with the Regulatory Position (Paragraph C)of this guide.The medical requirements for personnel requiring operator licenses, as detailed in ANSI N546-1976 and endorsed by this guide will be implemented by Site Administrative Procedures. 149 of 169

Nine Mile Point Unit, 2 FSAR The staff realizes that the necessary knowledge and experience can be gained in a variety of ways.Consequently, credit for equivalent experience should be given to applicants for SRO licenses.Applicants for SRO licenses at a facility may obtain their 1 yr operating experience in a licensed capacity (Operator or Senior Operator)at another nuclear power plant.In addition, actual operating experience in a position that is equivalent to a Licensed Operator or Senior Operator at military propulsion reactors will be acceptable on a one-for-one basis.Individual applicants must document this experience in their individual applications in sufficient detail so that the staff can make a finding regarding equivalency. Applicants for SRO licenses who possess a degree in engineering or applicable sciences are deemed to meet the above requirement, provided they meet the requirements set forth in Sections A.l.a and A.2 in enclosure 1 in the letter from H.R.Denton and all power reactor applicants and licensees, dated March 28, 1980, and have participated in a training program equivalent to that of a cold Senior Operator Applicant. The NRC has not imposed the 1-yr cold applicants for SRO licenses.work on a facility not yet in programs are designed to supply experience not available to them.experience requirement on Cold applicants are to operation; their training the equivalent of the Nine Mile Point Unit 2 Position The Upgrading of Operator Training and Senior Operator Training for Unit 2 is being performed as described-in Section 13.2 of the FSAR.This is also in accordance with the Site Administrative Procedures. 1.10-15 Nine Mile Point Unit 2 FSAR I.A.2.3 ADMINISTRATION OF TRAINING PROGRAMS FSAR Cross Reference Section 13.2.1 NUREG-0737 Position Pending accreditation of training institutions, licensees and applicants for operating licenses will assure that training center and facility instructors who teach-systems, integrated responses, transient, and simulator courses demonstrate SRO qualifications and are enrolled in appropriate requalification programs.The above position is a short-term position.In the future, accreditation of training institutions will include review of, the procedure for certification of instructors. The certification of instructors may or may not include successful completion of a Senior Operator examination. The purpose of the examination is to provide the NRC with reasonable assurance during the interim period that instructors are technically competent. The requirement is directed to permanent members of the training staff who teach the.subjects enumerated above, including members of other organizations who routinely conduct training at the facility.There is no intention to require guest lecturers who are experts in particular subjects (reactor theory, instrumentation, thermodynamics, health physics, chemistry, etc)to successfully complete a Senior Operator examination. Nor do we intend to require a system expert, such as the Supervisor-Instrument and Control Maintenance teaching the rod control"drive system to sit for a Senior Operator examin-ation.The use of guest lecturers should be limited.Nine Mile Point Unit 2 Position Training center and facility instructors who teach systems, integrated responses, transient, and simulator courses presently hold SRO licenses on Unit 1 and, as such, are enrolled in operator requalification programs, as outlined in site administrative procedures. The qualification of the training instructors meets the requirements of this task, as described in Section 13.2 of the FSAR.USAR Revision 0 1.10-16 April 1989 Nine Mile Point Unit 2'FSAR II.K.3.22 RCIC SUCTION SOURCE FSAR Cross Reference Sections 5.4.6, 7.4 NUREG-0737 Position The reactor core isolation cooling (RCIC)system takes suc-tion from the condensate storage tank with manual switchover to the suppression pool when the condensate storage tank level is low.This switchover should be made automatically. Until the automatic switchover is implemented, licensees should verify that clear and cogent procedures exist for the manual switchover of the RCIC system suction from the con-densate storage tank to the suppression pool.Nine Mile Point Unit 2 Position The Unit 2 project has implemented the NRC position to automatically transfer RCIC suction source.Condensate storage tank low water inventory automatically initiates transfer of the suction of the RCIC pump to the suppression pool.The modification of the RCIC system allows automatic switchover of pump suction from the condensate storage tank to the suppression pool if the condensate storage tank falls to a preset low level.Low level in the tank is monitored by two redundant level transmitters. If either transmitter senses low level, pump suction is automatically transferred to the suppression pool.These are different transmitters/trip units from those that activate switchover for the HPCS system.The condensate storage tank suction valve will be signaled to close upon opening of the suppression pool suction valve.The P&ID, Figure 5.4-9, and elementary diagram have been revised to reflect a relocation of the transmitter to the pump suction line.USAR Revision 0 1.10-93 April 1989 Nine Mile Point Unit 2 FSAR II.K.3.24 RCIC AND HPCI SUPPORT POWER'SAR Cross Reference Section 9.4 NUREG-0737 Position Long-term operation of the reactor core isolation cooling (RCIC)and high pressure coolant injection (HPCI)systems may require space cooling to maintain the pump room tem-peratures within allowable limits.Licensees should verify the acceptability of the consequences of a complete loss of ac power.The RCIC and HPCI systems should be designed to withstand a complete loss of offsite ac power to their sup-port, systems, including coolers, for at least 2 hr.Nine Mile Point Unit 2 Position The Unit 2 ECCS design employs a cubicle arrangement to en-sure physical, electrical, and environmental separation of each portion of the ECCS.The RCIC system is also located within a separate cubicle.The HPCS,pump room is cooled by either of two fully redundant Category I unit space coolers.The remaining ECCS pump rooms and the RCIC pump room are each cooled by one Category I unit space cooler with an ad-ditional cooler provided as a spare.These coolers are part of the reactor building heating, ventilation, and air con-ditioning (HVAC)system which utilize cooling water from the service water (SWP)system.The safety-related portions of the SWP system are powered from the standby diesel generators .following a loss of offsite power;therefore a reliable supply of cooling water is provided., Likewise, the control systems involved in the operation of the unit coolers also receive their power from the diesel generators following a loss of offsite power.This design assures that.the pump room temperatures are maintained within normal limits for an indefinite period following a complete loss of offsite power.1.10-94 Nine Mile Point Unit 2 FSAR'ABLE III.D.3.4-1 RESULTS OF TOXIC CHEMICAL ANALYSIS FOR THE CONTROL ROOM HABITABILITY STUDY Chemical Location J.A.FitzPatrick Plant Alcan Route 104 Nine Mile Point Unit 1 Nine Mil'e Point Unit 2 Oswego Wire Incorporated USAR Revision 0 Chemical N~Hq SOCO~Propane Halon Cl~Propane Nq Hcl CO~Hcl N~CO~Nq COq Hq SOHcl Halon Hq SOCO~Halon 1301 N~Isopropyl Alcohol Nq Propane H~SOMaximum Control Room Concentration (m'1.2 6.6 x 10 6.2 1.29 1.73 0.038 1.1 0.09 0.003 2.5 x 10 0.009 0.54 0.0 22.2 14.7 1.3 x 0.009 0.57 6.6 x 10 4 46.8 3.88 32.1 2.2 x 10 4 1.2 x 10 2.1 x 10 1.0 x 10 1.10-133 Toxic Limit (m'74-0.002 54.8 43.1 0.045 43.1 274 0.05 54.8 0.050 274 54.8 274 54.8 0.002 0.05 432 0.002 54.8 432 274 1.2 274 43.1 0.002 Allowable Time Period (min 15 2 15 15 2 15 15 15 2 15 15 2 15 15 2 15 15 2 15 15 15 15 15 15 2 April 1989 h Nine Mile Point Unit 2 FSAR In addition to the load combination requirement for the con-tainment design, there is a.fatigue analysis requirement for the liner of a concrete containment. For steel containment, the consideration of fatigue is specified in ASME Boiler and Pressure Vessel Code Section III, Division 1, Subsection NE.However, the liner on the concrete foundation mat.of the steel containment should be treated as the liner of a con-crete containment. Since the staff's position requires the pool liner to be designed in accordance with the ASME BEcPV Code Section III, Division 1, Subsection NE, it is suggested that a generic method to consider fatigue of both the steel containment and the steel liner in the concrete containment should be adopted.Position The absolute sum method of combining dynamic loads is used for the design of structures. The details of load com-binations used in designing the structures are covered in FSAR Section 3.8.The Unit 2 primary containment liner is evaluated for fatigue to the requirements of ASME Boiler and Pressure Ves-sel Code Section III, Division 1, Subsection NE.LICENSING ISSUE: 43-FLUID/STRUCTURE INTERACTION Issue The dynamic forcing functions for various loads have been established through testing on models that are generally more stiff than the actual structures to which the loads will be applied.By directly applying such forcing func-tions to actual structures in the analysis, the interactive effect between the fluid mass and the structure is neglected. Under certain conditions, this effect may be significant. It is proposed that a generic approach to study such effects should be established. Position This issue is not directly applicable to the Unit 2 Mark II containment. Since the Unit 2 containment is stiff in the suppression pool ,region and the dynamic forcing functions are conservatively defined, any interactive effect between the fluid mass and the structure is inherently included.Amendment 3 1.12-31 June 1983 Nine Mile Point Unit 2 FSAR LICENSING ISSUE 44-LONG-TERM POST-LOCA OPERABILITY OF DEEP-DRAFT ECCS PUMPS Issue IE Bulletin 79-15, dated July 1979, identified problems with deep-draft ECCS pumps that could threaten their long-term post-LOCA operability. Structure flexibility; shaft/column misalignment; vibrational frequencies near rotation speeds;inlet flow induced vortices;and dimensional deficiencies such*as those discovered with certain LaSalle ECCS pumps, could cause excessive vibration and bearing wear.The NRC staff has asked applicants to define programs and provide data that compare the expected service life with the ac-cumulated operating time and confirm the long-term operability. Position There are five safety-related deep draft pumps utilized in the Unit 2 design.These are three residual heat removal pumps, one low pressure core spray pump, and one high pres-sure core spray pump.The inherent design features of the Byron Jackson ECCS pumps in Unit 2 preclude excessive vibration and bearing wear.Each pump is supplied with a casing or suction barrel and is not installed in a wet sump.They do not have long, limber columns;the longest pump is only 24 ft, compared to the 30-to 160-ft pumps described in IE Bulletin 79-15.Also the pump assembly rigidity is enhanced by seismic rings between the assembly and the barrel.The pumps use a double-suction first stage to provide stability over a wide range of flows.Column frequencies are well removed from pump speed.Larger diameter barrels provide low flow velocities around pump inlets, and ring seismic restraints 'ct as flow straighteners to suppress vortex formation. The pumps have high-precision, keyed, sleeve-type couplings. An NRC letter dated December 8, 1983, requested additional information on methods used to qualify long-term operability of deep draft pumps.The following is a description of the method used.Long-term operability has been considered in the emergency core cooling system (ECCS)pump-design.The ECCS pumps'ffectiveness is evaluated by acceptance, qualification, and in-plant testing.Long-term operability is assured by preventive maintenance, functional testing and surveil-lance," and vibration monitoring. Scheduled preventive maintenance consists of resistance readings of motor windings;lubrication of critical rotating components; general cleaning and inspection of rotating electrical equipment; and inspection, overhaul, alignment, and adjust-USAR Revision 0 1.12-32 April 1989 Ni.'ne Mile Po'int Unit 2 FSAR ment of impeller lift.Functional-testing measurements of each pump's inlet pressure, differential pressure, flow rate, and vibration as prescribed by Section XI of the ASME B&PV Code and applicable addenda, as required by 10CFR50.55a, provide data for engineering analysis to identify per-formance.changes or trends.In addition, vibrati'on data bases, established during the ,preoperational/startup testing, are compared with functional-testing vibration data to monitor journal bearing wear and shaft whip.Functional testing and surveillance requirements are speci-fied in Unit 2 Technical Specifications, surveillance procedures, and inservice inspection (ISI)programs.Preventive maintenance and surveillance testing are sche-duled at periodic intervals as the ISI program test results indicate.As part of the Unit 2 plant ISI programs, vibration measurements will be taken in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50.55a. The data will be evaluated on a scheduled basis to predict potential bearing and journal failures and establish replacement schedules. Data will be available onsite for inspection. Vibration should be limited to 0.3 in/sec velocity peak-to-peak over all measured frequencies, as measured by an IRD 360 or equivalent equipment, when the motor and pump are operated as a unit over the normal design range of pressure and flow.This limit is based on normal operation. Higher momentary increases may be acceptable during starting or at shutoff.This limit is not based on what the equipment can withstand. The equipment damage threshold is higher: close to 0.020 inch, momentary and not sustained. Any sustained vibration over 0.3 in/sec may cause extensive bearing wear.These deep draft pumps, due to their relative shortness, demonstrate fewer of the problems associated with longer pumps.The hydraulic design has been developed over the last 40 years of experience in many applications. The ECCS pumps contain design features to preclude failure of the impellers, impeller staking, shafts, bearings, wear rings, couplings, and stuffing boxes.The design includes ,safety factors (loading criteria)based on the expected pressures, temperatures, and loadings defined in the design speci'fication. Lateral restraints are included in the pump to control deflections. Tolerances assuring alignment of the shaft and pumping elements are verified by design calculations. Motor shaft deflections within tolerance are predicted in a static seismic analysis and are verified by a qualification test of a similar motor.A dynamic analysis of the pump and motor is performed to determine USAR-Revision 0 1.12-32a April 1989 Nine Mile Point Unit"2 FSAR.resonances and predict loadings throughout the pump and motor.Tests are performed on each pump delivered. The tests include head versus flow, NPSH, and vibration monitoring. The assembled pumps are checked for proper assembly and low friction by hand turning (rotating) the shaft.Each pump is run for a total of 100 hr during testing.A qualifica-tion test of a similar pump motor was performed. This data provides qualification of the Unit 2 pumps motors by a similarity analysis.USAR Revision 0 1.12-32b April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume 5.3 Reactor Vessel 5.4 Component and Subsystem Design Appendixes 5A, 5B 13 13 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes 6A through 6C Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 13 14 15 15 15 15 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 7'7'7.4 7.5 7.6 7~7 Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety'ontrol Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A ELECTRIC POWER Introduction Offsite Power System Onsite Power System 16 16.16'16, 17 I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water'Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 ,18 19 20,21 21,22 23 USAR Revision 0 April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont:)Section CHAPTER 10 10.1 10.2 10.3 10.4 CHAPTER 11 Title STEAM AND POWER CONVERSION SYSTEM Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT Volume 23 23 23 2411.1 11.2 11.3 11.4 11.5 Appendix 11A Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25-CHAPTER 12 RADIATION PROTECTION 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)iv 26 Nine Mile Point Unit 2 FSAR CHAPTER 2 LIST OF TABLES'able Number Title 2~1 1 MINIMUM DISTANCE BY SECTOR BETWEEN RESTRICTED AREA BOUNDARY AND ROUTINE RELEASE POINTS 2.1-2 2~1 3 2.1-4 2.1-5 2.1-6 2~1 7 2.1-8 2.1-9 2.1-10 2.1-11 2.1-12 2~1 1 3 2.1-14 2.1-15 2.1-16 2'-17 2.1-18 1980 POPULATION AND POPULATION DENSITIES FOR TOWNS AND CITIES WITHIN 16 KM (10 MI)OF UNIT 2 1970-1980 POPULATION GROWTH FOR TOWNS AND CITIES WITHIN 16 KM (10 MI)OF UNIT 2 DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED POPULATION CENTERS WITH OVER 25,000 PEOPLE IN 1980 Amendment 7 2-iz December 1983 Nine Mile Point Unit 2 FSAR CHAPTER 2 LIST OF, TABLES (Cont)Table Number Title 2.1-19 2.1-20 2.1-21 2.1-22 2.2-1 2.2-2 2~2 3 2.2-4 DELETED DELETED DELETED DELETED DAILY TRAFFIC, VOLUME OF.COUNTY HIGHWAYS IN THE VICINITY OF UNIT 2 1978 FREIGHT TRAFFIC FOR LAKE ONTARIO AROUND OSWEGO HARBOR INDUSTRIAL FIRMS WITHIN 8 KM (5 MI)OF UNIT 2 ARMY CORPS OF ENGINEERS HAZARDOUS MATERIAL COMMODITY DESIGNATION FOR RATERBORNE COMMERCE 2.2-5 2.2-6 2~2 7 2.2-8 2.2-9 2.3-1 2.3-2 HAZARDOUS MATERIALS STORED/USED BY INDUSTRIES WITHIN 8 KM (5 MI)1978 LAKE ONTARIO CARGO TRANSPORT FOR OSWEGO HARBOR SOURCES OF TOXIC CHEMICALS WITHIN 8 KM (5 MI)OF UNIT 2 SITE PREDICTED VAPOR CONCENTRATIONS IN THE UNIT 2 CONTROL ROOM INPUT DATA FOR VAPOR RUN DESIGN BASIS TORNADO PARAMETERS VERTICAL PROFILE OF THE 100-YEAR RECURRENCE INTERVAL FASTEST MILE OF WIND Amendment, 24 2-x February 1985 Nine Mile Point Unit 2 FSAR 2.2 NEARBY INDUSTRIAL, TRANSPORTATION, AND MII ITARY FACILITIES 2.2.1 Locations and Routes Only one manufacturing or industrial plant, Alcan Aluminum Corporation's Alcan Sheet and Plate Division, is located within 8 km (5 mi)of Unit 2.There are also two electrical power generation facilities, the J.A.FitzPatrick Nuclear Power Plant operated by NYPA and Nine Mile Point Unit 1 operated by Niagara Mohawk Power Corporation, located within 8 km (5 mi)of Unit 2.Figure 2.1-2 shows the location of these two facilities relative to Unit 2.The principal products of the Alcan Aluminum Corporation plant are aluminum sheet and plate.There are no chemical plants, refineries, military bases, or underground gas storage facilities within 8 km of the plant.In addition, no pipeline or fuel storage facilities lie within the 8-km radius except those storage facilities associated with the Alcan plant, the FitzPatrick plant, and Nine Mile Point Units 1 and 2.Finally, there are no hazardous waste storage or disposal sites permitted by the state in the 8-km radius from the plant.Major transportation facilities are shown on Figure 2.2-1.The principal roadway within 8 km of Unit 2 is U.S.Route 104 which passes 6.2 km (3.9 mi)south of the plant and connects the city of Oswego and Mexico Village.Daily traffic volume for U.S.Route 104 was 5,841 vehicles in 1979.Highway access to the site is via two county routes, Route lA to the southwest and Route 29 to the east.A private east-west road crosses the site and connects these two county routes.Other local roads in the, vicinity generally had average daily traffic counts of fewer.than 2,000 vehicles in 1978-1979, the most current survey dates.Table 2.2-1 presents daily traffic volume counts for county highways within 8 km of the plant.One railroad company, Consolidated Rail Corporation (Conrail), transports freight in the vicinity, of the plant.The rail lines and spurs serving Unit 2, as well as the J.A.FitzPatrick plant and Nine Mile Point Unit 1, are shown on Figure 2.1-2.The closest rail line to Unit 2 is the Oswego-Mexico branch of Conrail located approximately 2.5 km (1.5 mi)from the Nine Mile Point site.This branch line has daily service on demand and averages one train daily, 5 days a week.A rail spur was constructed to serve Unit 2 during construction and operation of theplant.Possible Amendment 19 2.2-1 May 1985 Nine Mile Point Unit 2 FSAR r sources of traffic or hazardous materials utilizing ground transportation routes within 8 km of the plant are iden-tified and detailed in Section 2.2.3.The Oswego River passes within ll to 12 km (6.6 to 7.2 mi)of Unit 2 at its nearest point and serves as a major route for waterborne commerce on Lake Ontario.Freight traffic statistics are maintained by the U.S.Army Corps of Engineers. Totals for the river section from New York State Barge Canal'Lock No.8 to the port of the City of Oswego are the only statistics applicable for the nearest reach of river to the station.Table 2.2-2 details the 1978 freight traffic for this reach of river.The Port of Oswego, the easternmost port on Lake Ontario, is located approximately ll km (6.6 mi)southwest of Unit 2 and provides a link with all ports on the Great Lakes and St.Lawrence River.Ships in normal commercial lanes bound to and from the Port of Oswego pass no closer than 11.3 km (7 mi)to the intake structures of Unit 2.Regular commercial air service is provided at the Clarence E.Hancock Airport, located 49.8 km (31 mi)southeast of Unit 2 near Syracuse, NY.The nearest flight corridor associated with this airport is 22.2 km (13.8 mi)from the Nine Mile Point Station.Light plane traffic is handled at the Oswego County Airport in the town of Volney, approximately 19.3 km (12 mi)south of the Nine Mile Point site.Lakeside Airstrip, a private facility which operates primarily as a maintenance facility, with very little air traffic, is located along Route 176 approximately 10 km (6.2 mi)south of the Nine Mile Point site.It is not anticipated that there will be any significant in-crease in the number of industrial, transportation, and military facilities located within an 8-km radius of Unit 2 over the plant lifetime.There are also no significant changes expected in the nature of existing facilities or the extent of their activities within the designated area over the projected lifetime of Unit 2.2.2.2 Description 2.2.2.1 Description of Facilities Major industrial facilities within 8 km of Unit 2 are listed in Table 2.2-3.Alcan Rolled Products, located ap-proximately 4.5 km (2.7 mi)southwest of Nine Mile Point Station, is the largest employer with approximately 1,000 workers manufacturing aluminum sheet and plating.No hazar-dous materials are manufactured within the 8-km radius.Hazardous materials stored or used are discussed in Section 2.2.2.2.The New York State Department of USAR Revision 0 202-2 April 1989 Nine Mile Point Unit 2 FSAR.Environmental Conservation records the type, amount, and route of hazardous materials carried in the state.One rail line passes through the 8-km radius.Conrail has a branch line serving Alcan Aluminum, Nine Mile Point Units 1 and 2, and the James'.FitzPatrick Nuclear Power Plant.The main line is located approximately 3.5 km (2.1 mi)at its nearest point from Unit 2.Waterborne commerce statistics prepared by the U.S.Army Corps of Engineers only partially identify specific hazardous materials on Lake Ontario.Commerce is recorded by general commodity<'~.A listing of hazardous materials identified,and their commodity designations is provided in Table 2.2-4.Hazardous materials transported by air have not been identified because of the distance of airways and facilities from Unit 2.2.2.2.2 Description of Products and Materials To identify hazardous materials regularly stored or used within 8 km of Unit 2, surveys were conducted of industrial firms, pipeline companies, and distributors that might be expected to handle toxic chemicals or explosives. Appendix 2A describes the method used to collect data regarding hazardous materials used by various industries near.the-site.Hazardous materials considered are included in Table 2.2-4.Toxic chemicals and explosives stored or used by industries or distributors in the vicinity of the station are summarized in Table 2.2-5.No pipelines or local distribution and storage locations are found within 8 km of Unit 2.Waterborne .commerce for 1978 Lake Ontario traffic is described in Tables 2.2-2 and 2.2-6.Approximately 1.2 million tons of cargo were transported on Lake Ontario.Since more specific commodity categories are not used in data collection, there are no means of identifying types, frequency, and amounts of hazardous material shipments past the site.The nearest passage of commercial vessels to Unit 2 occurs when navigating to and from the City of Oswego harbor, located approximately 10 km (6.2 mi)from Nine Mile.Point St'ation.The Port of Oswego Authority indicates that none of the hazardous materials listed in Table 2.2-5 have been USAR Revision 0 2~2 3 April 1989 Nine Mile Point'nit 2 FSAR transported on Lake Ontario, either originating at or destined to the Port of Oswego.All industries reported receiving hazardous material shipments via U.ST Highway 104 and County Route 1 by truck.2.2.2.3 Projections of Industrial Growth There are no plans for major expansion in transportation, storage, or industrial facilities in the vicinity of Unit 2.2.2.3 Evaluation of Potential Accidents The consideration of a'ariety of potential accidents, and their effects on the plant or plant operation, is included.in this section.Types of accidents considered include explosions, flammable vapor clouds, toxic chemicals, fires, collisions with intake structures, and liquid spills.2.2~3~1 Determination of Design Basis Events 2.2.3'.1 Explosions Based on a comprehensive survey of industries within a 10-km (6.2-mi)radius of Unit 2, the nearest.highway on which explosive materials can be transported is Route 104,, which is a distance of about 6.2 km (3.9 mi)from safety-related structures. This separation distance far ex-ceeds the safe distance for truck traffic (approximately S48.6 m, 1,800.ft)given on Figure 1 of Regulatory Guide 1.91.In discussions with Conrail, it, was determined that no ex-plosive or flammable materials are transported to, the Oswego terminal of the rail line between Oswego and Mexico, NY.In any event, the distance from this rail line to Unit 2 is much greater ,than the safe distance for rail traffic given in Regulatory Guide 1.91.Since the nearest commercial shipping lanes on Lake Ontario are more than 10 km (6'mi)from Unit 2 (according to the U.S.Coast Guard), potential explosions on a ship or barge are not considered a design basis event'.This distance is well beyond the radius of the peak incident pressure of 1 psi as given in Regulatory Guide 1.91.Therefore, accord-ing to guidance contained in Regulatory Guide 1.91, ex-'losions on nearby transportation routes are not considered design basis events due to the separation distances of potential sources of explosions from Unit 2.Amendment 26 2.2-4 May 1986 Nine Mile Point Unit 2 FSAR This results in an effective release rate of 6,802 g/sec (1.17xl0'g/172 sec), thereby yielding a centerline puff concentration of 0.04 which is less than the critical value of 0.07.Therefore, the delayed ignition of the puff or plume release from the propane tank at the FitzPatrick station will not cause a 1-psi overpressure to reach the Unit 2 containment building.2.2.3.1.3 Toxic Chemicals Potential Sources of Toxic Chemicals According to Regulatory Guide 1.78, both onsite and offsite potential toxic gas hazards must be considered. Any toxic substance stored onsite in a quantity greater than 45 kg (100 lb)must be evaluated. Offsite sources to be evaluated include stationary, facilities and frequent transportation of toxic substances (truck, rail, and barge)within 8 km (5 mi)of the site.Frequent shipments are defined as exceeding 10/yr for truck shipments, 30/yr for rail shipments, and 50/yr for barge shipments. For the Nine Mile Point site, sources of potential toxic chemical hazards include chemicals stored onsite, as well as four stationary and two transportation sources within 8 km of the site.Table 2.2-7 lists the chemicals associated with each source along with their quantities and distances from the Unit 2 control room air intake.The three stationary sources include the James A.FitzPatrick plant, the ALCAN Rolled Products Division, Oswego Wire Inc., and Unit l.One transportation source of possible hazardous materials is truck traffic along Route 104, which passes within 6.2" km (3.9 mi)of the site.The second transpor-tation source is the railroad line between Oswego and Mexico, NY.Discussions with Conrail indicate that on an average, only one hazardous chemical shipment during an 18-month period passes through the Oswego terminal.Traffic on a spur to the site is not frequent enough (<30/yr)to warrant con-sideration.' Only those chemicals that have the potential to form a toxic vapor cloud or plume after release to=the environment need to be evaluated. This criterion is met by all chemicals listed in Table 2.2-7.8 USAR Revision 0 2.2-5b April 1989 Nine Mile Point Unit 2 FSAR Control Room Habitabilit Determination The effect of an accidental release of each of the chemicals described in the previous section on control room habitability is evaluated by calculating vapor concentrations inside the control room as a function of time following the accident.This calculation is performed using the conservative methodology outlined in NUREG-0570 and utilizing the assumptions described in Regulatory Guide 1.78.In a postulated accident, the entire content of the largest single storage container is released, resulting in a toxic vapor cloud and/or plume that is conservatively assumed to be transported by the wind directly toward the control room intake.The formation of the toxic cloud and/or plume is dependent on the characteristics of the chemical and the environment. The entire amount of a chemical stored as a gas is treated as a puff or cloud that has a finite volume determined from the quantity and density of'the stored chemical.A substance stored as a.liquid with a boiling point below the ambient temperature forms an instantaneous puff due to flashing (rapid gas formation) of some fraction of the stored quantity.The remaining liquid forms a puddle that quickly spreads into a thin layer on the ground, subsequently vaporizing and forming a ground-level vapor plume.A high boiling point liquid (above ambient temperature) forms a puddle that evaporates by forced convection with no flashing involved.The calculations are done by a computer program (VAPOR)based on NUREG-0570 methodology that requires the following input information: chemical physical properties, control room parameters, meteorology, distance from the spill to the control room intake, quantity of chemical released, and toxicity limits.The following Unit 2 control-room parameters are used: ventilation rate of 0.551 cu m/sec (1,167 cu ft/min), and net free volume of 5,935 cu m (209,600 cu ft).The most conservative meteorological condition is assumed for the calculation, consisting of Pasquill Class G stability, a wind speed of 0.5 m/sec (1.6 ft/sec), and an ambient temperature of 32.8'C (91 F).The criteria for determining chemical toxicity and setting limits for habitability determinations are taken from regulatory guidance documents. According to Regulatory Guide 1.78, the toxicity limit of a chemical is the maximum concentration that can be tolerated by an average human for 2 min without physical incapacitation (severe coughing, eye burn, severe skin irritation). Standard Review Plan Section USAR Revision 0 2.2-6 April 1989 Nine Mile Point Unit 2 FSAR (1,000 ft)to reach the intake structures and would be sub-ject to dilution during transport. Any liquid spills originating during common commercial ship transport would have to travel appromimately 10 km (6.2 mi)to reach the in-I~6 take location.Due to the combined effects of the submerged intake structures'esign and the distance between intake structure location and origin of the potential liquid spill, the risk of entrainment of any significant quantities of oil, or corrosive, cryogenic, or coagulable liquids by the intake structures is negligible. 2.2.3.1.7 Airplane Crashes The nearest air corridor is approximately 22.5 km (14 mi)east, of the site (Section 3.5'.6).There are only two air-fields between the 8-km (5-mi)and 24-km (15-mi)radii of the site;the Lakeside Airpark and Oswego County Airport are about 12 km (7.5 mi)and 19 km (12 mi)south of the site, respectively. The aircraft approaches to these airports are not near the plant site.The general aviation movements at these airports total approximately 1,460/yr and 19,900/yr, respectively. The annual movements are below the critical number at which a probability analysis for aircraft ac-cidents would be required according to Regulatory Guide 1.70.Therefore, the probability of aircraft crashing into the site is considered to be remote, and airplane crashes need not be considered design basis events.2.2.3.2 Effects of Design Basis Events Potential design basis events are identified in Section 2.2.3.1.The effects of these events on the safety-related components of the plant are insignificant. The potential for toxic chemical accidents affecting main con-trol room personnel has been evaluated. This shows no potential impact, on main control room habitability. Self-contained breathing apparatus, however, will be provided for main control room operators'mendment 26 2.2-9 May 1986 Nine Mile Point Unit 2 FSAR 2.2.4 References Transmittal from Mr.Martin Weiss, Oswego County Planning Board, November 7, 1979.Updated and verified, April 4, 1981.2.Waterborne Commerce of the United States, Part 3, 1978.Department of the Army, Corps of Engineers, Virginia.3.Telephone conversation between P.A.Hughes (SWEC)and J.Robinson (U.S.Coast Guard, 9th District). June 23, 1981'ransmittal from B.Gorman, Power Authority of the State of New York, December 7, 1979, to P.Johnson, Stone 6 Webster Engineering Corporation. 5.Patty, F.A.(ed.).Industrial Hygiene and Toxicology, Vol.I and II.Interscience Publishers, New York, NY, 1958, 1963, and 1978.6.Sax, N.E.Dangerous Properties of Industrial Materials, 3rd Edition, Van Nostrand Reinhold, New York, NY, 1968.7.Criteria for a Recommended Standard: Occupational Exposure to Carbon Dioxide, Publication No.NIOSH 76-194, August 1976.8.Tilton, B.E.and Bruce, R.M.Review of Criteria for Vapor-Phase Hydrocarbons, Environment Criteria and Assessment Office, USEPA, EPA-600/8-80-045, p 6-150.9.Fire Protection Handbook, 13th Edition, National Fire Protection Association, 1969, Boston, MA, p 15.14-45.10.Transmittal from R.J.Mangold, Alcan Aluminum Corporation, July 8, 1981, to P.D.Patel, Stone Ec Webster Engineering Corporation. Transmittal from T.J.Perkins, Niagara Mohawk Power Corporation, August 3, 1981, to K.A.Baraniak, Stone&Webster Engineering Corporation. 12.Burgess, D.S.and Zabetakes, M.-G.Detonation of a Flammable Cloud Following a Propane Pipeline Break.U.S.Bureau of Mines Report of Investigations (RI7752), 1973.Amendment 3 2.2-10 June 1983 Nine Mile Point Unit 2 FSAR TABLE 2.2-3 INDUSTRIAL FIRMS WITHIN 8 KM (5 MI)OF UNIT 2 Firm Alcan Aluminum Corporation Distance/Direction from Site (km 4.5/SW Aluminum sheet and plate 1,000 James A.FitzPatrick <1/E Nuclear Power Plant Electrical 515 generation Nine Mile'Point Unit 1 Adjacent to Unit 2 Electrical 450 generation SOURCE: References 4, 10, ll USAR Revision 0 1 of 1 April 1989

Nine Mile Point Uni.t 2 FSAR TABLE 2.2-5 HAZARDOUS MATERIALS STORED/USED BY INDUSTRIES WITHIN 8 KM (5 MI)Material Carbon dioxide Industrial User Alcan FitzPatrick Storage on Premises (Max.at O~eTL e MOd*~A*a Sla 65 tons Truck 6 tons 26,000 lb Truck 6,900 gal Maximum Quantity~Sh ed 10 tons 6,900 gal Shi ent~Fe ue e Weekly Infrequently, as needed system Average Quantity~Shi~ed yr 250 tons Small quantitres used to recharge Chlorine NMP Unit 1 Alcan 20,000 lb 30 tons Truck Truck 5,000 lb 1 (1 ton)cylinder 6,300 gal 12 tons Monthly Biweekly 56,000 gal 350 cylinders Helium Alcan 1,917 ft Truck 213 ft 9 cylinders (213 ft each)As needed 94 cylinders (20i022 ft)Hydrochloric acid Hydrogen Nitrogen Propane Sodium hydroxide Alcan FitzPatrick NMP Unit 1 Oswego Wire Alcan FitzPatrick NMP Unit 1 Oswego Wire FitzPatrick Alcan FitzPatrick Alcan NMP Unit 1 Oswego Wire 500 gal Truck 28,800 ft Truck 12,000 ft Truck 6,450 ft Truck 970,000 ft Truck 10,000 gal Truck 15,300 gal Truck 160,000 ft Truck 55 gal 128g000 ft 24,000 ft 515 ft 670,000'ft 6,900 gal 6,300 gal 385 gal 128,000 ft 24,000 ft 5,375 ft 670,000 ft 6,900 gal 6,300 gal 145,000 ft 160,000 ft 80i000 lb 5,000 gal 3,000 gal 165 gal 385 gal Truck Truck Truck Truck Truck 7,000 lb 3g000 lb 55 gal 55 gal 55 gal 22,500 lb 7,000 lb 3,000 lb 1,000 gal 55 gal 55 gal 1,000 gal Truck 22,500 lb Weekly Biweekly Bimonthly 10 Weeks Honthly Monthly Monthly Weekly Monthly Biweekly Monthly Monthly As needed Monthly 16,000 gal 221,000 ft 72,000 ft 27,305 ft 8,999,200 ft 129,000 gal 56,000 gal 8,000,000 ft 3,000 gal 200,000 gal 246,000 lb 10,000 gal 100 gal 660 gal U SAR Rev is ion 0 1 of 2 April 1989

Nine Mile Point Unit 2 FSAR TABLE 2.2-7 SOURCES OF TOXIC CHEMICALS WITHIN 8 KM (5 MI)OF UNIT 2 SITE Chemical Location Chemical Amount Distance to Intakes (m James A.Fitz-Patrick plant Alcan N2 H2 SOCO2 Propane Halon Clq Propane N2 HCL COR 0.305 0.346 1.18 0.221 0.260 0.181 0.363 0.260 0.226 0.533 x 10s x 10s x 10'10'10'10'10s x 10s x 107 x 10s 620 620 620 620 620 4,990 4,990 4,990 4,990 4i990 Route 104 HC1 N2 CO2 0.542 x 107 0.183 x 10'.272 x 10~5,470 5,470 5,470 Nine Mile Point Unit 1 N2 CO2 H2 SOHCL Halon 0.443 0.907 0.114 0.454 0.227 x 10s x 10'10'10'10e 290 265 290 290 290 Nine Mile Point Oswego Wire Incorporated H22 Halon 1301 N2 Isopropyl Alcohol N2 Propane H2 SOHCL 0.118 x 10'.113 x 10'.671 x 10s 0.330 x 10e 0.525 x 10e 0.947 x 10e 0.750 x 10e 0.182 x 10" 33 45 150 7, 080 7,080 7,080 7,080 7,080 USAR Revision 0 1 of 1 April 1989

Nine Mile Point Unit 2 FSAR TABLE 2.2-8 PREDICTED VAPOR CONCENTRATION IN THE UNIT 2 CONTROL ROOM Chemical Location James A.FitzPatrick plant Alcan Route 104 Nine Mile Point Unit 1 Nine Mile Point Unit 2 Oswego Wire Incorporated Chemical N~Hq SOCOq Propane Halon Clq Propane N~HCL CO~Hcl N~CO~Nq COq H~SOHalon Hcl Hq SOCO~Halon 1301 N~Isopropyl Alcohol Nq Propane Hq SOMaximum Control Room Concentration (m~11.2 6.6 x 10-~6.2 1.29 1.73 0.038 1.1 0.09 0.003 2.5 x 10-'.009 0.54 0.0 22.2 14.7 1.3 x 10-~0.57 0.009 6.6 x 10 46.8 3.88 32.1 2.2 x 10-4 1.2 x 10-~2.1 x 10 1.0 x 10-'oxic Limit 274 0.002 54.8 43.1 432 0.045 43.1 274 0.05 54.8 0.050 274 54.8 274 54.8 0.002 432 0.05 0.002 54.8 432 274 1.2 274 43.1 0.002 Allowable Time Period (min 15 2 15 15 15 2 15 15 15 2 15 15 2 15 15 2 15 15 2 15 15 15 15 15 15 2 USAR Revision 0 1 of 1 April 1989 ' Nine Mile Point Unit 2 FSAR Surveillance, including inking and routine preventive maintenance, is performed at least twice weekly.Charts are changed at 2-week intervals. Calibrations occur at least every 6 months with component checks'nd adjustments performed when required.'All meters and other equipment used in calibrations are, in turn,-calibrated at scheduled intervals. Inspection and maintenance of all equipment is accomplished in accordance with procedures in the instrument manufacturer's manuals.Inspection is carried out by qualified technicians capable of performing the maintenance, if required.The results of the inspections and maintenance'erformed are kept in a log.F 2.3.3.1.6 Data Acquisition and Reduction From January 1974 to October 1980, analog strip charts were changed every 2 weeks and processed. After each chart was scanned for instrument malfunctions, hourly values were read.The data were routinely keypunched on a monthly basis.After keypunch verification, a computer listing and quality control summary was generated of hourly readings.The'ata were again checked for inconsistencies by an instrument specialist and a qualified meteorologist. After incorporating any calibrations from site personnel, a final listing was generated. The data were then transferred to magnetic tape and a copy was made.2.3.3.1.7 Data Analysis Procedures All data were subject to quality control checks prior to finalization into monthly listings.At the end of each quarter, routine summaries of wind direction, speed, and stability were computed.Monthly and annual data analyses were performed as warranted for special projects in addition to the routine submittal of the data for Nine Mile Point Unit 1 to the NRC.2.3.3.2 Operational Measurements Program 2.3.3.F 1 Description The preoperational onsite meteorological measurements program has been upgraded and expanded to meet the intent and recommendations of Regulatory Guide 1.23 and NUREG-06S4 for the operational measurements program'.The preoperational, steel, open lattice 61-m (200-f t)meteorological tower serves as the primary installation. New meteorological sensors.were installed at the facility Amendment 3 2'31 June 1983 Nine Mile Point Unit 2 FSAR starting in July 1982 and the entire replacement was completed by February 1983.Supplemental inland measurements are obtained from instrumentation at the Oswego County Airport near Fulton.Back-up instrumentation is located east of'he J.A.FitzPatrick Plant.A map showing the detailed relationship of Unit 2 to the primary meteorological tower and the backup tower is shown on Figure 2;3-40.Figure 2.3-40A shows the location of the inland tower, the primary tower, and the backup tower with respect to Unit 2 on a larger scale map.The primary tower is instrumented .with wind direction and speed sensors at three levels: 9 m (30 ft), 30 m (100 ft), and 61 m (200 ft).Sigma theta is derived for each of the three wind levels.In addition, ambient temperature is measured at 8 m (27 ft)and temperature differences are determined between the 61-m (200-ft)and 8-m (27-ft)levels.Dew point temperature is obtained at the 8-m (27-ft)level.Near the base of the tower, precipitation and barometric pressure are also measured.The inland 10-m (33-ft)meteorological tower is located with good exposure in all directions and is situated away from all runways and buildings at the Oswego County Airport.The instrumentation provides wind speed and direction from which sigma theta values are calculated. The back-up wind direction and speed instrumentation is located east of the J.A.FitzPatrick Plant, on a.27-m (90-ft)utility pole.One coincident annual cycle of wind data from the backup instrumentation and the primary tower will not be available until mid-1984.At that time, a comparison of the two data sets will be made to determine the representativeness of the backup wind measurements. The results.of this comparison will be provided by the end of 1989.2.3.3.2.2 Meteorological Instrumentation The operational meteorological measurements program is designed to meet the NRC recommendations at the time of installation in mid-summer 1982 and is in accordance with Regulatory Guide 1.23.Manufacturers'odel numbers and specifications for the sensors are shown in Table 2.3-4-A.Component errors, as well as sensor and system accuracies, are listed in Table 2.3-5A.Wind Instruments All monitoring locations employ the Teledyne Geotech three-cup anemometer and vane.USAR Revision 0 2'-32 April 1989 Nine Mile Point Unit 2 FSAR 67.Dewey, K.E.Lake-Effect Snowstorms and the Record Breaking 1976-1977 Snowfall to the Lee of Lakes Erie and Ontario, Weatherwise, Vol.30, No.6, 1976.68.U.S.Department of Commerce Local Climatological Data-Monthly Summary-Syracuse, New=York.NOAA, Environmental, Data and Information Service, National Climatic Center, Asheville, NC, 1977-October 1983.69.Sykes, R., Pack, A.B.and Loveridge, E.The Climate and Snow Climatology of Oswego, New York.Lake Ontario Environmental Laboratory, Contribution No.2, Vol.1, June 1971, p.59.70.Hershfield, D.M.Rainfall Frequency Atlas of the United States for Durations From 30 Minutes to 24 Hours and Return Periods From 1 to 100 Years.Technical Paper No.40, Weather Bureau, U.S.Department of Commerce, Washington, D.C., 1961.Amendment 19 2.3-62a May 1985 Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK Amendment 19 2.3-62b May 1985 Nine Mile Point Unit 2 PSAR TABLE 2.4-15

SUMMARY

OF RESULTS ANALYSIS OF BUILDING FLOODING DUE TO PMP BASED ON HYDROMET 51 AND 52~Biidi Diesel generator Control building Auxiliary bay south Electrical tunnel-south area Stop logs C261-29 C261-24 C261-31 SA262-3 ET262-4 Length~ft 15 Total Flow~ftA 404.2 551.1 257.2 110.2 110.2 63.6 63.6 Bldg.Depth~in Distribution of Plow Flux Evenly over floor;provided caulking material to make stop logs watertight. C261-29 and C261-31 flows will combine and spread through El.261 corridors and into some rooms.C261-24 will flow down stairwell and spread through corridors on lower floors.No fix is required.Plow will be confined to auxiliary bay stairwell area.No fix is required.Plow will be spread evenly through each tunnel.Electrical tunnel-north area ET261-1 102.6 Auxiliary bay north RB railroad track bay Standby gas treatment Service water pump room (north)from auxiliary boiler room ET261-2 NA262-1 RR-261-1 SG261-2 SG261-1 SG261-6 AB261-3 17 102.6 63.6 NA 273.6 273.6 102.6 NA NA 2.5 Plow will be confined to auxiliary bay stairwell area.No fix is required.Doors are equipped with inflatable air seals;water leakage will be negligible. No safety-related equipment is in this area.Plow is spread evenly throughout the building (see Note 5).Plow into auxiliary boiler building is dis-tributed into the pumphouse if AB261-3 is open.USAR Revision 0 1 of 2 April 1989

Nine Mile Point Unit 2 FSAR TABLE 2.4-15 (Cont)B~B'd'ervice water pump room (south)from screenwell area Door SW261-14 Length~ft Total Flow~ftA 94.2 Bldg.Depth~in Distribution of Flow Flux Evenly throughout building.NOTES: l.Use hydrographs from Calculation No.12177-WH(B)-062 for water surface elevations. 2.Door sill elevation is in the door identification number, e.g., SH261-14, where"261" is the door sill elevation. 3.Calculation method for inflow through doorways from PHF submerged orifice discharge equation: 9=CA~gh ()-"Flow (cfs)C=Discharge coefficient =0.6 A=Cross sectional area of flow=length of door (L)x crack width of door opening (1/16 in due to flow"necking")g"-Gravity h=Headwater surface elevation on exterior of door 4.No credit has been taken in the analysis for sump~ater retainage or sump pump operation. 5.Since equipment structural pad height is 6 in, resultant building water depths less than this are acceptable. USAR Revision 0 2 of 2 April 1989

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 Title 6A through 6C INSTRUMENTATION AND CONTROL SYSTEMS Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components Volume 13 13 13 13 13 14 15 15 15 15 15 15 7.1 7'7'7,4 7.5 7.6 7'Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A ELECTRIC POWER Introduction Offsite Power System Onsite Power System 16 16 16 16,17 17'CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9Ag 9C 17 18 19 20,21 21,22 I USAR Revision April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume CHAPTER 10 10.1 10.2 10.3 10.4 STEAM AND POWER CONVERSION SYSTEM Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System 23 23 23 24 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11'11.2 11.3 11.4 11'Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems Appendix llA CHAPTER 12 RADIATION PROTECTION 24 24 25 25 25 25 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 2626 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 6A through 6C INSTRUMENTATION AND CONTROL SYSTEMS Title Reactor Vessel Component and Subsystem Design 5Ag 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components Volume 13 13 13 13 13 14 15 15 15 15 15 15 7'7'7'7'7.5 7.6 7'Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS 16 16 16 16,17 I 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 18 19 20,21 21,22 23 I USAR Revision April 1989 Nine Nile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 23 10.1 10.2 10.3 10.4 Summary, Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System 23 23 24 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 11.2 11.3 11.4 11.5 Appendix llA CHAPTER 12 RADIATION PROTECTION Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25 25 12.1 12.2 12.3 12~4 12.5 CHAPTER 13 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)-Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program CONDUCT OF OPERATIONS Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 25 25 25 26 26 26 26 26 26 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components through 6C INSTRUMENTATION AND CONTROL SYSTEMS Volume 13 13 13 13 13 14 15 15 15 15 15 15 7.1 7'7'7'7.5 7.6 7'Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS 16 16 16 16,17 17 I 17 9.1 9.2 9.3 9'9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 18 19 20,21 21,22 I USAR Revision April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section CHAPTER 10 10.1 10.2 10.3 10.4 CHAPTER 11 Title STEAM AND POWER CONVERSION SYSTEM Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT Volume 23 23 23 24 11.1 11.2 11.3 11.4 11'Appendix llA Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25 CHAPTER 12 RADIATION PROTECTION 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26.26'6 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSARTABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 6A through 6C INSTRUMENTATION AND CONTROL SYSTEMS Volume"13 13 13 13 13 14 15 15 15 15 15 15 7'7'7'7'7.5 7.6 7~7 Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15.15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 9.1 9.2 9.3 9.4 9.5 Appendixes ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 16 16'16'16, 17 17 17 17.18 19 20,21 21,22 I USAR Revision 0 I~I April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume CHAPTER 10 10.1 10.2 10.3 10.4 CHAPTER 11 STEAM AND POWER CONVERSION SYSTEM Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT 23 23 23 24 11.1 11.2 11.3 11.4 11.5 Appendix 11A Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems II 24 24 25 25 25 25 CHAPTER 12 RADIATION PROTECTION 25 12~1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13~1 13.2 13,.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26 26'6 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit.2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 Title Reactor Vessel Component and Subsystem Design 5Ag 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components ~through 6C INSTRUMENTATION AND CONTROL SYSTEMS Volume 13 13 13 13 13 14 15 15 15 15 15 15 7.1 7'7'7.4 7.5 7'7~7 Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 9.1 9.2 9.3 9.4 9.5 Appendixes ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9Ag 9C 16 16 , 16'16, 17 17 I 17 17.18 19 20,21 21,22 I USAR Revision April 1989 .Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS'(Cont), Section CHAPTER 10 10.1 10.2 10.3 10'Title STEAM AND POWER CONVERSION SYSTEM I Summary, Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System Volume 23 23 23 24 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 11.2 11.3 11.4 11.5 Appendix llA Source Terms 1 Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25 CHAPTER 12 RADIATION PROTECTION 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 iv Figure Number Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF FIGURES (Cont)Title 3.6A-40 3.6A-41 3.6A-42 3.6A-43 3.6A-44 3.6A-45 3.6A-46 3.6A-47 3.6A-48 3.6A-49 3.6A-50 3.6A-51 3.6A-52 3.6A-53 3.6A-54 HIGH ENERGY PIPE BREAKS REACTOR WATER CLEANUP OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS REACTOR WATER CLEANUP OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS STANDBY LIQUID CONTROL INSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT DELETED DELETED HIGH ENERGY PIPE COMPOSITE PLAN EL 175'-0" AND 215'-0" HIGH ENERGY PIPE COMPOSITE PLAN EL 240'-0" HIGH ENERGY PIPE COMPOSITE PLAN EL 261'-0" 27 Amendment 27 3-xli July 1986 Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF FIGURES (Cont)Figure Number 3.6A-55 3.6A-56 3.6A-57 3.6A-58 Title HIGH ENERGY PIPE COMPOSITE PLAN EL 289'-0" HIGH ENERGY PIPE COMPOSITE PLAN EL 306'-6" HIGH ENERGY PIPE COMPOSITE PLAN EL 328'-10" HIGH ENERGY PIPE COMPOSITE SECTION 1-1 3.6A-59 3.6A-60 3.6B-1 3.6B-2 3.6B-3 HIGH ENERGY PIPE COMPOSITE SECTION 2-2 HIGH ENERGY PIPE COMPOSITE SECTIONS 3-3 AND 4-4 TYPICAL RESTRAINT FORCE DEFLECTION CURVE TYPICAL PIPE WHIP RESTRAINT'ONFIGURATION BREAK LOCATIONS AND RESTRAINTS ANALYZED, PDA VERIFICATION PROGRAM 3.7A-l 3.7A-2 3.7A-3 3.7A-4 HORIZONTAL SSE DESIGN RESPONSE SPECTRA NORMALIZED TO 0.15 G VERTICAL SSE DESIGN RESPONSE SPECTRA NORMALIZED TO 0.15 G HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND RESPONSE SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTH-QUAKE)BASED ON 2.0 PERCENT DAMP1NG RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND RESPONSE SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE) BASED ON 1 PERCENT DAMPING RATIO Amendment 21 3-xlil September 1985 Nine Mile Point Unit 2 PSAR TABLE 3.2-1 (Cont)125-V DC Power S stems Scope of~Su~1 Location Electrical Classifi-cation Seismic C~at o Group Classifi-cation Quality (31, 32, Assurance 33, Re irement 34 Tornado Protection Notes 125-V dc emergency batteries and racks 125-V dc emergency battery chargers 125-V dc emergency switchgear 125-V dc emergency centers 125-V dc emergency distribution panels Emergency cables Cable tray and fabricated supports with safety functions DC containment penetrations Conduit and nonemergency cable tray Miscellaneous Com nents Reactor building polar crane Civil Structures Primary containment Reactor building, including fuel storage facilities and auxiliary bays Radwaste building Control building Diesel generator building Turbine building, including heater bay, except as noted Main steam tunnel Portion of turbine building Pipe tunnel portion of the turbine building between column lines AK and AM below el 261 ft Pipe tunnel portion of the turbine building between column lines 10 and 12 below el 248 ft Turbine building el 250 ft slab over the pipe tunnels between column lines 10 and 12 NA M,C,RB MiCiRB MiCgRB RB MgCgRB 1E 1E 1E NA 1E NA Non-1E NA NA NA NA NA NA NA I Z (22)NR T T (34)(29)(28g44)(28,29i 36)(20)USAR Revision 1 16 of 26 October 1989 1 I Nine'ile Point Unit 2 FSAR TABLE 3.2-1 (Cont)Penetration Z-328-3 2RCS-750-151-2 Extension of Primar Containment, Reactor Buildin E ui ment (DER)Penetration Z-45 2DER-002-034-2 (47)The equipment and its classification also apply to the air start system associated with the Division III (HPCS)diesel generator. (48)The GE compressor motor is Seismic Category I.The com-pressor motor starter is Seismic Category NA, but it is seismically mounted and evaluated to ensure that if failure occurs it will not cause degradation of safety-related equipment. USAR Revision 0 26h of 26 April 1989

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5'Appendixes CHAPTER 6 Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Volume 13 13 13 13 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes 6A through 6C Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 13 14 15 15 15 15 15 CHAPTER 7 7.1 7'7'7'7.5 7.6 7~7 Appendixes CHAPTER 8 8.1 8.2 8.3 Appendix 8A INSTRUMENTATION AND CONTROL SYSTEMS Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 7A, 7B ELECTRIC POWER Introduction Offsite Power System Onsite Power System 15 15 15 15 16 16 16 16 16 16 16.16'16, 17 17'CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 9.2 9.3 9'9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9Ag 9C 17.18 19 20,21 21,22 23 I USAR Revision 0 April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section CHAPTER 10 Title STEAM AND POWER CONVERSION SYSTEM Volume 23 10.1 10.2 10.3 10.4 CHAPTER ll Summary, Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT 23 23 24 11.1 11.2 11.3 11.4 11'Appendix llA Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25 CHAPTER 12 RADIATION PROTECTION 25 12.1 12.2 12.3 12.4 12.5 CHAPTER 13 13.1 13.2 13.3 13.4-13.5 13.6 Appendixes Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program CONDUCT OF OPERATIONS Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 25, 25 25 26 26 26 26 26 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 7.1 7'7'7.4 7'7'7~7.Appendixes CHAPTER 8 Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 6A.through 6C INSTRUMENTATION AND CONTROL SYSTEMS Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown.Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 7Ag 7B ELECTRIC POWER Volume 13 13 13 13 13 14 15 15 15 15 15 15 15 15 15 16'16 16 16 16 16 8.1 8.2 8.3 Appendix 8A CHAPTER 9 Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS 16 , 16 16,17 17 I 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 ,18 19 20,21 21,22 I USAR Revision 0 April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section CHAPTER 10 10.1 10.2 10.3 10'CHAPTER ll Title STEAM AND POWER CONVERSION SYSTEM Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT Volume 23 23 23 24 11.1 11.2 11.3 11.4 11.5 Appendix llA Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25 CHAPTER 12 RADIATION PROTECTION 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13~2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26 26 26'6 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR 3.7.3.1.3A Other Dynamic Loads Loading combinations and stress limits, including loads due to hydrodynamic effects, are described in Section 3.9.3.1A.A further discussion of hydrodynamic phenomena is included in the Design Assessment Report for Hydrodynamic Loads (Appendix 6A).3.7.3.2A Determination of Number of Equivalent Stress Cycles The following criteria are applied to all Category I subsystems: l.A total of five OBE and one SSE are considered. 2.For subsystems, except piping, 20 cycles (full sign reversals) per seismic event, i.e., a total of 120 cycles, are considered. 3.For all piping systems, 10 maximum stress cycles per OBE (i.e., a total of 50 cycles)are postulated. 4.Where time history analysis is performed, a minimum duration of 10 sec is assumed.3.7.3.3A Procedure Used for Modeling The procedure described in the following sections is specifically written for piping systems.Other subsystems are seismically qualified as described in Section 3.7.3.1.1A. 3.7.3.3.1A Summary Portions of piping systems that are bounded by anchors or equipment are statically and dynamically independent from the remainder of the piping.Generally, a piping system consists of several such subsystems. The analytical model and its geometric boundaries are described in detail in the following sections.3.7.3.3.2A Geometric Boundaries of Analytical Models For the purpose of analysis, piping systems are subdivided into smaller units (referred to as problems)that are bounded by structural anchors (6-deg-of-freedom constraints) or by other virtually rigid points such as equipment, penetrations, and piping of much larger diameter.Amendment 23 3.7A-19 December 1985 Nine Mile Point Unit 2 FSAR A branch line with a moment of inertia of 1/10 or less of the run pipe may be ignored in the model.However, if the branch line needs to be analyzed, its model includes the ef-fect of the run pipe.Where Category I piping is connected to nonseismic piping, the adjoining portion of the non-seismic piping up to the first anchor is included in the analytical model of the Category I piping, and all supports up to and including this anchor, are designed seismically (Section 3.7.3.13A). 3.7.3.3.3A Model The basic method of analysis used is NUPIPE, a finite element computer program (Appendix 3A)~In accordance with this method, the continuous piping is mathematically idealized as an assembly of elastic structural members con-necting discrete nodal points.Nodal points are placed in such a manner as to isolate particular types of piping elements such as straight runs of pipe, elbows, valves, etc, for which force-.deformation characteristics can be categorized. Nodal points are also placed at all discon-tinuities such as piping supports, concentrated weights, branch lines, and changes in cross section.System loads such as weights, equivalent thermal forces, fluid transient dynamic forces, and inertia forces are applied at the nodal points.Stiffness characteristics of the interconnecting members are related to the effective shear area and moment of inertia of the pipe.The stiffness of piping elbows and certain branch connectors is modified to account for.local deformation effects by the flexibility factors specified in ASME Section III, 1974, Subarticles NB-3600 (Safety Class 1 piping analysis)and NC-3600 (Safety Class 2 and 3 piping analysis). The increased stiffness of valve bodies is taken into consideration. 3.7.3.3.4A Selection of Mass Points The lumped masses are located to adequately represent the dynamic properties of the piping system.Mass points are generally selected in accordance with the following guidelines: At.-each node where a concentrated weight is placed (valves, flanges, or other in-line" piping components). 2~At each intersection where three or more piping elements are connected (branch connections, tees, and y-fittings). Amendment, 3 3.7A-20 June 1983 Nine Mile Point Unit 2 FSAR Res onse S ectrum Method When a piping system is analyzed by means of the response spectrum method, the computer code NUPIPE is used to cal-culate the modal response at each node point in the piping system due to the ARS excitation applied to the system.Generation or selection of the appropriate set of ARS for a subsystem supported at different elevations, and con-sideration of the effect of seismic differential displacements between restraints are discussed in Section 3.7.3.9A.The damping values for piping depend on pipe size and are given in Table 3.7A-1.The equations of motion and their solution are as previously described for structures (Section 3.7.2).Time Histor Method The applicable base motion time history is the structural response at a representative mass point of the structure to the ground motion time history.The equations of motion and their solution are the same as in Section 3.7.2.5A, but the scalar acceleration term in the excitation function is now the amplitude of the acceleration of the base of the sub-system (points of attachment), not of the ground.The ef-fect of parameter variations on the floor response spectra are taken into account (Section 3.7.2.9A). D namic Anal sis Formulation The basic equations of motion and their solutions are the same as for structures (Section 3.7.2).Absolute ac-celerations at points on the piping system are sometimes needed for qualification of critical, safety-related equipment. With the response spectrum method, the maximum absolute acceleration at a mass point in mode i is obtained from Newton's law by dividing the effective inertia force by the mass at the mass point: ta1=tMl'lQl (3.7A-6)Where:[M]=Diagonal mass matrix of the system[Qf=Effective inertia forces in mode i With the time history method, the absolute accelerations are obtained by adding the base acceleration to the relative ac-celerations of the mass points.I" Amendment, 26 3.7A-25 May 1986 Nine Mile Point Unit 2 FSAR Seismic Differential Dis lacements Descri tion of In ut The seismic differential displacements are also called seismic anchor movements. This effect is analyzed in a separate static load case for OBE anchor movements. The anchor movements are obtained from the seismic differential displacements of the structural nodes.The displacements are obtained in the following form, one set for each mass point, N, of the building model: Earth uake Direction Mass Node X (East-~West Vertical Z (North-~South Dg X Dp X D3 X Dg Y Dp D3 Dz z Dg z D3 z N Where: N X N N z DN (DN , DN)=SRSS of displacements in X (Y, Z)dir-x y z ection due to earthquake excitation in X, Y, and Z directions at Node N These are the movements of points on the walls relative to the foundation of the building.Relative displacements between mass points are used to determine the movements of support points.Support displacements are imposed on the system in a conservative manner.Combination of Anchor Movement Loads The individual X, Y, and Z anchor movement components of OBE are analyzed as three separate static anchor movement load cases in the NUPIPE computer program.These load cases are then combined by the SRSS method in NUPIPE, and the resultant load case is used in the code stress evaluation. Combined Seismic Res onse The system response to the response spectrum excitation (i.e., di splacements, internal forces and moments, stresses, and support reactions) is obtained by first combining the 3.7A-26 Nine Mile Point Unit 2 FSAR modal contributions for each earthquake component. In con-formance with Regulatory Guide 1.92, the effect of closely spaced modes is taken into account by the procedure described in Section 3.7.2.7A.The contributions of each of the three components are then combined by the SRSS methods;When the response spectrum method is used, response to the differential support motion is considered..In Safety Class 1 piping analysis, this motion is combined with the inertial response;the result is-then combined with other load cases.In the analysis of other piping classes, the seismic anchor movement is combined with secondary loads.Seismic load cases are combined with other load cases (thermal, weight, pressure, other occasional loads)in ac-cordance with ASME Section III, 1974.The load combinations are given in Section 3.9.3.1A.Fati ue Considerations For ASME Safety Class 1 piping, if Equation (10)of Subpara-graph NB-3653.1 is not satisfied, a fatigue analysis is per-formed in accordance with Subparagraph NB-3653.2 or Subarti-cle NB-3200.This analysis uses the total number of stress cycles of all OBEs.The number of earthquake cycles is discussed in Section 3.7.3.2A.Com uter Pro rams Used for Seismic Anal sis All analyses are performed with NUPIPE.This program han-dles response spectrum and support motion time history analyses.PSPECTRA is used for peak spreading, as well as for envelope generation, to obtain the ARS required as NUPIPE input to all spectral analyses.These programs used in piping analysis are described in Appendix 3A.Develo ment of Relative Dis lacements and Their A lication to Pi in Anal sis The relative displacement between a point on the reactor building and a point on the primary containment is obtained as follows: 1.The displacement time history at each point is calculated using as input the three-directional synthetic time history of ground motion.2.The displacement time history of the first point is substracted from that of the second to get a time history of relative displacement. Some examples of displacements are included on Figure 3.7A-35.USAR Revision 0 3.7A-27 April 1989 Nine Mile Point Unit 2 FSAR The effect of relative displacement between the supports is considered in the piping analysis.One support is selected as a reference point.Dynamic displacements at this reference point are taken either as zero or as displacements relative to a given structural node.At the'first (adjacent) support from the reference point, relative displacements between this support and the reference point are taken and added to the dynamic displacement of the reference point (the direction of displacements is determined and applied to the supports in relation to its function). The resultant displacements become the dynamic displacements of the first support.The first support then becomes the new reference point.This process is repeated until dynamic displacements at all supports are obtained.3.7.3.9A Multiply Supported Equipment Components with Distinct Inputs When a subsystem is attached to different parts of a structure, such as separate elevations on one wall or several walls, the response spectra of all structural nodes for which response spectra exist and which lie nearest to the support elevation at the subsystem, both below and above the support elevation, are enveloped, and this envelope spectrum is applied to the subsystem. In cases where a sub-system runs between two different buildings, a single ARS enveloping the spectra associated with all support points is used.USAR Revision 0 3'A-27a April 1989 Nine Mile Point Uni't 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3-6.4 6.5 6.6 Appendixes CHAPTER 7 7.1 7'7'7'7.5 7.6 7'Appendixes CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 9.1 9.2 9.3, 9.4 9.5 Appendixes Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency'Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 6A.through 6C INSTRUMENTATION AND CONTROL SYSTEMS Introduction Reactor Protection (Trip)-'System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 7A, 7B ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C Volume 13 13 13 13 13 14 ,.15 15 15 15 15 15 15 15 15 16 16 16 16 16 16 16'.16'16, 17 17 I 17 17:18 19 20,21 21,22 23 USAR Revision 0 April 1989 Nine Mile Point Unit 2 FSAR TABLE'OF CONTENTS (Cont)Section CHAPTER 10 10.1 10.2 10.3 10'Title STEAM AND POWER CONVERSION SYSTEM Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System Volume 23 23 23 24 11.1 11.2 11.3 11.4 11.5 Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems Appendix llA CHAPTER 12 RADIATION PROTECTION CHAPTER ll RADIOACTIVE WASTE MANAGEMENT 24 24 24 25 25 25 25 25 12.1 12.2 12.3 12.4 12.5 CHAPTER 13 13.1 13.2 13.3 13.413.5 13.6 Appendixes Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program CONDUCT OF OPERATIONS Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures. Industrial Security 13A, 13B 25 25 25 26 26 26.26 26 26 26'*26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)iv 26 Nine Mile Point Unit 2 FSAR Analytical modeling and seismic analysis are described in Section 3.7.3.8A.Static analysis and other dynamic analyses that contribute the remaining stresses in the code stress criteria are described in the following sections.Piping engineering and design specifications for Unit 2 allow the use of various types of branch connections, including pipe-to-pipe. Unless a specific branch connection is indica-ted in the specification or on the piping drawings, an unre-inforced pipe-to-pipe connection is used in the pipe stress analysis.No further action is required if the allowable stresses are met.If the allowable stresses are not met, then the piping stress calculation identifies the reinforce-ment of, the branch connection that is required.For cases where the branch line is decoupled from the run piping, the proper stress intensification factor is used in the analysis of both the branch line and the main run piping.If reinforcement for mechanical loads is required, it is so identified in the piping stress calculation and drawings.Reinforcement requirements for mechanical loads, identified by the pipe stress calculations, are incorporated on the piping drawings.Pressure reinforcement calculations required by ASME III, paragraph NB-3643, and ANSI B31.1, paragraph 104.3, are performed by the piping fabricator, and additional reinforcement, if required, is identified and added to the fabricated pipe.3.9.1.5.1A Static Analysis The static equation of equilibrium for the idealized system may be written in matrix form, as follows: KU=P-Q (3.9A-1)Where: K=Stiffness matrix for assembled system U=Nodal displacement vector External forces, weights, etc Equivalent thermal forces Cross-section area 0 E=Young's Modulus~<=Thermal expansion coefficient T=Average wall temperature less 70'F installation temperature USAR Revision 0 3.9A-3 April 1989 Nine Mile Point Unit 2 FSAR=Coordinate along pipe axis L=Length of pipe The unknown nodal displacements are obtained from the NUPIPE computer program by solving this equation using the Gaussian method.The nodal displacements are then applied to the individual members, and member stiffnesses are used to find internal forces.The nodal displacements at support locations can be used along with the support stiffness to determine support reactions. Dead Loads Wei ht, Pressure and Live Loads In NUPIPE, the effect of pressure is calculated simultaneously with the deadweight case.The analysis for deadweight assumes all flexible restraints, such as spring hangers, to be rigid.If a pipe has different contents (medium)and therefore different weights in various flow USAR Revision 0 3.9A-3a April 1989 Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK USAR Revision 0 3.9A-3b April 1989 Nine Mile Point Unit 2 FSAR modes, this is taken into consideration. Other details are discussed in Section 3.7.3.8.3A. Live loads are considered if they are expected to constitute a significant component of the total mechanical load.The filling of main steam lines with water during vessel flooding and alternate shutdown events is indicated on the main steam thermal transients and considered in pipe stress analysis in accordance with NB-3600.Spring hangers are designed to carry the full water-filled piping load during hydrotest. Additional deadweight stress as a result of filling the piping with water is considered in the NB-3600 analysis of the system.The main steam safety relief valve (S/RV)discharge piping has been designed and qualified for the steam hammer load due to steam blow'down. The results of the BWR Owners'roup Safety Relief Valve Test Program, in which Unit 2 has been a participant, show that the measured spring and support response was significantly less for water than steam.The test report, as documented in NEDE-24988-P, stated that"the maximum pipe response due to liquid discharge was generally less than 30%of that due to steam discharge." The test program was established to measure the S/RV discharge line (S/RVDL)response for alternate shutdown cooling conditions and to compare these loads with steam loads.Additional deadweight stress resulting from water-filled main steam safety relief is considered in the ND-3600 analysis of the main steam relief valve lines.Initial Dis lacements Anchor Movements NUPIPE permits calculation of the thermal initial support displacements combined with the thermal response due to the average pipe wall temperature change.Earthquake anchor movements are considered (Section 3.7.3.8.3A). In ASME Safety Class 1 analysis the loads due to OBE anchor movements are combined with the OBE inertia loads via absolute summation. In ASME Safety Class 2 and 3 analysis the code permits their exclusion from occasional loads if they are included with the thermal expansion loads.Thermal Loads A piping system may experience various operating modes.All operating modes are modeled as follows: Portions of piping with flowing medium have the temperature of the medium, while inactive branches have ambient temperature. Nonuniform temperature distributions along the pipe near branch connections of active and inactive legs are considered. USAR Revision 0 3.9A-4 April 1989 Nine Mile Point Unit 2 FSAR In Safety Class 1 analysis, stresses due distribution across the thickness of the geometric and material discontinuities transients must be considered. These are ASME Section III, Subarticle NB-3600, by: to temperature pipe wall and during thermal represented in E~hT , and E (~T-cx 1 2'b(aa bb((3.9A-2)Based on geometry, fluid type, transients, environmental data: insulation, thermal~hT ,~AT , and E~Ta-~T 1 2 ab a bb (3.9A-3)are obtained from the HTLOAD program (Appendix 3A), or hand calculations. USAR Revision 0 3.9A-4a April 1989 Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK USAR Revision 0 3.9A-4b April 1989 Nine Mile Point Unit 2 FSAR 3.9.1.5.2A Occasional Dynamic Loads Excluding Seismic and Hydrodynamic Inertia Loads Occasional loads are also matrix equation of motion: analyzed with NUPIPE.In the MU+CU+KU=F(t)(3.9A-4)Where: M=Mass matrix C=Damping matrix K=Stiffness matrix U=Displacement vector the forcing function F(t)is applied as a set of force time histories, one for each mass degree-of-freedom that experiences a dynamic load.Fluid Transients Fluid transients are considered in the following systems: 1.Main steam and main steam bypass systems.2.Main steam safety/relief valve (SRV)discharge system.3.Moisture separator/reheater safety relief system.4.Feedwater system.5.Emergency core cooling system (ECCS), including ECCS pressure relief valve discharge piping.6.Service water syst: em.7.Residual heat removal system.8.Reactor core isolation cooling system.9.Reactor water cleanup system.10.Standby liquid control system.11.Control rod drive system.Amendment 23 3.9A-S December 1985 Nine Mile Point Unit 2 FSAR The computer programs (Appendix 3A)used to calculate these force time histories due to water hammer, steam hammer, and pipe with air trapped in water lines, are WATHAM, STEHAM, and WATAIR, respectively. Jet Im in ement The effects of direct jet impingement on piping are evaluated after all other piping analyses are completed and targets from all postulated breaks have been identified. Amendment 19 3'A-5a May 1985 Nine Mile Point Unit 2 FSAR 3.9.3,.3A Design and Installation Details for Mounting of Pressure-Relief Devices Pressure-relieving devices for ASME Safety Class 1 and 2 system components are: 1.Main steam safety/relief valves (SRV).2.SRVs for protecting residual heat removal (RHR)system heat exchangers. The design and installation of main steam SRVs is described in Section 3.9.3.3B.4 The design and installation of SRVs for protecting the RHR system heat exchangers (Section 5.4.7.2.3) is in accordance with ASME Section III, Article NC-7000, and Regulatory Guide 1.67.Piping to and from SRVs is designed in accordance with ASME Section III, Paragraph NC-3677.The STEHAM computer program (Appendix 3A)is used to calculate fluid transient forces in each piping segment (straight pipe piece between two elbows, an elbow and a tee, or an elbow and a terminal end)downstream of the SRVs.'conservatively low value of valve opening time is used in this calculation. Water slugs in pipe segments ending in the suppression pool are taken into account.Dynamic stresses in the piping are computed by time history integration or the equivalent static methods using the NUPIPE computer program (Appendix 3A).These stresses are combined with those due to other mechanical loads, in accordance with load combinations described in Section 3.9.3.1A.Both SRVs protecting a heat exchanger are assumed to discharge concurrently. These loads meet design allowables provided by the vendor.3.9.3.4A Component Supports Expansion anchor bolts, used in supporting the mechanical components from concrete structures, are drilled-in wedge-type uniform hole anchors.Drilled-in bearing-type flared hole anchors are also used in supporting the mechanical components from concrete structures. Drilled-in wedge-type, uniform hole expansion anchors are designed for a minimum safety factor of four, as determined by the ultimate load tests performed by the manufacturer. The setting torque is determined from in-situ tests.USAR Revision 0 3.9A-23 April 1989 Nine Mile Point Unit 2 FSAR Drilled-in bearing-type, flared hole anchors are designed for a minimum safety factor of three, as determined by field testing.The loads are transferred into concrete by direct bearing against concrete.The bolt material is capable of reaching full ductility prior to failure.Due to these reasons, the anchors afford greater reliability, and a lower safety factor i's justified. The design, procurement, and installation of building steel comply with requirements of the AISC specification for the design, fabrication, and erection of structural steel for buildings, as described in Sections 3.8.4.2 and 3.8.4.6.3. The examination and inspection of building steel comply with the requirements of NRC Regulatory Guide 1.94, as described in Table 1.8-1.3.9.3.4.1A Pipe Supports The pipe support designs, using base plates and concrete.expansion anchor bolts, are performed using the flexibility criteria of NRC IE Bulletin 79-02 before they are released for fabrication. Verification of as-built conditions in accordance with NRC IE Bulletin 79-14 is.described in Section 3.7.3.8.1A. The bases for design and construction of ASME and non-ASME piping supports are given in Table 3.9A-16.USAR Revision 0 3.9A-23a April 1989 Nine Mile Point Unit 2 FSAR TABLE 3.9A-14 LOAD CONDITIONS FOR PIPE SUPPORTS Load Condition Number Plant Condition Normal Loads Primary sustained DL D~Bct 1 t So Allowable Stress ASME IZZ (1974, including Summer 1974 Addenda), Subsection NF;and Subsection NA, App XVIli Article XVZI-2000 Upset Upset Primary sustained and occasional associated with upset All primary and secondary DL+SRSS (OBEIgOCCU) DL+THER+SRSS (OBEIgOCCU) Emergency Faulted Primary sustained and occasional associated with emergency Primary sustained and occasional associated with faulted DL+SRSS (OBEIiOCCE) DL+SRSS (SSEIgOCCF) ASME III (1974, including Summer 1974 Addenda), Subsection NA, App.XVZI,-Article XVII-2110 ASME IIZ (1974, including Summer 1974 Addenda)>App.Fi Paragraph F-1370 KEY: DL OBEI OBET OCC(UiEiF) SSE THER*USAR Revision 0=Dead load=Operating basis earthquake inertia load of piping=Operating basis earthquake total, i.e., the absolute sum of the amplitudes of OBE inertia load and load due to OBE anchor movements=Primary occasional mechanical operating loads associated with upset, emergency, and faulted operating conditions, respectively, but excluding earthquake loads.Occasional loads may be vibratory or nonvibratory for load combination purposes.They are combined with each other and with other load types in the same way as in the associated piping analysis.(See notes to load combinations for piping, Table 3.9A-2).The maximum and the minimum response from each time history is used with the associated sign in the combination. =Safe shutdown earthquake inertia load of piping=Thermal load;a secondary load THER 1=Selecting the three moments from that thermal load whose three moments represent the maximum square root of the sum of the squares of the moments.The forces selected are the-most (+)of each force component along with its proper sign (each force component chosen may come from a different thermal load).THER 2=Same as for THER 1, except that the most (-)of each force component with signs is chosen.THER 3=Forces and moments are those for the normal operating condition.

• For feedwater piping, includes applicable thermal stratification load.1 of 1 April 1989

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 7.1 7'7'7'7.5 7.6 7~7 Appendixes CHAPTER 8 Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 6A.through 6C INSTRUMENTATION AND CONTROL SYSTEMS Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 7A, 7B ELECTRIC POWER Volume 13 13 13 13 13 14 15 15 15 15 15 15 15 15 15 16 16 16 16 16 16 8.1 8.2 8.3 Appendix 8A Introduction Offsite Power System Onsite Power System 16 , 16'16, 17 17 I CHAPTER 9, AUXILIARY SYSTEMS 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 ,18 19 20g21 21,22 23 I USAR Revision April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section CHAPTER 10 Title STEAM AND POWER CONVERSION SYSTEM Volume 23 10.1 10.2 10.3 10.4 CHAPTER 11 Summary.Description Turbine Generator Main Steam Supply Syst: em Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT 23 23 24 11.1 11.2 11.3 11.4 11.5 Appendix 11A Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems 24 24 25 25 25 25 CHAPTER 12 RADIATION PROTECTION 25 12.1 12.2 12.3 12.4 12.5 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR APPENDIX 3A COMPUTER PROGRAMS FOR DYNAMIC AND STATIC ANALYSIS OF CATEGORY I STRUCTURES, EQUIPMENT, AND COMPONENTS TABLE OF CONTENTS Section INTRODUCTION Title Pacae 3A-1 3A~1 3A.l.l 3A.1.2 3A.1.3 SHE LI 1 General Description Program Verification References 3A.1-1 3A.1-1 3A.l-l 3A.1-3 3A.2 3A.2.1 3A.2.2 3A.2.3 3A.3 3A.3.1 3A.3.2 3A.2.,3 ASAAS General Description Program Verification References TAC2D General Description Program Verification Ref'erences 3A.2-1 3A.2-1 3A.2-1 3A.2-4 3A.3-1 3A.3-1 3A.3-1 3A.3-5 3A.4 3A.4.'1 3A.4.2 3A.4.3 3A.5 3A.5.1 3A.5.2 3A.5.3 3A.6 3A.6.1 3A.6.2 3A.6.3 3A.7 3A.7.1 3A.7.2 3A.8 3A.8.1 3A.8.2 3A.8.3 Amendment 27 MAT 6 General Description Program Verification References STRUDL II and STRUDL-SW General Description Program Verification References Time'istory (TIMHIS6)Program General Description Program Verification References DELETED DELETED DELETED DINASAW General Description Program Verification References 3A-i 3A.4-1 3A.4-1 3A.4-1 3A~4-2 3A.5-1 3A.5-1 3A.5-1 3A.5-2 3A.6-1 3A.6-1 3A.6-1 3A.6-2 3A.7-1 3A.7-1 3A.7-1.3A.8-1 3A.8-1 3A.8-1 3A.8-3 July 1986 27 Nine Nile Point Unit 2 FSAR Section 3A.9 3A F 9.1 3A.9.2 3A.9.3 3A.10 3A.10.1 3A.10.2 3A.10.3 3A.11 3A.11.1 3A.11.2 3A.12 3A.12.1, 3A.12.2 3A.12.3 3A.13 3A~13.1 3A.13.2 3A.13.3 APPENDIX 3A TABLE OF CONTENTS (Cont)Title LIMITA II General Description Program Verification References LIMITA III General Description Program Verification References STARDYNE General Description Program Verification SSLAM General Description Program Verification References SSLOAD General Description Program Verification References Pacae 3A.9-1 3A.9-1 3A.9-4 3A.9-5 3A.10-1 3A.10-1 3A.10-2 3A.10-3 3A.ll-l 3A.ll-l 3A.ll-l 3A.12-1 3A.12-1 3A.12-1 3A.12-2 3A.13-1 3A.13-1 3A~13-1 3A:13-2 3A.14 3A.14.1 3A.14.2 3A.14.3 3A.14.4 MISSILE General Description High Trajectory Verification Low Trajectory Verification References 3A.3A.3A.3A.3A~14-1 14-1 14-1 14-2 14-3 3A.15 3A.15.1 3A.15.2 3A.15~3 3A.16 3A.16.1 3A;16.2, 3A.16'3A.17 3A.17.1 3A.17.2 3A.17.3 Amendment 19 NUPIPE General Description Program Verification References DELETED DELETED DELETED DELETED HTLOAD General Description Program Verification References 3A-ii 3A.15-1 3A.15-1 3A.15-1 3A.15-2 3A.16-1 3A.16-1 3A.16-1.3A.16-2 3A.17-1 3A.17-1 3A.17-2 3A.17-3 May 1985 N.'n~Nile Point Unit 2 FSAP.APPENDIX.3A TABLE OF CONTENTS (Cont)Section 3A.18 3A.18.1 3A.18.2 3A.18.3 3A.19" 3A.19.1 3A.19.2 3A.20 3A.20 F 1 3A.20.2 3A.20.3.3A.21 3A.21.1 3A 21.2 3A.21.3 JA.d2 3~.22.1 3.i.22.2 3A.22.3 Title GHOSH-WILSON General Description Program Verification References P SPECTRA General Description Program Verification STEHAM General Description Program Verification References WATHAM General Description Program Verification References PITRUST General Description Program Verification References ~Pa e 3A.'~.8-1 3h 1;3-)3A.18-1 3A.18-?3A.19-1 3A.19-1 3A.19-1 3A.20" 1 3A.20" 1 3A.20-1 3A.20.-2 3A.21-1 3A.21-1 3A.21-i 3A.21-z 3A.22-1 3A.22-1 3A.22-1 3A.22-2 3A.23 3A.23.1 3A~23.2 3A.23.3 3A.24 3A.24.1 3A.24.2 3A.24.:9 3A.25 3A.25.1 3A.25.2 3A.26 3A.26.1 3A.26.2 3A.26.3 PILUG General Description Program Verification References WATAI R General Description Program Verification References ANSYS General Description Program Verification CWI (Containment Wall Loading)General Description Pr'ogram Verification References 3A.23-1 3A.23-1 3A.23-1 3A.23-2 3A.24-1 3A.24-1 3A.24-1 3A.24-2 3A.25-1 3A.25-1 3A.25-2 3A.26-1 3A.26-1 3A.26-1 3n, 26 2 Nine Mile Point Unit 2 FSAR APPENDIX 3A'ABLE OF CONTENTS (Cont)23.Section 3A.27 3A.27.1 3A.27.2 3A.27.3 3A.28 3A.28.1 3A.28.2 3A.28.3 3A.28.4 3A.29 3A.30 3A.30.1 3A.30.2 3A.30.3 3A.31 3A.31.1 3A.31.2 3A.31.3 3A~32 3A.32.1 3A.32.2 3A.33 3A.33.1 3A.33.2 3A.33.3 Title LUG STR General Description Program Verification References Computer Programs for Structural Responses to Hydrodynamic Loading (TRANFUN AND INVTRAN)Introduction TRANFUN INVTRAN References NASTRAN BIJLAARD: Vessel Penetration Analysis General Description Program Verification References SLOSH: Simplified Tank Sloshing Analysis General Description Program Verification References SNUFFE: Supplement to NUPIPE for Fatigue Evaluation General Description Program Verification PITRIFE General Description Program Verification References Pacae 3A.27-1 3A.27-1 3A.27-1 3A.27-2 3A.28-1 3A.28"1 3A.28-1 3A.28-1 3A.28-3 3A.29-1 3A.30-1 3A.30-1 3A.30-1 3A.30-2 3A~31-1 3A.31-1 3A.31-1 3A.31-2 3A.32-1 3A.32-1 3A.32-1 3A.33-1 3A.33-1 3A.33-1 3A.33-2 Amendment 23 3A-iv December 1985 Nine Mile Point Unit 2 FSAR 3A.15 NUP IPE 3A.15.1 General Description NUPIPE was developed by the Nuclear Services Corporation and is fully documented.'he SWEC version of NUPIPE differs slightly from the public domain program NUPIPE in the post-processing of the analytical results.NUPIPE performs a linear elastic analysis of three-dimensional piping systems subjected to thermal, static, and dynamic loads.It utilizes the finite element method of analysis with special features incorporated to accommodate specific requirements in piping analysis.In addition, it checks analytical conformance to ASME Section III and ANSI B31.1.This program accepts the complete geometric and physical description of the piping system, provides a complete error and coordinate check for the inputs, and computes internal forces and moments, support and equipment reactions, and displacements and stress values for a variety of loading cases.3A.15.2 Program Verification NUPIPE has been verified with ADLPIPEor thermal, weight, and response spectrum seismic analyses.The results from both programs are presented in Tables 3A.15-1 through 3A.15-7.The model used for this comparison is presented on Figure 3A.15-1.The comparison is also made with ASME Benchmark solution for force time history dynamic response'. The model used for this comparison is shown on Figure 3A.15-2.The results for comparisons are presented in the form of plots on Figure 3A.15-2.The natural frequencies are given in Table 3A.15-8.The Safety Class 1 piping stress computation conforms with the hand calculations. The model used is shown on Figure 3A.15-3.The results are tabulated in Tables 3A.15-9 and 3A.15-10.3A.15-1 Nine Mile Point Unit 2 FSAR 3A.'15.3 References 1.Arthur D.I ittle, Inc.ADLPIPE: Static, Dynamic, Thermal Pipe Stress Analysis.2.American Society of Mechanical Engineers. Pressure Vessel and Piping;1972 Computer Programs Verification. Problem No.5.3A.15-2 Nine Mile Point Unit 2 FSAR APPENDIX 3B TABLE OF CONTENTS Section 3B.l 3B.2 3B.3 3B.3.1 3B.3.2 3B.3.3 3B.3.4 3B.3.5 3B.3.6 3B~3'3B.4 Title DESIGN BASES DESIGN FEATURES DESIGN EVALUATION Elevation 175 ft 0 in.215 ft 0 in.Elevation 215 ft 0 in.240 ft 0 in.Elevation 240 ft 0 in.261 ft 0 in.Elevation 261 ft 0 in.289 ft 0 in.Elevation 289 ft 0 in.306 ft 6.in.Elevation 306 ft 6 in.328 ft 10 in.Elevation 328 ft 10 in REFERENCES to Elevation to Elevation to Elevation to Elevation to Elevation to Elevation and Above Pacae 3B-1 3B-3 3B-5 3B-5 3B-6.3B-7 3B-8 3B-9.3B-10 3B-10 3B-ll USAR Revision 0 3B-i April 1989 Nine Mile Point'nit 2 FSAR APPENDIX 3B LIST OF TABLES Table Number Title 3B-1 3B-2 3B-3 3B-4 3B-5 3B-6 3B-7 HIGH ENERGY LINE BREAKS ANALYZED IN THE REACTOR BUIIDING HIGH ENERGY LINE BREAKS ANALYZED IN THE MAIN STEAM TUNNEL SUBCOMPARTMENT NODAL DESCRIPTION -HIGH ENERGY LINE BREAK"ANALYSIS IN REACTOR BUILDING SUBCOMPARTMENT,NODAL DESCRIPTION -MAIN STEAM TUNNEL HIGH ENERGY LINE BREAK'ANALYSIS SUBCOMPARTMENT VENT PATH DESCRIPTION REACTOR, BUILDING HIGH ENERGY LINE BREAK ANALYSIS (4-NODE MODEL)SUBCOMPARTMENT VENT PATH DESCRIPTION REACTOR BUILDING HIGH ENERGY LINE BREAK ANALYSIS (33-NODE MODEL)VENT PATH DESCRIPTION -MAIN STEAM TUNNEI HIGH ENERGY LINE BREAK ANALYSIS-TWO-PHASE BREAK IN MST-3 3B-8 3B-9 3B-10 3B-11 3B-12 VENT PATH DESCRIPTION -MAIN STEAM TUNNEL HIGH ENERGY LINE BREAK ANALYSIS-TWO-PHASE BREAK IN MST>>5 MASS AND ENERGY RELEASE FOR 4-IN RCIC DER IN VOLUME 175-1-BREAK NO.19 MASS, AND ENERGY RELEASE FOR 4-IN RCIC DER IN VOLUME 175-2-BREAK NO.20 MASS AND ENERGY RELEASE FOR 8-IN RWCU DER IN VOLUMES 215-1 AND 215-5 BREAK NO.16 AND 17 MASS AND ENERGY RELEASE FOR 4-IN RWCU DER IN VOLUME 215-9-BREAK NO.15 Nine Nile Point Unit 2 FSAR TABLE 38-5 SUBCOHPARTHEHT VENT PATH DESCRIPTION: HIGH-ENERGY LIKE BREAK ANALYSIS IN THE REACTOR BUILDING (45 NODE HOOEL)Vent Path Number From Vo luna Nurber To Volune Number Head Loss Coefficients Inertia Vent Factor Area L/A (1)Turning (ft2)(1/ft)Contraction Expansion Obstruction Loss Friction Sharp Edge Loss Total 1 175-'I 175-2 (a)2 175-1 175-9 (a)3 175-2 175-3 (a)4 175-2 175-3 (b)5 175-2 215-1 175-2 175-1 175-9 175-1 175-3 175-2 175-3 175-2 215-1 175-2 25.88 25.88 10.00 10.00 10.00 10.00 10.00 10.00 1.047 1.047 0.327 0.327 0.258 0.258 0.366 0.366 0.366 0.366 2.648 2.648 0.4932 0.4715 0.4517 0.4646 0.4517 0'646 O.C773 0.4982 0.8891 0.9729 0.8635 0.8161 0.8635 0.8161 0.993D 0.9113 0.200 0.200 0.3368 0.3445 0.1568 0.1546 0~1568 0.1546 0.0260 0.0260 0.0347 0.0347 0.0347 0.0347 0.0920 0.0920 0.631 0.631 1.411 1.411 1.745 1.815 1.507 1 470 1 F 507 1.470 1.762 1.702 6'175-3 175-4 175-4 175-3 21.00 21.00 0.215 0.215 0'24 0.224 0.898 1.122 1.584 1.808 7 175.4 175-5 175-5 175-4 242.86 242.86 0.015 0.015 0.200 0.200 0.994 1.194 1.847 2.047 8 175-4 175-6 175-6 175-4 265.09 265.09 0~014 0.014 0.200 0.200 0.992 1.192 1.840 2.040 9 175-4 175-7'175-7 175-4 241.26 241.26 0.014 0.014 0.2DO 0.200 0.994 1.194 1.848 2.048 10 175-4 175-8 11 175-4 175-9 175-8 175-4 175-9 175-4 240.31 240.31 140.18 140.18 0.015 0.015 0.020 0.020 0.200 0.200 0.200 0.200 0.99C 1.194 1.848 2.048 0.814 1.014 1.698 1.898 12 175-4 215-8 215-8 175-4 62.42 62.42 0.039 0.039 0.4964 0.4962 0.9849 0.9856 0.200 0.200 1.1548 1~1549 0'066 0.0066 2.843 2.843 USAR Revision 0 1 of 5 April 1989

Nine Nile Point Unit 2 FSAR TABLE 38-5 SUBCOHPARTHEHT VEHT PATH DESCRIPTION: HIGH-ENERGY LINE BREAK ANALYSIS IH THE REACTOR BUILDIHG (45 NOOE NOOEL)Vent Path Number From Volune Nunber To Volune Number Vent Area (ft2)Inertia Factor L/A (1/ft)Contraction Expansion Head Loss Coefficients Sharp (1)Turning Edge Obstruction Loss Friction Loss Total 25 215-6 215-8 215-8 215-6 21.00 N/A 0.321 N/A 0.3698 0.9655 3.424 (c)0.9010 0.0098 5.670 (c)26 27 215-8 215-9 215-8 215-10 215-9 215-8 215-10 215-8 H/A 14.33 N/A 14.33 N/A 0.313 N/A 0.313 (c)3.424 (c)3.424 2.087 2.185 (c)5.511 (c)5.609 28 215-8 240-5 240-5 215-8 52.03 52.03 0.045 0.045 0.4969 0.4970 0.9878 0.9876 0.200 0.200 1.1419 1.1418 0.0072 0.0072 2.834 2.834 29 215-9 215-10 215-10 215-9 15.75 15.75 0.414 0.414 0.4379 0.4379 0.7669 0.7669 0.0587 0.0587 0.0366 0.0366 1.300 1.300 30 240.1 240-2 240-2 240-1 101.05 101.05 0.064 0.064 0.835 0.835 0.557 0.557 31 240-1 261-1 261-1 240-1 28.38 28.38 0.336 0.336 0.200 0.200 0.652 0.852 0.379 0.579 32 240-3 240-4 240-4 240-3 37.83 37.83 0.110 0.110 0.200 0.200 0.504 0.704 1.093 1.293 33 240-3 240-5 240-5 240-3 16.38 N/A 0.234 N/A 3.424 (c)1.688 5.112 (c)34 240-3 240-3 261-3 261-3 39.68 39.68 0.143 0.143 0.200 0.200 0.867 1.617 1.067 1.817 35 36 240-5 240-7 240-5 240-8 240-7 240-5 240-8 240-5 2.299 2.299 2.299 2.299 0.091 0.091 0.093 0.093 0.4993 0.4962 0.4993 0.4958 0.9847 0.9971 0.9834 0.9971 1.2672 1.2711 1.2663 1.2707 0.0033 0.0033 0.0033 0.0033 2.755 2.768 2.752 2.767 USAR Revision 0 3of5 April 1989 0 Nine Nile Point Unit 2 FSAR TABLE 38-5 SUBCOHPARTHEHT VENT PATH DESCRIPTION: HIGH-EHERGY LINE BREAK ANALYSIS IH THE REACTOR BUILDING (45 NOOE HOOEL)Vent Path Number From Volune Number To Volune Number Vent Area (ft2)Inertia Factor L/A (1/ft)Head Loss Coefficients Sharp (1)Turning Edge Contraction Expansion Obstruction Loss Friction Loss Total 37 38 39 240-5 261-4 240.6 306-4 261-1 261-2 261-4 240-5 306-4 240.6 261-2 261-1 67.45 67.45 21.15 21.15 33.26 33.26 0.029 0.029 1.674 1.674 0.169 0.169960 0.4967 0.9868 0.9840 0.188 0.188 0.200 0.200 1.1615 1.1606 0.768 0.181 0.0064 0.0064 2.839 2.836 1.146 1.914 0.663 0.844 0.938 1.138 1.246 1.446 40 261-1 261-4 261-4 261-1 15.93 H/A 0.213 N/A 3.424 (c)1.765 5~189 (c)41 42 43 261-2 289-1 261-3 261-5 261-4 289-3 289-'I 261-2 261-5 261-3 289-3 261-4 26.30 26.30 49.95 49.95 503.31 503.31 0.293 0.293 0.227 0.227 0.010 0.010 0.4802 0.4796 0.9199 0.9224 0.200 0.200 0.200 0.200 1'607 1.0614 0.0023 0.0023 0.775 0.975 0.897 1.097 0.220 0.420 0.198 0.398 2.463 2.466 261-5 289-2 289-2 261-5 65.75 65.75 0.174 0.174 0.200 0.200 0'82 0.482 0.235 0.435 45 46 47 289.1 306-1 289-2 306-4 289-3 306-5 289-3 306-5 306-1 289-1 306-4 289-2 306-5 289-3 306-5 289-3 40.82 40.82 36.86 36.86 2079.0 2079.0 2590.0 2590.0 0.174 0.174 0.169 0.169 0.010 0.010 0.010 0.010 0.3166 0.4676 0.4156 0.3910 0.3948 0.3643 0.8746 0.4010 0.6116 0.6907 0.5307 0.6235 0.200 0.200 0.400 0.400 0.7511 0.6182 0.9317 0.9605 0.8459 0.8858 0.0108 0.0108 0.0015 0~0015 0.0013 0.0013 1.168 0.520 1.368 0.720 2.353 1.898 1.960 2.044 1.773 1.875 USAR Revision 0 4of5 April 1989

Nine Nile Point Unit 2 FSAR TABLE 38-5 SUBCOHPARTHENT VENT PATH DESCRIPTION: HIGH-ENERGY LINE BREAK ANALYSIS IN THE REACTOR BUILDING (45 NODE MODEL)Vent Path Number From Volcano Humber To Volune Nunber Inertia Vent Factor Area L/A (ft2)(1/ft)Contraction Expansion Head Loss Coefficients Sharp (1)Turning Edge Obstruction Loss Friction Loss Total 49 306.1 306-2 245.99 0.014 306.2 306-1 245.99 0.014 2.311 2.311 2.390 2.390 50 306-1 328-2 8.956 0.401 0.4969 0.9731 328-2 306-1 8.956 0.401 0.4932 0.9875 0~1645 0.1651 0.0272 0.0272 1.662'I.673 51 306-2 306-3 136.80 0.035 306.3" 306-2 136.80 0.035 1.645 1.645 1.959 1.959 52 306.3 306-4 92.48 0.445 306-4 3D6.3 92.48 0.445 0.324 0.324 0.390 0.390 53 306-5 328-1 508.58 0.010 0.4733 0.7057 328-1 306-5 508.58 0.010 0.4200 0.8962 1.0504 1.1151 0.0023 0.0023 2 232 2.434 5C 328-1 353-1 502.88 0.010 0.4209 0.9554 353-1 328-1 502.M 0.010 O.C887 0.7087 1.1522 1.0693 0.0023 0.0023 2.531 2.269 (1): The obstruction Loss includes losses from a grill, grating, wire mesh door, and/or vent curtains.These losses are described in Section 38.2: Design Features.(a): This vent path is a blowout panel.The values in this table are for after the panel has fully opened (if it is not assumed to foil closed under the single-fai lure criteria). The blowout panel is fully open 0.3 seconds after a 0.5 psid force is applied across it.The panel opens in the direction shown in the top listing for the vent path.(b): This Junction is used only for Break Numbers 6 and 9.This is explained in Table 38-1: High-Energy Line Breaks Analyzed in the Reactor Building and Section 38.3.2: Elevation 215'0<<to Elevation 240'0<<.(c): This J~tion has vent curtains.The curtain allo~s flow in onLy one direction. Vent curtains are discussed in Section 3B.2: Design Features, Section 3B.3.2: Elevation 215~0<<to Elevation 240'0", Section 3B.3.3: Elevation 240'0<<to Elevation 261'0", and Section 38.3.4: Elevation 261'0<<to Elevation 289'0<<.NOTE: the honogeneous equfL Ibrfun model (HEN)for choked flow is used for all breeks and nodalizations. Appendix 6B: THREED Subncompartment Analytical Nodal gives a description of the HEH used in the SWEC computer code THREED.USAR Revision 0 5of5 April 1989 0 Nine Hite Point Unit 2 FSAR TABLE 3B-6 SUBCOHPARTNENT VENT PATH DESCRIPTIOH: HIGH-ENERGY LINE BREAK ANALYSIS IH THE REACTOR BUILDIHG (46 HODE NODEL)Vent Path Number From Volune Number To Volune Number Vent Area (f t2)Inertia Factor L/A (1/f t)Contraction Expansion Head Loss Coefficients Sharp (1)Turning Edge Obstruction Loss Friction Loss Total 175-1 175.2 (a)2 175-1 175-9 (a)3 175-2 175-3 175.2 175-1 175-9'175-1 175-3 175-2 25.88 25.88 10.00 10.00 10.00 10.00 0.327 0.327 0.258 0.258 0.366 0.366 0.4932 0.4715 0.4517 0.4646 0.8891 0.9729 0.8635 0.8161 0.3368 0.3445 0.1568 0.1546 0.0260 0.0260 0.0347 0.0347 0.631 0.631 1.411 1.411 1.745 1.815 1.507 1.470 175-2 215-1 215-1 175-2 1.047 1.047 2.648 2.648 0.4773 0.4982 0.9930 0.9113 0.200 0.200 0.0920 0.0920 1.762 1.702 175-3 175-4'175-4 175-5 175-4 175-3 175-5 175-4 21.00 21.00 242.86 242.86 0.215 0.215 0.015 0.015 0.224 0.224 0.200 0.200 0.898 1.122 1.584 1.808 0.994 1.194 1.847 2.047 175-4 175-6 175-6 175-4 265.09 265.09 0.014 0~014 0.200 0.200 0.992 1.192 1.840 2.040 10 12 175-4 175-7 175-4 175-8 175-4 175.,9 175-4 215-8 175-10 215-3 175.7 175.4 175-8 175-4 175-9 175-4 215.8 175-4 215-3 175-10 241.26 241.26 240.31 240.31 140.18 140.18 62.42 62.42 81.30 81.30 0.014 0.014 0.015 0.015 0.020 0.020 0.039 0.039 0.121 0.121 0.4964 0.4962 0.9849 0.9856 0.200 0.200 0'00 0.200 0.200 0.200 0.200 0.200 0.200 0.200 1.1548 1.1549 0.0066 0.0066 0.994 1.194 1.848 2.048 0.994 1.194 1.848 2.048 0.814 1.014 1.698 1.898 2.843 2.843 1.337 1.537 0.763 0.963 USAR Revision 0 1of6 April 1989

Nine Nile Point Unit 2 FSAR TABLE 38-6 SUBCOHPARTNENT VENT PATH DESCRIPTION: HIGH-ENERGY LINE BREAK AHALYSIS IN THE REACTOR BUILOIHG (46 NODE MODEL)Vent Path Nurher From Voiune Nunber To Voiune Number Vent Area (ft2)Inertia Factor L/A (1/f t)Head Loss Coefficients Sharp (1)Turning Edge Contraction Expansion Obstruction Loss Friction Loss Total 25 26 27 215-8 215-9 215-8 215-10 215;8 215-8 215-9 215-8 215-10 215-8 240-5 240-5 N/A 14.33 H/A 14.33 52.03 52.03 N/A 0.313 N/A 0.313 0.045 0.045 0.4969 0.4970 0.9878 0.9876 (b)3.424 (b)3.424 0.200 0.200 1.1419 1.1418 0.0072 0.0072 2.087 2.185 (b)5.511 (b)5.609 2.834 2.834 28 215-9 215-10 215-10 215-9 15.75 15.75 0.414 0.414 0.4379 0.4379 0.7669 0.7669 0.0587 0.0587 0.0366 0.0366 1.300 1.300 29 240-1 240-2 240-2 101.05 240-1 101.05 0.064 0.064 0.835 0.835 0.557 0.557 30 31 240-1 261-1 240-3 240-4 261-1 240-1 240-4 240-3 28.38 28.38 37.83 37.83 0.336 0.336 0.110 0.110 0.200 0.200 0.200 0.200 0.652 0.852 0.379 0.579 0.504 0.704 1'93 1'93 32 240-3 240-5 240-5 240.3 16.38 H/A 0.234 H/A 3.424 (b)1.688 5.112 (b)33 240-3 240-3 261-3 261-3 39.68 39.68 0.143 0.143 0'00 0.200 0.867 1.617 1.067 1.817 34 240.5 240-7 240-7 240-5 2.299 2.299 0.091 0.091 0.4993 0.4962 0.9847 0.9971 1.2672 1.2711 0.0033 0.0033 2.755 2.768 35 240.5 240-8 240.8 240-5 2.299 2.299 0.093 0.093 0.4993 0.4958 0.9834 0.9971 1.2663 1.2707 0.0033 0.0033 2.752 2.767 36 240-5 261-4 261-4 240-5 67.45 67.45 0.029 0.029 0.4960 0.4967 0.9868 0.9840 0.188 0.188 1.1615 1.1606 0.0064 0.0064 2.839 2.836 USAR Revision 0 3of6 April 1989

Nine Nile Point Unit 2 FSAR TABLE 38-6 SUBCONPARTHENT VENT PATH DESCRIPTION: HIGH-ENERGY LINE BREAK ANALYSIS IN THE REACTOR BUILDING (46 NODE HODEL)Head Loss Coefficients Vent Path Number Fram Volune Number To Volune Number Vent Area (ft2)Inertia Factor L/A (1)Turning (1/ft)Contraction Expansion Obstruction Loss Sharp Edge Friction Loss Total 37 240.6 306.4 306-4 240-6 21.15 21.15 1.674 1.674 0.768 0.181 1.146 1.914 0.663 0.844 38 261.1 261-2 261-2 261-1 33.26 33.26 0.169 0.169 0.200 0.200 0.938 1.138 1.246 1.446 39 261-1 261-4 261-4 261-1 15.93 N/A 0.213 N/A 3.424 (b)1.765 5.189 (b)40 261-2 289.1 289-1 261-2 26.30.26.30 0.293 0.293 0.200 0.200 0.775 0.975 0.897 1.097 41 261-3 261-5 261-4 289.3 261-5 261-3 289-3 261-4 49.95 49.95 503.31 503.31 0.227 0.227 0.010 0.010 0.4802 0.4796 0.9199 0.9224 0.200 0.200 1.0607 1.0614 0.0023 0.0023 0.220 0.420 0.198 0.398 2.463 2.466 43 261-4 289-3 289-3 261-4 197.42 197.42 0.010 0.010 0.4922 0.4920 0.9682 0.9692 1.2078 1.2080 0.0040 0.0040 2.672 2.673 44 261-5 289-2 289-2 261-5 65.75 65.75 0.174 0.174 0.200 0.200 0.282 0.482 0.235 0.435 45 289-1 306-1 306-1 289-1 40.82 40.82 0.174 0.174 0.200 0.200 1.168 0.520 1.368 0.720 46 289.2 306.4 306-4 289-2 36.86 36.86 0.169 0.169 0.3166 0.4676 0.8746 0.4010 0.400 0.400 0.7511 0.6182 0.0108 0.0108 2.353 1.898 47 289.3 306.5 306-5 289-3 2079.0 2079.0 0.010 0.010 0.4156 0.3910 0.6116 0.6907 0.9317 0.9605 0.0015 0.0015 1.960 2.044 48 289-3 306-5 306-5 289-3 2590.0 2590.0 0.010 0.010 0.3948 0.3643 0.5307 0.6235 0.8459 0.8858 0.0013 0.0013 1.773 1.875 USAR Revision 0 4of6 April 1989 4 Hine Nile Point Unit 2 FSAR TABLE 38-6 SUBCONPARTHENT VENT PATH DESCRIPTIOH: HIGH-ENERGY LINE BREAK ANALYSIS IH THE REACTOR BUILDING (46 NODE HOOEL)Vent Path Number From Volune Number To Volune Number Vent Area (ft2)Inertia Factor L/A (1/f t)Head Loss Coefficients Sharp (1)Turn>ng Edge Contraction Expansion Obstruction Loss Friction Loss Total 49 289-3 306-5 306.5 289.3 202'6 202.16 0.010 0.010 0.4918 0.4894 0.9581 0.9674 1.2022 1.2050 0.0039 0.0039 2.656 2.666 50 51 306-1 306.2 306-1 328-2 306-2 306.1 328-2 306-1 245.99 245.99 7.192 7.192 0.014 0.014 0.493 0.493 0.4969 0.4932 0.9731 0.9S75 0.200 0.200 0.1645 0.1651 0.0272 0.0272 2.311 2.311 2.390 2.390 1.862 1.873 52 53 306-2 306.3 306-3 306-4 306-3 306-2 306-4 306-3 136.80 136.80 92.48 92.48 0.035 0.035 0.445 0.445 1.645 1.645 1.959 1.959 0.324 0.324 0.390 0.390 306-5 328-1 328-1 306-5 508.58 508.58 0.010 0.010 0.4733 0.4200 0.7057 0.8962 1.0504 1.1151 0.0023 0.0023 2 232 2.434 55 328-'I 353-1 353-1 328-1 502.88 502.88 0.010 0.010 0.4209 0.4887 0.9554 0.7087 1.1522 1.0693 0.0023 0.0023 2.531 2.269 56 SC328190 306-1 306-1 SC328190 0.170 0.170 20.65 20.65 0.5000 0.5000 1.0000 1.0000 0.2618 0.2618 1.762 1.762 57 SC328190 306-1 306-1 SC328190 0.049 0.049 71.51 71.51 0.5000 0.5000 1.0000 1.0000 0.5862 0.5862 2.086 2.086 5e SC32e190 306-1 306-1 SC328190 59 SC328190 328-2 328-2 SC328190 60 SC328190 328-2 328-2 SC328190 0.863 0.863 0.718 0.718 0.718 0.718 4.098 4.098 4.915 4.915 4.915 4.915 0.5000 0.5000 0.5000 0.5000 0.5000 0.5000 1.0000 1.0000 1.0000 F 0000 1 F 0000 1.0000 0.1458 0.1458 0.1458 0~1458 0~1458 0.1458 1.646 1.646 1.646 1.646 1.646 1.646 USAR Revision 0 5of6 April 1989

Nine Nile Point Unit 2 FSAR TABLE 38-6 SUBCOHPARTHEHT VEHT PATH DESCRIPTION: HIGH-ENERGY LINE BREAK ANALYSIS IH THE REACTOR BUILDING (46 NODE HODEL)Vent Path Number From Voiune Nunber To Volune Hwher Vent Area (ft2)Inertia Factor L/A (1/ft)Contraction Head Loss Coefficients Sharp (1)Turning Edge Expansion Obstruction Loss Friction Loss Total 61 SC328190 328-2 328-2 SC328190 0.181 0.181 19.390 19.390 0.5000 0.5000 1.0000 1.0000 0.3537 0.3537 1.854 1.854 62 SC328190 328-2 328-2 SC328190 0.181 0.181 19.390 19.390 0.5000 0.5000 1 F 0000 1.0000 0.3537 0.3537 1.854 1.854 63 SC328190 328-2 328-2 SC328190 0.181 0.181 19.390 19.390 0.5000 0.5000 1.0000 1.0000 0.3537 0.3537 1.854 1.854 64 SC328190 328-2 328-2 SC328190 0.181 0.181 19.390 19.390 0.5000 0.5000 1.0000 1.0000 0.3537 0.3537 1.854 1.854 This nodalization model is used for the 6" RNCU breaks in Voiunes 328-2 and SC328190~The fire deeper Junction between Volwes 175-2 and 215-1 is assumed to be open for the entire transient. (1): The obstruction loss includes losses from a grill, grating, wire mesh door, and/or vent curtains.These losses are described in Section 38.2: Design Features.(a): This vent path is a blowout panel.The values in this table are for after the panel has fully opened.The blowout panel is fully open 0.3 seconds after a 0.5 psid force is applied across it.The panel opens in the direction shown in the top listing for the vent path.(b): This Junction has vent curtains.The curtain allows flow in only one direction. Vent curtains are discussed in Section 3B.2: Design Features, Section 38.3.2: Elevation 215'Oa to Elevation 240'0", Section 38.3.3: Elevation 240'0" to Elevation 261'0", and Section 38.3.4: Elevation 261'Ow to Elevation 289'0".NOTE: The homogeneous equi Iibriun model (HEH)for choked flow is used for all breaks and nodalizations. Appendix 68: THREED Submcompartment Analytical Nodal gives a description of the HEH used in the SPEC computer code THREEO.USAR Revision 0 6of 6 April 1989

TO 261-4 FROM 215-8 TO 261-3 240-5 GENERAL AREA 240-3 TIP GU Bl GLE TO 261-1 240-7 PENETRATION AREA 240-8 PENETRATION AREA 240-1 PIPE CHASE 240-2 PENETRATION AREA 240"4 PIPE CHASE FROM 215-1 FROM 215-2 NOTES: s VENT CURTAIN JUNCTION~COON WITN LOUVER s DIRECTION Of VENT FLOW VOLUIIE 240 4 IS SHOWN ON SHEET 4 OF FIOURE SS I FIGURE 3B-2 NODALI2ATION DIAGRAM-REACTOR BUILDING HIGH-ENERGY LINE BREAK ANALYSIS (4S N ODE MODEL)SHEET 3 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989 4 Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK Amendment 18 3C-11b March 1985 Nine Mile Point Unit 2 FSAR reactor or that could increase the offsite radiation beyond the limits of 10CFR100.3C.2.9.2 RPV Steam Vent Line 28)The locations of postulated pipe breaks are shown on Figure 3.6A-15.The main steam 2-in vent line branches off the main steam line (2MSS-026-43-1) at.el 314 ft 10 in.It then loops its way up to el 342 ft 8 ll/16 in and drops vertically into the RPV head.28 28 I The MSS piping, if allowed to whip, could impact, targets such as drywell head, vessel dome, insulation support structure, main steam line 2MSS-026-43-1, and rupture restraint 2RHS*PRR014. Since the piping is a 2-in diameter line, the impacting forces of the piping system are relatively small and will not cause detrimental results to the targets mentioned above.The pipe whip due to a break in this line will not cause any loss of structural integrity to the targets mentioned above.Conclusions Using very conservative assumptions and criteria, no postulated failure of the MSS vent line can cause damage that could impair the ability to safely shut down the reactor or that could increase the offsite radiation effects beyond the limits of 10CFR100.3C.2.10 Main Steam Safety Relief Valve Piping (SVV)as f sa/The location of pipe breaks are shown on Figures 3.6A-16 and 3.6A-17'he main steam safety relief valve piping for each of the 18 SRVs consists of an 8-in connection off the main steam line to the SRV and a 10-in discharge line from the SRV to the suppression pool.The high-energy portion of the system is the 1-ft length for the connection from main steam pipe to the normally closed SRV.Two breaks are postulated for each SRV;they are terminal point, circumferential breaks for the 8-in connection. Targets from pipe whip are the 12-in RHS lines.Impact analysis shows failure of SVV piping cannot cause additional damage that could impair the Amendment 28 I'C-12 May 1987 Nine Mile Point Unit 2 FSAR TABLE'OF CONTENTS (Cont).Section 5.3 5.4 Appendixes CHAPTER 6 Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Volume 13 13 13 13 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes 6A.through 6C Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components 13 14 15 15 15 15 15 CHAPTER 7 7.1 7'7~3 7'7.5 7.6 7'Appendixes CHAPTER 8 INSTRUMENTATION AND CONTROL SYSTEMS Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 7Ai 7B ELECTRIC POWER 15 15 15 15 16 16 16 16 16 16 8.1 8.2 8.3 Appendix 8A Introduction Offsite Power System Onsite Power System=-16 , 16'16, 17 17 I~CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17.18 19 20,21 21,22 23 USAR Revision 0 April 1989 Nine Nile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section CHAPTER 10 Title STEAM AND POWER CONVERSION SYSTEM Volume 23 10.1 10.2 10.3 10.4 CHAPTER Summary Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System RADIOACTIVE WASTE MANAGEMENT 23 23 24 11.1 11.2 11.3~11.4 11.5 Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems Appendix 11A CHAPTER 12 RADIATION PROTECTION 24 24 25 25 25 25 25, 12.1-12.2 12.3 12.4.12.5 Ensuring That, Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program 25 25 25 26 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 13.2 13'13.4 13.5.13.6 Appendixes Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 26 26 26 26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific"Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26 Nine Mile Point Unit 2 FSAR CHAPTER 5 LIST OF FIGURES Figure Number 5.l-la 5.l-lb 5.1-2a, b, c 5.2-1 5.2-2 5.2-3 5.2-4 5.2-5 5.2-5a 5.2-6 5.2-7 5.2-8 5.2-9 5.3-1 5.3-2 5.3-3 5.3-4 Title RATED OPERATING CONDITIONS OF THE BOILING WATER REACTOR COOLANT VOLUMES OF THE BOILING WATER REACTOR NUCLEAR BOILER SYSTEM SAFETY RELIEF VALVE CAPACITY SIZING TRANSIENT"MSIV CLOSURE WITH HIGH FLUX TRIP" SAFETY RELIEF VALVE SCHEMATIC ELEVATION SAFETY RELIEF VALVE AND STEAM LINE SCHEMATIC NUCLEAR BOILER SYSTEM PAID SCHEMATIC OF SAFETY RELIEF VALVE WITH AUXILIARY ACTUATING DEVICE ABNORMAL AMBIENT CONDITIONS FOR ACTUATOR QUALIFICATION TEST TYPICAL BWR FLOW DIAGRAM CONDUCTIVITY'Hg CHLORIDE CONCENTRATION OF AQUEOUS SOLUTIONS AT 77 F (25 C)CALCULATED LEAK RATE VS CRACK LENGTH AS A FUNCTION OF APPLIED HOOP STRESS AXIAL THROUGHWALL CRACK LENGTH DATA CORRELATION BRACKET FOR HOLDING SURVEILLANCE CAPSULE MINIMUM TEMPERATURES REQUIRED VERSUS REACTOR PRESSURE PREDICTED ADJUSTMENT OF REFERENCE TEMPERATURE"A" AS A FUNCTION OF FLUENCE AND COPPER CONTENT REACTOR VESSEL USAR Revision 0 5-ix April 1989 Nine Mile Point'Unit 2 FSAR CHAPTER 5 LIST OF FIGURES (Cont)Figure Number 5.3-5 Title NOMINAL REACTOR VESSEL WATER LEVEL TRIP AND ALARM ELEVATION SETTINGS 5.4-1 RECIRCULATION SYSTEM ELEVATION AND ISOMETRIC 5.4-2a through REACTOR RECIRCULATION SYSTEM P&ID 5.4.26 5.4-3 5.4-4 5.4-5 5.4-6 5.4-7 5.4-8 RECIRCULATION PUMP HEAD, NPSH, FLOW AND EFFICIENCY CURVES OPERATING PRINCIPLE OF JET PUMP CORE FLOODING CAPABILITY OF RECIRCULATION SYSTEM MAIN STEAMLINE FLOW RESTRICTOR MAIN STEAM ISOLATION VALVE CUTAWAY VIEW DELETED 5.4-9a through RCIC SYSTEM 5.4-91 5.4-10 5.4-10a 5.4-10b 5.4-11 5.4-12 REACTOR CORE ISOLATION COOLANT SYSTEM PROCESS DIAGRAM RCIC TURBINE CHARACTERISTIC CURVES STEAM FLOW VS.POWER RCIC TURBINE CHARACTERISTIC CURVES STEAM FLOW VS.PRESSURE VESSEL COOLANT TEMPERATURE VERSUS TIME (TWO HEAT EXCHANGERS AVAILABLE) VESSEL COOLANT TEMPERATURE VERSUS TIME (ONE HEAT EXCHANGER AVAILABLE) 5.4-13a through RHR SYSTEM 5.4-13g USAR Revision 0 5-x April 1989 Nine Mile Point Unit 2 FSAR CHAPTER 5 LIST OF FIGURES (Cont)Figure Number 5.4-14 5.4-15 Title RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM AND DATA RHR PUMP CHARACTERISTIC CURVES 5.4-16a through REACTOR WATER CLEANUP AND FILTER 5.4-16f DEMINERALIZER SYSTEM PAID 5.4-17 5.4-18 REACTOR WATER CLEANUP SYSTEM DELETED USAR Revision 0 5-xa April 1989 ,Nine Mile Poi.nt Unit 2 FSAR THIS PAGE INTENTIONALlY BLANK Amendment 7 5-xb December 1983 Nine Mile Point Unit 2 FSAR (See Section 3.9.6A for the program for pumps and valves.)Subsequent inservice inspections will be performed in accordance with the requirements of 10CFR50.55a(g) as described in the Inservice Inspection Program.5.2.5 Reactor Coolant Pressure Boundary and ECCS Leakage Detection System 5.2.5.1 Leakage Detection Methods The nuclear boiler leak detection system (LDS)consists of temperature, pressure, level, flow, airborne gaseous and particulate fission product sensors, and process radiation sensors with associated instrumentation used to indicate and alarm leakage from the RCPB.The LDS in certain cases is used to initiate signals used for automatic closure of isolation valves to shut off leakage external to the containment. The system is assessed to be in conformance with Regulatory Guide 1.45.Those portions of the system which affect automatic isolation of leakage are designed to IEEE 279-1971 (refer to Table 3.2-1).Abnormal leakage from the following systems within the containment and within the selected areas of the plant outside the primary containment is detected, indicated, alarmed, and in certain cases, isolated.1.Main steam lines.2.RWCU system.3.RHR system.4 5.RCIC system.Feedwater system.6.HPCS.7.Coolant systems within the containment. 8.LPCS.9.RPV.10.Miscellaneous systems.Leak detection methods used to obtain conformance with Regulatory Guide 1.45 for plant areas inside the primary containment differ from those for areas located outside the Amendment 26 5.2-29 May 1986 Nine Mile Point Unit 2 FSAR primary containment. These areas are considered separately in the following sections.5.2.5.1.1 Detection of Leakage Within the Primary Containment The primary detection methods for small unidentified leaks within the primary containment include continuous monitoring of drywell floor drain tank fill rate and airborne gaseous and particulate radioactivity increases.(The sensitivities of these primary detection methods for unidentified leakage within the primary containment are listed in Table 5.2-8.)These variables are continuously indicated and/or recorded in the control room.If the unidentified leakage increases to a total of 5 gpm, the detecting instrumentation channel(s) will trip and activate an alarm in the main control room.This does not result in a containment isolation signal.The secondary detection methods (i.e., the monitoring of pressure and temperature of the primary containment atmosphere) are used to detect gross unidentified leakage.High primary containment pressure will alarm and trip the isolation logic which results in closure of the containment isolation valves.The detection of small identified leakage within the primary containment is accomplished by continuous drywell equipment drain tank fill rate monitoring. An alarm will be activated!in the main control room when the leak rate reaches 25 gpm averaged over a 24-hr period.The determination of the source of identified leakage within the primary containment is accomplished by monitoring the drain lines to the drywell equipment drain tank from various potential leakage sources.These include reactor recirculation pump seal drain flow and reactor vessel head seal drain line pressure.Additionally, temperature is monitored in the SRV discharge lines to the suppression pool to detect leakage through each of the SRVs.All of these monitors, except the reactor recirculation pump seal drain flow monitor, continuously indicate and/or record in the control room.All of these monitors trip and activate an alarm in the control room on detection of leakage from monitored components. Excessive leakage inside the primary containment (e.g., process line break or LOCA within primary containment) is detected by high primary containment pressure, low reactor water level or high steam line flow (for breaks downstream USAR Revision 0 5.2-30 April 1989 Nine Mile Point Unit 2 FSAR of the flow elements). The instrumentation channels for these variables trip when the monitored variable exceeds a predetermined limit to activate an alarm and trip the isolation logic which closes appropriate isolation valves (Table 5.2-9).The alarms and indication and isolation trip functions initiated by the LDSs are summarized in Tables 5.2-9 and.5.2-10.5.2.5.1.2 Detection of Leakage External to the Primary Containment (Within Reactor Building)The detection of leakage within the reactor building (outside the primary containment) is accomplished by detection of increases in reactor building floor drain sump and reactor building equipment drain tank fillup time and pumpout , time (Section 5.2.5.2.2). The reactor building floor drain sump monitors will detect unidentified leakage increases and activate an alarm in the main control room.The reactor building equipment drain tank monitors will detect identified leakage increases and activate an alarm in the main control room when leakage increases above normal background levels.See Section 5.2.5.2.2 for a discussion of the fuel pool liner leakage detection method.5'.2.5.1.3 Detection of Leakage External to the Primary Containment Areas outside the primary containment that are monitored for primary coolant leakage are: equipment areas in the auxiliary bays, the main steam tunnel, and the turbine buildi'ng. The process piping for each system to be monitored for leakage is located in compartments or rooms separate from other systems where feasible so that leakage may be detected by area temperature indications. These areas are monitored by dual element thermocouples for sensing high ambient temperature in all these areas and high differential temperature between the inlet and"outlet ventilation ducts in the main steam tunnel.The temperature elements are located or shielded so that they are sensitive to air temperature only and not to radiated heat from hot piping or equipment. Increases in ambient and/or differential temperature indicate leakage of reactor coolant USAR Revision 0 5.2-31 April 1989 Nine Mile Point Unit 2 FSAR 23 into the area.The monitors located in the main steam tunnel and turbine building have sensitivities suitable for detection of increases in ambient air temperature which are equivalent to reactor coolant leakage into the monitored areas of 2S gpm or less.The temperature trip set points are a function of room size and the type of ventilation provided.These monitors provide alarm, indication, and recording in the main control room, and'rip the isolation logic to close selected isolation valves (e.g., the main steam tunnel monitors close the MSIV and main steam line drain isolation valves and other valves[Table 5.2-9]).23 The turbine building temperature monitors alarm and indicate in the main control room and trip the isolation logic to close the main steam isolation and main steam line drain isolation valves when leakage exceeds 2S gpm.These sensors monitor ambient temperature in the enclosed space between the steam tunnel outlet and the inlet to the high pressure turbine.23 23 Excess-leakage external to the containment (e.g., process line break outside containment.) is detected by.low reactor water level, high process line flow, high ambient temperature in the piping or equipment areas, high differential flow, and low main condenser vacuum.These monitors provide alarm and indication in the main control room and trip the isolation logic to cause closure of appropriate system isolation valves on indication of excess leakage (Table 5.2-9).Set points for the high ambient temperature monitors in the piping and equipment areas of the reactor building and auxiliary bays are based on limiting the maximum environmental conditions of these areas to within the environmental qualification capabilities of the applicable equipment. 5.2.5.1.4 Intersystem Leakage Monitoring Leakage from the HPCS, LPCS, RCIC, and RHR systems outside containment is detected by a combination of methods, including high area temperature, high area radiation, high sump level, and reactor pressure vessel condition (see Section 5.2.5.1~3).Radiation monitors are used to detect reactor coolant leakage into cooling water systems supplying the RHR heat exchangers and the RWCU nonregenerative heat exchanger. These monitoring channels are part of the process radiation monitoring system.Process radiation monitoring channels monitor for leakage into each common cooling water header downstream of the RHR heat exchangers and the RWCU Amendment 23 5.2-32 December 1985 Nine Nile Point Unit 2 FSAR TABLE 5.2-1 (Cont)Code Case Number/Revision Applicable RaJ'-"" Title The required exposure times for low hydrogen electrodes were adhered to except for the exposure times were increased slightly for some site welding.For electrode E70XX, the exposure time was increased form 4 to 5 hr, and for electrode E80XX, from 2 to 4 hr.'n these cases, all covered electrodes continued to be issued in heated portable rod ovens.The increased exposure times are based on industry usage data and test data to meet the intent of Regulatory Guide 1.85 and Code Case 1644-9 requirements. Amendment 24 3b of 8 February 1986

Nine Mile Point Unit 2 FSAR TABLE 5'-8 LEAK DETECTION METHODS, ACCURACY, AND SENSITIVITY Leak Detection Method Drywell floor drain tank level Drywell equipment drain tank level 4 Airborne particulates Gaseous radioactivity ~Accurac 1 gpm 1 gpm Sensitivit 1 gpm/hr 1 gpm/hr 6.6-12 uCi/cc.9-07 uCi/cc'~'OTE: 6.6-12=6.6x10The airborne particulate radiation level corresponding to a 1" gpm/hr leak rate is 1.1-07 uCi/cc.'~'The gaseous radioactivity level corresponding to a 1 gpm/hr leak rate is 6.3-07 uCi/cc.Amendment 19 1 of 1 May 1985

~~l t Nine Mile Point Unit 2 FSAR r requirements. The'material for studs, nuts, and washers is SA-540 Grade B23 or B24 at the 130,000 psi-specified minimum yield strengths level.Hardness.tests are performed on all main closure bolting to demonstrate 'that heat treatment has been properly performed. A minimum of 45 ft-lb Charpy V-notch (C)energy and 25 mils V , lateral expansion is required at 70~F.The maximum reported ultimate tensile strength is below the 170,000-psi maximum specified. in Regulatory Guide 1.65.Also, the Charpy impact test, requirements of 10CFR50 Appendix G are satisfied, since the lowest reported Q energy is 46 ft-lb at+10OF, compared to the requirement of 45 ft-lb at 70 F, and the lowest reported C>expansion was 26 mils, compared to the 25 mils required.Studs, nuts, and washers are ultrasonically examined in accordance with ASME Section III, Paragraph NB-2585, and the following additional require-ments: 1.Examination was performed after heat treatment and prior to machining threads.2.3.Straight beam examination was performed on 100 percent of each stud.Reference standard for the radial scan is a 1/2-in diameter flat-bottom hole having a depth equal to 10 percent of the material thickness. For the end scan the standard of Paragraph NB-2585 is used.Nuts and washers were examined by angle beam from the outside circumference in accordance with ASME SA-388 in both the axial and circumferential directions. The.surface examinations required by Paragraph NB-2583 are applied after heat treatment and threading. There are no metal platings applied to closure studs, nuts, or washers.A-manganese-phosphate coating is applied to threaded areas of studs and nuts and bearing areas of nuts and washers to assist in retaining lubricant on these surfaces.Subsequent to fabrication, the studs are lubricated with a graphite/alcohol or nickel powder base lubricant. Regulatory Guide 1.65 defines acceptable materials and testing procedures with regard to reactor vessel closure stud bolting for light-water-cooled reactors.Amendment 11 5.3-9 June 1984 Nine Mile Point Unit: 2 FSAR The RPV closure studs are SA-540 Grade B23 or 24 (AISI-4340) and have a maximum ultimate tensile strength of 170 ksi.Additionally,=,the bolting material.was specified to have Charpy V-notch impact properties of 45 ft-lb minimum with 25 mils lateral expansion. Nondestructive examination before and after threading is specified to be in accordance ,,with=ASME Section III, Subsubarticle NB-2580 which complies with Reglatory Guide 1.65 (C.2).In accordance with Regulatory Guide 1.65 (C.2.b), the bolting materials were ultrasonically examined after final heat treatment and prior to threading. As required for compliance, the examination 'as done in accordance with SA-388., The procedures approved for use in practice were judged to ensure comparable material quality and, moreover, were considered adequate on the basis of compliance with the applicable" requirements of ASME Section III, Paragraph NB-2583.Additionally,'straight beam examination was performed on 100 percent of cylindrical surfaces, and from both ends of each stud using a 3/4-in maximum diameter transducer. In addition to the code-required notch, the reference standard for the radial scan contained a 1/2-in diameter flat-bottom hole with a depth equal to 10 percent of the thickness'he end scan standard contained a 1/4-in diameter flat-bottom hole 1/2-in deep.Angle beam ,ultrasonic examination was performed on the outer cylindrical surface in both a flat and circumferential .direction. Surface examinations were performed on the studs and nuts after final heat treatment and threading, as specified by Regulatory Guide 1.65, in accordance with Paragraph NB-2583 of the applicable ASME code.Radial scan-calibration is based on a 1/2-in (12.7-mm)diameter flat bottom hole of a depth equal to 10 percent of the material thickness. Angle beam examination is performed on the outer cylindrical surface of nuts and washers in accordance with ASME SA-388 in both axial and circumferential directions. No indication greater than, the indication from the applicable calibration feature was acceptable. A distance-amplitude correction curve in accordance with Paragraph NB-2858 is used for the longitudinal wave examination. In relationship to Regulatory Guide 1.65 (C.3), stud bolting surfaces are allowed to be exposed to high-purity fill water;nuts and washers are dry stored during refueling. 5.3-10 Nine Mile Point Unit 2 FSAR this time, the turbine bypass system diverts the steam.to the main condenser, and the feedwater system supplies the makeup water required to maintain reactor vessel inventory. In the event the reactor vessel is isolated and the feedwater supply unavailable, relief valves are provided to automatically (or remote manually)maintain vessel pressure within desirable limits.The water level in the reactor vessel drops due to continued steam generation by decay heat.Upon reaching a predetermined low level, the RCIC system is initiated automatically. The turbine-driven pump supplies demineralized makeup water from the condensate storage tank to the reactor vessel.An alternate source of water is available from the suppression pool.The RCIC system allows automatic switchover of pump suction from the condensate storage tank to the suppression pool if the condensate storage tank falls to a preset low level.Low level in the tank is monitored by two redundant level.transmitters. If either transmitter senses low level, pump suction is automatically transferred to the suppression pool.The turbine is driven with a portion of the decay heat steam from the reactor vessel and exhausts to the suppression pool.Suppression pool water is not maintained demineralized and is used only in the event all sources of demineralized water have been exhausted. If the main feedwater system is not operable, a reactor scram is automatically initiated when reactor water level falls to Level 3.The operator can then remotely manually initiate the RCIC system from the main control room, or the system is automatically initiated as follows.Reactor water level continues to decrease due to boil-off until Level 2 is reached.At this point, the high-pressure core spray (HPCS)and:the reactor core isolation cooling (RCIC)systems are automatically initiated to supply makeup water to the RPV.These systems'ontinue automatic injection until the reactor water level reaches Level 8, at which time the HPCS injection valve is closed and the RCIC steam supply valve is closed.In the nonaccident case, the-RCIC system is normally the only makeup.system used to furnish subsequent makeup water to the RPV.The operator remotely manually shuts down the HPCS system, from the main control room.When level reaches Level 2 again due to loss of inventory through the main steam relief valves or to the main condenser, the RCIC system automatically restarts as described in Section II.K.3.13. This system then maintains the coolant makeup supply.RPV pressure is regulated by the automatic or remote manual operation of the main steam relief valves which discharge to the suppression pool.USAR Revision 0 5.4-17 April 1989 Nine Mile Point Unit 2 FSAR To remove decay heat during a planned isolation event, assuming that the main condenser is not available, the steam condensing mode of the RHR system can be manually initiated. Residual steam is routed through the RHR heat exchangers where it is condensed and cooled, then returned to the RPV through an interconnection with the RCIC pump.Thus, closed loop cooling is provided by this mode.If the steam condensing mode is unavailable for any reason, the safety relief valves can be used to dump the residual steam to the suppression pool.The suppression pool will then be cooled by remote manual alignment of the RHR system in the suppression pool cooling mode which routes the pool water through the RHR heat exchangers, cools it, and returns it to the suppression pool in a closed cycle.Makeup water to the RPV is still supplied by the RCIC system.For the accident case with the RPV at high pressure, the HPCS system can also be used to automatically provide the required makeup flow.No manual operations are required.If the HPCS system is postulated to fail at these conditions and the RCIC capacity is insufficient, the automatic depressurization system (ADS)will automatically initiate depressurization of the RPV to permit the condensate pumps or the low pressure ECCS (LPCI and LPCS)to provide makeup coolant.Whenever the RCIC system is initiated, the LSTG turbine is tripped to prevent water induction into the turbine, and the control room is alarmed that the RCIC injection valve is open.Therefore, although manual actions can be taken to mitigate the consequences of a loss of feedwater, there are no short term manual actions which must be taken.Sufficient systems exist to automatically mitigate these consequences. During RCIC operation, the suppression pool acts as the heat sink for steam generated by reactor decay heat.This results in a rise in pool water temperature. Heat exchangers in the residual heat removal (RHR)system are used to maintain the pool water temperature within acceptable limits by cooling the water directly or by condensing generated steam.The condensate discharge from the RHR heat exchangers may be used as RCIC pump suction supply or it may be directed to the suppression pool;'The RCIC system is equipped with a discharge line fill pump that, operates to maintain the pump discharge line in a filled condition. Keeping the discharge line filled reduces the lag time between pump startup and attainment of full flow to the RPV.Additionally, its operation eliminates the possibility of RCIC pumps discharging into a dry pipe and minimizes water hammer effects.The fill pump is classified as Category I and Safety Class 2.The pump motor is USAR Revision 0 5.4-17a April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section 5.3 5.4 Appendixes CHAPTER 6 6.1 6.2 6.3 6.4 6.5 6.6 Appendixes CHAPTER 7 6A through 6C INSTRUMENTATION AND CONTROL SYSTEMS Title Reactor Vessel Component and Subsystem Design 5A, 5B ENGINEERED SAFETY FEATURES Engineered Safety Feature Materials Containment Systems Emergency Core Cooling Systems Habitability Systems Fission Product Removal and Control Systems Inservice Inspection of Safety Class 2 and Class 3 Components Volume 13 13 13 13 13 14 15 15 15 15 15 15 7.1 7.2 7'7'7.5 7.6 7~7 Appendixes 7A, 7B Introduction Reactor Protection (Trip)System (RPS)Instrumentation and Controls Engineered Safety Feature Systems Systems Required for Safe Shutdown Safety-Related Display Instrumentation All Other Instrumentation Systems Required for Safety Control Systems Not Required for Safety 15 15 15 16 16 16 16 16 CHAPTER 8 8.1 8.2 8.3 Appendix 8A CHAPTER 9 ELECTRIC POWER Introduction Offsite Power System Onsite Power System AUXILIARY SYSTEMS 16 16 16 16,17 17 I 17 9.1 9.2 9.3 9.4 9.5 Appendixes Fuel Storage and Handling Water Systems Process Auxiliaries Air Conditioning, Heating, Cooling, and Ventilation Systems Other Auxiliary Systems 9A, 9C 17 18 19 20~21 21,22 23 USAR Revision April 1989 Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont)Section Title Volume CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 23 10.1 10.2 10.3 10.4 Summary.Description Turbine Generator Main Steam Supply System Other Features of Steam and Power Conversion System 23 23 24 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT ll.1 11.2 11.3 11.4 11.5 Source Terms Liquid Waste Management Systems Gaseous Waste Management Systems Solid Waste Management System Process and Effluent Radiological Monitoring and Sampling Systems Appendix llA CHAPTER 12 RADIATION PROTECTION 24 24 25 25 25 25 25 12.1 12.2 12.3 12.4 12~5 CHAPTER 13 13.1 13.2 13.3 13.4 13.5 13.6 Appendixes Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program CONDUCT OF OPERATIONS Organizational Structure of Applicant Training Site Emergency Plan Operation Review and Audit Plant Procedures Industrial Security 13A, 13B 25 25 25 26 26 26 26 26 26.26 26 26 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR)26}}