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 t

1czek, Jr.

Vice President Nuclear Support Subscribed and sworn to before me thr sun day of ~C, 1990.

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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.: 87-063, Rev. 1 Implementation Document No.: Mod. PN2Y86MX162 USAR Affected Pages: Fig. 11.4-1a System: 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.: 87-118, Rev. 1 Implementation Document No.: Mod. PN2Y87MZ132 USAR Affected Pages: 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:

Technical Specification 3/4.6.1.5 requires drywell and suppression chamber internal pressure to be maintained between 0 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 shares"a common sensing line with 2CMS*PT1A, which is safety-it related. 2CMS-PT179 is installed as nonsafety-related.

shares a sensing line with 2CMS-PT168. This sensing line It 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.

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,Sum  ;;y Report "Page, j7 v 3 of .112 af Safety Evaluation No.: 87-148, Rev. 1 Implementation Document No.: Mod. PN2Y86MX184 USAR Affected Pages: Figures 9.3-5j, 11.2-1f, 11.2-1h System: Liquid Radwaste System (LWS)

Title of Change: 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.

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Safety Evaluation Summary Report Page 4 of 112 Safety Evaluation No.: 87-151 Xmplementation Document No.: Mod. PN2Y87MZ187 (Partial)

USAR Affected Pages: 9.4-45, 9.4-46, 9.4-47; Tables 9.4-6, 9.5-1 (Sh. 8), 9.5-2 (sh. 4) Figures 1.2-2, 1.2-19 (Sh. 1), 8.3-3 (Sh. 2),

9.4-2c, 9.4-14 (Sh. 1), 9.5-32, 9A. 3 5g 11 3 2g 12 ' 1 12 ~ 3 13 12.3-34, 12.3-46 System: N/A Title of Change: 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 safety change does not involve an unreviewed is concluded that question.

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Safety Evaluation Summary Report Page 6 of 112 Safety Evaluation No.: 87-175, Rev. 2 Implementation Document No.: Mod. PN2Y87MX259 (Partial)

USAR Affected Pages: Figure 10.1-6a System: Feedwater System (FWS)

Title of Change: 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.87-175, Rev. 2 (Continued)

Safety Evaluation Summary:

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, change does not involve an unreviewed itsafety is concluded that question.

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Safety Evaluation Summary Report Page 8 of 112 Safety Evaluation No.: 88-039, Rev. 2 Implementation Document No.: Temporary Mod.88-138 USAR Affected Pages: Nj'A System: Breathing Air System (AAS)

Title of Change: 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.: 88-046 Implementation Document No.: DRF L12-00766 USAR Affected Pages: N//A System: Fuel Title of Change: 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.: 88-059, Rev. 1 Implementation Document No.: Mod. PN2Y87MX134 USAR Affected Pages: 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: Fire Protection CO~ System Title of Change: 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.: 88-077 Implementation Document No.: Mod. PN2Y87MX233 USAR Affected Pages: 11.3-5; Figures 11.3-1a, 11.3-1b System: Offgas System (OFG)

Title of Change: 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 concluded that this change does not involve an unreviewed safety is question.

Safety Evaluation Summary Report Page 14 of 112 Safety Evaluation No.: 88U-110 Implementation Document No.: EE-80 Series Drawings USAR Affected Pages: Figures 9.5-5 through 9.5-39 System: Communications Systems Title of Change: 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.: 88U-121, Rev. 1 Implementation Document No.: LDCNs U-1295, U-1296 USAR Affected Pages: Listed Below System: 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.: 88U-323 Implementation Document No.: LDCN U-1081 USAR Affected Pages: 12 ' 9g 12 ' 10'2 3 Figures 12.3-1 13'2.3-15; through 12.3-66 System: N/A Title of Change: 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.: 89-004 Implementation Document No.: EDC 2E00130 USAR Affected Pages: Figure 6.2-38, Sheet 10 System: 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, change does not involve an it unreviewed is concluded that this safety question.

Safety Evaluation Summary Report Page 18 of 112 Safety Evaluation No.: 89-007 Implementation Document No.: Calculations MS-1722, Rev. 1; MS-1126, Rev. 2; MS-168S, Rev.

1; MS-1424, Rev. 4; PZ-002AK, Rev. 1 USAR Affected Pages: 3 6A 15' 6A 16'0 3 3 System: Exclusion Area Piping Title of Change: 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.: 89-009 Implementation Document No.: Temporary Modification USAR Affected Pages: N/A System: 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.: 89-014, Rev. 1 Implementation Document No.: Mod. PN2Y88MX093 (Partial)

USAR Affected Pages: Figures 9.2-1q, 9.2-6a, 9.2-17b, 9.3-1h System: N/A Title of Change: 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 issafety change does not involve an unreviewed concluded that question.

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Safety Evaluation Summary Report Page 23 of 112, Safety Evaluation No.: 89-016, Rev. 1 Implementation Document No.: N//A USAR Affected Pages: N/A System: 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.: 89-017 Implementation Document No.: Temporary Mod.89-059 USAR Affected Pages: N/A System: 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.: 89-019, Rev. 1 Implementation Document No.: Temporary Mods89-061, 89-062 USAR Affected Pages: N/A System: 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 line path will still provide for the removal of low point draincondensate 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.: 89-020 Implementation Document No.: Temporary Mod.89-063 USAR Affected Pages: N/A System: Reactor Recirculation System Title of Change: 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.: 89-021, Rev. 1 Implementation Document No.: Temporary Mod.89-066 USAR Affected Pages: N/A System: Service Water System Title of Change: 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.: 89-022 Implementation Document No.: RMU No. 052578 USAR Affected Pages: N/A System: Control Building HVAC System Title of Change: 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.: 89-024, Rev. 1 Implementation Document No.: N/A USAR Affected Pages: 9.4-40, 9.4-42 System: Turbine Building Ventilation System/Effluent Monitoring Title of Change: 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, change does not involve an unreviewed itsafety is concluded that question.

this

1 Safety Evaluation Summary Report Page 33 of 112 Safety Evaluation No.: 89-025 Implementation Document No.: Mod. PN2Y88MZ093 USAR Affected Pages: N/A System: Essential Lighting System Title of Change: 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.: 89-026 Implementation Document No.: Temporary Mod. 88-74 USAR Affected Pages: N//A System: Circulating Water System (CWS)

Title of Change: 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.: 89-028, Rev. 1 Implementation Document No.: Temporary Mod. 89-71 USAR Affected Pages: N/A System: 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.: 89-030 Implementation Document No.: Temporary Mod.89-050 USAR Affected Pages: N/A System: Offgas System (OFG)

Title of Change: Offgas H, Sampling Discharge Line Revision Description of Change:

To enable proper operation of the Offgas H, Sampling system, this temporary modification revises the sampling common discharge line connection to the offgas processH~ 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.: 89-042 Implementation Document No.: Temporary Mod.89-078 USAR Affected Pages: N/A System: 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.: 89-043 Implementation Document No.: Temporary Mod. 2087 USAR Affected Pages: N//A System: 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.: 89-045 Implementation Document No.: Temporary Nod. 89-76 USAR Affected Pages: N/A System: 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.

provide any alarms.

It provides no control nor does it

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.: 89-048 Implementation Document No.: Technical Specification Table 4.8.1.1.2-1 USAR Affected Pages: Table 1.8-1, page 122 of 169 System: Division I, Generators II, and III Diesel 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.: 89-054 Implementation Document No.: EDC 2M00287 USAR Affected Pages: 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 System: 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 safety change does not involve an unreviewed is concluded that question.

this

Safety Evaluation Summary Report Page 45 of 112 Safety Evaluation No.: 89-059 Implementation Document No.: EDC 2E10072 USAR Affected Pages: Fig. 5.1-2a System: 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.: 89-060, Rev. 2 Implementation Document No.: N/A USAR Affected Pages: N/A System: Miscellaneous Buildings Floor Drains System (DFM)

Title of Change: 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.: 89-061 Implementation Document No.: Procedure N2-OP-101D USAR Affected Pages: Table 13.5-6 (Sh. 4)

System: Reactor Recirculation System Title of Change: 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.: 89-066 Implementation Document No.: Drawings 12187-SK-032483-.25; 12177-BY-002Ag Bg Cg E 45065-C thru E-45069C USAR Affected Pages: Figure 1.2-1 System: Various Title of Change: Minor Construction Activities at the Nine Mile Point Site Description 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.: 89-068 Implementation Document No.: Temporary Mod.88-151 USAR Affected Pages: N/A 1

System: Turbine Building HVAC System Title of Change: 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.: 89-069, Rev. 4 Implementation Document No.: Temporary Mod.89-092 USAR Affected Pages: N/A System: 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 Unit 2 circulating water will be discharged to the Unitcanal.

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.89-069, Rev. 4 (Continued)

Safety Evaluation Summary:

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 operation or reliability, and will help to extend serviceequipment 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.89-069, Rev. 4 (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 54 of 112 Safety Evaluation No.: 89-070 Implementation Document No.: E&DCR C46950C, ECN SFC-612 USAR Affected Pages: Figure 9.1-6 (Sheets 3, 6)

System: 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.: 89-071 Implementation Document No.: Temporary Mod. 89-94 USAR Affected Pages: N/A System: 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.: 89-072 Implementation Document No.: 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 15A

~ 15 3A 1g

~ 15A 3A 15 2g 3A 1g 2g 6A.3-6, 6A.3-11, 6A.9-3 (Non-Proprietary), and 6A.3-11, 6A.3-27 (Proprietary)

System: N/A Title of Change: 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.: 89-073 Implementation Document No.: EDC 2M00308I EDC 2M10080 USAR Affected Pages: 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.: 89-074 Implementation Document No.: EDC 2S10095 USAR Affected Pages: 9A.2-2, 9B.2-1; Figures 9A.3-5, 9A.3-6, 9A.3-7 System: Fire Protection Title of Change: 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.: 89-077, Rev. 1 Implementation Document No.: WR 169489'and 169457 USAR Affected Pages: N//A System: 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.: 90-001 Implementation Document No.: Mod. PN2Y89MX158 USAR Affected Pages: Figure 10.1-5d System: Condensate System (CNM)

Title of Change: 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, safety involve unreviewed it is concluded question.

that this change does not an

Safety Evaluation Summary Report Page 64 of 112 Safety Evaluation No.: 90-003 Implementation Document No.: Calc. A-10.1-AA-26, Rev. 1 USAR Affected Pages: 2.2-2, 2.2-9 System: N//A Title of Change: 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, that NMPC helicopter operations do not constitute itan isunreviewed concluded safety question.

Safety Evaluation Summary Report Page 66 of 112 Safety Evaluation No.: 90-004 Implementation Document No.: Mod. PN2Y89MX155 USAR Affected Pages: Figure 10.1-6c System: Feedwater Pump Seal and Leakoff System (FWP)

Title of Change: 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.: 90-005 Implementation Document No.: QATR-1, Rev. 5 USAR Affected Pages: 17 ~ 2 1 System: N/A Title of Change: 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.

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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.: 90-007 Implementation Document No.: Mod'. PN2Y89MX157 USAR Affected Pages: Figure 10.1-6a System: 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 concluded that this modification does not involve an unreviewed is safety question.

Safety Evaluation Summary Report Page 69 of 112 Safety Evaluation No.: 90-009 Implementation Document No.: Mod. PN2Y90MZ003 USAR Affected Pages: Figure 10.1-5d System: Condensate System (CNM)

Title of Change: 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.: 90-010 Implementation Document No.: Mod. PN2Y90MZ005 USAR Affected Pages: Figures 9.3-12j, 10.1-5d System: Condensate System (CNM)

Title of Change: 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 issafety concluded that question.

this change does not involve an unreviewed

Safety Evaluation Summary Report Page 71 of 112 Safety Evaluation No.: 90-012 Implementation Document No.: EDC 2F00030 USAR Affected Pages: N/A System: Turbine Building Floor Drain System (DET/DFT)

Title of Change: 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

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drain system (DFT) to the equipment drain (DET) system.

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Safety Evaluation Summary:

The water from tank 2SST-TK1 is normally of permissible quality for influx to the equipment drain (DET) system. Should high conductivity water enter the equipment drain system via 2SST-TKl, a high conductivity alarm would be received in the radwaste control room, alerting the operator to take appropriate action as required by existing procedures.

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.: 90-013 Implementation Document No.: Temporary Mods90-003 thru 90-011 USAR Affected Pages: N//A System: 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. Reactor Building Equipment Drain System Trouble

2. Reactor Building Floor Drain System Trouble

3. Turbine Building Floor Drain System Trouble Turbine Building Equipment Drain System Trouble

5. Main Stack Floor Drain Sump Tank 3 System Trouble

6. Auxiliary Boiler Buil'ding Floor Drain System Trouble

7. Radwaste Building Floor/'Equipment Drain System Trouble

8. Condensate Storage Tank Floor Drain System Trouble

9. 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.: 90-015, Rev. 1 Implementation Document No.: Temporary Mod.90-012 USAR Affected Pages: N/A System: 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

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alternate means of processing drain water through the radwaste floor drain collector surge pumps 2LWS-P17A/B is accomplished by

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means of a temporary hose installed between a drain valve in the 2DFW-P1A discharge pipe and a suction strainer drain valve off

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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.: 90-020 Implementation Document=No.: Temporary Mod.90-025 UFSAR Affected Pages: N/A System: 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

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and maintenance of equipment which, on some occasions, results in

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storage of combustibles.~

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The temporary sprinkler system is charged from the water supply

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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.: 90-022 Implementation Document No.: FPEE-2-89-011, EDC 2S10168 USAR Affected Pages: Figure 9A.3-5 System: Fire Protection Title of Change: 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

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(FPEE) has been written analyzing and justifying the opening.

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This change references the FPEE on the fire protection arrangement drawing and associated USAR Figure 9A.3-5 to provide

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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.: 90-023 Implementation Document No.: N/A USAR Affected Pages: N/A System: 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 and bay. Radiation monitor 2LWS-CAB206 is currently inoperative, its repair requires its de-energization, which thecauses valve 2LWS-V142 to cycle automatically closed preventing 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.: 90-024 Implementation Document No.: EDC 2E00437 USAR Affected Pages: 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

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(duplication and omissions). The associated USAR figures are

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revised accordingly.

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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.: 90-029 Implementation Document No.: EDC 2M00340 USAR Affected Pages: 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-

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filters from the reactor building ~

normal ventilation system, the

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turbine building HVAC system,

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and the radwaste building HVAC system for the duration of

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the winter snow 'season. The equipment identification numbers

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for these pre-filters

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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 in existing systems provide a low temperature alarm and a trouble the event that the heating coil were to become inefficient, 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.

of This modification reactor building affects the non-safety related portions the 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.: 90-035 Implementation Document No.: Drawings EV 4K 3g EV 4L 3 EV-4M-1, EV 198AQ Og EM 002Gg EM-021M; Procedures N2-MMP-GEN-930, 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: Refueling Equipment Title of Change: Reactor Internals Storage Pool Gate Description of Change:

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This change involves the purchase and installation of the reactor

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internals storage pool gate to support refueling outage activities. Though this activity was deferred until afteron

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commercial operation, the gate details are already shown 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, not involve an it unreviewed is concluded that this safety question.

change does

0 Safety Evaluation Summary Report Page 85 of 112 Safety Evaluation No.: 90-036 Implementation Document No.: Temporary Mods.90-028, 90-029,90-030 USAR Affected Pages: N/A System: 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.: 90-040 Implementation Document No.: Temporary Mod.90-032 USAR Affected Pages: N/A System: 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 concluded that this temporary modification does not involve an is unreviewed safety question.

Safety Evaluation Summary Report Page 88 of 112 Safety Evaluation No.: 90-041 Implementation Document No.: EDC 2F0069 USAR Affected Pages: Figure 9.2-2 (Sheet 19)

System: Service Water System Title of Change: 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.: 90-042 Xmplementation Document No.: FPQAP-l, Rev. 2 USAR Affected Pages: 9A.3-32 System: Fire Protection Quality Assurance Program Title of Change: 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.: 90-044 Implementation Document No.: Temporary Modification USAR Affected Pages: N/A System: 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

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receiver tanks. Temperature data will be collected to determine if

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the calibration of the tank level instrumentation contains

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errors resulting from incorrect density values. The temperature

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

Safety Evaluation Summary Report Page 91 of 112 Safety Evaluation No.: 90-050 Implementation Document No.: N/A USAR Affected Pages: N/A System. Control Building Chilled Water System (HVK)

Title of Change: 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.: 90-066, Rev. 1 Implementation Document No.: EAS-34-0688B, NEDC-31538P USAR Affected Pages: 15.0-9, 15.0-12, 15.1-8; Table 15.0-3 (Sheets 1, 2, 3)

System Various Title of Change: 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.: 90-085 Implementation Document No.: EDC 2M10159 USAR Affected Pages: Figures 1.2-7 (Sheet 1), 12.3-28, 12.3-61 System: Radwaste Building Title of Change: 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, do it is concluded that these drawing changes not involve an unreviewed safety question.

Safety Evaluation Summary Report Page 95 of 112 Safety Evaluation No.: 90-107 Implementation Document No.: NMPC Letters NMP2L 0653, NMP2L 0665 USAR Affected Pages: 7~1 7a System: 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.: 90-108 Implementation Document No.: Procedures NTP-11, NTP-16 USAR Affected Pages: 1.10-16 System: N/A Title of Change: 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.: 90-109 Implementation Document No.: N/A USAR Affected Pages: Table 1.8-1, Sht. 149 of 169 System: N/A Title of Change: NMP2 FSAR Table 1.8-1 Revision to Licensed Personnel Medical Evaluation Requirements Description of Change:

This change to FSAR Table 1.8-1 revises the NMPC commitment from Regulatory Guide 1.134, Rev. 1, and the associated ANSI N546-1976, endorsed by this revision to the current requirements of Regulatory Guide 1.134, Rev. 2, 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.: 90-113 Implementation Document No.: Procedure N2-RTP-129, Spec.

P281F USAR Affected Pages: Table 5.2-8 System: Drywell Atmosphere Monitoring System Title of Change: Clarification of Leak Detection Details Description of Change:

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 setpoints:

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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.

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.: 90-114 Implementation Document No.: Calc. WH(C)-001 USAR Affected Pages: Table 2.4-15 System: N/'A Title of Change: 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, is concluded that this change does not involve an unreviewed it safety question.

Safety Evaluation Summary Report Page 101 of 112 Safety Evaluation No.: 90-115 Implementation Document No.: Drawings 945E400, 945E493 USAR Affected Pages: Figure 9.5-41 (Sheets 1 thru 12)

System: High-Pressure Core Spray System Title of Change: Division USAR III Diesel Generator 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

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is indicated

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as input to common alarm.

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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. Sheets 6 through 11: Legend for '!local" indication is revised for consistency.

6. 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.90-115 (Continued)

Safety Evaluation Summary:

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.: 90-116 Implementation Document No.: Appendix R Safe Shutdown Analysis USAR Affected Pages: 9B ~ 2 1 g 9B 2 2I 9B 2 3g 9B 4-

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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 System: Various Title of Change: 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:

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.

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

This change identifies revisions to USAR text and tables to correct inconsistencies between the USAR and source documentation. The USAR revisions relate to effect of acc idental release of toxic chemicalscalculations of the on control room habitability.

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.: 90-122 Implementation Document No.: 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)

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System: Fire Protection Title of Change: Fire Protection 1990 USAR Update Description of Change:

Th is change documents and evaluates revisions to the Fire Hazards An 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.90-122 (Continued)

Description of Change: (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 re consistent with the guidance provided in NRC Standard Review Plan 9.5.1 and Branch Technical Position CMEB 9.5-1 for the impl ementation and control of a Fire Protection Program, and provide an equivalent or greater level of safety to that already provided in the plant. None of the changes have any adverse impact on the plant's ability to safely shut down in the event of a fire Based on the evaluation performed, it is concluded that these changes do not involve an unreviewed safety question.

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

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USAR Figure 10.1-6c has been updated to delete instruments 2FWP-

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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

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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

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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,

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12.3-56, and 10.4-7d have been updated to reflect the as-built

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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 2M10043A, as

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EDC described in Safety Evaluation 88U-238.

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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

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USAR Tables 9A.3-2 Sheet 2, 9A.3-9 Sheet 2, 9A.3-1 Sheet 2, and

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9A.3-6 Sheet 5 have been revised to reflect calculation FPW-28

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Revision 8, as described in Safety Evaluation 89-056. These

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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

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~P=Pi uee Number ~F=Fi uee Number ~F=Fi uee Number 1-i 24 1.2-30 28 1.2-15 1-ii 24 1.2-31 28 S}1 1 RO 1-iii 24 1.2-32 0 S}l 2 RO 1-iv 24 1.2-33 23 S}1 3 RO 1-v RO 1.2-33a 18 1.2-16 RO 1-vi 1.2-33b 18 1.2-17 1-vii 26 1.2-34 0 S}l RO 1-viii 24 1.2-35 0 1'}l 2 RO 1-ix 24 1.2-36 0 S}l 3 RO 1-x RO 1.2-37 0 S}1 4 RO 1.2-38 0 Sjl 5 RO 1.1-1 19 1.2-39 23 S}1 6 RO 1.1-2 0 1.2-40 0 1.2-18 RO 1.1-3 24 1.2-41 21 1.2-19 F 1.1-1 21 F 1 ~ 2-1 RO S}1 1 RO F 1.2-2 23 S}1 2 Rl 1.2-1 0 F 1.2-3 26 1.2-20 1.2-2 0 F 1.2-4 26 S}l 1 26 1.2-3 21 F 1 ~ 2-5 26 S}1 2 RO 1.2-4 0 F 1.2-6 1.2-21 1.2-5 0 S}l 1 RO S}1 1 26 1.2-6 0 Sh 2 Rl S}1 2 RO 1.2-7 0 F 1.2-7 1.2-22 1.2-8 0 S}1 1 Rl S}1 1 26 1.2-9 0 S}1 2 Rl S}1 2 26 1.2-10 0 F 1.2-8 1.2-23 1.2-11 21 S}1 1 Rl Sjl 1 26 1.2-12 19 Sjl 2 26 Sh 2 26 1.2-13 0 F 1.2-9 1.2-24 RO 1.2"14 0 S}1 1 Rl 1.2-25 26 1.2"15 21 S}l 2 Rl 1.2-26 1.2-16 21 F 1.2-10 S}1 1 RO 1.2"17 0 Sh 1 Rl S}1 2 RO 1.2-18 18 S}l 2 Rl'O 1.2-27 1.2-19 0 F 1 ~ 2-11 S}1 1 0 1 ~ 2-20 RO S}1 1 Sh 2 RO 1.2-21 0 S}l 2 RO 1.2-28 RO 1.2-22 19 Sjl 3 RO 1.2-29 1.2-23 0 S}1 4 RO S}1 1 0 1.2-24 21 F 1.2-12 RO S}l 2 0 1.2-25 0 F 1.2-13 Sh 3 23 1.2-26 0 S}l 1 RO 1.2-30 0 1.2-27 18 S}1 2 26 1.2-31 RO 1.2"28 0 S}1 3 RO 1.2-32 1.2-29 0 F 1.2-14 RO S}1 1 RO USAR Revision EP 1-1 October 1989

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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25 1.10-69b.1 23 1.10-30a 23 1.10-60 7 1.10-69b.2 23 1.10-30b 14 1 ~ 10-61 Rl 1.10-69c 15 1.10"31 0 1.10-62 23 1.10-69d 15 1.10-32 0 1.10-63 7 1.10-69e 15 1.10"33 RO 1.10-64 26 1.10-69f 15 1.10-33a RO 1.10-64a 7 1.10-69g 15 1.10-33b 14 1.10-64b 20 1elo-6911 15 1.10-34 23 1.10-64c 23 1.10-69i 15 1.10-35 14 1.10-64d 23 1.10-69j 15 1.10-35a 14 '4 1.10-64e 10 1elo-69k 15 F 10-35b 1.10-64f RO 1.10-691 26 1.10-36 23 le10-64fa 10 1.10-69m 15 1.10-37 23 1.10-64fb 10 1.10-69n 15 1.10-38 0 1.10-64g 10 1.10-70 10 1.10-39 RO 1.10-64ga 10 1.10-70a 10 1.10-40 0 1.10-64gb 10 1.10-70b 10 1.10"41 0 1elo-64}1 27 1.10-71 0 USAR Revision EP 1-6 October 1989

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

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~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure 'umber 1.12-11 27 1.13-11 RO 1.12-12 3 1.13-12 9 1.12-13 18 1.13-13 9 1.12-14 23 1.13-14 Rl 1.12-15 23 1.13-15 9 1.12-16 3 1.13-16 9 1.12-17 28 1.13-17 Rl 1.12-18 3 1.13-18 9 1.12-19 3 1.13-19 19 1.12-20 3 1.13-20 9 1.12-21 28 1.13-21 9 1.12-22 3 1.13-22 19 1.12-23 3 1 ~ 13-23 9 1.12"24 3 1.13-24 9 1.12-25 3 1.12-26 3 1.12-27 3 1.12-28 3 1.12-29 3 1.12-30 3 1.12-31 3 1.12-32 RO 1.12-32a RO 1.12-32b RO 1.12-33 4 1.12-34 4 1.12-35 4 1.12-36 4 1.12-37 27 1.12-38 4 1.12-39 4 1.12-40 4 1.12-41 4 1.12-42 4 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 Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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RO 2 xx 24 T 2.1-13 7 T 2.2-4 2-xxl 13 T 2.1-14 7 S11 1 25 2-xxia 13 T 2.1-15 7 S11 2 25 2"xxib 13 T 2.1-16 7 S11 3 0 2 Xxl1 0 T 2.1-17 7 T 2.2-5 2 XX11 1 24 T 2.1-18 0 Sh 1 RO 2"xxlv 24 T 2.1-19 7 Sh 2 RO 2-xxv 24 T 2.1-20 7 T 2.2-6 0 2-xxvl 24 T 2.1-21 7 T 2 '-7 RO 2-xxvl,a 26 T 2 '-22 7 T 2".2-8 RO USAR Revision EP 2-1 October 1989

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 2.5-19 0 2.5-64 RO 2.5-111 0 2.5-20 0 2.5-65 RO 2.5-112 0 2.5-21 0 2.5-66 0 2.5-113 0 2e5-22 RO 2.5-67 0 2.5-114 0 2.5-22a RO 2.5"68 0 2.5-115 0 2.5"22b RO 2.5-69 0 2.5-116 0 2.5-23 0 2.5-70 0 2.5-117 0 2.5-24 0 2.5-71 0 2.5-118 0 2.5"25 0 2 ~ 5 72 RO 2.5-119 0 2.5-26 0 2 ~ 5 73 0 2.5-120 RO 2e5"27 0 2.5-74 0 2.5-121 RO 2.5"28 0 2 ~ 5 75 0 2.5-122 RO 2.5-29 0 2.5-76 0 2.5-123 0 2.5-30 0 2.5-77 0 2.5-124 RO 2.5-31 0 2.5-78 0 2.5-125 0 2.5-32 0 2.5-79 0 2.5-126 0 2e5-33 0 2.5-80 0 2.5-127 RO 2.5-34 0 2.5-81 0 2.5-128 28 2.5-35 0 2.5-82 0 2.5-129 0 2.5"36 0 2.5-83 RO 2.5-130 0 2 '-37 0 2.5-84 RO 2.5-131 0 2.5-38 0 2.5-85 0 2.5-132 0 2.5-39 0 2.5-86 RO 2.5-133 4 2.5-40 0 2.5-87 0 2.5"134 0 2.5-41 0 2.5-88 0 2.5-135 0 2.5-42 26 2.5-89 0 2.5-136 0 2.5-43 0 2.5"90 0 2.5-137 0 2.5"44 0 2.5-91 RO 2.5-138 0 2.5-45 0 2.5-92 0 2.5-139 0 2.5-46 0 2.5-93 0 2.5-140 0 2.5-47 0 2.5-94 0 2.5-141 0 2.5-48 RO 2.5-95 0 2.5-142 0 2.5"49 0 2.5-96 0 2.5-143 0 2.5"50 0 2.5-97 0 2.5-144 0 2.5-51 0 2.5-98 26 2.5"145 26 2.5-52 0 2.5-99 0 2.5-146 2 '-53 RO 2.5-100 0 2.5-147 2 ~ 5-54 RO 2.5-101 0 2.5"148 2 '-55 RO 2.5-102 0 2.5-149 2.5"56 RO 2.5-103 0 2.5-150 2.5-57 RO 2.5-104 0 2.5-151 2.5"58 0 2.5-105 0 2.5-152 2.5-59 0 2.5-106 0 2.5-153 2.5-60 RO 2.5-107 0 2.5-154 2.5-61 0 2.5-108 0 2.5-155 2.5-62 4 2.5-109 0 2.5-156 2.5-63 RO 2.5-110 0 2.5-157 USAR Revision EP 2-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~P=Fi're Number ~i'=Fi ure Number ~P=Fi ure Number 2.5-158 0 2.5-179 12 2.5-210 0 2.5-159 0 2.5-180 RO 2.5-211 0 2.5-160 0 2.5"181 0 2.5-212 0 2.5"161 0 2.5-182 0 2.5-213 0 2.5-162 0 2.5-183 0 2.5-214 0 2.5-163 0 2.5-184 0 2.5-215 0 2.5-164 0 2.5-185 0 2.5-216 0 2.5-165 0 2.5-186 0 2 '-217 0 2.5-166 0 2.5-187 0 2.5-218 0 2.5-167 27 2.5-188 0 2.5-219 13 2.5-167a 5 2.5-189 0 2.5-220 RO 2.5-167b RO 2.5-190 0 T 2.5-1 0 2.5-167c 5 2.5-191 0 T 2.5-2 2.5-167d 5 2.5-192 15 S}1 1 2.5-168 18 2.5-192a RO Sjl 2 2.5-168a 5 2.5-192b 11 Sh 3 2.5-168b 5 2.5-193 0 Sh 4 2.5-168c 5 2.5"194 RO Sh 5 2.5-168d 5 2.5-194.1 24 S}1 6 2.5-169 0 2.5-194.2 24 T 2.5-3 2.5-170 0 2.5"194a 14 S}1 1 2.5"171 Rl 2.5-194b 27 Sjl 2 2.5-171a RO 2.5-194c 26 Sjl 3 2.5-171b 5 2.5-194d 26 T 2.5-4

'.5-172 0 2.5-194e 19 T 2.5-5 2.5-173 RO 2 '-1948 14 S}1 1 2.5-173a RO 2.5-194g 14 S}1 2 2.5-173b RO 2.5-194}l 14 Sjl 3 2.5-174 RO 2.5-194i 14 T 2.5-6 2.5-174a 15 2.5-194j 14 T 2.5-7 2.5-174b 15 2 '-194k 26 T 2.5-8 2.5-174c 15 2.5-1941 26 T 2.5-9 2.5-174d 15 2.5-195 14 Sjl 1 2.5-175 11 2 '-196 0 Sh 2 2.5-176 ll 2.5-197 0 T 2.5-10 2.5-176a 5 2 '-198 0 T 2.5-11 2.5"176b 5 2.5-199 0 T 2.5-12 2.5-177 5 2 '-200 0 S}1 1 2.5"177a 18 2.5-201 0 S}1 2 2.5-177b RO 2.5-202 0 T 2.5-13 2.5-177c RO 2 '-203 0 T 2.5-14 2.5-177d RO 2.5-204 0 T 2 '-15 2.5-178 18 2 '-205 0 T 2 '-16 2.5-178a 12 2 '-206 0 S}1 1 2.5"178b 12 2.5-207 0 Sjl 2 2.5-178c RO 2.5-208 0 T 2 ~ 5-17 2.5'-178d 12 2.5-209 0 T 2.5-18 USAR Revision 1 EP 2-5 October 1989,

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~P=Pi ure Number ~P=Pi ure Number ~P=Pi ure Number 2.5-76 0 2.5-105J ll 2.5-135 2.5-136 11 2 ~ 5 77 0 2.5-106 0 12 2.5-78 0 2.5-107 0 2.5-137 12 2 '-79 0 2.5-108 0 2.5-138 12 2.5-80 0 2.5-109 0 2.5-139 12 2.5-81 0 2.5-110 5 2.5-140 12 2.5-82 0 2.5-111 5 2.5-141 12 2.5-83 0 2.5-112 0 2.5-142 12 2.5-84 6 2.5-113 5 2.5-143 12 2.5-85 0 2.5-114 0 2.5-144 12 2.5-86 0 2.5-115 2.5-145 12 2.5-87 0 Sjl 1 2.5-146 12 2.5-88 0 S11 2 2.5-147 12 2.5-89 0 2.5-116 2.5-148 12 2.5-90 0 2.5-117 2.5-149 12 2.5-91 0 Sh 1 2.5-150 28 2.5-92 0 Sjl 2 2.5-151 13 2.5-93 0 2.5-118 2.5-152 13 2.5-94 0 2.5-119 2.5-153 13 2.5-95 0 S11 1 2.5-154 22 2.5-96 0 S11 2 2.5-155 22 2.5-96A 5 Sjl 3 2.5-156 14 2.5-96B 5 Sjl 4 2.5-157 14 2.5-96C 5 2.5-120 2.5-158 14 2.5-96D 5 Sjl 1 2.5-159 14 2.5-96E 27 S11 2 2.5-160 14 2.5-96F 27 S11 3 2.5-161 14 2.5"97 0 S11 4 2.5-162 14

'.5-98 0 2.5-121 2.5-163 14 2.5-99 0 Sjl 1 0 2.5-164 14 2.5-100 0 Sjl 2 0 2.5-165 14 2.5"101 0 S11 3 0 2.5-166 14 2.5-102 0 2.5-122 0 2.5-167 14 2.5-102A 5 2.5-123 0 2.5-168 14 2.5-102B 5 2.5-124 0 2.5-169 14 2.5-103 0 2.5-125 0 2.5-170 14 2.5-104 0 2.5-126 0 2.5-171 14 2.5-105 0 2.5-127 22 2.5-172 14 2.5"105A 5 2.5-127a 9 2.5-173 14 2.5-105B 5 2.5-127b 9 2.5-174 14 2.5"105C 5 2.5-128 23 2.5-175 14 2.5-105D 5 2.5-129 5 2.5-176 14 2.5-105E 5 2.5-130 5 2.5-177 14 2.S-105F 5 2.5-131 5 2.5-178 14 2.5-105G 5 F 2.5-132 5 2.5-179 14 2.5-105H 5 2.5-133 5 2.5-180 14 2.5-105I 5 2.5-134 5 2.5-181 14 USAR Revision EP 2-7 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

0 Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~P=Fi ure Number ~F=Fi ure Number ~P=Pi ure Number Sh 79 T 2B-15 T 2B-20 S}1 80 Sh 1 T 2B-21 Sh 81 S}1 2 T 2B-22 Sh 82 Sh 3 T 2B-23 Sh 83 T 2B-16 T 2B-24 Sh 84 Sh 1 T 2B-25 Sh 85 Sh 2 Sh 1 Sh 86 Sh 3 Sh 2 Sh 87 T 2B-17 T 2B-26 Sh 88 S}1 1 T 2B-27 Sh 89 S}1 2 T 2B-28 Sh 90 Sh 3 T 2B-29 Sh 91 S}1 4 Sh 1 Sh 92 Sh 5 Sh 2 Sh 93 Sh 6 Sh 3 Sh 94 Sh 7 Sh 4 Sh 95 S}1 8 Sh 5 Sh 96 Sh 9 Sh 6 Sh 97 Sh 10 T 2B-30 Sh 98 Sh 11 T 2B-31 Sh 99 S}1 12 T 2B-32 Sh 100 T 2B-18 T 2B-33 Sh 101 Sh 1 Sh 1 Sh 102 Sh 2 Sh 2 Sh 103 Sh 3 Sh 3 Sh 104 Sh 4 Sh 4 Sh 105 Sh 5 Sh 5 Sh 106 Sh 6 Sh 6 Sh 107 Sh 7 Sh 7 S}1 108 Sh 8 Sh 8 T 2B-9 Sh 9 Sh 9 T 2B-10 S}1 10 Sh 10 Sh 1 Sh 11 Sh 11 S}1 2 Sh 12 Sh 12 Sh 3 T 2B-19 T 2B-34 Sh 4 Sh 1 Sh 1.

Sh 5 Sh 2 Sh 2 Sh 6 Sh 3 Sh 3 Sh 7 Sh 4 Sh 4 Sh 8 Sh 5 Sh 5 T 2B-ll Sh 6 Sh 6 T 2B-12 Sh 7 Sh 7 T 2B-13 Sh 8 Sh 8 T 2B-14 Sh 9 Sh 9 Sh 1 Sh 10 T 2B-35 Sh 2 Sh 11 Sh 1 Sh 3 Sh 12 Sh 2 USAR Revision EP 2-11 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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

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Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

'l Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ure' Number ~F=Fi ure Number ~F=Fi ure Number 2L-20 7 T 2L-21 7 T 2L-22 7 T 2L-23 7 T 2L-24 7 T 2L"25 7 T 2L-26 7 T 2L-27 7 T 2L-28 7 F 2L"1 7 F 2L-2 13 USAR Revision 1 EP 2-19 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page T=Table Amendment

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

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~F=Fi use Number F 241.16-26a RO F 241.16-26b RO F 241.16-27a RO F 241.16-27b RO F 241.16-27c RO F 241.16-28a RO F 241.16-28b RO F 241.16-29 RO F 241.16-30 RO F 241.16-31a RO F 241.16-31b RO F 241.16-32a RO F 241.16-32b RO F

F 241.16-46'mendment 241.16-32c 241.16-33 RO RO F 241.16-34 RO F 241.16-35 RO F 241.16-36 RO F 241.16-37 RO F 241.16-38 RO F 241.16-39 RO F 241.16-40 RO F 241.16"41 RO F 241.16-42 RO F 241.16-43 RO F 241.16-44 RO F 241.16-45 RO F RO App 2P RO 2P-1 RO 2P-2 RO 2P-3 RO 2P"4 RO 2P-5 RO 2P-6 RO 2P-7/8 (T 451.13-1) RO 2P-9/10 (T 451.13-2) RO 2P-11/12 (T 451.13-3) RO 2P-13/14 (T 451.13-4) RO 2P-15 RO 2P-16 RO 2P-17/18 RO 2P-19/20 (F 451 '4-1) RO 2P-21/22 (F 451 '4-2) RO 2P-23/24 (F 451.14-3) RO 2P-25 RO USAR Revision 1 EP 2-22 October 1989

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~F=Fi ure Number ~F=Fi ure Number 2P"26 RO App 2Q RO 2P"27 RO 2Q"1 RO 2P-28 RO 2Q-2 RO 2P-29 RO 2Q-3 RO 2P-30 RO 2Q-4 RO 2P"31 RO 2Q-5 RO 2P-32 RO 2Q-6 RO 2P-33/34 RO 2Q-7 RO 2P-35/36 (T 451.15-1) RO 2Q-8 RO 2P-37/38 (T 451.15-2) RO 2Q-9 RO 2P-39/40 (T 451.15-3) RO 2Q-10 RO 2P"41/42 (T 4S1.1S-4) RO 2Q-ll RO 2P-43/44 (T 451.15-5, Sh 1) RO 2Q-12 RO 2P-45/46 (T 451.15-5, Sh 2) RO 2Q-13 RO 2P-47/48 (T 4S1. 15-5, Sh 3) RO 2Q-14 RO 2P-49/50 (T 451.15-5, Sh 4) RO 2Q-15 RO 2P-51/52 (T 451.15-6, Sh 1) RO 2Q-16 RO 2P-53/54 (T 451.1S-6, Sh 2) RO 2Q-17 RO.

2P"55/56 (T 451.15-6, Sh 3) RO 2Q-18 RO 2P-57/58 (T 451.15-6, Sh 4) RO 2Q-19 RO 2P-59/60 (T 451.1S-7, Sh 1) RO 2Q-20 RO 2P-61/62 (T 451.15-7, Sh 2) RO 2Q-21 RO 2P-63/64 (T 451.15-7, Sh 3) RO 2Q-22 RO 2P-65/66 (T 451.15-7, Sh 4) RO T GI-1 RO USAR Revision 1 EP 2-23 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 3 Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ur'e Number ~F=Pi ure Number ~F=Fi ure Number 3 1 0 3-xxxvl 28 3.1-23 0 3 11 0 3-xxxvll 24 3.1-24 28 3 111 0 3 xxxvlll 24 3.1-25 0 3-lv 9 3-xxxlx 24 3.1-26 0 3-U 25 3-xl 24 3.1-27 0 3-Ul RO 3-xla 12 3.1-28 0 3 Vll 0 3-xlb 12 3.1-29 0 3-Vl1 1 0 3-xli 27 3.1-30 0 3 lX RO 3-xlil 21 3.1-31 0 3-x RO 3-xli2 21 3.1-32 0 3-xl 19 3-xiii 0 3.1-33 0 3-Xl1 24 3-xliii 24 3.1-34 27 3 xlla 24 3-xliv RO 3.1-35 0 3-xiib 24 3"xliva RO 3.1-36 0 3 Xlll 23 3-xlivb 18 3.1-37 0 3-xlv 8 3-xlv 0 3.1-38 0 3-XU RO 3-xlvi RO 3.1-39 0 3-xvl RO 3-xlvii RO 3.1-40 0 3-Xvl1 RO 3-xlviii RO 3.1-41 0 3-xvlll 28 3-xlix RO 3.1"42 0 3-xlx 28 3.1-43 19 3-xx 26 3.1-1 0 3.1"44 0 3-xxl 24 3.1-2 0 3.1-45 19 3 xxll 24 3.1-3 0 3.1-46 0 3 XX111 RO 3.1"4 0 3.1-47 27 3 xxlv 7 3.1-5 18 3.1-48 0 3-xxlva 7 3.1-6 12 3.1-49 0 3-xxivb 7 3.1-7 0 3.1-50 0 3-xxv 0 3.1-8 0 3.1-51 0 3-xxvl 24 3.1-9 0 3.1-52 28 3-xxvll 12 3.1-10 0 3.1"53 0 3 xxvlll 12 3.1-11 0 3.1-54 0 3-xxlx 12 3.1-12 0 3 '"55 0 3 xxx 12 3.1-13 28 3.1-56 0 3-xxxl 12 3.1-13a 19 3.1-57 0 3-xxxl 1 12 3.1-13b 19 3.1-58 0 3 xxxl la 21 3.1-14 0 3.1-59 RO 3-xxxiib 12 3.1-15 0 3.1-60 0 3-xxxl l l RO 3.1-16 0 3.1-61 0 3 xxxllla 24 3.1-17 0 3.1"62 0 3-xxxiiib 5 3.1-18 0 3.1-63 0 3-xxxlv 24 3.1-19 0 3.1-64 0 3 xxxlva 23 3.1-20 0 3.1"65 0 3"xxxivb 5 3.1-21 0 3.1-66 0 3-xxxv RO 3.1-22 0 3.1"67 0 USAR Revision 1 EP 3"1 October 1989

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

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

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

0 Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number Sjl 2 13 F 3C.3-1 12 F 3C ~ 3-2 12 F 3C.3-3 12 App 3D RO 3D-1 . RO 3D-2 RO 3D-3 RO 3D-4 RO 3D-5 RO 3D-6 RO 3D-7 RO 3D-8 RO 3D-9 RO 3D-10 RO 3D-ll RO 3D-12 RO 3D-13 RO 3D"14 RO 3D-15 RO 3D-16 RO 3D-17 RO 3D-18 RO 3D-19 RO T 3D-1 S}1 1 RO S}1 2 RO S}l 3 RO S}l 4 RO S}l 5 RO S}1 6 RO S}1 7 RO S}1 8 RO S}1 9 RO S}1 10 RO S}1 11 RO S}1 12 RO S}1 13 RO S}1 14 RO App 3E RO 3E-1 RO 3E-2 RO 3E"3 RO 3E-4 RO USAR Revision EP 3-14 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 4 Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 4.6-31 0 4.6-32 0 4.6"33 0 4.6-34 19 4.6-35 25 4.6"36 0 4.6-37 0 4.6-38 5 F 4.6"1 0 F 4.6-2 0 F 4.6-3 19 F 4.6-4 0 F 4.6"5a Rl F 4.6-5b RO F 4.6-5c Rl F 4.6-6 0 F 4.6-7 Sh 1 23 S}L 2 23 Sb 3 23 F 4.6-8 0 F 4.6-9 0 App 4A RO 4A-1 Rl 4A-2 RO USAR Revision 1 EP 4-2 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 5 Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 5-i 7 5.2"12 7 5.2-43 0 5-ii 24 5.2"12a 24 5.2-44 5 5-iii 24 5.2-12b 24 5.2-45 5 5-iv 0 5.2-12c 24 S.2-45a 5 5-v 24 5.2-12d 7 5.2"45b 5 5 v1 24 5.2-13 0 5.2-46 RO 5"vii 24 5.2-14 0 T 5.2-1 5 v111 RO 5.'2-15 0 S}1 1 RO 5 1x RO 5.2-16 0 Sh 2 23 5-x RO 5.2"17 Rl Sh 3 RO 5-xa RO 5.2-18 0 Sh 3a 23 5-xb 7 5.2-19 RO Sh 3b 24 5 x1 24 5 '-20 5 Sh 4 21 5.2-21 19 Sh 5 25

5. 1-1 0 5.2-21a Rl Sh 5a RO 5.1-2 0 5.2"21b 5 Sh 6 28 5.1-3 19 5.2-22 0 Sh 6a 23 5.1"4 0 5.2-23 0 S}1 6b 28 F 5.l-la 24 5.2-24 0 Sh 6bl 21 F 5 '-lb 19 5.2-25 0 Sh 6ba 19 F 5.1-2a F 5.1-2b RO 5.2-26 5.2-27 0 Sh 7 ll RO 0 Sh 8 19 F 5.1-2c RO 5.2-28 Rl Sh 8a 21 5.2-28a 22 Sh 8al RO

5. 2-1 -

15 5.2-28b 11 Sh 8b 26 5.2-2 0 5.2-29 26 Sh 8c 28 5 '-3 28 5.2-30 RO Sh 8d 28 5.2-4 24 5.2-31 RO T 5 '-2 0 5.2-4a 24 5.2-32 23 T 5.2-3 24 5.2-4b 7 5.2-32a 23 T 5.2-4 RO 5.2-5 RO 5.2-32b 5 T 5.2-5 5.2-5a RO 5 ~ 2 33 RO Sh 1 24 5.2-5b RO 5.2-33a 19 Sh 2 23 5.2"6 RO 5.2-33b 5 Sh 3 28 5.2-7 0 5.2-34 RO Sh 3a 28 5.2"8 7 5.2-35 RO Sh 4 Rl 5.2"8a 19 5.2-36 RO Sh 5 24 5.2"8b 7 5.2-37 23 Sh 6 23 5.2-9 13 5.2"37a RO T 5.2-6 23 5.2"9a 6 5.2-37b 23 T 5.2-7 5.2-9b 6 5.2-38 10 Sh 1 0 5.2-10 23 5.2-39 RO S}1 2 0 5.2-10a 7 5 '-40 Rl T 5.2-8 19 5.2-10b 7 5.2-41 0 T 5 '-9 RO 5.2-11 RO 5.2"42 0 T 5.2-10 RO USAR Revision EP 5-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page -Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

i Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~P=Pi ure Number ~P=Pi ure Number ~P=Pi ure Number Sh 2 24 Sh 1 0 Sjl 3 0 S11 2 23 5.4-2 28 S11 3 0 5.4-3 0 F 5.4"18 RO 5.4-1 0 F 5.4-19 23 5.4-2a RO 5.4-2b Rl App 5A 0 5.4-2c Rl 5A-i 24 5.4-2d RO 5A-1 24 5.4-3 0 5A-2 28 5.4-4 0 5A-2a 28 5.4-5 0 5A-2b 28 5.4-6 0 5A-3 0 5.4-7 28 T 5A-1 5.4-8 28 S11 1 5.'4-9a RO S}1 2 5.4-9b Rl T 5A-2 5.4"9c RO Sh 1 5.4-9d Rl S}1 2 5.4-'10 T 5A-3 S}1 1 23 T 5A-4 Sh 2 23 F 5.A-1 5.4-10a 24 F 5.A-2 5.4-10b 7 Att 5A-1 5.4-11 0 5.4-12 0 App 5B RO 5.4-13a RO 5B-1 RO 5.4"13b RO 5B-2 RO 5.4-13c RO 5B"3 RO 5.4-13d Rl 5.4-13e RO 5.4-13f RO 5.4-13g RO 5.4-14 Sh 1 23 S11 2 23 Sh 3 Rl 5.4-15 0 5.4-16a RO 5.4-16b RO

'.4-16c RO 5.4-16d RO 5.4-16e RO 5.4-16f RO 5.4-17 USAR Revision EP 5-3 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 6 Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

~S}1 1 27 6.2-27 5 6.2-54 RO S}1 2 28 6.2-28 5 6.2-54a RO T 6.1-2 6.2-29 0 6.2-54b 27 Sh 1 RO 6 '-30 0 6.2-55 21 USAR Revision 1 EP 6-1 October 1989

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~F=Fi ure Number ~F-Fi ure Number ~F=Fi ure Number 6.2-5Sa 27 6.2-71b 5 Sh 1 6.2-55b Rl 6.2-72 Rl S11 2 6.2-55c RO 6.2-72a RO T 6.2-3 6.2-55d RO 6.2-72b RO S11 1 RO 6.2-56 18 6.2-73 28 Sh 2 RO 6.2"57 RO 6.2-74 27 Sh 3 RO 6.2-57a RO 6.2"75 RO T 6.2-4 0 6.2-57b RO 6.2-75a 27 T 6.2-4a RO 6.2-57c RO 6.2"75b 5 T 6.2-5 0 6.2-S7d Rl 6.2-76 15 T 6 '-6 6.2-57e RO 6.2-76a 28 S11 1 RO 6.2-57K 26 6.2-76b 5 S11 2 RO 6.2-58 0 6.2-77 27 T 6.2-7 0 6.2-59 RO 6.2-77a RO T 6.2-8 0 6.2-59a RO 6.2-77b 15 T 6.2-9 RO 6.2-59b RO 6.2-78 8 T 6.2-10 0 6.2-60 28 6.2-79 15 T 6.2-11 0 6.2-60a 28 6.2-79a 15 T 6.2-12 0 6.2-60b 5 6.2-79b 15 T 6.2-13 0 6.2-61 26 6.2-80 RO T 6.2-14 0 6.2-61a RO 6.2-80a 15 T 6.2-15 6 '-61b RO 6.2-80b 15 S11 1 26 6.2-62 7 6.2-81 RO S11 2 0 6.2-62a 23 6.2-82 15 T 6.2-16 0 6.2-62b 7 6.2-83 Rl T 6.2-17 0 6.2"63 RO 6.2-83a 27 T 6.2-18 0 6.2-63a RO 6.2-83b 23 T 6.2-19 0 6.2"63b RO 6.2"84 27 T 6.2-20 0 6.2-64 18 6.2-84a 23 T 6.2-20a 21 6 '-65 17 6.2-84b 23 T 6 '-21 0 6.2-65a 17 6.2-85 27 T 6.2-22 0 6.2-65b 17 6.2-85a 17 T 6 '-23 0 6.2-66 0 6.2-85b 17 T 6 '-24 0 6.2"67 26 6.2-86 27 T 6.2-25 0 6.2-67a 21 6.2-86a 19 T 6.2-26 0 6.2"67b 21 6 '-86b 17 T 6 '-27 0 6.2"68 26 6.2-87 26 T 6.2-27A RO 6.2"68a 25 6.2-87a Rl T 6.2-28

'-29 ll 6.2-68b 5 6.2-87b 17 T 6 RO 6.2"69 6.2-69a ll 6.2-88 6.2-88a Rl Rl T

T 6.2-30 6.2-31 RO RO 5

6.2-69b . 5 6.2-88b RO T 6.2-32 RO 6,2-70 RO 6.2-89 15 T 6.2-33 RO 6.2-71 5 T 6.2-1 0 T 6.2-34 RO 6.2-71a 5 T 6 '-2 T 6.2-35 11 USAR Revision 1 EP 6-2 October 1989

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~F=Fi ure Number ~F-Fi ure Number ~F=Fi ure Number T 6.2-36 ll S}1 3 RO Sh 2 18 T 6.2-37 27 T 6.2-55d 6.2-59B 18 T 6.2-38 Sh 1 RO 6.2"59C 15 S}1 1 S}1 2 RO 6.2-59D RO

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T 6.2-43A 11 S}1 10 27 0 T 6 '-43B RO Sh 11 28 6.2-4 0 T 6.2-44 11 Sh 12 26 6.2-5 0 T 6.2-44A 11 Sh 13 28 6.2-6 0 T 6.2-44B 11 S}1 14 27 6.2-7 0 T 6.2-45 ll Sh 15 28 6.2-8 6.2-9 0

T 6.2"45A 11 S}L 16 28 0 T 6.2-45B 28 S}1 17 28 6 '-10 27 T 6 '-46 11 Sh 17a 28 6.2-11 0 T 6.2-47 11 S}1 18 RO 6.2-12 0 T 6.2-48 28 Sh 19 17 6.2-13 0 T 6.2"49 28 Sh 19a 17 6.2"14 0 T 6.2-50 0 S}l 20 RO 6.2-15 0 T 6.2-51 RO Sh 20a RO 6.2-16 0 T 6.2-52 RO S}1 21 26 6.2-17 0 T 6.2"53 RO Sh 22 27 6.2-18 0 T 6.2-54 Rl Sh 22a 26 6.2-19 0 T 6 '-55 21 S}1 23 28 6.2-20 18 T 6.2-55a Sh 23a RO 6.2-21 18 S}l 1 RO Sh 24 28 6 '-22 0 S}1 2 RO S}1 24a 27 6.2-23 18 S}1 3 RO Sh 24b 26 6.2-24 0 T 6.2"55b T 6.2-57 28 6 '-25 0 S}1 1 RO T 6.2-58 0 6.2-26 0 Sjl 2 RO T 6.2"59 6.2-27 0 Sjl 3 RO Sjl 1 RO 6.2-28 RO T 6 '-55c Sh 2 RO 6.2-28A RO S}1 1 Rl T 6.2-59A 6.2-28B RO S}1 2 RO Sh 1 18 6.2-28C RO USAR Revision 1 'EP 6-3 October 1989

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~F=Fi ure Number ~F-Fi ure Number " ~F=Fi ure Number F 6.2-29 0 F 6.2-39 0 F 6.2-61 F 6.2"29A ll F 6.2-39A 9 F 6 '-62 F 6.2-29B ll F 6.2-40 27 Sjl 1 11 F 6.2-29C 11 F 6.2-41 27 Sh 2 11 F 6.2-29D ll F 6.2-42 28 S}1 3 11 ll F 6.2-29E

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'-67 ll ll Sh 8 23 F 6.2-56 F 6 F 6.2-33A RO S}1 1 ll F 6.2-68 11 F 6.2-33B RO S}l 2 23 F 6.2-68A 27 F 6.2-34 0 S11 3 23 F 6.2-69 11 F 6.2-35 0 S}1 4 23 F 6 '-69A 27 F 6.2"36 0 Sh 5 23 F 6.2-70 F 6.2-37 0 S}1 6 23 Sh 1 Rl F 6.2"38 S}1 7 23 Sh 2 RO S}1 1 RO S}1 8 23 Sh 3 RO S}1 2 RO S}1 9 23 S}1 4 RO S}1 3 RO Sjl 10 23 S}1 5 RO.

Sh 4 RO F 6.2-57 ll Sh 6 RO S}l 5 RO F 6.2-58 ll S}1 7 RO S}1 6 RO F 6.2-59 S}1 8 RO S}1 7 RO Sh 1 ll Sjl 9 RO Sh 8 RO S}1 2 ll Sjl 10 RO RO S}1 3 ll S}1 11 RO S}1 9 Sh 10 RO Sjl 4 ll S}1 12 RO S}1 11 RO S}1 5 11 S}1 13 RO S}1 12 RO F 6.2"60 23 S}1 14 RO USAR Revision 1 EP 6-4 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 7 Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 7 l RO T 7.1-4 S}1 14 RO 7 ll 24 S}1 1 RO S}l 15 RO 7 ill 7-lv RO RO S}1 2 RO S}1 16 S}l 17 RO RO 7"v RO 7.2-1 23 S}l 18 RO 7-vl RO 7~2 2 RO F 7.2-1 7-vl1 24 7 '-3 RO S}l 1 23 7-viia RO 7 ' 3a RO Sh 2 23 7-viib 24 7.2-3b 26 S}l 3 RO 7 vill RO 7.2"4 9 S}1 4 Rl 7 lx RO 7 '-5 0 S}1 5 23 7-x 24 7.2-6 0 7 Xl 24 7~2 7 0 7.3-1 0 7-xii 24 7.2-8 9 7 ~3 2 23 7.2-9 0 7 ~3 3 Rl 7.1-1 RO 7 '-10 Rl 7.3-4 23.

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Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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~F=Fi ure Number'O ~F=Fi ure Number ~F=Fi ure Number Sjl 6 S}l 20 RO 7.6-24 10 F 7.4-2 RO Sh 21 RO 7.6-25 10 S}1 22 RO 7.6-26 18 7.5-1 RO 7.6-26a 18 7.5-1a RO 7.6-1 18 7.6-26b 24 7.5"lb RO 7.6-2 Rl 7.6-26c 18 7.5-2 27 7.6-2a RO 7.6-26d 18 7.5-3 0 7.6.2b 10 7.6-26e 18 7.5-4 RO 7.6-3 RO 7.6-26K Rl 7.5-5 27 7.6-3a 10 7.6-26g Rl 7.5-6 23 7.6-3b 10 7.6-26h 18 7~5 7 RO 7.6-4 Rl 7.6-27 0 T 7.5-1 7.6-4a 10 T 7.6-1 Rl S}1 1 Rl 7.6-4b 10 T 7 '-2 10 S}1 2 RO 7.6-5 26 T 7.6-3 Sjl 3 RO 7.6-6 Rl S}1 1 RO S}1 4 RO 7.6"6a 18 S}1 2 Rl S}1 5 RO 7.6-6b 10 T 7.6"4 10 S}1 6 Rl 7.6"7 27 T 7.6-5 27 Sjl 7 RO 7.6"8 24 T 7.6-6 27 Sh 8 RO 7.6-8a Rl F 7.6-1 S}1 9 RO 7.6-8b RO Sh 1 RO S}1 10 RO 7.6-8c RO Sh 2 RO

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Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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

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

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

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

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

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

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

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

 'S}1 2          0            S}1 1         RO          F 9.3-1la      RO Sh 3           0            S}1 2         RO          F 9.3-11b      RO S}1 4          0         F 9  '-5a        RO          F 9.3"llc      RO S}1 5        23          F 9.3-5b         RO          F 9.3-11d      RO USAR   Revision                       EP 9-4                      October 1989

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

0 Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 9.4-62 25 Sjl 10 RO T 9.4-9 26 9.4-63 23 Sh 11 RO T 9.4-10 9.4-64 5 Sh 12 26 Sjl 1 26 9.4-65 23, T 9.4"4 Sjl 2 26 9.4-66 Rl S}1 1 26 T 9.4-11 9.4-67 24 Sjl 2 26 S}1 1 28 9.4-67a 20 Sjl 3 26 S}1 2 28 9.4-67b 20 Sh 4 Rl T 9.4-12 9.4-68 0 Sjl 5 Rl S}1 1 28 9.4-69 23 Sh 5a Rl S}1 2 28 9.4-70 25 Sh 6 26 Sjl 3 28 9.4-71 0 S}1 7 26 Sh 4 28 9.4-72 23 T 9.4"5 S}1 5 28 9.4-72a 23 S}1 1 26 F 9.4-1a Rl 9.4-72b 23 Sh 2 26 F 9.4-1b RO 9.4-73 24 Sh 3 RO F 9.4-1c Rl T 9.4-1 S}1 4 26 F 9.4-1d RO Sh 1 Rl Sh 5 RO F 9.4-1e RO S}1 2 RO S}l 6 26 F 9.4-1f RO S}1 3 Rl S}1 7 26 F 9.4-2a RO T 9.4-2 S}1 8 26 F 9.4-2b Rl S}1 1 26 Sjl 9 26 F 9 '-2c RO Sjl 2 RO S}1 10 26 F 9.4-2d RO S}l 3 26 Sh 11 26 F 9.4-2e RO Sjl 4 26 S}1 12 26 F 9.4-3a RO S}1 5 26 Sjl 13 26 F 9.4-3b RO S}1 6 26 S}1 14 26 F 9.4-3c RO S}1 7 26 Sh 15 26 F 9.4-3d Rl Sjl 8 RO S}1 16 26 F 9.4-3e RO S}1 9 26 S}1 17 26 F 9.4-3f RO S}1 10 26 S}1 18 26 F 9 '-4 Sjl 11 26 S}1 19 26 S}l 1 RO S}1 12 26 S}1 20 26 S}1 2 RO Sjl 13 26 S}1 21 26 S}1 3 RO Sh 14 26 T 9.4-6 26 S}1 4 RO T 9.4-3 T 9.4-7 S}1 5 RO S}1 1 RO S}1 1 26 S}1 6 RO Sh 2 RO S}1 2 26 Sjl 7 RO S}1 3 RO T 9.4-8 S}1 8 RO S}1 4 26 S}1 1 26 S}1 9 RO S}1 5 RO S}1 2 26 F 9.4-5 S}1 6 RO S}1 3 26 Sh 1 RO S}1 7 RO sh 4 RO S}1 2 RO S}1 8 RO Sh 5 26 S}1 3 RO S}1 9 RO S}1 6 26 Sjl 4 RO USAR Revision EP 9-6 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi uue Number ~F=Fi uue Number ~P=Fi uee Number Sjl 5 RO Sjl 7 RO F 9 '-12d RO Sh 6 RO Sjl 8 Rl F 9.4-13 S}1 7 RO Sh 9 RO S}1 1 RO S}1 8 Rl Sjl 10 Rl Sjl 2 RO F 9.4-6 S}1 11 RO S}1 3 RO Sh 1 RO Sjl 12 RO Sh 4 RO Sjl 2 RO Sjl 13 RO Sjl 5 RO Sji 3 RO S}1 14 RO S}1 6 RO S}1 4 RO Sh 15 RO Sh 7 RO Sjl 5 RO S}1 16 RO Sh 8 RO S}1 6 RO S}1 17 Rl S}1 9 RO S}1 7 RO Sjl 18 RO Sjl 10 Rl F 9 '-7 Sjl 19 Rl Sjl 11 RO Sh 1 RO Sjl 20 Rl Sjl 12 RO Sh 2 RO Sjl 21 RO F 9.4-14 Sjl 3 RO S}1 22 RO S}1 1 RO Sh 4 RO Sjl 23 RO S}1 2 RO S}1 5 RO Sh 24 RO Sjl 3 RO S}1 6 RO S}1 25 RO F 9.4-15a RO S}1 7 RO F 9.4"loa RO F 9.4-16 Sjl 8 RO F 9.4-10b RO S}1 1 RO Sjl 9 RO F 9.4-10c RO S}1 2 RO S}1 10 RO F 9.4-10d RO S}1 3 RO S}1 11 RO F 9.4-10e Rl Sh 4 RO S}1 12 RO F 9.4-11 S}1 5 RO S}1 13 RO S}1 1 RO S}1 6 RO Sjl 14 RO Sjl 2 RO Sh 7 RO F 9.4-8a RO Sh 3 RO S}1 8 RO F 9.4-8b RO Sh 4 RO S}1 9 RO F 9.4-8c RO Sh 5 Rl F 9.4-17 F 9.4-8d RO S}1 6 RO Sh 1 Rl F 9.4-8e RO S}1 7 RO Sjl 2 Rl F 9.4-8f RO S}1 8 RO Sh 3 Rl F 9.4-8g RO S}1 9 RO Sh 4 RO F 9.4-8}1 RO S}1 10 RO S}1 5 RO F 9.4-8j RO S}1 11 RO S}1 6 RO F 9.4-8k RO S}1 12 Rl Sh 7 RO F 9.4-8L Rl S}1 13 RO S}1 8 RO F 9.4-9 Sjl 14 RO Sjl 9 RO S}1 1 Rl Sjl 15 Rl S}1 10 RO S}1 2 Rl S}1 16 RO S}1 11 RO S}1 3 Rl S}1 17 RO Sjl 12 RO Sh 4 RO F 9.4-12a RO S}1 13 RO S}1 5 Rl F 9.4-12b RO F 9.4-18 Sjl 6 RO F 9.4-12c RO S}1 1 RO USAR Revision 1 EP 9-7 October 1989

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

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

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table . Amendment T=Table Amendment

~F=Fi ure        Number     ~F=Fi  ure      Number      ~F=Fi ure      Number F  9A.3-18      RO            S}1 4        RO F  9A.3-19      28            Sh  5        RO F 9A.3-20       28            Sh  6        RO F  9A.3-21      28            Sh  7        RO F 9A.3-22       28            Sh  8        RO Sh  9        RO 9B-1                          Sh  10       RO 9C.5-1          RO App 9C          RO          F 5-1           RO 9C-i           RO          F 5-2           Rl 9C-ii          RO          F 5-3           RO 9C-iii         RO          F 5-4 9C.1-1          RO            S}1 1         RO 9C.2-1         RO            Sh 2          RO 9C.3-1         RO          9C.6-1          RO 9C.3-2          RO          9C.7-1          RO 9C.3-3          RO          9C.8-1          RO 9C.3"4          RO          9C.8-2          RO 9C.3-5          RO          9C.8-3          RO 9C.3-6          RO          9C.8-4          RO 9C.3-7          RO          9C.8-5          RO 9C.3-8          RO          9C.9-1          RO 9C.3"9          RO          9C.10-1         RO 9C.3-10         RO          9C.10-2         RO 9Ce3-11         RO          9C.10-3         RO 9C.3-12         RO          9C.10-4         RO T 3"1                       9C.10"5         RO S}1 1        RO S}1 2        RO T 3-2 Sh 1         RO Sh 2         RO S}1 3        RO S}1 4        RO T 3-3 Sh 1         RO Sh 2         RO Sh 3         RO T  3-4          RO T  3-5          RO 9C.4-1          RO T 4-1 Sh 1         RO Sh 2         RO Sh 3         RO

.USAR Revision EP 9-12 October 1989

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

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

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

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

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

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

Nine Mile Point'Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

~F=Fi ure      Number      ~F=Fi  ure     Number      ~F=Fi ure      Number 12.5-14           5 12.5-14a          5 12.5-14b          5 12.5-15          28 12.5-16         RO 12.5-17         RO 12.5-18         RO 12.5-19         26 12.5-20         26 T 12 '-1        Rl T 12.5"2        RO T 12.5-3          5 T 12.5-4          1 USAR  Revision  1                   EP 12-3                  October 1989

3 Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES CHAPTER 13 Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 13"i RO Sh 5 28 13.2-28 RO 13-ii RO T 13.1"5 28 13.2-29 RO 13-iii RO F 13.1-1 Rl 13.2-30 RO 13-iv RO F 13.1-1a Rl 13.2-31 RO 13-iva RO F 13.1-2 Rl 13.2-32 RO 13-ivb 9 F 13.1-3 RO 13.2-33 RO 13-v RO F 13.1-3a RO 13.2"34 RO 13-vi RO F 13.1"4 RO 13.2"35 RO 13-vii RO F 13.1-4a RO 13.2-36 RO 13-viii RO F 13.1-5 RO 13.2-37 RO F 13 '-5a 13 13.2-38 RO

13. 1-1 28 F 13.1-5b 9 13.2-39 RO 13.1-2 Rl F'3.1"6 RO 13.2-40 RO 13.1-2a RO F 13 '-7 RO T 13.2-1 RO 13.1-2b 9 F 13.1"8 RO F 13.2-1 28 13.1-3 RO F 13 '"9 RO 13.1-3a 9 F 13.1-10 RO 13.3"1 RO 13.1-3b 9 13.3-2 RO 13.1-4 RO 13.2-1 RO 13.1-4a RO 13.2-2 RO 13.4-1 RO 13.1"4b 1 13.2-3 RO 13.4"2 RO 13.1-5 RO 13.2-4 RO 13.4-2a RO 13.1-5a 9 13.2-5 RO 13.4-2b RO 13.1-5b 9 13.2-6 RO 13.4-3 RO 13.1-6 28 13 '-7 RO 13.4-4 RO T 13.1-1 RO 13.2-8 RO T 13.4"1 RO T 13.1-2 28 13.2-9 RO T 13.4-2 T 13.1"3 13.2-10 RO Sh 1 RO Sh 1 RO 13.2-11 RO S}1 2 RO Sh la RO 13.2-12 RO S}L 3 RO Sh 2 RO 13.2-13 RO T 13.4-3 Sh 2a RO 13.2-14 RO Sh 1 RO S}1 2b RO 13.2-15 RO Sh 2 RO Sh 2c RO 13.2-16 RO Sh 3 RO Sh 3 RO 13.2-17 RO F 13.4-1 RO Sh 3a RO 13.2-18 RO Sh 4 28 13.2-19 RO 13.5-1 RO Sh 5 23 13.2-20 RO 13.5-2 RO Sh 6 0 13.2-21 RO 13.5-3 RO S}1 7 28 13.2-22 RO 13.5-3a RO T 13.1"4 13.2-23 Rl 13.5-3b 6 Sh 1 28 13.2-24 RO 13.5"4 RO S}L 2 28 13.2-25 RO 13.5-4a 6 S}1 3 28 13.2-26 RO 13.5"4b 6 Sh 4 16 13.2-27 RO 13.5-5 RO USAR Revision EP 13-1 October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 13.5-6 RO 13A"14h 17 13A"41b 16 13.5-7 RO 13A-14i 17 13A-42 16 T 13.5-1 13A-14j 17 13A-43 16 S}1 1 RO 13A-14k 17 13A-43a 16 S}1 2 0 13A-141 17 13A-43b 16 T 13.5-2 23 13A-14m 17 13A-43c 16 T 13 '-3 13A-14n 17 13A-43d 16 S}1 1 RO 13A-14o 17 13A-44 0 S}1 2 RO 13A-14p 17 13A-45 0 S}1 3 RO 13A-14q 17 13A-46 16 T 13.5"4 28 13A-14r 17 13A-47 16 T 13.5-5 22 13A"14s 17 13A"48 16 T 13.5-6 13A-14t 17 13A-49 16 Sh 1 23 13A-14u 17 13A-50 0 Sh 2 RO 13A-14v 17 13A"51 0 S}1 3 RO 13A-15 16 13A-52 0 S}1 4 RO 13A"16 16 13A-53 0 S}1 5 23 13A-17 16 13A-54 0 T 13 ~ 5-7 23 13A-18 16 13A-55 0 F 13.5-1 0 13A-19 16 13A-56 16 13A-19a 16 13A-57 16 13.6-1 13A-19b 16 13A-58 16 13A-20 0 13A-59 16 App 13A 0 13A-21 0 13A-60 16 13A-1 0 13A-22 0 13A-61 16 13A-2 16 13A-23 0 13A-62 16 13A-3 16 13A"24 0 13A-63 16 13A-4 16 13A-25 0 13A"64 16 13A-5 0 13A-26 16 13A-65 16 13A-6 0 13A"27 16 13A"66 16 13A-7 0 13A-28 0 13A-67 16 13A-8 0 13A-29 0 13A"68 16 13A-9 0 13A-30 0 13A-68a 9 13A-10 0 13A-31 0 13A-68b 9 13A-ll 0 13A-32 0 13A"68c 17 13A-12 0 13A-33 0 13A"68d 17 13A-13 16 13A-34 0 13A-69 0 13A-14 16 13A-35 16 13A-70 16 13A-14a 16 13A-36 16 13A-71 16 13A-14b 17 13A-37 16 13A-72 0 13A-14c 17 13A-38 16 13A-72a 17 13A-14d 17 13A-39 16 13A-72b 17 13A-14e 17 13A"40 16 13A-72c 17 13A-14f 17 13A-41 16 13A-72d 17 13A-14g 17 13A-4la 16 13A-72e 17 USAR Revision EP 13-2 October 1989

l Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 13A-72f 17 13A-103 0 13A-130 16 13A-72g 17 13A-104 0 13A-130a 16 13A-72h 17 13A-105 0 13A-130b 16 13A-72i 17 13A-106 0 13A-131 0 13A-72j 17 13A-107 0 13A-132 0 13A-721% 17 13A-108 0 13A"133 0 13A-721 17 13A-109 0 13A-134 16 13A-72m 17 13A-110 16 13A"135 16 13A"72n 17 13A-ill 16 13A-136 16 13A-72o 17 13A"112 16 13A"137 16 13A-72p 17 13A-112a 16 13A-73 16 13A-112b 16 App 13B 13A-74 16 13A-113 0 13B-1 13A-74a 16 13A-114 0 13A-74b 16 13A-115 0 13A-75 16 13A-116 0 13A-76 16 13A-117 0 13A-77 16 13A-118 16 13A-78 0 13A-119 16 13A-79 16 13A-120 16 13A-80 16 13A-121 16 13A"81 16 13A-122 16 13A-82 16 13A"123 16 13A-83 16 13A-124 16 13A-83a 16 13A-124a 16 13A"83b 16 13A-124b 16 13A-84 16 13A-124c 16 13A-85 16 13A-124d 16 13A-86 16 13A-125 0 13A-87 16 13A-126 0 13A-88 16 13A-127 0 13A-89 16 13A-128 0 13A-90 16 13A-129 0 13A-91 16 13A-129a 17 13A-92 16 13A-129b 17 13A-93 16 13A-129c 17 13A-94 16 13A-129d 17 13A-95 16 13A-129e 17 13A-96 0 13A-129f 17 13A-97 0 13A-129g 17 13A"98 0 13A-129h 17 13A-99 0 13A-129i 17 13A-100 0 13A-129j 17 13A-101 0 13A-129k 17 13A-102 0 13A-1291 17 USAR Revision EP 13-3 October 1989

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment

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

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~P~Pi ure Number ~P=Pi use Number ~P=Pi ure Number T 14.2-114 T 14.2-129 Sh 1 22 Sh 1 24 S}1 1 22 Sh 2 RO Sh 2 22 Sh 2 24 S}1 3 12 T 14 '-115 Sh 2a 28 T 14.2-213 S}1 1 24 T 14.2-130 S}1 1 RO S}1 2 22 S}1 1 22 S}1 2 RO T 14.2-116 24 S}1 2 22 S}1 3 RO T 14.2-117 T 14.2-131 24 Sh 4 RO S}1 1 24 T 14.2-132 26 F 14.2-213-1 S}1 2 22 T 14.2-201 T 14.2-214 T 14.2-118 S}1 1 RO Sh 1 12 S}1 1 24 S}1 2 22 S}1 2 22 Sh 2 22 T 14 '-202 T 14 '-215 T 14.2-119 Sh 1 RO Sh 1 28 S}1 1 24 S}1 2 28 S}1 2 28 Sh 2 22 T 14.2-203 T 14.2-216 T 14.2-120 S}1 1 8 Sh 1 28 Sh 1 24 Sh 2 28 Sh 2 Rl Sh 2 22 T 14.2-204 e T 14.2-216A 16 T 14.2-121 Sh 1 22 T 14 '-217 Sh 1 24 Sh 2 RO Sh 1 RO S}1 2 22 T 14.2-205 12 S}1 2 RO T 14 '-122 T 14 '-206 T 14.2-218 Sh 1 24 Sh 1 12 S}1 1 22

 .S}i 2          22            S}1 2         RO              Sh 2        28 T 14    '-123                   Sh 3          RO           T  14.2-219 S}1 1         24            Sh 3a         28              Sh 1         8 S}1 2         22            S}1  3b       28              Sh 2        28 T 14    '-124                   Sh 4          16           T 14  '-220 S}1 1         22         T  14.2-207                      Sh 1        28 Sh 2          22            Sh 1          28              S}1 2       28 T 14    '-125                   Sh 2          28           T 14.2-221 S}1 1         24         T  14.2-208                      Sh 1        28 Sh'           22            S}1 1         28              S}1 2       RO Sh 3          22            S}1 2         28              S}1 3       22 T   14.2-126                 T 14   '-209                  T  14.2-222 S}1 1         24            Sh 1          28              Sh 1        RO Sh 2          22            S}1 2         RO              S}1 2       RO Sh 2a         22         T 14.2-210                       S}1 3       16 T 14.2-127                      Sh 1          RO           T  14.2-223 Sh 1          22            S}1 2           8             S}1 1       RO Sh 2          22         T 14   '-211                     S}1 2       22 T 14 ~ 2-128                    S}1 1         28           T  14.2-224 Sh 1          22            S}1 2         28              S}1 1       22 Sh 2          22         T 14 '-212                       Sh 2        12 USAR     Revision  1                    EP 14-4                  October 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number T 14.2-225 ~ Sh 2 28 S}1 1 RO Sh 1

                   '8 F  14.2-236-1   22             Sh   2      RO S}1 2         28         T  14.2-237                    Sh   2a     28 S}1 3         28            Sh 1         28             Sh   2b     28 T  14.2-226                    Sh 2         28             Sh   2c     28 S}1 1         RO         T  14.2-238     22             Sh   2d     28 S}1   2       RO         T  14.2-239                    Sh   3      28 T  14.2-227                    Sh 1         28          T  14.2-305 Sh 1          RO            Sh 2         28             Sh 1        22 Sh 2          RO         F  14.2-239-1     8            Sh 2        22 S}1 3         RO         T  14.2-240                 T 14.2-306     28 T 14   '-228                   Sh 1         28          T 14.2-307     28 S}L 1         28            Sh 2         RO          T 14   '-401   22 Sh 2          RO         T  14.2-241                 T 14.2-402 T  14.2-229      12            S}1 1        28             S}1 1       16 T  14.2-230                    S}1 2        RO             S}1 2       16 S}1 1         28            Sh 3         RO             Sh 3        16 S}1  2        28            S}1  4       22             S}1  4      16 S}1  3        28         T  14.2-241a    22          T 14.2-403     28 T  14.2-231                 T  14.2-24lb    22          F 14.2-1       24 S}1 1         28         T  14.2-242                 F 14   '-2     28 S}1 2         RO            Sh 1           8         F  14.2-3      24 Sh 3          28            Sh 2         28          F  14.2-4      28 Sh 4          RO         T  14.2-243                 F  14.2-5      RO T  14.2-232                    Sh 1         RO          F  14.2-6      22 S}1 1          28            S}1 2        RO          F'4.2-7        16 S}i 2          28         T  14.2-244 T  14.2-233                    Sh 1         28 S}1 1          22            S}i 2        28 Sh 2           RO            S}1 3        22 Sh 3           16         T  14.2-245 F  14.2-233-1    RO            Sh 1         22 T 14.2-234                     Sh 2         28 S}1 1          RO            Sh 3         22 S}1 2          RO         T  14.2-301 Sh 3           RO            Sh 1         RO S}1 4          28            Sh 2         Rl S}1 5          22         T 14   '-302    28 F 14   '-234-1    8         T 14.2-303 T  14.2-235                   S}1 1         28 S}1 1          12           S}1 2         RO S}1   2        22           Sh 2a         RO Sh 3           22           Sh 2b         28 T  14.2-236                   S}1 3         Rl Sh    1        RO         T 14   '-304 USAR    Revision                      EP 14-5                 October 1989

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

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number T 15.2-2 0 15.3-10 22 T 15.4-4 22 T 15.2-3 0 15.3-11 0 T 15.4-5 0 T 15.2-4 0 15.3-12 0 T 15.4-6 0 T 15.2-5 28 15.3-13 0 T 15.4-7 0 T 15.2-6 0 15.3-14 0 T 15.4-8 27 T 15.2-7 T 15 '-1 22 T 15.4-9 22 Sh 1 0 T 15 '-2 10 T 15.4-10 S}l 2 0 T 15.3-3 10 S}1 1 12 T 15.2-8 0 T 15.3-4 22 S}l 2 12 T 15.2-9 22 T 15.3-5 10 T 15.4-11 12 T 15.2-10 F 15.3-1 0 T 15.4-12 12 S}1 1 0 F 15.3-2 0 T 15.4-13 12 S}1 2 0 F 15.3-3 0 T 15.4-14 12 T 15.2-11 22 F 15.3-4 0 T 15.4-15 12 T 15.2-12 27 F 15.3-5 0 T 15.4-16 12 T 15.2-13 22 F 15.4-1 22 F 15.2-1 0 15.4-1 0 F 15.4-2 22 F 15.2-2 0 15.4-2 22 F 15.4-3 0 F 15.2-3 22 15.4-3 28 F 15.4-4 0 F 15.2-4 22 15.4-4 28 F 15.4-5 0 F 15.2-5 0 15.4-4a RO F 15.4-6 0. F 15.2-6 0 15.4-4b 28 F 15.4-7 0 F 15.2-7 0 15.4-5 0 F 15.4-8 0 F 15.2-8 0 15.4-6 0 F 15 '-9 10 15 '-7 22 15.5-1 F 15.2-10 22 15.4-8 0 15.5-2 F 15.2-11 22 15.4-9 0 15.5-3 Notes 15.4-10 0 T 15.5-1 S}1 1 22 15.4-11 0 F 15.5"1 S}1 2 22 15.4-12 22 F 15.2-12 0 15.4-13 22 15.6-1 12 F 15.2-13 0 15 '-14 0 15.6-2 12 F 15.2-14 0 15 '-15 22 15.6-3 RO F 15.2"15 0 15.4-15a 6 15.6"4 12 F 15.2-16 0 15.4-15b 27 15.6-5 0 F 15.2-17 0 15.4-16 22 15.6-6 0 15.4-17 12 15.6"7 12 15.3-1 0 15.4-18 RO 15.6-8 RO 15.3-2 0 15.4-18a RO 15.6-8a 12 15.3-3 0 15.4-18b 12 15.6-8b 12 15.3-4 22 15.4-19 12 15.6-9 25 15.3-5 0 15.4-20 0 15.6-10 0 15.3-6 0 15.4-21 28 15.6-11 RO 15.3-7 22 T 15.4-1 0 15.6-12 RO 15.3-8 27 T 15.4-2 0 15.6-12a RO 15.3"9 0 T 15 '-3 22 15.6-12a.l RO USAR Revision 1 EP 15"2 October 1989

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

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

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

Nine Mile Point Unit 2 FSAR ~ LIST OF EFFECTIVE PAGES CHAPTER 16 I Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number 'F=Fi ure Number ~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 Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number'3

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

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

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

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

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

Nine Mile Point Vnit 2 DAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Pi ure Number ~P=Fi ure Number ~FPi ure Number F 6A.5-40 23 6A.9"6 RO T 6A.10-3 21 F 6A.5-41 23 6A 9-7 RO T 6Ae10-4 21 F 6A.5-42 23 6A.9-8 20 T 6A.10-5 21 F 6A.5-43 23 6A.9-9 20 T 6A.10"6 21 6A.9-9a 20 T 6A.10-7 Rl 6A.6-1 0 6A.9"9b 20 T 6A.10-8 21 6A.6-2 0 6A.9-10 20 T 6A.10-9 21 6A.6-3 26 6A.9-11 20 F 6A.10-1 21 6A.6"4 0 6A.9-11al 20 F 6A.10-2 RO T 6A.6-1 23 6A.9-llbl 20 F 6A.10"3 RO T 6A.6-2 6A.9-lla 9 F 6A.10-4 RO Sb 1 23 6A.9-11b 9 F 6A.10-5 RO Sh 2 23 6A.9-11c 9 F 6A.10-6 RO F 6A.6-1 RO 6A.9-11d 9 F 6A.10-7 RO F 6A.6-2 0 6A.9-11e 9 F 6A.10-8 RO F 6A.6-3 0 6A.9-1lf 9 F 6A.10-9 RO F 6A.6-4 6A.9-12 23 F 6A.10-10 RO Sh 1 T 6A.9"1 Rl F 6A.10-11 Rl S}1 2 T 6A.9-2 RO F 6A.10-12 Rl F 6A.6-5 T 6A.9-2a RO F 6A.10-13 Rl F 6A.6-6 T 6A.9-2b RO F 6A.10-14 22 F 6A.6-7 T 6A.9-3 RO F 6A.10-15 22 T 6A.9-4 RO F 6A.10-16 22 6A.7-1 0 T 6A.9-5 RO F 6A.10-17 22 6A.7-2 7 T 6Ae9-6 RO F 6A.10-18 22 6A.7-3 0 T 6A.9-7 RO F 6A.10-19 22 6A.7-4 0 F 6A.9-1 23 F 6A.10-20 22 6A.7-5 23 F 6A.9-2 23 6A.7-5a 7 F 6A.9-3 23 6A.7-5b 7 6A.7-6 23 6A.10-1 Rl 6A.7-7 23 6A.10-2 RO T 6A.7-1 0 6A.10-3 21 T 6A.7-2 23 6A.10"4 22 F 6A.7-1 0 6A.10-5 21 6A.10-6 21 6A.8"1 6A..10-7 21 6A.8-2 6A.10-8 21 6A.10-9 RO 6A.9-1 0 6A.10-9a 24 6A.9-2 0 6A.10-9b 24 6A.9-3 0 6A.10-10 RO 6A.9-4 RO T 6A.10-1 RO 6A.9-4a RO T 6A.10-2 6A.9-4b RO S11 1 RO 6A.9-5 27 Sjl 2 RO 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 Page" Page T=Table Amendment T=Table Amendment T=Table Amendment ~F=Fi ure Number ~F=Fi ure Number ~F=Fi ure Number 98-i 98-ia 24 T 98 '-3 Sh 14 ll 24 Sh 1 23 Sh 15 RO 98-ib 98-ii 23 Sh 2 ll Sh 16 11 RO Sh 3 RO Sh 17 11 98-iii 24 Sh 4 11 Sh 18 RO 98-iv 4 Sh 5 RO Sh 19 11 sh 6 11 Sh 20 28 98.1-1 23 Sh 7 23 Sh 21 28 Sh 7a RO Sh 22 28 98.2-1 RO S}1 8 28 Sh 23 28 98 '-2 4 Sh 9 11 Sh 24 28 98.2-3 4 F 98.6-1 4 Sh 25 28 F 98 '-2 ll Sh 26 RO 98.3-1 23 F 98.6-3 ll Sh 27 RO F 98.6-4 ll Sh 28 RO 98 '-1 4 F 98.6-5 ll Sh 29 RO 98.4-2 98.4-3 22 F 98 '-6 ll Sh 30 RO 4 Sh 30a RO 98.4-4 4 98.7-1 23 Sh 31 ll 98.4-5 22 Sh 32 RO 98.4-6 4 98.8-1 RO Sh 33 RO 98.4-7 4 98.8-2 23 Sh 34 28 98.4-8 4 98.8-3 Rl S}1 35 28 F 98.4-1 22 98.8-4 23 Sh 36 23 F 98.4-2 22 98.8-5 Rl Sh 37 23 98.8-5a Rl Sh 38 23 98.5"1 RO 98.8-5b RO Sh 39 23 98.5-2 4 98.8-6 25 Sh 40 23 98.5-3 4 98.8-7 RO Sh 41 23 98.5-4 21 T 98 '-1 Sh 42 23 98 '-5 23 Sh 1 RO Sh 43 23 T 98.5-1 RO Sh la 28 Sh 44 23 Sh 2 11 Sh 45 23 98.6-1 22 S}1 3 RO Sh 46 23 98.6-2 11 sh 4 28 Sh 47 23 98.6-3 25 Sh 5 28 Sh 48 23 98.6-4 11 Sh 5a 28 Sh 49 23 T 98.6-1 Sh 6 11 Sh 50 23 Sh 1 28 S}1 7 28 Sh 51 ll Sh 2 28 Sh 8 28 Sh 52 RO Sh 3 RO Sh 9 28 Sh 53 RO Sh 4 RO Sh 10 RO Sh 54 23 Sh 5 RO Sh 11 11 Sh 55 RO Sh 6 RO Sh 12 RO Sh 56 19 T 98.6-2 11 Sh 13 11 Sh 57 19 USAR Revision SSA-1 October. 1989

Nine Mile Point Unit 2 FSAR LIST OF EFFECTIVE PAGES Page Page Page T=Table Amendment T=Table Amendment T=Table Amendment ~P=Pi ure Number ~F=Fi ure Number ~F=Fi ure Number S}1 58 RO Sh 23 RO 9B.10-1 RO Sh 59 ll Sh 24 RO Sh 60 RO Sh 25 28 9B.ll-l 21 Sh 60a RO Sh 26 28 Sh 61 RO Sh 27 28 9B.12-1 RO Sh 62 RO Sh 28 23 9B.12-2 RO Sh 63 RO Sh 29 23 9B.12-3 RO Sh 64 RO Sh 29a 23 9B.12-4 RO Sh 65 RO Sh 29b 23 9B.12-5 RO Sh 66 RO Sh 29c 23 9B.12-6 RO Sh 66a RO Sh 29d 23 9B.12-7 RO Sh 67 RO Sh 29e 23 9B.12-8 RO Sh 68 RO Sh 23 9B.12-9 RO Sh 69 RO 29'h 30 ll 9B.12-10 RO Sh Sh 70 71 RO Sh 31 ll 9B.12-11 RO RO Sh 32 RO Sh 72 RO Sh 33 23 Sh 73 RO Sh 33a 23 Sh 73a RO Sh 34 RO Sh 74 RO Sh 34a RO Sh 75 RO Sh 35 11 '3 Sh 75a RO Sh 36 T 9B.8-2 Sh 37 28 Sh 1 28 Sh 38 RO Sh 2 11 Sh 38a 23 Sh 3 28 Sh 38b Rl Sh 4 ll T 9B.8-3 Sh 5 28 Sh 1 23 Sh 6 28 Sh 2 RO Sh 7 28 Sh 3 RO Sh 8 11 Sh 4 RO S}1 9 11 Sh 5 RO Sh Sh 10 ll Sh 5a RO 11 11 S}1 6 RO Sh 12 ll Sh 7 RO S}1 13 28 Sh 8 RO Sh 14 28 Sh 9 RO Sh 15 28 Sh 10 RO Sh 16 28 S}1 11 23 Sh 17 28 Sh 12 RO Sh 18 28 Sh 13 Rl Sh 19 RO Sh 14 RO Sh 20 RO Sh 21 RO 9B.9-1 RO Sh 22 RO USAR Revision SSA-2 October 1989

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Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont) Section Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6,3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7.2 Reactor Protection (Trip) System (RPS) Instrumentation and Controls . 15 7 ' Engineered Safety Feature Systems 15 7.4 Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7 ~7 Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System 16 8.3 Onsite Power System 16 i 17 Appendix 8A 17 CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems 18 9.3 Process Auxiliaries 19 9' Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C 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 Summary, Description 23 10.2 Turbine Generator '23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix 11A 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26 12.5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26 13.3 Site Emergency Plan 26, 13.4 Operation Review and Audit 26 13.5 Plant Procedures 26 13.6 Industrial Security 26 Appendixes 13A, 13B 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 Title

1. 1-1 HEAT BALANCE AT RATED POWER

1. 2-1 PLOT PLAN 1.2-2 STATION ARRANGEMENT 1.2-3 DELETED 26 1.2-4 DELETED 1.2-5 DELETED 1.2-6 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN Sjl. 1 EK 175'-0" AND 188.'-6"

l. 2-6 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN 196'-0" S}1. 2 EK 1.2-7 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN EL 215'-0~~

1.2-7 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN SI1. 2 EK 240'-0" 1.2-8 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN-S11. 1 EL 261'-0" AND MISCELLANEOUS

1. 2-8 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN Sjl. 2 EL 215'-0" AND MISCELLANEOUS 1.2-9 GENERAL ARRANGEMENT, REACTOR BUIKDING PLAN S11. 1 EL 289'-0" 1.2-9 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN Sh. 2 EL 306'-0" 1.2-10 GENERAL ARRANGEMENT, REACTOR BUILDING PLAN Sh. 1 EL 328'-10" 1.2-10 GENERAL ARRANGEMENT, REACTOR BUILDING PEAN Sh. 2 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 GENERAL ARRANGEMENT, REACTOR BUILDING SECTIONS (SHEETS 1 THROUGH 4) 1.2-12 GENERAL ARRANGEMENT, REACTOR BUILDING SECTION 2-2 1 1.2-13 GENERAL ARRANGEMENT, RADWASTE BUILDING PLAN EL 261 '0", 270 '9 I'ND 309 '0" (SHEETS 1 THROUGH 3) 1.2-14 GENERAL ARRANGEMENT, RADWASTE BUILDING SECTIONS 1.2-15 GENERAL ARRANGEMENT, CONTROL ROOM PLAN EL 360'-0" I 288'-6" I 261'-0" (SHEETS 1 THROUGH 3)

1. 2-16 GENERAL ARRANGEMENT, CONTROL BUILDING 1.2-17 GENERAL ARRANGEMENT, EMERNGECY DIESEI GENERATOR BUILDING PLAN (SHEETS 1 THROUGH 6) 1.2-18 GENERAL ARRANGEMENT, EMERGENCY DIESEL GENERATOR BUILDING SECTIONS

1. 2-19 GENERAL ARRANGEMENT, TURBINE BUILDING PLAN EL 250'-0" (SHEETS 1 AND 2) 1.2-20 GENERAL ARRANGEMENT, TURBINE BUILDING PLAN EL 277'-6" (SHEETS 1 AND 2)

GENERAL ARRANGEMENT, TURBINE BUILDING PLAN EL 306'-6" (SHEETS 1 AND 2) 1.2-22 GENERAL ARRANGEMENT, TURBINE BUILDING '" I SECTION 1-1 (SHEETS 1 AND 2) 1.2-23 GENERAL ARRANGEMENT, TURBINE BUILDING PLAN SECTION 2-2 AND 4-4.(SHEETS 1 AND 2)

1. 2-24 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 GENERAL ARRANGEMENT, SCREENWELL BUILDING WATER TREATMENT AND SERVICE WATER PUMPS PLAN (SHEETS 1 AND 2) 1.2-27 GENERAL ARRANGEMENT, SCREENWELL BUILDING WATER TREATMENT AND SERVICE WATER PUMPS PLAN SECTION (SHEETS 1 AND 2) 1.2-28 GENERAL ARRANGEMENT, SCREENWELL BUILDING WATER TREATMENT AND,SERVICE WATER PUMPS PLAN SECTION 1.2-29 GENERAL ARRANGEMENT AND DETAILS, INTAKE AND DISCHARGE TUNNELS (SHEETS 1 THROUGH 3) 1.2-30 GENERAL ARRANGEMENT AND DETAILS, INTAKE STRUCTURE 1 ~ 2-31 GENERAL ARRANGEMENT AND DETAILS, MAIN STACK 1.2-32 GENERAL ARRANGEMENT, NORMAL SWITCHGEAR BUILDING PLANS (SHEETS 1 THROUGH 3) 1 ~ 2 33 GENERAL ARRANGEMENT, NORMAL SWITCHGEAR BUILDING 1.2-34 GENERAL ARRANGEMENT, AUXILIARY BOILER HOUSE 1.2-35 GENERAL ARRANGEMENT, STANDBY GAS TREATMENT BUILDING EL 261'-0" 1.2>>36 GENERAL ARRANGEMENT, STANDBY GAS TREATMENT BUILDING AND RAILROAD ACCESS IOCK SECTION 1 ~ 2 37 GENERAL ARRANGEMENT, CONDENSATE STORAGE TANK BUILDING (SHEETS 1 AND 2) 1.2-38 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 ~ Title 1.2-39 COOLING TOWER SECTION BELOW THE FILL LEVEL 1.2-40 GENERAL ARRANGEMENTi HYDROGEN STORAGE AREA 1.7-1 PIPING AND INSTRUMENTATION DIAGRAM (SWEC) (SHEETS 1 THROUGH 5) 1.7-2 PIPING AND INSTRUMENT SYMBOLS (GE) 1.7-3 LOGIC DIAGRAMS SYMBOLS (SWEC) (SHEETS 1 AND 2) 1.7-4 ELECTRICAL'NE-LINE DIAGRAMS SYMBOLS (SWEC) 1.8-1 ENGINEERED SAFETY-FEATURE FILTER DRAIN ARRANGEMENT 1.10-1 DELETED 1.10-2 DELETED 1.10,-3 DELETED 1.10-4 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 2.6 in November 1972. It had a starting speed of about would continue to operate with speeds of 1 to mph and 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 training to be acquainted with the relevant quality sufficient, 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 least sufficient training to be acquainted with the not, at 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 NRC Licenses. 4 '.1, Supervisors Requiring

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 experience requirement on cold applicants for SRO licenses. Cold applicants are to work on a facility not yet in operation; their training programs are designed to supply the equivalent of the experience not available to them. 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 HABITABILITYSTUDY Allowable Maximum  Control                          Time Chemical                              Room Concentration          Toxic Limit   Period Location               Chemical              (                       (           (min J.A. FitzPatrick m'1.2                    m'74 N~                                                        15 Plant                    Hq SO            6.6 x      10             0.002           2 CO~               6.2                       54.8          15 Propane           1.29                      43.1          15 Halon             1.73 Alcan                    Cl~               0.038                     0.045           2 Propane           1.1                       43.1          15 Nq                0.09                      274           15 Hcl               0.003                     0.05          15 CO~               2.5 x 10                  54.8            2 Route 104                Hcl               0.009                     0.050         15 N~                0.54                      274           15 CO~               0.0                       54.8            2 Nine Mile Point          Nq                22.2                      274           15 Unit  1                  COq               14.7                      54.8          15 Hq SO            1.3 x                     0.002           2 Hcl               0.009                     0.05          15 Halon             0.57                      432           15 Nine Mil'e Point         Hq SO            6.6 x      10 4 0.002           2 Unit  2                  CO~               46.8                      54.8          15 Halon 1301        3.88                      432           15 N~                32.1                      274           15 Oswego Wire              Isopropyl         2.2 x 10      4 1.2           15 Incorporated             Alcohol Nq                1.2 x 10                  274           15 Propane           2.1 x 10                  43.1          15 H~ SO            1.0 x 10                  0.002           2 USAR  Revision 0                               1.10-133                            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, that a generic method to consider fatigue of it is suggested 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 straighteners to suppress vortex formation. The pumps have as flow 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 is evaluated by acceptance, qualification, pumps'ffectiveness 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 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7.4 Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for 16 Systems Not Required Safety'ontrol 7~7 for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System . 16 8.3 Onsite Power System '16, 17 Appendix 8A I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water 'Systems ,18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C 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 Summary .Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix 11A 25 - CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26

13. 3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR) 26 iv

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       1980 POPULATION AND POPULATION DENSITIES FOR TOWNS AND CITIES WITHIN 16 KM (10 MI) OF UNIT 2 2 1 3
 ~         1970-1980 POPULATION GROWTH        FOR TOWNS AND CITIES WITHIN 16 KM (10 MI)        OF UNIT 2

2. 1-4 DELETED

2. 1-5 DELETED

2. 1-6 DELETED 2 1 7

 ~         DELETED 2.1-8       DELETED 2.1-9       DELETED 2.1-10      DELETED 2.1-11      DELETED 2.1-12      DELETED 2 1 13
 ~         DELETED 2.1-14      DELETED 2.1-15      DELETED 2.1-16      DELETED 2 '-17      DELETED 2.1-18      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 DELETED 2.1-20 DELETED 2.1-21 DELETED 2.1-22 DELETED 2.2-1 DAILY TRAFFIC, VOLUME OF .COUNTY HIGHWAYS IN THE VICINITY OF UNIT 2

2. 2-2 1978 FREIGHT TRAFFIC FOR LAKE ONTARIO AROUND OSWEGO HARBOR 2 2 3

 ~           INDUSTRIAL FIRMS WITHIN 8      KM (5 MI) OF UNIT 2

2. 2-4 ARMY CORPS OF ENGINEERS HAZARDOUS MATERIAL COMMODITY DESIGNATION FOR RATERBORNE COMMERCE 2.2-5 HAZARDOUS MATERIALS STORED/USED BY INDUSTRIES WITHIN 8 KM (5 MI)

2. 2-6 1978 LAKE ONTARIO CARGO TRANSPORT FOR OSWEGO HARBOR 2 2 7

 ~           SOURCES  OF TOXIC CHEMICALS     WITHIN 8 KM (5 MI)  OF UNIT 2 SITE 2.2-8         PREDICTED VAPOR CONCENTRATIONS IN THE UNIT 2 CONTROL ROOM 2.2-9         INPUT DATA FOR VAPOR RUN 2.3-1         DESIGN BASIS TORNADO PARAMETERS 2.3-2         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 the plant. 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, on nearby transportation routes are not consideredex-'losions 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 Distance/ Direction from Site Firm (km Alcan Aluminum 4.5/SW Aluminum 1,000 Corporation sheet and plate James A. FitzPatrick <1/E Electrical 515 Nuclear Power Plant generation Nine Mile'Point Adjacent Electrical 450 Unit 1 to Unit 2 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) Storage on Shi ent Premises Maximum Average Industrial (Max. at Quantity Quantity Material User O~eTL e MOd* ~A* a Sla ~Sh ed ~Fe ue e ~Shi ~ed yr Carbon dioxide Alcan 65 tons Truck 6 tons 10 tons Weekly 250 tons FitzPatrick 26,000 lb Truck 6,900 gal 6,900 gal Infrequently, Small quantitres as needed used to recharge system NMP Unit 1 20,000 lb Truck 5,000 lb 6,300 gal Monthly 56,000 gal Chlorine Alcan 30 tons Truck 1 (1 ton) 12 tons Biweekly 350 cylinders cylinder Helium Alcan 1,917 ft Truck 213 ft 9 cylinders As needed 94 cylinders (213 ft each) (20i022 ft ) Hydrochloric acid Alcan 500 gal Truck 55 gal 385 gal Weekly 16,000 gal Hydrogen FitzPatrick 28,800 ft Truck 128g000 ft 128,000 ft Biweekly 221,000 ft NMP Unit 1 12,000 ft Truck 24,000 ft 24,000 ft Bimonthly 72,000 ft Oswego Wire 6,450 ft Truck 515 ft 5,375 ft 10 Weeks 27,305 ft Nitrogen Alcan 970,000 ft Truck 670,000 'ft 670,000 ft Honthly 8,999,200 ft FitzPatrick 10,000 gal Truck 6,900 gal 6,900 gal Monthly 129,000 gal NMP Unit 1 15,300 gal Truck 6,300 gal 6,300 gal Monthly 56,000 gal Oswego Wire 160,000 ft Truck 145,000 ft 160,000 ft Weekly 8,000,000 ft Propane FitzPatrick 1,000 gal Truck 22,500 lb 22,500 lb Monthly 3,000 gal Alcan 80i000 lb Truck 7,000 lb 7,000 lb Biweekly 200,000 gal Sodium hydroxide FitzPatrick 5,000 gal Truck 3g000 lb 3,000 lb Monthly 246,000 lb Alcan 3,000 gal Truck 55 gal 1,000 gal Monthly 10,000 gal NMP Unit 1 165 gal Truck 55 gal 55 gal As needed 100 gal Oswego Wire 385 gal Truck 55 gal 55 gal Monthly 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 Distance Amount to Intakes Chemical Location Chemical (m James A. Fitz- N2 0.305 x 10s 620 Patrick plant H2 SO 0.346 x 10s 620 CO2 1.18 x 10' 620 Propane 0.221 10' 620 Halon 0.260 10' 620 Alcan Clq 0.181 10' 4,990 Propane 0.363 10s 4,990 N2 0.260 x 10s 4,990 HCL 0.226 x 107 4,990 COR 0.533 x 10s 4i990 Route 104 HC1 0.542 x 107 5,470 N2 0.183 x 5,470 CO2 x 10~ 10'.272 5,470 Nine Mile Point N2 0.443 x 10s 290 Unit 1 CO2 0.907 x 10' 265 H2 SO 0.114 10' 290 HCL 0.454 10' 290 Halon 0.227 10e 290 Nine Mile Point H22 0.118 x 33 Halon 1301 x 10'.113 45 N2 x 10s 10'.671 150 Oswego Wire Isopropyl 0.330 x 10e 7, 080 Incorporated Alcohol N2 0.525 x 10e 7,080 Propane 0.947 x 10e 7,080 H2 SO 0.750 x 10e 7,080 HCL 0.182 x 10" 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 Maximum Allowable Control Room Time Chemical Concentration Limit Period Location Chemical ( m~ (min James A. N~ 11.2 274 15 FitzPatrick Hq SO 6.6 x 10-~ 0.002 2 plant COq 6.2 54.8 15 Propane 1.29 43.1 15 Halon 1.73 432 15 Alcan Clq 0.038 0.045 2 Propane 1.1 43.1 15 N~ 0.09 274 15 HCL 0.003 0.05 15 CO~ 2.5 x 54.8 2 10-'.009 Route 104 Hcl 0.050 15 N~ CO~ 0.54 0.0 10-'oxic 274 54.8 15 2 Nine Mile Nq 22.2 274 15 Point Unit 1 COq 14.7 54.8 15 H~ SO 1.3 x 10-~ 0.002 2 Halon 0.57 432 15 Hcl 0.009 0.05 15 Nine Mile Hq SO 6.6 x 10 0.002 2 Point Unit 2 CO~ 46.8 54.8 15 Halon 3.88 432 15 1301 N~ 32.1 274 15 Oswego Wire Isopropyl 2.2 x 10-4 1.2 15 Incorporated Alcohol Nq 1.2 x 10-~ 274 15 Propane 2.1 x 10 43.1 15 Hq SO 1.0 x 0.002 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.are The results of the inspections and kept in a log. maintenance'erformed 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- ft) 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 Total Bldg. Length Flow Depth ~Biidi ~ft ~ftA ~in Distribution of Plow Flux Diesel generator Stop 404.2 Evenly over floor; provided caulking logs material to make stop logs watertight. 15 551.1 Control building C261-29 257.2 C261-29 and C261-31 flows will combine and C261-24 110.2 spread through El. 261 corridors and into some C261-31 110.2 rooms. C261-24 will flow down stairwell and spread through corridors on lower floors. No fix is required. Auxiliary bay south SA262-3 63.6 Plow will be confined to auxiliary bay stairwell area. No fix is required. Electrical tunnel ET262-4 63.6 Plow will be spread evenly through each tunnel. south area Electrical tunnel ET261-1 102.6 north area ET261-2 102.6 Auxiliary bay north NA262-1 63.6 Plow will be confined to auxiliary bay stairwell area. No fix is required. RB railroad track bay RR-261-1 17 NA NA Doors are equipped with inflatable air seals; water leakage will be negligible. No safety-related equipment is in this area. Standby gas treatment SG261-2 273.6 Plow is spread evenly throughout the building SG261-1 273.6 (see Note 5). SG261-6 102.6 Service water pump room AB261-3 NA 2.5 Plow into auxiliary boiler building is dis-(north) from auxiliary tributed into the pumphouse if AB261-3 is open. boiler room USAR Revision 0 1 of 2 April 1989

Nine Mile Point Unit 2 FSAR TABLE 2.4-15 (Cont) Total Bldg. Length Flow Depth B~B'd'ervice Door ~ft ~ftA ~in Distribution of Flow Flux water pump room SW261-14 94.2 Evenly throughout building. (south) from screenwell area 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7 ' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7,4 Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7 ' Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System 16 8.3 Onsite Power System 16,17 Appendix 8A 17' CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems 18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9Ag 9C I 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 Summary .Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11 ' Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11 ' Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26 13.2 Training 26 13.3 Site Emergency Plan 26 13.4 Operation Review and Audit 26 13.5 Plant Procedures 26 13.6 Industrial Security 26 Appendixes 13A, 13B 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5Ag 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7 ' Introduction 15 7 ' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7 ' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7 ' Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System 16 8.3 Onsite Power System 16,17 Appendix 8A I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems 18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C 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 Summary, Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 -Radiation Sources 25 12.3 Radiation Protection Design Features 25 12 4

  ~          Dose Assessment                         26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13.1 Organizational Structure of Applicant 26

13. 2 Training 26

13. 3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7 ' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7 ' Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System 16 8.3 Onsite Power System 16,17 Appendix 8A 17 I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems 18 9.3 Process Auxiliaries 19 9' Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C I 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 Summary .Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11 ' Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25

12. 2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26 12.5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26 13.2 Training 26

13. 3 Site Emergency Plan 26.

13. 4 Operation Review and Audit 26 Plant Procedures

                                                        '6

13. 5

13. 6 Industrial Security 26 Appendixes 13A, 13B 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 Title Volume 5.3 Reactor Vessel "13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7 ' Introduction 15. 7 ' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7 ' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7~7 Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16' 8.2 Offsite Power System 16 8.3 Onsite Power System '16, 17 Appendix 8A 17 CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems .18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C I USAR Revision I 0 April 1989

       ~   I

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont) Section Title Volume CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 23 10.1 Summary . Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix 11A II 25 CHAPTER 12 RADIATION PROTECTION 25 12 1

  ~         Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)                     25

12. 2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26 13 1~ Organizational Structure of Applicant 26 13.2 Training 26 13,. 3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26'6

13. 5 Plant Procedures

13. 6 Industrial Security 26 Appendixes 13A, 13B 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5Ag 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes ~ through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7.4 Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7 ' All Other Instrumentation Systems Required for Safety 16 7~7 Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System , 16 8.3 Onsite Power System '16, 17 Appendix 8A 17 I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems .18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9Ag 9C I 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 I 10.1 Summary, Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10 ' Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT

11. 1 Source Terms 1 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25

12. 2 Radiation Sources 25

12. 3 Radiation Protection Design Features 25 12.4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26

13. 3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 26 CHAPTER 14 INITIAL TEST PROGRAM 26

14. 1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR) 26 iv

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF FIGURES (Cont) Figure Number Title 3.6A-40 HIGH ENERGY PIPE BREAKS REACTOR WATER CLEANUP OUTSIDE CONTAINMENT 3.6A-41 HIGH ENERGY PIPE BREAKS REACTOR WATER CLEANUP OUTSIDE CONTAINMENT 3.6A-42 HIGH ENERGY PIPE BREAKS STANDBY LIQUID CONTROL INSIDE CONTAINMENT 3.6A-43 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-44 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-45 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-46 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-47 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-48 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-49 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT 3.6A-50 DELETED 27 3.6A-51 DELETED 3.6A-52 HIGH ENERGY PIPE COMPOSITE PLAN EL 175'-0" AND 215'-0" 3.6A-53 HIGH ENERGY PIPE COMPOSITE PLAN EL 240'-0" 3.6A-54 HIGH ENERGY PIPE COMPOSITE PLAN EL 261'-0" Amendment 27 3-xli July 1986

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF FIGURES (Cont) Figure Number Title

3. 6A-55 HIGH ENERGY PIPE COMPOSITE PLAN EL 289'-0"

3. 6A-56 HIGH ENERGY PIPE COMPOSITE PLAN EL 306'-6" 3.6A-57 HIGH ENERGY PIPE COMPOSITE PLAN EL 328'-10" 3.6A-58 HIGH ENERGY PIPE COMPOSITE SECTION 1-1 3.6A-59 HIGH ENERGY PIPE COMPOSITE SECTION 2-2

3. 6A-60 HIGH ENERGY PIPE COMPOSITE SECTIONS 3-3 AND 4-4 3.6B-1 TYPICAL RESTRAINT FORCE DEFLECTION CURVE 3.6B-2 TYPICAL PIPE WHIP RESTRAINT'ONFIGURATION 3.6B-3 BREAK LOCATIONS AND RESTRAINTS ANALYZED, PDA VERIFICATION PROGRAM 3.7A-l HORIZONTAL SSE DESIGN RESPONSE SPECTRA NORMALIZED TO 0.15 G 3.7A-2 VERTICAL SSE DESIGN RESPONSE SPECTRA NORMALIZED TO 0.15 G 3.7A-3 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 3.7A-4 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) Electrical Group Quality (31, 32, Scope of Classifi- Seismic Classifi- Assurance 33, Tornado

                                       ~Su ~1    Location cation          C~at o        cation    Re  irement 34   Protection Notes 125-V  DC   Power   S   stems 125-V dc emergency         batteries and racks                                                 1E                            NA 125-V dc emergency         battery chargers 125-V dc emergency switchgear                                                                              NA 125-V dc emergency centers                                                                                 NA 125-V dc emergency distribution panels                              M,C,RB   1E Emergency cables                                  MiCiRB   1E Cable tray and fabricated supports with safety functions                   MiCgRB   NA DC  containment penetrations                      RB       1E Conduit and nonemergency cable tray                                       MgCgRB   NA                            NA                                     (34)

Miscellaneous Com nents Reactor building polar crane Non-1E (22) Civil Structures (29) Primary containment (28g44) Reactor building, including fuel storage facilities and auxiliary bays (28,29i 36) Radwaste building NA NR (20) Control building I T Diesel generator building Z T 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 NA NA 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 if is seismically mounted and evaluated to ensure that failure occurs related equipment. it will not cause degradation of safety-USAR Revision 0 26h of 26 April 1989

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont) Section Title Volume 5.3 Reactor Vessel 13 5' Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7 ' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7~7 Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System . 16 8.3 Onsite Power System '16, 17 Appendix 8A 17' CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems .18 9.3 Process Auxiliaries 19 9' Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9Ag 9C 23 I 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 Summary, Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER ll RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11 ' Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25, 12.2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26

13. 3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26

-13. 5 Plant Procedures 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A . through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7 ' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7.4 Systems Required for Safe Shutdown 16 7' . Safety-Related Display Instrumentation '16 7 ' All Other Instrumentation Systems Required for Safety 16 7 ~ 7. Control Systems Not Required for Safety 16 Appendixes 7Ag 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System , 16 8.3 Onsite Power System 16,17 Appendix 8A 17 I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems ,18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C I 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 Summary .Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10 ' Other Features of Steam and Power Conversion System CHAPTER ll RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25

12. 2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26 13 2~ Training 26

13. 3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures 26'6

13. 6 Industrial Security Appendixes 13A, 13B 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, branch line needs to be analyzed, its model includes the ef-if the 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 X Z Mass (East- (North-Node ~West Vertical ~South Dg X Dg Dz Y z Dp X Dp Dg z D3 D3 D3 X z N N N N X z Where: 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, NB-3653.1 is not satisfied, if Equation (10) of Subpara-fatigue analysis is per-graph a 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 at all process is repeated until dynamic displacements 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14

6. 3- Emergency 'Core Cooling Systems ,. 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A . through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip)

            -'System (RPS) Instrumentation and Controls                                          15 7 '            Engineered Safety Feature Systems                 15 7 '            Systems Required for Safe Shutdown                16 7.5            Safety-Related Display Instrumentation                                   16 7.6            All Other Instrumentation Systems Required for Safety                       16 7 '            Control Systems Not Required for Safety                                        16 Appendixes 7A, 7B                                                16 CHAPTER 8      ELECTRIC POWER                                    16 8.1            Introduction                                      16
                                                            '. 16 8.2            Offsite     Power System 8.3            Onsite     Power System                          '16, 17 Appendix  8A                                                     17     I CHAPTER 9      AUXILIARY SYSTEMS                                 17 9.1            Fuel Storage and Handling                         17 9.2            Water Systems                                   :18 9.3,           Process Auxiliaries                               19 9.4            Air Conditioning, Heating, Cooling, and Ventilation Systems                           20,21 9.5            Other Auxiliary Systems                           21,22 Appendixes 9A,      9C                                           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 Summary .Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10 ' Other Features of Steam and Power Conversion System CHAPTER ll RADIOACTIVE WASTE MANAGEMENT 24 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 Radiation Sources 25

12. 3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26.

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26

13. 3 Site Emergency Plan 26 '*

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures. 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 26 CHAPTER 14 INITIAL TEST PROGRAM 26 14.1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR) 26 iv

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, fabricator, paragraph 104.3, are performed by the piping 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 different pipe has different in various contents flow (medium) and therefore weights 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 to temperature distribution across the thickness of the pipe wall and geometric and material discontinuities during thermal transients must be considered. These are represented in ASME Section III, Subarticle NB-3600, by: 1 2'b(aa E ~ hT , and E (~ T -cx bb( (3.9A-2) Based on geometry, fluid type, insulation, thermal transients, environmental data:

    ~ 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 analyzed with NUPIPE. In the matrix equation of motion: 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 Guide 1.67. III, Article NC-7000, and Regulatory 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 Loads D~Bct 1 t So Allowable Stress Normal Primary sustained DL ASME IZZ (1974, including Summer 1974 Addenda), Subsection NF; and Subsection NA, App XVIli Article XVZI-2000 Upset Primary sustained DL+SRSS (OBEIgOCCU) and occasional associated with upset Upset All primary and DL+THER+SRSS (OBEIgOCCU) secondary Emergency Primary sustained and occasional DL+SRSS (OBEIiOCCE) ASME III (1974, including Summer 1974 Addenda), associated with Subsection NA, emergency App. XVZI,- Article XVII-2110 Faulted Primary sustained DL+SRSS (SSEIgOCCF) ASME IIZ (1974, including and occasional Summer 1974 Addenda)> associated with App. Fi faulted Paragraph F-1370 KEY: DL = Dead load OBEI = Operating basis earthquake inertia load of piping OBET = Operating basis earthquake total, i.e., the absolute sum of the amplitudes of OBE inertia load and load due to OBE anchor movements OCC(UiEiF) = 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. SSE = Safe shutdown earthquake inertia load of piping THER* = 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.

USAR Revision 0 1 of 1 April 1989

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont) Section Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A . through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7 ' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7~7 Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System , 16 8.3 Onsite Power System '16, 17 Appendix 8A 17 I CHAPTER 9, AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems ,18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20g21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C 23 I 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 Summary .Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply Syst: em 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix 11A 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

12. 5 Health Physics Program 26 CHAPTER 13 CONDUCT OF OPERATIONS 26

13. 1 Organizational Structure of Applicant 26 13.2 Training 26 13.3 Site Emergency Plan 26

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 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 Title Pacae INTRODUCTION 3A-1 3A 1

 ~                   SHE LI 1                             3A.1-1 3A.l.l                General Description                  3A.1-1 3A.1.2                Program   Verification               3A.l-l 3A.1.3                References                           3A.1-3 3A.2                  ASAAS                                3A.2-1 3A.2.1                General Description                  3A.2-1 3A.2.2                Program   Verification               3A.2-1 3A.2.3                References                           3A.2-4 3A.3                  TAC2D                                3A.3-1 3A.3.1                General Description                  3A.3-1 3A.3.2                Program Verification                 3A.3-1 3A. 2.,3              Ref'erences                          3A.3-5 3A.4                  MAT 6                                3A. 4-1 3A. 4.'1              General Description                  3A. 4-1 3A. 4.2               Program Verification                 3A. 4-1 3A. 4. 3              References                           3A ~ 4-2 3A. 5                 STRUDL   II  and STRUDL-SW           3A.5-1 3A.5.1                General Description                  3A.5-1 3A.5.2                Program   Verification               3A.5-1 3A.5.3                References                           3A.5-2 3A.6                  Time'istory (TIMHIS6)      Program   3A. 6-1 3A.6.1                General Description                  3A. 6-1 3A.6.2                Program Verification                 3A.6-1 3A.6.3                References                           3A.6-2 3A.7                  DELETED                              3A.7-1 3A.7.1                DELETED                              3A.7-1    27 3A.7.2                DELETED                              3A.7-1.

3A.8 DINASAW 3A.8-1 3A.8.1 General Description 3A.8-1 3A.8.2 Program Verification 3A.8-1 3A.8.3 References 3A.8-3 Amendment 27 3A-i July 1986

Nine Nile Point Unit 2 FSAR APPENDIX 3A TABLE OF CONTENTS (Cont) Section Title Pacae 3A. 9 LIMITA II 3A.9-1 3A F 9.1 General Description 3A.9-1 3A.9.2 Program Verification 3A.9-4 3A.9.3 References 3A.9-5 3A.10 LIMITA III 3A.10-1 3A.10.1 General Description 3A.10-1 3A.10.2 Program Verification 3A.10-2 3A.10.3 References 3A.10-3 3A.11 STARDYNE 3A.ll-l 3A.11.1 General Description 3A.ll-l 3A.11.2 Program Verification 3A.ll-l 3A.12 SSLAM 3A.12-1 3A.12.1, General Description 3A.12-1 3A.12.2 Program Verification 3A.12-1 3A.12.3 References 3A.12-2 3A.13 SSLOAD 3A. 13-1 3A ~ 13.1 General Description 3A. 13-1 3A.13.2 Program Verification 3A ~ 13-1 3A.13.3 References 3A:13-2 3A.14 MISSILE 3A. 14-1 3A.14.1 General Description 3A. 14-1 3A.14.2 High Trajectory Verification 3A. 14-1 3A.14.3 Low Trajectory Verification 3A. 14-2 3A.14.4 References 3A 14-3

                                               ~

3A. 15 NUPIPE 3A. 15-1 3A. 15. 1 General Description 3A. 15-1 3A. 15. 2 Program Verification 3A. 15-1 3A. 15 3

      ~       References                    3A.15-2 3A.16          DELETED                       3A. 16-1 3A.16.1        DELETED                       3A.16-1 3A;16.2,       DELETED                       3A.16-1.

3A.16 ' DELETED 3A.16-2 3A.17 HTLOAD 3A. 17-1 3A.17.1 General Description 3A.17-1 3A.17.2 Program Verification 3A.17-2 3A.17.3 References 3A.17-3 Amendment 19 3A-ii May 1985

N.'n~ Nile Point Unit 2 FSAP. APPENDIX. 3A TABLE OF CONTENTS (Cont) Section Title ~Pa e 3A. 18 GHOSH-WILSON 3A. '~.8-1 3A.18.1 General Description 3h 1;3-) 3A.18.2 Program Verification 3A.18-1 3A.18.3 References 3A.18-? 3A.19 " P SPECTRA 3A. 19-1 3A.19.1 General Description 3A. 19-1 3A.19.2 Program Verification 3A. 19-1 3A.20 STEHAM 3A. 20" 1 3A.20 F 1 General Description 3A. 20" 1 3A.20.2 Program Verification 3A.20-1 3A.20.3. References 3A. 20.-2 3A. 21 WATHAM 3A. 21-1 3A.21. 1 General Description 3A. 21-1 3A 21.2 Program Verification 3A. 21-i 3A.21.3 References 3A. 21-z JA. d2 PITRUST 3A.22-1 3~.22.1 General Description 3A.22-1 3.i. 22 . 2 Program Verification 3A.22-1 3A. 22. 3 References 3A.22-2 3A.23 PILUG 3A.23-1 3A.23. 1 General Description 3A.23-1 3A 23.2

   ~            Program    Verification            3A.23-1 3A.23.3          References                         3A.23-2 3A.24            WATAIR                             3A.24-1 3A.24.      1    General Description                3A.24-1 3A.24.2          Program    Verification            3A.24-1 3A.24.:9         References                         3A.24-2 3A.25            ANSYS                              3A.25-1 3A.25.1          General Description                3A.25-1 3A.25.2          Program    Verification            3A.25-2 3A. 26           CWI    (Containment Wall Loading)  3A. 26-1 3A. 26. 1        General Description                3A. 26-1 3A.26.2           Pr'ogram  Verification            3A. 26-1 3A.26.3           References                        3n, 26 2

Nine Mile Point Unit 2 FSAR APPENDIX 3A'ABLE OF CONTENTS (Cont) Section Title Pacae 3A.27 LUG STR 3A. 27-1 3A.27.1 General Description 3A. 27-1 3A.27.2 Program Verification 3A. 27-1 3A.27.3 References 3A. 27-2 3A.28 Computer Programs for Structural 3A.28-1 Responses to Hydrodynamic Loading (TRANFUN AND INVTRAN) 3A.28. 1 Introduction 3A.28"1 3A.28.2 TRANFUN 3A.28-1 3A.28.3 INVTRAN 3A.28-1 3A.28.4 References 3A.28-3 3A. 29 NASTRAN 3A.29-1 3A. 30 BIJLAARD: Vessel Penetration 3A.30-1 Analysis 3A. 30. 1 General Description 3A.30-1 3A.30.2 Program Verification 3A.30-1 3A.30.3 References 3A.30-2 3A. 31 SLOSH: Simplified Tank Sloshing 3A ~ 31-1 Analysis 3A.31. 1 General Description 3A. 31-1 3A.31.2 Program Verification 3A. 31-1 3A.31.3 References 3A. 31-2 3A 32

     ~            SNUFFE:    Supplement       to  NUPIPE     3A. 32-1 for Fatigue Evaluation 3A.32.1        General Description                        3A.32-1 3A.32.2        Program Verification                       3A.32-1

23. 3A.33 PITRIFE 3A.33-1 3A.33.1 General Description 3A.33-1 3A.33.2 Program Verification 3A.33-1 3A.33.3 References 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 Title Pacae 3B.l DESIGN BASES 3B-1 3B.2 DESIGN FEATURES 3B-3 3B.3 DESIGN EVALUATION 3B-5 3B.3.1 Elevation 175 ft 0 in. to Elevation 215 ft 0 in. 3B-5 3B.3.2 Elevation 215 ft 0 in. to Elevation 240 ft 0 in. 3B-6. 3B.3.3 Elevation 240 ft 0 in. to Elevation 261 ft 0 in. 3B-7 3B.3.4 Elevation 261 ft 0 in. to Elevation 289 ft 0 in. 3B-8 3B.3.5 Elevation 289 ft 0 in. to Elevation 306 ft 6. in. 3B-9. 3B.3.6 Elevation 306 ft 6 in. to Elevation 328 ft 10 in. 3B-10 3B ~ 3 ' Elevation 328 ft 10 in and Above 3B-10 3B.4 REFERENCES 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 HIGH ENERGY LINE BREAKS ANALYZED IN THE REACTOR BUIIDING 3B-2 HIGH ENERGY LINE BREAKS ANALYZED IN THE MAIN STEAM TUNNEL 3B-3 SUBCOMPARTMENT NODAL DESCRIPTION HIGH ENERGY LINE BREAK "ANALYSIS IN REACTOR BUILDING 3B-4 SUBCOMPARTMENT,NODAL DESCRIPTION MAIN STEAM TUNNEL HIGH ENERGY LINE BREAK 'ANALYSIS 3B-5 SUBCOMPARTMENT VENT PATH DESCRIPTION REACTOR, BUILDING HIGH ENERGY LINE BREAK ANALYSIS (4-NODE MODEL) 3B-6 SUBCOMPARTMENT VENT PATH DESCRIPTION REACTOR BUILDING HIGH ENERGY LINE BREAK ANALYSIS (33-NODE MODEL) 3B-7 VENT PATH DESCRIPTION MAIN STEAM TUNNEI HIGH ENERGY LINE BREAK ANALYSIS - TWO-PHASE BREAK IN MST-3 3B-8 VENT PATH DESCRIPTION MAIN STEAM TUNNEL HIGH ENERGY LINE BREAK ANALYSIS TWO-PHASE BREAK IN MST>>5 3B-9 MASS AND ENERGY RELEASE FOR 4-IN RCIC DER IN VOLUME 175 BREAK NO. 19 3B-10 MASS, AND ENERGY RELEASE FOR 4-IN RCIC DER IN VOLUME 175-2 BREAK NO. 20 3B-11 MASS AND ENERGY RELEASE FOR 8-IN RWCU DER IN VOLUMES 215-1 AND 215-5 BREAK NO. 16 AND 17 3B-12 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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Vo luna Volune Area L/A (1) Turning Edge Number Nurber Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 1 175-'I 175-2 25.88 0.327 0.631 0.631 175-2 175-1 25.88 0.327 1.411 1.411 (a) 2 175-1 175-9 10.00 0.258 0.4932 0.8891 0.3368 0.0260 1.745 175-9 175-1 10.00 0.258 0.4715 0.9729 0.3445 0.0260 1.815 (a) 3 175-2 175-3 10.00 0.366 0.4517 0.8635 0.1568 0.0347 1.507 175-3 175-2 10.00 0.366 0.4646 0.8161 0.1546 0.0347 1 470 (a) 4 175-2 175-3 10.00 0.366 0.4517 0.8635 0 ~ 1568 0.0347 1 F 507 175-3 175-2 10.00 0.366 0 '646 0.8161 0.1546 0.0347 1.470 (b) 5 175-2 215-1 1.047 2.648 O.C773 0.993D 0.200 0.0920 1.762 215-1 175-2 1.047 2.648 0.4982 0.9113 0.200 0.0920 1.702 6 '175-3 175-4 21.00 0.215 0 '24 0.898 1.122 175-4 175-3 21.00 0.215 0.224 1.584 1.808 7 175.4 175-5 242.86 0.015 0.200 0.994 1.194 175-5 175-4 242.86 0.015 0.200 1.847 2.047 8 175-4 175-6 265.09 0 ~ 014 0.200 0.992 1.192 175-6 175-4 265.09 0.014 0.200 1.840 2.040 9 175-4 '175-7 241.26 0.014 0.2DO 0.994 1.194 175-7 175-4 241.26 0.014 0.200 1.848 2.048 10 175-4 175-8 240.31 0.015 0.200 0.99C 1.194 175-8 175-4 240.31 0.015 0.200 1.848 2.048 11 175-4 175-9 140.18 0.020 0.200 0.814 1.014 175-9 175-4 140.18 0.020 0.200 1.698 1.898 12 175-4 215-8 62.42 0.039 0.4964 0.9849 0.200 1.1548 0 '066 2.843 215-8 175-4 62.42 0.039 0.4962 0.9856 0.200 1 ~ 1549 0.0066 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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Volune Volune Area L/A (1) Turning Edge Number Nunber Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 25 215-6 215-8 21.00 0.321 0.3698 0.9655 3.424 0.9010 0.0098 5.670 215-8 215-6 N/A N/A (c) (c) 26 215-8 215-9 H/A N/A (c) (c) 215-9 215-8 14.33 0.313 3.424 2.087 5.511 27 215-8 215-10 N/A N/A (c) (c) 215-10 215-8 14.33 0.313 3.424 2.185 5.609 28 215-8 240-5 52.03 0.045 0.4969 0.9878 0.200 1.1419 0.0072 2.834 240-5 215-8 52.03 0.045 0.4970 0.9876 0.200 1.1418 0.0072 2.834 29 215-9 215-10 15.75 0.414 0.4379 0.7669 0.0587 0.0366 1.300 215-10 215-9 15.75 0.414 0.4379 0.7669 0.0587 0.0366 1.300 30 240.1 240-2 101.05 0.064 0.835 0.835 240-2 240-1 101.05 0.064 0.557 0.557 31 240-1 261-1 28.38 0.336 0.200 0.652 0.852 261-1 240-1 28.38 0.336 0.200 0.379 0.579 32 240-3 240-4 37.83 0.110 0.200 0.504 0.704 240-4 240-3 37.83 0.110 0.200 1.093 1.293 33 240-3 240-5 16.38 0.234 3.424 1.688 5.112 240-5 240-3 N/A N/A (c) (c) 34 240-3 261-3 39.68 0.143 0.200 0.867 1.067 240-3 261-3 39.68 0.143 0.200 1.617 1.817 35 240-5 240-7 2.299 0.091 0.4993 0.9847 1.2672 0.0033 2.755 240-7 240-5 2.299 0.091 0.4962 0.9971 1.2711 0.0033 2.768 36 240-5 240-8 2.299 0.093 0.4993 0.9834 1.2663 0.0033 2.752 240-8 240-5 2.299 0.093 0.4958 0.9971 1.2707 0.0033 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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Volune Volune Area L/A (1) Turning Edge Number Number Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total

                                              '                                                                 2.839 37   240-5  261-4   67.45    0.029            '960      0.9868          0.188   1.1615     0.0064 261-4  240-5   67.45    0.029          0.4967      0.9840          0.188   1.1606     0.0064           2.836 38   240.6  306-4   21.15     1.674                                               0.768              1.146   1.914 306-4  240.6   21.15     1.674                                               0.181              0.663   0.844 39   261-1  261-2   33.26    0.169                                      0.200                        0.938   1.138 261-2  261-1   33.26     0.169                                     0.200                        1.246   1.446 40   261-1  261-4    15.93    0.213                                     3.424                        1.765   5 ~ 189 261-4  261-1     H/A     N/A                                     (c)                                      (c) 41   261-2  289-'I   26.30    0.293                                     0.200                        0.775   0.975 289-1 261-2    26.30    0.293                                     0.200                        0.897   1.097 42    261-3 261-5    49.95    0.227                                     0.200                        0.220   0.420 261-5 261-3    49.95    0.227                                     0.200                        0.198   0.398 43    261-4 289-3  503.31     0.010          0.4802     0.9199                  1 '607     0.0023            2.463 289-3 261-4  503.31     0.010          0.4796     0.9224                  1.0614     0.0023            2.466 261-5 289-2    65.75    0.174                                     0.200                        0 '82   0.482 289-2 261-5    65.75    0.174                                     0.200                        0.235   0.435 45    289.1 306-1    40.82    0.174                                     0.200                         1.168  1.368 306-1 289-1    40.82    0.174                                     0.200                        0.520   0.720 46    289-2 306-4    36.86    0.169          0.3166     0.8746          0.400   0.7511     0.0108            2.353 306-4  289-2   36.86    0.169          0.4676     0.4010          0.400   0.6182     0.0108             1.898 47   289-3 306-5  2079.0     0.010          0.4156     0.6116                  0.9317     0.0015             1.960 306-5  289-3 2079.0     0.010          0.3910     0.6907                  0.9605     0 ~ 0015          2.044 289-3 306-5  2590.0     0.010          0.3948     0.5307                  0.8459     0.0013             1.773 306-5  289-3  2590.0    0.010          0.3643      0.6235                 0.8858     0.0013             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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Volcano Volune Area L/A (1) Turning Edge Number Humber Nunber (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 49 306.1 306-2 245.99 0.014 2.311 2.311 306.2 306-1 245.99 0.014 2.390 2.390 50 306-1 328-2 8.956 0.401 0.4969 0.9731 0 ~ 1645 0.0272 1.662 328-2 306-1 8.956 0.401 0.4932 0.9875 0.1651 0.0272 'I.673 51 306-2 306-3 136.80 0.035 1.645 1.645 306.3 " 306-2 136.80 0.035 1.959 1.959 52 306.3 306-4 92.48 0.445 0.324 0.324 306-4 3D6.3 92.48 0.445 0.390 0.390 53 306-5 328-1 508.58 0.010 0.4733 0.7057 1.0504 0.0023 2 232 328-1 306-5 508.58 0.010 0.4200 0.8962 1.1151 0.0023 2.434 5C 328-1 353-1 502.88 0.010 0.4209 0.9554 1.1522 0.0023 2.531 353-1 328-1 502.M 0.010 O.C887 0.7087 1.0693 0.0023 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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Volune Volune Area L/A (1) Turning Edge Number Number Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 175-1 175.2 25.88 0.327 0.631 0.631 175.2 175-1 25.88 0.327 1.411 1.411 (a) 2 175-1 175-9 10.00 0.258 0.4932 0.8891 0.3368 0.0260 1.745 175-9 '175-1 10.00 0.258 0.4715 0.9729 0.3445 0.0260 1.815 (a) 3 175-2 175-3 10.00 0.366 0.4517 0.8635 0.1568 0.0347 1.507 175-3 175-2 10.00 0.366 0.4646 0.8161 0.1546 0.0347 1.470 175-2 215-1 1.047 2.648 0.4773 0.9930 0.200 0.0920 1.762 215-1 175-2 1.047 2.648 0.4982 0.9113 0.200 0.0920 1.702 175-3 175-4 21.00 0.215 0.224 0.898 1.122 175-4 175-3 21.00 0.215 0.224 1.584 1.808

            '175-4  175-5   242.86    0.015                                      0.200                       0.994  1.194 175-5    175-4   242.86    0.015                                      0.200                       1.847  2.047 175-4    175-6   265.09    0.014                                      0.200                       0.992  1.192 175-6    175-4   265.09    0 ~ 014                                    0.200                       1.840  2.040 175-4    175.7   241.26    0.014                                      0.200                       0.994  1.194 175-7    175.4   241.26   0.014                                       0.200                       1.848  2.048 175-4    175-8   240.31   0.015                                      0 '00                       0.994   1.194 175-8    175-4   240.31   0.015                                      0.200                        1.848  2.048 10    175-4    175-9   140.18   0.020                                      0.200                       0.814   1.014 175.,9   175-4   140.18   0.020                                      0.200                        1.698  1.898 175-4    215.8    62.42   0.039          0.4964       0.9849         0.200    1.1548     0.0066          2.843 215-8    175-4    62.42   0.039          0.4962       0.9856         0.200    1.1549     0.0066          2.843 12    175-10   215-3    81.30   0.121                                      0.200                       1.337   1.537 215-3    175-10   81.30   0.121                                      0.200                       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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Voiune Voiune Area L/A (1) Turning Edge Nurher Nunber Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 25 215-8 215-9 N/A N/A (b) (b) 215-9 215-8 14.33 0.313 3.424 2.087 5.511 26 215-8 215-10 H/A N/A (b) (b) 215-10 215-8 14.33 0.313 3.424 2.185 5.609 27 215;8 240-5 52.03 0.045 0.4969 0.9878 0.200 1.1419 0.0072 2.834 215-8 240-5 52.03 0.045 0.4970 0.9876 0.200 1.1418 0.0072 2.834 28 215-9 215-10 15.75 0.414 0.4379 0.7669 0.0587 0.0366 1.300 215-10 215-9 15.75 0.414 0.4379 0.7669 0.0587 0.0366 1.300 29 240-1 240-2 101.05 0.064 0.835 0.835 240-2 240-1 101.05 0.064 0.557 0.557 30 240-1 261-1 28.38 0.336 0.200 0.652 0.852 261-1 240-1 28.38 0.336 0.200 0.379 0.579 31 240-3 240-4 37.83 0.110 0.200 0.504 0.704 240-4 240-3 37.83 0.110 0.200 1 '93 1 '93 32 240-3 240-5 16.38 0.234 3.424 1.688 5.112 240-5 240.3 H/A H/A (b) (b) 33 240-3 261-3 39.68 0.143 0 '00 0.867 1.067 240-3 261-3 39.68 0.143 0.200 1.617 1.817 34 240.5 240-7 2.299 0.091 0.4993 0.9847 1.2672 0.0033 2.755 240-7 240-5 2.299 0.091 0.4962 0.9971 1.2711 0.0033 2.768 35 240.5 240.8 2.299 0.093 0.4993 0.9834 1.2663 0.0033 2.752 240-8 240-5 2.299 0.093 0.4958 0.9971 1.2707 0.0033 2.767 36 240-5 261-4 67.45 0.029 0.4960 0.9868 0.188 1.1615 0.0064 2.839 261-4 240-5 67.45 0.029 0.4967 0.9840 0.188 1.1606 0.0064 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 Inertia Vent Fram To Vent Factor Sharp Path Volune Volune Area L/A (1) Turning Edge Number Number Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 37 240.6 306-4 21.15 1.674 0.768 1.146 1.914 306.4 240-6 21.15 1.674 0.181 0.663 0.844 38 261.1 261-2 33.26 0.169 0.200 0.938 1.138 261-2 261-1 33.26 0.169 0.200 1.246 1.446 39 261-1 261-4 15.93 0.213 3.424 1.765 5.189 261-4 261-1 N/A N/A (b) (b) 40 261-2 289-1 26.30 0.293 0.200 0.775 0.975 289.1 261-2 . 26.30 0.293 0.200 0.897 1.097 41 261-3 261-5 49.95 0.227 0.200 0.220 0.420 261-5 261-3 49.95 0.227 0.200 0.198 0.398 261-4 289-3 503.31 0.010 0.4802 0.9199 1.0607 0.0023 2.463 289.3 261-4 503.31 0.010 0.4796 0.9224 1.0614 0.0023 2.466 43 261-4 289-3 197.42 0.010 0.4922 0.9682 1.2078 0.0040 2.672 289-3 261-4 197.42 0.010 0.4920 0.9692 1.2080 0.0040 2.673 44 261-5 289-2 65.75 0.174 0.200 0.282 0.482 289-2 261-5 65.75 0.174 0.200 0.235 0.435 45 289-1 306-1 40.82 0.174 0.200 1.168 1.368 306-1 289-1 40.82 0.174 0.200 0.520 0.720 46 289.2 306-4 36.86 0.169 0.3166 0.8746 0.400 0.7511 0.0108 2.353 306.4 289-2 36.86 0.169 0.4676 0.4010 0.400 0.6182 0.0108 1.898 47 289.3 306-5 2079.0 0.010 0.4156 0.6116 0.9317 0.0015 1.960 306.5 289-3 2079.0 0.010 0.3910 0.6907 0.9605 0.0015 2.044 48 289-3 306-5 2590.0 0.010 0.3948 0.5307 0.8459 0.0013 1.773 306-5 289-3 2590.0 0.010 0.3643 0.6235 0.8858 0.0013 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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Volune Volune Area L/A (1) Turn>ng Edge Number Number Number (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 49 289-3 306.5 202 '6 0.010 0.4918 0.9581 1.2022 0.0039 2.656 306-5 289.3 202.16 0.010 0.4894 0.9674 1.2050 0.0039 2.666 50 306-1 306-2 245.99 0.014 2.311 2.311 306.2 306.1 245.99 0.014 2.390 2.390 51 306-1 328-2 7.192 0.493 0.4969 0.9731 0.200 0.1645 0.0272 1.862 328-2 306-1 7.192 0.493 0.4932 0.9S75 0.200 0.1651 0.0272 1.873 52 306-2 306-3 136.80 0.035 1.645 1.645 306.3 306-2 136.80 0.035 1.959 1.959 53 306-3 306-4 92.48 0.445 0.324 0.324 306-4 306-3 92.48 0.445 0.390 0.390 306-5 328-1 508.58 0.010 0.4733 0.7057 1.0504 0.0023 2 232 328-1 306-5 508.58 0.010 0.4200 0.8962 1.1151 0.0023 2.434 55 328-'I 353-1 502.88 0.010 0.4209 0.9554 1.1522 0.0023 2.531 353-1 328-1 502.88 0.010 0.4887 0.7087 1.0693 0.0023 2.269 56 SC328190 306-1 0.170 20.65 0.5000 1.0000 0.2618 1.762 306-1 SC328190 0.170 20.65 0.5000 1.0000 0.2618 1.762 57 SC328190 306-1 0.049 71.51 0.5000 1.0000 0.5862 2.086 306-1 SC328190 0.049 71.51 0.5000 1.0000 0.5862 2.086 5e SC32e190 306-1 0.863 4.098 0.5000 1.0000 0.1458 1.646 306-1 SC328190 0.863 4.098 0.5000 1.0000 0.1458 1.646 59 SC328190 328-2 0.718 4.915 0.5000 1.0000 0.1458 1.646 328-2 SC328190 0.718 4.915 0.5000 F 0000 0 ~ 1458 1.646 60 SC328190 328-2 0.718 4.915 0.5000 1 F 0000 0 ~ 1458 1.646 328-2 SC328190 0.718 4.915 0.5000 1.0000 0.1458 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) Head Loss Coefficients Inertia Vent From To Vent Factor Sharp Path Voiune Volune Area L/A (1) Turning Edge Number Nunber Hwher (ft2) (1/ft) Contraction Expansion Obstruction Loss Friction Loss Total 61 SC328190 328-2 0.181 19.390 0.5000 1.0000 0.3537 1.854 328-2 SC328190 0.181 19.390 0.5000 1.0000 0.3537 1.854 62 SC328190 328-2 0.181 19.390 0.5000 1 F 0000 0.3537 1.854 328-2 SC328190 0.181 19.390 0.5000 1.0000 0.3537 1.854 63 SC328190 328-2 0.181 19.390 0.5000 1.0000 0.3537 1.854 328-2 SC328190 0.181 19.390 0.5000 1.0000 0.3537 1.854 64 SC328190 328-2 0.181 19.390 0.5000 1.0000 0.3537 1.854 328-2 SC328190 0.181 19.390 0.5000 1.0000 0.3537 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 261-3 240-3 240-5 TIP GENERAL AREA GU Bl GLE TO 261-1 240-7 240-8 240-1 240-2 240"4 PENETRATION PENETRATION PIPE PENETRATION PIPE AREA AREA CHASE AREA CHASE FROM 215-1 FROM 215-2 NOTES: FIGURE 3B-2 NODALI2ATION DIAGRAM - REACTOR BUILDING HIGH-ENERGY LINE BREAK s VENT CURTAIN JUNCTION ANALYSIS (4S N ODE MODEL) SHEET 3 OF 6

         ~   COON WITN LOUVER NIAGARA MOHAWK POWER CORPORATION s  DIRECTION Of VENT FLOW NINE MILE POINT        -  UNIT 2 VOLUIIE 240   4 IS SHOWN ON  SHEET 4 OF FIOURE SS I                 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 ft 10 in. 8 ll/16 in and drops It then loops its way up to el 342 vertically into the RPV head. The such MSS as piping, if allowed to whip, could impact, targets drywell head, vessel dome, insulation support 28 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 28 I 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) The location of pipe breaks are shown on Figures 3.6A-16 and as 3.6A-17 f main steam safety

               'he 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.

sa/ 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 Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A. through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7' Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7~3 Engineered Safety Feature Systems 15 7' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7' Control Systems Not Required for Safety 16 Appendixes 7Ai 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System , 16 8.3 Onsite Power System=- '16, 17 Appendix 8A 17 I

                                                                           ~

CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems .18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20,21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C 23 USAR Revision 0 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 Summary Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER RADIOACTIVE WASTE MANAGEMENT

11. 1 Source Terms 24 11.2 Liquid Waste Management Systems 24 11.3 Gaseous Waste Management Systems 25

~ 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix 11A 25 CHAPTER 12 RADIATION PROTECTION 25,

12. 1 Ensuring That, Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25

 -12.2           Radiation Sources                       25

12. 3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26

  . 12.5         Health Physics Program                  26 CHAPTER 13   CONDUCT OF OPERATIONS                   26

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26 13 ' Site Emergency Plan 26 13.4 Operation Review and Audit 26 13.5 Plant Procedures 26

 . 13.6          Industrial Security                    26 Appendixes 13A, 13B                                  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 Title 5.l-la RATED OPERATING CONDITIONS OF THE BOILING WATER REACTOR 5.l-lb COOLANT VOLUMES OF THE BOILING WATER REACTOR 5.1-2a, b, c NUCLEAR BOILER SYSTEM 5.2-1 SAFETY RELIEF VALVE CAPACITY SIZING TRANSIENT "MSIV CLOSURE WITH HIGH FLUX TRIP" 5.2-2 SAFETY RELIEF VALVE SCHEMATIC ELEVATION 5.2-3 SAFETY RELIEF VALVE AND STEAM LINE SCHEMATIC 5.2-4 NUCLEAR BOILER SYSTEM PAID 5.2-5 SCHEMATIC OF SAFETY RELIEF VALVE WITH AUXILIARY ACTUATING DEVICE 5.2-5a ABNORMAL AMBIENT CONDITIONS FOR ACTUATOR QUALIFICATION TEST 5.2-6 TYPICAL BWR FLOW DIAGRAM 5.2-7 CONDUCTIVITY'Hg CHLORIDE CONCENTRATION OF AQUEOUS SOLUTIONS AT 77 F (25 C) 5.2-8 CALCULATED LEAK RATE VS CRACK LENGTH AS A FUNCTION OF APPLIED HOOP STRESS 5.2-9 AXIAL THROUGHWALL CRACK LENGTH DATA CORRELATION 5.3-1 BRACKET FOR HOLDING SURVEILLANCE CAPSULE 5.3-2 MINIMUM TEMPERATURES REQUIRED VERSUS REACTOR PRESSURE 5.3-3 PREDICTED ADJUSTMENT OF REFERENCE TEMPERATURE "A " AS A FUNCTION OF FLUENCE AND COPPER CONTENT 5.3-4 REACTOR VESSEL USAR Revision 0 5-ix April 1989

Nine Mile Point 'Unit 2 FSAR CHAPTER 5 LIST OF FIGURES (Cont) Figure Number Title 5.3-5 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 RECIRCULATION PUMP HEAD, NPSH, FLOW AND EFFICIENCY CURVES 5.4-4 OPERATING PRINCIPLE OF JET PUMP 5.4-5 CORE FLOODING CAPABILITY OF RECIRCULATION SYSTEM 5.4-6 MAIN STEAMLINE FLOW RESTRICTOR 5.4-7 MAIN STEAM ISOLATION VALVE CUTAWAY VIEW 5.4-8 DELETED 5.4-9a through RCIC SYSTEM 5.4-91 5.4-10 REACTOR CORE ISOLATION COOLANT SYSTEM PROCESS DIAGRAM 5.4-10a RCIC TURBINE CHARACTERISTIC CURVES STEAM FLOW VS. POWER 5.4-10b RCIC TURBINE CHARACTERISTIC CURVES STEAM FLOW VS. PRESSURE 5.4-11 VESSEL COOLANT TEMPERATURE VERSUS TIME (TWO HEAT EXCHANGERS AVAILABLE) 5.4-12 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 Title 5.4-14 RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM AND DATA 5.4-15 RHR PUMP CHARACTERISTIC CURVES 5.4-16a through REACTOR WATER CLEANUP AND FILTER 5.4-16f DEMINERALIZER SYSTEM PAID 5.4-17 REACTOR WATER CLEANUP SYSTEM 5.4-18 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 RCIC system.

5. 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 into the area. The monitors located in the main steam 23 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. Excess -leakage external to the containment (e.g., process line break outside containment.) is detected by. low reactor 23 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 23 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/ Applicable Revision 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 electrode E80XX, from 2 to 4 hr. 'n form 4 to 5 hr, and for 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 ~Accurac Sensitivit Drywell floor drain tank level 1 gpm 1 gpm/hr Drywell equipment drain tank level4 1 gpm 1 gpm/hr Airborne particulates 6. 6-12 uCi/cc ' Gaseous radioactivity '.9-07 uCi/cc'~'OTE:

6. 6-12 = 6. 6x10

The 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 lateral expansion is required at 70~F. VThe 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. 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.

3. 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 water; nuts and washers are dry stored during refueling. fill 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 thetheHPCSRCIC system is postulated to fail at these conditions capacity is insufficient, the automatic and 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 that, operates to maintain the pump discharge line in a fill pump filled condition. Keeping the discharge line filled ofreduces full the lag time between pump startup and attainment flow to the RPV. Additionally, its operation eliminates the possibility of RCIC pumps discharging into a dry pipe and minimizes water hammer effects. The as Category I and Safety Class 2. fill pump is classified The pump motor is USAR Revision 0 5.4-17a April 1989

Nine Mile Point Unit 2 FSAR TABLE OF CONTENTS (Cont) Section Title Volume 5.3 Reactor Vessel 13 5.4 Component and Subsystem Design 13 Appendixes 5A, 5B 13 CHAPTER 6 ENGINEERED SAFETY FEATURES 13 6.1 Engineered Safety Feature Materials 13 6.2 Containment Systems 14 6.3 Emergency Core Cooling Systems 15 6.4 Habitability Systems 15 6.5 Fission Product Removal and Control Systems 15 6.6 Inservice Inspection of Safety Class 2 and Class 3 Components 15 Appendixes 6A through 6C 15 CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS 15 7.1 Introduction 15 7.2 Reactor Protection (Trip) System (RPS) Instrumentation and Controls 15 7 ' Engineered Safety Feature Systems 15 7 ' Systems Required for Safe Shutdown 16 7.5 Safety-Related Display Instrumentation 16 7.6 All Other Instrumentation Systems Required for Safety 16 7~7 Control Systems Not Required for Safety 16 Appendixes 7A, 7B 16 CHAPTER 8 ELECTRIC POWER 16 8.1 Introduction 16 8.2 Offsite Power System 16 8.3 Onsite Power System 16,17 Appendix 8A 17 I CHAPTER 9 AUXILIARY SYSTEMS 17 9.1 Fuel Storage and Handling 17 9.2 Water Systems 18 9.3 Process Auxiliaries 19 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems 20~21 9.5 Other Auxiliary Systems 21,22 Appendixes 9A, 9C 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 Summary . Description 23 10.2 Turbine Generator 23 10.3 Main Steam Supply System 24 10.4 Other Features of Steam and Power Conversion System CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT ll. 11.2 1 Source Terms Liquid Waste Management Systems 24 24 11.3 Gaseous Waste Management Systems 25 11.4 Solid Waste Management System 25 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 25 Appendix llA 25 CHAPTER 12 RADIATION PROTECTION 25

12. 1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 25 12.2 Radiation Sources 25 12.3 Radiation Protection Design Features 25

12. 4 Dose Assessment 26 12 5

  ~          Health Physics Program                 26 CHAPTER 13    CONDUCT OF OPERATIONS                  26

13. 1 Organizational Structure of Applicant 26

13. 2 Training 26

13. 3 Site Emergency Plan 26.

13. 4 Operation Review and Audit 26

13. 5 Plant Procedures 26

13. 6 Industrial Security 26 Appendixes 13A, 13B 26 CHAPTER 14 INITIAL TEST PROGRAM 26

14. 1 Specific Information,To Be Included in Preliminary Safety Analysis Report (PSAR) 26}}