ML17054D432: Difference between revisions

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Polar-grid sector populations between 10 and 20 km (6.2 and 12.4 mi)are based on 1980 U.S.Census data and New York State population projections.
Polar-grid sector populations between 10 and 20 km (6.2 and 12.4 mi)are based on 1980 U.S.Census data and New York State population projections.
Sector populations were determined by assuming that the population of a minor civil division (i.e., a town)is evenly distributed over its land area.The proportion of each civil division's area in each grid sector was then determined and applied to each civil division's total population, yielding the population in each grid sector.Population projections, based on 1978 projections supplied by the New York State Department of Commerce, Economic Development Board, were applied to each civil division, assuming that each portion would maintain its relative share of any population change.Population density was calculated by dividing the population in each sector by its land area'.Population distribution within a 20-km (12.4-mi)radius of the plant for 1980 through 2030 is shown on Figures 2.5-3 through 2.5-9 and listed in Tables 2.5-3 through 2.5-9.Transient population within 20 km (12.4 mi)of Unit 2 is limited due to the rural, undeveloped character of the area.There are, however, a number of school, industrial, and recreational facilities in the area that create small, daily 2.5-2 Nine Mile Point Unit 2 ER-OLS TABLE 2.5-1 1980 POPULATION AND POPULATION DENSITIES FOR TOWNS AND CITIES WITHIN 20 KM (12.4 MI)OF UNIT 2 City of Oswego Oswego (town)Granby Richland Scriba Volney Mexico Hannibal Palermo New Haven Minetto 1980 Po ulation 19,793 7,865 6, 341 5, 594 5, 455 5, 358 4, 790 4, 027 3,253 2, 421 1, 905 Population Density eo le s km 1,029.0 116.9 55.2 40.9 52.9 46.0 41.8 38.5 31.6 31.7 125.5 SOURCE: Reference 1 1 of 1 V 0 0 Nine Mile Point Unit 2 ER-OLS pact the overall visual quality of the area.The view of the cooling tower will be the only noticeable changers The cooling tower is 165 m (541 ft)above ground level and is visible at some locations, as shown for selected locations on Figures 3.1-4 through 3.1-7.Depending on meteorological conditions, the natural-draft cooling tower will emit evaporative plumes that may be visible from locations within the 16-km (10-mi)area.Expected visible plume occurrences are described in Section 5.3.3.1, and predicted frequency of plume occurrences are shown on Figures 5.3-1 through 5.3-25.The anticipated plumes for 5-percent, 1-percent, and O.l-percent occurrences at selected locations are shown on Figures 3.1-4 through 3.1-7, and an analysis of their visual impacts is presented in Section 5.8.1.1.The plume occurrence denotes the maximum extent of plume that is, visible for a certain percent of time, as shown on the figures.Starting in April and continuing through September, when recreational activities on the lake and along the shoreline are frequent, the cooling tower will be visible from the shoreside by fishermen, recreational users, and others at facilities such as the Ontario Bible Conference Association Camp (a lakefront facility bordering the site on the west).Cooling tower plumes are not expected to have a significant visual impact.Most visually sensitive sites, listed in Table 3'-1, are located in vegetated or developed areas, specifically within the city of Oswego.Therefore, distant views that might include the plume are not possible from these sites.However, at locations along the shoreline at elevated grades, such as Fort Ontario (Figure 3.1-7), plumes may be visible.The visual impact of Unit 2 is minimal due to the limited number of locations from which the plant is visible, the lack of visibility from many visually sensitive or intensive land use areas, and the small portion of plant structures that can be seen above the surrounding vegetation.
Sector populations were determined by assuming that the population of a minor civil division (i.e., a town)is evenly distributed over its land area.The proportion of each civil division's area in each grid sector was then determined and applied to each civil division's total population, yielding the population in each grid sector.Population projections, based on 1978 projections supplied by the New York State Department of Commerce, Economic Development Board, were applied to each civil division, assuming that each portion would maintain its relative share of any population change.Population density was calculated by dividing the population in each sector by its land area'.Population distribution within a 20-km (12.4-mi)radius of the plant for 1980 through 2030 is shown on Figures 2.5-3 through 2.5-9 and listed in Tables 2.5-3 through 2.5-9.Transient population within 20 km (12.4 mi)of Unit 2 is limited due to the rural, undeveloped character of the area.There are, however, a number of school, industrial, and recreational facilities in the area that create small, daily 2.5-2 Nine Mile Point Unit 2 ER-OLS TABLE 2.5-1 1980 POPULATION AND POPULATION DENSITIES FOR TOWNS AND CITIES WITHIN 20 KM (12.4 MI)OF UNIT 2 City of Oswego Oswego (town)Granby Richland Scriba Volney Mexico Hannibal Palermo New Haven Minetto 1980 Po ulation 19,793 7,865 6, 341 5, 594 5, 455 5, 358 4, 790 4, 027 3,253 2, 421 1, 905 Population Density eo le s km 1,029.0 116.9 55.2 40.9 52.9 46.0 41.8 38.5 31.6 31.7 125.5 SOURCE: Reference 1 1 of 1 V 0 0 Nine Mile Point Unit 2 ER-OLS pact the overall visual quality of the area.The view of the cooling tower will be the only noticeable changers The cooling tower is 165 m (541 ft)above ground level and is visible at some locations, as shown for selected locations on Figures 3.1-4 through 3.1-7.Depending on meteorological conditions, the natural-draft cooling tower will emit evaporative plumes that may be visible from locations within the 16-km (10-mi)area.Expected visible plume occurrences are described in Section 5.3.3.1, and predicted frequency of plume occurrences are shown on Figures 5.3-1 through 5.3-25.The anticipated plumes for 5-percent, 1-percent, and O.l-percent occurrences at selected locations are shown on Figures 3.1-4 through 3.1-7, and an analysis of their visual impacts is presented in Section 5.8.1.1.The plume occurrence denotes the maximum extent of plume that is, visible for a certain percent of time, as shown on the figures.Starting in April and continuing through September, when recreational activities on the lake and along the shoreline are frequent, the cooling tower will be visible from the shoreside by fishermen, recreational users, and others at facilities such as the Ontario Bible Conference Association Camp (a lakefront facility bordering the site on the west).Cooling tower plumes are not expected to have a significant visual impact.Most visually sensitive sites, listed in Table 3'-1, are located in vegetated or developed areas, specifically within the city of Oswego.Therefore, distant views that might include the plume are not possible from these sites.However, at locations along the shoreline at elevated grades, such as Fort Ontario (Figure 3.1-7), plumes may be visible.The visual impact of Unit 2 is minimal due to the limited number of locations from which the plant is visible, the lack of visibility from many visually sensitive or intensive land use areas, and the small portion of plant structures that can be seen above the surrounding vegetation.
 
3.1.3 Architectural Rendering'of the Plant Figure 3'-8 shows an architectural rendering of the Unit 2 facility, including all major station features and land-scaping whether actually completed or planned.3.1-3  
====3.1.3 Architectural====
Rendering'of the Plant Figure 3'-8 shows an architectural rendering of the Unit 2 facility, including all major station features and land-scaping whether actually completed or planned.3.1-3  


Nine Mile Point Unit 2 ER-OLS All components cooled by the service water system are designed based on a maximum service water system inlet temperature of 25 C (77 F).Table 3.4-1 provides the maximum flow rates and heat gains for each of the following plant conditions:
Nine Mile Point Unit 2 ER-OLS All components cooled by the service water system are designed based on a maximum service water system inlet temperature of 25 C (77 F).Table 3.4-1 provides the maximum flow rates and heat gains for each of the following plant conditions:
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For a given ambient wet-bulb temperature, an increase in relative humidity of ambient air results in a decrease in total moisture removed by cooling tower exit air and a decrease in the evaporative cooling.Conversely, a decrease in ambient relative humidity results in an increase in cooling tower exit air moisture content and an increase in the evaporative cooling.At the design wet-bulb temperature of 23 C (74 F)and a relative humidity of 50 percent, the increase in moisture content of air in the tower is 0.018 kg (0.039 lb)of water per 0.454 kg (1 lb)of dry air.With ambient relative humidities of 25 and 100 percent, the 3.6-4 Nine Mile Point Unit 2, ER-OLS increases in moisture content are 0'24 and 0.012-kg (0.053 and 0.026 lb)of water per 0.454 kg (1 lb)of dry air, respectively.
For a given ambient wet-bulb temperature, an increase in relative humidity of ambient air results in a decrease in total moisture removed by cooling tower exit air and a decrease in the evaporative cooling.Conversely, a decrease in ambient relative humidity results in an increase in cooling tower exit air moisture content and an increase in the evaporative cooling.At the design wet-bulb temperature of 23 C (74 F)and a relative humidity of 50 percent, the increase in moisture content of air in the tower is 0.018 kg (0.039 lb)of water per 0.454 kg (1 lb)of dry air.With ambient relative humidities of 25 and 100 percent, the 3.6-4 Nine Mile Point Unit 2, ER-OLS increases in moisture content are 0'24 and 0.012-kg (0.053 and 0.026 lb)of water per 0.454 kg (1 lb)of dry air, respectively.
The effects of these additional amounts, of moisture added to the atmosphere on ground-level ambient relative humidity are discussed in Section 5.3.3.1.1.5.
The effects of these additional amounts, of moisture added to the atmosphere on ground-level ambient relative humidity are discussed in Section 5.3.3.1.1.5.
 
3.6.2 Sanitary Waste Treatment The normal sanitary waste flow from Unit 2, based on a normal operating force of 300 people.,and an estimated 124 1/day/person (33 gpd/person), is 37,472 l/day (9,900 gpd)..The maximum flow, based on an estimated maintenance outage work force of 1,500 people, is 187,358 1/day (49,500 gpd).Sanitary wastes from Unit 2 will be treated along with sanitary wastes generated at Unit 1.The combined sanitary waste flows will be treated and monitored to comply with the following State Pollutant Discharge Elimination System (SPDES)permit effluent limitations:
====3.6.2 Sanitary====
Waste Treatment The normal sanitary waste flow from Unit 2, based on a normal operating force of 300 people.,and an estimated 124 1/day/person (33 gpd/person), is 37,472 l/day (9,900 gpd)..The maximum flow, based on an estimated maintenance outage work force of 1,500 people, is 187,358 1/day (49,500 gpd).Sanitary wastes from Unit 2 will be treated along with sanitary wastes generated at Unit 1.The combined sanitary waste flows will be treated and monitored to comply with the following State Pollutant Discharge Elimination System (SPDES)permit effluent limitations:
Parameter Limits Settleable solids Total suspended solids 5-day biochemical oxygen demand (BOD>)Chlorine residual pH 0.1 mg/1 maximum daily 25 mg/1 average daily'i'5 mg/1 maximum daily'5 mg/1 average daily'~'5.
Parameter Limits Settleable solids Total suspended solids 5-day biochemical oxygen demand (BOD>)Chlorine residual pH 0.1 mg/1 maximum daily 25 mg/1 average daily'i'5 mg/1 maximum daily'5 mg/1 average daily'~'5.
mg/1 maximum daily'~''ppm maximum daily 6.0-9.0 Fecal coliforms 200 MPN/100 ml-30-day geomet-ric mean 400 MPN/100 ml-7-day geomet-ric mean'''Daily average calculated by dividing monthly discharge by number of days in month.'Daily maximum is the maximum discharged in 1 day.3.6-5  
mg/1 maximum daily'~''ppm maximum daily 6.0-9.0 Fecal coliforms 200 MPN/100 ml-30-day geomet-ric mean 400 MPN/100 ml-7-day geomet-ric mean'''Daily average calculated by dividing monthly discharge by number of days in month.'Daily maximum is the maximum discharged in 1 day.3.6-5  
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Closest accessible shoreline-closest occupied beach.2 of 2  
Closest accessible shoreline-closest occupied beach.2 of 2  


Nine Mile Point Unit 2 ER-OLS 6.3 HYDROLOGICAL
Nine Mile Point Unit 2 ER-OLS 6.3 HYDROLOGICAL 6.3.1 Preapplication and/or Preoperational Monitoring Hydrologic measurements to determine the magnitude and direction of currents in the Nine Mile Point vicinity were made off the Nine Mile Point promontory in 1969, 1970, 1976, and 1977.The 1976 and 1977 studies were conducted after both Unit 1 and the James A.FitzPatrick (JAF)plant were operational.
 
====6.3.1 Preapplication====
and/or Preoperational Monitoring Hydrologic measurements to determine the magnitude and direction of currents in the Nine Mile Point vicinity were made off the Nine Mile Point promontory in 1969, 1970, 1976, and 1977.The 1976 and 1977 studies were conducted after both Unit 1 and the James A.FitzPatrick (JAF)plant were operational.
The scope of each study is summarized below;results are provided in Section 2.3.1.Currents were measured continuously from May through October 1969 and from July through October 1970 at two fixed towers placed offshore from the Nine Mile Point site, one in 7-m (24 ft)of water and one in 14 m (46 ft)of water.Hourly current speed and direction were recorded simultaneously from three depths at, each location, utilizing reduced-sized Savonius rotor meters.In addition, drifting drogues were released and tracked during the 1969 study.These studies have been reported by Gunwaldsen et al'''nd the Power Authority of the State of New York'uring 1976 and 1977, additional postoperational hydrothermal surveys were conducted for the JAF plant'~'.The focus of this study was on thermal plume mapping.Current speed and direction, lake temperature, and lake level were also monitored.
The scope of each study is summarized below;results are provided in Section 2.3.1.Currents were measured continuously from May through October 1969 and from July through October 1970 at two fixed towers placed offshore from the Nine Mile Point site, one in 7-m (24 ft)of water and one in 14 m (46 ft)of water.Hourly current speed and direction were recorded simultaneously from three depths at, each location, utilizing reduced-sized Savonius rotor meters.In addition, drifting drogues were released and tracked during the 1969 study.These studies have been reported by Gunwaldsen et al'''nd the Power Authority of the State of New York'uring 1976 and 1977, additional postoperational hydrothermal surveys were conducted for the JAF plant'~'.The focus of this study was on thermal plume mapping.Current speed and direction, lake temperature, and lake level were also monitored.
During the two June 1976 surveys, the current was monitored 3 m (10 ft)below the water surface at a fixed tower positioned approximately 610 m (2,000 ft)east and along the same depth contour (9 m[30 ft])of the JAF plant discharge.
During the two June 1976 surveys, the current was monitored 3 m (10 ft)below the water surface at a fixed tower positioned approximately 610 m (2,000 ft)east and along the same depth contour (9 m[30 ft])of the JAF plant discharge.
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Anticipated transients without a scram are also considered.
Anticipated transients without a scram are also considered.
Accident integrated doses include combined dose contributions from airborne and contained sources and represent the maximum dose for the area specified.
Accident integrated doses include combined dose contributions from airborne and contained sources and represent the maximum dose for the area specified.
 
2.3 CHEMICAL ENVIRONMENT Engineered Safety Feature (ESF)systems are designed to perform their safety functions in the temperature, pressure, and humidity conditions described in the EQEDC.Unit 2 does not utilize any chemical additives to the water recirculated by the ECCS during normal or accident conditions.
===2.3 CHEMICAL===
ENVIRONMENT Engineered Safety Feature (ESF)systems are designed to perform their safety functions in the temperature, pressure, and humidity conditions described in the EQEDC.Unit 2 does not utilize any chemical additives to the water recirculated by the ECCS during normal or accident conditions.
Amendment 16 2-3 December 1984 Nine Mile Point Unit 2 EQD Reactor Water Limits'hutdown Condition an accident, the containment and, drywell d below 5 percent (by volume)atmospheres are mainta inc hydrogen, as discussed in FSAR Section 6.2.5~reactor (normal operation), suppression pool, Water for the reac or n d ECCS is not chemically fuel storag p ra e ool, RHR system, an ll d b ion exchange systems within in'nhibited and is contro e y io the following normal operating limi'mits: 'Refueling and Fuel Suppression Storage , Pool Water Pool Wate Quality Parameter Conductivity Chlorides (as Cl-)510 mho/cm 925 C 50.5 ppm s3 umho/cm 925 C 60.5 ppm 510 umho/cm 925 C h 50.5 ppm pH 5.3 to 8.6 9 25oC 5.3 to 7.5 925 C 5.3 to 8.6 925 C 51 ppm 55 ppm Total suspended solids'n stations are provided for periodic analysis of ea or water, r fue'suppression pool water to assure comp iance wi limits of the plant technical specifications.
Amendment 16 2-3 December 1984 Nine Mile Point Unit 2 EQD Reactor Water Limits'hutdown Condition an accident, the containment and, drywell d below 5 percent (by volume)atmospheres are mainta inc hydrogen, as discussed in FSAR Section 6.2.5~reactor (normal operation), suppression pool, Water for the reac or n d ECCS is not chemically fuel storag p ra e ool, RHR system, an ll d b ion exchange systems within in'nhibited and is contro e y io the following normal operating limi'mits: 'Refueling and Fuel Suppression Storage , Pool Water Pool Wate Quality Parameter Conductivity Chlorides (as Cl-)510 mho/cm 925 C 50.5 ppm s3 umho/cm 925 C 60.5 ppm 510 umho/cm 925 C h 50.5 ppm pH 5.3 to 8.6 9 25oC 5.3 to 7.5 925 C 5.3 to 8.6 925 C 51 ppm 55 ppm Total suspended solids'n stations are provided for periodic analysis of ea or water, r fue'suppression pool water to assure comp iance wi limits of the plant technical specifications.
2.4 SPRAY/SUBMERGENCE n a roach for Unit 2 was to locate d flood 1 1 d b 1'th corn onents above postulate oo away from sources of water spray, ere d tions.or ualification under these con i d to h sical constrain s o'bl building arrangements, this is not easi e the plant.in A endix 3C of the FSAR, an evaluation has tes that the reactor an b been performed which demonstrates t a e effects of safely s u h t down when considering the e ec s o ed b one of the spray/submergence.
2.4 SPRAY/SUBMERGENCE n a roach for Unit 2 was to locate d flood 1 1 d b 1'th corn onents above postulate oo away from sources of water spray, ere d tions.or ualification under these con i d to h sical constrain s o'bl building arrangements, this is not easi e the plant.in A endix 3C of the FSAR, an evaluation has tes that the reactor an b been performed which demonstrates t a e effects of safely s u h t down when considering the e ec s o ed b one of the spray/submergence.
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Nine Mile Point Unit 2 EQD TABIE 2-4 WILL BE PROVIDED IN A FUTURE AMENDMENT Amendment 16 1 of 1 , December 1984  
Nine Mile Point Unit 2 EQD TABIE 2-4 WILL BE PROVIDED IN A FUTURE AMENDMENT Amendment 16 1 of 1 , December 1984  


Nine Mile Point Unit 2 EQD SECTION 3 FUNCTIONAL PERFORMANCE REQUIREMENTS
Nine Mile Point Unit 2 EQD SECTION 3 FUNCTIONAL PERFORMANCE REQUIREMENTS 3.1 SYSTEM LIST The systems required to mitigate an accident are listed in Table 3-1.This table also lists components/systems that are listed in Table 3.2-1 of the FSAR which have a quality group classification of A, B, or C, or designated either QA Category I or Seismic Category I.3.2 SYSTEM/ACCIDENT MATRIX The system/accident matrix shown in Table 3-2 identifies those systems that are required to respond to accidents which result in harsh environments.
 
===3.1 SYSTEM===
LIST The systems required to mitigate an accident are listed in Table 3-1.This table also lists components/systems that are listed in Table 3.2-1 of the FSAR which have a quality group classification of A, B, or C, or designated either QA Category I or Seismic Category I.3.2 SYSTEM/ACCIDENT MATRIX The system/accident matrix shown in Table 3-2 identifies those systems that are required to respond to accidents which result in harsh environments.
As discussed in Sections 2.1 and 2.2 and the EQEDC, generally only two of the several design basis accidents discussed in FSAR Section 15 and FSAR Appendix 15A are used to define harsh environment, for equipment.
As discussed in Sections 2.1 and 2.2 and the EQEDC, generally only two of the several design basis accidents discussed in FSAR Section 15 and FSAR Appendix 15A are used to define harsh environment, for equipment.
qualification.
qualification.
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No environmental qualification is required.Amendment 16 5 of 5 December 1984 t
No environmental qualification is required.Amendment 16 5 of 5 December 1984 t
Nine Mile Point Unit 2 EQD TABLE 3-3 SWEC/GE SYSTEM CROSS REFERENCE~sstem Nuclear Boiler Mainsteam Feedwater Automatic Depressurization Recirculation Control Rod Drive Redundant Reactivity Control Standby Liquid Control Neutron Monitoring Process Radiation Monitoring Post Accident Sampling Residual Heat Removal Low-Pressure Core Spray High-Pressure Core Spray Ieak Detection Reactor Core Isolation Cooling Reactor Water Cleanup ISC B22 MSS B22 FWS B22 B22 RCS B35 RDS RRS C12 C22 SLS-C41 NMS C51 D13 SSP D24 E12 CSL E21 CSH LDS ICS E22 E31 E51 WCS G33 SWEC Code GE Code Amendment 16 1 of 1 December 1984 0
Nine Mile Point Unit 2 EQD TABLE 3-3 SWEC/GE SYSTEM CROSS REFERENCE~sstem Nuclear Boiler Mainsteam Feedwater Automatic Depressurization Recirculation Control Rod Drive Redundant Reactivity Control Standby Liquid Control Neutron Monitoring Process Radiation Monitoring Post Accident Sampling Residual Heat Removal Low-Pressure Core Spray High-Pressure Core Spray Ieak Detection Reactor Core Isolation Cooling Reactor Water Cleanup ISC B22 MSS B22 FWS B22 B22 RCS B35 RDS RRS C12 C22 SLS-C41 NMS C51 D13 SSP D24 E12 CSL E21 CSH LDS ICS E22 E31 E51 WCS G33 SWEC Code GE Code Amendment 16 1 of 1 December 1984 0
Nine Mile Point Unit 2 EQD SECTION 4 QUALIFICATION METHODOLOGY
Nine Mile Point Unit 2 EQD SECTION 4 QUALIFICATION METHODOLOGY 4.1 HARSH ENVIRONMENT 4.1.1 BOP Equipment-Electrical The methodology established for the equipment qualification program is in accordance with the guidelines provided in NUREG-0588 for Category II plant and consistent with applicable Regulatory Guides and consensus national standards (ANSI and IEEE), and'n compliance with the requirements of 10CFR50.49.
 
===4.1 HARSH===
ENVIRONMENT 4.1.1 BOP Equipment-Electrical The methodology established for the equipment qualification program is in accordance with the guidelines provided in NUREG-0588 for Category II plant and consistent with applicable Regulatory Guides and consensus national standards (ANSI and IEEE), and'n compliance with the requirements of 10CFR50.49.
The methodology consists of developing the Equipment Qualification Environmental Design Criteria (EQEDC)''', which establishes the temperature, pressure, humidity, and radiation dose levels, for normal, abnormal, and accident'onditions.
The methodology consists of developing the Equipment Qualification Environmental Design Criteria (EQEDC)''', which establishes the temperature, pressure, humidity, and radiation dose levels, for normal, abnormal, and accident'onditions.
Post-accident operability time is developed to assure that the equipment will be qualified to maintain a safety function during a post-acciden event.These requirements are specification for the safety The specification mandates accomplished in accordance accordance with the quality 10CFRSO Appendix B.included i'n the procurement related electrical equipment.
Post-accident operability time is developed to assure that the equipment will be qualified to maintain a safety function during a post-acciden event.These requirements are specification for the safety The specification mandates accomplished in accordance accordance with the quality 10CFRSO Appendix B.included i'n the procurement related electrical equipment.

Revision as of 16:12, 6 May 2019

Valcor Valves & Gordos Limit Switches.
ML17054D432
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Issue date: 05/28/1982
From:
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To:
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ML17054D434 List:
References
QDR-5437-245-01, QDR-5437-245-1, NUDOCS 8303110359
Download: ML17054D432 (260)


Text

y~~S4d PN<We.'e"'f g>~+j/~+3 g Nine Mile Point Unit 2 ER-OLE 2.3 WATER 2.3.1 Hydrology 2.1.1 Surface Water 2.3.1.1.Seasonal Temperature Structure of Lake Ontario Lake Ontar'o is a large temperate lake that experiences seasonal chan es in its thermal structure, which, in turn, alters its irculation patterns.The changes in stratification r suit from atmospheric heat exchange and wind-induced mixi g.Natural warming o+the lake begins in mid-March and con-tinues until mid-Sept mber.At the onset of warming, the surface water temperat re in the shallow littoral zone rises more rapidly than in r gions just offshore.The disap-pearance of an offshore surface temperature of 4 C (39.2 F)in late June signals the rt, of the summer season in the lake.In general, vertica stratification over the entire basin is established at, this t, e by the combined effects of lake warming and the advectz n of the warmer, nearshore water.The lake's mean surface temperature reaches 21 C (69.8 F), and the temperature of e hypolimnion varies with depth, ranging between 3.8 C a 4.0 C (38.8 F and 39'F)In late September the warming process ds.The lake's mean surface temperature drops rapidly to b ow 17 C (62.6 F), and the thermocline begins to weaken.The vertical tem-perature gradient decreases as the surfac layer and deeper water effectively mix.(Mixing is the c nsequence of con-vection caused by cooling at the surface an is enhanced by the weakening of the thermocline, which perm'ts wind-induced turbulence to extend to greater depths.)The fall cooling process resembles spring warming but in revers The break-down of temperature stratification throughout th lake marks the onset of the winter season.The date of ov turn dif-fers from year to year, depending on the occu ence of storms.The lake surface is cooled below 4 C (3 F), and surface isotherms tend to be parallel to shore.Wi h con-tinued cooling, ice forms in the nearshore region.2.3.1.1.2 Water Circulation in Lake Ontario The annual average large-scale circulation pattern of Lake Ontario is counterclockwise (cyclonic flow), with flow+to the east along the south shore in a relatively narrow band and a somewhat less pronounced flow to the west along th 2.3-1 Nine Mile Point, Unit 2 ER-OLS north shore.The conceptual model explaining this general circulation pattern is presented in detail in the James A.FitzPatrick Nuclear Power Plant (JAF)316(a)Demonstration' The general circulation described above has been documented by observations collected over long periods (months).The circulation patterns that are observed at a specific time, however, are more complex as a result of the lake's response to the shifting winds.At times, a major shift in wind di s-tribution can alter the currents in a matter of hours, while at other times, some features of the current pattern can continue even with an opposing wind'wo important examples of wind-induced changes in the general circulation pattern are upwelling and internal oscillations.

Upwelling is characterized by the rising of colder, heavier, bottom water toward the surface.A variety of mechanisms has been proposed to account for the observed oscillations of the thermocline.

The most direct ex-planation is that an upwelling displaces the thermocline from equilibrium by converting kinetic energy of the wind to potential energy of the thermocline position.When the wind stress is removed, internal waves are set in motion and con-tribute to the dissipation of this energy.Internal waves increase in amplitude after storms, and in Lake Ontario the oscillations have a period of nearly 17.5 hr, roughly three complete oscillations every 2 days.These oscillations are a common feature of lake temperature records and are prominent in intake temperature records such as those of Nine Mile Point Unit 1 (Unit 1)and the JAF plant.2.3.1.1.3 Geomorphology at Nine Mile Point Nine Mile Point is a slight promontory along the south shore of Lake Ontario.The offshore slope at the plant is steep (5-10 percent grade)at the beach and flattens to 2-3 per-cent grade to the 5-m (15-ft)depth, then steepens to a 4-percent slope lakeward.The slope at'the 6-m (20-ft)depth contour is steeper at, 0he plant than to the east or west of the plant.A number of observations of the bottom sediments along the south shore of Lake Ontario have been made.Sutton et al'~'xamined nearshore bottom sediments (0-33 m{0-108 ft])in 1968 and 1969 between Rochester and Stony Point, and stated several conclusions relevant to the Nine Mile Point site: 1.There is generally a west-to-east transport of sediment.2 0 3 2 Nine Mile Point Unit 2 ER-OLS 2.Sites of sediment accumulation occur in nearshore shallow areas where the shoreline is irregular and where there are local deviations from the above transport pattern.3.In general, the coarser sands, boulders, pebbles, and cobbles lie in the beach or nearshore area, and finer sediments are found lakeward.4.Several small patches of sand occur offshore between Oswego and Mexico Bay, and it is hypothesized that these originate from the Oswego River.Visual observations made in the Nine Mile Point vicinity during the 1973-1976 aquatic programs (Section 6.5.2.1.2.7) corroborate the earlier observations of Sutton et al'.3.1.1.4 Currents at Nine Mile Point Current, measurements were made off the Nine Mile Point promontory from May to October 1969 and from July to October 1970.Two fixed underwater towers were placed in the lake, one in 7.3 m (24 ft)of water and one in 14.0 m (46 ft)of water, and provided average hourly current speed and direction data.In addition, two drogue surveys were conducted in 1969 to obtain the overall current pattern at the site.Results from these studies are presented in the JAF 316(a)Demonstration' and are summarized in the fol-lowing paragraphs.

Methods used in these studies are described in Section 6.3.1.The wind speed-frequency data indicate that over the year a speed in excess of 9 m/s (20 mph)occurs 21.6 percent of the time, based on readings averaged over a 6-hr period.From June through September, winds in excess of 9 m/s (20 mph)occur 13.9 percent of the time.The current speed of.6-hr duration exceeded with comparable frequency (June-September) at the 6-m (19-ft)depth is about 0.06 m/s (0.2 fps).The predominant current, direction in the preceding studies is alongshore.

On those occasions when onshore or offshore currents were observed, their magnitudes were substantially less than those of alongshore currents'ased on this near-field data, alongshore currents from the east are just slightly more likely to occur than from the west.Overall lake circulation patterns are typically west to east along the south shore of Lake Ontario (Section 2.3.1.1.3).

On-shore and offshore currents each account for only about 5 percent of the observations.

Approximately 30 percent of 2~3 3 Nine Mile Point Unit 2 ER-OLS the observations were below the meter threshold, 0.03 m/s (0.08 fps).2.3.1.1.5 Ambient Thermal Structure at Nine Mile Point Data on the thermal structure of the lake in the vicinity of Nine Mile Point are available from studies conducted from 1969 through 1978 in the Oswego and/or Nine Mile Point areas.Temperature data were gathered as part of all monitoring studies;however, the frequency of sampling and locations sampled varied during the years.A complete description of the sampling programs is presented in Section 6.1.1 and the yearly reports.

The results of these studies are also provided in the yearly reports'nd are summarized in the following paragraphs.

Vertical temperature profiles revealed the existence of transient thermal gradients equal to or greater than 1 C/m (1.8 F/3.3 ft)throughout the study area.The gradients existed primarily in the summertime.

They were not seasonally stable, since they were generated and destroyed by surface heating and cooling and mixing within the water column over periods dependent upon meteorologi=al conditions.

Although gradients were observed in sequential weeks for up to 3-to 4-week periods, the gradients observed were at different temperatures and at different depths from week to week and therefore were not, persistent.

When the gradients were observed, they appeared to be uniform from station to station.The temperature data recorded during June through September (1968-1972) in the existing intake of the Oswego Steam Station were statistically analyzed and show that tem-peratures in excess of 22.0 C (74 F)occurred only 12 per-cent of the time during June through September and, hence, less than 4 percent of the time on an annual basis.Since the lake is generally isothermal in the top 6 m (20 ft), the temperature obtained at the intake depth of 4~9 m (16 ft)~can be considered to be representative of the surface water temperature.

The natural seasonal progression of temperatures in the Nine Mile Point vicinity from mid-April through December 1976 is shown on Figure 2.3-1 for the 12-m (40-ft)depth contours at the NMPE control transect (approximately 32 km[20 mi]east of Unit 2)'~'.The maximum surface temperatures recorded at the 6-and 12-m (20-"and 40-ft)contours were 23.2~C (73 8oF)and 22 3oC (72 loF)on August 23 and 25, 1976, respectively.

The minimum surface temperature at both locations was 1.1 C (34.0 F)during mid-December.

The plot 2.3-4 Nine Mile Point Unit 2 ER-OLS (Figure 2.3-1)shows approximately 10 occurrences of cold water intrusions during the sampling period.The largest observed intrusions during the sampling year occurred on August 2 and 10.A secondary intrusion occurred on or about August 25.2.3.1.1.6 Existing Thermal Plumes 2'.1~1.6.1 Nine Mile Point Unit 1 Thermal Plume Surveys Thermal surveys of the Unit 1 plume were made during the first 6 yr of the plant's operation (1970-1975).

A total of 29 field surveys of the plumes resulting from the discharge of heated condenser cooling water into Lake Ontario have been conducted~

'.Section 6.1.2 provides descriptions of the methods used in these surveys.The results are sum-marized in Table 2.3-1.An examination of these data covering a 6-yr period shows that the plume extent and direction are strongly dependent on wind-induced lake currents, wave action, and upwelling.

However, the extent of the plume has no direct relationship with the actual wind speed;that is, high winds do not necessarily cause the longest plumes.Comparisons of plume surveys condu=ted during days of similar ambient temperatures show no definite relationship between the heat load and the area of thermal influence.

Also, there is no simple relationship between the heat load and the plume's'ffshore extent, even for the same wind speed and direction.

These observations indicate the stochastic nature of the plumes, as influenced by the hydrodynamic characteristics of the lake.The EPA guidance for 316(a)demonstrations recommends a dis-charge zone description and defines the discharge zone as"that portion of the receiving waters which falls within the 2 C isotherm of the plume 30%or more of the time".A cumulative frequency distribution analysis of the 29 sets of data (Table 2.3-1)was performed to define the surface plume area.The measured surface areas within the 2 C (3.6 F)isotherm were arranged in a series of descending sizes.The area that is exceeded with a selected frequency is then ob-tained from the resulting cumulative frequency curve (Figure 2.3-2).As shown in the figure, the surface plume area is greater than 81 ha (200 acres)30 percent of the time.A similar analysis was performed for the estimated volumes of the plume within the 2 C (3.6 F)rise isotherm.The cumulative frequency curve is shown on Figure 2.3-3.The volume exceeds 5.2 x 10~cu m (420 acre-ft)30 percent of the time.Thus, the calculated mean depth of the dis-2.3-5 Nine Mile Point Unit, 2 ER-OLS charge zone based on the estimated surface area and the es-timated volume is 0.64 m (2.1 f t).Due to the stochastic nature of the plume, the actual shape of a plume which extends over an area of 81 ha (200 acres)cannot be readily determined.

The four surveys with 2'C (3.6 F)isotherms closest to the 81-ha (200-acre) size have common areas almost symmetrical around the point of dis-charge along the plant transect (NMPP).A representative area enclosing the common area of all the plumes around the discharge point is illustrated as the discharge zone in Figure 2.3-4.The representative discharge zone extends about 572 m (1,875 ft)on each side of the discharge point along the shore, and to a maximum of about 721 m (2,365 ft)offshore.2.3.1.1.6.2 James A.FitzPatrick Plant Thermal Plume Surveys Triaxial hydrothermal field surveys of the JAF plant thermal plume were conducted during June, August, and October of 1976 and in April, June, and November of 1977.The sur-veys included simultaneous tri axial measurements oi tem-perature and dye concentration along fixed transects in the vicinity of the JAF and Unit 1 plants.Lake currents at three depths, lake level, and wind speed and direction were also continuously monitored before and during each survey.Section 6.1.1.3 provides a description of the survey procedures.

Table 2.3-2 contains the maximum observed 5T, the ambient temperature, a summary of the pertinent plant operating data, and prevailing lake conditions during each of the 19 triaxial surveys.The 1976 and 1977 surveys were conducted under plant generating loads ranging between 702 and 822 MWe (86 and 100 percent of capacity).

Current velocities were generally low, as evidenced by the fact that the lake current exceeded 15 cm/sec (0.5 fps)during only one of the surveys.The surveys were performed during April, June, August, October, and November.These time periods are indicative of conditions during late winter to early spring, late spring to early summer, summer, fall, and late fall to early winter.The results of the 19 postoperational hydrothermal surveys indicate that isothermal conditions prevail in the study area throughout most of the year due to the mechanical 2.3-6 Nine Mile Point Unit 2 ER-OLS Several studies-have been conducted by investor-owned utilities, including a 1973 survey performed by Rochester Gas and Electric Company at the Sterling site, approximately 35 km (22 mi)west of Nine Mile Point'"'.A comprehensive water quality investigation was conducted in the Mexico Bay area by New York State Electric and Gas Corporation during April 1977 to March 1978'.NMPC and the Power Authority of the State of New York (PASNY)sponsored water quality surveys in the Nine Mile Point study area from 1973 through 1978.Less extensive water quality monitoring reports were compiled in 1979 and 1980 by NMPC'~~,"'.The 1978 NMPC/PASNY survey provides the latest extensive data base and is used in this report for analysis of seasonal trends and for comparison with previous studies for long-term water quality trends''

2.3.3.3 Lake Ontario Water Quality Overview Lake Ontario has been designated by NYSDEC as Class A-Special Waters (International Boundary Waters), 6NYCRR702.1'~

'ts waters are suitable for use as public water supplies, for culinary or food-processing purposes, and for primary contact recreation.

In general, the water in Lake Ontario near Nine Mile Point has been found to be of good quality, with relatively low nutrient concentrations, low bacterial densities, and little industrial contamination.

Relatively high levels of dissolved oxygen, more than adequate for most aquatic organisms, were found during all seasons.The total dissolved solids (TDS)concentrations in Lake Ontario have increased since the early 1900s and are now above the New York State Water Quality Standard'uality of the water in the Nine Mile Point study area was determined to be similar to the general water quality previously reported for the lake.Spatial and temporal variations in water quality have been attributed to natural thermal stratification, action of wind.and storms, the Oswego River, west-to-east longshore currents, and hypolim-netic upwellings of cold, often nutrient-rich waters'.

2.3.3.4 Water Quality Parameters Monitored in Nine Mile Point Region Waters I The 45 water quality parameters measured in the Nine Mile Point site studies and reported in this section are listed in Table 2.3-12.Parameters 1 through 17 were used to as-sess the general chemical quality of the water.Parameters 18 through 24 are the major nutrients necessary for algal growth and are useful in identifying any potential influence 2.3-11 Nine Mile Point Unit 2 ER-OLS from agricultural and sanitary waste discharges.

Parameters 25 through 31 are generally used to indicate contamination of waters by sanitary and industrial wastes.Trace metals analyses, parameters 32 through 45, provide a basis for the evaluation of toxicity impacts on aquatic life (Section 5.5)and were included to characterize ambient water quality relative to criteria based on toxicity'to aquatic life.The sampling locations, survey designs, and analytical procedures utilized in the Nine Mile Point studies conducted for NMPC and PASNY are described in Section 6.6.2.3.3.5 Water Quality in the Nine Mile Point Region of I ake Ontario Table 2.3-13 summarizes the water quality data for Lake On-tario in the vicinity of Nine Mile Point.An 8-yr record of water quality is presented.

In addition to year-to-year trend description, data in Table 2.3-13 cover historical high and low values for the Nine Mile Point region and yearly mean, maximum, and minimum values for each sampling year.Significant spatial water quality variability in Lake Ontario waters of the Nine Mile Point region was not evident in the raw transect data, excepting solids and temperature.

Trends evident in important selected water quality parameter subsets are summarized in the following paragraphs.

Water Tem erature Water temperature influences the kinetics of chemical and biochemical reactions.

This parameter displays seasonal variations directly related to air temperature.

Water tem-perature was measured monthly or twice monthly in Lake On-tario in the water quality monitoring program.In addition, continuous in situ monitoring was conducted.

Long-term trends indicate no significant change in water temperature over time.Seasonal water temperature variations are illus-trated on Figure 2.3-6.Spatial temperature variations are evident in the raw data presented in References 6 through 11 and 44 and 45.The Nine Mile Point Unit, 1 (Unit 1)discharge elevates lake sur-face temperature, particularly in the nearshore region.The JAF plant has less of a temperature effect, as evidenced by data taken from the water column in the vicinity of its dis-charge (Section 2.3.1.1.1).

2.3-12 Nine Mile Point Unit 2 ER-OLS Iron All mean annual iron concentrations in the study area are less than the standard of 300 ug/l.Maximum iron concentrations reported from 1973 through 1977 exceeded the standard.Near the end of the monitoring program, a trend toward decreasing iron concentrations can be noted, with the 1978 maximum of 220 ug/l.L Zinc Sample contamination has previously been noted for the 1974 data.Excluding 1974 data, zinc concentrations ranged, on an average yearly basis, from less than 14 ug/1 to 50.6 ug/1.No long-term trends were evident in the data.Maximum zinc concentrations in 1973 and 1978 exceeded the state standard of 300 ug/l.2.3.3.6 Wastewater Discharges The major waste constituent released to Lake Ontario as a result of site and vicinity water usage is heat.Unit 1 and the JAF plant use Lake Ontario water for cooling.Heated cooling water discharges are rapidly assimilated and cooled to ambient, water temperatures outside defined mixing zones (Section 2.3.l.l.l).

Waste discharges from the preceding facilities plus ef-fluents from the Unit 2 site contribute minor amounts of TDS to the Lake Ontario Nine Mile Point regional waters.2.3-19 Nine Mile Point Unit 2 ER-OLS 2.3.4 References Sweers,.H.E.Structure, Dynamics and Chemistry of Lake Ontario: Investigations Based on Monitor Cruises in 1966 and 1967.Mar.Sci.Branch, Dept.of Energy, Mines and Resources, Ottawa, Canada.Manuscript Rept., Series 10, 1969.2.Power Authority of the State of New York.James A.FitzPatrick Nuclear Power Plant 316(a)Demonstration Submission.

Prepared for United States Atomic Energy Commission, 1971.3.Csanady, G.T.The Coastal Boundary Layer in Ontario.Chapter II.The Summer-Fall Regime.Physical.Oceanogr., 1972, Vol.2, p.168-176.Lake J.Sutton, R.G.;Lewis, T.L.;and Woodrow, D.I.Near Shore Sediments in Southern Lake Ontario, Their Dispersal Pat-terns and Economic Potential.

Proc.13th Conf.Great Lakes Res., 1970, p.308-318.5.Gunwaldsen, R.W~;Brodfeld, B.;and Hecker, G.E.Cur-rent and Temp'erature Surveys in Lake Ontario for James A.FitzPatrick Nuclear Power Plant.Proc.13th Conf.Great Lakes Res.,'970, p.914-926.6.Quirk, Lawler 6 Matusky Engineers.

1973 Nine Mile Point Aquatic Ecology Studies.Prepared for Niagara Mohawk Power Corporation and Power Authority of the State of New York, 1974.7.Lawler, Matusky 6 Skelly Engineers.

1974 Nine Mile Point Aquatic Ecology Studies.Prepared for Niagara Mohawk Power Corporation and Power Authority of the State of New York, 1975.8.Lawler, Matusky 6 Skelly Engineers.

1975 Nine Mile Point Aquatic Ecology Studies.Prepared for Niagara Mohawk Power Corporation, 1976.9.I awler, Matusky 6 Skelly Engineers.

1976 Nine Mile Point Aquatic Ecology Studies.2 vols.Prepared for Niagara Mohawk Power Corporation and Power Authority of the State of New York, 1977.10.Texas Instruments, Inc.Nine Mile Point Aquatic Ecology Studies 1977 Annual Report.Prepared for Niagara Mohawk Power Corporation and Power Authority of the State of New York, 1978.2.3-20 Nine Mile Point Unit 2 ER-OLS TABLE 2.3-3 (Cont)Map No.+Name of System Intake Count Distance (km/mi)and Direction~from Uni 2 Distance (km/mi)by Water from Unit 2 Average Wi thdrawa I Rate 1 8-81~ou m da~md Product ion Population Ca aci~Te of use Served ouu~tuda~md~common s 15 Chaumont Village (Jefferson County)60/37 NNE 61/38 265 0.07 Domestic 550 908 0.24 Winter (Dec-Mar)usage is approx.189 cu m/day (0.05 mgd);summer usage (Jun-Sep)avg.341 cu m/day (0.09 mgd)16 Cape Vincent 65/41 N Village (Jefferson County)65/41 757 0 20 Domestic 750 908 0.24 Wi thdrawa I s fluctuate between Jun and Sep from 473 to 1,136 cu m/day (0.125 to 0.3 mgd)+Locations corresponding to map numbers are shown on Figure 2.3-4.SOURCES: References 20, 22, 24, 25, and 28 4of4 0

Nine Mile Point, Unit 2 ER-OLS 2.4 ECOLOGY 2.4.1 Terrestrial Ecology 2.4.1.1 Site and Vicinity The following description of, the existing terrestrial eco-systems in the vicinity of Unit 2 is derived primarily from 1)1979 aerial photographs, 2)a 1979 terrestrial field sur-vey (see Section 6.5'for methodology), and 3)review of pertinent literature as referenced.

Stereoscopic false color infrared and true color aerial photographs of the Unit 2 site were taken in August, 1979 to delineate areas of existing environmental stress and to facilitate vegetative mapping (Figures 2.4-1 and 2.4-2).In addition, a terrestrial field survey was conducted in Sep-tember 1979 to provide quantitative and qualitative descrip-tions of the floral and faunal communities within 1.6 km (1.0 mi)of the geographic center of the Unit 2 site (Figure 2.4-2).To provide information in the general vicinity of the site, up to 80 km (50 mi), data were obtained from the habitat and wildlife inventory of the Oswego County Coastal Zone, conducted in 1976, the Port Ontario Harbor terrestrial vertebrate study, conducted in 1977, the Napanee District Land Use Strategy Plan, and from communication with state and local wildlife personnel, 2.4.1.1.1 General Site Characteristics Unit 2 is located within the Oneida Plain physiographic region of Oswego County, NY'.The site also lies within the 93.8-sq km (36.2-sq mi)area defined by the St.Lawrence Eastern Ontario Commission as the Oswego County Coastal Zone'~'.The topography of the Oneida Plain, which extends south of Lake Ontario, is most appropriately described as a series of undulating hills.The lake plain rises from a minimum of 76.2 m (250 ft)above sea level in the numerous wetlands along the Lake Ontario shoreline to a maximum of 93.9 m (308 ft)above sea level at Derby Hill in the town of Mexico.

The south shore of Lake Ontario is basically un-derlain by Oswego sandstone.

The closest state or federal wildlife management area is the Deer Creek Marsh Wildlife Management Area, operated by the New York State Department of Environmental Conservation (NYSDEC), located about 31 km (19 mi)east-southeast of the site.The closest area to the north is the Point Petre Provincial Wildlife Area in Prince Edward County (Athol, Ontario)about 69 km (43 mi)from the site'"'.The only 2'-1 Nine Mile Point Unit 2 ER-OLS p other wildlife management area in the vicinity of the site is an Audubon bird sanctuary located 3 km (1.9 mi)from the site on the Lake Ontario shore, east, of Nine Mile Point Road (Figure 2.4-3).This is the closest protected wildlife area to the site, and management consists primarily of the erec-tion of nest boxes and the maintenance of visitor trails':aa 4 2.4.1.1.2 Terrestrial Communities and Their Interactions With Their Environment The coastal zone of Oswego County lies in a transitional area between boreal forest and northeastern hardwood forest.

The proximity of Lake Ontario appreciably modifies the climate, and thus has a significant effect on the floral and faunal associations of the region.

The climax community is a deciduous forest with an extensive herbaceous ground cover.The biota of the area are charac-teristic of a transitional zone with high species diversity'wo basic ecosystems are present in the coastal zone: wetlands and upland areas.The wetlands generally result from disruption of drainage caused by the drumlin topography of the region'~They are generally transitional and in-clude shallow ponds, shrub swamps, wood swamps, and inter-mittently wet bottomland-like forests.Much of the original mature forest land of the Oneida Plain was cleared in the past for farming, but a great deal has since been abandoned'~'.

As such, the uplands are mostly second-growth communities in a variety of successional stages.For this region, the mature climax hardwood com-munity is composed of the beech-maple-hemlock association.

Ironwood (~Car inus caroliniana), witch hazel (Hamamelis understory.

Ground cover, although generally sparse due to the closed canopy, consists of false Solomon's seal"~2 The vegetation in the vicinity of the site may be divided into a number of distinct community types (Figure 2.4-2).The forested cover types described in the following para-graphs were sampled quantitatively along three transects using a point-quarter sampling technique (Section 6.5.1.1)during the 1979 field survey.The remaining cover types are described qualitatively, based on observations made during 2.4-2 Nine Mile Point Unit 2 ER-OLS 2.5 SOCIOECONOMICS 2.5'Demography Unit 2 is located on Lake Ontario in the town of Scriba, in the north central portion of Oswego County, approximately 10 km (6.2 mi)northeast of the city of Oswego.In 1980, Oswego County had an estimated population of 113,901, at an average density of 43.0 people/sq km (111 people/sq mi)'his population density is considerably lower than the state average of 137 people/sq km (356 people/sq mi).The 1980 population and the population density for the 10 towns and 1 city within 20 km (12.4 mi)of Unit 2 are listed in Table 2.5-1.Town and city boundaries are shown on Figure 2.5-1.The 80-km (50-mi)area surrounding the station contains all or portions of 10 New York State counties and portions of Canada.Also within 80 km (50 mi)is the Syracuse Standard Metropolitan Statistical Area (SMSA).Political boundaries of counties and population centers within 80 km (50 mi)are shown on Figure 2.5-2.For population projection purposes, 1985 is used as the year of initial plant operation.

The difference between the population of 1985 and 1986, the year of actual commercial operation, should not differ to any significant extent.Therefore, since projections are calculated at 5-yr inter-vals based on the decennial census, 1985 provides the best estimate of population distribution at the start of commer-cial operation.

2.5.1.1 Population Within 20 Km (12.4 Mi)The total 1980 population within 20 km (12.4 mi)of Unit 2 is estimated to be 46,349, a l.l-percent increaSe over the 1970 total.This population is projected to increase to ap-proximately 64,970 by the year 2000 and to approximately 106,509 by 2030.The 20-km (12.4-mi)area contains all or portions of 1 city and 10 towns: the city of Oswego and the towns of Minetto, Scriba, New Haven, Oswego, Mexico, Palermo, Richland, Volney, Granby, and Hannibal.City and town boundaries are shown on Figure 2.5-1.'f the 10 towns and 1 city in the 20-km (12.4-mi)area, the city of Oswego is the largest in population size, containing approximately 19,793 people in 1980.Next, in order of population, are Granby, Richland, Scriba, and Volney, with estimated 1980 populations of 6,341, 5,594, 5,455, and 5,358, respectively.

Population growth and the 2.5-1 Nine Mile Point Unit.2 ER-OLS 1970-1980 percent change in population for the towns and city within the 20-km (12.4-mi)area are listed in Table 2.5-2.It is expected that a large portion of in the 20-km (12.4-mi)area will southeastern fringes of.the city of rounding towns of Scriba, Palermo, New absorbing much of the city's satellite the population growth occur around the Oswego, with the sur-Haven, and Volney growth'~'.

Population distribution within 8 km (5 mi)of the station is based on a field house count conducted in October 1981 and town-specific people per household factors.Between 8 and 10 km (5 and 6.2 mi), population distribution is based on a house count taken from U.S.Geological Survey maps (photorevised 1978)on which houses have been symbolically identified'.

Houses were used to estimate the area population by applying a factor'of 2.65 persons/household for each house in the town of Scriba and 2.43 persons/household for each house in the town of New Haven.Population figures within 10 km (6.2 mi)of the site were then projected by multiplying the base-year population by the Oswego County growth factor, supplied by the New York State Department of Commerce, Economic Develop-ment Board, which used the cohort-component method to obtain projections'~'.

Polar-grid sector populations between 10 and 20 km (6.2 and 12.4 mi)are based on 1980 U.S.Census data and New York State population projections.

Sector populations were determined by assuming that the population of a minor civil division (i.e., a town)is evenly distributed over its land area.The proportion of each civil division's area in each grid sector was then determined and applied to each civil division's total population, yielding the population in each grid sector.Population projections, based on 1978 projections supplied by the New York State Department of Commerce, Economic Development Board, were applied to each civil division, assuming that each portion would maintain its relative share of any population change.Population density was calculated by dividing the population in each sector by its land area'.Population distribution within a 20-km (12.4-mi)radius of the plant for 1980 through 2030 is shown on Figures 2.5-3 through 2.5-9 and listed in Tables 2.5-3 through 2.5-9.Transient population within 20 km (12.4 mi)of Unit 2 is limited due to the rural, undeveloped character of the area.There are, however, a number of school, industrial, and recreational facilities in the area that create small, daily 2.5-2 Nine Mile Point Unit 2 ER-OLS TABLE 2.5-1 1980 POPULATION AND POPULATION DENSITIES FOR TOWNS AND CITIES WITHIN 20 KM (12.4 MI)OF UNIT 2 City of Oswego Oswego (town)Granby Richland Scriba Volney Mexico Hannibal Palermo New Haven Minetto 1980 Po ulation 19,793 7,865 6, 341 5, 594 5, 455 5, 358 4, 790 4, 027 3,253 2, 421 1, 905 Population Density eo le s km 1,029.0 116.9 55.2 40.9 52.9 46.0 41.8 38.5 31.6 31.7 125.5 SOURCE: Reference 1 1 of 1 V 0 0 Nine Mile Point Unit 2 ER-OLS pact the overall visual quality of the area.The view of the cooling tower will be the only noticeable changers The cooling tower is 165 m (541 ft)above ground level and is visible at some locations, as shown for selected locations on Figures 3.1-4 through 3.1-7.Depending on meteorological conditions, the natural-draft cooling tower will emit evaporative plumes that may be visible from locations within the 16-km (10-mi)area.Expected visible plume occurrences are described in Section 5.3.3.1, and predicted frequency of plume occurrences are shown on Figures 5.3-1 through 5.3-25.The anticipated plumes for 5-percent, 1-percent, and O.l-percent occurrences at selected locations are shown on Figures 3.1-4 through 3.1-7, and an analysis of their visual impacts is presented in Section 5.8.1.1.The plume occurrence denotes the maximum extent of plume that is, visible for a certain percent of time, as shown on the figures.Starting in April and continuing through September, when recreational activities on the lake and along the shoreline are frequent, the cooling tower will be visible from the shoreside by fishermen, recreational users, and others at facilities such as the Ontario Bible Conference Association Camp (a lakefront facility bordering the site on the west).Cooling tower plumes are not expected to have a significant visual impact.Most visually sensitive sites, listed in Table 3'-1, are located in vegetated or developed areas, specifically within the city of Oswego.Therefore, distant views that might include the plume are not possible from these sites.However, at locations along the shoreline at elevated grades, such as Fort Ontario (Figure 3.1-7), plumes may be visible.The visual impact of Unit 2 is minimal due to the limited number of locations from which the plant is visible, the lack of visibility from many visually sensitive or intensive land use areas, and the small portion of plant structures that can be seen above the surrounding vegetation.

3.1.3 Architectural Rendering'of the Plant Figure 3'-8 shows an architectural rendering of the Unit 2 facility, including all major station features and land-scaping whether actually completed or planned.3.1-3

Nine Mile Point Unit 2 ER-OLS All components cooled by the service water system are designed based on a maximum service water system inlet temperature of 25 C (77 F).Table 3.4-1 provides the maximum flow rates and heat gains for each of the following plant conditions:

1~Normal operation.

2.Normal shutdown.3.Loss-of-coolant accident (LOCA)without loss of offsite power (LOP).4.LOCA coincident with a LOP.The actual service water system flow and heat gain will vary below the maximum values given in Table 3.4-1 depending on plant and ambient conditions.

3.4.1.3 Intake and Discharge Systems 3.4.1.3.1 System Description The source and discharge point of all cooling water required by Unit 2 is Lake Ontario..Six service water pumps supply water for the two cooling systems: the service water system and the circulating water system.A detailed description of the intake and discharge systems is provided in FSAR Section 9.2.5.3.4.1.3.2 Operational Modes During normal plant operation, the intake flow required for the service water pumps is conveyed through two intake structures that are connected to the onshore screenwell via pipes located within tunnels below the lake bottom.The plant discharge is conveyed from the discharge bay through the diffuser nozzles to the lake via the discharge tunnel below the lake'ottom.

This is further discussed in FSAR Section 9.2.5.3.4.1.3.3 Quantities of Heat Distributed The average heat rejected to the lake by the service water discharge system is 1.75 x 10 g-cal/sec (2.5 x 10 Btu/hr).During normal operation, the maximum heat rejected is 3.29 x 10~g-cal/sec (4.7 x 108 Btu/hr).3~4-3 Nine Mile Point.Unit 2 ER-OLS 3.4.1.3.4 Quantities of Water Withdrawn, Consumed, and Discharged During normal operation, an average total flow of 3,380 1/s (53,600 gpm)is withdrawn from the lake: 2,440 1/s (38,675 gpm)for the service water system requirements and 940 l/s (14,925 gpm)for the fish diversion system.Table 3.3-1 lists monthly minimum, average, and maximum total intake flows.The closed-loop circulating water system uses discharge from the service water system for its makeup requirements.

Depending on the meteorological conditions, the combined plant discharge flow ranges from a minimum of 1,450 l/s (23,055 gpm)to a maximum of 2,210 1/s (35,040 gpm)during normal operation.

During a normal shutdown, the maximum plant discharge is approximately 3,080 1/s (48,800 gpm)..Discharge flows from the water treatment system and the radwaste system flows are discussed in Section 3.3.FSAR Figure 9.2-1 shows the service water intake and discharge systems'ater use.The monthly minimum, maximum, and-average cooling water intake and discharge flows are listed in Table 3.3-1.3.4.1.3.5 Water Temperatures The, ambient lake water temperature ranges from 0 C to 26 C (32 F to 78 F).When int'ake water temperature is less than 3.3 C (38 F), tempering flow is provided to maintain a minimum mixed intake flow temperature of 3.3 C (38 F)..The combined plant discharge temperature ranges from 0.6OC to 15.6 C (1.0 F to 28.0 F)above the ambient lake temperature.

The submerged discharge diffuser will cause considerable cold water dilution of the heated discharge.

Therefore, the maximum predicted change in the lake surface temperature, resulting from the plant discharge, is 1.3 C (2.3 F).This value is consistent with the New York State Water Quality Standards limiting lake surface temperature to a maximum of 1.7 C (3 F)above ambient.The monthly minimum, maximum, and average plant discharge differential temperatures above the lake temperatures are listed in Table 3.3-1.During normal operation, the plant discharge flow and temperature vary with fluctuations in the meteorological conditions (Section 2.3.2).3.4>>4 Nine Mile Point Unit 2 ER-OLS Downstream of the rotary gates, flow from both vertical shafts merges into a common bay and then divides into two 1.2-m (4-ft)wide screenbays.

A trash rack and an angled, flush-mounted traveling water screen are located in each screenbay.

The two traveling water screens are angled 25 deg to the upstream direction of flow with their downstream ends converging.

The trash rack is cleaned by a rake, and debris collected by the rack is deposited into the trash rake hopper and disposed of in a New York State-approved landfill.I.After passing through the traveling water screens, the two screenbays merge into a common intake bay from which the service water pumps take suction.Two motor-operated rotary valves, arranged in parallel and normally closed, are located upstream of the two screenbays to provide a redundant flow path to the service water pumps.A fish bypass and return.system is provided at the downstream end of the screens.Fish entering the screenbays pass through the trash racks and are guided by two angled, flush-mounted traveling water screens into 15-cm (6-in)wide bypass slots at the downstream end of the screens.The two slots converge and at their junction the fish are transported through a funnel-shaped transition of two 46-cm (18-in)pipes which combine into a single 61-cm (24-in)pipe leading to the jet pump.The jet pump discharges a bypass flow and the fish into the fish discharge pipe located in Tunnel No.2, which is not utilized for plant discharge.

A fish holding tank is also provided at the jet pump discharge for periodic sampling.The fish are transported through the return pipe to a vertical riser and discharged into the lake in an easterly direction, parallel to the lake, bottom.3.4.2.2 Discharge System The discharge flow consists of service water bypass (service water discharge not utilized as circulating water system makeup), circulating water system blowdown, water treatment system discharge, and liquid radwaste;all of which discharges into the discharge bay.The discharge system consists of an onshore discharge bay, a discharge portion of Tunnel No.1, a discharge tunnel, and a two-port diffuser, as shown on Figure 3.4-4.The discharge bay is located on the west.side of the two intake shafts and is separated from the shafts by a wall that extends up to 3.4-'7 Nine Mile Point Unit 2 ER-OLS el 85 m (279 ft)and which acts as a weir, as shown on Figure 3.4-6.Stoplog slots are provided from the top of each weir, el 85 m (279 ft), to the operating deck, el 87 m (285 ft), with a stoplog gate normally in place between the south shaft and the discharge bay.This provides an alternate discharge path, as discussed in FSAR Section 9.2.5~The discharge flow enters a 1.4-m (4.5-ft)diameter steel discharge pipe that is located on the north wall of the discharge bay and which connects the discharge bay to the discharge portion of Tunnel No.1.Tunnel No.2 does not have discharge capability.

After traveling through the discharge portion of Tunnel No.1, the discharge flow continues past the point where the 1.4-m (4.5-ft)diameter intake pipe rises to its intake st'ructure, and enters into the smaller Gunite-lined discharge tunnel, as shown on Figure 3.4-4.Both the discharge portion of the intake tunnel and the discharge tunnel have sufficient area for the plant discharge flow.The discharge portion of Tunnel No.1 terminates at a point approximately 457 m (1,500 ft)from the shoreline, where the discharg flow enters a 1.4-m (4.5-ft)diameter steel riser leading to a two-port'diffuser located on the lake bottom.The 1.4-m (4.5-ft)diameter riser divides into two 0.9-m (3.0-ft)diameter steel pipes with 0.46-m (1.5-ft)diameter nozzles at the end of each, as shown on Figure 3.4-7.The~nozzles are oriented to face offshore 120 deg apart and inclined upward at a 5-deg angle from horizontal to minimize bottom scouring.The invert of the nozzle openings is 0.9 m (3.0 ft)off the lake bottom, providing 11.35 m (37.25 ft)of water above the nozzle centerlines at minimum controlled lake el 74.4 m (244.0 f t)(USLS 1935 Datum).The location and orientation of the nozzles were designed and located to comply with New York Codes, Rules, and Regulations (6NYCRR704), 1976.This regulation stipulates that the lake surface temperature will not be increased by more than 1.7 C (3 F)after the addition of heat, from an artifical origin.To meet the 1.7'C (3 F)requirement of 6NYCRR704, the mathematical model developed by Koh and Fan for a row of equally spaced round jets discharging at an arbitrary angle of inclination to the horizontal into stagnant water was used'.From this model, standard nomograms published by the EPA were generated'~'..

Depth corrections by Robideau were applied to the EPA nomographs to obtain more conservative results'.New York State Regulation 6NYCRR652 (1976)governs discharges to hypolimnetic waters 3.4-8 Nine Mile Point Unit 2 ER-OLS of a lake.Through an extensive lake temperature monitoring program conducted in 1973 in the Oswego-Nine Mile vicinity, it was determined that a seasonally stable stratified layer or thermocline does not exi'st at Nine Mile Point.Therefore, the discharge does not enter the hypolimnion.

Input data for the preceding mathematical models are listed in Table 3'-1.Analysis of worst-case conditions resulted in the predicted temperature.distribution presented on Figure 5.3-6..The model predicts the maximum surface temperature rise to be 1~3 C (2.3 F)~3.4.2.3 Cooling Tower The cooling tower is a single-cell, wet-evaporative, natural-draft cooling tower utilizing a counterflow-type design.The location of the tower is shown on Figure 3.1-1.The cooling tower design point is at an atmospheric condition of 23 C (74 F)wet-bulb temperature and 50 percent relative humidity.During these meteorological conditions, the tower is designed to operate at an 8.9 C (16 F)approach, with a 15 C (27 F)range.Depending on the meteorological conditions, the cooling tower is designed to supply water ranging from 6.7 C to 34 C (44 F to 93 F)to the main condenser.

Selection of the design conditions for the cooling tower was based upon meteorological data from Rochester, NY, for the period January 1, 1949, through December 31, 1958.Onsite meteorological data obtained during 1974 and 1978 show the Rochester data to be similar to site data.Rochester, located approximately 113 km (70 mi)west of the Nine Mile Point site on the shore of Lake Ontario, is the nearest meteorological station with a sufficiently long period of data and a climate approximately that of the site upon which the cooling tower design could be based.The frequency distribution of hourly j.oint dry-bulb temperature

-wet-bulb temperature occurrences is plotted on Figure 3.4-8, with the relative humidity curves superimposed.

The cooling tower performance curve for the design condition is also plotted on this figure.This curve defines the.frequency with which the design point is equaled or exceeded.From Figure 3.4-8, the design point is equaled or exceeded approximately 33 hr per year, or approximately 3 percent, of the summertime hours when the wet-bulb temperatures are over 18 C (65 F).The cooling tower performance curves are shown on FSAR Figures 2C-2 and 2C-3~At the design point of 23 C (74 F)3~4-9 Nine Mile Point Unit 2 ER-OLS wet-bulb temperature and 50 percent relative humidity, the cold water temperature is 31.9'C (89.5 F)and the evaporation rate is 820 1/s (12,950 gpm);or 2.2 percent of the circulating water flow.The concrete cooling tower is 165 m (541 ft)in height, with a bottom diameter of 123 m (405 ft)and a top diameter of 83 m (273 ft)(Figure 3.4-9).The top of the cold water basin wall is at el 80.01 m (262.5 ft), providing 0.6 m (2 ft)of freeboard above the normal water elevation in the basin.The bottom of the tower fill is at el 90.2 m (295.8 ft), the centerline of the upper distribution piping is at el 93.2 m (305.75 ft), and the drift eliminator's approximately at el 93.4 m (306.3 ft).Slide gates are provided in the upper distribution flumes to isolate the center section of the tower fill and force all water to the perimeter of the tower during winter operation.

An ice prevention ring is provided at the top of the air inlet opening around the tower perimeter.

The ice prevention ring provides a veil of water to restrict-the air inlet opening and prevent ice formation during extremely cold weather conditions.

Bypass gates are provided on three of the six inlet risers at the cold water basin level for winter startup and shutdown operations.

The bypass gates each have a capacity of approximately 14,130 1/s (224,000 gpm).Sixteen wind baffles, spaced 22.5 deg apart, are located around the perimeter of the tower air inlet opening.These baffles minimize the local blow-through from the tower during high-wind conditions.

Aircraft warning lights are provided on the tower in accordance with FAA requirements.

An access ramp is provided into the cold water basin for periodic removal of sedimentation.

All sedimentation removed from the tower basin is disposed of in a New York State-approved landfill.3.4.2.4 Main Condenser The main condenser provides a heat sink for the turbine exhaust steam, turbine bypass steam, and other flows.It also provides deaeration and holdup capacity for the condensate which is reused after a period of radioactive decay.3.4-10 Nine Mile Point Unit 2 ER-OIS certain assumptions have been made regarding quantity of leakage, removal in the turbine building, radioactivity levels in the leakage, and partition factors.Estimated doses are based on a level of 50,000 uCi/sec (after 30-min decay).The turbine building ventilation system discharges through the main plant stack.All releases from the stack are measured by an online isotopic effluent monitor.The radioactive gaseous effluent from the turbine building ventilation system is presented in Table 3.5-9~In calculating doses for Section 5.4, activities listed in Table 3.5-9 were used.3.5.2.1.6 Radwaste Building Ventilation Certain tanks and equipment and some radwaste building service areas are vented to discharge gases to the combined radwaste/reactor building exhaust vent.This release point is monitored to ensure that the discharge is-below the limits required by applicable regulations.

FSAR Section 12.2.1.5 presents a description of radiation sources in the radwaste building.3.5.2.2 Description of the Off-Gas System The off-gas processing system is provided to reduce the total amount of gaseous radwastes released from the plant.The piping and instrumentation diagram for the off-gas system is shown on FSAR Figure 11.3-1.Two trains of four charcoal beds each are arranged in series to provide a 522-hr decay period for xenon isotopes and a 29.6-hr decay period for krypton isotopes,'assuming 25-scfm flow rate (preceding holdup-time values are based on NUREG-0016, Revision', calculation methods).The minimum decay period provided by the system, assuming 52.5-cfm flow rate, is 274 hr for xenon and 13.7 hr for krypton.The system also provides for a delay time of 7.6 hr for Argon-41 (calculated using NUREG-0016, Revision 1).The design is based on 348,900 uCi/sec continuous activity flow rate for noble gases measured after a 30-min decay period.Consequently, the activity flow rate used as a design basis is significantly higher than the activity flow rate of 50,000 uCi/sec given in Table 3.5-8, which is an expected value and considered more representative for normal plant operation (Section 5.4).Process off gas is removed from the main condenser by steam jet air ejectors.The estimated mass flow rates for off gas to be handled by each steam jet air ejector unit is: Dry air 63 kg/hr (138 lb/hr)3.5-7 Nine Mile Point Unit 2 ER-OLS Hg Op Hp0 Noble gases 20 kg/hr (43 lb/hr)156 kg/hr (344 lb/hr)1,696 kg/hr (3,740 lb/hr)(as dilution steam)Negligible NOTE: The off-gas system inlet temperature is approximately 121 C (250 F).The preceding quantities are used as the design basis for the off-gas system.Furthermore, the system is designed to accommodate variations in flow rates without compromising performance abilities'he off-gas system is located in the turbine building and operates in the following manner.Steam jet air ej ectors remove noncondensable gases from the main condenser, provide the required pressure at the inlet of the off-gas=system, and maintain the hydrogen concentration below the 4-percent (by volume)flammability limit by providing the required steam flow for dilution at all power levels.-Hydrogen analyzers are used to confirm these concentrations.

Low steam flow is sensed and results in an alarm signal.A steam preheater raises the temperature of the gas stream prior to entering the catalytic recombiner, where all but approximately 6.4 kg/hr (14 lb/hr)of water vapor recombines.

Further water removal occurs in the freezeout dryer.The activity of the off gas is reduced by passage through a series of ambient temperature charcoal adsorber tanks, and HEPA filters are used to remove any particulate matter.Major components of the off-gas system are duplicated to provide two parallel off-gas trains.Components requiring servicing are placed in individually shielded cubicles to minimize personnel exposure during maintenance.

The'off-gas system includes the following equipment and is shown on FSAR Figure 11.2-1.3.5.2.2.1 Preheaters Following pressurization of the gas stream and dilution by the air ejectors, the off-gas mixture enters a preheater.

The preheater uses steam from the auxiliary steam system to raise the temperature of the gaseous mixture to 143 C (290'F).This temperature rise serves to: l.Ensure complete vaporization of any liquid water.3.5-8 Nine Mile Point Unit 2 ER-OLS 3.6 NONRADIOACTIVE WASTE SYSTEMS 3.6.1 Wastes Containing Chemicals or Biocides 3.6.1.1 Discharges to Water 3.6.1.1.1 Description of Nonradioactive Waste Treatment Systems and Sources of Discharges The Unit 2 chemical waste treatment.

system handles wastewaters from regeneration of ion exchange resins used in the makeup demineralization water treatment system..A 227,100-1 (60,000-gal) capacity waste neutralizing tank, sized for two complete regenerations of the makeup demineralizer system, provides for acid and caustic wastewater self-neutralization.

Additional neutralization, if required, is achieved through the addition of concentrated sulfuric acid or sodium hydroxide (caustic).

The acid or caustic is added into the tank and mixed by use of a full-flow recirculation line to achieve a pH of not less than 6.5 and not greater than 8.5.After neutralization and sampling, the waste neutralization tank's contents are routed to the discharge bay and subjected to extensive dilution prior to discharge, as described in Section 3.3.1.Figure 3.3-1 illustrates the flow pathways.The cooling tower blowdown is a flow of water released from the unit to minimize the buildup of total dissolved solids (TDS)in the circulating water.Sodium hypochlorite is added to the cooling water immediately upstream of the condensers, while sulfuric acid is added immediately downstream of the condensers.

A fraction of the cooling water is continually removed from the system.This cooling tower blowdown is routed to the discharge bay and released to Lake Ontario, as described in Section 3.3.1 and shown on Figure 3.3-1.3.6.1.1.2 Chemicals Processed Through Each System The average and maximum quantities of chemicals added to the circulating water and used for regeneration of makeup demineralizer ion exchange resins are listed in Table 3.3-3.The frequency and purpose of these additions are also indicated in Table 3.3-3.Sulfuric acid and sodium hypochlorite are added to the circulating water system.Sulfuric acid and sodium hydroxide are used for regeneration of makeup water treatment ion exchange resins.3.6-1 Nine Mile Point Unit 2 ER-OLS 3.6.1.1.3 Average and Maximum Concentrations of Natural Materials in Effluent Streams Average and maximum expected concentrations of selected chemicals discharged in the Unit 2 combined discharge (cooling tower ,blowdown, demineralizer regeneration wastewater, and service water bypass)are listed in Table 3.6-1.These elements represent the response of natural lake water constituents to evaporative concentration in the cooling cycle.Trace constituents listed in Table 2.3-13, but not appearing in Table 3.6-1, are conservative and respond in the manner indicated for elements not, subject to inplant additions.

Average and maximum water quality constituent values were calculated using Nine Mile Point regional water quality data (Section 2.3.3).Average water quality parameter concentrations and average cooling tower evaporation rates were used to estimate average effluent values;maximum values of monthly mean water quality concentrations were coupled with maximum evaporation rates to estimate maximum effluent values.Chemicals added to this discharge due to demineralizer regeneration wastes, corrosion of condenser tubing, and biofouling/corrosion control were included in the calculations.

The chemical constituents listed in Table 3.6-1 consist primarily of lake water constituents, concentrated by the evaporative cooling process.Average (202 mg/1)and maximum (266 mg/l)TDS concentrations of ambient intake water taken directly from the fake exceed the 200 mg/1 TDS standard for New York State Class A-Special Waters (discussed in detail in Section 2.3.3).Sodium hypochlorite, sodium hydroxide, and sulfuric acid are added to the plant effluent as a result of additions to the circulating water system and discharges generated during the regeneration of makeup water demineralizer ion exchange resins.In general, the chemical contribution of Unit 2 to the Nine Mile Point regional water quality of Lake Ontario is a minor increase in TDS levels of the receiving waters in the immediate vicinity of the discharge, as discussed in detail in Section 5.5.3.6.1.1.4 Concentration Factor as a Seasonal Basis for Evaporative Cooling Systems The cooling tower is expected to be operated at a yearly average of 1.67 cycles of concentration, based on average monthly concentration factors.The maximum hypothesized monthly concentration factor is 2.23, which may occur during the months of July and August.Seasonally, the concentration factors based on average evaporation rates are 3.6-2 Nine Mile Point.Unit 2 ER-OLS as follows: for the January-March period, 1.48;April-June, 1.76;July-September, 1.85;and October-December, 1.60.3.6.1.1.5 Operating Cycles for Each Waste Treatment System or Discharge The cooling tower blowdown represents a continuous and relatively constant flow waste stream during normal Unit 2 oper'ation.

The average blowdown rate is 950 l/s (15,068 gpm);the minimum blowdown rate, which dictates the maximum chemical concentrations, is 706 1/s (11, 188 gpm).Sodium hypochlorite addition is not constant and depends on the chlorine demand of the circulating water.In addition, the duration and frequency of sodium hypochlorite addition are altered to assure compliance with regulatory requirements of no greater than 0.5.mg/1 maximum free available chlorine for no longer than 2 hr/day.Sulfuric acid additions to the circulating water system are likewise controlled by demand, in this case, alkalinity.

Quantities are not likely to fluctuate to any great degree, due to'the rather narrow range of alkalinity values reported for Lake-Ontario's Nine Mile-Point region (Section 2.3.3).Makeup demineralization wastewaters are generated approximately once per month.During startup, the large additional demand of high-quality wat r necessitates regeneration once a day.The quantities of sodium hydroxide and sulfuric acid per regeneration are listed in Section 3.3.2.3.6.1.2 Discharges to Land: Characteristics and Quantities of Sludges and Proposed Methods of Ultimate Disposal Sludge and sediment accumulated in the cooling tower basin are projected to be removed at 5-yr intervals.

These materials consist of solids including chemicals and biocides, concentrated through the evaporative cooling process and collected in the cooling tower basin.The 5-yr estimated volume-is 1,668 cu m (58,900 cu ft).The sludge will be chemically analyzed, removed, and disposed of offsite in a New York State-licensed disposal facility suitable for wastes of this nature.There are no other planned discharges to land.3.6-3 Nine Mile Point Unit 2 ER-OLS 3.6.1.3 Discharges to Air The natural-draft cooling tower requires 19 to 38 million l/s (40 to 80 million, cfm)of ambient air to dissipate the waste heat from the main condenser in the circulating water system.The airflow rate is dependent on ambient atmospheric conditions and therefore varies throughout the year, reaching a maximum in the winter.The effluents are commonly described as cooling tower drift and visible plumes.3.6.1.3.1 Cooling Tower Drift As the circulating water flows through the fill section of a cooling tower, the action of the falling water over the splash bars creates small water droplets, some of which are entrained in the air flowing through the tower.The size distribution of these droplets is given in Section 5.3.3.1~1.2.Most droplets are between 10 and 600 microns.Those droplets which leave the tower in-the exit airflow are referred to as drift.The drift rate for natural-draft cooling towers varies with the exit airflow.Based on'anufacturers'tandard designs for natural-draft cooling towers, a maximum drift rate of 0.0005 percent of the circulating water flow is assumed.This results in a maximum drift emission rate of about 0.76 1/s (12 gpm).3.6.1.3.2 Evaporation Ambient air induced through a cooling tower becomes heated and moisture-laden as a result of the evaporative cooling process, and a visible plume is formed when the air is discharged from the tower.The frequency of occurrence and extent of the visible plume depend upon meteorological conditions existing at the time and upon the design and physical parameters of the cooling tower.A detailed evaluation of visible plume occurrences is presented in Section 5.3.3.1.1.1.

For a given ambient wet-bulb temperature, an increase in relative humidity of ambient air results in a decrease in total moisture removed by cooling tower exit air and a decrease in the evaporative cooling.Conversely, a decrease in ambient relative humidity results in an increase in cooling tower exit air moisture content and an increase in the evaporative cooling.At the design wet-bulb temperature of 23 C (74 F)and a relative humidity of 50 percent, the increase in moisture content of air in the tower is 0.018 kg (0.039 lb)of water per 0.454 kg (1 lb)of dry air.With ambient relative humidities of 25 and 100 percent, the 3.6-4 Nine Mile Point Unit 2, ER-OLS increases in moisture content are 0'24 and 0.012-kg (0.053 and 0.026 lb)of water per 0.454 kg (1 lb)of dry air, respectively.

The effects of these additional amounts, of moisture added to the atmosphere on ground-level ambient relative humidity are discussed in Section 5.3.3.1.1.5.

3.6.2 Sanitary Waste Treatment The normal sanitary waste flow from Unit 2, based on a normal operating force of 300 people.,and an estimated 124 1/day/person (33 gpd/person), is 37,472 l/day (9,900 gpd)..The maximum flow, based on an estimated maintenance outage work force of 1,500 people, is 187,358 1/day (49,500 gpd).Sanitary wastes from Unit 2 will be treated along with sanitary wastes generated at Unit 1.The combined sanitary waste flows will be treated and monitored to comply with the following State Pollutant Discharge Elimination System (SPDES)permit effluent limitations:

Parameter Limits Settleable solids Total suspended solids 5-day biochemical oxygen demand (BOD>)Chlorine residual pH 0.1 mg/1 maximum daily 25 mg/1 average daily'i'5 mg/1 maximum daily'5 mg/1 average daily'~'5.

mg/1 maximum daily'~ppm maximum daily 6.0-9.0 Fecal coliforms 200 MPN/100 ml-30-day geomet-ric mean 400 MPN/100 ml-7-day geomet-ric mean'Daily average calculated by dividing monthly discharge by number of days in month.'Daily maximum is the maximum discharged in 1 day.3.6-5

-Nine Mile Point Unit 2 ER-OLS 3.6.3 Other Wastes 3.6.3.1 Descriptions of Miscellaneous Wastes Waste streams discussed in this section include filter backwash, storm water, roof drains, nonradioactive plant drains, treated radioactive wastewater, transfer pit drain, and cooling tower sludge.Filter backwash consists of resuspended filtered lake water solids.The quality and quantity of storm water and roof drains are essentially that of incident precipitation.

The nonradioactive plant drains consist.of administration building, service building, and water treatment and demineralizer building floor drains.(Turbine and reactor building drains go to the radwaste treatment system.)Treated radioactive wastewater is composed of drains and reject waters treated for removal of radioactive substances (Section 3.5).The floor drain for the diesel generator building and the transfer pit drain have the potential for contamination with oil.Cooling tower sludge consists of suspended solids retained in the cooling basin.3.6.3.2 Estimates of Waste Quantities to be Disposed and Their Pollutant Concentration at Points of Release The filter backwash generates 0.032 cu m/sec (50 gpm)of wastewater for a 15-min period once every 3 weeks.The suspended solids concentration will vary as a function of the quantity of suspended matter in the lake water filtered to supply the makeup water system.The quantities of storm water and roof drainage vary and are directly dependent upon the storm event that generates them.The design flow is based on a maximum daily (24-hr)rainfall of 12.7 cm (5 in), with a return frequency of 100 yr.Nonradioactive floor drains are discharged to the storm drain system at variable flow rates, dependent upon maintenance and cleaning schedules for the facility.The combined nonradioactive floor drains, storm water, and transfer pit and roof drains are estimated to generate a flow not greater than 14,000 cu m/day (3.7 mgd).Treated radioactive wastewaters are quantified in Section 3.5.The volume of cooling tower sludge generated in 5 yr is estimated to be approximately 1,668 cu m (58,900 cu ft).The cooling tower sludge removal frequency from the cooling tower basin is anticipated to be once every 5 yr.3.6-6 0 N I 284 000 E.L SHORE LINE ATION CENTER INFO M N I 283000 0 N ugIT DIY.K g,XATT 0 0(SYSTEM T gi I~RO 06(E PB UNIT 2 REVETMENT-DITCH TOP EL 263.00'-MAIN STACK 99 6 0 8 TOP/BERM EL 263.00 TOP/BEAM EL 265.00 IDENTIFICATION LEGEND A REACTOR BUILDING 8 TURBINE BUILDING C RADWASTE BUILDING 0 HEATER BAYS E SCREENWELL BUILDING F CONDENSATK STORAGE TANK BLDG G CONTROL BUILDING H NORMAL SW ITCHGEAR BUILDING J ADMIN 1ST RAT ON BUILDING SE AGE T J(TM NT P T+1 RLO CtO O t 1 P/BERM 256.OO'i I Il pAVE PARIU LOT u IIT~~~~03Yu5(gV~XRI)C TOWER AVE pal Lol JI I ytAII TRANSMISSION LINES TOP/BERM EL 2.00 t TAJ L EGENO ORIGINAL GROUNO CONTOUR NEW GROUND CONTOUR FENCE LINE N I 282 000'RCIt 266.C P/BKR 273.G I~~NSM Io LINE I'GRO i)i.hl l Y 11 1<I l RA IL ROAD NOTES I.GRID COORDINATES REFER TO NEW YORK STATE COORDINATE SYSTKM 2.ELEVAT IONS REFER To MEAN SEA LKVEL 3.ORIGINAL CONTOUR INTERVAL-2 FKET<~(itltA~tttt EXIST NG N I 28 I 000~RA ILROAD TOP/EL 27 RM 00 FIGURE 3.1-1 STATION LAYOUT 200 0 200 400 I 100 SCALE IN FEET NIAGARA MOHAWK POWER CORPORATION NINE MlLE POINT-UNIT 2 ENVIRONMENTAL REPORT-OLS

+~,.O 1~-

Nine Mile Point Unit 2 ER-OLS CHAPTER 5 TABLE OF CONTENTS (Cont)Section Title P acae.5.3.3.2.3 5.3;4 Effects of Heat Dissipation Sys-tem Operation on Wildlife References 5.3-44 5.3-49 5.4.1 5.4.1.1 5.4.1.1.1 5.4.1.1.2 5.4.1.1.3 5'.1.2 5.4.1.2.1 5.4.1.2.2 5,.4.1.2'5~4.2 5.4..2.1 5.4.2.2 5'.4.2.3 5.4,.2.3.1 5.4.2.3.2 5.4.3 5.4.3.1 5.4.3.2 5.4.3.3 5.4.4 5.4.4.1 5.4.4.2 5.4.4.3 5.4.4.4 5.4.4.4.1 5.4.4.4.2 5.4.5 5.4.6 RADIOLOGICAL IMPACT FROM ROUTINE OPERATION Exposure, Pathways Exposure of Flora and Fauna Gaseous Pathways Iiquid Pathways Direct Radiation Exposure of Man Gaseous Pathways Liquid Pathways Direct Exposure Radioactivity in the Environment Radioactivity in Surface Waters Radioactivity in Air Radionuclide Concentrations Liquid Effluents Gaseous Effluents Dose Rate Estimates for Biota Other than Man.Doses through Gaseous Pathways Doses-through Liquid Pathways, Direct Radiation Doses Dose Rate Estimates for Man Liquid Pathways Gaseous Pathways Direct Radiation from Facility Annual Population Doses Eighty-Kilometer (Fifty-Mile)

Radius Population Doses Contiguous U.S.Population Doses Summary of Annual Radiation Doses Reference 5.4-1 5.4-1 5.4-1 5.4-1 5.4-2 5.4-2 5.4-2 5,.4-3.5.4-4 5 4-5 5.4-5 5.4-5 5.4-.5 5'4-5'5.4-5 5'.4-..6.5.4-7 5.4-7 5.4-7 5.4-7 5.4-8'.4-8" 5.4-8 5:4-9 5.4-9 5.4-9 5.4-9., 5.4-9 5.4-11 5.5 5.5.'1 5.5.2 5.5.2.1 5.5.2.1.1 NONRADIOLOGICAL WASTE SYSTEM IMPACTS Identification of Nonradiological Effluent Discharges Compliance with Effluent Standar'ds Discharges to Water Cooling System Discharge 5.5-1~5.5-1 5.5-1 5.5-1 5.5-2 Nine Mile Poin't Unit, 2 ER-OLS CHAPTER 5 TABLE OF CONTENTS (Cont)Section 5.5.2.1.2 5.5.2.1.3 5.5.2.1.4 5.5.2.2 5.5.2.3 5'.3 5..1 5.5.3.2 5.5.3.3 5.5.4 5.5.5 5.5.6 5.6 5.6.1 5.6.1.1 5.6.1.2 5.6'.3 5.6.2 5',F 1 5.6.3 5.6.3.1 5.6.3.2 5.6.3.3 5.6.3.4 5.6.4 Title.Treated Sanitary Effluent Storm Water, Roof, and Yard Drainage Floor Drainage Discharges to Air Discharges to Land Impacts Associated with Nonradio-logical Effluent Discharges Discharges to Water Discharges to Air Solid Waste Land Impacts Unavoidable Adverse Impacts Irreversible and Irretrievable Commitment of Resources References TRANSMISSION SYSTEM IMPACTS Terrestrial Impact on Flora Impact on Fauna Right-of-Way Management Aquatic Identification of Operational and Maintenance Activities Associated with Transmission Facilities Transmission System Impacts to Man Land Use Impact Audible Noise from Transmission Lines Means to Reduce Impacts of Trans-mission Systems Maintenance Practices to Reduce Visual Impacts References Pacae 5.5-3 5.5-3 5.5-3 5.5-4 5.5-4 5.5-5 5.5-5 5.5-6 5.5-6 5.5-7 5.5-7 5.5-8 5.6-1 5.6-1 5.6-1., 5.6-1 5.6-3 5.6-6 5.6-6 5.6-6 5.6-6 5.6-7 5.6-7 5.6-8 5.6-10 5.7 5.8 5.8.1 5.8.1.1 5.8.1'5.8.1.3 URANIUM FUEL CYCLE IMPACTS SOCIOECONOMIC IMPACTS Physical Impacts Land Use Impacts Nonradioactive Gaseous Emissions Potential Adverse Impacts Due to Noise 5.7-1 5.8-1 5.8-1 5.8-1 5.8-1 5.8-2 Nine Mile Point Unit 2 ER-OLS fraction of the station water use.Table 3.3-1 details the evaporative losses associated with plant cooling water use (a maximum of 0.871 cu m/sec[13,800 gpm], a minimum of 0.246 cu m/sec[3,900 gpm])and lists service water and fish diversion system maximum, average, and minimum monthly flow rates.Lake Ontario water is used for drinking water supply, indus-trial water supply, agricultural water supply, commercial fishing, sportfishing, swimming, boating, and commercial shipping," as discussed in Section 2.3.2.Unit 2 operation will not impact the availability of drinking, agricultural, and industrial water supplies, considering the low rate of consumption of Lake Ontario water (Section 5.2.1).No impact on swimming, recreational boating, or commercial shipping will occur as a result of Unit 2 operation.

The facility intake structures, located approximately 304.8 m (1,000 ft)offshore and approximately 146.3 m (480 ft)closer to shore than the discharge structure, are well removed'rom any swimming reer'eational use (Section 2.1.3);The intake structures (located at a lesser'depth than the discharge structure) are submerged 3.05 m (10 ft)below the mean low surface water elevation.

Station operation will not change surface water elevations, and no significant al-teration of circulation patterns is expected (Section 5.2.1);thus recreational boating will not be af.-fected by station operation.

Commercial shipping vessels pass no closer than 11.3 km (7 mi)from the intake and dis-charge structures and will not be affected by station operation (Section 2.3.2).Commercial and sportfishing water uses will be minimally af-fected by hydrologic alterations resulting from Unit 2 operation, with impacts restricted, to the dilution zone of the, thermal.plume and localized regions of the intake structures.

Standing stocks of commercially and rec-reationally important species will be subject to insig-nificant alterations, as discussed in detail, in.Sections 5.3.1 and 5'.2.Groundwater Groundwater is used for public and private water supplies by several communities in Oswego County (Section 2.3.2).No other groundwater, use has been identified.

Unit 2 operation wi-ll not affect this water use.No station effluents will be discharged to groundwater.

An ongoing groundwater dewatering program for the reactor containment foundation will produce a minor cone of depression (Section 5.2.1).5.2-3 Nine Mile Point Unit 2 ER-OLS Since all groundwater use occurs upgradient of the site and groundwater discharge onsite is toward the lake, no present or anticipated groundwater uses will be affected by station operation.

5.2.2.2 Analysis of Water Quality Changes and Potential Impacts to Water Use I ake Ontario water uses that are susceptible to impacts resulting from station operation, due to changes.in water quality, include swimming, drinking, agricultural and indus-trial water consumption, commercial fishing, and sportfishing.

As discussed in Sections 5.3 and 5', thermal and chemical releases from Unit 2 become significantly diluted within a defined region, well before the point of withdrawal or use for drinking water, agricultural or indus-trial water supplies, or swimming.Effluent chemical constituents from Unit 2 are largely natural lake constituents concentrated in the circulating water system by a maximum factor of 2.33 and an average fac-tor of 1.67 (Section 3.6.1).Table 3.6-1 lists the concen-trations ,of important water quality parameters at the edge of the dilution zone of the thermal plume and the average concentration in Nine Mile Point regional waters.There is a minor increase of these concentrations at the edge of the dilution zone as a result of station operation.

Extensive additional dilution prior to withdrawal or.in situ use will result in'a negligible impact of plant operation on swimming, drinking, agricultural, and"industrial water uses.Aquatic biota will be subject to impacts of heat, induced flow patterns, and elevated concentrations of water quality constituents in the dilution zone (Sections 5.3'and 5.5).However, as discussed in Section 5.3.2, the dilution zone is an extremely small volume fraction of the.receiving water body, and wastes discharged to this volume will not produce a significant impact on the average standing stock of com-mercially.

and recreationally important fish species.Consequently, there will be no significant impacts to com-mercial or recreational fishing.5.2.2.3 Mitigating Measures Impacts to Lake Ontario water use resulti'ng from the operation of the facility are minimal.Impacts to aquatic biota are mitigated by the fish diversion system (Section 5'.1).Further mitigation of the minor impacts associated with the water use of Unit 2 is, therefore, unwarranted.

5.2-4 Nine Mile Point Unit 2 ER-OLS generally exhibit an initial fright reaction to elevated noise levels, followed by a period of acclimation, depending on the intensity of the noise level and the degree to which it is monotonous or, repetitive'.

Onsite, this reaction will also be related to the noise levels present prior to the commencement of plant operation, since previous con-ditions may reduce the period of acclimation.

The predicted maximum noise level at the property boundary during operation of the plant (including Unit 1 and ambient)ranges from about 32'to 40 dBA (Section 5.8.1.3).During operation of the tower, the intensity and quality of the noise will remain more or less constant.In the presence of these monotonous sounds, the animals are expected to adapt to them and resume their normal patterns of behavior.Consequently, the noise produced by station operation should have no permanent adverse impact on the wildlife in the area.The height and width of the cooling tower present a poten-tial hazard to migratory species of birds.From the base (el 79.3 m[260 ft], 4.3 m (14 ft]above lake level), the tower extends approximately 164.9 m (541 ft)above grade, and its width varies from 136 m (446 ft)at the base to 83.2 m (273 ft)at the top.It will also occasionally produce visible plumes that extend somewhat.below the top of the tower (FSAR Figures 2.3-1 through 2.3-25)~The assess-ment of potential impact, discussed in the following paragraphs, is based on considerations of bird migratory patterns, migratory cues, and meteorology in the Oswego area.Hochbaum states that a bird's eyes are the basic sensory or-gan from which it receives its initial orientation'~~'.

In flight, birds must maintain true spatial orientation.

On clear days with good visibility, orientation is not a problem.However, at night and/or under adverse weather conditions, such as low ceilings with precipitation and/or fog, nocturnally migrating birds may.become spatially disoriented.

Herbert states that for birds to maintain a visual horizon under adverse weather conditions, they are forced to migrate at lower elevations'.

In general, most small birds migrate.at elevations above 152.4 m (500 ft)',.Shadows and lights, such as aircraft warning lights atop tall buildings, television-radio towers, and ceilometers, may spatially disorient birds that normally utilize natural land and water shadows against the horizon as visual cues'.In attempting to orient themselves, birds may seek new visual references and thus orient them-selves to a false horizon.Their flight may then become er-5.3-45 Nine Mile Point Unit 2 ER-OLS ratic and uncontrolled with the discrepant visual and sen-sory cues.Birds may also fly directly into the ground, building, tower guy wires, or other brightly illuminated structures at night because of a complete loss of visual cues.'This may occur when the light source is constant or is a continually rotating beam and completely obliterates any background, causing birds to lose their visual cues to the horizontal.

Major periods of potential bird mortality would be expected to occur during peak periods of nocturnal migration under unfavorable weather conditions, although losses may occur at any time during the year.Studies have shown that most bird losses coincide with overcast, weather conditions, wind shifts due to passing cold fronts, and precipitation and/or fog.Some kills, however, have occurred on clear nights.Guy wires associated with radio and TV towers appear to be responsible for a large percentage of bird mortalities'ome quantitative information is available on bird kills at TV towers and large buildings.

During the 1972 fall season, 561 birds were killed at four TV towers in North Dakota't also has been reported that 576 birds were killed during 1 night at the Washington Monument in Washington, DC'ird collisions with cooling towers have been observed and recorded at the Three Mile Island Nuclear Station on the Susquehanna River near Harrisburg, PA;the Davis/Besse Nu-clear Power Station on the southeast shore of Lake Erie near Port Clinton, OH;and the Beaver Valley Power Station-Unit 1 on the Ohio River.At the Three'ile Island site, 66 bird collisions were reported from July 17, 1973 through May 31, 1975 (predominantly passerines, vireos, kinglets, and warblers).

At the Ohio site, 157 bird casualties were reported during the fall of 1972 and spring and fall of 1973 seasons.It was also reported that, ducks and gulls readily avoided the Davis/Besse tower.At the Beaver Valley site, 27 bird casualties (only passerines) were observed during 9 seasons of monitoring.

The mortality of birds from a nuclear power plant with cooling towers appears small compared to mortality due to other hazards encountered during migration.

For example, migrating game species face an additional hazard during the fall migration period.Throughout New York State, as well as other parts of the country, large numbers of migratory game birds are harvested during annual hunting seasons 5.3-46 Nine Mile Point Unit 2 ER-OLS (Table 2.4-7).The harvest of game birds has not been detrimental to the survival of these species.In assessing the potential impact of the natural-draft cooling tower at, the Unit 2 site, all of the preceding fac-tors must be taken into consideration.

It is anticipated that the majority of the bird mortalities associated with the cooling tower will occur during the spring and fall migration periods, since the Nine Mile Point Station is located in a major flyway'"'.Mortalities will primarily occur when weather conditions are unfavorable, forcing birds to migrate below 152.4 m (500 ft)at night.The potential for mass mortalities at the site is reduced for a number of reasons: The cooling tower associated with the facility is located south of the plant and is lighted in ac-cordance with FAA regulations, using high-intensity white beacons flashing at 40 flashes/minute'.

The tower will occasionally produce visible plumes that extend below the 152.4-m (500-f t)level (Section 5.3.3.1.1.1).

These plumes, by them-selves, are not expected to affect overall ambient visibility.

Also, the height of the tower (164.9 m (541 ft])is well below normal migration levels.2.Along Lake Ontario, the spring and fall migration periods may extend over 2 to 3 months, with peak movements expected over a 6-to 8-week period during the year.The potential for large mor-talities of migratory birds within this period is further reduced by the low frequency of'ccurrence of unfavorable weather conditions.

Data provided by the Rochester weather tapes (1949 to 1958)in-dicate that the total frequency in occurrence of ceilings below 152.4 m (500 ft)with visibility of zero to 1.6 km (1 mi)are 1.3 percent of the time in the spring (March, April, and May)and 0.7 percent of the time in the fall (September, October, and November).

During a 17-day study con-melodia)was killed at the Nine Mile Point meteorological tower and no bird mortalities oc-curred at the stacks'.Lake Ontario, in the vicinity of the site, is moderately used by migratory waterfowl and birds for resting and feeding during migration.

The potential for mortality from waterfowl and hawks 5.3-47 Nine Mile Point Unit 2 ER-Of S (Falconiformes) flying into the cooling tower should be reduced because these birds are most ac-tive diurnally when orientation is generally not a problem.This conclusion is supported in other studies on bird mortality at towers.These studies indicate that, only a small percentage of the birds that are killed are waterfowl or hawks'hen the low frequency of occurrence of ceilings below 152.4 m (500 ft)is combined with the short period of-time of moderate bird migrations (6 to 8 weeks/yr), the potential for mass mortalities at the site is greatly reduced.Some losses of passerine species may occur, even during the day, but these are not expected to be appreciable when compared to other sources of bird mortality occurring from natural and manmade hazards during migration.

5.3-48 Nine Mile Point Vnit 2 ER-OLS TABLE 5A-1 (Cont)Parameter Prima Or anisms Fish Crustaceans Mollusks Al ae~Muskrat.Heron Duck Raccoon Deer Vegetation yield (kg/sq m)Vegetation exposure period (hr)Holdup time-crop exposure to ingestion by deer Effective soil surface density (kg/sq m)Buildup time on soil, tb(hr)crop retention factor particu-lates/iodine Absolute humidity (g/cu m)Fraction of year deer consumes crop C-10 fractional equilibrium ratio: continuous release intermittent release 0 7 6,570.5 0.0 200 1 75+05 0.2 partic-ulates;1.0 iodine 10.3 0 75 1.0 0 073 NOTE: 8 86-09=8.86x10+<<>Edge of mixing xone and nearest shoreline<<>1,603 m (5,259 ft)east c>>Unit 2 stack (continuous)

(+>Unit 2 stack (intermittent) c>>Radwaste/reactor building vent (continuous) 2 of 2

Nine Nile Point Unit 2 ER-OLS TABLE SA-2 (Cont)Incremental Regions<>>km 0 to 10 10 to 20 20 to 30 30 to 40 40 to 50 50 to 60 60 to 70 70 to 80 Approximate Distance From Site to Point of Analysis km 15 25 35 55 65 75 Dilution Factor 738 307 348 404 457 504 548 589~Boa tin 1.5+04 1.5+04 1 5t04 1 5+04 1 5+04 1 5+04 1.5+04 1 5+04 Recreation Shoreline 3 1+05 4.7+05 6.9+04 1 9+05 1 8+04 1 2+04 1 4+05 Population Usage~~eo l~e/~r Transit Time to Point of Analysis~br~15 46 76 107 137 168 199 229 Other Locations<<>

Edge of initial mixing zone<~i Closest accessible shoreline<>>

Approximate Distance From Site to Point of Intake km 15 Dilution Factor 5.9 307 Transit Time to Intake jar 0.0 (assumed)46 NOTE: 1 5+04=1 Sx10i<<aPublic water supply systems used to calculate 80-km (50-mi)radius population doses from ingestion of potable water.<>>Public water supply system used to calculate the dose to the maximum offsite individuals from the ingestion of potable water and irrigated foods.<>>Regions used to calculate 80-km (50-mi)radius population doses from ingestion of fish, boating, shoreline recreation (assumed one-eighth of fish caught in each region), and swimming.<+>Locations used to calculate doses to maximum offsite individuals from ingestion of aquatic foods, and from swimming and boating.<>>Location used to calculate doses to maximum offsite individuals from shoreline recreation.

Closest accessible shoreline-closest occupied beach.2 of 2

Nine Mile Point Unit 2 ER-OLS 6.3 HYDROLOGICAL 6.3.1 Preapplication and/or Preoperational Monitoring Hydrologic measurements to determine the magnitude and direction of currents in the Nine Mile Point vicinity were made off the Nine Mile Point promontory in 1969, 1970, 1976, and 1977.The 1976 and 1977 studies were conducted after both Unit 1 and the James A.FitzPatrick (JAF)plant were operational.

The scope of each study is summarized below;results are provided in Section 2.3.1.Currents were measured continuously from May through October 1969 and from July through October 1970 at two fixed towers placed offshore from the Nine Mile Point site, one in 7-m (24 ft)of water and one in 14 m (46 ft)of water.Hourly current speed and direction were recorded simultaneously from three depths at, each location, utilizing reduced-sized Savonius rotor meters.In addition, drifting drogues were released and tracked during the 1969 study.These studies have been reported by Gunwaldsen et alnd the Power Authority of the State of New York'uring 1976 and 1977, additional postoperational hydrothermal surveys were conducted for the JAF plant'~'.The focus of this study was on thermal plume mapping.Current speed and direction, lake temperature, and lake level were also monitored.

During the two June 1976 surveys, the current was monitored 3 m (10 ft)below the water surface at a fixed tower positioned approximately 610 m (2,000 ft)east and along the same depth contour (9 m[30 ft])of the JAF plant discharge.

During the two August 1976 and October 1976 surveys, currents were monitored at the 3-, 6-, and 9-m (10-, 20-, and 30-ft)depths at.the same location.The first 1977 survey was conducted on April 13 and 14.Three in situ current monitoring locations were established:

one was the same as the 1976 location;the second was approximately 0.8 km (0.5 mi)directly offshore of the JAF plant;and the third was midway between the JAF plant and Unit 1 and 2 sites at the 9-m (30-ft)depth contour (Figure 6.6-1).Currents were monitored at the 4.5-m (15-ft)depth at all three locations during the 2-day April study.Subsequent 1977 surveys were conducted on June 14 with monitoring at the same location and depth.The last survey was conducted on November 2 with current monitoring at a 4.5-m (15-ft)depth at the original station east of the 6.3-1 Nine Mile Point Unit 2 ER-OLS JAF plant, and a second station located 0.8 km (0.5 mi)offshore of the JAF plant'he results of all current measurement programs are summarized in Section 2.3.1.6.3.2 Site Preparation and Construction Monitoring Drainage of the site during construction is provided by two ditches and five storm water lines.One of the'rainage ditches is located at the eastern edge of the site and the other at the western edge of the site, as shown on FSAR Figure 2.4-6.The western ditch drains the majority of the site area, as well as conveying all discharges from the sanitary treatment plant to the lake.Flows in this ditch are measured on a weekly basis by a rectangular weir located at'he discharge outlet.Suspended solids, pH, settleable solids, and oil and grease are also'easured.Monitoring data are reported to the New York State Department of Environmental Conservation i: n accordance with State Pollutant Discharge Elimination Syst: em Permit requirements.

The eastern drainage ditch and the storm water lines handle only runoff and, therefore, are not required to be monitored.

As discussed in FSAR Section 2.5.during construction are monitored located at the reactor building elevation data are collected approxima'tely once every week.piezometers will continue until construction.

4, groundwater levels by four piezometers site.Only groundwater at each piezometer Monitoring by these the completion of 6.3.3 Operational Monitoring Station operation will not affect surface water flow or groundwater; therefore, no operational hydrological-monitoring programs are planned for these parameters.

Sediment transport in Lake Ontario will not be altered;therefore, sediment transport monitoring is not required.6." 3-2 Nine Mile Point Unit, 2 ER-OLS Site 1-1300 hr September 27, 1979 to 1200 hr September 28, 1979 0100 hr September 29, 1979 to 1500 hr September 30, 1979 Site 2-1500 hr September 30, 1979 to 1500 hr October 1, 1979 Site 3-1500 hr September 27, 1979 to 1200 hr September 28, 1979 Site 4-1400 hr September 29, 1979 to 1400 hr September 30, 1979 During the ambient noise-measurement program, the noise-monitoring sites were visited once during the daytime and once during the nighttime hours.At each visit to the primary noise-monitoring sites, the system was switched into the standby mode, and the hourly statistical data (Leq, Lg>, Lzz,.and L>p)stored in the analyzer memory was retrieved and recorded on a data sheet.The B&K system was then set up and calibrated for the hand-held statistical measurements'his method of data collection consisted of using a statistical sampling technigue that provides an accurate description of the short-term variations in the ambient noise environment and a sound level meter to sample the existing A-weighted sound levels in 5-sec intervals.

A series of 50 samples.was generally more than sufficient to provide a statistically reliable sample defining the minimum (L9g)dBA noise levels obtainable at each site.During the 50-sample time period (4 min,.10 sec), all activity in the area was noted and all noise sources were identified.

Each of the 50 instantaneous sound level readings was recorded on a data sheet by a checkmark next.to the correct dBA level.The collected data were later used to determine the appropriate statistical descriptors, such as the L>p, Lz,, Lzz, and Leq levels, which correspond to the residual, average, intrusive, and equivalent levels, respectively.

Residual octave band sound levels were also obtained.The residual octave band sound.level is the minimum repeatable sound level reading obtained in each octave band (63, 125, 250, 500, 1k, 2k, 4k, and 8k Hz)in the absence of any identifiable or intermittent local noise sources, such as passing cars and barking dogs.From the residual octave band data, the residual dBA noise level can be calculated at each site and should agree with the minimum (Lgg)dBA levels obtained by using the hand-held statistical sampling technique.

6.7-5 Nine Mile Point Unit 2 ER-OLS This ambient noise measurement procedure was followed during each visit to the noise-monitoring sites.At the end of each visit, the CNA was recalibrated and switched from the standby mode to the active mode.to begin another noise measurement period.Each site was visited twice daily for a total of four or five ambient noise measurement sessions during the survey.In addition, the NAGRA tape recorder was used to record a 3-min ambient noise sample at each of the nine noise-monitoring sites.These tape recordings were obtained during the nighttime, when the.ambient noise levels were generally lower, so that power plant noise was usually audible at each of the noise-monitoring sites.'hroughout the survey, periodic observations and measurements were made of the meteorological conditions, including-wind speed and dire'ction, wet-bulb and dry-bulb ambient air temperature, and sky conditions'or the entire ambient noise survey, the winds were generally calm, ranging from 0 to 8 km/h (5 mph).This minimized the impact of wind in the trees,'which tends to be a problem when measuring low ambient noise levels.6.7'Seismic Monitoring' There is no preoperational seismic monitoring program planned at the Unit 2 site.However, Niagara Mohawk Power Corporation, in conjunction with other state utilities, is funding a seismic monitoring research program in New York state, as described in FSAR Section 2.5.6.7.3 Air Quality Monitoring Programs The potential sources of gaseous emissions at Unit 2 are two standby diesel generators, one HPCS diesel generator,'ne diesel-driven emergency fire pump, and a natural-draft cooling tower'(NDCT).

The diesel units will burn No.2 fuel oil'0.5 percent su1fur content)and, due to infrequent operation, will emit small amounts'of pollutants (i.e., nitrogen oxides[NOx], sulfur dioxide fSOz], and particulates), as described in Section 3.6.3.4.Criteria-pollutant emi'ssions from these~sources', even" with the addition of the particulate emissions from the NDCT, will not exceed'n emission requirement of 100 tons/yr and.are not considered a major source.'Therefore, the sources are not subject'to prevention of significant deterioration (PSD)or emission offset (EO)regulations.

On this basis,-a post-operational air quality monitoring program is neither necessary nor required by state or federal.regulations for this facility.6.7-6 Nine Mile Point Unit 2 ER-OLS 7A.2 SYSTEMS ANALYSIS In lieu of developing detailed fault trees for safety-related systems, Unit 2 systems are analyzed in the same manner as the GG1 study;that is, system failures are deter-mined by writing the Boolean equation for the system and then substituting failure rate data into the equations to calculate system unavailability.

The same types of failures as analyzed in a fault tree are analyzed in tabular format.These types of failures are: 1.Hardware failures.2.Maintenance outage.3.Valve plugged.4.Testing outage.5.Initiating circuit failure.The following accident cases were chosen for Unit 2: 1.Transient, requiring reactor scram initiated by the loss of offsite power, designated transient Tq.2.Transient requiring reactor scram initiated by the loss of the power conversion system (PCS)or reac-tor scram initiated by other causes (except loss of offsite power)where the PCS is initially available, designated ,transient Tz>.Offsite and/or onsite emergency power is assumed to be available during Tzz.3.Small loss-of-coolant accident (LOCA)where the equivalent leak diameter is less than 34 cm (13.5 in), designated S..In the GG1 study and in the RSS, these cases were the initiating events that mostly contributed to risk;therefore, system unavailabilities are calculated for these cases only.Transients, not LOCAs, strongly dominate the risk in BWRs.The Boolean reduction of the transient and LOCA event trees in this study came directly-from the GG1 study.Large LOCAs were several orders of magnitude less significant than small LOCAs and transients.

7A.2-1 Nine Mile Point Unit 2 ER-OLS The following safety-related systems are analyzed: 1.Reactor protection system (RPS).2.Emergency ac power system (EPS).3.DC power system (DCPS).4.Vapor suppression system (VSS)~5.High-pressure core spray system (HPCS).6.Reactor core isolation cooling system (RCIC).7.Low-pressure core spray system (LPCS).8.Automatic depressurization system (ADS).9.Low-pressure coolant injection system (LPCI).10.Residual heat removal system (RHR).ll.Service water system (SW).A brief system description is presented in the following paragraphs.

Table 7A.2-1 provides a listing of the cal-'ulated system unavailabilities for Unit 2.7A.2.1 Reactor Protection System The RPS consists of two subsystems:

the reactor protection system logic (RPSL)and the control rod drive (CRD)system.The RPSL monitors various plant parameters and systems status and initiates a reactor scram if predetermined values are reached.When a scram is initiated by the RPS, the CRD system inserts negative reactivity necessary to shut down the reactor.Each control rod is individually controlled by a hydraulic control unit (HCU).When a scram signal is received, high-pressure water stored in an accumulator in the HCU or reactor pressure forces the control rod into the core.P Complete descriptions of these subsystems are provided in FSAR Sections 7.1.3 and 3.9.4/4.6, respectively.

7A.2-2 Nine Mile Point Unit.2 ER-OLS TABLE 7A.4-1 CONTAINMENT FAILURE MODE SYMBOLS Containment Failure Modes After Core Melt Containment failure due to RPV steam explosion Containment failure due to containment steam explosion Containment failure due to overpressure from burning of a combustible gas mixture uI Containment failure due to detonation of a combustible gas mixture Y'ontainment isolation failure Containment failure due to wetwell overpressure Containment failure due to drywell overpressure Containment failure due to large leakage Standby gas treatment system (SGTS),failure

Nine Mile Point Unit 2 ER-OIS The final results of the CRAC2 consequence model are displayed as a set of complementary cumulative distribution functions (CCDFs).A CCDF is defined as the probability that the consequences will exceed a given magnitude.

CRAC2 determines the final CCDFs by summing the effects of all trials.A trial is defined as one combination of accident release parameters, weather conditions, and downwind population.

The curves produced from the CRAC2 CCDF output may be then used to evaluate the health and economic risks to the public from a large scale core melt accident in a given region surrounding the plant.Figure 7A.6.1 provides an overall view of the site region.Figure 7A.6-2 shows a schematic of the CRAC2 consequence model.Table 7A.6-2 provides on identification of the sources for the input parameters to CRAC2 for Unit 2.Tables 7A.6-3 through 7A~6-7 provide the CRAC2 input for Unit 2 for the ,isotopes, release parameters, evacuation, population, and meteorological data requirements, respectively.

7A.6.2 Discussion of Health and Economic Impacts The results of CRAC2 computations are presented in Figures 7A~6-3 through 7A.6-7.CCDFs representing acute fatalities, acute injuries, latent fatalities, total whole-body man-Rem, and property damage are provided.Table 7A.6-8 shows the sensitivity of early effects (acute fatalities and injuries), late effects (latent fatalities), and economic effects (property damage)to various parameters.

Acute fatalities are dominated by the high probability of Release Category 2 (Section 7A.5).Release Category 1, although possessing rather rapid timing and a large quantity of released activity is not as consequential a release as Category 2.Release Category 3 has a relatively high probability but a lower amount of released activity.Category 4 is characterized by releases through the SGTS, therefore the activity released is much lower.Category 4 does not contribute to acute fatality consequences.

Acute injuries are dominated by Categories 2 and 3 due to their relatively high probability of occurrence and higher release fractions.

The lower activity magnitude of Release Category 3 is not quite as important for injuries as it is for fatalities because of the lower dose thresholds for Nine Mile Point Unit 2 ER-OLS injuries.Release Category 4 makes a small but essentially negligible contribution to acute injuries.The Oswego County, New York Radiological Emergency Response Plan (RERP)outlines six evacuation scenarios covering the various combinations of season and time of day.No one evacuation model dominated early effects.The difference in early effect consequences among the 6 models differed by no more than 10 percent.Latent fatalities result from lower doses than those that produce acute fatalities.

These are integral effects over large areas and long time periods.According to the Committee of the Biological Effects of Ionizing Radiation (BEIR)', solid tumors may take as long as 30 yr to develop, whereas leukemia can occur within 5 yr.Release Categories 2 and 3 with their higher probabilities of occurrence, dominate the latent fatality CCDFs.Economic impact is assessed in terms of the total cost to all affected property.As with latent fatalities, property damage CCDFs are dominated by Release Categories 2 and 3.The results indicate that the probability of causing$1,000 total costs is about the same as causing$10,000,000 total costs.Therefore, for the accidents postulated herein,$10,000,000 total costs would be a minimum value.Figure 7A.6-6 indicates that the probability of property damages is relatively constant to a total cost of about$10,000,000.

The demography and annual wind rose frequencies for the Unit 2 site are such that approximately 46 percent of the time the wind blows out over Lake Ontario including sectors containing both land and lake.,Therefore, there is roughly 50 percent probability that a release will be blown toward an unpopulated or sparsely populated area.Only 9 percent of the total 80-km (50-mi)regional population resides in sectors which border Lake Ontario, and one-half of these people live beyond 72 km (45 mi)where there is essentially zero risk of fatality.There is little doubt that releases blown in these directions will result in considerably lower health consequences due to the deposition mechanisms and the lack of people liable to exposure.Exposure pathways could result from the ingestion of fish caught from the lake, ingestion of drinking water from the lake, and direct exposure from contaminated beaches and nearshore land.Interdicting these pathways is entirely possible;however, the socioeconomic impact of such action 7A.6-4 Nine Mile Point Unit 2 ER-OLS is difficult to assess.A liquid pathway consequence analysis is not within the scope of this study;however, the economic effect of the loss of drinking water supply and recreational areas would be temporarily felt.Some beaches and recreational areas might suffer permanent closure or abandonment by the public.Commercial fishing does take place on Lake Ontario.However, it is concentrated in the far northeast corner of the lake and does not constitute a major industry.Nearly 90 percent of all fish commercially caught in the lake are landed by Canadian fishermen.

Some of these fish could be temporarily affected by a release from Unit 2.For the Unit 2 site, the CRAC2 results revealed that fatalities would most likely occur within 32 km (20 mi)of the plant and in no case would fatalities occur beyond 72 km (45 mi).Injuries would most likely occur'within 56 km (35 mi)of the plant.Although the risk of injury exists beyond 80 km (50 mi);the probability of occurence is very low.For comparison purposes, the CCDFs for acute and latent fatalities for GG1, Limerick, and PB2 (rebaselined RSS results)have been plotted against the Unit 2 results.These comparisons are shown on Figures 7A.6-8 and 7A.6-9.Because of the uncertainty bands associated with each curve, the CCDFs for acute and latent fatalities for the four plants may be considered consistent.

7A.6.3 Risk Due to External Causes.The foregoing analysis has confined" itself to event sequences generated by inplant failures (with the exception of loss of offsite power).However, the possibility exists that some large external event could initiate an accident or adversely affect the plant's response to an internal initiating event.The Unit 2 plant is not considered singularly vulnerable to external initiators.

It is located in an area of low seismic activity, far away from a large body of seawater, and in an area of relatively low tornado probability.

Therefore, earthquakes, hurricanes, tidal waves, and tornadoes are not expected to be high probability events.Man-made hazards such" as aircraft impact, accidents at nearby industrial or military facilities, and pipeline accidents are not considered viable because the site is located at least 32 km (20 mi)from any major air traffic lane and 64 km (40 mi)from the nearest major airport (Syracuse, New York).Also, there are no large industrial 7A.6-5 Nine Mile Point Unit 2 ER-OLS or military facilities or pipelines near the site.The risk from transportation accidents exists only from dangerous materials on vehicular and rail traffic destined to/from the site itself.There are no major highways or rail lines carrying dangerous materials near the site.Single rail spurs and access roads provide egress routes from the three plants on site including Unit 2.The hazards due to flooding from Lake Ontario, flooding from internal sources, fires, chemical hazards, turbine missile hazards, and sabotage exist at about the same probability as at any U.S.nuclear power plant and are taken into account in the basic design criteria of the plant.The following FSAR sections provide an indepth treatment of these topics: Title Fire Protection Flooding Turbine Missiles Chemical Hazards Security Seismic Design Tornado Design FSAR Section 9.5.1, Appendix 9A 3.4 3.5.1.3 2.2, 6 F 4.4.2, 9'.1 13.6 3.7, 3.8 3.3 Some external events will affect only one accident sequence while some external events will affect all accident sequences.

With external causes taken into account, it is expected that the event-sequence probabilities and hence the release category probabilities will increase slightly.However, because Unit 2 is less than or equal to most U.S.sites with respect to external vulnerability, it is anticipated that external events will not be significant contributors to risk at Unit 2.7A.6.4 Limitations and Sources of Uncertainties 7A.6.4.1 Limitations The following limitations are identified in this study: 1.Following the RSSMAP methodology, full fault trees were not, developed for the Unit 2 systems analysis.7A.6-6 Nine Mile Point Unit 2 EQD TABLE OF CONTENTS Section 2.1 2.2 2.3 2.4 3 3.1 3.2 3.3 4.1 4.1.1 4.1.2 4.1.3 4.2 4.2.1 4.2.2 5 5.1 5.2 Title INTRODUCTION ENVIRONMENTAL CONDITIONS TEMPERATURE, PRESSURE,'AND REL IVE HUMIDITY RADIATION ENVIRONMENT CHEMICAL ENVIRONMENT SPRAY/SUBMERGENCE FUNCTIONAL PERFORMANC REQUIREMENTS SYSTEM LIST SYSTEM/ACCIDENT MA IX POST-ACCIDENT OPE BILITY TIME Q ALIFICATION THODOLOGY HA H ENVIRON NT BOP quipme-Electrical NSSS quipment-Electrical BOP/NS Equipment-Mechanical MILD E ONMENT BOP E ipme t Mild Environment Qua ificatio Program NSS Mild Envir nment alification P gram UALIFICATION DOCUM TATION MASTER LISTS (ML)SYSTEM COMPONENT-EVAL TION WORK (SCEW)SHEET MAINTENANCE/SURVEILLANCE OGRAM Pacae 2-1 2-1 2-2 2-3 2-'4 4-10 5-1 5-1 5-2 6-1 CO 3-13-1P, P 3-1 g 4-1 4-1~(P 4-1 p.4-4.4-6.4-8 4-9 APPEND XES A D P 7-1 SAFETY-RELATED ELECTRICAL EQUIP NT MASTER LIST (ML)SYSTEM COMPONENT EVALUATION WORK (CE SHEETS TEST AND ACCIDENT ENVIRONMENTAL PROF LE SAFETY-RELATED MECHANICAL EQUIPMENT Amendment 16 December 1984 Nine Mile Point Unit 2 EQD LIST OF TABLES Table No.Title 2-1 Harsh Environment Zones 2-2 2-3 3-1 3-2 3-3 5-1 5-2 Mild Environment Zones Mil'd Environment Zones with Special Filters Equipm'ent Inside Containment Subject to'ubmergence, Spray, or Froth Systems List System/Accident Matrix SWEC/GE System Cross Reference Safety-Related Mechanical Equipment Categories EQD Master List.Format System Component Evaluation Work (SCEW)Sheet Parameters IIST OF FIGURES Fi ure No.Title 5-1 EQD System Component Evaluation Work (SCEW)Sheet Format Amendment 16 December 1984 Nine Mile Point Unit 2 EQD SECTION 1 INTRODUCTION The purpose of this document is to establish the methodologies and summarize the results of the,,environmental qualification program for Nine Mile Point Unit 2.The information supports Section 3.11 of the Final Safety Analysis Report (FSAR)and is provided in accordance with 10CFR50.49 and the guidance of Appendix E, NUREG 0588, Interim Staff Position on Environ...ental Qualification of Safety-Related Electrical Equipment, December 1979.Amendmen't 16 December.1984

Nine Mile Point Unit 2 EQD'SECTION 2 ENVIRONMENTAL CONDITIONS The Equipment Qualification Environmental Design Criteria (EQEDC)ocument summarizes the indoor environmental design conditions for normal, abnormal, and'accident conditions.

The scope of the EQEDC is limited to establishing the environmental conditions of temperature, pressure, humidity, and, radiation (beta, gamma, and neutron).Seismic and hydrodynamic loading conditions are not within the scope of this EQEDC.These parameters are the environmental design limits to which safety-related equipment is designed and qualified.

These data have been-=incorporated into safety-related equipment design or procurement specifications to ensure that the proper functional performance of the system or equipment during design mode of operation is adequately demonstrated.

The environmental data for temperature, pressure, humidity, and radiation are defined in the EQEDC for each building zone that contains equipment which requires environmental qualification.

Data are listed for normal operating conditions, abnormal operating conditions, and the accident event that impacts the zone ambient environment.

The harsh environment zones are listed in Table 2-1.Mild environmental zones are listed in Table 2-2.Mild environmental zones with special filters are listed in Table 2-3.2.1 TEMPERATURE, PRESSURE, AND RELATIVE HUMIDITY The plant heating, ventilating, and air conditioning'(HVAC) systems maintain indoor temperature and pressure conditions in QA Category I buildings for all normal operating modes.Minimum, average, and maximum temperatures are defined and listed in the EQEDC.During normal operation relative humidity is not controlled but is limited to specified maximum percentages in areas that are mechanically cooled.Elsewhere, relative humidity is limited only, by the effect of the indoor sensible heat load.Normal conditions are assumed to exist on a continuous basis until an abnormal or accident condition occurs, with the Amendment 16 2-1 December 1984 Nine Mile Point Unit 2 EQD abnormal or accident condition then lasting for the duration listed in the EQEDC.At the conclusion of the abnormal or accident condition duration it is assumed that conditions, except radiation, will return to normal.Abnormal operating conditions are reasonably expected or anticipated deviations from normal conditions, other than accident conditions.

Abnormal operating conditions narc specifically defined in the EQEDC and generally include: the failure of operating equipment, the loss of which does no requi t require immediate plant shutdown;the loss of specific t transformers or all grid connections; the loss of nonsafe y-related HVAC;and plant operation during test conditions.

An accident condition is an unexpected event, occurring during the course of operation, that has been postulated for analytical purposes and has the capability of causing a release of radioactivity to the environs that could endanger public safety if not mitigated.

A main steam line pressure boundary rupture is an example of an accident condition.

The test pressure, durations, and frequencies for containment leak rate testing are as follows: Test Fre uenc Test Pressure.si Containment Preoperational Test (1 time only)40 40 Postoperational Test (3 per 10 yr)The pressurization period is approximately 5 hr, followed y b a 4-hr pressure stabilization period and a minimum test of 24 hr after stabilization.

All other environmental conditions are the normal conditions as listed in the EQEDC.2'RADIATION ENVIRONMENT Integrated radiation environments are specified in terms of rads for gamma and beta radiation.

The gamma values are based on energy deposition in tissue (rads)or exposure in air (roentgen).

However, the corresponding absorbed dose w ic h'would occur in equipment materials (e.g., carbon)when t in expose posed to the environment would differ only sligh ly magnitude.

For equipment qualification testing, the equivalence of 1 rad to 1 roentgen is an appropriate assumption.

The beta environment is stated in terms of a surface air dose'and does not account for any shielding Amendment 16 2-2 December 1984 Nine Mile Point Unit 2 EQD between the airborne or plateout activity and the material of, interest.The total integrated dose equals the normal plus the accident conditions.

Neutron-environments are specified in terms of neutron fluence (neutrons/cm~)

for that portion of the spectrum hl Mev.For normal operating conditions, the radiological environments are specified as, doses integrated over a 40-yr plant life for gamma and beta radiation.

A plant capacity factor of 0.8 is used to develop the integrated doses for all equipment which operates in conjunction with normal reactor operation.

Expected operation time over the 40-yr life of the plant is used to determine integrated doses in the vicinity of other auxiliary systems and equipment, such as fuel handling systems.Radiation dose contributions due to abnormal conditions that are expected during the life of the plant are included in the 40-yr normal operating conditions.

Radiation dose contributions due to abnormal conditions are for the MSIV isolation event resulting from a transient caused by a loss of condenser vacuum, an MSIV closure, or a turbine trip.For accident conditions, accident radiological doses are in addition to normal operational conditions.

The accident dose contribution is determined for the single most limiting accident.Dose profiles as a function of time (t)following the accident are specified.

The actual accident dose that equipment is evaluated against is determined based on the required operation time of the device following an accident.In most cases, the post-LOCA (DBA)environmental conditions will be the basis for the radiological requirements.

Anticipated transients without a scram are also considered.

Accident integrated doses include combined dose contributions from airborne and contained sources and represent the maximum dose for the area specified.

2.3 CHEMICAL ENVIRONMENT Engineered Safety Feature (ESF)systems are designed to perform their safety functions in the temperature, pressure, and humidity conditions described in the EQEDC.Unit 2 does not utilize any chemical additives to the water recirculated by the ECCS during normal or accident conditions.

Amendment 16 2-3 December 1984 Nine Mile Point Unit 2 EQD Reactor Water Limits'hutdown Condition an accident, the containment and, drywell d below 5 percent (by volume)atmospheres are mainta inc hydrogen, as discussed in FSAR Section 6.2.5~reactor (normal operation), suppression pool, Water for the reac or n d ECCS is not chemically fuel storag p ra e ool, RHR system, an ll d b ion exchange systems within in'nhibited and is contro e y io the following normal operating limi'mits: 'Refueling and Fuel Suppression Storage , Pool Water Pool Wate Quality Parameter Conductivity Chlorides (as Cl-)510 mho/cm 925 C 50.5 ppm s3 umho/cm 925 C 60.5 ppm 510 umho/cm 925 C h 50.5 ppm pH 5.3 to 8.6 9 25oC 5.3 to 7.5 925 C 5.3 to 8.6 925 C 51 ppm 55 ppm Total suspended solids'n stations are provided for periodic analysis of ea or water, r fue'suppression pool water to assure comp iance wi limits of the plant technical specifications.

2.4 SPRAY/SUBMERGENCE n a roach for Unit 2 was to locate d flood 1 1 d b 1'th corn onents above postulate oo away from sources of water spray, ere d tions.or ualification under these con i d to h sical constrain s o'bl building arrangements, this is not easi e the plant.in A endix 3C of the FSAR, an evaluation has tes that the reactor an b been performed which demonstrates t a e effects of safely s u h t down when considering the e ec s o ed b one of the spray/submergence.

This is achieve y following:

Amendment 16 December 1984 Nine Mile Point Unit 2 EQD 1.Separation and/or protection of the safety-related components from water sources.2.Qualification of the components for the expected spray/submerged condition.

3.Verification that'omponent failure will not preclude safe shutdown of the reactor.In general, only equipment in the primary containment wet well is subject to submerged conditions.

In addition, electrical cable in the lowest elevations of some buildings may be located below postulated flood levels.In these instances, the equipment is required to be environmentally qualified for its required function under flooded conditions.

Due to the presence of water containing systems in many areas of the plant, and the requirement for piping break/crack postulation in accordance with Standard Review Plans 3.6.1 and 3.6.2, many safety-related electrical components are subject to water spray conditions.

With few exceptions, Class 1E instrumentation, electrical cables, motor-operated and solenoid-operated valves and dampers are qualified to LOCA, steam, and spray environment.

Motors, motor control centers, switchgear, and load centers are drip-proof but are not spray-proof.

When components are not qualified for operation under spray condition, they are separated or protected from water spray if they are required to remain operable to safely shut down the reactor.Table 2-4 identifies equipment inside the containment subject to submergence, spray, or froth during postulated design basis events.Amendment 16 2-5 December 1984

Nine Hile Point Unit 2 CQD TABLE 2-1 iiARSN ENVlRONMENT ZONES 7.one AON17r503 AON17504 AON17r505 ABN19614 AON19615 AON21523 AON24031 ABN2403?ABN24033 ABS175()8 ABS 17509 ABS17510 ABS17511 AOS 19620 AOS24034 ABS24035 AOS24036 HST24044 MS124045 HST26146 HS126147 MSI28948 MST28949 PC1 75101 7.ono PC199112 PC215121 PC240208 PC240600 PC240601 PC240602 PC?40603 PC240604 PC240605 PC240606 PC240607 PC240608 PC240609 PC240610 PC24061 1 PC240612 PC250618 PC250619 PC250620 PC250621 PC250622 PC250623 PC250624 PC25062 7one PC 2r50 6 26 PC250627 PC250628 PC250629 PC250630 PC261207 PC26 1636 PC26 1637 PC261638 PC261639 PC261640 PC261641 PC261642 PC261643 PC261644 PC26 1645 PC261646 PC261647 PC261648 PC261649 PC261650 PC261651 PC279657 PC?79658 7one PC279659 PC280663 PC280664 PC280665 PC287669 PC287670 PC287671 PC287672 PC287673 PC287674 PC289679 PC289680 PC289681 PC289682 PC289683 PC289684 PC289685 PC289686 PC297691 PC297692 PC297693 PC299697 PC299698 PC299699 Zone PC299700 PC303705 PC303706 PC303707 PC306711 PC306712 PC306713 PC328185 SC1 75102 SC1 75103 SC175104 SC175 lOry SC1 75106 SC I 15107 SC1 75108 SC175109 SC175110 SC175111 SC196113 SC196114 SC196115 SC'1 961 16 SC19611/SC196118 7one SC196119 SC1 96120 SC196204 SC215122 SC215123 SC215124 SC215125 SC215127 SC215128 SC21 5129 SC215130 Sc215131 SC215132 SC215205 SC215?06 SC240135 SC240136 SC240137 SC240138 SC240139 SC240140 SC240141 SC240142 SC240143 Zona SC261 14r5 SC261146 SC261147 SC261 149 SC261150 SC261 151 SC261152 SC289155 SC289156 SC?89158 SC289159 SC289160 SC289161 SC289162 SC289163 SC289164 SC289165 SC289 166 SC289167 SC289168 SC289 169 SC289170 SC306172 SC306173 7ane SC306174 SC306175 SC306176 SC306177 SC306178 SC306179 SC306180 SC306181 SC306182 SC306183 SC306184 SC306215 SC328 186 SC328187 SC3?.8189 SC328192 SC328193 SC3?8194 SC328195 SC3?8196 SC328 197 SC3?8199 SC328222 SC353201 Zone SC353202 SG261355 SG261356 Amendment 16 1 of 1 December 1984

Nine Mile Point Unit 2 EQD TABI E 2-2 MIFD ENVIRONMENT ZONES Zone Control Buildin El 215'-0" CB215258 CB215259 CB215305 CB215306 CB215307 El 237'-0" Cable Vault Area Cable Vault Area Cable Vault Area Cable Vault Area Cable Vault Area CB237261 CB237265 CB237266 CB237267 CB237272 CB237273 CB237274 El 261'-0" Cable Vault Area Cable Vault Area Cable Vault Area Cable Vault Area Cable Vault Area Cable Vault Area Cable Vault Area CB2 61275 CB261276 CB261277 CB261279 CB261280 CB261281 CB261282 CB261283 CB261284 CB261286 CB261289 CB261290 CB261292 CB261293 CB261294 CB261295 Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Standby Switchgear Room Amendment 16 1 of 3 December 1984

Nine Mile Point Unit 2 EQD TABLE 2-2 (Cont)Zone El 289'-0" CB289297 CB289298 CB289301 CB289394 CB289395 El 306'-0" Relay Room Relay Room Relay Room Relay Room Relay Room CB306311 CB306312 CB306313 CB306314 CB306315 CB306317 CB306321 Main Control Main Control Main Control Main Control Main Control Main Control Main Control Room Room Room Room Room Room Room El 261'-0" DG2 61330 DG261331 DG261332 DG261333 DG261334 DG261335 El 272'-0" Diesel Generator Rooms Diesel Generator Rooms Diesel Generator Rooms Diesel Generator Rooms Diesel Generator Rooms Diesel Generator Rooms DG272337 DG272338 DG272339 DG272340 DG272341 DG272342 Diesel Diesel Diesel Diesel Diesel Diesel Generator Generator Generator Generator Generator Generator Rooms Rooms Rooms Rooms Rooms Rooms Amendment 16 2 of 3 December 1984 L

Nine Mile Point Unit 2 EQD TABI.E 2-2 (Cont)Zone Electrical Tunnels El 215'-0" Descri tion ET2 15239 ET215240 ET215241 ET215243 ET215244 Service Water Buildin Electrical Electrical Electrical Electrical Electrical Tunnels Tunnels Tunnels Tunnels Tunnels El 224'-0" SW224365 SW224366 El 261'-0" SW261367 SW261368 Service Water Pump Room Service Water Pump Room Service Water Pump Room Service Water Pump Room Amendment 16 3 of 3 December 1984

Nine Mile Point Unit 2 EQD TABLE 2-3 MILD ENVIRONMENT ZONES WITH SPECIAL FILTERS Zone Control Buildin El 289'-0" Descriptions CB289297 CB289298 CB289301 CB289394 El 306'-0" Relay Room Relay Room Relay Room Relay Room CB306311 CB306312 CB306313 CB306314 CB306315 CB306317 Main Control Room Main Control Room Main Control Room Main Control Room Main Control Room Main Control Room Amendment, 16 1 of 1 December 1984

Nine Mile Point Unit 2 EQD TABIE 2-4 WILL BE PROVIDED IN A FUTURE AMENDMENT Amendment 16 1 of 1 , December 1984

Nine Mile Point Unit 2 EQD SECTION 3 FUNCTIONAL PERFORMANCE REQUIREMENTS 3.1 SYSTEM LIST The systems required to mitigate an accident are listed in Table 3-1.This table also lists components/systems that are listed in Table 3.2-1 of the FSAR which have a quality group classification of A, B, or C, or designated either QA Category I or Seismic Category I.3.2 SYSTEM/ACCIDENT MATRIX The system/accident matrix shown in Table 3-2 identifies those systems that are required to respond to accidents which result in harsh environments.

As discussed in Sections 2.1 and 2.2 and the EQEDC, generally only two of the several design basis accidents discussed in FSAR Section 15 and FSAR Appendix 15A are used to define harsh environment, for equipment.

qualification.

These two accidents, loss of coolant accident inside the primary containment and high energy line break outside the containment, envelop all other plant conditions with respect to their effect on the equipment environment.

With few exceptions, all equipment required to function following any accident is qualified for this worst case environment.

For some components, this worst case combination of accident and environmental conditions results in significant qualification problems.In these instances, an evaluation was performed to develop the environmental conditions for the accidents in which these components are required to operate.These conditions then become the basis for their qualification.

Not all systems listed in Table 3-1 include equipment located in harsh environments.

Some components.

listed in Table 3-1 are not required to operate following accident conditions and therefore do not require harsh environment qualification.

Justification for this is given in the notes to Table 3-2.A cross reference of GE and SWEC systems is given in Table 3-3.3.3 POST-ACCIDENT OPERABII ITY TIME Equipment must be qualified for the length of time it is required to perform its safety function and must remain in a Amendment 16 3-1 December 1984 Nine Mile Point Unit 2 EQD safe mode after the function is performed.

The length of time the equipment is required to function following the onset of an accident is its post-accident operability period (PAOP).Equipment can have a PAOP that ranges from a short time period, but not less than 1 hr immediately following the onset of an accident, to 100 days for components requiring operation for an extended period after the onset of an accident.The approach to determine operability times is similar to that used for accident conditions in that the most limiting case is used for environmental qualification.

In most cases, post accident operability time i's based on the accident requiring the longest functional capability.

This is combined with the worst case accident environment, even though a shorter PAOP may be applicable.

The PAOP is indicated in the EQD Master List, Appendix A.Amendment 16 3-2 December 1984 Nine Mile Point Unit 2 EQD TABLE 3-1 SYSTEMS LIST Abbreviation

~S stem ISC CIS RDS SLS NMS/TIP RPS LDS PRM/ARM RHS CSL CSH ICS FHE SSP SFC ADS/SVV IAS SWP GTS EGS Reactor System and Nuclear Boiler Containment Isolation (See Note 1 to Table 3.1-2)Control Rod Drive Standby Liquid Control Neutron Monitoring/Traversing Incore Probe Reactor Protection System Leak Detection (See Note 2 to Table 3.1-2)Process Radiation Monitoring/Area Radiation Monitoring Residual Heat Removal Low Pressure Core Spray High Pressure Core Spray Reactor Core Isolation Cooling Fuel Service, Reactor Vessel, Invessel, Storage, and Refueling Equipment Post-Accident Sampling System Spent Fuel Pool Cooling Automatic Depressurization/Main Steam Safety Relief Instrument Air Service Water Standby Gas Treatment Emergency Diesel Generators (including CSH DG)Amendment, 16 1 of 2 December 1984

Nine Mile Point Unit 2 EQD Abbreviation

~S stem TABLE 3-1 (Cont)EGF EGA CMS GSN HCS HVN ACP DCP RPC RRS CNS DFM DWS TME Diesel Generator Fuel Oil (including CSH DG)Diesel Generator Starting.Air (including CSH DG)Containment Monitoring Nitrogen Inerting Hydrogen Recombiner Control Building Chilled Water Chilled Water-Ventilation Reactor Building Ventilation Diesel Generator Building Ventilation Yard Structures Ventilation Control Building Air Conditioning Auxiliary AC Power System DC Power Systems Reactor Building Polar Crane Redundant Reactivity Control Condensate Makeup/Drawoff Miscellaneous Floor Drains Domestic Water System Turbine Gland Seal and Exhaust Amendment 16 2 of 2 December 1984

Nine Mile Point Unit 2 EQD Accident TABLE 3-2 SYSTEM/ACCIDENT MATRIX FSAR Abbreviation Reference Control Rod Drop Accident Fuel Handling Accident Loss of Coolant Accident (inside primary containment)

High Energy Line Break (ICS/WCS)(outside primary containment)

Main Steam Line Break (outside primary containment)

Feedwater Line Break (outside pr..mary conta.nment)Anticipated Transients Without Scram CRDA FHA LOCA HELB MSLB FWLB ATWS 15.4.9 15.7.4 15.6.5 15.6.4 15.6.4 15.6.6 15.8 Amendment.

16 1 of 5 December 1984

Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)Accident~sstem CZS<1)CRDA X X FHA LOCA HELB MSLB FWLB ATWS ISC X SLS NMS/TIP RPS LDS<2)PRM/ARM X X X CSL CSH ICS FHE'SP SFC IAS ADS/SVV SWP'X X X GTS EGS EGF X'X X Amendment 16 2 of S December 1984

~~

Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)Accident~Sstem EGA CRDA FHA LOCA HELB X X X X MSLB FWLB ATWS CMS GSN X X X X HCS HVK HVN HVR X X X X X X X HVP HVC ACP DCP RPC'4'X X X X'RRS CNS~~'WS'6'ME<<

~Amendment 16 3 of 5 December 1984 A

Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)Notes CIS, primary containment isolation, includes the following systems whose only post-accident function is primary containment isolation (unless, otherwise noted):~Reactor coolant system (also serves an ATWS function)~Reactor water cleanup system (also serves an ATWS function and is part of LDS)~Service air system~Breathing air system~Reactor building closed loop cooling water system~Main steam system (also part of ADS/SVV and LDS)~Feedwater system (also serves an ATWS function)~Containment purge system~Reactor building floor and equipment drain systems (also part of LDS)~Fire protection system~Leakage monitoring system LDS, the leak detection system, includes temperature, flow, and/or level instrumentation, in the following systems: Main steam system Reactor system Reactor core isolation cooling system Reactor building floor and equipment drain systems Residual heat removal system Reactor water cleanup system Amendment 16 4 of 5 December 1984

Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)FHE, which includes fuel service, reactor vessel, invessel, storage, and refueling equipment, performs no post accident function.Selected components are seismically qualified to ensure proper functioning during refueling operations.

Refer to FSAR Section 9.1.RPC, the reactor building polar crane, performs no post accident function.The crane is seismically qualified to prevent failure that could jeopardize safe operation of the reactor and to ensure proper functioning during refueling operations.

Refer to FSAR Section 9.1.One CNS boundary valve is used to prevent bypass leakage in the event of a LOCA inside the primary containment.

DWS and TME require QA Category I components based on special system considerations.

No environmental qualification is required.Amendment 16 5 of 5 December 1984 t

Nine Mile Point Unit 2 EQD TABLE 3-3 SWEC/GE SYSTEM CROSS REFERENCE~sstem Nuclear Boiler Mainsteam Feedwater Automatic Depressurization Recirculation Control Rod Drive Redundant Reactivity Control Standby Liquid Control Neutron Monitoring Process Radiation Monitoring Post Accident Sampling Residual Heat Removal Low-Pressure Core Spray High-Pressure Core Spray Ieak Detection Reactor Core Isolation Cooling Reactor Water Cleanup ISC B22 MSS B22 FWS B22 B22 RCS B35 RDS RRS C12 C22 SLS-C41 NMS C51 D13 SSP D24 E12 CSL E21 CSH LDS ICS E22 E31 E51 WCS G33 SWEC Code GE Code Amendment 16 1 of 1 December 1984 0

Nine Mile Point Unit 2 EQD SECTION 4 QUALIFICATION METHODOLOGY 4.1 HARSH ENVIRONMENT 4.1.1 BOP Equipment-Electrical The methodology established for the equipment qualification program is in accordance with the guidelines provided in NUREG-0588 for Category II plant and consistent with applicable Regulatory Guides and consensus national standards (ANSI and IEEE), and'n compliance with the requirements of 10CFR50.49.

The methodology consists of developing the Equipment Qualification Environmental Design Criteria (EQEDC), which establishes the temperature, pressure, humidity, and radiation dose levels, for normal, abnormal, and accident'onditions.

Post-accident operability time is developed to assure that the equipment will be qualified to maintain a safety function during a post-acciden event.These requirements are specification for the safety The specification mandates accomplished in accordance accordance with the quality 10CFRSO Appendix B.included i'n the procurement related electrical equipment.

that the qualification will be with IEEE 323-1974 and in assurance program referenced in Based on these specification requirements, the equipment manufacturer develops an equipment qualification program.Safety-related equipment is evaluated by comparing the environmental conditions by which equipment operability has been demonstrated with required conditions.

This evaluation includes review for both 40-yr normal and abnormal'environments and accident environments resulting from a spectrum of LOCAs and HELBs.The equipment justification is considered acceptable when it is demonstrated that equipment can perform its required safety function under postulated environmental conditions.

All qualification testing and analysis of safety-related equipment are being evaluated for compliance with Category II NUREG-0588 guidelines.

Equipment testing is reviewed to determine the extent to which it simulates plant conditions and provides sufficient margin.Factors considered during the review of testing include test Amendment 16 4-1 iDecember 1984 Nine Mile Point Unit 2 EQD procedures, test setup, test sequence, margin, and test anomalies.

Supplemental analyses (i.e., beta shielding thermal degradation) are performed, as required, to support qualification.

All analyses based on partial test data are completed using approved methodologies with adequate justification.

Equipment specific analyses are contained in the EQ file along with appropriate justification.

A System Component Evaluation Work (SCEW)'heet is completed for each equipment/component listed on the master list (Appendix A), with the results of the qualification document review, in summarized form.A SCEW sheet with a description of its entries is provided in Section 5.2 of this document.SCEW sheets demonstrate that each required parameter i;s enveloped by the qualified values.Additionally, SCEN sheets provide equipment description, safety function, qualified life, and references of all applicable qualification documents and explanatory notes.Acji~n Aging effects on all safety-related electrical equipment are considered in the EQ program to conform to the requirements of Section 4 of NUREG-0588.

Arrhenius aging aging and is the aging.When justification is methodology is used for accelerated thermal preferred method for evaluating equipment other methods are used, appropriate provided.In the case where accelerated aging was used, the procedure employed considered the expected application and design life of the device being tested.Synergistic effects, where known, are considered in the accelerated aging program.Specifically, where a supplier has identified or is aware of synergistic effects for.,a particular component, it has been addressed.

Appropriate documentation is included in the EQ file.Where required, a maintenance or replacement schedule consistent with qualified life is provided as part of the support documentation and is referenced on the SCEW sheets.When type testing was selected as the qualification method," the type test was run on the device(s)in a specified sequence that was set down as part of the written test procedure.

All sequential testing was performed on the same Amendment 16 4-2 December 1984 Nine Mile Point Unit 2 EQD unit(s), including aging.The sequence given in IEEE 323-1974, Paragraph 6'.2, is generally used.However, other sequences used are justifiable on the basis that.it is severe enough to verify that the device qualified will perform its intended functions within the requirements of the purchase specification before, during, and after a design basis accident.Marcain Qualification type test results were reviewed to verify that adequate margin exists between the most severe specified service conditions for the equipment and the conditions used in type testing.Margins are in addition to any conservatism applied during the derivation of local environmental conditions of the equipment.

Margin accounts for production variations of equipment and inaccuracies.in test instrumentation.

Increased levels of testing, number of test cycles, and test duration are among the methods used for ensuring adequate margin.Some equipment's required by the design to perform its safety function only within the first 10 hr of an.accident.For this equipment in general, a time margin of at least 1 hr in excess of the time assumed in the accident analysis was used.For all other equipment, the 10-percent time margin identified in IEEE 323-1974 was used unless a.reduced amount, could be justified.

Dose Rate and S ner istic Effects Qualification for radiation was based on the calculated total integrated dose.Safety-related electrical equipment qualified for use in a nuclear radiation environment was exposed to radiation which simulated the conservatively calculated integrated dose (normal and accident)that the equipment is expected to withstand prior to completion of its intended safety function.In general, a gamma radiation source, typically C0-60, is used to simulate expected radiation exposures Where beta and gamma radiation exposure is expected, beta radiation is taken into account either during simulated exposure (directly or as a gamma equivalent) or during evaluation of the results.Reduction in the total beta dose was allowed only after considering appropriate shielding factors.If the beta radiation dose contribution to the equipment or component was calculated to be less than 10 percent of the total gamma radiation dose to which the equipment or component had been qualified, then Amendment 16 December 1984 Nine Mile Point Unit 2 EQD the equipment or component was considered qualified for.the beta'nd gamma radiation environment.

The dose rate, energy spectrum, or particle type was addressed to arrive at a gamma equivalent total dose'o which the equipment must be exposed., Actual testing using dose rate, energy spectrum, or particle type as qualification parameters was not considered.

Synergistic effects involving dose rate are not addressed.

However;where synergistic effects of radiation and temperature were identified prior to the initiation of qualification, they are'included in the program.~Anal sis I The use of analysis for qualification is in conformance with 10CFR50.49(f).

4.1.2 NSSS Equipment-Electrical Safety-related electric NSSS equipment located in a harsh environment includes all three categories of 10CFR50.49(b).

A Master List of this equipment is provided in Appendix A.s Category 1, 10CFR50.49(b) equipment is that equipment classified by the NSSS vendor as safety-related in the Master Parts List (MPL).Category 2, 10CFR50.49(b) equipment has been identified through review of the electrical connections for all equipment, classified as nonsafety-related in the MPL.Those items connected to ESF or RPS power without being electrically separated in accordance with Regulatory Guide 1.75 are included in the qualification program'.Category 3, 10CFR50.49(b) equipment has been identified and is included in the qualification program.The approach taken by General Electric to environmentally qualify safety-related equipment within the NSSS Scope of Supply for Unit 2 to a level consistent with NUREG-0588 is described in the GE Licensing Topical Report NEDE-24326-1-P'"'.

This report has been approved by the NRC.The methodology described in this report is consistent with applicable Regulations (lOCFR50 Appendix A), applicable Regulatory Guides, and with applicable consensus national standards (ANSI and IEEE).The work performed under this guidance is controlled in a manner consistent with the commitments contained in the NRC-approved GE Licensing Topical Report on Quality Assurance.

Amendment 16 December 1984 Nine Mile Point Unit 2 EQD The approach to qualification described in NEDE-24326-1-P's predicated on type testing being the preferred approach.Depending upon either the unique characteristics of the specific devices or on the availability of other sources of qualification data, other, approaches such as partial type test with justification by analysis, operating experience, analysis or.combination of the above mentioned approaches may be used.For any of these approaches the eventual approach used is justified in the accompanying qualification report.This justification is based on the demonstrated ability of the product to meet its intende'd safety function.Where type testing is performed, the approach usually taken is as follows: Assure the device conditions as well conditions.

is functional under normal as under extremes.of such 2.Device is aged to an end-of-qualified life condition.

3.Device is subjected to dynamic simulation.

4.Device is subjected to design basis event conditions and post design basis event conditions.

5.Device is inspected for failures which may not have been apparent during the operational te'sting which may-have occurred'uring exposure to an environmental extreme.The specific sequence of tests undertaken during environmental qualification may vary depending upon the function of the device and the nature of the event for which qualification is being de'monstrated.

The associated qualification report contains a justification of the actual sequence used.When a product is tested, where practical, the interface associated with the product is included in the test.The specific sequences of environments applied during the testing are determined, using engineering judgment, to best select the sequence to which the product would be subjected during actual installation.

Furthermore, where synergisms between environments are known, these effects are taken into consideration during the planning and conducting of the test.All tests that are conducted include adequate margins as described in NEDE-24361-1-P'~'.

.Following the completion of the tests all of the associated documentation that led to the test and was generated during Amendment 16 December 1984 Nine Mile Point Unit 2 EQD the test is formally assembled.

into a qualificati'on report.That report is available for NRC audit..For devices not qualified by test (e.g., device's classified as safety-related solely because they perform a pressure boundary function;devices that perform their safety function prior to the onset of harsh environments in which they do not contribute to the mitigation of the event after performance of the intended safety function',=

etc)qualification reports are also prepared demonstrating the adequacy of their qualification.

As with devices qualified by test, these qualification reports are in an auditable form.The last step of qualification i to ensure'that the device tested is similar to the device installed in the field.Therefore, before full qualification can be assured, there is a verification of the similarity between the tested device and the installed device.4.1.3 BOP/NSSS Equipment-Mechanical The Mechanical Equipment Qualification (MEQ)Program provides a documented analysis of the nonmetallic materials, used in safety-related mechanical equipment, to demonstrate that the environmental effects due to plant operation and postulated accidents would not degrade these materials in such a way as to prevent this equipment from performing its required safety function.The MEQ Program details the environmental design conformance review of safety-related mechanical equipment located in'harsh environment.

The conformance review includes nonmetallic subcomponents of mechanical equipment.

Equipment categories included in this review are listed in Table 4-1.Safety-related mechanical equipment inc'luded in the MEQ program is identified in Appendix D.Environmental conditions listed in the EQEDC are used as the basis for the MEQ review.Generally, mechanical equipment has not been shown to be as sensitive to radiation exposure as electrical components; Metallic portions of the equipment are particularly resistant to radiation.

Nonmetallic parts of mechanical equipment,.

while more sensitive to radiation and temperature, are used in the equipment so that the degradation of mechanical properties will not substantially affect the required safety function of the component.

I Amendment 16 December 1984 Nine Mile Point Unit 2 EQD Methodolo The review consists of the following five-step.

process.1.Identification of safety-related mechanical equipment 2.Identification of nonmetallic components 3.Identification of environmental design conditions 4.Identification of nonmetallic material capabilities 5.Evaluation of environmental effects The MEQ Program consists of analyses of safety-related equipment located in systems required for the following functions:

1.Emergency reactor shutdown 2.Emergency core cooling (short-term) 3.Reactor core cooling (long-term post accident)4.Primary containment isolation 5.Containment integrity 6.Prevention of release of radioactive material To accomplish the above functions, complete systems and portions of systems are included in the MEQ Program.Category I mechanical equipment within those systems that are located in a harsh environment, and required for performance of the above functions, are included in the MEQ Program.The review is performed by using the specifications, SWEC drawings, vendor drawings, and manuals.Of the environmental conditions (temperature, pressure, humidity, and radiation) only radiation and temperature were considered in the review.Pressure and humidity were not considered relevant since the design of nonmetallic portions of mechanical equipment for these parameters is governed by system process conditions which have been identified in the specification and addressed by the.equipment manufacturer.

Each material identi f i ed was examined effect of the environmental conditions to determine the on the material Amendment 16 December 1984 Nine Mile Point Unit 2 EQD properties.

For initial screening, it was conservatively chosen to use the threshold radiation level and maximum service temperature.

Materials handbooks, textbooks, and industry and government reports were researched to obtain material data.In some cases vendor data were utilized to supplement the above sources.A conservative initial screening of the~nonmetallic components was made by the comparison of the material capabilities (threshold radiation level and maximum service temperature) with the maximum postulated environmental conditions.

Those items which were not shown to be acceptable based on the comparison were evaluated in further detail considering:

1.Degree of material degradation.

2.Material properties affected.3.Equipment/component function.4.Degree of functional degradation.-

~Acce tance Criteria In order to be considered acceptable, nonmetallic portions of mechanical equipment must either be shown to be acceptable for the plant environment by either of the following:

I 1.Exhibiting threshold radiation values and maximum service temperatures above the maximum.postulated environmental conditions.

2.Demonstrating by engineering analysis of material capabilities and function that the safety function of the component is not compromised.

4.2 MILD ENVIRONMENT Mild environment plant areas are listed in Table 2-2.These areas or zones were selected based on the following guidelines and criteria: 1.Safety-related equipment in these zones is located outside of containment, and is not subject to accident environments due to a LOCA or pipe breaks.2.Environmental conditions:

10CFR50.49, Paragraph c.(iii)defines a mild environment as: An Amendment 16 December 1984 Nine Mile Point Unit 2 EQD environment that would;at no time be significantly more severe than the environment that.would occur during normal plant operation, including anticipated operational occurrences.

Anticipated operational occurrences, as defined in 10CFRSO Appendix A, means those conditions of normal operation which are expected to occur one or more times during the life of the nuclear power unit and include, but are not limited to, loss of power to all recirculation pumps, tripping of the turbine generator set, isolation of the main condenser, and loss of all offsite power.Review of Unit 2 environmental conditions has shown that there is no significant change in environmental conditions, except radiation, in these zones during an accident.The total integrated dose for normal 40-yr service plus 100-days post-accident is less than 10" rads, which is lower than the threshold damage level for organic materials.

Electronic components (in particular, metal oxide semiconductor devices)may have a threshold damage level at somewhat lower doses.Justification for the use of these electronic components in the specified radiation environment shall be provided.Plant zones listed in Table 2;3 are served by the special control room air filters and will not experience any significant increase, in radiation during normal 40-yr service or accident;therefore, the use of electronic equipment in these zones is considered justified.

Equipment located in the zones liste'd in Table 2-2 are not exposed to environmental conditions that may cause common mode failures due to environmental conditions during DBE.Immediate access following a DBE is not required other than normal and periodic maintenance.

Therefore, these plant, zones may be considered mild environment areas.4.2.1 BOP Equipment Mild Environment Qualification Program Safety-related equipment located in a mild environment meeting the following requirements is considered adequately qualified.

A Certificate of Compliance (C of C)stating that the functional requirements of the equipment subjected to the specified Unit 2 environmental conditions have been met.2.The C of C shall identify the supplied equipment by equipment mark number.Amendment 16 December 1984 Nine Mile Point Unit 2 EQD 3.The, equipment has been manufactured in accordance with a quality assurance program that meets the requirements of 10CFR50, Appendix B, and states compliance with 10CFR21.4.2.2 The requirements for any scheduled surveillance, maintenance calibration,, periodic tests, and parts replacements necessary to maintain qualification.

NSSS Mild Environment Qualification Program Safety-related NSSS vendor-supplied equipment that is located in a mild environment is considered qualified if: 1.The equipment manufacturer's design environmental parameters envelop the Unit 2 specific environment.

2.The equipment manufacturer's design functional characteristics envelop the Unit 2 application specific functional performance requirements.

3.The NSSS vendor provides a Product Quality Certification (PQC)in accordance with NEDO 11209'he PQC establishes a tie between the supplied item and the respective equipment drawing which in turn provides further reference to the applicable environmental and functional performance specifications.

Amendment 16 4-10 December 1984 Nine Mile Point Unit 2 EQD TABLE 4-1 SAFETY-RELATED MECHANICAL EQUIPMENT CATEGORIES Air Treatment E ui ment Fans Dampers Air treatment units Hydrogen recombiner Unit coolers Process Fluid S stem E ui ment Pumps Valves-air-and electric-operated, check, relief Heat exchanger Strainer Containment Inte rit and Isolation S stem E ui ment Locks and hatches Isolation valves Penetration seals and gaskets Miscellaneous E i ment Nonmetallics used in ventilation systems Nonmetallics used in process fluid systems Amendment 16 1 of 1 December 1984 I

Nine Mile Point Unit 2 EQD SECTION 5 QUALIFICATION DOCUMENTATION

'5.1 MASTER LISTS (ML)The equipment and components that are within the scope of 10CFR50.49(b) are listed in the ML in Appendix A and are included in the qualification program.This list includes and identifies 10CFR50.49(b) equipment categories 1, 2, and 3.All safety-related equipment added as a result of the TMI action oitems (see FSAR Section 1.10)have been included in the Unit 2 qualification program and qualified as required.The ML includes and identifies the follow'ing:

Equipment/components associated with the systems required to mitigate an accident.listed in Tables 3-1 and 3-2 and located: in harsh environment, Category 1, 10CFR50.49(b), are identified.

2.Nonsafety-related equipment/component connected to safety-related power buses without being electrically separated in accordance with Regulatory Guide 1.75, are under review.If the review identifies such cases they will be included in the Qualification Program and identified in the Master List accordingly.

3.Post-accident monitoring equipment located'in harsh environment, and is specified as Category 1 and 2, Revision 2, Regulatory Guide 1.97, are identified.

An important feature of the ML is its capability to identify all qualification documentation as'sociated with any of the listed safety-related electrical equipment or components through reference to the associated SCEW sheets for that particular equipment or component.

The~identity of any qualification document associated with any of the listed items can be accessed through either the individual equipment identification number, (e.g., 2CSI*FV114)or through a generic equipment manufacturer and model number (e.g., Rosemount 1153B pressure transmitter).

Amendment 16 5-1 December'984 Nine Mile Point Unit 2 EQD Examples of documentation accessible through the MI reference to the SCEW sheets are purchase specifications, vendor records (e.g., test plans and test reports), and SWEC-generated documentation (e.g., aging analyses of mechanical equipment and equipment operability periods).For each device, the ML provides a summary of the key elements of the Environmental Qualification Program.Table 5-1 contains the heading for the ML, with a description of each entry.The first four characters of the device indicate the unit number and the major system in which the device is used.The subsequent characters are used to further segregate the devices by specific type and number.5.2 SYSTEM COMPONENT EVALUATION WORK (SCEW)SHEET The SCEW sheet presents a description of the individual equipment and its location.A comparison is made, in summary, of the actual environmental parameters of the zone specified, with the environmental parameters encompassed in the qualification prcgram.It also contains references to all of the suppor."ive environmental qualification documents which demonstrate that the equipment is qualified to perform its safety function in the postulated environmental conditions.

Reference to the qualification documents that contain detailed supporting information, including test data, can be found listed in the individual equipment or component SCEW sheet.In general, there is a SCEW sheet for every line item on the ML.Some SCEW sheets may consist of more than one page when the individual equipment has components, which are located in different zones or are otherwise qualified separately.

Referenced documents are test reports and other such items that are retained in Supplier's Document Data Form (SDDF)files.Other documents which may be referenced

'are equipment specifications, Equipment Qualification Environmental Design Criteria (EQEDC), and calculations of composite environmental zone profiles, qualified life'and supplemental analyses for equivalent gamma radiation and the post-accident operability period.The SCEW sheet format is shown on Figure 5-1.The description of the entries is given in Table 5-2.SCEW sheets are compiled in Appendix B.Amendment 16 5-2 December 1984 Nine Mile Point Unit 2 EQD Associated with the SCEW sheets are graphs of time dependent environmental parameters, such as temperature and pressure for both specified accident conditions and qualification test conditions.

These profiles of accident and test conditions are compiled in Appendix C and may be used for comparison of the applicable accident conditions and zones to the environment simulated in the qualification test.Amendment 16 5-3 December 1984 lf I I NINE NILE POIHT-UNIT 2 DOCKET NUMBER 50-410 QUAL REF 4 REV'.Figure 5-1 SYSTB CONPONEHT EVALUATIOH NORK SHEET PAGE 1 OF 1 13-Dec-84 as ENVIROHNEHTAL COHDITIONS AND QUALIFICATION a a I EQUIPMENT DESCRIPTION

~<<<<%~~<<~a I DOCUNENT REFERENCE a a'='='='='*====================t I PARANETER I SPECIFIED I QUALIFIED s QUAL)MARGIH)'RENARKS (EQUIP HO.: ISPEC HO.)lSYSTENl a a a a<TYPE((DESCRIPTIOH) a a a a a INANUFACTURER:

a a INODEL NO)t)SAFETY FUNCTIONS a a IOPa CODE)IACCURACY-" SPEC: s DENOl (ZONE NO.l IFLOOD LEVEL t ELEVATIOHt IABOVE FLOOD s LEVEL?IABOVE SPRAY/s FROTH LEVEL?IDOCUNEHTATIOH ACCEPTABILITY:

I VALUE s VALUE I SPECIFIED s QUALIFIED I NETHOD t DEMO a a Cft)I?I CC a'5 21~~a a 1l a a a a a>>a a a a I IOP TINEt 2 s I I IITBP (F)'a I I"" s" I I NOTE I)I NORMAL s 1 I 2 I I NA I NOTE 2 al ABNORMAL(a.1 I 2 I I HA aa ACCIDENT)I a, 1 I'2 l aI I'PRESS(PSIG)

I"----I-----'----t----" I"-"--I---s-HOTE I la HORNAL.I a s 1 I 2 I I NA Il ABHORNALI a I I 2 I HA ls ACCIDENT(a I 1 I 2 a a'IRH (X)'"----'----'----I--"--'-"--I---I-HOTE 1 ts NORNAL I 1 I 2 I HA sl ABNORMAL)a I 1 t 2 I s NA ll ACCIDENT(a)1 I 2 I~, s I a aRADIATIOH'

--"--I-----I-----'-"--I""---I"--s" HOTE I)I HORN GAMMA)s I.1 a 2 HA I II ACC GANMA I 1 t 2 I I It HORN BETA t I t 1 I 2 I I NA II ACC BETA I a 1 s 2 I a a II NEUTRON I I s 1 a 2 a a a ttSPRAY s I HA IISUBNERGEHCEI a a HA I a a Ie<<C a@<<a<<<<>>C~s I I a I I a I I sl OOCUNEHT REFERENCEt NOTES'.FOR CONPLETE EHVIROHNENTAL CONDITIONS,I as 1.EQUIPNEHT QUALIFICATION ENVIRONMEHTAL DESIGH"SEE THE DOCUNENT REFERENCED.

s I CRITERIAe EQEDC 1)REV I)NAY 2)1984 2 NORNAI.TENPERATURES ARE SHONH AS , I I a 2, VEHDOR ENVIRONNEHTAL QUALIFICATION REPORT, NAX DESIGN/AVERAGE.

ls SDDF 4 la 3.EQUIPMENT OPERABILITY TINE DATA SHEET)a a a a Is s NUREG 0588,CATII(a a a a a a a tl a II a a a a a a INAIHT/SURVEILL

--" s REFERENCEs II a (QUALIFIED LIFE---a a I (YEARS)t a REFEREHCE:

It a ls a a a a a a I a a a a a Amendment 16 1 of 1 December 1984 0 ,/

Nine Mile Point Unit 2 EQD SECTION 6 MAINTENANCE/SURVEIjjANCE PROGRAM A preventive maintenance and surveillance program is being developed by NMPC to ensure the continued environmental qualification of equipment, during plant operation.

The objectives of this preventive

~maintenance and surveillance program are and to ensure that'he qualified equipment-will perform its intended function in the environment in which it is expected to operate and to maintain retrievable records.The list of environmentally qualified equipment identifies equipment to be included in the preventive maintenance and surveillance program.The list will be kept current to include mechanical equipment and ensure that equipment added to the plant because of design modifications is incorporated into the qualification program and the preventive maintenance and surveillance program.For each piece of equipment, a preventive maintenance and surveillance program is being developed based on information such as requirements resulting from the equipment qualification report, and Unit 2 plant specific thermal and radiation qualified life calculations, manufacturer's recommendations, previous experience with similar equipment, etc.The qualification specific requirements are identified for each piece of equipment.

The initially developed preventive maintenance and surveillance programs will be modified during plant life if additional information, such as corrective maintenance frequency, surveillance testing, and industry experience (e.g., NRC information notices, circulars or bulletins, manufacturers'lert, TER's, reliability data bases, etc.), identifies any unanticipated degradation trends.In addition, the preventive maintenance and surveillance program identifies the lubricants suitable for each application and environment.

These preventive maintenance and surveillance activities are performed by appropriately qualified personnel using detailed procedures, as necessary.

The plant maintenance program will incorporate the scheduling and documentation of maintenance requirements and activities.

Schedules will identify when equipment.maintenance, replacement, testing, or calibration is required.Appropriate plant departments will complete the Amendment 16 6-1 December 1984 Nine Mile Point Unit 2 EQD work.On completion of scheduled activities, a notification will be made indicating work completion, which will document completion and facilitate rescheduling.

'his scheduling program will be used to alert appropriate plant departments of preventive maintenance, surveillance, and replacement requirements for environmentally qualified equipment.

Quality assurance and control programs will require inspections, verifications, and audits of activities and procedures important to safety.These programs will be performed on environmentally qualified equ'ipment to ensure that schedules, maintenance, procedures, replacements, and documentation are completed in a correct and timely manner.The preventive maintenance and surveillance program will be consistent with NRC requirements and will be implemented at the time of plant heatup.Amendment 16 6-2 December 1984 Nine Mile Point Unit 2 EQD SECTION 7 REFERENCES 1.Equipment Qualification Environmental Design Criteria, (EQEDC), Stone 6 Webster Engineering Corporation, Document No.EQEDC-l, Revision 1, May 2, 1984.2.Title 10, Code of Federal Regulations, Paragraph 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.Federal Register, Vol.48, No.15.January 21, 1983.3.Regulatory Guide 1.75, Physical Independence of Electric Systems, Revision 2, September 1978.4.Shirley, N.C.et al.General Electric Qualification Program, Licensing Topical Report, NEDE-,24326-1-P, January 1983.5.General Electric Nuclear Energy Business Group, BWR Qualizy Assuranc Program, NED0-11209-04A, March 1978.6.NUREG-0588, Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment.

7.IEEE Standard 323-1974, IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations.8.U.S.Nuclear Regulatory Commission Standard Review Plan, NUREG-0800.

9.10CFR50, Appendix B.10.10CFR21.Amendment 16 7-1 December 1984 0

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+ZCCPwtlOVZ65

+iZCCP+!!GV273 ZCCPwtfGV93A ZCCP+!fGV93B c,CCP+l'lGV94A ZCCP>'.lQV9>R P304R P304R P30QR P3QQR P30<R P30cf R P304R P30>>R P30>>R P304R P3GQR P35QR P30clR P30QR P30qR P3CtlR P304R C071!f C071H ZCNE ABH1750%ABS17509 AB!ll 755/ABS17509 PCZ%0612 SCZtl0135 SC215122 SC215122 SC261145 SC261105 PC2616%9 PC2616ctl SC261105 SC261105 SC215122 SC215122 SC261145 SC2611>>>>5 SC2%0135 PCZ50630 SC2611i5 SC2611q5 PC261609 PC2616Q1 SCZ61145 SCZ>>>>0135 ZX%REF H H H H H H H H H H H H H H H H H H H H H H H H H H OPCOD A A A A A A A A A A A A A A A k A A A A A A A A CPT 100 DYS 100 OYS 100 DYS 100 OYS 100 DYS 100 OYS 100 OYS 100 DYS 100 DYS 100 DYS 100 DYS 1GO DYS 100 OYS 100 DYS 100 DYS 100 OYS 100 DYS 100 DYS 100 DYS 100 OYS 100 DYS 1,00 DYS 1CO DYS 100 DYS+=Regulatory Guide 1.97.

PAGE 3 EQUXPHKHT ID ZCES<RAK105 ZCES~RAK106 CeS<WAK107 ZCKSaRAK108 ZCESi'RA)(109 ZCES+RAK231 ZCESwRAK232 ZCKS<Z01E DESCRIPTION IhSTRUtlEHT RACK XhSTRUHENT RACK XNSTRL4l:-NT RACK IHSTRB(EilT RACK IHSTRL".(KNT RACh Xt(ST(((2(Ei(T RACK Xt(STRL(KKHT RACK PENETRATXCN NEUTRON HiQH (B)VENGCR NAKE tlERCURY CO.t t ERCVR Y CO.tlERCURY CO.HERCURY CO.HERCURY CO.tlERCURY CO.HeRCURY CO CGiiAX CORP SPEC C051P C051P C051P C051P C051P C061P C061P E021P ZONE SC261145 SC261145 SC261 45 SCc89155 SCZ89155 l(STZ8949 HSTZ8949 PC250621 ZI GREF H H H H H H H H GPCOO GPT ZCESRZOZE ZCESvZ06E ZCESxZ08E ZCESKZ10E ZCESwZ11E ZCESwZXZE ZCESxZX7E ZCESNZ18E ZCES<ZX9E ZCESvcZZOK ZCKSxZZXE ZCES>ZZZE ZCES~Z23E ZCESwZ24E ZCESAZ25E ZCESKZ26E ZCES<Z29K ZCKSNZ30K ZCES+Z5)E PENETRATION HEUTRCN t(GN (B)PEHETRATIOli iNSTR (G)PEtiETRATIGN COiiTRGL (G)PENETRATXGN CONTROL (G)PEiN-TRATION iNEUTRON tlG l (G)PENETRATIGH NEUTRON HO,I (G)PENKTRATIOH RPS CONTROL (Y)CONAX CORP CGiNAX CORP COiiA'(CORP CGNAX CORP CGNAX CORP COt(AX CORP CO)iAX CORP PENETRATIO.'l COitTRGL (Y)PEHETRATXON CCNTROL (Y)PEHKTRATXGN 600V POKER (Y)P c HETR AT I ON XhSTR (H)PENETRATICH NEUTRON HON (Y)PEH TRATIGH NEUTRON t G<t (Y)PENETRATION CONTROL (Y)PENETRATXGil RPS CONTROL (Y)PENETRATION NEUTRON tlOil (0)PENETRATXGN HKUTRGN HON (0)PENETRATIGH RPS COitTROL (B)CONAX CORP COtiAX CORP CGNAX CORP CGNAX CORP CGNAX CORP COtiAX CORP CONAX CORP CONAX CORP CGNAX CORP CGNAX CORP CONAX CORP PEHETR PGHKR CONT&INSTR (Y)CCNAX CORP E021P PCZ40603 H E021P PC240603 H E021P PCc40603 H E021P PC240603 H E021P PC2506c.5 H E021P PC240607 H E021P PC250627 H E021P PC240609 H EOZiP PC~50627 H E021P PC240609 H EOZlP PC250627 H E021P PC240609 H E021P PCZ50627 H E021P PC240609 H E021P PC250527 H E021P PCi.40609 H E021P PCc.50630 H E021P PCc.40612 H E021P PC240601 H PAGE 0 EG'JIPllENT ID ZCKS>>Z52E 2CES>>Z53E ZCES>>Z54E ZCES>>Z57E ZCES<Z58E ZCES>>Z59E 2CES-Z03E c,CES ZONK c.CKS-Z13K ZCKS-ZlQK 2CES-Z15E 2CES-Z16E ZCES-Z27E ZCES ZZOK ZCES-Z31E 2CES-Z32E 2CKS-Z33E ZCKS-Z3QE 2CES-Z355 ZCKS-Z36E 2CES-Z37E ZCES-Z38E 2CES-Z39E ZCES-ZQOE DKSCRIPTXO".l PENETRATXGN RPS CONTROL (G)PENETRATION HPCS CCiNTROL (P)VENDOR NAHK CONAX CCRP CONAX CCRP PEh TRATICN RPIS INSTR (N)PEiNKTRATIGil RPXS IhSTR (N)P EhETRAT ION RP XS XNSTR (N)PENETRATION RPIS INSTR (N)PENETRATXOli RPIS INSTR (N)PENETRATION RPIS IHSTR (H)P~NcTRATION RPIS INSTR (H)PEiNETRATXON RPXS INSTR (N)PENETRATION 600V PCHER (N)PENKTRATICH 600V POiiZR (H)PEtiKTRATIGN CONTROL (N)PENETRATION CONTROL (tl)PENETQAT C"l INSTR (N)PFNKTRATION INSTR (N)PEiiETRATXON CONTROL'(N)PENETRATICN COiiTROL (H)PEhETRATXCN INSTR (N)PENKTRATXON CC.'lTROL (N)CGiNAX CORP CC:lAX CORP CGNAX COicP CGNAX CORP COr(AX CORP PKNETRATICN HPCS CCNTROL (0)CCiNAX CORP PKNETR F"HKR CO'NT 2, IhSTR (G)PEhFTR POHER CGiNT 8 XiNSTR (Y)COiNAX CCRP PENETR POHER CChT 8 IhSTR (Y)COiNAX CCRP SPEC E021P ZCNE PC250623 ZI OREF E021P PC261609 H 0"1P PC"506~0 H E021P PCc,151Z1 H E021P PC215121 H 021P PC2151Z1 H KOc.lP P C250621 H E021P PCZC0603 H E021P PCZ50625 H EOZIP PCZQ0607 H E021P PC250627 H E021P PCZO0609 H E021P PC250630 H EOc,lP PCZQ0612 H E021P PCZ616%1 H E021P PCZ61601 H E021P PC261601 H EOZ1P PC261601 H E021P PC261601 H E021P PC261641 H E021P PC261601 H K021P PC261601 H E021P PCZ616cll H E021P P C261601 H OPCOD GPT PAGE'EQUIFHKNT ID 2CES-Z40E ZCES-Z41E ZCES-Z42E ZCES-Z43E 2CES-Z44E 2CES-Z45E ZCES-Z46E ZCES-Z47E ZCKS-Z40E ZCES-Z49E 2CES-ZSOE ZCES-Z55E 2CES-Z56E ZCES-Z60E DESCRIPTION PEHETRATIOH CONTROL (N)PEHETRATIOiH COHTROL (N)PENETRATION IHSTR (H)PENETRATION CONTROL (H)PENETRATION INSTR (H)PENETRATIOH 13.8 HV (H)PENETRATIOH 13.8 HV (H)PENETRATION 600V POHER (H)PENETRATION UNASSIGNED PEHETRATIOH 600V FOHER (N)PENETRATION UNASSIGNED PENETRATION 600V FOHER (H)VENDOR HAHE CCNAX CORP COHAX CORP P EHETRATIOH UhSIGNED PENETR POHER CONT 4 INSTR (H)CONAX CORP SPEC ZONE~ZI%REF E021P PC261641 H E021P FC261649 H E021P PC261649 H E021P PC261649 H EOZlP PC261649 H E021P PC261649 H E021P PC261649 H E021P PC261641 H E021P PC261644 H E021P PC261649 H E021P PC261649 H E021P PC261641 H E021P PCZ15121 H EO ZIP PC215121 H OFCOD OPT A PAGE , 6 EGUIPHENT ID ZCt S<<CAB)OA ZCHS<<CAB)08 ZCHS4ALT))A

+2CHS>>LTl)B LUCIS>>LT9A

+CCIIS<<LT98 ZDS>>P hl.66A ZCHS>>PtiL668

+ZCPS<<PT)A+ZCHS>>PT)B+ZCHS<<PT2A+ZCVSvPTc.B

+ZCt!S>>PT7A

+ZVS<<PT78 2CHS<<SOVZ3A ZCES>>SOV238 ZCHS<<SOV23C 2CHS<<SOV23D ZCtlS>>SOV23E ZCHS<<SOV23F

+ZCtS<<SOV24A

+ZCt!SvSOV248

+2CHS<<SOV24C

+2CtS<<SOV240

'2Ct S>>SOVZSA ZCHS<<SOVZ58 ZCIS<<SOV25C ZCt S>>SOV25D+2CHS>>SOV26A

+ZCHSvSOV268

+-ZCKS>>SOV26D

+ZCltS>>SOV32A

+2CVS<<SOV3ZB

+2CHS>>SOV33A

+ZCHS>>SOV338

+'ZCHS<<SOV34A

+ZCt!S>>SOV348

+ZCHSvSOV35A

+2CI!S>>SOV358

+ZCHS>>SOV60A

+2CVIS>>SOV608

+.ZCHS>>SOV6)A

+ZCHS>>SOV618

+'c.Ct IS>>SOV62A+2CHS<<SOV628

+iZCIS>>SCV63A

+2CIS>>SOV638 DESCRIPTION CONTIIT ATH LEAKAGE RADN CONTIIT ATtl LEAKAGE RADN SUPPRESSION POOL LEVEL SUPPRESSION POOL LEVEL SUPPRESSICN POOL LEVEL SUPPRESSIO'I POOI LEVEL H.Z ANALYZER PNL A H.2 ANALYZER PNL 8 COi'ITAINI IENT DRYHELL PRESS CO'iiTAINIIENT DRYIIELL PRESS CONTAINHEtlT DRYHELL PRESS CONTAINHEiNT DRYHELL PRESS SUPPRESSION CHAISER PRESS SUPPRESSION CHAHBER PRESS DRYHELL AIR SAIPLE DRYHELL AIR SAHPLE DRYilKLL AIR SAtPLE DRYHELL AIR SAtPLE CRYHELL AIR SAIPLE DRYHELL AIR SAIPLE DHAIR CIPL INBD ISOL CHAIR SIPL IhoD ISCL DH AIR SIPL OUTBD ISOL DH AIR SIPL OUTBD ISOL SUPP CHt!8 AIR SAIPLE SUPP CHIS AIR SAtPLE SUPP CHHB AIR SAtPLE SUPP CHHB AIR SAtPLE SUPP CHt!8 AIR StPL INBD ZSO SI!PP CHIIB AIR SVIPL ZN BD ISO SUPP CHHB AIR SHPL OUTBD ISO DRYIIELL SIPL RTN OUTBD ISOL DRYHELL<SIPL RTN CUTBD ZSOL DRYHELLt SIPL RTN INBD ISOL DRYKELI StPL RTH INBD ZSOL SUPP CHHB StPL RTN IhBD ISOL SUPP CHI!8 SV<PL RTN IhBD ISCL SUPP CHIIB SIPL RTN OUTBD ISOL SUPP CHIS SIPL RTN ZNBD ISOL DH RADN CUTBD Zt>>ET ISOL DH RADN CUTDD INLET ZSOL DH RADN INBD INLET ZSOL DH RADN ZNSD INLET ISOL DH RADN OUTBD Olfii.ET ISOL DH RADN OUTBD OUTLET ISOL DH RADN INBD OUTLET ISCL DH RADN INBD OUTLET ISOI.VENDOR NAHK KAV~c INSTH~!AN INSTH ROSEHOUNT ROSEViCUiNT ROSEHOUNT ROSEROUNT COtlSZP INC.CC'SIP IKC.ROSEt!CUNT ROSEHCUNT ROSEt tOUNT ROSEHOUiiT ROSEt!0 JNT TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET RCCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET RCCK CORP TARGET ROCH CORP TARGET ROCK CORP TARGKT ROCK CCRP TARGET RCCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET RCCK CORP TARGET ROCK CORP TARGET ROCK CORP TA'RGET RCCK CCRP TARGET ROCR CORP TARGET ROCK CORo TARGET ROCR CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CCRP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP C071H C07)H C07)H C07)H C001C C001C C07)H C07)H C071H C071H C071H C07)H P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X P304X SC)75102 SC)75105 SC175102 SC)75102 ABN24033 ABS24036 SC289155 SC269155 SC261145 SCZ61145 SC240135 SC261145 PC289680 PC289681 PC4289680 PC289680 PC289680 PC289660 PC28968)PC269681 SC289155 SC289155 PCZ)5121 PC21512)PCZ)5121 PC215121 PC215121 PCZ)5121 SC215122 SC261145 SC 261145 PCZ61644 PC261649 PCZ)5121 PCZ)512)SC215122 P304X SC215122 P304X SC289155 P304X SC306175 P304X PC306713 P304X P304X P304X P304X P304X PC306713 SC289155 SC261145 PC261644 PC261649 SPEC ZONE PZB)F SC289155 P28)F SC289155 ZI TREF H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H.H H H H H H H H H H OPCOD A A A A A A A A A A A A A A A A A A A CPT 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 6 6 6 6 6 6 6 6 DAY DAY OAY DAY DAY OAY DAY DAY DAY DAY DAY DAY DAY DAY DAY DAY DYS DYS DYS DYS DYS DYS DYS DYS DYS HRS HRS HRS HRS HRS HRS HRS HRS+=Regulatory Guide 1.97.

PAGE 7 EWJIPIIEHT XD ZCIISvSCV64A ZCHSKSOV648 ZCIIS<<SQV65A ZCHS<cSGV74A ZCI IS<'SQV74B ZCI!S<SOV7SA ZCllS<<SGV75B ZCI!SccSQV76A ZCIIS<'SOV76B ZCHS<cSOV77A ZCIIS<<SOV778

+ZCIIS cc TE 102+c.Cf tS<'<TE 103+~>>CIISccTE104

+ZCIIS<c TE105+>>".Cf!S x TE106+ZC!IS<<TE107+'ZCISccTE108

+>>.Ct IS<t TE1 09+ZCIS<<TEXI6

+>>iCIIS<cTE117

+ZCtlS>TE118

+ZCIISsTE119

+ZCHS<tTE120

+ZCI IS<<TE121+CCHS<TE122+>>>>Ct IS<<TE123+ZCHS<cTE124 ZCIIS<<TESOA ZCIIS<<TESOB ZCIIS<fTESOC ZCIIS)cTESOD ZCIISccTE51A ZCtIS<<TE51B 2CI IS<<T ESXC ZCIISc<TE510 ZCIIS<<TESZA ZCt$<TESZB ZCHSv<TESZC ZCHS<cTESZD ZCIIS<TE53A cCtIS<<TE530 c,CIIS<cTE53C C,CI!S<ETE53D ZCIIS>lTE54A ZCIIS<TE54B ZCHS<cTE54C 2CMS*TE101 DESCRXPTXCH Hc/0?ANALYZER XN XSOL HZ/02 ANALYZER XHL XSOL HZ/02 ANALYZER OUT XSGL PAS SAIIPLE A LOOP PAS SAHPLE-0 LOOP PAS SAIIPLE-A LCQP PAS SAtFLE-B LCQP FOST LOCA SA!!PL SUCT ISCL V POST LOCA SAH!<PL SUCT XSQL V PCST LOCA S'I!PL RTH ISCL V POST LOCA SAHPL PTN XSCL V DRYKELL AREA TEIIP DRYItELL AREA TEtfP DRYHELL AREA TEIIP DRYhELL AREA TEI!?DRYhELL AREA TEt!P SUPP CHAt!BER AREA TEf!P SUPP CHA't!BER AREA TEt!P SUPP CHAi'!BER AREA TEt!P DRYHELL ARc":A TEt!P DRYHELL AREA TEI!P DRYhELL A'QEA TEt!P DRYflELL AREA TEIIP DRYHELL AREA TEIL DRYhELL AQEA TEt!P SUPP CHAI!BER AREA TEf!P SU?P CHANGER AREA TEKP SUPP CHA!!BER AREA TEI!P SUPPR POCL HATER TEIIP SUFPP.POOL HATER TEt!P SUPPR POOL hATER T I!P SUPPR POOL ltATER TBIP SUFPR PCQL hATER TEIP SUPPR PQQL HATER TEfP SUPPR PCCL!INTER TBIP SUPFR PCCL HATER TEI!F SUrPR FCQL HATER TB!P SUPFR POOL NATc:R TEIP SUPPR FCQL HATER TEIL SbrPR POCL HATER TEIIP S<JPP PCCL hATER TEI!P SUPP PCCL HATER TEI!P SUPP PCQL HATER TEILo SUPP POCL HATER TEI!P SUPP PCQ'ATER TEHP SL<rPP POOL fiATER TEI!P SUPP PC L HATER TEHP DRYWELL AREA TEMP TARGET TARGET TAPGE<TAr<GET TARGET TARGET TARGET TARGET TARGET TARGET TARGET PYCO PYCO PYCO PYCO PYCO PYCQ PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO P YiCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO FYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYiO PYCO ROCK CCRP ROCK CCRP ROCK CORP RG K ROCK ROCK ROCK ROCK ROCK POCK Ri>>CK VENDOR NAKE SPEC P304X P304X P304X P304n P304X P304X P304X P304X P304X P304X P304X CO41D C041D CC410 C041D C041D C0410 C041D C0410 C0410 C041D C041D C0410 C0410 C0410 C041D C0410 C041D C0410 C0410 CO41D C041D CO>>10 C0410 CO>>0 C0410 CO410 C0410 C041D C0410 C041D CC410 CO/10 C0410 ,C 0410 C0410 C0410 C041D ZONE ABttc.403'3 AB S c.>>03 6 ADNZ4033 SC240135 SC245135 SC"40135 SC2>>0135 SCZ40135 SC240135 SC240135 SC" 40135 PC<289681 PCZ51641 PC261649 PC250619 PC c.40612 SC215122 PC215121 PC215121 PC306713 PC269681 PC261649 PCZ61638 PC250625 FCZ>>0603 SCc.1512?PC2151 1 PC215121 SC196113 SC195113 SC196113 SC196113 SC196113 SC196113 SC196113 SC196113 SC195113 SC196113 SC196113 SC196113 SC195116 SC196116 SC195116 SC195116 SC195116 SC196116 SC196116 PC3067 ZI H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H 13 H I!REF OP COD A A A A A A A A A A A CPT 100 0YS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS+=REGULATORY GUIDE 1.97.

PAGE 8 EQ)Ict.ENT XD ZCt!StTK5%0 ZC2iSxTE55A ZCI!Si'TE5cB ZCI!Si'TESSC ZCISiiTE559 ZC"cvTK"5A ZCtISi'TE55B ZCI!S>TE56C ZCIISvTE560 2CtIS>TE57A ZCIISwTE57B ZC!ISwTE57C i.Ct IS)s TE57 0 ZCIIStTE58A ZCIIS<TE58B ZCIISiiTE58 ZCIIS~TE589 ZCIIS<TE59A ZCIIS~TK599 ZCI!SiiTES9C ZCIISaTE590

+ZCHS~TE67A

+ZCI!SwTE67B

+ettlS<TE68A

+ZCtlSi TK58B+ZCIIS<TK59A

+ZCIISiiTE69B

+<<CtIS+TE70A

+ZCHSwTE70B DESCRIPTIOH SUPP FOCL HATER TEtP S'L'PP FQQL HATER TFIP SUPP PQQL hATER TEiP S"i"P POQ'ATER TEtP SUPP FOOL HATcR TEt!P SUPP PCQL HATER TEI!P SUPP PQQL hATER TctP SU"P FQCL HATER TEIP SU?P PQQL HATER TEt!P SL'FP FQCL V!ATER TEi SUPP FQQL HATER TEIP SU?i".PQ L H"TER TEIP SUPP PCQL HATER TEIP SUPP PGQL HATER TE!P SUPP POOL I;ATER TEIP SUPP POQL HATER TEtP SucP PQCL hATER TEIP SUF?PQQL HATER TEtP SUPP PGQ'L HATER TEtP SUPP PQQ'ATER TEtP SUrP PQQL HATEiR TEt!P SUPP FQCL IIATER TEIIP SUPP PCQL HATER TEtP SUPP FQQL HATKR TEtP SUPP PQQL IIATER TEIP SUPP PQQL HATER TEIP SUPP PGQL VATER TEtP SUPP POOL HATFR TE'IP SUPP PQQL HATER TEIIP VEHDQR HAH" PYCO PYCO PYCO PYCO F YCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO P CQ PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCO PYCQ PYCO PYCO SAEC COR10 COQID CO%10 CO%10 CO:I10 CO%ID C0410 CO%ID C0 F10 C0410 CO%ID CO%10 COi10 CO%10 C3010 CO%10 Cceio CO%ID CO%10 CO%10 CO%ID C0019 CO%ID CO~ID C0410 CO%ID C04 0 CO%19 CO%10 ZONK 5C195116 SCI96116 SC196116 SC195116 SC196116 SC196116 SC196116 SC 195116 SC196116 SC196116 SC195116 SC196116 SC196116 SC196113 SC195113 SC196113 SC196113 SC195113 SC196113 SC196113 SC196113 PC215121 PC215121 PC215121 FC215121 PC215121 PCZ15121 SC215122 SC215122 Zi TREF H H H H H H H H H H H H H N H H H H H tl H H H Hi H H H 0?COD QPT+=Regulatory Guide 1,97, PAGE 9 EQUIP))EHT ZO 2CPSVAOV104 ZCPS vAOV105+ZCPS>AOV106

+ZCPSiik V107+ZCPS))AOV108

+ZCPSi!AOVX09

+ZCPSi!ACV110

+ZCPSgAOV111

+ZCPS>SOV119

+ZCPS>SQV120

+.ZCPci!SCV121

+'ZCi"SxSCVIZZ DESCRZPTZCH 2CPS-FHl DH Ihl.CUTBD V ZC?S-FHZ SUPPR XNL OUTGO V ZCPS-FN1 GH X!HL ZhSO V ZCPS-FN1 SUPPR Xhl XNSD V DRYHELL EYiH XHBD XSC'SUFPR EXH Xh=D ZSQL V DRYHELL EXH OUTED ISOL V SJPPR EXH CJTBD ISQL V SUPPR XiP CUTBD ISGL V DRYhELL Ihi CiJTB'D ISO!V SUPPR I)F Xh=D XSGL V DRYHELL INL NSD XSOL V VENDOR H!THE POSI-SEAL IHTFR.FOSX-SEAL XNTER POSI-SFi".L IHT ER.FCSI-SEAL ZiNTER.POSZ-SEAL INTER.POSZ-SEAL XHT.PCSZ-SEAL INTER POSI-SEAL INTER.TARGET ROCK CCRP Tk'RGET ROCK CORP TARG<<T RCCK CORP TARGET RO K CORP SPEC P304D P304D P3045 P304D F304D P3C4D P304D P304O P304X P304X P304X F304X ZON SC269155 SC215125 PC269681 PC215121 PCZ89681 PC215121 SC289155 SC21512Z SC2151!22 SC289155 FCZ15121 PC289681 ZX TREF H H H H H H H H H H H H CFCOO GPT 8 8 8 8 8 8 8 8 A A A A+=Regulatory Guide 1.97.

PAGE 10 EQUIPtlENT ID+'ZCSttvAQV108 CCSHwttCVICO QCSHT.ING SPEC ZONE ZX C051H SC175 03 H P30iR SC289155 H P304R ABN17503 H P3CQY SC196110 H P303W PC306711H TREF A A A A 100 OYS 100 DYS 100 OYS 100 DYS GPCGD GPT+=Regulatory Guide 1.97.

PAGE 12 EQUXPttENT XD ZDER<ttOV119 ZDERwt tOV120 ZDER~ttOV128 c.DERE!tOV129 ZOER+ttOV130 ZDERxt tOV131 DESCRXPTXON GATE VALVE GATE VALVE GLOBE VALVE GLOBE VALVE GLOBc VALVE GLOBE VALVE VENDOR NAttE VELAN VELAN UELAN VELAN VELAN VELAN SPEC P304S P30QS P304R P300R P30RS P304S ZONE PCZ15121 SC215125 PC2%0606 PC200506 PC&0603 S"2003.35 ZX%REF H H H H H H OPCOD A A B B A A OPT 6 HRS 6 HRS N/A N/A 6 HRS 6 HRS PAGE 13 E'tttIPt i tT 10 2DFR>LS143 2Q FR vLS144 2DFR>LS145 2DFRvLS146 20FRtLS147 20 F RMLS14 8 2DFR<<LS3A 2DFR>HQV120

+2QF Rat tQV121 2DFRxttQV139

+2DFRxtlQV140 DESCRIPTXON RHS 8 PtP RH FLD HTR LVL RHS C PttP Ri't FLO HTR LVL ICS PttP RHi FLD HTR LVL CSH Pt'.P RH FLD HTR LVL CSL Pi't?Rtt FLO HTR LVL RHS A PHP Ril FLD HTR LVL 2RHSx51A CUBECLE FLOQDEO GATE'VALVE GATE VALVE GATE VALVE GATE VALVE VEtFQOR NAttE HAGNETROL VAGtt TRQL ttAGNETRQt.

ttAGNETRCL HAGNETt'OL HAGNETROL ttAGNETRQL VELAN VELAN'VELAN VELAN SPEC C021L C0 21L C021L C02 L C021L C021L C021L P304S P304S P304S P304S ZONE ABS17509 ABS17508 SC175106 SC175108 AB."t17503 ABN17504 ABN17505 SC215123 PC215121 SCC't0 37 PC240601 ZZ TREF H H H H H H H H H H H OPCOD OPT A A A A+=Regulatory Guide 1.97.

PAGE 10 EQUIPHKNT ID 2DNStkKCAI 2DMS+ttCCBI DESCRIPTION 125li~aC ViCC RB ELEV.200 125VDC HCC RB ELEV.206 VENDOR NA!'iE GOtP Do INC.GOVLD SPEC ZONK ZI'QRKF EDISON ABNZ0033 H EOIM ABS20036 H OPCOD OPT PAGE 15 EQJIPHEHT ID 2EHStHCC102 ZEHSditCC302 DESCRIPTIOH ST~~KOBY HCC CLASS lE EHERG HiCC VEHDCR HAHE GOLR.D GOULD SPEC ZOHE ZI QREF E015Q A""HZ%033 H E015Q ABS20036 H OPCOD OPT PAGE 16 EQUIPHEtiT ZD DESCRIPTZOH VFHDOR HAIIE SPEC ZOHE ZZ QREF OPCOD OPT ZEJANPHLIOOA ZEJA<PtiL3005 ZEJAxXDIOOA ZEJA<XD3005 RB 120V HEATER PhL RB 120V HEATER PHL DIST XFHR 600V-ZOOY/1ZOV DZST XFHR 600V-ZOSY/120V BROHH BOVERI BRONH BOVERZ SQUARE IDis SQUARE D E01RT ABHZR033 EOlRT ABSZR036 K E011T ABHZR033 H E011T ABSZR036 H PAGE 17 EQUIPHENT ID DESCRIPTIOi'l VEiNDCR NAHe SPEC ZONE ZI TREF~OPCOD OPT ZEJS>PNLIOIA ZEJSwPiV 103A ZEJSxPNL104A SHSR RH A EHER 600V Phl.AB-N EHER 600V PhL AB-N tHER 600V PNL ZEJSvPh" 303B ZEJSxPNL304B AB-S EHER 600V PNL AB-S EllKR 600V PNL ZEJSxPNL302B AB-S EHER 600V PNL BRO!iN BOVERI BRCHN BOVFRI BROHil BOVERI BROh.l BOVERI BRO!iN BOVFRI BROhl GQVERI E014T ABN24033 E014T AGN24033 H E014T ABN24033 H E014T ABSZ4036 H E014T ABS24036 H E014T ABS24036 H PAGs 18 EQUIPNENT ID ZEPSvSH8001 ZEPSvSHG002 ZEPSwSHG003 ZEPSwSHG004 DESCRIPTIOi l 13.6HV EllERG SHG001 13.6HV ENERG ShS002 13.6HV EHFRG SHG003 13.6HV EllERG ShG004 VENDOR NAHE GOULD BROHN BOVE GOL" 0 BROHN BOVE GOULD BROHN BOVE GCULD BROS BOVE SP C E015N E015N E015N E015N ZOilE ABN24033 ON~4033 ABS24036 ABS24036 ZI QREF H H H H OPCOD OPT PAGE 19 EQUIPHENT ID+ZFFHwSOV218

+a.rPi4SQV 19+RFPH<SOV220

+ZFPKwSOV221 DESCRIPTION ZRCS-PlA FIRE PROT HTR CONT ZRCS-P1A FIRE PROT HTR CONT 2RCS-P18 FIRE PROT HTR CONT ZRCS-P18 FIRE PROT HTR CONT VENDOR VMlE TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP SPEC P30QX P30QX P30QX P30QX ZONE SC200135 PC250625 SC200135 PC 250619 ZI TREF H H H H OPCOD OPT 8 8 8+=Regulatory Guide 1.97.

PAGE 20 EGUIcVENT ID+ZFHSiiAQV23A

+ZfttS+AQV23B

+ZFHSmtlQVZIA

+ZFHSi tlOVZIB DESCRIPTION FEEOHATER TESTABLE CHECK FFEDitATER TESTABLE CHECK GATE VALVE GATE VALVE VEhDCR NAPE Ah~NOR/DARLING ANCHOR/DARLIitB VELAN VELAN SPEC P303H P303H P30CR P30~R ZONE t(ST20005 t!STZR045 ttST24005 HSTZQ005 ZI TREF H H H H QPCOD QPT A 006 HRS A 006 HRS A 006 HRS A 006 HRS egu atory Guide 1.97.

PAGE 21 t(tUEPt!ENT ID ZGTS((AOVIOI ZGTS((CHIA ZGTS((CH19 c.GTSxDl!P1A ZGTS((Ct!PXB 2GTSRDt!P2A ZGTS+Oit!PZB ZGTS((FHZA ZGTS((FNZB ZGTS('t!GVIA ZGTS((t!OVID ZGTS((t!GVZA ZGTS('3!OVZB ZGTS((lfOVZBA ZGTS(3!GV289 2STS((t!QV3A ZGTSot!OV39 ZGTSwt!CV4 ZGTS((HOV49 ZSTS((PDITZIA ZS(S((PDITZZB ZGTS((PV5A ZGTS>PV59 ZGTS+SGVI 02 ZGTS~TEX26A ZSTS((TEX269 ZGTS((TEY26A ZGTS((TEY269 ZSTS((TZS 3A ZGTS((TIS239 ZGTS>XDIA ZGTS<XO19 DESCRIPTION PRIl ARY CONT PURGE ISCL V FILTER TRAXH A HEATER FILTeR TRAXH 9 HEATER TCRNADO DCIPER-SSTS BLDS TORNADO DAt!PER-SSTS BLDG TORNADO DAttPER-SSTS BLOS TORNADO DAt!PER-SSTS BLDG wFLTXA DISCHARGE FAN ((FLTZB DISCHARGE FA",l BUTTERFLY OR TRICEHTRXC VA'E BUTTERFLY GR TRXCEHTRZC VALVE BUTTERFLY CR TPyCet!TRIC VA(V BUTTERFLY OR TRICENTRIC VALVE CROSS-BLEED L VLV CROSS-BLEED L VLV BUTTERFLY OR TRICENTRIC VALVE B(JTTERFLY CR TRICE'iTRIC VALVE GATE VALVE GATE VALVE ZSTS((FLT lA DIFF PRESS ZGTS((FLT 19 DIFF PRESS RX BLDG IN/GUT DIFF PRESS RX BLDG IH('OUT DIFF PRFSS PRXttARY CONT PURGE ISOL V FLTR TRAIN HTR IHLET TEt!P FLTR TRAIN HTR INLET Tit!P FLTR TRAXN HTR CUTLET TEt!P FLTR TRAIN HTR CUTLET TEHP CHARCCAL ADSCRB Tet!P H CHARCOAL ADSORB TEt!P H XFHR 600-480V XFHR 600V-480V VENDOR HAKE POSX-SEAL IHT.tliNE SAeETY APPL Hit!E SA.FTY APPL PACIFIC AIR PROD PACIFIC AZR PRCO PACXFIC AIR PROD PACIFIC AZR PROD BUFFALO FORGE BUFFALO FORGE CLCH CORP CLOH CCRP CLGH CGPP CI.OH CORP CLO!l CORP CLC!i CORP CLOtl CORP CLOH CCRP VELAH VELAN tlIHE SAFETY APPL HIHe SAFETY APPL CLCH CORP CLCH CORP TARGET ROCK CORP HINE SAFETY APPL tlI¹SAFETY APPL HXNE SAFETY APPL t!XNE SAFETY APPL NINE SAFETY APPL llltiE SAFETY APFL HIHE SAFETY APPL llINE SAFETY APPL SPEC P304D P243U P243U P413T P413T P413T P413T P413S F413S P304Y P304Y P304Y P304Y P304Y P304Y P304Y P304Y P304R P304R P243U P243U P304Y P304Y P30(tX P243U P243U PZ43U P243U P243U P243U PZ43U PZ43U ZONE SC306181 SSZ61355 SG261355 SGZ61356 SG261355 50261355 SS261355 SS261355 SG261355 SC306181 SC306181 SS"61355 SGc.613o5 SS261355 SS261355 SS261355 SS261355 SG261356 SG261355 SG261356 SS261355 SS261355 SS261355 SC306181 SG 261356 SS261355 SG261356 SG261355 SG261355 SS2613o5 SGc.61356 SS261355 Zl t!REF H H H H H H H H H H H H H H H H H H H H H OPCOD C A A B 9 9 9 A A A A A A A A A A A A A A A A C A A A A A A A A GPT PAGE ZZ Et)UIP))EHT XD ZHCSiiIPhLZZA ZHCSsXPiV 228+ZHCSi t!QVlA+ZHCSxt!CV18

+ZHCS+!!QVZA

+ZHCSxt)OVZB

+2)lCSiit!QV3A

+ZHCSiit)QV38

+ZHCSxt)OV4A

+ZHCSw?IQVCB

+ZPCSiit'QV>A

+ZHCS~)!OV58

+"HCSii)iQVi6

+ZHCSx"QV68 ZHCS+RBNRIA 2HCS>RB))R18 ZHCSiiSGVIOA 2?iCSwSGV103 ZHCS+SQVIIA

?HCSxSOV118 DESCRIPTZON HZ RECOi)!8 PHR CAB H2 RECCi?BIiNER CAB RBihRlA OUTLET CUTBD ZSOL RBNRlA OUTLET OUTBD ISOL RBNR1A XhLET OUTLBD XSCL RBNRlA IhLET CUTLBD ISCL RBNR1A Xh>>ET GUTLBD ISCL RBiiR18 Zti" ET OUTLBD XSOL RBhRlA OUTLET Xt)30 ZSCL RBNR18 CiJTLET ZNBD XSQL RBN1A INLET XNSD ISGL RBN18 INLFT INBD ISQL RBt)lA ZN'T IHSD ZSCL RBN18 IiNLET INSD XSQL HYCRGGEH RECCHB lA HYDRCGEH RECO!iiB 18 RBNR1A CLG HTR IhLET RBNR18 CLG l>>>S P30>>S P30>>S F3045 P30>>S P300S P30>>S P30>>>>S P30QS P30>>S P30>>S PZBZH P28 i.H P30>>X P30>>>>X P30>>X F30%X ZCiKc AB))20033 ABSZQ036 SC215123 SCZI5132 SC215122 SC215122 SC240140 SCZQ0103 PC215121 PC215121 FC215121 PC215121 PC250621 PC250629 SCZQ0135 SCZQ0135 SC?))0135 SCZ>>0135 SCZQ0135 SC240135 Zl OREF H H H H H H H H H H H H H H H H H H H H OPCOD OPT A A A A A A A A A A A1 A A 1 A A A A A+=Regulatory Guide 1.97. PAGE 23 EOUIPHENT ID+<<ZHVR<<AODIA +ZHVR<<AODIB +<<ZHVR<<AODIOA +<<ZtiVR<<cAODIOB ZHVR<<AGD114 ZHVR<<r<<ODZOQ 2H'VR<<AOD3QA <<.HVR<<iAGD3QB +rZHVR<<AGD5A +2HVR<<AGD58 +wHVR<<AGD9A +<HVR<<AGD98 2HVR<<CAB14A ZHVR<<CABIQB ZtfVR<<Cr'832A 2HVR<<CAB328 ZHVR<<F E18A czif VR<<F e 188 ZHVR<<FEISC 2HVR<<FE SD ZHVrc<<cFE36A ZHVR<<FF368 <<.HVR<<eE37A ZHVR<<FE378 2HVR<<SGV235 ZHVR<<TISI15 ZHVQ<<TIS16A 2HVR<<TXS168 2Hl/R<<TIS19A ?HVR<<TIS198 <<HVQ<<TXS22A ZHcVR<<TISZ c.B c.HVR<<TXS23A <<.ii'VR<<TISc238 2fiVR<<TXS23C 2HVR<<TXS 3D ZHVR<<TXS23E ZHVR<<TISc23F 2H'VR<<TISZQA 2HVR<<TXS<<.QB 2HVR<<TXSZ5A ZHVR<<TXSZDD ZtlVR<<TIS25C ZHVR<<TIS 258?hVR<<iTIS?6A 2HVR<<TXS258 ZHVR<<TXS25C DESCRIPTION SUPPLY AIR ISOL DtPR SUPPLY AIR ISOL DtPR EXH AXR ISGL DtPR EXH AXR ISOL DHPR R CXRC AIR OIPP.-RX BLDG RFAC HO EVAC FLT3 DISCH DiPR<<UCQ13A TEST OtPR UC4138 TEST DtPR<<UC413A XhiLET OFPR<<UC4138 ItiLET CtPR EXH AIR ZSOL DtPR EXH AIR ZSOL D!PR RX BLDG ABV REFUEL FL FAON RX BLDG ADV REFUEL FL FADN RX BLDG BLH REFUEL FL RAON RX BLDG BLH REeFUeL FL RADN RX BLDG Et!KRG RKCXRC UC413 A RX BLDG Kt!KQG RECXRC UC4138 RX BLDG EHKRG RECIQC UC413A RX SLOG Et!KRG RKCXRC U 4138 ABV REFUEL FLAIR FLOH ABV REFUEL FLAIR FLON BLH REFUEL'FLAIR FLOH BLH REFUEL FLAXR FLO'ri GLOVE VALVE RHR HT E.c R'f 8<<UC406 KLKC tf"C ARKA UCQ09A eLEC lrCC AReA U 4098 ELEC H"C AREA<<UCQOSA ELEC HCC AREA<<UCQOSB LPCS PP Rtf<<UCQOZA LPCS PP RH<<UC'f628 RHR PP Rtf A fcUCQOIA RHR PP RH C<<UCQOIB PHR PP Rt'I 8<<UC>>OIC RHR PP Pt'l A<<UCQOID RhP PP R"f C<<UCQOle RHR PP Rfl 8<<UC>>OIF HPCS PP RH<<UCQ03A HPCS PP Rtf<<UC4038 GEN AREA EL175<<UCQOQA GEh AREA EL175<<UCQOQB GEN AREA EL175<<UCQOQC GEN AREA.EL175<<UCQOQD GEN AREA EL215<<UC407A GEN AREA ELZ15<<UC4078 GEN AREA EL?15<<UC407C VeNDOR N"'tf PACIFIC AIR PACIFIC AXR P"CXFXC AXR PACIFIC AIR PACIFIC AXR PACXFXC AIR PACXFIC AXR PACIFIC AXR PACIFIC AXR PACIFIC AIR PACXFIC AXR PACIFIC AIR HCC FOifERS HCC POrfKiQS HCC POH RS t!CC POHERS HCC PCHKRS k!CC PCHKRS t!CC POriE'RS l!CC PGHFRS TARGET ROCK t!CC POHKRS t'CC POci'eRS t!CC POiiERS HCC PCrieRS HCC FOHERS t!CC POciKRS ttCC PO!iKRS l!CC PGHERS HCC PGHERS HCC F""eRS HCC PC!tERS lfCC PC!fERS HCC PGHEQS HCC PCHERS HCC PCKKPS l!CC FOHKRS lf C FCciERS HCC PGHKRS HCC PCHEPS HcCC POHKRS HCC PGiiKQS ffCC POHKRS PROD PROD PROD PROD P D FROG PROD PROD PROD PROD PROD PROD SPEC PQI3T PQ13T PQ13T PQ13T PQ13T PQ13T P>>13T PQ13T PQ13T PQ13T FQ13T PQ157 P<<.SI P c.SIF PZSIF P28IF C071A C071A C071A C071A C071A C671A'C071A C071A P3OQX C071A C071A C071A C071A C071A C071A C071A C071A C071A C071A C071A C671A C071A C071A C071A C071A C071A C071A C071A C071A C071A C071A SC289155 SC 289155 SC289155 SC209155 SC306175 SC289155 SCc.89155 SCZS9155 SC289155 SCZ89155 SC289155 SCZS9155 SC328187 SCGZ8187 SC3281S7 SC328187 SCc.89155 SCZ89155 SC289155 SC289155 SC353ZOZ SC353c202 SC289155 SCZ89155 SCZ89155 ABS19620 ABSZ>>036 ABSZQ035 AEN24633 ABNZ>>033 AB!f17503 ADN1 7503 ABN17504 ABSI7508 ABS17509 ADftl7504 ABS17508 r<<BSI7509 SC196115 SC196116 SC195116 SC196113 SC196113 C'96'15 SC215122 SC215122 SC215122 H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H PQ13T.02 P413T.02 P413T.02 P413T.03 P413T.Ol PQ13T.01 PQ13T.02 PQIGT.02 PQ13T.02 P413T.02 H H H H H H H H H ZZ fcREF H PQ13T.02 OPCOD OPT 8 8 8 8 C C 8 8 8 8 8 8+=Regulatory Guide 1.97. PAGE 24 EQUIP!!ENT ZD ZHVrRcvTXS259 ZHVRxTXS~6c ZHVR+T S27A ZHVR+TXS228 ZHVR+TZSZ7C ZHavaR>TIS20A ZHVRviTXSZSB Zt!VR>TXSZOC ZHVRaaTIS30A ZHVR>TES303 ZHVRxTXS3)A ZHVR>TIS3)B ZIIVR>>TZS35A ZHVRa TIS353 ZHVR>TIS3SA ZHVRaaTZS30S ZHVRaaaJC40)A ZHVRxUC40)B ZHVRaaUC40)C ZHVR+UC40)O ZHVR>aJC40)E ZHVR+aJC40)F ZHaac'aaUC402A ZHVRNUC4023 ZHVRvUC403A c.HVR>>UC40'3 ZHVRanJC404A ZHIV~UC4048 ZHVR~UC404C ZHVR~UC4040 ZHVRmUC405 ZHV4aaUC405 ZHVR+Ua.407A ZHVRwUC4023 ZHVR>U 407C ZHVrRaaUC4070 ZHVR<UC407E ZHVQ+UaC408A ZHVR+UC4003 ZHVR~aJC409A ZHVrRa+UC4098 ZHVRviUC4)OA ZHVRtUC4)03 HVQaaU"4)DC rHVRxUC4))A ZHVR>UC4))S ~ZHVRNUC4))C DESCRIPTION GEN AREA ELZ)5 xUC407D G ii ARcA EL215%UC402E GEN AREA EL240 IaUC4)DA GEii a"'REA EI.240 ViUC4)GS G N AREA EL?40 xUC4)OC GEH AQEA EL261>UC4))A GEN AREA EL251 wUC4))8 GEII AREA EL261 NLaC4~)C GEN ARFA EL261 wLaC4)ZA GEii AREA EL261 taUC4)28 UC413A INLET TEIP U 41'33 ihLET TFI!P GEN AREA EL26)+aJC4)4A GsH AREA ELZ6)taUC4)48 GTS RH A~UC4)+A GTS Ri'I A aaUC4)53 RHR PU!P RiH A-UNZT CLR RHR PUlP Rtl C-UNIT CLR RHR PU!iP RH 8-UtiIT CLR RHR PUHP Rtl A-UiNIT CLR RHR PU!!?Rtl C-UNIT CLR RHR PPi!P Rtl S-LiNiIT CLR LPCS FU!P Rtl UaNIT-.CLR LPCS PUt!P Rll UNIT CLR HPCS PU!P Rtl UiNIT CLR HPCS PU!IP RH UNIT CLR RS EL 175 GEN AREA U'IXT CLR RS EL 175 GEH ARcA UNIT CLR RB EL 175 GEN AREA UNIT CLR RB EL 175 GEN AREA UNZT CLR RHR HEAT EXCH RH UNIT CLR RHR HEAT EXCH RII LriPiT CLR RB EL 215 GcN AREA UNIT CLR RB EL Z)5 GEN AREA UNIT CLR RB EL 215 GcN AREA U!IXT CLR RB EL Z)5 GEN AREA L'NIT CLR RB EL 215 GEN ARcA UNET CLR ELEC ataiCC AREA LNIT CLR ELEC HCC ARcA U!IIT CLR ELEC I!CC AREA UNIT CLR ELEC HCC AREA UNET CLR RB EL 240 GEN AREA UNIT CLR RB EL 240 GEN AREA U!IIT CLR RB EL 240 GcN AREA LiNIT CLR RS EL Z61 GEN AREA UiN'IT CLR RB SPACE COOLER ELEV 261 RB SPACE COOLER ELEV 261 VEh~~OR NAIIE I!CC FCHERcS HCC PO!aERS HCC POHERS HCC PO'riERS l!CC FOHERS PCC PCri RS HCC FOHERS Il"C POHERS HCC POHERS HCC POHERS I!CC PCHERS I!CC POHERS t!CC PCHERS HCC POHERS taCC PCHERS HCC PCNERS A!IERiC'N AIR A!IERECAN AIR AIIERICAH AIR AIIERiCAN AIR A!IERICAN AIR AHERICAN AIR AIIERICAN AIR Al!ERICAN AER AtlERICAN AER A!!ERICAN AIR AtlERICAN AiR AIIERICAN AXR AclcRXCAN AXQ AHERXCAN AIR Al!FRXCAN AXR AailERICAN AIR AHERXCAN AiR A!IERICAN AIR AHERXCAN AIR AIIERICAN AIR At!ERICAN AIR AttcRXCAN AIaQ At!ERICAiN AiR Al!EPICAN AXR A"FRICAN AXR AHERICAN AIR AIIcRICAN AER AHERICAN AXR AHERiCAti AiR AHERICAti AXR AHERZCA'I AIR FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT FLT C07)A C07)A C071A C02)A C07)A C071A C07)A C07)A C071A CD71A C07)A C07)A C07)A CD7)A C071A C02)A P412tl P41?Jl F412H P41211 P412tt P4)ZH P412tl F41211 P4)ZH P>>1~I!P4)~"I P>>12H P412H P4)c.H P4)ZII P4)Ztl P41?t I P4)ZH P412itaa P4)ZH P4)ZH P41211 F412II P412H P412Hi P41211 F412!I P4)Z'I P4)cZt1 F4)ZH P4)ZH SCZ)5122 SCc)5122 SC240135 SC24C)35 SC240135 SC26))45 SC261)45 SC261145 SC)75)C5 SC)73106 SCZ69155 SC209155 SCc.6)145 SC261)45 SGZ61355 SGc.61355 ASN)7504 ABS)7500 ABS)75D9 ABN)7504 ASS)7508 ABS)7509 ABN)7503 ABN)7503 SC)75)00 SC)25~09 SC)96116 SC)96113 SC)96113 SC)96116 ASN)9615 ABS19620 SCZ)5122 CZ 5122 SCZ)5122 SC215)ZZ SCZ)5122 ABN24033 ABN24033 ABS24036 ASS24036 SC24O)35 SCZ40135 SC240135 SCc.61145 SC261.145 SC261145 SPEC ZONE ZX h H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H QREF OPCOO OPT 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 PAGE 25 EOUIPt'ENT ID ZHVRKUC412A ZHVRxUC41ZB ZHVR<UC413A ZHVR)UC413B ZHVRwUC414A ZHVRYiUC414B ZHVRKUC415A ZHVRwUC415B DESCRIPTXON RCIC PUt!P RCOH UNIT CLR RCXC PL".P ROON UNIT CLR EHERGENCY RECIRC UNIT CLR EHEFGENCY RECXRC UNIT CLR EL 261 GEN AREA UNIT CLR EL 261 GEN ARFA U.'tXT CLR SG SPACE COOLER EL261 SG SPACE COOLER ELZ61 VEtiDOR NAtlE Al!ERICAN AIR FLT Al!ERICA t AIR FLT AHERICAN AIR FLT AtlERICAN AXR FLT AtFRICAN AIR FLT At!ERICAN AIR FLT AHERXCAN AIR FLT AHERXCAN AXR FLT SPEC PRIZH P412tl P4i2H P412a l P41ZH P412tl P412.H P412tl ZONE SC175106 SC175106 SC289155 SC289155 SC"61145 SC261145 SG261356 SG261355 ZX CREF H H H H H lt H H OPCOD OPT B B A A B B B B PAGE 26 EGUIPtlEHT XO+ZXAS'>>PT161 +'ZZASIPT186 +ZZASiiPT230 +GXASNPT231 +ZXAStiPT232 +ZIASvPT233 +ZIASwPT23Q +ZIASvPT235 +ZIAS<PT236 ZIAS+SOVX161 ZIASYSOVX186 ZZASxSOVY181 2IASgSOVY186 +ZIASxSOV16Q +ZXAStSOV165 +ZZASiiSOV166 +ZXASKSOV167 +ZZASwSOV168 +ZIAS<SOV160 +ZIAS>>SOVISQ +ZXASNSOV185 DESCRZPTXG:I ADS HEADER A PRESSURE ADS HEADER 8 P?ESSURE ADS ACCUIFJLATOR TK32 AOS ACCIP.".c%.ATOR TK33 ADS ACCUI>>i%.ATCR TK34 ADS ACCLQIULATOR TK35 ADS ACCUtn%ATOR TK36 ADS ACClnfL>>ATGR TK37 ADS ACCUllULATGR TK38 ADS HEADER A PRESSURE ADS H ADeR 8 PRESSURE ADS HEAOEQ A PRESSURE ADS HEADEP 8 PRESSU?E IiNSTR AIR CCNTtlT ISOL V IhSTR AIR CONTHT ZSGL V IhSTR AIR CCHTtiiT ISCL V ZhSTR AXR CGIITtlT ISGL V IHSTQ AIR CGiITIIT ZSGL V INSTR AIR COhTHT ZSOL V INSTR AZR COHTIIT ZSOL V IHSTR AIR CONTHT ISOL V VEhOGR HAKE ROSE!IOliHiT ROSH IOUNT ROSEitlOUiti ROS t'OWiT ROSEt QUNT ROSEHOUilT ROSBIGUiHT ROSEtlOUiiT RGSB IOUIIT TARGET RCCK T'RGET ROCK TARGET ROCK CORP TAQGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET RCCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET RGCK CORP SPEC C071H C07ltl C07'l C071tl C071H C071H C071H C071H C07 tl P30QX P30QX P304X P30QX P30QX P30cIX P30QX P30QX P30QX P30QX P30QX P304X ZON SC269155 SC269155 SCZS9155 SCZS9155.SC269155 SC306175 SC306175 SC306175 SC306175 SC289155 SC289155 SC269155 SC289155 SC289155 SC289155 SCc.S9155 SCZQ0135 SC289155 PC289681 PCc.89681 PCZQ0603 ZX GREF H H H H H H H H H H H H H H H H H H H H H A A A A A A A A A A A A DYS DYS OYS DYS DYS DYS HON NOH IIOiH t.lG'I HGH 0?COD GPT+=Regulatory Guide 1.97. PAGE 27 EOUXPHEHT ID+ZICS<AOV156 +ZXCS<AQV157 ZXCS<F VZOS ZXCSiit!GV116 ZICSvt:OVZZO +ZXCS+i'OV121 +'ZICS>t(OVZZZ ZXCSi t(QV124+ZXCS<t(GVX26 +ZZCS<t!QVIZS ZZCS>!!OV129 +ZICSiit'OV136 +ZZCS>t(OV143 +ZICSiitlGV148 +iZZCSiii!'OV1~64 +ZICSwtlQV170 ZZCSxPCV115 DESCRIPTZGiN TESTABLE CHKCH V TESTAD'Cr".ECK V TEST BYP TO ChDS STOR TH RCIC LUBE OXL HATER SUPPLY RCIC STEA!l SPLY V TO TURBINE STEA)(SPLY LXHE XSOL V (OUTBD)RCIC TURB EXH TO SUPFR POOL RCIC TEST FCV TO CNDS STOR TK.RCIC XNJFCTION SHUTOFF VALVE RCIC ST SPLY LINK ISOL V PU!!P SUCT FRG!l CNQS STGR TANH PCIC PtP SUCT FRCH SU.""PR PGGL RCIC HIN FLOH TO SUPPP.POOL RCIC VAC SRHR ZSGL V(ZNBRD)RCZC VAC BRHR XSCL V (OJTBRD)RCXC STEAtl LINK HARtl-UP L(iBK OJL CLR PRESS CGiiT V VENDOR Nisi!E ANCHORi'DARLING At(CHCRi'DARLING COPES-VULCAti VELAN V"LAN VELAN VELAH VELAH VELAN VELA)i EhG.CO.V~LAtt VELA!i VELAN VKLAH'VELAN VELAN COPES VP CAH SPEC P303H P303H C051H P304R P304R P304R P304R P304R P304R P304R'P304R P304R P 304'R P304S P304S P304R C05ltl ZGhE SC289155 PC328185 SC175106 SC175)06 SC175106 SCZ61150'C196118 SC175106 SCZ89155 PC261649 ABNZ4031 SC196117 SC196117 SC196118 SC196118 PC261649 SC175106 ZI ()REF H H H H H H H H H H H H H H H H H OPCOD A A A A A A A A A A A A A A A A A GPT lZ HRS 12 HRS 6 HRS 12 HRS 1Z HRS 12 hRS 12 HRS 6 HRS 12 HRS 12 HRS 1Z HRS 12 Hi%5 12 HRS 12 HRS 12 HRS 12 HRS 12 HRS+=Regulatory Guide 1.97. PAGE 28 EQJIPHEHT IO DESCRIPTIOH VENDOR HAKE SPEC ZGHEZI QREF OPCOD OPT 2IS xSOV119 ZISC+SOV120 ZvSCi'SOVIZ ZISCxSOV12% SOLEHOIO Or ERATED SOLEHOIO OPERATED SOLENOID OPERATED SOLEHOID OPERATED VALVE VALVE GLODc Vgl'VF GLOSE VALVE TARGET ROCK TARGET ROCK TARGET ROCK TARGET ROCK P30QX P30QX P30QX P30Elx SC200135 SC2151"2 SCZ00135 SC215122 H H H H A 100 DYS A 100 DYS PAGE 29 EQUIPHEHT ZD+2LHSi'SOV152 +c.Li!StiSOV153 +.2LHS<SOV156 +ZLHSwSOV157 DESCRIPTZOH DRYHELL PRESS IHB ZSOL DRYhELL PRESS OUT ZSOL SUPP CHUB PRESS IHS ZSOL SUPP CHUB PRESS OUT ISOL VEhDOR HAKE TARGET ROCK CORP TARGET RCCK CORP TARGET ROCK CORP TARGET ROCK CORP SPEC P30VC P30QX P30QX P30QX ZOHE PC299699 SC289155 PC215121 SC215130 ZZ TREF H H H H OPCOD B B B B OPT 6 HRS 6 HP.S 6 HRS 6 HRS+=Regulatory Guide 1.97. PAGE 30 EttUIPtlENT ZD+ZHSS!HYV6A +ZtlSSt<HYV6B +2ltSSaHYV6C +2<KSS!<HYV65 +Zl'iSS>H YV7A+2tlSS!<HYV78 +ZtlSSvHYV7C +ZHSSxHYV70 ZttSS!<!tQV108+Zt tSS!t tOVlll+ZtlSS<<tlQV112 2l fSSwtlOV118 Zt lSS+t tDV119~ZtSSxt lOV189 ZttSSKtlOV207 +ZHSSxKO'JZ08 ZHSS<!RVV190 ZHSS>SOV97A ZtSSxSO'J978 ZtSS>SOV97C .ZttSS<SOV970 DESCRZPTZON HN STtl LINE A INBD ISOLV HN STH LINE B XHBD ZSOLV tlN STH LIHc C It!BD XSOLV KH STtl LIHE 0 INBD ISOL V li<H ST<tl LIhE A OUTGO tSIV t"t STH LlhE B OUTBD llSIV Htl STtl LINE C OUTBD llSIV HN STFI LIiNE 0 OUTED HSIV REAC BESSEL HEAD VENT V ttN STEAN DRN XHSD ZSOL V ttN STEA!t ORN CUTBD XSOL V R=AC BeSS"-L HEAD VettT V REAC BESSFL HEAD VENT V XSOL CLG STH LltlE ORV ZSB5 tSIV DRH ISCL V XSB5 tSIV ORh XSOL V REACTOR HEAD VENT RELIEF BTKH HSXV LXtlE 5R V BTKiH lSIV LIHE DR V BThit tlSIV LZNE DR V DTKi'l tlSIV LIHE OR V VENDOR HAHE FLUID SYSTEHS FLUID SYSTElS FLUID SYSTEttS FLUID SYSTEtS FLUID SYSTEtS FLUID SYSTEtlS FLUID SYSTEHS FLUID SYSTEtS VELAH VELAN VELAN VELAH VELAN VELAN VELAil VELAN GPE CONTROLS TARGeT ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET POCK CORP SPEC P3030 P3030 P3035 P303D P3030 P303D P3030 P3030 P304R P304R P304R P304R P304R P304R P304R P304R P3055 P304X P304X P304X P304X ZONE PC250519 PC250619 PCZ50619 PC250619 HST24045 tlSTZ4045 HST24045 llSTZ4045 PC306711 PCZ40601 HST24045 PC306711 PC306711 PC261649 PCZ40600 HSTZ4045 PC240600 HS!24045 HST24045 HST24045 HST24045 ZI@REF H H H H H H H H H H H H H H H H H H H H H OPCCD A A A A A A A A C A A C C C C A OPT 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS OC6 HRS 006 HRS 006 HRS 006 HRS 006 HRS+=Regulatory Guide l.97. PAGE 31 UZPllENT ID+2RCSiiSOV104 +2RCStiSOV65A +ERCSiiSOV65B +2RCS>SOV66A +2RCSvSQV66B +2RCSwSOV67A +2RCSvSOV61B +2RCSKSOV58A +2RCS~SOV68B +2RCSiiSOV79A +2RCS>SOV79B +2RCSxSGV80A +2RCSttSOV80B +2RCSvSOV81A +2RCSxSOV81B +2RCSwSOV82A +2RCSvSOVSCB +2RCS*SOV105 DESCRIPTION 2RCS-PlA OZSCH StP ZN30 ISOL RCS HYDR LZNE ISOL SOV RCS HYDR LINE ISOL SOV-RCS HYDR LINE ISOL SOV RCS HYDR LINE ISGL SOV RCS HYDR LItiE ZSOL SOV RCS HYDR LINE ZSO'OV RCS HYDR LINE ISCL SOV RCS HYDR LZiiE ISGL SGU RCS ZNBD HYD LINE ISOL SOV RCS IiNSD HYO LZNE ISOL SOV RCS INBO HYO LINE ISQL SOV RCS INBD HYD LINE ZSCL SOV RCS INSO HYO LIiNE ZSGL SOV RCS ZhSD HYD LINE ISQL SOV RCS INSD HYO LItiE ISOL SOV RCS INBD HYD LINE ZSOL SOV 2RCS-PlA DISCH SMP OUTBD ISOL VENDOR NAttE TARGET ROCK CORP TARGET ROCK CORP TARGET RO"K CO."P TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGET ROCK CORP TARGcT ROCK TARGFT ROCK TARGET RCCK TARGET ROCK TARGET ROCK TARGcT ROCK TARGET ROCK TARiET ROCK TARGET ROCK SPEC P30>>X P304X P30>>X P30>>X P30>>X P304X P304X P304X P304X P304X P304X P30>>'X P304X P304X P304X P304X P304X P304 ZZ TREF H H H H H H H H H H H H H H H H H 5 H ZOhE FC261641 SC261145 SC261145 SCZ61145 SC261145 SC261145 SC261145 SC261145 SC261145 FC261644 PCZ61649-FC261644 PC261649 PC261644 FC261649 PC251644 PCZ61649 X PC26164 OFCCD A A A A A A A A A A A A A A A A A A OPT 006 HRS 006 HRS.006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS 006 HRS+=Regulatory Guide 1.97. PAGE 32 E'WZPIIKNT ZD ZRHS<<AGV163 ZRHSvAGV16C '2R!IS'AOV39A ZRHS~AOV393 ZRHS<<EcV5 ZRHSiiFV3SA ZRHS<<FV383 ZRHSwFV38 ZRHS>HCV53A ZRIIS<<HCV535 ZRHS>HCV53C ZRI!S~HCVSRA +ZRHS~HQVIC +ZRHSÃt IQVIGR+ZRHS<<t!QV112+ZRHS<<tlQV113 ZRHSi<HQV115 ZRHS<<tfQVZI6"RhSx"QVI"A ZRHS~tfOVZZB RH~<<uQVIRZ ZRHS<'HOV1R9 +ZRHSxtfQV15A +ZRHSwt!0<J153 ZRHS<HO<JZB ZRHSQ!GVZZA ZRHSvitfQVZZB ZRHS<<tfQV23A ZRHSx!!OV233 +ZRHS>tfOVZRA +ZRHS<'tfQVZRB ZRHSwtDVZRC +ZRHSvct fQV25A+ZRHSxt!QV253 +ZRHS<tlQV26A+ZRHSttfQV253 +ZRHS<<tfQV27A+ZRHS<;t!QV27B +ZRHS<<tfQV30A +ZRHSwtfOV303 ZRHSwHCV32A ZRHSvtlQV323 ZRHSPIQ<J33A +ZRHSwHQV33B ZRIIS)<HQV37A ZRHSntfQV373 ZRHS<<KOVRA DESCRZPTIOil RHR B TESTABLE CHECK VALVE VCH090-E-i!f7 RHR A SHT DN COOLING CHK VALVE RHR 3 SHT DN CCCLING CHK VALVE ZRHSNPDTISB RHR LCQP A TEST RETURN RHR LCQP A TEST RETURN RHR LGGP C TEST RETURN RHS LIhK A TO c.HSS-RFV1 RHS L.NE D TO 2l!SS-RFV1 RHS LiNE C TO Zl!SS-RiV1 2"ISS-<I~VI SPUTDKN I."NE A RHR P<t!P PlC SUCTION RHR HEAD SFPAY ISLN RHR SHT Q."t CLG SUCT XSQL RHR SHT DN CLG SUCT XSGL RHR SFRVICE NATFR CROSS TIE RHR SKRVXCE HTR CROSS TZE RHR H.E.A Stl'ELL-SIDE CUTLET RHR H.E.3 SHELL-SIDE GUTLET RHR DXSCHARGE TO RAD!lASTK RHR DISCHARGE TO RADIIASTE RHR A RKAC CNTIGIT SPRAY PHR 3 REAC CNT<nli SPRAY RHR 3 SHT DN COOLING SUCT RHR A STM LINK ZSQL RHP.3 STtf LXNE XSQL RKR A STH LINK XSO'.RHR B STtl LINK ISQL LPCI Xh<.KT A LPCZ Zii" ET B LPCX Xii" ET C RHP.A REAC CtlTICIT SPRAY RHR 3 REAC CHT!EIT SPRAY RHR H.E.A VENT TO SU?P POOL RHR H.E.B VENT TO SUPP POOL RHR H.E.A VEi!T TO SUPP PG L RHR H E B V<:NT TO SUPP PCQ'HR A R<N TO SUPP POOL ZSGL RHR B RTN TC SL;P POOL ZSQL RHR H E A FLOh TO RCIC RHR HE ED B FLGH TO RCIC RHR A SUPP POC'PRAY RHR B SUPP POOL SPRAY RHR H.E.A FLCH TO SL'?P POCL RHR H.E.3 FLCH TO,SUPP PCCL RHR A HIN FLQH BYPASS VKNQQR h<At!K ANCHCRIDARLZhG At!CHGRIDARLING ANCHCRIDARLING AiNCHCRIDARLIhG DRAGON VALVE COPIES-VU'AN COPIES-VIF CAN COPIES-VIF CAN Vc:LAN VELAN VKLAN VEL Ail CLOH VELAN V LAN h~CO V KLAN VKLAN V" LLI CLOH CORP CLCH CORP VKLAN VELAN VKLAN VELAN CLGH CGRP VELAN V LAN VELAN VEL Ail VELAN VELA'N VKLA<t VELAN VELA!l VELAN ViL"N.ViLAN VCLAN CLCH CORP CLCH CORP VFLAN KHG VELAN Vil.AiN VELAtl ViLAN ViLAN ENG.CO.SP C P303H P303H P303H P303H C15 C CG51!I C051!I C051H P30RE P30RE PSORE P30R P30RY P3GRR P30RR P30RR P3GRR P30RR P30RY P3GRY P30RR P3CRR P3CRR P3CRR P30RY P30RR P30RR P30RR P30RR PSGRR P3GRR P30RR P30RR P30RR P30R'R P30RR P30RR P30RR P30RY P30RY P30RR P30RR P30RR P30RR P30RR P3GRR P30RR ZONE PC289685 PC306711 PC250620 PC250628 SCZR0135 SC19511R SC215122 SC215122 PC305711 PC305712 PC30671Z PC2616R3 SC175111 SC"89155 PC2506ZR SC2R01R2 ABS17510 ABS17510 ABN17505 ABS1751G ADS175C9 ABS17 509 SC289155 SC289155 SC175111 SC215125 SC215129 SC175103 SC175111 SC209155 SC269155 SCc.89155 SCZ89155 SCZ69155 ABN19615 ADS196ZG ABiN19615 ABS19620 SC196113 SC195113 ABN17505 ABS17510 SC215122 SC215122 ABN17505 ABS17510 SC19611R ZZ f!RKF H H H H H H H H H H H h H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A*A A A A 100 100 100 6 100 100 100 100 100 100 100 100 6 6-100 100 100 6 6 6'00 100 100 100 100 100 100 100 100 100 100 100 100 100 CPCOD OPT DYS DYS DYS HRS DYS DYS DYS DYS OYS DYS DYS DYS HRS HRS DYS DYS DYS hRS HRS HRS DYS DYS 0 S DYS DYS DYS DYS DYS DYS DYS DYS DYS DYS DYS+=Regulatory Guide 1.97. PAGe 33 EQUIPtlENT XD ZRHSxHOVRC +ZRHS>PQVQCA +ZRHSt!!OVACB +ZRHSicHOV57A +ZRHSiittQY678 ZRHSicHQVSA ZRHSciPQYBB ZRHSxttOVBOA ZRHSxHOV808 ZRHS>HOV9A ZRHS~!!QV93 ZRHSxPT99A ZRHS'PT998 ZR tSqcQV126 ZRHSiSQV35A ZR'tS~SOV358 ZRHS>SQV35A ZRHSccSQV358 ZRHSc'SOV70A ZRHSccSQV708 ZRHS+SOV71A ZRHS-SQV718 +2RHSA'MOVlA +2RHS*MOV1B +2RHS*FT63A +2RHS*FT64A +2RHS*FT63B +2RHS*FT64B DiSCRIPTXON RHR C tlIN FLOH BYPASS RHR A SHT Dh CLG RETURN RHR 8 SHT ON CLG RETURN RHR A SHT ONCLG CV BYPASS RhR 8 SHT Dil CLG CV BYPASS RHR H.E.ElA BYPASS RHR H.E.E18 BYPASS Gi OBE VALVE GLOBE VAI.VE RHR H.E.A SHELL SICc, Xt!LET RHR H E 8 SHcLL SIDE ZtO cT RHS A STEAH SUPPLY RQQtt XCS RHS 8 STEA!ii SUPPLY ROON ICS ZR!tS<Ec'8 S!!P CROSS-TIE DRiN RHR A REAC SA!!PLZhS SYS XSOL V RHR 8 REAC SA!lPLIhS SYS XSOL V RHR A REAC SAPLING SYS ISQL V RHR 8 R AC SAHPLZNS SYS ISO'STEAtl LXhE CRAIii STEA!l LZiVE DRAIN STEAN LIhi ORAIil STEA!l LihE DRAIN RHS DMP PlA SUCTION RHS DMP PlB.SUCTION RHS A CONTAINMENT RHS A SUPP POOL RHS B CONTAINMENT RHS B SUPP, POOL VENDOR N"!!E VcLAN VELAN VELAN VELAN VcLAtt CLOil CORP CLOH CCRP VcLAN CLOH CORP CLOH CORP RQSEHCUiiT ROSEI!CUiiT TARGET RCCH CORP TARGET RQCil CORP TARGET RQC'cl CORP TARGET RO il CORP TARGET ROCH CORP TARGET PQCH CCRP TARGET RQCH CCRP TARGET RQ"H CCRP TARGET RCCH CQR?GLOW CORP GLOW CORP SPiC P30QR PBONR P30~R P30iR P30%R P3CQY P30QY PIC~Q P30tlo P3CQY P304Y C071!l C071H P3CQXP30%V P30tlX P3CQX P3OQX o30"V P30QX P30QX P3CQX P304Y P304Y.C071M C071M C071M C071M ZCNE ABS17508 SCZtt0140 SC200103 PC250620 PCZ305ZO AEN17505 ABS17509 SC213125 SC215129 ABi!19615 ABS19520 SC175105 SC215122 ABS17510 ABN17505 ABS17510 ABill7303 ABS17510 SC175103 SC1.75111 SC175103 S"175111 ZZ TREF H H H H H H H H H H H H H H H H H H H H H H OPCQO A A A A A A A A A A A A A A A A A A A A OPT 100 OYS 100 DYS 100 DYS 100 DYS 100 OYS 100 DYS 100 DYS 6 HRS 6 HRS 100 DYS 100 DYS 100 OYS 100 DYS 100 DYS 100 OYS 100 DYS 6 HRS 6 HRS+=Regulatory Guide 1.97. PAGE 34 EQUIPHENT IO+2RHS>RE1A+2RHSiiRE13 +2RMS+RElC +2RMS*RE1D DESCRIPTION REAC BLDG OH HATCH RADN RFAC BLDG DH HATCH RADN REAC BLDG IN H RADN REAC BLDG IN H RADN VEiNDDR NAHE HAltAN INSTH HAHAN INSTH KAMAN INSTM KAMAN INSTM SPEC ZONE ZI P281F PC2616W H P281F PC261699 H P281F P281F TREF CPCDD OPT+=Reguiato~Guide.'l.'97. PAGE 35 EQUXPttENT ZD 2RSSaFT106 2RSS-PT10S 2RSS-PT109 2RSS-PT110 ERSS-PTlll DESCRZPTXOH RCZC PttP DZSCH FLOH ADS ACCUttULATOR TAh7(PRESS ADS ACCLHL" ATORTAhN PRESS ADS ACCUttULATORTAHN PRESS ADS ACCmtULATORTAHN PRESS VEtiDOR hAatE ROSEl tOUHT ROSEtlOU:tT ROSEtiOUHT ROSEt!OUitT ROSEHOUi'tT SPEC ZOhE ZZ QREF C071H SC175105 H C071H SC289155 H C071t t SC289155 H C071H SC306175 H C071H SC306175 H OPCOD OPT PAGE 36 EOOIP}l=NT ID+eS S~HCVX60+esAs>Hcv161 ZSAS~HCV162 +esAs<Hcv163 DESCRIPTION SERVICE AIR CNTHT XSOL V SERVICE AIR CNTHT ISOL V ScRV~CE AIR CNTHT ISOL V SERVICE AIR CNTHT XSOL V VENDOR NAHE VELAN VELAN VELAN VELAN SPEC P304H P304H P304H P304H ZONE SCZ40135 SCZ69155 PC240503 PC289601 ZX TREF H H H H OPCOD OPT+=Regulatory Guide 1.97. PAGE 37 EQUIPHENT ID DESCRIPTIOil VENDOR NAVE SPEC ZONE ZI QREF OPCOD OPT ZSCV+Fi<<101A ZSCV~Ph" 3018 ZSCV>XO101A ZSCV+%<)301B GTS t!ISC 120/240V PhL GTS HISC 120/240 Pht.DIST XFt!R 600V-120/240V DIST XFHR 600V-120/240V BRO)LN BOVERI BROhN BOVERI SQUARE D SQUARE<<0 E014T ABNZ4033 H E014T ABSZ4036 H E011T ABN24033 H EOllT ABS24036 H PAGE 38 EIIUIFHENT ZD ZSFC<<AOV153 ZSFC<<AOV154 2SFC<<AGV19A ZSFC<<AOVI9B c.SFC<<AOV33A 2SFC: AQV33B 2SFC<<FT36A ZSFC<<FT36B 2SFC<<FT5SA c,SFC<<FT585 2SFC<<HV114 2SFC<<HV116 ZSFCciHV121 ZSFC<<HV148 ZSFC<<HV149 ZSFC<<HV17A 2SFC<<KV17B ZSF C<<HVISA ZSFC<<HVISB ZSFC<<HV35A c.SFC<<HV37A 2SFC<<HV37B ZSFC<<HV54A ZSFC<<HV6A ZSFC<HV6B 2SFC<<LS33A ZSFC<<LS33B ZSFC<<LS33C 2SFC<<LS33D 2SFC<<LS34A c.SFC<<LS34B 2SFC<<LS55A ZSFC<<LS55B 2SFC<<LT32A ZSFC<<LT32B ZSFCccHIA ZSFC<<tllB 2SFC<<PT3A ZSFC<<PT3B 2SFC<<PT30A FSFC<<PT30B ZSFC<<TF31A c.SFC<<TESA ZSFC<<TESB DESCRXPTIOil FILTER HDR ZhL ISOL VCH FILTER HQR ItiL ISOL VCH 2SFC-FLTlA OUTLET ZSFC-FLTlB OUTLET SKIN!IER SURGE TAhK LEVEL SK>t!!IcR SU4GE TAh".<LEVcL SF PQQ!.CLG SYS FLGH L SF PGQL CLG SYS FLCH L SFC Ft!P DXSCH FLCH SFC P!!P DISCH FLOH FUFL XFR CHAN GATE A DR V CASK HQLG XFR PU!!P SUCT CASK HDLG XFR PL>P DISCH V CASK GATK DRAIN VALVE GATE DRAIhS KGR ISOL VLV ZSFC-F1A BYPASS ZSFC-FlB BYPASS 2SFC-FlA XNLET 2SFC-FlB XNLET 2SFC-TKlA INLET V 2SFC-HT EXChGR DISCH V ZSFC-HT EXCKGR DISCH V SKIVJ!ER SURGE TAhK CUTLET SF PCQL CLG HTR XCOtlN SF FOO'LG HTR XCC'NN SKItD!EP.SURGE TAhK LEVEL SKIt!it!ER SURGE TAihK LEVEL SKIIOIER SURGK TA!FK LEVEL SKZID!ER SURGE TANK LEVEL SFC SKII!!IER SURGE TK HZ LVL SF POOL HTR LVL LOH SF POOL HTR LVL LCN SF PCQL SURGK TANK HATER LVL SF POOL SURGE TANK HATER LVL FUKL POOL CHC t!QTOR FUcL POOL CHC l!GTCR SF PGQL CIRC PP A SUCT PRESS SF PCOL CIRC PP B SUCT PRESS SF PQGL CIRC PNP DISCH PRESS SF POOL CXRC Pl!P DISCH PRKSS SF POOL SURGE TANK TEHP OUTL SF PGQL HT EXCH CUT TE!!P SF POOL HT EXCH OUT TEtIP POSX-SEAL PGSX-ScAL PCS I-SFAL POSE-SEAL POSI-SEAL POSI-SEAL ROSKHGUNT ROSEVQ'Ji!T ROSE!!CUNT XQ!!QX POSE-SEAL POSE-SEAL XC!!QX XG!ICX FGSI-ScAL PQSI-ScAL POSE-SEAc POSE-SEAL PCSI-SEAL I QSI-SEAL PCSZ-SEAL POSX-SEAL PQSI-SEAL POSZ-ScA HAGKKTRCL t!AGNETROL ttAGNKTROL t!AGt!KTROL tlAGNKTRQL VASNETROL HAGNcTROL t!AGNETROL RGSEt!CUNT RQS=!!CUNT GOULD PIPiP GOULD PU!!P RQS El!CUNT RGSKI!OWT RGSEi!O'-'NT RQScl!CUNT PYCO PYCO PYCO INTERN INTERN INTER.INTcR.iNTER.INTER.ZiNTER.INTER.XNTER.INTER.ZIITE.INTER.ZNTcR INTER~INTER.INTER.INTER.ZNTER.S INC.S INC.VEhTiGR NAKE SPEC P304D P304D P304D P304D P304D P304D C071H C071!I C021tt C071H P304K P304D P304D P304K P304K P304D P304D P304D P304D P304D F3040 P304D P304D P3045 P304D CC21L C021L C021L COZlL COZXL COZlL COZIL C021L C071!I C071tl P222X IZAAK C071H C071II C07ltl C021H C041D CC41D C041D ZCNE SCZS9162 Scc.89162 SC326193 SC3061.76 SC32S199 SC326199 SC215122 SC2151c.Z SC269162 SCZ89161 SC306182 SC328199 SC328199 SC306182 SC30618Z SC26916Z SC289161 SC269162 SC2S9162 SC328192 SC215122 SC215122 SC328193 SC269162 SC289161 SC328193 SC328187 SC328193 SC3c.8167 SC328193 SC3281S7 SC353202 SC353202 SC326197 SC328187 SC289162 SCZ69161 SCZ61145 SC261145 SC?61145 SCZ61145 SC3c.8193 SC21512Z SC215122 ZI QREF H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H H OFCOD GPT 100 DYS 100 DYS 100 DYS 100 OYS 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 0YS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS A 100 DYS PAGE 39 EQUIPHENT ID 2SLS>HCV)11 2SLSxt!OVIA 2SLS~!.OVID +ESLS+fOV5A+eS S~t.OV55 DESCRIPTION STBY LIQ TEST TK VALVE SEALEO GLOBE VALVE SEALED GLCSE VAL'VE STOP CHECK STOP CHECK VENDOR NAttE VELAN VELAN VELAN VELAN VELAN SPEC P30QL P30QS P30RS P300S P30RS ZONE SC289155 SCc.89155 SCc,89155 SC289155 SC289155 ZI QREF H H H H H OPCOD A A A A.A OPT 7 DYS 7 DYS 7 DYS 7.OYS 7 DYS+=Regulatory Guide 1.97. PAG 40 EQUXP¹NT XD ZSHP+AQVZOA ZShVwAOVZOB ZShPWAOVZZA ZShPNAOVZZB ZSiiPMAOV97A ZSHP+AOV97B ZS!VwttOV)5A ZSHP+t!QV15B 2Sl!Put!QV17A ZShPet!QV17B ZShPxt!OV18A ZSHo~t~OVIOB ZShV<!!OV19A ZShP+t!QV19B ZSHPat!OVZIB ZSHP+t!QV33A ZSHPiit!QV33B ZSHP+t!OV38A ZSl!PxttQV38B c.SHPat-!QV39A ZShP+ttOV39B ZSHP+HOV90A ZShPvt!QV90B ZSt&>PTXQOA ZSHP>PTXQOB'ESCRXPTXQil SHP TO RHSwPIA SL CLR SH?TO RHS<PIA SL CLR SHP FRO!l RHSKPIA SL CLR SHP FROH RHS>PXB SL CLR SHP FR CLG COIL ZHVRaUC413A SHP FR CLG COIL ZHVRIUCQ13B SVCE HTR TO ZHVRQUC403A SVCE HTR TO ZHVR<UCQ03B GATE VALVE GATE VALVE GATE VAI.VE GATE VALVE ShP TO CCP HT EXCH ISOL V SnP TO CCP HT EXCH XSCL V GATE VALVE BUTTERFLY OR TRICENTRIC VALVE BUTTERFLY QR TRXCENTRIC VA'LVE SHP TO RBCLCH SYS SHP TO RBCLCH SYS SHP TO RBCLCH SYS SHP TO RBCLCil SYS BUTTERFLY CR TRICENTRIC VALVE BUTTERFLY OR TRXCENTRIC VALVE SHP TO CCP HT EXCHS PRESS SnP TO CCP HT EXCHS PRESS VENDOR NAt!E XO!!QX XQt!OX XO!!QX XOt!OX XOHQX VELAN VELAN VELAN ENG VFLAH VELAN V LAil CLQH CORP CLC!l CORP VELAN Ct.Oil CORP CLPH CQRP VELAN VELAiN VELAit VELAN CLOH CORP CLOH CORP ROSE!!QU.'tT ROSEHQUNT SPEC P304H P30QH P30QH P304H P304H P30QH P30QR P304R P304R P30QR P30QR P30QR P304Y P30QY P30QR P304Y P304Y P30QR P30QR P30QR P30QR P304Y P304Y C071tl C071H ZO'l" ABN17504 ABS17509 ABN17504 ASS 17509 SC289155 SC289155 SC175105 SC195116 SC196113 SC175105 SC196113 SC196116 ABN21523 ABh21523 SC328197 ABti17505 ABS17510 SCc51145 SC261145 SC261145 SCc.61145 ABN17505 ABS17510 ABN17503 ABN17503 ZX TREF H H H H H H H H H H H H H H H H H H H H H H K H H OPCOD A A A A A A A A A A A A A A A A A A A A A A OPT 100 DYS 100 DYS 100 DYS 100 DYS CON CON 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS 100 DYS PAGE 41 EQUXPHEt(T XD 2VBS)Pt(LA105 2VBSNPHLA106 2VBS>FN'105 2VBSxPNLB106 DESCRIPTXON ttSLIV DIST PtiL(G/H)HSLIV DIST PNL MSLXV DIST FNL ttSLIV DIST PtiL(Y/H)VEhDOR NAt(E BROhN BOVERI BRONN BOVERI BROHH BOV RX BROhN BOVERX SPEC ZONE-E014T-ABN24033 ZX QREF E014T ABS24036 H E014T ABN24033 H E014T ABSZ4036 H OPCOD 0?T PAGE 42 Et!UXPHENT ID ZHCSW!!OV101 +'ZhCSM!!OV102 2¹SQtOVX03 ZhCSx!lOV104 ZnCSst!OV105 +EhCS>HOV112 +EhCS<t!OV200 ZHCS-tlCV106 ZhCS-HCV107 2hCS-HOV108 ZHCS-t!OV109 Zt!CS-tlOVX10 ZHCS t OV111 DESCRIPTION QhCU REAC VESSEL DRN PHCU P1A t'.P18 SUCT XSOLV RHCU XtiL ISOL V RHCU It!L FRO!l RECIRC 8 RnCU It!L FRO!!RECIRC A RnCU PXA~PXB SUCT ISOL V RhCU RETUPN ISOL R!i U DRn TO hASTE COLL TH V RhCU DXSCH TO NU CO!!D V DRN RESTRXCTIt!8 ORF BYP V RhCU REGEit HX DISCH V FLTR D!!!!LZR BYP V RliCU HX BYP V VENDOR hAHE VELAN VELAN VELAN VELAN'VELAN VELAN VELAN VELAN VELA!t VELAN'VELAN VELAN VELAN SPEC P304R P304R P304Q P304R P304R P304R P304P.P304R P304R P304R P304R P304R P304R ZOi!E PCZ61648 PCZ40606 PCZ40606 PC240508 PCc.40505 SCZ40142 HST26'46 SC305176 SC305176 SC306176 SC306176 SC306176 SC305176 ZI t!REF H H H H H H H H H H H H H C A C ,C C A C C C C C C 6 HRS 6 HRS OPCOD OPT+=Regulatory Guide 1.97. ~l:~ 12/Zic'84 REVZSZCN: 6<t ISS<JE DATE: l2 (2,[/$g h~?PZ-ENVZRG'N!EHTAL QUALIF CATION DATA MASTER LIST!NSSS)PAGE 9 ff<<%if%<<<<<<ff<f<f if ff ff<<<<<<<f<f<f<<<f<<<f<f<f<f<<if ff<f<<<<<<<<<<if<<f<f<<ff<f ff if<<<<<<<<<<<f<<<<<i<f<<<f ff ff V<<<<ff<f<<<f<f<f<<<<<f ff<f<f ff<fff<<off<<ff<<<<<<ff<f<<<f<f)f<<<f<r<f<<<<ÃI<f<f<<<<<<<<<<<<<<<<<<if<<ff<f<f<f<f<fuff<ff%<<Yc<f ff ff)f!f)f<f l!ARH ciC EQUIP?tcNT DE+CRTPTZGN EhJ.ECHE ECUALST GP TXl!E QUAL REF St<BC XD.ENVTYP GC R"ARMS Xt!STSTAT<f<f<f W<f<f<f<i<f<f r'f ff K ff ff ff ff<f ff<<ff<f<f r'f ff<f<f<<<f 4<f<f%<<<f)f<f%)f Riff ff ff<f ff ff<<<f ff ff<f ff)i<f<<<f<f<f<f<f<f<f Yr Yi?f ff<f<f<f<f<f<f<f ff<fÃ<f<f ff ff<f tf<f<f<f%<f ff)f<f<f<f<f ff<f ff<f<f ff<f ff<f ff)f<<<f ff ff<f<f<f<f Yc<f<<ff<f<f<f<f Vf%<f<f ff<f<f<f Vi<f<f ff C72-H050D ZISC~PT15D 82<.-H067L ZISC<<PT16A PRESSURE TRANS!!ITTER PRESSURE TRANSt!ITTER SC251145 SC261145 HARSH HARSH 10CD PGCCABM BZZ-t!067C ZXSC<PT168 PRESS<JRE TRAHStlZTTER SCc.61145 HARSH 100D PGOOABK 822-NO67R DISCEPT)6C FRESSURE TRANS?liTTER SCZ61145 100D PSOOABH BZ2-N0578 ZXSC<rPT16D PRESSURE TRANS!!XTTER SCZ61145 HARSH 100D P80QABL 822-HC94A ZXSC<<PT17A PRESSJRE TRANSt'!XTTER SC261145 HARSH 100D PGOOACS BZ?-NC948 ZZS<<P<178 PRESSURE TRANSMZTTER SC261145 1COD PSCOACT 822-H094E ZXSC<rPTX7C PRESSURE TRANSMITTER SC261145 HA'RSH 100D PGOOACU BZZ-NC94F ZZSC<rPT17D PRESSURE TRANS!!ITTER SC261145 HARSH 100D PGOOACV 822-H403A ZZSC+PTZA PRESSLRE TRANS'.!XTTER S 261145 ZM PSQOADC 822-cN403E ZXSC<PTZB PR"SSIB TRANS!!XTT R SC261145 HARSH ZM FSCQADE BZcZ-N4038 ZXSC<fPTZC 822-t!403F 2ISC<<PTZD PRFSS'JRE TRAhS!!ITTER PRESSURE TRANS!IITTER SC261145 SCZ6145 HARSH 8 2M Ztl PSOOADD PSOOADF 8"2-N078C ZISC<fPT4A PRESSURE TRANS!!XTTER 8C261145 HARSH 100D P800ACE 4~' 12/Zlr 8%RFVXSXON: Oj ISSUE DATE-!2,/g(te,jt lo!PZ-ENVIRONHENTAL QJALIFICATXON DATA HASTKR l.IST l NSSS)PAGE 12 r r j%%jj Cvrjjhjjj+jjjjjrjjjj.jjcjjjjjrcfjjjjjjjjNfif jjjfjrjr4fjj rjjjjjfjjjjjj rjjjfjr jr'rjjjf)jrjrjjjjjr jf jr jj jr jj jr jr'jrjgcrjjjr jj jCcfgjjjjjf jr jr jr jr (jjjjjrjjjrjj+jfjjhfjjjrrj jrcjgjrjf jjjjjjjjjjjjjjgjrgjjjjjrj.ji4cjrj j.jjrjrjrjjjjjjjjjjjj tQRH NO EQUIP.!EiNT OFSCRXPTXOiN Ei!V.ZONE KQUALST CP TX!!E QUAL REF S!LEC XD.EliVTYP OC R E!V.RHS Ll!STSTAT cr'j jj cr'j cj jrrj jr cj jr jj jj jr'j jj jj jj jj jj jc jt jj jf jj jj jj jj cj cr'j jf jr jj jr W cjrr'j jr jr'f cj jj jr jj jf jj jr'j jj jj jr jj jj cj jj r!jj Cj jj jj jj jr'j jj jj jj jj jr'j jr'r'j cr'j cj jf jj jr jj jf jj jc jf jc jj jj rr'j jj jr cj jr'c jr'r jr jj jr'r'i'j jj rr'j jr cc%jj~~jj jj jj jj jj jj rc rr jj jj jr'r jj jj jj jc jj jj jj jj jj 82Z-F013H 2!!SS<PSV121 SAFETY RELXEF VALVE PCZ89660 C 100D PBOOAAZ HARSH A B22-FD13F ZHSS jiPSVI 22 SAFETY RELZEF VAL'VE PC289680 C HARS'H 1000 PSOOr"AT 0" Z-F0130 ZHSSNPSV)23 BZc.-F013V 2l!SS jrPSV12%BZZ-F013S ZHSSccPSi j j 25 SAFETY RELXEF VALVE SAFETY RELIEF VALVE SAFETY RELXEF VALVE PC269560 PCZ69560 PC289660 C HARSH C HARSH 1000 A PSOOAAR 1DGD PSOOABD 10CD PBCOABF B22-F013H ZllSS~PSV126 SAFETY RELIEF VAVLE PCc.S9680" HARSH 10GD PSOOAAX BZZ-F013H ZHSSjcPSV127 SAFETY RELIEF VALVE PC289580 HARSH 1000 PGCOAAV BZZ-F013B c.HSSj'PSV128 SAFETY RELXEF VALVE PCZ896SO HAR'l 100D PSOOAAP BZZ-F013U c.HSSc PSV129 SAFETY RELIEF VALVE PCc.89560 HARSH 1000 PSOOABE BZZ-F 013R 2!!SS<PSV~30 B22-FD13J ZHSScrPSV131 SAFETY RELIEF VALVE SAFFTY RELXEF VALVE PC289660 PCZ69680 HARSH HARSH loCD PBOCABC 10OD PSCO""H BZZ-F013G ZHSSc'PSV132 BZZ-~013A Zl!SScPSV133 8" 2-F013N c.HSSrrPSV13% SAFETY R LIEF VALVE SAFETY RELIEF VALVE SAFETY RELIEF VALVE pc2695eo PC209580 PC269666 HARSH HARSH 1OOD PGOOAAU 1000 PBOOAAO A 10CD PSOOABA 0 NINE MILE POINT-UHIT 2 DOCKET NUMBER 50-410 QUAL REF I C071MBF REV 0 SYSTEM COMPONENT EVALUATION NORK SHEET.PASE 1 OF 1 13-Dec-84~~~~EQUIPMEHT DESCRIPTION a a a a a a a a ENVIRONMENTAL COHDITIOHS AND QUALIFICATION a a a a a e sEQUIP HO.s 2SFCwFTSBB sSPEC NOas C071M aSYSTEM: e SPENT FUEL POOL CODLING a a e TYPE: (DESCRIPTIOH) l FLO)t TRANSMITTER a a a a lMAHUFACTURERs ROSEMOUNT a a lMODEL NOa s 1153 a a eSAFETY FUNCTION: s TO MOHITOR SPENT FUEL POOL e DISCHARGE FLOM a a eOP CODEs A a a a a a e sACCURACY"" HDTE 5 s SPECs 0.25X DEMDs 4.85X a a t ZONE NO.s SC289161 lFLOOD LEVEL I ELEVATIOHs HA)ABOVE FLOOD l LEVEL?NA eABOVE SPRAY/l iFRO'IH LEVEL?NA a a a DOCUMENTATION ACCEPTABILITY: lACCEPTABLE 70 HUREG 0588,CATI a a e a a a a eNIHT/SURVEILL ---l REFERENCEs 2 a a sQUALIFIEO LIFE--" lYEARS)$10 ei REFERENCEs 2 a a I DOCUMENT REFERENCE a e a PARAMETER i SPECIFIED a QUALIFIED e a QUAL eMARGIHe a a e VALUE i VALUE I SPECIFIED e QUALIFIED a METHOD i DEMO e REMARKS a a a a a a a a a a a a a a a a a a a a saOP TIMEs e 100 DAYS e 655 DAYS e 3'eTEST IDEHT l YES eTEMP (F)'-----'----'----'----'----'--'NOTE I s I NORMAL e e120/108 ei 120 ei 1 I 2 e eTEST-IDENT a eHA e eNOTE 2 e es ABNORMAL al HA s'A e e1 i'e TEST-IDENT l HA ee e e ACCIDENT e 175 a 303 s 1 s 2)TEST-IDENT e YES sPRESSlPSIG)' -"--'"---'----'----'--""'--'NOTE 1 el NORMAl.s-0.25 l ATMOS l I l 2 lTEST-IDENT l HA ls ABNORMALe HA a HA l 1 I 2 aTEST"IDENT a HA e le ACCIDENTe 2.8 e 55 s I I 2 e7EST-IDENT s YES e leRH lX)s a I a s a s s HOTE I eea NORMAL e 50 e 95 i'l e2 aTES7-IDEH7 ea HA l ss ABHORMALl N l NA l I s 2 sTEST IDENT I HA e al ACCIDENTa 100 s 100 l 1 s 2 eTEST IDENT s HA IRADIATION'


'----'----'----'----'--'NOTE 1 eia tiORtl GAMMAl 1.3E6 ei s 1 I 2 aTEST-IDENT e HA e NOTE 4 ae ACC GAMMA I 2 6E6 I s 1 ei 2 aTEST-IDENT e YES e NOTE 4 ee NORM BETA I NA e es 1 s e2 e TEST-IDENT e eNA e eNOTE 3 sa ACC BETA a 1~3E7 s 1 a 2)TEST-IDENT l HA a NOTE 3 le HEUTROH I NA a s 1 e 2 e7EST-IDEHT s HA a taSPRAY e NA e YES a a 2 a e HA eeSUBMERGENCEl NA l HA e a a tN e a a a a a a a a a a a a a a a ls DOCUMENT REFERENCEs HOTESs 1~FOR COMPLETE ENVIRONMENTAL CONDITIONS,l ll 1.EQUIPMEHT QUALIFICATION ENVIROtiMENTAL DESIGN SEE THE DOCUMENT REFERENCED.

CRITERIA, EQEDC-I, REV 1, MAY 2, 1984'.HORNL TEMPERATURES ARE SHONH AS ll 2.VENDOR ENVIRONMENTAL QUALIFICATIOH REPORT, NX DESIGN/AVERASE.

SDDF 0 IEEE 07.131-5000A 3.UHI7 IS COMPLETELY SEALED.THERE IS ae 3~EQUIPMEHT OPERABILITY TIME DATA SHEETs HO EFFECT OF BETA RADIATIOH DN THE a a tLater)'RANSMITTER.

4.VENDOR IRRADIATED THE TRANSMITTERS Ill FOR COMBINED VALUE OF ACCIDENT AHD HORMAL RADIATION LEVELS.S.SPEC ACCURACY INCLUDES OHLY THE EFFECTS OF LINEARITY, HYSTERESIS AND a a REPEATAB IL I 7 Y.a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a

NINE MILE PDINT-UNIT 2 DOCKET NUMBER 50-410 QUAL REF 8 C071t(BG REV 0 SYSTEM COMPONENT EVALUATION NDRK SHEET PAGE 1 OF I 13-Dec-84~g>>>>~ENVIRONMENTAL COHDITIOHS AHD QUALIFICATIOH EQUIPMENT DESCRIPT ION I DOCUMENT REFEREt(CE-I I PARAMETER I SPECIFIED I QUALIFIED I I QUAL IMARGINI I VALUE I VALUE I SPECIFIED I QUALIFIED I METHOD a DEMO I REMARKS sEGUIP HO.: ISPEC HO,: ISYSTEM: I SPENT FUEL POOL COOLING I I I TYPE: (DESCRIPTION) a LEVEL TRANSMITTER I I I I IMANUFACTURERl ROSEMOUNT I I I MODEL HO.: 1153 I I ISAFE'TY FUNCTION)I TO MONITOR SPENT'UEL POOL I LEVEL I I (OP.CODEl A I I I I I I IACCURACY--HOTE 5 SPEC: 0'5X DEMO)3.IX I I OZONE HO.)SC328187 (FLOOD LEVEL I ELEVATIOtl:

NA IABOVE FLOOD I LEVEL?HA IABOVE SPRAY/s iFROTH LEVEL?HA I I I DOCUMENTATION ACCEPTABILITY)

IACCEPTABLE TO NUREG 0588,CATI I I I I I I I I IMAINI'/SURVEILI.

-"-s iREFEREHCE:

2 I I IQUALIFIED LIFE (YEARS)l 10 e iREFEREHCEl 2 11 I I I I I I I I I I I I I I I I I I I I OP TIME'100 DAYS I 655 DAYS I 3 I 2 I TEST IDENT I YES ITEMP (F)'-----'----'----'-"--'---"'--'NOTE 1 I ss NORMAL I 104/89 I 120 I I I 2 ITEST-IDEHT e HA I HOTE 2 ee ABHORMALe 133 I HA I 1 I 2 ITEST-IDENT I NA I se ACCIDENTI 175 I 303 I I'2 ITEST IDENT I YES I IIPRESS(PSIG)I


'I-----I-----I-----I-----I---I-NOTE 1 al NORMAL I 0 25 I ATMOS I I I 2 iTEST IDENT I HA I II ABNORMALI NA I NA I 1 I 2'TEST IDEHT I'NA I ss ACCIDENTe 2.8 I 55 I 1 a 2 ITEST-IDENT I YES I IRH (X)'I NOTE 1 I I I I I I al NORMAL I 50 I 95 I I I 2)TEST IDENT I HA s sl ABNORHALI HA I NA I I I 2 ITEST IDENT a NA I II ACCIDEHTI 100 I 100 I 1 I 2 ITEST-IDENT I HA IRADIATIOH'


'----'----'----'----'--'NOTE I ai NORM GAMMA'I I~BE3 I I I 2 ITEST IDEHT I HA I NOTE 4 ta ACC GAMMA I 2.6E6 I I I I 2 ITEST-IDENT I YES I NOTE 4 la HORN BETA I NA I I 1 I 2 ITEST IDEHT I HA NOTE ls ACC BETA I 1.3E7 I I I I 2 ITEST-IDENT I HA s NOTE 3 el NEUTRON I HA I I 1 I 2 ITEST IDENT e HA IISPRAY I HA I YES I I 2 I I HA I IISUBMERGENCEI NA I NA I I I s HA s I I I I I I I I I I I I I I I I I I I I I I I I II DOCUMENT REFEREHCE:

NOTES'~FOR COMPLETE EHVIROHMENTAL CONDITIONS,I ls 1.EGUIPMEHT QUALIFICATION EHVIRONMEHTAL DESIGN SEE THE DOCUMENT REFEREHCED.

se CRITERIA, EQEDC-l, REV 1, MAY 2, 1984.2 ABNORMAL TEMPERATURES ARE SHO)(H AS I I 21 VEHDOR ENVIRONMENTAL QUALIFICATIOH REPORT)MAX DESIGN/AVERAGE.

SDDF 0 IEEE 07.131-5000A 3.UHIT IS COMPLETELY SEALED.THERE IS el 3.EQUIPMEHT OPERABILITY TIME DATA SHEET)HO EFFECT OF BETA RADIATION ON THE I I (Later)TRANSMITTER.

4~VENDOR IRRADIATED THE TRANSHITIERS FOR COMBINED VALUE OF ACCIDENT AND NORMAL RADIATIOH LEVELS.5.SPEC ACCURACY INCLUDES ONLY THE EFFECTS OF LINEARITY)

HYSTERESIS AND REPEATABILITY

~I I

NINE NILE POINT-UNIT 2 DOCKET NUNBER 50-410 QUAL REF 4 E015HAA REV 0 EQUIPNENT DESCRIPT IOH SYSTEN CONPONENT EVALUATION MORK SHEET PAGE 1 OF 1 ENVIRONMENTAL COHDITIONS AND QUALIFICATION 10-Dec-84 I I I I I I DOCUNEHT REFERENCE I=-"==""="=""""=======""""===-"""=" I'ARANETER i SPECIFIED a QUALIFIED I QUAL NARGIH a I VALUE I VALUE a SPECIFIED I QUALIFIED I NETHOD I DENO I RENARKS I IEQUIP HO 2EPS4SMGOOI 11 I~I I I I~I I I N1O I~aSPEC HO.)E015H" I IOP.TINE: I 100 DAYS I 100 DAYS I 3 I 2 a AN+DATA a YES I NOTE 3 I ISYSTEN: asTENP (F)'-----I-----a-----I---"-I-----I---I-NOTE I (EPS SMGR)ENERGEHCY) 13'KVII HORNAL I 104/89 I 104/95 I 1 I 2 I TEST SIN I HA I NOTE 2 I I ITYPE)(DESCRIPTION) l15 KV)1000 NVA NETAL CLAD ISMITCHGEAR I I INANUFACTURERl BROMN-BOVERI I I siNODEL HO,l HK-1000 I I ISAFETY FUNCTIOH: ITRIPPIHG OF RCS PUNPS AHD NVP IPENETRATION PROTECTION I I IOP.CODE)A I I IACCURACY--ii SPEC: NA DENO: HA IZONE NO.: ABH24033 IFLOOD LEVEL I ELEVATION:

HA IRBOVE FLOOD LEVEL?NA IABOVE SPRAY/I FROTH LEVEL?HA I I I DOCUNENTATIOH ACCEPTABILITY:

II ABNORNALI NA l48 HRS Q(26(1 I 2 I TEST-SIN I NA I 11 ACCIDEHTi NA I I I I 2 I HA I NA I I'PRESS(PSIG)'

-""-'----'----'"---'----'--'NOTE 1 11 NORNAL I"0'5 MG I ATNOS I 1 I 2 I TEST SIN I NA I sl ABHORNALI HA I HA I I I 2'HA I HA I a I RCCIDEHTI NA I NA I I I 2 I HA I NA I aaRH tX)'I I I I I I t(OTE 1 Il NORNAL I 50 I 90 I I I 2 a TEST SIN I NA I ABNORNALI NA I HhI NA I NA 11 ACCIDENTI HA I NA t 1 I 2 I HA I NA I 1(RADIATION)

I" a I"" i I I a HOTE I ts NORN GANNha I,BE3 I 1 I 2 t HA I HA Ia ACC GANIIA I 2.2E4 I I I I 2 I TEST-SIN s YES I 11 NORN BETA I NA I I I I 2 t NR I NR I al RCC BETA I NA I I 1 I 2 I NA I NA lt NEUTRON I HA I t 2 I NR I NA 1.0E5 CRITERIA)EQEDC"I, REV 1)NAY 2)1984'~NORNAL TEMPERATURES ARE SHOMN AS 2a VENDOR ENVIROHNEHTAL QUALIFICATION REPORT)NAX DESIGN/AVERAGE.

11 SDDF N IEEE (.330-50003C 3.BASED OH THE ARRHEHIUS CURVES IH REF ss 3.EQUIPNENT OPERABILITY TINE DATA SHEET: 2 A(.L MATERIALS IH THE SMITCHGEAR SHOMa LTR QUALIFIED LIFE SUBSTANTIALLY LONGER I THAN 40 YEARS t 100 DAYS AT AVERAGE I 1(SPRAY I NA I I I I Hh I Hh saSUBNERGENCEt HA I I s NA I HA I I I I I I I I I I I I I I I I I I I I I I ll DOCUMENT REFERENCEl NOTES: 1.FOR CONPLETE ENVIRONNEHTAL CONDITIONS,a II 1.EQUIPNENT QUALIFICRTION EHVIROHNENTAL DESIGH SEE THE DOCUNENT REFERENCED a IACCEPTABLE TO NUREG 0588,CATllll TENPERATURE OF 95F TO MHICH THE SMGR IS QUALIFIED BY VENDOR.SIHCE HNP2 SMGR IS OPERATED AT 89F, RATHER THAN 95F)AS QUALIFIED, ADDITIONAL ll OPERATIOH TINE BEYOHD 100 DAYS POST" INAIHT/SURVEILL

"--ACCIDENT IS AVAILRBL.REFERENCEl 2 I I IQUALIFIED LIFE"--I (YEARS)l 40 REFERENCEl 2 11 I I I I I I l sI I I 4,VENDOR TESTED VAI.UE INCLUDES CONBIHED I VALUE OF BOTH ACCIDENT AND HORNAL RADIATION VALUES~

0 e NIHE NILE POINT-UNIT 2 DOCKET HUNGER 50-410 QUAL REF 4 E015HAB REV 0 SYSTEN CONPOHENT EVALUATION WORK SHEET PAGE OF 10-Dec-84~>>~ENVIROHNENTAL CONDITIONS AND QUALIFICATION EQUIPNEHT DESCRIPT ION I I I I I I DOCUNENT REFERENCE'=============================

PARANETER'PECIFIED'UALIFIED'URL'HARBIN'EHARKS I I (EQUIP NO~'.sSPEC HO.: sSYSTEN: 2EPS+SWG002 E015N VALUE I VALUE I SPECIFIED I QUALIFIED I NETHOD I DENO I I I I I I I I I I I I I I I I I I I I I I IIOP.TINE:

I 100 DAYS I 100 DAYS I 3 I 2 I AHtDATA a YES I NOTE 3 IITENP (FI: I-----I-----I-----I-----I-----I---I-NOTE 1 IEPS-SMGR)ENERGEHCY, 13.8 KVII NORNAL I 104/89 I 104/95 I 1 I 2 I TEST-SIN a NA a NOTE 2 I I I TYPE: (DESCRIPTIOHI sl5 KV)1000 NVA NETAL CLAD ISWITCHGEAR I I lNAHUFACTURERl BROWN-BOVERI I I INODEL Ho,l HK-1000 I I ISAFETY FUNCTION'TRIPPING OF RCS PUNPS.AND NVP IPENETRATION PROTECTION I I IOP.CODE: A I I I I I I IACCURACY--SPEC: NA DENO: HA I I aZOHE HO.: ABH24033 IFLOOD LEVEL I ELEVATIOHl HA (ABOVE FLOOD I LEVEL?NA (ABOVE SPRAY/I FROTH LEVEL?HA I I I DOCUNEHTAT ION ACCEPTABILITY'1 ABNORNAL(HA 148 HRS Q(26(I (2 I TEST-SIN I HA I 11 ACCIDENT(HR I-(1 I 2 I HA I HA IPRESS(PSIGII


t-----'---"'"---'----'--'HOTE 1 ss HORNAL I-0'5'G I ATNOS a I I 2 I TEST-SIN I NA I II ABHORNALI NA I NA I 1 I 2'NA I NA I II ACCIDENTI HA a HA I 1 I 2 I HA I NA a>>))))IV)~NOTE I I I I I I 11 NORNAL I 50 s 90 I 1 I 2 I TEST SIN I HA I la ABNORNALI NA I HA I 1 s 2 I HA I HA a 11 ACCIDEHTa NA I HA (1 I 2 I HA I NA I I aRADIATION

~I I I t I I I NOTE I 11 HORN GANNAI 1'E3 I 1 I 2 (HR I HA (11 ACC GANNA s 2.2Eh I 1,0E5 I I s 2 I TEST-SIN I YES t sa HORN BETA a HA I s 1 I 2 I HA I HA I la ACC BETA I HA I I I 2 I NA I NA I la NEUTRON'HA I 1 I 2 I HA t HA I 1(SPRAY I NA I I I s NA I HA HOTE 4 IISUBNERGEHCE(HA I I I I HA I HA I I I I I I I I I I I I I I I I 11 I I I I I I I ta OOCUNEHT

REFERENCE:

NOTES: 1.FOR CONPLETE ENVIRONNENTAL CONDITIONS,I II 1.EQUIPNENT QUALIFICATIOH ENVIRONNENTAL DESIGN SEE THE DOCUNENT REFERENCED, CRITERIA)EQEDC 1)REV I)NAY 2)1984~2.NORNAL TENPERATURES ARE SHOWN AS sl 2.VENDOR ENVIRONNEHTAL QUALIFICATIOH REPORT)NAX DESIGN/AVERAGE.

SDDF I IEEE (.330-50003C ABASED OH THE RRRHEHIUS CURVES IN REF la 3~EQUIPNENT OPERABILITY TINE DATA SHEETS 2 ALL MATERIALS IH THE SWITCHGEAR SHOWI II LTR QUALIFIED LIFE SUBSTRHTIRLLY

).O(IGER I la THAH 40 YEARS t 100 DAYS AT AVERAGE t IACCEPTABLE TO HUREG 0588)CATIlea TENPERATURE OF 95F TO WHICH THE SMGR I I I I I I I I (HA IHT/SURVE ILL REFEREHCE:

2 I I IQUALIFIED LIFE---(YERRSI: 40 I

REFERENCE:

2 I)IS QUALIFIED BY VENDOR.SINCE NNP2 II SMGR IS OPERATED'AT 89F)RATHER THAN I 1(95F, AS QUALIFIED)

RDDITIOHAL OPERATION TINE BEYOND 100 DAYS POST-I 11 ACCIDENT IS AVAILABLE tl 4~VENDOR TESTED VALUE INCLUDES CONBIHED I I I VALUE OF BOTH ACCIDENT AND HORNAL I I RADIATIOH VALUES.I I I I 11 I I I I I I I II I I I I I I I I I I I I I

NINE NILE POINT-UNIT 2 DOCKET HU)tBER 50-410 QUAL REF 4 E015NAC REV 0 SYSTEM CO)tPONENT EVALUATION MORK SHEET PAGE 1 OF 1 10-Dec-84~~ENVIRONMENTAL COHDITIONS AHD QUALIFICATION EQUIPNENT DESCRIPTION I I I I I I DOCUMENT REFERENCE a I 1 t==============================)

)PARA)tETER I SPECIFIED l QUALIFIED s QUAL atthRGIHI REMARKS I I IEQUIP NO.: eSPEC NO.l lSYSTEN: 2EPS<SM6003 E015H VALUE l VALUE I SPECIFIED l QUALIFIED l METHOD l DEMO l I 11 I I I I I I I I I I I I I I I I I I IlOP,TINE:

I 100 DAYS I 100 DAYS I 5 I 2 I AN>DATA I YES 1 NOTE 3 IITEHP (F)'I I I I" I a NOTE I IEPS-SMGR)E)IERGEHCY) 13.8 KVII NORMAL I 104/88 I 104/95 I 1 I 2 I TEST-SIN I NA I NOTE 2 I ITYPEt (DESCRIPTION) 115 KV, 1000 llVA ttETAL CLAD lSMITCHGEAR I I IHANUFACTURERl BROMH-BOVERI I I tttODEL HO.: HK-1000 I I ISAFETY FUHCTIONl aTRIPPING OF RCS PU))PS AND NVP IPENETRATION PROTECTION I I lOP.CODEt A I I I I I I IACCURACY--1 SPEC: HA DEMO: Hh I I)ZONE HO.l ABN24036 aFLOOD LEVEL I ELEVATION:

tlA IABOVE FLOOD LEVEL?Nh)ABOVE SPRAY/I FROTH LEVEL?HA I I IDOCUNENTATION ACCEPTABILITY:

I l ABNORMAL)NA l46 HRS 81261 I I 2 1 TEST-SI)t I NA I l l ACCIDENTI NA a-I 1 I 2 a HA I HAPRESS(PS16)'


'----'----'----'----'--'NOTE 1 al NORMAL I-0'5'6 I ATMOS l 1 I 2 I TEST-SIN l NA 1 as ABHORHAL)HA I NA I 1 I 2'HA I NA I sl ACCIDEHTI NA I NA a I l 2 I HA I Nh I I I III e I NOTE I I I I I I I I NORMAL I 50 s 90 1 1 I 2 I TEST-Sill I Nh s 11 ABNORHALI NA I HA l 1 s 2 I HA s Hh I a I ACCIDENT)HA I HA I 1 I 2 I NA I Hh I I IRADIATIOH'

--"--t-----a---"" I-----l-----a---l-NOTE I al NORM GAMMA)I,BEE I 1 I 2 I Nh l Nh ss ACC 6AKHA a 2'E4 s 1 OE5 I 1 s 2 I TEST Silt I YES a aa NOR)l BETA I HA I 1 l 2 l Hh l Nh 11 ACC BETA a NA l I 2 I HA I NA 11 NEUTRON a HA I I 1 I 2 I Hh I HA I IISPRAY I Nh I I I l Hh I Hh NOTE 4 saSUBHER6ENCEs Hh I I Nh s NA s I I I<u)IQVV'I ss I~I I I I I I I aSPEC HOil E015N'eOP1TINEl l (00 DAYS I 100 DAYS I 3 I 2 I AHtDATA a YES I NOTE 3 s (SYSTEl(: TEMP (F)'--"--'----'----'--"-'----'--'HOTE 1 eEPS-SM6R, EMERGENCY, 13.8 KVI(HORNAL'104/88 I 104/95 l 1 a 2 I TEST-SIN a NA I NOTE 2 I I ITYPE: (DESCRIPTIOH) 1 15 KV, 1000 NVA NETAL CLAD (SMITCHGEAR I I lNANUFACTURER)

BROMN-BOVERI I I (NODEL NO,l NK-1000 I I ISAFETY FUNCTION: ITRIPPIH6 OF RCS PUNPS AND NVP lPENETRATION PROTECTION I lOP, CODEl A I I I I I I lACCURACY-" l SPEC: NA I DEl(0: HA I I (LONE HO.l ABN24036 (FLOOD LEVEL I ELEVATION:

NA (ABOVE FLOOD l LEVEL?HA IABOVE SPRAY/11 ABNORMAL(NA l48 KRS (1(2(st 1 l 2 I TEST-SIN l NA I ll ACCIDENT(NA l-l 1 I 2 I KA I HA I l(PRESSlPSIG)l


1----" I-----I-----I----" t---I-NOTE 1 ls KORNAL l 0125 M6 l ATMOS I 1 i 2 I TEST SIN s NA I 11 ABNORl(ALI HA I NA I I l 2'HA I HA I 11 ACCIDENT(HA l KA I 1 I 2 a HA I NA IRH (X)'-----I-----'----I-----'----'--I-NOTE 1 la NORNAL I 50 t 90 I I l 2 l TEST-SIN I NA al ABNORNALI NA I HA.I 1 I 2 i KA I NA I tl ACCIDENT(HA I KA I 1 l 2 I HA I NA l t (RADIATIONS a"-"--I-----I-----I-----a-----I---I-NOTE I as HORN GANNAa 1.863 I I 1 l 2 I HA l HA 11 ACC 6ANNA l 2 2E4 I 1.0E5 I 1 e 2 I TEST-SI)(l YES I aa NORN BETA I HA I I 1 I 2 a HA l HA I 11 ACC BETA t NA l I I l 2 t NA I NA 11 NEUTRON l HA I a 1 I 2 a HA l HA atSPRAY s NA I I I I NA a HA I t(SUB)(ERGENCE(HA I I l NA a NA I NOTE 4 ll 1.EQUIPNENT QUALIFICATIOH ENVIRONNEHTAL DES16N , SEE THE DOCUMENT REFERENCED.

CRITERIA)EQEDC 1)REV 1)NAY 2)1984~2.NORNAL TEMPERATURES ARE SHOMH AS aa 2.VENDOR ENVIRONMENTAL QUALIFICATION REPORT, NAX DESI6N/AVERAGE:

iiii SDDF I IEEE 1.330-50003C 3,BASED ON THE ARRHENIUS CURVES IN REF I I I 11 I I I I I I I I I I I I I I I I I I I ls DOCU)(ENT

REFERENCE:

NOTES!1.FOR CONPLETE ENVIRONNENTAL COHDITIOKS,I s FROTH LEVEL?HA EQUIPMENT OPERARILITY TINE DATA SHEET: 2 ALL NATERIALS IH THE SMITCHGEAR SHOM(LTR QUALIFIED LIFE SUBSTANTIALLY LONGER s IDOCUNEHTATION ACCEPTABILITY' i THAN 40 YEARS i 100 DAYS AT AVERAGE I (ACCEPTABLE TO KUREG 0588,CATllas TENPERATURE OF 95F TO MHICH THE SMGR IS QUALIFIED BY VENDOR.SINCE KNP2 SM6R IS OPERATED AT 89F, RATHER THAN I I 95F)AS QUALIFIED)

ADDITIOHAL OPERATION TINE BEYOND 100 DAYS POST-tNAIHT/SURVEILL

"--I

REFERENCE:

2 lQUALIFIED LIFE---I (YEARS)l 40 REFEREHCEl 2 I I I I I I ACCIDENT IS AVAILABLE.

I 41VEHDOR TESTED VALUE INCLUDES CONBINED I VALUE OF BOTH ACCIDENT AND NORNAL RADIATION VALUES~I I 1 1 I I 11 I I I I (I I I I I lt I

HlHE MILE PDIHT-UHIT 2 DOCKET NUMBER 50-410 QUAL REF 0 PBOOABQ REV 0<<s SYSTEN COMPONENT EVALUATION HORK SHEET PAGE 1 OF 1 20-Dec-84.

~<<<<I<<I g<<>><<al Ral>>~<<<<I<<I jg<<p<<<<5 1 N ENVIRONMENTAL CONDITIONS AHD QUALIF ICAT ION t EQUIPMEHT DESCRIPT IOH I I (---ccaios ae Rsc<<0 5$I (EQUIP HO: B22-N073C LSPEC HO,: aSYSTEMl a HUCLEAR BOILER (TYPE)(DESCRIPTIOH)

I LEVEL TRANSNITTER)MANUFACTURER:

RDSEMDUHT IMDDEL HO.: 11536, ISRFETY FUNCTIONS I REACTOR l(ATER LEVEL-a SAFEGUARDS ACTUATIOH tOP.CODEl A I I I I IRCCURACY"-(NOTE 4)a SPEC;>/-BX DEMOl=<t/-GX I I (ZONE Ho.l SC261145 IFLOOD LEVEL I ELEVATIOH; HA)ABOVE FLDOD ie LEVEL'?HA IABOVE SPRAY/I FROTH LEVEL'?HA t e iDOCUMEHTAT ION ACCEPTABILITY' HUREG 0588,CAT I QUAL IF I CAT IOH IN PROGRESS l(NOTE 3)I I IMAIHT/SURVEILL

---

REFERENCE:

LATER I I sQUALIFIED LIFE---(YEARS)t LATER REFEREHCE:

I I I I Il I'DOCUMENT REFERENCE<It PARAMETER I SPECIFIED I QUALIFIED I t QUAL tNRRBIHI REMARKS I I I I II (I t a HOTESc (CONTINUED) sl 5.NORMAL RHD ABNORMAL TEMPERATURES lsi ARE SIMULATED BY ACCELERATED AGING sa AS DOCUNENTED IH REFERENCE 2~ll I I I I I I I I I I 11 I I I I ll THE DEVICE AHD FOR THE MOST LINITIHB CONTRIBUtOR (I.e.',RRDIATIOH)

TO IHACCURACY.

VERIF I CAT ION OF a ACCEPTRBILITY OF DEVICE APPLICATIOH I MILL BE, COVERED UNDER A SEPARATE a PROGRAM'USIHB THE PROPOSED METHODS OF I THE LICEHSIH6 REVIEH GROUP ll (LRG"ll)e SETPOIHT NETHODOL06Y PR06RAN.THE RE-a SUL.TS OF THIS SEPARATE PROBRAN HILL BEI ISSUED PEHDIHG HRC(IC6B)APPROVAL OF'THE LR6 SETPOIHT.I I I VALUE I VALUE I SPECIFIED I QUALIFIED I METHOD I DEMO I Ie I I I I I I I<zs I slOP~TIMEc I 100 DAYS s 100 DAYS s 3 I 2 I AN t DATA I YES LITEMP (F)~I I I t I I I NOTE I sl NORMAL I 85 I SEE HOTES I 1 I 2 I TEST-SIM I HA I NOTE 2 ls ABHORMALL 87 I SEE NOTES I 1 i 2 I TEST SIN I HA I NOTE 5 ea ACCIDEHTI 200 I 318 I I I 2 s TEST SIM a YES ssPRESS(PSIG)I


I--"--I-----I-----I"""--I---I-NOTE 1 II HORMAL a AT)LOS a ATMOS I I I 2 a TEST"SIN I HA I as ABHORMALI ATMOS I SEE BELON I 1 I 2 I HA I HA I ls ACCIDENT)2,8 I 63 I 1 a 2 I TEST-SIM I YES I I'RH (X)'-"---I"-""-'---" I"-"--'""--I---I-NOTE I II NORMAL I 50 I SEE BELOH I 1 t 2 I HA I HA I ta ABNORNALI 50 I SEE BELON I 1 I 2 I HA a HA a et ACCIDEHTt 100 I STERN/100 I 1 I 2 I TEST SIM I=HA I slRADIATIOH'

--""-I-----L-----t-->>-" I---"-I---s-HOlE I ts HORN GANMAI 7.7E5 tIHCL BELOH s I I 2 a HA'HR I Iia ACC GAMMA I 2.6E6 I 2'E7 I I I 2 I TEST-SIN I YES I II HORN BETA ,'A I SHIELDED t I I 2 (HA l HA II ACC BETA a I 6E7 I SHIELDED I 1 I 2 I NA I'A II HEUTROH L HA l iHA I't 2 I HAA I I(SPRAY I HA I HA I I I)IA I HA I IISUBMERGEHCEI HA I HA I I HA I HA I I==I I II I I I I I I I II DDCUMEHT REFEREHCE'OTES:

1~FOR COMPLETE ENVIRONMENTAL CONDITIONS)I lt 1 EQUIPMEHT QUALIFICRTIOH EHVIRONNEHTAL DESIGN SEE THE DOCUMENT REFERENCED.

a It CRITERIAI EQEDC-Ir REV Is MRY 2s 1984.2.NORMAL TEMPERATURES ARE SHONH AS I I I 2 VEHDOR ENVIRONMENTAL QUALIFICRTIOH REPORTs MAX DESIGN/AVERA6E.

Ie SDDF 5 3.QURLIFICATIDH DOCUMEHTATIOH IH I 1(3 EQUIPMEHT OPERABILITY TIME DATA SHEET'ROGRESS.

SCHEDULED PUBLICATION IS FEBRUARY, 1985.4,THE ACCURACY IS EXPRESSED AS'PERCENTAGE OF THE UPPER RANGE DF

NINE NILE POINT-UNIT 2 DOCKET NUHBER 50-410 SYSTEM COHPOHEHT EVALUATION MURK SHEET PAGE I OF I QUAL REF a PBOOAEX REV 0 20-Dec-84~<<>><<<<<<~ENVIRONNENTAL CDHDITIOHS AND QUALIFICATION s s EQUIPHEHT DESCRIPTION al'I DOCUHENT REFERENCE s s s l==============================as PARAHETER (SPECIFIED a QUALIFIED I e QUAL IHARGIHI REHARKS e a VALUE s VALUE a SPECIFIED a QUALIFIED s HETHOD I DEHO I s s EQee 1 as ash Qessea aen.Ne e.nnlA s s--s---s-s s-s s s s C41 F004h ss s s s s s s s s ISPEC HO.: 21A9370AB llOP.TINEA' 1 HOUR I SEE NOTES I 3 I 2 ITEST-IDENT I YES'OTE 3 ISYSTEN: ssTENP (F): I-----a"--"-I-----a-----s-----e---e-NOTE I s STANDBY LIQUID CONTROL ea HORHAL a 103 s SEE HOTES a 1 I 2 I HA a NA I s ls ABHORHALs 141 s SEE NOTES I I s 2 I KA I NA a HOTE 4 s aTYPEl (DESCRIPTION)

I a ACCIDENT as 175 s'00 I 1 ss 2 (TEST-IDENT s aYES as a CONTROL VALVE (EXPLOSIVE) l(PRESS(PS(6)

I-----a-----I-----a-----5-----a---a-NOTE I s al KDRHAL I ATHOS I HA s I I 2 s HA s HA I s al ABHORHAL(ATHOS I KA a 1 a 2 a HA s NA I s IHANUFACTURERl COHAX CORP s s ACCIDENT(2 8 a 16 5 (1 a 2 e TEST IDENT e YES s I IRH (X)'-----(-----'----'----I-----I---I-NOTE 1 s IHODEL NO.: 1832-159-01 (VE)es NORMAL a 50 a HA a I a 2 s HA s HA e s I 1532-159-01 (REPLACEHENT KIT)s s ABHORNA(.a 90 e NA I I a 2 I NA a HA aSAFETY FUNCTION:---I a ACCIDEHTI 100 e 100 I 1 I 2 e TEST-IDENT I YES a s SLC INJECTION VALVERADIATIOH'


'----'----'----'----'--'NOTE I s se HORN 6AHNAI 4.9E4 I SEE BELOM I 1 I 2 a NA a NA a s II ACC GAHHA I l.19E4 I 4.IE5 I I I 2 ITEST-IDENT I YES I HOTE 5 sOP CODE: A II HORN BETA a NA s SEE ABOVE I I s 2 I NA s HA s s aa ACC BETA I 1.2E5 I SEE ABOVE a I I 2 a HA e HA ai NEUTRON a HA s HA I 1 I 2 (HA s NA a I(SPRAY a KA s KA I s s HA I NA sACCURACY--IISUBHERGENCEa HA s KA I I-'A e HA I cess:n~Mes s s>>s s SPEC~Nh s s s DEHO: HA s s s s s s e s s s s>ZONE NO.t SC28'9155 aFLOOD LEVEL la DOCUHENT

REFERENCE:

NDTES: 1.FOR COHPLETE EHVIROHNEHTAL CONDITIOHS,I ELEVATIOH:

NA ls I, EQUIPHENT QUALIFICATION ENVIRONNENTAL DESIGN SEE THE DOCUHENT REFERENCED.

IABDVE FLOOD ea CRITERIA, EQEDC-I, REV 1, NAY 2, 1984.2.HAINTEKANCE REQUIREHEHTS IN ORDER s LEVEL?HA s s 2.VENDOR ENVIRONHEKTAL QUALIFICATION REPORT)TO NAINTAIH QUALIFIED LIFE(REPLACE I aABOVE SPRAY/II SDDF I (6E HEDC-30713)

PRIHER/TRI66ER ASSEHBLY AHD INLET s FROTH LEVEL?NA la 3.EQUIPHENT OPERABILITY TIHE DATA SHEET: FITTIH6 EVERY 3 YEARS, s s 3.THE VALVE SELF-ACTUATED AFTER 34 HIH aDOCUHEHTATION ACCEPTABILITY'l OF EXPOSURE TO DESIGN BASIS LOCA COND I IACCEPTABLE TO NURE6 0588,CATII I I AND DENOHSTRATED THE OPERABILITY OF s PER NEDE 24326-I-P Ie EXPLOSIVE CHARGE IN ITS END-OF-LIFE s s CONDITIOH.

THE PRESSURE BUILD-UP IH I s UNVEHTED CHARGEe DUE TO AGING AND H16HI 55'EHPERATURES INCREASES THE VOLATILITY s sHAINT/SURVEILL

-NDTE 2 le OF THE EXPLOSIVE AND RAISES THE a a REFEREHCE:

2 IIHOTES: (CONTINUED)

PROBABILITY FOR IHADVERTENT SELF-ACT-s s es 5,THE SPECIFIED VALUE REPRESENTS 10X UAT ION.SELF-ACTUATIOH OPENS THE IQUALIFIED LIFE---li OF THE 1 HOUR TOTAL INTEGRATED VALVE IS A CHAN6E IN THE SAFE a (YEARS): 40 YEARS(NOTE 2)s 5 DOSE FOR DESIGN BASIS LOCA CONDITIONS,'IRECTION, s s s s s s

REFERENCE:

2 4.NORMAL AHD ABHORHAL TEHPERATURES TO O la MHICH THE EQUIPNENT IS SUBJECTED MERE a SIHULATED BY ACCELERATED AGING AS I DOCUHEHTED IH REFEREKCE 2.s

NINE NILE POINT-UHIT 2 DDCKET NUMBER 50-410 QUAL REF 4 PBOOAFN REV 0 SYSTEM COMPONENT EVALUATION MORK SHEET PA6E OF 1 20-Oec-84'>>I ENVIROMHEHTAL CONDITIONS AND QUALIF I CATION EQUIPMENT DESCRIPT IOH 11 I l DOCUMENT REFERENCE a I I I>t t PARAMETER,(SPECIFIED l QUALIFIED I QUAL lHARGIN(REMARKS si s EQUIP NO.t C51-K001A aSPEC NO)112C2276 (SYSTEMS HEUTROH MONITORING I I a TYPE)(DESCRIPTIOH)

I PULSE PREAMPLIFIER I I I I aHANUFACTURER:

GE I I IHODEL NO: (12C2276 I I ISAFETY FUNCTION: I" HO SAFETY FUNCTION I I I I O (OP~CODEI C (REF 2)IACCURACY--I SPECs MA I DEHOl HA I I (ZONE NO.: SC240135 siFLOOD LEVEL s ELEVATION'A (ABOVE FLOOD LEVEL?HA tABOVE SPRAY/I FROTH LEVEL?HA I I IDOCUHENTAT IOH ACCEPTABILITY:

lACCEPTABLE TO NURE6 0588,CATII a PER HEDE 24326 I P I I I I I I lHAINT/SURVEILL

---

REFERENCE:

HA I I IQUALIFIED LIFE---(YERRS): NA O si REFEREHCEl I la VALUE I VALUE l SPECIFIED l QUALIFIED a METHOD l DEMO t I>>>>I>>>>I I I I I I I I I I I I I I I>>>>I I (OP.TIHEl l NA I HA 1 3 I"'(FHEA s NA s(TEMP (F)'I s l t" I s NOTE 1 NORMAL l 90 l NA l 1 l 2 l NA l NA l NOTE 2 sl ABNORHALI 96 t NA I I I 2 I HA l HA'I sl ACCIDENTt 175 l NA t 1 I 2 I HA a HA I l IPRESS(PS(6)l


I-----'----'""--'----I---I-NOTE I sl HORHAL I ATHOS I HA I 1 I 2 (NA I HA 11 ABNORt(ALl ATHOS I NA 1 I a 2 I HA l HA st ACCIDENT(2 8 I NA l 1 t 2 I NA 1(RH (X)l I I" I t a (l NOTE I ll NORMAL a 50 l NA I 1 I 2 I NA I HA 11 ABNORHALI 90 l HA l 1 l 2 I HA i t(A I<<l ACCIDENT(100 I HA (1 I 2 I HA l HA I l(RADIATION:

I-----(---'--t----" l-----l---"-t---l-NOTE I el HORH GAHHAI 3.6E5 e HA I 1 l 2 l HA l NA I si ACC GAHHA I 1 7E7 I HA I 1 l 2 i HA i NA tt HORN BETA I NA s HA=l 1 i 2 i NA I NA e tl ACC BETA I 6'E6 a HA I I l 2 I HA I NA I aa HEUTRON I HA I HA I I l 2 I HA I HA taSPRAY (NA I HA I MA I HA I taSUBHERGENCEl NA I HA (NA I HA II>>>>--I I I I I I I I I I I I I I I I I I I I I 11 DOCUHENT

REFERENCE:

MOTES: 1,FOR COMPLETE ENVIRONMENTAL CONDITIONS,I aa l.EQUIPMENT QUALIFICATION ENVIRONMENTAL DESI6N SEE THE DOCUMENT REFERENCED.

11 CRITERIA, EQEDC"1, REV 1, HAY 2, 1984.2.NORMAL TEMPERATURES ARE SHOMH AS I I 2~VENDOR ENVIRONMENTAL QUALIFICATION REPORT, HAX DESI6H/AVERAGE.

ts SDDF I (6E HEDC-30422)

EQUIPHEHT OPERABILITY TIHE DATA SHEETl I I I I lii I I I I I I 11 I I I I I I 11 I I 11 I I I I I I I I I I I I I I I I I I I I

HIHE MILE POINT-UHIT 2 DOCKET NUMBER 50-410 QUAL REF 4 P800AJX REV 0 SYSTEM CONPOHEHT EVALUATION WDRK SHEET PAGE 1 OF I 20-Dec-84~~t~See<<t 5<<>>>~~EQUIPMENT DESCRIPTION s s s s ENVIRDNMENTAL CONDITIOHS AND QUALIFICAT(ON s s s I s t DOCUMEHT REFERENCE s>>tl PARAMETER I SPECIFIED s QUALIFIED I a QUAL IMAR61Ns REMARKS lEQUIP HO l E22-N055C lSPEC HO.: 184C4775 (SYSTEM: H16H PRESSURE s CORE SPRAY s s (TYPES'DESCRIPTION)

I LEVEL TRANSMITTER s s I (MANUFACTURERS 6OULD, IHC, s s aMDDEL NO.: PD3218 aSAFETY FUNCTION;s HIGH SUPPRESSIOH POOL a LEVEL s s sOP.CODE: A s s s s s s (ACCURACY--SPEC:+/-6.8'H20 s DEMO: (+/-6.8'H20 s s (ZONE NO l SC175105 aFLOOD LEVEL l ELEVATIOHl NA aABOVE FLOOD LEVEL?HA aABOVE SPRAY/FROTH LEVEL?HA a s (DDCUMEHTATIOH ACCEPTABILITY:

HUREG 0588 CAT lQUALIFICATION IH PROGRESS (HOTE 3)s s e s (MAIHT/SURVEILL

---s REFEREHCE:

HA s s sQUALIFIED LIFE---lYEARS): 15 YEARS s

REFERENCE:

2 tt s VALUE I VALUE a SPECIFIED t QUALIFIED a METHOD (DEMO s s ss s s s s s s a" s i 1-a->>---s------s----0--a-c-I----s------s->>---"--s----s------

---s i s i sOP TIME'24 HR (50 DAY a 3 a 2 e TEST IDENT (YES, s ssTEMp (F)(s s s s s a s NOTE t(ORMAL I 85 l SEE NOTES l 1 I 2 lTEST-IDENT l HA I NOTE 2 ABHORMALl 104 a SEE NOTES (I l 2 (TEST"IDENT I HA I NOTE 4 la ACCIDENTl 175 a 290 I I t 2 aTEST-IDEHT s YES aPRESS(PS(6)(-----'----'---"'---"'----'--'NOTE I H NORHAL I ATMOS l SEE BELOW s 1 I 2 I , HA'HA s tt ABNORMAL(ATMOS t SEE BELOW I I I 2 s HA I HA ts ACCIDEHTs 2.8 l 17's 1 s 2 aTEST IDENT I I t tRH (X)'"---"'---" (---"-I-"---'----'-"a-NOTE 1 as NORMAL I 50 ,s SEE BELOW s I (2 I H(}I HA a a(ABHDRHALl 90 i SEE BELOW l 1 s 2 i NA I NA l ts ACCIDENTI 100 s 100 a I I 2 aTEST"IDENT t HA sRADIATION'


'---"'----'---"'-"--'--'NOTE t t(NORM GAMHAt 1.(E7 i SEE BELOW I I I 2 I NA I HA a (i ACC GAMMA I 9 0E6 a 5 35E7 I 1 s 2 aTEST IDENT I al NORM BETA a HA s SHIELDED s I i 2 a HA s HA a la ACC BETA I la2E7 s SHIELDED a 1 s 2 a NA I a la HEUTROH I HA s NA a I a 2 a NA I a tsSPRAY I NA a HA a a NA I HA s asSUBMERGEHCEa HA I NA I s HA t HA I ll s 0 a s s s s s as sa DOCUMEHT REFERENCE)

NOTES: I.FOR COHPLETE ENVIRONMENTAL COHDITIONSst at 1.EQUIPMENT QUALIFICATION ENVIRONMENTAL DES16N SEE THE DOCUMENT REFERENCED.

aa CRITERIA, EQEDC-l, REV 1, MAY 2, 1984.2.HORHAL TEMPERATURES ARE SHOWH AS ls 2.VENDOR ENVIRONMENTAL QUALIFICATION REPORT, MAX DESIGN/AVERAGE.

tl SDDF 4 3,QUALIFICATION DOCUMENTATION l t 3 EQUIPMEt(T OPERABILITY TIME DATA SHEETS IH PROGRESS.SCHEDULED PUBLICATION IS FEBRUARY)1985, tt 4.NORMAL AND ABNORMAL TEMPERATURES Ill t ARE SIMULATED BY ACCELERATED A61HG s e AS DOCUMENTED IN REFERENCE 2.s a as s s s s s s as\s s s s s s s s I as s s s s s s s I s I s s a s s s s s s s s s s I s s

NINE NILE POIHT-UNIT 2 DOCKET NU)(BER 50-410~IS~IS QUAL REF I PGOOAOM REV 0 SYSTE)(CO)(PONENT EVALUATION MORK SHEET PAGE 1 OF 1 ENVIROHHENTAL COHDITIOHS AND QUALIFICATIOH 20-Oec-84 EQUIPHEHT DESCRIPT(OH I al l ai l DOCUNENT REFERENCE=l t PARANETER l SPECIFIED l QUALIFIED I QUAL tt(ARGIH t I I I I I I REKARKS VALUE 1 VALUE I SPECIFIED 1 QUALIFIED I HETHOD I DEl(O a I I IEQUIP HO.: E31-N092 lSPEC HO)163C1563 ISYSTEHl I LEAKAGE DETECTION I I (TYPEE (DESCRIPTIOH)

I PRESSURE TRANSMITTER I I I I atlAHUFACTURER'OSEt(OUNT I I l tlODEL NO.: (151 I I tSAFETY FUNCTION: PRESSURE INTEGRITY/Cl.ASS lE ASSOCIATED I (OPa CODE)8 (REFERENCE 2)I I I I IACCURACY"-SPEC: NA DEMO: NA I t LONE HO.l SC261145)FLOOD LEVEL I ELEVATIOH)

NA IABOVE FLOOD LEVEL'?NA IABOVE SPRAY/a FROTH LEVEL?HA I)DDCUHEHTATION ACCEPTABILITY:

aACCEPTABLE TG HUREG 0588,CAT t PER HEDE 24326-1-P I I I I t (NAINT/SURVEILL

---REFERENCE)

NA I I tQUALIFIED LIFE---(YEARS): 15 t REFEREt(CE:

2 II--I I<<I<<<<I<<>>I I AH4DATA l, NA a(OP,TI)(E:

I NA s NA s 3 l 2 I-'----t"--t-NOTE I NA 1 NA l NOTE 2'(TE)(P (F)'t NORHAL t 85 s SEE NOTES I, 1 l 2 la ABHOR)(AL(104 I SEE HOTES a i1 l 2 la ACCIDENTI 200 a>200 I 1 (2 I HA t NA t NOTE 3 I AN~DATA 1 YES I I'PRESSlPSIG)

'-"--'----'----'---I I a NOTE 1 I NA a NA a I NA I NA a aa NORNAL 1 AT)(OS I HA a 1 a 2 ABHORNAU HA I NA I 1 1 2 I I ACCIDENT)2.8 a NA I 1 I 2RH (X)'l NOR)(AL 1 50 l NA I 1 t 2 sa ABNORNALi 90 t HA I 1 a 2 NA I NA NOTE I I NA I NA ai a NA I NA I I ACCIDENT I 100 a 100 I 1 I 2'RADIATIOH' I I as NDRH GAHHA(1,1ES lit(CL BELOM l I a 2 I AN)DATA l NA t NOTE 1 l NA t NA I AN>DATA t YES a NA l NA l tt ACC GANNA s 2a3E7 s l<3EB I 1 t 2 la NORH BETA a HA (SHIELDED I I l 2 II'I I I I I I I I I I I I~I I I I (I I I I I I I I I I I I I I I I REFERENCE 2.I I I I I I I I I I I I I I I I as ACC BETA's 6 3E6 a SHIELDED I 1 i 2 I NA I NA I aa NEUTRON a at(A I NA t I t 2 (HA l NA I slSPRAY I HA I NA I a HA I NA a(SUBHERGEHCE(NA I HA a I HA I HA I I I I I I~I I I I I I I I I I I I I (ll DOCUMENT

REFERENCE:

NOTES: 1.FOR COMPLETE ENVIRON)(ENTAL CONDITIONS,I l a 1 EQUIP)(ENT QUALIFICATIOH ENVIROHHEHTAL DESIGN SEE THE DOCUMENT REFERENCED

~sa CRITERIA)EQEDC-I)REV 1)t(AY 2, 1984 2 ABNORMAL TEKPERATURES ARE SHOMN AS ta 2 VENDOR EHVIROHNENTAL QUALIFICATION REPORT)HAX DESIGN/AVERAGE.

l SDDF 4 (GE NEDC"30409) 3 HORHAL AHD ABHDRKAL TE)(PERATURES 1 as i3, EQUIPHEHT OPERABILITY Tlt(E DATA SHEETl TO MHICH THE EQUIPMENT IS SUBJECTED l MERE ACCDUNTED FOR IH THE ACCELERATED l AGING ANALYSIS AS DOCUNENTED IN

APPENDIX C Replace with existing Appendix C tab from Volume l.

380 380 T E S T P R 0 F I L E P413T LIMIT SWITCHES 320 300 280 280 220 n.200 180 1 OO 120 100 L0Q(TIME IN M IN UTES)100 90 80 e=.--T E S T P R 0 F I L E P41 3T LIMIT SWITCHES 50 30 20 100 LOG(TI M IN M IN UTES)TEST PROFILE DATA FOR P413T LINIT SWITCHES TINE LO6(NINUTES)

TENP(F)PRES(PSIB)

TINE (NIN)0 30sec 50sec 7hr 7.5hr-3.00-0.30-0.08 2.62 2'5 100 370 340 340 320 0 100 100 100 75 0.001 0.5 0,83 420 450 Iday 2days 3.16 3.46 320 260 75 10 1440 2880 4days 5days 30days 3.76 3'6 4.64 260 200 200 10 10 10 5760 7200 43200

350 T E S T P R 0 F I L F P413T SOLENOID VALVES 30O 250 4 200 I 150 100 I-1 1 L O C (Tl M E IN M I N UTES)110 100 00~eo T E S'T P R O F I L E P413T SOLENOID VALVES Cfi CL 1JJ CA Cll 4J CL TO 50 40 20 10 0-1 1 LOC (Tl M E IN M I NUT'ES)TEST PROFILE DATA FOR P413T SOLENOID VALVES TINE LOSININUTES)

TENP{F)PRES)PS I 6)TINE<NIN)0 Bain 3hr 3hr-3.00 0.90 2.26 2'6 0 346 346 320 0 110 110 75 0.001 8 180 180.1 4days 26days 3.76 4.57 250 200 15 0 5760 37440

A C C I D E N T, C 0 N D I T I 0 N 180 ZONE ABN1T505 1 7'0 180 150 I-140 150 120 I 110 100-2 0, LOG QTI M E IN M I NUTEQ)A C C.I D E N T C 0 N D I T I 0 N ZONE ABN1750$2.8 2.8 2.4 22 C/l 1.8 1.8 1.4 c/7 1 Cll lal 1 0.8 0.8 0.4 0.2 0 0 ,,4 LOG(TIME IN MINUTES)ACCIDENT CONDITON FOR 1ONE ABNI7503--4'CIC DER HELD in Secondary Containaent TEHPERAT TIHE LOB(HINUTES)

TEHP(F)T I HE (HIN)PRESSURE TIHE LOB(HINUTES)

PRES(PSIB)

TINE (H IN)URE 0-4.00 104 0 0001 0-4 00 0 0.0001 1.0sec 100sec-1.77 0.22 175 175 0.017 1.67 ihr id ay 1.78 3.16 150 125 60 1440 3days 10days 100days 3.64 4.16 5.16 115 104 104 4320 14400 144000 1.0sec 100sec ihr 3hrs lday 10days 100days-1.77 0.22 1.78 2.26 3.16 4.16 5.16 28 28 13 08 03 0 0 0.017 1.67 60 180 1440 14400 144000

A C C I D E N T C 0 N D I T I 0 N ZONE MST24044 340 330 32O 310 300 200 280 2'BO 250 240 230 220 210 200 1 SIO 180 1 TO 1BO 1%0 140-2 0 4.I 0 G (Tl M E IN M I N UTES)A C C I D E N T C 0 N D I T I 0 N ZONK MST24044 28 28 20 18 1B 14 12 10 0 4-2 0 2 I 0G (TIM E IN M I NUTES)ACCIDENT CONDITIONS FOR ZONE HST24044--Hain Steaa Line Break in Hain Steaa Tunnel TURE 0 0,05sec"4.00-3.10 140 340 0.0001 0.0008 E-TEHPERA TIHE LOS(HINUTES)

TEHP<F)TIHE(HIN)P R E S 8 U R TIHE LOS(HINUTES)

PRES(PSIG)

T I HE (HIN)Ssec-1'0 340 0 F 08 0 0.(sec isec-4.00-2.77-1'7 0 20 20 0.0001 0.0017 0.017 10sec 1hr (day 10days 100days-0.77 1.78 3~16 4.16 5.16 275 275 175 i40 140 0'7 60 1440 14400 144000 2sec Ssec 10sec 1hr 1day 10days 100days-1'8-0.89-0.77 1.78 3.16 4,16 5.16 27'27'5 0.8 0,3 0 0 0.033 0.13 0.17 60 1440 14400 144000

A C C I D E N T C 0 N D I T I'N ZONE PC175101 220 210 200 190 180 1 70 1BO 150 130 120 110 100 BO LOG(TIME IN M I NUTES)A C C I D E N T C 0 N D I T I 0 N ZONK PC1 751 01 30 20 15 10 LOG(TIME 2 4.IN M I NVTES)ACCIDEHT COHDITIOHS FOR ZOHE PC175101--Design Basis Accident Analysis Prieary Cantainaent TEMPER TIME LOS (MI HUTES)TEMP I j)TIME (MIH)PRESSU TIME LOS(MIHUTES)

PRES{PSIS)

TIME IMIH)ATUR 0-4.00 90 0.0001 RE 0-4.00 0 0.0001 E 0.5sec 2hr-2.08 2.08 150 200 0.008333 120 lsec 6hr-1.78 2.56 40 40 0.016666 360 6hr lday 10days 30days 100days 2.56 3.16 4.16 4.64 5.16 212 212 150 135 90 360 1440 14400 43200 144000 lday 5days 10days 30days 100days 3.16 3.86 4.16 4.64 5.16 25 10 7 5 0.8 1440 7200 14400 43200 144000

APPENDIX D Replace with existing Appendix D tab in Volume l.

Nine Mile Point Unit 2 EQD APPENDIX D WILL BE PROVIDED IN A FUTURE AMENDMENT Amendment 16 D-1 December 1984

~t