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| | number = ML17054D432 | | | number = ML17054D432 |
| | issue date = 05/28/1982 | | | issue date = 05/28/1982 |
| | title = Valcor Valves & Gordos Limit Switches. | | | title = Valcor Valves & Gordos Limit Switches |
| | author name = | | | author name = |
| | author affiliation = NUS CORP. | | | author affiliation = NUS CORP. |
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| {{#Wiki_filter:y~~S4d PN < We.'e"'f Nine Mile Point Unit g>~+j/~+3 g 2 ER-OLE 2.3 WATER 2.3.1 Hydrology | | {{#Wiki_filter:}} |
| : 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.
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| 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)
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| In late September the warming process ds. The lake's mean surface temperature drops rapidly to b ow 17 C (62.6 F),
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| 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.
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| 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
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| 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.
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| FitzPatrick Nuclear Power Plant ( JAF) 316(a)
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| 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.
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| 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.
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| A number of observations of the bottom sediments along the south shore of Lake Ontario have been made. Sutton et nearshore bottom sediments (0-33 m {0-108 ft]) in al'~'xamined 1968 and 1969 between Rochester and Stony Point, and stated several conclusions relevant to the Nine Mile Point site:
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| : 1. There is generally a west-to-east transport of sediment.
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| 2 3 2 0
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| Nine Mile Point Unit 2 ER-OLS
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| : 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.
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| : 3. In general, the coarser sands, boulders, pebbles, and cobbles lie in the beach or nearshore area, and finer sediments are found lakeward.
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| : 4. Several small patches of sand occur offshore between hypothesized Oswego and that Mexico Bay, and these originate from the Oswego it is River.
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| 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 Currents at Nine Mile Point al'.3.1.1.4 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.
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| 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) .
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| 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
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| ~
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| Nine Mile Point Unit 2 ER-OLS the observations were below the meter threshold, 0.03 m/s (0.08 fps).
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| 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'''.
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| in The results of these studies are also provided the yearly are summarized in the following paragraphs.
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| reports'nd 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.
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| 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)~~
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| can be considered to be representative of the surface water temperature.
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| 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
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| 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.
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| 2.3.1.1.6 Existing Thermal Plumes 2 '.1 1.6.1
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| ~ 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
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| '.
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| 29 field surveys of the plumes resulting from the discharge of heated condenser cooling water into Lake Ontario have been conducted''~
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| marized in Table 2.3-1.
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| Section 6.1.2 provides descriptions of the methods used in these surveys. The results are sum-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.
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| 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.
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| 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
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| 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 ft) .
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| 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.
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| 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.
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| Section 6.1.1.3 provides a description of the survey procedures.
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| 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).
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| 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.
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| 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.
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| 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
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| Nine Mile Point Unit 2 ER-OLS Several studies have been conducted by investor-owned
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| -
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| 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''''
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| 2.3.3.3 Lake Ontario Water Quality Overview Lake Ontario has been designated by NYSDEC as Class A-Special 6NYCRR702.1'~ 'ts Waters (International Boundary Waters),
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| 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 contamination.
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| densities, and little industrial 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 .
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| Oswego River, west-to-east longshore currents, and hypolim-netic upwellings of cold, often nutrient-rich waters''''.
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| 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
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| 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.
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| 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.
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| Trends evident in important selected water quality parameter subsets are summarized in the following paragraphs.
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| 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.
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| 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).
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| : 2. 3-12
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| 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.
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| 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.
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| Maximum zinc concentrations in 1973 and 1978 exceeded the state standard of 300 ug/l.
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| 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).
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| 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.
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| : 2. 3-19
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| 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.
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| : 2. Power Authority of the State of New York. James A.
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| FitzPatrick Nuclear Power Plant 316(a) Demonstration Submission. Prepared for United States Atomic Energy Commission, 1971.
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| : 3. Csanady, G.T. The Coastal Boundary Layer in Lake Ontario. Chapter II. The Summer-Fall Regime. J.
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| Physical. Oceanogr., 1972, Vol. 2, p. 168-176.
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| 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.
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| : 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.
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| Great Lakes Res.,'970, p. 914-926.
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| : 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.
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| : 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.
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| : 8. Lawler, Matusky 6 Skelly Engineers. 1975 Nine Mile Point Aquatic Ecology Studies. Prepared for Niagara Mohawk Power Corporation, 1976.
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| : 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.
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| : 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.
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| 2.3-20
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| Nine Mile Point Unit 2 ER-OLS TABLE 2.3-3 (Cont)
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| Distance Distance Average
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| ( km/mi) and (km/mi) Wi thdrawa I Product ion Map Name of System Direction by Water Rate 1 8 -81 Population Ca aci No. + Intake Count ~from Uni 2 from Unit 2 ~ou m da ~md ~Te of use Served ouu~tuda ~md ~common s 15 Chaumont 60/37 NNE 61/38 265 0.07 Domestic 550 908 0.24 Winter (Dec-Village Mar) usage (Jefferson is approx.
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| County) 189 cu m/day (0.05 mgd);
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| summer usage (Jun-Sep) avg. 341 cu m/
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| day (0.09 mgd) 16 Cape Vincent 65/41 N 65/41 757 0 20 Domestic 750 908 0.24 Wi thdrawa I s Village fluctuate (Jefferson between Jun County) and Sep from 473 to 1,136 cu m/day (0. 125 to 0.3 mgd)
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| +Locations corresponding to map numbers are shown on Figure 2.3-4.
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| SOURCES: References 20, 22, 24, 25, and 28 4of4
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| 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
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| : 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.
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| 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'',
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| 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.
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| 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
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| Nine Mile Point Unit 2 ER-OLS other wildlife management area in the vicinity of the site p 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 trails':
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| aa 4
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| to the site, and management consists primarily of the erec-tion of nest boxes and the maintenance of visitor 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:
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| 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.
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| 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.
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| Ironwood (~Car inus caroliniana), witch hazel (Hamamelis understory. Ground cover, although generally sparse due to the closed canopy, consists of false Solomon's seal
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| "~
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| 2 The vegetation in the vicinity of the site may be divided into a number of distinct community types (Figure 2.4-2).
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| 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
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| 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 population density is considerably lower than the state mi)'his 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.
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| 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.
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| 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.
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| 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.
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| 2.5.1.1 Population Within 20 Km (12.4 Mi)
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| 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
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| 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.
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| It is expected that a large portion of the population growth in the 20-km (12.4-mi) area will occur around the southeastern fringes of . the city of Oswego, with the sur-rounding towns of Scriba, Palermo, New Haven, and Volney absorbing much of the city's satellite growth'~'.
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| 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'of to estimate the area population by applying a factor 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'~'.
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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. 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.
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| Transient population within 20 km (12.4 mi) of Unit 2 is limited due to the rural, undeveloped character of the area.
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| There are, however, a number of school, industrial, and recreational facilities in the area that create small, daily 2.5-2
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| 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 Population Density 1980 Po ulation eo le s km City of Oswego 19,793 1,029.0 Oswego (town) 7,865 116.9 Granby 6, 341 55.2 Richland 5, 594 40.9 Scriba 5, 455 52.9 Volney 5, 358 46.0 Mexico 4, 790 41.8 Hannibal 4, 027 38.5 Palermo 3,253 31.6 New Haven 2, 421 31.7 Minetto 1, 905 125.5 SOURCE: Reference 1 1 of 1
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| V 0
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| 0
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| Nine Mile Point Unit 2 ER-OLS The view of pact the overall visual quality of the area. changers the cooling tower will be the only noticeable The cooling tower is 165 m (541 ft) above ground level and is visible at some locations, as 3.1-7. shown for selected locations on Figures 3.1-4 through Depending on meteorological conditions, the natural-draft cooling tower will emit evaporative16-kmplumes that may be visible from locations within the (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.
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| 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 the site on Association Conference Camp (a lakefront facility bordering the west) .
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| 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.
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| 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.
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| 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.
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| : 3. 1-3
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| 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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| 1 ~ Normal operation.
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| : 2. Normal shutdown.
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| : 3. Loss-of-coolant accident (LOCA) without loss of offsite power (LOP).
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| : 4. LOCA coincident with a LOP.
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| 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.
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| 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.
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| 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.
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| 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).
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| During normal operation, the maximum heat rejected is 3.29 x 10~ g-cal/sec (4.7 x 108 Btu/hr).
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| 3 ~ 4-3
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| Nine Mile Point. Unit 2 ER-OLS
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| : 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.
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| Table 3. 3-1 lists monthly minimum, average, and maximum total intake flows.
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| The closed-loop circulating water system uses discharge from the service water system for its makeup requirements.
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| 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).
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| .
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| Discharge flows from the water treatment system and the radwaste system flows are discussed in Section 3.3.
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| FSAR Figure 9.2-1 shows the service water intake and discharge systems'ater use. The monthly minimum, maximum, and average
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| -
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| cooling water intake and discharge flows are listed in Table 3.3-1.
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| 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)..
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| 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.
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| 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.
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| During normal operation, the plant discharge flow and temperature vary with fluctuations in the meteorological conditions (Section 2.3.2).
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| 3.4>>4
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| 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.
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| 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.
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| I.
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| 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.
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| A fish bypass and return .system is provided at the downstream end of the screens.
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| 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.
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| 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.
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| 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.
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| 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.
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| 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
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| : 3. 4-'7
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| 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.
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| 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.
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| 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.
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| 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)3.4-7. diameter nozzles at the end of each, as shown on Figure The
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| ~
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| 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 ft) (USLS 1935 Datum) .
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| 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.
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| 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, standardcorrections nomograms published by the EPA were generated'~'.. Depth by Robideau were applied to the EPA nomographs to obtain more conservative results' . New York State Regulation 6NYCRR652 (1976) governs discharges to hypolimnetic waters
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| : 3. 4-8
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| 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.
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| Therefore, the discharge does not enter the hypolimnion.
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| 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)
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| ~ ~
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| 3.4.2.3 Cooling Tower The cooling tower is a single-cell, wet-evaporative, natural-draft cooling tower utilizing a counterflow-type design.
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| 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.
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| 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).
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| 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
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| 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.
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| The concrete cooling tower is 165 m (541 ft) in height, with a bottom diameter of 123 m (405 ft)Theand a top diameter of 83 m (273 ft) (Figure 3.4-9). 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).
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| 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.
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| 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.
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| 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).
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| 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.
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| Aircraft warning lights are provided on the tower in accordance with FAA requirements.
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| 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.
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| 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.
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| : 3. 4-10
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| 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.
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| 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.
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| 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.
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| 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).
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| 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:
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| Dry air 63 kg/hr (138 lb/hr) 3.5-7
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| Nine Mile Point Unit 2 ER-OLS Hg 20 kg/hr (43 lb/hr)
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| Op 156 kg/hr (344 lb/hr)
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| Hp0 1,696 kg/hr (3,740 lb/hr)
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| (as dilution steam)
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| Noble gases Negligible NOTE: The off-gas system inlet temperature is approximately 121 C (250 F).
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| 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 -
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| 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.
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| 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.
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| The 'off-gas system includes the following equipment and is shown on FSAR Figure 11.2-1.
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| 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.
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| 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:
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| : l. Ensure complete vaporization of any liquid water.
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| : 3. 5-8
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| 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).
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| 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.
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| 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.
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| 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.
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| 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.
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| Sulfuric acid and sodium hydroxide are used for regeneration of makeup water treatment ion exchange resins.
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| 3.6-1
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| 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
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| ( 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.
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| 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).
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| 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.
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| 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
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| : 3. 6-2
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| 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.
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| 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) .
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| 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.
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| Sulfuric acid additions to the circulating water system are likewise controlled by demand, in this case, alkalinity.
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| 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).
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| 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.
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| 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.
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| 3.6-3
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| 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.
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| 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.
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| ~ 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.
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| 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).
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| 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.
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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
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| 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.
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| 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).
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| 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:
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| Parameter Limits Settleable solids 0.1 mg/1 maximum daily Total suspended solids 25 mg/1 average daily'i'5 mg/1 maximum daily'5 5-day biochemical mg/1 average oxygen demand (BOD>) mg/1 maximum daily'~'
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| daily'~'5.
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| Chlorine residual ' ppm maximum daily pH 6.0-9.0 Fecal coliforms 200 MPN/100 ml 30-day geomet-ric mean 400 MPN/100 ml 7-day geomet-ric mean
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| '''Daily average calculated by dividing monthly discharge by number of days in month.
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| 'Daily maximum is the maximum discharged in 1 day.
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| : 3. 6-5
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| -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.
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| (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.
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| 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.
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| The quantities of storm water and roof drainage vary and are directly dependent upon the storm event that generates them.
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| 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.
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| 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).
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| The cooling tower sludge removal frequency from the cooling tower basin is anticipated to be once every 5 yr.
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| : 3. 6-6
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| 0 0 8
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| IDENTIFICATION LEGEND STACK TOP/BERM 263.00 263.00'-MAIN NI 284 000 EL A REACTOR BUILDING 8 TURBINE BUILDING DIY.K UNIT 2 REVETMENT-DITCH SYSTEM ugIT C RADWASTE BUILDING g,XATT TOP EL 0 0 HEATER BAYS E SCREENWELL BUILDING 0 N E.
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| TOP/BEAM EL 265.00 F CONDENSATK STORAGE TANK BLDG L T gi I G CONTROL BUILDING H NORMAL SW ITCHGEAR BUILDING SHORE LINE (E J ADMIN1ST RAT ON BUILDING
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| ~ RO INFO M ATION CENTER 0 06 99 6
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| NI 283000 SE AGE T J(TM NT u
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| ( IIT PB P T 03 gV Yu5( JI TRANSMISSION LINES t 1
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| ~XRI ) I L EGENO TAJ ORIGINAL GROUNO CONTOUR P/BERM ytAII AVE 256.OO' i NEW GROUND CONTOUR I pal 1
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| +
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| RLO Il ~ ~ Lol FENCE LINE CtO pAVE C TOP/BERM PARIU EL 2.00 O LOT TOWER
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| ~ ~
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| t N I 282 000 NOTES 266. I. GRID COORDINATES REFER TO P/BKR I'GRO i)i .hl NEW YORK STATE COORDINATE 273. NSM Io Y SYSTKM C
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| G I
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| LINE l
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| ~ ~
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| : 2. ELEVAT IONS REFER To MEAN RA ILROAD SEA LKVEL 11 1
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| 'RCIt
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| < Il 3. ORIGINAL CONTOUR INTERVAL 2 FKET
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| ( < ~
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| itltA EXIST NG
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| ~ tttt N I 28 I 000 FIGURE 3.1-1
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| ~RA ILROAD TOP/ RM EL 27 00 STATION LAYOUT 200 0 200 400 I 100 NIAGARA MOHAWK POWER CORPORATION SCALE IN FEET NINE MlLE POINT-UNIT 2 ENVIRONMENTAL REPORT-OLS
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| +~,.O 1
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| ~-
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| Nine Mile Point Unit 2 ER-OLS CHAPTER 5 TABLE OF CONTENTS (Cont)
| |
| Section Title P acae.
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| 5.3.3.2.3 Effects of Heat Dissipation Sys-tem Operation on Wildlife 5.3-44 5.3;4 References 5.3-49 RADIOLOGICAL IMPACT FROM ROUTINE OPERATION 5.4-1 5.4.1 Exposure, Pathways 5.4-1 5.4.1.1 Exposure of Flora and Fauna 5.4-1 5.4.1.1.1 Gaseous Pathways 5.4-1 5.4.1.1.2 Iiquid Pathways 5.4-2 5.4.1.1.3 Direct Radiation 5.4-2 5 '.1.2 Exposure of Man 5.4-2 5.4.1.2.1 Gaseous Pathways 5,. 4-3.
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| 5.4.1.2.2 Liquid Pathways 5. 4-4 5,.4.1.2 ' Direct Exposure 5 4-5 5 4.2
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| ~ Radioactivity in the Environment 5.4-5 5.4..2. 1 Radioactivity in Surface Waters 5.4-5 5.4.2.2 Radioactivity in Air 5. 4-.5 5'.4.2.3 Radionuclide Concentrations 5 '4-5 5.4,.2.3. 1 Liquid Effluents 4-5 '5.
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| 5.4.2.3.2 Gaseous Effluents 5'. 4-..6 5.4.3 Dose Rate Estimates for Biota Other than Man .5. 4-7 5.4.3. 1 .Doses through Gaseous Pathways 5.4-7 5.4.3.2 Doses-through Liquid Pathways, 5.4-7 5.4.3.3 Direct Radiation Doses 5.4-7 5.4.4 Dose Rate Estimates for Man 5. 4-8 5.4.4.1 Liquid Pathways 4-8 '.
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| "
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| 5.4.4.2 Gaseous Pathways 5.4-8 5.4.4.3 Direct Radiation from Facility 5:4-9 5.4.4.4 Annual Population Doses 5.4-9 5.4.4.4.1 Eighty-Kilometer (Fifty-Mile) Radius Population Doses 5.4-9 5.4.4. 4.2 Contiguous U.S. Population Doses 5. 4-9 .,
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| 5.4.5 Summary of Annual Radiation Doses 5. 4-9 5.4.6 Reference 5.4-11 5.5 NONRADIOLOGICAL WASTE SYSTEM IMPACTS 5.5-1 ~
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| : 5. 5.'1 Identification of Nonradiological Effluent Discharges 5.5-1 5.5.2 Compliance with Effluent Standar'ds 5.5-1 5.5.2.1 Discharges to Water 5.5-1 5.5.2.1.1 Cooling System Discharge 5.5-2
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| | |
| Nine Mile Poin't Unit, 2 ER-OLS CHAPTER 5 TABLE OF CONTENTS (Cont)
| |
| Section Title. Pacae 5.5.2.1.2 Treated Sanitary Effluent 5.5-3 5.5.2.1.3 Storm Water, Roof, and Yard Drainage 5.5-3 5.5.2.1.4 Floor Drainage 5.5-3 5.5.2.2 Discharges to Air 5.5-4 5.5.2.3 Discharges to Land 5.5-4 5 '.3 Impacts Associated with Nonradio-logical Effluent Discharges 5.5-5 5' '..1 Discharges to Water 5.5-5 5.5.3.2 Discharges to Air 5.5-6 5.5.3.3 Solid Waste Land Impacts 5.5-6 5.5.4 Unavoidable Adverse Impacts 5.5-7 5.5.5 Irreversible and Irretrievable Commitment of Resources 5.5-7 5.5. 6 References 5.5-8 5.6 TRANSMISSION SYSTEM IMPACTS 5.6-1 5.6.1 Terrestrial 5.6-1 5.6.1.1 Impact on Flora 5. 6-1.,
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| 5.6.1.2 Impact on Fauna 5.6-1 5.6 '.3 Right-of-Way Management 5.6-3 5.6.2 Aquatic 5.6-6 5 ',F 1 Identification of Operational and Maintenance Activities Associated with Transmission Facilities 5.6-6
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| : 5. 6.3 Transmission System Impacts to Man 5.6-6 5.6.3. 1 Land Use Impact 5.6-6
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| : 5. 6.3.2 Audible Noise from Transmission Lines 5.6-7 5.6.3.3 Means to Reduce Impacts of Trans-mission Systems 5.6-7
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| : 5. 6.3. 4 Maintenance Practices to Reduce Visual Impacts 5. 6-8 5.6.4 References 5. 6-10 5.7 URANIUM FUEL CYCLE IMPACTS 5.7-1 5.8 SOCIOECONOMIC IMPACTS 5.8-1 5.8.1 Physical Impacts 5.8-1 5.8.1.1 Land Use Impacts 5.8-1 5.8.1 ' Nonradioactive Gaseous Emissions 5.8-1 5.8.1.3 Potential Adverse Impacts Due to Noise 5.8-2
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| 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.
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| 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).
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| 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);
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| 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.
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| 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).
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| 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.
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| Sections 5.3.1 and 5 '.2.
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| 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).
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| 5.2-3
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| 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.
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| 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 and chemical releases
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| ', thermal 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.
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| 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.
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| 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).
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| 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.
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| Consequently, there will be no significant impacts to com-mercial or recreational fishing.
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| 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.
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| 5.2-4
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| 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 priorcon- to the commencement of plant operation, since previous ditions may reduce the period of acclimation.
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| 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.
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| Consequently, the noise produced by station operation should have no permanent adverse impact on the wildlife in the area.
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| 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 tower extends approximately 164.9 m (541 ft) above grade, level), the 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.
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| Hochbaum states that a bird's eyes are the basic sensory or-gan from which it receives its initial orientation'~~'.
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| flight, birds must maintain true spatial orientation. On In 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 (500 ft)',.
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| birds migrate. at elevations Shadows and lights, such as above aircraft lights atop tall buildings, television-radio towers, and 152.4 m warning 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
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| Nine Mile Point Unit 2 ER-OLS ratic and uncontrolled with the discrepant visual and sen-sory cues.
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| 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' occur when the light source is constant or is a continually
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| '. 'This may rotating beam and completely obliterates any background, causing birds to lose their visual cues to the horizontal.
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| 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.
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| nights' Some
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| '. kills, however, Guy wires associated have occurred on clear 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 also has been reported that 576 birds were killed during Dakota't 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
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| 'ile July 17, Island site, 66 bird collisions were reported from 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.
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| 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
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| 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.
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| 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.
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| 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:
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| 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- ft) 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.
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| : 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'.
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| 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
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| 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.
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| 5.3-48
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| Nine Mile Point Vnit 2 ER-OLS TABLE 5A-1 (Cont)
| |
| Prima Or anisms Parameter Fish Crustaceans Mollusks Al ae~ Muskrat. Heron Duck Raccoon Deer Vegetation yield (kg/sq m) 0 7 Vegetation exposure period (hr) 6,570.5 Holdup time crop exposure to 0.0 ingestion by deer Effective soil surface density 200 (kg/sq m)
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| Buildup time on soil, tb(hr) 1 75+05 crop retention factor particu- 0.2 partic-lates/iodine ulates; 1.0 iodine Absolute humidity (g/cu m) 10. 3 Fraction of year deer consumes crop 0 75 C-10 fractional equilibrium 1.0 ratio: continuous release 0 073 intermittent release NOTE: 8 86-09 = 8.86x10 +
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| << >Edge of mixing xone and nearest shoreline
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| <<>1,603 m (5,259 ft) east c>>Unit 2 stack (continuous)
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| (+>Unit 2 stack (intermittent) c>>Radwaste/reactor building vent (continuous) 2 of 2
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| | |
| Nine Nile Point Unit 2 ER-OLS TABLE SA-2 (Cont)
| |
| Population Usage Transit Time Approximate Distance From ~~eo l~e/ ~r to Point of Incremental Regions<>>
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| km Site to Point of Analysis km Dilution Factor ~Boa tin Recreation Shoreline ~br~
| |
| Analysis 0 to 10 738 1. 5+04 15 10 to 20 15 307 1. 5+04 3 1+05 46 20 to 30 25 348 1 5t04 4. 7+05 76 30 to 40 35 404 1 5+04 6. 9+04 107 40 to 50 457 1 5+04 1 9+05 137 50 to 60 55 504 1 5+04 1 8+04 168 60 to 70 65 548 1. 5+04 1 2+04 199 70 to 80 75 589 1 5+04 1 4+05 229 Other Locations<<>
| |
| Edge of zone<~i initial mixing Approximate Distance From Site to Point of Intake km Dilution Factor 5.9 jar Transit Time to Intake 0.0 (assumed)
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| Closest accessible 15 307 46 shoreline<>>
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| NOTE: 1 5+04 = 1 Sx10i
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| <<aPublic water supply systems used to calculate 80-km (50-mi) radius population doses from ingestion of potable water.
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| <>>Public water supply system used to calculate the dose to the maximum offsite individuals from the ingestion of potable water and irrigated foods.
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| <>>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.
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| <+>Locations used to calculate doses to maximum offsite individuals from ingestion of aquatic foods, and from swimming and boating.
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| <>>Location used to calculate doses to maximum offsite individuals from shoreline recreation. Closest accessible shoreline closest occupied beach.
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| 2 of 2
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| 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.
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| 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.
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| 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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| 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.
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| 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
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| : 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.
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| The eastern drainage ditch and the storm water lines handle only runoff and, therefore, are not required to be monitored.
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| As discussed in FSAR Section 2.5. 4, groundwater levels during construction are monitored by four piezometers located at the reactor building site. Only groundwater elevation data are collected at each piezometer approxima'tely once every week. Monitoring by these piezometers will continue until the completion of construction.
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| 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.
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| Sediment transport in Lake Ontario will not be altered; therefore, sediment transport monitoring is not required.
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| 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 -
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| 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>,
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| 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
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| .
| |
| 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.
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| The collected data were later used to determine the appropriate statistical descriptors, such as the L>p, Lz,,
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| Lzz, and Leq levels, which correspond to the residual, average, intrusive, and equivalent levels, respectively.
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| 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.
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| : 6. 7-5
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| | |
| 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.
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| 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.
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| 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.,
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| 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
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| ~
| |
| 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
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| post-operational air quality monitoring program is neither necessary nor required by state or federal regulations for .
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| this facility.
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| 6.7-6
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| | |
| 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.
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| These types of failures are:
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| : 1. Hardware failures.
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| : 2. Maintenance outage.
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| : 3. Valve plugged.
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| : 4. Testing outage.
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| : 5. Initiating circuit failure.
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| The following accident cases were chosen for Unit 2:
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| : 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).
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| : 2. Emergency ac power system (EPS).
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| : 3. DC power system (DCPS).
| |
| : 4. Vapor suppression system (VSS) ~
| |
| : 5. High-pressure core spray system (HPCS).
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| : 6. Reactor core isolation cooling system (RCIC).
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| : 7. Low-pressure core spray system (LPCS).
| |
| : 8. Automatic depressurization system (ADS).
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| : 9. Low-pressure coolant injection system (LPCI).
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| : 10. Residual heat removal system (RHR).
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| 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 monitors various plant parameters and systems RPSL status and initiates a reactor scram are reached.
| |
| if predetermined values 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
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| | |
| 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.
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| Figure 7A.6-2 shows a schematic of the CRAC2 consequence model.
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| 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
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| ~
| |
| 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.
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| 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 FSAR Section Fire Protection 9.5.1, Appendix 9A Flooding 3.4 Turbine Missiles 3.5.1.3 Chemical Hazards 2.2, 6 4.4.2, F 9 '.1 Security 13.6 Seismic Design 3.7, 3.8 Tornado Design 3.3 Some external events will affect only one accident sequence while external events will affect all accident sequences.
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| some With external causes taken into account, expected that the event-sequence probabilities it and hence the is 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, anticipated that external events will not be significant it is 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 Title Pacae INTRODUCTION ENVIRONMENTAL CONDITIONS 2-1 2.1 TEMPERATURE, PRESSURE, 'AND REL IVE 2-1 HUMIDITY CO 2.2 RADIATION ENVIRONMENT 2-2 2.3 CHEMICAL ENVIRONMENT 2-3 2.4 SPRAY/SUBMERGENCE 2-'4 3 FUNCTIONAL PERFORMANC REQUIREMENTS 3-1 3.1 SYSTEM LIST 3-1P, P 3.2 SYSTEM/ACCIDENT MA IX 3-1 g 3.3 POST-ACCIDENT OPE BILITY TIME Q ALIFICATION THODOLOGY 4-1 4.1 HA H ENVIRON NT 4-1 ~ (P 4.1.1 BOP quipme Electrical 4-1 p.
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| 4.1.2 NSSS quipment Electrical 4- 4.
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| 4.1.3 BOP/NS Equipment-Mechanical 4-6 .
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| 4.2 MILD E ONMENT 4-8 4.2.1 BOP E ipme t Mild Environment 4-9 Qua ificatio Program 4.2.2 NSS Mild Envir nment 4-10 alification P gram 5 UALIFICATION DOCUM TATION 5-1 5.1 MASTER LISTS (ML) 5-1 5.2 SYSTEM COMPONENT- EVAL TION WORK 5-2 (SCEW) SHEET MAINTENANCE/SURVEILLANCE OGRAM 6-1 P 7-1 APPEND XES A SAFETY-RELATED ELECTRICAL EQUIP NT MASTER LIST (ML)
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| SYSTEM COMPONENT EVALUATION WORK ( CE SHEETS TEST AND ACCIDENT ENVIRONMENTAL PROF LE D SAFETY-RELATED MECHANICAL EQUIPMENT Amendment 16 December 1984
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| | |
| Nine Mile Point Unit 2 EQD LIST OF TABLES Table No. Title 2-1 Harsh Environment Zones 2-2 Mild Environment Zones 2-3 Mil'd Environment Zones with Special Filters Equipm'ent Inside Containment Subject Spray, or Froth to'ubmergence, 3-1 Systems List 3-2 System/Accident Matrix 3-3 SWEC/GE System Cross Reference Safety-Related Mechanical Equipment Categories 5-1 EQD Master List. Format 5-2 System Component Evaluation Work (SCEW)
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| Sheet Parameters IIST OF FIGURES Fi ure No. Title 5-1 EQD System Component Evaluation Work (SCEW) Sheet Format Amendment 16 December 1984
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| | |
| 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.
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| 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 except radiation, will return to normal.
| |
| is assumed that conditions, 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 t require requi immediate plant shutdown; the loss of specific transformers or all grid connections; the loss of nonsafe ty-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 Pressure . si Test Fre uenc Containment Preoperational Test 40 (1 time only)
| |
| Postoperational Test 40 (3 per 10 yr)
| |
| The pressurization period is approximately 5 hr, followed b y 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 wh'ic would occur in equipment materials (e.g., carbon) when posed to the environment would differ only sligh t ly in expose 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.
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| 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 an accident, the containment and, drywell atmospheres are mainta inc d below 5 percent (by volume) hydrogen, as discussed in FSAR Section 6.2.5 ~
| |
| Water for the reac reactoror (normal n operation), suppression pool, ra e p ool, RHR system, an d ECCS is not chemically fuel storag
| |
| 'nhibited and is contro e d b y io in the following normal ll operating ion exchange systems within
| |
| 'mits:
| |
| limi
| |
| 'Refueling and Fuel Suppression Reactor Water Storage , Pool Water Limits 'hutdown Pool Wate Quality Parameter Condition Conductivity 510 mho/cm s3 umho/cm 510 umho/cm 925 C 925 C 925 C h
| |
| Chlorides 50.5 ppm 60.5 ppm 50.5 ppm (as Cl-)
| |
| pH 5.3 to 8.6 5.3 to 7.5 5.3 to 8.6 9 25oC 925 C 925 C Total 51 ppm 55 ppm 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 corn onents above postulate d flood oo 1 1 d away from sources of water spray, ere b 1' th or ualification under these i con d tions.
| |
| to h sical constrain s o d building arrangements, this is not easi'bl e the plant.
| |
| in A endix 3C of the FSAR, an evaluation has been performed which demonstrates tes tthat a thee reactor an b safely s h u t down when considering the effects e ec s oof spray/submergence. This is achieve ed b y one of the 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
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| Nine Hile Point Unit 2 CQD TABLE 2-1 iiARSN ENVlRONMENT ZONES 7.one 7.ono 7one 7one Zone 7one Zona 7ane Zone AON17r503 PC199112 PC 2r50 6 26 PC279659 PC299700 SC196119 SC261 14r5 SC306174 SC353202 AON17504 PC215121 PC250627 PC280663 PC303705 SC1 96120 SC261146 SC306175 SG261355 AON17r505 PC240208 PC250628 PC280664 PC303706 SC196204 SC261147 SC306176 SG261356 ABN19614 PC240600 PC250629 PC280665 PC303707 SC215122 SC261 149 SC306177 AON19615 PC240601 PC250630 PC287669 PC306711 SC215123 SC261150 SC306178 AON21523 PC240602 PC261207 PC287670 PC306712 SC215124 SC261 151 SC306179 AON24031 PC?40603 PC26 1636 PC287671 PC306713 SC215125 SC261152 SC306180 ABN2403? PC240604 PC26 1637 PC287672 PC328185 SC215127 SC289155 SC306181 ABN24033 PC240605 PC261638 PC287673 SC1 75102 SC215128 SC289156 SC306182 ABS175()8 PC240606 PC261639 PC287674 SC1 75103 SC21 5129 SC?89158 SC306183 ABS 17509 PC240607 PC261640 PC289679 SC175104 SC215130 SC289159 SC306184 ABS17510 PC240608 PC261641 PC289680 SC175 lOry Sc215131 SC289160 SC306215 ABS17511 PC240609 PC261642 PC289681 SC1 75106 SC215132 SC289161 SC328 186 AOS 19620 PC240610 PC261643 PC289682 SC I 15107 SC215205 SC289162 SC328187 AOS24034 PC24061 1 PC261644 PC289683 SC1 75108 SC215?06 SC289163 SC3?.8189 ABS24035 PC240612 PC26 1645 PC289684 SC175109 SC240135 SC289164 SC328192 AOS24036 PC250618 PC261646 PC289685 SC175110 SC240136 SC289165 SC328193 HST24044 PC250619 PC261647 PC289686 SC175111 SC240137 SC289 166 SC3?8194 MS124045 PC250620 PC261648 PC297691 SC196113 SC240138 SC289167 SC328195 HST26146 PC250621 PC261649 PC297692 SC196114 SC240139 SC289168 SC3?8196 HS126147 PC250622 PC261650 PC297693 SC196115 SC240140 SC289 169 SC328 197 MSI28948 PC250623 PC261651 PC299697 SC 961 16
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| '1 SC240141 SC289170 SC3?8199 MST28949 PC250624 PC279657 PC299698 SC19611/ SC240142 SC306172 SC328222 PC1 75101 PC25062 PC?79658 PC299699 SC196118 SC240143 SC306173 SC353201 Amendment 16 1 of 1 December 1984
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| Nine Mile Point Unit 2 EQD TABI E 2-2 MIFD ENVIRONMENT ZONES Zone Control Buildin El 215'-0" CB215258 Cable Vault Area CB215259 Cable Vault Area CB215305 Cable Vault Area CB215306 Cable Vault Area CB215307 Cable Vault Area El 237'-0" CB237261 Cable Vault Area CB237265 Cable Vault Area CB237266 Cable Vault Area CB237267 Cable Vault Area CB237272 Cable Vault Area CB237273 Cable Vault Area CB237274 Cable Vault Area El 261'-0" CB2 61275 Standby Switchgear Room CB261276 Standby Switchgear Room CB261277 Standby Switchgear Room CB261279 Standby Switchgear Room CB261280 Standby Switchgear Room CB261281 Standby Switchgear Room CB261282 Standby Switchgear Room CB261283 Standby Switchgear Room CB261284 Standby Switchgear Room CB261286 Standby Switchgear Room CB261289 Standby Switchgear Room CB261290 Standby Switchgear Room CB261292 Standby Switchgear Room CB261293 Standby Switchgear Room CB261294 Standby Switchgear Room CB261295 Standby Switchgear Room Amendment 16 1 of 3 December 1984
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| Nine Mile Point Unit 2 EQD TABLE 2-2 (Cont)
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| Zone El 289'-0" CB289297 Relay Room CB289298 Relay Room CB289301 Relay Room CB289394 Relay Room CB289395 Relay Room El 306'-0" CB306311 Main Control Room CB306312 Main Control Room CB306313 Main Control Room CB306314 Main Control Room CB306315 Main Control Room CB306317 Main Control Room CB306321 Main Control Room El 261'-0" DG2 61330 Diesel Generator Rooms DG261331 Diesel Generator Rooms DG261332 Diesel Generator Rooms DG261333 Diesel Generator Rooms DG261334 Diesel Generator Rooms DG261335 Diesel Generator Rooms El 272'-0" DG272337 Diesel Generator Rooms DG272338 Diesel Generator Rooms DG272339 Diesel Generator Rooms DG272340 Diesel Generator Rooms DG272341 Diesel Generator Rooms DG272342 Diesel Generator Rooms Amendment 16 2 of 3 December 1984
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| L Nine Mile Point Unit 2 EQD TABI.E 2-2 (Cont)
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| Zone Descri tion Electrical Tunnels El 215'-0" ET2 15239 Electrical Tunnels ET215240 Electrical Tunnels ET215241 Electrical Tunnels ET215243 Electrical Tunnels ET215244 Electrical Tunnels Service Water Buildin El 224'-0" SW224365 Service Water Pump Room SW224366 Service Water Pump Room El 261'-0" SW261367 Service Water Pump Room SW261368 Service Water Pump Room Amendment 16 3 of 3 December 1984
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| Nine Mile Point Unit 2 EQD TABLE 2-3 MILD ENVIRONMENT ZONES WITH SPECIAL FILTERS Zone Descriptions Control Buildin El 289'-0" CB289297 Relay Room CB289298 Relay Room CB289301 Relay Room CB289394 Relay Room El 306'-0" CB306311 Main Control Room CB306312 Main Control Room CB306313 Main Control Room CB306314 Main Control Room CB306315 Main Control Room CB306317 Main Control Room Amendment, 16 1 of 1 December 1984
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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
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| 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.
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| 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.
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| 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.
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| 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.
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| 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.
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| Not all systems listed in Table 3-1 include equipment located in harsh environments.
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| 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.
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| 3.3 POST-ACCIDENT OPERABII ITY TIME Equipment must required to perform be qualified for the length of time its safety function and must remain itinisa Amendment 16 3-1 December 1984
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| 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.
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| 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.
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| The PAOP is indicated in the EQD Master List, Appendix A.
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| Amendment 16 3-2 December 1984
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| Nine Mile Point Unit 2 EQD TABLE 3-1 SYSTEMS LIST Abbreviation ~S stem ISC Reactor System and Nuclear Boiler CIS Containment Isolation (See Note 1 to Table 3.1-2)
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| RDS Control Rod Drive SLS Standby Liquid Control NMS/TIP Neutron Monitoring/Traversing Incore Probe RPS Reactor Protection System LDS Leak Detection (See Note 2 to Table 3.1-2)
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| PRM/ARM Process Radiation Monitoring/Area Radiation Monitoring RHS Residual Heat Removal CSL Low Pressure Core Spray CSH High Pressure Core Spray ICS Reactor Core Isolation Cooling FHE Fuel Service, Reactor Vessel, Invessel, Storage, and Refueling Equipment SSP Post-Accident Sampling System SFC Spent Fuel Pool Cooling ADS/SVV Automatic Depressurization/Main Steam Safety Relief IAS Instrument Air SWP Service Water GTS Standby Gas Treatment EGS Emergency Diesel Generators (including CSH DG)
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| Amendment, 16 1 of 2 December 1984
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| Nine Mile Point Unit 2 EQD TABLE 3-1 (Cont)
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| Abbreviation ~S stem EGF Diesel Generator Fuel Oil (including CSH DG)
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| EGA Diesel Generator Starting .Air (including CSH DG)
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| CMS Containment Monitoring GSN Nitrogen Inerting HCS Hydrogen Recombiner Control Building Chilled Water HVN Chilled Water-Ventilation Reactor Building Ventilation Diesel Generator Building Ventilation Yard Structures Ventilation Control Building Air Conditioning ACP Auxiliary AC Power System DCP DC Power Systems RPC Reactor Building Polar Crane RRS Redundant Reactivity Control CNS Condensate Makeup/Drawoff DFM Miscellaneous Floor Drains DWS Domestic Water System TME Turbine Gland Seal and Exhaust Amendment 16 2 of 2 December 1984
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| Nine Mile Point Unit 2 EQD TABLE 3-2 SYSTEM/ACCIDENT MATRIX FSAR Accident Abbreviation Reference Control Rod Drop Accident CRDA 15.4.9 Fuel Handling Accident FHA 15.7.4 Loss of Coolant Accident LOCA 15.6.5 (inside primary containment)
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| High Energy Line Break (ICS/WCS) HELB 15.6.4 (outside primary containment)
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| Main Steam Line Break MSLB 15.6.4 (outside primary containment)
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| Feedwater Line Break FWLB 15.6.6 (outside pr..mary conta .nment)
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| Anticipated Transients Without ATWS 15.8 Scram Amendment. 16 1 of 5 December 1984
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| Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)
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| Accident
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| ~sstem CRDA FHA LOCA HELB MSLB FWLB ATWS CZS< 1 ) X X ISC X
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| SLS NMS/TIP RPS LDS<2) X PRM/ARM X X CSL CSH ICS FHE
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| 'SP SFC IAS ADS/SVV 'X X X SWP GTS X
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| '
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| EGS EGF X X Amendment 16 2 of S December 1984
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| ~ ~
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| Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)
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| Accident
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| ~Sstem CRDA FHA LOCA HELB MSLB FWLB ATWS EGA X X X X CMS X X GSN X X HCS HVK X X HVN X X HVR X X X HVP HVC X ACP X X DCP X '
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| RPC'4' RRS CNS~~'WS'6'ME<<
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| ~
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| Amendment 16 3 of 5 December 1984
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| A Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)
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| Notes CIS, primary containment isolation, includes the following systems whose only post-accident function is primary containment isolation (unless, otherwise noted):
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| ~ Reactor coolant system (also serves an ATWS function)
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| ~ Reactor water cleanup system (also serves an ATWS function and is part of LDS)
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| ~ Service air system
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| ~ Breathing air system
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| ~ Reactor building closed loop cooling water system
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| ~ Main steam system (also part of ADS/SVV and LDS)
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| ~ Feedwater system (also serves an ATWS function)
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| ~ Containment purge system
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| ~ Reactor building floor and equipment drain systems (also part of LDS)
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| ~ Fire protection system
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| ~ Leakage monitoring system LDS, the leak detection system, includes temperature, flow, and/or level instrumentation, in the following systems:
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| 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
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| Nine Mile Point Unit 2 EQD TABLE 3-2 (Cont)
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| 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.
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| 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.
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| One CNS boundary valve is used to prevent bypass leakage in the event of a LOCA inside the primary containment.
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| DWS and TME require QA Category I components based on special system considerations. No environmental qualification is required.
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| Amendment 16 5 of 5 December 1984
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| t Nine Mile Point Unit 2 EQD TABLE 3-3 SWEC/GE SYSTEM CROSS REFERENCE
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| ~sstem SWEC Code GE Code Nuclear Boiler ISC B22 Mainsteam MSS B22 Feedwater FWS B22 Automatic Depressurization B22 Recirculation RCS B35 Control Rod Drive RDS C12 Redundant Reactivity Control RRS C22 Standby Liquid Control SLS - C41 Neutron Monitoring NMS C51 Process Radiation Monitoring D13 Post Accident Sampling SSP D24 Residual Heat Removal E12 Low-Pressure Core Spray CSL E21 High-Pressure Core Spray CSH E22 Ieak Detection LDS E31 Reactor Core Isolation Cooling ICS E51 Reactor Water Cleanup WCS G33 Amendment 16 1 of 1 December 1984
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| 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.
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| These requirements are included i'n the procurement specification for the safety related electrical equipment.
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| The specification mandates that the qualification will be accomplished in accordance with IEEE 323-1974 and in accordance with the quality assurance program referenced in 10CFRSO Appendix B.
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| Based on these specification requirements, the equipment manufacturer develops an equipment qualification program.
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| 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
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| 'environments and accident environments resulting from a spectrum of LOCAs and HELBs. equipment justification is considered acceptable when it The is demonstrated that equipment can perform its required safety function under postulated environmental conditions.
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| 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 conditions and provides it simulates plant sufficient margin. Factors considered during the review of testing include test Amendment 16 4-1 iDecember 1984
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| Nine Mile Point Unit 2 EQD procedures, test setup, test sequence, margin, and test anomalies.
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| 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.
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| 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.
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| 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.
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| 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.
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| Arrhenius aging methodology is used for accelerated thermal aging and is the preferred method for evaluating equipment aging. When other methods are used, appropriate justification is provided.
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| In the case where accelerated aging was used, the procedure employed considered the expected application and design life of the device being tested.
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| 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, documentation it has been addressed.
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| is included in the EQ file.
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| Appropriate 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.
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| When type testing was selected as the qualification method, "
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| 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
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| Nine Mile Point Unit 2 EQD unit(s), including aging. The sequence given in IEEE 323-1974, Paragraph other sequences used are 6 '.2, is generally justifiable on used. However, 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.
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| 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.
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| Some equipment's required by the design to perform its safety function only within the first 10 hr of an. accident.
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| 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.
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| For all other equipment, the 10-percent time margin identified in IEEE 323-1974 was used unless a .reduced amount, could be justified.
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| 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
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| Nine Mile Point Unit 2 EQD the equipment or component was considered qualified for .the beta'nd gamma radiation environment.
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| 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.
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| Synergistic effects involving dose rate are not addressed.
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| However; where synergistic effects of radiation and temperature were identified prior to the initiation of qualification, they are 'included in the program.
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| ~Anal sis I
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| The use of analysis for qualification is in conformance with 10CFR50.49(f).
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| 4.1.2 NSSS Equipment - Electrical Safety-related electric NSSS equipment located in a harsh environment includes all three categories of 10CFR50.49(b).
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| A Master List of this equipment is provided in Appendix A.
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| 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.
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| 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 (10CFR50 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.
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| Amendment 16 December 1984
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| Nine Mile Point Unit 2 EQD The approach to qualification described in on type testing being the preferred approach.
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| NEDE-24326-1-P's predicated 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
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| .
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| 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.
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| Where type testing is performed, the approach usually taken is as follows:
| |
| Assure the device is functional under normal conditions as well as under extremes .of such conditions.
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| : 2. Device condition.
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| is aged to an end-of-qualified life
| |
| : 3. Device is subjected to dynamic simulation.
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| : 4. Device is subjected to design basis event conditions and post design basis event conditions.
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| : 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.
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| 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'~'.
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| . Following the completion of the tests all of the associated documentation that led to the test and was generated during Amendment 16 December 1984
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| Nine Mile Point Unit 2 EQD the test is formally assembled. into a qualificati'on report.
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| That report is available for NRC audit..
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| 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.
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| I Amendment 16 December 1984
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| | |
| Nine Mile Point Unit 2 EQD Methodolo The review consists of the following five-step. process.
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| : 1. Identification of safety-related mechanical equipment
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| : 2. Identification of nonmetallic components
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| : 3. Identification of environmental design conditions
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| : 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.
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| Each material identi fi ed was examined to determine the effect of the environmental conditions on the material Amendment 16 December 1984
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| | |
| 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.
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| : 2. The C of C shall identify the supplied equipment by equipment mark number.
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| 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.
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| The requirements for any scheduled surveillance, maintenance calibration,, periodic tests, and parts replacements necessary to maintain qualification.
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| 4.2.2 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.
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| : 2. The equipment manufacturer's design functional characteristics envelop the Unit 2 application specific functional performance requirements.
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| : 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.
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| Amendment 16 4-10 December 1984
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| | |
| 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
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| | |
| I Nine Mile Point Unit 2 EQD SECTION 5 QUALIFICATION DOCUMENTATION
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| '5.1 MASTER LISTS (ML)
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| 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.
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| This list includes and identifies 10CFR50.49(b) equipment categories 1, 2, and 3.
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| 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.
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| The ML includes and identifies the follow'ing:
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| 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.
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| : 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.
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| review identifies such cases they will be included If the 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.
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| 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).
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| Amendment 16 5-1 December'984
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| | |
| 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) .
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| 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.
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| 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
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| | |
| ~
| |
| ~
| |
| a a
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| <<<<%
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| NINE NILE POIHT DOCKET NUMBER QUAL REF 4 (EQUIP HO.:
| |
| ISPEC HO.)
| |
| lSYSTENl a
| |
| a a
| |
| a
| |
| <TYPE(
| |
| -
| |
| (DESCRIPTIOH)
| |
| UNIT 2 50-410 EQUIPMENT DESCRIPTION REV a'='='='='*====================t I as a a I IOP al TINEt IITBP (F)'
| |
| )I NORMAL
| |
| <<
| |
| PARANETER I SPECIFIED ABNORMAL(
| |
| ACCIDENT)
| |
| I a
| |
| VALUE Cft a
| |
| a I
| |
| a SYSTB I QUALIFIED s VALUE
| |
| '. Figure 5-1 CONPONEHT EVALUATIOH NORK SHEET ENVIROHNEHTAL COHDITIONS AND QUALIFICATION s
| |
| )
| |
| I s
| |
| I a>>
| |
| I a,
| |
| DOCUNENT REFERENCE SPECIFIED
| |
| .1 1
| |
| 1 I
| |
| s I
| |
| I I
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| I QUALIFIED I NETHOD
| |
| ?Ia CC
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| "
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| '2 2
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| 2 2
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| a'5 21~
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| "
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| a s
| |
| s I
| |
| I QUAL PAGE
| |
| "
| |
| ~
| |
| OF a
| |
| a I
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| I I
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| aI I
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| l NA HA 1
| |
| 1
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| )MARGIH) t DEMO a a
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| a I
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| I I
| |
| a aa 13-Dec-84 RENARKS NOTE I NOTE 2
| |
| '
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| 1l
| |
| ~
| |
| ~
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| I a
| |
| a a
| |
| a I'PRESS(PSIG) I "---- I
| |
| ----- ' ---- t ----" I
| |
| "-"-- I - - -s - HOTE I a
| |
| la HORNAL. I a s 1 I 2 I I NA a
| |
| a Il ABHORNALI a
| |
| I I 2 I HA INANUFACTURER: ls ACCIDENT(
| |
| a I 1 I 2 a a a
| |
| a 'IRH (X)' "- --- ' ---- ' ---- I --"-- ' -"-- I - - -I - HOTE 1 INODEL NO)t ts NORNAL I 1 I 2 I HA sl ABNORMAL) a I 1 t 2 I s NA
| |
| )SAFETY FUNCTIONS ll ACCIDENT( a ) 1 I 2 I ~, s I a aRADIATIOH' --"-- I
| |
| ----- I ----- ' -"-- I
| |
| ""--- I
| |
| "- -s " HOTE I a
| |
| a )I HORN GAMMA) s I. 1 a 2 HA I II ACC GANMA I 1 t 2 I I IOPa CODE) 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
| |
| <<a<<<<>>
| |
| s I HA IACCURACY - " IISUBNERGEHCEI a a HA I SPEC:
| |
| a a Ie <<C a@ C~
| |
| s s DENOl I I a
| |
| I I (ZONE NO.l a I I IFLOOD LEVEL sl OOCUNEHT REFERENCEt NOTES'.FOR CONPLETE EHVIROHNENTAL CONDITIONS,I t ELEVATIOHt as 1. EQUIPNEHT QUALIFICATION ENVIRONMEHTAL DESIGH "SEE THE DOCUNENT REFERENCED.
| |
| IABOVE FLOOD s I CRITERIAe EQEDC 1) REV I) NAY 2) 1984 2 NORNAI. TENPERATURES ARE SHONH AS , I s LEVEL? I a 2, VEHDOR ENVIRONNEHTAL QUALIFICATION REPORT, NAX DESIGN/AVERAGE.
| |
| IABOVE SPRAY/ ls SDDF 4 s FROTH LEVEL? la 3. EQUIPMENT OPERABILITY TINE DATA SHEET) a a a a IDOCUNEHTATIOH ACCEPTABILITY: 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
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| ,/
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| | |
| 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 maintain retrievable records.
| |
| is expected to operate and to 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 additional information, such as corrective maintenance if 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 indicating work completion, which will document made 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 PAGE 1 ENVIRONMENTAL QUALIFICATION DOCUMENT SAFETY-RELATED ELECTRICAL EQUIPMENT MASTER LIST (M )
| |
| EQ'JXP! lENT XD DESCRXPTXON VENDOR NAHE SPiC ZONE ZI QREF OPCOD OPT
| |
| + 2AASwHCV130 BRTHG AXR CNTHT ISOL V VELAN P30AH SC 289155 H
| |
| + ZAAStHCV135 BRTHG AIR CNTHT XSOL V VELAN P30iH SCZC0100 H
| |
| +ZAAS<HCV136 BRTHG AIR CNTHT ISOL V ViLAN P30QH PCZ89581 H
| |
| +ZAAS vHCV137 BRTHG AXR CNTHT ISOL V VELAN P30~H PCZ00503 H
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 2 EQUIPtiEHT ID DESCRIPTIGN VEHDOR HAHE SPEC ZCNE ZX %REF OPCOD CPT ZCCP>>AGV37A AIR OPERATED PLUS VALVE ATTHGGDt.t!GRRILL P30LiK ABH1750% H A 100 DYS ZCCP>>AGV37B AIR OPERATED PLUS VALVE ATTHG DZ!l RRXLL P30QK ABS17509 H A 100 OYS ZCCPi'AGV3SA AIR OPERATED PLUS VALVE ATTHOGDtt!QRRZLL P30QK AB!ll755/ H A 100 DYS ZCCP>AGV3SB A R CFERATFD PLUS VALVE ATTHCGDc'tlGRRILL P304K ABS17509 H A 100 OYS
| |
| +ZCCP>HQVXZZ ORS-CONT ISG ZNBD VELAH P30QR PCZ%0612 H A 100 DYS
| |
| +ZCCPw'.fCV12ct DRS-CChT XSO CUTBD VELAil P30QR SCZtl0135 H A 100 OYS ZCCP>>t!GVZQA GATE VLV SFCicEZA I~V cT VcLAN P30>>R SC215122 H A 100 OYS
| |
| +ZCCP>>t'GVIRB GATE VLV SFC+ 1B XHLET VELAN P304R SC215122 H A 100 DYS
| |
| +ZCCP+t!GV15A RCS-CONT ISO OUTBO VELAN P304R SC261145 H A 100 DYS
| |
| +ZCCP<HGVX5B RCS-CGilT ISO GiJTBD VELAH P30QR SC261105 H A 100 DYS
| |
| +ZCCPwt!OV16A RCS-CONT ISO INBD V LAiN P3QQR PC2616%9 H A 100 DYS
| |
| +ZCCPwtfOVX6B RCS-CGiNT ISO XHSO VELAtl ENG.CO. P30<R PC2616ctl H A 1GO DYS
| |
| +2CCPii! fGV17A RCS-CG!tT ISO OUTBD VELAN P30cf R SC261105 H A 100 OYS
| |
| +ZCCP tt!OV17B RCS-CONT ISG CUTBD VELAN P304R SC261105 H A 100 DYS ZCCP+t'QV~SA GATE VLV. SFCYEXA OUTLET VELAN P30>>R SC215122 H A 100 DYS ZCCPv'lGV'SB GATE VLV. SFC+EZB OJTLET VELAN P30>>R SC215122 H k 100 OYS ZCCP+tfCVZZA GATE VLV. RCS OUTLET BLCCK VLV VELAN P304R SC261145 H A 100 DYS ZCCP+tfGVZZB GATE VLV. RCS CUTLET O'LOCK VLV VELAH P3GQR SC2611>>>>5 H A 100 DYS
| |
| +ZCCPwtlOVZ65 DPS-CONT ZSO OUTc".D VELAN P35QR SC2%0135 H A 100 DYS
| |
| +iZCCP+!!GV273 DRS-CONT ZSO XHBD VELAN EhS CORP P30clR PCZ50630 H A 100 OYS ZCCPwtfGV93A GATE VLV. RCS INLET BLOCK VLV VELAH P30QR SC2611i5 H A 100 DYS ZCCP+!fGV93B GATE VLV. RCS Zt!LET BLOCK VLV VELAN P30qR SC2611q5 H A 1,00 DYS c,CCP+l'lGV94A RCS-CONT ZSO Xt!BD ViLAH P3CtlR PC261609 H A 1CO DYS ZCCP>'.lQV9<B RCS-CiiNT XSO XiHBD VELAN P304R PC2616Q1 H A 100 DYS ZCCPc'PT90A RBCLCH TO PCS-PlA CLRS ROSEVG'JNT C071! f SCZ61145 H ZCCPicPT9OB RBCLCH TO ZRCS-PlA CLRS ROSEtlGUNT C071H SCZ>>>>0135 H
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 3 EQUXPHKHT ID DESCRIPTION VENGCR NAKE SPEC ZONE ZI GREF GPCOO GPT ZCES<RAK105 IhSTRUtlEHT RACK tlERCURY CO. C051P SC261145 H ZCES~RAK106 XhSTRUHENT RACK t t ERCVR Y CO. C051P SC261145 H CeS<WAK107 XNSTRL4l:-NT RACK tlERCURY CO. C051P SC261 45 H ZCKSaRAK108 IHSTRB(EilT RACK HERCURY CO. C051P SCc89155 H ZCESi'RA)(109 IHSTRL".(KNT RACh HERCURY CO. C051P SCZ89155 H ZCES+RAK231 Xt(ST(((2(Ei(T RACK tlERCURY CO. C061P l(STZ8949 H ZCESwRAK232 Xt(STRL(KKHT RACK HeRCURY CO C061P HSTZ8949 H ZCKS<Z01E PENETRATXCN NEUTRON HiQH (B) CGiiAX CORP E021P PC250621 H ZCESRZOZE PENETRATION HEUTRCN t(GN (B) CONAX CORP E021P PCZ40603 H ZCESvZ06E PEHETRATIOli iNSTR (G) CGiNAX CORP E021P PC240603 H ZCESxZ08E PEtiETRATIGN COiiTRGL (G) COiiA'( CORP E021P PCc40603 H ZCESKZ10E PENETRATXGN CONTROL (G) CGNAX CORP E021P PC240603 H ZCESwZ11E PEiN-TRATION iNEUTRON tlG l (G) CGNAX CORP E021P PC2506c.5 H ZCESwZXZE PENETRATIGH NEUTRON HO,I (G) COt(AX CORP E021P PC240607 H ZCESxZX7E PENKTRATIOH RPS CONTROL (Y) CO)iAX CORP E021P PC250627 H ZCESNZ18E PEHETR PGHKR CONT & INSTR (Y) CCNAX CORP E021P PC240609 H ZCES<ZX9E PENETRATIO.'l COitTRGL (Y) CONAX CORP EOZiP PC~50627 H ZCESvcZZOK PEHETRATXON CCNTROL (Y) COtiAX CORP E021P PC240609 H ZCKSxZZXE PEHKTRATXGN 600V POKER (Y) CGNAX CORP EOZlP PC250627 H ZCES>ZZZE P c HETR AT I ON XhSTR ( H ) CGNAX CORP E021P PC240609 H ZCES~Z23E PENETRATICH NEUTRON HON (Y) CGNAX CORP E021P PCZ50627 H ZCESwZ24E PEH TRATIGH NEUTRON t G<t (Y) COtiAX CORP E021P PC240609 H ZCESAZ25E PENETRATION CONTROL (Y) CONAX CORP E021P PC250527 H ZCESKZ26E PENETRATXGil RPS CONTROL (Y) CONAX CORP E021P PCi.40609 H ZCES<Z29K PENETRATION NEUTRON tlOil (0) CGNAX CORP E021P PCc.50630 H ZCKSNZ30K PENETRATXGN HKUTRGN HON (0) CGNAX CORP E021P PCc.40612 H ZCES+Z5)E PENETRATIGH RPS COitTROL (B) CONAX CORP E021P PC240601 H
| |
| | |
| PAGE 0 EG'JIPllENT ID DKSCRIPTXO".l VENDOR NAHK SPEC ZCNE ZI OREF OPCOD GPT ZCKS>>Z52E PENETRATXGN RPS CONTROL (G) CONAX CCRP E021P PC250623 2CES>>Z53E PENETRATION HPCS CCiNTROL (P) CONAX CCRP E021P PC261609 H ZCES>>Z54E PKNETRATICN HPCS CCNTROL (0) CCiNAX CORP 0"1P PC"506~0 H ZCES>>Z57E PKNETR F"HKR CO'NT 2, IhSTR (G) E021P PCc,151Z1 H ZCES<Z58E PEhFTR POHER CGiNT 8 XiNSTR ( Y ) COiNAX CCRP E021P PC215121 H ZCES>>Z59E PENETR POHER CChT 8 IhSTR (Y) COiNAX CCRP 021P PC2151Z1 H 2CES-Z03E PEh TRATICN RPIS INSTR (N) CGiNAX CORP KOc.lP P C250621 H c,CES ZONK PEiNKTRATIGil RPXS IhSTR (N) CC:lAX CORP E021P PCZC0603 H c.CKS-Z13K P EhETRAT ION RP XS XNSTR ( N ) CGNAX COicP E021P PCZ50625 H ZCKS-ZlQK PENETRATION RPIS INSTR (N) EOZIP PCZQ0607 H 2CES-Z15E PENETRATXOli RPIS INSTR (N) E021P PC250627 H 2CES-Z16E PENETRATION RPIS IHSTR (H) E021P PCZO0609 H ZCES-Z27E P~NcTRATION RPIS INSTR (H) E021P PC250630 H ZCES ZZOK PEiNETRATXON RPXS INSTR (N) EOc,lP PCZQ0612 H ZCES-Z31E PENETRATION 600V PCHER (N) E021P PCZ616%1 H 2CES-Z32E PENKTRATICH 600V POiiZR (H) E021P PCZ61601 H 2CKS-Z33E PEtiKTRATIGN CONTROL (N) E021P PC261601 H ZCKS-Z3QE PENETRATION CONTROL (tl) EOZ1P PC261601 H 2CES-Z355 PENETQAT C"l INSTR (N) CGNAX CORP E021P PC261601 H ZCKS-Z36E PFNKTRATION INSTR (N) E021P PC261641 H 2CES-Z37E PEiiETRATXON CONTROL '(N) E021P PC261601 H ZCES-Z38E PENETRATICN COiiTROL (H) K021P PC261601 H 2CES-Z39E PEhETRATXCN INSTR (N) COr(AX CORP E021P PCZ616cll H ZCES-ZQOE PENKTRATXON CC.'lTROL (N) E021P P C261601 H
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| | |
| PAGE
| |
| '
| |
| EQUIFHKNT ID DESCRIPTION VENDOR HAHE SPEC ZONE ~ ZI %REF OFCOD OPT 2CES-Z40E PEHETRATIOH CONTROL (N) E021P PC261641 H ZCES-Z41E PEHETRATIOiH COHTROL (N) E021P FC261649 H ZCES-Z42E PENETRATION IHSTR (H) CCNAX CORP E021P PC261649 H ZCES-Z43E PENETRATION CONTROL (H) E021P PC261649 H A 2CES-Z44E PENETRATION INSTR (H) COHAX CORP EOZlP PC261649 H 2CES-Z45E PENETRATIOH 13.8 HV (H) E021P PC261649 H ZCES-Z46E PENETRATIOH 13.8 HV (H) E021P PC261649 H ZCES-Z47E PENETRATION 600V POHER (H) E021P PC261641 H ZCKS-Z40E PENETRATION UNASSIGNED E021P PC261644 H ZCES-Z49E PEHETRATIOH 600V FOHER (N) E021P PC261649 H 2CES-ZSOE PENETRATION UNASSIGNED E021P PC261649 H ZCES-Z55E PENETRATION 600V FOHER (H) E021P PC261641 H 2CES-Z56E P EHETRATIOH UhSIGNED E021P PCZ15121 H ZCES-Z60E PENETR POHER CONT 4 INSTR (H) CONAX CORP EO ZIP PC215121 H
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| | |
| PAGE , 6 EGUIPHENT ID DESCRIPTION VENDOR NAHK SPEC ZONE ZI TREF OPCOD CPT ZCt S<<CAB)OA CONTIIT ATH LEAKAGE RADN KAV~c INSTH PZB)F SC289155 H ZCHS<<CAB)08 CONTIIT ATtl LEAKAGE RADN ~!AN INSTH P28)F SC289155 H ZCHS4ALT))A SUPPRESSION POOL LEVEL ROSEHOUNT C071H SC)75102 H
| |
| +2CHS>>LTl)B SUPPRESSION POOL LEVEL ROSEViCUiNT C07)H SC)75105 H LUCIS>>LT9A SUPPRESSICN POOL LEVEL ROSEHOUNT C07)H SC175102 H
| |
| +CCIIS<<LT98 SUPPRESSIO'I POOI LEVEL ROSEROUNT C07)H SC)75102 H ZDS>>P hl.66A H.Z ANALYZER PNL A COtlSZP INC. C001C ABN24033 H ZCHS>>PtiL668 H.2 ANALYZER PNL 8 CC'SIP IKC. C001C ABS24036 H
| |
| + ZCPS<<PT)A COi'ITAINIIENT DRYHELL PRESS ROSEt!CUNT C07)H SC289155 H
| |
| + ZCHS>>PT)B CO'iiTAINIIENT DRYIIELL PRESS ROSEHCUNT C07)H SC269155 H
| |
| + ZCHS<<PT2A CONTAINHEtlT DRYHELL PRESS ROSEt tOUNT C071H SC261145 H
| |
| + ZCVSvPTc.B CONTAINHEiNT DRYHELL PRESS ROSEHOUiiT C071H SCZ61145 H
| |
| + ZCt!S>>PT7A SUPPRESSION CHAISER PRESS ROSEt! 0 JNT C071H SC240135 H
| |
| + ZVS<<PT78 SUPPRESSION CHAHBER PRESS C07)H SC261145 H 2CHS<<SOVZ3A DRYHELL AIR SAIPLE TARGET ROCK CORP P304X PC289680 H 100 DAY ZCES>>SOV238 DRYHELL AIR SAHPLE TARGET ROCK CORP P304X PC289681 H 100 DAY ZCHS<<SOV23C DRYilKLL AIR SAtPLE TARGET ROCK CORP P304X PC4289680 H 100 OAY 2CHS<<SOV23D DRYHELL AIR SAtPLE TARGET RCCK CORP P304X PC289680 H 100 DAY ZCtlS>>SOV23E CRYHELL AIR SAIPLE TARGET ROCK CORP P304X PC289680 H 100 DAY ZCHS<<SOV23F DRYHELL AIR SAIPLE TARGET ROCK CORP P304X PC289660 H 100 OAY
| |
| + ZCtS<<SOV24A DHAIR CIPL INBD ISOL TARGET ROCK CORP P304X PC28968) H 100 DAY
| |
| + ZCt!SvSOV248 CHAIR SIPL IhoD ISCL TARGET ROCK CORP P304X PC269681 H 100 DAY
| |
| + 2CHS<<SOV24C DH AIR SIPL OUTBD ISOL TARGET ROCK CORP P304X SC289155 H 100 DAY
| |
| + 2CtS<<SOV240 DH AIR SIPL OUTBD ISOL TARGET ROCK CORP P304X SC289155 H 100 DAY
| |
| '2Ct S>>SOVZSA SUPP CHt!8 AIR SAIPLE TARGET RCCK CORP P304X PCZ)5121 H 100 DAY ZCHS<<SOVZ58 SUPP CHIS AIR SAtPLE TARGET ROCH CORP P304X PC21512) H 100 DAY ZCIS<<SOV25C SUPP CHHB AIR SAtPLE TARGET ROCK CORP P304X PCZ)5121 H 100 DAY ZCt S>>SOV25D SUPP CHHB AIR SAtPLE TARGKT ROCK CCRP P304X PC215121 H 100 DAY
| |
| + 2CHS>>SOV26A SUPP CHt!8 AIR StPL INBD ZSO TARGET RCCK CORP P304X PC215121 H A 100 DAY
| |
| + ZCHSvSOV268 SI!PP CHIIB AIR SVIPL ZN BD ISO TARGET ROCK CORP P304X PCZ)5121 H A 100 DAY
| |
| + -ZCKS>>SOV26D SUPP CHHB AIR SHPL OUTBD ISO TARGET ROCK CORP P304X SC215122 H A 100 DYS
| |
| + ZCltS>>SOV32A DRYIIELL SIPL RTN OUTBD ISOL TARGET ROCK CORP P304X SC261145 H A 100 DYS
| |
| + 2CVS<<SOV3ZB DRYHELL< SIPL RTN CUTBD ZSOL TARGET ROCK CORP P304X SC 261145 H A 100 DYS
| |
| + 2CHS>>SOV33A DRYHELLt SIPL RTN INBD ISOL TARGET RCCK CORP P304X PCZ61644 H A 100 DYS
| |
| + ZCHS>>SOV338 DRYKELI StPL RTH INBD ZSOL TARGET ROCK CORP P304X PC261649 H A 100 DYS
| |
| + 'ZCHS<<SOV34A SUPP CHHB StPL RTN IhBD ISOL TARGET ROCK CORP P304X PCZ)5121 H A 100 DYS
| |
| + ZCt!S>>SOV348 SUPP CHI!8 SV<PL RTN IhBD ISCL TA'RGET RCCK CCRP P304X PCZ)512) H A 100 DYS
| |
| + ZCHSvSOV35A SUPP CHIIB SIPL RTN OUTBD ISOL TARGET ROCR CORP P304X SC215122 .H A 100 DYS
| |
| + 2CI!S>>SOV358 SUPP CHIS SIPL RTN ZNBD ISOL TARGET ROCK CORo P304X SC215122 H A 100 DYS
| |
| + ZCHS>>SOV60A DH RADN CUTBD Zt>> ET ISOL TARGET ROCR CORP P304X SC289155 H A 6 HRS
| |
| + 2CVIS>>SOV608 DH RADN CUTDD INLET ZSOL TARGET ROCK CORP P304X SC306175 H A 6 HRS
| |
| +. ZCHS>>SOV6)A DH RADN INBD INLET ZSOL TARGET ROCK CORP P304X PC306713 H A 6 HRS
| |
| + ZCHS>>SOV618 DH RADN ZNSD INLET ISOL TARGET ROCK CORP P304X PC306713 H A 6 HRS
| |
| + 'c.Ct IS>>SOV62A DH RADN OUTBD Olfii.ET ISOL TARGET ROCK CCRP P304X SC289155 H A 6 HRS
| |
| + 2CHS<<SOV628 DH RADN OUTBD OUTLET ISOL TARGET ROCK CORP P304X SC261145 H A 6 HRS
| |
| + iZCIS>>SCV63A DH RADN INBD OUTLET ISCL TARGET ROCK CORP P304X PC261644 H A 6 HRS
| |
| + 2CIS>>SOV638 DH RADN INBD OUTLET ISOI. TARGET ROCK CORP P304X PC261649 H A 6 HRS
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 7 EWJIPIIEHT XD DESCRXPTXCH VENDOR NAKE SPEC ZONE ZI I!REF OP COD CPT ZCIISvSCV64A Hc/0? ANALYZER XN XSOL TARGET ROCK CCRP P304X ABttc.403'3 H A 100 0YS ZCHSKSOV648 HZ/02 ANALYZER XHL XSOL TARGET ROCK CCRP P304X AB S c. >> 03 6 H A 100 DYS ZCIIS<<SQV65A HZ/02 ANALYZER OUT XSGL TAPGE< ROCK CORP P304X ADNZ4033 H A 100 DYS ZCHS<cSGV74A PAS SAIIPLE A LOOP TAr<GET RG K P304n SC240135 H A 100 DYS ZCI IS<'SQV74B PAS SAHPLE-0 LOOP TARGET ROCK P304X SC245135 H A 100 DYS ZCI!S<SOV7SA PAS SAIIPLE-A LCQP TARGET ROCK P304X SC"40135 H A 100 DYS ZCllS<<SGV75B PAS SAtFLE-B LCQP TARGET ROCK P304X SC2>>0135 H A 100 DYS ZCI!SccSQV76A FOST LOCA SA!!PL SUCT ISCL V TARGET ROCK P304X SCZ40135 H A ZCIIS<'SOV76B POST LOCA SAH!<PL SUCT XSQL V TARGET ROCK P304X SC240135 H A ZCHS<cSOV77A PCST LOCA S'I!PL RTH ISCL V TARGET POCK P304X SC240135 H A ZCIIS<<SOV778 POST LOCA SAHPL PTN XSCL V TARGET Ri>>CK P304X SC" 40135 H A
| |
| +ZCIIS cc TE 102 DRYKELL AREA TEIIP PYCO CO41D PC<289681 H
| |
| + c. Cf tS<'< TE 103 DRYItELL AREA TEtfP PYCO C041D PCZ51641 H
| |
| +~>>CIISccTE104 DRYHELL AREA TEIIP PYCO CC410 PC261649 H
| |
| +ZCIIS<cTE105 DRYhELL AREA TEI!? PYCO C041D PC250619 H
| |
| +>>".Cf!S xTE106 DRYhELL AREA TEt!P PYCO C041D PC c.40612 H
| |
| +ZC! IS<<TE107 SUPP CHAt!BER AREA TEf!P PYCQ C0410 SC215122 H
| |
| +'ZCISccTE108 SUPP CHA't!BER AREA TEt!P PYCO C041D PC215121 H
| |
| +>>.Ct IS<t TE1 09 SUPP CHAi'!BER AREA TEt!P PYCO C0410 PC215121 H
| |
| +ZCIS<<TEXI6 DRYHELL ARc":A TEt!P PYCO C0410 PC306713 H
| |
| +>>iCIIS<cTE117 DRYHELL AREA TEI!P PYCO C041D PC269681 H
| |
| +ZCtlS>TE118 DRYhELL A'QEA TEt!P PYCO C041D PC261649 H
| |
| + ZCIISsTE119 DRYflELL AREA TEIIP PYCO C0410 PCZ61638 H
| |
| + ZCHS<tTE120 DRYHELL AREA TEIL PYCO C0410 PC250625 H
| |
| + ZCI IS<< TE121 DRYhELL AQEA TEt!P PYCO C0410 FCZ>>0603 H
| |
| +CCHS< TE122 SUPP CHAI!BER AREA TEf!P P YiCO C041D SCc.1512? H
| |
| +>>>>Ct IS<<TE123 SU?P CHANGER AREA TEKP PYCO C0410 PC2151 1 H
| |
| + ZCHS<cTE124 SUPP CHA!!BER AREA TEI!P PYCO C041D PC215121 H ZCIIS<<TESOA SUPPR POCL HATER TEIIP PYCO C0410 SC196113 H ZCIIS<<TESOB SUFPP. POOL HATER TEt!P PYCO C0410 SC195113 H ZCIIS<fTESOC SUPPR POOL hATER T I!P PYCO CO41D SC196113 H ZCIIS)cTESOD SUPPR POOL ltATER TBIP PYCO C041D SC196113 H ZCIISccTE51A SUFPR PCQL hATER TEIP PYCO CO>>10 SC196113 H ZCtIS<<TE51B SUPPR PQQL HATER TEfP PYCO C0410 SC196113 H 2CI IS<< T ESXC SUPPR PCCL !INTER TBIP PYCO CO>> 0 SC196113 H ZCIISc<TE510 SUPFR PCCL HATER TEI!F PYCO C0410 SC196113 H ZCIIS<<TESZA SUrPR FCQL HATER TB!P PYCO CO410 SC195113 H ZCt $ <TESZB SUPFR POOL NATc:R TEIP PYCO C0410 SC196113 H ZCHSv<TESZC SUPPR FCQL HATER TEIL FYCO C041D SC196113 H ZCHS<cTESZD SbrPR POCL HATER TEIIP PYCO C0410 SC196113 H ZCIIS<TE53A S<JPP PCCL hATER TEI!P PYCO C041D SC195116 H cCtIS<<TE530 SUPP PCCL HATER TEI!P PYCO CC410 SC196116 H c,CIIS<cTE53C SUPP PCQL HATER TEILo PYCO CO/10 SC195116 H C,CI!S<ETE53D SUPP POCL HATER TEI!P PYCO C0410 SC195116 H ZCIIS>lTE54A SUPP PCQ'ATER TEHP PYCO ,C 0410 SC195116 H ZCIIS<TE54B SL<rPP POOL fiATER TEI!P PYCO C0410 SC196116 H ZCHS<cTE54C SUPP PC L HATER TEHP PYiO C0410 SC196116 H 2CMS*TE101 DRYWELL AREA TEMP PYCO C041D PC3067 13 H
| |
| + = REGULATORY GUIDE 1.97.
| |
| | |
| PAGE 8 EQ)Ict.ENT XD DESCRIPTIOH VEHDQR HAH" SAEC ZONK Zi TREF 0?COD QPT ZCt!StTK5%0 SUPP FOCL HATER TEtP PYCO COR10 5C195116 H ZC2iSxTE55A S'L'PP FQQL HATER TFIP PYCO COQID SCI96116 H ZCI!Si'TE5cB SUPP PQQL hATER TEiP PYCO CO%10 SC196116 H ZCI!Si'TESSC S"i"P POQ'ATER TEtP PYCO CO%10 SC195116 H ZCISiiTE559 SUPP FOOL HATcR TEt!P F YCO CO:I10 SC196116 H ZC"cvTK"5A SUPP PCQL HATER TEI!P PYCO CO%ID SC196116 ZCtISi'TE55B SUPP PQQL hATER TctP PYCO C0410 SC196116 H ZCI!S>TE56C SU"P FQCL HATER TEIP PYCO CO%ID SC 195116 H ZCIISvTE560 SU?P PQQL HATER TEt!P PYCO C0 F10 SC196116 H 2CtIS>TE57A SL'FP FQCL V!ATER TEi PYCO C0410 SC196116 H ZCIISwTE57B SUPP FQQL HATER TEIP PYCO CO%ID SC195116 H ZC!ISwTE57C SU?i". PQ L H"TER TEIP PYCO CO%10 SC196116 H
| |
| : i. Ct IS)s TE57 0 SUPP PCQL HATER TEIP PYCO COi10 SC196116 H ZCIIStTE58A SUPP PGQL HATER TE!P PYCO CO%10 SC196113 H ZCIIS<TE58B SUPP POOL I;ATER TEIP PYCO C3010 SC195113 N ZCIISiiTE58 SUPP POQL HATER TEtP P CQ CO%10 SC196113 H ZCIIS~TE589 SucP PQCL hATER TEIP PYCO Cceio SC196113 H ZCIIS<TE59A SUF? PQQL HATER TEtP PYCO CO%ID SC195113 H ZCIIS~TK599 SUPP PGQ'L HATER TEtP PYCO CO%10 SC196113 ZCI!SiiTES9C SUPP PQQ'ATER TEtP PYCO CO%10 SC196113 H ZCIISaTE590 SUrP PQQL HATEiR TEt!P PYCO CO%ID SC196113 H
| |
| + ZCHS~TE67A SUPP FQCL IIATER TEIIP PYCO C0019 PC215121 tl
| |
| + ZCI!SwTE67B SUPP PCQL HATER TEtP PYCO CO%ID PC215121 H
| |
| + ettlS<TE68A SUPP FQQL HATKR TEtP PYCO CO~ID PC215121 H
| |
| + ZCtlSi TK58B SUPP PQQL IIATER TEIP PYCO C0410 FC215121 H
| |
| + ZCIIS<TK59A SUPP PQQL HATER TEIP PYCO CO%ID PC215121 Hi
| |
| + ZCIISiiTE69B SUPP PGQL VATER TEtP PYCQ C04 0 PCZ15121 H
| |
| + <<CtIS+TE70A SUPP POOL HATFR TE'IP PYCO CO%19 SC215122 H
| |
| + ZCHSwTE70B SUPP PQQL HATER TEIIP PYCO CO%10 SC215122 H
| |
| + = Regulatory Guide 1,97,
| |
| | |
| PAGE 9 EQUIP))EHT ZO DESCRZPTZCH VENDOR H!THE SPEC ZON ZX TREF CFCOO GPT 2CPSVAOV104 2CPS-FHl DH Ihl. CUTBD V POSI-SEAL IHTFR. P304D SC269155 H 8 ZCPS vAOV105 ZC?S-FHZ SUPPR XNL OUTGO V FOSX-SEAL XNTER P304D SC215125 H 8
| |
| + ZCPS>AOV106 ZCPS-FN1 GH X!HL ZhSO V POSI-SFi".L IHT ER. P3045 PC269681 H 8
| |
| + ZCPSiik V107 ZCPS-FN1 SUPPR Xhl XNSD V FCSI-SEAL ZiNTER. P304D PC215121 H 8
| |
| + ZCPS))AOV108 DRYHELL EYiH XHBD XSC' POSZ-SEAL INTER. F304D PCZ89681 H 8
| |
| + ZCPSi!AOVX09 SUFPR EXH Xh=D ZSQL V POSZ-SEAL XHT. P3C4D PC215121 H 8
| |
| + ZCPSi!ACV110 DRYHELL EXH OUTED ISOL V PCSZ-SEAL INTER P304D SC289155 H 8
| |
| + ZCPSgAOV111 SJPPR EXH CJTBD ISQL V POSI-SEAL INTER. P304O SC21512Z H 8
| |
| + ZCPS>SOV119 SUPPR XiP CUTBD ISGL V TARGET ROCK CCRP P304X SC2151!22 H A
| |
| + ZCPS>SQV120 DRYhELL Ihi CiJTB'D ISO! V Tk'RGET ROCK CORP P304X SC289155 H A
| |
| + .ZCPci!SCV121 SUPPR I)F Xh=D XSGL V TARG<<T RCCK CORP P304X FCZ15121 H A
| |
| + 'ZCi"SxSCVIZZ DRYHELL INL NSD XSOL V TARGET RO K CORP F304X PC289681 H A
| |
| + = Regulatory Guide 1.97.
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| | |
| PAGE 10 EQUIPtlENT ID DESCRIPTIOit VEtiDCR NAKE SPEC ZOtlE ZI TREF OPCOD OPT
| |
| + 'ZCSttvAQV108 "CSH-PI DISCH TEST CHECK AhCHORr'DARLING 'P303H PC306718 A CCSHwttCVICO REACTOR VESSEL tlAltD CONTROL VELAN P300E PC306711 A QCSH<tt HFCS SYS PRESSL'RE tlOTOR GOULDS PUttPS INC. PA SC175108 A
| |
| + = Regulatory Guide 1.97.
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| | |
| PAGE ll EQUXP!!ENT XD DESCRXPTXGN VENDOR NAHE SPEC ZONE ZX TREF GPCGD GPT 2CSLNFVXXQ CGRE SPRAY PU."9 TEST BYPASS CGP ES-VULCAN C051H SC175 03 H
| |
| + 2CiLw"GV~ OQ LPCS XNJECTXGN VALVE V LAN P30iR SC289155 H A 100 OYS 2CSLAiHGV107 GATE VALVE VELAN P304R ABN17503 H A 100 DYS
| |
| + CCSL+HGV112 LPCS PiNP SUCT VALVE CLGH CORP P3CQY SC196110 H A 100 OYS
| |
| + 2CSLA'AOV101 INBD TESTABLE CHECK ANCHOR/DA>T.ING P303W PC306711H A 100 DYS VALVE
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 12 EQUXPttENT XD DESCRXPTXON VENDOR NAttE SPEC ZONE ZX %REF OPCOD OPT ZDER<ttOV119 GATE VALVE VELAN P304S PCZ15121 H A 6 HRS ZDERwt tOV120 GATE VALVE VELAN P30QS SC215125 H A 6 HRS ZDER~ttOV128 GLOBE VALVE UELAN P304R PC2%0606 H B N/A c.DERE!tOV129 GLOBE VALVE VELAN P300R PC200506 H B N/A ZOER+ttOV130 GLOBc VALVE VELAN P30RS PC&0603 H A 6 HRS ZDERxt tOV131 GLOBE VALVE VELAN P304S S"2003.35 H A 6 HRS
| |
| | |
| PAGE 13 E'tttIPt i tT 10 DESCRIPTXON VEtFQOR NAttE SPEC ZONE ZZ TREF OPCOD OPT 2DFR>LS143 RHS 8 PtP RH FLD HTR LVL HAGNETROL C021L ABS17509 H 2Q FR vLS144 RHS C PttP Ri't FLO HTR LVL VAGtt TRQL C0 21L ABS17508 H 2DFR>LS145 ICS PttP RHi FLD HTR LVL ttAGNETRQt. C021L SC175106 H 2DFRvLS146 CSH Pt'.P RH FLD HTR LVL ttAGNETRCL C02 L SC175108 H 20FRtLS147 CSL Pi't? Rtt FLO HTR LVL HAGNETt'OL C021L AB."t17503 H 20 F RMLS14 8 RHS A PHP Ril FLD HTR LVL HAGNETROL C021L ABN17504 H 2DFR<<LS3A 2RHSx51A CUBECLE FLOQDEO ttAGNETRQL C021L ABN17505 H 2DFR>HQV120 GATE 'VALVE VELAN P304S SC215123 H A
| |
| +2QF Rat tQV121 GATE VALVE VELAN P304S PC215121 H A 2DFRxttQV139 GATE VALVE 'VELAN P304S SCC't0 37 H A
| |
| +2DFRxtlQV140 GATE VALVE VELAN P304S PC240601 H A
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 10 EQUIPHKNT ID DESCRIPTION VENDOR NA!'iE SPEC ZONK ZI 'QRKF OPCOD OPT 2DNStkKCAI 125li~aC ViCC RB ELEV. 200 GOtP Do INC. EDISON ABNZ0033 H 2DMS+ttCCBI 125VDC HCC RB ELEV. 206 GOVLD EOIM ABS20036 H
| |
| | |
| PAGE 15 EQJIPHEHT ID DESCRIPTIOH VEHDCR HAHE SPEC ZOHE ZI QREF OPCOD OPT 2EHStHCC102 ST~~KOBY HCC CLASS lE GOLR.D E015Q A""HZ%033 H ZEHSditCC302 EHERG HiCC GOULD E015Q ABS20036 H
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| | |
| PAGE 16 EQUIPHEtiT ZD DESCRIPTZOH VFHDOR HAIIE SPEC ZOHE ZZ QREF OPCOD OPT ZEJANPHLIOOA RB 120V HEATER PhL BROHH BOVERI E01RT ABHZR033 ZEJA<PtiL3005 RB 120V HEATER PHL BRONH BOVERZ EOlRT ABSZR036 K ZEJAxXDIOOA DIST XFHR 600V-ZOOY/1ZOV SQUARE IDis E011T ABHZR033 H ZEJA<XD3005 DZST XFHR 600V-ZOSY/120V SQUARE D E011T ABSZR036 H
| |
| | |
| PAGE 17 EQUIPHENT ID DESCRIPTIOi'l VEiNDCR NAHe SPEC ZONE ZI TREF ~ OPCOD OPT ZEJS>PNLIOIA SHSR RH A EHER 600V Phl. BRO!iN BOVERI E014T ABN24033 ZEJSwPiV 103A AB-N EHER 600V PhL BRCHN BOVFRI E014T AGN24033 H ZEJSxPNL104A AB-N tHER 600V PNL BROHil BOVERI E014T ABN24033 H ZEJSxPNL302B AB-S EHER 600V PNL BROh.l BOVERI E014T ABSZ4036 H ZEJSvPh" 303B AB-S EHER 600V PNL BRO!iN BOVFRI E014T ABS24036 H ZEJSxPNL304B AB-S EllKR 600V PNL BROhl GQVERI E014T ABS24036 H
| |
| | |
| PAGs 18 EQUIPNENT ID DESCRIPTIOi l VENDOR NAHE SP C ZOilE ZI QREF OPCOD OPT ZEPSvSH8001 13.6HV EllERG SHG001 GOULD BROHN BOVE E015N ABN24033 H ZEPSvSHG002 13.6HV ENERG ShS002 GOL" 0 BROHN BOVE E015N ON~4033 H ZEPSwSHG003 13.6HV EHFRG SHG003 GOULD BROHN BOVE E015N ABS24036 H ZEPSwSHG004 13.6HV EllERG ShG004 GCULD BROS BOVE E015N ABS24036 H
| |
| | |
| PAGE 19 EQUIPHENT ID DESCRIPTION VENDOR VMlE SPEC ZONE ZI TREF OPCOD OPT
| |
| +ZFFHwSOV218 ZRCS-PlA FIRE PROT HTR CONT TARGET ROCK CORP P30QX SC200135 H 8
| |
| +a.rPi4SQV 19 ZRCS-P1A FIRE PROT HTR CONT TARGET ROCK CORP P30QX PC250625 H 8
| |
| +RFPH<SOV220 2RCS-P18 FIRE PROT HTR CONT TARGET ROCK CORP P30QX SC200135 H
| |
| +ZFPKwSOV221 ZRCS-P18 FIRE PROT HTR CONT TARGET ROCK CORP P30QX PC 250619 H 8
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 20 EGUIcVENT ID DESCRIPTION VEhDCR NAPE SPEC ZONE ZI TREF QPCOD QPT
| |
| + ZFHSiiAQV23A FEEOHATER TESTABLE CHECK Ah~NOR/DARLING P303H t(ST20005 H A 006 HRS
| |
| + ZfttS+AQV23B FFEDitATER TESTABLE CHECK ANCHOR/DARLIitB P303H t!STZR045 H A 006 HRS
| |
| + ZFHSmtlQVZIA GATE VALVE VELAN P30CR ttST24005 H A 006 HRS
| |
| + ZFHSi tlOVZIB GATE VALVE VELAN P30~R HSTZQ005 H A 006 HRS egu atory Guide 1.97.
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| | |
| PAGE 21 t(tUEPt!ENT ID DESCRIPTION VENDOR HAKE SPEC ZONE Zl t!REF OPCOD GPT ZGTS((AOVIOI PRIl ARY CONT PURGE ISCL V POSX-SEAL IHT. P304D SC306181 H C ZGTS((CHIA FILTER TRAXH A HEATER tliNE SAeETY APPL P243U SSZ61355 H A ZGTS((CH19 FILTeR TRAXH 9 HEATER Hit!E SA. FTY APPL P243U SG261355 H A c.GTSxDl!P1A TCRNADO DCIPER-SSTS BLDS PACIFIC AIR PROD P413T SGZ61356 H B ZGTS((Ct !PXB TORNADO DAt!PER-SSTS BLDG PACIFIC AZR PRCO P413T SG261355 H 9 2GTSRDt!P2A TORNADO DAttPER-SSTS BLOS PACXFIC AIR PROD P413T 50261355 H 9 ZGTS+Oit!PZB TORNADO DAt!PER-SSTS BLDG PACIFIC AZR PROD P413T SS261355 H 9 ZGTS((FHZA wFLTXA DISCHARGE FAN BUFFALO FORGE P413S SS261355 H A ZGTS((FNZB ((FLTZB DISCHARGE FA",l BUFFALO FORGE F413S SG261355 H A ZGTS('t!GVIA BUTTERFLY OR TRICEHTRXC VA'E CLCH CORP P304Y SC306181 H A ZGTS((t!OVID BUTTERFLY GR TRXCEHTRZC VALVE CLOH CCRP P304Y SC306181 H A ZGTS((t!GVZA BUTTERFLY CR TPyCet!TRIC VA( V CLGH CGPP P304Y SS"61355 H A ZGTS('3!OVZB BUTTERFLY OR TRICENTRIC VALVE CI.OH CORP P304Y SGc.613o5 H A ZGTS((lfOVZBA CROSS-BLEED L VLV CLO!l CORP P304Y SS261355 H A ZGTS( 3 !GV289 CROSS-BLEED L VLV CLC!i CORP P304Y SS261355 H A 2STS((t! QV3A BUTTERFLY OR TRICENTRIC VALVE CLOtl CORP P304Y SS261355 H A ZGTSot!OV39 B(JTTERFLY CR TRICE'iTRIC VALVE CLOH CCRP P304Y SS261355 H A ZGTSwt!CV4 GATE VALVE VELAH P304R SG261356 H A ZGTS((HOV49 GATE VALVE VELAN P304R SG261355 H A ZSTS((PDITZIA ZSTS((FLT lA DIFF PRESS tlIHE SAFETY APPL P243U SG261356 H A ZS(S((PDITZZB ZGTS((FLT 19 DIFF PRESS HIHe SAFETY APPL P243U SS261355 H A ZGTS((PV5A RX BLDG IN/GUT DIFF PRESS CLCH CORP P304Y SS261355 A ZGTS>PV59 RX BLDG IH('OUT DIFF PRFSS CLCH CORP P304Y SS261355 A ZGTS+SGVI 02 PRXttARY CONT PURGE ISOL V TARGET ROCK CORP P30(tX SC306181 C ZGTS~TEX26A FLTR TRAIN HTR IHLET TEt!P HINE SAFETY APPL P243U SG 261356 A ZSTS((TEX269 ZGTS((TEY26A FLTR TRAIN HTR INLET Tit!P FLTR TRAXN HTR CUTLET TEt!P tlI¹ SAFETY APPL P243U SS261355 A HXNE SAFETY APPL PZ43U SG261356 A ZGTS((TEY269 FLTR TRAIN HTR CUTLET TEHP t!XNE SAFETY APPL P243U SG261355 A ZSTS((TZS 3A CHARCCAL ADSCRB Tet!P H NINE SAFETY APPL P243U SG261355 A ZGTS((TIS239 CHARCOAL ADSORB TEt!P H llltiE SAFETY APFL P243U SS2613o5 A ZGTS>XDIA XFHR 600-480V HIHE SAFETY APPL PZ43U SGc.61356 A ZGTS<XO19 XFHR 600V-480V llINE SAFETY APPL PZ43U SS261355 A
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| | |
| PAGE ZZ Et)UIP))EHT XD DESCRIPTZON VENDOR NA'))E SPEC ZCiKc Zl OREF OPCOD OPT ZHCSiiIPhLZZA HZ RECOi)!8 PHR CAB ATCi)IC INT. P28ZH AB))20033 H A ZHCSsXPiV 228 H2 RECCi?BIiNER CAB H2 RECO!!3 F)iR CAB P282H ABSZQ036 H A
| |
| + ZHCSi t!QVlA RBihRlA OUTLET CUTBD ZSOL HZ RECO)!3 FhR CAB P304S SC215123 H A
| |
| + ZHCSxt!CV18 RBNRlA OUTLET OUTBD ISOL RBNR1A OTLT OTBD XSC P30>>>>S SCZI5132 H A
| |
| + ZHCS+!!QVZA RBNR1A XhLET OUTLBD XSCL RBNRIA Zh" T OTBQ ISO P30>>S SC215122 H A
| |
| + ZHCSxt)OVZB RBNRlA IhLET CUTLBD ISCL H2 RECCH3 P))R CAB P30>>S SC215122 H A
| |
| + 2)lCSiit!QV3A RBNR1A Xh>> ET GUTLBD ISCL HZ RECO)tB PhR CAB F3045 SC240140 H A
| |
| + ZHCSiit)QV38 RBiiR18 Zti" ET OUTLBD XSOL HZ RECOHB PHR CAB P30>>S SCZQ0103 H A
| |
| + ZHCSxt)OV4A RBhRlA OUTLET Xt)30 ZSCL VELAH P300S PC215121 H
| |
| + ZHCSw?IQVCB RBNR18 CiJTLET ZNBD XSQL VELA?) P30>>S PC215121 H
| |
| + ZPCSiit'QV>A RBN1A INLET XNSD ISGL HZ RECOHB PhR CAB P30>>>>S FC215121 H A
| |
| + ZHCS~)!OV58 RBN18 INLFT INBD ISQL HZ RECC!!3 PHR CAB P30QS PC215121 H A
| |
| + "HCSii)iQVi6 RBt)lA ZN'T IHSD ZSCL . HZ RECC!!3 Pi!R CAB P30>>S PC250621 H A 1
| |
| + ZHCSx"QV68 RBN18 IiNLET INSD XSQL HZ RECOH3 FNR CAB P30>>S PC250629 H A ZHCS+RBNRIA HYCRGGEH RECCHB lA HZ RFCO'i!8 PHR CAB PZBZH SCZQ0135 H A 1 2HCS>RB))R18 HYDRCGEH RECO!iiB 18 H2 RECCHB Pi)R CAB P28 i.H SCZQ0135 H A ZHCSiiSGVIOA RBNR1A CLG HTR IhLET TARGET RGCH CCRP P30>>X SC?))0135 H A 2?iCSwSGV103 RBNR18 CLG l<TR XNLET TARGET ROCK CGRP P30>>>>X SCZ>>0135 H A ZHCS+SQVIIA RBNR1A CLG HTR DRAIN TARGET ROCH CORP P30>>X SCZQ0135 H A
| |
| ?HCSxSOV118 RBNR18 CLG HTR DRAIN TARGET ROCK CORP F30%X SC240135 H A
| |
| + = Regulatory Guide 1.97.
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| PAGE 23 EOUIPHENT ID DESCRIPTION VeNDOR N"'tf SPEC ZZ fcREF OPCOD OPT
| |
| + <<ZHVR<<AODIA SUPPLY AIR ISOL DtPR PACIFIC AIR PROD PQI3T SC289155 H PQ13T. 02 8
| |
| + ZHVR<<AODIB SUPPLY AIR ISOL DtPR PACIFIC AXR PROD PQ13T SC 289155 H PQ13T. 02 8
| |
| + <<ZHVR<<AODIOA EXH AXR ISGL DtPR P"CXFXC AXR PROD PQ13T SC289155 H P413T. 02 8
| |
| + <<ZtiVR<<cAODIOB EXH AXR ISOL DHPR PACIFIC AIR PROD PQ13T SC209155 P413T. 02 8 ZHVR<<AGD114 R CXRC AIR OIPP.-RX BLDG PACIFIC AXR P D PQ13T SC306175 H C ZHVR<<r<<ODZOQ RFAC HO EVAC FLT3 DISCH DiPR PACXFXC AIR FROG PQ13T SC289155 H P413T. 03 C 2H'VR<<AOD3QA <<UCQ13A TEST OtPR PACXFIC AXR PROD P>>13T SCc.89155 H P413T. Ol 8
| |
| <<.HVR<<iAGD3QB UC4138 TEST DtPR PACIFIC AXR PROD PQ13T SCZS9155 H PQ13T. 01 8
| |
| + rZHVR<<AGD5A <<UC413A XhiLET OFPR PACIFIC AXR PROD PQ13T SC289155 H PQ13T. 02 8
| |
| + 2HVR<<AGD58 <<UC4138 ItiLET CtPR PACIFIC AIR PROD PQ13T SCZ89155 H PQIGT. 02 8
| |
| + wHVR<<AGD9A EXH AIR ZSOL DtPR PACXFIC AXR PROD FQ13T SC289155 H PQ13T. 02 8
| |
| + <HVR<<AGD98 EXH AIR ZSOL D!PR PACIFIC AIR PROD PQ157 SCZS9155 H P413T. 02 8 2HVR<<CAB14A RX BLDG ABV REFUEL FL FAON P<<.SI SC328187 H ZHVR<<CABIQB RX BLDG ADV REFUEL FL FADN P c.SIF SCGZ8187 H ZtfVR<<Cr'832A RX BLDG BLH REFUEL FL RAON PZSIF SC3281S7 H 2HVR<<CAB328 RX BLDG BLH REeFUeL FL RADN P28IF SC328187 H ZHVR<<F E18A RX BLDG Et!KRG RKCXRC UC413 A HCC FOifERS C071A SCc.89155 H czif VR<<F e 188 RX BLDG Kt!KQG RECXRC UC4138 HCC POrfKiQS C071A SCZ89155 H ZHVR<<FEISC RX BLDG EHKRG RECIQC UC413A HCC POH RS C071A SC289155 H 2HVR<<FE SD RX SLOG Et!KRG RKCXRC U 4138 t!CC POHERS C071A SC289155 H ZHVrc<<cFE36A ABV REFUEL FLAIR FLOH HCC PCHKRS C071A SC353ZOZ H ZHVR<<FF368 ABV REFUEL FLAIR FLON k!CC PCHKRS C671A SC353c202 H
| |
| <<.HVR<<eE37A BLH REFUEL'FLAIR FLOH t!CC POriE'RS 'C071A SC289155 H ZHVR<<FE378 BLH REFUEL FLAXR FLO'ri l!CC PGHFRS C071A SCZ89155 H 2HVR<<SGV235 GLOVE VALVE TARGET ROCK P3OQX SCZ89155 H ZHVR<<TISI15 RHR HT E.c R'f 8 <<UC406 t!CC POHKRS C071A ABS19620 H ZHVQ<<TIS16A KLKC tf"C ARKA UCQ09A t'CC POci'eRS C071A ABSZ>>036 H 2HVR<<TXS168 eLEC lrCC AReA U 4098 t!CC POiiERS C071A ABSZQ035 H 2Hl/R<<TIS19A ELEC H"C AREA<<UCQOSA HCC PCrieRS C071A AEN24633 H
| |
| ?HVR<<TIS198 ELEC HCC AREA<<UCQOSB HCC FOHERS C071A ABNZ>>033 H
| |
| <<HVQ<<TXS22A LPCS PP Rtf <<UCQOZA t!CC POciKRS C071A AB!f17503 H ZHcVR<<TISZ c.B LPCS PP RH <<UC'f628 ttCC PO!iKRS C071A ADN1 7503 H c.HVR<<TXS23A RHR PP Rtf A fcUCQOIA l!CC PGHERS C071A ABN17504 H
| |
| <<.ii'VR<<TISc238 RHR PP RH C <<UCQOIB HCC PGHERS C071A ABSI7508 H 2fiVR<<TXS23C PHR PP Rt'I 8 <<UC>>OIC HCC F""eRS C071A ABS17509 H 2HVR<<TXS 3D RHR PP Pt'l A <<UCQOID HCC PC!tERS C071A ADftl7504 H ZHVR<<TXS23E RhP PP R"f C <<UCQOle lfCC PC!fERS C671A ABS17508 H ZHVR<<TISc23F RHR PP Rfl 8 <<UC>>OIF HCC PGHEQS C071A r<<BSI7509 2H'VR<<TISZQA HPCS PP RH <<UCQ03A HCC PCHERS C071A SC196115 H 2HVR<<TXS<<.QB HPCS PP Rtf <<UC4038 HCC PCKKPS C071A SC196116 H 2HVR<<TXSZ5A GEN AREA EL175 <<UCQOQA l!CC FOHKRS C071A SC195116 H ZHVR<<TXSZDD GEh AREA EL175 <<UCQOQB lf C FCciERS C071A SC196113 H ZtlVR<<TIS25C GEN AREA EL175 <<UCQOQC HCC PGHKRS C071A SC196113 H ZHVR<<TIS 258 GEN AREA .EL175 <<UCQOQD HCC PCHEPS C071A C'96'15 H
| |
| ?hVR<<iTIS?6A GEN AREA EL215 <<UC407A HcCC POHKRS C071A SC215122 H 2HVR<<TXS258 GEN AREA ELZ15 <<UC4078 HCC PGiiKQS C071A SC215122 H ZHVR<<TXS25C GEN AREA EL?15 <<UC407C ffCC POHKRS C071A SC215122 H
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 24 EQUIP!!ENT ZD DESCRIPTION VEh~~OR NAIIE SPEC ZONE ZX QREF OPCOO OPT ZHVrRcvTXS259 GEN AREA ELZ)5 xUC407D I!CC FCHERcS C07)A SCZ)5122 h ZHVRxTXS~6c G ii ARcA EL215 %UC402E HCC PO!aERS C07)A SCc)5122 H ZHVR+T S27A GEN AREA EL240 IaUC4)DA HCC POHERS C071A SC240135 H ZHVR+TXS228 GEii a"'REA EI.240 ViUC4)GS HCC PO'riERS C02)A SC24C)35 H ZHVR+TZSZ7C G N AREA EL?40 xUC4)OC l!CC FOHERS C07)A SC240135 H ZHavaR>TIS20A GEH AQEA EL261 >UC4))A PCC PCri RS C071A SC26))45 H ZHVRviTXSZSB GEN AREA EL251 wUC4))8 HCC FOHERS C07)A SC261)45 H Zt!VR>TXSZOC GEII AREA EL261 NLaC4~)C Il"C POHERS C07)A SC261145 H ZHVRaaTIS30A GEN ARFA EL261 wLaC4)ZA HCC POHERS C071A SC)75)C5 H ZHVR>TES303 GEii AREA EL261 taUC4)28 HCC POHERS CD71A SC)73106 H ZHVRxTXS3)A UC413A INLET TEIP I!CC PCHERS C07)A SCZ69155 H ZHVR>TIS3)B U 41'33 ihLET TFI!P I!CC POHERS C07)A SC209155 H ZIIVR>>TZS35A GEN AREA EL26)+aJC4)4A t!CC PCHERS C07)A SCc.6)145 H ZHVRa TIS353 GsH AREA ELZ6)taUC4)48 HCC POHERS CD7)A SC261)45 H ZHVR>TIS3SA GTS RH A ~UC4)+A taCC PCHERS C071A SGZ61355 H ZHVRaaTZS30S GTS Ri'I A aaUC4)53 HCC PCNERS C02)A SGc.61355 H ZHVRaaaJC40)A RHR PU!P RiH A - UNZT CLR A!IERiC'N AIR FLT P412tl ASN)7504 H 8 ZHVRxUC40)B RHR PUlP Rtl C - UNIT CLR A!IERECAN AIR FLT P41?Jl ABS)7500 H 8 ZHVRaaUC40)C RHR PU!iP RH 8 - UtiIT CLR AIIERICAH AIR FLT F412H ABS)75D9 H 8 ZHVR+UC40)O RHR PUHP Rtl A - UiNIT CLR AIIERiCAN AIR FLT P41211 ABN)7504 H 8 ZHVR>aJC40)E RHR PU!!? Rtl C - UNIT CLR A! IERICAN AIR FLT P412tt ASS)7508 H 8 ZHVR+aJC40)F RHR PPi!P Rtl S - LiNiIT CLR AHERICAN AIR FLT P4)ZH ABS)7509 H 8 ZHaac'aaUC402A LPCS FU!P Rtl UaNIT-.CLR AIIERICAN AIR FLT P412tl ABN)7503 H 8 ZHVRNUC4023 LPCS PUt!P Rll UNIT CLR Al!ERICAN AER FLT F41211 ABN)7503 H 8 ZHVRvUC403A HPCS PU!P Rtl UiNIT CLR AtlERICAN AER FLT P4)ZH SC)75)00 H 8 c.HVR>>UC40'3 HPCS PU!IP RH UNIT CLR A!!ERICAN AIR FLT P>>1~I! SC)25~09 H 8 ZHVRanJC404A RS EL 175 GEN AREA U'IXT CLR AtlERICAN AiR FLT P4)~"I SC)96116 H 8 ZHIV~UC4048 RS EL 175 GEH ARcA UNIT CLR AIIERICAN AXR FLT P>>12H SC)96113 H 8 ZHVR~UC404C RB EL 175 GEN AREA UNIT CLR AclcRXCAN AXQ FLT P412H SC)96113 H 8 ZHVR~UC4040 RB EL 175 GEN AREA UNZT CLR AHERXCAN AIR FLT P4)c.H SC)96116 H 8 ZHVRmUC405 RHR HEAT EXCH RH UNIT CLR Al!FRXCAN AXR FLT P4)ZII ASN)9615 H 8 ZHV4aaUC405 RHR HEAT EXCH RII LriPiT CLR AailERICAN AIR FLT P4)Ztl ABS19620 H 8 ZHVR+Ua.407A RB EL 215 GcN AREA UNIT CLR AHERXCAN AiR FLT P41? t I SCZ)5122 H 8 ZHVRwUC4023 RB EL Z)5 GEN AREA UNIT CLR A!IERICAN AIR FLT P4)ZH CZ 5122 H 8 ZHVR>U 407C RB EL 215 GcN AREA U!IXT CLR AHERXCAN AIR FLT P412itaa SCZ)5122 H 8 ZHVrRaaUC4070 RB EL Z)5 GEN AREA L'NIT CLR AIIERICAN AIR FLT P4)ZH SC215)ZZ H ZHVR<UC407E RB EL 215 GEN ARcA UNET CLR At!ERICAN AIR FLT P4)ZH SCZ)5122 H 8 ZHVQ+UaC408A ELEC ataiCC AREA LNIT CLR AttcRXCAN AIaQ FLT P41211 ABN24033 H 8 ZHVR+UC4003 ELEC HCC ARcA U!IIT CLR At!ERICAiN AiR FLT F412II ABN24033 H 8 ZHVR~aJC409A ELEC I!CC AREA UNIT CLR Al!EPICAN AXR FLT P412H ABS24036 H 8 ZHVrRa+UC4098 ELEC HCC AREA UNET CLR A"FRICAN AXR FLT P412Hi ASS24036 H 8 ZHVRviUC4)OA RB EL 240 GEN AREA UNIT CLR AHERICAN AIR FLT P41211 SC24O)35 H 8 ZHVRtUC4)03 RB EL 240 GEN AREA U!IIT CLR AIIcRICAN AER FLT F412! I SCZ40135 H 8 HVQaaU"4)DC RB EL 240 GcN AREA LiNIT CLR AHERICAN AXR FLT P4)Z'I SC240135 H 8 rHVRxUC4))A RS EL Z61 GEN AREA UiN'IT CLR AHERiCAti AiR FLT P4)cZt1 SCc.61145 H 8 ZHVR>UC4))S ~ RB SPACE COOLER ELEV 261 AHERICAti AXR FLT F4)ZH SC261.145 H 8 ZHVRNUC4))C RB SPACE COOLER ELEV 261 AHERZCA'I AIR FLT P4)ZH SC261145 H 8
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| | |
| PAGE 25 EOUIPt'ENT ID DESCRIPTXON VEtiDOR NAtlE SPEC ZONE ZX CREF OPCOD OPT ZHVRKUC412A RCIC PUt!P RCOH UNIT CLR Al!ERICAN AIR FLT PRIZH SC175106 H B ZHVRxUC41ZB RCXC PL".P ROON UNIT CLR Al!ERICA t AIR FLT P412tl SC175106 H B ZHVR <UC413A EHERGENCY RECIRC UNIT CLR AHERICAN AIR FLT P4i2H SC289155 H A ZHVR) UC413B EHEFGENCY RECXRC UNIT CLR AtlERICAN AXR FLT P412a l SC289155 H A ZHVRwUC414A EL 261 GEN AREA UNIT CLR AtFRICAN AIR FLT P41ZH SC"61145 H B ZHVRYiUC414B EL 261 GEN ARFA U.'tXT CLR At!ERICAN AIR FLT P412tl SC261145 lt B ZHVRKUC415A SG SPACE COOLER EL261 AHERXCAN AIR FLT P412.H SG261356 H B ZHVRwUC415B SG SPACE COOLER ELZ61 AHERXCAN AXR FLT P412tl SG261355 H B
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| PAGE 26 EGUIPtlEHT XO DESCRZPTXG:I VEhOGR HAKE SPEC ZON ZX GREF 0?COD GPT
| |
| + ZXAS'>>PT161 ADS HEADER A PRESSURE ROSE! IOliHiT C071H SC269155 H
| |
| + 'ZZASIPT186 ADS HEADER 8 P?ESSURE ROSH IOUNT C07ltl SC269155 H
| |
| + ZZASiiPT230 ADS ACCUIFJLATOR TK32 ROSEitlOUiti C07'l SCZS9155 H
| |
| + GXASNPT231 AOS ACCIP.".c%.ATOR TK33 ROS t'OWiT C071tl SCZS9155 H
| |
| + ZXAStiPT232 ADS ACCUI>>i%.ATCR TK34 ROSEt QUNT C071H .SC269155 H
| |
| + ZIASvPT233 ADS ACCLQIULATOR TK35 ROSEHOUilT C071H SC306175 H
| |
| + ZIASwPT23Q ADS ACCUtn% ATOR TK36 ROSBIGUiHT C071H SC306175 H
| |
| + ZIASvPT235 ADS ACClnfL>> ATGR TK37 ROSEtlOUiiT C071H SC306175 H
| |
| + ZIAS<PT236 ADS ACCUllULATGR TK38 RGSB IOUIIT C07 tl SC306175 H ZIAS+SOVX161 ADS HEADER A PRESSURE TARGET RCCK P30QX SC289155 H A DYS ZIASYSOVX186 ADS H ADeR 8 PRESSURE T'RGET ROCK P30QX SC289155 H A DYS ZZASxSOVY181 ADS HEAOEQ A PRESSURE TARGET ROCK CORP P304X SC269155 H A OYS 2IASgSOVY186 ADS HEADEP 8 PRESSU?E TAQGET ROCK CORP P30QX SC289155 H A DYS
| |
| + ZIASxSOV16Q IiNSTR AIR CCNTtlT ISOL V TARGET ROCK CORP P30QX SC289155 H A DYS
| |
| + ZXAStSOV165 IhSTR AIR CONTHT ZSGL V TARGET ROCK CORP P30cIX SC289155 H A DYS
| |
| + ZZASiiSOV166 IhSTR AIR CCHTtiiT ISCL V TARGET RCCK CORP P30QX SCc.S9155 H A
| |
| + ZXASKSOV167 ZhSTR AXR CGIITtlT ISGL V TARGET ROCK CORP P30QX SCZQ0135 H A HON
| |
| + ZZASwSOV168 IHSTQ AIR CGiITIIT ZSGL V TARGET ROCK CORP P30QX SC289155 H A NOH
| |
| + ZIAS<SOV160 INSTR AIR COhTHT ZSOL V TARGET ROCK CORP P30QX PC289681 H A IIOiH
| |
| + ZIAS>>SOVISQ INSTR AZR COHTIIT ZSOL V TARGET ROCK CORP P30QX PCc.89681 H A t.lG'I
| |
| + ZXASNSOV185 IHSTR AIR CONTHT ISOL V TARGET RGCK CORP P304X PCZQ0603 H A HGH
| |
| + = Regulatory Guide 1.97.
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| PAGE 27 EOUXPHEHT ID DESCRIPTZGiN VENDOR Nisi!E SPEC ZGhE ZI ()REF OPCOD GPT
| |
| + ZICS<AOV156 TESTABLE CHKCH V ANCHORi'DARLING P303H SC289155 H A lZ HRS
| |
| + ZXCS<AQV157 TESTAD' Cr".ECK V At(CHCRi'DARLING P303H PC328185 H A 12 HRS ZXCS<F VZOS TEST BYP TO ChDS STOR TH COPES-VULCAti C051H SC175106 H A 6 HRS ZXCSiit!GV116 RCIC LUBE OXL HATER SUPPLY VELAN P304R SC175)06 H A 12 HRS ZICSvt:OVZZO RCIC STEA!l SPLY V TO TURBINE V"LAN P304R SC175106 H A 1Z HRS
| |
| + ZXCS+i'OV121 STEA)( SPLY LXHE XSOL V (OUTBD) VELAN P304R SCZ61150'C196118 H A 12 hRS
| |
| + 'ZICS>t(OVZZZ RCIC TURB EXH TO SUPFR POOL VELAH P304R H A 12 HRS ZXCSi t(QV124 RCIC TEST FCV TO CNDS STOR TK. VELAH P304R SC175106 H A 6 HRS
| |
| + ZXCS<t(GVX26 RCIC XNJFCTION SHUTOFF VALVE VELAN P304R SCZ89155 H A 12 HRS
| |
| + ZZCS<t!QVIZS RCIC ST SPLY LINK ISOL V VELA)i EhG. CO. P304R PC261649 H A 12 HRS ZZCS>!!OV129 PU!!P SUCT FRG!l CNQS STGR TANH V~LAtt 'P304R ABNZ4031 H A 1Z HRS
| |
| + ZICSiit'OV136 PCIC PtP SUCT FRCH SU.""PR PGGL VELA!i P304R SC196117 H A 12 Hi%5
| |
| + ZZCS>t(OV143 RCIC HIN FLOH TO SUPPP. POOL VELAN P 304'R SC196117 H A 12 HRS
| |
| + ZICSiitlGV148 RCIC VAC SRHR ZSGL V(ZNBRD) VKLAH P304S SC196118 H A 12 HRS
| |
| + iZZCSiii!'OV1~64 RCZC VAC BRHR XSCL V (OJTBRD) 'VELAN P304S SC196118 H A 12 HRS
| |
| + ZICSwtlQV170 RCXC STEAtl LINK HARtl-UP VELAN P304R PC261649 H A 12 HRS ZZCSxPCV115 L(iBK OJL CLR PRESS CGiiT V COPES VP CAH C05ltl SC175106 H A 12 HRS
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| + = Regulatory Guide 1.97.
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| | |
| PAGE 28 EQJIPHEHT IO DESCRIPTIOH VENDOR HAKE SPEC ZGHE ZI QREF OPCOD OPT 2IS xSOV119 SOLEHOIO Or ERATED VALVE TARGET ROCK P30QX SC200135 H A 100 DYS ZISC+SOV120 SOLEHOIO OPERATED VALVE TARGET ROCK P30QX SC2151"2 H A 100 DYS ZvSCi'SOVIZ SOLENOID OPERATED GLODc Vgl 'VF TARGET ROCK P30QX SCZ00135 H ZISCxSOV12% SOLEHOID OPERATED GLOSE VALVE TARGET ROCK P30Elx SC215122 H
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| | |
| PAGE 29 EQUIPHEHT ZD DESCRIPTZOH VEhDOR HAKE SPEC ZOHE ZZ TREF OPCOD OPT
| |
| + 2LHSi'SOV152 DRYHELL PRESS IHB ZSOL TARGET ROCK CORP P30VC PC299699 H B 6 HRS
| |
| + c.Li!StiSOV153 DRYhELL PRESS OUT ZSOL TARGET RCCK CORP P30QX SC289155 H B 6 HP.S
| |
| + .2LHS<SOV156 SUPP CHUB PRESS IHS ZSOL TARGET ROCK CORP P30QX PC215121 H B 6 HRS
| |
| + ZLHSwSOV157 SUPP CHUB PRESS OUT ISOL TARGET ROCK CORP P30QX SC215130 H B 6 HRS
| |
| + = Regulatory Guide 1.97.
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| | |
| PAGE 30 EttUIPtlENT ZD DESCRZPTZON VENDOR HAHE SPEC ZONE ZI @REF OPCCD OPT
| |
| + ZHSS!HYV6A HN STtl LINE A INBD ISOLV FLUID SYSTEHS P3030 PC250519 H A 006 HRS
| |
| + ZtlSSt<HYV6B HN STH LINE B XHBD ZSOLV FLUID SYSTElS P3030 PC250619 H A 006 HRS
| |
| + 2ltSSaHYV6C tlN STH LIHc C It!BD XSOLV FLUID SYSTEttS P3035 PCZ50619 H A 006 HRS
| |
| + 2<KSS!<HYV65 KH STtl LIHE 0 INBD ISOL V FLUID SYSTEtS P303D PC250619 H A 006 HRS
| |
| + Zl'iSS>H YV7A li<H ST<tl LIhE A OUTGO tSIV FLUID SYSTEtS P3030 HST24045 H A 006 HRS
| |
| + 2tlSS!<HYV78 t"t STH LlhE B OUTBD llSIV FLUID SYSTEtlS P303D tlSTZ4045 H A 006 HRS
| |
| + ZtlSSvHYV7C Htl STtl LINE C OUTBD llSIV FLUID SYSTEHS P3030 HST24045 H A OC6 HRS
| |
| + ZHSSxHYV70 HN STFI LIiNE 0 OUTED HSIV FLUID SYSTEtS P3030 llSTZ4045 H A 006 HRS ZttSS!<! tQV108 REAC BESSEL HEAD VENT V VELAH P304R PC306711 H C
| |
| + Zt tSS! t tOVlll ttN STEAN DRN XHSD ZSOL V VELAN P304R PCZ40601 H A 006 HRS
| |
| + ZtlSS<<tlQV112 ttN STEA!t ORN CUTBD XSOL V VELAN P304R HST24045 H A 006 HRS 2l fSSwtlOV118 R=AC BeSS"-L HEAD VettT V VELAH P304R PC306711 H C Zt lSS+t tDV119 ~
| |
| REAC BESSFL HEAD VENT V VELAN P304R PC306711 H C ZtSSxt lOV189 XSOL CLG STH LltlE ORV VELAN P304R PC261649 H C ZttSSKtlOV207 ZSB5 tSIV DRH ISCL V VELAil P304R PCZ40600 H C
| |
| +ZHSSxKO'JZ08 XSB5 tSIV ORh XSOL V VELAN P304R HSTZ4045 H A 006 HRS ZHSS<!RVV190 REACTOR HEAD VENT RELIEF GPE CONTROLS P3055 PC240600 H ZHSS>SOV97A BTKH HSXV LXtlE 5R V TARGeT ROCK CORP P304X HS!24045 H ZtSSxSO'J978 BTKiH lSIV LIHE DR V TARGET ROCK CORP P304X HST24045 H ZtSS>SOV97C . BThit tlSIV LZNE DR V TARGET ROCK CORP P304X HST24045 H ZttSS<SOV970 DTKi'l tlSIV LIHE OR V TARGET POCK CORP P304X HST24045 H
| |
| + = Regulatory Guide l.97.
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| | |
| PAGE 31 UZPllENT ID DESCRIPTION VENDOR NAttE SPEC ZOhE ZZ TREF OFCCD OPT
| |
| + 2RCSiiSOV104 2RCS-PlA OZSCH StP ZN30 ISOL TARGET ROCK CORP P30>>X FC261641 H A 006 HRS
| |
| +2RCStiSOV65A RCS HYDR LZNE ISOL SOV TARGET ROCK CORP P304X SC261145 H A 006 HRS
| |
| +ERCSiiSOV65B RCS HYDR LINE ISOL SOV TARGET RO"K CO."P P30>>X SC261145 H A .006 HRS
| |
| +2RCS>SOV66A RCS HYDR LINE ISOL SOV TARGET ROCK CORP P30>>X SCZ61145 H A 006 HRS
| |
| +2RCSvSQV66B RCS HYDR LINE ISGL SOV TARGET ROCK CORP P30>>X SC261145 H A 006 HRS
| |
| +2RCSwSOV67A RCS HYDR LItiE ZSOL SOV TARGET ROCK CORP P304X SC261145 H A 006 HRS
| |
| +2RCSvSOV61B RCS HYDR LINE ZSO'OV TARGET ROCK CORP P304X SC261145 H A 006 HRS
| |
| +2RCSKSOV58A RCS HYDR LINE ISCL SOV TARGET ROCK CORP P304X SC261145 H A 006 HRS
| |
| +2RCS~SOV68B RCS HYDR LZiiE ISGL SGU TARGET ROCK CORP P304X SC261145 H A 006 HRS
| |
| +2RCSiiSOV79A RCS ZNBD HYD LINE ISOL SOV TARGcT ROCK P304X FC261644 H A 006 HRS
| |
| +2RCS>SOV79B RCS IiNSD HYO LZNE ISOL SOV TARGFT ROCK P304X PCZ61649 H A 006 HRS
| |
| +2RCSxSGV80A RCS INBO HYO LINE ISQL SOV TARGET RCCK P30>>'X -
| |
| FC261644 H A 006 HRS
| |
| +2RCSttSOV80B RCS INBD HYD LINE ZSCL SOV TARGET ROCK P304X PC261649 H A 006 HRS
| |
| +2RCSvSOV81A RCS INSO HYO LIiNE ZSGL SOV TARGET ROCK P304X PC261644 H A 006 HRS
| |
| +2RCSxSOV81B RCS ZhSD HYD LINE ISQL SOV TARGcT ROCK P304X FC261649 H A 006 HRS
| |
| +2RCSwSOV82A RCS INSD HYO LItiE ISOL SOV TARGET ROCK P304X PC251644 H A 006 HRS
| |
| +2RCSvSOVSCB RCS INBD HYD LINE ZSOL SOV TARiET ROCK P304X PCZ61649 H A 006 HRS
| |
| +2RCS*SOV105 2RCS-PlA DISCH SMP TARGET ROCK P304 X PC26164 5 H A 006 HRS OUTBD ISOL
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 32 E'WZPIIKNT ZD DESCRZPTIOil VKNQQR h<At!K SP C ZONE ZZ f!RKF CPCOD OPT ZRHS<<AGV163 RHR B TESTABLE CHECK VALVE ANCHCRIDARLZhG P303H PC289685 H A ZRHSvAGV16C VCH090-E-i!f7 At!CHGRIDARLING P303H PC306711 H A 100 DYS
| |
| '2R!IS'AOV39A RHR A SHT DN COOLING CHK VALVE ANCHCRIDARLING P303H PC250620 H A ZRHS~AOV393 RHR 3 SHT DN CCCLING CHK VALVE AiNCHCRIDARLIhG P303H PC250628 H A ZRHS<<EcV5 ZRHSNPDTISB DRAGON VALVE C15 C SCZR0135 H ZRHSiiFV3SA RHR LCQP A TEST RETURN COPIES-VU'AN CG51! I SC19511R H A 100 DYS ZRHS<<FV383 RHR LCQP A TEST RETURN COPIES-VIF CAN C051! I SC215122 H A 100 DYS ZRHSwFV38 RHR LGGP C TEST RETURN COPIES-VIF CAN C051H SC215122 H A 6 HRS ZRHS>HCV53A RHS LIhK A TO c.HSS-RFV1 Vc:LAN P30RE PC305711 H A ZRIIS<<HCV535 RHS L.NE D TO 2l!SS-RFV1 VELAN P30RE PC305712 H A ZRHS>HCV53C RHS LiNE C TO Zl!SS-RiV1 VKLAN PSORE PC30671Z H A ZRI!S~HCVSRA 2"ISS-<I~VI SPUTDKN I."NE A VELAil P30R PC2616R3 h A
| |
| +ZRHS~HQVIC RHR P<t!P PlC SUCTION CLOH P30RY SC175111 H A 100 DYS
| |
| +ZRHSÃt IQVIGR RHR HEAD SFPAY ISLN VELAN P3GRR SC"89155 H A 100 DYS
| |
| +ZRHS<<t! QV112 RHR SHT Q."t CLG SUCT XSQL V LAN h~ CO P30RR PC2506ZR H A 100 DYS
| |
| +ZRHS<<tlQV113 RHR SHT DN CLG SUCT XSGL V KLAN P30RR SC2R01R2 H A 100 DYS ZRHSi<HQV115 RHR SFRVICE NATFR CROSS TIE VKLAN P3GRR ABS17510 H A 100 OYS ZRHS<<tfQVZI6 RHR SKRVXCE HTR CROSS TZE V"LLI P30RR ABS17510 H A 100 DYS "RhSx"QVI "A RHR H.E. A Stl'ELL-SIDE CUTLET CLOH CORP P30RY ABN17505 H A 100 DYS ZRHS~tfOVZZB RHR H.E. 3 SHELL-SIDE GUTLET CLCH CORP P3GRY ABS1751G H A 100 DYS RH~<<uQVIRZ RHR DXSCHARGE TO RAD!lASTK VKLAN P30RR ADS175C9 H A 6 HRS ZRHS<'HOV1R9 RHR DISCHARGE TO RADIIASTE VELAN P3CRR ABS17 509 H A 6 HRS
| |
| +ZRHSxtfQV15A RHR A RKAC CNTIGIT SPRAY VKLAN P3CRR SC289155 H A -100 DYS
| |
| +ZRHSwt!0<J153 PHR 3 REAC CNT<nli SPRAY VELAN P3CRR SC289155 H A 100 DYS ZRHS<HO<JZB RHR 3 SHT DN COOLING SUCT CLGH CGRP P30RY SC175111 H A 100 DYS ZRHSQ!GVZZA RHR A STM LINK ZSQL VELAN P30RR SC215125 H A 6 hRS ZRHSvitfQVZZB RHP. 3 STtf LXNE XSQL V LAN P30RR SC215129 H A 6 HRS ZRHS<<tfQV23A RKR A STH LINK XSO'. VELAN P30RR SC175103 H A 6 HRS ZRHSx!!OV233 RHR B STtl LINK ISQL VEL Ail P30RR SC175111 H A
| |
| +ZRHS>tfOVZRA LPCI Xh<.KT A VELAN PSGRR SC209155 H A '00 DYS
| |
| +ZRHS<'tfQVZRB LPCZ Zii" ET B VELA'N P3GRR SC269155 H A 100 DYS ZRHSwtDVZRC LPCX Xii" ET C VKLA<t P30RR SCc.89155 H A 100 0 S
| |
| +ZRHSvct fQV25A RHP. A REAC CtlTICIT SPRAY VELAN P30RR SCZ89155 H A 100 DYS
| |
| +ZRHSxt!QV253 RHR 3 REAC CHT!EIT SPRAY VELA!l P30RR SCZ69155 H A 100 DYS
| |
| +ZRHS< tlQV26A RHR H.E. A VENT TO SU?P POOL VELAN P30R'R ABN19615 H A 100 DYS
| |
| +ZRHSttfQV253 RHR H.E. B VENT TO SUPP POOL ViL"N . P30RR ADS196ZG H A 100 DYS
| |
| +ZRHS <<tfQV27A RHR H.E. A VEi!T TO SUPP PG L ViLAN P30RR ABiN19615 H A 100 DYS
| |
| +ZRHS<;t!QV27B RHR H E B V<:NT TO SUPP PCQ'HR VCLAN P30RR ABS19620 H A 100 DYS
| |
| +ZRHS<<tfQV30A A R<N TO SUPP POOL ZSGL CLCH CORP P30RY SC196113 H A 100 DYS
| |
| +ZRHSwtfOV303 RHR B RTN TC SL;P POOL ZSQL CLCH CORP P30RY SC195113 H A 100 DYS ZRHSwHCV32A RHR H E A FLOh TO RCIC VFLAN KHG P30RR ABN17505 H A 100 DYS ZRHSvtlQV323 RHR HE ED B FLGH TO RCIC VELAN P30RR ABS17510 H ZRHSPIQ<J33A RHR A SUPP POC'PRAY P30RR SC215122 H
| |
| * 100 DYS
| |
| +ZRHSwHQV33B RHR B SUPP POOL SPRAY Vil.AiN P30RR SC215122 H A 100 DYS ZRIIS)<HQV37A RHR H.E. A FLCH TO SL'?P POCL VELAtl P30RR ABN17505 H A ZRHSntfQV373 RHR H.E. 3 FLCH TO,SUPP PCCL ViLAN P3GRR ABS17510 H A ZRHS<<KOVRA RHR A HIN FLQH BYPASS ViLAN ENG. CO. P30RR SC19611R H A
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGe 33 EQUIPtlENT XD DiSCRIPTXON VENDOR N"!!E SPiC ZCNE ZZ TREF OPCQO OPT ZRHSxHOVRC RHR C tlIN FLOH BYPASS VcLAN P30QR ABS17508 H A 100 OYS
| |
| + ZRHS>PQVQCA RHR A SHT Dh CLG RETURN VELAN PBONR SCZtt0140 H A 100 DYS
| |
| + ZRHSt!!OVACB RHR 8 SHT ON CLG RETURN VELAN P30~R SC200103 H A 100 DYS
| |
| + ZRHSicHOV57A RHR A SHT ONCLG CV BYPASS VELAN P30iR PC250620 H A 100 DYS
| |
| + ZRHSiittQY678 RhR 8 SHT Dil CLG CV BYPASS VcLAtt P30%R PCZ305ZO H A 100 OYS ZRHSicHQVSA RHR H.E. ElA BYPASS CLOil CORP P3CQY AEN17505 H A 100 DYS ZRHSciPQYBB RHR H.E. E18 BYPASS CLOH CCRP P30QY ABS17509 H A 100 DYS ZRHSxttOVBOA Gi OBE VALVE VcLAN PIC~Q SC213125 H A 6 HRS ZRHSxHOV808 GLOBE VAI.VE P30tlo SC215129 H A 6 HRS ZRHS>HOV9A RHR H.E. A SHELL SICc, Xt!LET CLOH CORP P3CQY ABi!19615 H A 100 DYS ZRHS~!!QV93 RHR H E 8 SHcLL SIDE ZtO cT CLOH CORP P304Y ABS19520 H A 100 DYS ZRHSxPT99A RHS A STEAH SUPPLY RQQtt XCS RQSEHCUiiT C071! l SC175105 H ZRHS'PT998 RHS 8 STEA!ii SUPPLY ROON ICS ROSEI!CUiiT C071H SC215122 H ZR tSqcQV126 ZR!tS<Ec'8 S!!P CROSS-TIE DRiN TARGET RCCH CORP P3CQX ABS17510 H A 100 OYS ZRHSiSQV35A RHR A REAC SA!!PLZhS SYS XSOL V TARGET RQCil CORP P30%V ABN17505 H A 100 DYS ZR'tS~SOV358 RHR 8 REAC SA!lPLIhS SYS XSOL V TARGET RQC'cl CORP P30tlX ABS17510 H A 100 DYS ZRHS>SQV35A RHR A REAC SAPLING SYS ISQL V TARGET RO il CORP P3CQX ABill7303 H A 100 OYS ZRHSccSQV358 RHR 8 R AC SAHPLZNS SYS ISO' TARGET ROCH CORP P3OQX ABS17510 H A 100 DYS ZRHSc'SOV70A STEAtl LXhE CRAIii TARGET PQCH CCRP o30"V SC175103 H A 6 HRS ZRHSccSQV708 STEA!l LZiVE DRAIN TARGET RQCH CCRP P30QX SC1.75111 H A 6 HRS ZRHS+SOV71A STEAN LIhi ORAIil TARGET RQ"H CCRP P30QX SC175103 H A ZRHS-SQV718 STEA!l LihE DRAIN TARGET RCCH CQR? P3CQX S"175111 H A
| |
| +2RHSA'MOVlA RHS DMP PlA SUCTION GLOW CORP P304Y
| |
| +2RHS*MOV1B RHS DMP PlB.SUCTION GLOW CORP P304Y.
| |
| +2RHS*FT63A RHS A CONTAINMENT C071M
| |
| +2RHS*FT64A RHS A SUPP POOL C071M
| |
| +2RHS*FT63B RHS B CONTAINMENT C071M
| |
| +2RHS*FT64B RHS B SUPP, POOL C071M
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 34 EQUIPHENT IO DESCRIPTION VEiNDDR NAHE SPEC ZONE ZI TREF CPCDD OPT
| |
| + 2RHS>RE1A REAC BLDG OH HATCH RADN HAltAN INSTH P281F PC2616W H
| |
| + 2RHSiiRE13 RFAC BLDG DH HATCH RADN HAHAN INSTH P281F PC261699 H
| |
| +2RMS+RElC REAC BLDG IN H RADN KAMAN INSTM P281F
| |
| +2RMS*RE1D REAC BLDG IN H RADN KAMAN INSTM P281F
| |
| + = Reguiato~ Guide.'l.'97.
| |
| | |
| PAGE 35 EQUXPttENT ZD DESCRZPTXOH VEtiDOR hAatE SPEC ZOhE ZZ QREF OPCOD OPT 2RSSaFT106 RCZC PttP DZSCH FLOH ROSEl tOUHT C071H SC175105 H 2RSS-PT10S ADS ACCUttULATOR TAh7( PRESS ROSEtlOU:tT C071H SC289155 H 2RSS-PT109 ADS ACCLHL" ATORTAhN PRESS ROSEtiOUHT C071t t SC289155 H 2RSS-PT110 ADS ACCUttULATORTAHN PRESS ROSEt!OUitT C071H SC306175 H ERSS-PTlll ADS ACCmtULATORTAHN PRESS ROSEHOUi'tT C071H SC306175 H
| |
| | |
| PAGE 36 EOOIP}l=NT ID DESCRIPTION VENDOR NAHE SPEC ZONE ZX TREF OPCOD OPT
| |
| + eS S~HCVX60 SERVICE AIR CNTHT XSOL V VELAN P304H SCZ40135 H
| |
| + esAs>Hcv161 SERVICE AIR CNTHT ISOL V VELAN P304H SCZ69155 H ZSAS~HCV162 ScRV~CE AIR CNTHT ISOL V VELAN P304H PC240503 H
| |
| + esAs<Hcv163 SERVICE AIR CNTHT XSOL V VELAN P304H PC289601 H
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAGE 37 EQUIPHENT ID DESCRIPTIOil VENDOR NAVE SPEC ZONE ZI QREF OPCOD OPT ZSCV+Fi<< 101A GTS t!ISC 120/240V PhL BRO)LN BOVERI E014T ABNZ4033 H ZSCV~Ph" 3018 GTS HISC 120/240 Pht. BROhN BOVERI E014T ABSZ4036 H ZSCV>XO101A DIST XFt!R 600V-120/240V SQUARE D E011T ABN24033 H ZSCV+%<)301B DIST XFHR 600V-120/240V SQUARE <<0 EOllT ABS24036 H
| |
| | |
| PAGE 38 EIIUIFHENT ZD DESCRXPTIOil VEhTiGR NAKE SPEC ZCNE ZI QREF OFCOD GPT ZSFC<<AOV153 FILTER HDR ZhL ISOL VCH POSX-SEAL INTERN P304D SCZS9162 H 100 DYS ZSFC<<AOV154 FILTER HQR ItiL ISOL VCH PGSX-ScAL INTERN P304D Scc.89162 H 2SFC<<AGV19A 2SFC-FLTlA OUTLET PCS I-SFAL INTER. P304D SC326193 H 100 DYS ZSFC<<AOVI9B ZSFC-FLTlB OUTLET POSE-SEAL INTcR. P304D SC3061.76 H 100 DYS c.SFC<<AOV33A SKIN!IER SURGE TAhK LEVEL POSI-SEAL iNTER. P304D SC32S199 H 100 OYS 2SFC: AQV33B SK>t!!IcR SU4GE TAh".< LEVcL POSI-SEAL INTER. P304D SC326199 H 100 DYS 2SFC<<FT36A SF PQQ!. CLG SYS FLGH L ROSKHGUNT C071H SC215122 H ZSFC<<FT36B SF PGQL CLG SYS FLCH L ROSEVQ'Ji!T C071! I SC2151c.Z H 2SFC<<FT5SA SFC Ft!P DXSCH FLCH ROSE!!CUNT C021tt SC269162 H c,SFC<<FT585 SFC P!!P DISCH FLOH C071H SCZ89161 H 2SFC<<HV114 FUFL XFR CHAN GATE A DR V XQ!!QX P304K SC306182 H A 100 DYS 2SFC<<HV116 CASK HQLG XFR PU!!P SUCT POSE-SEAL ZiNTER. P304D SC328199 H A 100 DYS ZSFCciHV121 CASK HDLG XFR PL>P DISCH V POSE-SEAL INTER. P304D SC328199 H A 100 DYS ZSFC<<HV148 CASK GATK DRAIN VALVE XC!!QX P304K SC306182 H A 100 DYS ZSFC<<HV149 GATE DRAIhS KGR ISOL VLV XG!ICX P304K SC30618Z H A 100 DYS ZSFC<<HV17A ZSFC-F1A BYPASS FGSI-ScAL XNTER. P304D SC26916Z H A 100 0YS 2SFC<<KV17B ZSFC-FlB BYPASS PQSI-ScAL INTER. P304D SC289161 H A 100 DYS ZSF C<<HVISA 2SFC-FlA XNLET POSE-SEAc ZIITE. P304D SC269162 H A 100 DYS ZSFC<<HVISB 2SFC-FlB XNLET POSE-SEAL INTER. P304D SC2S9162 H A 100 DYS ZSFC<<HV35A 2SFC-TKlA INLET V PCSI-SEAL ZNTcR P304D SC328192 H A 100 DYS c.SFC<<HV37A 2SFC-HT EXChGR DISCH V I QSI-SEAL INTER ~ F3040 SC215122 H A 100 DYS 2SFC<<HV37B ZSFC-HT EXCKGR DISCH V PCSZ-SEAL INTER. P304D SC215122 H A 100 DYS ZSFC<<HV54A SKIVJ!ER SURGE TAhK CUTLET POSX-SEAL INTER. P304D SC328193 H A 100 DYS ZSFC<<HV6A SF PCQL CLG HTR XCOtlN PQSI-SEAL INTER. P3045 SC269162 H A 100 DYS ZSFC<HV6B SF FOO'LG HTR XCC'NN POSZ-ScA ZNTER. P304D SC289161 H A 100 DYS 2SFC<<LS33A SKItD!EP. SURGE TAhK LEVEL HAGKKTRCL CC21L SC328193 H ZSFC<<LS33B SKIt!it!ER SURGE TAihK LEVEL t!AGNETROL C021L SC328187 H ZSFC<<LS33C SKIIOIER SURGK TA!FK LEVEL ttAGNKTROL C021L SC328193 H 2SFC<<LS33D SKZID!ER SURGE TANK LEVEL t!AGt!KTROL COZlL SC3c.8167 H 2SFC<<LS34A SFC SKII!!IER SURGE TK HZ LVL tlAGNKTRQL COZXL SC328193 H c.SFC<<LS34B VASNETROL COZlL SC3281S7 H 2SFC<<LS55A SF POOL HTR LVL LOH HAGNcTROL COZIL SC353202 H ZSFC<<LS55B SF POOL HTR LVL LCN t!AGNETROL C021L SC353202 H 2SFC<<LT32A SF PCQL SURGK TANK HATER LVL RGSEt!CUNT C071! I SC326197 H ZSFC<<LT32B SF POOL SURGE TANK HATER LVL RQS=! !CUNT C071tl SC328187 H ZSFCccHIA FUKL POOL CHC t!QTOR GOULD PIPiP S INC. P222X SC289162 H ZSFC<<tllB FUcL POOL CHC l!GTCR GOULD PU!!P S INC. IZAAK SCZ69161 H 2SFC<<PT3A SF PGQL CIRC PP A SUCT PRESS RQS El !CUNT C071H SCZ61145 H ZSFC<<PT3B SF PCOL CIRC PP B SUCT PRESS RGSKI!OWT C071II SC261145 H 2SFC<<PT30A SF PQGL CIRC PNP DISCH PRESS RGSEi!O'-'NT C07ltl SC?61145 H FSFC<<PT30B SF POOL CXRC Pl!P DISCH PRKSS RQScl!CUNT C021H SCZ61145 H ZSFC<<TF31A SF POOL SURGE TANK TEHP OUTL PYCO C041D SC3c.8193 H c.SFC<<TESA SF PGQL HT EXCH CUT TE!!P PYCO CC41D SC21512Z H ZSFC<<TESB SF POOL HT EXCH OUT TEtIP PYCO C041D SC215122 H
| |
| | |
| PAGE 39 EQUIPHENT ID DESCRIPTION VENDOR NAttE SPEC ZONE ZI QREF OPCOD OPT 2SLS>HCV)11 STBY LIQ TEST TK VALVE VELAN P30QL SC289155 H A 7 DYS 2SLSxt!OVIA SEALEO GLOBE VALVE VELAN P30QS SCc.89155 H A 7 DYS 2SLS~!.OVID SEALED GLCSE VAL'VE VELAN P30RS SCc,89155 H A 7 DYS
| |
| + ESLS+ fOV5A STOP CHECK VELAN P300S SC289155 H A. 7 . OYS
| |
| + eS S~t.OV55 STOP CHECK VELAN P30RS SC289155 H A 7 DYS
| |
| + = Regulatory Guide 1.97.
| |
| | |
| PAG 40 EQUXP¹NT XD VENDOR NAt!E SPEC ZO'l" ZX TREF OPCOD OPT ZSHP+AQVZOA SHP TO RHSwPIA SL CLR XO!!QX P304H ABN17504 H A 100 DYS ZShVwAOVZOB SH? TO RHS<PIA SL CLR XQt!OX P30QH ABS17509 H A 100 DYS ZShPWAOVZZA SHP FRO!l RHSKPIA SL CLR XO!!QX P30QH ABN17504 H A 100 DYS ZShPNAOVZZB SHP FROH RHS>PXB SL CLR XOt!OX P304H ASS 17509 H A 100 DYS ZSiiPMAOV97A SHP FR CLG COIL ZHVRaUC413A P304H SC289155 H CON ZSHP+AOV97B SHP FR CLG COIL ZHVRIUCQ13B XOHQX P30QH SC289155 H A CON ZS!VwttOV)5A SVCE HTR TO ZHVRQUC403A VELAN P30QR SC175105 H A 100 DYS ZSHP+t!QV15B SVCE HTR TO ZHVR<UCQ03B VELAN P304R SC195116 H A 100 DYS 2Sl!Put!QV17A GATE VALVE VELAN ENG P304R SC196113 H A 100 DYS ZShPet! QV17B GATE VALVE VFLAH P30QR SC175105 H A 100 DYS ZShPxt!OV18A GATE VAI.VE VELAN P30QR SC196113 H A 100 DYS ZSHo~t ~OVIOB GATE VALVE V LAil P30QR SC196116 H A 100 DYS ZSHP>PTXQOB'ESCRXPTXQil ZShV<!!OV19A ShP TO CCP HT EXCH ISOL V CLQH CORP P304Y ABN21523 H A 100 DYS ZShP+t !QV19B SnP TO CCP HT EXCH XSCL V CLC!l CORP P30QY ABh21523 H A 100 DYS ZSHPat!OVZIB GATE VALVE VELAN P30QR SC328197 H A 100 DYS ZSHP+t!QV33A BUTTERFLY OR TRICENTRIC VALVE Ct.Oil CORP P304Y ABti17505 H A 100 DYS ZSHPiit!QV33B BUTTERFLY QR TRXCENTRIC VA'LVE CLPH CQRP P304Y ABS17510 H A 100 DYS ZSHP+t!OV38A SHP TO RBCLCH SYS VELAN P30QR SCc51145 H A 100 DYS ZSl!PxttQV38B SHP TO RBCLCH SYS VELAiN P30QR SC261145 H A 100 DYS
| |
| : c. SHPat-!QV39A SHP TO RBCLCH SYS VELAit P30QR SC261145 H A 100 DYS ZShP+ttOV39B SHP TO RBCLCil SYS VELAN P30QR SCc.61145 H A 100 DYS ZSHP+HOV90A BUTTERFLY CR TRICENTRIC VALVE CLOH CORP P304Y ABN17505 H A 100 DYS ZShPvt!QV90B BUTTERFLY OR TRXCENTRIC VALVE CLOH CORP P304Y ABS17510 K A 100 DYS ZSt&>PTXQOA SHP TO CCP HT EXCHS PRESS ROSE!!QU.'tT C071tl ABN17503 H SnP TO CCP HT EXCHS PRESS ROSEHQUNT C071H ABN17503 H
| |
| | |
| PAGE 41 EQUXPHEt(T XD DESCRIPTXON VEhDOR NAt(E SPEC ZONE ZX QREF OPCOD 0?T 2VBS) Pt(LA105 ttSLIV DIST PtiL(G/H) BROhN BOVERI - E014T - ABN24033 2VBSNPHLA106 HSLIV DIST PNL BRONN BOVERI E014T ABS24036 H 2VBS>FN'105 MSLXV DIST FNL BROHH BOV RX E014T ABN24033 H 2VBSxPNLB106 ttSLIV DIST PtiL(Y/H) BROhN BOVERX E014T ABSZ4036 H
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| | |
| PAGE 42 Et!UXPHENT ID DESCRIPTION VENDOR hAHE SPEC ZOi!E ZI t!REF OPCOD OPT ZHCSW!!OV101 QhCU REAC VESSEL DRN VELAN P304R PCZ61648 H C
| |
| + 'ZhCSM!!OV102 PHCU P1A t'. P18 SUCT XSOLV VELAN P304R PCZ40606 H A 6 HRS 2¹SQtOVX03 RHCU XtiL ISOL V VELAN P304Q PCZ40606 H C ZhCSx! lOV104 RHCU It!L FRO!l RECIRC 8 VELAN P304R PC240508 H ,C ZnCSst!OV105 RnCU It!L FRO!! RECIRC A 'VELAN P304R PCc.40505 H C
| |
| + EhCS>HOV112 RnCU PXA ~ PXB SUCT ISOL V VELAN P304R SCZ40142 H A 6 HRS
| |
| + EhCS<t!OV200 RhCU RETUPN ISOL VELAN P304P. HST26'46 H ZHCS-tlCV106 R!i U DRn TO hASTE COLL TH V VELAN P304R SC305176 H C ZhCS-HCV107 RhCU DXSCH TO NU CO!!D V VELA!t P304R SC305176 H C 2hCS-HOV108 DRN RESTRXCTIt!8 ORF BYP V VELAN P304R SC306176 H C ZHCS-t !OV109 RhCU REGEit HX DISCH V 'VELAN P304R SC306176 H C Zt!CS-tlOVX10 FLTR D!!!!LZR BYP V VELAN P304R SC306176 H C ZHCS t OV111 RliCU HX BYP V VELAN P304R SC305176 H C
| |
| + = Regulatory Guide 1.97.
| |
| | |
| ~l
| |
| :
| |
| ~
| |
| | |
| 12/Zic'84 PAGE 9 REVZSZCN: 6<t h~?PZ-ENVZRG'N!EHTAL QUALIF CATION DATA MASTER LIST !NSSS)
| |
| ISS<JE DATE: l2 (2,[/$
| |
| g ff<<% if% <<<< <<ff <f<fifffff<< << << <f<f<f <<<f << <f <f <f <f << ifff<f << << << << << if< <f<f << ff<f ffif<< << << << <<<f << << <i <f << <f ffffV << << 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 ffff)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
| |
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| 12/Zlr 8% PAGE 12 RFVXSXON: Oj lo!PZ-ENVIRONHENTAL QJALIFICATXON DATA HASTKR l.IST l NSSS)
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| ISSUE DATE- !2,/g(te,jt r r j%%jj Cvrjjhjjj+jjjjjrjjjj.jjcjjjjjrcfjjjjjjjjNfif jjjfjrjr4fjjrjjjjjfjjjjjj rjjjfjrjr'rjjjf)jrjrjjjjjr jfjr jj jr jj jr jr'jrjgcrjjjrjj jCcfgjjjjjfjrjrjrjr (jjjjjrjjjrjj+jfjjhfjjjrrj jrcjgjrjfjjjjjjjjjjjjjjgjrgjjjjjrj.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 jjcr'j cj jrrjjrcj jr jjjjjr'jjjjjjjjjjjjc jt jjjf jjjjjjjjcj cr'j jfjr jjjr W cjrr'jjrjr'fcj jjjr jjjfjjjr'jjjjj jr jjjjcj jjr! jj Cj jjjjjjjr'jjjjjjjjjjr'jjr'r'jcr'j cj jfjjjrjjjfjjjc jfjc jjjjrr'j jjjrcj jr'c jr'r jr jjjr'r'i'jjjrr'j jrcc% jj~~ jjjjjjjjjjjjrc rr jj jjjr'r jj jjjjjc jj jjjjjjjj 82Z-F013H SAFETY RELXEF VALVE PCZ89660 C 100D PBOOAAZ 2!!SS<PSV121 HARSH A B22-FD13F SAFETY RELZEF VAL'VE PC289680 C 1000 PSOOr"AT ZHSS jiPSVI 22 HARS'H 0" Z-F0130 SAFETY RELXEF VALVE PC269560 C 1000 PSOOAAR ZHSSNPSV)23 HARSH A BZc.-F013V SAFETY RELIEF VALVE PCZ69560 C 10CD PBCOABF 2l!SS jrPSV12% HARSH BZZ-F013S SAFETY RELXEF VALVE PC289660 1DGD PSOOABD ZHSSccPSi j j 25 B22-F013H SAFETY RELIEF VAVLE PCc.S9680" 10GD PSOOAAX ZllSS~PSV126 HARSH BZZ-F013H SAFETY RELIEF VALVE PC289580 1000 PGCOAAV ZHSSjcPSV127 HARSH BZZ-F013B SAFETY RELXEF VALVE PCZ896SO 100D PSOOAAP c.HSSj'PSV128 HAR 'l BZZ-F013U SAFETY RELIEF VALVE PCc.89560 1000 PSOOABE c.HSSc PSV129 HARSH BZZ-F 013R SAFETY RELIEF VALVE PC289660 loCD PBOCABC 2! !SS<PSV~ 30 HARSH B22-FD13J SAFFTY RELXEF VALVE PCZ69680 10OD PSCO""H ZHSScrPSV131 HARSH BZZ-F013G SAFETY R LIEF VALVE pc2695eo 1OOD PGOOAAU ZHSSc'PSV132 BZZ-~013A SAFETY RELIEF VALVE PC209580 1000 PBOOAAO Zl!SScPSV133 HARSH A 8" 2-F013N SAFETY RELIEF VALVE PC269666 10CD PSOOABA c.HSSrrPSV13% HARSH
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| 0 NINE MILE POINT - UHIT 2 DOCKET NUMBER 50-410 SYSTEM COMPONENT EVALUATION NORK SHEET . PASE 1 OF 1 QUAL REF I C071MBF REV 0 13-Dec-84
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| ~ ~
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| ~ ~
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| )ABOVE FLOOD ll CRITERIA, EQEDC-I, REV 1, MAY 2, 1984 '.HORNL SEE THE DOCUMENT REFERENCED.
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| NX TEMPERATURES ARE SHONH AS l LEVEL? NA 2. VENDOR ENVIRONMENTAL QUALIFICATIOH REPORT, DESIGN/AVERASE.
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| eABOVE SPRAY/ SDDF 0 IEEE 07. 131-5000A 3.UHI7 IS COMPLETELY SEALED. THERE IS ilFRO'IH LEVEL?
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| a DOCUMENTATION NA ACCEPTABILITY:
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| QUAL REF 8 C071t(BG UNIT 2 50-410 EQUIPMENT DESCRIPT ION REV 0
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| I ta ACC GAMMA I 2.6E6 I I I I 2 ITEST-IDENT I YES I NOTE 4 (OP. CODEl A la HORN BETA I NA I I 1 I 2 ITEST IDEHT I HA NOTE I
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| I el NEUTRON I HA I I 1 I 2 ITEST IDENT e HA I I I I IISPRAY I HA I YES I 2 I HA I IACCURACY - -
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| IABOVE FLOOD se CRITERIA, EQEDC-l, REV 1, MAY 2, 1984. 2 TEMPERATURES ARE SHO)(H AS I LEVEL? HA I I 21 VEHDOR ENVIRONMENTAL QUALIFICATIOH REPORT) MAX DESIGN/AVERAGE.
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| IABOVE SPRAY/ SDDF 0 IEEE 07. 131-5000A 3.UHIT IS COMPLETELY SEALED. THERE IS iFROTH LEVEL?
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| s HA el 3. EQUIPMEHT OPERABILITY TIME DATA SHEET) HO EFFECT OF BETA RADIATION ON THE I
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| I DOCUMENTATION ACCEPTABILITY) 4 ~ VENDOR IRRADIATED THE TRANSHITIERS IACCEPTABLE TO NUREG 0588,CATI FOR COMBINED VALUE OF ACCIDENT AND I NORMAL RADIATIOH LEVELS.
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| I I 5.SPEC ACCURACY INCLUDES ONLY THE I
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| I EFFECTS OF LINEARITY) HYSTERESIS AND I
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| I REPEATABILITY~
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| I IQUALIFIED LIFE (YEARS)l 10 iREFEREHCEl 2 e
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| NINE NILE POINT - UNIT 2 DOCKET NUNBER 50-410 SYSTEN CONPONENT EVALUATION MORK SHEET PAGE 1 OF 1 QUAL REF 4 E015HAA REV 0 10-Dec-84 ENVIRONMENTAL COHDITIONS AND QUALIFICATION EQUIPNENT DESCRIPT IOH I II I I I DOCUNEHT REFERENCE I =-"==""="=""""=======""""===-"""=" I 'ARANETER i SPECIFIED a QUALIFIED I QUAL NARGIH a RENARKS I VALUE I VALUE a SPECIFIED I QUALIFIED I NETHOD I DENO I I ~ I ~ I I I IEQUIP HO N1O I ~ 2EPS4SMGOOI 11 I I I I
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| I II ABNORNALI NA l48 HRS Q(26( 1 I 2 I TEST-SIN I NA I ITYPE) (DESCRIPTION) 11 ACCIDEHTi NA I I I I 2 I HA I NA I l15 KV) 1000 NVA NETAL CLAD I'PRESS(PSIG)' -""- ' ---- ' ---- ' "- - - ' ---- ' - -' NOTE 1 ISMITCHGEAR 11 NORNAL I "0 '5 MG I ATNOS I 1 I 2
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| I sl ABHORNALI HA I HA I I I 2 HA I HA I INANUFACTURERl BROMN-BOVERI a I RCCIDEHTI NA I NA I I I 2 I HA I NA I I
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| I lt NEUTRON I HA I t 2 I NR I NA 1(SPRAY I NA I I I I Hh I Hh IACCURACY -- saSUBNERGENCEt HA I I s NA I HA I
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| I I I ii SPEC: NA II II I DENO: HA II I II II I I I IZONE NO.: ABH24033 II I IFLOOD LEVEL ll DOCUMENT REFERENCEl NOTES: 1.FOR CONPLETE ENVIRONNEHTAL CONDITIONS,a I ELEVATION: HA II 1. EQUIPNENT QUALIFICRTION EHVIROHNENTAL DESIGH SEE THE DOCUNENT REFERENCED a IRBOVE FLOOD CRITERIA) EQEDC"I, REV 1) NAY 2) 1984 ' ~ NORNAL TEMPERATURES ARE SHOMN AS LEVEL? NA 2a VENDOR ENVIROHNEHTAL QUALIFICATION REPORT) NAX DESIGN/AVERAGE.
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| IABOVE SPRAY/ 11 SDDF N IEEE (.330-50003C 3.BASED OH THE ARRHEHIUS CURVES IH REF I FROTH LEVEL? HA ss 3. EQUIPNENT OPERABILITY TINE DATA SHEET: 2 A(.L MATERIALS IH THE SMITCHGEAR SHOMa I QUALIFIED LIFE SUBSTANTIALLY LONGER I I LTR I DOCUNENTATIOH ACCEPTABILITY: THAN 40 YEARS t 100 DAYS AT AVERAGE I 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.
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| REFERENCEl 2 4,VENDOR TESTED VAI.UE INCLUDES CONBIHED I I VALUE OF BOTH ACCIDENT AND HORNAL I
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| IQUALIFIED LIFE " -- RADIATION VALUES~
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| I (YEARS) l 40 REFERENCEl 2 11 I I I I II lsI I
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| NIHE NILE POINT - UNIT 2 DOCKET HUNGER 50-410 SYSTEN CONPOHENT EVALUATION WORK SHEET PAGE OF QUAL REF 4 E015HAB REV 0 10-Dec-84
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| ~ >> ~
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| 'URL ENVIROHNENTAL CONDITIONS AND QUALIFICATION EQUIPNEHT DESCRIPT ION I II I I I DOCUNENT REFERENCE
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| '===== ========================'' PARANETER 'PECIFIED 'UALIFIED 'HARBIN'EHARKS I
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| I HA HA I I I I SPEC: NA I I I I I I DENO: HA I I I I I I I I 11 I I I I aZOHE HO.: ABH24033 I I I IFLOOD LEVEL ta OOCUNEHT
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| ==REFERENCE:==
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| NOTES: 1.FOR CONPLETE ENVIRONNENTAL CONDITIONS,I I ELEVATIOHl HA II 1. EQUIPNENT QUALIFICATIOH ENVIRONNENTAL DESIGN SEE THE DOCUNENT REFERENCED, (ABOVE FLOOD CRITERIA) EQEDC 1) REV I) NAY 2) 1984 ~ 2.NORNAL TENPERATURES ARE SHOWN AS I LEVEL? NA sl 2. VENDOR ENVIRONNEHTAL QUALIFICATIOH REPORT) NAX DESIGN/AVERAGE.
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| (ABOVE SPRAY/ SDDF I IEEE (.330-50003C ABASED OH THE RRRHEHIUS CURVES IN REF I FROTH LEVEL? HA ACCEPTABILITY'1 la 3 ~ EQUIPNENT OPERABILITY TINE DATA SHEETS 2 ALL MATERIALS IH THE SWITCHGEAR SHOWI I
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| I II LTR QUALIFIED LIFE SUBSTRHTIRLLY ).O(IGER I I DOCUNEHTAT ION la THAH 40 YEARS t 100 DAYS AT AVERAGE t IACCEPTABLE TO HUREG 0588)CATIlea TENPERATURE OF 95F TO WHICH THE SMGR I
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| I IS QUALIFIED BY VENDOR. SINCE NNP2 I
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| I OPERATION TINE BEYOND 100 DAYS POST- I (HA IHT/SURVE ILL 11 ACCIDENT IS AVAILABLE REFEREHCE: 2 tl 4 ~ VENDOR TESTED VALUE INCLUDES CONBIHED I I
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| I IQUALIFIED LIFE - -- I I I I VALUE OF BOTH ACCIDENT AND HORNAL RADIATIOH VALUES. I I I I (YERRSI: 40 11 I I I I I
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| ==REFERENCE:==
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| 2 I I I I
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| ) II I I I I I II II I I I I
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| NINE NILE POINT - UNIT 2 DOCKET HU)tBER 50-410 SYSTEM CO)tPONENT EVALUATION MORK SHEET PAGE 1 OF 1 QUAL REF 4 E015NAC REV 0 10-Dec-84
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| ~ ~
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| ENVIRONMENTAL COHDITIONS AHD QUALIFICATION EQUIPNENT DESCRIPTION I II I I I DOCUMENT REFERENCE a I 1 t==============================) ) PARA)tETER I SPECIFIED l QUALIFIED s QUAL atthRGIHI REMARKS I
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| I VALUE l VALUE I SPECIFIED l QUALIFIED l METHOD l DEMO l I 11 I I I I I I I I IEQUIP NO.: 2EPS<SM6003 I I I I I I I I I I eSPEC NO.l E015H IlOP,TINE: I 100 DAYS I 100 DAYS I 5 I 2 I AN>DATA I YES 1 NOTE 3 lSYSTEN: IITEHP (F)' I I I I
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| " 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
| |
| I l ABNORMAL) NA l46 HRS 81261 I I 2 1 TEST-SI)t I NA I ITYPEt (DESCRIPTION) ll ACCIDENTI NA a
| |
| - I 1 I 2 a HA I HA 115 KV, 1000 llVA ttETAL CLAD ''PRESS(PS16)' ---- ' ---- ' ---- ' ---- ' ---- ' - -' NOTE 1 lSMITCHGEAR I
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| al NORMAL I -0 '5'6 I ATMOS l 1 I 2
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| '
| |
| I TEST-SIN l NA 1 I as ABHORHAL) HA I NA I 1 I 2 HA I NA I IHANUFACTURERl BROMH-BOVERI sl ACCIDEHTI NA I NA a I l 2 I HA I Nh I I
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| I I NOTE tttODEL HO.: HK-1000 II NORMAL I 50 s 90 1 1 I 2 I TEST-Sill I Nh s I
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| I 11 ABNORHALI NA I HA l 1 s 2 I HA s Hh I ISAFETY FUHCTIONl a I ACCIDENT) HA I HA I 1 I 2 I NA I Hh I aTRIPPING OF RCS PU))PS AND NVP I IRADIATIOH' --"- - t
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| |
| I ss ACC 6AKHA a s 1 OE5 I 1 s 2 I TEST Silt I YES a NOTE 4 lOP. CODEt A aa NOR)l BETA I HA I 1 l 2 l Hh l Nh I
| |
| I 11 ACC BETA a NA l I 2 I HA I NA I
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| I 11 NEUTRON a HA I I 1 I 2 I Hh I HA I I
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| I IISPRAY I Nh I I l Hh Hh IACCURACY -- saSUBHER6ENCEs Hh I
| |
| I I Nh I
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| s NA s I II << I 1 SPEC: HA 11 I I I I DEMO: Hh I I I I I I I I II I I I I
| |
| )ZONE HO.l ABN24036 I I I aFLOOD LEVEL ll DOCUMENT REFEREHCE: NOTES: 1.FOR COMPLETE ENVIRON)tENTAL CONDITIONS,I I ELEVATION: tlA ll 1. EQUIPNEHT QUALIFICATION ENVIRON))ENTAL DESIGH SEE THE DOCUMENT REFERENCED IABOVE FLOOD CRITERIA) EQEDC-1) REV 1) HAY 2) 1984 ~ 2.NORMAL TEMPERATURES ARE SHOMN AS LEVEL? Nh lt 2. VENDOR ENVIRON)tENTAL QUALIFICATION REPORT, MAX DESIGN/AVERAGE.
| |
| )ABOVE SPRAY/ SDDF 0 IEEE 1.550-50003C 5.BASED OH THE ARRHENIUS CURVES IN REF I FROTH LEVEL? HA sl 3. EQUIP)IENT OPERABILITY TINE DATA SHEET! 2 ALL MATERIALS IN THE SMITCH6EAR SHOMl I
| |
| I LTR QUALIFIED LIFE SUBSTANTIALLY LONGER l I I IDOCUNENTATION ACCEPTABILITY: THAN 40 YEARS + 100 DAYS AT AVERAGE
| |
| )ACCEPTABLE TO HUREG 0588)CATIlls TEMPERATURE OF 95F TO MHICH THE SMGR I la IS QUALIFIED BY VENDDR, SINCE NHP2 I SMGR IS OPERATED AT 89F) RATHER THAM I Il 95F, AS QUALIFIED, ADDITIONAL ll OPERATION TINE BEYOND 100 DAYS POST-
| |
| )HAINT/SURVEILL - -- I I ACCIDEHT IS AVAILABLE.
| |
| I I REFEREHCE: 2 4.VENDOR TESTED VALUE INCLUDES COMBINED I II VALUE OF BOTH ACCIDENT AND NORMAL lQUALIFIEO LIFE - -- la RADIATIOH VALUES' II I I IYEARS)l 40
| |
| | |
| ==REFERENCE:==
| |
| 2 II I I II l
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| I II I I II I lt I I I II
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| I
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| 'l
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| NINE NILE POINT " UNIT 2 DDCKET NUMBER 50-410 SYSTEN COMPONENT EVALUATION MDRK SHEET PAGE 1 OF 1 QUAL REF I E015HAD REV 0 (0-Dec-84
| |
| ~ I ~
| |
| ENVIRONMENTAL CONDITIOHS AND QUALIF ICAT IOH EQUIP)(ENT DESCRIPT IOH I II I I DOCUMENT REFERENCE a l==============================a a PARAMETER I SPECIFIED l QUALIFIED I I QUAL (NARGIH( REMARKS l VALUE l VALUE l SPECIFIED QUALIFIED llETHOD l DEMO I I--------
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| a a I Call Isis iEQUIP raeuar sail 1 Saue I HO ssnr iiui hiss Cafu>u)IQVV'I 11 ss i
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| I 11 ABNORl(ALI HA I NA I I l 2 HA I HA I lNANUFACTURER) BROMN-BOVERI 11 ACCIDENT( HA l KA I 1 I 2 a HA I NA I I
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| I al ABNORNALI NA I HA . I 1 I 2 i KA I NA I ISAFETY FUNCTION: tl ACCIDENT( HA I KA I 1 l 2 I HA I NA l ITRIPPIH6 OF RCS PUNPS AND NVP t (RADIATIONS a
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| "- "- - I - -- -- I ----- I
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| - - - -- a
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| --- -- I - - -I - NOTE I lPENETRATION PROTECTION as HORN GANNAa 1.863 I I 1 l 2 I HA l HA I 11 ACC 6ANNA l 2 2E4 I 1.0E5 I 1 e 2 I TEST-SI)( l YES I NOTE 4 lOP, CODEl A aa NORN BETA I HA I I 1 I 2 a HA l HA I I
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| I 11 ACC BETA t NA l I I l 2 t NA I NA I
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| I 11 NEUTRON l HA I a 1 I 2 a HA l HA I HA I atSPRAY s NA I I I I NA a I lACCURACY -" t(SUB)(ERGENCE( HA I I l NA a NA I II I l SPEC: NA 11 I I I I I DEl(0: HA I I I I I I I I I I I I I I (LONE HO.l ABN24036 I I I (FLOOD LEVEL ls DOCU)(ENT
| |
| | |
| ==REFERENCE:==
| |
| NOTES! 1.FOR CONPLETE ENVIRONNENTAL COHDITIOKS,I I ELEVATION: NA ll 1. EQUIPNENT QUALIFICATIOH ENVIRONNEHTAL DES16N , SEE THE DOCUMENT REFERENCED.
| |
| (ABOVE FLOOD CRITERIA) EQEDC 1) REV 1 ) NAY 2) 1984 ~ 2.NORNAL TEMPERATURES ARE SHOMH AS l LEVEL? HA aa 2. VENDOR ENVIRONMENTAL QUALIFICATION REPORT, NAX DESI6N/AVERAGE:
| |
| IABOVE SPRAY/ iiii SDDF I IEEE 1.330-50003C 3,BASED ON THE ARRHENIUS CURVES IN REF 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 II 95F) AS QUALIFIED) ADDITIOHAL OPERATION TINE BEYOND 100 DAYS POST-tNAIHT/SURVEILL " -- II ACCIDENT IS AVAILABLE. I I
| |
| | |
| ==REFERENCE:==
| |
| 2 41VEHDOR TESTED VALUE INCLUDES CONBINED I VALUE OF BOTH ACCIDENT AND NORNAL lQUALIFIED LIFE - -- RADIATION VALUES~
| |
| I I I (YEARS) l 40 1 1 I I REFEREHCEl 2 11 I I I I I I I I I (
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| I ls ABHORMALL 87 I SEE NOTES I 1 i 2 I TEST SIN I HA I NOTE 5 (TYPE) (DESCRIPTIOH) ea ACCIDEHTI 200 I 318 I I I 2 s TEST SIM a YES I LEVEL TRANSNITTER 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
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| )MANUFACTURER: RDSEMDUHT ls ACCIDENT) 2,8 I 63 I 1 a 2 I TEST-SIM I YES I I'RH (X)' - "--- I "- ""- ' ---"I "-"-- ' ""-- I
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| - - -I - NOTE I IMDDEL HO.: 11536, 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 ISRFETY FUNCTIONS I REACTOR l(ATER LEVEL-et ACCIDEHTt slRADIATIOH' --""- ----- ----- -->>-" ---"-
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| |
| I II I I I I (ZONE Ho.l SC261145 II I IFLOOD LEVEL II DDCUMEHT REFEREHCE'OTES: 1 ~ FOR COMPLETE ENVIRONMENTAL CONDITIONS)I I ELEVATIOH; HA lt 1 EQUIPMEHT QUALIFICRTIOH EHVIRONNEHTAL DESIGN SEE THE DOCUMENT REFERENCED. a
| |
| )ABOVE FLDOD It CRITERIAI EQEDC-Ir REV Is MRY 2s 1984. 2.NORMAL TEMPERATURES ARE SHONH AS I ie LEVEL'? HA II 2 VEHDOR ENVIRONMENTAL QUALIFICRTIOH REPORTs MAX DESIGN/AVERA6E.
| |
| IABOVE SPRAY/ Ie SDDF 5 3.QURLIFICATIDH DOCUMEHTATIOH IH I I FROTH LEVEL'?HA 1(3 EQUIPMEHT OPERABILITY TIME DATA SHEET'ROGRESS. SCHEDULED PUBLICATION t IS FEBRUARY, 1985.
| |
| iDOCUMEHTATION ACCEPTABILITY' e 4,THE ACCURACY IS EXPRESSED AS' HUREG 0588,CAT PERCENTAGE OF THE UPPER RANGE DF I QUALIF I CAT IOH IN PROGRESS THE DEVICE AHD FOR THE MOST LINITIHB II l(NOTE 3) II CONTRIBUtOR (I.e.',RRDIATIOH) TO I
| |
| I II IHACCURACY. VERIF I CAT ION OF a (I ACCEPTRBILITY OF DEVICE APPLICATIOH IMAIHT/SURVEILL - -- t a HOTESc (CONTINUED) MILL BE, COVERED UNDER A SEPARATE I
| |
| a
| |
| | |
| ==REFERENCE:==
| |
| LATER sl 5.NORMAL RHD ABNORMAL TEMPERATURES PROGRAM'USIHB THE PROPOSED METHODS OF I I
| |
| lsi THE LICEHSIH6 REVIEH GROUP ll (LRG"ll)e I
| |
| sQUALIFIED LIFE - -- sa ARE SIMULATED BY ACCELERATED AGING AS DOCUNENTED IH REFERENCE 2 ~ SETPOIHT NETHODOL06Y PR06RAN. THE RE- a (YEARS)t LATER ll SUL.TS OF THIS SEPARATE PROBRAN HILL BEI II REFEREHCE: I I ISSUED PEHDIHG HRC(IC6B) APPROVAL OF' I II I I I THE LR6 SETPOIHT. I I I I I 11 I I I I I I ll
| |
| | |
| 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
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| IHODEL NO.: 1832-159-01 (VE)es NORMAL a 50 a HA a I a 2 s HA s HA e s
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| 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 VALVE ''RADIATIOH' - ---- ' ---- ' ---- ' ---- ' ---- ' - -' 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 II s>>
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| sOP CODE: A 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 s
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| |
| | |
| ==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 sHAINT/SURVEILL - NDTE 2 55'EHPERATURES I
| |
| le s UNVEHTED CHARGEe DUE TO AGING AND H16HI OF THE INCREASES THE VOLATILITY s 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,
| |
| | |
| ==REFERENCE:==
| |
| 2 4.NORMAL AHD ABHORHAL TEHPERATURES TO O la MHICH THE EQUIPNENT IS SUBJECTED MERE SIHULATED BY ACCELERATED AGING AS DOCUHEHTED IH REFEREKCE 2.
| |
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| NINE NILE POINT - UHIT 2 DDCKET NUMBER 50-410 SYSTEM COMPONENT EVALUATION MORK SHEET PA6E OF 1 QUAL REF 4 PBOOAFN REV 0 20-Oec-84
| |
| '
| |
| >>
| |
| I ENVIROMHEHTAL CONDITIONS AND QUALIF I CATION EQUIPMENT DESCRIPT IOH 11 I l DOCUMENT REFERENCE a I I I
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| I sl ABNORHALI 96 t NA I I I 2 I HA l HA 'I a TYPE) (DESCRIPTIOH) sl ACCIDENTt 175 l NA t 1 I 2 I HA a HA I I PULSE PREAMPLIFIER l IPRESS(PS(6)l ----- I ----- ' ---- ' ""- - ' ---- I - - -I - NOTE I I
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| |
| I I (ZONE NO.: SC240135 I I I I
| |
| siFLOOD LEVEL 11 DOCUHENT
| |
| | |
| ==REFERENCE:==
| |
| MOTES: 1,FOR COMPLETE ENVIRONMENTAL CONDITIONS,I s ELEVATION'A aa l. EQUIPMENT QUALIFICATION ENVIRONMENTAL DESI6N SEE THE DOCUMENT REFERENCED.
| |
| (ABOVE FLOOD 11 CRITERIA, EQEDC"1, REV 1, HAY 2, 1984. 2.NORMAL TEMPERATURES ARE SHOMH AS LEVEL? HA I I 2~ VENDOR ENVIRONMENTAL QUALIFICATION REPORT, HAX DESI6H/AVERAGE.
| |
| tABOVE SPRAY/ ts SDDF I (6E HEDC-30422)
| |
| I FROTH LEVEL?HA EQUIPHEHT OPERABILITY TIHE DATA SHEETl I I I I I I IDOCUHENTATIOH ACCEPTABILITY: lii lACCEPTABLE TO NURE6 0588,CATII II II II a PER HEDE 24326 I P 11 I
| |
| I I
| |
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| |
| I lHAINT/SURVEILL - --
| |
| | |
| ==REFERENCE:==
| |
| II HA II I I I I
| |
| IQUALIFIED LIFE - -- 11 II 11 I I (YERRS): NA II O si I
| |
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| I I
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| II II
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| HIHE MILE POINT - UHIT 2 DOCKET NUMBER 50-410 SYSTEM CONPOHEHT EVALUATION WDRK SHEET PAGE 1 OF I QUAL REF 4 P800AJX REV 0 20-Dec-84
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| ~
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| t See <<t 5<< >> > ~ ~
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| ~
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| ENVIRDNMENTAL CONDITIOHS AND QUALIFICAT(ON s s s s EQUIPMENT DESCRIPTION s s I t DOCUMEHT REFERENCE s s
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| s >>tl PARAMETER I SPECIFIED s QUALIFIED I a QUAL IMAR61Ns REMARKS tt
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| ---s- - a-c -I ----s ----s->>- --"-- s----s------
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| s VALUE I VALUE a SPECIFIED t QUALIFIED a METHOD ( DEMO s s a"
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| lEQUIP HO l E22-N055C ss i s 1-a->>-- - s s
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| s s s s s s s
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| lSPEC HO.: 184C4775 i sOP TIME' 24 HR ( 50 DAY a 3 a 2 e TEST IDENT ( YES, s s s s s s a s (SYSTEM: H16H PRESSURE ssTEMp (F)( NOTE s CORE SPRAY t(ORMAL I 85 l SEE NOTES l 1 I 2 lTEST-IDENT l HA I NOTE 2 s
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| s ABHORMALl 104 a SEE NOTES ( I l 2 (TEST"IDENT I HA I NOTE 4 (TYPES'DESCRIPTION) la ACCIDENTl 175 a 290 I I t 2 aTEST-IDEHT s YES a I LEVEL TRANSMITTER ''PRESS(PS(6)( ----- ' -- -- ' ---" ' ---" ' ---- ' - -' NOTE I s
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| s H NORHAL I ATMOS l SEE BELOW s 1 I 2 I , HA ' HA s I tt ABNORMAL( ATMOS t SEE BELOW I I I 2 s HA I HA (MANUFACTURERS 6OULD, IHC, ts ACCIDEHTs 2.8 l 17 ' s 1 s 2 aTEST IDENT I I s
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| s t tRH (X)' "- - -" ' ---" (
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| --- "- I
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| -"--- ' ---- ' - "a - NOTE 1 aMDDEL NO.: PD3218 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 aSAFETY FUNCTION; ts ACCIDENTI 100 100 a I I 2 aTEST"IDENT t HA s
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| - -'
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| s s HIGH SUPPRESSIOH POOL ''RADIATION' ----- ' ---" ' ---- ' ---" ' -"-- ' NOTE t a LEVEL t( NORM GAMHAt 1. (E7 i SEE BELOW I I I 2 I NA I HA a s
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| s (i ACC GAMMA I 9 0E6 a 5 35E7 I 1 s 2 aTEST IDENT I sOP. CODE: A al NORM BETA a HA s SHIELDED s I i 2 a HA s HA a s
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| s la ACC BETA I la2E7 s SHIELDED a 1 s 2 a NA I a s
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| s la HEUTROH I HA s NA a I a 2 a NA I a s
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| tsSPRAY I NA HA NA I HA s
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| -- a a a s
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| (ACCURACY asSUBMERGEHCEa HA I NA I s HA t HA I SPEC: +/- 6.8 'H20 ll s 0
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| s DEMO: ( +/- 6.8 'H20 s a s s s s s s (ZONE NO l SC175105 as aFLOOD LEVEL sa DOCUMEHT REFERENCE) NOTES: I.FOR COHPLETE ENVIRONMENTAL COHDITIONSst l ELEVATIOHl NA at 1. EQUIPMENT QUALIFICATION ENVIRONMENTAL DES16N SEE THE DOCUMENT REFERENCED.
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| aABOVE FLOOD aa CRITERIA, EQEDC-l, REV 1, MAY 2, 1984. 2.HORHAL TEMPERATURES ARE SHOWH AS LEVEL? HA ls 2. VENDOR ENVIRONMENTAL QUALIFICATION REPORT, MAX DESIGN/AVERAGE.
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| aABOVE SPRAY/ tl SDDF 4 3,QUALIFICATION DOCUMENTATION FROTH LEVEL?HA lt 3 EQUIPMEt(T OPERABILITY TIME DATA SHEETS IH PROGRESS. SCHEDULED PUBLICATION a
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| s IS FEBRUARY) 1985, (DDCUMEHTATIOH ACCEPTABILITY: tt 4.NORMAL AND ABNORMAL TEMPERATURES HUREG 0588 CAT Illt ARE SIMULATED BY ACCELERATED A61HG lQUALIFICATION IH PROGRESS s e AS DOCUMENTED IN REFERENCE 2.
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| s a (HOTE 3) as s s s s s s e s s s
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| (MAIHT/SURVEILL - -- as
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| \
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| s s
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| s s s s REFEREHCE: HA s s s s I s
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| sQUALIFIED LIFE - -- as s s s s s s lYEARS): 15 YEARS s I s
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| s
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| ==REFERENCE:==
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| 2 I s s a s s s s s s s s s s s I s
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| NINE NILE POIHT - UNIT 2 DOCKET NU)(BER 50-410 SYSTE)( CO)(PONENT EVALUATION MORK SHEET PAGE 1 OF 1 QUAL REF I PGOOAOM REV 0 20-Oec-84
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| ~ IS ENVIROHHENTAL COHDITIOHS AND QUALIFICATIOH EQUIPHEHT DESCRIPT(OH I I I I al l ai l DOCUNENT REFERENCE I I I
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| =l t PARANETER l SPECIFIED l QUALIFIED I QUAL tt(ARGIHt REKARKS I
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| I VALUE 1 VALUE I SPECIFIED 1 QUALIFIED I HETHOD I DEl(O a IEQUIP HO.: E31-N092 II - - I I << I << << I <<>> I I lSPEC HO ) 163C1563 a(OP,TI)(E: I NA s NA s 3 l 2 AH4DATA l, NA ISYSTEHl '(TE)(P - ' ---- t " - -t -
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| I NOTE I i1 (F)'t I LEAKAGE DETECTION NORHAL t 85 s SEE NOTES I, 1 l 2 NA 1 NA l NOTE 2 I
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| I la ABHOR)(AL( 104 I SEE HOTES a l 2 I HA t NA t NOTE 3 (TYPEE (DESCRIPTIOH) la ACCIDENTI 200 >200 I 2 AN~DATA YES I I PRESSURE TRANSMITTER I'PRESSlPSIG) ' - "- -
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| a
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| ' - -- - '
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| 1
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| ----
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| (
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| ' - -- I I
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| 1 I a NOTE 1 I
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| I aa NORNAL 1 AT)(OS I HA a 1 a 2 I NA a NA a I
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| I ABHORNAU HA I NA I 1 1 2 I NA I NA a atlAHUFACTURER'OSEt(OUNT I I ACCIDENT) 2.8 a NA I 1 I 2 NA I NA I
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| I ''RH (X)'l NOTE I l tlODEL NO.: (151 NOR)(AL 1 50 l NA I 1 t 2 I NA I NA ai I
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| I sa ABNORNALi 90 t HA I 1 a 2 a NA I NA tSAFETY FUNCTION: II ACCIDENT I 100 a 100 I 1 I 2 I AN)DATA l NA t PRESSURE INTEGRITY/Cl.ASS 'RADIATIOH' I I NOTE 1 lE ASSOCIATED as NDRH GAHHA( 1,1ES lit(CL BELOM l I a 2 l NA t NA I
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| tt ACC GANNA s 2a3E7 s l<3EB I 1 t 2 I AN>DATA t YES a (OPa CODE) 8 (REFERENCE 2) la NORH BETA a HA ( SHIELDED I I l 2 NA l NA l I 's I as ACC BETA 6 3E6 a SHIELDED I 1 i 2 I NA I NA I aa NEUTRON at(A a I NA t I t 2 ( HA l NA I I
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| I slSPRAY I HA NA HA NA IACCURACY "- a(SUBHERGEHCE( NA I
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| I HA I
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| a a
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| I HA I
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| I HA I II ~ I SPEC: NA I I I I I ABNORMAL I DEMO: NA I I I I I I I I I I t LONE HO. l SC261145 (
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| )FLOOD LEVEL ll DOCUMENT
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| ==REFERENCE:==
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| NOTES: 1.FOR COMPLETE ENVIRON)(ENTAL CONDITIONS,I I ELEVATIOH) NA la 1 EQUIP)(ENT QUALIFICATIOH ENVIROHHEHTAL DESIGN SEE THE DOCUMENT REFERENCED ~
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| IABOVE FLOOD sa CRITERIA) EQEDC-I) REV 1) t(AY 2, 1984 2 TEKPERATURES ARE SHOMN AS LEVEL'? NA ta 2 VENDOR EHVIROHNENTAL QUALIFICATION REPORT) HAX DESIGN/AVERAGE. l IABOVE SPRAY/ SDDF 4 (GE NEDC"30409) 3 HORHAL AHD ABHDRKAL TE)(PERATURES 1 a FROTH LEVEL?HA as i3, EQUIPHEHT OPERABILITY Tlt(E DATA SHEETl TO MHICH THE EQUIPMENT IS SUBJECTED l I MERE ACCDUNTED FOR IH THE ACCELERATED l
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| )DDCUHEHTATION ACCEPTABILITY: AGING ANALYSIS AS DOCUNENTED IN aACCEPTABLE TG HUREG 0588,CAT II' REFERENCE 2.
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| I I t PER HEDE 24326-1-P II I I I I I I I II I II t
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| (NAINT/SURVEILL - -- ~
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| II I
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| I REFERENCE) NA (
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| I II I
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| tQUALIFIED LIFE - -- II II I I I I (YEARS): 15 I I II t REFEREt(CE: 2 I I I I I I I I I I II II II I I
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| APPENDIX C Replace with existing Appendix C tab from Volume l.
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| T E S TP413T PLIMITRSWITCHES 0 F I L E 380 380 320 300 280 280 220
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| : n. 200 180 1 OO 120 100 L0Q(TIME IN M IN UTES)
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| T E S TP41 3T PLIMITRSWITCHES 0 F I L E 100 90 e
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| 80
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| =.--
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| 50 30 LOG(TI 20 10 0
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| M IN M IN UTES)
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| TEST PROFILE DATA FOR P413T LINIT SWITCHES TINE 0 30sec 50sec 7hr 7.5hr Iday 2days 4days 5days 30days LO6(NINUTES) -3.00 -0.30 -0.08 2.62 2 '5 3.16 3.46 3.76 3 '6 4.64 TENP(F) 100 370 340 340 320 320 260 260 200 200 PRES(PSIB) 0 100 100 100 75 75 10 10 10 10 TINE (NIN) 0.001 0.5 0,83 420 450 1440 2880 5760 7200 43200
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| T E S T P R 0 F I L F P413T SOLENOID VALVES 350 30O 4
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| 250 200 I
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| 150 100 I
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| 1 1 L O C (Tl M E IN M I N UTES)
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| T E S'TP413T P R O F SOLENOID VALVES I L E 110 100 00
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| ~ eo Cfi CL TO 1JJ 50 CA Cll 40 4J CL 20 10 0
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| 1 LOC (Tl M E 1
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| IN M I NUT'ES)
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| TEST PROFILE DATA FOR P413T SOLENOID VALVES TINE 0 Bain 3hr 3hr 4days 26days LOSININUTES) -3.00 0.90 2.26 2 '6 3.76 4.57 TENP{F) 0 346 346 320 250 200 PRES )PS I 6) 0 110 110 75 15 0 TINE <NIN) 0.001 8 180 180.1 5760 37440
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| A C C I D E N T, ZONE ABN1T505 C 0 N D I T I 0 N 180 1 7'0 180 150 I
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| 140 150 I
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| 120 110 100 2 0, LOG QTI M E IN M I NUTEQ)
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| A C C.I D E N ZONE T ABN1750$ C 0 N D I T I 0 N 2.8 2.8 2.4 22 C/l 1.8 1.8 1.4 c/7 1 Cll 1
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| lal 0.8 0.8 0.4 0.2 0
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| 0 ,,4 LOG(TIME IN MINUTES)
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| ACCIDENT CONDITON FOR 1ONE ABNI7503
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| - - 4'CIC DER HELD in Secondary Containaent TEHPERAT URE TIHE 0 1.0sec 100sec ihr id ay 3days 10days 100days LOB(HINUTES) -4.00 -1.77 0.22 1.78 3.16 3.64 4.16 5.16 TEHP(F) 104 175 175 150 125 115 104 104 T I HE (HIN) 0 0001 0.017 1.67 60 1440 4320 14400 144000 PRESSURE TIHE 0 1.0sec 100sec ihr 3hrs lday 10days 100days LOB(HINUTES) -4 00 -1.77 0.22 1.78 2.26 3.16 4.16 5.16 PRES(PSIB) 0 28 28 13 08 03 0 0 TINE (H IN) 0.0001 0.017 1.67 60 180 1440 14400 144000
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| A C C I D E N T C 0 N D ZONE MST24044 I T I 0 N 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.
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| I 0 G (Tl M E IN M I N UTES)
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| 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
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| 4 2 0 2 I 0G (TIM E IN M I NUTES)
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| ACCIDENT CONDITIONS FOR ZONE HST24044 - - Hain Steaa Line Break in Hain Steaa Tunnel TEHPERA TURE TIHE 0 0,05sec Ssec 10sec 1hr (day 10days 100days LOS(HINUTES) "4.00 -3.10 -1 '0 -0. 77 1. 78 3 ~ 16 4. 16 5. 16 TEHP<F) 140 340 340 275 275 175 i40 140 TIHE(HIN) 0.0001 0.0008 0 08 F 0 '7 60 1440 14400 144000 P R E S 8 U R E-TIHE 0 0.(sec isec 2sec Ssec 10sec 1hr 1day 10days 100days LOS(HINUTES) -4.00 -2.77 -1 '7 -1 '8 -0.89 -0.77 1.78 3.16 4,16 5.16 PRES(PSIG) 0 20 20 27 ' 27 ' 5 0.8 0,3 0 0 T I HE (HIN) 0.0001 0.0017 0.017 0.033 0.13 0.17 60 1440 14400 144000
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| A C C I D E N T C ZONE PC175101 0 N D I T I' N 220 210 200 190 180 1 70 1BO 150 130 120 110 100 BO LOG(TIME IN M I NUTES)
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| A C C I D E N T C ZONK PC1 751 01 0 N D I T I 0 N 30 20 15 10 2 4.
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| LOG(TIME IN M I NVTES)
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| ACCIDEHT COHDITIOHS FOR ZOHE PC175101 -- Design Basis Accident Analysis Prieary Cantainaent TEMPER ATUR E TIME 0 0.5sec 2hr 6hr lday 10days 30days 100days LOS (MI HUTES) -4.00 -2.08 2.08 2.56 3.16 4.16 4.64 5.16 TEMP I j) 90 150 200 212 212 150 135 90 TIME (MIH) 0.0001 0.008333 120 360 1440 14400 43200 144000 PRESSU RE TIME 0 lsec 6hr lday 5days 10days 30days 100days LOS(MIHUTES) -4.00 -1.78 2.56 3.16 3.86 4.16 4.64 5.16 PRES{PSIS) 0 40 40 25 10 7 5 0.8 TIME IMIH) 0.0001 0.016666 360 1440 7200 14400 43200 144000
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| APPENDIX D Replace with existing Appendix D tab in Volume l.
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| Nine Mile Point Unit 2 EQD APPENDIX D WILL BE PROVIDED IN A FUTURE AMENDMENT Amendment 16 D-1 December 1984
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| ~t}}
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