ML20087M264
| ML20087M264 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/31/1984 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20087M263 | List: |
| References | |
| ENVR-840331, NUDOCS 8403290146 | |
| Download: ML20087M264 (79) | |
Text
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l BVPS-2 ER-OLS Y
INSERTION INSTRUCTIONS FOR AMENDMENT 5 p
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Remove old pages and insert Amendment 5 pages as instructed below.
Transmittal letters along with these insertion instructions should either be filed or entered in volume 1 in front of any existing letters, instructions, distribution lists, etc.
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LEGEND Remove / Insert Columns Entries beginning with "T"
or "F" designate table or figure numbers,
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respectively. All other entries are page numbers:
l T2.3-14 = Table 2.3-14 F5.4-3 = Figure 5.4-3 2.1-9 = Page 2.1-94 EP2-1 = Page EP2-1 vii = Page vii Pages printed back to back are indicated by a "/":
1.2-5/1.2-6 = Page 1.2-5 backed by Page 1.2-6 T2.3-14(5 of 5)/T2.3-15(1 of 3) = Table 2.3-14, sheet 5 of 5, backed by Table 2.3-15, sheer. 1 of 3 Location Column Ch = Chapter, S = Section, Ap = Appendix Remove Insert Location VOLUME 1 1
EP-i/ blank EP-i/ blank After frontispiece EP2-1/EP2-2 EP2-1/EP2-2 After EP2-3/ blank EP2-3/ blank Chapter 2 tab i
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3.6-8/ blank March 1984 Amendment 5 1 of 3 i-8403290146 840319 P
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BVPS-2 ER-OLS I!!SERTIOf2 I!!STRUCTIO!!S FOR A!!E!!D11EllT 5 (Cont)
Remove Insert Location VOLUl!E 2 EP-i/ blank After frontispiece EP5-1/EP5-2 EP5-1/EP5-2 After EP5-3/EP5-4 EP5-3/EPS-4 Chapter 5 tab 5.6-3/5.6-4 5.6-3/5.6-4 S 5.6 5.6-5/5.6-6 5.6-5/ blank T5.6-1 (1 of 1)/
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EP5D-1/ blank EPSD-1/ blank After Appendix SD tab SD-i/ blank thru SD-i/ blank After TSD-1 (1 of 1)/
Appendix SD blank Title page EP7-1/ blank EP7-1/ blank After Chapter 7 tab 7-v/ blank 7-v/ blank After 7-iii/ blank 7.1-3/7.1-4 7.1-3/7.1-4 S 7.1 7.1-19/7.1-20 7.1-19/7.1-20 thru S 7.1 7.1-21/7.1-22 7.1-22a/ blank 7.1-29/7.1-30 7.1-29/7.1-30 S 7.1 7.1-31/7.1-32 7.1-31/7.1-32 T7.1-3 (1 of 1)/
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BVPS-2 ER-OLS IllSERTIO!1 INSTRUCTIONS FOR A!!ENDMENT 5 (Cont)
G Remove Insert Location T8.1-1 (1 of 2)/
T8.1-1 (1 of 2)/
S 8.1 T8.1-1 (2 of 2) thru T8.1-1 (2 of 2) thru T8.1-4/ blank T8.1-4/ blank 8.2-1/8.2-2 8.2-1/8.2-2 S 8.2 T8.2-1 (1 of 1)/ blank T8.2-1 (1 of 1)/ blank S 8.2 EPQ1-1/EPQ1-2 EPQ1-1/EPQ1-2 After May 4, 1983 tab QE291.7-1/
QE291.7-1/
After QE291.8-1 QE291.8-1 QE291.5-1/QE291.6-1 EPQ2-1/ blank EPQ2-1/ blank After October 20, 1983 tab QE451.5-1/QE451.6-1 QE451.5-1/QE451.5-2 After TE451.5-1/TE451.5-2 Figure E451.4-1 QE451.7-1/ blank QE451.6-1/QE451.7-1 After TE451.5-1/E451.5-2 s._,/
December 2, 1983 tab After QE460.1-1/
thru QE450.2-1/ blank QE450.2-1 i
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Amendment 5 3 of 3 March 1984 l
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BVPS-2 ER-OLS SUlt!!ARY LIST OF EFFECTIVE PAGES 9
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EP2-1 2
EP2-2 thru EP2-3 5
EP3-1 thru EP3-3 4
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EP4-1 0
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EPS-3 thru EP5-4 5
EP5A-1 2
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BVPS-2 ER-OLS LIST OF EFFECTIVE PAGES Page, Table (T),
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Number T2.2-14 (1 thru 2 of 2) 0 T2.2-15 (1 of 1) 0 T2.2-16 (1 of 1) 0 T2.2-17 (1 thru 3 of 3) 0 F2.2-1 1
F2.2-2 1
2.3-1 thru 2.3-2b 1
2.3-3 thru 2.3-5 1
T2.3-1 (1 thru 4 of 4) 1 T2.3-2 (1 of 1) 1 T2.3-3 (1 of 1) 1 T2.3-4 (1 of 1) 1 T2.3-5 (1 of 1) 1 T2.3-6 (1 of 1) 1 T2.3-7 (1 of 1) 1 T2.3-8 (1 of 1) 1 T2.3-9 (1 thru 2 of 2) 1 T2.3-10 (1 of 1) 1 T2.3-11 (1 of 1) 1 12.3-12 (1 of 1) 1 F2.3-1 0
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Amendment 5 EP2-2 March 1984
BVPS-2 ER-OLS LIST OF EFFECTIVE PAGES (Cont)
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Amendment 5 EP2-3
!! arch 1984
BVPS-2 ER-OLS Ohio River Valley Water Sanitation Commission 1976. Assessment of Validity of Water Sampling Locations on the Ohio River and Lower Reach of Major Tributaries.
River Quality Cross Section Study, November 1976.
i Pennsylvania Department of Environmental Resources (DER) 1974. Rules and Regulations, Title 25.
l
- Shirazi, M.A.
and Davis, L.R.
1974.
Workoook of Thermal Plume Prediction. Vol. 2, Surface Discharge. U.S. Environmental Protection Agency, EPA RZ-72-005b.
I U.S.
Army Corps of Engineers 1970. Analysis of Flood Heights, Ohio River at Shippingport, Pennsylvania.
Hydrologic Engineering Investigation, Pittsburgh District, Pennsylvania.
U.S.
Army Corps of Engineers 1976.
Letter from E.W.
- Thomas, Assistant Chief, Engineering Division, Pittsburgh District, to R.L.
j Naymark, Duquesne Light Company, dated September 17, 1976.
I U.S.
Army Corps of Engineers 1978.
Letter from E.W.
- Thomas, Assistant Chief, Engineering Division. Pittsburgh District, to W.H.
Bohlke, Stone & Webst?r Engineering Corporation, dated June 15, 1978.
U.S.
Army Corps of Engineers, Ohio River Division, January 1981.
4 Profiles - Ohio River.
U.S.
Army Corps of Engineers, Pittsburgh District, 1967. Map of Regional Hydrology.
U.S.
Army Corps of Engineers, Pittsburgh District, June 1977.
Frequency Profile - Ohio River Mile O to Mile 54.
U.S.
Geological Survey (USGS) 1976. Water Resources Data for Ohio, Water Year 1975. Vol. 1, Ohio River Basin.
U.S.
Geological Survey 1978. Water Resources Data for Pennsylvania, Water Year 1977. Vol. 3, Ohio River and St. Lawrence River Basins.
Water Data Report PA-77-3.
U.S.
Geological Survey 1981. Water Resources Data for Pennsylvania, 1975 to 1980.
Yotsukura, N.
and Sayre, W.W.
1976. Transverse Mixing in Natural Channels. Water Resources, Vol. 12, No. 4, August 1976.
4 Amendment 5 2.4-17 March 1984 a
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BVPS-2 ER-OLS TABLE 2,4-6 RIVER STAGE I!JFORMATION FOR THE liEW CUMBERLAND POOL
- River Level River Stage at the Site (feet)
Downstream dam failure (minimum water level)
El 648.6
!Jormal pool El 664.5 Ordinary high water El 675.0 Maximum high water El 693.0 l 100 year flood **
El 695.0 l 500 year flood ***
El 700.0 Standard project flood (SPF)****
El 705.0 SPF with upstream dam failure El 725.2 Probable maximwn flood El 730.0 IJOTES :
- U.S.
Army Corps of Engineers 1970.
- U.S. Army Corps of Engineers 1981.
- U.S.
Army Corps of Engineers 1977.
- Reduced frem 707.2 feet in January 1970.
Amendraent 5 1 of 1 March 1964 1
1 BVPS-2 ER -OLS
('~x 2.6 REGIONAL HISTORIC, ARCHAEOLOGICAL, ARCHITECTURAL, SCENIC,
(
CULTURAL, AND NATURAL FEATURES Historic sites in the Beaver Valley Power Station (BVPS) region including National Register Historic Places within 10 miles of BVPS-2 and State of Pennsylvania historic sites within 5 miles of BVPS-2 are indicated in Tables 2.6-1 and 2.6-2.
However, the historic character of the region, summarized in the following sections, remains as described in Sections 2.2 and 2.3 of the Environmental Report Construction Permit Stage (ER-CPS).
2.6.1 Historic Background of the Region
.The Beaver Valley Power Station - Units 1 and 2 (BVPS-1 and BVPS-2) is located on a series of terraces on the south bank of the Ohio River about 25 miles northwest of Pittsburgh, Pennsylvania. The region has played an important role in the nation's history, primarily as a result of its location along the Ohio River in the area known in the early nineteenth century as the " Gateway to the West."
Some traces of the history of the area when it was an important stepping-cff point for the west, can still be found within a few miles of BVPS-2.
Many of the physical structures, however, have disappeared.
k))
There are 12 National Register Historic Places within 10 miles of the BVPS-2 site as presented in Table 2.6-1.
These sites, except for the U.S.
Public Lands Survey Marker, were registered after the publication of the ER-CPS.
Only the Beginning Point of the United States Public Lands Survey (U.S.
Department of Interior 1981a) located on the Pennsylvania-Ohio border 4.8 miles west-northwest of I
the station is within 5 miles of the station. The properties listed in the National Register of Historic Places are generally located in nearby towns and cities and are examples of the area's early industrial history, its famous persons, and strategic location.
The State of Pennsylvania also maintains a data base of historic sites. At present, there are 12 recorded sites in the area within l
5 miles of the station.
The locations and distances of the sites from the station are listed in Table 2.6-2.
During the construction permit stage, SVPS-2 was evaluated in accordance with the requirements of the National Historic Preservation Act to determine whether any historic landmarks would be affected by station construction or operation. The Advisory Council on Historic Preservation (1969) concluded that the probable effect of the station could not be judged to be sufficiently adverse to warrant council comment.
This conclusion was reaffirmed in 1978 by the Pennsylvania State Historic Preservation Office (Pennsylvania
)
Historical and Museum Commission 1978).
1 i
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Amendment 5 2.6-1 March 1984 l
BVPS-2 ER-OLS Historic preservation officers for Pennsylvania, Ohio, and West Virginia were contacted in 1983 to verify listings of historic places and reevaluate the potential impacts on these places due to the operation and mai:.tenance of BVPS-2.
Based on the results of this assessment, no impact on flational Register or other historic places during the operation or maintenance of BVPS-2 is expected l
(Pennsylvania Historical and !!useum Commission It33a, Ohio Historic Society 1983, West Virginia Department of Culture and History 1983).
2.6.2 Natural Landmarks There are no registered natural landmarks in any of the three counties located within a 5-mile radius of the station (U.S.
Department of Interior 1981b).
~.6.3 Regional Archaeological Sites A number of archaeologically significant sites are located in the upper Ohio River region. Almost every major floodplain in the area was the site of a prehistoric Indian village which was occupied intermittently for many thousands of years.
The first Indians inhabited the region as early as 12,000 B.C. when the glaciers began to recede. Numerous Indian artifacts, such as stone arrowheads,
- tools, and utensils, have been excavated from some of these sites,
)
but many of the sites have been destroyed by urban and industrial expansion.
The Anthropology Center of the Carnegie !!useum of Pittsburgh lists several archaeological sites in the BVPS vicinity.
One Indica village site is near the abandoned Shippir.gport ferry docks on the south bank of the Ohio River about 0.5 mile upriver from the station.
Other archaeological sites are found along the Ohio Rivor at Industry and Vanport and throughout the Raccoon Creek valley beginning at the mouth of the creek 5 miles upriver from the station site (Carnegic Museum Archaeology Center 1978, 1981).
2.6.4 Visual Effects of the Station The immediate area surrounding the station is one of physical and cultural contrasts. Along the Ohio River, major industrial plants commingle with small-to medium-sized towns on the river terraces.
Steep bluffs rise 400 to 600 feet above the river with many small, short streams cutting bep canyons down to the river's edge.
Above and back from the river, rolling hills surround expansive, plateau-like level areas. The area has many small farms, scattered rural settlements, and small crossroads villages. To the west of the site, the topography becomes more gentle, while to the east, even a mile back from the river, there are many steep-walled stream valleys and precipitous changes in elevation.
O Amendment 5 2.6-2 March 1984
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i BVPS-2 ER-OLS i
Seen in this setting, BVPS-2 poses no severe visual change. Almost all views of the plant are confined to the Ohio River Valley or the j
top of the adjacent bluffs, where the panorama has shown evidence of industry for decades. In addition, due to its proximity to BVPS-1 and Shippingport Atomic Power. Station (SAPS), almost all views which include BVPS-2 also include BVPS-1 and SAPS.
The Bruce Mansfield
- Plant, located approximately 1 mile northeast of BVPS-2, further j
reinforces the industrial character of the region. Therefore, no new or unique viewscape is created by BVPS-2, and visual impacts from BVPS-2 can be considered negligible.
I Depending on meteorological conditions, the cooling tower plume may 4
be visible over a greater area.
However, experience with BVPS-1 indicates that when the plume is most extensive, the background sky i
is usually light white. and the clouds and fog merge with the plume, making it much less noticeable.
In addition, plumes from BVPS-1 and the Bruce Mansfield Plant already exist and will occur simultaneously with those from BVPS-2.
Thus, a minimal change will be added to the j
view by BVPS-2 plumes. Plume description and occurrence is discussed further in Section 5.1.4.
i Since BVPS-2 does not change the established visual character of the area, no ground-level photographs are included in this section.
1 I
2.6.5 Transmission Corridor i
- Historic, archaeological, architectural,
- scenic, cultural, and natural features of the region will not be impacted by BVPS-2 transmission since existing corridors and transmission towers will be i
utilized in all offsite areas.
2.6.6 References for Section 2.6 j
Advisory Council on Historic Preservation 1969. Letter dated April j
14, 1969.
j Carnegie Museum Archaeology Center 1978.
Letter from Dr. Stanley 1
Lance, Field Archaeologist, dated August 17, 1978.
I Carnegie Museum Archaeology Center 1981. Personal communication from Dr. Stanley Lance, Field Archaeologist, December 29, 1981.
4 ohio Historic Society 1983. Signed concurrence by W. Ray Luce, Stata j
Historic Preservation Officer, September 12, 1983 on letter from E.G.
- Nelson, Stone & Webster Engineering Corp. (SWEC), dated August 30,
~
1983.
Pennsylvania Historical and Museum Coinmission 1978. Stamped approval I
by Vdnce Packard, State Historic Preservation Officer, August 17, 1978 on letter from Stuart L.
Miner, Environmental Planner, NUS Corporation, dated August 14, 1978.
i O
Amendment 4 2.6-3 February 1984 r
BUPS-2 ER-OLS Pennsylvania Historical and Museum Commission 1983a.
Signed I
concurrence by !!s. Brenda Barrett, Director, !Jovember 14, 1983 on letter from E.G. !!elson, SWEC, dated October 25, 1983.
Pennsylvania Historical and Museum Commission 1983b.
Letter from Ms.
Donna Williams, Chief, Division of Planning and Protection, September 29, 1983.
Pennsylvania Historical and !!useum Commission 1984.
Listing of historic properties in Beaver County from state data base in letter from Ms. Sharon Kukla, dated January 25, 1984.
U.S.
Department of Interior 1981a. National Register of Historic Places. Heritage Conservation and Recreation Service, Annual Listing of Historic Properties.
U.S.
Department of Interior 1981b.
National Registry of Natural Landmarks. Heritage Conservation and Recreation Service.
West Virginia Department of Culture and History 1983. Letter from Rodney S. Collins, Director, Historic Preservation Unit, dated August 23, 1983.
O Amendment 5 2.6-4 March 1984
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BVPS-2 ER-OLS I
i TABLE 2.6-1 O
NATIONAL REGISTER OF HISTORIC PLACES SITES WITHIN 10 MILES j
OF BEAVER VALLEY POWER STATION Distance from Direction Station from Site Location (Miles)
Station
- ]
Pennsylvania Fort McIntosh Site
- Beaver 9.0 NE Matthew S. Quay House
- Beaver 9.0 NE William B. Dunlap Mansion
- Bridgewater 9.0 NE J
B.F. Jones Memorial Library
- Aliquippa 10.0 E
Merrill Lock No. 6*
Industry 5.2 NE I
Ohio Beginning Point of U.S.
East Liverpool (on 4.8 WNW Public Land Survey Ohio-Pennsylvania boundary) i East Liverpool Post East Liverpool 7.5 W
I Office
- j East Liverpool Pottery
- East Liverpool 7.2 W
i Cassius Clark Thompson East Liverpool 7.0 W
House
- Carnegie Public Library
- East Liverpool 7.5 W
Ikirt House
- East Liverpool 7.5 W
West Virginia Old Courthouse
- New Manchester
- 10.0 SW NOTE:
- Sites added to National Register since publication of the ER-CPS.
g,,j Amendment 4 1 of 1 February 1984
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BVPS-2 ER-OLS TABLE 2.6-2 O
ADDITIONAL HISTORIC SI1ES WITHIN 5 MILES OF BVPS Approximate Distance Name Location (miles)
Direction Indian Petroglyphs*
Smiths Ferry 3.75 WNW Service Creek Monuments
- John Anderson Cemetery
- Raccoon Township 4.50 SE Christler's Landing
- Shippingport 0.50 NNE Christy Home*
Shippingport 0.50 NME Bethlehem Charch*
Shippingport 1.25 NE Nelson Place
- Greene Township 4.00 SW Littell Homestead
- Greene Township 4.00 S
Bakers Landing
- Potter Township 5.00 ENE Shippingport Atomic Power Shippingport 0.25 SW Station **
l Mill Creek Church ***
Greene Township 4.50 SW NOTES:
- Pennsylvania Historical and !!useum Commission 1978.
- Pennsylvania Historical and Museum Commission 1983b. This site has been determined to be eligible for the !!ational Register.
- Pennsylvania Historical and !!useum Commission 1984.
Amendment 5 1 of 1 March 1984
i BVPS-2 ER-OLS
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3.6.8 Screenwash System 4
3.6.8.1 Main Intake Structure The main intake structure is common to both units.
When only BVPS-1 is operating, the intake traveling screens are backwashed at 770 gpm for approximately 10 minutes, three times a day.
When both BVPS-1 and BVPS-2 are operating, the frequency and daily average flows are doubled.
3.6.8.2 Auxiliary Intake Structure i
The auxiliary intake structure is common to both units.
Although the auxiliary intake structure is not normally used, the intake travelling screens are backwashed at 195 gpm for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> once a week to prevent the buildup of debris.
i 3.6.9 Salt and Water Drift I
A mathematical model was developed to determine the downwind distribution of salt and water deposition rate and airborne salt concentration resulting from cooling tower operation. A detailed description of the model and results are contained in Appendix 3B.
The model takes into account the follcwing: configuration and performance of the towers, drift rate, exit velocity, total dissolved solids level, droplet size distrfbution, evaporation rate, plume buoyancy, wind speed, wind direction, wet-bulb terperature, and relative humidity.
One year of onsite meteorological data l
(January 1, 1976 to December 31, 1976) was used in the drift model.
j A maximum salt deposition rate of 9.9 pounds per acre per year (0.11 mg/cm2/ year) occurs approximately 4,750 feet east of the cooling towers.
The maximum water deposition rate of 20,300 pounds per acre per year (227.3 mg/cm2/ year) occurs at a distance of l
approximately 4,000 feet east of the towers. The maximum annual average airborne salt concentration is predicted to be 0.07 g/m3 i
(7 x 10-8 mg/1) approximately 7,000 feet east of the towers, while the maximum hourly airborne concentration of 21.9 g/m3 (2.19 x 10-5 mg/1) occurs 3,250 feet west-southwest of the towers. These j
maxima are the largest values occurring over the entire spatial grid f
of the model. Spatial averages of these concentrations are not given due to their insignificance in light of the small impacts caused by
]
the maximum values (section 5.3.3).
3.6.10 References for Section 3.6 Duquesne Light Company (DLC) 1978. Letter from R.J. McAllister, DLC, to B. Smith, U.S. Environmental Protection Agency, Region III,- dated l
July 20, 1978.
f I
J Amendment 4 3.6-7 February 1984 4
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BVPS-2 ER-OLS
- LaQue, F. L. and Copson, H. R. 1963. Corrosion Reristance of Metals and Alloys, Second Edition.
Reinhold Publishing Corporation, New York, N.Y.
NUS Corporation 1975.
1974 Baseline Report and Addenda November 1973 through December 1974. Aquatic Ecology Study.
U.S.
Environmental Protection Agency 1974. Effluent Guidelines and Standards for the Steam Electric Power Generating Point Source Category. 40 CFR 423.
Federal Register, Vol. 39, No. 196.
O Amendment 4 3.6-8 February 1984
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!! arch 1984 O
BVPS-2 ER-OLS from the operation of BVPS-1, although generally inaudible, are in
~si essence included in the 1977 ambient survey data.
Therefore, it is not necessary to include the BVPS-1 sound levels in the BVPS-2 predictions to arrive at station impact.
The total BVPS-2 operational sound levels, determined by logarithmically combining the contribution of each major source, are presented in Table 5.6-1.
The prediction includes the effects of hemispherical divergence, atmospheric absorption (except for the low frequency noise from the transformer where it has little or no effect), and man-made barriers, but does not include the attenuating effects of intervening topography, vegetation, and meteorology. The levels predicted are assumed to be constant and are represented statistically by an L as eq indicated in Table 5.6-1.
5.6.1.6 Impact Assessment The noise from the operation of a nuclear power station is that of a continuous nonvarying noise source. The loudness does not vary from day to day or between night and day except for an occasional infrequent, short-term event, such as the release of excess steam.
Since there are no state or local noise regulations currently in effect, the potential acoustical impact of the plant is assessed by comparing the predicted plant sound levels with requisite levels identified by the USEPA. The USEPA (1974) identifies an average day / night sound level (L of 55 dB as the maximum level for residentialareasbelowwhihS) speech, sleep, relaxation, privacy,and
(N other activity interference will not occur.
Examination of Table 5.6-1 shows that, in the noise-sensitive areas adjacent to the BVPS site, the existing community L sound levels are above 55 dB, dn indicating that there may already exist some speech and activity interference.
The predicted BVPS-2 operational noise levels also shown in Table 5.6-1 are for the summertime, when all the previously described noise sources could be operating, which represents a worst case condition. During the winter months, the turbine hall power roof ventilation system operate: intermittently and the summer wall vents are closed, resulting in lower operational noise levels.
The predicted L sound levels for BVPS-2 are lower at all locations than dn the USEPA-suggested 55 dB level except at location 2, where it is exceeded by only 3 dB.
Combining the existing community L sound levels with the predicted d
sound levels, nit can be seen that there is no BVPS-2 operational Ldp change in the community Ldn sound levels, except at location 2 where there is a 2 dB increase. Location 2 is at the B7PS property line in the vicinity of the nearest residential area. The BVPS-2 operational noise prediction, as previously described, is for a worst case i
condition that does not take into account the effects of topography, vegetation, and meteorology which would tend to reduce the predicted scUnd levels. The BVPS-2 operational yearly average Ldn sound levels will be somewhat less than the predicted Ldn sound levels due to the seasonal variations in BVPS-2 operatior.al noise from reduced ventilation noise levels during the cooler months. Additionally, as v
5.6-3 1
BVPS-2 ER-OLS the noise activity at the Bruce Mansfield Plant increases, the impact of BVPS-2 will be less obvious. Therefore, there is no anticipated community reaction to the BVPS-2 operational noise.
5.6.2 Effects of Gaseous Emissions on Ambient Air Quality 5.6.2.1 Ground-Level Impact Under Normal Diffusion Conditions The fossil-fueled equipment used at BVPS is discussed in Section 3.7.2.
The four auxiliary boilers, four emergency diesel generators, the diesel fire protection pump, and the standby diesel generator at the plant will emit sulfur dioxide (50 ),
nitrogen 2
- oxides, carbon monoxide (CO), hydrocarbons, and particulate matter (Table 3.7-1).
The auxiliary boilers have an estimated operating I
time of 1,424 hours0.00491 days <br />0.118 hours <br />7.010582e-4 weeks <br />1.61332e-4 months <br /> per year. The diesel generators, the diesel fire protection pump, and the standby diesel generator operate only during emergency situations, but will be tested regularly for an estimated annual operating time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, twice a month),
26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> (1/2-hour per week),
and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, once per month),
respectively.
The auxiliary boilers and diesels will burn No. 2 fuel oil. The uncontrolled emission rates of the pollutants given in Table 3.7-1 indicate that the units will not be major sources of these pollutants and thus not subject to the Clean Air Act Nr.en dments of 1977.
A major source is one which emits or has the potential to emit 100 (or 250, depending on the source category) tons per year or more of any ef the applicable pollutants. The applicable EPA requirement (40 CFR 52,2) for a Prevention of Significant Deterioration (PSD) analysis is 250 tons per year or more, which the station sources do not meet.
Therefore, nu impact analysis need be performed.
In addition, since the auxiliary boilers have a heat input of less than 250 x 106 Btu / hour, and since the emergency diesels are not steam generators, the Federal New Source Performance Standards for 50,
2 nitrogen oxides, and particulates are not applicable to these units.
- However, the state S0 and particulate emission regulations are 2
applicable due to a heat input of greater than 2.5 x 106 Ctu/ hour to each unit.
The emission rates of these pollutants from each unit (Table 3.7-1) ara below the state standard.
I 5.6.3 References for Section 5.6 Capano, G.A. and Bradley, W.E.
1976. Noise Prediction Techniques for Siting Large Natural Draft and Mechanical Draft Cooling Towers.
Stone & Webster Engineering Corporation, presented at the 38th Annual Meeting of the American Pcwer Conference, Chicago, Ill., April 1976.
I
- Schultz, M.W.
and Ringlee, R.J.
1960.
Some Characteristics of Audible Noise of Power Transformers and their Relationship to Audibility Criteria and Noise Ordinances.
Power Apparatus and Systems, American Institute of Electrical Engineers, June 1960.
l O
Amendment 5 5.6-4 March 1984 l
t BVPS-2 ER-OLS i
1 U.Sc Environmental Protection Agency (USEPA) 1974.
Information on O
Levels of Environmental Noise Requisite to Protect Public Health and l
Welfare with an Adequate Margin of Safety. Report No. 550/9-74-004.
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TABLE 5.6-1 BVPS OPERATIONAL NOISE AND COMMUNITY SOUND LEVELS (dBA re: 0.0002 microba r)
BVPS-2 Predicted Equipment Sound Larvel Cont ribut ion (6 el__
t t
lurbine Hal1 Existing Combined Cooling Main intake ran Power Roor Summer Ai-Community Community / Station Location
- Tower T ra nsfo rme r Ventilation Ventilation Ventilation intake Jola_1 L L
dn dr du 1
33 30 23 25 26 20 36 42 70 70 2
51 41 38 to 37 31 52 58 61 63 3
29 28 19 22 24 18 33 39 67 67 4
35 32 25 28 29 23 38 44 61 61 5
30 30 21 24 26 20 35 41 66 66 6
34 32 25 28 28 22 38 44 63 63 NOTE:
- Predicted sound level locations a re shown on Figure 5.6-1.
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T7.3-1 (1 of 1) 0 Amendment 5 EP7-1 March 1984
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BVPS-2 ER-OLS LIST OF FIGURES Figure Number Title 7.1-1 Schematic Outline of Atmospheric Pathway Consequence Model 7.1-2 Risk Curve for Early Fatalities 7.1-3 Risk Curve for Total Latent Cancer Fatalities 7.1-4 Risk Curve for Total Population Whole Body llan-Rem 7.1-5 Point Estimate Risk Curve for Thyroid Cancer Fatalities 7.1-6 Risk Curve for Population with Bone Marrow Dose > 200 Rem 7.1-7 Risk Curv6 for Total Coat with Decontamination 1.1-8 Isorisk Contours of Latent Cancer Fatality per Reactor Year to an Individual O
O Amendment 5 7-v March 1984
7 BVPS-2 ER-OLS
-~s Reactors, U.S. Department of Energy (USDOE), formerly ERDA. The SAPS
)
terminated operation in 1982 and is scheduled for decommissioning by the USDOE. The SAPS area is leased by DLC to the USDOE.
The low population zone (LPZ) surrounding BVPS-2 encompasses an area within an approximate 3.6-mile radius of the BVPS-2 reactor containment centerline.
The distance for the LPZ is based on the requirements of 10 CFR 100.
The 3.6-mile radius meets the requirement that the LPZ be an area in which sufficient protective measures can be taken to assure that the resident population does not receive a dose in excess of a specified level resulting from a postulated accident condition.
No population centers with populations equal to or greater than 25,000 exist within the LPZ, or within an area of radius 1 1/3 times the LPZ radius, approximately 4.8 miles.
The population center nearest to BVPS-2, as defined by 10 CFR 100, is the township of McCandless, Pennsylvania, which supported approximately 26,250 people in 1950 at a density of 1,608 people per square mile.
The township's closest corporate boundary to the station is approximately 17 miles east of BVPS-2.
Existing population centers with over 25,000 people are presented in FSAR Table 2.1-24.
Cities and towns projected to become population centers with over 25,000 people during the period 1980 to 2030 are listed in FSAR Table 2.1-25.
The projected population distribution for 2010, based on 1980 census data, is found in FSAR Tables 2.1-7,
(~}
2.1-14, and 2.1-21.
\\ _/
The safety analysis of the BVPS-2 site has also included a review of potential external hazards generated by man (offsite activities that might cause an accident). This review encompassed nearby industrial, transportation, and military facilities that might create explosive, missile, toxic gas, or similar hazards. The risk to BVPS-2 from such hazards has been found to be negligible. A more detailed discussion of the compliance with siting criteria and the consideration of external hazards is given in FSAR Section 2.2.
Also discussed in the FSAR are design provisions required for severe natural phenomena such as earthquakes, floods, and tornadoes.
7.1.2.3 Emergency Preparedness An Emergency Preparedness Plan for BVPS is in place and is exercised on an annual basis. The plan applies to the operation of BVPS-1 during the construction of BVPS-2 and will be modified to address both units upon completion and operation of BVPS-2.
The BVPS Emergency Preparedness Plan provides guidance for coping with both onsite and offsite emergency situations.
It ranges in scope from relatively minor unusual events and occurrences involving small releases of radioactive material to a major nuclear accident having significant offsite radiological consequences. This plan, together with the interrelated state and county emergency plans, s
(
)
Amendment 5 7.1-3 March 1984
BVPS-2 ER-OLS provides detailed arrangements for extending emergency measures to a radius of approximately 10 miles from BVPS. The elements of response to offsite emergency conditions are continued in the emergency plans and emergency operating procedures of the responsible offsite emergency organization.
The 10-mile emergency planning zone surrounding BVPS encompasses three states: Pennsylvania, Ohio, and West Virginia; and three counties: Beaver County, Pa; Columbiana County, Ohio; and Hancock County, West Virginia.
Continuing liaison with the emergency organizations of these jurisdictions ensures compatability with the BVPS plan. The coordination and liaison with offsite emergency organizations include formal agreements that individual organizations will perform their respective emergency functions in response to requests from BVPS.
7.1.3 Accident Risk and Impact Assessment 7.1.3.1 Design Basis Accidents This section evaluates the environmental impact of postulated accidents and occurrences involving radioactivity. Assumptions used in these evaluations are based on normal operating conditions. This is in contrast to the highly causervative assumptions employed in the FSAR, where worst-case conditions are posttilated.
Radiation doses are calculated using the core radioactivity given in ESAR Table 12.2-3 a X /Q value of 9.6x10-9 sec/m,
and the 3
calculational methods described in Regulatory Guides 1.4, Revision 2, and 1.145, Revision 1, except that the average breathing rate is used.
The X /Q value of 9.6x10** sec/m3 is the 0- to 2-hour value for the northwest sector of the exclusion area boundary. This is the 50-percent direction dependent (worst sector) value and is based on onsite meteorological data from January 1, 1976 through December 31, 19S0.
Section 2.3.4 describes the methodology used to develop meteorological values. Table 7.1-1 gives the integrated gamma, beta, and thyroid doses at the exclusion area boundary (EAB) from these accident analyses.
As is evidenced in Table 7.1-1, the resulting doses from the accidents described in the following sections are well below the values specified in 10 CFR 100.
The environmental impact from such accidents would be minimal.
The design conditions are categorized as follows:
1.
Incidents of moderate frequency These are events that can reasonably be expected to occur during any year of operation.
Amendment 2 7.1-4 August 1983
BVPS-2 ER-OLS
[/)
release category parameters used for the analysis are presented in N
Table 7.1-3.
s-Potential radiological consequences have been calculated for the nine release categories using the CRAC2 computer code.
This code incorporates the models developed in the RSS.
The analyses are site specific and employ environmental parameters associated with the BVPS-2 location. Meteorological data used in the analyses represent one full year of hourly averages of wind speed and direction, atmospheric lapse rate, and precipitation. Population data for the year 2010 is based on 1980 census data for the area within a 350-mile radius of the plant.
Habitable land fraction out to 350 miles is also a site-specific input.
In addition, the analyses require land ~
use statistics as a function of state, including land value, farm product values, and grouing season information for the area out to 350 miles.
A diagram of the consequence analysis model is given on Figure 7.1-1.
In order to calculate consequences and their associated probabilities, weather data for 1 year are sampled.
It would be prohibitively expensive to model the radioactivity release starting at each of the 8,760 possible hourly start times.
Instead, a provision known as " bin sampling" is used.
In this method, all of the hourly meteorological data are first classified into groups or bins (there are 29 bins defined in CRAC2) on the basis of similarity 7-s of weather sequences. Samples are selected from each bin.
This q j against exclusion or inappropriate weighting of some weather ensures sequences.
Protective actions modeled which would reduce radiation doses include evacuation of nearby population, sheltering of non-evacuees, long-term relocation of people, and interdiction and decontamination of contaminated land. The evacuation plan used (refer to Appendix 7A) is site specific and includes two possible evacuation schemes. The l
evacuation parameters i: sed in the model were extracted from a recent i
evacuation and mass notification study performed for BVPS (Alan M.
Voorhees and Associates 1980).
7.1.3.2.1.6 Calculation of Risk Curves This secticn describes the analytical techniques used to compile and assemble the results into risk diagrams.
The assembly process is based on a matrix multiplication process. Matrices were constructed for the following separate analyses:
initiating events, plant
- states, release categories, and consequences. Multiplication of the first three of these matrices provides the probability of occurrence associated with each release category, as shown in Table 7.1-2.
These probabilities were then multiplied by the consequence matrix provided by the CRAC2 runs done on a conditional basis (release category probability equal to 1).
This operation provides the additional probability associated with the weather conditions and OV Amendment 5 7.1-19.
March 1984
BVPS-2 ER-OLS evacuation scenarios to yield the total probability and consequences that make up the risk curves.
7.1.3.2.2 Dose and Health Impacts of Atmospheric Releases The results of the calculations for dose and health impacts are presented in the form of probability distributions functions, sometimes referred to as CCDFs (complementary cumulative distribution functions), or final risk curves.
All of the release categories shown in Table 7.1-2 are included in each risk curve.
I Figures 7.1-2 through 7.1-6 represent the probability distribution functions for the damage indices of early fatalities, total latent effects, population whole body man-Rem, thyroid cancer fatalities, and population with bone marrow dose over 200 Rem, respectively.
Early fatalities refer to those deaths which might result within 1 year of : postulated accident.
The total latent effects include fatalities from leukemia, cancers of the lung, gastrointestinal tract, breast, and bone, but do not include thyroid cancers.
The population whole body man-Rem is the sum of the number cf people exposed times the whole body dose received for each dose level.
The final risk curves represent the product of the analysis of initiating events, plant response, containment response, and site consequences for severe accident sequences at BVPS-2.
Incorporated into each of these distributions is the probability of a plant state resulting in a release to the environment described by any of the nine release categories, for each year of reactor operation.
The left side of Figure 7.1-2 shows that there is approximately one chance in 10 million per reactor year that one or more fatalities might occur as a result of a severe accident at BVPS-2.
This frequency of exceeding a given number of fatalities decreases as the damage index (number of ratalities) increases. Additionally, the risk curve shows that the probability of exceeding one early fatality and the probability of exceeding approximately 200 early fatalities are about the same.
Figure 7.1-3 shows the probability distribution for fatal cancers (excluding data groups " thyroid" and "whole body").
Calculation of these effects is based upon the dose response model presented in the BEIR report (National Academy of Sciences 1972) and is consistent with models developed in BEIR III (National Academy of Sciences 1980). There is typically a latent period after exposure of from 2 to 30 years before a cancer might be manifested. In addition, individuals are considered to be at risk of leukemia induction for 30 years after the latent period following exposure, while for all other cancers they are assumed to be at risk for the remainder of their lives. As a result, the predicted number of fatal cancers may be distributed over many years. The dose used in predicting the number of latent effects is a result of both acute and chronic exposure.
Amendment 5 7.1-20 March 1984
l BVPS-2 ER-OLS Figure 7.1-4 provides the probability distribution for total O
1 population whole body dose in man-Rem. Acute and chronic whole body doses to the population within 350 miles of the plant were used to generate this risk curve.
The thyroid cancer fatality risk-distribution is presented in Figure 7.1-5.
These results are based upon the assumption that 4% of the radiation induced thyroid nodules result in thyroid cancer fatality.
l Figure 7.1-6 shows the probability distribution for the population i
exceeding a bone marrow dose of 200 Rem and provides an estimate of the number of people which might require supportive medical trea tment.
As an indication of the spatial distribution of individual latent cancer fatality risk per year of reactor operation, contours of l
constant risk (isorisk curves) are plotted on a map of the site out to 10 miles (Figure 7 1-8).
7.1.3.2.3 Economic Impacts Placing monetary values on the cost of human radiation exposure is at best a difficult and controversial task. However, it is possible to assess the economic impacts of avoidance of adverse health effects.
Such a calculation has been performed for BVPS-2.
The results are shown on Figure 7.1-7, which is the probability distribution function I
for total cost of offsite mitigating actions including decontamination efforts. Factors which contribute to these estimated costs include the following:
Evacuation costs, Value of milk contaminated and condcmned, Costs of decontamination of property where practicel, and Indirect costs due to loss of property use and incomes derived therefrom.
The loss of land use and associated incomes derives from the possible need to interdict the land and property until it is free of contamination or'can be economically decostaminated.
Several comments can be made concerning economic risks based upon Figure 7.1-7.
The initial plateau portion of the curve indicates l
that the probability of total costs exceeding 1 million dollars and the probability of total costs exceeding 20 million dollars are the This is a direct result of calculating evacuation. costs based l
same.
l upon evacuation of the entire 10-radial-mile area of the plant.
The i
right side of.the risk' curve indicates that, although very unlikely l
(less than one chance in one hundred million), costs could exceed d
Amendment 5 7.1-21 March 1984 r
i
BVPS-2 ER-OLS several billion dollars (1980 dollars), These costs do not include the cost of decontamination and repair or replacement of the facility, nor the cost of replacement power.
7.1.3.2.4 Releases to Ground Water 7.1.3.2.4.1 Introduction Releases of radioactivity to the ground-water system could occur following a postulated core meltdown with eventual penetration of the containment basemat.
Core debris which exits the melt hole would then enter the water table, which is normally at an elevation of approximately 20 feet below the containment
- basemat, and radionuclides in the debris would be leached in the ground-water system.
It is also possible for containment sump water, which could be rich in dissolved fission products, to be released through a breach in the containment.
An analysis of the potential consequences of such an event is presented by the USNRC staff in NUREG-0440, " Liquid Pathway Generic Study" or LPGS (USNRC 1978a). This generic report provides the basis for the comparative evaluation of BVPS-2.
The LPGS presents analyses for a four-loop Westinghouse pressurized water reactor (PWR) located at a number of land sites, one of which is on a river system which is very similer to the one at BVPS-2.
The LPGS river site is on the Clinch River approximately 21 miles upstream of its juncture with the Tennessee River. The balance of this river system consists of the Tennessee River (567 miles),
the Ohio River (46 miles) and the Mississippi River (954 miles). This system contains a number of dams and reservoirs, principally along the Tennessee River segment.
The BVPS-2 river system is similar, consisting of 946 miles of the Ohio River and the same 954 miles of the lower Mississippi River.
Like the Tennessee, there are numerous dams along the Ohio. However, unlike the Tennessee, which is an important recreational resource, the Ohio is heavily industrialized.
In the LPGS, carameters for each generic site (including the Clinch River site) were chosen to be representative of the full spectrum of similar sites, in this case river sites.
Parameters used for analysis in the LPGS, although typical, do not represent any actual plant. site.
In the LPGS it was concluded that individual and population doses for the liquid pathways would be small fractions of the airborne pathways dose which could result from a core meltdown accident.
Individual and population doses are reported in the LPGS for the principal liquid pathways: drinking water, aquatic food, and direct exposure from swimming and shoreline usage. Exposure resulting from O
Amendment 5 7.1-22 March 1984
~
BVPS-2 ER-OLS crop irrigation was also considered but was found to contribute insignificantly to dose (USNRC 1978a).
Doses to individuals and populations were calcul?ted in the LPGS without taking credit for possible interdiction methods such as isolation of contaminated ground water, the temporary restriction of fishing, or the provision of alternate sources of drinking water (or additional purification equipment). Such interdiction methods would be highly successful in preventing exposure to radioactivity, and the l
liquid pathways consequences would therefore be economic and societal rather than radiological.
}
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OV Amendment :i 7.1-22a March 1984
BVPS-2 ER-OLS (perhaps orders of magnitude) smaller than that calculated in the LPGS.
The fish harvest downstream of the BVPS site is estimated to be more than a factor of 3.8 larger than that estimated in the LPGS.
Since this pathway is also dominated by Sr-90 and Cs-137 (Sandia National Laboratories 1981), population exposure via this pathway will also be substantially less than that calculated in the LPGS.
The shoreline and immersion pathway includes such activities as swimming, wading, and sunbathing.
These are external exposure pathways, and dosage is dominated by Ru-106, Cs-137, and Co-60.
For the BVPS site having a ground-water travel time of 25 years and assuming that Kd for Co-60 is 75, the transmitted fraction is vanishingly small, as has already been shown to be the case for Cs-137 and Ru-106.
It is therefore concluded that the direct exposure dose would be negligible in comparison with those calculated in the LPGS.
7.1.3.2.4.5 Liquid Pathway Crparison Results l
On the basis of BVPS site features and the specific comparisons of both radionuclide source and pathway populations, it is apparent that the spectrum of liquid pathways doses following a severe accident would be much lower for BVPS-2 than the doses calculated in the LPGS for a river-sited plant.
O~
This is mainly due to the much smaller source released to the Ohio River which in turn results mainly from a much longer ground-water transport time.
If shorter times are postulated, the adverse effect l
would be small and would probably be offset through the assumption of I
more realistic distribution coefficient (Kd) values.
In the extreme, if the same radionuclide source as in the LPGS were postulated, the pathways doses would still be within the same order of magnitude, since the pathways population ratios are not large.
l 7.1.3.3 Risk Consideration The previous material has dealt with the likelihood of occurrence (frequency) of accidents as well as their impacts (consequences).
Because it is difficult to compare such results with other types of risk in our environment, it is useful to combine these results into average risk values.
A common way in which this combination of factors is used to estimate risk is to multiply the probabilities by the consequences.
The resultant risk is then expressed as a number of consequences expected per unit of time.
Such a quantification of risk does not at all mean that there is universal ~ agreement that peoples' attitudes about risks, or what constitutes an acceptable risk, can or should be n
v Amendment 2 7.1-29 August 1983
BVPS-2 ER-OLS.
covered solely by such a measure.
At best, it can be a contributing factor to a risk judgment, but not necessarily a decisive factor.
To accomplish these comparisons, the mean values for a damage index (for example, early fatalities) as calculated by CRAC2 for each release category were weighted by the corresponding release category frequency, and then summed. The resulting value is representative of the risk for the particular damage index per year of reactor operation. The results of these calculations are presented in Table 7.1-4 for early fatalities, latent cancer fatalities, population whole body man-Rem, thyroid cancer fatalities, population with bone marrow dose over 200 Rem, and the total cost with decontamination.
The mean risk of early fatality per year of BVPS-2 operation for all i
release categories is approximately 0.0002, for evacuation to 10 miles.
The population at risk for early fatalities is within a 20-mile radius of the plant. The 2010 population within 20 miles of the plant, shown in FSAR Table 2.1-4, is 489,932.
Accidental fatalities per year for a population of this size, based upon overall averages for the United States, are approximately 103 from motor vehicle accidents, 38 from falls, 15 from drowning, 14 from burns, and 6 from firearms (National Research Council 1980). The risk of early fatalities due to the operation of BVPS-2 is therefore very small in relation to other fatal risks to which the population ia exposed.
I For comparison with the population whole body dose mean value of 309 man-Rem, also shown in Table 7.1-4, the whole body dose to the population within 350 miles of BVPS-2 due to natural radiation from the environment can be calculated.
In the northeastern United
- States, at the altitude of BVPS-2, the average annual dose to an individual due to natural radiation is approximately 103 mrem (National Academy of Sciences 1980).
If the population at risk around BVPS-2 is considered to be those people within 350 miles, or a population of 94,971,369 as shown in FSAR Table 2.1-21, the population dose frcm natural radiation is 9,782,000 man-Rem.
Based upon population whole body dose, the risk due to severe accidents resulting from operation of BVPS-2 is very small compared to the risk due to natural radiation.
The average number of latent cancer fatalities for the lifetime of the population within 350 miles of the reactor, due to one year of l
reactor operation, is approximately 2.1 x 10-2 In comparison, assuming a representative United States population, the expected number of deaths per year dae to cancer would be approximately l
195,300 (U.S. Bureau of Census 1982). Although this is comparing a lifetime risk to a yearly risk, it is evident that the risk of cancer fatality due to severe accidents is very small in relation to existing cancer fatality risks.
Amendment 5 7.1-30 March 1984
_-~
BVPS-2 ER-OLS x
7.1.3.4 Uncertainties The _ methodology employed to provide ~this present risk assessment for j
BVPS-2 is essentially that of the Reactor Safety Study.
There are substantial uncertainties associated with the numerical estimates of the likelihood, as well as the consequences, of reactor accidents that are evaluated using this methodology.
One of the chief areas of uncertainty is the magnitude of the source term, or fission product release to the atmosphere. This uncertainty arises from neglect of attenuation of fission products during transit through the primary coolant system following a postulated accident.
Present analyses assume that fission products released from the core exit directly to the containment.
Another uncertainty is the chemical form of the fission products released. WASH-1400 considered elemental iodine as the specie s released while recent investigations iodine may be released as a less volatile (USNRC 1981b) indicate a cesium iodine. A thorough discussion of the uncertainties in the source term is provided in a British study, SRD 256 (United Kingdom Atomic Energy Authority 1982).
Reduction of the source term as postulated by these documents would result in substantially lower estimates of detrimental health effects.
Additional uncertainties arise in the dose response model, evacuation model, and meteorological model employed by the CRAC2 code. In this present analysis, conservative reductions in evacuation speed based
"'S upon estimates of the relative probability of bad weather have been made.
Although the attempt has been made in probabilistic risk
- gg assessment studies to provide realistic state-of-the-art analysis of consequences, there remain many areas of conservatism.
7.1.4 References for Section 7.1 Alan H.
Voorhees and Associates 1980. Study Report for the Beaver Valley Power Station, Evacuation and Mass Notification.
- Bell, M.J. 1973. ORIGEN - The ORNL Isotope Generation and Depletion Code.
Commonwealth Edison Company 1981. Zion Probabilistic Safety Study.
(
Electric Power Research Institute (EPRI) 1982. ATHS: A Reappraisal, Part III.
Frequency of Anticipated Transients. EPRI-NP-2230.
National Academy of Sciences 1972.
The Effects on Populations of Exposure to T.ow Levels of Ionizing Radiation.
National Academy of Sciences 1980.
The Effects on Populations of Exposure to Low Levels of Ionizing Radiation.
i Amendment 2 7.1-31 August 1983 l
BUPS-2 ER-OLS l National Research Council 1980.
Energy in Transition 1985-2010, Final Report of the Committee on Nuclear and Alternativ? Energy Systems (CONAES), Chapter 9.
- Rose, P.S.
and Burrows, T.W.
1976. ENDF/B-IV Fission Product Decay Data.
Sandia National Laboratories 1981.
The Consequences from Liquid Fathways After a Reactor Heltdown Accident. NUREG/CR-1596.
United Kingdom Atomic Energy Authority 1982.
The Technical Basis of Spectral Source Terms for Assessing Uncertainties in Fission Product Release During Accidents in PWR's with Special Reference to Sizewall B.
SRD 256.
U.S.
Bureau of Census 1982.
Statistical Abstract of the United States: 1982-83, 103d edition.
Washington, D.C.
U.S.
Nuclear Regulatory Commission (USNRC) 1975.
Reactor Safety Study - An Assessment of Accident Risks in U.S.
Commercial Nuclear Power Plant. NUREG-75/014 (WASH-1400).
USNRC 1976.
Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Pressurited Water Reactors (PWR-GALE Code), NUREG-0017, office of Standards Development.
USNRC 1978a. Liquid Pathway Generic Study. NUREG-0440.
USNRC 1978b. Risk Assessment Review Group Report to the U.S. Nuclear Regulatory Commission. NUREG/CR-0400.
USNRC 1980.
Clarification of TMI Action Plan Requirements. NUREG-0737.
USNRC 1981a.
Final Environmental Statement Related to the operation of San Onofre Nuclear Generating Station, Units 2 and 3.
USNRC 1981b. Technical Basis for Estimating Fission Product Behavior During LWR Accidents. NUREG-0772.
USNRC 1982.
Draft Environmental Statement Related to the operation of Seabrook Station. Units 1 and 2.
USNRC 1983.
Final Environmental Statement Related to the operation of Catawba Nuclear Station, Units 1 and 2.
Westinghouse Electric Corporation 1982.
Sizewell B Probabilistic Safety Study. WCAP-9991, Revision 1.
Amendment 5 7.1-32 March 1984
BVPS-2 ER-OLS TABLE 7.1-3 j
RELEASE CATEGORY PARAMETERS Time to Release Warning Sensible Release Release
- Duration Time **
Heat Rate ***
Category (hr)
(hr)
(hr)
(cal /sec)
BV-1 2.5 1.0 1.0 1.0x108 BV-2 0.72 2.0 0.2 7.9x108 BV-3 6.0 2.0 0.5 9.8x108 BV-4 8.3 0.5 4.1 2.4x107 j
BV-5 4.3 0.5 4.1 2.3x107 i
BV-6 20.1 0.5 16.0 2.9x107 BV-7 4.5 0.5 4.0 1.0x10s BV-8 21.0 0.5 2.0 1.0x108 l
BV-9 95.0 10.0 80.0 0
i NOTES:
- Time between reactor shutdown and release to atmosphere.
E
- Time from beginning of official warning to beginning of atmospheric release.
- Due to thermal heat content of the released gases.
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Over 200 Rom Fata11ttes 1.82x10
- 2.87 92.9 5.8x10
- 2.8x10 '
BV-1 2.89x10 BV-2 7.23x10~'
5.88x10
- O.90 53.0 4.5x10
- 1.tx10 BV 3 9.55x10
8.1Gx10
- 12.7 734.0 3.Gx10 1.3x10
- 2.Gx10
- BV-4 5.21x10 '
2.83x10 '
41 9 2.350.0 7.1x10
- 55 307.0 9.2x10 3.5x10-'
BV-5 7.48x10-*
3.68x10
- BV-G 1.GGx10-*
1.62x10 '
243.0 11.230.0 7.Ox10
- 1.2x10-'
BV-7 0
8.G9x10 '
1.4 404.0 0
9.ix10-'
BV-8 0
4.43x10
- O.7 432.0 0
2.8x10-'
BV-9 O
4.Gx10-*
O.1
__ 552.0
_ O 3.7x10-'
TOTAL 2.3Gx10-*
2.OGx10-'
309.4 16.410.0 1.5x10 1.8x10 '
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BVPS-2 ER-OLS LIST OF EFFECTIVE PAGES i
Page, Table (T),
Amendment or Figure (F)
Number 8-i thru S-iii E
8.1-1 thru 8.1-3 5
T8.1-1 (1 thru 2 of 2) 5 T8.1-2 (1 of 1) 0 T8.1-3 (1 of 1) 5 T8.1-4 (1 of 1) 5 8.2-1 thru 8.2-2 5
T8.2-1 (1 of 1) 5 i
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Amendment 5 EP8-1 March 1984
i i
BVPS-2 ER-OLS 1
(
CHAPTER 8 i,
TABLE OF CONTENTS Section Title Page 8
ECON 0!!IC AND SOCIAL EFFECTS OF STATION OPERATION 8.1-1 8.1 BENEFITS 8.1-1 8.1.1 Primary Benefits 8.1-1 8.1.2 Other Social and Economic Benefits 8.1-2 l
8.1.2.1 Tax Revenues.
8.1-2 8.1.2.2 Peyrolls and Employment 8.1-2 8.1.2.3 Environmental Studies 8.1-3 l
8.1.2.4 Coal and Fuel Oil Conservation.
8.1-3 8.1.2.5 Air Quality 8.1-3 8.2 COSTS 8.2-1 8.2.1 Internal Costs 8.2-1 8.2.2 External Costs 8.2-2 l
1 l
1 l
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\\s Amendment 5 8-i March 1984
BVPS-2 ER-OLS LIST OF TABLES Table Number Title 8.1-1 Annual Benefits from BVPS-2 8.1-2 Typical E::pected BVPS-2 Ccpacity 8.1-3 BVPS-2 Generation (kWh) Forecast by Customer Class (1986-1990) 8.1-4 Projected Coal and Fuel Oil Savings by CAPCO due to Operation of BVPS-2 8.2-1 BVPS-2 Internal Costs over 40-Year Operational Life (1986 Dollars)
)
1 O
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l Amendment 5 8-iii March 1984
BVPS-2 ER-OLS fr.
CHAPTER 8 lN ECONOMIC AND SOCIAL EFFECTS OF STATION OPERATION A
8.1 BENEFITS This section describes the benefits associated with the operation of Deaver Valley Power Station - Unit 2 (BVPS-2) and supplements those benefits presented in Chapter 8 of the Environmental Report Construction Permit Stage. The costs presented in this Chapter are in 1986 dollars.
8.1.1 Primary Benefits Beaver Valley Power Station - Unit 2 is scheduled to be operational in May 1986 and will generate 833 MWe (net) of reliable base load electric power to meet the projected needs of industrial, commercial, residential, and other customers for the area served by the Central Area Power Coordination (CAPCO) group.
The ownership of the participants in BVPS-2 is as follows:
Duquesne Light Company 13.74 percent The Cleveland Electric Illuminating Company 24.47 percent f\\
Ohio Edison Company 41.88 percent
%.J l
The Toledo Edison Company 19.91 percent The BVPS-2 is intended to help supply electric energy to five major cities and their surrounding areas.
These cities are Pittsburgh, Cleveland, Akron, Youngstown, and Toledo, which have broad economic bases of business and industry.
Socioeconomic benefits are both* direct and indirect.
Direct benefits affect the owners and operators of the facility and their customers (Table 8.1-1).
Indirect benefits, often referred to as external effects, impact persons and interests in the vicinity of the proposed activity or those indirectly related to the facility. These indirect benefits, which include the expansion of business and industry, are the backbone for economic growth in an area. An important factor in this growth is an adequate supply of electric energy.
The BVPS-2 will help contribute electric energy needed to maintain economic growth in these areas.
The BVPS-2 is expected to generate approximately 4,962 million net kilowatt-hours (kWh) annually assuming an average capacity factor of approximately JS percent (Table 8.1-2).
Of the 1989-projected generation of 5,617 million kWh, approximately 1,417 million kWh will go to residential customers, 1,289 million kWh to commercial N-Amendment 5 8.1-1 March 1984
BVPS-2 ER-OLS customers, 2,637 million kWh to industrial customers, 36 million kWh to street lighting, and 237 million kWh to sales for resale and other lh uses, as shown in Table 8.1-3.
The primary benefit of the proposed plant lies in the 4,962 million kWh oer year of electricity to be delivered to customers over its 40-year operational life.
This can also be represented by an annual revenue to CAPCO of $229,786,000 in 1986, which will rise to $357,137,499 in 1987 when BVPS-2 is fully operational.
This value is based on the rate structure and fuel I clauses of each CAPCO party in effect as of mid-1983.
No sales cf steam or other products or services from the plant are anticipated.
There is also a savings in natural fuel resources-this is discussed further in Section 8.1.2.4.
8.1.2 Other Social and Economic Benefits 8.1.2.1 Tax Revenues Although tax rates levied on BVPS-2 are under the discretion of state and local authorities, certain tax revenues generated during the operation of BVPS-2 can be approximated.
There is a minimal amount of local property tax assessed on non-utility property. The Commonwealth of Pennsylvania, under the Public Utility Realty Tax Act (PURTA), levies a tax of 30 mills on certain utility property. The taxable property includes land, buildings,
- towers, smokestacks, and other structures but excludes machinery, equipment, poles, and transmission towers whether or not attached to taxable property.
This tax revenue is distributed to various local governments in the state based upon a formula established by the state.
The state will realize an estimated levelized annual PURTA l tax of $15,735,053 (in 1986 dollars).
In addition to the PURTA
- tax, Ohio and Pennsylvania vill also realize an average annual gross l receipts tax of S13,000,000 (in 1956 dollars) through taxes on the sale of electricity.
Pennsylvania and the federal government will jointly realize average annual state and federal corporate net income l tax revenue of approximately 090 million (in 1986 dollars) paid by plant owners on the sale of electricity generated by BVPS-2.
In addition to these tax revenues, the federal, state, and local governments will realize tax revenues through the collection of personal income taxes on the payroll generated in operating the plant. A discussion of these revenues followa.
8.1.2.2 Payrolls and Employment l The present worth of the payroll in 1986 dollars for the 465 operating parsennel of BVPS-2 is estimated to be approximately l $126 million (40 years).
From the cperating payroll, personal income taxes will be realized by various municipalities and the state and federal governments.
The federal income tax to be paid by the operating personnel on an annual Amendment 5 8.1-2 March 1984
BVPS-2 ER-OLS
(T basis is estimated to be $3,294,990 (in 1986 dollars) assuming 1983 I
(s_,/
rates.
State income tax paid by operating personnel is estimated to be S431,985 on an annual basis (in 1986 dollars). Local wage taxes l
to be paid by operating personnel to various municipalities are estimated at $183,768 on an annual basis (in 1986 dollars).
Total annual local,
- state, and federal taxes are $122,600,000 in 1986 dollars (Table 8.1-1).
8.1.2.3 Environmental Studies The operation of BVPS-2 will contribute to knowledge of the surrounding environment.
These contributions will result from ecological studies already completed and monitoring activities that will be conducted throughout the life of the plant.
The data from these studies will provide the scientific community with information which will enable it to predict the effect of a similar activity on the environment.
These studies are discussed in Chapters 2, 5, and 6.
8.1.2.4 Coal and Fuel Oil Conservation The operation of BVPS-2 will result in a significant savings of coal and fuel oil. As shown in Table 8.1-4, the operation of BVPS-2 will result in the savings of 1,730,500 tons of coal in 1986 and 2,603,502 tons of coal in 1987. The next four years of operation will save a total of 9,150,505 tons of coal. The operation of BVPS-2 will also I)
save 4,153,200 gallons of fuel oil in 1986, 1,607,100 gallons in
(__/
- 1987, and 6,615,200 gallons during the years 1988 through 1991. The dollar savings of coal and fuel oil associated with the on-schedule operation of BVPS-2 is estimated to be $189 million (in 1986 dollars) for the years 1986 through 1989.
8.1.2.5 Air Quality The on-schedule operation of BVPS-2 will result in less coal and fuel oil burned by CAPCO utilities, thus precluding the emission of air pollutants associated with burning coal and oil. The quantities of I
sulfur dioxide, nitrogen oxides, particulate matter, carbon monoxide, and non-methane hydrocarbon emissions due to a delay of BVPS-2 operation for 1986 are shown in Table 8.1-1.
,a 4
\\_ /
Amendment 5 8.1-3 March 1984
BVPS-2 ER-OLS TABLE 8.1-1 b
ANNUAL BENEFITS FROM BVPS-2 Direct Benefits Expected average annual generation * (kWh/yr) 4,962x10s Capacity (kwe) 833x103 i
Proportional distribution of electrical energy expected (kWh/yr for 1989)
Industrial 2,637x10s Commercial 1,289x10s Residential 1,417x10s Other 273x10s Expected average annual steam sold from the facility 0
Expected average annual delivery of other beneficial products O
Revenues ** from delivered benefits Electrical energy generated (1987)
$357,000,000 Steam sold 0
(,,,
other products 0
Indirect Benefits Annual taxes **
j State PURTA, gross receipts tax
$ 28,735,000 State, federal income tax 90,000,000 State personal income tax 432,000 Federal personal income tax 3,295,000 Local wage tax 184,000 Research Past and present environmental studies Environmental enhancement Recreation None Navigation None.
Air quality (savings in emissions, May 1986-December 1986, tons)
SO 5,300 2
No 13,066 Particulates 525 others:
CO 402 l
HC 47
\\j Amendment 5 1 of 2 March 1984
l t
BVPS-2 ER-OLS 1
TABLE 8.1-1 (Cont)
Indirect Benefits (Cont)
Environmental monitoring Meteorological, ecological, radiological Savings of coal (tons /yr) 2.4x106 Savings of fuel oil *** (gal /yr) 2.5x105 Operating employment (number of employees) 465 NOTES:
- Based on 68.0 percent plant capacity factor.
- 1986 dollars.
- Represents increased running of peaking units if BVPS-2 is not in service for the first 3 years.
The annual savings equals the total savings for 1986 through 1989 divided by the 3 years of delay.
O Amendment 5 2 of 2 March 1984
BVPS-2 ER-OLS TABLE 8.1-2 TYPICAL EXPECTED BVPS-2 CAPACITY Annual Average NSSS rating - MWt 2,652 Maximum net capacity (MNC) - MWe 833 Plant capacity factor (PCF) - percent 68*
Annual plant net production - million kWh 4,962 (MNC x PCF x hrs / year)
NOTE:
- Typical average plant capacity factor for plant lifetime.
O O
1.f 1
BVPS-2 ER-OLS TABLE 8.1-3 DVPS-2 GENERAT ION ( kWh) FORECAST BY CUSTOMER CLASS (1986-1990) 13Lslome r C I a s s 1983 198J DCJ D32 1220 Residential 884,601,880 1,368,298,400 1,030.041,400 1,416,874,600 1,153,552,400 Comme rc i a l 795,401,340 1,235,260,260 934,762,210 1,289,406,400 1,052,687,900 fudustrial 1,614,127,300 2,5i1,154,100 1,912,774,700 2,637,112,000 2,138,932,500 Street lighting 23,777,725 36,311,395 26,913,752 36,270,070 29,332,719 Other 38,457,013 60,125,947 45,897,810 63.848,114 52,757,992 Sales for resale
__101 61L180 163J49.880 124.610.170
_173.254.150 142.736.400 Total gene ra t i on 3,461,000,000 5.375,000,000 4,075,000,000 5,617,000,000 4,570,000,000 March 1984
- or 1 Amendment 5 O
O O
BVPS-2 ER-OLS TABLE 8.1-4 PROJECTED COAL AND FUEL OIL SAVINGS BY CAPCO DUE TO OPERATION OF BVPS-2 Coal Fuel Oil Year (Tons)
(Gallons) 1986 1,730,500 4,153,200 1987 2,603,502 1,607,100 1988 1,988,600 1,222,500 1989 2,628,756 1,685,100 1990 2,296.425 1,828,000 1991 2,236,724
_1,879,600 Total 13,484,507 12,375,500 O
o d
Amendment 5 1 of 1 M weh 1984
BVPS-2 ER-OLS TABLE 8.2-1
)
BVPS-2 INTERNAL COSTS OVER 40-YEAR OPERATIONAL LIFE (1986 DOLLARS)
Description Cost 4
Plant cost
$3,076,000,000 l
Fuel 772,763,000 i
Operation and maintenance 939,292,000 i
1 USNRC fees for Construction Permit 1,069,000 USNRC fees for Operating License 1,024,500 USNRC annual operating fees 2,800,000 Decommissioning 65,800,000 Total
$4,859,000,000 l
O 4
i
(,/
Amendmcnt 5 1 of 1 March 1984
BVPS-2 ER-OLS I
i NRC LETTER DATED MAY 4, 1983 l
LIST OF EFFECTIVE PAGES Page, Table (T),
Amendment or Figure (F)
Number Index (1 thru 4 of 4) 1 QE100.1-1 1
TE100.1-1 (1 thru 2 of 4) 1 2
TE100.1-1 (3 thru 4 of 4) 4 QE240.01-1 1
QE240.02-1 1
QE240.03-1 1
QE240.04-1 1
QE240.05-1 1
QE290.1-1 1
O QE290.2-1 1
QE290.3-1 1
QE290.4-1 1
QE291.1-1 3
QE291.1-2 3
QE291.2-1 1
QE291.3-1 1
QE291.4-1 1
QE291.5-1 2
QE291.6-1 2
QE291.7-1 1
QE291.8-1 5
QE291.9-1 1
QE291.10-1 1
QE291.11-1 1
QE291.12-1 1
QE291.13-1 1
QE291.14-1 1
QE291.15-1 thru QE291.15-2 2
QE291.15-3 1
TE291.15-1 1
QE291.16-1 1
QE291.17-1 thru QE291.17-2 1
Amendment 5 EPQ1-1 March 1984
\\
BVPS-3 ER-OLS LIST OF EFFECTIVE PAGES (Cont)
Page. Table (T),
Amendment or Figure (F)
Number QE291.18-1 1
TE291.18-1 (1 thru 4 of 4) 1 QE291.19-1 1
i l
QE291.20-1 1
QE291.21-1 1
PE291.22-1 1
QE291.23-1 1
QE291.24-1 1
QE291.25-1 1
QE291.26-1 1
QE291.27-1 1
QE291.28-1 1
QE291.29-1 2
QE291.30-1 2
QE291.31-1 1
?E320.1-1 thru QE320.1-2 3
TE320.1-1 3
TE320.1-2 3
TE320.1-3 3
TE320.1-4 3
QE451.1-1 thru QE451.1-2 1
QE451.2-1 1
QE451.3-1 1
(
QE470.1-1 1
l QE470.2-1 1
QE470.3-1 thru QE470.3-2 1
i l
QE470.4'1 1
l l
l l
Amendment -e EPQ 1-2 February 1984 0
~..
4 BVPS-2 ER-OLS i
NRC Letter: May 4, 1983 1
i Question E291.7 (ER Section 2.4,2) i Indicate the surface area (in hectares or acres) of the New Cumberland Pool. Also, indicate the surface area of the river from the BVPS site to an 80 km (50 mi) distarice downstream.
(Note: Assume i
j normal pool elevations.)
Responses t
i The following estimates of river surface area were provided by the l
U.S. Army Corps of Engineers and are based on normal pool elevations:
Surfa Area River Section River Miles (ac.es) 4 l
New Cumberland Peol 31.7 to 54.4 2,840 1
Pike Island Pool 54.4 to 84.3 5,140 Hannibal Pool 84.3 to 126.4 6,650 Shippingport (BVPS site) to 35.0 to 84.3 8,420 Pike Island Dam (total = 49.3 mi)
(approximately 50 ml 7'
downstream of BVPS)
Reference:
i i
f U.S Army Corps of Engineers 1983.
Personal communications between G. Armocida, U.S. Army Corps of Engineers, and D. Knowles, Stone &
Webster Er,gineering Corporation, May 18 and May 19, 1983.
i I
4 f
1 l
Amendment 1 QE291.7-1 July 1983 i
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BVPS-2 ER-OLS NRC Letter: !!ay 4,1983 O
Question E291.8 (ER Section 3.4.2.7)
Indicate the experience, during BVPS Unit 1 operation, with regard to required frequency of dredging at the intake.
E
Response
An Operation Surveillance Test (OST) procedure " Silt Check" had been used ut BVPS-1 since it began operation. This procedure required a quarterly check of silt buildup on the inside of the main intake structure.
If the ritt buildup exceeded the limits in the OST, the silt buildup was removed. Trending of this quarterly data was used to develop a test procedure, " Silt Check-tiain Intake Structure" to replace the OST procedure.
This test procedure, effective tiarch 1983, requires a semi-annual check of silt buildup on the inside of the. main intake structure. Recent BVPS-1 operating experience has shown that silt has been removed from inside the main intake structure once per year.
When abnormal buildup is observed, soundings are taken in front of the intake structure to determine the need for dredging.
Silt buildup has been removed from in ftont of the main intake structure only once: in August 1981.
O i
Amendment 5 QE291.8-1 tiarch 1984
BVPS-2 ER-OLS NRC LETTER DATED
(' 'g)
OCTOBER 20, 1983
/
LIST OF EFFECTIVE PAGES Page, Table (T),
Amendment or Figure (F)
_ti,umbe r INDEX (1 thru 2 of 2) 4 QE291.32-1 4
QE291.33-1 thru QE291.33-2 4
i TE291.33-1 (1 of 1) 4 I
l QE310.1-1 4
)
QE31J.2-1 4
QE310.3-1 thru QE310.3-2 4
QE310,4-1 4
QE310.5-1 4
QE310.6-1 4
TE310.6-1 (1 thru 2 of 2) 4 Ql310.7-1 4
p
QE310.8-1 4
(
QE310.9-1 4
QE310.10-1 4
QE451.4-1 thru QE451.4-4 4
TE451.4-1 (1 of 1) 4 TE451.4-2 (1 of 1) 4 TE451.4-3 (1 of 1) 4 TE451.4-4 (1 of 1) 4 FE451.4-1 4
QE451.5-1 thru QE451.5-2 5
TE451.5-1 (1 of 1) 5 TE451.5-2 (1 of 1) 5 QE451.6-1 4
QE451.7-1 4
QE460.1-1 4
QE460.2-1 4
l l
(~'/
T g,
Amendment 5 EPQ2-1 March 1984 l
l
BVPS-2 ER-OLS
/N NRC Letter: October 20, 1983 s-Question E451.5 (ER Section 2.3)
In the assesssment of long-term (routine) diffusion estimates (which is cross referenced to FSAR Section 2.3.5),
a methodology is described.
Relestes from the process vent, attached to the Beaver Valley Power Station Unit 1 natural draft ccoling tower, are considered to be totally elevated.
According to staff review of effluents expected to be emitted from this process vent, radioiodines will be released. The diffusion models are based on the assumption that all radioactive material is in gaseous form.
Provide a transport and deposition assessment of radioiodines captured by the cooling tower drift.
Response
An assessment of the quantity of radiciodines that may be captured by the cooling tewer drift and its subsequent transport and deposition has been performed.
This assessment leads to the conclusion that less than 0.1 percent of radioiodines leaving the process vent will be captured by drift and that the FSAR analysis of relative deposition (Section 2.3.5) due to gaseous emissions from the process
[ \\
vent is
- n. ore conservative than that of drift deposition of
\\~-
radioiodines. The details of this assessment are discussed below.
The amount of radioiodines that may be captured by cooling tower drift is proportional to the ratio of the drift volume to exit air volume leaving the tower. Based ori e drift loss percentage of 0.05 of the circulating water flow and an exit air volume of approximately 35 x 106 cfr at the design condition, this volume ratio is less than 1 x 10 6 Due to the turbulent flow characteristic of the cooling tower / process vent system interface, the contact time between the radiciodines and the drift droplets is unfavorable for sustaining a radioiodine-drift water reaction. Therefore, the maximum amount of
~
radioiodines leaving the process vent and becoming suspended in the drift droplets is estimated to be less than 0.1 percent of the total iodine released from this vent.
It is assumed that once iodine becomes associated with a drift droplet, it will remain with the dr?plet throughout its flight path.
In order to assess the transport and deposition of the very small amount of radiciodines that may be captured by the drift, the results of the existing salt drif t modeling analysis (En Section 3.6.9) were adapated to produce values of normalized deposition rate (D/Q) similar to those in FSAR Tables 2.3-53 and 2.3-54.
This was done by dividing the predicated salt depositon amounts by the quantity of solids leaving the cooling tower in the drift. The solids emission rate was determined from the drift rate (0.05 percent of the
/T N-Y Amendment 5 QE451.5-1 March 1984
BVPS-2 ER-OLS circulating water flow),
the circulating water flow rate (507,400 gpm), and the concentration of dissolved solids in the water (412 ppm).
This yields an emission rate of 45S,278 lbs of salt per year which can be used to transform salt deposition (lbs/ acre / year) to values of D/Q (M 2).
These D/Q values are indicative of how drif t is transported and dispersed without considering the actual amount of radiciodines being emitted from the vent and captured by drift.
The results of this dispersion analysis are presented in Tables E451.5-1 and 2 which give the highest D/Q values for both the annual-average and grazing season periods in each sector for the individual receptors (vegetable garden, milk cow, milk goat, meat
- animal, and residents),
at the site boundary, and at the 10 radial population distances.
These tables can be compared directly to FEAR Tables 2.3-53 and 54 which provide D/Q values for gaseous emissiens from the process vent in the absence of cooling tower drift.
Although two different meteorological data periods were used to generate these tables (1976 for drift D/Q values and 1976-1980 for gaseous D/Q values),
year to year variation in meteorological parameters should not significantly affect the comparison of the magnitudes of the D/Q values.
The analysis indicates that the magnitude af drif t dicpersion is somewhat sinilar to gaseous dispersion as evidenced by the similarity of the two sets of D/Q values. The highest annual drift D/Q value is 3.75 x 10 9 M2 compared with a gaseous D/Q value of 1.10 x 10 s M 2, The major differences between the two kinds of D/Q values lie in their spatial distribution. The drift D/Q values at the closest set of distances (site boundary) are generally much smaller than the gaseous D/Q values.
Although the different meteorological data periods may be responsible in part for the smaller drift D/Q values, the larger plume rise of the warm, buoyant cooling tower effluent, which ca ries the drift well above the top of the cooling tower ber;re it tegins to fall to the ground, most likely accounts for most of these dif ferences.,Although drift D/Q values are higher than the gaseous D/Q valaes by small amounts, the maximum drift D/Q value for each set of distances is always less than the gaseous D/Q value (except for grazing season value at 2.412 m).
Tnis fact, combined with the low percentage
(<0.1 percent) of entrained iodine in the drift, leads to the conclusion that the FSAR analysis of relative depcsition (Section 2.3.5) due to gaseous emissions from the process vent is more conservative than an assessment of drift deposition of radiciodines.
knendment 5 QE451.5-2 March 1984 s
BVPS-2 ER-OLS NRC Letter: October 20, 1983
(~'
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Question E451.6 (ER Section 2.3)
One complete year (8,760 hours0.0088 days <br />0.211 hours <br />0.00126 weeks <br />2.8918e-4 months <br />) of consecutive hourly meteorological data (i.e., no missing data) is used by the staff in evaluating the environmental impact of postulated accidents through a probabilistic risk assessment (PRA) using a version of the computer code CRAC Calculation of Reactor Accident Consequence (CRAC).
Data recovery for each annual period of record is less than 100 percent, requiring that data be substituted to enable the staff to perform the PRA.
For the one-year data set considered to be most representative of meteorological conditions in the vicinity of the Beaver Valley site, provide substituted data for all missing periods for wind speed, wind direction, atmospheric stability, and precipitation.
Provide the basis for selection of the one-year period, identify the source of substituted data, and provide a brief description of the bases for selecting substituted data. The data set selected for the FRA should be encoded on a magnetic tape as described in the enclosed guidance.
Response
one complete year (8,760 hours0.0088 days <br />0.211 hours <br />0.00126 weeks <br />2.8918e-4 months <br />) of consecutive hourly meteorological data for the BVPS site in NRC format for use in the computer code CRAC will be provided under separate cover. The 1-year perio.d of (s_,T January 1, 1979 through December 31, 1979 was chosen for this purpose
)
since this calendar year displayed the highest data recovery percentage (93.1 percent) from among the fi've years of data (1976-1980).
The factors in determining the method of data substitution are threefold. First, an analysis of the missing periods of wind speed, wind direction, and atmospheric stability indicate that the majority of outages are 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or less in duration.
Second, missing data periods of upper level data often coincide with those of the lower level data, making this possible method of substitutions sporadic.
- Third, the influence of the valley / ridge terrain characteristic of the BVPS cite area on low-level (35-ft) wind data along with the large difference in height increment between the 150-35 ft AT and the 500-35 ft AT cast significant doubt on the validity of substituting upper level (150- and 500-ft) data for lcw-level data.
Therefore, to be consistent and preserve the rep re sen' ivenes s of the low-level data, the substitution of data for missing hours was done by inserting the previous good hour of data, i.e.,
persistance.
This method best maintains the validity of the data.
The onsite precipitation data for the January 1979 to December 1979 period has a data recovery percentage of 93 percent.
The missing hours of data have been replaced with the corresponding hourly precipitation amounts from observations at the Greater Pittsburgh Airport.
O Amendment 4 QE451.6-1 February 1984
DVP5-2 ER-OLS flRC Letter: October 20, 1983 Question E451.7 (ER Section 2.3)
Section 2.3.6 of the ER provides a qualitative description of air quality in the vicinity of the site and states that these conditions will not " adversely affect station operation." Describe station sources of criteria air pollutants, including estimated emissions, and compare these emissions to the Dellinimus criteria established by the Environmental Protection Agency.
If station emissions are in excess of the impact of De!!inimus levels, provide a quantitative assessment of the station emissions on local air quality using current EPA guidelines on atmospheric depression modeling.
Response
Station sources of criteria air pollutants along with their respective estimated emissions are described in Section 3.7.2.
The applicable EPA requirement for a Prevention of Significant
.')eterioration (PSD) analysis (40 CFR 52.21) is a new source with potential to emit more than 250 tons per year of any criteria pollutant. As indicated in Table 3.7-1, Amendment 4,
none of the station sources exceed this 250-tons-per-year criterion, therefore the Deliinimis levels are not applicable.
O Amendment 4 QE451.7-1 February 1984
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BVPS-2 ER-OLS TABLE E451.5-2 GRAZING S13 SON AVER 4GE D/Q VALUES (x 10-' M-') FOR COOLING TOWER DRIFT individual Receptors Population Distances (meters)
Downwind Site veg.
Milk Milk Meat Rest-Sector Boundary Garden Cow Goat C 4,a1 dence 805 2.412 4.023 5.633 7.242 12.070 24.140 40.230 56.330 72.420 N
1.06
.440 0.543 1.09 i.45 1.03
.528 0.257 0.149 <.126 c.126
<.12G
<.126 c.126 NNE O.190 1.53
.400 1.50 1.55 1.18 1.53 0.943 0.540 0.355 <.328
<.328
<.328
<.328
<.328 NE 1.85
.495 489 0.495 1.28 1.51 2.97 1.75 0.992 0.537 <.489
.489 c.489
<.489
<.489 ENE 4.71
.529 4.71 2.56 3.29 1.76 1.54 0.476 <.383
<.386
<.386
<.386
<.386 E
O.443 4.94
.628 2.04 2.04 4.94 3.63 4.07 2.17 1.08 O.612 <.494
<.494
<.494
<.494
<.494 ESE 1.30 3.20 1.89 3.20 3.25 1.94 2.28 1.23 0.626 0.348 <.292
<.292
<.292
<.292
<.292 SE 1.24 1.95
.327.327 1.09 1.95 1.24 1.54 0.846 0.382 0.228 <.188
<.188 c.188
<.188
<.188 SSE 1.48 1.40
.442.171 1.38 1.51 1.33 1.12 0.636 0.384 0.190 <.171
<.171
<.171
<.171
<.171 S
2.16 1.21 1.10 1.74 1.78 1.71 1.78 0.856 0.507 0.329 <.264
<.264
<.264
<.264
<.264 SSW 1.44 0.835
.478.206 0.835 1.22 1.38 0.860 0.371 0.265 0.135 <.129
<.129
<.129
<.129
<.129 LW 1.73 1.27
.922 1.19 1.27
.986 1.27 0.594 0.264 0.136 <.129
<.129
<.120
<.129
<.129 WSW 1.58 1.53
.464 1.40 1.53 1.85 1.53 0.772 0.395 0.193 <.178 c.178
<.178
<.178
.178 W
2.24 1.23
.653 1.04 1.23 2.00 2.42 1.11 0.494 0.234 <.216
<.216
<.216
<.216
<.216 WNW 1.34 0.628
.421.110 0.628 0.628 1.88 1.22 0.516 0.304 0.121 <.110
<.110 c.110
<.110
<.110 NW 1.9S
.148 0.570 1.98 1.21 1.29 0.654 0.283 0.161 <.149
<.149
<.149
<.149
<.149 NNW O.328
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<.034
<.034
<.034
(.034 Amendment 5 1 of 1 March 1984 O
O O
e BVPS-2 ER-OLS IIRC LETIER DATED DECE!!BER 2,1983 LIST OF EFFECTIVE PAGES Page, Table (T),
Amendment or Figure (F) flumber I!JDEX (1 of 1) 5 QE450.1-1 thru QE450.1-4 5
QE450.2-1 5
[
O n
4 Amendment 5 EPQ3-1
?! arch 1984 G.
l
1 l
BVPS-2 ER-OLS i
J 9
NRC QUESTIONS AND RESPONSE INDEX l
BEAVER VALLEY POWER STATION - UNIT 2
]
EINIRONMENTAL REPORT - OPERATING LICENSE STAGE DOCKET No. 50-412 DECE!!BER 2,1983 ER-OLS l
!!RC QUESTION SECTION KEYWORDS l
E450.1 7.1 Fatality and cancer from risk estimates and economic impact from damage to BVPS-2 I
E450.2 7A.2 Basis for assumption of supportive medical treatment in severe I
accielent analysis i
t 4
O i
4 l
I a
i 4
a 1 of 1 l
~..... -
BVPS-2 ER-OLS NRC Letter: December 2, 1983 b
Question E450.1 While you have tried to follow the staff's approach to and the structure of presentation of the results of such analyses in several DES / FESS persuant to the Statement of Interim Policy (Federal Register, June 13, 1983),
a.
Your use of the population data for the year 1980, instead of the data for the plant mid-life year, is consistent with the sta f f's practice.
Please provide basis for your selection of this populatica data; and b.
Information regarding the following items are ab'sent in ER-OL:
1.
Risk estimates to an individual of early fatality as a function of distance or as isepleths, ii. Probability distribution and risk estimates of thrynid cancer fatalities, I
i iii. Estimated person-rem and cancer fatalities (excluding thyroid, and thyroid only) CCDFs and risks within the 50-mi region, l
iv.
Estimated distributions of number of persons exposed l
above 25 rems to whole-body, 300 rems to thyroid, and 200 rems to total bone marrou from early exposure, and v.
Estimated economic cost of damage to the plant.
f Either provide this information, or a justification why such infor-mation is unnecessary in support of your Environmental Report.
Response
a.
The results of the severe accident analysis for BVPS-2 provided in Section 7.1.3.2 has been revised. The analysis is now based upon the projected populatica distribution for the year 2010. Refer to Section 7.1, Amendment 5.
b.
(i)
CRAC2 calculations for the BVPS-2 plant and site indicate that the risk of fatality due to early exposure within the 10-mi b emergency planning zone (EPZ) are quite limited.
Only those people living within 1.5 miles of the plant are predicted to be at risk of early fatality with mean risk to the entire population of approximately 3.8 x 10-7 per reactor-year. The individual risk of early fatality ranges O
Amendment 5 QE450.1-1 March 1984
BVPS-2 ER-OLS from approximately 1.5 x 10-13 per reactor-year to 5.9 x
10-S per reactor-year in the populated land elements.
Approximately 40 percent of the 48 land elements within 1.5 miles are unpopulated. Because of the extremely low fatality risk and the limited area irvolved, the plotting of early fatality isopleths would not provide significant additional information, b.
(ii)
The risk curve for thyroid cancer is provided on Figure 7.1-5, Amendment 5.
b.
(iii) Generation of risk curves for the population within 50 miles of BVPS-2 requires an additional set of CRAC runs. The additional information gained by performing these analyses does not warrant the additional effort required.
However, without performing additional analyses, some estimates of risk within 50 miles are possible.
Detailed output for latent cancer fatalities as a function of location due to early exposure was avail-able in numerical form from the CRAC2 analyses. These results indicate that the ratio of latent cancer fatalities within 50 miles to that within 350 miles is approximately 0.65.
The populatien within 50 miles of the plant, therefore, assumes about 65 percent of the total latent cancer fatality risk due to early exposure.
Assuming that the latent cancer fatalities due to chronic exposure are spatially distributed approximately the same as the population, then the apportionment of this cancer fatality risk between the pcpulation within 50 miles and the total population can be estimated. The ratio of the pcpulations is:
P (0-50 mi) 3,950,000 = 0.04
=
P (0-350 mi) 94,971,000 The mean valua for the latent cancer fatalities due to early exposure (for the total population) is 1.86 x 10-3 per reactor-year, while the mean value for latent cancer fatality due to chronic exposure is 1.85 x 10-2 per reactor-year.
The estimated cancer risk (early and chronic) within 50 miles is 0.65(1.36x10-3) +
0.04(1.85x10-2) = 1.95x10-3 per reactor-year.
The total cancer fatality risk mean value for the population within 350 miles is 2.0 a 10-2 per reactor year.
Therefore, the cancer risk assumed by the population within 50 miles of the plant is approxi-mately 10 percent of the total cancer risk. A similar relationship would hola for the distribution of population total body man-Rem between the population Amendment 5 QE450.1-2 March 1984
PVPS-2 ER-OLS within 50 miles of BVPS-2 and the total population x
1 within 350 miles.
v b.
(iv)
The CCDF for population with bone marrow dose greater than 200 Rem is shown on Figure 7.1-6, Amendment 5.
Producing risk curves for population with whole body dose above 25 Rem and population with thyroid dose above 300 Rem requires separate CRAC2 calcr.3ations with the present version of the code.
The value of the information gained by performing these analyses does not warrant the additional effort required.
The results for the population with bone marrow dose greater than 200 Rem can be used as an indication of the order of magnitede of the least number of people to receive 300 Rem thyroid dose or 25 Rem whole body dose.
b.
(v)
The aconomic cost of damaces to the plant would be
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associated with decontamination, repair or replacement of the plant, and replacement power. Although no detailed methodology has been developed to estimate the contribution of an accident to the economic risk to the licensee for decontamination and restoration cf
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the plant, experience in these areas is being gained
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as cleanup of Three Mile Island Unit 2 continues.
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The economic penalty associated with an accident l
occuring during the first year of operation of BVPS-2 can be estimated at $1,600 million, in time-of-expenditure
- Jollars, for decontamination and restoration (Comptroller General of the United
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States 1981).
l l
In addition, during each restoration year, the utility l
will need to purchase replacement power for the dam-l
)
aged unit. This cost is estimated to be approximately
$575 million, in 1986 dollars, assuming the plant would be shut down for eight years and that the energy which would have been produced by BVPS-2 (assuming a 67-percent average capacity factor) would be replaced largely by coal-fired generation within the CAPCO grid.
This -est is bt;ed, in part (1987-1991), on production cost savings data previously provided in response to NRC question E320.1 of the BVPS-2 Environ-mental Report, Amendment 3.
These projected cost savings were subsequently estimated for the years 1992-1994 to provide E years of data for prediction of power replacement costs.
The estimated CAPCO produc-tion cost savings for the years 1992, 1993, and 1994 were SES million,
$66 million, a-d $65 million, in 1986 dollars, respectively.
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Amendment 5 QE450.1-3 March 1984 i
BVPS-2 ER-OLS j,
If the probability of sustaining a total loss of the plant is assumed equal to the sum of the probabilities of the occurence of core-melt accidents, there would be approximately 5.1 chances in 100,000 that a dis-abling accident would occur during each year of service life of BVPS-2.
Multiplying the previously estimated cost of $2,175 million for an accident at BVPS-2 during the initial year of its cperation by the 5.1 x 10-5 probability results in an economic risk of
$111,000 applicable to BVPS-2 during that year.
The economic risk in subsequent years is assumed to be the same with the effects of inflation on restoration and cleantip costs approximately offset by the effects of plant depreciation and reduced capacity.
Reference:
Comptroller General of the United States 1981.
" Report to the Congress," EMD-81-106, Washington, DC, August 26, 1981.
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BVPS-2 ER-OLS NRC Letter: December 2, 1983 q
Question E450.2 As stated in Section 7A.2, the estimates of early fatalities in ER-OL were made with the assumption of supportive medical treatment.
Please discuss this basis for this assumption, including the availability of such medical treatment to all persons requiring the treatment subsequent to acute radiological exposure resulting from severe accidents in the BVPS-2 reactor.
Re sporase :
The CCDF for population having bone marrcw doses in cxcess of 200 Rem indicates that the frequency of exceeding the capacity of supportive treatment facilities (2,500-5,000 beds, WASH-1400) is very small (about 7 out of one hundred million per year of reactor operation).
This frequency is, in effect, an estimate of the probability of having underpredicted the number of early fatalities by using the supportive medical treatment dose response function.
Inherent in the consequetu analysis performed for SVPS-2 is the assumption of a 10-mile sheltering distance.
Increasing the sheltering distance to 25 miles would tunher reduce the likelihood of exceeding the capacity of treatment facilities.
ry p)
Amendment 5 QE450.2-1 March 1984 y