Text

Provides Suppl to Request for Change to TSs Re Radiological Dose Assessment Methodology
	ML18102A211
Person / Time
Site:	Salem
Issue date:	06/24/1996
From:	Dawn Powell; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LR-N96178, NUDOCS 9606280185
	Download: ML18102A211 (42)
	v • d • e

~1 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUN 2 41996 LR-N96178 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENT TO REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS RADIOLOGICAL DOSE ASSESSMENT METHODOLOGY SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS.

50~272 AND 50-311 Gentlemen:

I This supplement is being submitted to request review and approval of a revised dose asse~sment methodology to be used for Public Service Electric & Gas Company's (PSE&G) Salem Generating Station Units 1 and 2.

As outlined in a recently submitted request for a Technical Specification change (ref. letter LR-N96154, dated June 10, 1996), PSE&G is in the process of upgrading the Control Room ventilation system at Salem and has taken the opportunity to assess the previously licensed methodology against more recent methods developed in the industry.

As a result, PSE&G determined that a revised calculational methodology that is more representative of postulated post-accident doses was warranted.

In support of the Control Room ventilation modification, PSE&G has utilized a computer code, ARCON95, which is described in NUREG/CR-6331, Atmospheric Relative Concentrations in Building Wakes.

ARCON95 methodology has been used for the calculation of atmospheric dispersion factors, (X/Q's), for various accidents and release points relative to the Salem Control Room air intake structures.

The applicable dispersion factors were then used in dose assessment calculations for the Control Room to determine compliance to General Design Criteria 19. provides more details on the revised methodology and assessment results for the design basis Control Room doses.

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95-2168 REV. 6/94

t Document Control Desk LR-N96178 2

JUN 2 4 1996 Revised doses at the Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) are not included as part of this submittal since these doses are not relevant to the Control Room dose assessment and the updated methodology used, ARCON95, was not applied in revising these values.

Should PSE&G commit to methodologies other than that currently approved for determining EAB and LPZ doses, such as that presented in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants, and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, a separate submittal will be made.

If any further information pertaining to this supplement is needed, please call.

Attachment Sincerely,

!/),/?.~

D. R. Powell Manager -

Licensing and Regulation C

Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager -

Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625

~------------------------------

LR-N96178

REVISED DOSE ASSESSMENT METHODOLOGY The exposure to Salem Generating Station (SGS) Control Room personnel following a radiological accident is dependent on the isotopic mix and concentration at the outside air intakes as well as the filtering and isolation capabilities of the HVAC system.

The isotopic concentration at the air intakes is a function of the dispersion which takes place during transport of the effluent from the potential release points to the intakes and the type and magnitude of radionuclides released, (e.g. source term).

In support of the modifications to the Control Room ventilation system, analyses were performed to determine the design basis dispersion factors, x/Q's, at the Unit 1 and Unit 2 air intakes.

Various accident scenarios were analyzed as well as release points.

Using the calculated x/Q, a revised dose analysis was performed for the design bases accident.

This analysis included the use of thyroid dose conversion factors (DCFs) found in the International Commission on Radiation Protection's (ICRP)

Standard ICRP30.

Details of this revised methodology are provided in the following discussion.

CONTROL ROOM DOSE ASSESSMENT Release Points and Accident Scenarios Calculations of x/Q at the Control Room intakes were made for potential release points from Salem Units 1 and 2 and from the Hope Creek Generating Station (HCGS) located within the same protected area.

The release points included are:

the main plant vents, inboard main steamline safety valve vents, Penetration Area pressure relief panels, Penetration Area smoke hatches, Unit 1 and 2 Containments, the HCGS Filtration Recirculation and Ventilation System (FRVS) vent and the HCGS main steam blowout panel.

Figure 1 provides the location of the postulated Salem release points as well the proximity to the Control Room air intakes or receptors.

These intakes are located directly adjacent to their respective Containment structure 31' above the plant grade.

Figure 2 provides an overview plan showing the relationship of the Hope Creek Generating Station to the SGS Control Room air intakes.

The roofs of the SGS Turbine, Service and Auxiliary Buildings create a flat, continuous surface at a height of 40' above grade between, and to the east of, the Containment buildings.

1

LR-N96178 Mechanical equipment on the roof of the Turbine building provides scattered obstructions to a height of 30' above the roof.

For the purposes of dispersion modeling and consideration of building wake effects, only the portion of the Containment structures projecting above this 40' continuous plane are used to define the building wake zone or "cavity."

The main plant vent releases from both Salem and Hope Creek occur in a horizontal direction at the top of the Containment domes.

These vents were modeled as "capped" vent releases due to their horizontal orientation.

All other release points are at elevations significantly below the level of the containment structures, in what is known as the building wake cavity.

These releases are also horizontal with the exception of the main steam safety valve discharges.

All horizontal releases were modeled as ground-level releases at their actual heights above the plant grade.

The main steam safety valve releases were also modeled as ground releases, but the release height was adjusted to account for plume rise.

The accident scenarios modeled include:

1.

SGS Loss of Non-Emergency AC Power

2.

SGS Steam Generator Tube Rupture -

One Faulted Steam Generator

3.

SGS Steam Generator Tube Rupture - Three Intact Steam Generators

4.

SGS Control Rod Ejection

5.

SGS Main Steam Line Break -

One Faulted Steam Generator

6.

SGS Main Steam Line Break - Three Intact Steam Generators

7.

SGS Reactor Coolant Pump Locked Rotor

8.

SGS Loss of Coolant Accident*

9.

SGS Process Line Break Release from Smoke Hatch

10.

Hope Creek Radiological Accidents from FRVS

11.

Hope Creek Main Steam Line Break Blowout Panel

Includes Fuel Handling Accident Effluent flow rates vary considerably during the course of some accident scenarios.

Because ARCON95 is a steady-state, continuous release model, it was necessary in some instances to combine the results from different computer runs to model the applicable scenario.

A total of 72 combinations of sources, receptors and flow rates were calculated and are included in Table 1.

The resulting x/Q values from each run for the 0-2 hr, 2-8 hr, 8-24 hr, 1-4 day and 4-30 day periods following the accident were derived and are listed in Table 2.

Then the appropriate x/Q values for each time period were selected to represent the duration of each accident scenario.

The selected 2

LR-N96178 x/Q values, along with descriptions of the scenarios are presented in Table 3.

An example of the relationship between the values presented in Table 2 and 3 is shown in the first accident scenario on the Loss of Non-Emergency AC Power.

During the first two hours of the accident, the effluent release rate was 77.37 m3 /sec, divided among four main steam safety valves.

This combination was modeled in Run 1.

During the period 2-32 hours following the accident, the flow rate was 21.28 m3 /sec, was also divided among four main steam safety valves, and was modeled in Run 5.

In situations such as this where the flow rate was undetermined for the remainder of the accident, the last flow rate was used for the duration.

Therefore, when the Loss of Non-Emergency AC Power scenario was assembled in Table 3, the x/Q value for the 0-2 hour period was obtained from Run 1 and the x/Q values for the remaining time periods were obtained from Run 5.

Methodology PSE&G determined that the previously used methodology was too simplistic in comparison to the more recently developed methods of calculating x/Q values at receptors located on or near onsite buildings and structures.

Dispersion in the vicinity of such structures is dominated by complex flow patterns generated by the buildings and structures themselves rather than by natural turbulence.

To address these complexities and better model the dispersion, PSE&G decided to use the NRC sponsored model known as ARCON95, published as NUREG/CR-6331, Atmospheric Relative Concentrations in Building Wakes, (April 1, 1995 version).

The ARCON95 model is a straight-line Gaussian dispersion model which has been adapted to model close-in receptors within the building wakes at nuclear power facilities.

ARCON95 also has the capability to handle dispersion under low wind speeds and within building wakes.

In addition, the model has the capability to use hourly meteorological data to directly calculate the 95th percentile dispersion values on a wind direction dependent basis.

Specific details on the model can be found in the NRC issued NUREG/CR and will not be repeated in this submittal.

Releases from the main steam safety valves consist of high velocity, vertically discharged, steam released through 10" diameter vents.

These steam releases quickly lose their positive buoyancy due to rapid cooling from expansion and the substantial entrainment of ambient air that occurs due to the high velocity, small exit diameter, releases.

For these reasons, plume rise was calculated for all of the main steam safety valve releases using 3

LR-N96178 the NRC version of the Briggs momentum plume rise equations.

Plume rise was calculated using the average wind speed for stable meteorological conditions only, which is 7.3 mph.

The average wind speed during stable conditions only is more representative of the meteorological conditions responsible for the 95th percentile x/Q.

Plume rise is limited to the minimum of either the calculated plume rise or 80% of the height of the building wake cavity.

Because ARCON95 does not calculate plume rise, these values were calculated outside of the model.

The resultant plume rise heights were input into ARCON95 as increased release heights.

The calculated plume rise heights for each accident scenario/flow rate combination, and their percentage of the building cavity height, are listed in Table 4.

It is worth reiterating that even when a plume height is input into ARCON95, those releases within the building wake cavity are still treated as a ground-level release.

The model simply realizes the three-dimensional geometry of the situation, calculates the actual distance from the plume height to the receptor and uses this distance, termed the slant range, as the receptor distance from the source.

The effect of capping the plume rise at 80% of the building wake cavity height and the concept of the slant range receptor distance are shown in Figures 4a through 4c.

Figure 4a shows a high velocity steam release from an inboard Main Steam Safety Valve.

In the absence of the building wake induced turbulence, this plume would be expected to rise to an elevation of 300'.

However, the 80% cap restriction limits its rise to 161.6' above grade.

This elevation is then used to calculate a slant range receptor distance of 132.5', where the actual source to receptor distance in the absence of plume rise would be 26.8'.

Figures 4b and 4c show a more detailed example of the slant range receptor concept, in this case for a Unit 1 Plant Vent release and the Unit 1 Air Intake.

In a traditional modeling exercise, vent releases which are trapped within the building wake are treated in the horizontal dimension only.

In this instance, the receptor distance would be 90.4' horizontally between the Unit 1 vent and the air intake.

However, the slant range gives credit for the actual three dimensional distance between the vent and the air intake, which in this case is 186.7'.

Figure 4c shows how the slant range concept is actually applied in ARCON95.

The release is treated as ground level, and the x/Q value is evaluated at a downwind distance equivalent to the slant range, 186.7'.

4

LR-N96178 The onsite hourly meteorological data for the seven year period of 1988 through 1994 were used in the analysis.

The analysis utilized wind direction and speed from the lower and mid levels of the meteorological tower (33' and 150'), and the 300'-33' delta temperature.

Delta temperature was used to determine the atmospheric stability for each hour utilizing the NRC delta temperature/stability criteria found in ANSI/ANS-2.5.

ARCON95 utilizes wind speed and direction from both tower levels.

For each scenario or model run, the model selects the wind level that is closest in elevation to the release or plume height.

Wind speeds from the selected level are then adjusted to the release height using stability dependent adjustment factors.

Wind directions from the selected level are also used.

The ARCON95 model uses a centerline x/Q for the 0-2 hour calculation, a sector average x/Q for 8-24 hour, 1-4 day and 4-30 day calculations, and a combination of the two for the 2-8 hour calculations.

This produced some cases where the x/Q values increased with time.

Since such an increase is contrary to the accepted understanding of atmospheric dispersion, this feature of the model was discussed with the authors of ARCON95.

As a result an alternative methodology was suggested to determine x/Q values for time periods beyond two hours.

The alternative determined a 30-day x/Q value at the 50% level from ARCON95 and assumed that this value represented an annual average x/Q.

The x/Q values for those time periods beyond the 0-2 hour period were then determined by logarithmic interpolation between the 0-2 hour ARCON95 x/Q, and the annual x/Q approximated from ARCON95.

This same technique is endorsed by the NRC for offsite assessment of 95th percentile x/Qs in Regulatory Guide 1.145.

Before proceeding with this technique, a series of test runs were made.

The results showed that in some cases the ARCON95 x/Q values did increase with time, but that the x/Q value for time periods beyond 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months computed using the NRC Regulatory Guide 1.145 technique decreased in a consistent manner, though they were slightly conservative as compared to ARCON95 in some cases.

Therefore, it was determined to follow the suggestion of the ARCON95 authors and to use the logarithmic interpolation technique to determine all x/Q values for time periods beyond 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

5

LR-N96178 Resulting x/O Values at the Control Room Air Intakes The results indicate that of the many input variables in the ARCON95 calculations, the model is clearly most sensitive to receptor distance, and less sensitive to release height, flow rate and meteorology.

Because all scenarios were modeled as ground-level releases, the shortest distances between the source and receptor produced the highest x/Q values.

The x/Q values at the Control Room air intakes are conservative with respect to their application at other more distant receptors such as the centerline location of the Control Room redesign.

The ARCON95 model is somewhat sensitive to meteorology in that the low wind speed stable cases are responsible for the concentrations at the high end of the cumulative frequency distribution.

This is the case for all dispersion modeling evaluations which involve ground-level releases only.

However, the model was not sensitive to wind direction, despite the fact that only those hours within a 90° window centered on the source/receptor axis are used in the calculations.

This was illustrated by those instances where the receptor distances are identical, but the source/receptor geometric relationships are nearly mirror images of each other, i.e., a Unit 1 release on the Unit 1 intake versus a Unit 2 release on the Unit 2 intake.

Despite the fact that the contributing wind directions are separated by several directional sectors, the x/Q values from these runs were nearly identical.

The ARCON95 model is not sensitive to release height other than the fact that release height allows use of the slant range receptor distance previously described.

The model is also somewhat sensitive to effluent flow rate, in that it allows credit for an initial plume dilution that is a function of flow rate.

However, this value is capped at 100 m3 /sec.

Design Bases Dose Calculation For Salem Unit 1 and Unit 2 accident conditions evaluated, the most limiting radiological condition for Control Room habitability results from a Loss of Coolant Accident (LOCA).

The updated post-LOCA Control Room dose analysis uses the ARCON95 X/Q methodology and thyroid dose conversion factors consistent with the Industry Standard ICRP30 rather than our current design basis thyroid dose conversion factors, which are consistent with ICRP2.

The dispersion factors used for LOCA analysis were taken from Run 61 and are as follows:

1.72E-03 sec/m 3 for 0-2 hours, 1.22E-03 sec/m 3 for 2-8 hours, 1.03E-03 sec/m 3 for 8-24 hours, 7.13E-04 6

LR-N96178 sec/m 3 for 1-4 days, and 4.19E-04 sec/m 3 for 4-30 days.

Other design input parameters used in the calculation are provided in Table 5.

The resulting calculated post-LOCA doses are 3.1 rem (whole body gamma), 27.1 rem (thyroid), and 22.7 rem (beta skin), which are within the respective GDC 19 and equivalent dose limits of 5 rem (whole body gamma), 30 rem (thyroid), and 30 rem (beta skin).

Credit for the Control Room Emergency Air Conditioning System charcoal filters is taken in determining the these values.

Conclusion The use of ARCON95 provides a more representative model for deriving the dispersion factors used in the Control Room dose analysis.

Though the resulting calculated doses are higher than those presented in Salem's UFSAR, it is not unexpected in light of the larger dispersion factor and more conservative assumptions used in the radiological design analysis such as increased ECCS leakage and higher control room inleakage.

However, the calculated doses remain below the limiting criteria of GDC 19.

7

Run#

1 2

3 4

5 6

7 8

Table i Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Loss of AC Power, Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow= 77.37 m 3/sec or 19.34 m3/sec per valve, Plume height = 44.25 m above plant grade or 69% of building wake cavity height Loss of AC Power, Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow= 77.37 m3/sec or 19.34 m3/sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Loss of AC Power, Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow= 77.37 m 3/sec or 19.34 m 3/sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Loss of AC Power, Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow= 77.37 m3/sec or 19.34 m3/sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Loss of AC Power, Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow= 21.29 m 3/sec or 5.32 m3/sec per valve, Plume height= 27.1 m above plant grade or 32% of building wake cavity height Loss of AC Power, Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow= 21.29 m 3/sec or 5.32 m 3/sec per valve, Plume height = 27.1 m above plant grade or 32% of building wake cavity height Loss of AC Power, Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow= 21.29 m 3 /sec or 5.32 m 3 /sec per valve, Plume height= 27.1 m above plant grade or 32% of building wake cavity height Loss of AC Power, Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow= 21.29 m 3/sec or 5.32 m 3/sec per valve, Plume height = 27.1 m above plant grade or 32% of building wake cavity height Intalle Receptor Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 METEOROLOGICAL EVALUATION SERVICES

Run#

9 10 11 12 13 14 15 16 Table 1 (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Steam Generator Tube Rupture, One Faulted Steam Generator Unit 1 Inboard Main Steam Safety Valve Set l, Total Flow=

26.69 m 3 /sec for one valve, Plume height = 49.3 m above plant grade or 80% of buildipg wake cavity height Steam Generator Tube Rupture, One Faulted Steam Generator Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow =

26.69 m 3 /sec for one valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Steam Generator Tube Rupture, One Faulted Steam Generator Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow=

26.69 m 3 /sec for one valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Steam Generator Tube Rupture, One Faulted Steam Generator Unit 2 Inboard Main Steam Safety Valve Set 1, Total.Flow=

26.69 m 3 /sec for one valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Steam Generator Tube Rupture, One Faulted Steam Generator Unit 1 Inboard Main Steam Safety Valve Set 2, Total Flow=

26.69 m 3 /sec for one valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Steam Generator Tube Rupture, One Faulted Steam Generator Unit 2 Inboard Main Steam Safety Valve Set 2, Total Flow=

26.69 m 3 /sec for one valve, Plume height= 49.3 m above plant grade or 80% of building wake cavity height Steam Generator Tube Rupture, One Faulted Steam Generator Unit 2 Inboarci Main Steam Safety Valve Set 2, Total Flow=

26.69 m 3 /sec for one valve, Plume height= 49.3 m above plant grade or 80% of building wake cavity height Intalle Receptor Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 METEOROLOGICAL EVALUATION SERVICES

Run#

17 18 19 20 21 22 23 24 Table I (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Steam Generator Tube Rupture, Three Intact Steam Generators Unit 1 Inboard Main Steam Safety Valve Set 2, Total Flow=

54.97 m3/sec or 18.32 m3/sec per valve, Plume height= 43.2 m above plant grade or 67% o( building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 1 Inboard Main Steam Safety Valve Set 2, Total Flow=

54.97 m3/sec or 18.32 m3/sec per valve, Plume height= 43.2 m above plant grade or 67% of building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 2 Inboard Main Steam Safety Valve Set 2, Total Flow=

54.97 m3/sec or 18.32 m3/sec per valve, Plume height= 43.2 m above plant grade or 67% of building wake cavity height Control Rod Eject, Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow= 3,898 m3/sec or 194.9 m3/sec per valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Control Rod Eject, Unit 1 Inboard Main Steam Safety Valve Set 1, Total Flow= 3,898 m3/sec or 194.9 m3/sec per valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Control Rod Eject, Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow= 3,898 m3/sec or 194.9 m3/sec per valve, Plume height = 49.3 m above plant grade or 80% of building wake cavity height Control Rod Eject, Unit 2 Inboard Main Steam Safety Valve Set 1, Total Flow= 3,898 m3/sec or 194.9 m3/sec per valve, Plume height= 49.3 m above plant grade or 80% of building wake cavity height Intalie Receptor Unit 1 Unit2 Unit 1 Unit2 Unit 1 Unit 2 Unit 1 Unit 2 METEOROLOGICAL EVALUATION SERVICES

Run#

25 26 27 28 29 30 31 32 33 34 Table I (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Control Rod Eject, Unit 1 Containment Leak, Ground-level release, Total Flow= 4.lOE-4 m3/sec Control Rod Eject, Unit 1 Containment Leak, Ground-level release, Total Flow= 4.lOE-4 m3/sec Control Rod Eject, Unit 2 Containment Leak, Ground-level release, Total Flow= 4.lOE-4 m3/sec Control Rod Eject, Unit 2 Containment Leak, Ground-level release, Total Flow= 4.lOE-4 m3/sec Steam Generator Tube Rupture, Three Intact Steam Generators Unit 1 lnbo~d Main Steam Safety Valve Set 2, Total Flow=

41.57 m3/sec or 13.86 m3/sec per valve, Plume height= 38.3 m above plant grade or 56% of building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 1 Inboard Main Steam Safety Valve Set 2, Total Flow=

41.57 m3/sec or 13.86 m3/sec per valve, Plume height= 38.3 m above plant grade or 56% of building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 2 Inboard Main Steam Safety Valve Set 2, Total Flow=

41.57 m3/sec or 13.86 m3/sec per valve, Plume height= 38.3 m above plant grade or 56% of building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 1 Inboard Main Steam Safety Valve Set 2, Total Flow=

20.98 m3/sec or 6.99 m3/sec per valve, Plume height= 29.6 m above plant grade or 38% of building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 1 Inboard Main Steam Safety Valve Set 2, Total Flow=

20.98 m3/sec or 6.99 m3/sec per valve, Plume height= 29.6 m above plant grade or 381Yi1 of building wake cavity height Intahe Receptor Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2

- -t -

METEOROLOGICAL EVALUATION SERVICES

Run#

35 36 37 38 39 40 41 42 43 Table I (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Steam Generator Tube Rupture, Three Intact Steam Generators Unit 2 Inboard Main Steam Safety Valve Set 2, Total Flow=

20.98 m 3/sec or 6.99 m3/sec per valve, Plume height= 29.6 m

above plant grade or 38% of building wake cavity height Steam Generator Tube Rupture, Three Intact Steam Generators Unit 2 Inboard Main Steam Safety Valve Set 2, Total Flow=

20.98 m 3/sec or 6.99 m3/sec per valve, Plume height= 29.6 m above plant grade or 38% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 1 Penetration Area Pressure Relief, Ground-level release, Total Flow= 13.08 m 3/sec for one blowout panel Main Steam Line Break, One Faulted Steam Generator Unit 1 Penetration Area Pressure Relief, Ground-level release, Total Flow= 13.08 m 3/sec for ~ne blowout panel Main Steam Line Break, One Faulted Steam Generator Unit 2 Penetration Area Pressure Relief, Ground-level release, Total Flow= 13.08 m 3/sec for one blowout panel Main Steam Line Break, One Faulted Steam Generator Unit 2 Penetration Area Pressure Relief, Ground-level release, Total Flow= 13.08 m 3 /sec for one blowout panel Main Steam Line Break, Three Intact Steam Generators Unit 1 Main Steam Safety Valve Set 1, Total Flow= 59.04 m 3/sec or 19.68 m 3/sec per valve, Plume height= 44.6 m above plant grade or 70% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 1 Main Steam Safety Valve Set 1, Total Flow= 59.04 m 3/sec or 19.68 m 3/sec per valve, Plume height= 44.6 m above plant grade or 70% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 2 Main Steam Safety Valve Set 1, Total Flow= 59.04 m 3/sec or 19.68 m 3/sec per valve, Plume height= 44.6 m above plant grade or 7ocx1 of building wake cavity height Intalle Receptor Unit 1 Unit 2 Unit 1 Unit2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 METEOROLOGICAL EVALUATION SERVICES

Run#

44 45 46 47 48 49 50 51 Table I (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Main Steam Line Break, One Faulted Steam Generator Unit 2 Main Steam Safety Valve Set 1, Total Flow= 59.04 m3/sec or 19.68 m 3/sec per valve, Plume height= 44.6 m above plant grade or 70% of buildipg wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 1 Main Steam Safety Valve Set 1, Total Flow= 17.81 m3 /sec or 5.94 m 3/sec per valve, Plume height= 28.0 m above plant grade or 34% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 1 Main Steam Safety Valve Set 1, Total Flow= 17.81 m3/sec or 5.94 m 3/sec per valve, Plume height= 28.0 m above plant grade or 34% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 2 Main Steam Safety Valve Set 1, Total Flow= 17.81 m3/sec or 5.94 m 3 /sec per valve, Plume height= 28.0 m above plant grade or 34% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 2 Main Steam Safety Valve Set 1, Total Flow= 17.81 m 3 /sec or 5.94 m 3 /sec per valve, Plume height= 28.0 m above plant grade or 34% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 1 Main Steam Safety Valve Set 1, Total Flow= 29.68 m 3/sec or 9.89 m 3 /sec per valve, Plume height= 33.5 m above plant grade or 46% of building wake cavity height Main Steam Line Break, One Faulted Steam Generator Unit 1 Main Steam Safety Valve Set 1, Total Flow= 17.81 m 3/sec or 5.94 rn3/sec per valve, Plume height= 28.0 rn above plant grade or 34% of building wake cavity height Main Stearn Line Break, One Faulted Steam Generator Unit 2 Main Stearn Safety Valve Set 1, Total Flow= 17.81 rn3/sec or 5. 94 rn:l /sec per valve, Plume height = 28.0 m above plant grade or 341% of building wake cavity height Int.a/le Receptor Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 METEOROLOGICAL EVALUATION SERVICES

Run#

52 53 54 55 56 57 58 59 Table 1 (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Source Main Steam Line Break, One Faulted Steam Generator Unit 2 Main Steam Safety Valve Set 1, Total F1ow = 17.81 m3 /sec or 5.94 m3/sec per valve, Plume height= 28.0 m above plant grade or 34% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 1 Main Steam Safety Valve Set 1, Total Flow= 77.37 m3/sec or 19.34 m3 /sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 1 Main Steam Safety Valve Set 1, Total Flow= 77.37 m3/sec or 19.34 m3 /sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 2 Main Steam Safety Valve Set 1, Total Flow= 77.37 m3/sec or 19.34 m3 /sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 2 Main Steam Safety Valve Set 1, Total Flow= 77.37 m3/sec or 19.34 m3 /sec per valve, Plume height = 44.3 m above plant grade or 69% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 1 Main Steam Safety Valve Set 1, Total Flow = 21.29 m3 /sec or 5.32 m 3/sec p'ervalve, Plume height= 27.1 m above plant grade or 32% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 1 Main Steam Safety Valve Set 1, Total Flow = 21.29 m3 /sec or 5.32 m3/sec per valve, Plume height= 27.1 m above plant grade or 32% of building wake cavity height Reactor Coolant Pump Locked Rotor Unit 2 Main Steam Safety Valve Set 1, Total Flow= 21.29 m3/sec or 5.32 m3 /sec per valve, Plume height = 27.1 m above plant grade or 32% of building wake cavity height Intalle Receptor Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 METEOROLOGICAL EVALUATION SERVICES

Run#

60 61 62 63 64 65 66 67 68 69 70 71 72 Table 1 (continued)

Salem Generating Station Control Room Habitability Analysis Listing of All X/Q Runs and Run Specific Model Inputs Intahe Source Receptor Reactor Coolant Pump Locked Rotor Unit 2 Main Steam Safety Valve Set 1, Total Flow = 21.29 m3 /sec or 5.32 m3/sec per valve, Plume height= 27.1 m above plant grade or 32% of build!ng wake cavity height Unit 2 Loss of Coolant Accident, Unit 1 Main Vent Total Flow=

42.48 m3/sec, Capped vent, Plume height= 59.2 m above plant grade or 100% of building wake cavity height Unit 1 Loss of Coolant Accident, Unit 1 Main Vent Total Flow=

42.48 m 3/sec, Capped vent, Plume height= 59.2 m above plant grade or 100% of building wake cavity height Unit 2 Loss of Coolant Accident, Unit 2 Main Vent Total Flow =

42.48 m 3 /sec, Capped vent, Plume height= 59.2 m above plant grade or 100% of building wake cavity height Unit 1 Loss of Coolant Accident, Unit 2 Main Vent Total Flow=

42.48 m 3 /sec, Capped vent, Plume height= 59.2 m above plant grade or 100% of building wake cavity height Unit 2 Hope Creek FRVS, Total Flow= 1.59 m3 /sec, Capped vent, Plume height= 61.5 m above plant grade Unit 1 Hope Creek FRVS, Total Flow = 1.59 m3 /sec, Capped vent, Plume height= 61.5 m above plant grade Unit 2 Hope Creek Main Steam Blowout Panels, Total Flow =

28.32 m 3 /sec, Plume height= 13.4 m above plant grade Unit 1 Hope Creek Main Steam Blowout Panels, Total Flow=

28.32 m3 /sec, Plume height= 13.4 m above plant grade Unit 2 CVCS Line Break, Unit 1, Smoke Hatch, Total Flow =

1.43 m3/sec, Plume height= 13.0 m above plant grade Unit 1 CVCS Line Break, Unit 1, Smoke Hatch, Total Flow =

1.43 m3/sec, Plume height= 13.0 m above plant grade Unit 2 CVCS Line Break, Unit 2, Smoke Hatch, Total Flow=

1.43 m 3 /sec, Plume height= 13.0 m above plant grade Unit 1 CVCS Line Break, Unit 2, Smoke Hatch, Total Flow=

1.43 m 3 /sec, Plume height= 13.0 m above plant grade Unit 2 METEOROLOGICAL EVALUATION SERVICES

Run 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Rev. 1, 3/12/96 Table 2 Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values for All Runs and Time Periods 0-2 hr 2-8 hr 8-24 hr 1-4 day 4-30 day Annual*

(2 hr)

(8 hr)

(16 hr)

(3 day)

(26 day) 4.04E-03 2.72E-03 2.24E-03 l.46E-03 7.90E-04 3.73E-04 1.98E-03 1.4 lE-03 l.20E-03 8.30E-04 4.91E-04 2.59E-04 l.96E-03 l.40E-03 1 :18E-03

8. l 7E-04 4.82E-04 2.53E-04 4.17E-03 2.84E-03 2.35E-03 l.SSE-03 8.SlE-04 4.lOE-04 1.45E-02 9.89E-03 8.17E-03 5.40E-03 2.98E-03 l.44E-03 2.88E-03 2.06E-03 l.74E-03 l.20E-03 7.12E-04 3.74E-04 2.97E-03 2.13E-03 1.80E-03 l.25E-03 7.46E-04 3.95E-04 l.46E-02 l.OOE-02 8.32E-03 5.54E-03 3.09E-03 l.SlE-03

3. lOE-03 2.09E-03 l.72E-03 1.12E-03 6.06E-04 2.86E-04 1.76E-03 1.25E-03 1.06E-03 7.3 lE-04 4.30E-04 2.25E-04 1.75E-03 1.24E-03 l.OSE-03 7.25E-04 4.26E-04 2.22E-04 3.22E-03 2.20E-03 1.81E-03 l.20E-03 6.59E-04 3.18E-04 2.91E-03 1.92E-03 l.56E-03 9.97E-04 5.23E-04 2.37E-04 1.61E-03 l.14E-03 9.57E-04 6.56E-04 3.82E-04 1.97E-04 1.6 lE-03 l.14E-03 9.SSE-04 6.54E-04 3.80E-04 1.96E-04 3.00E-03 2.03E-03 1.66E-03 1.09E-03 5.90E-04 2.79E-04 3.90E-03 2.58E-03

2. lOE-03 l.34E-03 7.02E-04 3.19E-04 1.88E-03 1.33E-03 l.12E-03 7.67E-04 4.47E-04 2.31E-04 l.88E-03 l.33E-03

l. l lE-03 7.62E-04 4.43E-04 2.28E-04 3.99E-03 2.69E-03 2.21E-03 1.45E-03 7.85E-04 3.72E-04 2.53E-03 l.73E-03 l.43E-03 9.45E-04 5.22E-04 2.53E-04 l.56E-03 1.12E-03 9.5 lE-04 6.64E-04 3.97E-04 2.12E-04 l.54E-03 l.llE-03 9.37E-04 6.64E-04 3.91E-04 2.08E-04 2.58E-03 l.78E-03 l.48E-03 9.95E-04 5.60E-04 2.78E-04 9.66E-02 6.92E-02 5.86E-02 4.09E-02 2.43E-02 l.29E-02 METEOROLOGICAL EVALUATION SERVICES

Run 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 Rev. 1, 3/ 12/96 Table 2 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values for All Runs and Time Periods 0-2 hr 2 hr 3.06E-03 2.99E-03 9.SOE-02 5.02E-03 2.12E-03 2.lOE-03 5.17E-03 8.54E-03 2.54E-03 2.SlE-03 8.72E-03 7.64E-03 1.99E-03 l.94E-03 7.04E-03 3.99E-03 1.97E-03 1.95E-03 4.09E-03 1.28E-02 2.90E-03 2.85E-03 1.3 lE-02 8.07E-03 2-8 hr 8 hr 2.2 lE-03 2.16E-03 6.79E-02 3.32E-03 1.SOE-03 l.48E-03 3.49E-03 5.67E-03 1.80E-03 1.77E-03 5.90E-03 5.25E-03 l.4 lE-03 1.37E-03 4.89E-03 2.69E-03 l.4 lE-03 1.39E-03 2.79E-03 8.65E-03 2.08E-03 2.03E-03 8.92E-03 5.45E-03 8-24 hr 16 hr 1.88E-03 1~83E-03 5.74E-02 2.71E-03 l.26E-03 1.24E-03 2.87E-03 4.62E-03 1.SlE-03 1.49E-03 4.85E-03 4.36E-03 1.19E-03

1. lSE-03 4.07E-03 2.2 lE-03 1.19E-03 1.17E-03 2.30E-03 7.1 lE-03 1.76E-03 1.72E-03 7.36E-03 4.48E-03 1-4 day 3 da l.32E-03 1.28E-03 3.99E-02 1.73E-03 8.64E-04 8.52E-04 1.88E-03 2.96E-03 l.04E-03 1.02E-03 3.17E-03 2.90E-03 8.21E-04 7.92E-04 2.74E-03 1.44E-03 8.24E-04 8.1 lE-04 1.52E-03 4.65E-03 1.23E-03 1.19E-03 4.85E-03 2.93E-03 4-30 day 26 da 7.95E-04 7.71E-04 2.36E-02 9.1 lE-04 5.03E-04 4.95E-04 1.02E-03 1.57E-03 6.07E-04 5.91E-04 1.72E-03 l.62E-03 4.81E-04 4.61E-04 1.SSE-03 7.78E-04 4.87E-04 4.78E-04 8.35E-04 2.53E-03

. 7.29E-04 7.0SE-04 2.66E-03 1.59E-03 Annual*

4.28E-04 4.13E-04 l.25E-02 4.lSE-04 2.60E-04 2.54E-04 4.82E-04 7.18E-04

3. lSE-04 3.04E-04.

8.19E-04 7.94E-04 2.SlE-04 2.38E-04 7.74E-04 3.67E-04 2.56E-04 2.SlE-04 4.02E-04 1.20E-03 3.87E-04 3.71E-04 1.28E-03 7.52E-04 METEOROLOGICAL EVALUATION SERVICES

J Run 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 Rev. l, 3/ 12/96 Table 2 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values for All Runs and Time Periods 0-2 hr 2 hr 2.61E-03 2.57E-03 8.29E-03 4.04E-03 1.98E-03 1.96E-03 4.17E-03 1.45E-02 2.88E-03 2.97E-03 1.46E-02 1.72E-03 8.90E-04 8.72E-04 l.69E-03 4.54E-05 5.23E-05 5.18E-05 6.13E-05

1. lSE-02 2.00E-03 2.00E-03 l.14E-02 2-8 hr 8 hr 1.87E-03 1.83E-03 5.64E-03 2.72E-03 1.4 lE-03 1.40E-03 2.84E-03 9.89E-03 2.06E-03 2.13E-03 l.OOE-02 1.22E-03 6.35E-04 6.22E-04 1.20E-03 3.23E-05 3.72E-05 3.78E-05 4.46E-05 8.24E-03 1.45E-03 l.45E-03 8.23E-03 8-24 hr 16 hr 1.58E-03 l.54E-03 4.66E-03 2.24E-03 1.20E-03 l.18E-03 2.35E-03 8.17E-03 1.74E-03 1.80E-03 8.32E-03 1.03E-03 5.36E-04 5.25E-04 1.02E-03 2.72E-05 3.14E-05 3.23E-05 3.8 lE-05 6.97E-03 1.23E-03 1.24E-03 6.99E-03 1-4 day 3 da

1. lOE-03 1.07E-03 3.07E-03 l.46E-03 8.30E-04 8.17E-04 1.SSE-03 5.40E-03 l.20E-03 l.25E-03 5.54E-03 7.13E-04 3.72E-04 3.63E-04 7.04E-04 1.88E-05 2.17E-05 2.30E-05 2.70E-05 4.85E-03 8.67E-04 8.75E-04 4.90E-03 4-30 day 26 da 6.49E-04 6.30E-04 1.69E-03 7.90E-04 4.91E-04 4.82E-04 8.SlE-04 2.98E-03 7.12E-04 7.46E-04 3.09E-03 4.19E-04 2.20E-04 2.15E-04 4.15E-04 1.1 lE-05 1.28E-05 l.4 lE-05 l.65E-05 2.88E-03 5.24E-04 5.32E-04 2.95E-03 Annual*

3.42E-04 3.30E-04 8.1 lE-04 3.73E-04 2.59E-04 2.53E-04 4.lOE-04 1.44E-03 3.74E-04 3.95E-04 l.5 lE-03 2.19E-04 1.15E-04 l.13E-04 2.18E-04 5.79E-06 6.69E-06 7.71E-06 8.99E-06 1.53E-03 2.83E-04 2.89E-04 1.58E-03

Approximated from 50% 30-day X/Q METEOROLOGICAL EVALUATION SERVICES

Table 3 Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0-2 hr 2-8 hr 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 day)

Loss of Non-Emergency AC Power Source: Unit 1 lnboaI'd MSSV, Set 1 4.04E-03 9.89E-03 8.17E-03 5.40E-03 Receptor: Unit 1 Control Room Air Intake Flow: 77.37 m3 /sec, 0-2 hours 21.29 m3/sec, 2-32 hours divided among 4 valves Rwz No. 1 Ru11 No. 5 Ru11 No. 5 Run No. 5 Loss of Non-Emergency AC Power Source: Unit 1 Inboard MSSV, Set 1 1.98E-03 2.06E-03 1.74E-03

.1.20E-03 Receptor: Unit 2 Control Room Air Intake Flow: 77.37 m 3 /sec, 0-2 hours 21.29 m3/sec, 2-32 hours divided among 4 valves Ru11 No. 2 Run No. 6 Ru11 No. 6 Run No. 6 Loss of Non-Emergency AC Power Source: Unit 2 Inboard MSSV, Set 1 1.96E-03 2.13E-03 1.BOE-03 1.25E-03 Receptor: Unit 1 Control Room Air Intake Flow: 77.37 m 3/sec, 0-2 hours 21.29 m 3 /sec, 2-32 hours divided among 4 valves Run No. 3 Run No. 7 Run No. 7 RunNo. 7 Loss of Non-Emergency AC Power Source: Unit 2 Inboard MSSV, Set I 4.17E-03 1.00E-02 8.32E-03 5.54E-03 Receptor: Unit 2 Control Room Air Intake Flow: 77.37 m 3/sec, 0-2 hours 21.29 m 3 /sec, 2-32 hours divided among 4 valves Run No. 4 Run No. 8 Run No. 8 Run No. 8 (Rev. 1, 3/ 12/96) 4-30 day (26 day) 2.98E-03 Rwz No. 5 7.12E-04 Ru11 No. 6 7.46E-04 Ru11 No. 7 3.09E-03 Run No. 8 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0-2 hr 2-8 hr 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 dalJ)

Steam Generator Tube Release - One Faulted Steam Generator Source: Unit 1 Inboard MSSV, Set 1

3. lOE-03 2.09E-03 l.72E-03 l.12E-03 Receptor: Unit 1 Control Room Air Intake Flow:

26.69 m 3/sec, 0-2 hours through one valve Run No. 9 Run No. 9 Run No. 9 Run No. 9 Steam Generator Tube Release - One Faulted Steam Generator Source: Unit 1 Inboard MSSV, Set 1 l.76E-03 l.25E-03 l.06E-03 7.3 lE-04 Receptor: Unit 2 Control Room Air Intake Flow:

26.69 m3/sec, 0-2 hours through one valve Run No. 10 Run No. 10 Run No. 10 Run No. 10 Steam Generator Tube Release - One Faulted Steam Generator Source: Unit 2 Inboard MSSV, Set 1 1.75E-03 l.24E-03 l.OSE-03 7.25E-04 Receptor: Unit 1 Control Room Air Intake Flow:

26.69 m:1 /sec, 0-2 hours through one valve RunNo. 11 Run No. 11 Run No. 11 Run No. 11 Steam Generator Tube Release - One Faulted Steam Generator Source: Unit 2 Inboard MSSV, Set 1 3.22E-03 2.20E-03 1.8 lE-03 l.20E-03 Receptor: Unit 2.Control Room Air Intake Flow: 26.69 m 3/sec, 0-2 hours through one valve RunNo. 12 RunNo. 12 RunNo. 12 RunNo. 12

(~ev. 1, 3/ 12/Yl>)

4-30 day (26 dm1) 6.06E-04 Run No. 9 4.30E-04 Run No. 10 4.26E-04 Run No. 11 6.59E-04 Run No. 12 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0- 2 hr 2 - 8 hr 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 daZJ)

Steam Generator Tube Release - Three Intact Steam Generators Source: Unit 1 Inboard MSSV, Set 2 3.90E-03 3.32E-03 4.62E-03 2.96E-03 Receptor: Unit 1 Control Room Air Intake Flow: 54.97 m3 /sec, 0-2 hours 41.57 m:1/sec, 2-8 hours 20.98 111:1/scc, 8-32 hours Run No. 17 R1111 No. 29 Run No. 33 Rrm No. 33 through three valves Steam Generator Tube Release - Three Intact Steam Generators Source: Unit 1 Inboard MSSV, Set 2 l.88E-03 l.SOE-03 l.SlE-03 l.04E-03 Receptor: Unit 2 Control Room Air Intake Flow: 54.97 m3/sec, 0-2 hours 41.57 m:l/sec, 2-8 hours 20.98 m:l/sec, 8-32 hours Run No. 18 Run No. 30 Run No. 34 Run No. 34 through three valves Steam Generator Tube Release - Three Intact Steam Generators Source: Unit 2 Inboard MSSV, Set 2 l.88E-03 l.48E-03 1.49E-03 1.02E-03 Receptor: Unit 1 Control Room Air Intake Flow: 54.97 m3/sec, 0-2 hours 41.57 m3/sec, 2-8 hours 20.98 m 3/sec, 8-32 hours Run No. 19 Run No. 31 Run No. 35 Run No. 35 through three valves (Rev. l, 3/ 1'2/<J6) 4-30 day (26 da11) l.57E-03 Rw1 No. 33 6.07E-04 Ru11 No. 34 5.91E-04 Run No. 35 METEOROLOGICAL EVALUATION SEHVICES

Table 3 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0-2 hr 2-8 hr 8-24 hr 1-4 day Accident Scenal'io (2 hr)

(8 hr)

(16 hr)

(3 da11)

Steam Generator Tube Release - Three Intact Steam Generators Source: Unit 2 Inboard MSSV, Set 2 3.99E-03 3.49E-03 4.85E-03 3.17E-03 Receptor: Unit 2 Control Room Air Intake Flow: 54.97 m 3/sec, 0-2 hours 41.57 m:3/sec, 2-8 hours 20.98 m 3/sec, 8-32 hours Run No. 20 Run No. 32 Run No. 36 Run No. 36 through three valves Control Hod Ejection Source: Unit 1 Inboard MSSV, Set 1 for 0-102 seconds, use for 0-2 hr 2.53E-03 6.92E-02 5.86E-02 4.09E-02 Containment leak for 2 hr-30 days Receptor: Unit 1 Control Room Air Intake Flow: 3,898.7 m 3/sec, 0-2 hours through 20 valves Run No. 21 Run No. 25 Run No. 25 Run No. 25 4.lOE-4 m 3/sec, 2 hr-30 days Control Rod Ejection Source: Unit 1 Inboard MSSV, Set 1 for 0-102 seconds, use for 0-2 hr 1.56E-03 2.21E-03 1.88E-03 1.32E-03 Containment leak for 2 hr-30 days Receptor: Unit 2 Control Room Air Intake Flow: 3,898.7 m 3 /sec, 0-2 hours through 20 valves Run No. 22 Run No. 26 Run No. 26 Run No. 26 4.lOE-4 m 3/sec, 2 hr-30 days (Rev. 1, 3/ 12/96) 4-30 day (26 day) l.72E-03 Ru11 No. 36 2.43E-02 Run No. 25 7.95E-04 Run No. 26 METEOROLOGICAL EVALUATION SERVICES

Table 3 {continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0- 2 hr 2-8 hr*

8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 day)

Control Rod Ejection Source: Unit 2 Inboard MSSV, Set 1 for 0-102 seconds, use for 0-2 hr 1.54E-03 2.16E-03 l.83E-03 1.28E-03 Contairunent leak for 2 hr-30 days Receptor: Unit 1 Control Room Air Intake Flow: 3,898.7 m:3/sec, 0-2 hours through 20 valves Run No. 23 Run No. 27 Ru11 No. 27 Run No. 27

4. IOE-4 m:1/scc, 2 hr-30 days Control Rod Ejection Source: Unit 2 Inboard MSSV, Set 1 for 0-102 seconds, use for 0-2 hr 2.58E-03 6.79E-02 5.74E-02 3.99E-02 Containment leak for 2 hr-30 days Receptor: Unit 2 Control Room Air Intake Flow: 3,898.7 m 3 /sec, 0-2 hours through 20 valves Run No. 24 Run No. 28 Run No. 28 Run No. 28

4. lOE-4 m 3 /sec, 2 hr-30 days Main Steam Line Break, One Faulted Steam Generator Source: Unit 1 Penetration Area Pressure 7.64E-03 5.25E-03 4.36E-03 2.90E-03 Relief Receptor: Unit 1 Control Room Air Intake Flow:

13.08 m 3/sec, 0-2 hours 0.0 m 3 /sec, 2 hr-30 days Run No. 37 Run No. 37 Run No. 37 Run No. 37 (Rev. 1, 3/12/96) 4-30day (26 dal/)

7.7 lE-04 Rim No. 27 2.36E-02 Ru11 No. 28 1.62E-03 Run No. 37 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Salen1 Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0 - 2 hr 2 - 8 hr 8-24 hr 1-4 day Accident Scenal'io (2 hr)

(8 hr)

(16 hr)

(3 dal/)

Main Steam Line Break, One Faulted Steam Generator Source: Unit 1 Penetration Arca Pressure l.99E-03 1.4 lE-03 l.19E-03 8.21E-04 Relief Receptor: Unit 2 Control Room Air Intake Flow:

13.08 m 3 /sec, 0-2 hours 0.0 m:i /sec, 2 hr-30 days Run No. 38 Run No. 38 Run No. 38 Run No. 38 Main Steam Line Break, One Faulted Steam Generator Source: Unit 2 Penetration Area Pressure l.94E-03 l.37E-03

l. lSE-03 7.92E-04 Relief Receptor: Unit 1 Control Room Air Intake Flow:

13.08 m 3 /sec, 0-2 hours 0.0 m 3 /sec, 2 hr-30 days Run No. 39 Run No. 39 Run No. 39 Run No. 39 Main Steam Line Break, One Faulted Steam Generator Source: Unit 2 Penetration Area Pressure 7.04E-03 4.89E-03 4.07E-03 2.74E-03 Relief Receptor: Unit 2 Control Room Air Intake Flow:

13.08 m 3 /sec, 0-2 hours 0.0 m 3 /sec, 2 hr-30 days Run No. 40 Run No. 40 Run No. 40 Run No. 40 (Rev. l, 3/ 12/96) 4-30 day (26 dau) 4.81 E-04 Rw1 No. 38 4.6 lE-04 Ru11 No. 39 1.SSE-03 Run No. 40 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0 - 2 hr 2-8 hr 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 dm1)

Main Steam Line Break - Three Intact Steam Generators Source: Unit 1 Inboard MSSV, Set 1 3.99E-03 8.65E-03 4.48E-03 2.93E-03 Receptor: Unit 1 Control Room Air Intake Flow: 59.04 m 3 /sec, 0-2 hours 17.81 m 3 /sec, 2-8 hours 29.68 m:1 /sec, 8-32 hours Rw1 No. 11 Run No. 45 Rw1 No. 49 Rw1 No. 49 through three valves Main Steam Line Break - Three Intact Steam Generators Source: Unit I Inboard MSSV, Set 1 1.97E-03 2.08E-03 l.58E-03

1. lOE-03 Receptor: Unit 2 Control Room Air Intake Flow: 59.04 m 3 /sec, 0-2 hours 17.81 m 3 /sec, 2-8 hours 29.68 m 3 /sec, 8-32 hours Run No. 42 Run No. 46 Run No. 50 Run No. 50 through three valves Main Steam Line Break - Three Intact Steam Generators Source: Unit 2 Inboard MSSV, Set 1 1.95E-03 2.03E-03 1.54E-03 l.07E-03 Receptor: Unit 1 Control Room Air Intake Flow: 59.04 m 3 /sec, 0-2 hours 17.81 m 3 /sec, 2-8 hours 29.68 m 3 /sec, 8-32 hours Run No. 43 Run No. 47 Run No. 51 Run No. 51 through three valves (Rev. l, 3/ 12/96) 4-30 day (26 dm1) 1.59E-03 Rw1 No. 49 6.49E-04 Run No. 50

e.

6.30E-04 Run No. 51 METEOROLOGICAL EVALUATION SEFlVICES

Table 3 (continuedj Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0- 2 h,.

2-8 hr 8-24 hr 1-4 day Accident Scena,.io (2 hr)

(8 hr)

(16 hr)

(3 dal/)

Main Steam Line Break - Three Intact Steam Generators Source: Unit 2 Inboard MSSV, Set 1 4.09E-03 8.92E-03 4.66E-03 3.07E-03 Receptor: Unit 2 Control Room Air Intake Flow: 59.04 m 3/sec, 0-2 hours 17.81 m:1/sec, 2-8 hours 29.68 m:1/scc, 8-32 hours Ru11 No. 44 Ru11 No. 48 Rw1 No. 52 Ru11 No. 52 through three valves Reactor Coolant Pump Locked Rotor Source: Unit I Inboard MSSV, Set 1 4.04E-03 9.89E-03 8.17E-03 5.40E-03 Receptor: Unit I Control Room Air Intake Flow: 77.37 m:1/sec, 0-2 hours 29.68 m3 /sec, 2-32 hours through four valves Run No. 53 Run No. 57 Run No. 57 Run No. 57 Reactor Coolant Pump Locked Rotor Source: Unit I Inboard. MSSV, Set 1 l.98E-03 2.06E-03 1.74E-03 l.20E-03 Receptor: Unit 2 Control Room Air Intake Flow: 77.37 m 3/sec, 0-2 hours 29.68 m 3/sec, 2-32 hours through four valves Run No. 54 Run No. 58 Run No. 58 Run No. 58 Reactor Coolant Pump Locked Rotor Source: Unit 2 Inboard MSSV, Set I l.96E-03 2.13E-03 1.80E-03 1.25E-03 Receptor: Unit 1 Control Room Air Intake Flow: 77.37 m 3/sec, 0-2 hours 21.29 m 3/sec, 2-32 hours through four valves Run No. 55 Run No. 59 Run No. 59 Run No. 59 (Rev. l, 3/ 12/96) 4-30 day (26 dm1) l.69E-03 Rw1 No. 52 2.98E-03 Ru11 No. 57 7.12E-04 Run No. 58 7.46E-04 Run No. 59 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Sale1n Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0-2 hr 2-8 hr 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 datJ)

Reactor Coolant Pump Locked Rotor Source: Unit 2 Inboard MSSV, Set 1 4.17E-03 l.OOE-02 8.32E-03 5.54E-03 Receptor: Unit 2 Control Room Air Intake Flow: 77.37 m 3 /sec, 0-2 hours 21.29 m 3 /sec, 2-32 hours through four valves Rw1 No. 56 Run No. 60 Run No. 60 Run No. 60 Loss of Coolant Accident Source: Unit 1 Main Vent 1.72E-03 l.22E-03 1.03E-03 7*.13E-04 Receptor: Unit 1 Control Room Air Intake Flow: 42.48 m:i /sec, all time periods Run No. 61 Run No. 61 Run No. 61 Run No. 61 Loss of Coolant Accident Source: Unit 1 Main Vent 8.90E-04 6.35E-04 5.36E-04 3.72E-04 Receptor: Unit 2 Control Room Air Intake Flow: 42.48 m 3/sec, all time periods Run No. 62 Run No. 62 Run No. 62 Run No. 62 Loss of Coolant Accident Source: Unit 2 Main Vent 8.72E-04 6.22E-04 5.25E-04 3.63E-04 Receptor: Unit I Control Room Air Intake Flow: 42.48 m 3/sec, all time periods Run No. 63 Run No. 63 Run No. 63 Run No. 63 Loss of Coolant Accident Source: Unit 2 Main Vent 1.69E-03 l.20E-03 l.02E-03 7.04E-04 Receptor: Unit 2 Control Room Air Intake Flow: 42.48 m 3/sec, all time periods Run No. 64 Run No. 64 Run No. 64 Run No. 64 (Rev. 1, 3/ 12/96) 4-30day (26 daz1}

3.09E-03 Run No. 60

4. l 9E-04 Run No. 61 2.20E-04 Run No. 62

2. lSE-04 Run No. 63

4. lSE-04 Run No. 64 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Salem Generating Station Control Room Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0 - 2 hr 2-8hr 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr)

(3 dau)

Hope Creek Source: Hope Creek FRVS 4.54E-05 3.23E-05 2.72E-05 1.88E-05 Receptor: Unit I Control Room Air Intake Flow:

1. 59 m3 /sec, all time periods Run No. 65 Run No. 65 Run No. 65 Run No. 65 Hope Creek Source: Hope Creek FRVS 5.23E-05 3.72E-05 3.14E-05 2.17E-05 Receptor: Unit 2 Control Room Air Intake Flow:

1.59 m 3 /sec, all time periods Run No. 66 Run No. 66 Run No. 66 Run No. 66 Hope Creek Source: Hope Creek Main Steam Blowout 5.18E-05 3.78E-05 3.23E-05 2.30E-05 Receptor: Unit I Control Room Air Intake Flow: 28.32 m 3/sec, all time periods Run No. 67 Run No. 67 Run No. 67 Run No. 67 Hope Creek Source: Hope Creek Main Steam Blowout 6.13E-05 4.46E-05 3.81E-05 2.70E-05 Receptor: Unit 2 Control Room Air Intake Flow: 28.32 m 3 /sec, all time periods Run No. 68 Run No. 68 Run No. 68 Run No. 68 (Rev. l, 3/ 12/96) 4-30 day (26 day) 1.1 lE-05 Run No. 65 l.28E-05 Run No. 66 1.41E-05 Run No. 67 1.65E-05 Run No. 68 METEOROLOGICAL EVALUATION SERVICES

Table 3 (continued)

Salem Generating Station Control Romn Habitability Analysis 95th Percentile X/Q Values by Accident Scenario 0 - 2 hr 2-8 hi" 8-24 hr 1-4 day Accident Scenario (2 hr)

(8 hr)

(16 hr}

(3 da11}

Salem Smoke Hatch Source: Unit I Smoke Hatch l.15E-02 8.24E-03 6.97E-03 4.85E-03 Receptor: Unit 1 Control Room Air Intake Flow:

1.43 m:l /sec, all time periods Run No. 69 Run No. 69 Run No. 69 Run No. 69 Salem Smoke Hatch Source: Unit 1 Smoke Hatch 2.00E-03 1.45E-03 l.23E-03 8.67E-04 Receptor: Unit 2 Control Room Air Intake Flow:

1.43 m:1 /sec, all time periods Run No. 70 Run No. 70 Run No. 70 Run No. 70 Salem Smoke Hatch Source: Unit 2 Smoke Hatch 2.00E-03 1.45E-03 l.24E-03 8.75E-04 Receptor: Unit I Control Room Air Intake Flow:

1.43 m 3 /sec, all time periods Run No. 71 Run No. 71 Run No. 71 Run No. 71 Salem Smoke Hatch Source: Unit 2 Smoke Hatch l.14E-02 8.23E-03 6.99E-03 4.90E-03 Receptor: Unit 2 Control Room Air Intake Flow:

1.43 m3/sec, all time periods RunNo. 72 Run No. 72 Run No. 72 Run No. 72 (Rev. l, 3/ 12/96) 4-30 day (26 day) 2.88E-03 Run No. 69 5.24E-04 Run No. 70 5.32E-04 Run No. 71 2.95E-03 Run No. 72 METEOROLOGICAL EVALUATION SERVICES

Table 4 Salem Generating Station Control Room Habitability Analysis Plume Rise Values for Main Steam Safety Value Releases Number Total Flow Per Vertical of Active Flow Valve Velocity Accident Scenario Valves (m 3/sec)

(m.3/sec)

(ml sec)

Loss of Non-Emergency AC Power 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4

77.37 19.34 381.73 Loss of Non-Emergency AC Power 2 - 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months 4

21.29 5.32 10~.04 Steam Generator Tube Release One Faulted Steam Generator 1

26.69 26.69 526.73 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Steam Generator Tube Release Three Intact Steam Generators 3

54.97 18.32 361.62 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Steam Generator Tube Release Three Intact Steam Generators 3

41.57 13.86 273.46 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Steam Generator Tube Release Three In tact Steam Generators 3

20.98 6.99 138.02 8 - 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months Final Pe1*ce11t Plume lit of Cavity (ft agl)

Height 145.2 69 88.8 32 161.6 80 141.7 67 125.7 56 97.1 37 METEOROLOGICAL EVALUATION SERVICES

Table 4 (continued)

Salem Generating Station Control Room Habitability Analysis Plume Rise Values for Main Steam Safety Value Releases Number Total Flow Per Vertical of Active Flow Value Velocity Accident Scenario Values (1113/sec)

(m3/sec)

(ml sec)

Control Rod Ejection 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 20 3898.7 194.93 3847.09 Main Steam Line Break Three Intact Steam Generators 3

59.04 19.68 388.38 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Main Stea1n Line Break Three Intact Steam Generators 3

17.81 5.94 117.16 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Main Steam Line Break Three Intact Steam Generators 3

26.68 9.89 195.24 8 - 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months Final Pe1*cent Plume lit of Cavity (ft a!!l)

I/eight

161.6 80 146.3 70 91.9 34 110.0 46

METEOROLOGICAL EVALUATION SERVICES

Unit 2 Plant Vent Figure I Salem Generating Station Overview of Source/Receptor Relationships Unit 2 Penetration Area Pressure Relief Main Steam Safety Valve Set No. 2 Unit 2 Unit 1 Smoke Hatches Unit 2 Unit 1 Auxilary Building

= Receptors Unit 1 Penetration Area Pressure Relief Unit 1 Plant Vent N 4--<-----

Plant North

= Release Points 100 Feet METEOROLOGICAL EVALUATION SERVICES

Figure 2 Salem/Hope Creek Plot Plan Showing Relationship of Hope Creek Unit 1 With Salem Control Room Air Intakes

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METEOROLOGICAL EVALUATION SERVICES

FVRS Exhaust Figure 3 Hope Creek Generating Station Cross Sectional View Showing Release Points I

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View From West View From South METEOROLOGICAL EVALUATION SERVICES

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300 Elevation Above Plant Grade (ft.)

200 100 0

100 200 300 400 500 Receptor Distance Downwind (ft)

Figure 4a - Plume Rise Assumptions for Main Steam Safety Valve Releases 300 Elevation Above Plant Grade (ft.)

200 100 0

100 200 300 400 500 Receptor Distance Downwind (ft)

Figure 4b - Illustration of the "Slant Range" Concept Used in ARCON95 Model 300 Elevation Above Plant Grade (ft.)

200 100 0

Ground Level XJQ at

---., /"Sl'"l..,,,.. R*~pt~ Oi>t."~

100 200 300 400 500 Receptor Distance Downwind (ft)

Figure 4c - Illustration of Actual Treatment of Vent Releases in ARCON95 METEOROLOGICAL EVALUATION SERVICES

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t Table 5 Salem LOCA Analysis Parameters Parameter Containment Containment Volume Activity Release Paths and Associated Source Terms Containment Pressure Relief Line Discharge Containment Leakage ESF Leakage/Sump Iodine Form/Source RCS Core/Containment Atmosphere Elemental Particulate Organic Evolve from Sump (from ESF Leakage)

Containment Leakage Containment Leakage Filtration Containment Leakage Release Path Spray Initiation Time Spray Coverage (Single Spray Train operational)

Spray Flow (Single Spray Train) 1of4 Value 2.6E+06 ft3 RCS Activity (with pre-accident iodine spike) homogeneously dispersed 100% Noble Gas/Core 25% Halogens/Core (after plateout DF = 2) 50% Halogens/Core 100% Elemental 91%

5%

4%

100% Elemental 0.1 %/c;f for 181 d 0.05%/d for duration 0%

Unit 1 Vent 90 sec 0.6 2460 gpm

Table 5 Salem LOCA Analysis Parameters Iodine Removal Lambda, h(1 During Spray Injection Phase Elemental Particulate Organic Gravitational Particulate Maximum Allowed OF for Airborne Iodine Removal Injection Spray Cutoff Time (Single Spray Train)

Mixing Rate Between Sprayed and Unsprayed Regions Sump Volume Long Term sump pH ESF Leakage (Maximum Expected x 2)

Fraction of ESF Leakage That Becomes Airborne Duration of ESF Leakage ESF Filter Efficiency Fraction of Airborne ESF Leakage Release Filtered ESF Leakage Release Pathway Duration of Release via the Containment Vacuum Relief Line Containment Atmosphere Release Volume via the Containment Vacuum Relief Line Containment Vacuum Relief Line Release Filtration Efficiency 2 of 4 20 6.7 0.0 0.06 100 48 min 117,000 cfm 295,000 gal

~ 7.0 7680 cc/hr 0.1 18 min to 30 Days 90%, All Iodine Forms 0.0 First 30 min 0.5 After 30 min Unit 1 Vent 5 sec 1014 ft3 0%

Table 5 Salem LOCA Analysis Parameters Control Room Envelope Volume Control Room Occupancy Factors 0 - 8 hrs 8 - 24 hrs 1 - 4 days 4 - 30 days Control Room Control Room Breathing Rate (0 - 30 days)

Normal Operation Intake Flow (unfiltered)

Control Room Pressurization Mode Actuation Signal (LOCA)

Control Room Damper Closure Time Time for Diesel Generator Fully Operational after LOOP Time for EACS fans to Reach Full Speed after Start Filtered Emergency Makeup Flow to support Pressurization Filter Recirculation Flow 1 train operational 2 trains operational EACS Filter Efficiency Unfiltered lnleakage 3 of 4 81,420 ft3 1

1 0.6 0.4 3.47E-04 m3/sec 1,200 cfm SIS 20 secs 13 sec 15 sec 2,500 cfm 5,500 cfm 13,500 cfm 95% for all iodine forms 60 cfm

Table 5 Salem LOCA Analysis Parameters Physical Data for Submersion and Inhalation Dose Conversion Nuclide 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Kr-85m Kr-85 Kr-87 Kr-88 Average Beta Energy*

MeV/dis l.82E-1 4.87E-1 4.07E-1 6.08E-1 3.68E-1 l.42E-1 l.OOE-1 l.90E-1 3.03E-1 2.55E-1 2.50E-1 l.32E+O 3.59E-1 Average Gamma Thyroid Dose Energy*

Factor (ICRP30)**

MeV/dis rem/Ci 3.81E-1 l.08E+6 2.26E+O 6.44E+3 6.03E-1 l.80E+5 2.60E+O l.07E+3 1.56E+O 3.13E+4 2.0lE-2 4.52E-2 4.15E-2 2.47E-1 l.58E-1 2.23E-3 7.83E-1 l.94E+O DOE/TIC-11206, Kocher, D.C. - Radioactive Decay Tables - A Handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessments - 1981 EPA-520/1-88-020, Federal Guidance Report No. 11, Eckerman et al.,

Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, 1988 4 of 4

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Number of Pages (Including cover sheet)

DATE: _&..J__/_cJ-_¥ li_f_(o __

TO: ~~

Licensing & Regulation Fax# (609) 339-1448 LOCATION: __

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Phone/Fax# -----------------

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ML18102A211

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