ML20138F100

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Revs 10 & 11 to ODCM, Part 2
ML20138F100
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 12/13/1996
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20138F075 List:
References
PROC-961213, NUDOCS 9705050261
Download: ML20138F100 (19)
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Text

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ATTACIIMENT 1 VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 1996 ANNUAL REPORT - PART 2 OFFSITE DOSE CALCULATION MANUAL - REVISION 10 & 11 l

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9705050261 970428 PDR ADOCK 05000424 8 PDR

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OFFSITE DOSE CALCULATION MANUAL FOR ,

SOUTHERN NUCLEAR OPERATING COMPANY  ;

VOGTLE ELECTRIC GENERATING PLANT l

1 Revision 11 December 13, 1996 l

4 VEGP ODCM DISTRIBUTION LIST 1

1. Paul D. Rushton
~ 6. VEGP Main Control Room Podium
7. Nancy D. Lacey
8. William L. Burmeister
9. Robert C. Hand
10. Primary Chemistry Lab
11. Service Bldg. (Chemistry)
12. Indira Kochery
13. Bruce L. Kaplan
14. Bob Brown
15. James A. Bailey
16. Ravi Grover
17. Charles S. Myers, Jr.
18. VEGP Document control
19. Dudley Carter i 20. Anthony S. Parton

, 21. Joe B. Sills

22. Dwight Hostetter )
23. Michael C. Nichols i
24. Shan Sundaram ]
28. Alan V. Fowler
29. Steve White 1

i I

i Rev. 11

VEGP ODCM REVISION LOG Revision Number Date 0 8/85 1 8/86 2 11/86 3 3/87 4 7/87 5 '10/87 6- 9/88 7 3/91 8 2/93 9 1/94 10 2/96 11 12/96 11 Rev. 11

VEGP ODCM REFERENCES

1. J.S. Boegli, R.R. Bellamy, W.L. Britz, and R.L. Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-Oll),, October 1978. l I

2.

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Fvaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Reculatory Guide 1.109, March 1976.

3.

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Reculatory Guide 1.109. Revision 1, October 1977.

4. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC Reculatorv Guide 1.111, March 1976.
5. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC Regulatory Guide 1.111, Revision 1, July 1977.
6. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," U.S. NRC Regulatorv Guide 1.113, April 1977.
7. W.R. Stokes III, T.W. Hale, J.L. Pearman, and G.R. Buell, " Water Resources Data, Georgia, Water Year 1983," U.S. Geological Survey Water Data Recort GA-83-1, June 1984.
8. Direct communication with the Water Resources Division, U.S. Geoloaical Su rvey, U.S. Department of the Interior, February 1985.
9. Bernd Kahn, et al., Bioaccumulation of P-32 in Bluegill and Catfish,"

NUREG/CR-3981, February 1985.

10. Memo from S.E. Ewald, Georgia Power Company, to C.C. Eckert, Georgia Power Company, May 9, 1988.
11. Voctle Electric Generatina Plant Units 1 and 2 Final Safety Analysis Reoort, Georgia Power Company.

1 1

12. Voetle Electric Generatina Plant Units 1 and 2 Environmental Reoort -

Operatino License Stace, Georgia Power Company. 1 I

13. Memo from A.C. Stalker, Georgia Power Company, to D.F. Hallman, Georgia Power Company, May 9, 1988.
14. Vootle Electric Generatinc Plant Land Use Survey - 1988, Georgia Power  !

Company, April 1988. l l

15. Letter to Southern Comoany Services from Pickard, Lowe. and Garrick, IngA, Washington, D.C., April 27, 1988. I
16. Letter to Bill Ollinger, Georgia Power Company, from T.L. Broadwell, l Georgia Power Company, Atlanta, Georgia, June 22, 1988.
17. Letter to Bill Ollinger, Georgia Power Company, from R.D. Just, Georgia Power Company, Atlanta, Georgia, July 8, 1988.
18. L.A. Currie, Lower Limit of Detection: Definition and Elaboration of a Proposed Position of Radiological Effluent and Environmental Measurements, U.S. NRC Report NUREG/CR-4007, 1984.

ix Rev. 11

VEGP ODCM CHAPTER 2 LIOUID EFFLUENTS 2.1 LIMITS OF OPERATION The following Liquid Effluent Controls implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10.

l 2.1.1 Licuid Effluent Monitorino Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive liquid l effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits specified in Section 2.1.2 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 2.3.

2.1.1.1 Applicability This limit applies at all times. '

2.1.1.2 Actions With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint to a conservative value.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. Restore the INOPERABLE instrumentation to OPERABLE status within 30 days, or if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a timely manner. l This control does not affect shutdown requirements or MODE changes.

2.1.1.3 Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL 2-1 Rev. 11

VEGP ODCM Table 2-2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Surveillance Requirementsd Instrument CHANNEL CHANNEL SOURCE k CHANNEL OPERATIONAL CHECK CHECK CALIBRATION TEST

1. Radwaste Monitors Providing Alarm and Automatic Termination of Release
a. Liquid Radwaste Effluent Line (RE-0018) D P RD Qa(1)
b. Steam Generator Blowdown Effluent Line (RE-0021) D M Rb ga(1)
c. Turbine Building Effluent Line (RE-0848) D M RD ga(1)
2. Radwaste Monitors Providing Alarm, but Not Automatic Termination of Release NSCW Effluent Line (RE-0020 A&B) D M Rb ga(2)
3. Flowrate Measuremena Devices
a. Liquid Radwaste Effluent Line (FT-0018),

(FT-1035), or (FT-1036) DC NA R NA

b. Steam Generator Blowdown Effluent Line (FT-0021) DC NA R NA
c. Flow to Blowdown Sump (AFQI-7620, FR7620 pen 1) DC NA R Q i

I 2-5 Rev. 11

VEGP ODCM Table 2-2 (contd). Notation for Table 2-2

a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section 10.2) : l (1)

The CHANNEL isolation of thisOPERATIONAL TEST pathway (for item shall also a below demonstrate only) and controlthat automatic l room alarm annunciation occur if any of the following conditions exists:

(a) Instrument indicates measured levels above the alarm / trip setpoint; (b) Circuit failures (c) Instrument indicates a downscale frilure; or (d) Instrument controls not set in operate mode.

(Annunciation via computer printout.)  !

(2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions l {

exists:

(a) Instrument indicates measured levels above the alarm / trip setpoint; (b) Circuit failure; 1 (c) Instrument indicates a downscale failure; or (d) Instrument controls not set in operate mode.

(Annunciation via computer printout.)

b. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurements assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
c. CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
d. All requirements in this table apply to each unit.

2-6 Rev. 11

VEGP ODCM 2.1.2 Licuid Effluent Concentration Control In accordance with Technical Specifications 5.5.4.b and 5.5.4.c, the l concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 x 10-4 gCi/mL total activity.

2.1.2.1 Applicability _

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This limit applies at all times.

2.1.2.2 Actions With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the limits stated in Section 2.1.2, immediately restore the concentration to within the stated limits.

This control does not affect shutdown requirements or MODE changes.

2.1.2.3 Surveillance Requirements The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 2-3. The results of radioactive analyses shall be used with the calculational methods in Section 2.3 to assure that the concentration at the point of release is maintained within the limits of Section 2.1.2.

2.1.2.4 Basis This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II. A design objectives of Appendix I,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was conserted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2 (1959). The resulting concentration of 2 x 10-4 was then 2-7 Rev. 11

VEGP ODCM 2.1.3 Licuid Effluent Dose Control In accordance with Technical Specifications 5.5.4.d and 5.5.4.e, the dose or dose l commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

2.1.3.1 Applicability These limits apply at all times.

2.1.3.2 Actions With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the limits of Section 2.1.3, prepare and submit to the Nuclear Regulatory Commission within 30 days a special report which identifies l the cause(s) for exceeding the limit (s); defines the corrective actions to be taken to reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits of Section 2.1.3.

This control does not affect shutdown requirements or MODE changes.

2.1.3.3 Surveillance Requirements At.least once per 31 days, cumulative dose contributions from liquid effluents for the current calendar quatter and the current calendar year shall be determined, for each unit, in accordance with Section 2.4.

2.1.3.4 Basis This control is provided to implement the requirements of Sections II.A, III.A and IV. A of Appendix I, 10 CFR Part 50. The limits stated in Section 2.1.3 implement the guides set forth in Section II. A of Appendix I. The ACTIONS stated in Section 2.1.3.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water 2-11 Rev. 11

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c VEGP ODCM j 2.1.4 Licuid Radwaste Treatment System Control In accordance with Technical Specification 5.5.4.f, the LIQUID RADWASTE TREATMENT l SYSTEM shall be OPERABLE. The appropriate portions of the system shall be used l to reduce. radioactivity in liquid wastes prior to their discharge when the d

projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ of a MEMBER OF

. THE PUBLIC in 31 days.

, 2.1.4.1 Applicability

This limit applies at all times.

i- 2.1.4.2 Actions i

With radioactive liquid waste being discharged without treatment and in excess i of the above limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not t

in operation, prepare and submit to the Nuclear Regulatory Commission within 30 days a special report which includes the following information: l

a. Explanation of why liquid radwaste was being discharged without treatment, l identification of any inoperable equipment or subsystems and the reason for the inoperability, 4

i b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s)~taken to prevent a recurrence.

This control does not affect shutdown requirements or MODE changes.

2.1.4.3 Surveillance Requirements 1.

I

. Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with Section 2.5, during periods in which the LIQUID RADWASTE TREATMENT SYSTEMS are not being fully utilized.

2 The LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting the controls of Sections 2.1.2 and 2.1.3.

4 2-13 Rev. 11

VEGP ODCM CHAPTER 3 GASEOUS EFFLUENTS 3.1 LIMITS OF OPERATION The following Limits of Operation implement requirements established by Technical Specifications Section 5.0.

Terms printed in all capital letters are defined in l Chapter 10. I 3.1.1 Gaseous Effluent Monitorino Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive gaseous l

effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 3.1.2.a are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 3.3.

3.1.1.1 Applicability These limits apply as shown in Table 3-1.

3.1.1.2 Actions With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or restore the setpoint to a value that will ensure that the lir.iits of Section 3.1.2.a are met.

With less than the minimen number of radioactive gaseous effluent monitoring instrumentation channels OPRRABLE, take the ACTION shown in Table 3-1. Restore the inoperable instrumentation to operable status within 30 days, or if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a l

timely manner.

This control does not affect shutdown requirements or MODE changes.

3.1.1.3 Surveillance Requirements Each radioac ive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL 3-1 Rev. 11

VEGP ODCM Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Surveillance Requirements CHANNEL Instrument CHANNEL OPERA-l CHANNEL SOURCE CALIBRA- TIONAL CHECK CHECK TION TEST MODES C

1. GASEOUS RADWASTE TREATMENT SYSTEM (Common)
a. Noble Gas Activity Monitor, with Alarm and Automatic Termination of During Release (ARE-0014) P P Rb Qa(I) Rhn
b. Effluent System Flowrate Measuring Device During (AFT-0014) P NA R NA Release
2. Turbine Building Vent (Each Unit)
a. Noble Gas Activity During Rb Monitor (RE-12839C) D M Qa(2) Release '
b. Iodine and Particulate During Samplers (RE-12839A&B) NA NA NA Release i i
c. Flowrate Monitor During (FT-12839 or FIS-12862) D NA R NA Release
d. Sampler Flowrate During Monitor (FI-13211) D NA R O Release
3. Plant Vent (Each Unit)
a. Noble Gas Activity Monitor (RE-12442C or RE-12444C) D M RD Qa(2) g
b. Iodine Sampler /

Monitor (RE-12442B or RE-12444B) NA NA/R NA All

c. Particulate Sampler /

Monitor (RE-12442A or RE-12444A) NA NA/R Q All

d. Flowrate Monitor (FT-12442 or 12835) D NA R NA All
e. Sampler Flowrate Monitor (FI-12442 or FI-12444) D NA R 0 All 3-5 Rev. 11

VEGP ODCM Table 3-2 (contd). Notation for Table 3-2 '

a.

In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section 10.2): l

)

(1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway (for item a. below only) and control room l annunciation occur if any of the following conditions exists:

(a) Instrument indicates measured levels above the alarm / trip setpoint; 1

(b) Circuit failure; j (c) Instrument indicates a downscale failure; or (d) Instrument controls not set in operate mode.

(Annunciation via computer printout.)

(2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exists: l (a) Instrument indicates measured levels above the alarm / trip setpoint; I

l (b) circuit failure; '

I (c) Instrument indicates a downscale failure; or (d) Instrument controls not set in operate mode.

(Annunciation via computer printout. )

b. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology, or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For any subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used,
c. MODES in which surveillance is required. "All" means "At all times."

"During release" means "During radioactive release via this pathway."

d. The channel check shall consist of visually verifying that the collection device (i.e. , particulate filter or charcoal cartridge, etc.) is in place for sampling.

3-6 Rev. 11

VEGP ODCM 3.1.2 Gaseous Effluent Dose Rate Control In accordance with Technical Specifications 5.5.4.c and 5.5.4.g, the licensee l shall conduct operations so that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY are limited as follows:

a. For noble gases: Less than or equal to a dose rate of 500 mrem /y to the total body and less than or equal to a dose rate of 3000 mrem /y to the skin, and
b. For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem /y to any organ.

3.1.2.1 Applicability This limit applies at all times.

3.1.2.2 Actions With a dose rate due to radioactive material released in gaseous effluents exceeding the limit stated in Section 3.1.2, immediately decrease the release rate to within the stated limit.

These limits do not affect shutdown requirements or MODE changes.

3.1.2.3 Surveillance Requirements The dose rates due to radioactive materials in areas at or,beyond the SITE BOUNDARY due to releases of gaseous effluents shall be determined to be within the above limits, in accordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-3.

3.1.2.4 Basis This control is provided to ensure that gaseous effluent dose rates will be maintained within the limits that historically have provided reasonable assurance that radioactive material discharged in gaseous effluents will not result in a dose to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceeding the limits specified in Appendix I of 10 CFR Part 50, while allowing operational flexibility for effluent releases. For MEMBERS 3-7 Rev. 11

VEGP ODCM 3.1.3 Gaseous Effluent Air Dose Control i

In accordance with Technical Specifications 5.5.4.e and 5.5.4.h, the air dose due l

to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:  !

l

a. During any calendar quarter: Less than or equal to 5 mrad for gamma j radiation and less than or equal to 10 mrad for beta radiation, and  ;
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

l 3.1.3.1 Applicability )

This limit applies at all times.

l 3.1.3.2 Actions With the calculated air dose from radioactive noble gases in gaaeous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days a special report which identifies the cause(s) for l l exceeding the limit (s) ; defines the corrective actions that have been taken to I reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases of radioactive noble gases in gaseous effluents will be in compliance with the limits of Section 3.1.3.

This control does not affect shutdown requirements or MODE changes.

3.1.3.3 Surveillance Requirements Cumulative air dose contributions from noble gas radionuclides released in gaseous effluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in accordance with section 3.4.2 at least once per 31 days.

3.1.3.4 Basis

'This control is provided to implement the requirements of Sections II.B, III.A and IV. A of Appendix I,10 CFR Part 50. Section 3.1.3 implements the guides set

~

forth in Section II.B of Appendix I. The ACTION statements in Section 3.1.3.2 provide the required operating flexibility and at the same time implement the iTuides set forth in Section IV. A of Appendix I, assuring that the releases of 3-11 Rev. 11

VEGP ODCM 3.1.4 Control on Gaseous Effluent Dose to a Member of the Public In accordance with Technical Specifications 5.5.4.e and 5.5.4.1, the dose to a l MEMBER OF THE .PUBLIC from I-131, I-133, tritium, and all radionuclides in  ;

4 particulate form with half-lives greater than 8. days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall

'be limited to the followings j

-a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, I and I

b. During any calendar year: Less than or equal to 15 mrem to any organ.

3.1.4.1 Applicability l

This l'imit applies at all times. I 3.1.4.2 Actions With the calculated dose from the release of I-131, I-133, tritium, or radio-nuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days a special report which identifies the l cause(s) for exceeding the limit; defines the corrective actions that have been taken to reduce the releases of radiciodines and radionuclides in particulate form with half-lives greater than 8 . days in gaseous effluents; and defines proposed corrective actions to assure that subsequent releases will be in compliance with the limits stated in Section 3.1.4.

This control does not affect shutdown requirements or MODE changes.

3.1.4.3 Surveillance Requirements Cumulative organ dose contributions to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and radionuclides in particulate fom with half-lives greater than 8 days released in gaseous effluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in accordance with Section 3.4.3 at least once per 31 days.

3-13 Rev. 11

VEGP ODCM 3.1.5 Gaseous Radwaste Treatment System Control In accordance with Technical Specification 5.5.4.f, the GASEOUS WASTE PROCESSING l 4 SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS WASTE PROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous wastes prior to their discharge when the projected doses in 31 days due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY would exceed 0.2 mrad to air from gamma radiation, 0.4 mrad to air from beta radiation, or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

3.1.5.1 Applicability These limits apply at all times.

3.1.5.2 Actions

, With gaseous waste being discharged without treatment and in excess of the limits in Section 3.1.5, prepare and submit to the Nuclear Regulatory Commission within

} 30 days a special report which includes the following information:

l

a. Identification of any inoperable equipment or subsystem and the reason for
inoperability,
b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
c. Summary description of action (s) taken to prevent a recurrence.

This control does not affect shutdown requirements or MODE changes.

3.1.5.3 Surveillance Requirements Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days, in accordance with Section 3.5.1, when the GASEOUS WASTE PROCESSING SYSTEM or the VENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.

The GASEOUS WASTE PROCESSING SYSTEM and the VENTILATION EXHAUST TREA*1NENT SYSTEM shall be demonstrated OPERABLE:

3-15 Rev. 11

I l

l I

l VEGP ODCM ii Table 3-7. Attributes of the Controlling Receptor i

The locations of members of the public in the vicinity of the plant site, and the exposure pathways associated with those locations, are determined in the Annual Land Use Census. Dispersion and deposition values were calculated based on site meteorological data collected for the period January 1, 1985 through December 31, l 1987 Based on an analysis of this information, the current controlling receptor for the plant site is described as follows (References 14, 15, 16, and 17).

Sector: WSW Distance: 1.2 miles Ace Group: Child Exposure Pathways: Inhalation and ground plane Discersion Factors (576) 9 :

Ground-Level release points: 6.20 x 10~7 s/m 3 l Mixed-Mode release points: 1.27 x 10"7 s/m3 l Deposition Factors (676) 9 :

Ground-Level release points: 2.80 x 10"9 m"2 l Mixed-Mode release points: 9.90 x 10-10 m -2 l l

3-43 Rev. 10 l

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