ML20108A019

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Radiological Effluent Control Manual
ML20108A019
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/13/1996
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20107N199 List:
References
PROC-960313, NUDOCS 9605020059
Download: ML20108A019 (36)
v • d • e


Text

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0 l POINT BEACH NUCLEAR PLANT .,

UNIT 1 AND 2 4

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$ RADIOLOGICAL EFFLUENT CONTROL MANUAL I i

j WISCONSIN ELECTRIC l j

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March 13,1996 l REVISION 0 DRAFT i

i 9605020059 960424 PDR ADOCK 05000266 p PDR j

I POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR l MANUAL Revision 0 DRAFT  ;

l March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE OF CONTENTS l

l l

PAGE l 1.0 RADIOLOGICAL EFFLUENT CONTROL PROGRAM ............... 1 l

1.1 Basis . . . . . . . . . . . . ..... . . .......... ....... 1 i

l 1.2 Basis Statement ............. .. ................... 1 1.3 Responsibilities .... ............................... 3 1.4 Manual Revisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... 3 1.5 RECP Parameters Reportable in the Annual Monitoring Report ...... 4 1.6 Other RECP Reportable Events ...... ........... ..... 6 2.0 RADIOACTIVE EFFLUENT CONTROL . ....................... 7

( 2.1 Liquid Radioactive Effluent Treatment System .. .......... ... 7 2.2 Gaseous Radioactive Effluent Treatment System . . ............. 7 2.3 Effluent Control and Accountability . . . . . . . . . . . . . . . . . . . . . . . . 8 l 3.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS . .....................13 3.1 Objective . . . . . . . . . . . . . . . . . . .. .... ........... . 13 3.2 Operability Specifications . . . . . . . . . . ..................13 4.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . .................... . 18 4.1 Objective .. .. ... ..... . . . ..... ... .. . 18 4.2 Radioactive Monitoring Instrumentation Surveillance Requirements . . . . 18 O

V 4.3 Definitions . . . . . . . . . . ... .. ..... .... ... .... 18

POINT BEACII NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL O

U PAGE 5.0 RADIOACTIVE EFFLUENT RELEASE LIMITS ..................23 5.1 Objective . . . . . . .... ............... ...........23 5.2 Radioactive Effluent Concentrations . . . . . . . . . . . . . . . . . . . . . . 23 5.3 Radioactive Liquid Effluent Release Limits .............. . . . 23 5.4 Radioactive Gaseous Effluent Concentrations .... . . . . . . . . . . . . 24 5.5 Radioactive Gaseous Effluent Release Limits . . . . . . . . . . . . . . . . 24 5.6 Quarterly Summary . . ........... .................25 5.7 Radioactive Effluent Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . 25 5.8 Total Do se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 5.9 Explosive Gas Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 5.10 Solid Radioactive Waste . . . . . . . ......................27 6.0 RADIOACTIVE EFFLUENT SAMPLING AND ANALYSIS REQUIREMENTS 28 f 6.1 Purpose . ... .. . .... ... . ...... .... . .... ..... ... . . 28 6.2 Radioactive Liquid Waste Sampling and Analysis .. ...........28 J

6.3 Radioactive Gaseous Waste Sampling and Analysis ............ . 28

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1 POINT BEACH NUCLEAR PLANT RECM {

RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL l

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LIST OF TABLES AND FIGURES j SECTION 2.0 PAGE Table 2-1 Radioactive Liquid Waste Effluent Monitors .................. 9 Figure 2-1 Radioactive Liquid Waste Effluent Monitors ............. . . . 10 Table 2-2 Radioactive Gaseous Waste Effluent Monitors ... .. .........11 1 Figure 2-2 Radioactive Gaseous Waste Effluent Monitors ............ . . . 12 SECTION 3.0 Table 3-1 Radioactive Liquid Waste Effluent Monitoring Instrumentation . . . . . . 14 ;

Table 3-2 Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . 15 SECTION 4.0 Table 4-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ........... ............. . . 19 Table 4-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .......... . . . . . . . 20 I

SECTION 6.0 Table 6-1 Radioactive Liquid Waste Sampling and Analysis Program . . . . . . . . . 29 Table 6-2 Radioactive Gaseous Waste Sampling and Analysis Program . . . . . . . . 31 1

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1 POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL

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1.0 RADIOLOGICAL EFFLUENT CONTROL PROGRAM 1.1 Basis The Radiological Effluent Control Program (RECP) shall conform to 10 CFR 50.36a for th control of radioactive effluents and maintaining doses to members of the public from radioactive effluents as low as reasonably achievable (ALARA). The RECP also is established to control the amount and concentrations of radioactivity in PBNP effluent pursuant to the following documents:

1.1.1 10 CFR 50.34a-Design objectives for equipment to control releases of radioactive material in effluents-nuclear power reactors,  !

1.1.2 10 CFR 50, Appendix A, Criterion 60-Control of releases of radioactive material to the environment, 1.1.3 10 CFR 50, Appendix A, Criterion 63-Monitoring fuel and waste storage,  !

l 1.1.4 10 CFR 50, Appendix A, Criterion 64-Monitoring radioactivity releases, 1.1.5 10 CFR 20.1302-Compliance with dose limits for individual b members of the public, j 1.1.6 16 CFR 20.1501-General, 1.1.7 PBNP General Design Criterion 17-Monitoring Radioactivity I Releases, and 1.1.8 PBNP General Design Criterion 70-Control of releases of radioactivity to the environment.

1.2 Basis Statement Liquid effluent from the radioactive waste disposal system are diluted by the circulating water system prior to release to Lake Michigan. With two pumps operating per unit, the rated Gow of the circulating water system is approxi- J mately 340,000 gpm per unit. Operation of a single circulating water pump per unit reduces the nominal flow rate by about 40%. Liquid waste from the waste disposal system may be discharged to the circulating water system of either unit via the service water return header. Because of the low radioactivity levels in the circulating water discharge, the concentrations of ;

liquid radioactive effluents at this point are not measured directly. Instead, i the concentrations in the circulating water discharge are calculated from the measured concentration of the liquid effluent, the discharge flow rate of the effluent and the nominal Dow in the circulating water system.

Page 1 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 c RADIOLOGICAL EFFLUENT CONTROL MANUAL I%^)l The release of radioactive materials in liquid effluents to unrestricted areas is monitored and controlled to conform to the dose objectives in Section II.A of Appendix I to 10 CFR 50 and will be as low as reasonably achievable ]

(ALARA) in accordance with the requirements of 10 CFR Parts 50.34a and 50.36a. The monitoring and control also is undertaken to keep the i

concentrations of radionuclides in PBNP liquid effluent released to l unrestricted areas conforming to the maximum effluent concentration (MEC) values specified in Table 2, Column 2 of Appendix B to 10 CFR 20.

Furthermore, the appropriate portions of the liquid radwaste treatment systems will be used as required to keep the releases ALARA.

These actions provide reasonable assurance that the resulting average annual dose or dose commitment from liquid effluent from each unit of the Point Beach Nuclear Plant for any individual in an unrestricted area from all pathways of exposure will not exceed the 10 CFR 50, Appendix I dose objectives. Thus, discharge of liquid wastes not exceeding these release limits will not result in significant exposure to members of the public as a result of consumption of drinking water from the lake, even if the effect of potable water treatment systems on reducing radioactive concentrations of the water supply is conservatively neglected.

Prior to release to the atmosphere, gaseous wastes are mixed in the auxiliary building vent with the now from at least one of two auxiliary building exhaust fans. Further dilution then occurs in the atmosphere. Release of radionuclides to the atmosphere is monitored and controlled so that effluents to unrestricted areas conform to the dose objectives of Sections II.B and C of Appendix I to 10 CFR 50. Monitoring and control also is undertaken to ensure that at the point of maximum ground concentration at the site boundary, the radionuclide concentrations in the atmosphere will conform to the limits specified in Table 2, Column 1 of Appendix B to 10 CFR 20.

Furthermore, the appropriate portions of the gaseous radwaste treatment system are used as required to keep the radioactive releases to the atmosphere ALARA.

In order to achieve the dose objectives of Appendix I to 10 CFR 50 and the aforementioned concentration limits, the setpoints for releases to the atmosphere and to Lake Michigan utilize the methodology found in the Offsite Dose Calculation Manual. Setpoints for releases to the atmosphere are based on the dilution provided by building vents as well as the highest annual average x/Q at the site boundary. Setpoints for releases to Lake Michigan are based only on dilution by circulation water. Together, control and monitoring provide reasonable assurance that the annual dose from each unit's effluents, to an individual in an unrestricted area will not exceed the dose objectives of O Appendix I to 10 CFR 50.

Page 2 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 n RADIOLOGICAL EFFLUENT CONTROL MANUAL h Implementation of the RECP will keep average annual releases of radioactive material in PBNP effluents and their resultant committed effective dose equivalents at small percentages of the dose limits specified in 10 CFR 20.1301. At the same time, the methodology of implementing the RECP permits the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such numerical guides for design objectives set forth in Appendix I but still within levels that assure that the average population exposure is equivalent to small fractions of doses from natural background radiation.

Compliance with the provisions of Appendix I to 10 CFR Part 50 constitutes adequate demonstration of conformance to the standards set forth in 40 CFR Part 190 regarding the dose commitment to individuals from the uranium fuel cycle.

1.3 hsponsibilities l All required actions of the Radiological Effluent Control Program shall be conducted using approved procedures. The responsibility for the implementation of the approved procedures reside with the Manager-PBNP.

( 1.4 Manual Revisions 1.4.1 Revisions of the RECM shall be documented and reviews performed of the revisions shall be retained as required by TS 15.7.8.6. The review documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the revision, and
b. A determination that the change will maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302,10 CFR 50.36a, Appendix I to 10 CFR 50, and 40 CFR 190. l l

1.4.2 Revisions shall become effective after review and approval pursuant to the appropriate PBNP administrative procedure and T.S. 15.7. 8.7.

1.4.3 Revisions shall be submitted to the NRC in the form of a complete, ,

legible copy of the entire manual either as part of, or concurrent i with, the Annual Monitoring Report for the period of the report in which the revision was made. Each change shall be identified by q markings in the margin of the affected pages, clearly indication the Q area of the page that was changed. Each copy shall indicate the date the revision was implemented.

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Page 3 of 32 INFORMATION USE

, 1 POINT BEACH NUCLEAR PLANT RECM RADIOLGGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 1.5 RECP Parameters Reportable in the Annual Monitorine Report

't Information relative to the monthly quantities of liquid, gaseous, and solid

. radioactive effluents released from PBNP and effluent volumes used in maintaining the releases within 10 CFR 20 limits shall be reported in the Annual Monitoring Report as follows:

1.5.1 Liquid Releases

a. Total radioactivity in curies released and average diluted discharge concentrations of the following release categories:

gamma isotopic, gross alpha, tritium, and strontium (beta

, emitters other than tritium).

b. Total volume (in gallons) of liquid waste released into circulating water discharge. I i
c. Total volume (in gallons) of dilution water used.
d. The maximum concentration of tritium and gross gamma g radioactivity released (averaged over the period of a single )

( release).

u

e. Estimated monthly total radioactivity in curies of individual
radionuclides released based on representative isotopic analyses,
f. Semiannual and annual totals of monthly quantities of individual radionuclides, as determined by isotopic analyses.

1.5.2 Releases to the Atmosphere

a. Total radioactivity (in Curies), by month, released of:
1. Noble Gases.
2. Halogens.
3. Particulates, subdivided into beta emitters (strontium, etc.),

gross alpha, and gamma emitters.

4. Tritium.

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LJ Page 4 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL

b. Maximum release rate (for any one-hour period).
c. Estimated monthly total radioactivity (in Curies) released, by nuclide, based on representative analyses performed by beta and by gamma isotopic analyses.
d. Semi-annual and annual totals of monthly isotopic radionuclide quantities.

', 1.5.3 Solid Waste

a. The total amount of solid waste shipped, buried, or stored (in cubic feet).
b. Estimated total radioactivity and isotopic content (in Curies) determined by scaling factors, gamma isotopic and/or other suitable analyses.
c. The dates of shipment and burial site if shipped for burial.

4 g d. The type of waste shall be indicated, i.e., dry activated waste, g resins, evaporator concentrates, filters, scrap metal, asbestos, etc.

l 4 1.5.4 Doses l

The air doses and the doses to the hypothetical maximum exposed individual calculated following the ODCM methodology shall be

! reported.

1.5.5 Explosive Gas Monitoring In accordance with note 7 to Table 3-2, a Special Circumstance Report shall be included in the Annual Monitoring Report if the Waste Gas Holdup System Explosive Gas Monitor is out of service for greater than 14 days.

iO V

Page 5 of 32 INFORMATION USE

S POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 0 1.6 Other RECP Reportable Events 1.6.1 Radioactive Effluent Non-Treatment If the effluent treatment system for radioactive liquids or for releases to the atmosphere is inoperable and effluents are being discharged for 31 days without the treatment required to meet the release limits specified in Section 5, a special report shall be prepared and submitted to the Commission within thirty days which includes the following information:

a. Identification of the inoperable equipment or subsystem and the reason for inoperability.
b. Actions taken to restore the inoperable equipment to operable status,
c. Summary description of actions taken to prevent a recurrence.

1.6.2 Radioactive Effluent Release Limit Exceedence O

/ If the quantity of radioactive material actually released in liquid or gaseous effluents during any calendar quarter exceeds twice the quarterly limit as specified in Section 5, a special report shall be l prepared and submitted to the Commission within thirty days of i determination of the release quantity. I 1.6.3 Major Change to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous, and solid) shall be reported to the U.S.

Nuclear Regulatory Commission with the annual update to the l FSAR for the period in which the major change was complete. The i discussion of each change shall include:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;
b. Information necessary to support the reason for the change;

,q c. A description of the equipment, components and processes b/ involved and the interfaces with other plant systems; Page 6 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 9 d. An evaluation of the change, which shows how the predicted releases of radioactive materials in liquid effluents and gaseous effluents and/or quantity of solid waste will differ from those previously predicted in the license application and am?ndments thereto;

e. An evaluation of the change, which shows the expected maximum exposures to an individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; '
f. An estimate of the exposure to plant operating personnel as a result of the change.

2.0 RADIOACTIVE EFFLUENT CONTROL 2.1 Liauid Radioactive Effluent Treatment System The liquid radioactive effluent treatment system consists of those components or devices used to reduce radioactive material in liquid effluent. The system consists of the following:

b' 2.1.1 blowdown evaporator or waste evaporator, 2.1.2 polishing demineralizers, 2.1.3 boric acid evaporator feed demineralizers, 2.1.4 boric acid evaporators, 2.1.5 boric acid evaporator condensate demineralizers.

2.2 Gaseous Radioactive Effluent Treatment System The gaseous radioactive effluent treatment system consists of those components or devices utilized to reduce radioactive material in effluent released to the atmosphere. The system consists of the following:

2.2.1 gas decay tanks, 2.2.2 drumming area ventilation exhaust duct filter assembly, n 2.2.3 Unit 1 and 2 containment purge exhaust filter assemblies, 1]

a 2.2.4 air ejector decay duct filter assembly, Page 7 of 32 INFORMATION USE

POINT BEACII NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 EADIOLOGICAL EFFLUENT CONTROL MANUAL 0 2.2.5 auxiliary building ventilation filter assembly (nominal 11,214 cfm exhaust pathway),

2.2.6 chemistry laboratory exhaust duct filter assembly, 2.2.7 service building ventilation exhaust duct filter assembly, 2.2.8 auxiliary building ventilation filter assemblies (nominal 34,150 cfm exhaust pathway) 2.3 Ef0uent Control and Accountability 2.3.1 Radiation Monitoring System

a. Description The computerized Radiation Monitoring System (RMS) at Point Beach Nuclear Plant consists of area, process, and effluent monitors. The effluent components of the RMS are designed to  ;

detect and measure radioactivity in liquid and gaseous releases from PBNP. A description of the liquid and gaseous effluent monitors and associated isolation and control functions are q presented in Tables 2-1 and 2-2. ,

b. Calibration Calibration of the RMS detectors is accomplished according to the procedures of the PBNP Health Physics Calibration Manual
c. Setpoints The methodology for determining efnuent RMS detector setpoints is described in the ODCM.
d. Alarms Response to alarms received from RMS ef0uent detectors is described in the PBNP RMS Alarm Setpoint and Response Book.
e. Effluent Detector Operability and Surveillance Detector operability and surveillance requirements are addressed in Sections 3 and 4 of this manual.

2.3.2 Efnuent Treatment Schematic The liquid and gaseous waste processing How paths, equipment, k and radiation monitors are depicted in Figures 2-1 and 2-2.

Page 8 of 32 INFORMATION USE

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V POINT BEACII NUCLEAR PLANT RADIOLOGICAL EFFLUENT CONTROL (v'D RECM MAJOR g

MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS CIIANNEL NUMBER NAME CONTROL FUNCTION DETECTOR TYPE 1 (2) RE-216 Containment Fan Coolers Liquid None Scintillation Monitors RE-218 Waste Disposal System Liquid Shuts waste liquid overboard Scintillation Monitor 1 (2) RE-219 Steam Generator Blowdown Liquid Shuts steam generatoi blowdown isolation Scintillation Monitors valves, blowdown tank outlet valves and steam generator sample valves RE-220 Spent Fuel Pool Liquid Monitor None Scintillation RE-223 Waste Distillate Overboard Liquid Shuts waste distillate overboard isolation valve Scintillation Monitor 1 (2) RE-229 Service Water Discharge Monitors None Scintillation RE-230 Retention Pond Discharge Liquid None Scintillation Monitor 1 (2) RE-222 Steam Generator Blowdown Tank Shuts steam generator blowdown isolation GM TuSe Outlet Monitor valves and blowdown tank outlet valves Page 9 of 32 INFORMATION USE

POINT BEACII NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL i

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(') POINT BEACII NUCLEAR PLANT ~'s RECM 3 V RADIOLOGICAL EFFLUENT CONTROL (O MAJOR (V MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS CilANNEL NUMBER NAME CONTROL FUNCTION DETECTOR TYPE 1 (2) RE-212 Containment Noble Gas Monitor Actuates containment ventilation isolation Scintillation RE-214 Auxiliary Building Exhaust Ventilation Shuts gas release valve and shifts auxiliary Scintillation Noble Gas Monitor building exhaust through carbon filters 1 (2) RE-215 Condenser Air Ejector Noble Gas None Scintillation Monitors RE-225 Combined Air Ejector Low-Range None Scintillation Noble Gas Monitor RE-221 Drumming Area Vent Noble Gas None Scintillation Monitor RE-224 Gas Stripper Building Exhaust Noble None Scintillation Gas Monitor 1 (2) RE-305 Unit I and 2 Purge Exhaust Noble Containment ventilatien isolation Scintillation Gas Monitors (Channel 5 on SPING Units No. 21 and No. 22)

RE-315 Auxiliary Building Exhaust Ventilation None Scintillation Noble Gas Monitor (Chamiel 5 on SPING Unit No. 23)

RE-325 Dmmming Area Ventilation Noble None Scintillation Gas Monitor (Channel 5 on SPING Unit No. 24)

Page 11 of 32 INFORMATION USE

POINT BEACII NUCLEAR PLANT RECM j RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT l March 13,1996 i;O RADIOLOGICAL EFFLUENT CONTROL MANUAL

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POINT BEACII NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 o RADIOLOGICAL EFFLUENT CONTROL MANUAL b 2.3.3 Release Accountability Control and accountability of radioactivity in PBNP effluents is accomplished by the RMS in conjunction with the characterization of radionuclide distributions by laboratory analyses of grab samples from the various waste streams. Sampling frequencies and analysis requirements are set forth in Section 6.0 of this manual. Additional aspects of grab sampling and release accountability are described in the PBNP Release Accountability Manual.

3.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION OPERABil.ITY REOUIREMENTS 3.1 Obiective The operability of detectors is specified in order to ensure that liquid and gaseous radioactive effluents are adequately monitored and to ensure that alarm or trip setpoints are established such that effluent releases do not exceed the values cited in Section 5.

p 3.2 Operability Specifications

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(/ 3.2.1 The radioactive effluent monitoring instrumentation channels listed in Tables 3-1 and 3-2 shall be operable. The alarm or trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

3.2.2 If fewer than the minimum number of radioactive effluent monitoring channels are operable, the action statement listed in either Table 3-1 or 3-2 opposite the channel shall be taken. Best effort shall be made to return an inoperable channel to operable status within 30 days. If the channel is not returned to an operable status within 30 days, the circumstances of the instrument failure and schedule for repair shall be reported to the NRC Resident Inspector.

3.2.3 If a radioactive effluent monitoring instrumentation channel alarm or trip setpoint is found less conservative than required by the ODCM, the channel shall be declared inoperable or the setpoint shall be changed to the ODCM value or a more conservative value.

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Page 13 of 32 INFORMATION USE

1 POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR  !

MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL )

8 TABl.E 3-1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION l

l Minimum Channels Instrument Operable Action

1. Liquid Radwaste System
a. RE-223, Waste Distillate Tank Discharge, 1 Note 1 i or RE-229, Service Water Discharge (for I applicable unit) l
b. RE-218, Waste Condensate Tank Discharge, 1 Note 1 or RE-229, Service Water Discharge (for l applicable unit)
c. Waste Condensate Tank Discharge Flow 1 Note 4 i Meter
d. Waste Distillate Tank Flow Rate Recorder i Note 4 l
2. Steam Generator Blowdown System
a. For Each Unit; RE-219, Steam Generator i Note 2 i Blowdown Liquid Discharge, or RE-222, S Blowdown Tank Monitor, or RE-229, Service Water Discharge
b. Steam Generator Blowdown Flow Indicators 1 Note 9 (1 per steam generator)
3. Service Water System r.. RE-229, Service Water Discharge 1 Note 3 (1 per unit)
b. For Each Unit; RE-216, Containment Cooling 1 Note 3 Fan Service Water Return, or RE-229, Service Water Discharge
c. RE-220, Spent Fuel Pool Heat Exchanger 1 Note 3 Service Water Outlet or RE-229, Service Water Discharge (for applicable unit)
4. Retention Pond Discharge System
a. RE-230, Retention Pond Discharge 1 Note 3
b. Retention Pond Discharge Composite 1 Note 8 Sampler
c. Retention Pond Discharge Flow Determination NA
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1

  • Retention pond discharge flow may be determined from pump run time and pump performance curves.

Page 14 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 3-2 l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i Minimum l Channels Instrument Operable Action

1. Gas Decay Tank System l
a. RE-214, Noble Gas (Auxiliary 1 Note 1 i Building Vent Stack), or RE-315 l Noble Gas (Auxiliary Building Vent l SPING) l
b. Gas Decay Tank Flow 1 Note 4 Measuring Meter
2. Auxiliary Building Ventilation System
a. RE-214, Noble Gas (Auxiliary 1 Note 6 ,

Building Vent Stack) or Re-315, l Noble Gas (Auxiliary Building Ver.t SPING) e b. Isokinetic Iodine and Particulate -

Continuous Air Sampling System 1 Note 5 I

3. Condenser Air Ejector System
a. RE-225 Noble Gas (Combined Air 1 Note 6 Ejector Discharge Monitor); or RE-215, Noble gas (Air Ejector Monitors - 1 per unit); or RE-214, Noble Gas (Auxiliary Building Vent Stack); or RE-315, Noble Gas (Auxiliary Building Vent SPING)
b. Flow Rate Monitor - Air Ejectors 1 Note 9
4. Containment Purge and Vent System
a. RE-212, Noble Gas Monitors 1 Note 6 (1 per unit); or RE-305, Noble Gas (Purge Exhaust SPING - 1 per unit)
b. 30 cfm Forced Vent Path Flow Indicators 1 Note 9
c. Iodine and Particulate -

Continuous Air Samplers 1 Note 5 O

V

d. Sampler Flow Rate Measuring Device 1 Note 9 Page 15 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 0 TABLE 3-2 (continued)

Minimum Channels Instrument Operable Action

5. Fuel Storage and Drumming Area Ventilation System
a. RE-221, Noble Gas (Drumming Area Stack), or RE-325, Noble Gas (Drumming Area SPING) 1 Note 6
b. Isokinetic Iodine and Particulate -

Continuous Air Sampling System 1 Note 5

6. Gas Stripper Building Ventilation
a. RE-224, Noble Gas (Gas Stripper Building), or RE-305, (Unit 2 ,

INrge Exhaust SPING) 1 Note 6

b. Iodine and Particulate -

Continuous Air Sampler 1 Note 5

c. Sampler Flow Rate Measuring Device 1 Note 9
7. Waste Gas Holdup System Explosive Gas Monitoring System
a. Oxygen Monitor 1 Note 7 o\J Page 16 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 0 NOTATIONS FOR TABLES 3-1 AND 3-2 Note 1: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided that prior to initiating a release, two separate samples are analyzed by two technically qualified people in accordance with the applicable part of Tables 6-1 and 6-2 and the release rate is reviewed by two technically qualified people.

Note 2: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are analyzed for gamma radioactivity in accordance with Table 6-1 at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the secondary coolant specific activity is less than 0.01 Ci/cc dose equivalent I-131 or once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the activity is greater than 0.01 pCi/cc dose equivalent I-131.

Note 3: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided that at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples are collected and analyzed in accordance with Table 6-1.

i Note 4: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided the flow rate is estimated at least once every four hours during actual gaseous or liquid batch releases.

Note 5: If the number of channels operable is fewer than the minimum required, effluent releases

~. (m} via the affected pathway may continue provided samples are continuously collected with

\d auxiliary sampling equipment.

Note 6: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are collected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and are analyzed in accordance with Table 6-2.

Note 7: If the number of channels operable is fewer than the minimum required, addition of waste gas to the Waste Gas Holdup System may continue for up to 14 days, provided grab samples are taken from the on-service gas decay tank and analyzed either daily during normal operations or every four hours when the primary system is being degassed (other

, than normal gas stripping of the letdown flow). If the monitoring system is out of service i for greater than 14 days, in addition to the above sampling, a report of the cause and corrective action for failure and repair of the gas monitor shall be included in the Annual Monitoring Report.

' Note 8: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are collected twice per week and analyzed in accordance with Table 6-1.

Note 9: If the number of channels operable is fewer than the minimum required, effluent releases via this pathway may continue provided the flow is estimated or determined with auxiliary indication at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Page 17 of 32 INFORMATION USE

POINT BEACll NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 0 4.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS 4.1 Obiective To verify that radioactive liquid and gaseous effluent monitoring instrumentation is demonstrated to be operable by periodic inspection, testing, and calibration.

4.2 Radioactive Monitorine Instrumentation Surveillance Reauirements Each radioactive effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, calibration, functional test, and source check at the frequencies shown in Tables 4-1 and 4-2.

4.3 Definitions 4.3.1 Source Check The assessment of channel response by exposing the channel detector to a source of increased radiation.

4.3.2 Channel Check A qualitative determination of acceptable operability by observing channel behavior during operation. This shall include comparison of the channel with other independent channels measuring the same variable.

4.3.3 Functional Test The injection of a simulated signal into the channel to verify that it is operable, including alarm and/or trip initiating action.

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l Page 18 of 32 INFORMATION USE

POINT BEACII NUCLEAR PLANT RADIOLOGICAL EFFLUENT CONTROL f' RECM MAJOR g

MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 4-1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS Channel Functional Source Instrument Description Check Calibrate Test Check

1. Liquid Radwaste System
a. RE-223, Waste Distillate Tank Discharge D R Q P
b. RE-218, Waste Condensate Tank Discharge D R Q P
c. Waste Condensate Tank Discharge Flow Meter P/D R NA NA
d. Waste Distillate Tank Flow Rate Recorder P/D R NA NA
2. Steam Generator Blowdown System
a. RE-219, Steam Generator Blowdown Liquid Discharge (1 per unit) D R Q M
b. RE-222, Blowdown Tank Monitor (1 per unit) D R Q M
c. Steam Generator Blowdown Flow Indicator (1 per steam generator) D R NA NA
3. Service Water System
a. RE-229, Service Water Discharge (1 per unit) D R Q M
b. RE-216, Containment Cooling Fan Service Water Return (1 per unit) D R Q M
c. RE-220, Spent Fuel Pool IIeat Exchanger Service Water Outlet D R Q M
4. Retention Pond Discharge System
a. RE-230, Retention Pond Discharge D R Q M
b. Retention Pond Discharge Composite Sampler W NA NA NA
c. Retention Pond Discharge Effluent Sump Pumps W R NA NA Page 19 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RADIOLOGICAL EFFLUENT CONTROL g RECM MAJOR O

(V MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 4-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS Channel Functional Source Channel Description Check Calibrate Test Check

1. Gas Decay Tank System
a. RE-214, Noble Gas (Auxiliary Bitilding Vent Stack) D R Q M
b. Gas Decay Tank Flow Measuring Device P R NA NA
2. Auxiliary Building Ventilation System
a. RE-214, Noble Gas (Auxiliary Building Vent Stack) D R Q M
b. RE-315, Noble Gas (Auxiliary Building SPING) D R Q M
c. Isokinetic lodine and Particulate Continuous Air Sampling System W R NA NA
3. Condenser Air Ejector System
a. RE-225, Noble Gas (Combined Air Ejector Discharge) D R Q M
b. RE-215, Noble Gas (Air Ejectors -

1 per unit) D R Q M

c. Flow Rate Monitor - Air Ejectors (1 per unit) D R NA NA Page 20 of 32 INFORMATION USE

V

) POINT BEACH NUCLEAR PLANT RADIOLOGICAL EFFLUENT CONTROL d RECM MAJOR g

MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 4-2 (continued)

Channel Functional Source Channel Description Check Calibrate Test Check

4. Containment Purge and Vent System
a. RE-212, Noble Gas (1 per unit) D R Q M*
b. 30 cfm Vent Path Flow Indicator P/D R NA NA
c. RE-305, Noble Gas (Purge Exhaust SPING -

I per unit) D R Q M*

d. Iodine and Particulate Continuous Air Sampler P/W NA NA NA
e. Sampler Flow Rate Measuring Device P/D R NA NA
5. Fuel Storage and Drumming Area Ventilation Stack
a. RE-221, Noble Gas (Drumming Area Vent Stack) D R Q M
b. RE-325, Noble Gas (Drumming Area SPING) D R Q M
c. Isokinetic lodine and Particulate Continuous Air Sampling System W NA NA NA
6. Gas Stripper Building Ventilation System
a. RE-224 Noble Gas D R Q M
b. Iodine and Particulate Continuous Air Sampler W NA NA NA
c. Sampler Flow Rate Measuring Device W R NA NA
7. Waste Gas Holdup System Explosive Gas Monitoring System
a. Oxygen Monitor D Q** Q NA Page 21 of 32 INFORMATION USE .

l POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 0 NOTATIONS FOR TABLES 4-1 AND 4-2 l

D = Daily 1

W = Weekly M = Monthly Q = Quarterly R = Each Refueling Interval (but not to exceed 18 months)

P/D = Prior to or immediately upon initiation of a release or daily if a release continues for more than one day P/W = Prior to or immediately upon initiation of a release or weekly if a release continues for more than one week P = Prior to or immediately upon initiation of a release

  • = Source check required prior to containment purge j
    • = The channel calibration shall include the use of standard gas samples appropriate to the recommendations of the manufacturer of the gas analyzer equipment in use and include calibration points in the range of interest. I NA = not applicable 69.

U Page 22 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 9 5.0 RADIOACTIVE EFFLUENT RELEASE LIMITS 5.1 Obiective To ensure controlled releases of radioactive materials in liquid and gaseous effluents to unrestricted areas are within applicable 10 CFR 20 concentration limits and to ensure the quantities of radioactive material released during any calendar year are such that resulting radiation exposures do not exceed the dose objectives of 10 CFR 50, Appendix I.

5.2 Radioactive Liquid Effluent Concentrations  ;

5.2.1 Alarm setpoints for liquid effluent monitors shall be determined and adjusted utilizing the methudologies and parameters given in the ODCM.

l 5.2.2 The liquid effluent monitor setpoints shall be established to ensure that l radioactive materials released as effluents shall not result in concentrations i to unrestricted areas in excess of the values specified in 10 CFR 20, Appendix B, Table II.

5.2.3 During release of radioactive liquid effluents, at least one condenser S circulating water pump shall be in operation and the service water return header shall be lined up only to the unit whose circulating water pump is operating.

5.3 Radioactive Liauid Effluent Release Limits l 5.3.1 The annual calculated total quan:ity of radioactive material above background released from PBNP in liquid effluents shall not result in an unrestricted area estimated annual dose or dose commitment from all exposure pathways to any individual in excess of 6 millirem to the total body or 20 millirem to any organ.

5.3.2 Quarterly limits are defined as one quarter (1/4) of the annual limits.

5.3.3 Compliance with these release limits will be demonstrated by periodic dose calculations utilizing the methodology of the ODCM.

V Page 23 of 32 INFORMATION USE

i POINT BEACH NUCLEAR PLANT RECM i RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 0 5.4 Radioactive Gaseous Effluent Concentrations 5.4.1 Alarm setpoints for the gaseous effluent monitors shall be determined and adjusted utilizing the methodologies and parameters given in the ODCM.

5.4.2 The gaseous effluent monitor setpoints are established to ensure that radioactive materials released shall not result in concentrations to '

unrestricted areas in excess of the values specified in 10 CFR 20, Appendix B. Table II.

5.4.3 During the release of radioactive gaseous effluents from the gas decay tanks through the auxiliary building vent, at least one auxiliary building exhaust fan shall be in operation.

5.5 Radioactive Gaseous Effluent Release Limits 5.5.1 The annual calculated total quantity of radioactive materials above background released from PBNP to the atmosphere shall not result in an unrestricted area estimated annual dose or dose commitment from all exposure pathways to any individual in excess of the following:

(3 10 millirem to the total body or 30 millirem to the skin from gaseous iy a.

effluents near ground level;

b. 30 millirem to any organ from all radiciodines and radioactive material in particulate form; and
c. Furthermore, the annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas shall not exceed 20 millirads for gamma radiation or 40 millirads for beta radiation.

5.5.2 Quarterly limits are defined as one quarter (1/4) of the annual limits.

5.5.3 Compliance with these release limits will be demonstrated by periodic dose calculations utilizing the methodology of the ODCM.

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Page 24 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 9 5.6 Ouarterly Summarv 5.6.1 A summary of radioactive effluent releases shall be made on a quarterly basis as described in the ODCM.

5.6.2 If the calculations required by 5.3.3 or 5.5.3 of this section exceed the corresponding quarterly limit during any calendar quarter, a summary of radioactive effluent releases shall be made monthly until it is determined that release quantities are within the annual limits.

5.6.3 If the calculations required by 5.3.3 or 5.5.3 of this section exceed twice the corresponding quarterly limit during any calendar quarter, a special report will be prepared and submitted per Technical Specification 15.7.8.4.D.

5.6.4 If the calculations required by 5.3.3 or 5.5.3 of this section demonstrate that quarterly releases exceed the quarterly limit, corrective actions shall be taken to ensure that subsequent releases in that calendar year will be in compliance with quarterly and annual limits.

p 5.7 Radioactive Effluent Treatment b 5.7.1 The gaseous radioactive effluent treatment system shall be operated. If the gaseous effluent treatment system becomes inoperable, the effluent reporting requirements of Section 5.6 shall apply. These provisions do not include the gas decay tanks, the auxiliary building ventilation exhaust  ;

charcoal filter, and the air ejector decay duct charcoal filter assembly. j l

a. A gas decay tank (s) shall be operated whenever required to maintain gaseous releases within the limits of Section 5.5.1.a and Section 5.5.1.c.
b. The auxiliary building ventilation exhaust charcoal filter shall be operated when required to maintain gaseous releases within the limit of Section 5.5.1.b for radiciodines.
c. The air ejector charcoal filter shall be operated when required to maintain releases within the limit of Section 5.5.1.b for radioiodines. I
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N Page 25 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 9 5.7.2 The liquid radioactive effluent treatment system shall be operated. If the liquid radioactive effluent system becomes inoperable, the effluent

. reporting requirements of Section 5.6 shall apply. These provisions do not include the processing of steam generator blowdown, the processing of liquid wastes collected in the waste holdup tank, the processing of secondary side sampling and turbine building wastes through the retention pond, and the processing of preplanned tank batch releases.

a. Steam generator blowdown shall be processed to reduce radioactive effluents when required to maintain releases within the dose objectives of Section 5.3.1.
b. Wastes collected in the waste holdup tank shall be processed to reduce radioactive effluents when required to maintain releases within the dose 4

objectives of 5.3.1.

c. Preplanned tank batch releases may be made without processing under any of the following conditions, provided the dose objectives of 5.3.1 are not exceeded:

73 1. Processing or disposal of tank contents would prevent plant g operation or delay plant start-up or shutdown; or i

2. The tank release is necessary to conform to Technical Specification operating requirements; or
3. The tank release is necessary to eliminate a chemical contaminant  !

to satisfy chemistry specifications; or l

4. The tank release is desired for any other reason and a cost-benefit
analysis has been performed. j ID x>

v Page 26 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 8 5.8 Total Dose 5.8.1 Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstration of conformance to the standards set forth in 40 CFR 190.

5.8.2 If the calculations required by 5.3.3 or 5.5.3 of this section exceed twice the annual dose objectives of Sections 5.3.3 and 5.5.3, dose calculations shall be performed as described in the ODCM and shall include direct radiation contributions from reactor units and from any outside storage tanks in addition to effluent pathways.

5.8.3 A report will be submitted to the Commission within 30 days upon completion of the dose calculations required by Section 5.8.2, if the  !

calculated dose to any member of the general public exceeds the 40 CFR l 190 annual dose limits. I l

5.9 Explosive Gas Mixture i

5.9.1 The concentration of oxygen in the on-service gas decay tank shall be I limited to less than or equal to 4% by volume.

5.9.2 If the concentration of oxygen in the on-service gas decay tank is greater  !

than 4% by volume, immediately suspend all additions of waste gases to l the on-service gas decay tank.

5.9.3 Reduce the oxygen concentration to less than 4% oxygen by volume as soon as possible. If the on-service gas decay tank is at or near capacity and the tank must be isolated to permit the required decay time to conform with dose objectives of Appendix I to 10 CFR 50, it will not be possible to immediately reduce the oxygen concentration. In this case, the tank will be isolated and the oxygen concentration reduced as soon as the gas decay requirements are satisfied.

5.10 Solid Radioactive Waste The solid radwaste system shall be used in accordance with the Process Control Program to process radioactive wastes to meet all shipping and burial ground requirements. If the provisions of the Process Control Program are not satisfied, shipments of defectively processed or defectively packaged radioactive waste from the site will be suspended. The Process Control Program shall be used to verify solidification of radwaste.

O Page 27 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL

) -

U 6.0 RADIOACTIVE EFFLUENT SAMPLING AND ANALYSIS REOUIREMENTS 6.1 Purpose The purpose of this section is to specify the sampling frequency, the analysis frequency, and analysis requirements for radioactive liquid and gaseous effluents in order to verify that the concentrations and quantities of radioactive material released from :he site in liquid and gaseous effluents do not exceed the objectives specified in St.ction 5.

6.2 Radioactive Liauid Waste Sampline and Analysis The concentration of radioactivity in liquid waste shall be determined by sampling and analysis in accordance with Table 6-1.

6.3 Radioactive Gaseous Waste Samnline and Analysis The concentration of radioactivity in gaseous wastes shall be determined by samphng and analyses in accordance with Table 6-2.

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i Page 28 of 32 INFORMATION USE

(m ) POINT BEACH NUCLEAR PLANT RADIOLOGICAL EFFLUENT CONTROL g RECM MAJOR g

MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 6-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Level Sampline Minimum Type of of Detection' Liauid Release Type Freauency Analysis Frecuency Activity Analysis5 (uCi/cc)

1. Batch Releases 2 a, Waste Condensate Tank Prior to Prior to Release Gamma Emitters 5 x 10 7
b. Waste Distillate Tank Release I-131 1 x 10'
c. Monitor Tanks
d. Other tanks containing Monthly on composites ob- Gross Alpha 1 x 10~'

radioactivity to be dis- tained from batches re- Tritium I x 10 5 charged. leased during the current month Quarterly on composites Sr-89/90 5 x 10' obtained from batches re-leased during the current quarter

2. Continuous Releases 5
a. Steam Generator Blowdown Grab Samples Twice Weekly Gamma Emitters 5 x 10 7 Twice Weekly I-131 1 x 10 4
b. Service Water Monthly on Grab Gross Alpha 1 x 10'7 Composites Tritium 1 x 105 Quarterly on Grah Sr-89/90 5 x 10' Composites
c. Retention Pond Continuous Weekly Gamma Emitters 5 x 10 '

Composite

  • I-131 1 x 10 4 Monthly on Weekly Gross Alpha 1 x 10-7 Composite Tritium I x 105 Quarterly on Sr-89/90 5 x 10' Monthly Composites Page 29 of 32 INFORMATION USE

1 POINT BEACil NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 8 NOTES FOR TABLE 6-1

1. The principal gamma emitter for which the gamma isotopic LLD applies is Cs-137.

Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters are inherently determined by the operating characteristics of the counting system. All idemifiable gamma emitters will be reported in the Annual Monitoring

. Report.

2. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses each batch shall be isolated ar.J mixed to assure representative sampling.
3. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g.,

from a volume of a system that has an input flow during the release.

4. A continuous composite is one in which the method of sampling employed results in a specimen that is representative of the liquids released. l
5. Identified entrained noble gases shall be reported as gaseous effluents.

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Page 30 of 32 INFORMATION USE

I l

('~' POINT BEACH NUCLEAR PIANT RADIOLOGICAL EFFLUENT CONTROL (V 'l RECM MAJOR g

MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 6-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Ixvel Samplina Minimum Tvoe of of Detection' Gaseous Release Type Freauen_cy 5

Analysis Frequency Activity Analysis (uCi/cc)

1. Gas Decay Tank Prior to Prior to Release Gamma Emitters 1 x 10 4 Release
2. Containment Purge or Prior to Purge2 Prior to Purge Gamma Emitters 1 x 10' Continuous Vent or Vent or Vent Tritium I x 10'
3. Continuous Releases: Continuous' Weekly Analysis Gamma Emitters 1 x 10 "

of Charcoal and I-131 1 x 10 "

a. Unit 1 Containment Purge and Vent Particulate Samples
b. Unit 2 Containment Purge and Vent
c. Drumming Area Vent Monthly Composite Gross Alpha 1 x 10 "
d. Gas Stripper Building Vent of Particulate Sample
e. Auxiliary Building Vent Quarterly Composite Sr-89/90 1 x 10~"

of Particulate Sample Noble Gas Monitor Noble gases 1 x 104 Gross Beta or gamma Monthly

  • Monthly Gamma Emitters 1 x 104 (Grab)

Monthly Tritium 1 x 10*

Page 31 of 32 INFORMATION USE

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT March 13,1996 RADIOLOGICAL EFFLUENT CONTROL MANUAL 8 NOTES FOR TABLE 6-2

1. The principal ganuna emitters for which the LLD specification applies are Cs-137 in particulates and Xe-133 in gases. Because gamma isotopic analyses are performed, the LLDs for ali other gamma emitters are inherently determined by the operating characteristics of the counting system. All identifiable gamma emitters will be reported in the Annual Monitoring Report.
2. Tritium grab samples will be taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded.
3. The ratio of the sample flow rate to the release flow rate shall be known or estimated for the time period covered by each sampling interval.

4

4. Tritium grab samples will be taken every seven days from the drumming area ventilation exhaust / spent fuel pool area whenever there is spent fuel in the spent fuel pool.

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V Page 32 of 32 INFORMATION USE

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