ML20203K320
| ML20203K320 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/25/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20203K296 | List: |
| References | |
| PROC-971125, NUDOCS 9712220310 | |
| Download: ML20203K320 (38) | |
Text
.-
l POINT BEACH NUCLEAR PLANT UNIT I AND 2 RADIOLOGICAL EFFLUENT CONTROL MANUAL WCONSIN ELECTRIC November 25,1997 Revision 0 DRAFT 9712220310 971213 PDR ADOCK 05000266 P
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' RADIOLOGICAL EFM.UENT CONTROL MANUAL TABLE OF CONTENTS ~
L J.0 RA DIO L OGIC A L E F FLU ENT CONTRO L P ROGRAM,...........................................................;... ! '
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i 1. 2 B as i s S t a t e m e n t........ m...................................................... m....
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- 1. 3 R e s no n s i b i l i t i e s.......................... _...............................................................
. 1.4 M a n u a l R e v i s i o n r............................................................................................
1.5 RECP Parameters Reportable in the Annual Monitorinc Renort................................................... 4 '
l.6 Ot her R EC P R enortable Event s...........................................m.........................................m...........6 2.0 RA DIO A CTI V E E F FL UE NT C ONTI J L............................................................................m......... 7 l 2. I Liquid Radioactive Em uent Treatment System.....................................................~..................... 7
~ 2.2 Gaseous Radioactive E f0 uent T reatment S vsten.J......................................................................... 7.
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2.3 E fH uen t Cont rol and A ecou n tabilitv............................................................................................. 8 3.0 R ADIOACTIVE EFFLUENT MONITORINO INSTRUMENTATION OPERABil IT'r 7
R E O U I R E M E NTS.....................,.........................................,................................................... 1 3 3.1Obiective,......................................,........................................................................................13 3.2 O ne rabi l i t v S nec i 6 c at io n s.:........................................................................................................... 1 p
4.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE "REOUIREMENTS..............................,......................................................................................................!8 4.l'Obiective...............................,.......................................................................................................I8 L 4.2 Eadioactive Manitorine 1nstrumentation Surveillance Reauirements...........................................18
~.4.3Dennitions................................................................................................................................18 L 5.0 RA DIO ACTIVE EFFL UENT RE LE AS E LI MITS....................................................................... 25 5.1Obiective..................................................................................................................................25 (5.2 B ad ioactive Liauid E fTluent Concentrations........................................................................... 25
- NUCLl!AR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Rev;sion 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 5.3 Radioactis e Liquid E f0 uent Release Limits............................................................... 25 5.4 Radioactive Gaseous Efuuent Concentrations........
....................................m26 5.5 Rgdioactive.Raseous Ef0uent Release Limits..................
..... 26
.................................mm.
5.6 Atmospheric Re! ease Fate Limitation;............
..... 2 7 5.7 Cumulative and Proiected Dose.s..........
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5.8 Radioactive Ef0uent Treatmenj..........
.... 2 8 5.9 Tota 1 Dose..........
...................................................................29 5.10 E x n ! o si v e G a s M i x t u re...................................................... ~............. -.... m..... 2 9 5.I 1 Solid Radinaci ve Waste....................
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6.0 RADIOACTIVE EFFLUENT SAMPLING AND ANAI YSIS REOUIREMENTS.................. 30 6.1 Purnose..
... 30 6.2 Radioactive Liauid Waste Samojine and Anabss..
...... 3 0 m..
6.3 Radioactive Gaseous Waste Sampline and Analvsis.
..... 3 0 LIST OF TABLES TA B L E 2 - 1...........................................
.. 9 TA B L E 2-2..........
...... I 1 TABLE 3-1.......
....... 14 T A B L E 3 -2...........................................................
.... 15 NOTATIONS FOR TABLES 31 AND 3-2.......
....17 TABLE 4-1.........
... 19 TABLE 4 7....
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NOTATIONS FOR TABLES 4-1 AND 4-2......
...... 24 TA B L E 6-1.........................
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NUCL8AR POWER BUSINESS UNIT.
- RECM' RADIOLOGICAL EFFLUENT CONTROL'-
- MAJOR-
< MANUAL:
Revision 0 DRAFT -
RADIOLOGICAL EFFLUENT CONTROL MANUAL L
- - 4 N OTE S F O R TA B L E 6-1...........................................................................
< TABLE 62...............................................................................................................................................33 L N OT E S F O R TA B L E 6-2....................................................................................
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LIST OF FIGURES -
N FIGURE 2-1...........................................................................................................................................10 FIGURE 2-2............................................................................................................................................12 1
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RADIOLOGICAL EFFLUENT CONTROL:
~ MAJOR' MANUALS Revision 0 DRAFT
- November 25,1997 i RADIOLOGICAL EFFLUENT CONTROL MANUAL
- 1.0 J RADIOLOGICAL EFFLUENT CONTROL PROGRAM :
-1.1' Basis The Radiological Effluent _ ontrol Program (RECP) shall conform to 10 CFR 50.36a for C
the 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 4
- 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, l.1.3
'10 CFR 50,' Appendix A, Criterion 63 Monitoring fuel and waste storage, 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 members cf the
- public, 1.1.6 10 CFR 20.1501-General, 1.1.7 PBNP General Design Criterion 17 Monitoring Radioactivity Releases, and 1.1.8 PBNP General Design Criterion 70-Control of releases of radioactivity to the environment.
i-Page1of34' INFORMATION USE '.
. NUCLEAR POWER BUSINESS UNIT-'
RFCM i RADIOLOGICAL = EFFLUENT CONTROli MAJOR ~
Revision 0 DRAFT L MANUAL-~
' November 25,19971
- RADIOLOGICAL EFFLUENT CGNTROL MANUAL -
- 1.2 - i pasis Statement Liquid emuent from the radioactive waste disposal system are diluie' by the circulating
{
d water system prior to release to Lake Michigan. With two pumps operating per unit, the rated How of the circulating water system is approximately 340,000 gpm per unit.
Operation of a single circulating water pump per unit reduces the nominal Dow 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 ofliquid radioactive emuents at this point are not measured directly. Instead, 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.
f.
The release of radioactive materials in liquid effluents to unrestricted areas is monitored and controlled to conform to the dose objectives in Section ll.A of Appendix 1 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 concentrations of radionuclides in PBNP liquid efHuent released to unrestricted areas conforming to ten times the maximum effluent concentration (MEC) values specified in Table 2, Column 2 of Appendix B to 10 CFR 20.1001-20.2402.
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 ofliquid wastes not exceeding these release limits will not result in signihcant exposure to members of the public as a 2
i 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.
n Prior to release to the atmosphere, gaseous wastes are mixed in the auxiliary building-
- vent with the flow 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 t
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 e
keep the radioactive releases to the atmosphere ALARA.
Page 2 of 34 INFORMATION USE y
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NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL hfAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL In order to achieve the dose objectives of Appendix 1 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 yJQ 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 Appendix I to 10 CFR 50.
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 ofimplementing 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 Responsibilitie.2 All required actions of the Radiological Effluent Control Program shall be conducted using apprcved procedures. The responsibility for the imp'ementation 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 cuatrol required pursuant to 10 CFR 20.1302,10 CFR 50.36a, Appendix 1 to 10 CFR 50, and 40 CFR 190.
Page 3 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 1.4.2 Revisions shall occome effective afler review ard approval pursuant to the appropriate PBNP administrative procedure and T.S.15.7.8.7.
1.43 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 with, the Annual Monitoring Report for the period of the report in which the revision was made. Each change shall be identified by markings in the margin of the affected pages, clearly indication the area of the page that was changed. Each copy shall indicate the date the revision was implemented.
1.5 RECP Parameters Renor:able in the Annual Monitorine Reno.n Information relative to the monthly quantities ofliquid, gaseous, and solid radioactive eftluents 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 reletse categories? gamma isotopic, gross alpha, tritium, and strontium (beta emitters othennan tritium),
- b. Total volume (in gallons) ofliquid waste released into circulating water discharge,
- c. Total volume (in gallons) of dilution water used.
- d. The maximum concentration of tritium and gross gamma radioactivity released (averaged over the period of a single release),
- c. Estimated monthly total radioactivity in curies ofindividual radionuclides released based on representative isotopic analyses.
- f. Semiannual and annual totals of monthly quantities ofindividual radionuclides, as determined by isotopic analyses.
1.5.2 Releases to the Atmosphere
- a. Total gross radioactivity (in Curies), by month, released of:
1.
Noble Gases.
2.
Halogens.
Page 4 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTRUL hlAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 3.
Particulates, subdivided into beta emitters (strontium, etc.), gross alpha, and gamma emitters.
4.
- b. Maximum release rate (for any one-hour period).
Estimated monthly total radioactivity (in Curies) released, by nuclide, for c.
I 131,1-133, H-2, and radioactive particulates with half lives greater than eight days, based on representative analyses performed by beta and by gamma isotopic analyses,
- d. Semiannual 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.
The dates of shipmeut and burial site if shipped for burial.
c.
- d. The type of waste shall be indicated, i.e., dry activated waste, resins, evaporator concentrates, filters scrap metal, asbestos, etc.
1.5.4 Doses 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 consecutive days.
Page 5 of 34 INFORMATION USE
. NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 1,6 Qlher 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 efflaents are being discharged for 31 days without the treatment required to meet the release limits specified in Section 5.0, a special report shall be prepared and submitted to the Commission within thirty days which includes the following infonna' ion:
Identification of the inoperable equipment or subsystem and the reason for a.
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 If the quantity of radioactive raaterial actually released in liquid or gaseous effluents during any calendar quarter exceeds twice the quar:erly limit as specified in Jection 5.0, a special report shall be prepared and submitte to the i
Commission within thirty days or detemtination of the release quantity.
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 FSAR for the period in which the major change was complete. The 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 leason for the change;
- c. A description of the equipment, components and processes involved and the interfaces with other plant systems;
- d. An evaluati-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 applica%n and amendments thereto; Page 6 of 34 INFORMATION USE
NUCLEAR POWER 13USINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MAhUAL
- 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 Llauld Rglipactive Efnuent Treatment System The liquid radioactive efnuent treatment system consists of those components or devices used to reduce radioactive material in liquid efnuent. The system consists of the following:
2.1.1 blowdown evaporator or waste evaporator, 1
2.1.2 polishing demineralizers, 2.1.3 boric acid evaporator feed deminemlizers, 2.1.4 boric acid evaporators, 2.1.5 boric acid evaporator condensate demitarailzers.
2.2 Opseous Radioactive Ef0uer1 Treatment Systerp The gaseous radioactive ef0uent treatment system consists of those components or devices utilized to reduce radioactive material in efiluent 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, 2.2.3 Unit I and 2 containment purg exhaust Siter assemblies, 2.2.4 air ejector decay duct filter assembly, 2.2.$
auxiliary building ventilation filter assembly (nominal 11,214 cfm exhaust pathway), -
Page 7 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT RECM f
l RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 2.2.6 chemistry laboratory exhaust duct filter assembly, t
2.2.7 service building ventilation exhaust duct f.lter assembly, 2.2.8 auxiliary building ventilation filter assemblies (nominal 34,150 cfm exhaust I
pathway) i 2.3 E0luem Controlgnd Accountability 2.3.1 Radiation Monitoring System
- a. Description The computerized Radiation Monitoring System (RMS) at Point Beach Nuclear Plant consists of area and process monitors. The effluent monitors are those process monitors that are designed to detect and measure radioactivity in liquid and gaseous releases from PBNP. A description of the liquid and gaseous enluent monitors and associated isolation and control functions are presented in Tables 21 and 2 2.
- b. Calibration Calibration of the RMS detecte.s is accomplished according to the procedures of the PBNP IIcalth Physics Calibration Manual
- c. Setpoints The methodology for determining effluent RMS detector setpoints is described in the ODCM.
- d. Alarms Response to alarms received from RMS c01uent detectors is described in the PBNP RMS Alarm Setpoint and Response Book.
i
- e. Eftluent Detector Operability and Sun eillance Detector operability and surveillance requirements are addressed in Sections 3 and 4 of this manual.
2.3.2 Eftluent Treatment Schematic The liquid and gaseous waste processing flow paths, equipment, and radiation i
monitors are depicted in Figures 21 and 2 2.
i Page8of34 INFORMATION USE
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Page 12 of 34 INFORh!ATION USE
NUCLEAR POWER BUSINESS UNIT REChi RADIOLOGICAL EFFLUENT CONTROL hfAJOR h1ANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL hiANUAL 2.33 Release Accountability Control and accountability of radioactivity in PBNP effluents is accomplished by the RhtS in conjunction with the characterization of radionuclide l
distributions by laboratory analyses of grab samples from the various waste streams. Sampling frequen.ies and analysis requirements are set forth in l
Section 6.0 of this manual. Additional aspects of grab sampling and release accoumability are described in the PBNP Release Accountability hianual.
3.0 RADS a ACTIVE EFFLUENT N10NITORINO INSTRUhlFNTATION OPERABILITY REOUIREhiENTS i
3.1 Objective 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 5.0, 3.2 Onerability Snecifications 3.2.)
The radioactive effluent monitoring instrumentation channels listed in Tables 31 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 ODCh!.
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 retum an inoperable channel to operable status within 30 days. If the channel is not retumed 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 ODChi, the channel shall be declared inoperable or the setpoint shall be changed to the ODChi
- value or a more conservative value.
r Page 13 of 34 INFORh1ATION USE
. NUCLEAR POWER BUSINESS UNIT REChi l
RADIOLOOICAL EFFLUENT CONTROL h1AJOR h1ANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL h1ANUAL TABLE 31 RADIOACTIVE LlQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrums.nl Onerable Action u
1.
Liquid Radwaste System a.
RE 223, Waste Distillate Tank Discharge, or i
Note !
RE 229, Service Water Discharge (for applicable unit) b.
RE 218, Waste Condensate Tank Discharge, or i
Note i RE 229 Service Water Discharge (fbr applicable unit) c.
Waste Condensate Tank Discharge Flow Meter 1
Note 4 d.
Waste Distillate Tank Flow Rate Recorder i
Note 4 2.
Steam Generator Blowdown System a.
For Each Unit; RE 219, Steam Generator i
Note 2 Dlowdown Liquid Discharge, or RE 222, Blowdow n Tank Monitor, or RE-229, Service Water Discharge b.
Steam Generator Blowdown Flow Indicators 1
Note 9 (I per steam generator) 3, Service Water System a.
RE 229, Service Water Discharge (I per unit) i Note 3 b.
For Each Unit; RE 216, Containment Cooling Fan i
Note 3 Service Water Return, or RE 229, Service Water Discharge c.
RE 220, Spent Fuel Pool liest Exchanger Service i
Note 3 Water Outlet or RE 229 Service Water Discharge (for applicable unit) 4.
Retention Pond Discharge System a.
RE 230, Retention Pond Discharge i
Note 3 b,
Retention Pond Discharge Composite Sampler i
Note 8 c.
Retention eond Discharge Flow Determination 14A
- Retention pond discharge flow may be determined from pump run time and pump performance curves.
Page 14 of 34 INFORh!ATION USE
NUCLEAR POWER BUSINESS UNIT REChi RADIOLOGICAL EFFLUENT CONTROL h1AJOR h1ANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL h1ANUAL TABLE 3 2 RADIOACTIVE GASEOUS EFFLUENT h10NITORING INSTRUh1ENTAT10N hlinimum Channels Instrument Onerable Action 1.
Gas Decay Tank System a.
RE 214, Noble Gas (Auxiliary Duilding i
Note 1 Vent Stack), or RE 315 Noble Gas (Auxiliary Building Vent SPING) b.
Gas Decay Tank Flow hicasuring hieter i
Note 4 2.
Auxiliary Duilding Ventilation System a.
RE 214 Noble Gas (Auxiliary Building 1
Note 6 Vent Stack) or Re 315, Noble Gas (Auxiliary Building Vent SPING) b.
Isokinetle lodine and Particulate -
1 Note 5 Continuous Air Sampling System 3.
Condenser Air Ejector System n.
RE 225, Noble Gas (Combined Air 1
. Note 6 Ejector Discharge blonitor); or RE 215, Noble gas (Air Ejector hionitors 1 per unit); or RE 214, Noble Gas (Auxiliary Building Vent Stack); or RE 315, Noble Gas (Auxiliary Building Vent SfiNG) b, Flow Rate hionitor Air Ejectors Note 9 Page 15 of 34 INFORhlATION USE
NUCLEAR POWER 13USINESS UNIT REChi RADIOLOGICAL EFFLUENT CONTROL htAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL h1ANUAL Table 3 2 hiinimum Channels Instrument Operable Action 4.
Containment Purge and Vent System a.
RE 212, Noble Gas hionitors -
1 Note 6 (1 per unit); or RE 305, Noble Gas (Purge Exhaust SPING. I per unit) b.
30 efm Forced Vent Path Flow Indicators 1
Note 9 e.
lodine and Partic.ulate Continuous Air i
Note 5 Samplers d.
Sampler Flow Rate hicasuring Device 1
Note 9
' 5.
Fuel Storage and Drumming Area Ventilation System a,
RE 221, Noble Gas (Drumming Area 1
Note 6 Stack), or RE 325, Noble Gas (Drumming Area SPING) b.
Isokinetic lodine and Particulate -
1 Note 5 Continuous Air Sampling System 6.
Gas Stripper Building Ventilation RE 224, Noble Gas (Gas Stripper 1
Note 6 a.
Iluilding), or RE 305,(Unit 2 Purge Exhaust SPING) b.
Iodine and Particulate Continuous Air 1
Note 5 Sampler e.
Sampler Flow Rate hicasuring Device 1
- Note 9 7.
. Waste Gas lloldup System Explosive Gas hionitoring System a.
Oxygen hionitor i
Note 7 Page 16 of 34 INFORh1ATION USE
NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL i
NQTATIONS FOR TABI ES 31 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 relea'e, two separate samples are analyzed by two technically qualified people in accordance with the applicable part of Tables 61 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 l
via this pathway may continue provided grab samples are analyzed for gamma radioactivity in accordance with Table 61 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 pCi/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 1-131.
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 61.
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 l
via the affected pathway may continue provided samples are continuously collected with 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 lloidup 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 nonnat operations or every four hours when the primary system is being degassed (other than normal gas stripping of the letdown 11ow). If the monitoring system is out of sersice 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.
4 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 />.
- Page 17 of 34
. INFORMATION USE
_ ~. _.. _. _ _ _. _ _ _ _.,. -.
NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL < EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT I
November 25,1997
- RADIOLOGICAL EFFLUENT CONTROL MANUAL i
4.0 RADIOACTIVE EFFLUFNT MONITORING INSTRUMENTATION SURVEILI.ANCE REOUlREMENTS i
4.1 Obiective i
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 'Nrveillance Reauirements i
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 41 and 4-2.
4 i
4.3 Definitions 4.3.1 Source Check The assessment of channel response by exposing the channel detector to a source ofincreased radiation.
4.3.2 Channel Check A qualitative determination of acceptable operability by observing charmel 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.
Page 18 of 34 --
INFORMATION USE
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s NUCLEAR POWER BUSINESS UNIT REChi RADIOLOGICAL EFFLUENT CONTROL A1AJOR h1ANUAL :
Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL
. Table 4-1 Channel Functional Source Instrument Description Check Cahbrate Test Ci d
+
. 3.
. Service Water System -
- a. RE-229, Service Water Discharge D
R Q
h1 (I per unit)
- b. RE-216, Containment Cooling Fan Servie D
R Q
h1
- Water Return (I per unit)
- c. RE-220, Spent Fuel Pool IIcat Exchanger D
R Q
h1
. Service Water Outlet
- 4.
Retention Pond Discharge Syvem
- a. RE-230, Retention Pond Discharge D
R Q
ht
- b. Retention Pond Discharge Composite W
NA NA NA Sampler -
- c. Retention l'ond Dixharge Elliuent Sump W
R NA NA INmps Page 20 of 34 INFORMATION USE
NtJCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENTCONTROL
- MAJOR MANUAL-Revision 0 DRAFT November 25,1997
. RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 4-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS Channel Functimal Source Channel Description Check Calibrate Test Check 1.
Gas Decay Tank System
- a. RE-214, Noble Gas (Ausiliary Building Vent D
R Q
M Stack
' b. Gas Decay Yank Flow Measuring Device P
R NA NA 2.
Auxilia.y Building Ventilation System
- a. RE-214 Noble Gas (Auxiliry Building Vent D
R Q
M Stack)
- b. RE-315, Noble Gas (Auxiliary Building SPING)
D R
Q M
- c. isokinetic lodine and Particulate Continuous Air W
R NA NA Sampling System 3.
Condenser Air Ejector System i
- a. RE-225, Noble Gas (Combined Air Ejettor D
R Q
M Discharge)
- b. RE-215, Noble Gas (Air Ejectors - 1 per unit)
D R
Q M
- c. Flow Rate Momtor-Air Ejectors (I per unit)
D R
N?.
NA Page 21 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT REChi RADIOLOGICAL EFFLUENT CONTROL htAJOR MANUAL-Revision 0 DiL\\FT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL htANUAL Table 4-2 Channel Ftmetitmal Serrte Cn' anne! Description Check Calibrate Test Chect 4.
Containmer.t Purge and Ven: System
- a. RE-212, Noble Gas (I per unit)
D R
Q M*
i
- b. 30 cfre Vent Path Flow IWicator P/D R
NA NA
- c. RE-305, Noble Gas (Purge Exhaust SPING -
D R
Q M*
I per uv4)
^
- d. lodine and Particulate Continuous Air Sampler P/W NA NA NA l
- e. Sampler Flow Rate Measuring Duvice P/D R
NA NA i
i 5.
I'uel Storage and Drumming Area Ventilation Stack
- a. RE-221, Noble Gas (Drumming Area Vent Stack)
D R
Q M
- b. ?E-325. Noble Gas (D umming Area SP.NG)
D R
Q M
- c. Isokin-tic iodine and Particalate Continuous Air W
NA NA NA Sampling System Page 22 o1~34 INFORh!ATION USE i
w.,--
..y
NUCLEAR POWER BUSINESS UNIT RECat RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Resision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CL JTROL MANUAL Table 4-2 Channel Functional f<wme Channel Descrision Check Ca!ibrate Ten (hk 6.
Gas Stripper Building Ventilation System
- a. RE-224 Noble Gas D
R Q
M t,. lodine and Particulate Continuous Air Sampler W
NA NA NA
- c. Sampler Flow Rate Measuring Device W
R NA' NA 7.
Waste Gas Itoldup System Explosive Gas Monitoring System
- a. Oxygen Monitor D
Q" Q
NA Page 23 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL i
NOTATIONS FORTADLES 4 l AND 4 2 j
r i
Daily
-i D
=
t Weekly
{
W
=
Monthly
[
M
=
Quarterly Q
=
Each Refueling Interval (but not to exceed 18 months)
R
=
i I
Prior to or immediately upon initiation of a release or daily if a release continues for moie P/D
=
than one day Prior to or immediately upon initiation of a release or weekly if a release continues for P/W
=
more than one week Prior to or immediately upon initiation of a release P
=
t Source check required prior to containment purge
=
e The channel calibration shall include the use of standard gas samples appropriate to the
=
recommendations of the manufacturer of the gas analyzei equipment in usu and include calibration points in the range ofinterest.
not applicable NA
=
9 i
l Page 24 of 34
-INFORMATION USE -
f RECM l
NUCLEAR POWER BUSINESS UN T htAJOR l
RADIOLOGICAL EFFLUENT CONTROL htANUAL -
Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL h1ANUAL 1
W 5.0 -
RADIOACTIVE EFFLUENT REl. EASE LihilTS 5.1 Objective l
4 t
To ensure controlled rele: es of radioactive materials in liquid and gaseous effluents to i
unrestricted areas are within applicable 10 CFR 20 concentration limits and to ensure the t
quartitles 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 1.
5.2 Radinactive Liauid Efiluent Concentrations i
I 5.2.1 Alarm setpoints for liquid effluent monitors shall be detennined and adjusted utilizing the methodologies and parameters given in the ODChl.
5.2.2 The liquid efiluent monitor setpoints shall be established to ensure that radioactive materials released as effluents shall not result in concentrations to unrestricted areas in excess of ten times the concentration values specified in Appendix B. Table !!, Column 2, of 10 CFR 20.1001 20.2402.
5.2.3 During release of radioactive liquid elliuents, at least one condenser 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 I lauid EfilutnLBelease 1,imits 5.3.1 The annual calculated total quantity of radioactive material above background released from PUNP in liquid effluents shall not iesult 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 For the purpose ofinitiating the use of the liquid ellluent treatment system whenever the projected dose for a petiod of 31 days will exceed 2% of the dose guidelines of Appendix I to 10 CFR 50, the 2% of the Appendix 1 values, as given in Section 5.3.1, are 0,12 mrem for the whole body and 0.4 mrem for any organ, 5.3.3 Quarterly limits are defined as one half of the annual limits.
5.3,4
' Compliance with these release limits will be demonstrated by periodic dose calculations utilizing the nathodology of the ODChi.
page 25 of 34 INFORMATION USE
..a.-=-
NUCLEAR POWER BUSINESS UNIT RECh1 l
RADIOLOGICAL EFFLUENT CONTROL h1AJOR h1ANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL h1ANUAL f
i 5.4 Radioactive Gaseous Efnuent concentrations I
54.1 Alami setpoints for the gaseous ef0uent monitors shall be detennined and adjustec utilizing the methodologies and parameters given in the ODChi.
l 8
5.4.2 The gaseous efauent monitor setpoints are established to ensure that l
radioactive materials released shall not result in concentrations to unrestricted l
areas in excess of the values specified in 10 CFR 20 Appendix B, Tuble 11.
l 5.4.3 During the release of radioactive gaseous efauents fiom the gas decay tanks i
through the auxiliary building vent, at least one auxiliary building exhaust fan
[
shall be in operation.
5.5 Radioactive Oaseous Efauent 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:
10 milliren, to the total bc,Jy or 30 mill! rem to the skin from gaseous a.
ef0uents near ground levelt
- b. 30 millirem to any organ from all 1 131, I 133,113 and radioactive materials in particulate form whose half life is >8 days; and I
- c. Furthennore, the annual air dose from gaseous efnuents at any location near ground level which could be occupied by individuals in unrestricted areas shall not exceed 20 millitads for gamma radiation or 40 millirads for beta radiation.
5.5.2 For the purpose ofinitiating the use of the atmospherie efauent treatment system whenever the projected dose for a period of 31 days will exceed 2% of the dose guidelines of Appendix I to 10 CFR 50, the 2% of the Appendix 1 values, as given in Section 5.5.1, are:
- a. 0.2 mrem to the total body and 0.6 mrem to the skin, and
- b. 0.6 mrem to any organ, 5.5.3 Quarterly limits are denned as one half of the annual limits.
5.5.4 Compliance with these release limits will be demonstrated by periodic dose l
- calculations utilizing the methodology of the ODCh1.
I Page 26 of 34 INFORMATION USE.
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.J.-
_ - - - ~.. - - -
NUCLEAR POWER BUSINESS UNIT RECM
' RADIOLOGICAL EFFLUENT CONTROL MAJOR i
MANUAL Revision 0 URAFT i
November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 5.6 Atmospherie Release Ra.le Limitations lhe rate of release of radioactive effluents to the atmosphere from the site, which if continued for one. year, shall not result in dose rates at or beyond the site boundary that
. exceed the fnllowing values, i
5.6.1 For noble gases:
l 5
- a. 500 mrern/yr to the total body
- b. 3000 mrem /yr to the skin 5.6.2 For 1 131,1 133,113, and all particulate form radionuclides with a half life
>S days:
1500 mrrm/yr to any organ 5.6.3 The instantaneous, limiting release rates for the above annual rates, are calculated in Section 3.10 of the ODCM for various release types. Below are default values for various releases. Check the ODCM for the methodology to calculate release rates for more specific radionuclide mixtures or contact the cognitant Radiological Engineer,
- a. For noble gases, the whole body dose is limiting yielding a rate of 8.73E 02 Ci/sec.
- b. For particu'.ates, radioiodines and }{ 3, as described above, the release,
. ratu are 1.14t! 06 Ci/sec for radiolodines 1.52E 06 Ci/sec for cesiums -
2.16F 05 Ci/see for cobalts 3.62F41 Ci/sec fo 013 As a conservative measure, the limiting release rate should be applied to the whole radionuclide mixture based upon the presence or absence of the above major dose contributors.
Page 27 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT REChi
[
RADIOLOGICAL EFFLUENT CONTROL h1AJOR MANUAL Revision 0 DRAFT i
November 25,1997 RADIOLOGICAL EFFLUFNT CON 1 ROL MANUAL Cumulat ve and Projectsd Doses 5.7 i
5.7.1 Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current cawndar year, in accordance with the methodology and parameters of the ODChi, shall be made at least every 31 days.
i 5.7.2 Because of the length of time required to complete all facen, Of the required calculations and to obtain the radioanaly:ieal results for effluent samples sent to a contracted analytical laboratory, the c'etermination of the current quarter i
dose may not be finished until the following quarter.
[
5.7.3 If the calculations required by Sections 5.3.4 or 5.5.4 exceed the
[
corresponding quarterly limit during any calendar quarter, a special report will be prepared and submitted per Technical Specification 15.7.8.4.D.
5.7.4 If the calculations required by Sections 5.3.4 or 5.5.4 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.
5.8 Radh,w!ve Ellluent Treatment 5.8.1 The gaseous radioactive effluent treatment sys,em shall be operated whenever the projected dose for a 31 day period, from I 131,1 133,113, and radioactive particulates with a half life >8 days, exceeds the values of Section 5.5.2 (2% of the Appendix 1 values). If the gaseous effluent treatment system i-becomes inoperable, the efiluent reponing requirements of Section 1.6 shall apply.
- a. A gas decay tank (s) shall be operated whenever required to maintain gaseous releases within the limits of Section 5.5.2.a.
- b. The auxiliary building ventilation exhaust charcoal filter shall be operated when required to maintain gaseous releases within the limit of Section 5.5.2.b for radiciodines.
- c. The air ejector charcoal filter shall be operated when required to maintain
. releases within the limit of Section 5.5.2.b for radiciodines.
The liquid radioact ve efiluent treatment system shall be operated whenever i
5.8.2 the projected dose for a 31 day period exceeds the values of Section 5.3.4 (2% of the Appendix 1 values), if the liquid effluent treatment system becomes inoperable, the ellluent reporting requirements of Section 1.6 shall apply.
Page 28 of 34 INFORhtATION USE
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, NUCLEAR POWER B SI ESS UNIT RECM UN RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL i
5.9 Total Dose 5.9.1 Compliance with the provisions of Appendix 1 to 10 CFR 50 is adequate l
demonstration of conformance to the standards set forth in 40 CFR 190.
4 t
s 5.9.2 If the calculations required by 5.3.4 or 5.5.4 exceed twice the annual dose objectives of Sections 5.3 and 5.5, 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 'n addition to effluent path-
^
ways.
5.9.3 A report will be submitted to the Commission withm 30 days upon completion of the dose calculations required by Section 5.9.2, if the calculated dose to any member of the general public exceeds the 40 CFR 190 annual dose limits.
5.10 Fxnlosive Gas Mixture 5.10.1 The concentration of oxygen in the on service gas decay tank shall be limited to less than or equal to 4% by volume, 5.10.2 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 the on senice gas decay tank.
5.10.3 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 ! to 10 CFR 50, it will not be possible to immediately reduce the oxygen concentration in thu, case, the tank will be isolated and the oxygen concentration reduced as soon as the gas decay requirements are satisfied.
5.11 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.
1 Page 29 of 34 INFORMATION USE
NUCLEAR POWER 13USINESS UNIT REChi RADIOLOGICAL EFFLUENT CONTROL h1AJOR h1ANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL hfANUAL 6.0 RADIOACTIVE EFFLUENT SAh1Pl.ING AND ANALYSilitEOUIREhfENTS 6.1 Purmse Pursuant to the requirements of 10 CFR 20.1302, 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 the site in liquid anJ gaseous effluents do not exceed the objectives specified in Section 5.0.
6.2 Radioasjive 1.iauld Waste Samnliu and Analvris The concentration of radios.tivity in liquid waste shall be determined by sampling and analysis in accordance with Table 61.
6.3 Radioactive Gaseous Waste Samnline and Analysis The concentration of radioactivity in gaseous wastes shall be determined by sampling and analyses in accordance with Table 6 2.
Page 30 of 34 INFORh1ATION USE
NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 6-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Lese (
Sampling Minimum Type of of Detec. on 1 iquid Release Type Frecuency Analysis Trequency Activity Analysis, 6:Ci'cc)
- 1. Batch Releases
- a Waste Condensate Tank Prior to Prior to Release Gamma Emitters 5 x 10
- b. Waste Distillate Tank Release I-131 I x 10*
- c. Monitor Tanks
- d. Other tanks containing radioacti tity to be discharged Monthly on composites Gross Alpha I x 10(~,
obtained from batches Tritium a c 10 reieased darmg the current month Quaner!y on composites Sr-89 90 5 x 10 '
obtained from batches released during the current quarter
- 2. Continuous Releases'
- a. Steam Generator Blowdown Grab Sarapies Twice Weekly Gamma Emitters 5 x 10 '
Twice Weekly I-131 1 x 10*
- b. Service Water Mc,athly on Grab Gross Alptu I x 10" Lomposites Tritrum I x 10 4
Quarterly on Grab St-89/90 5 x 10' Composites
- c. Retention Pond Continuoug Weekly Gamma Emitters 5 x 10' Compaite I-131 1 x,0*
Monthly on Weekly Gross Alpha I x 10 Composite Tritium I x 10 '
Quarterly on Sr-8990 5 x 10*
Monthly Compesite Page 31 of 34 INFORMATION USE
NUCLEAR POWER HUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT l
November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL k
tLOTES FOR TABLE 61 1.
The principal gamma emitter for which the gamrna isowpic 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 tlse counting system. All identifiable gamrna emitters will be reported in the Annual Monitoring Report.
1 2.
A batch release is the discharge ofliquid wastes of a discrete volume. "rior to sampling for analyses each batch shall be isolated and mixed to assure representative sampling.
l 3.
A continuous release is the discharge ofliquid westes 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.
5.
Identified entrained noble gases shall be reported as gaseous efiluents.
1 Page 32 of 34 INFORMATION USE i
NUCLEAR POWER BUSINESS UNfT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABL' 6-2 RADIOACTIVF. GASEOUS WASTE SAMPLING AND ANAt.YSIS PROGRMt I ower Level Sampling Minimum Type of of Detectkws' Goseous Release Type Frequency AnahY_ Freauenev Activity Analysis
{pCi'cc)
- 1. Gas Decay Tank Prior to IYior to Release Gamma Emitters 1 x 104 Release r
- 2. Containment Purge or Prior to Purge Prior to Purge Gamma Emitters 1 x 10' Continuous Vent or Vent or Vent Tritium i s 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 s 10 '
4
- d. Gas Stripper Building Vent of Particulate Sample
- c. Auxiliary Building Vent Quarterfy Composite Sr-39/90
- x Io-"
of Particulate Sample Noble Gas Monitor Noble gases 1 x 10+
Gross Beta or gamma Monthly
- hionthly Gamma Emita: s I x 10' (Grab)
Monthly Tritium i x 10+
Page 33 ofM INFORMATION USE
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L
~ NUCLEAR POWER BUSINESS UNIT RECM RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL NOTES FOR TABLE 6 2 i
1.
The principal gamma emitters for which the LLD specification applies are Cs 137 in pas:lculates and.
Te 133 in gases. Because gamma isotopic analyses are performed. the LLDs for all other gamma emitters are inherently determined by the operating character.'..
.f the counting system. All identifiable gamma emitters will be reported in the Annual Munitoring 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.
i.
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.
Tritium grab samples will be taken every :even days frvin th-drumming area ventilation exhaust / spent l
fuel pool area whenever there is spent fuel in the spent fuel pool.
t Page 34 of 34 INFORMATION USE
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 PRAFT December 2,1997 OFFSITE DOSE CALCU,LATION MANUAL 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION 1.1 Pumoss The PBNP Offsite Dose Calculation Manual contains the current methodology and parameters for the calculation of offsite doses due to radioactive gaseous and liquid effluents. This manual describes a methodology for demonstratina compliance with 10 CFR 50, Appendix I dose limits. Compliance with Appendix i demonstrated by periodic calculation of offsite doses based on actual plant releases und comparison to Appendix I dose limits.
The manual also details the methodology for the determinaSn of gaseous and liquid effluent monitor alarm set points. The PBNP Radiation Monitoring System (RMS) effluent monitor alarm set points are established to ensure that controlled releases of liquid and gaseous radioactive effluents are maintained as low as is reasonably achievable. The setpoints also are established to ensure that concentrations of radioactive material released in effluents to the atmosphere do not exceed the values of Table 2, Column 1, of Appendix B to 10 CFR 20.1001-20.2402 at or beyond the site boundary and to ensure that the concentrations of radioactive materials released in liquid effluents to the unrestricted area confom4 to (do not exceed) 10 times the concentration values in Table 2, Column 2 of Appendix B to 10 CFR 20.1001-20.2402.
The manual also details the methodology for evaluating the radiologicalimpact of sewage treatment sludge disposal. This methodology addresses the commitments made to the United States Nuclear Regulatory Commission in our application dated October 8,1987 (NRC-87 104) and accepted by the USNRC in a letter dated January 13,1988. This application was subr.itted in accordance with the provisions of 10 CFR 20.302(a). A, copy of the submc.d ud subsequent modifications is contained in Appendices E and F.
Dose limits are estabiahed in the application to ensure the health and safety of the madmally exposed member of the general public and the inadvertent ir.truder.
10 CFR 50, Appendix I dose limits do not apply to sewage treatment sludge disposal.
4 Page1 of120
-NUCLEAR POWER BUSINESS UNIT ODCM
' OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997
{
OFFSITE DOSE CALCULATION MANUAL 1.2 Gertsral Restionsibilities The primary responsibility for the implementation of the PBNP 'fsite dose calculation program and for any actions required by the program resides wita the Radiological
~ Engineering (RE). RE will provide the technical, rergdatery, licensing, and administrative support necessary to fulfill the requ'reinents of this manual. The l
calculation of offsite doses and analysis of data are RE respnWbilities.
The Manager, PBNP is responsible for assuring that Ridiation Monitoring System alarm set points are established and maintained in accordanc.e with the methodologies o stlined in this manual. The Manager, PBNP is also responsible for assuring the performance of periodic release summaries for the purpose of demonstrating compliance with PBNP efnuent release limits.
1.3 Manual Revisions This manual describes the current scope of the PBNP offsite dose calculation program.
l The program and the manual are maintained by RE. Program items or procedures may be periodically updated or changed, either to reDect new parameters or to improve program l
effectiveness. This manual may be revised at the discretion of RE with the concurrence of the PBNP Manager's Supenisory Staff (MSS).
2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING A computerized Radiation Monitoring System (RMS)is installed at Point Beach Nuclear Plant (PBNP). The RMS includes area, process, and effluent monitors. A description of those monitors used for liquid and gaseous effluents is presented in Tables 2-1 and 2-2. The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are depicted in Figures 2-1 and 2-2. Calibration of the RMS detectors is accomplished in accordance with procedures contained in the PBNP Health Physics Calibration Manual. The set point methodology is described in Section 3 of this manual.
The RMS is designed to detect and measure liquid and gaseous releases from the plant effluent pathways. The RMS will initiate isolation and control functions on certain effluent streams identified in Tables 2-1 and 2-2. Complete monitoring and accounting of nuclides released in liquid and gaseous effluents is accomplished with the RMS together with the characterization of nuclide distributions by laboratory analysis of grab samples. Sampling frequencies and analysis l
requirements are described in Tables 6-1 and 6-2 of the Radiological Effluent Control Manual.
The various aspects of grab sampling and release accountability are described in the PBNP Release Accountability Manual.
Page 2 of 120 J
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- NUCLEAR POWER BUSINESS UNIT:
'ODCM OFFSITE DOSE CALCULATION MANUAL-Revision 11 DRAFT.
l December 2,1997 OFFSITE DOSE CALCULATION MANUAL '
13.0-
' METIIODOLOGY FOR DETERMINING ALARM SET POINTS' l
3.l' Introduction I
I The selection and maintenance of alert and alarm set points for each effluent monitor of Ae PBNP radiation monitoring system will be accomplished within the guidelines of this section. The computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct set points. The alert set i
point, typically twice the steady state reading, is intended to delineate a changing plant condition which may warrant corrective action.' The high alarm or trip set point either will actuate a control function as applicable or will require corrective action to be C
initiated.
3.2 Objective The effluent monitor set points are established to ensure that controlled releases ofliquid j
and gaseous radioactive effluents are maintained as low as is reasonably achievable, to -
- l ensure releases result in concentrations to unrestricted areas within specified limits and to ensure that the dose limits of 10 CFR 50, Appendix ! are not exceeded.
3.3 Alert Set Point Guidelines The alert set point of each effluent monitor generally will be set to alarm at two times the established steady-state reading. The alert set point is normally set at concentrations well below the alarm set point value and is never to be set in excess of the alarm set point. In the course of plant operations, certain situations may require a deviation from the two times steady-state guideline. The intent of the alert set point is to warn of changing plant conditions which may warrantun evaluation of the cause of the increased radiation. If the increased reading is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity of t
the detector, an evaluation should be made to determine the impact of the release. The alert set point may be adjusted with the approval of the Duty Shift Superintendent. Alert set point adjustments are to be made in accordance with the PBNP RMS Alarm Set Point and Response Book.
3
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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUp L Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 3.4 Alarm or Trin Set Point Guidelines in accordance with the requirements of 10 CFR 20.1001 - 20.2402 and TS stated in Section 5 of the Radiological Effluent Control Manual, the alarm or trip set point for effluent monitors shall be established to armunciate at radiation levels which would result in an unrestricted area concentration equal to or less than the applicable maximum l
effluent concentration (MEC) for a single radionuclide. However, for a mixture of radionuclides, the set point shall be established so that the summation of fractions, as l
defined in Appendix B of 10 CFR 20 (see Section 3.6), is less than or equal to one (1).
The appropriate detailed response to an effluent alarm is described in the PBNP RMS Alarm Set Point and Response Book.
3.5 Monitor Calibration and Calibration Constant Determination Calibration of the RMS effluent detec*nts is accomplished in accordance with procedures contained in the PBNP Health Physics Calibration Manual. Noble gas effluent monitors apply the calibration constant to standardize all gaseous releases to the 1985-1991 average isotopic noble gas distribution. The calibration constants are based on the calculated monitor response to the beta energy distribution in the 1985-1991 average isotopic noble gas distribution.
Noble gas effluent monitor calibration constants are derived from the following formulae:
1 Cal. Constant
=
Sensitivity and r
SPonse Sensitivity
=
Z (microCi / cc.)
where:
the calculated counts per minute registered by monitor Monitor response
=
exposed to the 1985-1991 average noble gas isotopic distribution total concentration ofisotopes in the 1985-1991 average E( Ci/cci)
=
noble gas isotopic distribution Page 8 of 120
-NUCLEAR POWER BUSINESS UNIT'
- ODCM OFFSITE DOSE CALCULATION MANUAll Revision 11 DRAFT December 2; 1997:
1 OFFSITE DOSE CALCULATION MANUAlf The liquid effluent monitors apply the derived calibration constant to standardize all_
L liquid releases to the total concentration in the release path. The calibration constants are -
based on the monitor response to the 1985 1991 average liquid isotopic distribution. _
Each liquid monitor channel displays the effluent concentration in terms of a total release t
concentration.
Liquid effluent monitor calibration constants are derived from the following formulae:
- Cal. Cunstant - =
Sensitivity -
and n r esponse
_ Sensitivity
=
- I(pCi / cci) where:
the counts per minute registered by monitor exposed to Monitor _ Response
=
calibration source total concentration on radionuclides in the 1985-1991 I(pCi/cci)
=
average liquid efiluent isotopic distribution -
The QAD computer program may be utilized to predict or determine monitor calibration 4
constants, Application of the QAD program may be appropriate for detennining monitor
' response for accident source terms or other instances when the use of a calibration source is impracticable. The methodology for detennination of calibration cons' ants using the t
l QAD program is maintained by the staffif the RE.
3.6 -
Determination of the Effective Maximum Effluent Concentration (EMEC) for Liauid Releases y
Pursuant to PBNP TS, the concentration of radioactive materials in liquid effluent may
~
. not exceed 10 times the s alues of Column 2, Table 2, of Appendix B to
-10 CFR 20.1001-20.2402. However, as a conservative measure, the following
- determination of the EMEC and the subsequent setpoint determination for liquid effluent
= (Section 3.7)' o not employ the augmented concentration values.
d U
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NUCLEAR POWER BUSINESS UNIT.
ODCM-OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997
?
OFFSITE DOSE CALCULATION MANUAL in order to fulfill the requirements of 10 CFR 20, the RMS set point must be a value which will alarm when a liquid efnuent would contain enough radionuclides to cause the ef0uent concentration limit of 10 CFR 20, Appendix B, Table 2, Column 2 for a single radionuclide to be exceeded, or for a mixture of radionuclides, the summation of fractions (SOF), as defined in Appendix B, to exceed one (1). Dividing the average isotopic concentrations for the years 1985 1991 by the SOF scales the total ofindividual concentrations up to the value where the SOF equals one. This total concentration is called the effective maximum ef0uent concentration (EMEC) and its calculation is described below. (For a complete discussion of the EMEC derivation, see Appendix A.)
The SOF is calculated using the formula found in the revised 10 CFR 20, Appendix E, Note 4:
E C /MECi
^
SOF
=
i where:
Ci concentration of radionuclide "i" (pCi/ml) in effluent (annual
=
discharge / total volume of discharge) maximum effluent concentration for unrestricted areas from MECi 4
Appendix B, Table 2, Column 2 of the revised 10 CFR 20.
The SOF for radionuclides in liquid ellluent for the years 1985 through 1991 were averaged and applied to the average of the isotopic concentrations for the same years.
Na-24 and H-3 were not used in the calculations (see Appendix A for details).
Next, the " effective MEC" or EMEC is calculated using the formula:
IC / E(C SIEC)or EC
- 1/SOF EMEC
=
i i
i i
where the variables are the same as defined above.
The average EMEC, based on 1985-1991 data is 4.29E-06 pCi/cc. This is the maximum -
non H-3 radionuclide mixture concentration that could be released in liquid effluent without the SOF exceeding one (1).
flowever, the 10 CFR 20, Appendix B criterion is that the SOF for all radionuclides, including H-3 which cannot be measured by the liquid effluent Nal RMS monitors, be less than or equal to one (1). Therefore, the above equation modified by a factor of 0.70 (see Appendix A) to account for H-3 becomes Page 10 of 120
NUCLEAR POWER BUSINESS UNIT ODCM
. OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL IC
- 0.70/SOF.
= 0.70 IC / I(C /MEC;) or EMEC i.
i i
The EMEC becomes 0.70
- 4.29E-06 = 3.00E-06 pCi/cc.
EMEC
=
Only three radionuclides identified in PBNP liquid effluent have a lower MEC (10 CFR 20, Appendix B, Table 2). They are I 131 (1E-06), Cs-134 (9E-07), and Cs-137 (l E-06).
Note that the use of the 0.7 modifying factor sets the SOF for non-tritium radionuclides to 0.7 and allows an SOF of 0.3 for H 3. A SOF of 0.3 limits the discharge concentration of H-3 to 0.3 MEC or 3E-04 pCi/cc. The factor of 0.3 may be changed as needed for -
releases for which the isotopic mixture and concentrations are known as long as the total SOF $1.
3.7
. jletermination of Liauid Effluent Monitor Alarm Set Point The alarm set point for each liquid monitor is based upon the 1985-1991 average radionuclide concentration in the effluent discharged to the unrestricted area. The radionuclide concentration in the release is calculated assuming a minimum circulating water flow rate of 206,000 gpm and the maximum flow rate of the individual liquid effluent waste stream. The isotopic distribution of the waste stream is obtained from the historical PBNP release data for the seven years mentioned above. Set points are determined such that the sum of all radionuclides in the mixture, when released into the circulating water system, will be maintained at or below the unrestricted area EMEC.
Set points are calculated using the formula Circ water flow rate (gpm)
EMEC
=
Waste Discharge F!ow Rate (gpm) 4 where SP = - RMS alarm set point in Ci/cc effective maximum effluent concentration EMEC
=
Cire water flow rate =. total flow from Unit I + Unit 2 flow rate for effluent line on which the
. Waste discharge flow rate
=
monitor is located Page11 of120
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997
- 0. FSITE DOSE CALCULATION MANUAL Maximum waste discharge flow rates and monitors associated with each liquid effluent pathway are described in Table 3.71.
Default alarm set points normally are established based upon the maximum waste discharge flow rate and the minimum circulation water flow rate. The liquid release monitor default set points are listed in Table 3.7-2. Alarm set points may be adjusted for batch releases, when actual flow rates are known. Alarm set point adjustment; which are higher than default values, are to be made in accordance with the provisions and methodologies of this section and requires approval of the MSS. Lower alarm set point values maybe used without MSS approval if the default values lie outside the upper range of the monitor or if compliance with applicable limits will not be compromised.
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NUCLEAR POWER BUSINESS LNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL
- TABLE 3.7-1 SUS 151ARY OF LIOUID DILUTION AND EFFLUENT PATiiWAY FLOW RATES
- LIQUID EFVLUENT
- DISCHARGE FLOW RATE PATHWAY MONITOR PATHWAY:
' (GPM)'
RECIRCULATION WATER 1 pump, either unit 206,000 None 2 pumps, either unit 350,000 1 pump, each unit 392,000 1 pump, one unit &
530,000 2 pumps, other unit 2 pumps, each unit 680,000 SERVICE WATER RETURN 1 (2) RE-229 (normal cooldown per pump l
2 pumps @ 7500 gpm 15,000 3 pumps @ 6300 gpm 18,900 4 pumps @ 5100 gpm 20,400 5 pumps @ 4300 gpm 21,500 6 pumps @ 3700 gpm 22,200 STEAM GENERATOR 1 (2) RE-219 & I (2) RE-222 BLOWDOWN Max flow 200 RETENTION POND RE-230 Max Flow Rate 360 (2 pumps)
(sliding gate open) 1670 Page 13 of 120 -
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NUCLEAR POWER BUSINESS UNIT ODCM-OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-1, cont i
SUMMARY
OF LIOUID DILUTION AND EFFLUENT PA'l HWAY FLOW RATES
. LIQUID EFFLUENT D!SCHARGE FLOW RA'1 E PATHWAY MONITOR PATHWAY (GPM) -
SPENT FUEL POOL RE-220 Max Flow Rate 700 WASTE DISTILLATE &
RE-218 & RE-223 CONDENSATE TANK DISCHARGE Max Flow Rate 100 CONTAINMENT FAN 1 (2) RE-216 COOLER RETURN Max Flow Rate per 4000
= Containment s
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